ML20205F423
| ML20205F423 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 12/31/1998 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20205F417 | List: |
| References | |
| NUDOCS 9904060250 | |
| Download: ML20205F423 (26) | |
Text
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l Enclosure l PG&E Letter HBL-99-003 !
I HUMBOLDT BAY POWER PLANT UNIT 3 !
ANNUAL FACILITY STATUS AND SURVEY REPORT JANUARY 1 THROUGH DECEMBER 31,1998 i
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9904060250 990331 E7 PDR ADOCK 05000133A R PDR j
. e TABLE OF CONTENTS )
l A. - FACILITY STATUS.... .. . ., . . . . . , , ,
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- 1. Unit 3 Condition... ... .. . .. . . . . , ,I l
- 2. Caisson Sump Sample Results.. . . . . . . .... . . .I j
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- B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . .. . .3
- 1. Summary Description of the Radiological Environmental Monitoring Program . . .3 i
- a. Technical Specification Monitoring Requirements.. . .. . .. .3
- b. SAFSTOR Offsite Dose Calculation Manual Monitoring Requirements . .5
- 2. EPA Interlaboratory Comparison Program.. . .. . . .5
- 3. Monitoring Results . .. . . . . . .5
- a. Radiological Environmental Monitoring Program Annual Summary. .5 l 1
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- b. Airborne Pathway. . . . .6
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c; Direct Radiation . Pathway. .. . . . .6 (1) Onsite Locations.. . . . .6 I
(2) Ofr site Locations... . .6
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- d. Waterborne Pathway. . .7 (1) Surface Water.. . .. . . . . . . . . .. .. .7 (2) Groundwater... . . . . . . . . . . . . . . . . .7
- e. Ingestion Pathway. . . . . . , , .7 i
- f. Terrestrial Pathway. . 7 j i
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-3 f LIST OF TABLES Table Pace A-1 Caisson Sump Sample Results .. . . . ., , .2 B-1 HBPP Radiological Environmental Monitoring Program.. . . .8 B-2 Distances And Directions to Offsite Environmental Monitoring Stations.. . .c B-3 TES Participation - EPA Interlaboratory Cross-Check Program Data. . . .10 B-4 Radiological Environmental Monitoring Program Annual Report Summary. . II B-5 Onsite Environmental TLD Stations.. . . 13 B-6 Offsite Enviromnental TLD Stations . . . . . . 14 B-7 Discharge Canal Sample Results.. ... ... . 15 B-8 Groundwater Mcnitoring Well Results . . , . . . .. . . .17 LIST OF FIGURES Finure Page B-1 HBPP Onsite TLD Locations.. . . 19 B-2 HBPP Onsite Monitoring Well Locations. . . .20 B-3 HBPP Offsite TLD Locations. .21 B-4 Offsite Emironmental Radiation Level Trends . . 23 1
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PACIFIC GAS AND ELECTRIC COMPANY ANNUAL FACILI FY STATUS AND SURVEY REPORT FOR llUMBOLDT BAY POWER PLANT UNIT 3, COVERING TIIE PERIOD l JANUARY l TilROUGil DECEMBER 31,1998 This annual report is requirst t,y Section Vll.J.1 of the Humboldt Bay Power Plant (HBPP) Unit 3 Technical Specifications. This report describes the status of the facility, presents the results of facility measurements and results of the Radiological Environmental Monitoring Program (REMP) for the per' J of January I through December 31,1998.
3 A. FACILITY STATUS
- 1. Unit 3 Condition The facility remained in SAFSTOR status during the repoit period.
- 2. Caisson Sump Sample ResultsSection VI.B.I.c of the Technical Specifications required that the caisson sump wata Se sampled and analyzed monthly (for total alpha, beta, and gamma activity), and that the aserage and maximum values for the results be reported annually. This requirement was deleted by bcense (
amendment 32, effective 5/7/98. Data collected prior to 5/7/98 is reported in Table A-1 1
l TABLE A-1 CAISSON SUMP SAMPLE RESULTS Alpha Activity Beta Activity Gamma Activity (pCill)
Date (pCill) (pCill) Cs-137 Co-60 1/28/98 <1310 (MDA) <7150 (MDA) 4.8 3.6 <4.6 (M DA) 2/25/98 <l481 (MDA) <5995 (MDA) 3.2 i 3.0 <4.2 (MDA) l 3/25/98 <l892 (MDA) 4888*5713 <8.7 (MDA) <7.5 (MDA)
Calculated Alpha Activity Beta Activity Gamma Activity (pCi/l)
Parameters (pCi/II (pCill) Cs-137 Co-60 Average Note 4 4888
- 5713 4.0
- 2.3 Note 4 Maximum Note 4 4888
- 5713 48*3.6 Note 4 Notes:
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- 1. Alpha and Beta analyses are perf- . on a measured aliquot of sample. The typical LLDs for the analyses with I ml aliquots are ai.croximately 2,000 pCill for Alpha and 10,000 pCi/l for Beta. The MDA for the analyses ranged from 1,310 to 1,892 pCi/l for Alpha and from 6,991 to 7,150 pCi/l for Beta. Results that are at or below these values are reported as "<MDA"
- 2. Gamma activity measurements are performed on the original sample, with results corrected to the time l of sampling. Naturally occurring isotopes are not reported. The typical gamma activity lower limit of detection (LLD) is approximately 10 pCi/l for both Cs-137 and Co-60. The Minimum Detectable Activity (MDA) for these analyses ranged from 8.7 to 8.8 pCi/l for Cs-137 and from 4.2 to 7.5 pCi/l for Co-60.
