Text

Submittal of 2015 Annual Radiological Environmental Operating Report
	ML16118A159
Person / Time
Site:	Diablo Canyon
Issue date:	04/21/2016
From:	Welsch J; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	DCL-16-045, NEI 99-04
	Download: ML16118A159 (130)
	v • d • e

Pacific Gas and Electric Company"'

James M. Welsch Diablo Canyon Power Plant Vice President, Nuclear Generation P.O. Box 56 Avila Beach, CA 93424 805.545.3242 E-Mail: JMW1@pge.com April 21, 2016 PG&E Letter DCL-16-045 U.S. Nuclear Regulatory Commission 10 CFR 50, Appendix I ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 2015 Annual Radiological Environmental Operating Report

Dear Commissioners and Staff:

In accordance with Diablo Canyon Power Plant, Units 1 and 2, Technical Specification 5.6.2, "Annual Radiological Environmental Operating Report," Pacific Gas and Electric Company hereby submits the 2015 Annual Radiological Environmental Operating Report (AREOR). The AREOR contains material consistent with the objectives of the Offsite Dose Calculation Manual, and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

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

If you have any questions regarding this submittal, please contact Mr. Martin Wright at (805) 545-3821.

Sincerely, A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek I~

. . Document Control Desk PG&E Letter DC~-16-045 Wf~~ April 21, 2016

' ~ Page 2 bnsm/4540/64124185 Enclosure cc: Diablo Distribution cc/enc: Larry Allen, Air Pollution Control Officer, San Luis Obispo County Air Pollution Control District Penny Borenstein, San Luis Obispo County Health Officer Marc L. Dapas, NRC Region IV Administrator Kenneth A Harris Jr., Executive Officer, CRWQCB Gonzalo L. Perez, Branch Chief, California Department of Public Health John Reynoso, DCPP Acting NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Executive Officer, San Luis Obispo County Air Pollution Control District A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure PG&E Letter DCL-16-045 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

2015 Annual Radiological Environmental Operating Report Diablo Canyon Power Plant January 1, 2015 - December 31, 2015

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2015 Diablo Canyon Power Plant ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)

January 1, 2015 - December 31, 2015

, Prepared By Pacific Gas & Electric Company Diablo Canyon Power Plant Prepared by: .£.-Z.;;__ ~ Date: o/'I/ 2a1(,

Martin-Wright; DCPP RP Senior Advising Engineer Reviewed&A Date: LI / (p I 1h PG&E Submittal Letter DCL-16-045

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EXECUTIVE

SUMMARY

This report contains results from the operational Radiological Environmental Monitoring Program (REMP) for Diablo Canyon Power Plant (DCPP) compiled for the period January 1, 2015 through December 31, 2015.

The purpose of the REMP was to assess the levels of radiation or radioactivity in the environment and to verify that DCPP was operating within its design parameters. This data was used to assure that plant effluents did not result in a significant radiological dose to offsite individuals.

Operation of DCPP continued to have no detectable offsite radiological impact. Samples analyzed from the offsite sampling stations continued to show no radiological contribution from plant operations.

The offsite radiological doses received by the general public from plant operations were less than one millirem (mr) annually which is insignificant whert *compared to the 310 millirem average annual radiation exposure to people in the United States from natural radiation sources (e.g. cosmic, terrestrial, radon, etc).

More than 260 environmental samples, 880 air samples, artd 1400 thermo luminescent dosimeter (TLD) phosphors were collected over the course of the 2015 REMP monitoring period. Approximately 1782

(

radionuclide analyses were performed on the environmental samples.

The REMP was conducted in accordance with DCPP Program Directive CY2, "Radiological Monitoring and Controls Program," and RPl.IDl 1, "Environmental Radiological Monitoring Procedure." This report was submitted per DCPP License Technical Specification 5.6.2.

The types of samples (matrix ID) collected for this monitoring period were as follows:

Air Particulate (AP) Air Cartridges (AC) for iodide monitoring Carbon-14 (AC14)

Direct Radiation (TLD) Mille (MK) Meat (MT) Vegetation (VG)

Drinking Water (DW) Ground Water (GW), Monitor Well (GW) Surface Water (SW)

Aquatic Vegetation (AV) Fish (FH) Mussels (IM) Sediment (SD)

The ambient direct radiation levels in the DCPP offsite environs did not change and were within the pre-operational background range.

The ambient onsite direct radiation levels within the DCPP plant site boundary near the ISFSI were elevated due to dry cask spent fuel storage. The remaining onsite REMP environmental TLD locations were not affected by the ISFSI due to ISFSI topographical elevation and placement within an onsite hillside which provided shielding to the rest of the site.

An evaluation of direct radiation measurements and member of public occupancy .times within the site boundary indicated all federal criteria for member of public dose limits (10CFR20.1301) were conservatively met. An evaluation of direct radiation measurements indicated all federal EPA 40CFR190 criteria were conservatively met.

Groundwater isotopic monitoring was conducted in accordance with the nuclear industry NEI 07-07 Groundwater Protection Initiative (GPI). Concentrations of tritium were detected in three shallow monitoring wells (stations OWl, DYl, and GWl) near the power block. This tri~ium was evaluated and attributed to rain-washout of gaseous tritium exiting the plant vent system (via an approved isotopic-effluents discharge path). No groundwater tritium has been attributed to DCPP system leaks or spills. It should also be noted that studies of the DCPP site groundwater gradient indicated that any groundwater (subsurface) flow beneath the DCPP power block was not used as a source of drinking water. Due to topography and site characteristics, this groundwater gradient flow discharged into the Pacific Ocean which is approximately 100 yards from the power block.

An Old Steam Generator Storage Facility (OSGSF) long term storage mausoleum was constructed within the DCPP site boundary in 2007 for storage of eight retired DCPP steam generators and two retired DCPP reactor heads. This OSGSF did not cause any changes to the ambient direct radiation levels within the DCPP environs during 2015. The OSGSF in-building sumps were inspected quarterly by REMP personneL These OSGSF sumps have remained empty and dry during 2015.

The results of the 2015 REMP showed no unusual environmental isotopic findings from DCPP site

operations. These results were compared to DCPP preoperat~onal isotopic data and showed no unusual trends.

Diablo Canyon site operations had no significant environmental radiological impact on airborne, surface water, drinking water, marine life, aquatic vegetation, terrestrial vegetation, sediment, milk, or meat radioactivity.

TABLE OF CONTENTS Executive Summary 1.0 Introduction 2.0 Program Design 2.1 Monitoring Zones 2.2 Pathways Monitored 2.3 Descriptions ofREMP Monitoring 2.3.l Direct Radiation 2.3.2 Airborne Radioactivity 2.3.3 Airborne Carbon-14 2.3.4 Water,borne 2.3.5 Marine Biological, Beach Sand, and Ocean Sediment 2.3.6 Food Crops 2.3.7 Milk 2.3.8 Meat 3.0 Radiological Data Summary of Tables 4.0 Analysis of Environmental Results 4.1 REMP Sampling Variance I Deviations 4.2 Comparison of Achieved LLDs with Requirements 4.3 Comparison of Results against Reporting Levels 4.4 Data Analysis by Media Type 4.4.1 Direct Radiation 4.4.2 Airborne Radioactivity 4.4.3 Waterborne 4.4.4 Marine Biological, Beach Sand, and Ocean Sediment 4.4.5 Food Crops 4.4.6 Milk 4.4.7 Meat 5.0 Groundwater Monitoring 6.0 Old Steam Generator Storage Facility 7.0 Lab Cross Check Program 8.0 DCPP Annual Land Use Census

9.0 DCPP Wind Rose 10.0 References Appendix A Individual Analytical Sample Results Photograph credits: Tom Hook, John Lindsey, and Martin Wright

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LIST OF TABLES Table Title 2.1 Radiological Environmental Monitoring Program 2.2 Distances and Directions to Environmental Monitoring Stations 2.3 Detection Capabilities for Environmental Lower Limit of Detection (LLD) 2.4 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.1 Direct Radiation Summary Table 3.2 REMP Airborne Summary Table 3.3 Surface Water Summary Table 3.4 Drinking Water Summary Table 3.5 Mussel Summary Table 3 .6 Fish Summary Table

3. 7 Algae Summary Table 3.8 Kelp Summary Table 3.9 Vegetative Crops Summary Table 3.10 Milk Summary Table 3.11 Meat Summary Table 3.12 Ocean Sediment Summary Table 3.13 Beach Sand Suillmary Table 3.14 Groundwater Summary Table 3.15 Monitoring Well Summary Table 8 DCPP Land Use Census LIST OF FIGURES Figure Title 2.1 Diablo Canyon Off-site REMP Locations 2.2 Diablo Canyon On-site REMP Locations 2.3 Diablo Canyon REMP Stations 8 DCPP Land Use Census Map

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1.0 INTRODUCTION

Diablo Canyon Power Plant (DCPP) consists of two Westinghouse pressurized water reactors (PWR).

Unit 1 began commercial operation in 1985, and Unit 2 began commercial operation in 1986.

The purpose of the Radiological Environmental Monitoring Program (REMP) is to verify that Diablo Canyon Power Plant (DCPP) is operating within its design parameters and to assure that plant effluents do not result in a significant radiological dose to offsite individuals.

Operation of DCPP continues to have no detectable radiological impact offsite. Samples analyzed from the offsite sampling stations continue to show no radiological contribution from plant operations. The annual radiological doses received by the general public from plant operations were less than one millirem (mr) which is insignificant when compared to the 310 millirem average annual radiation exposure to people in the United States from natural radiation sources (e.g. cosmic, terrestrial, radon, etc).

This Annual Radiological Environmental Operating Report (AREOR) summarized the findings of the REMP conducted by DCPP. The remainder of this AREOR was organized as follows:

Section 2: Provided a description of the overall REMP design. Included was a summary of the requirements for REMP sampling and tables listing routine sampling and TLD monitoring locations with distances from the plant. Tables listing Lower Limit of Detection requirements and Reporting Levels (NRC notification if levels exceeded) were also included.

Section 3: Consisted of the summarized data as required by the Radiological Environmental Monitoring Program. The summaries were provided similar to that specified by the NRC Branch Technical Position on Environmental Monitoring.

Section 4: Provided a summary of the results for the samples collected. The performance of the program in meeting the requirements was discussed, and the data acquired during the monitoring period was analyzed. Also included was environmental TLD preoperational data trending.

Section 5: Provided a summary of groundwater monitoring in accordance with the nuclear industry NEI 07-07 Groundwater Protection Initiative.

This and previous DCPP AREOR's can be found on the NRC website at:

http://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-info.html DCPP REMP sent replicate split san1ples of stations 7G I vegetation (quarterly), 5F2 milk (monthly), 5S2 drinking water (monthly), DWI drinking water (monthly), OUT seawater (monthly), DCM kelp (quarterly), DCM perch (quarterly), DCM rockfish (quarterly), and DCM ocean sediment (annually) to the California Department of Public Health - Radiologic Health Branch (CDPH -RHB) Laboratory as part of a California State split sampling program.

These split samples were independently analyzed by the CD PH-RHB.

Other pathways independently monitored by the CDPH-RHB were quarterly direct radiation TLD stations (MTl , !Al , !Cl, 4Dl , 5F3, 5Sl , 7Dl, 7Cl , 7FI , and 8S2) and weekly air sampling particulate and 1- 131 (at stations 5F3 and 7Dl).

The general public can access these CDPH-RHB split sampling data results via the internet at:

http://www.cdph.ca.gov/programs/Pages/RHB-RadReport.aspx

2.0 PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Diablo Canyon Power Plant (DCPP) was designed with the following specific objectives in mind. These objectives continue to be in force, to varying degrees, throughout facility operation:

To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by facility operation. Preoperational data was also used in this comparison.

To provide assurance to regulatory agencies and the public that the station's environmental impact was known and within anticipated limits.

To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.

The environmental media selected were based on the critical dose pathways of the radionuclides from the environment to man. They included the following: direct radiation, air, water, fish, ocean sediment, and invertebrates. Supplemental samples such as algae, kelp, local agricultural crops, recreational beach sand,

groundwater, meat, and milk were also collected. The sampling locations were determined by land use, site meteorology, and local demographics. Guidance for this monitoring program was provided by the Radiological Assessment Branch Technical Position on Radiological Environmental Monitoring, Revision 1, November 1979 (NUREG-1301).

Radiological Environmental Monitoring Program (REMP) samples were collected by DCPP REMP personnel and sent to General Engineering Labs (GEL) in Charleston, South Carolina for isotopic analysis.

Fish (except market fish) and ocean sediment samples were collected by contract divers of Tenera Environmental and given to DCPP REMP personnel for shipment to GEL.

Market fish samples were collected by local commercial fishermen and then purchased by DCPP REMP personnel in one of two local fish markets for shipment to GEL.

Environmental direct radiation analyses were conducted by the use of thermo-luminescent dosimeters (TLD). Environmental TLD analysis was conducted by Mirion Technologies in Irvine California.

The detailed sampling requirements of the REMP were given in Table 2.1 of this report.

Data summary tables of REMP sampling for the period were shown in section 3 9f this report.

Any deviations from the REMP sampling schedule I requirements were documented in section 4 of this report.

Direct dose (environmental TLD) results were shown in section 4 of this report.

Individual REMP sample isotopic results were shown in Appendix A of this report. Detected concentrations ( > MDC) of nuclear power plant related isotopes have been highlighted with yellow background for quick identification by the reader. Naturally occurring isotopes (e.g. NORM) were not highlighted (including gross beta, Be-7, K-40, thorium, radium, radon, lead, etc).

2.1 MONITORING ZONES The REMP was designed to allow comparison of levels of radioactivity in samples from the areas possibly influenced by DCPP to levels found in areas not influenced by the facility operations. Areas with the potential to be influenced by facility operations were called "indicator" stations. Areas with sufficient distance from the plant that were not likely to be

influenced by facility operations were called "control" stations. The distinction between the two zones was based on distance and relative direction from the plant. Analysis of survey data from the two zones aided in determination of site environmental influence. Analysis .

from the two zones assisted in differentiation between radioactive releases and seasonal variations in the natural environmental background radioactivity.

2.2 PATHWAYS MONITORED Direct Radiation Airborne Radioactivity Waterborne Pathways Marine Biological, Beach Sand, and Ocean Sediment Food Crops Milk Meat

2.3 DESCRIPTION

S OF REMP MONITORING 2.3.1 Direct Radiation Direct ambient radiation was measured at 32 stations in the vicinity ofDCPP using Panasonic UD814 TLD badges. The TLD badges had valid element correction factors (ECF), were calibrated using a NIST-traceable caesium-137 source, were annealed prior to placement, and were sealed in watertight packaging. Three TLD badges were placed at each station and each badge contained 3 calcium sulfate phosphors for a total of 9 calcium sulfate phosphors at each station. The 9 phosphors were analyzed and averaged to provide a single station reading. That single reading was converted into an uR/hr doserate dependent on the in-field exposure time period. Then the uR/hr doserate was converted and reported into millirem (mr) per standard (91 day) quarter. These TLD badges were exchanged and processed on a quarterly basis.

Direct ambient radiation was meas~red at 8 stations in the vicinity of the Independent Spent Fuel Storage Installation (ISFSI) using Panasonic UD814 i

TLD badges. The ISFSI TLD badges were processed in the same method described in the previous paragraph.

The Env TLD badge packets were distributed and ~ollected from the field stations by DCPP REMP personnel and then shipped to Mirian Technologies for processing. Control badges accompanied the field badges during shipment and deployment to measure any non-station dose received during transit time periods.

Control badge exposure was subtracted from field badge exposure. Env TLD exposure was reported over a standard 91 day quarter.

DCPP Environmental TLD standard quarter results were measurements of all environmental gamma radiation sources (cosmic, terrestrial, radon, man-made, etc) at each station during the deployment period.

2.3.2 Airborne Radioactivity Air particulate and radioiodine sampling were performed weekly at six indicator stations: MTl, 082, 181, 7Dl, 881and882. Air particulate and radioiodine sampling was performed weekly at one control station: 5Fl.

Constant flow air samplers (F&J model DF-1) were used to draw air through paper filters to collect air particulates and through triethylenediamine (TEDA) impregnated charcoal cartridges to collect radioiodine. The air sampling flow rate was conducted at approximately 2.55 cubic meters per hour. The air sampling

.collection filters were located approximately seven feet above the ground. The sample volum~s were determined by F&J Corporation model DF-1 flow meters (corrected to standard temp~rature and pressure, 8TP) which were installed 1

downstream of the sample filters. At the end of the weekly sampling period, the particulate filter and TEDA charcoal cartridge were collected. All necessary data regarding the air volume readings, flow rate, sampler time on I off, date bf collection, and sampler station location were recorded and submitted to GEL along with the filter samples for isotopic analysis.

Approximately 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after sampling (to allow for radon and thoron daughter decay), the particulate filter papers collected from the field were placed on individual planchets and counted for gross beta activity in a low background, thin window gas proportional counter.

Quarterly gamma spectroscopy isotopic anaJysis was performed on composites of

the filters (by station) to detennine the activity concentration of gamma emitting isotopes. The quarterly composite sample time is reported at the midpoint of the quarter monitored.

Due to the short half-life of lodine-131, each station weekly TEDA impregnated charcoal cartridge was counted for gamma spectroscopy isotopic analysis to determine the radioiodine concentration.

2.3.3 Airborne Carbon-14 Air Carbon-14 (C-14) supplemental sampling was perfonned weekly at stations OS2 (no1ihwest sector), 8S 1 (southeast sector), and SF 1 (control station in San Luis Obispo) throughout 2015.

General Engineering Labs (GEL) and DCPP REMP worked together to develop a method for sampling environmental airborne inorganic C-14. Inorganic C-14 (as C0 2) is the primary exposure pathway to man via photosynthesis in plants. A constant flow air san1pler was used to draw air through a solid phase carbon sensitive sorbent cartridge. The air sampler was set at a flow rate of 1.0 standard liter per minute. The air sample filter cartridge head was located approximately seven feet above the ground. At the end of the weekly sampling period, the filter cartridge was collected. All necessary data regarding the air volume, flow rate, sampler time on I off, date of collection, and sampler station location were

recorded and submitted to GEL along with the sample filter for C-14 analysis. At GEL, a suitable portion of the solid sorbent material was processed through a method utilizing wet oxidation to remove volatile C0 2 from the media in a closed distillation system. Once removed from the media, C-14 as carbon dioxide was sparged through a dilute acid solution for trapping any tritiated water present in the sample. After sparging through dilute acid, the C0 2 was trapped in a sorbing solution which was added to liquid scintillation cocktail and finally counted in a liquid scintillation counter. It should be noted that C-14 results in Appendix Care reported in uCi/cubic meter. This method met the following specifications:

Validated to retain 99.9% of inorganic C-14 in air

Validated at collection rates of approximately 1.0 liter per minute

Validated for total collection capacity over a l week sampling interval

Accurate analysis of C-14 over a wide range of concentrations

Methodology free from interference by other radionuclides

Detection capability of approximately 0.8 pCi (8E-7 uCi) per cubic meter 2.3.4 Waterborne Water samples (drinking water, surface water, monitor wells, and groundwater) were collected at the frequencies shown in Table 2.1 Ocean surface water samples were collected at Diablo Cove (station DCM),

Rattlesnake Canyon (station 7C2), and at the plant Outfall (station OUT).

Drinking water samples were collected from Diablo Creek Weir (station 5S2),

Diablo Creek Outlet (station WN2), Blanchard Spring (station 1A2), and from the DCPP drinking water system (station DWI). San Luis Obispo (SLO) city drinking water was also collected from a control station located at 4325 South Higuera Street, Offsite Emergency Lab (station OEL) in SLO.

Supplemental groundwater samples were collected from Water Well 02 (WW2) and DCSF96- l (8S3).

Supplemental on-site monitoring well samples were collected from french drain systems labeled Observation Well 01 (OWl), Observation Well 02 (OW2), and

Drywell 115 (DYl). These shallow French drain well systems were located in close proximity to the facility power block structures and within the protected area.

Two new on-site monitoring wells were installed in December 2011 as part of the industry Groundwater Protection Initiative (GPI). Isotopic sampling of these wells was initiated in 2012. These two new onsite wells were downgradient of the power block and located along the west side of the power block. These two new monitoring wells were labeled Groundwater I (GWI) and Groundwater 2 (GW2).

After collection, the samples were securely sealed and labeled with sample type, station ID, date, time of collection, person performing the collection and sent to GEL for analysis.

2.3.5 Marine Biological, Beach Sand, and Ocean Sediment The REMP required sampling ofrockfish (genus Sebastes), perch (family Embiotocidae), mussels (genus Mytilus), and ocean sediment from indicator station DCM and control station 7C2.

All other marine samples collected were considered supplemental. These supplemental marine samples included the following: intertidal algae, intertidal mussels, kelp, rockfish, perch, beach sand, and market fish. The intertidal samples were collected by DCPP personnel during low tidal conditions. Kelp was collected quarterly by DCPP personnel from the offshore kelp bed in the vicinity of the site.

Quarterly samples of fish and annual samples of ocean sediments were collected from the plant environs by contracted divers (TENERA Environmental). The Tenera divers fillet the fish and leave a small portion of skin for identification.

Only edible portions of the fish were analyzed (fish fillets).

Beach sand was collected by DCPP personnel between the high and low tide boundaries at nearby recreational beaches.

Market Fish caught locally by commercial fishermen were pmchased from two local fish markets (A vita Beach Pier-703 and Morro Bay-2F 1).

All samples were subject to unavailability due to seasonal fluctuations or unfavorable sampling conditions. The above samples were sealed in plastic bags immediately upon collection. In-shell mussels were sent to GEL where GEL personnel removed the meat & internal organs for analysis. The samples were labeled with sample type, station ID, date, time of collection, and the individual who performed collection. The samples were then frozen (to prevent spoilage odor) before they were shipped to GEL for analysis.

2.3.6 Food Crops The REMP required broadleaf food vegetation collected in the nearest off-site locations of the highest calculated annual average ground level D/Q (dispersion parameter) within 5 miles. There was no broadleaf food vegetation available that satisfied this requirement. Because these food products were unavailable, the DCPP REMP conducted additional weekly air sampling in the SE (station 8S2) and NNW (station IS I) sectors.

Additional representative samples of food crops (in season) were collected monthly from supplemental stations: Cal Poly Farm (5F2), Kawaoka Farm in Arroyo Grande (7G 1), Mello Farm (7Cl) along the DCPP site access road, and quarterly from local gardens (3Cl , 6Cl, and 7El).

The vegetation samples at 5F2, 7Gl, 7Cl , 3Cl , and 7El were collected by DCPP personnel and sealed immediately in plastic bags. The quarterly garden vegetation sample at 6C 1 was provided to DCPP personnel by the land occupant (due to difficulty of property access and occupant requested privacy).

The samples were labeled with sample type, station ID, collection date, collection time, and the individual who perfonned collection. The samples were normally frozen before they were shipped to GEL for analysis (to prevent spoilage odor).

2.3.7 Milk There were no animals within the 5 mile vicinity of the plant utilized for milk consumption by hwnans. However, supplemental samples of cow milk were collected monthly from Cal Poly Farm (5F2) which was approximately 13 miles from DCPP.

Two 1-gallon plastic containers of milk were collected each sampling period by DCPP personnel. Forty grams of sodium bisulfite preservative were added to each gallon of milk sample. The containers were sealed and shaken thoroughly to distribute the preservative. The containers were labeled with sample type, station ID, collection date, collection time, and the individual who performed collection.

The samples were then express-shipped (due to the short half-life of I-131) to GEL for analysis.

2.3.8 Meat A rancher routinely grazed (free range, grass fed) cattle within three miles of the site boundary between the northwest to east sectors (clockwise). This livestock meat would then be offered at local farmer's markets and private distribution.

Because it was possible for this vendor to provide an individual's sole-source of annual meat consumption, this meat sampling was included in the REMP.

REMP personnel obtained commercially packaged meat samples directly from the land owner. Gamma spec and total strontium 89/90 analyses were performed on th~ meat.

Control station free range, grass fed meat sampling was conducted of ranches outside the influence ofDCPP. This meat was purchased by REMP personnel from the Whole Foods Market in SLO. The control station meat consisted of Hearst Ranch meat which is located approximately 37 miles north of the DCPP site. This REMP station code was CCM (Control Cow Meat) and provided a control meat sample location far from the site.

Property owners could hunt deer and wild pig (in season) within 5 miles of the site boundary. The REMP could not obtain deer meat samples from these property owners (voluntary participation) in 2015. Gamma spec and strontium analyses were performed on the deer meat if provided.

The meat was initially packaged by the livestock owners or commercial processes. The meat was purchased at local grocery stores or turned over to REMP personnel by the land owners. The unopened packages were then separated by species and placed into large over-pack zip-lock bags. Each bag was labeled with sample type, station ID, collection date, collection time, and the individual who performed the collection. The samples were then frozen and shipped to GEL for isotopic analysis.

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TABLE2.1:

Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling Collection Frequency Type of Required or and/or Sample Type Samples and Sample Stations Analysis Supplemental Locations 1

1. Direct Radiation2 Thirty-two routine monitoring stations containing thermo luminescent dosimeters (TLDs) such that at least two (2) phosphors are present at each station, placed as follows:

An inner ring of stations, one in OS1, OS2, Quarterly Gamma Dose Required each terrestrial meteorological WN1, 1S1, sector in the general area of the 2S1, 3S1, 4S1, SITE BOUNDARY; 5S1, 6S1, 7S1, 8S1' 9S1' 8S2, 5S3, and MT1 An outer ring of stations, one in OB1, 1A1, 1C1, Quarterly Gamma Dose Required each terrestrial meteorological 2D1, 3D1, 4C1, sector in the 2.5 to 14 km range 5C1, 6D1, and from the site; and 7C1 One or two areas to serve as 2F2, 4D1, 5F1 Quarterly Gamma Dose Required control stations; and The balance of the stations to 5F3, 7D1, 7D2, Quarterly Gamma Dose Required be placed in special interest 7F1, and 7G2 areas such as population centers, nearby residences, or schools.

A minimum of four stations IS1' IS2, IS3, Quarterly Gamma Dose Required around the ISFSI IS4, IS5, IS6, IS7, IS8

2. Airborne Samples from~ 4 stations:

Radioiodine Three samples from close to the OS2, 8S1, Continuous sampler 1-131 analysis Required three SITE BOUNDARY and MT1 operation with sample locations ( OS2, 8S1, & MT1 ) in collection weekly, or different sectors. more frequently if required by dust loading.

One sample from the vicinity of 7D1 Continuous sampler 1-131 analysis Required a community having the highest operation with sample calculated annual average collection weekly, or ground level D/Q. more frequently if required by dust loading.

If food products are unavailable, 1S1 &8S2 Continuous sampler 1-131 analysis Required additional air sampling will be operation with sample done in the NNW (station 1S1) collection weekly, or and SE (Station 8S2) sectors. more frequently if required by dust loading.

One sample from a control 5F1 Continuous sampler 1-131 analysis Required location. operation with sample collection weekly, or more frequently if required by dust loading.

Table 2.1 (continued)

Exposure Pathway Number of Representative Sampling Collection Type of Analysis Required or and/or Sample Type Samples and Sample Stations Frequency Supplemental 1

Locations

3. Airborne Samples from~ 4 stations: \

Particulate Three samples from close to the OS2, 8S1, Continuous Weekly gross beta Required three SITE BOUNDARY and MT1 sampler operation radioactivity locations ( OS2, 8S1, & MT1 ) in with sample analysis following 3

different sectors. collection weekly, filter change

or more frequently Quarterly gamma 4

if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).

One sample from. the vicinity 9f 701 Continuous Weekly gross beta Required a community having the highest sampler operation radioactivity calculated annual average with sample analysis following 3

ground level D/Q. collection weekly, filter change

or more frequently Quarterly gamma 4

if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).

lffood products are unavailable, 1S1 & 8S2 Continuous Weekly gross beta Required additional air sampling will be sampler operation radioactivity done in the NNW (station 1S1) with sample analysis following 3

and SE (Station 8S2) sectors. collection weekly, filter change .

or more frequently Quarterly gamma if required by dust isotopic analysis4 loading. of composite consisting of approx. 12 filters (by location).

One sample from a control 5F1 Continuous Weekly gross beta Required location. sampler operation radioactivity with sample analysis following 3

collection weekly, filter change

or more frequently Quarterly gamma 4

if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).

4. Airborne Carbon-14 Samples from 3 stations: OS2,8S1 Continuous C-14 analysis Supplemental One sample from each of the 5F1 (control) sampler operation_

NW and SE sectors close to the with sample site (OS2 and 8S1). collection weekly, or more frequently One sample used as a control if required by dust station (5F1). loading.

/

Table 2.1 (continued)

Exposure Pathway Number of Representative Sampling Collection Type of Analysis Required or and/or Sample Type Samples and Sample Stations Frequency Supplemental 1

Locations

5. Waterborne 4

a. Surface Ocean One sample from the plant OUT, DCM, Monthly Gamma isotopic Required Water Outfall, Diablo Cove, and an and 7C2 (grab sample) and tritium area not influenced by plant analysis.

discharge.

One sample from the plant OUT, DCM, Quarterly Gross Beta, Supplemental Outfall, Diablo Cove, and an and 7C2 (grab sample) Total Sr 89/90, area not influenced by plant Fe-55, and Ni-63 discharge.

4

b. Drinking Water One sample from the plant DW1and5S2 Monthly Gamma isotopic , Required drinking water, one sample from OEL (control) (grab sample) 1-131, and tritium Diablo Creek (upstream of analysis.

plant), and one control sample.

One sample from the plant DW1and5S2 Quarterly Gross Beta, Supplemental drinking water, one sample from OEL (control) (grab sample) Total Sr 89/90, Diablo Creek (upstream of Fe-55, and Ni-63 plant), and one control sample.

4 One sample from Diablo Creek WN2and1A2 Quarterly Gamma isotopic , Supplemental (downstream of plant) and one (grab sample) tritium, 1-131, gross sample from Blanchard Spring. beta, Total Sr 89/90, Fe-55, and Ni-63 4

c. Groundwater One sample from wells located OW1, OW2, Quarterly Gamma isotopic , Supplemental under or downgradient from the DY1, GW1, (grab sample, tritium, gross beta, plant power block. and GW2 when available) Total Sr 89/90, Fe-55, and Ni-63 4

One sample from a well located WW2, 8S3 Quarterly Gamma isotopic , Supplemental outside the plant power block (grab sample, tritium, gross beta, (control sample). when available) Total Sr 89/90, Fe-55, and Ni-63 4

d. Sediment One sample of offshore ocean DCM and 7C2 Annual Gamma isotopic Required sediment from Diablo Cove and (grab sample)

Rattlesnake Canyon.

One sample of offshore ocean DCM and 7C2 Annual Total Sr 89/90, Supplemental sediment from Diablo Cove and (grab sample) Fe-55, and Ni-63 Rattlesnake Canyon.

4 One sample from each of five AVA, MOO, Semi- Annual Gamma isotopic , Supplemental local recreational beaches. PMO, CYA, (grab sample) Total Sr 89/90, and CBA Fe-55, and Ni-63 4

e. Marine Flora One sample.of kelp DCM, PON, Quarterly Gamma .isotopic Supplemental POS, and 7C2 (when available) 4 One sample of intertidal algae DCM and 7C2 Quarterly Gamma isotopic Supplemental (when available)

Table 2.1 (continued)

Exposure Pathway Number of Representative Sampling Collection Type of Required or and/or Sample Type Samples and Sample Stations Frequency Analysis Supplemental 1

Locations

6. Ingestion

a. Milk S13mples from milking animals in 5F2 Semimonthly Gamma isotopic4 Suppleme.ntal three locations within 5 km when animals are and 1-131 distance having the highest on pasture; analysis.

dose potential. If there are none, monthly at other then one sample from milking times.

animals in each of three areas between 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location I I

15 to 30 km distant and in the least prevalent wind direction.

NOTE: The sample (5F2) should be taken monthly even if there are no indicator samples available.

4

b. Fish and One sample of rock fish (family DCM and 7C2 Quarterly Gamma isotopic Required Invertebrates Sebastes) and one sample of (grab sample) analysis on perch (family Embiotocidae) edible portions of each sample.

4 One sample of rock fish PON andPOS Quarterly Gamma isotopic Supplemental (family Sebastes) and (grab sample) analysis on one sample of perch edible portions (family Embiotocidae) of each sample.

One sample of mussel DCM and 7C2 Quarterly Gamma isotopic4 Required (family Mytilus) (grab sample) analysis on edible portions of each sample.

4 One sample of mussel PON Annual Gamma isotopic Supplemental (family Mytilus) (grab sample) analysis on edible portions of each sample.

4 One sample of mussel POS Quarterly Gamma isotopic Supplemental (family Mytilus) (grab sample) analysis on edible portions of each sample.

4 One sample of locally harvested 7D3 OR 2F1 Quarterly C?amma isotopic Supplemental market fish. (should (grab sample) analysis on alternate edible portions between of each sample.

locations)

Table 2.1 (continued)

Exposure Pathway Number of Representative Sampling Collection Type of Required or and/or Sample Type Samples and Sample Stations Frequency Analysis Supplemental Locations 1

c. Broadleaf Three samples of broadleaf Monthly Gamma isotopic4 Required Vegetation 5 vegetation grown nearest (when available) analysis (that (see notation #5) off-site locations of highest includes 1-131) calculated annual average on edible ground level D/Q !E milk portion.

sampling is not performed.

One sample of each of the Monthly Gamma isotopic4 Required similar broadleafvegetation (when available) analysis (that (see notation #5) grown 15 to 30 km distant in the includes 1-131) least prevalent wind direction !E on edible milk sampling is not performed. portion.

d. Vegetative One sample of broadleaf 5F2, 7C1, Monthly Gamma isotopic4 Supplemental Crops vegetation or vegetables or fruit and 7G1 (when available) analysis on edible portion.

One sample of broadleaf 3C1, 6C1, 7E1 Quarterly Gamma isotopic4 Supplemental ve~etation or vegetables or fruit. (as provided by analysis on land owner) edible portion.

e. Meat sample One sample of each species BCM, BGM, Quarterly Gamma isotopic4 Supplemental (cow, goat, sheep, deer, or pig) BSM, JDM, (as available and analysis, and of edible meat portion JPM,ACM, provided by land Total Sr 89/90 slaughtered for personal ADM,APM, owners within 8 on edible consumption (not mass market). CCM km of plant site) portion.

Table Notations I. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program, and submitted in the next Annual Radioactive Effluent Release Report, including a revised figure(s) and table for the ERMP reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the section of the new location(s) for obtaining samples.

2. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor. There are normally three calcium sulfate phosphors in an environmental TLD BADGE. Fihn badges shall not be used as dosimeters for measuring direct radiation.

3. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than I 0 times the yearly mean of control samples, gamma isotopic analysis shall be perf01med on the individual samples.

4. Ganuna isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

5. Ifbroadleafvegetation food products are unavailable, additional air sampling as specified in Table 2.1, Parts 2 & 3 will be done in the NNW (station ISI) and SE (Station 8S2) sectors.

6. The Branch Technical Position (Nov 79) states, "Any locatioll'from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location".

Although milk sampling performed at 5F2 is outside the 5-mile radius and is supplemental to the REMP, this notification should take place if 5F2 milk sampling ceases.

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TABLE2.2 Distances and Directions to Environmental Monitoring Stations Radial Direction** Radial Distance**

Station (True Heading) From Plant Code(a) Station Name Degrees km Miles OSI Exclusion Fence-Northwest Corner 320 0.16 0.1 OS2 North Gate 320 0.8 0.5 lSl Wastewater Pond 330 0.64 0.4 2Sl Back Road-300 m North of Plant 0 0.32 0.2 3Sl Road NW of230 kV Switchyard 23 0.64 0.4 4Sl Back Road Between Switchyards 43 0.8 0.5 5Sl 500 kV Switchyard 58 0.64 0.4 5S2 Diablo Creek Weir 65 0.96 0.6 5S3 Microwave Tower Road 70 1.02 0.7 6Sl Microwave Tower 94 0.8 0.5 7Sl Overlook Road 112 0.48 0.3 8Sl Target Range 125 0.8 0.5 8S2 Southwest Site Boundary 128 1.76 1.1 8S3 DCSF 96-1 (monitor well) 145 0.52 0.33 9Sl South Cove 167 0.64 0.4 MTl Meteorological Tower I85 0.32 0.2 DCM Diablo Cove Marine 270 0.32 0.2 WNI Northwest Guard Shack 290 0.32 0.2 WN2 Diablo Creek Outlet 283 0.25 O.IS lAI Crowbar Canyon 327 2.56 1.6 1A2 Blanchard Spring 33I 2.4 1.5 OBI Point Buchon 325 5.76 3.6 ICI Montana de Oro Camrnrround 336 7.52 4.7 3CI Ranch Vegetation 20 7.I6 4.5 4CI Clark Valley Gravel Pit 45 9.28 5.8 SCI Junction Prefumo/See Canyon Roads 64 7.52 4.7 6CI Household Garden 98 7.24 4.5 7CI Pecho Creek Ruins (Mello Farm) I20 6.56 4.I 7C2 Rattlesnake Canyon I24 7.52 4.7 2DI Sunnyside School - 10 11.04 6.9 3DI Clark Valley 24 9.92 6.2 4DI Los Osos Valley Road 36 12.16 7.6 6DI Junction See/Davis Canyon Roads 89 13.4 8.3 7Dl Avila Gate 118 10.56 6.6 7D2 Avila Beach lIO I2.I6 7.6 7D3 Avila Pier I20 I 1.0 6.9 7EI Avila Valley Barn 103 13.94 8.7 2Fl Morro Bay (Commercial Landing) 0 I7.44 10.9 2F2 Morro Bay Power Plant 358 I7.9 I 1.2 5Fl SLOOEL 79 I6.41 10.2 5F2 Cal Poly Farm 60 20.16 12.6 5F3 SLO County Health Department 70 20.32 12.7

Table 2.2 (continued)

Radial Direction** Radial Distance**

Station (True Heading) From Plant Code(a) Station Name Degrees km Miles 7Fl . Shell Beach 110 17.28 10.8 7Gl Arroyo Grande (Kawaoka Farm) 115 26.88 16.8 7G2 Oceana Substation 118 27.68 17.3 AVA Avila Beach (near pier) 109 11.75 7.3 CBA Cambria Moonstone Beach 330 45.86 28.5 CYA Cayucos Beach (near pier) 350 26.87 16.7 DYl Drywell 115' 77 0.041 0.026 DWI Drinking Water (Plant Potable Water Sys) 161 0.59 0.37 GWl Groundwater Monitoring Well 1 271 0.15 0.09 GW2 Groundwater Monitoring W~ll 2 204 0.21 0.13

rs1-rs8 ISFSI I 65 0.48 0.3 MDO Montana de Oro (Spooners Cove) 336 7.56 4.7 OWl Observation Well 01 336 0.07 0.046 OW2 Observation Well 02 157 0.07 0.045 OEL Offsite Emergency Lab 79 16.41 10.2 OUT : Plant Outfall 270 0.32 0.2 PMO Pismo Beach (near pier) 113 20.76 12.9 PON Pacific Ocean North of Diablo Cove* 305 2.4 1.5 POS Pacific Ocean South of Diablo Cove 180 0.64 0.4 WW2 Water Well 02 70 1.02 0.63 BCM Blanchard (Fa.mi.) Cow Meat 320 1.94 1.2 BGM Blanchard (Farm) Goat Meat 320 1.94 1.2 BSM Blanchard (Farm) Sheep Meat 320 1.94 1.2 CCM Control Cow Meat 328 59.5 37 JDM Johe (Property) D_eer Meat 21 5.24 3.26

The reference point used is the dome of Unit 1 containment.

Station Code (XYZ):

X - First number (0-9) represents the radial sector in which the station is located:.

0 - Northwest 5 - East-northeast 1 - North-northwest 6 - East 2 ~North 7 - East-southeast 3 - North-northeast 8 - Southeast 4 - Northeast 9 - South-southeast Y - Letter (S, A-H) represents the distance from the plant:

S - On-site A 2 miles from plant (but off-site)

B 4 miles from plant C 6 niiles from plant D 8 miles from plant E 10 miles from plant F 15 miles from plant G 20 miles from plant H - Greater than 20 miles from plant Z - Second number represents the station number within the zone.

Table 2.2 (continued)

Station Codes exceptions:

The following stations do not follow the coding system:

Diablo Cove Marine (DCM)

Montana de Oro (MDO)

Meteorological Tower (MTI)

Pismo Beach (PMO)

Northwest guard shack (WNl)

Cayucos Beach (CYA) .

Diablo Creek outlet (WN2)

Cambria Moonstone Beach (CBA)

Pacific Ocean North (PON)

Blanchard Cow Meat (BCM)

Pacific Ocean South (POS)

Blanchard Goat Meat (BGM)

Offsite Emergency Lab (OEL)

Blanchard Sheep Meat (BSM)

Plant outfall (OUT)

Control Cow Meat (CCM)

Drinking water (DWI)

Johe Deer Meat (JDM)

Water Well 02 (WW2)

Johe Pig Meat (JPM)

Observation Well 01 (OWI)

Andre Cow Meat (ACM)

Observation Well 02 (OW2)

Andre Deer Meat (ADM)

Drywell 115 (DYl)

Andre Pig Meat (APM)

Avila Beach (AVA)

ISFSI TLDs (IS 1 - IS8)

Groundwater Monitoring Well I (GWI)

Groundwater Monitoring Well 2 (GW2)

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TABLE2.3:

Detection Capabilities 'for Environmental Sample Analysis (a)

Lower Limits of Detection (LLD) (b)

Airborne Food Water Particulate or

Fish Milk Products Soil/Sediment Analvsis, ([!Ci/L} Gases (oCi/m') 3 (pCi/kgi wet} ([!Ci/L} <nCi/kf!. wet) ([!Ci/kgi drv) e Gross beta 4 0.01 H-3 400c Mn-54 15 130 150 Fe-59 30 260 300 Co-58 *15 130 "

150 Co-60 15 130 150 Zn-65 30 260 300 Zr-95 30 300 Nb-95 15 150 I-131 Id 0.07 I 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 600 La-140 15 15 150 Table Notations a) The gamma emitters and corresponding LLD values listed are derived from standard ODCM guidance for environmental samples as found in Table 4.12-1 in NUREG-1301. This list does not*

, mean th~t only th~se nuclides are to be considered. Other peaks that are identifiable, together with those of the above'nuclides, shall also be analyzed and reported in the Annual Radiological En~ironmental Operating Report. .

b) The LLD is defined, for purposes of these specifications, as the a-priori smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a* "real" signal.

c) If no drinking water pathway exists, a value of 3,000 pCi/L may be used for tritium. All groundwater wells should use the 400 pCi/L tritium value regardless of drinking water use.

d) The LLD value of 1 pCi/L for 1-131 is applicable only to sources used as drinking water.

If no drinking water pathway exists, a value of 15 pCi/L may be used forl-131.

e) The gamma emitters LLD values liste<l: for soil/sediment we derived from the Cs-134/13710:1 ratio-established in the environmental LLDs in NUREG-1301, Table 4.12-1.

TABLE 2.3 (Continued)

Table Notations For a particular measurement system, which may include radiochemical separation:

LLD 4.66sb Ex V x 2.22 x Y x exp(-A.t)

Where:

LLD the "a priori" the lower limit of detection as defined above (as pCi per unit mass or volume) the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E the counting efficiency (as counts per transformation) v the sample size (in units of mass or volume) 2.22 the number of transformations per minute per pico-curie y the fractional radiochemical yield (when applicable)

A, the radioactive decay constant for the particular radionuclide t the elapsed time between sample collection (or end of the sample collection period) and.

time of counting The value of Sb used in the calculation of the LLD for a detection system will be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background will include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).

Analyses will be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Environmental Radiological Operating Report.

Typical values ofE, V, Y and t should be used in the calculation. It should be recognized that the LLD is defined as a-priori (before the fact) limit representing the capability of a measurement system and not as a-posteriori (after the fact) limit for a particular measurement.

TABLE 2.4: Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Water Particulate or Fish Milk Food Products Analysis (pCi/L) G:\ses (pCi/m3 ) (pCi/kg, wet) (pCi/L) .(pCi/kg, wet)

I H-3

20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 ** 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

For drinking water samples. This is the 40 CPR 141 value. If no drinking water pathway exists, a value of 3D,OOO pCi/L may be used.

- If no drinking water pathway exists, a value of 20 p~i/L may be used

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Figure 2.1- Diablo Canyon Off-site Stations This page intentionally left blank.

NW Pacific Ocean 5 Mile Radius SE

~

N LEGEND I

0 5 miles

Dosimetry Station D Air Particulate Station e Biological Sampling Station

Diablo Canyon Power Plant Units 1 and 2 Diablo Canyon off-site stations.

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Figure 2.2- Diablo Canyon On-site Stations This page intentionally left blank.

4S1A

~

cu u

\

WN1A c:

J 0

Cl'.)

2 en t t 6S1A Met Building --1--1~

Met Station E _ __,,___

~

LEGEND A Dosimetry Station

Air Particulate Station N

Biological Station I

Breakwater DCPP Onsite ERMP Stations

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Figure 2.3- Diablo Canyon Station Locations Thitl page intentionally left blank.

Dosimetry Sectors N Dosimetry &Air

Biological Prote cted .Area Site Boundary A 0 250 500 1,000 1,500 2,000

-==i-==----i::::::===---- Feet

This page intentionally left blank 3.0 RADIOLOGICAL DATA-

SUMMARY

OF TABLES This section summarized the analytical results of the environmental samples collected during the monitoring period. The results were presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (NUREG-1301).

Each table was nuclide specific and the total numbers of analyses for that radionuclide were provided. Additionally, the number of measurements which exceeded the Reporting Levels (NRC Notification Level) found in Table 2.4 of this report were provided. The first column listed the matrix or pathway sampled during the period. The second column listed the nuclides analyzed and number of samples performed. The third column provided the required a-priori Lower Limit of Detection (LLD) for radionuclides that have detection capability requirements as specified in Table 2.3 of this report. The fourth, fifth, and sixth columns contained the mean and range of results for locations. The seventh column contained the number of reportable occurrences for the location pathway. Occasionally, the required LLD may not be met. An example of this

occurrence might be due to hold times between sampling and analysis. Such cases, if any, were addressed in Section 4.2 of this report.

The a-posteriori Minimum Detectable Concentration (MDC) listed for each analysis in Appendix C was used as the detection evaluation point for each sample collected. The MDC was calculated by the laboratory with each analysis (a-posteriori) and incorporated conditions observed at the laboratory during the analysis. This MDC value mathematically represents the lowest concentration of activity that could be detected by the laboratory with a 95% confidence level. The MDC was also understood as the concentration where there was only a 5% probability of falsely reporting a positive detection in a true blank sample. Note that the a-posteriori MDC equation used by the environmental lab was the same as the a-priori Lower Limit of Detection (LLD) equation specified in NUREG-1301.

For this report, a sample was considered to yield a "detectable measurement" when the "result" concentration exceeded the associated a-posteriori MDC value for that analysis.

Additionally, the tables provided the mean of all sample results analyzed for the specified radionuclide/ media type, the range, and the number of samples that were considered to have detectable activity of all the samples counted:

The mean value consisted of the average of detectable concentrations

The lowest and highest detected concentration values were listed as the range

The number of deteCtable measurements and the total number of measurements were listed. For example, (4/20) would indicate that 4 of the 20 samples collected (for that sample type and that radionuclide) contained detectable radioactivity (>MDC).

The radionuclides reported in this section represented those that:

had an LLD requirement in Table 2.3, or a Reporting Level listed in Table 2.4

were of specific interest for any other reason The radibnuclides routinely analyzed and reported w.ithin a gamma spectroscopy analysis were:

Ac-228, Ag-108m, Ag-1 lOm, Ba-140, Be-7, Bi-212, Bi-214, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131, K-40, La-140, Mn-54, Nb-95, Pb-210, Pb-212, Pb-214, Ra-224, Ra-226, Ru-103, Ru-106, Sb-124, Sb-125, Th-234, Tl-208, Zn-65, and Zr-95.

Table 3.1 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCAJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( Bl RangeCB> Mean CB) RangeCBJ Mean CB> Range(B) Occurrences Direct Radiation

( mR/std quarter) 5Sl, 0.4 mi, 58° See Table 2.2 2F2, 4Dl, 5Fl IEnv TLD Badges< C> ( 38~ 5 mR/qtr I 21.8 I 20.0 - 24.o c12112) I 16.0 11.2 - 24.o (348/348) I 13.8 110.0 - 17 .9 (36/36) I 0

~

IS4, 0.3 mi, 65° ISl - IS8 lrsFSI TLDJ. l 0

c 96 )I 5 mR/qtr I 102.2 190.8 - 113.7 c12112) I 44.1 I22.0 - 113.7 (96/96) I 0 Table Notation:

(A) Sensitivity ofTLD system

( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.

( C) 96 TLD badges are distributed quarterly at 32 locations (29 indicator stations and 3 control stations). Each quarter there are 3 badges per station.

( D ) 24 ISFSI TLD badges are distributed quarterly at 8 locations surrounding the ISFSI protected area within the site boundary. Each quarter there are 3 badges per station.

Table3.2 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115

(

Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCA) Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean<Bl Range(B) Mean (Bl Range (Bl Mean (Bl Range (Bl Occurrences Airborne Iodine (364) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79°

( pCi/meter 3

) 1~131' 0.07 I None Detected ( 0 I 52 ) I None Detected ( 0 I 312) l.14E-2 I l.14E-2 ( 11 52) 0 Airborne Air Particulates (364) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79°

( pCi/meter 3

) I GrossBetal 0.01 3.19E-2 I 8.21E-3 to 9.55E-2 ( 52/52) 2.85E-2 I 3.74E-3 to 9.55E-2 (311/312) 4.lOE-2 I 4.72E-3 to 9.78E-2 ( 51/52) 0 Gammaisotopic<Cl (28) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79° Cs-134 0.05 None Detected ( 0 I 4) None Detected ( 0 I 24 ) None Detected ( 0 I 4 ) 0 Cs-137 0.06 None Detected ( 0 / 4) None Detected ( 0 I 24 ) None Detected ( 0 I 4 ) 0 Airborne Air Carbon-14 (156) 8Sl, 0.5 mi, 125° OS2, 8Sl 5Fl, 10.2 mi, 79° 3

( uCi/meter ) Carbon-14 l.OOE-06 None Detected ( 0 I 52 ) None Detected ( 0 I 104) None Detected ( 0 I 52 ) 0 Table Notation:

(A) Unless specified, all required LLDs were met in accordance with Table 2.3

( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.

( C) These gamma isotopic samples are quarterly composite samples of all weekly particulate air sample filters. Approximately 13 particulate filters for each REMP location.

Plant related radionuclides, not naturally occurring isotopes.

Table3.3 Environmental Radiologieal Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(AJ Name, Distance, and Direction All Indicator. Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( BJ Range( BJ Mean (BJ Range (B) Mean (BJ Range (B) Occurrences Surface Water DCM, 0.2 mi, 270° DCM, OUT 7C2,4.7 mi, 124°

( pCi/Liter ) Gamma Isotopic ( 36 )

Mn-54 15 none detected (0I 12 ) none detected ( 0 I 24 ) . none detected ( 0I 12 ) 0 Fe-59 30 none detected (OJ 12) none detected ( 0 I 24 ) none detected ( 0I 12 ) 0 Co-58 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12) 0 Co-60 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Zn-65 30 none detected (0I 12 ) none detected" ( 0 I 24 ) none detected ( 0I 12 ) 0 Zr-95 30 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Nb-95 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 1-131 15 none detected ( 0I 12 ) _none detected .( 0 I 24 ) none detected (0I 12 ) 0 Cs-134 15 none detected ( 0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Cs-137 18 none detected (0I 12) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Ba-140 60 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 La 140. 15 none detected ( 0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Additional Analysis Gross Beta ( 36) 4 375 I ?15-575 (12/12) 345 I 215-575 (24/24) 322 I 130-517 (9/12) 0 Fe-55 ( 36) rione detected ( 0 I 12 ) . none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Ni-63 ( 36) none detected ( 0 I 12 ) i:tone detecied ( 0 I 24 ) none detected ( 0 I 12 ) 0 Tritium H-3 ( 36 ) 400 none detected ( 0 I 12) none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Total Sr 89/90 ( 36 ) none detected ( 0 I 12) none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Table Notation:

(A) Unless specified, all required LLDs were met in accordance with Table 2.3

( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 _samples out of 12 collected showed activity.

Table 3.4 Environmental Radiological Monitoring Program Summary Report Period: 1/1115 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County , State)

Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean<BJ Range< BJ Mean (BJ Range (BJ Mean (BJ Range CBJ Occurrences Drinking Water 5S2, 0.6 mi, 65° DWI, 5S2, WN2, 1A2 OEL, 10.2 mi, 79°

( pCi/Liter ) Gamma Isotopic ( 45 )

Mn-54 15 none detected (0/ 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Fe-59 30 none detected (0I 12 ) none detected ( 0 133 ) none detected (0/ 12 ) 0 Co-58 15 none detected (0/ 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Co-60 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0/ 12 ) 0 Zn-65 30 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 Zr-95 30 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Nb-95 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 I-131 1 none detected (0I 12 ) none detected ( 0 I 33) none detected ( 0I 12 ) 0 Cs-134 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 Cs-137 18 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Ba-140 60 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 La 140 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Additional Analysis Gross Beta ( 45) 4 7.34 I 2.64 - 13.7 c4112) 6.06 I 2.64 - 13.7 c8/33) 5.3 I I.99 - 8.62 c2112 ) 0 Fe-55 ( 45) none detected ( 0 I 12 ) none detected ( 0 I 33) none detected ( 0 I 12 ) 0 Ni-63 ( 45) none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 TritiumH-3 ( 45) 400 none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 Total Sr 89/90 ( 45 ) none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 Table Notation:

(A) Unless specified, all required LLDs were met in accordance with Table 2.3

( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means*

10 samples out of 12 collected showed activity.

Table3.5 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(Al Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( BJ Range( BJ Mean(BJ

Range(BJ Mean (BJ Range(BJ Occurrences Mussels

( pCi/kg) DCM, 0.2 mi, 270° DCM, PON, POS 7C2, 4.7 mi, 124° Gamma Isotopic (13)

Mn-54 none detected (0I 4) none detected ( 0I 9) -* none detected ( 0 I 4 ) 0 Fe-59 none detected {0I 4) none detected ( 0I 9) none detected (0I 4) 0

' Co-58 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0

- Co-60 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 Zn-65 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 Zr-95 none detected (0I 4) none detected ( 0I 9) none detected ( 0I 4 ) 0 Nb-95 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 I-131 60 none detected (0I 4) none detected (0I 9) none detected (0I 4) 0 Cs-134 60 none detected ( 0I 4 ) none detected (0I 9) none detected ( 0I 4) 0 I

Cs-137 80 none detected ( 0I4) none detected (0I 9) none detected ( 0I 4) 0 Ba-140 none detected (0I 4) none detected (0I 9) none detected ( 0I 4 ) 0 La-140 none detected (0I 4) none detected (0I 9) none detected ( 0I 4) 0 Table Notation:

(A ) Unless specified, all required LLDs were met in accordance with Table 2.3

( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.

Table 3.6 Environmental Radiological Monitoring Program Summary Report Period: 111/15 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State) l Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectiodAJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) MeanCB> RangeCBJ Mean (BJ RangeCBJ Mean CB> Range<BJ Occurrences Fish

( pCi/kg) POS, 0.4 mi, 180° DCM, PON, POS, 2Fl, 7D3 7C2, 4.7 mi, 124° Gamma Isotopic ( 37)

Mn-54 130 none detected ( 0 I 8 ) none detected ( 0 129 ) none detected ( 0 I 8 ) 0 Fe-59 260 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Co-58 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Co-60 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Zn-65 260 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Zr-95 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Nb-95 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 I-131 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Cs-134 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Cs-137 150 6.36 I 6.36 ( 1/8) 6.36 I 6.36 ( 1129) 4.78 I 4.78 ( 1/8) 0 Ba-140 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 La-140 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Table Notation:

( A ) Unless specified, all required LLDs were met in accordance with Table 2.3

( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.

Table 3.7 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Perfonned (LLD) Mean< BJ Rang~BJ Mean (BJ Range< BJ Mean<BJ Range< BJ Occurrences Algae*

( pCi/kg) DCM, 0.2 miles, 270° DCM, 0.2 miles, 270° 7C2, 4.7 miles, 124° Gamma Isotopic (4)

Mn-54 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Fe-59 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Co-58 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Co-60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Zn-65 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Zr-95 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Nb-95 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 I-131 60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Cs-134 60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Cs-137 80 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4 ) 0 Ba-140 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4 ) 0 La-140 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Table Notation:

( A ) Unless specified, all required LLDs were met in accordance with Table 2.3

( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.

These samples are supplemental samples.

Table 3.8 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/3l/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)

Lower Limit Indicator with Medium or Pathway Type and Total of Highest Anriual Mean

Number of Sampled . Number of Analyses DetectionCAJ Name, Distance, and Direction All Indicator Locations Aii Control Locations Reportable (Uhit of Measure) P()rformed (LLD) ,MeanCBJ RangeB> MeanCBJ

Range Mean Range Occurrences Kelp*

( pCi/kg) DCM, 0.2 mi, 270° DCM, PON, POS 7C2, 4.7 mi, 124° Gamma Isotopic ( 16)
Mn-54 none detected ( 0I 4 ) none detected (0I 12 ) none detected (0I4) 0 Fe-59 none detected ( 0I 4 ) none detected (0I 12 ) none detected (0I4) 0 Co-58 none* detected ( 0 I 4) none detected (0I 12 ) none detected ( 0I 4) 0 Co-60 none detected ( 0I 4 ) none detected (0I 12 ) none det~cted ( 0I 4) 0 Zn-65 none detected ( 0I 4 ) none detected (0I 12) none detected (0I 4) 0 Zr-95 - none detected ( 0I 4 ) none detected (0I 12) none detected ( 0I 4 ) 0 Nb-95 none detected (0I4) none detected (0I 12 ) none detected ( 0I 4 ) 0 1-131 60 none detected (0I4) none detected (0I 12) none detected (0I4) 0 Cs-134 60 none detected ( 0I 4 ) , none detected (0I 12 ) none detected ( 0I 4) 0 c Cs"137 80 none detected ( 0I 4 ) none detected (0I 12) none detected (0I 4) 0 Ba-140 none detected ( 0I 4 ) none detected (0I 12) none detected (0I4) 0 La-140 none detected ( 0I 4 ) none detected (0I 12 ) none detected ( 0I 4 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2 .3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity. ~
These samples ate supplemental samples.
Table3.9 Environmental Radiological Monitoring Program Summary Report Period: 1/1115 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<A> Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< Bl Range< Bl Mean (Bl Range(B) Mean (Bl Range(B) Occurrences Vegetative Crops
( pCi/kg) 6Cl, 4.5 mi, 98° 3Cl, 5F2, 6Cl, 7Cl, 7El 7Gl, 16.8 mi, 115° Gamma Isotopic ( 55 )
Mn-54 None Detected ( 014) None Detected ( 0142) None Detected (0/ 13 ) 0 Fe-59 None Detected ( 014) None Detected ( 0 I 42) None Detected (0/ 13 ) 0 Co-58 None Detected ( 014) None Detected ( 0 142) None Detected (0/ 13 ) 0 Co-60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Zn-65 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Zr-95 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Nb-95 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 I-131 60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Cs-134 60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Cs-137 80 31.0 (1/4) 31.0 ( 1/ 42) None Detected ( 0I 13) 0 Ba-140 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected ( 0I 13) 0 La-140 None Detected ( 0 I 4 ) None Detected ( 0 I 42) None Detected ( 0I 13) 0 Table Notation:
(A) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
Table 3.10 Environmental Radiological Monitoring Program Summary Report Period: 111/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< Bl Range<Bl Mean<Bi Range< Bl Mean <Bl Range<Bl Occurrences Milk
( pCi/Liter ) 5F2, 12.6 mi, 60° Iodine extraction ( 12 )
1-131 1 Not Applicable Not Applicable None Detected ( 0 / 12) 0 Gamma Isotopic ( 12 )
Mn-54 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Fe-59 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Co-58 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Co-60 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Zn-65 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Zr-95 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Nb-95 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Cs-134 15 .Not Applicable Not Applicable None Detected ( 0 /12) 0 Cs-137 18 Not Applicable Not Applicable None Detected ( 0 /12) 0 Ba-140 60 Not Applicable Not Applicable None Detected ( 0112) 0 La-140 15 Not Applicable Not Applicable None Detected ( 0 /12) 0
,p*" .. ;
I "<..><<' "' ,,,, .* ,.._
.. I I Total Sr 89/90 <12) I I Not Applicable I Not Applicable I None Detected ( 0112) I 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.11 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Perfonned (LLD) Mean< BJ RangtfB) Mean<BJ Range<BJ Mean (BJ Range<BJ Occurrences Meat
( pCi/kg)
BCM, 1.5 mi, 331° BCM, 1.5 mi, 331° CCM, 37mi, 328° Gamma Isotopic ( 8 )
Mn-54 none detected (0I 4) none detected ( 0I 4 ) none detected ( 0I 4) 0 Fe-59 none detected (0I 4) none detected (0I4) none detected ( 0I 4) 0 Co-58 none detected ( 0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Co-60 none detected (0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Zn-65 none detected ( 0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Zr-95 none detected ( 0I 4) none detected ( 0I 4 ) none detected (0I4) 0 Nb-95 none detected (0I4) none detected (0I4) none detected (0I4) 0 1-131 60 none detected ( 0I 4 ) none detected (0I4) none detected (0I4) 0 Cs-134 60 none detected ( 0I 4 ) none detected (0I4) none detected (0I4) 0 Cs-137 80 none detected (0I4) none detected (0I4) none detected (0I4) 0 Ba-140 none detected (0I4) none detected (0I4) none detected (0I4) 0 La-140 none detected (0I4) none detected ( 0I 4 ) none detected (0I4) 0 I
., .. I I Total Sr 89/90 c8) I I none detected ( 0/4 ) I none detected ( 0 I 4 ) I none detected ( 0 I 4 ) I 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis, e.g. (10/12) means 10 samples out of 12 collected showed activity.
Table 3.12 Environmental Radiological Monitoring Program Summary Report Period: 111115 -12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCA> Name, Distance, and Direction Indicator Locations Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range 8 ' Mean CB) Range Mean Range Occurrences Ocean Sediment
( pCi/kg dry ) DCM, 0.2 mi, 270° DCM, 0.2 mi, 270° 7C2, 4.7 mi, 124° Gamma Isotopic ( 4 )
Mn-54 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Fe-59 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Co-58 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Co-60 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Zn-65 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Zr-95 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Nb-95 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 I-131 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Cs-134 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Cs-137 180 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Ba-140 600 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 La-140 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Fe-55 ( 2) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Ni-63 ( 2) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Total Sr 89/90 ( 2 ) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations' is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.13 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Analyses DetectionCAl Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Peifonned (LLD) Mean< Bl RangeCBJ Mean CB> Range Mean CB> RangeCB> Occurrences Beach Sand
( pCi/kg dry ) AVA, 7.3 mi, 109° A VA, MDO, PMO, CYA CBA, 28.5 mi, 330° Gamma Isotopic ( 10 )
Mn-54 150 none detected (0I2) none detected ( 0I 8) none detected ( 0I 2 ) 0 Fe-59 300 none detected (0I2) none detected (0I 8) none detected ( 0I 2 ) 0 Co-58 150 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Co-60 150 none detected (0I 2) none detected (0/8) none detected ( 0I 2 ) 0 Zn-65 300 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Zr-95 300 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Nb-95 150 none detected (0I2) none detected (0I 8) none detected ( 0I 2) 0 I-131 none detected (0I 2) none detected (0I 8) none detected (0I2) 0 Cs-134 150 none detected ( 0I 2 ) none detected ( 0I 8) none detected (0I2) 0 Cs-137 180 none detected ( 0I 2 ) none detected ( 0I 8) none detected (0I2) 0 Ba-140 600 none detected ( 0I 2 ) none detected (0I 8) none detected (0I2) 0 La-140 150 none detected ( 0I 2 ) none detected (0I 8) none detected (0I2) 0 Fe-55 ( 10) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Ni-63 ( 10) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Total Sr 89/90 ( 10 ) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.14 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< BJ Range< BJ Mean (BJ Range<Bl Mean<Bl Range<Bl Occurrences Groundwater
( pCi/Liter ) 8S3, 0.3 mi, 145° 8S3, 0.3 mi, 145° WW2, 0.6 mi, 70° Gamma Isotopic ( 8 Mn-54 15 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Fe-59 30 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Co-58 15 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Co-60 15 none detected 0/4) none detected ( 0I 4 l none detected ( 0I 4 ) 0 Zn-65 30 none detected 0/4) none detected (. 0 I 4 1 none detected ( 0I 4 ) 0 Zr-95 30 none detected 0/4) none detected 0/4) none detected ( 0I 4 ) 0 Nb-95 15 none detected 0/4) none detected 0/4 none detected (0I 4 ) 0 I-131 15 none detected 0/4) - none detected ( 0/4 none detected (0I 4 ) 0 Cs-134 15 none detected ( 0I 4 ) none detected ( 0I 4 ) none detected (0I 4) 0 Cs-137 18 none detected (0I4) none detected (0I4) none detected (0I 4) 0 Ba-140 60 none detected (0I4) none detected (0I4) none detected (0I4) 0 La-140 15 none detected ( 0I 4 ) none detected (0I4) none detected (0I 4 ) 0 I .. ... "I .. .. l Gross Beta ( 8 4 7.79 I 1.75-21.2 ( 414) 7.79 I 1.75-21.2 ( 414) 11.8 I 4.16-39.7 (214) 0 Fe-55 ( 8) none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Ni-63 ( 8) none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Total Sr 89/90 ( 8 ) none detected ( 0 I 4 ) none detected 0/4) none detected ( 0 I 4 ) 0 TritiumH-3 ( 8) 400 none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.
Table 3.15 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< BJ Range<BJ Mean <BJ Range(B) Mean (BJ Range<BJ Occurrences Monitoring Wells DYI, 0.03 mi, 77° DYI, GWI, GW2, OWl, OW2 WW2, 0.6 mi, 70°
( pCi/Liter ) Gamma Isotopic ( 18 )
Mn-54 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Fe-59 30 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Co-58 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Co-60 15 none detected 0/2) none detected ( 0I 14 ) none detected ( 0 I 4 ) 0 Zn-65 30 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Zr-95 30 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Nb-95 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 I-131 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Cs-134 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Cs-137 18 none detected (0I2) none detected (0I 14) none detected ( 0 I 4 ) 0 Ba-140 60 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 La-140 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Gross Beta ( 18) 4 23.4 I 21.3 to 25.5 ( 2/2) 19.6 I 6.0 to 44.5 ( 12/14) 11.8 I 4.16 to 39.7 c2/4 l 0 Fe-55 ( 181 none detected 0/2) none detected ( 0 114 ) none detected ( 0 I 4 ) 0 Ni-63 ( 18) none detected 0/2) none detected ( 0 I 14 ) none detected ( 0 I 4 ) 0 Total Sr 89/90 ( 18 ~ none detected 0/2) none detected ( 0 I 14 ) none detected ( 0 I 4 ) 0 Tritium H-3 ( 19 400 7,280 I 4580 to 11,600 ( 313) 2,790 I 252 to 11,600 <10115 l none detected ( 0 I 4 ) 0
,. Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.
Note : Monitoring well tritium concentrations due to rain washout of an approved airborne discharge pathway from plant vents.
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4.0 ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 REMP SAMPLING VARIANCE I DEVIATIONS The DCPP Radiological Environmental Monitoring Program (REMP) allowed for deviations in the REMP sampling schedule "if samples were unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of sampling equipment." Such deviations did not compromise the program's effectiveness and were normally anticipated for any radiological environmental monitoring program.
The DCPP REMP included both required and supplemental samples. This section described the variances/deviations with sampling and described some of the supplemental sampling conducted during the year.
4.1.1 DIRECT RADIATION The ISFSI projects team loaded an additional 8 spent fuel dry casks onto the DCPP ISFSI pad from May 1st to July 3rd, 2015.
4.1.2 AIRBORNE RADIOACTIVITY The 2015 mean percent availability for on-site and off-site particulate and iodine (P&I) air samplers was 99.5 percent. In other words, all P&I air samplers were up and running 99.5 percent of the time. Less than 0.4 percent of run time could_be attributed to equipment problems, filter exchange, or calibration processes. Specific 2015 air sampling run time deviations were as follows:
2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months oflost run time occurred at station MTI on 3/4/ 15 due to site maintenance
6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months oflost run time occurred at stations 1S1 and 8S2 on 3/14/15 due to site maintenance
60.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of lost run time occurred at station 8S2 during the week of 3/4/15 due to air sample pump failure
149 .8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of lost run time occurred at station SF 1 during the week of 4/8/ 15 due to air sample pump failure Actual 2015 percent availabilities for each station were as follows:
OS2 = 99.9 %
lSl = 99.8 %
5Fl = 98.2 %
7Dl = 100 %
8Sl = 99.7 %
8S2 = 99.1 %
MTI = 99.9 %
Airborne C-14 supplemental sampling was performed weekly at stations 8S 1 (SE Sector), OS2 (NW Sector), and 5Fl (control station in San Luis Obispo) in 2015 .
General Engineering Labs (GEL) and DCPP REMP worked together to develop a method for sampling inorganic environmental airborne C-14 (as C0 2 ). It should be noted that C-14 lab data was reported in units ofuCi/m 3 (not pCi/m 3) within Appendix A.
GEL has monitored C-14 samples from various locations around the US. In some instances a very slight negative bias has been observed in annual data sets. The bias was not enough to mask any true positive detection ofC-14. GEL believes tills bias may be the result of the sorbent piclcing up other chemical species in the field during the week long collection. These chemical species (possibly S0 2 or N0 2 ) could cause some quenching effects in the liquid scintillation analysis and
varies by site location. This chemical interference created a net effect where some field cartridges were slightly lower in activity than laboratory blanks. The bias was less than the average two sigma method uncertainty and significantly less than the method average detection limit.
4.1.3 MARINE SAMPLES DCM supplemental quarterly intertidal algae samples were unavailable during 2015.
All remaining 2015 marine samples were collected as scheduled (including allowable variation).
The California Department of Fish and Game issued regulations prohibiting the collection of abalone along the central and southern coast of California. PG&E considers it unlikely that future collection of abalone will be allowed within the DCPP environs. The REMP has therefore ceased routine abalone sampling. Note that the sampling of abalone was previously performed and was supplemental to the REMP.
4.1.4 TERRESTRIAL SAMPLES All 2015 terrestrial samples were collected as scheduled (including allowable variation) with the following exceptions:
Supplemental Blanchard Sheep Meat (BSM) and Blanchard Goat Meat (BGM) were not available and were not provided by the rancher during all of 2015. Blanchard sheep and goats were not within 5 miles of the DCPP site in 2015 . The changes in Blanchard ranch operations were due to the ongoing severe drought conditions along the central coast of California.
4.1.5 OCEAN SURFACE WATER, DRINKING WATER, AND GROUNDWATER All 2015 water samples were collected as scheduled (including allowable variation) with the following exceptions :
Observation Well 02 (OW2) was dry during all four quarters of2015 . No OW2 monitoring well water samples were obtained in 2015.
Drywell 115 (DYi) was dry during the fourth quarter of 2015.
4.1.6 REPLICATE SAMPLES Replicate sampling was conducted within the REMP for program strength and quality. A replicate sample is an additional sample (same matrix type and station) taken independently from the original scheduled REMP sample. The replicate sample collection is performed by a different person and shipped to GEL to ensure independent analysis result correlation and method consistency.
Replicate samples were taken from:
7C2 - Ocean Sediment (2/5/15)
DCM - Ocean Sediment (2/ 19/15)
5F2 - Vegetation (6/23/15)
7GI - Vegetation (9/ 17/15)
The results of the replicate analyses were within expected correlation of routine sampling.
4.2 COMPARISON OF ACHIEVED LLDS WITH REQUIREMENTS For each analysis having an LLD requirement, criteria and process procedures were in place to achieve the calculated "a-priori " (before the fact) LLD. Meeting these process criteria satisfies the "a-priori" LLD requirements. The "a-posteriori " (after the fact) Minimum Detectable Concentration (MDC) for that analysis was also compared with the required "a-priori" (before the fact) LLD.
Table 2.3 of this report list the required "a-priori" Lower Limits of Detection (LLDs) for environmental sample analyses required by the DCPP Radiological Environmental Monitoring Program. Occasionally an LLD may have been unachievable due to sampling process situations, such as hold times between sampling and analysis.
Air sampling a-priori LLDs were not met for REMP P&I samples from 2125115 through 3/4/ 15 due to shipping weather (snow) delays.
All remaining analyzed REMP samples met the specified "a-priori" LLD requirements in 2015.
4.3 COMPARISON OF RESULTS AGAINST REMP REPORTING LEVELS NRC notification was required whenever a Reporting Level listed in Table 2.4 of this document was exceeded. Reporting Levels were the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.
It should be noted that environmental isotopic concentrations were averaged over the calendar quarter for the purposes of this comparison, and that Reporting Levels applied only to DCPP plant related effluent radioactivity.
No REMP Reporting Levels were exceeded during this 2015 monitoring period.
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4.4 DATA ANALYSIS BY MEDIA TYPE The REMP data for each media type is discussed below. A sample was considered to yield a "detectable measurement" when the resultant concentration exceeded the MDC for that analysis.
4.4.1 Direct Radiation (Environmental TLDs)
Direct radiation was continuously measured at 32 locations surrounding DCPP using Panasonic UD-814 thermo-luminescent dosimeters (TLDs). These 32 locations were made up of29 indicator stations & 3 control stations. These station TLD dosimeters were distributed and collected e:rery calendar quarter for processing. Methodology from ANSl/HPS Nl3.3 7-2014 "Environmental Dosimetry - Criteria for System Design and Implementation" was used to evaluate and report the Env TLD data. Historical background baseline values for each station were established from 1987 to 2008 Env TLD data.
DCPP enviromnental TLD results were measurements of all environmental gamma radiation sources (cosmic, terrestrial, radon, and man-made) at each station during the deployment period.
Transient and lab storage background dose contributions were subtracted prior to repotiing.
Technically, these TLDs read out in units ofmilliroentgen. Because gamma radiation has a
quality factor of approximately I for conversion from milliroentgen to millirem, the env ironmental TLD unit of reporting was converted to millirem (mr) for consistency of unit reporting and ease of exposure communications.
An evaluation of direct radiation measurements and member of public occupancy times within the site boundary indicated all federal criteria for member of public dose limits (1 OCFR20.130 I) were conservatively met. An evaluation of direct radiation measurements indicated all federal EPA 40CFR 190 criteria were conservatively met. Comparing data from the 2015 DCPP Annual Radiological Effluent Release Report (ARERR), dose to a member of the public resulting from gaseous effluent releases at DCPP was an extremely small fraction of measured Env TLD dose.
Therefore, it was concluded that gaseous effluents from DCPP had negli gible impact on measured Env TLD values.
The following chart reports the 2015 quarterly Env TLD individual station results. These indi vidual station results were compared to a Historical Quarterly Baseline value that was calculated using individual station data from 1987 to 2008.
Cha.ii column repo1iing methodology was as fo ll ows:
ND = not detected
Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseline; If_::: 5, report "ND". If > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4
Annual TLD Result= Qtr I + Qtr 2 + Qtr 3 + Qtr 4 Standard Quarter TLD Results
Annual Investigation Level Dose = Annual TLD Result - Historical Annual Baseline; If_::: I 0, repo1i "ND" . If > l 0, report value (mrem).
If "Investigation Level Dose" was detected, an evaluation of DCPP contribution was conducted ai1d explained within this report.
2015 Quarterly REMP Env TLD Analysis 2015 Annual REMP Env 11D At!aiYsis

~~

Uistorical 201 5 Standard Quarter 201 5 Qua rterly Investigation Level Historical 2015 Annual 201 5 Annual DCPP Distance Quarterly Baselin e T LD Res ults (mrcm) Dose (mrem) Ann ual Baselin e TLDResult lnvestigation Level Station ID in miles frnrem) Qtr l Qtr 2 Qtr 3 Qtr 4 Qtr I Qtr 2 Qtr 3 Qtr 4 (m rem) (mrem) Dose (mrem)
MT! 0.2 20.9 22. 1 20.3 16.7 18.6 ND ND ND ND 83.6 77.7 ND WNI 0.2 12.7 13.9 12.0 8.5 11.0 ND ND ND ND 50.8 45.4 ND OSI O. l 20.3 2 1.8 20.3 16.6 18.4 ND ND ND ND 8 1.2 77. l ND SSI 0.4 23.0 24.0 22.2 20.8 20.0 ND ND ND ND 92.0 87.0 ND 6SI 0.5 14.0 14.6 13.3 12.8 12.4 ND ND ND ND 56.0 53.1 ND 8S I 0.5 16.3 18.0 16.5 16.3 15.4 ND ND ND ND 65.2 66.2 ND 8S2 I. I 20.4 21.8 19.8 19. l 18.9 ND ND ND ND 81. 6 79.6 ND 5S3 0.7 18.6 19.3 17.8 18.2 17. 1 ND ND ND ND 74.4 72.4 ND 2F2 11.2 13.8 15.0 14.6 13.0 12.4 ND ND ND ND 55.2 55.0 ND 2Dl 6.9 12.2 14.4 13.2 12.2 10.9 ND ND ND ND 48.8 50.7 ND 4Dl 7.6 12.3 13.2 10.4 10.0 10.4 ND ND ND ND 49.2 44.0 ND 5Fl 10.2 17.7 17.9 17.0 15.7 15.4 ND ND ND ND 70.8 66.0 ND IA! 1. 6 12. 1 13.0 12.5 10.8 10.5 ND ND ND ND 48.4 46.8 ND 7D2 7.6 16.7 17.7 16.1 15.1 14.9 ND ND ND ND 66.8 63.8 ND 7G2 17.3 17.3 19.8 19.l 17.9 17. 1 ND ND ND ND 69.2 73.9 ND 7CI 4.1 18.0 18.6 17.3 16.6 15.5 ND ND ND ND 72.0 68.0 ND 7Fl 10.8 16.7 17.9 16.6 16.6 15.8 ND ND ND ND 66.8 66.9 ND OB I 3.6 10.3 l 1.8 9.8 7.2 9.3 ND ND ND ND 4 1.2 38. 1 ND 7DI 6.6 1 I.9 12.4 10.7 10.7 9.9 ND ND ND ND 47.6 43.7 ND 4C I 5.8 11.0 11.8 10.1 9.9 9.4 ND ND ND ND 44.0 41.2 ND OS2 0.5 17.l 18.0 17.0 13.9 15.3 ND ND ND ND 68.4 64.2 ND ISi 0.4 16.8 18.7 18.0 16.3 15.6 ND ND ND ND 67.2 68.6 ND 2Sl 0.2 16.9 17.5 17.2 16.0 14.7 ND ND ND ND 67 .6 65.4 ND 3SI 0.4 20.4 21.6 20.0 19.4 18.7 ND ND ND ND 8 1.6 79.7 ND 4Sl 0.5 18.9 20.4 18.7 17.5 17. 1 ND ND ND ND 75 .6 73.7 ND 7SI 0.3 18.3 2 1.1 20.0 19.0 17.5 ND ND ND ND 73.2 77.6 ND 9Sl 0.4 2 1. 7 23.6 22.3 21.1 20.2 ND ND ND ND 86.8 87.2 ND IC! 4.7 13.4 14.6 14. l 12.l 11.8 ND ND ND ND 53.6 52.6 ND SCI 4.7 16.6 16.4 l 5. 1 16.2 14.5 ND ND ND ND 66.4 62.2 ND 3D I 6.2 12.9 14.0 13.8 12.5 11.3 ND ND ND ND 5 1.6 51.6 ND 6DI 8.3 15.5 15.3 13.7 13.2 12.9 ND ND ND ND 62.0 55. 1 ND 5F3 12.7 19.8 17.5 16.3 16.0 14.7 ND ND ND ND 79.2 64.5 ND ND = not detected The 20 15 AREOR hi storical background has been determi ned using Env TLD results fro m 1987 to 2008 (before ISFSI operation). DCPP became operational in 1986.
Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseline. I f~ 5, report "ND. l f > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4 Annua l TLD Resu lt = Qtr l + Qtr 2 + Qtr 3 + Qtr 4 TLD Resu lts Arnmal Investigation Level Dose = Annua l TLD Result - Historical Annual Baseli ne. I f ~ 10, report "ND" . If > 10, report value (mrem).
See DCPP Station ID Maps in Figure 2.1 and Figure 2.2
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The following graph illustrated overall trending of Env TLDs with regard to distance from the DCPP plant site.
lnner ring, outer ring, special interest, and control stations were combined and averaged to obtain a single standard quarter value for each represented plot line.
Inner and outer ring TLD averages remained within and trended with pre-operational Env TLD ranges. DCPP operations did not affect Env TLD results.
30.0 - r - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
.,. Beginning of Start ISFSI Loact--+
plant operation - Inner Ring Stations
~-Fukushima Event
- special Interest Stations
- control Stations
- Outer Ring Stations 20.0 -l--/Yr---l--=--!.Nr----l.,.._--a--.-----,.-------A-----.---t-1\-i----!----A--.---~ Inner Ring Stations --OS1 , WN1 , OS2 ,
1S1 , 2S 1, 3S1, 4S1, 551 , 5S3, 6S1 , 7S1.
8S1 . 8S2, 9S1, and MT1 Special Interest Stations - 7F1 , 70 1, 702 , 7G2, and 5f3 Outer Ring Stations - 1A1 , 061 , 1C1 ,
201 , 301 , 4C 1, 5C1 , 60 1, and 7C1 5.0 -!------...-----------------~~~-----~
0.0+-- - - , . . . ; . - - - . . . - - -....... . - - -......- - --.----;;..,-----.......------1 1980 1985 1990 1995 2000 2005 2010 2015 2020 Year
The following graph illustrated averaged Env TLD results from the southeast sector (stations 8S 1, 8S2) and northwest sector (stations OS 1, OS2, OB 1).
These sectors were chosen for graphical trending due to their historically hjgh averaged wind directions and would therefore indicate the most gaseous effluent impact on environmental TLD results.
The southeast and northwest sectors Env TLD averages trended with pre-operational Env TLD ranges. DCPP operations did not affect Env TLD results within these sectors.
Averaged control stations (2F2, 401 , SF 1) were provided for reference.
30. o ..----~------------------.-..-------,
.., Beginning of Start ISFSI Loa~ :
plant operation
~ Fukushima Event - Southeast Sector Average 25.0 + - - - -- -- - - - -- -- - - - - - - - - - - -- - - ---1 - Northwest Sector Average
--=--Control Stations Southeast Sector - BS l end 852
'C
J Northwest Sector -081 , 052 , end 081
~ 15.0 UJ er:
E 1 0 . 0 + - - - -- -- - - - - - -- -- - - - - - - - - - T - - - - - - - - - 1 5.0 +----~----------------~---------1 0.0 +-----.,.....;...--...,...---.,...-----.---...,...-----"'.,...-"----r------!
1980 1985 1990 1995 2000 2005 2010 2015 2020 Year
Direct Radiation (ISFSI Env TLDs)
DCPP was licensed with an exclusion area boundary (i.e. site boundary) as an approximate 880 yard radius from U-1 Containment center. No permanent public access was permitted within the exclusion area. The unrestricted area (outside the site boundary) surrounding DCPP was sparsely inhabited out to five mi les from the site (ref 2015 Land Use Census within Section 8).
The direct radiation levels within a very small area surrounding the onsite ISFSI were elevated due to dry cask spent fuel storage. ISFSI pad TLD stations IS-1 through IS-8 were located adjacent to the ISFSI pad fencing (see map in Figure 2.2 of this report). The remaining onsite areas were not affected due to the ISFSI topographical elevation and placement within an onsite hillside which provided radiation shielding to the rest of the site.
The first spent fuel dry cask canister was loaded onto the ISFSI pad in Jw1e 2009. The small increase in radiation levels at the ISFSI pad prior to the first spent fuel canister load was due to storage of Radioactive Material (RAM) equipment in seatrains at the ISFSI pad prior to an outage. These seatrains of RAM were removed prior to the first load of spent fuel dry cask canisters.
Dry cask loading Campaign # 2 occurred in May 2010.
Dry cask loading Campaign # 3 occurred during the first quarter of 2012 and ended on 3/ 17/2012.
Dry cask loading Campaign# 4 occurred from August to October of2013.
Dry cask loading Campaign #5 occurred from 5/1/15 to 7/3/ 15 with the addition of8 dry casks onto the onsite ISFSI.
The following chart repo1ts the 2015 quarterly ISFSI Env TLD individual station results. These individual ISFSI station results were compared to the 1987 to 2008 Historical Quarterly Baseline value at station 5S 1. Station 5S 1 was used for historical baseline pmposes due to 5S 1 close proximity to the ISFSI pad and 5Sl pre-ISFSI historical data.
Chart column reporting methodology was as follows :
ND = not detected
Quarterly Investigation Level Dose= Standard Quarter TLD result - Historical Quarterly Baseline; If.::::: 5, report "ND". If > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4
Annual TLD Result= Qtr 1 + Qtr 2 + Qtr 3 + Qtr 4 Standard Quarter TLD Results
Annual Investigation Level Dose = Annual TLD Result - Historical Annual Baseline; If.::::: 10, report "ND". If > 10, report value (mrem).
"Investigation Level Dose" was detected at ISFSI Env TLD stations IS-3 through IS-7 due to DCPP spent fuel dry casks stored on the ISFSI pad.
An evaluation of direct radiation measurements outside the site boundary indicated all federal EPA 40CFR190 criteria for public dose limits were conservatively met.
An evaluation of direct radiation measmements and member of public occupancy times within the site boundary indicated all federal criteria for member of public dose limits (10CFR20.l30 l) were conservatively met.
The following pages also contain a pictme of the ISF SI pad and a trend graph of onsite lSFSI pad averaged TLD results (IS-1 through IS-8).
. ~~~~~~-
2015 Quarter I ISFSJ Env TLD Anal sis -~~~~~~~~~~--'
2015 Annual ISFSI Env 1LD Anal sis Historica l 2015 Standard Quarter 2015 Quarterly investigation Level Historical 2015 Ann ual 2015 Annual DCPP Distance Quarterly Baseline TLD Results (mrem) Dose (mrcm) Annua l Baseline TLDResult lnvestigation Level Sta ti on ID in miles (mrem) Qtr I Qtr2 Qtr3 Qtr4 Qtrl Qtr2 Qtr3 Qtr4 (mrem) (mrem) Dose (mrem)
IS-I 0.3 23.0 23.6 22.6 23.3 24. 1 ND ND ND ND 92.0 93.6 ND IS-2 0.3 23.0 23.9 24.2 25.5 24.4 ND ND ND ND 92.0 98.0 ND lS-3 0.3 23. 0 33. 1 36.9 49.6 48.6 10.1 13.9 26.6 25.6 92 .0 168.2 76.2 IS-4 0.3 23. 0 90.8 92.6 111 .5 l 13.7 67.8 69.6 88.5 90.7 92.0 408.6 3 16.6 IS-5 0.3 23.0 53 .3 52. 1 51.8 50.3 30.3 29.1 28.8 27.3 92.0 207.5 115.5 IS-6 0.3 23.0 49.6 48 .8 48.4 43 .5 26.6 25.8 25.4 20.5 92 .0 190.3 98. 3 IS-7 0.3 23.0 37. 0 35.6 41.5 40.4 14.0 12.6 18.5 17.4 92.0 154.5 62.5 lS-8 0.3 23.0 22.8 23.3 23 .6 22 .0 ND ND ND ND 92.0 9 1.7 ND ND = not detected Historical Baseline from REMP Stat ion 5S l was used due to proxi mi ty to LSFSI and 5SI historical pre-lSFSI monitoring time frame fro m 1987 to 2008 Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseli ne. If::; 5, report "ND". If > 5, report value (m rem).
Historical Annual Ba eline = Historical Quarterly Baseline X 4 Annual TLD Res ult = Qtr l + Qtr 2 + Qtr 3 + Qtr 4 TLD Res ults Annual Investigation Leve l Dose = Annual TLD Result - Historical Annual Baseline. If S I 0, report "ND". If > 10, report value (mrem).
See DCPP Station ID Map in Figure 2.2 The Investi gation Level quarterly and annual doses were due to spent fue l dry casks stored on the ISFS I pad.
The DCPP lSFSI Pad is located conserva ti ve ly within the DCPP site boundary (unrestr icted area).
The DCPP ISFSl Pad is topographically elevated above most of the site and is built into a hillside. These characteristics shi eld the rest of the site from ISFSI related rad iation.
No permanent public access is permitted within the DCPP site boundary (within the unrestricted area).
Access occupancy surrounding the ISFSI is isolated and co ntrolled by DCPP Security.
I OCFR20. l30 I member of public exposure and 40CFR l 90 unrestri cted area exposure were evaluated. Dose limits were not exceeded and were conservatively met.
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Onstte ISFSI Boundary TLD Stations 1..
50.0 ,__ _ _ _ _ _ISFSI
_ _Load
_ _Slart 1 - - ISFSI Sta tion a i 45.0 +---....___...~
f\ ~--A---1'-------------1 OM~* ISFSI St>Uons (AY<I) :
IS 1, IS2. ISJ. 1$4 , IS5, 1$6, 1$/ , & IS8 40.0 *- - - - --"- -- --1 1-- - - - -*~------*- -------
1i:>i
![ 35.0
i;:
w
~
30.0 *- - - - -* - - - - - - - - - - - - - - - - - - - - - - - - -
25.0 20.0 I 15.0 1-----------..-----......
2005 2010 2015 2020 2025 2030

'I 2035 Year

4.4.2 Airborne Air particulate and radioiodine samples were collected weekly from six indicator stations (MTl, OS2, lSl , 7Dl , 8Sl , and 8S2) in the DCPP environs and at one control station (5Fl). A total of 364 air particulate filters and 364 iodine cartridges were collected and analyzed as part of the normal REMP.
Natural occurring gross beta activity was detected in every weekly air particulate sample collected from all indicator and control stations. Comparison of the data showed that the mean values of gross beta activities for the indicator stations were consistent with those obtained for the control station and historical trending. Normal background gross beta values ranged from 3.7E-3 to 9.5E-2 pCi/m3 .
Gamma isotopic analyses were performed on quarterly composites of the air particulate filters from each of the REMP air stations. The midpoint date of the quarter was used to label the composite.
A total of 364 REMP weekly charcoal cartridges were analyzed for 1-131. 1-131 was detected one time at station 5Fl during the week of December 9-16, 2015. This is the control station located in San Luis Obispo (SLO). No other air stations closer to the site detected 1-131 during this time period. One possible explanation for I-131 at this location was it's proximity to the SLO sewage treatment facility (about 0.9 miles). Medical isotopes from the sewage treatment facility or from a person treated with 1-131 (thyroid ablation) in close proximity to the air sampler were the most likely sources of 1-131 detection at this location. *This I-131 detection in SLO was not due to DCPP operations.
Appendix A contains individual air sampling station data results.
4.4.3 Drinking Water and Ocean Surface Water Drinking Water Drinking water samples were collected from indicator stations DWI , 582, WN2, IA2, and control station OEL. The samples were analyzed for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55 , and Nickle-63. No plant related radionuclides were detected in any of the 2015 drinking water samples.
The results of the drinking water samples collected from both the indicator and control stations were individually listed in Appendix A.
Ocean Surface Water Ocean surface water samples were collected monthly from indicator stations OUT, DCM, and control station 7C2. The samples were analyzed for gamma emitters, gross beta, tritium, total strontium 89/90, lron-55 , and Nickle-63. No DCPP related radionuclides were detected in any of the 20 15 ocean surface water samples.
The resu lts of the surface water samples collected from both the indicator and control stations were individually listed in Appendi x A.
4.4.4 Ingestion Marine Biological Samples Mussels were collected quarterly from stations DCM, 7C2, and POS. Mussels were collected annually from station PON (due to small mussel bed/availability at station PON).
Fish samples were collected quarterly from stations DCM, PON, POS, 7C2 (control), and a local fish market (7D3 or 2F I). Market fish sam ples were locally caught fish.
Cs-137 was detected in fish at the following stations, dates, and concentrations:
7C2 Rockfish 2/5/ 15 4.78 pCi/kg
POS Perch 5122115 6.36 pCi/kg Pre-operational (pre-1985) DCPP REMP sampling observed measurable Cs-137 in fish and sediment due to atmospheric nuclear weapons testing fallout from the l 960's and l 970's. Finding Cs-137 in fish or sediment has been historically common in SLO County and the DCPP environs
due to atomic weapons testing fallout. The historical fish Cs-137 concentrations have ranged from 3 to 14 pCi/kg. These 2015 concentrations ofCs-137 detected in fish were within this range.
This Cs-137 activity was also in agreement with the 1981 California Dept of Health Services Radiological Health Branch report and was considered part of SLO County background radioactivity. The preoperational 1981 ranges ofCs-137 observed in the Diablo cove (DCM) fish were 0 to 26 pCi/kg (decay corrected 0 to 12 pCi/kg in 2015). The 1981 ranges ofCs-137 observed in market fish were 0 to 38 pCi/kg (decay corrected 0 to 17 pCi/kg in 2015). The 1981 ranges of Cs-137 observed in ocean sediment were 0 to 93 pCi/kg (decay corrected 0 to 42 pCi/kg in 20 15). The 1981 ranges ofCs-137 observed in soil were 0 to 298 pCi/kg (decay corrected 0 to 135 pCi/kg in 2015).
Another recent background source of Cs-137 into California environs was due to the March 2011 Fukushima Event and subsequent jet stream isotopic dispersion to the United States.
Because Cs-137 has an isotopic half-life of approximately 30 years, this contaminant should be detected in the DCPP environs for the next 10 to 40 years depending on initial concentration and the detection sensitivity of the REMP analyses. Cs-137 has a longer environmental half-life in coastal seawaters than in open oceans due to input sources like rain watershed runoff and storm condition sediment re-suspension.
No Cs-134 was found in these fish samples. Cs-134 has a shorter isotopic half-life (approximately 2 years), would be indicative of nuclear reactor fission products, and would not be attributed to atomic weapons testing. Because Cs-134 was absent in the REMP fish analyses; fish Cs-137 concentrations were attributed to either pre-l 980's nuclear weapons testing or Fukushima related fallout.
All other marine fish and mussel samples did not detect any DCPP related radionuclides in 2015.
The results of the marine biological samples collected from both the indicator and control stations were individually listed in Appendix A.
Marine Aquatic Vegetation Supplemental marine aquatic kelp sampling was performed quarterly at REMP sample indicator stations DCM, PON, POS, and 7C2 (control). Supplemental intertidal algae sampling was performed quarterly at REMP sample station 7C2.
Each sample was analyzed for gamma emitting radionuclides. No DCPP related isotopes were detected in 2015.
The results of the marine aquatic vegetation samples collected from both the indicator and control stations were individ ually listed in Append ix A.
Ocean Sediment and Recrea tional Beach Sampling Ocean sediment sam ples were collected annually from stations DCM and 7C2. Supplemental recreational beach sand samples were collected semi-annually from stations Avila Beach (AV A),
Montana de Oro Spooner's Cove (MDO), Pismo Beach near pier (PMO), Cayucos Morro Strand State Beach (CYA), and Cambria Moonstone Beach (CBA). Each sample was analyzed for gamma emitting radionuclides, total strontium 89/90, lron-55, and Nickle-63.
Only natural occurring isotopes where detected in the ocean sediment and recreational beach sand san1ples collected for 2015. The results were individually listed in Appendix A.
4.4.5 Vegetation (Food Crops)
Samples of broad leaf vegetation were collected monthly (when available) from two indicator stations (7C1 and 7G 1), and one control location (5F2). Supplemental samples were also collected quarterly from residence or commercial gardens at stations 3Cl, 6Cl, and 7El. The samples were analyzed for gamma emitting radionuclides and for Iodine-131 on edible portions.
No DCPP related isotopes were detected in 2015 vegetation.
The results of the vegetation samples collected from both the indicator and control stations were individually listed in Appendix A.
4.4.6 Milk There are no milking animals (for human consumption) within 5 miles of the plant site. In substitution, the DCPP REMP required additional air sampling at stations 882 and 1S1.
Supplemental samples of milk were collected monthly from Cal Poly Fann (station 5F2) due to Cal Poly dairy being the closest milk producer relative to the DCPP site and regardless of the availability of milk stations within 5 miles of the plant.
The milk samples were analyzed for gamma emitting radionuclides, Iodine-131 , and total strontium 89/90. No DCPP related radionuclides were detected in station 5F2 milk samples during 2015 .
The results of the milk samples were individually listed in Appendix A.
4.4. 7 Meat Products Meat products were collected quarterly when available or provided from landowners.
Blanchard cattle were allowed to graze on the northern lands around DCPP during 2015.
Blanchard Cow Meat (BCM) was sampled quarterly for gamma emitting radionuclides and total strontium 89/90.
Supplemental Blanchard Sheep Meat (BSM) and Blanchard Goat Meat (BGM) were not available and were not provided by the rancher during all of 2015. Blanchard sheep and goats were not within 5 miles of the DCPP site in 2015. The changes in Blanchard ranch operations were due to the ongoing severe drought conditions along the central coast of California.
Control station free range, grass fed beef sampling was conducted of ranches outside the influence of DCPP. This meat was purchased by REMP personnel from the Whole Foods Market in SLO. The control station meat consisted of Hearst Ranch beef which is located approximately 37 miles north of the DCPP site. This REMP station code was CCM (Control Cow Meat).
No DCPP related isotopes were detected in 2015 meats.
The results of the meat samples were individually listed in Appendix A.
5.0 GROUND WATER MONITORING Diab lo Canyon is committed to improving management of situations involving inadvertent radiological releases that get into onsite groundwater. This commitment reflects the nuclear industry's high standard of public radiation safety and protection of the environment. Trust and confidence on the part of local communities, California State, the NRC, and the general public is paramount to this commitment.
Groundwater gradient studies of the DCPP ISFSI site and a general assessment of sub-regional hydro-geologic conditions indicates that groundwater (subsurface) flow beneath the Diablo Canyon power block is west to northwest toward the Pacific Ocean. Any groundwater present beneath the DCPP power block was not used as a source of drinking water.
5.1 NEI 07-07 GROUNDWATER PROTECTION INITIATIVE - REPORTING 5.1.1 NEI 07-07 Objective 2.4 (b), Annual Reporting:
"Document in the AREOR all on-site ground water sample results that are included in the REMP as described in the DCPP Offsite Dose Calculation Manual (ODCM)".
Onsite groundwater monitoring points are described in the RBMP and reported in this 2015 Annual Radiological Environmental Operating Report (ARBOR) as follows:
Observation Well 01 (OWl), Observation Well 02 (OW2), Drywell 115 (DYl), DCSF96-1 (8S3),
Water Well 02 (WW2), Groundwater Well I (GWl), Groundwater Well 2 (GW2), and Diablo Creek Outlet (WN2) were used for Groundwater Protection Initiative (GPI) data reporting and were described in 2015 DCPP ARBOR Table 2.1.
5.2 GROUNDWATER SAMPLING OVERVIEW:
As part of the nuclear industry NEI 07-07 Groundwater Protection Initiative (GPI), DCPP began sampling various ground water sources in 2006. These sources included onsite monitoring wells (OWl, OW2, DYl, & 8S3), an aquifer well (WW2), Diablo Canyon creek (5S2 & WN2), and a groundwater spring (1A2). Two additional groundwater monitoring wells (stations GWl and GW2) were installed along the western side of the DCPP site on December 14, 2011. RBMP began sampling these two new wells during the first quarter of 2012.
One groundwater aquifer well (WW2) was available within the plant site boundary. This well was located about 250 feet above and to the east of the power block. WW2 was sampled quarterly for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55, and Nickle-63. No plant related radionuclides were detected in 2015.
One shallow (approximately 70 feet deep) subsurface monitoring well (8S3) was located southeast at approximately 0.3 miles from the power block. 8S3 was sampled quarterly for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55, and Nickle-63. No plant related radionuclides were detected in 2015.
Three shallow (approximately 37 to 73 feet deep) French drain system monitoring wells were located within the plant protected area and in close proximity to the containment structures, spent fuel pools, and radiologically controlled area auxiliary building. These French drain systems were labeled Observation Well 01 (OWl), Observation Well 02 (OW2), and Drywell 115 (DYl).
OW2 was not sampled in 2015 due to no water present in the well during the entire 2015 timeframe. There has been an ongoing severe drought in San Luis Obispo County which contributed to this dry well.
French drain monitoring wells OWl and DYl contained low levels of tritium throughout 2015 due to rainwater washout of gaseous tritium exiting the plant vent system (via an approved 1
effluents discharge path). These tritium concentrations were evaluated and were not due to a plant system leak or spill. This tritium was evaluated and attributed to the rain-washout of gaseous tritium exiting the plant vent system via an approved effluent discharge path. DCPP conducted rain-washout studies to document this phenomenon. These monitoring wells consisted of French drain systems that discharge into the associated monitoring well (OWl, OW2, or DYl). Rain communicated with these French drain systems via building structure to ground interfaces. Once rain water entered the monitoring wells, the water remained stagnant until another rain event caused transport. Subsequent quarterly sampling routinely indicated consistent tritium values due to monitoring well stagnation.
OWl was connected to subsurface groundwater flow fissures and routinely trends with rain fall.
DYl routinely experienced the highest rain-washout tritium concentrations due to its close proximity to the plant-vent gaseous discharge points.
The specific ranges of tritium detected in these power block monitoring wells for 2015 were as follows:
OWl - Observation Well 01 ( 1,130 to 1,590 pCi/L) 4 of 4 samples collected for tritium analysis.
OW2 - Observation Well 02; no samples collected (well dry)
DYl - Drywell 115 ( 4,580 to 11,600 pCi/L) 3 of 4 samples collected for tritium analysis.
No other DCPP related isotopes were detected in OWl, OW2, or DYL As mentioned previously, two down-gradient monitoring wells were added to the REMP in 2012.
Groundwater Well l (GWl) was located between the DCPP protected area and the cliff boundary of the Pacific Ocean. This well opening was located at approximately 85' above sea level on the same plane as the power block and was approximately 85' deep.
Groundwater Well 2 (GW2) was located between the DCPP protected area and the cliffboundary
of the Pacific Ocean. This well opening was located at approximately 85' above sea level on the same plane as the power block and was approximately 85' deep.
The specific ranges of tritium detected in GWl monitoring well for 2015 were as follows:
GWl - Groundwater Well 1 ( 252 to 306 pCi/L) 3 of 4 samples collected for tritium analysis.
This tritium was evaluated and attributed to the rain-washout of gaseous tritium exiting the plant vent system via an approved effluent discharge path.
No other DCPP related isotopes were detected in GWl or GW2 in 2015.
All other samples of groundwater at 582, 1A2, and WN2 did not indicate the presence of tritium or any other DCPP related isotopes (only NORM isotopes were observed) in 2015.
The results of groundwater sampling were individually listed in Appendix A.
Rain washout of tritium is discussed within NRC Regulatory Issue Summary (RIS) 2008-003, "Return/Re-use of Previously Discharged Radioactive Effluents".
(,
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N j
~
0
\./ELL ID 0 \./ ATER SURFACE ELEVATION LIN E OF ESTIMATED POTENTIDMETRIC SURF ACE GROUNDWATER GRADIENT MAP
~r9') cardna PACIFIC GAS AND ELECTRIC DIABLO CANYON NUCLEAR POWER PLANT FIGURE.
SITE LOCATI ON E N TRIX SAN LUIS OBISPO COUNTY, CALIFORNIA
6.0 OLD STEAM GENERATOR STORAGE FACILITY MONITORING In accordance with the DCPP Offsite Dose Calculation Manual (ODCM), the Old Steam Generator Storage Facility (OSGSF) in-building sumps were inspected quarterly. If water was found in the sump of a vault containing plant equipment, the expectation was to sample that sump water and dispose of the water per plant protocols via an approved discharge pathway.
For reference, the following equipment was placed into this OSGSF on the following dates:
3/2/08 (outage 2Rl4), four DCPP Unit Two (U-2) Steam Generators
2/14/09 (outage I RI 5), four DCPP Unit One (U-1) Steam Generators
1116109 (outage 2Rl5), one DCPP Unit Two (U-2) Reactor (Rx) Head
I 0/23/ 10 (outage IR 16), one DCPP Unit One (U-1) Rx Head As of I 0/23/10, the OSGSF contains eight old Steam Generators and two old Rx Heads.
No water was found in any OSGSF sumps during 2015 inspections.
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7.0 CROSS CHECK PROGRAM This page intentionally left blank.
8.0 DCPP LAND USE CENSUS This page intentionally left blank.
2015 DCPP Land Use Census Diablo Canyon Power Plant (DCPP) was owned and operated by Pacific Gas & Electric (PG&E) Company. PG&E owned and provided environmental stewardship to approximately 14 miles of Pacific Ocean coastline and approximately 13,000 acres surrounding the 1,000 acre DCPP site boundary. The PG&E property extended roughly from Avila Beach to Montana de Oro State Park.
DCPP was located approximately seven miles WNW of Avila Beach and approximately four miles SSE of Montana de Oro State Park.
DCPP Radiological Environmental Monitoring Program (REMP) personnel conducted a Land Use Census (LUC) in the vicinity ofDCPP for 2015. The LUC was based on Nuclear Regulatory Commission (NRC) Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants". The LUC also provided compliance with 10 CFR 50 Appendix I Section IV (B)(3); "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure".
DCPP Program Directive CY2, "Radiological Monitoring and Controls Program" required performance of a LUC. DCPP procedure RPI .IDI l, "Environmental Radiological Monitoring Procedure", required identification of the nearest milk animal, nearest residence, and the nearest broadleaf producing garden greater than 50 square meters (500 square feet) in each of the landward meteorological sectors within a radial distance of 8 kilometers (5 miles) of the Unit One Containment (CTMT) structure. A LUC was conducted at least once per year during the growing season (between Feb 15 and Dec 1) for the Diablo Canyon environs.
The 2015 LUC was conducted via a helicopter over-flight and landowner telephone interviews.
The helicopter over-flight was conducted on March 5th, 2015. Telephone interviews were conducted March 10th through November 25th, 2015. Ten individual landowners or tenants were contacted.
Milk:
No milk animals were identified within the first 8 kilometers (5 miles) of any sector.
Residences:
The nearest residence, relative to all sectors, was a small trailer located in the NNW sector about 2.42 kilometers (1.5 miles) from the plant. One ranch worker occupied this BLANCHARD trailer approximately 1 day per week (midweek) during the year.
A total of eighteen structures were identified within the 8-kilometer (5-mile) radius of the plant, which were confirmed or appear to have been occupied in 2015. A new structure (trailer) was identified in the ESE sector at 5.42 km (3.37 miles). Six abandoned structures were identified during the LUC.
The nearest residence in each sector was summarized in Table 8.
Gardens:
The LUC identified two household gardens greater than 50 square meters (500 square feet) that produced broadleafvegetation. The READ garden (REMP station 3Cl) was approximately 1/.i acre and located in the NNE sector at 7.13 kilometers (4.43 miles). The KOONZE garden (REMP station 6Cl) was approximately 500 square feet and locat_ed in the E sector at 7.43 kilometers (4.62 miles).
MELLO managed a farm in the ESE sector along the southern site access road coastal plateau.
The farm started at approximately 4.8 km (3 mi) and extended to 7.8 km (4.8 mi) from the site. This commercial farm produced no broadleaf vegetation. The farm area was about 100 acres of land with rotational planting. Commercial crops consisted of about 100% cereal grass (oat hay) and straw grass.
Less than 10 farm workers periodically occupied this area during the growing season.
Additional Land Use:
It should be noted that the term "site-boundary" referred to the area within a radius of approximately 1.2 km (0.74 mi) from the Unit One CTMT structure. The area outside the "site-boundary" was also referred to as the "unrestricted area". Much of the area outside the site-boundary was routinely used for rotational cattle grazing by five separate cattle operations. For purposes of this land use census, the five cattle ranches were called BLANCHARD, SINSHEIMER, READ, ANDRE, and MELLO.
BLANCHARD solely allowed cattle to graze within DCPP environs in 2015. BLANCHARD did not graze any goats or sheep within 8 km (5 miles) ofDCPP in 2015 due to extreme drought conditions in San Luis Obispo County.
BLANCHARD's livestock were sold under the "Old Creek Ranch" label at local farmer's markets in 2015. "Old Creek Ranch" labeled meats were sampled quarterly by REMP personnel in 2015. The REMP station codes were BCM, BGM, and BSM (if available).
SINSHEIMER had about 100 cattle outside the site-boundary in the NNE sector. These cattle were allowed to breed and about 90 calves were sold to mass market in 2015.
READ had about 72 adult cattle and 68 calves outside the site-boundary in the NNE sector.
About 68 yearling cattle were sold to mass market in 2015.
ANDRE had about 80 cattle outside the site-boundary in the ENE sector. About 80 calves were sold to mass market in ~015. ANDRE did not slaughter any cattle in 2015 for personal consumption.
MELLO managed about 800 ~attle outside the site-boundary' in the E, ESE, and SE sectors.
Harris Ranch Beef Corporation owned these cattle and sold all oftbem to mass market in 2015. MELLO did not slaughter any cattle in 2015 for personal consumption.
Two landowners (JOHE and ANDRE) harvested wild game ~or personal consumption outside the site-boundary in the NNE, NE, and ENE sectors. This wild game consisted of approximately two deer per landowner.
There was a California State Park Ranger Office in the NNW sector at 7.48 kilometers (4.65 miles) from the site. Approximately three State Parks staff personnel occupied this office from 1000 to 1500 each day (365 days per year).
There was a public campground (Islay Creek Campground) located in the NNW sector at Montana de Oro State Park at 7.36 kilometers (4.57 miles). This campground was near Spooner's Cove.
Approximately 713,000 people visited Montana de Oro State Park via day-use permit.
Approximately 22,000 people spent the night at Islay Creek Campground.
There was public access to hiking trails at the north and south ends of the PG&E property in 2015.
The Point Buchan Trail was located at the north end of PG&E property and had about 18,000 visitors in 2015. The trail traversed about 3.5 miles of coastline from Coon Creek to Crowbar Canyon.
The trail was open to the public for day hikes Thursday thru Monday from approximately 0800-1700.
Two to three people from California Land Management occupied the trail head booth near Coon Creek during operational days from 0700 to 1730. This trail was originally opened to the public on July 13, 2007.
The Pecha Coast Trail was located at the south end of PG&E property and had about 3,000 visitors in 2015. The trail was approximately 3. 7 miles long and led from the Avila Beach DCPP entrance gate to the Point San Luis Lighthouse property and up the coastline to Rattlesnake Canyon.
Access was controlled (via web-site reservation permission only) and conducted by docents. This trail was just slightly outside the 5 mile radius of the site. Pecha Coast Trail hikes were only available on Wednesdays (about 20 people) and Saturdays (about 40 people).
Thirty to forty Port San Luis Lighthouse keepers occupied the lighthouse grounds on Tuesdays, Thursdays, and Saturdays from 0800-1600. Special events were also held at the lighthouse throughout the year (e.g. weddings, fundraisers, reunions, etc). The lighthouse property was owned by the Port San Luis Harbor District.
Groundwater Protection Initiative (GPI) Review:
There were no site construction activities or spills that warranted changes to GPI monitoring frequencies, monitoring locations, contract lab analytical capabilities, or analytical detection thresholds in 2015.
There were no changes in on-site or near site groundwater usage. Groundwater beneath the site power block was not used as a source of drinking water.
Additional On-site Information:
The Old Steam Generator Storage Facility (OSGSF) was located within the site-boundary in the ENE sector (68.3 degrees) at 0.99 km (0.61 mi) from Unit One CTMT.
The following plant equipment was placed into the Old Steam Generator Storage Facility for the duration of the plant operating license on the dates indicated below.
Unit One old steam generators (4 total): 2/14/2009 Unit Two old steam generators (4 total) : 3/2/2008 Unit One old reactor head (1 total) : 10/23/2010 Unit Two old reactor head (1 total) : 11/6/2009 The on-site Independent Spent Fuel S~orage Installation (ISFSI) pad was located within the site-boundary in the ENE sector (58.47 degrees) at 0.36 km (0.22 mi) from Unit One CTMT.
DCPP loaded it's first ISFSI dry cask onto the pad on 6/23/2009.
The fifth ISFSI (dry cask) loading campaign occurred from May 1st to July 3rd in 2015.
Eight dry casks were added to the ISFSI pad in 2015.
Table 8 summarizes the nearest residence location in each meteorological sector.
The Land Use Figure shows the location of the residences and gardens in the vicinity ofDCPP.
Table8 Land Use Census 2015 Distance in Kilomet~rs (and Miles) from the center point ofU-1 CTMT Nearest Milk Animal, Residence, and Vegetable Garden
)
22Yz Degree (a) Nearest Nearest Residence Nearest Radial Sector Milk Animal Residence Azimuth Vegetable km (mi) Degree Garden km (mi)
NW None 5.76 (3.58) 325.2 None NNW None 2.42 (1.5) (b) 332.0 None N None None - None I
NNE None 5.18 (3.22) 21.5 7.13 (4.4) (c)
NE None 7.94 (4.'94) 36.4 None ENE None 7.15 (4..45) 63.8. None E None 5.97 (3.71) 89.9 7.43 (4.6) (d)
ESE None 5.42 (3.37) 122.0 5.31 (3.3) (e)
. SE None None - None Table Notation:
(a) Sectors not shown contain no land (other than islets not used. for the purposes indicated in.
thjs table) beyond the site-boundary.
(b) BLANCHARD trailer is the residence used for critical receptor calculations.
(c) The READ (station 3C1) vegetable garden is located in the NNE sector and located at the 20.24 azimuth degree. There is also a limited use residence at this location.
(d) The KOONZE (station 6Cl) vegetable garden is located in the E sector and located at the 97.52 azimuth degree. There is also a :('ull time residence at this location.
(e) The MELLO garden is the commercial farm along the westward side of the site access road; however, it does not produce broadleafvegetation. This farm extends from 4.8 km to 7.8 km (3 to 4.8 miles) from the plant.
\
NNW NW PaCific Ocean 5 Mile Radius J SE UNITS 1AND2 DIABLO CANYON SITE ~
N D Gardens or Farm I
A Residences 0 1 2 3 4 5
\
SCALE IN MILES Units 1 and 2 Diablo Canyon Power Plant Land Use Census.
9.0 DCPP WIND ROSE CHART This page intentionally left blank.
Joint requenc Distribution w*md pee d. an d. \V"md **repti"on...
Diablo Canyon Power Plant 10 eter e\*el 20 S N
39.36 4 .3$
4.8S
\\' 2.21 E 2.65 0.93 5.50
1. 10 5.17 2.01 s
Camis excluded.
0. H 6.8 1 5 19 4 2*U Rings drawn at 0% Intervals.
Wind flow is FROM the 1rections stiown.
Wind Speed ( Miles Per Hour) 603 obse<vabons wece- mi$$' 9.
PERCE! T OCC RRE CE: \ ind SpCICd ( Mib Per Hour PERC LOW ER BO N lJ O ( TEuORY
!lJ ill 4 0 1 4 1.1 0. 1 0.00 .00 1.2 0.77 0.00 1.S6 0.97 0.00 0.00 O.i6 0.* 9 .C>> 0.00
1. 8 I. 7 0,0! .00 ,$<6 0.07 0.00
~XE 1,0 0.00 00 0. 1 ~ 0.00 0_6 0.1 0.00 0.00 w 0.02 0.00 0.00
0. 1 0.09 0.00 0.00 3. 14 1.46 0. 13 1.4)7 0.3 0.00 .00 w '- 12.6 .74 4.3 0.06 .00 \V 1.)2 ...62 0.6 0.11 603 1\.1
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Joint Frequenc Di tr ibufo
\Vind peed and Wind Dlreetion Diablo Canyon o"er Pl nt 10 l\<leter e\*el 2011-2015 33.07 3.63 3.11 w 2.26 E 4.37 1.46 8 .47 2 .62 s
Cafms excluded.
Rings drawn at 10% intervals..
Wind flow i$ FROM he direciions shown.
Wind Speed (Miles Per Hour) 2155 ob$ervai*tK>ns wete mi$sing .
: Wind peed Mi ' r*r I loot) p RC 0 pc'ed {Mil P~r l!uur D II AT : ORY ATE.GORY JlIB, '11 2..2 ill w ~ DIR ~ ill 0.76 0 .:? 0.02 0.21 0.67 (),11 0.0.
0.9:? 0 7 O.ot 0I 0. I 0 .01 0.9 016 0.0 0 I 0 , 0 0 .01 0.94 o. 0 6 0.00 0 ~6 0.40 O.Ol Ul.t .06 0 .01 0.' 2 o. 0,1 0.10
1. 0 0 -. 0.07 0.49 -
Cl .62 4. 2. 4 IA 2.54 2.44 I, 6 0.79 0 .16 0.58 3.47 6.65 10.41 6 .95 *U 1.94 2.0 - I. ~ 0-26 or 0.47 I . .S. 2.35 1.62 0.45 0. 19 Tffr OB ' = 4 1 69* Ml"SL (j(JIJ} ' = 2 155 c LMOHS = 0
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10.0 REFERENCES
1. DCPP Interdepartmental Administrative Procedure (IDAP), RPl.IDl 1, "Environmental Radiological Monitoring Procedure." *
2. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (NUREG-1301)
\ I
3. DCPP Program Directive, CY2, "_Radiological Monitoring and Controls Program."
4. NEI 07-07, "Industry Ground Water Protection- Final Guidance Document", August 2007
5. NRC Regulatory Issue Summary 2008-03, "Return/Re-use of Previously Discharged Radioactive Effluents"; February 13, 2008
6. "Groundwater Gradient Analysis", by Entrix Corporation, March 2010
7. "Groundwater Gradient Analysis", by Cardno/Entrix Corporation, June 2012
8. Diablo Canyon Power Plant Site Conceptual Model Report, by ERM July 30, 2014
9. ANSI/RPS Nl3.37-2014, "Environmental Dosimetry - Criteria for System Design and Implementation"
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APPENDIX A ANALYTICAL SAMPLE RESULTS
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2015 DCPP REMP Analysis Results Appendix A OS2 North Gate - Air Charcoal Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units OS2 North Gate(364535014 -AC 3-Jan-15 lodine-131 1.60E-03 9.77E-03 5.48E-03 pCi/m3 OS2 North Gate 365107014 -AC 1O-Jan-15 lodine-131 1.99E-04 1.37E-02 7.98E".03 pCi/m3
OS2 North Gate(365598014 -AC 17-Jan-15 lodine-131 5.34E-03 1.28E-02 7.32E-03 pCi/m3 OS2 North Gate 366039014 -AC 24-Jan-15 lodine-131 4.34E-03 9.72E-03 5.69E-03 pCi/m3 OS2 North Gate(366510014) -AC 31-Jan-15 lodine-131 3.02E-03 1.12E-02 6.47E-03 pCi/m3 OS2 North Gate(367027013)-AC 7-Feb-15 lodine-131 -2.25E-03 7.45E-03 4.74E-03 pCi/m3 OS2 North Gate 367398014 -AC 14-Feb-15 lodine-131 -1.89E-04 1.44E-02 8.42E-03 pCi/m3 OS2 North Gate 367754014) -AC 21-Feb-15 lodine-131 2.49E-03 1.40E-02 8.00E-03 pCi/m3 OS2 North Gate 368316014 -AC 28-Feb-15 lodine-131 3.37E-03 1.74E-02 9.99E-03 pCi/m3 OS2 North Gate 368671014 -AC 7-Mar-15 lodine-131 3.09E-03 1.04E-02 5.88E-03 pCi/m3 OS2 North Gate(369085014) - AC 14-Mar-15 lodine-131 5.65E-04 8.75E-03 5.11E-03 pCi/m3 OS2 North Gate 369559014 -AC 21-Mar-15 lodine-131 -4.99E-03 1.23E-02 8.06E-03 pCi/m3 OS2 North Gate(369948013) - AC 28-Mar-15 lodine-131 5.50E-04 1.01E-02. 6.05E-03 pCi/m3 OS2 North Gate 370730013 -AC 4-Apr-15 lodine-131 9.09E-04 9.94E-03 5.89E-03 pCi/m3 OS2 North Gate(371198013) -AC 11-Apr-15 lodine-131 -9.01E-04 9.57E-03 5.85E-03 pCi/m3 OS2 North Gate 371634014 -AC 18-Aor-15 lodine-131 -6.56E-04 8.38E-03 4.97E-03 oCi/m3 OS2 North Gate 372080014 -AC 26-Aor-15 lodine-131 -1.85E-03 7.50E-03 4.85E-03 oCi/m3 OS2 North Gate(372573014)-AC 2-Mav-15 lodine-131 -1.70E-03 1.52E-02 9.14E-03 pCi/m3 OS2 North Gate 373065014 -AC 9-Mav-15 lodine-131 2.91E-03 1.22E-02 6.82E-03 oCi/m3 OS2 North Gate 373540014 - AC 16-Mav-15 lodine-131 8.29E-03 1.33E-02 7.94E-03 oCi/m3 OS2 North Gate 373878013 -AC 23-May-15 lodine-131 1.53E-03 1.04E-02 5.93E-03 pCi/m3 OS2 North Gate 374367015 -AC 30-May-15 lodine-131 -3.48E-03 7.33E-03 5.25E-03 pCi/m3 OS2 North Gate(37 4810010 - AC 6-Jun-15 lodine-131 -3.27E-03 1.02E-02 8.05E-03 pCi/m3 OS2 North Gate 375327013 -AC 13-Jun-15 lodine-131 1.82E-03 9.78E-03 5.71E-03 oCi/m3 OS2 North Gate 375745013 -AC 20-Jun-15 lodine-131 -1.34E-03 8.37E-03 5.28E-03 pCi/m3 OS2 North Gate 376116012 -AC' 27-Jun-15 lodine-131 4.29E-03 1.16E-02 7.08E-03 oCi/m3 OS2 North Gate 376776015 -AC 4-Jul-15 lodine-131 1.01E-02 1.82E-02 1.06E-02 oCi/m3 OS2 North Gate 37730601.3 -AC 11-Jul-15 lodine-131 2.28E-03 1.88E-02 1.10E-02 oCi/m3 OS2 North Gate 377783013 -AC 18~Jul-15 lodine-131 -2.45E-03 8.83E-03 5.80E-03 oCi/m3 OS2 North Gate 378239013 - AC 25-Jul-15 lodine-131 4.51 E-03 1.24E-02 7.79E-03 oCi/m3 OS2 North Gate 378741010 -AC 1-Auo-15 lodine-131 -8.91E-04 1.22E-02 7.62E-03 oCi/m3 OS2 North Gate(379291013 -AC 8-Auo-1.5 lodine-131 4.33E-03 1.06E-02 5.92E-03 oCi/m3 OS2 North Gate 379712013 -AC 15-Aug-15 lodine-131 -1.51E-04 1.67E-02 1.01 E-02 pCi/m3 OS2 North Gate 380128014 -AC 22-Aug-15 lodine-131 5.97E-04 9.31E-03 6.29E-03 pCi/m3 OS2 North Gate 380527013 -AC , 29-Aug-15 lodine-131 -2.08E~03 1.15E-02 7.26E-03 pCi/m3 OS2 North Gate 380911013 -AC 5-Sep-15 lodine-131 -1.75E-03 9.14E-03 5.86E-03 pCi/m3 OS2 North Gate 381297013 -AC 12-Sep-15 lodine-131 -3.01E-03 1.65E-02 1.05E-02 pCi/m3 OS2 North Gate 381776013 -AC 19-Sep-15 lodine-131 4.98E-03 9.16E-03 5.15E-03 pCi/m3 OS2 North Gate 382121013 -AC 26-Sep-15 lodine-131 -2.12E-03 8.82E-03 6.53E-03 pCi/m3 OS2 North Gate 382853013 -AC 3-0ct-15 lodine-131 -6.53E-03 1.16E-02 8.92E-03 pCi/m3 OS2 North Gate 383405002 -AC 10-0ct-15 lodine-131 2.01 E-03 1.10E-02 6.37E-03 pCi/m3 OS2 North Gate 383823013 -AC 17-0ct-15 lodine-131 3.00E-03 1.20E-02 6.90E-03 pCi/m3 OS2 North Gate 384293003 -AC 24-0ct-15 lodine-131 3.23E-03 7.95E-03 5.58E-03 pCi/m3 Page.1 of91
2015 DCPP REMP Analysis Results Appendix A OS2 North Gate. 384829014) - AC 31-0ct-15 lodine-131 3.67E-03 1.17E-02 6.73E-03 pCi/m3 OS2 North Gate 385443013 -AC 7-Nov-15 lodine-131 -4.22E-04 1.10E-02 6.55E-03 pCi/m3 OS2 North Gate 385912004) -AC 14-Nov-15 lodine-131 -5.68E-03 1.07E-02 7.78E-03 pCi/m3 OS2 North Gate 386331002 -AC 21-Nov-15 lodine-131 -1.41E-03 1.48E-02 8.81E-03 pCi/m3 OS2 North Gate 386665015) - AC 28-Nov-15 lodine-131 8.54E-04 9.93E-03 6.08E-03 pCi/m3 OS2 North Gate 387181015 -AC 5-Dec-15 lodine-131 9.59E-04 8.82E-03 5.00E-03 pCi/m3 OS2 North Gate 387767014 -AC 12-Dec-15 lodine-131 1.48E-04 1.01E-02 5.84E-03 pCi/m3 OS2 North Gate(388120014) - AC 19-Dec-15 lodine-131 -2.10E-03 1.40E-02 8.55E-03 pCi/m3 OS2.. North Gate 388206014 -AC 25-Dec-15 lodine-131 -3.47E-03 1.38E-02 9.06E~03 pCi/m3
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OS2 North Gate -Air Carbon 14 Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units OS2 North Gate 364535017) - AC14 3-Jan-15 Carbon-14 1.76E-07 5.50E-07 3.31E-07 uCi/m3 OS2 North Gate 365107017 -AC14 10-Jan-15 Carbon-14 1.85E-07 6.26E-07 3.76E-07 uCi/m3 OS2 North Gate 365598017)-AC14 17-Jan-15 Carbon-14 -2.46E-07 6.36E-07 3.74E-07 uCi/m3 OS2 North Gate 366039017 -AC14 24-Jan-15 Carbon-14 3.55E-07 6.57E-07 3.98E-07 uCi/m3 OS2 North Gate(366510017) -AC14 / 31-Jan-15 Carbon-14 4.91E-07 6.78E-07 4.13E-07 uCi/m3 OS2 North Gate(367027017) -AC14 7-Feb-15 Carbon:.14 -1..70E-07 6.20E-07 3.66E-07 uCi/m3 OS2 North Gate 367398017 -AC14 14-Feb-15 Carbon-14 4.65E-08 6.77E-07 4.04E-07 uCi/m3 OS2 North Gate(367754017) -AC14 21-Feb-15 Carbon-14 4.36E-08 6.30E-07 3.76E-07 uCi/m3 OS2 North Gate 368316017 -AC14 28-Feb-15 Carbon-14 3.54E-07 6.23E-07 3.78E-07 uCi/m3 OS2 North Gate 368671017 -AC14 7~Mar-15 Carbon-14 3.07E-07 5.64E-07 3.42E-07 uCi/m3 OS2 North Gate 369085017 -AC14 14-Mar-15 Carbon-14 4.50E-07 5.95E-07 3.64E-07 uCi/m3 OS2 North Gate 369559017 -AC14 21-Mar-15 Carbon-14 1.42E-07 5.91E-07 3.55E-07 uCi/m3 OS2 North Gate(369948015)-AC14 28-Mar-15 Carbon-14 -1.27E-07 6.03E-07 3.57E-07 uCi/m3 OS2 North Gate 370730015 -AC14 4-Aor-15 Carbon-14 -2.39E-07 5.96E-07 3.50E-07 uCi/m3 OS2 North Gate 371198015 -AC14 11-Aor-15 Carbon-14 -1.82E-07 6.38E-07 3.77E-07 uCi/m3 OS2 North Gate 371634017 -AC14 18-Aor-15 Carbon-14 2.09E-07 6.23E-07 3.75E-07 uCi/m3 OS2 North Gate 372080017) -AC14 26-Aor-15 Carbon-14 3.62E-09 6.42E-07 3.83E-07 uCi/m3 OS2 North Gate(372573017) -AC14 2-Mav-15 Carbon-14 -3.34E-07 6.89E-07 4.04E-07 uCi/m3 OS2 North Gate 373065017 -AC14 9-Mav-15 Carbon-14 8.89E-08 6.87E-07 4.11E-07 uCi/m3 OS2 North Gate 373540015 -AC14 16-Mav-15 Carbon-14 -5.18E-07 6.32E-07 3.67E-07 uCi/m3 OS2 North Gate 373878015 -AC14 23-Mav-15 Carbon-14 -4.79E-07 7.02E-07 4.09E-07 uCi/m3 OS2 North Gate 374367016 -AC14 30-Mav-15 Carbon-14 1.52E-07 6.80E-07 4.08E-07 uCi/m3 OS2 North Gate 374810017 -AC14 6-Jun-15 Carbon-14 -1.14E-08 6.57E-07 3.91E-07 uCi/m3 OS2 North Gate 375327015)-AC14 13-Jun-15 Carbon-14 -1.33E-07 5.12E-07 3.03E-07 uCi/m3 OS2 North Gate 375745015 -AC14 20-Jun-15 Carbon-14 -3.27E-07 6.09E-07 3.57E-07 uCi/m3 OS2 North Gate 376116014 -AC14 27-Jun-15 Carbon-14 -7.95E-09 5.50E-07 3.27E-07 uCi/m3 OS2 North Gate 376776017 -AC14 4-Jul-15 Carbon-14 1.28E-07 6.11E-07 3.66E-07 uCi/m3 OS2 North Gate 377306015)-AC14 11-Jul-15 Carbon-14 1.00E-07 5.92E-07 3.55E-07 uCi/m3 OS2 North Gate 377783015) - AC14 18-Jul-15 Carbon-14 -1.55E-07 6.09E-07 3.60E-07 uCi/m3 OS2 North Gate 378239015 -AC14 25-Jul-15 Carbon-14 5.74E-07 5.89E-07 3.62E-07 uCi/m3 OS2 North Gate 378741012 -AC14 1-Aug-15 Carbon-14 3.40E-07 5.43E-07 3.30E-07 uCi/m3 OS2 North Gate 379291015 -AC14 8-Aug-15 Carbon-14 7.43E-08 5.78E-07 3.46E-07 uCi/m3 OS2 North Gate 379712015 -AC14 15-Aug-15 Carbon-14 3.83E-08 6.02E-07 3.60E-07 uCi/m3 Page 2 of 91
2015 DCPP REMP Analysis Results Ap.pendix. A OS2 North Gate(380128017)-AC14 22-Aug-15 Carbon-14 -4.23E-07 6.32E-07 3.69E-07 uCi/m3 OS2 North Gate(380527015) -AC14 29-Aug-15 Carbon-14 3.34E-08 6.00E-07 3.58E-07 uCi/m3 OS2 North Gate(380911015)-AC14 5-Sep-15 Carbon-14 -1.02E-07 6.50E-07 3.85E-07 uCi/m3 OS2 North Gate(381297015 -AC14 12-Sep-15 Carbon-14 -4.38E-07 5.70E-07 3.32E-07 uCi/m3 OS2 North Gate(381776015 -AC14 19-Sep-15 Carbon-14 -1.08E-07 5.89E-07 3.49E-07 uCi/m3 OS2 North Gate(382121015 -AC14 26-Sep-15 Carbon-14 -1.91 E-07 5.22E-07 3.07E-07 uCi/m3 OS2 North Gate(382853015) -AC14 3-0ct-'15 Carbon-14 2.49E-07 5.60E-07 3.38E-07 uCi/m3 OS2 North Gate(383405001) -AC14 \ 10-0ct-15 Carbon-14 4.28E-07 5.68E 3.46E-07 uCi/m3 OS2 North Gate(383823015 -AC14 17-0ct-15 Carbon-14 1.14E-07 5.25E-07 3.15E-07 uCi/m3 OS2 North Gate(384293017) -AC14 24-0ct-15 Carbon-14 2.18E-07 5.60E-07 3.37E-07 uCi/m3 OS2 North Gate(384829017 -AC14 31-0ct-15 Carbon-14 -2.38E-07 5.40E-07 3.17E-07 uCi/m3 OS2 North Gate(385443015) -AC14 7-Nov-15 Carbon~14 -1.86E-07 5.37E-07 3.17E-07 uCi/m3 OS2 North Gate(385912003)-AC14 14-Nov-15 Carbon-14 1.91E-07 5.67E-07 3.41E-07 uCi/m3 OS2 North Gate(386331001 -AC14 21-Nov-15 Carbon-14 2.11E-07 6.56E-07 3.95E-07 uCi/m3 OS2 North Gate(386665017 -AC14 28-Nov-15 Carbon-14 -3.86E-07 5.32E-07 3.11 E-07 uCi/m3 OS2 North Gate(387181016 -AC14 5-Dec-15 Carbon-14 -2.88E-07 5.96E-07 3.50E-07 uCi/m3 OS2. North Gate(387767015) - AC 14 12-Dec-15 Carbon-14 -5.35E-08 5.57E-07 3.31E-07 uCi/m3 OS2 North Gate(388120015 -AC14 19-Dec-15 Carbon-14 -5.17E-07 6.87E-07 4.00E-07 uCi/m3 OS2 North Gate(388206015 -AC14 25-Dec-15 Carbon-14 -1.63E-07 6.27E-07 3.71E-07 uCi/m3
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l OS2 North Gate - Air Particulate Samole Name Date Collected Nuclide Result MDC 2 Sicima TPU Units OS2 North Gate 364535007 -AP .3-Jan-15 BETA 5.46E-02 1.24E-03 1.21E-02 oCi/m3 OS2 North Gate 365107007 - AP 10-Jan-15 BETA 8.02E-02 1.26E-03** 1.16E-02 oCi/m3 OS2 North Gate(365598007) - AP
17-Jan-15 BETA 4.17E-02 1.26E-03 1.15E-02 pCi/m3 OS2 North Gate 366039007 - AP 24-Jan-15 BETA 4.74E-02 ~
1.38E-03 1.22E-02 pCi/m3 OS2 North Gate 366510007 -AP 31-Jan-15 BETA 7.45E-02 1.50E-03 1.14E-02 pCi/m3 OS2 North Gate 367027006 - AP 7-Feb-15 BETA 3.23E-02 1.27E-03 1.34E-02 pCi/m3 OS2 North Gate 367398008 - AP 14-Feb-15 BETA 3.69E-02 1.55E-03 1.32E-02 pCi/m3 OS2 North Gate(367754007) - AP 21-Feb-15 BETA 5.95E-02 1.40E-03 1.27E-02 pCi/m3 OS2 North Gate 368316007 -AP 28-Feb-15 BETA 1.51E-02 1.37E-03 1.16E-02 pCi/m3 OS2 North Gate 368671007 -AP 7-Mar-15 BETA 5.87E-02 1.36E-03 1.16E-02 pCi/m3 OS2 North Gate 369085007 - AP 14-Mar-15 BETA 2.??E-02 1.39E-03 1.31E-02 pCi/m3 OS2 North Gate 369559007 - AP 21-Mar-15 BETA 2.27E-02 1.38E-03 1.06E-02 pCi/m3 OS2 North Gate 369948014 -AP 28-Mar-15 BETA 1.71E-02 1.35E-03 1.07E-02 pCi/m3 OS2 North Gate 370730014 -AP . 4-Aor-15 BETA. 1.60E-02 1.49E-03 1.01 E-02 pCi/m3 OS2 North Gate 371198014 -AP 11-Apr-15 BETA 8.44E-03 1.36E-03 1.14E-02 pCi/m3 OS2 North Gate 371634007 -AP 18-Aor-15 BETA 2.86E-02 1.37E-03 1.10E-02 pCi/m3 OS2 North Gate 372080007 -AP 26-Aor..:15 BETA 1.97E-02 1.57E-03 1.07E-02 pCi/m3 OS2 North Gate 372573007 -AP 2-May-15 BETA 2.44E-02 1.48E-03 1.08E-02 oCi/m3 OS2 North Gate 373065007 -AP 9-May-15 BETA 1.32E-02 1.36E-03 1.05E-02 pCi/m3 OS2 North Gate 373540013 -AP 16-Mav-15
BETA 1.23E-02 1.47E-03 1.05E-02 pCi/m3 OS2 North Gate 373878014 -AP 23-May-15 BETA 9.04E-03 1.44E-03 1.31E-02 pCi/m3 OS2 North Gate 374367009 -AP 30-May-15 BETA 1.21E-02 1.36E-03 9~64E-03 pCi/m3 OS2 North Gate 374810011 -AP 6-Jun-15 BETA 9.38E-03 1.55E-03 1.30E-02 oCi/m3 Page 3 of 91
2015 DCPP REMP Analysis Results Appendix A OS2 North Gate(375327014) -AP 13-Jun-15 BETA 9.52E-03 1.44E-03 1.11E-02 pCi/m3 OS2 North Gate(375745014) -AP 20-Jun-15 BETA 1.84E-02 1.45E-03 1.14E-02 pCi/m3 OS2 North Gate(376116013) - AP 27-Jun-15 BETA 1.05E-02 1.35E-03 1.06E-02 pCi/m3 OS2 North Gate 376776016 -AP 4-Jul-15 BETA 4.79E-03 1.39E-03 1.15E-02 oCi/m3 OS2 North Gate(377306014 -AP 11-Jul-15 BETA- 7.36E"03 1.25E-03 1.08E-02 pCi/m3 OS2 North Gate 377783014 -AP 18-Jul-15 BETA 1.78E-02 1.26E-03 1.02E-02 pCi/m3 OS2 North Gate(378239014) -AP 25-Jul-15 BETA 1:89E-02 1.30E-03 8.?0E-03 pCi/m3 OS2 North Gate(378741011) - AP 1-Aug-15 BETA 2.09E-02 1.26E-03 9.?0E-03 pCi/m3 OS2 North Gate 379291014)-AP 8-Aug"'.15 BETA 1.72E-02 1.37E-03 1.06E-02 oCi/m3 OS2 North Gate 379712014)-AP 15-Aug-15 BETA .1.84E-02 1.32E-03 1.05E-02 pCi/m3 OS2 North Gate 380128007 -AP 22-Aug~15 BETA 3.57E-02 1.40E-03 1.32E-02 oCi/m3 OS2 North Gate(380527014) -AP 29-Aug-15 BETA 1.40E-02 1.34E-03 1.11E-02 pCi/m3 OS2 North Gate(380911014)-AP 5-Sep-15 BETA 2.98E-02 1.35E-03 9.78E-03 pCi/m3 OS2 North Gate 381297014 -AP 12-Sep-15 BETA 2.17E-02 1.42E-03 1.20E-02 pCi/m3 OS2 North Gate(381776014) -AP 19-Sep-15 BETA 2.14E-02 1.48E-03 1.09E-02 pCi/m3 OS2 North Gate 382121014 -AP 26-Sep-15 BETA 2.11E-02 1.33E-03 9.64E-03 pCi/m3 OS2 North Gate(382853014) -AP 3-0ct-15 BETA 2.78E-02 1.43E-03 1.19E-02 pCi/m3 OS2 North Gate 383405003 - AP 10-0ct-15 BETA 4.50E-02 1.42E-03 1.12E-02 oCi/m3 OS2 North Gate 383823014 -AP 17-0ct-15 BETA 3.26E-02 1.42E-03 1.22E-02 oCi/m3 OS2 North Gate(384293006) - AP 24-0ct-15 BETA 3.?0E-02 1.65E-03 1.01 E-02 pCi/m3 OS2 North Gate 384829007 -AP 31-0ct-15 BETA 1.88E-02 1.68E-03 8.30E-03 pCi/m3 OS2 North Gate 385443014 -AP 7-Nov-15 BETA 2.50E-02 1.75E-03 8.78E-03 oCi/m3 OS2 North Gate 385912005 -AP 14-Nov-15 BETA 3.89E-02 1.75E-03 8.61E-03 oCi/m3 OS2 North Gate 386331003 i-AP 21-Nov-15 BETA 3.26E-02 1.84E-03 8.36E-03 oCi/m3 OS2 North Gate(386665016)-AP 28-Nov-15 BETA 5.89E-02 1.32E-03 9.00E-03 pCi/m3 OS2 North Gate 387181014) -AP 5-Dec-15 BETA 3.78E-02 1.51 E-03 1.08E-02 oCi/m3 OS2 North Gate 387767013 -AP 12-Dec-15 BETA 8.23E-03 1.61E-03 1.05E-02 pCi/m3 OS2 North Gate 388120013 -AP 19-Dec-15 BETA 1.15E-02 1.88E-03 9.82E-03 oCi/m3 OS2 North Gate 388206013 -AP 25-Dec-15 BETA 1.73E-02 1.58E-03 8.80E-03 oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Beryllium-? 1.43E-01 1.13E-02 2.24E-02 oCi/m3 OS2 North Gate 377522007 - AP 16-May-15 Bervllium-7 8.18E-02 1.00E-02 1.60E-02 oCi/m3 OS2 North Gate1 383567007 -AP 15-Aug-15 Bervllium-7 9.85E-02 7.76E-03 1.93E-02 oCi/m3 OS2 North Gate 389387007 -AP 14-Nov-15 Bervllium-7 1.20E-01 9.79E-03 1.94E-02 - oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Cesium-134 6.49E-05 7.29E-04 4.14E-04 oCi/m3 OS2 North Gate 377522007 -AP 16cMav-15 Cesium-134 -1.52E-04 7.74E-04 4.97E-04 oCi/m3 OS2 North Gate 383567007 -AP 15-Aug-15 Cesium-134 -2.65E-04 5.47E-04 4.31E-04 oCi/m3 OS2 North Gate 389387007 i-AP 14-Nov-15 Cesium-134 -2.54E-04 4.65E-04 4.23E-04 oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Cesium-137 1.48E-04 6.47E-04 3.69E-04 oCi/m3 OS2 North Gate 377522007) - AP 16-May-15 Cesium~137 3.57E-04 6.05E-04 3.20E-04 oCi/m3 OS2 North Gate 383567007) - AP 15-Aug-"15 Cesium-137 2.04E-05 6.23E-04 3.76E-04 oCi/m3 OS2 North Gate 389387007) - AP I 14-Nov-15 Cesium-137 -8.35E-05 4.60E-04 3.53E-04 oCi/m3
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Page 4 of 91
2015 DCPP REMP Analysis Results Appendix A 1A2 Bl anch ard Spnng - Drinkino Water Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units 1A2 Blanchard Spring(365880002) - OW 26-Jan-15 BETA -4.82E-01 2.37E+OO 1.41 E+OO pCi/L 1A2 Blanchard Sorino(371630005 - OW 21-Aor-15 BETA 2.73E+OO 2.23E+OO 1.54E+OO pCi/L 1A2 Blanchard Spring(377777002) - OW / 21-Jul-15 BETA 2.04E+OO 2.82E+OO 1.77E+OO pCi/L 1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 BETA 2.73E+OO 3.58E+OO 2.27E+OO pCi/L 1A2 Blanchard Spring(387205001) - OW 8-Dec-15 BETA 1.19E-01 2.53E+OO 1.52E+OO pCi/L 1A2*Blanchard Spring(365880002 - OW 26-Jan-15 Barium-140 4.81E-01 9.26E+OO 5.40E+OO pCi/L 1A2 Blanchard Sprino(371630005 - OW 21-Apr-15 Barium-140 -1.74E+OO 8.85E+OO 5.26E+OO pCi/L 1A2 Blanchard Spring 377777002 - DW 21-Jul-15 Barium-140 6.47E+OO 1.04E+01 6.54E+OO pCi/L 1A2 Blanchard Sprino(383939001 - DW 21-0ct-15 Barium-140 -1.40E+OO 9.81E+OO 5.84E+OO pCi/L 1A2 Blanchard Spring(387205001) - OW 8-Dec-15 Barium-140 3.26E+OO 8.90E+OO 5.45E+OO pCi/L 1A2 Blanchard Spring(365880002)- OW 26-Jan-15 Cesium-134 4.65E-01 2.32E+OO 1.38E+OO pCi/L 1A2 Blanchard Spring 371630005 - OW 21-Apr-15 Cesium-134 3.55E-01 2.09E+OO 1.24E+OO oC.i/L 1A2 Blanchard Spring(377777002) - DW 21-Jul-15 Cesium-134 -2.83E-01 2.24E+OO 1.39E+OO pCi/L 1A2 Blanchard Spring 383939001 -DW 21-0ct-15 Cesium-134 1.06E+OO 2.00E+OO 1.93E+OO oCi/L 1A2 Blanchard Spring(387205001 -DW 8~Dec-15 Cesium-134 -4.80E-01 1.94E+OO 1.20E+OO pCi/L 1A2 Blanchard Spring(365880002 -DW 26-Jan-15 Cesium-137 1.81E-01 2.22E+OO 1.50E+OO oCi/L 1A2 Blanchard Sorina(371630005 -DW 21-Apr-15 Cesium-137 5.14E-01 1.95E+OO 1.30E+OO pCi/L 1A2 Blanchard Spring(377777002) - OW 21-Jul-15 Cesium-137 -5.60E-01 2.31E+OO 1.44E+OO pCi/L 1A2 Blanchard Sorina(383939001 - OW 21-0ct-15 Cesium-137 -6.96E-01 1.93E+OO 1.22E+OO pCi/L 1A2 Blanchard Sorino(387205001 - DW 8-Dec-15 Cesium-137 8.61E-01 2.06E+OO 1.37E+OO pCi/L 1A2 Blanchard Sorino(365880002 - DW 26-Jan-15 Cobalt-58 1.25E+OO 1.98E+OO 1.90E+OO pCi/L 1A2 Blanchard Sorino(371630005 - OW - 21-Aor-15 Cobalt-58 -9.64E-01 1.69E+OO 1.51E+OO pCi/L 1A2 Blanchard Sprino(377777002 -DW 21-Jul-15 Cobalt-58 -7.61 E-01 1.99E+OO 1.26E+OO pCi/L 1A2 Blanchard Spring, 383939001 -DW 21-0ct-15 Cobalt-58 -3.31 E-01 1.90E+OO 1.35E+OO oCi/L 1A2 Blanchard Spring' 387205001 -DW 8-Dec-15 Cobalt-58 -3.94E-01 1.97E+OO 1.21E+OO pCi/L 1A2 Blanchard Spring, 365880002 -DW 26-Jan-15 Cobalt-60 1.16E-01 2.28E+OO 1.34E+OO oCi/L 1A2 Blanchard Sorino1 371630005 - ow 21-Aor-15 Cobalt~6o 1.51 E-01 2.04E+OO 1.20E+OO pCi/L 1A2 Blanchard Sorino(377777002 - OW 21-Jul-15 Cobalt-60 1.22E+OO --.. 2.55E+OO 1.51E+OO pCi/L 1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 Cobalt-60 2.89E-01 2.10E+OO 1.22E+OO pCi/L 1A2 Blanchard Sorino(387205001 - OW 8-Dec-15 Cobalt-60 -6.50E-02 2.20E+OO 1.63E+OO pCi/L 1A2 Blanchard Sorino(365880002 - DW 26-Jan-15 lodine-131 -1.01 E-01 4.00E-01 2.44E-01 pCi/L 1A2 Blanchard Sorino(371630005 - OW 21-Aor-15 lodine-131 1.41 E-01 5.34E-01 3.12E-01 pCi/L 1A2 Blanchard Sorino(377777002 - OW 21-Jul-15 lodine-131 -2.28E-01 6.68E-01 4.21E-01 pCi/L
~
1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 lodine-131 -t.27E-01 4.16E-01 2.59E-01 pCi/L 1A2 Blanchard Sorino(387205001 - DW 8-Dec-15 lodine-131 1.43E-01 7.16E-01 4.23E-01 pCi/L 1A2 Blanchard Sorino(365880002 - OW 26-Jan-15 lron-55 2.13E+01 6.75E+01 4.68E+01 pCi/L 1A2 Blanchard Sorina(371630005 - OW 21-Apr-15 lron-55 5.63E+01 8.95E+01 6.91E+01 pCi/L 1A2 Blanchard Sorina(377777002 - OW 21-Jul-15
lron-55 8.09E+OO 8.65E+01 6.50E+01 pCi/L 1A2 Blanchard Soring(383939001 - OW 21-0ct-15 lron-55 -2.84E+01 6.67E+01 4.58E+01 pCi/L 1A2 Blanchard Spring 387205001 -DW 8-Dec-15 lron-55 -1.74E+OO 3.68E+01 2.48E+01 pCi/L 1A2 Blanchard Spring 365880002 -DW 26-Jan-15 lron-59 -1.82E+OO 4.02E+OO 2.61E+OO pCi/L 1A2 Blanchard Spring 371630005 -OW 21-Apr-15 lron-59 -1.96E+OO 3.28E+OO 2.24E+OO pCi/L 1A2 Blanchard SorinQ 377777002 -DW 21-Jul-15 lron-59 3.49E+OO 5.04E+OO 3.27E+OO oCi/L Page 5 of 91
Pacific Gas and Electric Company"'
James M. Welsch Diablo Canyon Power Plant Vice President, Nuclear Generation P.O. Box 56 Avila Beach, CA 93424 805.545.3242 E-Mail: JMW1@pge.com April 21, 2016 PG&E Letter DCL-16-045 U.S. Nuclear Regulatory Commission 10 CFR 50, Appendix I ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 2015 Annual Radiological Environmental Operating Report
Dear Commissioners and Staff:
In accordance with Diablo Canyon Power Plant, Units 1 and 2, Technical Specification 5.6.2, "Annual Radiological Environmental Operating Report," Pacific Gas and Electric Company hereby submits the 2015 Annual Radiological Environmental Operating Report (AREOR). The AREOR contains material consistent with the objectives of the Offsite Dose Calculation Manual, and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
There are no new or revised regulatory commitments in this report (as defined by NEI 99-04).
If you have any questions regarding this submittal, please contact Mr. Martin Wright at (805) 545-3821.
Sincerely, A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Diablo Canyon
Palo Verde
Wolf Creek I~
. . Document Control Desk PG&E Letter DC~-16-045 Wf~~ April 21, 2016
' ~ Page 2 bnsm/4540/64124185 Enclosure cc: Diablo Distribution cc/enc: Larry Allen, Air Pollution Control Officer, San Luis Obispo County Air Pollution Control District Penny Borenstein, San Luis Obispo County Health Officer Marc L. Dapas, NRC Region IV Administrator Kenneth A Harris Jr., Executive Officer, CRWQCB Gonzalo L. Perez, Branch Chief, California Department of Public Health John Reynoso, DCPP Acting NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Executive Officer, San Luis Obispo County Air Pollution Control District A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Diablo Canyon
Palo Verde
Wolf Creek
Enclosure PG&E Letter DCL-16-045 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
2015 Annual Radiological Environmental Operating Report Diablo Canyon Power Plant January 1, 2015 - December 31, 2015
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2015 Diablo Canyon Power Plant ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)
January 1, 2015 - December 31, 2015
, Prepared By Pacific Gas & Electric Company Diablo Canyon Power Plant Prepared by: .£.-Z.;;__ ~ Date: o/'I/ 2a1(,
Martin-Wright; DCPP RP Senior Advising Engineer Reviewed&A Date: LI / (p I 1h PG&E Submittal Letter DCL-16-045
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EXECUTIVE
SUMMARY
This report contains results from the operational Radiological Environmental Monitoring Program (REMP) for Diablo Canyon Power Plant (DCPP) compiled for the period January 1, 2015 through December 31, 2015.
The purpose of the REMP was to assess the levels of radiation or radioactivity in the environment and to verify that DCPP was operating within its design parameters. This data was used to assure that plant effluents did not result in a significant radiological dose to offsite individuals.
Operation of DCPP continued to have no detectable offsite radiological impact. Samples analyzed from the offsite sampling stations continued to show no radiological contribution from plant operations.
The offsite radiological doses received by the general public from plant operations were less than one millirem (mr) annually which is insignificant whert *compared to the 310 millirem average annual radiation exposure to people in the United States from natural radiation sources (e.g. cosmic, terrestrial, radon, etc).
More than 260 environmental samples, 880 air samples, artd 1400 thermo luminescent dosimeter (TLD) phosphors were collected over the course of the 2015 REMP monitoring period. Approximately 1782
(
radionuclide analyses were performed on the environmental samples.
The REMP was conducted in accordance with DCPP Program Directive CY2, "Radiological Monitoring and Controls Program," and RPl.IDl 1, "Environmental Radiological Monitoring Procedure." This report was submitted per DCPP License Technical Specification 5.6.2.
The types of samples (matrix ID) collected for this monitoring period were as follows:
Air Particulate (AP) Air Cartridges (AC) for iodide monitoring Carbon-14 (AC14)
Direct Radiation (TLD) Mille (MK) Meat (MT) Vegetation (VG)
Drinking Water (DW) Ground Water (GW), Monitor Well (GW) Surface Water (SW)
Aquatic Vegetation (AV) Fish (FH) Mussels (IM) Sediment (SD)
The ambient direct radiation levels in the DCPP offsite environs did not change and were within the pre-operational background range.
The ambient onsite direct radiation levels within the DCPP plant site boundary near the ISFSI were elevated due to dry cask spent fuel storage. The remaining onsite REMP environmental TLD locations were not affected by the ISFSI due to ISFSI topographical elevation and placement within an onsite hillside which provided shielding to the rest of the site.
An evaluation of direct radiation measurements and member of public occupancy .times within the site boundary indicated all federal criteria for member of public dose limits (10CFR20.1301) were conservatively met. An evaluation of direct radiation measurements indicated all federal EPA 40CFR190 criteria were conservatively met.
Groundwater isotopic monitoring was conducted in accordance with the nuclear industry NEI 07-07 Groundwater Protection Initiative (GPI). Concentrations of tritium were detected in three shallow monitoring wells (stations OWl, DYl, and GWl) near the power block. This tri~ium was evaluated and attributed to rain-washout of gaseous tritium exiting the plant vent system (via an approved isotopic-effluents discharge path). No groundwater tritium has been attributed to DCPP system leaks or spills. It should also be noted that studies of the DCPP site groundwater gradient indicated that any groundwater (subsurface) flow beneath the DCPP power block was not used as a source of drinking water. Due to topography and site characteristics, this groundwater gradient flow discharged into the Pacific Ocean which is approximately 100 yards from the power block.
An Old Steam Generator Storage Facility (OSGSF) long term storage mausoleum was constructed within the DCPP site boundary in 2007 for storage of eight retired DCPP steam generators and two retired DCPP reactor heads. This OSGSF did not cause any changes to the ambient direct radiation levels within the DCPP environs during 2015. The OSGSF in-building sumps were inspected quarterly by REMP personneL These OSGSF sumps have remained empty and dry during 2015.
The results of the 2015 REMP showed no unusual environmental isotopic findings from DCPP site
operations. These results were compared to DCPP preoperat~onal isotopic data and showed no unusual trends.
Diablo Canyon site operations had no significant environmental radiological impact on airborne, surface water, drinking water, marine life, aquatic vegetation, terrestrial vegetation, sediment, milk, or meat radioactivity.
TABLE OF CONTENTS Executive Summary 1.0 Introduction 2.0 Program Design 2.1 Monitoring Zones 2.2 Pathways Monitored 2.3 Descriptions ofREMP Monitoring 2.3.l Direct Radiation 2.3.2 Airborne Radioactivity 2.3.3 Airborne Carbon-14 2.3.4 Water,borne 2.3.5 Marine Biological, Beach Sand, and Ocean Sediment 2.3.6 Food Crops 2.3.7 Milk 2.3.8 Meat 3.0 Radiological Data Summary of Tables 4.0 Analysis of Environmental Results 4.1 REMP Sampling Variance I Deviations 4.2 Comparison of Achieved LLDs with Requirements 4.3 Comparison of Results against Reporting Levels 4.4 Data Analysis by Media Type 4.4.1 Direct Radiation 4.4.2 Airborne Radioactivity 4.4.3 Waterborne 4.4.4 Marine Biological, Beach Sand, and Ocean Sediment 4.4.5 Food Crops 4.4.6 Milk 4.4.7 Meat 5.0 Groundwater Monitoring 6.0 Old Steam Generator Storage Facility 7.0 Lab Cross Check Program 8.0 DCPP Annual Land Use Census
9.0 DCPP Wind Rose 10.0 References Appendix A Individual Analytical Sample Results Photograph credits: Tom Hook, John Lindsey, and Martin Wright
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LIST OF TABLES Table Title 2.1 Radiological Environmental Monitoring Program 2.2 Distances and Directions to Environmental Monitoring Stations 2.3 Detection Capabilities for Environmental Lower Limit of Detection (LLD) 2.4 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.1 Direct Radiation Summary Table 3.2 REMP Airborne Summary Table 3.3 Surface Water Summary Table 3.4 Drinking Water Summary Table 3.5 Mussel Summary Table 3 .6 Fish Summary Table
3. 7 Algae Summary Table 3.8 Kelp Summary Table 3.9 Vegetative Crops Summary Table 3.10 Milk Summary Table 3.11 Meat Summary Table 3.12 Ocean Sediment Summary Table 3.13 Beach Sand Suillmary Table 3.14 Groundwater Summary Table 3.15 Monitoring Well Summary Table 8 DCPP Land Use Census LIST OF FIGURES Figure Title 2.1 Diablo Canyon Off-site REMP Locations 2.2 Diablo Canyon On-site REMP Locations 2.3 Diablo Canyon REMP Stations 8 DCPP Land Use Census Map
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1.0 INTRODUCTION
Diablo Canyon Power Plant (DCPP) consists of two Westinghouse pressurized water reactors (PWR).
Unit 1 began commercial operation in 1985, and Unit 2 began commercial operation in 1986.
The purpose of the Radiological Environmental Monitoring Program (REMP) is to verify that Diablo Canyon Power Plant (DCPP) is operating within its design parameters and to assure that plant effluents do not result in a significant radiological dose to offsite individuals.
Operation of DCPP continues to have no detectable radiological impact offsite. Samples analyzed from the offsite sampling stations continue to show no radiological contribution from plant operations. The annual radiological doses received by the general public from plant operations were less than one millirem (mr) which is insignificant when compared to the 310 millirem average annual radiation exposure to people in the United States from natural radiation sources (e.g. cosmic, terrestrial, radon, etc).
This Annual Radiological Environmental Operating Report (AREOR) summarized the findings of the REMP conducted by DCPP. The remainder of this AREOR was organized as follows:
Section 2: Provided a description of the overall REMP design. Included was a summary of the requirements for REMP sampling and tables listing routine sampling and TLD monitoring locations with distances from the plant. Tables listing Lower Limit of Detection requirements and Reporting Levels (NRC notification if levels exceeded) were also included.
Section 3: Consisted of the summarized data as required by the Radiological Environmental Monitoring Program. The summaries were provided similar to that specified by the NRC Branch Technical Position on Environmental Monitoring.
Section 4: Provided a summary of the results for the samples collected. The performance of the program in meeting the requirements was discussed, and the data acquired during the monitoring period was analyzed. Also included was environmental TLD preoperational data trending.
Section 5: Provided a summary of groundwater monitoring in accordance with the nuclear industry NEI 07-07 Groundwater Protection Initiative.
This and previous DCPP AREOR's can be found on the NRC website at:
http://www.nrc.gov/reactors/operating/ops-experience/tritium/plant-info.html DCPP REMP sent replicate split san1ples of stations 7G I vegetation (quarterly), 5F2 milk (monthly), 5S2 drinking water (monthly), DWI drinking water (monthly), OUT seawater (monthly), DCM kelp (quarterly), DCM perch (quarterly), DCM rockfish (quarterly), and DCM ocean sediment (annually) to the California Department of Public Health - Radiologic Health Branch (CDPH -RHB) Laboratory as part of a California State split sampling program.
These split samples were independently analyzed by the CD PH-RHB.
Other pathways independently monitored by the CDPH-RHB were quarterly direct radiation TLD stations (MTl , !Al , !Cl, 4Dl , 5F3, 5Sl , 7Dl, 7Cl , 7FI , and 8S2) and weekly air sampling particulate and 1- 131 (at stations 5F3 and 7Dl).
The general public can access these CDPH-RHB split sampling data results via the internet at:
http://www.cdph.ca.gov/programs/Pages/RHB-RadReport.aspx
2.0 PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Diablo Canyon Power Plant (DCPP) was designed with the following specific objectives in mind. These objectives continue to be in force, to varying degrees, throughout facility operation:
To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by facility operation. Preoperational data was also used in this comparison.
To provide assurance to regulatory agencies and the public that the station's environmental impact was known and within anticipated limits.
To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
The environmental media selected were based on the critical dose pathways of the radionuclides from the environment to man. They included the following: direct radiation, air, water, fish, ocean sediment, and invertebrates. Supplemental samples such as algae, kelp, local agricultural crops, recreational beach sand,
groundwater, meat, and milk were also collected. The sampling locations were determined by land use, site meteorology, and local demographics. Guidance for this monitoring program was provided by the Radiological Assessment Branch Technical Position on Radiological Environmental Monitoring, Revision 1, November 1979 (NUREG-1301).
Radiological Environmental Monitoring Program (REMP) samples were collected by DCPP REMP personnel and sent to General Engineering Labs (GEL) in Charleston, South Carolina for isotopic analysis.
Fish (except market fish) and ocean sediment samples were collected by contract divers of Tenera Environmental and given to DCPP REMP personnel for shipment to GEL.
Market fish samples were collected by local commercial fishermen and then purchased by DCPP REMP personnel in one of two local fish markets for shipment to GEL.
Environmental direct radiation analyses were conducted by the use of thermo-luminescent dosimeters (TLD). Environmental TLD analysis was conducted by Mirion Technologies in Irvine California.
The detailed sampling requirements of the REMP were given in Table 2.1 of this report.
Data summary tables of REMP sampling for the period were shown in section 3 9f this report.
Any deviations from the REMP sampling schedule I requirements were documented in section 4 of this report.
Direct dose (environmental TLD) results were shown in section 4 of this report.
Individual REMP sample isotopic results were shown in Appendix A of this report. Detected concentrations ( > MDC) of nuclear power plant related isotopes have been highlighted with yellow background for quick identification by the reader. Naturally occurring isotopes (e.g. NORM) were not highlighted (including gross beta, Be-7, K-40, thorium, radium, radon, lead, etc).
2.1 MONITORING ZONES The REMP was designed to allow comparison of levels of radioactivity in samples from the areas possibly influenced by DCPP to levels found in areas not influenced by the facility operations. Areas with the potential to be influenced by facility operations were called "indicator" stations. Areas with sufficient distance from the plant that were not likely to be
influenced by facility operations were called "control" stations. The distinction between the two zones was based on distance and relative direction from the plant. Analysis of survey data from the two zones aided in determination of site environmental influence. Analysis .
from the two zones assisted in differentiation between radioactive releases and seasonal variations in the natural environmental background radioactivity.
2.2 PATHWAYS MONITORED Direct Radiation Airborne Radioactivity Waterborne Pathways Marine Biological, Beach Sand, and Ocean Sediment Food Crops Milk Meat
2.3 DESCRIPTION
S OF REMP MONITORING 2.3.1 Direct Radiation Direct ambient radiation was measured at 32 stations in the vicinity ofDCPP using Panasonic UD814 TLD badges. The TLD badges had valid element correction factors (ECF), were calibrated using a NIST-traceable caesium-137 source, were annealed prior to placement, and were sealed in watertight packaging. Three TLD badges were placed at each station and each badge contained 3 calcium sulfate phosphors for a total of 9 calcium sulfate phosphors at each station. The 9 phosphors were analyzed and averaged to provide a single station reading. That single reading was converted into an uR/hr doserate dependent on the in-field exposure time period. Then the uR/hr doserate was converted and reported into millirem (mr) per standard (91 day) quarter. These TLD badges were exchanged and processed on a quarterly basis.
Direct ambient radiation was meas~red at 8 stations in the vicinity of the Independent Spent Fuel Storage Installation (ISFSI) using Panasonic UD814 i
TLD badges. The ISFSI TLD badges were processed in the same method described in the previous paragraph.
The Env TLD badge packets were distributed and ~ollected from the field stations by DCPP REMP personnel and then shipped to Mirian Technologies for processing. Control badges accompanied the field badges during shipment and deployment to measure any non-station dose received during transit time periods.
Control badge exposure was subtracted from field badge exposure. Env TLD exposure was reported over a standard 91 day quarter.
DCPP Environmental TLD standard quarter results were measurements of all environmental gamma radiation sources (cosmic, terrestrial, radon, man-made, etc) at each station during the deployment period.
2.3.2 Airborne Radioactivity Air particulate and radioiodine sampling were performed weekly at six indicator stations: MTl, 082, 181, 7Dl, 881and882. Air particulate and radioiodine sampling was performed weekly at one control station: 5Fl.
Constant flow air samplers (F&J model DF-1) were used to draw air through paper filters to collect air particulates and through triethylenediamine (TEDA) impregnated charcoal cartridges to collect radioiodine. The air sampling flow rate was conducted at approximately 2.55 cubic meters per hour. The air sampling
.collection filters were located approximately seven feet above the ground. The sample volum~s were determined by F&J Corporation model DF-1 flow meters (corrected to standard temp~rature and pressure, 8TP) which were installed 1
downstream of the sample filters. At the end of the weekly sampling period, the particulate filter and TEDA charcoal cartridge were collected. All necessary data regarding the air volume readings, flow rate, sampler time on I off, date bf collection, and sampler station location were recorded and submitted to GEL along with the filter samples for isotopic analysis.
Approximately 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after sampling (to allow for radon and thoron daughter decay), the particulate filter papers collected from the field were placed on individual planchets and counted for gross beta activity in a low background, thin window gas proportional counter.
Quarterly gamma spectroscopy isotopic anaJysis was performed on composites of
the filters (by station) to detennine the activity concentration of gamma emitting isotopes. The quarterly composite sample time is reported at the midpoint of the quarter monitored.
Due to the short half-life of lodine-131, each station weekly TEDA impregnated charcoal cartridge was counted for gamma spectroscopy isotopic analysis to determine the radioiodine concentration.
2.3.3 Airborne Carbon-14 Air Carbon-14 (C-14) supplemental sampling was perfonned weekly at stations OS2 (no1ihwest sector), 8S 1 (southeast sector), and SF 1 (control station in San Luis Obispo) throughout 2015.
General Engineering Labs (GEL) and DCPP REMP worked together to develop a method for sampling environmental airborne inorganic C-14. Inorganic C-14 (as C0 2) is the primary exposure pathway to man via photosynthesis in plants. A constant flow air san1pler was used to draw air through a solid phase carbon sensitive sorbent cartridge. The air sampler was set at a flow rate of 1.0 standard liter per minute. The air sample filter cartridge head was located approximately seven feet above the ground. At the end of the weekly sampling period, the filter cartridge was collected. All necessary data regarding the air volume, flow rate, sampler time on I off, date of collection, and sampler station location were
recorded and submitted to GEL along with the sample filter for C-14 analysis. At GEL, a suitable portion of the solid sorbent material was processed through a method utilizing wet oxidation to remove volatile C0 2 from the media in a closed distillation system. Once removed from the media, C-14 as carbon dioxide was sparged through a dilute acid solution for trapping any tritiated water present in the sample. After sparging through dilute acid, the C0 2 was trapped in a sorbing solution which was added to liquid scintillation cocktail and finally counted in a liquid scintillation counter. It should be noted that C-14 results in Appendix Care reported in uCi/cubic meter. This method met the following specifications:
Validated to retain 99.9% of inorganic C-14 in air
Validated at collection rates of approximately 1.0 liter per minute
Validated for total collection capacity over a l week sampling interval
Accurate analysis of C-14 over a wide range of concentrations
Methodology free from interference by other radionuclides
Detection capability of approximately 0.8 pCi (8E-7 uCi) per cubic meter 2.3.4 Waterborne Water samples (drinking water, surface water, monitor wells, and groundwater) were collected at the frequencies shown in Table 2.1 Ocean surface water samples were collected at Diablo Cove (station DCM),
Rattlesnake Canyon (station 7C2), and at the plant Outfall (station OUT).
Drinking water samples were collected from Diablo Creek Weir (station 5S2),
Diablo Creek Outlet (station WN2), Blanchard Spring (station 1A2), and from the DCPP drinking water system (station DWI). San Luis Obispo (SLO) city drinking water was also collected from a control station located at 4325 South Higuera Street, Offsite Emergency Lab (station OEL) in SLO.
Supplemental groundwater samples were collected from Water Well 02 (WW2) and DCSF96- l (8S3).
Supplemental on-site monitoring well samples were collected from french drain systems labeled Observation Well 01 (OWl), Observation Well 02 (OW2), and
Drywell 115 (DYl). These shallow French drain well systems were located in close proximity to the facility power block structures and within the protected area.
Two new on-site monitoring wells were installed in December 2011 as part of the industry Groundwater Protection Initiative (GPI). Isotopic sampling of these wells was initiated in 2012. These two new onsite wells were downgradient of the power block and located along the west side of the power block. These two new monitoring wells were labeled Groundwater I (GWI) and Groundwater 2 (GW2).
After collection, the samples were securely sealed and labeled with sample type, station ID, date, time of collection, person performing the collection and sent to GEL for analysis.
2.3.5 Marine Biological, Beach Sand, and Ocean Sediment The REMP required sampling ofrockfish (genus Sebastes), perch (family Embiotocidae), mussels (genus Mytilus), and ocean sediment from indicator station DCM and control station 7C2.
All other marine samples collected were considered supplemental. These supplemental marine samples included the following: intertidal algae, intertidal mussels, kelp, rockfish, perch, beach sand, and market fish. The intertidal samples were collected by DCPP personnel during low tidal conditions. Kelp was collected quarterly by DCPP personnel from the offshore kelp bed in the vicinity of the site.
Quarterly samples of fish and annual samples of ocean sediments were collected from the plant environs by contracted divers (TENERA Environmental). The Tenera divers fillet the fish and leave a small portion of skin for identification.
Only edible portions of the fish were analyzed (fish fillets).
Beach sand was collected by DCPP personnel between the high and low tide boundaries at nearby recreational beaches.
Market Fish caught locally by commercial fishermen were pmchased from two local fish markets (A vita Beach Pier-703 and Morro Bay-2F 1).
All samples were subject to unavailability due to seasonal fluctuations or unfavorable sampling conditions. The above samples were sealed in plastic bags immediately upon collection. In-shell mussels were sent to GEL where GEL personnel removed the meat & internal organs for analysis. The samples were labeled with sample type, station ID, date, time of collection, and the individual who performed collection. The samples were then frozen (to prevent spoilage odor) before they were shipped to GEL for analysis.
2.3.6 Food Crops The REMP required broadleaf food vegetation collected in the nearest off-site locations of the highest calculated annual average ground level D/Q (dispersion parameter) within 5 miles. There was no broadleaf food vegetation available that satisfied this requirement. Because these food products were unavailable, the DCPP REMP conducted additional weekly air sampling in the SE (station 8S2) and NNW (station IS I) sectors.
Additional representative samples of food crops (in season) were collected monthly from supplemental stations: Cal Poly Farm (5F2), Kawaoka Farm in Arroyo Grande (7G 1), Mello Farm (7Cl) along the DCPP site access road, and quarterly from local gardens (3Cl , 6Cl, and 7El).
The vegetation samples at 5F2, 7Gl, 7Cl , 3Cl , and 7El were collected by DCPP personnel and sealed immediately in plastic bags. The quarterly garden vegetation sample at 6C 1 was provided to DCPP personnel by the land occupant (due to difficulty of property access and occupant requested privacy).
The samples were labeled with sample type, station ID, collection date, collection time, and the individual who perfonned collection. The samples were normally frozen before they were shipped to GEL for analysis (to prevent spoilage odor).
2.3.7 Milk There were no animals within the 5 mile vicinity of the plant utilized for milk consumption by hwnans. However, supplemental samples of cow milk were collected monthly from Cal Poly Farm (5F2) which was approximately 13 miles from DCPP.
Two 1-gallon plastic containers of milk were collected each sampling period by DCPP personnel. Forty grams of sodium bisulfite preservative were added to each gallon of milk sample. The containers were sealed and shaken thoroughly to distribute the preservative. The containers were labeled with sample type, station ID, collection date, collection time, and the individual who performed collection.
The samples were then express-shipped (due to the short half-life of I-131) to GEL for analysis.
2.3.8 Meat A rancher routinely grazed (free range, grass fed) cattle within three miles of the site boundary between the northwest to east sectors (clockwise). This livestock meat would then be offered at local farmer's markets and private distribution.
Because it was possible for this vendor to provide an individual's sole-source of annual meat consumption, this meat sampling was included in the REMP.
REMP personnel obtained commercially packaged meat samples directly from the land owner. Gamma spec and total strontium 89/90 analyses were performed on th~ meat.
Control station free range, grass fed meat sampling was conducted of ranches outside the influence ofDCPP. This meat was purchased by REMP personnel from the Whole Foods Market in SLO. The control station meat consisted of Hearst Ranch meat which is located approximately 37 miles north of the DCPP site. This REMP station code was CCM (Control Cow Meat) and provided a control meat sample location far from the site.
Property owners could hunt deer and wild pig (in season) within 5 miles of the site boundary. The REMP could not obtain deer meat samples from these property owners (voluntary participation) in 2015. Gamma spec and strontium analyses were performed on the deer meat if provided.
The meat was initially packaged by the livestock owners or commercial processes. The meat was purchased at local grocery stores or turned over to REMP personnel by the land owners. The unopened packages were then separated by species and placed into large over-pack zip-lock bags. Each bag was labeled with sample type, station ID, collection date, collection time, and the individual who performed the collection. The samples were then frozen and shipped to GEL for isotopic analysis.
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TABLE2.1:
Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling Collection Frequency Type of Required or and/or Sample Type Samples and Sample Stations Analysis Supplemental Locations 1
1. Direct Radiation2 Thirty-two routine monitoring stations containing thermo luminescent dosimeters (TLDs) such that at least two (2) phosphors are present at each station, placed as follows:
An inner ring of stations, one in OS1, OS2, Quarterly Gamma Dose Required each terrestrial meteorological WN1, 1S1, sector in the general area of the 2S1, 3S1, 4S1, SITE BOUNDARY; 5S1, 6S1, 7S1, 8S1' 9S1' 8S2, 5S3, and MT1 An outer ring of stations, one in OB1, 1A1, 1C1, Quarterly Gamma Dose Required each terrestrial meteorological 2D1, 3D1, 4C1, sector in the 2.5 to 14 km range 5C1, 6D1, and from the site; and 7C1 One or two areas to serve as 2F2, 4D1, 5F1 Quarterly Gamma Dose Required control stations; and The balance of the stations to 5F3, 7D1, 7D2, Quarterly Gamma Dose Required be placed in special interest 7F1, and 7G2 areas such as population centers, nearby residences, or schools.
A minimum of four stations IS1' IS2, IS3, Quarterly Gamma Dose Required around the ISFSI IS4, IS5, IS6, IS7, IS8
2. Airborne Samples from~ 4 stations:
Radioiodine Three samples from close to the OS2, 8S1, Continuous sampler 1-131 analysis Required three SITE BOUNDARY and MT1 operation with sample locations ( OS2, 8S1, & MT1 ) in collection weekly, or different sectors. more frequently if required by dust loading.
One sample from the vicinity of 7D1 Continuous sampler 1-131 analysis Required a community having the highest operation with sample calculated annual average collection weekly, or ground level D/Q. more frequently if required by dust loading.
If food products are unavailable, 1S1 &8S2 Continuous sampler 1-131 analysis Required additional air sampling will be operation with sample done in the NNW (station 1S1) collection weekly, or and SE (Station 8S2) sectors. more frequently if required by dust loading.
One sample from a control 5F1 Continuous sampler 1-131 analysis Required location. operation with sample collection weekly, or more frequently if required by dust loading.
Table 2.1 (continued)
Exposure Pathway Number of Representative Sampling Collection Type of Analysis Required or and/or Sample Type Samples and Sample Stations Frequency Supplemental 1
Locations
3. Airborne Samples from~ 4 stations: \
Particulate Three samples from close to the OS2, 8S1, Continuous Weekly gross beta Required three SITE BOUNDARY and MT1 sampler operation radioactivity locations ( OS2, 8S1, & MT1 ) in with sample analysis following 3
different sectors. collection weekly, filter change
or more frequently Quarterly gamma 4
if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).
One sample from. the vicinity 9f 701 Continuous Weekly gross beta Required a community having the highest sampler operation radioactivity calculated annual average with sample analysis following 3
ground level D/Q. collection weekly, filter change
or more frequently Quarterly gamma 4
if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).
lffood products are unavailable, 1S1 & 8S2 Continuous Weekly gross beta Required additional air sampling will be sampler operation radioactivity done in the NNW (station 1S1) with sample analysis following 3
and SE (Station 8S2) sectors. collection weekly, filter change .
or more frequently Quarterly gamma if required by dust isotopic analysis4 loading. of composite consisting of approx. 12 filters (by location).
One sample from a control 5F1 Continuous Weekly gross beta Required location. sampler operation radioactivity with sample analysis following 3
collection weekly, filter change
or more frequently Quarterly gamma 4
if required by dust isotopic analysis loading. of composite consisting of approx. 12 filters (by location).
4. Airborne Carbon-14 Samples from 3 stations: OS2,8S1 Continuous C-14 analysis Supplemental One sample from each of the 5F1 (control) sampler operation_
NW and SE sectors close to the with sample site (OS2 and 8S1). collection weekly, or more frequently One sample used as a control if required by dust station (5F1). loading.
/
Table 2.1 (continued)
Exposure Pathway Number of Representative Sampling Collection Type of Analysis Required or and/or Sample Type Samples and Sample Stations Frequency Supplemental 1
Locations
5. Waterborne 4
a. Surface Ocean One sample from the plant OUT, DCM, Monthly Gamma isotopic Required Water Outfall, Diablo Cove, and an and 7C2 (grab sample) and tritium area not influenced by plant analysis.
discharge.
One sample from the plant OUT, DCM, Quarterly Gross Beta, Supplemental Outfall, Diablo Cove, and an and 7C2 (grab sample) Total Sr 89/90, area not influenced by plant Fe-55, and Ni-63 discharge.
4
b. Drinking Water One sample from the plant DW1and5S2 Monthly Gamma isotopic , Required drinking water, one sample from OEL (control) (grab sample) 1-131, and tritium Diablo Creek (upstream of analysis.
plant), and one control sample.
One sample from the plant DW1and5S2 Quarterly Gross Beta, Supplemental drinking water, one sample from OEL (control) (grab sample) Total Sr 89/90, Diablo Creek (upstream of Fe-55, and Ni-63 plant), and one control sample.
4 One sample from Diablo Creek WN2and1A2 Quarterly Gamma isotopic , Supplemental (downstream of plant) and one (grab sample) tritium, 1-131, gross sample from Blanchard Spring. beta, Total Sr 89/90, Fe-55, and Ni-63 4
c. Groundwater One sample from wells located OW1, OW2, Quarterly Gamma isotopic , Supplemental under or downgradient from the DY1, GW1, (grab sample, tritium, gross beta, plant power block. and GW2 when available) Total Sr 89/90, Fe-55, and Ni-63 4
One sample from a well located WW2, 8S3 Quarterly Gamma isotopic , Supplemental outside the plant power block (grab sample, tritium, gross beta, (control sample). when available) Total Sr 89/90, Fe-55, and Ni-63 4
d. Sediment One sample of offshore ocean DCM and 7C2 Annual Gamma isotopic Required sediment from Diablo Cove and (grab sample)
Rattlesnake Canyon.
One sample of offshore ocean DCM and 7C2 Annual Total Sr 89/90, Supplemental sediment from Diablo Cove and (grab sample) Fe-55, and Ni-63 Rattlesnake Canyon.
4 One sample from each of five AVA, MOO, Semi- Annual Gamma isotopic , Supplemental local recreational beaches. PMO, CYA, (grab sample) Total Sr 89/90, and CBA Fe-55, and Ni-63 4
e. Marine Flora One sample.of kelp DCM, PON, Quarterly Gamma .isotopic Supplemental POS, and 7C2 (when available) 4 One sample of intertidal algae DCM and 7C2 Quarterly Gamma isotopic Supplemental (when available)
Table 2.1 (continued)
Exposure Pathway Number of Representative Sampling Collection Type of Required or and/or Sample Type Samples and Sample Stations Frequency Analysis Supplemental 1
Locations
6. Ingestion
a. Milk S13mples from milking animals in 5F2 Semimonthly Gamma isotopic4 Suppleme.ntal three locations within 5 km when animals are and 1-131 distance having the highest on pasture; analysis.
dose potential. If there are none, monthly at other then one sample from milking times.
animals in each of three areas between 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location I I
15 to 30 km distant and in the least prevalent wind direction.
NOTE: The sample (5F2) should be taken monthly even if there are no indicator samples available.
4
b. Fish and One sample of rock fish (family DCM and 7C2 Quarterly Gamma isotopic Required Invertebrates Sebastes) and one sample of (grab sample) analysis on perch (family Embiotocidae) edible portions of each sample.
4 One sample of rock fish PON andPOS Quarterly Gamma isotopic Supplemental (family Sebastes) and (grab sample) analysis on one sample of perch edible portions (family Embiotocidae) of each sample.
One sample of mussel DCM and 7C2 Quarterly Gamma isotopic4 Required (family Mytilus) (grab sample) analysis on edible portions of each sample.
4 One sample of mussel PON Annual Gamma isotopic Supplemental (family Mytilus) (grab sample) analysis on edible portions of each sample.
4 One sample of mussel POS Quarterly Gamma isotopic Supplemental (family Mytilus) (grab sample) analysis on edible portions of each sample.
4 One sample of locally harvested 7D3 OR 2F1 Quarterly C?amma isotopic Supplemental market fish. (should (grab sample) analysis on alternate edible portions between of each sample.
locations)
Table 2.1 (continued)
Exposure Pathway Number of Representative Sampling Collection Type of Required or and/or Sample Type Samples and Sample Stations Frequency Analysis Supplemental Locations 1
c. Broadleaf Three samples of broadleaf Monthly Gamma isotopic4 Required Vegetation 5 vegetation grown nearest (when available) analysis (that (see notation #5) off-site locations of highest includes 1-131) calculated annual average on edible ground level D/Q !E milk portion.
sampling is not performed.
One sample of each of the Monthly Gamma isotopic4 Required similar broadleafvegetation (when available) analysis (that (see notation #5) grown 15 to 30 km distant in the includes 1-131) least prevalent wind direction !E on edible milk sampling is not performed. portion.
d. Vegetative One sample of broadleaf 5F2, 7C1, Monthly Gamma isotopic4 Supplemental Crops vegetation or vegetables or fruit and 7G1 (when available) analysis on edible portion.
One sample of broadleaf 3C1, 6C1, 7E1 Quarterly Gamma isotopic4 Supplemental ve~etation or vegetables or fruit. (as provided by analysis on land owner) edible portion.
e. Meat sample One sample of each species BCM, BGM, Quarterly Gamma isotopic4 Supplemental (cow, goat, sheep, deer, or pig) BSM, JDM, (as available and analysis, and of edible meat portion JPM,ACM, provided by land Total Sr 89/90 slaughtered for personal ADM,APM, owners within 8 on edible consumption (not mass market). CCM km of plant site) portion.
Table Notations I. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program, and submitted in the next Annual Radioactive Effluent Release Report, including a revised figure(s) and table for the ERMP reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the section of the new location(s) for obtaining samples.
2. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor. There are normally three calcium sulfate phosphors in an environmental TLD BADGE. Fihn badges shall not be used as dosimeters for measuring direct radiation.
3. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than I 0 times the yearly mean of control samples, gamma isotopic analysis shall be perf01med on the individual samples.
4. Ganuna isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
5. Ifbroadleafvegetation food products are unavailable, additional air sampling as specified in Table 2.1, Parts 2 & 3 will be done in the NNW (station ISI) and SE (Station 8S2) sectors.
6. The Branch Technical Position (Nov 79) states, "Any locatioll'from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location".
Although milk sampling performed at 5F2 is outside the 5-mile radius and is supplemental to the REMP, this notification should take place if 5F2 milk sampling ceases.
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TABLE2.2 Distances and Directions to Environmental Monitoring Stations Radial Direction** Radial Distance**
Station (True Heading) From Plant Code(a) Station Name Degrees km Miles OSI Exclusion Fence-Northwest Corner 320 0.16 0.1 OS2 North Gate 320 0.8 0.5 lSl Wastewater Pond 330 0.64 0.4 2Sl Back Road-300 m North of Plant 0 0.32 0.2 3Sl Road NW of230 kV Switchyard 23 0.64 0.4 4Sl Back Road Between Switchyards 43 0.8 0.5 5Sl 500 kV Switchyard 58 0.64 0.4 5S2 Diablo Creek Weir 65 0.96 0.6 5S3 Microwave Tower Road 70 1.02 0.7 6Sl Microwave Tower 94 0.8 0.5 7Sl Overlook Road 112 0.48 0.3 8Sl Target Range 125 0.8 0.5 8S2 Southwest Site Boundary 128 1.76 1.1 8S3 DCSF 96-1 (monitor well) 145 0.52 0.33 9Sl South Cove 167 0.64 0.4 MTl Meteorological Tower I85 0.32 0.2 DCM Diablo Cove Marine 270 0.32 0.2 WNI Northwest Guard Shack 290 0.32 0.2 WN2 Diablo Creek Outlet 283 0.25 O.IS lAI Crowbar Canyon 327 2.56 1.6 1A2 Blanchard Spring 33I 2.4 1.5 OBI Point Buchon 325 5.76 3.6 ICI Montana de Oro Camrnrround 336 7.52 4.7 3CI Ranch Vegetation 20 7.I6 4.5 4CI Clark Valley Gravel Pit 45 9.28 5.8 SCI Junction Prefumo/See Canyon Roads 64 7.52 4.7 6CI Household Garden 98 7.24 4.5 7CI Pecho Creek Ruins (Mello Farm) I20 6.56 4.I 7C2 Rattlesnake Canyon I24 7.52 4.7 2DI Sunnyside School - 10 11.04 6.9 3DI Clark Valley 24 9.92 6.2 4DI Los Osos Valley Road 36 12.16 7.6 6DI Junction See/Davis Canyon Roads 89 13.4 8.3 7Dl Avila Gate 118 10.56 6.6 7D2 Avila Beach lIO I2.I6 7.6 7D3 Avila Pier I20 I 1.0 6.9 7EI Avila Valley Barn 103 13.94 8.7 2Fl Morro Bay (Commercial Landing) 0 I7.44 10.9 2F2 Morro Bay Power Plant 358 I7.9 I 1.2 5Fl SLOOEL 79 I6.41 10.2 5F2 Cal Poly Farm 60 20.16 12.6 5F3 SLO County Health Department 70 20.32 12.7
Table 2.2 (continued)
Radial Direction** Radial Distance**
Station (True Heading) From Plant Code(a) Station Name Degrees km Miles 7Fl . Shell Beach 110 17.28 10.8 7Gl Arroyo Grande (Kawaoka Farm) 115 26.88 16.8 7G2 Oceana Substation 118 27.68 17.3 AVA Avila Beach (near pier) 109 11.75 7.3 CBA Cambria Moonstone Beach 330 45.86 28.5 CYA Cayucos Beach (near pier) 350 26.87 16.7 DYl Drywell 115' 77 0.041 0.026 DWI Drinking Water (Plant Potable Water Sys) 161 0.59 0.37 GWl Groundwater Monitoring Well 1 271 0.15 0.09 GW2 Groundwater Monitoring W~ll 2 204 0.21 0.13
rs1-rs8 ISFSI I 65 0.48 0.3 MDO Montana de Oro (Spooners Cove) 336 7.56 4.7 OWl Observation Well 01 336 0.07 0.046 OW2 Observation Well 02 157 0.07 0.045 OEL Offsite Emergency Lab 79 16.41 10.2 OUT : Plant Outfall 270 0.32 0.2 PMO Pismo Beach (near pier) 113 20.76 12.9 PON Pacific Ocean North of Diablo Cove* 305 2.4 1.5 POS Pacific Ocean South of Diablo Cove 180 0.64 0.4 WW2 Water Well 02 70 1.02 0.63 BCM Blanchard (Fa.mi.) Cow Meat 320 1.94 1.2 BGM Blanchard (Farm) Goat Meat 320 1.94 1.2 BSM Blanchard (Farm) Sheep Meat 320 1.94 1.2 CCM Control Cow Meat 328 59.5 37 JDM Johe (Property) D_eer Meat 21 5.24 3.26
The reference point used is the dome of Unit 1 containment.
Station Code (XYZ):
X - First number (0-9) represents the radial sector in which the station is located:.
0 - Northwest 5 - East-northeast 1 - North-northwest 6 - East 2 ~North 7 - East-southeast 3 - North-northeast 8 - Southeast 4 - Northeast 9 - South-southeast Y - Letter (S, A-H) represents the distance from the plant:
S - On-site A 2 miles from plant (but off-site)
B 4 miles from plant C 6 niiles from plant D 8 miles from plant E 10 miles from plant F 15 miles from plant G 20 miles from plant H - Greater than 20 miles from plant Z - Second number represents the station number within the zone.
Table 2.2 (continued)
Station Codes exceptions:
The following stations do not follow the coding system:
Diablo Cove Marine (DCM)
Montana de Oro (MDO)
Meteorological Tower (MTI)
Pismo Beach (PMO)
Northwest guard shack (WNl)
Cayucos Beach (CYA) .
Diablo Creek outlet (WN2)
Cambria Moonstone Beach (CBA)
Pacific Ocean North (PON)
Blanchard Cow Meat (BCM)
Pacific Ocean South (POS)
Blanchard Goat Meat (BGM)
Offsite Emergency Lab (OEL)
Blanchard Sheep Meat (BSM)
Plant outfall (OUT)
Control Cow Meat (CCM)
Drinking water (DWI)
Johe Deer Meat (JDM)
Water Well 02 (WW2)
Johe Pig Meat (JPM)
Observation Well 01 (OWI)
Andre Cow Meat (ACM)
Observation Well 02 (OW2)
Andre Deer Meat (ADM)
Drywell 115 (DYl)
Andre Pig Meat (APM)
Avila Beach (AVA)
ISFSI TLDs (IS 1 - IS8)
Groundwater Monitoring Well I (GWI)
Groundwater Monitoring Well 2 (GW2)
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TABLE2.3:
Detection Capabilities 'for Environmental Sample Analysis (a)
Lower Limits of Detection (LLD) (b)
Airborne Food Water Particulate or
Fish Milk Products Soil/Sediment Analvsis, ([!Ci/L} Gases (oCi/m') 3 (pCi/kgi wet} ([!Ci/L} <nCi/kf!. wet) ([!Ci/kgi drv) e Gross beta 4 0.01 H-3 400c Mn-54 15 130 150 Fe-59 30 260 300 Co-58 *15 130 "
150 Co-60 15 130 150 Zn-65 30 260 300 Zr-95 30 300 Nb-95 15 150 I-131 Id 0.07 I 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 600 La-140 15 15 150 Table Notations a) The gamma emitters and corresponding LLD values listed are derived from standard ODCM guidance for environmental samples as found in Table 4.12-1 in NUREG-1301. This list does not*
, mean th~t only th~se nuclides are to be considered. Other peaks that are identifiable, together with those of the above'nuclides, shall also be analyzed and reported in the Annual Radiological En~ironmental Operating Report. .
b) The LLD is defined, for purposes of these specifications, as the a-priori smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a* "real" signal.
c) If no drinking water pathway exists, a value of 3,000 pCi/L may be used for tritium. All groundwater wells should use the 400 pCi/L tritium value regardless of drinking water use.
d) The LLD value of 1 pCi/L for 1-131 is applicable only to sources used as drinking water.
If no drinking water pathway exists, a value of 15 pCi/L may be used forl-131.
e) The gamma emitters LLD values liste<l: for soil/sediment we derived from the Cs-134/13710:1 ratio-established in the environmental LLDs in NUREG-1301, Table 4.12-1.
TABLE 2.3 (Continued)
Table Notations For a particular measurement system, which may include radiochemical separation:
LLD 4.66sb Ex V x 2.22 x Y x exp(-A.t)
Where:
LLD the "a priori" the lower limit of detection as defined above (as pCi per unit mass or volume) the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E the counting efficiency (as counts per transformation) v the sample size (in units of mass or volume) 2.22 the number of transformations per minute per pico-curie y the fractional radiochemical yield (when applicable)
A, the radioactive decay constant for the particular radionuclide t the elapsed time between sample collection (or end of the sample collection period) and.
time of counting The value of Sb used in the calculation of the LLD for a detection system will be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background will include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Analyses will be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Environmental Radiological Operating Report.
Typical values ofE, V, Y and t should be used in the calculation. It should be recognized that the LLD is defined as a-priori (before the fact) limit representing the capability of a measurement system and not as a-posteriori (after the fact) limit for a particular measurement.
TABLE 2.4: Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Water Particulate or Fish Milk Food Products Analysis (pCi/L) G:\ses (pCi/m3 ) (pCi/kg, wet) (pCi/L) .(pCi/kg, wet)
I H-3
20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 ** 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
For drinking water samples. This is the 40 CPR 141 value. If no drinking water pathway exists, a value of 3D,OOO pCi/L may be used.
If no drinking water pathway exists, a value of 20 p~i/L may be used
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Figure 2.1- Diablo Canyon Off-site Stations This page intentionally left blank.
NW Pacific Ocean 5 Mile Radius SE
~
N LEGEND I
0 5 miles
Dosimetry Station D Air Particulate Station e Biological Sampling Station
Diablo Canyon Power Plant Units 1 and 2 Diablo Canyon off-site stations.
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Figure 2.2- Diablo Canyon On-site Stations This page intentionally left blank.
4S1A
~
cu u
\
WN1A c:
J 0
Cl'.)
2 en t t 6S1A Met Building --1--1~
Met Station E _ __,,___
~
LEGEND A Dosimetry Station
Air Particulate Station N
Biological Station I
Breakwater DCPP Onsite ERMP Stations
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Figure 2.3- Diablo Canyon Station Locations Thitl page intentionally left blank.
Dosimetry Sectors N Dosimetry &Air
Biological Prote cted .Area Site Boundary A 0 250 500 1,000 1,500 2,000
-==i-==----i::::::===---- Feet
This page intentionally left blank 3.0 RADIOLOGICAL DATA-
SUMMARY
OF TABLES This section summarized the analytical results of the environmental samples collected during the monitoring period. The results were presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (NUREG-1301).
Each table was nuclide specific and the total numbers of analyses for that radionuclide were provided. Additionally, the number of measurements which exceeded the Reporting Levels (NRC Notification Level) found in Table 2.4 of this report were provided. The first column listed the matrix or pathway sampled during the period. The second column listed the nuclides analyzed and number of samples performed. The third column provided the required a-priori Lower Limit of Detection (LLD) for radionuclides that have detection capability requirements as specified in Table 2.3 of this report. The fourth, fifth, and sixth columns contained the mean and range of results for locations. The seventh column contained the number of reportable occurrences for the location pathway. Occasionally, the required LLD may not be met. An example of this
occurrence might be due to hold times between sampling and analysis. Such cases, if any, were addressed in Section 4.2 of this report.
The a-posteriori Minimum Detectable Concentration (MDC) listed for each analysis in Appendix C was used as the detection evaluation point for each sample collected. The MDC was calculated by the laboratory with each analysis (a-posteriori) and incorporated conditions observed at the laboratory during the analysis. This MDC value mathematically represents the lowest concentration of activity that could be detected by the laboratory with a 95% confidence level. The MDC was also understood as the concentration where there was only a 5% probability of falsely reporting a positive detection in a true blank sample. Note that the a-posteriori MDC equation used by the environmental lab was the same as the a-priori Lower Limit of Detection (LLD) equation specified in NUREG-1301.
For this report, a sample was considered to yield a "detectable measurement" when the "result" concentration exceeded the associated a-posteriori MDC value for that analysis.
Additionally, the tables provided the mean of all sample results analyzed for the specified radionuclide/ media type, the range, and the number of samples that were considered to have detectable activity of all the samples counted:
The mean value consisted of the average of detectable concentrations
The lowest and highest detected concentration values were listed as the range
The number of deteCtable measurements and the total number of measurements were listed. For example, (4/20) would indicate that 4 of the 20 samples collected (for that sample type and that radionuclide) contained detectable radioactivity (>MDC).
The radionuclides reported in this section represented those that:
had an LLD requirement in Table 2.3, or a Reporting Level listed in Table 2.4
were of specific interest for any other reason The radibnuclides routinely analyzed and reported w.ithin a gamma spectroscopy analysis were:
Ac-228, Ag-108m, Ag-1 lOm, Ba-140, Be-7, Bi-212, Bi-214, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131, K-40, La-140, Mn-54, Nb-95, Pb-210, Pb-212, Pb-214, Ra-224, Ra-226, Ru-103, Ru-106, Sb-124, Sb-125, Th-234, Tl-208, Zn-65, and Zr-95.
Table 3.1 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCAJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( Bl RangeCB> Mean CB) RangeCBJ Mean CB> Range(B) Occurrences Direct Radiation
( mR/std quarter) 5Sl, 0.4 mi, 58° See Table 2.2 2F2, 4Dl, 5Fl IEnv TLD Badges< C> ( 38~ 5 mR/qtr I 21.8 I 20.0 - 24.o c12112) I 16.0 11.2 - 24.o (348/348) I 13.8 110.0 - 17 .9 (36/36) I 0
~
IS4, 0.3 mi, 65° ISl - IS8 lrsFSI TLDJ. l 0
c 96 )I 5 mR/qtr I 102.2 190.8 - 113.7 c12112) I 44.1 I22.0 - 113.7 (96/96) I 0 Table Notation:
(A) Sensitivity ofTLD system
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
( C) 96 TLD badges are distributed quarterly at 32 locations (29 indicator stations and 3 control stations). Each quarter there are 3 badges per station.
( D ) 24 ISFSI TLD badges are distributed quarterly at 8 locations surrounding the ISFSI protected area within the site boundary. Each quarter there are 3 badges per station.
Table3.2 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115
(
Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCA) Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean<Bl Range(B) Mean (Bl Range (Bl Mean (Bl Range (Bl Occurrences Airborne Iodine (364) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79°
( pCi/meter 3
) 1~131' 0.07 I None Detected ( 0 I 52 ) I None Detected ( 0 I 312) l.14E-2 I l.14E-2 ( 11 52) 0 Airborne Air Particulates (364) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79°
( pCi/meter 3
) I GrossBetal 0.01 3.19E-2 I 8.21E-3 to 9.55E-2 ( 52/52) 2.85E-2 I 3.74E-3 to 9.55E-2 (311/312) 4.lOE-2 I 4.72E-3 to 9.78E-2 ( 51/52) 0 Gammaisotopic<Cl (28) 7Dl, 6.6 mi, 118° OS2, lSl, 7Dl, 8Sl, 8S2, MTl 5Fl, 10.2 mi, 79° Cs-134 0.05 None Detected ( 0 I 4) None Detected ( 0 I 24 ) None Detected ( 0 I 4 ) 0 Cs-137 0.06 None Detected ( 0 / 4) None Detected ( 0 I 24 ) None Detected ( 0 I 4 ) 0 Airborne Air Carbon-14 (156) 8Sl, 0.5 mi, 125° OS2, 8Sl 5Fl, 10.2 mi, 79° 3
( uCi/meter ) Carbon-14 l.OOE-06 None Detected ( 0 I 52 ) None Detected ( 0 I 104) None Detected ( 0 I 52 ) 0 Table Notation:
(A) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
( C) These gamma isotopic samples are quarterly composite samples of all weekly particulate air sample filters. Approximately 13 particulate filters for each REMP location.
Plant related radionuclides, not naturally occurring isotopes.
Table3.3 Environmental Radiologieal Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection(AJ Name, Distance, and Direction All Indicator. Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( BJ Range( BJ Mean (BJ Range (B) Mean (BJ Range (B) Occurrences Surface Water DCM, 0.2 mi, 270° DCM, OUT 7C2,4.7 mi, 124°
( pCi/Liter ) Gamma Isotopic ( 36 )
Mn-54 15 none detected (0I 12 ) none detected ( 0 I 24 ) . none detected ( 0I 12 ) 0 Fe-59 30 none detected (OJ 12) none detected ( 0 I 24 ) none detected ( 0I 12 ) 0 Co-58 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12) 0 Co-60 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Zn-65 30 none detected (0I 12 ) none detected" ( 0 I 24 ) none detected ( 0I 12 ) 0 Zr-95 30 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Nb-95 15 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 1-131 15 none detected ( 0I 12 ) _none detected .( 0 I 24 ) none detected (0I 12 ) 0 Cs-134 15 none detected ( 0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Cs-137 18 none detected (0I 12) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Ba-140 60 none detected (0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 La 140. 15 none detected ( 0I 12 ) none detected ( 0 I 24 ) none detected (0I 12 ) 0 Additional Analysis Gross Beta ( 36) 4 375 I ?15-575 (12/12) 345 I 215-575 (24/24) 322 I 130-517 (9/12) 0 Fe-55 ( 36) rione detected ( 0 I 12 ) . none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Ni-63 ( 36) none detected ( 0 I 12 ) i:tone detecied ( 0 I 24 ) none detected ( 0 I 12 ) 0 Tritium H-3 ( 36 ) 400 none detected ( 0 I 12) none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Total Sr 89/90 ( 36 ) none detected ( 0 I 12) none detected ( 0 I 24 ) none detected ( 0 I 12 ) 0 Table Notation:
(A) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 _samples out of 12 collected showed activity.
Table 3.4 Environmental Radiological Monitoring Program Summary Report Period: 1/1115 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County , State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean<BJ Range< BJ Mean (BJ Range (BJ Mean (BJ Range CBJ Occurrences Drinking Water 5S2, 0.6 mi, 65° DWI, 5S2, WN2, 1A2 OEL, 10.2 mi, 79°
( pCi/Liter ) Gamma Isotopic ( 45 )
Mn-54 15 none detected (0/ 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Fe-59 30 none detected (0I 12 ) none detected ( 0 133 ) none detected (0/ 12 ) 0 Co-58 15 none detected (0/ 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Co-60 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0/ 12 ) 0 Zn-65 30 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 Zr-95 30 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Nb-95 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 I-131 1 none detected (0I 12 ) none detected ( 0 I 33) none detected ( 0I 12 ) 0 Cs-134 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected ( 0I 12 ) 0 Cs-137 18 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Ba-140 60 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 La 140 15 none detected (0I 12 ) none detected ( 0 I 33 ) none detected (0I 12 ) 0 Additional Analysis Gross Beta ( 45) 4 7.34 I 2.64 - 13.7 c4112) 6.06 I 2.64 - 13.7 c8/33) 5.3 I I.99 - 8.62 c2112 ) 0 Fe-55 ( 45) none detected ( 0 I 12 ) none detected ( 0 I 33) none detected ( 0 I 12 ) 0 Ni-63 ( 45) none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 TritiumH-3 ( 45) 400 none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 Total Sr 89/90 ( 45 ) none detected ( 0 I 12 ) none detected ( 0 I 33 ) none detected ( 0 I 12 ) 0 Table Notation:
(A) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means*
10 samples out of 12 collected showed activity.
Table3.5 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection(Al Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean( BJ Range( BJ Mean(BJ
Range(BJ Mean (BJ Range(BJ Occurrences Mussels
( pCi/kg) DCM, 0.2 mi, 270° DCM, PON, POS 7C2, 4.7 mi, 124° Gamma Isotopic (13)
Mn-54 none detected (0I 4) none detected ( 0I 9) -* none detected ( 0 I 4 ) 0 Fe-59 none detected {0I 4) none detected ( 0I 9) none detected (0I 4) 0
' Co-58 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0
- Co-60 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 Zn-65 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 Zr-95 none detected (0I 4) none detected ( 0I 9) none detected ( 0I 4 ) 0 Nb-95 none detected (0I 4) none detected ( 0I 9) none detected (0I 4) 0 I-131 60 none detected (0I 4) none detected (0I 9) none detected (0I 4) 0 Cs-134 60 none detected ( 0I 4 ) none detected (0I 9) none detected ( 0I 4) 0 I
Cs-137 80 none detected ( 0I4) none detected (0I 9) none detected ( 0I 4) 0 Ba-140 none detected (0I 4) none detected (0I 9) none detected ( 0I 4 ) 0 La-140 none detected (0I 4) none detected (0I 9) none detected ( 0I 4) 0 Table Notation:
(A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
Table 3.6 Environmental Radiological Monitoring Program Summary Report Period: 111/15 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State) l Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectiodAJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) MeanCB> RangeCBJ Mean (BJ RangeCBJ Mean CB> Range<BJ Occurrences Fish
( pCi/kg) POS, 0.4 mi, 180° DCM, PON, POS, 2Fl, 7D3 7C2, 4.7 mi, 124° Gamma Isotopic ( 37)
Mn-54 130 none detected ( 0 I 8 ) none detected ( 0 129 ) none detected ( 0 I 8 ) 0 Fe-59 260 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Co-58 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Co-60 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Zn-65 260 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Zr-95 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Nb-95 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 I-131 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Cs-134 130 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Cs-137 150 6.36 I 6.36 ( 1/8) 6.36 I 6.36 ( 1129) 4.78 I 4.78 ( 1/8) 0 Ba-140 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 La-140 none detected ( 0 I 8 ) none detected ( 0 I 29 ) none detected ( 0 I 8 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
Table 3.7 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Perfonned (LLD) Mean< BJ Rang~BJ Mean (BJ Range< BJ Mean<BJ Range< BJ Occurrences Algae*
( pCi/kg) DCM, 0.2 miles, 270° DCM, 0.2 miles, 270° 7C2, 4.7 miles, 124° Gamma Isotopic (4)
Mn-54 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Fe-59 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Co-58 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Co-60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Zn-65 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Zr-95 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 Nb-95 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected (0I4) 0 I-131 60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Cs-134 60 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Cs-137 80 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4 ) 0 Ba-140 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4 ) 0 La-140 DCM algae unavailable in 2015 DCM algae unavailable in 2015 none detected ( 0I 4) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.
These samples are supplemental samples.
Table 3.8 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/3l/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Anriual Mean
Number of Sampled . Number of Analyses DetectionCAJ Name, Distance, and Direction All Indicator Locations Aii Control Locations Reportable (Uhit of Measure) P()rformed (LLD) ,MeanCBJ RangeB> MeanCBJ
Range Mean Range Occurrences Kelp*
( pCi/kg) DCM, 0.2 mi, 270° DCM, PON, POS 7C2, 4.7 mi, 124° Gamma Isotopic ( 16)
Mn-54 none detected ( 0I 4 ) none detected (0I 12 ) none detected (0I4) 0 Fe-59 none detected ( 0I 4 ) none detected (0I 12 ) none detected (0I4) 0 Co-58 none* detected ( 0 I 4) none detected (0I 12 ) none detected ( 0I 4) 0 Co-60 none detected ( 0I 4 ) none detected (0I 12 ) none det~cted ( 0I 4) 0 Zn-65 none detected ( 0I 4 ) none detected (0I 12) none detected (0I 4) 0 Zr-95 - none detected ( 0I 4 ) none detected (0I 12) none detected ( 0I 4 ) 0 Nb-95 none detected (0I4) none detected (0I 12 ) none detected ( 0I 4 ) 0 1-131 60 none detected (0I4) none detected (0I 12) none detected (0I4) 0 Cs-134 60 none detected ( 0I 4 ) , none detected (0I 12 ) none detected ( 0I 4) 0 c Cs"137 80 none detected ( 0I 4 ) none detected (0I 12) none detected (0I 4) 0 Ba-140 none detected ( 0I 4 ) none detected (0I 12) none detected (0I4) 0 La-140 none detected ( 0I 4 ) none detected (0I 12 ) none detected ( 0I 4 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2 .3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity. ~
These samples ate supplemental samples.
Table3.9 Environmental Radiological Monitoring Program Summary Report Period: 1/1115 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<A> Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< Bl Range< Bl Mean (Bl Range(B) Mean (Bl Range(B) Occurrences Vegetative Crops
( pCi/kg) 6Cl, 4.5 mi, 98° 3Cl, 5F2, 6Cl, 7Cl, 7El 7Gl, 16.8 mi, 115° Gamma Isotopic ( 55 )
Mn-54 None Detected ( 014) None Detected ( 0142) None Detected (0/ 13 ) 0 Fe-59 None Detected ( 014) None Detected ( 0 I 42) None Detected (0/ 13 ) 0 Co-58 None Detected ( 014) None Detected ( 0 142) None Detected (0/ 13 ) 0 Co-60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Zn-65 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Zr-95 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Nb-95 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 I-131 60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Cs-134 60 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected (0I 13 ) 0 Cs-137 80 31.0 (1/4) 31.0 ( 1/ 42) None Detected ( 0I 13) 0 Ba-140 None Detected ( 0 I 4) None Detected ( 0 I 42) None Detected ( 0I 13) 0 La-140 None Detected ( 0 I 4 ) None Detected ( 0 I 42) None Detected ( 0I 13) 0 Table Notation:
(A) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (10/12) means 10 samples out of 12 collected showed activity.
Table 3.10 Environmental Radiological Monitoring Program Summary Report Period: 111/15 - 12/31/15 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< Bl Range<Bl Mean<Bi Range< Bl Mean <Bl Range<Bl Occurrences Milk
( pCi/Liter ) 5F2, 12.6 mi, 60° Iodine extraction ( 12 )
1-131 1 Not Applicable Not Applicable None Detected ( 0 / 12) 0 Gamma Isotopic ( 12 )
Mn-54 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Fe-59 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Co-58 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Co-60 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Zn-65 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Zr-95 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Nb-95 Not Applicable Not Applicable None Detected ( 0 I 12) 0 Cs-134 15 .Not Applicable Not Applicable None Detected ( 0 /12) 0 Cs-137 18 Not Applicable Not Applicable None Detected ( 0 /12) 0 Ba-140 60 Not Applicable Not Applicable None Detected ( 0112) 0 La-140 15 Not Applicable Not Applicable None Detected ( 0 /12) 0
,p*" .. ;
I "<..><<' "' ,,,, .* ,.._
.. I I Total Sr 89/90 <12) I I Not Applicable I Not Applicable I None Detected ( 0112) I 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.11 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Perfonned (LLD) Mean< BJ RangtfB) Mean<BJ Range<BJ Mean (BJ Range<BJ Occurrences Meat
( pCi/kg)
BCM, 1.5 mi, 331° BCM, 1.5 mi, 331° CCM, 37mi, 328° Gamma Isotopic ( 8 )
Mn-54 none detected (0I 4) none detected ( 0I 4 ) none detected ( 0I 4) 0 Fe-59 none detected (0I 4) none detected (0I4) none detected ( 0I 4) 0 Co-58 none detected ( 0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Co-60 none detected (0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Zn-65 none detected ( 0I 4) none detected ( 0I 4 ) none detected ( 0I 4 ) 0 Zr-95 none detected ( 0I 4) none detected ( 0I 4 ) none detected (0I4) 0 Nb-95 none detected (0I4) none detected (0I4) none detected (0I4) 0 1-131 60 none detected ( 0I 4 ) none detected (0I4) none detected (0I4) 0 Cs-134 60 none detected ( 0I 4 ) none detected (0I4) none detected (0I4) 0 Cs-137 80 none detected (0I4) none detected (0I4) none detected (0I4) 0 Ba-140 none detected (0I4) none detected (0I4) none detected (0I4) 0 La-140 none detected (0I4) none detected ( 0I 4 ) none detected (0I4) 0 I
., .. I I Total Sr 89/90 c8) I I none detected ( 0/4 ) I none detected ( 0 I 4 ) I none detected ( 0 I 4 ) I 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis, e.g. (10/12) means 10 samples out of 12 collected showed activity.
Table 3.12 Environmental Radiological Monitoring Program Summary Report Period: 111115 -12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Medium or Pathway Type and Total of Highest Annual Mean Number of Sampled Number of DetectionCA> Name, Distance, and Direction Indicator Locations Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean(B) Range 8 ' Mean CB) Range Mean Range Occurrences Ocean Sediment
( pCi/kg dry ) DCM, 0.2 mi, 270° DCM, 0.2 mi, 270° 7C2, 4.7 mi, 124° Gamma Isotopic ( 4 )
Mn-54 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Fe-59 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Co-58 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Co-60 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Zn-65 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Zr-95 300 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Nb-95 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 I-131 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Cs-134 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Cs-137 180 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Ba-140 600 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 La-140 150 none detected ( 0 I 2) none detected ( 0 I 2) none detected ( 0 I 2) 0 Fe-55 ( 2) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Ni-63 ( 2) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Total Sr 89/90 ( 2 ) none detected ( 0 I 1) none detected ( 0 I 1) none detected ( 0 I 1) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations' is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.13 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Analyses DetectionCAl Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Peifonned (LLD) Mean< Bl RangeCBJ Mean CB> Range Mean CB> RangeCB> Occurrences Beach Sand
( pCi/kg dry ) AVA, 7.3 mi, 109° A VA, MDO, PMO, CYA CBA, 28.5 mi, 330° Gamma Isotopic ( 10 )
Mn-54 150 none detected (0I2) none detected ( 0I 8) none detected ( 0I 2 ) 0 Fe-59 300 none detected (0I2) none detected (0I 8) none detected ( 0I 2 ) 0 Co-58 150 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Co-60 150 none detected (0I 2) none detected (0/8) none detected ( 0I 2 ) 0 Zn-65 300 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Zr-95 300 none detected (0I2) none detected (0/8) none detected ( 0I 2 ) 0 Nb-95 150 none detected (0I2) none detected (0I 8) none detected ( 0I 2) 0 I-131 none detected (0I 2) none detected (0I 8) none detected (0I2) 0 Cs-134 150 none detected ( 0I 2 ) none detected ( 0I 8) none detected (0I2) 0 Cs-137 180 none detected ( 0I 2 ) none detected ( 0I 8) none detected (0I2) 0 Ba-140 600 none detected ( 0I 2 ) none detected (0I 8) none detected (0I2) 0 La-140 150 none detected ( 0I 2 ) none detected (0I 8) none detected (0I2) 0 Fe-55 ( 10) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Ni-63 ( 10) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Total Sr 89/90 ( 10 ) none detected ( 0 I 2 ) none detected ( 0 I 8 ) none detected ( 0 I 2 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B ) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g. , (I 0/12) means 10 samples out of 12 collected showed activity.
Table 3.14 Environmental Radiological Monitoring Program Summary Report Period: 111115 - 12/31115 Name of Facility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< BJ Range< BJ Mean (BJ Range<Bl Mean<Bl Range<Bl Occurrences Groundwater
( pCi/Liter ) 8S3, 0.3 mi, 145° 8S3, 0.3 mi, 145° WW2, 0.6 mi, 70° Gamma Isotopic ( 8 Mn-54 15 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Fe-59 30 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Co-58 15 none detected 0/4) none detected (0I4 l none detected ( 0I 4 ) 0 Co-60 15 none detected 0/4) none detected ( 0I 4 l none detected ( 0I 4 ) 0 Zn-65 30 none detected 0/4) none detected (. 0 I 4 1 none detected ( 0I 4 ) 0 Zr-95 30 none detected 0/4) none detected 0/4) none detected ( 0I 4 ) 0 Nb-95 15 none detected 0/4) none detected 0/4 none detected (0I 4 ) 0 I-131 15 none detected 0/4) - none detected ( 0/4 none detected (0I 4 ) 0 Cs-134 15 none detected ( 0I 4 ) none detected ( 0I 4 ) none detected (0I 4) 0 Cs-137 18 none detected (0I4) none detected (0I4) none detected (0I 4) 0 Ba-140 60 none detected (0I4) none detected (0I4) none detected (0I4) 0 La-140 15 none detected ( 0I 4 ) none detected (0I4) none detected (0I 4 ) 0 I .. ... "I .. .. l Gross Beta ( 8 4 7.79 I 1.75-21.2 ( 414) 7.79 I 1.75-21.2 ( 414) 11.8 I 4.16-39.7 (214) 0 Fe-55 ( 8) none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Ni-63 ( 8) none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Total Sr 89/90 ( 8 ) none detected ( 0 I 4 ) none detected 0/4) none detected ( 0 I 4 ) 0 TritiumH-3 ( 8) 400 none detected ( 0 I 4 ) none detected ( 0 I 4 ) none detected ( 0 I 4 ) 0 Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.
Table 3.15 Environmental Radiological Monitoring Program Summary Report Period: 1/1/15 - 12/31/15 Name ofFacility: Diablo Canyon Power Plant Location of Facility: San Luis Obispo, CA (County, State)
Lower Limit Indicator with Highest Medium or Pathway Type and Total of Annual Mean Number of Sampled Number of Detection<AJ Name, Distance, and Direction All Indicator Locations All Control Locations Reportable (Unit of Measure) Analyses Performed (LLD) Mean< BJ Range<BJ Mean <BJ Range(B) Mean (BJ Range<BJ Occurrences Monitoring Wells DYI, 0.03 mi, 77° DYI, GWI, GW2, OWl, OW2 WW2, 0.6 mi, 70°
( pCi/Liter ) Gamma Isotopic ( 18 )
Mn-54 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Fe-59 30 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Co-58 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Co-60 15 none detected 0/2) none detected ( 0I 14 ) none detected ( 0 I 4 ) 0 Zn-65 30 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Zr-95 30 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Nb-95 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 I-131 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Cs-134 15 none detected (0I2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Cs-137 18 none detected (0I2) none detected (0I 14) none detected ( 0 I 4 ) 0 Ba-140 60 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 La-140 15 none detected 0/2) none detected (0I 14 ) none detected ( 0 I 4 ) 0 Gross Beta ( 18) 4 23.4 I 21.3 to 25.5 ( 2/2) 19.6 I 6.0 to 44.5 ( 12/14) 11.8 I 4.16 to 39.7 c2/4 l 0 Fe-55 ( 181 none detected 0/2) none detected ( 0 114 ) none detected ( 0 I 4 ) 0 Ni-63 ( 18) none detected 0/2) none detected ( 0 I 14 ) none detected ( 0 I 4 ) 0 Total Sr 89/90 ( 18 ~ none detected 0/2) none detected ( 0 I 14 ) none detected ( 0 I 4 ) 0 Tritium H-3 ( 19 400 7,280 I 4580 to 11,600 ( 313) 2,790 I 252 to 11,600 <10115 l none detected ( 0 I 4 ) 0
,. Table Notation:
( A ) Unless specified, all required LLDs were met in accordance with Table 2.3
( B) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis e.g., (10/12) means 10 samples out of 12 collected showed activity.
Note : Monitoring well tritium concentrations due to rain washout of an approved airborne discharge pathway from plant vents.
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4.0 ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 REMP SAMPLING VARIANCE I DEVIATIONS The DCPP Radiological Environmental Monitoring Program (REMP) allowed for deviations in the REMP sampling schedule "if samples were unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of sampling equipment." Such deviations did not compromise the program's effectiveness and were normally anticipated for any radiological environmental monitoring program.
The DCPP REMP included both required and supplemental samples. This section described the variances/deviations with sampling and described some of the supplemental sampling conducted during the year.
4.1.1 DIRECT RADIATION The ISFSI projects team loaded an additional 8 spent fuel dry casks onto the DCPP ISFSI pad from May 1st to July 3rd, 2015.
4.1.2 AIRBORNE RADIOACTIVITY The 2015 mean percent availability for on-site and off-site particulate and iodine (P&I) air samplers was 99.5 percent. In other words, all P&I air samplers were up and running 99.5 percent of the time. Less than 0.4 percent of run time could_be attributed to equipment problems, filter exchange, or calibration processes. Specific 2015 air sampling run time deviations were as follows:
2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months oflost run time occurred at station MTI on 3/4/ 15 due to site maintenance
6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months oflost run time occurred at stations 1S1 and 8S2 on 3/14/15 due to site maintenance
60.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of lost run time occurred at station 8S2 during the week of 3/4/15 due to air sample pump failure
149 .8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of lost run time occurred at station SF 1 during the week of 4/8/ 15 due to air sample pump failure Actual 2015 percent availabilities for each station were as follows:
OS2 = 99.9 %
lSl = 99.8 %
5Fl = 98.2 %
7Dl = 100 %
8Sl = 99.7 %
8S2 = 99.1 %
MTI = 99.9 %
Airborne C-14 supplemental sampling was performed weekly at stations 8S 1 (SE Sector), OS2 (NW Sector), and 5Fl (control station in San Luis Obispo) in 2015 .
General Engineering Labs (GEL) and DCPP REMP worked together to develop a method for sampling inorganic environmental airborne C-14 (as C0 2 ). It should be noted that C-14 lab data was reported in units ofuCi/m 3 (not pCi/m 3) within Appendix A.
GEL has monitored C-14 samples from various locations around the US. In some instances a very slight negative bias has been observed in annual data sets. The bias was not enough to mask any true positive detection ofC-14. GEL believes tills bias may be the result of the sorbent piclcing up other chemical species in the field during the week long collection. These chemical species (possibly S0 2 or N0 2 ) could cause some quenching effects in the liquid scintillation analysis and
varies by site location. This chemical interference created a net effect where some field cartridges were slightly lower in activity than laboratory blanks. The bias was less than the average two sigma method uncertainty and significantly less than the method average detection limit.
4.1.3 MARINE SAMPLES DCM supplemental quarterly intertidal algae samples were unavailable during 2015.
All remaining 2015 marine samples were collected as scheduled (including allowable variation).
The California Department of Fish and Game issued regulations prohibiting the collection of abalone along the central and southern coast of California. PG&E considers it unlikely that future collection of abalone will be allowed within the DCPP environs. The REMP has therefore ceased routine abalone sampling. Note that the sampling of abalone was previously performed and was supplemental to the REMP.
4.1.4 TERRESTRIAL SAMPLES All 2015 terrestrial samples were collected as scheduled (including allowable variation) with the following exceptions:
Supplemental Blanchard Sheep Meat (BSM) and Blanchard Goat Meat (BGM) were not available and were not provided by the rancher during all of 2015. Blanchard sheep and goats were not within 5 miles of the DCPP site in 2015 . The changes in Blanchard ranch operations were due to the ongoing severe drought conditions along the central coast of California.
4.1.5 OCEAN SURFACE WATER, DRINKING WATER, AND GROUNDWATER All 2015 water samples were collected as scheduled (including allowable variation) with the following exceptions :
Observation Well 02 (OW2) was dry during all four quarters of2015 . No OW2 monitoring well water samples were obtained in 2015.
Drywell 115 (DYi) was dry during the fourth quarter of 2015.
4.1.6 REPLICATE SAMPLES Replicate sampling was conducted within the REMP for program strength and quality. A replicate sample is an additional sample (same matrix type and station) taken independently from the original scheduled REMP sample. The replicate sample collection is performed by a different person and shipped to GEL to ensure independent analysis result correlation and method consistency.
Replicate samples were taken from:
7C2 - Ocean Sediment (2/5/15)
DCM - Ocean Sediment (2/ 19/15)
5F2 - Vegetation (6/23/15)
7GI - Vegetation (9/ 17/15)
The results of the replicate analyses were within expected correlation of routine sampling.
4.2 COMPARISON OF ACHIEVED LLDS WITH REQUIREMENTS For each analysis having an LLD requirement, criteria and process procedures were in place to achieve the calculated "a-priori " (before the fact) LLD. Meeting these process criteria satisfies the "a-priori" LLD requirements. The "a-posteriori " (after the fact) Minimum Detectable Concentration (MDC) for that analysis was also compared with the required "a-priori" (before the fact) LLD.
Table 2.3 of this report list the required "a-priori" Lower Limits of Detection (LLDs) for environmental sample analyses required by the DCPP Radiological Environmental Monitoring Program. Occasionally an LLD may have been unachievable due to sampling process situations, such as hold times between sampling and analysis.
Air sampling a-priori LLDs were not met for REMP P&I samples from 2125115 through 3/4/ 15 due to shipping weather (snow) delays.
All remaining analyzed REMP samples met the specified "a-priori" LLD requirements in 2015.
4.3 COMPARISON OF RESULTS AGAINST REMP REPORTING LEVELS NRC notification was required whenever a Reporting Level listed in Table 2.4 of this document was exceeded. Reporting Levels were the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.
It should be noted that environmental isotopic concentrations were averaged over the calendar quarter for the purposes of this comparison, and that Reporting Levels applied only to DCPP plant related effluent radioactivity.
No REMP Reporting Levels were exceeded during this 2015 monitoring period.
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4.4 DATA ANALYSIS BY MEDIA TYPE The REMP data for each media type is discussed below. A sample was considered to yield a "detectable measurement" when the resultant concentration exceeded the MDC for that analysis.
4.4.1 Direct Radiation (Environmental TLDs)
Direct radiation was continuously measured at 32 locations surrounding DCPP using Panasonic UD-814 thermo-luminescent dosimeters (TLDs). These 32 locations were made up of29 indicator stations & 3 control stations. These station TLD dosimeters were distributed and collected e:rery calendar quarter for processing. Methodology from ANSl/HPS Nl3.3 7-2014 "Environmental Dosimetry - Criteria for System Design and Implementation" was used to evaluate and report the Env TLD data. Historical background baseline values for each station were established from 1987 to 2008 Env TLD data.
DCPP enviromnental TLD results were measurements of all environmental gamma radiation sources (cosmic, terrestrial, radon, and man-made) at each station during the deployment period.
Transient and lab storage background dose contributions were subtracted prior to repotiing.
Technically, these TLDs read out in units ofmilliroentgen. Because gamma radiation has a
quality factor of approximately I for conversion from milliroentgen to millirem, the env ironmental TLD unit of reporting was converted to millirem (mr) for consistency of unit reporting and ease of exposure communications.
An evaluation of direct radiation measurements and member of public occupancy times within the site boundary indicated all federal criteria for member of public dose limits (1 OCFR20.130 I) were conservatively met. An evaluation of direct radiation measurements indicated all federal EPA 40CFR 190 criteria were conservatively met. Comparing data from the 2015 DCPP Annual Radiological Effluent Release Report (ARERR), dose to a member of the public resulting from gaseous effluent releases at DCPP was an extremely small fraction of measured Env TLD dose.
Therefore, it was concluded that gaseous effluents from DCPP had negli gible impact on measured Env TLD values.
The following chart reports the 2015 quarterly Env TLD individual station results. These indi vidual station results were compared to a Historical Quarterly Baseline value that was calculated using individual station data from 1987 to 2008.
Cha.ii column repo1iing methodology was as fo ll ows:
ND = not detected
Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseline; If_::: 5, report "ND". If > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4
Annual TLD Result= Qtr I + Qtr 2 + Qtr 3 + Qtr 4 Standard Quarter TLD Results
Annual Investigation Level Dose = Annual TLD Result - Historical Annual Baseline; If_::: I 0, repo1i "ND" . If > l 0, report value (mrem).
If "Investigation Level Dose" was detected, an evaluation of DCPP contribution was conducted ai1d explained within this report.
2015 Quarterly REMP Env TLD Analysis 2015 Annual REMP Env 11D At!aiYsis

~~

Uistorical 201 5 Standard Quarter 201 5 Qua rterly Investigation Level Historical 2015 Annual 201 5 Annual DCPP Distance Quarterly Baselin e T LD Res ults (mrcm) Dose (mrem) Ann ual Baselin e TLDResult lnvestigation Level Station ID in miles frnrem) Qtr l Qtr 2 Qtr 3 Qtr 4 Qtr I Qtr 2 Qtr 3 Qtr 4 (m rem) (mrem) Dose (mrem)
MT! 0.2 20.9 22. 1 20.3 16.7 18.6 ND ND ND ND 83.6 77.7 ND WNI 0.2 12.7 13.9 12.0 8.5 11.0 ND ND ND ND 50.8 45.4 ND OSI O. l 20.3 2 1.8 20.3 16.6 18.4 ND ND ND ND 8 1.2 77. l ND SSI 0.4 23.0 24.0 22.2 20.8 20.0 ND ND ND ND 92.0 87.0 ND 6SI 0.5 14.0 14.6 13.3 12.8 12.4 ND ND ND ND 56.0 53.1 ND 8S I 0.5 16.3 18.0 16.5 16.3 15.4 ND ND ND ND 65.2 66.2 ND 8S2 I. I 20.4 21.8 19.8 19. l 18.9 ND ND ND ND 81. 6 79.6 ND 5S3 0.7 18.6 19.3 17.8 18.2 17. 1 ND ND ND ND 74.4 72.4 ND 2F2 11.2 13.8 15.0 14.6 13.0 12.4 ND ND ND ND 55.2 55.0 ND 2Dl 6.9 12.2 14.4 13.2 12.2 10.9 ND ND ND ND 48.8 50.7 ND 4Dl 7.6 12.3 13.2 10.4 10.0 10.4 ND ND ND ND 49.2 44.0 ND 5Fl 10.2 17.7 17.9 17.0 15.7 15.4 ND ND ND ND 70.8 66.0 ND IA! 1. 6 12. 1 13.0 12.5 10.8 10.5 ND ND ND ND 48.4 46.8 ND 7D2 7.6 16.7 17.7 16.1 15.1 14.9 ND ND ND ND 66.8 63.8 ND 7G2 17.3 17.3 19.8 19.l 17.9 17. 1 ND ND ND ND 69.2 73.9 ND 7CI 4.1 18.0 18.6 17.3 16.6 15.5 ND ND ND ND 72.0 68.0 ND 7Fl 10.8 16.7 17.9 16.6 16.6 15.8 ND ND ND ND 66.8 66.9 ND OB I 3.6 10.3 l 1.8 9.8 7.2 9.3 ND ND ND ND 4 1.2 38. 1 ND 7DI 6.6 1 I.9 12.4 10.7 10.7 9.9 ND ND ND ND 47.6 43.7 ND 4C I 5.8 11.0 11.8 10.1 9.9 9.4 ND ND ND ND 44.0 41.2 ND OS2 0.5 17.l 18.0 17.0 13.9 15.3 ND ND ND ND 68.4 64.2 ND ISi 0.4 16.8 18.7 18.0 16.3 15.6 ND ND ND ND 67.2 68.6 ND 2Sl 0.2 16.9 17.5 17.2 16.0 14.7 ND ND ND ND 67 .6 65.4 ND 3SI 0.4 20.4 21.6 20.0 19.4 18.7 ND ND ND ND 8 1.6 79.7 ND 4Sl 0.5 18.9 20.4 18.7 17.5 17. 1 ND ND ND ND 75 .6 73.7 ND 7SI 0.3 18.3 2 1.1 20.0 19.0 17.5 ND ND ND ND 73.2 77.6 ND 9Sl 0.4 2 1. 7 23.6 22.3 21.1 20.2 ND ND ND ND 86.8 87.2 ND IC! 4.7 13.4 14.6 14. l 12.l 11.8 ND ND ND ND 53.6 52.6 ND SCI 4.7 16.6 16.4 l 5. 1 16.2 14.5 ND ND ND ND 66.4 62.2 ND 3D I 6.2 12.9 14.0 13.8 12.5 11.3 ND ND ND ND 5 1.6 51.6 ND 6DI 8.3 15.5 15.3 13.7 13.2 12.9 ND ND ND ND 62.0 55. 1 ND 5F3 12.7 19.8 17.5 16.3 16.0 14.7 ND ND ND ND 79.2 64.5 ND ND = not detected The 20 15 AREOR hi storical background has been determi ned using Env TLD results fro m 1987 to 2008 (before ISFSI operation). DCPP became operational in 1986.
Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseline. I f~ 5, report "ND. l f > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4 Annua l TLD Resu lt = Qtr l + Qtr 2 + Qtr 3 + Qtr 4 TLD Resu lts Arnmal Investigation Level Dose = Annua l TLD Result - Historical Annual Baseli ne. I f ~ 10, report "ND" . If > 10, report value (mrem).
See DCPP Station ID Maps in Figure 2.1 and Figure 2.2
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The following graph illustrated overall trending of Env TLDs with regard to distance from the DCPP plant site.
lnner ring, outer ring, special interest, and control stations were combined and averaged to obtain a single standard quarter value for each represented plot line.
Inner and outer ring TLD averages remained within and trended with pre-operational Env TLD ranges. DCPP operations did not affect Env TLD results.
30.0 - r - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
.,. Beginning of Start ISFSI Loact--+
plant operation - Inner Ring Stations
~-Fukushima Event
- special Interest Stations
- control Stations
- Outer Ring Stations 20.0 -l--/Yr---l--=--!.Nr----l.,.._--a--.-----,.-------A-----.---t-1\-i----!----A--.---~ Inner Ring Stations --OS1 , WN1 , OS2 ,
1S1 , 2S 1, 3S1, 4S1, 551 , 5S3, 6S1 , 7S1.
8S1 . 8S2, 9S1, and MT1 Special Interest Stations - 7F1 , 70 1, 702 , 7G2, and 5f3 Outer Ring Stations - 1A1 , 061 , 1C1 ,
201 , 301 , 4C 1, 5C1 , 60 1, and 7C1 5.0 -!------...-----------------~~~-----~
0.0+-- - - , . . . ; . - - - . . . - - -....... . - - -......- - --.----;;..,-----.......------1 1980 1985 1990 1995 2000 2005 2010 2015 2020 Year
The following graph illustrated averaged Env TLD results from the southeast sector (stations 8S 1, 8S2) and northwest sector (stations OS 1, OS2, OB 1).
These sectors were chosen for graphical trending due to their historically hjgh averaged wind directions and would therefore indicate the most gaseous effluent impact on environmental TLD results.
The southeast and northwest sectors Env TLD averages trended with pre-operational Env TLD ranges. DCPP operations did not affect Env TLD results within these sectors.
Averaged control stations (2F2, 401 , SF 1) were provided for reference.
30. o ..----~------------------.-..-------,
.., Beginning of Start ISFSI Loa~ :
plant operation
~ Fukushima Event - Southeast Sector Average 25.0 + - - - -- -- - - - -- -- - - - - - - - - - - -- - - ---1 - Northwest Sector Average
--=--Control Stations Southeast Sector - BS l end 852
'C
J Northwest Sector -081 , 052 , end 081
~ 15.0 UJ er:
E 1 0 . 0 + - - - -- -- - - - - - -- -- - - - - - - - - - T - - - - - - - - - 1 5.0 +----~----------------~---------1 0.0 +-----.,.....;...--...,...---.,...-----.---...,...-----"'.,...-"----r------!
1980 1985 1990 1995 2000 2005 2010 2015 2020 Year
Direct Radiation (ISFSI Env TLDs)
DCPP was licensed with an exclusion area boundary (i.e. site boundary) as an approximate 880 yard radius from U-1 Containment center. No permanent public access was permitted within the exclusion area. The unrestricted area (outside the site boundary) surrounding DCPP was sparsely inhabited out to five mi les from the site (ref 2015 Land Use Census within Section 8).
The direct radiation levels within a very small area surrounding the onsite ISFSI were elevated due to dry cask spent fuel storage. ISFSI pad TLD stations IS-1 through IS-8 were located adjacent to the ISFSI pad fencing (see map in Figure 2.2 of this report). The remaining onsite areas were not affected due to the ISFSI topographical elevation and placement within an onsite hillside which provided radiation shielding to the rest of the site.
The first spent fuel dry cask canister was loaded onto the ISFSI pad in Jw1e 2009. The small increase in radiation levels at the ISFSI pad prior to the first spent fuel canister load was due to storage of Radioactive Material (RAM) equipment in seatrains at the ISFSI pad prior to an outage. These seatrains of RAM were removed prior to the first load of spent fuel dry cask canisters.
Dry cask loading Campaign # 2 occurred in May 2010.
Dry cask loading Campaign # 3 occurred during the first quarter of 2012 and ended on 3/ 17/2012.
Dry cask loading Campaign# 4 occurred from August to October of2013.
Dry cask loading Campaign #5 occurred from 5/1/15 to 7/3/ 15 with the addition of8 dry casks onto the onsite ISFSI.
The following chart repo1ts the 2015 quarterly ISFSI Env TLD individual station results. These individual ISFSI station results were compared to the 1987 to 2008 Historical Quarterly Baseline value at station 5S 1. Station 5S 1 was used for historical baseline pmposes due to 5S 1 close proximity to the ISFSI pad and 5Sl pre-ISFSI historical data.
Chart column reporting methodology was as follows :
ND = not detected
Quarterly Investigation Level Dose= Standard Quarter TLD result - Historical Quarterly Baseline; If.::::: 5, report "ND". If > 5, report value (mrem).
Historical Annual Baseline = Historical Quarterly Baseline X 4
Annual TLD Result= Qtr 1 + Qtr 2 + Qtr 3 + Qtr 4 Standard Quarter TLD Results
Annual Investigation Level Dose = Annual TLD Result - Historical Annual Baseline; If.::::: 10, report "ND". If > 10, report value (mrem).
"Investigation Level Dose" was detected at ISFSI Env TLD stations IS-3 through IS-7 due to DCPP spent fuel dry casks stored on the ISFSI pad.
An evaluation of direct radiation measurements outside the site boundary indicated all federal EPA 40CFR190 criteria for public dose limits were conservatively met.
An evaluation of direct radiation measmements and member of public occupancy times within the site boundary indicated all federal criteria for member of public dose limits (10CFR20.l30 l) were conservatively met.
The following pages also contain a pictme of the ISF SI pad and a trend graph of onsite lSFSI pad averaged TLD results (IS-1 through IS-8).
. ~~~~~~-
2015 Quarter I ISFSJ Env TLD Anal sis -~~~~~~~~~~--'
2015 Annual ISFSI Env 1LD Anal sis Historica l 2015 Standard Quarter 2015 Quarterly investigation Level Historical 2015 Ann ual 2015 Annual DCPP Distance Quarterly Baseline TLD Results (mrem) Dose (mrcm) Annua l Baseline TLDResult lnvestigation Level Sta ti on ID in miles (mrem) Qtr I Qtr2 Qtr3 Qtr4 Qtrl Qtr2 Qtr3 Qtr4 (mrem) (mrem) Dose (mrem)
IS-I 0.3 23.0 23.6 22.6 23.3 24. 1 ND ND ND ND 92.0 93.6 ND IS-2 0.3 23.0 23.9 24.2 25.5 24.4 ND ND ND ND 92.0 98.0 ND lS-3 0.3 23. 0 33. 1 36.9 49.6 48.6 10.1 13.9 26.6 25.6 92 .0 168.2 76.2 IS-4 0.3 23. 0 90.8 92.6 111 .5 l 13.7 67.8 69.6 88.5 90.7 92.0 408.6 3 16.6 IS-5 0.3 23.0 53 .3 52. 1 51.8 50.3 30.3 29.1 28.8 27.3 92.0 207.5 115.5 IS-6 0.3 23.0 49.6 48 .8 48.4 43 .5 26.6 25.8 25.4 20.5 92 .0 190.3 98. 3 IS-7 0.3 23.0 37. 0 35.6 41.5 40.4 14.0 12.6 18.5 17.4 92.0 154.5 62.5 lS-8 0.3 23.0 22.8 23.3 23 .6 22 .0 ND ND ND ND 92.0 9 1.7 ND ND = not detected Historical Baseline from REMP Stat ion 5S l was used due to proxi mi ty to LSFSI and 5SI historical pre-lSFSI monitoring time frame fro m 1987 to 2008 Quarterly Investigation Level Dose = Standard Quarter TLD result - Historical Quarterly Baseli ne. If::; 5, report "ND". If > 5, report value (m rem).
Historical Annual Ba eline = Historical Quarterly Baseline X 4 Annual TLD Res ult = Qtr l + Qtr 2 + Qtr 3 + Qtr 4 TLD Res ults Annual Investigation Leve l Dose = Annual TLD Result - Historical Annual Baseline. If S I 0, report "ND". If > 10, report value (mrem).
See DCPP Station ID Map in Figure 2.2 The Investi gation Level quarterly and annual doses were due to spent fue l dry casks stored on the ISFS I pad.
The DCPP lSFSI Pad is located conserva ti ve ly within the DCPP site boundary (unrestr icted area).
The DCPP ISFSl Pad is topographically elevated above most of the site and is built into a hillside. These characteristics shi eld the rest of the site from ISFSI related rad iation.
No permanent public access is permitted within the DCPP site boundary (within the unrestricted area).
Access occupancy surrounding the ISFSI is isolated and co ntrolled by DCPP Security.
I OCFR20. l30 I member of public exposure and 40CFR l 90 unrestri cted area exposure were evaluated. Dose limits were not exceeded and were conservatively met.
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Onstte ISFSI Boundary TLD Stations 1..
50.0 ,__ _ _ _ _ _ISFSI
_ _Load
_ _Slart 1 - - ISFSI Sta tion a i 45.0 +---....___...~
f\ ~--A---1'-------------1 OM~* ISFSI St>Uons (AY<I) :
IS 1, IS2. ISJ. 1$4 , IS5, 1$6, 1$/ , & IS8 40.0 *- - - - --"- -- --1 1-- - - - -*~------*- -------
1i:>i
![ 35.0
i;:
w
~
30.0 *- - - - -* - - - - - - - - - - - - - - - - - - - - - - - - -
25.0 20.0 I 15.0 1-----------..-----......
2005 2010 2015 2020 2025 2030

'I 2035 Year

4.4.2 Airborne Air particulate and radioiodine samples were collected weekly from six indicator stations (MTl, OS2, lSl , 7Dl , 8Sl , and 8S2) in the DCPP environs and at one control station (5Fl). A total of 364 air particulate filters and 364 iodine cartridges were collected and analyzed as part of the normal REMP.
Natural occurring gross beta activity was detected in every weekly air particulate sample collected from all indicator and control stations. Comparison of the data showed that the mean values of gross beta activities for the indicator stations were consistent with those obtained for the control station and historical trending. Normal background gross beta values ranged from 3.7E-3 to 9.5E-2 pCi/m3 .
Gamma isotopic analyses were performed on quarterly composites of the air particulate filters from each of the REMP air stations. The midpoint date of the quarter was used to label the composite.
A total of 364 REMP weekly charcoal cartridges were analyzed for 1-131. 1-131 was detected one time at station 5Fl during the week of December 9-16, 2015. This is the control station located in San Luis Obispo (SLO). No other air stations closer to the site detected 1-131 during this time period. One possible explanation for I-131 at this location was it's proximity to the SLO sewage treatment facility (about 0.9 miles). Medical isotopes from the sewage treatment facility or from a person treated with 1-131 (thyroid ablation) in close proximity to the air sampler were the most likely sources of 1-131 detection at this location. *This I-131 detection in SLO was not due to DCPP operations.
Appendix A contains individual air sampling station data results.
4.4.3 Drinking Water and Ocean Surface Water Drinking Water Drinking water samples were collected from indicator stations DWI , 582, WN2, IA2, and control station OEL. The samples were analyzed for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55 , and Nickle-63. No plant related radionuclides were detected in any of the 2015 drinking water samples.
The results of the drinking water samples collected from both the indicator and control stations were individually listed in Appendix A.
Ocean Surface Water Ocean surface water samples were collected monthly from indicator stations OUT, DCM, and control station 7C2. The samples were analyzed for gamma emitters, gross beta, tritium, total strontium 89/90, lron-55 , and Nickle-63. No DCPP related radionuclides were detected in any of the 20 15 ocean surface water samples.
The resu lts of the surface water samples collected from both the indicator and control stations were individually listed in Appendi x A.
4.4.4 Ingestion Marine Biological Samples Mussels were collected quarterly from stations DCM, 7C2, and POS. Mussels were collected annually from station PON (due to small mussel bed/availability at station PON).
Fish samples were collected quarterly from stations DCM, PON, POS, 7C2 (control), and a local fish market (7D3 or 2F I). Market fish sam ples were locally caught fish.
Cs-137 was detected in fish at the following stations, dates, and concentrations:
7C2 Rockfish 2/5/ 15 4.78 pCi/kg
POS Perch 5122115 6.36 pCi/kg Pre-operational (pre-1985) DCPP REMP sampling observed measurable Cs-137 in fish and sediment due to atmospheric nuclear weapons testing fallout from the l 960's and l 970's. Finding Cs-137 in fish or sediment has been historically common in SLO County and the DCPP environs
due to atomic weapons testing fallout. The historical fish Cs-137 concentrations have ranged from 3 to 14 pCi/kg. These 2015 concentrations ofCs-137 detected in fish were within this range.
This Cs-137 activity was also in agreement with the 1981 California Dept of Health Services Radiological Health Branch report and was considered part of SLO County background radioactivity. The preoperational 1981 ranges ofCs-137 observed in the Diablo cove (DCM) fish were 0 to 26 pCi/kg (decay corrected 0 to 12 pCi/kg in 2015). The 1981 ranges ofCs-137 observed in market fish were 0 to 38 pCi/kg (decay corrected 0 to 17 pCi/kg in 2015). The 1981 ranges of Cs-137 observed in ocean sediment were 0 to 93 pCi/kg (decay corrected 0 to 42 pCi/kg in 20 15). The 1981 ranges ofCs-137 observed in soil were 0 to 298 pCi/kg (decay corrected 0 to 135 pCi/kg in 2015).
Another recent background source of Cs-137 into California environs was due to the March 2011 Fukushima Event and subsequent jet stream isotopic dispersion to the United States.
Because Cs-137 has an isotopic half-life of approximately 30 years, this contaminant should be detected in the DCPP environs for the next 10 to 40 years depending on initial concentration and the detection sensitivity of the REMP analyses. Cs-137 has a longer environmental half-life in coastal seawaters than in open oceans due to input sources like rain watershed runoff and storm condition sediment re-suspension.
No Cs-134 was found in these fish samples. Cs-134 has a shorter isotopic half-life (approximately 2 years), would be indicative of nuclear reactor fission products, and would not be attributed to atomic weapons testing. Because Cs-134 was absent in the REMP fish analyses; fish Cs-137 concentrations were attributed to either pre-l 980's nuclear weapons testing or Fukushima related fallout.
All other marine fish and mussel samples did not detect any DCPP related radionuclides in 2015.
The results of the marine biological samples collected from both the indicator and control stations were individually listed in Appendix A.
Marine Aquatic Vegetation Supplemental marine aquatic kelp sampling was performed quarterly at REMP sample indicator stations DCM, PON, POS, and 7C2 (control). Supplemental intertidal algae sampling was performed quarterly at REMP sample station 7C2.
Each sample was analyzed for gamma emitting radionuclides. No DCPP related isotopes were detected in 2015.
The results of the marine aquatic vegetation samples collected from both the indicator and control stations were individ ually listed in Append ix A.
Ocean Sediment and Recrea tional Beach Sampling Ocean sediment sam ples were collected annually from stations DCM and 7C2. Supplemental recreational beach sand samples were collected semi-annually from stations Avila Beach (AV A),
Montana de Oro Spooner's Cove (MDO), Pismo Beach near pier (PMO), Cayucos Morro Strand State Beach (CYA), and Cambria Moonstone Beach (CBA). Each sample was analyzed for gamma emitting radionuclides, total strontium 89/90, lron-55, and Nickle-63.
Only natural occurring isotopes where detected in the ocean sediment and recreational beach sand san1ples collected for 2015. The results were individually listed in Appendix A.
4.4.5 Vegetation (Food Crops)
Samples of broad leaf vegetation were collected monthly (when available) from two indicator stations (7C1 and 7G 1), and one control location (5F2). Supplemental samples were also collected quarterly from residence or commercial gardens at stations 3Cl, 6Cl, and 7El. The samples were analyzed for gamma emitting radionuclides and for Iodine-131 on edible portions.
No DCPP related isotopes were detected in 2015 vegetation.
The results of the vegetation samples collected from both the indicator and control stations were individually listed in Appendix A.
4.4.6 Milk There are no milking animals (for human consumption) within 5 miles of the plant site. In substitution, the DCPP REMP required additional air sampling at stations 882 and 1S1.
Supplemental samples of milk were collected monthly from Cal Poly Fann (station 5F2) due to Cal Poly dairy being the closest milk producer relative to the DCPP site and regardless of the availability of milk stations within 5 miles of the plant.
The milk samples were analyzed for gamma emitting radionuclides, Iodine-131 , and total strontium 89/90. No DCPP related radionuclides were detected in station 5F2 milk samples during 2015 .
The results of the milk samples were individually listed in Appendix A.
4.4. 7 Meat Products Meat products were collected quarterly when available or provided from landowners.
Blanchard cattle were allowed to graze on the northern lands around DCPP during 2015.
Blanchard Cow Meat (BCM) was sampled quarterly for gamma emitting radionuclides and total strontium 89/90.
Supplemental Blanchard Sheep Meat (BSM) and Blanchard Goat Meat (BGM) were not available and were not provided by the rancher during all of 2015. Blanchard sheep and goats were not within 5 miles of the DCPP site in 2015. The changes in Blanchard ranch operations were due to the ongoing severe drought conditions along the central coast of California.
Control station free range, grass fed beef sampling was conducted of ranches outside the influence of DCPP. This meat was purchased by REMP personnel from the Whole Foods Market in SLO. The control station meat consisted of Hearst Ranch beef which is located approximately 37 miles north of the DCPP site. This REMP station code was CCM (Control Cow Meat).
No DCPP related isotopes were detected in 2015 meats.
The results of the meat samples were individually listed in Appendix A.
5.0 GROUND WATER MONITORING Diab lo Canyon is committed to improving management of situations involving inadvertent radiological releases that get into onsite groundwater. This commitment reflects the nuclear industry's high standard of public radiation safety and protection of the environment. Trust and confidence on the part of local communities, California State, the NRC, and the general public is paramount to this commitment.
Groundwater gradient studies of the DCPP ISFSI site and a general assessment of sub-regional hydro-geologic conditions indicates that groundwater (subsurface) flow beneath the Diablo Canyon power block is west to northwest toward the Pacific Ocean. Any groundwater present beneath the DCPP power block was not used as a source of drinking water.
5.1 NEI 07-07 GROUNDWATER PROTECTION INITIATIVE - REPORTING 5.1.1 NEI 07-07 Objective 2.4 (b), Annual Reporting:
"Document in the AREOR all on-site ground water sample results that are included in the REMP as described in the DCPP Offsite Dose Calculation Manual (ODCM)".
Onsite groundwater monitoring points are described in the RBMP and reported in this 2015 Annual Radiological Environmental Operating Report (ARBOR) as follows:
Observation Well 01 (OWl), Observation Well 02 (OW2), Drywell 115 (DYl), DCSF96-1 (8S3),
Water Well 02 (WW2), Groundwater Well I (GWl), Groundwater Well 2 (GW2), and Diablo Creek Outlet (WN2) were used for Groundwater Protection Initiative (GPI) data reporting and were described in 2015 DCPP ARBOR Table 2.1.
5.2 GROUNDWATER SAMPLING OVERVIEW:
As part of the nuclear industry NEI 07-07 Groundwater Protection Initiative (GPI), DCPP began sampling various ground water sources in 2006. These sources included onsite monitoring wells (OWl, OW2, DYl, & 8S3), an aquifer well (WW2), Diablo Canyon creek (5S2 & WN2), and a groundwater spring (1A2). Two additional groundwater monitoring wells (stations GWl and GW2) were installed along the western side of the DCPP site on December 14, 2011. RBMP began sampling these two new wells during the first quarter of 2012.
One groundwater aquifer well (WW2) was available within the plant site boundary. This well was located about 250 feet above and to the east of the power block. WW2 was sampled quarterly for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55, and Nickle-63. No plant related radionuclides were detected in 2015.
One shallow (approximately 70 feet deep) subsurface monitoring well (8S3) was located southeast at approximately 0.3 miles from the power block. 8S3 was sampled quarterly for gamma emitters, gross beta, tritium, total strontium 89/90, Iron-55, and Nickle-63. No plant related radionuclides were detected in 2015.
Three shallow (approximately 37 to 73 feet deep) French drain system monitoring wells were located within the plant protected area and in close proximity to the containment structures, spent fuel pools, and radiologically controlled area auxiliary building. These French drain systems were labeled Observation Well 01 (OWl), Observation Well 02 (OW2), and Drywell 115 (DYl).
OW2 was not sampled in 2015 due to no water present in the well during the entire 2015 timeframe. There has been an ongoing severe drought in San Luis Obispo County which contributed to this dry well.
French drain monitoring wells OWl and DYl contained low levels of tritium throughout 2015 due to rainwater washout of gaseous tritium exiting the plant vent system (via an approved 1
effluents discharge path). These tritium concentrations were evaluated and were not due to a plant system leak or spill. This tritium was evaluated and attributed to the rain-washout of gaseous tritium exiting the plant vent system via an approved effluent discharge path. DCPP conducted rain-washout studies to document this phenomenon. These monitoring wells consisted of French drain systems that discharge into the associated monitoring well (OWl, OW2, or DYl). Rain communicated with these French drain systems via building structure to ground interfaces. Once rain water entered the monitoring wells, the water remained stagnant until another rain event caused transport. Subsequent quarterly sampling routinely indicated consistent tritium values due to monitoring well stagnation.
OWl was connected to subsurface groundwater flow fissures and routinely trends with rain fall.
DYl routinely experienced the highest rain-washout tritium concentrations due to its close proximity to the plant-vent gaseous discharge points.
The specific ranges of tritium detected in these power block monitoring wells for 2015 were as follows:
OWl - Observation Well 01 ( 1,130 to 1,590 pCi/L) 4 of 4 samples collected for tritium analysis.
OW2 - Observation Well 02; no samples collected (well dry)
DYl - Drywell 115 ( 4,580 to 11,600 pCi/L) 3 of 4 samples collected for tritium analysis.
No other DCPP related isotopes were detected in OWl, OW2, or DYL As mentioned previously, two down-gradient monitoring wells were added to the REMP in 2012.
Groundwater Well l (GWl) was located between the DCPP protected area and the cliff boundary of the Pacific Ocean. This well opening was located at approximately 85' above sea level on the same plane as the power block and was approximately 85' deep.
Groundwater Well 2 (GW2) was located between the DCPP protected area and the cliffboundary
of the Pacific Ocean. This well opening was located at approximately 85' above sea level on the same plane as the power block and was approximately 85' deep.
The specific ranges of tritium detected in GWl monitoring well for 2015 were as follows:
GWl - Groundwater Well 1 ( 252 to 306 pCi/L) 3 of 4 samples collected for tritium analysis.
This tritium was evaluated and attributed to the rain-washout of gaseous tritium exiting the plant vent system via an approved effluent discharge path.
No other DCPP related isotopes were detected in GWl or GW2 in 2015.
All other samples of groundwater at 582, 1A2, and WN2 did not indicate the presence of tritium or any other DCPP related isotopes (only NORM isotopes were observed) in 2015.
The results of groundwater sampling were individually listed in Appendix A.
Rain washout of tritium is discussed within NRC Regulatory Issue Summary (RIS) 2008-003, "Return/Re-use of Previously Discharged Radioactive Effluents".
(,
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N j
~
0
\./ELL ID 0 \./ ATER SURFACE ELEVATION LIN E OF ESTIMATED POTENTIDMETRIC SURF ACE GROUNDWATER GRADIENT MAP
~r9') cardna PACIFIC GAS AND ELECTRIC DIABLO CANYON NUCLEAR POWER PLANT FIGURE.
SITE LOCATI ON E N TRIX SAN LUIS OBISPO COUNTY, CALIFORNIA
6.0 OLD STEAM GENERATOR STORAGE FACILITY MONITORING In accordance with the DCPP Offsite Dose Calculation Manual (ODCM), the Old Steam Generator Storage Facility (OSGSF) in-building sumps were inspected quarterly. If water was found in the sump of a vault containing plant equipment, the expectation was to sample that sump water and dispose of the water per plant protocols via an approved discharge pathway.
For reference, the following equipment was placed into this OSGSF on the following dates:
3/2/08 (outage 2Rl4), four DCPP Unit Two (U-2) Steam Generators
2/14/09 (outage I RI 5), four DCPP Unit One (U-1) Steam Generators
1116109 (outage 2Rl5), one DCPP Unit Two (U-2) Reactor (Rx) Head
I 0/23/ 10 (outage IR 16), one DCPP Unit One (U-1) Rx Head As of I 0/23/10, the OSGSF contains eight old Steam Generators and two old Rx Heads.
No water was found in any OSGSF sumps during 2015 inspections.
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7.0 CROSS CHECK PROGRAM This page intentionally left blank.
8.0 DCPP LAND USE CENSUS This page intentionally left blank.
2015 DCPP Land Use Census Diablo Canyon Power Plant (DCPP) was owned and operated by Pacific Gas & Electric (PG&E) Company. PG&E owned and provided environmental stewardship to approximately 14 miles of Pacific Ocean coastline and approximately 13,000 acres surrounding the 1,000 acre DCPP site boundary. The PG&E property extended roughly from Avila Beach to Montana de Oro State Park.
DCPP was located approximately seven miles WNW of Avila Beach and approximately four miles SSE of Montana de Oro State Park.
DCPP Radiological Environmental Monitoring Program (REMP) personnel conducted a Land Use Census (LUC) in the vicinity ofDCPP for 2015. The LUC was based on Nuclear Regulatory Commission (NRC) Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants". The LUC also provided compliance with 10 CFR 50 Appendix I Section IV (B)(3); "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure".
DCPP Program Directive CY2, "Radiological Monitoring and Controls Program" required performance of a LUC. DCPP procedure RPI .IDI l, "Environmental Radiological Monitoring Procedure", required identification of the nearest milk animal, nearest residence, and the nearest broadleaf producing garden greater than 50 square meters (500 square feet) in each of the landward meteorological sectors within a radial distance of 8 kilometers (5 miles) of the Unit One Containment (CTMT) structure. A LUC was conducted at least once per year during the growing season (between Feb 15 and Dec 1) for the Diablo Canyon environs.
The 2015 LUC was conducted via a helicopter over-flight and landowner telephone interviews.
The helicopter over-flight was conducted on March 5th, 2015. Telephone interviews were conducted March 10th through November 25th, 2015. Ten individual landowners or tenants were contacted.
Milk:
No milk animals were identified within the first 8 kilometers (5 miles) of any sector.
Residences:
The nearest residence, relative to all sectors, was a small trailer located in the NNW sector about 2.42 kilometers (1.5 miles) from the plant. One ranch worker occupied this BLANCHARD trailer approximately 1 day per week (midweek) during the year.
A total of eighteen structures were identified within the 8-kilometer (5-mile) radius of the plant, which were confirmed or appear to have been occupied in 2015. A new structure (trailer) was identified in the ESE sector at 5.42 km (3.37 miles). Six abandoned structures were identified during the LUC.
The nearest residence in each sector was summarized in Table 8.
Gardens:
The LUC identified two household gardens greater than 50 square meters (500 square feet) that produced broadleafvegetation. The READ garden (REMP station 3Cl) was approximately 1/.i acre and located in the NNE sector at 7.13 kilometers (4.43 miles). The KOONZE garden (REMP station 6Cl) was approximately 500 square feet and locat_ed in the E sector at 7.43 kilometers (4.62 miles).
MELLO managed a farm in the ESE sector along the southern site access road coastal plateau.
The farm started at approximately 4.8 km (3 mi) and extended to 7.8 km (4.8 mi) from the site. This commercial farm produced no broadleaf vegetation. The farm area was about 100 acres of land with rotational planting. Commercial crops consisted of about 100% cereal grass (oat hay) and straw grass.
Less than 10 farm workers periodically occupied this area during the growing season.
Additional Land Use:
It should be noted that the term "site-boundary" referred to the area within a radius of approximately 1.2 km (0.74 mi) from the Unit One CTMT structure. The area outside the "site-boundary" was also referred to as the "unrestricted area". Much of the area outside the site-boundary was routinely used for rotational cattle grazing by five separate cattle operations. For purposes of this land use census, the five cattle ranches were called BLANCHARD, SINSHEIMER, READ, ANDRE, and MELLO.
BLANCHARD solely allowed cattle to graze within DCPP environs in 2015. BLANCHARD did not graze any goats or sheep within 8 km (5 miles) ofDCPP in 2015 due to extreme drought conditions in San Luis Obispo County.
BLANCHARD's livestock were sold under the "Old Creek Ranch" label at local farmer's markets in 2015. "Old Creek Ranch" labeled meats were sampled quarterly by REMP personnel in 2015. The REMP station codes were BCM, BGM, and BSM (if available).
SINSHEIMER had about 100 cattle outside the site-boundary in the NNE sector. These cattle were allowed to breed and about 90 calves were sold to mass market in 2015.
READ had about 72 adult cattle and 68 calves outside the site-boundary in the NNE sector.
About 68 yearling cattle were sold to mass market in 2015.
ANDRE had about 80 cattle outside the site-boundary in the ENE sector. About 80 calves were sold to mass market in ~015. ANDRE did not slaughter any cattle in 2015 for personal consumption.
MELLO managed about 800 ~attle outside the site-boundary' in the E, ESE, and SE sectors.
Harris Ranch Beef Corporation owned these cattle and sold all oftbem to mass market in 2015. MELLO did not slaughter any cattle in 2015 for personal consumption.
Two landowners (JOHE and ANDRE) harvested wild game ~or personal consumption outside the site-boundary in the NNE, NE, and ENE sectors. This wild game consisted of approximately two deer per landowner.
There was a California State Park Ranger Office in the NNW sector at 7.48 kilometers (4.65 miles) from the site. Approximately three State Parks staff personnel occupied this office from 1000 to 1500 each day (365 days per year).
There was a public campground (Islay Creek Campground) located in the NNW sector at Montana de Oro State Park at 7.36 kilometers (4.57 miles). This campground was near Spooner's Cove.
Approximately 713,000 people visited Montana de Oro State Park via day-use permit.
Approximately 22,000 people spent the night at Islay Creek Campground.
There was public access to hiking trails at the north and south ends of the PG&E property in 2015.
The Point Buchan Trail was located at the north end of PG&E property and had about 18,000 visitors in 2015. The trail traversed about 3.5 miles of coastline from Coon Creek to Crowbar Canyon.
The trail was open to the public for day hikes Thursday thru Monday from approximately 0800-1700.
Two to three people from California Land Management occupied the trail head booth near Coon Creek during operational days from 0700 to 1730. This trail was originally opened to the public on July 13, 2007.
The Pecha Coast Trail was located at the south end of PG&E property and had about 3,000 visitors in 2015. The trail was approximately 3. 7 miles long and led from the Avila Beach DCPP entrance gate to the Point San Luis Lighthouse property and up the coastline to Rattlesnake Canyon.
Access was controlled (via web-site reservation permission only) and conducted by docents. This trail was just slightly outside the 5 mile radius of the site. Pecha Coast Trail hikes were only available on Wednesdays (about 20 people) and Saturdays (about 40 people).
Thirty to forty Port San Luis Lighthouse keepers occupied the lighthouse grounds on Tuesdays, Thursdays, and Saturdays from 0800-1600. Special events were also held at the lighthouse throughout the year (e.g. weddings, fundraisers, reunions, etc). The lighthouse property was owned by the Port San Luis Harbor District.
Groundwater Protection Initiative (GPI) Review:
There were no site construction activities or spills that warranted changes to GPI monitoring frequencies, monitoring locations, contract lab analytical capabilities, or analytical detection thresholds in 2015.
There were no changes in on-site or near site groundwater usage. Groundwater beneath the site power block was not used as a source of drinking water.
Additional On-site Information:
The Old Steam Generator Storage Facility (OSGSF) was located within the site-boundary in the ENE sector (68.3 degrees) at 0.99 km (0.61 mi) from Unit One CTMT.
The following plant equipment was placed into the Old Steam Generator Storage Facility for the duration of the plant operating license on the dates indicated below.
Unit One old steam generators (4 total): 2/14/2009 Unit Two old steam generators (4 total) : 3/2/2008 Unit One old reactor head (1 total) : 10/23/2010 Unit Two old reactor head (1 total) : 11/6/2009 The on-site Independent Spent Fuel S~orage Installation (ISFSI) pad was located within the site-boundary in the ENE sector (58.47 degrees) at 0.36 km (0.22 mi) from Unit One CTMT.
DCPP loaded it's first ISFSI dry cask onto the pad on 6/23/2009.
The fifth ISFSI (dry cask) loading campaign occurred from May 1st to July 3rd in 2015.
Eight dry casks were added to the ISFSI pad in 2015.
Table 8 summarizes the nearest residence location in each meteorological sector.
The Land Use Figure shows the location of the residences and gardens in the vicinity ofDCPP.
Table8 Land Use Census 2015 Distance in Kilomet~rs (and Miles) from the center point ofU-1 CTMT Nearest Milk Animal, Residence, and Vegetable Garden
)
22Yz Degree (a) Nearest Nearest Residence Nearest Radial Sector Milk Animal Residence Azimuth Vegetable km (mi) Degree Garden km (mi)
NW None 5.76 (3.58) 325.2 None NNW None 2.42 (1.5) (b) 332.0 None N None None - None I
NNE None 5.18 (3.22) 21.5 7.13 (4.4) (c)
NE None 7.94 (4.'94) 36.4 None ENE None 7.15 (4..45) 63.8. None E None 5.97 (3.71) 89.9 7.43 (4.6) (d)
ESE None 5.42 (3.37) 122.0 5.31 (3.3) (e)
. SE None None - None Table Notation:
(a) Sectors not shown contain no land (other than islets not used. for the purposes indicated in.
thjs table) beyond the site-boundary.
(b) BLANCHARD trailer is the residence used for critical receptor calculations.
(c) The READ (station 3C1) vegetable garden is located in the NNE sector and located at the 20.24 azimuth degree. There is also a limited use residence at this location.
(d) The KOONZE (station 6Cl) vegetable garden is located in the E sector and located at the 97.52 azimuth degree. There is also a :('ull time residence at this location.
(e) The MELLO garden is the commercial farm along the westward side of the site access road; however, it does not produce broadleafvegetation. This farm extends from 4.8 km to 7.8 km (3 to 4.8 miles) from the plant.
\
NNW NW PaCific Ocean 5 Mile Radius J SE UNITS 1AND2 DIABLO CANYON SITE ~
N D Gardens or Farm I
A Residences 0 1 2 3 4 5
\
SCALE IN MILES Units 1 and 2 Diablo Canyon Power Plant Land Use Census.
9.0 DCPP WIND ROSE CHART This page intentionally left blank.
Joint requenc Distribution w*md pee d. an d. \V"md **repti"on...
Diablo Canyon Power Plant 10 eter e\*el 20 S N
39.36 4 .3$
4.8S
\\' 2.21 E 2.65 0.93 5.50
1. 10 5.17 2.01 s
Camis excluded.
0. H 6.8 1 5 19 4 2*U Rings drawn at 0% Intervals.
Wind flow is FROM the 1rections stiown.
Wind Speed ( Miles Per Hour) 603 obse<vabons wece- mi$$' 9.
PERCE! T OCC RRE CE: \ ind SpCICd ( Mib Per Hour PERC LOW ER BO N lJ O ( TEuORY
!lJ ill 4 0 1 4 1.1 0. 1 0.00 .00 1.2 0.77 0.00 1.S6 0.97 0.00 0.00 O.i6 0.* 9 .C>> 0.00
1. 8 I. 7 0,0! .00 ,$<6 0.07 0.00
~XE 1,0 0.00 00 0. 1 ~ 0.00 0_6 0.1 0.00 0.00 w 0.02 0.00 0.00
0. 1 0.09 0.00 0.00 3. 14 1.46 0. 13 1.4)7 0.3 0.00 .00 w '- 12.6 .74 4.3 0.06 .00 \V 1.)2 ...62 0.6 0.11 603 1\.1
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Joint Frequenc Di tr ibufo
\Vind peed and Wind Dlreetion Diablo Canyon o"er Pl nt 10 l\<leter e\*el 2011-2015 33.07 3.63 3.11 w 2.26 E 4.37 1.46 8 .47 2 .62 s
Cafms excluded.
Rings drawn at 10% intervals..
Wind flow i$ FROM he direciions shown.
Wind Speed (Miles Per Hour) 2155 ob$ervai*tK>ns wete mi$sing .
: Wind peed Mi ' r*r I loot) p RC 0 pc'ed {Mil P~r l!uur D II AT : ORY ATE.GORY JlIB, '11 2..2 ill w ~ DIR ~ ill 0.76 0 .:? 0.02 0.21 0.67 (),11 0.0.
0.9:? 0 7 O.ot 0I 0. I 0 .01 0.9 016 0.0 0 I 0 , 0 0 .01 0.94 o. 0 6 0.00 0 ~6 0.40 O.Ol Ul.t .06 0 .01 0.' 2 o. 0,1 0.10
1. 0 0 -. 0.07 0.49 -
Cl .62 4. 2. 4 IA 2.54 2.44 I, 6 0.79 0 .16 0.58 3.47 6.65 10.41 6 .95 *U 1.94 2.0 - I. ~ 0-26 or 0.47 I . .S. 2.35 1.62 0.45 0. 19 Tffr OB ' = 4 1 69* Ml"SL (j(JIJ} ' = 2 155 c LMOHS = 0
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10.0 REFERENCES
1. DCPP Interdepartmental Administrative Procedure (IDAP), RPl.IDl 1, "Environmental Radiological Monitoring Procedure." *
2. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (NUREG-1301)
\ I
3. DCPP Program Directive, CY2, "_Radiological Monitoring and Controls Program."
4. NEI 07-07, "Industry Ground Water Protection- Final Guidance Document", August 2007
5. NRC Regulatory Issue Summary 2008-03, "Return/Re-use of Previously Discharged Radioactive Effluents"; February 13, 2008
6. "Groundwater Gradient Analysis", by Entrix Corporation, March 2010
7. "Groundwater Gradient Analysis", by Cardno/Entrix Corporation, June 2012
8. Diablo Canyon Power Plant Site Conceptual Model Report, by ERM July 30, 2014
9. ANSI/RPS Nl3.37-2014, "Environmental Dosimetry - Criteria for System Design and Implementation"
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APPENDIX A ANALYTICAL SAMPLE RESULTS
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2015 DCPP REMP Analysis Results Appendix A OS2 North Gate - Air Charcoal Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units OS2 North Gate(364535014 -AC 3-Jan-15 lodine-131 1.60E-03 9.77E-03 5.48E-03 pCi/m3 OS2 North Gate 365107014 -AC 1O-Jan-15 lodine-131 1.99E-04 1.37E-02 7.98E".03 pCi/m3
OS2 North Gate(365598014 -AC 17-Jan-15 lodine-131 5.34E-03 1.28E-02 7.32E-03 pCi/m3 OS2 North Gate 366039014 -AC 24-Jan-15 lodine-131 4.34E-03 9.72E-03 5.69E-03 pCi/m3 OS2 North Gate(366510014) -AC 31-Jan-15 lodine-131 3.02E-03 1.12E-02 6.47E-03 pCi/m3 OS2 North Gate(367027013)-AC 7-Feb-15 lodine-131 -2.25E-03 7.45E-03 4.74E-03 pCi/m3 OS2 North Gate 367398014 -AC 14-Feb-15 lodine-131 -1.89E-04 1.44E-02 8.42E-03 pCi/m3 OS2 North Gate 367754014) -AC 21-Feb-15 lodine-131 2.49E-03 1.40E-02 8.00E-03 pCi/m3 OS2 North Gate 368316014 -AC 28-Feb-15 lodine-131 3.37E-03 1.74E-02 9.99E-03 pCi/m3 OS2 North Gate 368671014 -AC 7-Mar-15 lodine-131 3.09E-03 1.04E-02 5.88E-03 pCi/m3 OS2 North Gate(369085014) - AC 14-Mar-15 lodine-131 5.65E-04 8.75E-03 5.11E-03 pCi/m3 OS2 North Gate 369559014 -AC 21-Mar-15 lodine-131 -4.99E-03 1.23E-02 8.06E-03 pCi/m3 OS2 North Gate(369948013) - AC 28-Mar-15 lodine-131 5.50E-04 1.01E-02. 6.05E-03 pCi/m3 OS2 North Gate 370730013 -AC 4-Apr-15 lodine-131 9.09E-04 9.94E-03 5.89E-03 pCi/m3 OS2 North Gate(371198013) -AC 11-Apr-15 lodine-131 -9.01E-04 9.57E-03 5.85E-03 pCi/m3 OS2 North Gate 371634014 -AC 18-Aor-15 lodine-131 -6.56E-04 8.38E-03 4.97E-03 oCi/m3 OS2 North Gate 372080014 -AC 26-Aor-15 lodine-131 -1.85E-03 7.50E-03 4.85E-03 oCi/m3 OS2 North Gate(372573014)-AC 2-Mav-15 lodine-131 -1.70E-03 1.52E-02 9.14E-03 pCi/m3 OS2 North Gate 373065014 -AC 9-Mav-15 lodine-131 2.91E-03 1.22E-02 6.82E-03 oCi/m3 OS2 North Gate 373540014 - AC 16-Mav-15 lodine-131 8.29E-03 1.33E-02 7.94E-03 oCi/m3 OS2 North Gate 373878013 -AC 23-May-15 lodine-131 1.53E-03 1.04E-02 5.93E-03 pCi/m3 OS2 North Gate 374367015 -AC 30-May-15 lodine-131 -3.48E-03 7.33E-03 5.25E-03 pCi/m3 OS2 North Gate(37 4810010 - AC 6-Jun-15 lodine-131 -3.27E-03 1.02E-02 8.05E-03 pCi/m3 OS2 North Gate 375327013 -AC 13-Jun-15 lodine-131 1.82E-03 9.78E-03 5.71E-03 oCi/m3 OS2 North Gate 375745013 -AC 20-Jun-15 lodine-131 -1.34E-03 8.37E-03 5.28E-03 pCi/m3 OS2 North Gate 376116012 -AC' 27-Jun-15 lodine-131 4.29E-03 1.16E-02 7.08E-03 oCi/m3 OS2 North Gate 376776015 -AC 4-Jul-15 lodine-131 1.01E-02 1.82E-02 1.06E-02 oCi/m3 OS2 North Gate 37730601.3 -AC 11-Jul-15 lodine-131 2.28E-03 1.88E-02 1.10E-02 oCi/m3 OS2 North Gate 377783013 -AC 18~Jul-15 lodine-131 -2.45E-03 8.83E-03 5.80E-03 oCi/m3 OS2 North Gate 378239013 - AC 25-Jul-15 lodine-131 4.51 E-03 1.24E-02 7.79E-03 oCi/m3 OS2 North Gate 378741010 -AC 1-Auo-15 lodine-131 -8.91E-04 1.22E-02 7.62E-03 oCi/m3 OS2 North Gate(379291013 -AC 8-Auo-1.5 lodine-131 4.33E-03 1.06E-02 5.92E-03 oCi/m3 OS2 North Gate 379712013 -AC 15-Aug-15 lodine-131 -1.51E-04 1.67E-02 1.01 E-02 pCi/m3 OS2 North Gate 380128014 -AC 22-Aug-15 lodine-131 5.97E-04 9.31E-03 6.29E-03 pCi/m3 OS2 North Gate 380527013 -AC , 29-Aug-15 lodine-131 -2.08E~03 1.15E-02 7.26E-03 pCi/m3 OS2 North Gate 380911013 -AC 5-Sep-15 lodine-131 -1.75E-03 9.14E-03 5.86E-03 pCi/m3 OS2 North Gate 381297013 -AC 12-Sep-15 lodine-131 -3.01E-03 1.65E-02 1.05E-02 pCi/m3 OS2 North Gate 381776013 -AC 19-Sep-15 lodine-131 4.98E-03 9.16E-03 5.15E-03 pCi/m3 OS2 North Gate 382121013 -AC 26-Sep-15 lodine-131 -2.12E-03 8.82E-03 6.53E-03 pCi/m3 OS2 North Gate 382853013 -AC 3-0ct-15 lodine-131 -6.53E-03 1.16E-02 8.92E-03 pCi/m3 OS2 North Gate 383405002 -AC 10-0ct-15 lodine-131 2.01 E-03 1.10E-02 6.37E-03 pCi/m3 OS2 North Gate 383823013 -AC 17-0ct-15 lodine-131 3.00E-03 1.20E-02 6.90E-03 pCi/m3 OS2 North Gate 384293003 -AC 24-0ct-15 lodine-131 3.23E-03 7.95E-03 5.58E-03 pCi/m3 Page.1 of91
2015 DCPP REMP Analysis Results Appendix A OS2 North Gate. 384829014) - AC 31-0ct-15 lodine-131 3.67E-03 1.17E-02 6.73E-03 pCi/m3 OS2 North Gate 385443013 -AC 7-Nov-15 lodine-131 -4.22E-04 1.10E-02 6.55E-03 pCi/m3 OS2 North Gate 385912004) -AC 14-Nov-15 lodine-131 -5.68E-03 1.07E-02 7.78E-03 pCi/m3 OS2 North Gate 386331002 -AC 21-Nov-15 lodine-131 -1.41E-03 1.48E-02 8.81E-03 pCi/m3 OS2 North Gate 386665015) - AC 28-Nov-15 lodine-131 8.54E-04 9.93E-03 6.08E-03 pCi/m3 OS2 North Gate 387181015 -AC 5-Dec-15 lodine-131 9.59E-04 8.82E-03 5.00E-03 pCi/m3 OS2 North Gate 387767014 -AC 12-Dec-15 lodine-131 1.48E-04 1.01E-02 5.84E-03 pCi/m3 OS2 North Gate(388120014) - AC 19-Dec-15 lodine-131 -2.10E-03 1.40E-02 8.55E-03 pCi/m3 OS2.. North Gate 388206014 -AC 25-Dec-15 lodine-131 -3.47E-03 1.38E-02 9.06E~03 pCi/m3
-.,,-;c* *:'""" ',, "' ~;;*-*' ... *., :' :/::,,*> .:* ,* ,. ',,, .. ' ~* *' i -~
).*,'.*,:;, :.:, .\.. * *' : *. .* "** ;'>*\;.'
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OS2 North Gate -Air Carbon 14 Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units OS2 North Gate 364535017) - AC14 3-Jan-15 Carbon-14 1.76E-07 5.50E-07 3.31E-07 uCi/m3 OS2 North Gate 365107017 -AC14 10-Jan-15 Carbon-14 1.85E-07 6.26E-07 3.76E-07 uCi/m3 OS2 North Gate 365598017)-AC14 17-Jan-15 Carbon-14 -2.46E-07 6.36E-07 3.74E-07 uCi/m3 OS2 North Gate 366039017 -AC14 24-Jan-15 Carbon-14 3.55E-07 6.57E-07 3.98E-07 uCi/m3 OS2 North Gate(366510017) -AC14 / 31-Jan-15 Carbon-14 4.91E-07 6.78E-07 4.13E-07 uCi/m3 OS2 North Gate(367027017) -AC14 7-Feb-15 Carbon:.14 -1..70E-07 6.20E-07 3.66E-07 uCi/m3 OS2 North Gate 367398017 -AC14 14-Feb-15 Carbon-14 4.65E-08 6.77E-07 4.04E-07 uCi/m3 OS2 North Gate(367754017) -AC14 21-Feb-15 Carbon-14 4.36E-08 6.30E-07 3.76E-07 uCi/m3 OS2 North Gate 368316017 -AC14 28-Feb-15 Carbon-14 3.54E-07 6.23E-07 3.78E-07 uCi/m3 OS2 North Gate 368671017 -AC14 7~Mar-15 Carbon-14 3.07E-07 5.64E-07 3.42E-07 uCi/m3 OS2 North Gate 369085017 -AC14 14-Mar-15 Carbon-14 4.50E-07 5.95E-07 3.64E-07 uCi/m3 OS2 North Gate 369559017 -AC14 21-Mar-15 Carbon-14 1.42E-07 5.91E-07 3.55E-07 uCi/m3 OS2 North Gate(369948015)-AC14 28-Mar-15 Carbon-14 -1.27E-07 6.03E-07 3.57E-07 uCi/m3 OS2 North Gate 370730015 -AC14 4-Aor-15 Carbon-14 -2.39E-07 5.96E-07 3.50E-07 uCi/m3 OS2 North Gate 371198015 -AC14 11-Aor-15 Carbon-14 -1.82E-07 6.38E-07 3.77E-07 uCi/m3 OS2 North Gate 371634017 -AC14 18-Aor-15 Carbon-14 2.09E-07 6.23E-07 3.75E-07 uCi/m3 OS2 North Gate 372080017) -AC14 26-Aor-15 Carbon-14 3.62E-09 6.42E-07 3.83E-07 uCi/m3 OS2 North Gate(372573017) -AC14 2-Mav-15 Carbon-14 -3.34E-07 6.89E-07 4.04E-07 uCi/m3 OS2 North Gate 373065017 -AC14 9-Mav-15 Carbon-14 8.89E-08 6.87E-07 4.11E-07 uCi/m3 OS2 North Gate 373540015 -AC14 16-Mav-15 Carbon-14 -5.18E-07 6.32E-07 3.67E-07 uCi/m3 OS2 North Gate 373878015 -AC14 23-Mav-15 Carbon-14 -4.79E-07 7.02E-07 4.09E-07 uCi/m3 OS2 North Gate 374367016 -AC14 30-Mav-15 Carbon-14 1.52E-07 6.80E-07 4.08E-07 uCi/m3 OS2 North Gate 374810017 -AC14 6-Jun-15 Carbon-14 -1.14E-08 6.57E-07 3.91E-07 uCi/m3 OS2 North Gate 375327015)-AC14 13-Jun-15 Carbon-14 -1.33E-07 5.12E-07 3.03E-07 uCi/m3 OS2 North Gate 375745015 -AC14 20-Jun-15 Carbon-14 -3.27E-07 6.09E-07 3.57E-07 uCi/m3 OS2 North Gate 376116014 -AC14 27-Jun-15 Carbon-14 -7.95E-09 5.50E-07 3.27E-07 uCi/m3 OS2 North Gate 376776017 -AC14 4-Jul-15 Carbon-14 1.28E-07 6.11E-07 3.66E-07 uCi/m3 OS2 North Gate 377306015)-AC14 11-Jul-15 Carbon-14 1.00E-07 5.92E-07 3.55E-07 uCi/m3 OS2 North Gate 377783015) - AC14 18-Jul-15 Carbon-14 -1.55E-07 6.09E-07 3.60E-07 uCi/m3 OS2 North Gate 378239015 -AC14 25-Jul-15 Carbon-14 5.74E-07 5.89E-07 3.62E-07 uCi/m3 OS2 North Gate 378741012 -AC14 1-Aug-15 Carbon-14 3.40E-07 5.43E-07 3.30E-07 uCi/m3 OS2 North Gate 379291015 -AC14 8-Aug-15 Carbon-14 7.43E-08 5.78E-07 3.46E-07 uCi/m3 OS2 North Gate 379712015 -AC14 15-Aug-15 Carbon-14 3.83E-08 6.02E-07 3.60E-07 uCi/m3 Page 2 of 91
2015 DCPP REMP Analysis Results Ap.pendix. A OS2 North Gate(380128017)-AC14 22-Aug-15 Carbon-14 -4.23E-07 6.32E-07 3.69E-07 uCi/m3 OS2 North Gate(380527015) -AC14 29-Aug-15 Carbon-14 3.34E-08 6.00E-07 3.58E-07 uCi/m3 OS2 North Gate(380911015)-AC14 5-Sep-15 Carbon-14 -1.02E-07 6.50E-07 3.85E-07 uCi/m3 OS2 North Gate(381297015 -AC14 12-Sep-15 Carbon-14 -4.38E-07 5.70E-07 3.32E-07 uCi/m3 OS2 North Gate(381776015 -AC14 19-Sep-15 Carbon-14 -1.08E-07 5.89E-07 3.49E-07 uCi/m3 OS2 North Gate(382121015 -AC14 26-Sep-15 Carbon-14 -1.91 E-07 5.22E-07 3.07E-07 uCi/m3 OS2 North Gate(382853015) -AC14 3-0ct-'15 Carbon-14 2.49E-07 5.60E-07 3.38E-07 uCi/m3 OS2 North Gate(383405001) -AC14 \ 10-0ct-15 Carbon-14 4.28E-07 5.68E 3.46E-07 uCi/m3 OS2 North Gate(383823015 -AC14 17-0ct-15 Carbon-14 1.14E-07 5.25E-07 3.15E-07 uCi/m3 OS2 North Gate(384293017) -AC14 24-0ct-15 Carbon-14 2.18E-07 5.60E-07 3.37E-07 uCi/m3 OS2 North Gate(384829017 -AC14 31-0ct-15 Carbon-14 -2.38E-07 5.40E-07 3.17E-07 uCi/m3 OS2 North Gate(385443015) -AC14 7-Nov-15 Carbon~14 -1.86E-07 5.37E-07 3.17E-07 uCi/m3 OS2 North Gate(385912003)-AC14 14-Nov-15 Carbon-14 1.91E-07 5.67E-07 3.41E-07 uCi/m3 OS2 North Gate(386331001 -AC14 21-Nov-15 Carbon-14 2.11E-07 6.56E-07 3.95E-07 uCi/m3 OS2 North Gate(386665017 -AC14 28-Nov-15 Carbon-14 -3.86E-07 5.32E-07 3.11 E-07 uCi/m3 OS2 North Gate(387181016 -AC14 5-Dec-15 Carbon-14 -2.88E-07 5.96E-07 3.50E-07 uCi/m3 OS2. North Gate(387767015) - AC 14 12-Dec-15 Carbon-14 -5.35E-08 5.57E-07 3.31E-07 uCi/m3 OS2 North Gate(388120015 -AC14 19-Dec-15 Carbon-14 -5.17E-07 6.87E-07 4.00E-07 uCi/m3 OS2 North Gate(388206015 -AC14 25-Dec-15 Carbon-14 -1.63E-07 6.27E-07 3.71E-07 uCi/m3
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l OS2 North Gate - Air Particulate Samole Name Date Collected Nuclide Result MDC 2 Sicima TPU Units OS2 North Gate 364535007 -AP .3-Jan-15 BETA 5.46E-02 1.24E-03 1.21E-02 oCi/m3 OS2 North Gate 365107007 - AP 10-Jan-15 BETA 8.02E-02 1.26E-03** 1.16E-02 oCi/m3 OS2 North Gate(365598007) - AP
17-Jan-15 BETA 4.17E-02 1.26E-03 1.15E-02 pCi/m3 OS2 North Gate 366039007 - AP 24-Jan-15 BETA 4.74E-02 ~
1.38E-03 1.22E-02 pCi/m3 OS2 North Gate 366510007 -AP 31-Jan-15 BETA 7.45E-02 1.50E-03 1.14E-02 pCi/m3 OS2 North Gate 367027006 - AP 7-Feb-15 BETA 3.23E-02 1.27E-03 1.34E-02 pCi/m3 OS2 North Gate 367398008 - AP 14-Feb-15 BETA 3.69E-02 1.55E-03 1.32E-02 pCi/m3 OS2 North Gate(367754007) - AP 21-Feb-15 BETA 5.95E-02 1.40E-03 1.27E-02 pCi/m3 OS2 North Gate 368316007 -AP 28-Feb-15 BETA 1.51E-02 1.37E-03 1.16E-02 pCi/m3 OS2 North Gate 368671007 -AP 7-Mar-15 BETA 5.87E-02 1.36E-03 1.16E-02 pCi/m3 OS2 North Gate 369085007 - AP 14-Mar-15 BETA 2.??E-02 1.39E-03 1.31E-02 pCi/m3 OS2 North Gate 369559007 - AP 21-Mar-15 BETA 2.27E-02 1.38E-03 1.06E-02 pCi/m3 OS2 North Gate 369948014 -AP 28-Mar-15 BETA 1.71E-02 1.35E-03 1.07E-02 pCi/m3 OS2 North Gate 370730014 -AP . 4-Aor-15 BETA. 1.60E-02 1.49E-03 1.01 E-02 pCi/m3 OS2 North Gate 371198014 -AP 11-Apr-15 BETA 8.44E-03 1.36E-03 1.14E-02 pCi/m3 OS2 North Gate 371634007 -AP 18-Aor-15 BETA 2.86E-02 1.37E-03 1.10E-02 pCi/m3 OS2 North Gate 372080007 -AP 26-Aor..:15 BETA 1.97E-02 1.57E-03 1.07E-02 pCi/m3 OS2 North Gate 372573007 -AP 2-May-15 BETA 2.44E-02 1.48E-03 1.08E-02 oCi/m3 OS2 North Gate 373065007 -AP 9-May-15 BETA 1.32E-02 1.36E-03 1.05E-02 pCi/m3 OS2 North Gate 373540013 -AP 16-Mav-15
BETA 1.23E-02 1.47E-03 1.05E-02 pCi/m3 OS2 North Gate 373878014 -AP 23-May-15 BETA 9.04E-03 1.44E-03 1.31E-02 pCi/m3 OS2 North Gate 374367009 -AP 30-May-15 BETA 1.21E-02 1.36E-03 9~64E-03 pCi/m3 OS2 North Gate 374810011 -AP 6-Jun-15 BETA 9.38E-03 1.55E-03 1.30E-02 oCi/m3 Page 3 of 91
2015 DCPP REMP Analysis Results Appendix A OS2 North Gate(375327014) -AP 13-Jun-15 BETA 9.52E-03 1.44E-03 1.11E-02 pCi/m3 OS2 North Gate(375745014) -AP 20-Jun-15 BETA 1.84E-02 1.45E-03 1.14E-02 pCi/m3 OS2 North Gate(376116013) - AP 27-Jun-15 BETA 1.05E-02 1.35E-03 1.06E-02 pCi/m3 OS2 North Gate 376776016 -AP 4-Jul-15 BETA 4.79E-03 1.39E-03 1.15E-02 oCi/m3 OS2 North Gate(377306014 -AP 11-Jul-15 BETA- 7.36E"03 1.25E-03 1.08E-02 pCi/m3 OS2 North Gate 377783014 -AP 18-Jul-15 BETA 1.78E-02 1.26E-03 1.02E-02 pCi/m3 OS2 North Gate(378239014) -AP 25-Jul-15 BETA 1:89E-02 1.30E-03 8.?0E-03 pCi/m3 OS2 North Gate(378741011) - AP 1-Aug-15 BETA 2.09E-02 1.26E-03 9.?0E-03 pCi/m3 OS2 North Gate 379291014)-AP 8-Aug"'.15 BETA 1.72E-02 1.37E-03 1.06E-02 oCi/m3 OS2 North Gate 379712014)-AP 15-Aug-15 BETA .1.84E-02 1.32E-03 1.05E-02 pCi/m3 OS2 North Gate 380128007 -AP 22-Aug~15 BETA 3.57E-02 1.40E-03 1.32E-02 oCi/m3 OS2 North Gate(380527014) -AP 29-Aug-15 BETA 1.40E-02 1.34E-03 1.11E-02 pCi/m3 OS2 North Gate(380911014)-AP 5-Sep-15 BETA 2.98E-02 1.35E-03 9.78E-03 pCi/m3 OS2 North Gate 381297014 -AP 12-Sep-15 BETA 2.17E-02 1.42E-03 1.20E-02 pCi/m3 OS2 North Gate(381776014) -AP 19-Sep-15 BETA 2.14E-02 1.48E-03 1.09E-02 pCi/m3 OS2 North Gate 382121014 -AP 26-Sep-15 BETA 2.11E-02 1.33E-03 9.64E-03 pCi/m3 OS2 North Gate(382853014) -AP 3-0ct-15 BETA 2.78E-02 1.43E-03 1.19E-02 pCi/m3 OS2 North Gate 383405003 - AP 10-0ct-15 BETA 4.50E-02 1.42E-03 1.12E-02 oCi/m3 OS2 North Gate 383823014 -AP 17-0ct-15 BETA 3.26E-02 1.42E-03 1.22E-02 oCi/m3 OS2 North Gate(384293006) - AP 24-0ct-15 BETA 3.?0E-02 1.65E-03 1.01 E-02 pCi/m3 OS2 North Gate 384829007 -AP 31-0ct-15 BETA 1.88E-02 1.68E-03 8.30E-03 pCi/m3 OS2 North Gate 385443014 -AP 7-Nov-15 BETA 2.50E-02 1.75E-03 8.78E-03 oCi/m3 OS2 North Gate 385912005 -AP 14-Nov-15 BETA 3.89E-02 1.75E-03 8.61E-03 oCi/m3 OS2 North Gate 386331003 i-AP 21-Nov-15 BETA 3.26E-02 1.84E-03 8.36E-03 oCi/m3 OS2 North Gate(386665016)-AP 28-Nov-15 BETA 5.89E-02 1.32E-03 9.00E-03 pCi/m3 OS2 North Gate 387181014) -AP 5-Dec-15 BETA 3.78E-02 1.51 E-03 1.08E-02 oCi/m3 OS2 North Gate 387767013 -AP 12-Dec-15 BETA 8.23E-03 1.61E-03 1.05E-02 pCi/m3 OS2 North Gate 388120013 -AP 19-Dec-15 BETA 1.15E-02 1.88E-03 9.82E-03 oCi/m3 OS2 North Gate 388206013 -AP 25-Dec-15 BETA 1.73E-02 1.58E-03 8.80E-03 oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Beryllium-? 1.43E-01 1.13E-02 2.24E-02 oCi/m3 OS2 North Gate 377522007 - AP 16-May-15 Bervllium-7 8.18E-02 1.00E-02 1.60E-02 oCi/m3 OS2 North Gate1 383567007 -AP 15-Aug-15 Bervllium-7 9.85E-02 7.76E-03 1.93E-02 oCi/m3 OS2 North Gate 389387007 -AP 14-Nov-15 Bervllium-7 1.20E-01 9.79E-03 1.94E-02 - oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Cesium-134 6.49E-05 7.29E-04 4.14E-04 oCi/m3 OS2 North Gate 377522007 -AP 16cMav-15 Cesium-134 -1.52E-04 7.74E-04 4.97E-04 oCi/m3 OS2 North Gate 383567007 -AP 15-Aug-15 Cesium-134 -2.65E-04 5.47E-04 4.31E-04 oCi/m3 OS2 North Gate 389387007 i-AP 14-Nov-15 Cesium-134 -2.54E-04 4.65E-04 4.23E-04 oCi/m3 OS2 North Gate 371385007 -AP 14-Feb-15 Cesium-137 1.48E-04 6.47E-04 3.69E-04 oCi/m3 OS2 North Gate 377522007) - AP 16-May-15 Cesium~137 3.57E-04 6.05E-04 3.20E-04 oCi/m3 OS2 North Gate 383567007) - AP 15-Aug-"15 Cesium-137 2.04E-05 6.23E-04 3.76E-04 oCi/m3 OS2 North Gate 389387007) - AP I 14-Nov-15 Cesium-137 -8.35E-05 4.60E-04 3.53E-04 oCi/m3
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Page 4 of 91
2015 DCPP REMP Analysis Results Appendix A 1A2 Bl anch ard Spnng - Drinkino Water Sample Name Date Collected Nuclide Result MDC 2 Sigma TPU Units 1A2 Blanchard Spring(365880002) - OW 26-Jan-15 BETA -4.82E-01 2.37E+OO 1.41 E+OO pCi/L 1A2 Blanchard Sorino(371630005 - OW 21-Aor-15 BETA 2.73E+OO 2.23E+OO 1.54E+OO pCi/L 1A2 Blanchard Spring(377777002) - OW / 21-Jul-15 BETA 2.04E+OO 2.82E+OO 1.77E+OO pCi/L 1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 BETA 2.73E+OO 3.58E+OO 2.27E+OO pCi/L 1A2 Blanchard Spring(387205001) - OW 8-Dec-15 BETA 1.19E-01 2.53E+OO 1.52E+OO pCi/L 1A2*Blanchard Spring(365880002 - OW 26-Jan-15 Barium-140 4.81E-01 9.26E+OO 5.40E+OO pCi/L 1A2 Blanchard Sprino(371630005 - OW 21-Apr-15 Barium-140 -1.74E+OO 8.85E+OO 5.26E+OO pCi/L 1A2 Blanchard Spring 377777002 - DW 21-Jul-15 Barium-140 6.47E+OO 1.04E+01 6.54E+OO pCi/L 1A2 Blanchard Sprino(383939001 - DW 21-0ct-15 Barium-140 -1.40E+OO 9.81E+OO 5.84E+OO pCi/L 1A2 Blanchard Spring(387205001) - OW 8-Dec-15 Barium-140 3.26E+OO 8.90E+OO 5.45E+OO pCi/L 1A2 Blanchard Spring(365880002)- OW 26-Jan-15 Cesium-134 4.65E-01 2.32E+OO 1.38E+OO pCi/L 1A2 Blanchard Spring 371630005 - OW 21-Apr-15 Cesium-134 3.55E-01 2.09E+OO 1.24E+OO oC.i/L 1A2 Blanchard Spring(377777002) - DW 21-Jul-15 Cesium-134 -2.83E-01 2.24E+OO 1.39E+OO pCi/L 1A2 Blanchard Spring 383939001 -DW 21-0ct-15 Cesium-134 1.06E+OO 2.00E+OO 1.93E+OO oCi/L 1A2 Blanchard Spring(387205001 -DW 8~Dec-15 Cesium-134 -4.80E-01 1.94E+OO 1.20E+OO pCi/L 1A2 Blanchard Spring(365880002 -DW 26-Jan-15 Cesium-137 1.81E-01 2.22E+OO 1.50E+OO oCi/L 1A2 Blanchard Sorina(371630005 -DW 21-Apr-15 Cesium-137 5.14E-01 1.95E+OO 1.30E+OO pCi/L 1A2 Blanchard Spring(377777002) - OW 21-Jul-15 Cesium-137 -5.60E-01 2.31E+OO 1.44E+OO pCi/L 1A2 Blanchard Sorina(383939001 - OW 21-0ct-15 Cesium-137 -6.96E-01 1.93E+OO 1.22E+OO pCi/L 1A2 Blanchard Sorino(387205001 - DW 8-Dec-15 Cesium-137 8.61E-01 2.06E+OO 1.37E+OO pCi/L 1A2 Blanchard Sorino(365880002 - DW 26-Jan-15 Cobalt-58 1.25E+OO 1.98E+OO 1.90E+OO pCi/L 1A2 Blanchard Sorino(371630005 - OW - 21-Aor-15 Cobalt-58 -9.64E-01 1.69E+OO 1.51E+OO pCi/L 1A2 Blanchard Sprino(377777002 -DW 21-Jul-15 Cobalt-58 -7.61 E-01 1.99E+OO 1.26E+OO pCi/L 1A2 Blanchard Spring, 383939001 -DW 21-0ct-15 Cobalt-58 -3.31 E-01 1.90E+OO 1.35E+OO oCi/L 1A2 Blanchard Spring' 387205001 -DW 8-Dec-15 Cobalt-58 -3.94E-01 1.97E+OO 1.21E+OO pCi/L 1A2 Blanchard Spring, 365880002 -DW 26-Jan-15 Cobalt-60 1.16E-01 2.28E+OO 1.34E+OO oCi/L 1A2 Blanchard Sorino1 371630005 - ow 21-Aor-15 Cobalt~6o 1.51 E-01 2.04E+OO 1.20E+OO pCi/L 1A2 Blanchard Sorino(377777002 - OW 21-Jul-15 Cobalt-60 1.22E+OO --.. 2.55E+OO 1.51E+OO pCi/L 1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 Cobalt-60 2.89E-01 2.10E+OO 1.22E+OO pCi/L 1A2 Blanchard Sorino(387205001 - OW 8-Dec-15 Cobalt-60 -6.50E-02 2.20E+OO 1.63E+OO pCi/L 1A2 Blanchard Sorino(365880002 - DW 26-Jan-15 lodine-131 -1.01 E-01 4.00E-01 2.44E-01 pCi/L 1A2 Blanchard Sorino(371630005 - OW 21-Aor-15 lodine-131 1.41 E-01 5.34E-01 3.12E-01 pCi/L 1A2 Blanchard Sorino(377777002 - OW 21-Jul-15 lodine-131 -2.28E-01 6.68E-01 4.21E-01 pCi/L
~
1A2 Blanchard Sorino(383939001 - OW 21-0ct-15 lodine-131 -t.27E-01 4.16E-01 2.59E-01 pCi/L 1A2 Blanchard Sorino(387205001 - DW 8-Dec-15 lodine-131 1.43E-01 7.16E-01 4.23E-01 pCi/L 1A2 Blanchard Sorino(365880002 - OW 26-Jan-15 lron-55 2.13E+01 6.75E+01 4.68E+01 pCi/L 1A2 Blanchard Sorina(371630005 - OW 21-Apr-15 lron-55 5.63E+01 8.95E+01 6.91E+01 pCi/L 1A2 Blanchard Sorina(377777002 - OW 21-Jul-15
lron-55 8.09E+OO 8.65E+01 6.50E+01 pCi/L 1A2 Blanchard Soring(383939001 - OW 21-0ct-15 lron-55 -2.84E+01 6.67E+01 4.58E+01 pCi/L 1A2 Blanchard Spring 387205001 -DW 8-Dec-15 lron-55 -1.74E+OO 3.68E+01 2.48E+01 pCi/L 1A2 Blanchard Spring 365880002 -DW 26-Jan-15 lron-59 -1.82E+OO 4.02E+OO 2.61E+OO pCi/L 1A2 Blanchard Spring 371630005 -OW 21-Apr-15 lron-59 -1.96E+OO 3.28E+OO 2.24E+OO pCi/L 1A2 Blanchard SorinQ 377777002 -DW 21-Jul-15 lron-59 3.49E+OO 5.04E+OO 3.27E+OO oCi/L Page 5 of 91

DCL-16-045, Submittal of 2015 Annual Radiological Environmental Operating Report

Contents

Text

Dear Commissioners and Staff:

SUMMARY

1.0 INTRODUCTION

2.3 DESCRIPTION

SUMMARY

10.0 REFERENCES

Dear Commissioners and Staff:

SUMMARY

1.0 INTRODUCTION

2.3 DESCRIPTION

SUMMARY

10.0 REFERENCES

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DCL-16-045, Submittal of 2015 Annual Radiological Environmental Operating Report

Text

Dear Commissioners and Staff:

SUMMARY

1.0 INTRODUCTION

2.3 DESCRIPTION

SUMMARY

10.0 REFERENCES

Dear Commissioners and Staff:

SUMMARY

1.0 INTRODUCTION

2.3 DESCRIPTION

SUMMARY

10.0 REFERENCES

Navigation menu

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