- 3. For purpo:,es of this report, LLD is defined as the a oriori (before the fact) lower limit of detection which represents the desired capability of the measurement system. MDA is defined as the a costeriori (after the fact) limit of detection capability considering a given instrument, procedure and type of sample.
- 4. Results identified as "<MDA" are not included in the calculation of average and maximum values.
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B. RAblOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1
- 1. Summary Description of the Radiological Environmental Monitoring Program The NRC Radiological Assessment Branch issued a Branch Technical Position (BTP) on l
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environmental monitoring in March 1978. Revision 1 of the BTP was issued as Generic Letter 79- i 65 and sets forth an example of an acceptable minimum radiological monitoring program. The specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures ofindividuals resulting from plant effluents.
Many of the exposure pathway sample requirements specified in the BTP are not required for the HBPP REMP because of the baseline conditions established in the SAFSTOR Decommissioning Plan and the Environmental Report as discussed below. In addition, the nuclides specified for analysis by the BTP have been revised to refler' the available source term at a nuclear power plant which has been shut down since July 2; 1976.
l The Environmental Report, submitted to the NRC as Attachmer.t 6 to the SAFSTOR license l amendment request, established baseline conditions for soil, biota and sediments. In accordance with the NRC approved SAFSTOR Decommissioning Plan, now called the Defueled Safety Analysis Report (DSAR), these baseline conditions will only need to be reestablished prior to final l decommissioning if a significant release occurs during SAFSTOR as the result of an accident.
The Environmental Report also contains a description of the demography and human activities within the environs surrounding the site.
The REMP consists of the collection and analysis of both onsite and offsite environmental samples.
Sample collection is performed by HBPP personnel and sample analysis is performed by PG&E's Technical and Ecological Services (TES). Analysis of TLDs used for monitoring direct radiation is performed by the Diablo Canyon Power Plant (DCPP) Dosimetry Group. A summary of the REMP is provided as Table B-1, "HBPP Radiological Environmental Monitoring Program."
Sample collection for the REMP is performed at the sampling stations defined by Table B-2, Distances and Directions to Envirenmental Monitoring Stations; Figure B-1, HBPP Onsite TLD Locations, Figure B-2, HBPP Onsite Monitoring Well Locations, and Figure B-3, HBPP Offsite Sampling Locations.
License amendment 32 established a SAFSTOR Offsite Dou Calculation Manual (ODCM) for l Humboldt Bay Power Plant (HBPP). The REMP requirements were removed from the License l Technical Specifications, and incorporated into Specification Section 2.11 of the SAFSTOR ODCM, effective May 7,1998. The following sections describe the implementation of the HBPP Radiological Emironmemal Monitoring Program (REMP) under the applicable requirements.
- a. Technical Specification Monitoring Rec,uirements (prior to May 7,1998)
(1) Offsite Environmental Monitoring Stations The Tecluica' Specificati. u dection V.A 4) :cquired fba uJsite enuronmental monitoring stations (Statiom i, 2,14 and 25) to be maintained throg the SAFSTOR i
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e f period. These stations are requiied to be equipped with dosimetry devices that can be compared with those used onsite.
The Technical Specificatiom (Section V.B.4) required that if TLDs are the dosimetry devices used, they shall be monitored at least quarterly, with average and maximum values reported annually.
Section V.B.4 also required that if the results from any station indicate that the total radiation dose would be 25 mrlyr or more above background, an investigation shall be conducted and necessary mitigative actions taken.
1 (2) Onsite Environmental Monitoring Stations The Technivil Specifications (Section V.A.6) established requirements for onsite environmental monitoring stations.
(a) A continuous sampler shall be provided for monitoring water in the discharge canal.
Section V.B.6.a required that the continuous sampler shall normally be operating and that if the sampler is not operable, dip samples shall be taken.
Section V.B.6.a required that the composite samples shall be analyzed weekly when the sampler has been operating.
Section V.B.6.a also required that average and maximum activity and concentrations shall be reported annually. Dip samples shall not be used in determination of average and maximum concentrations.
(b) A total of 16 onsite dosimeters are required to be located within the site perimeter fence line at locations specified on Technical Specification Fig. ire V-2.
Section V.B.6.b required that the onsite dosimeter stations be monitored at least quarterly and that average and mammum dosimetry values shall be reported annually.
(c) The onsite groundwater monitoring program consists of five wells constructed in the vicinity of Unit 3.
Section V.B.6.c required that the wcils be sampled quartedv for total gross alpha, total gross beta, total gamma activity and tritium and that average and maximum sample results shall be prepared annually. After transfer of these requirements into S: ODCM, PG&E performed a safety evaluation under 10 CFR 50 59 and determined that gross a'pha and beta monitoring was no longer necessarv.
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- b. SAFSTOR Offsite Dose Calculation Manu. Monitoring Requirements (effective May 7, 1998) .
(1) Offsite Environmental Monitoring - Direct Radiation The SAFSTOR ODCM requires four ofTsite environmental monitoring stations equipped with TLDs to monitor gamma exposure. The TLDs are to be exchanged quaiterly. The stations selected to satisfy this requirement are Stations 1,2,14 and 25.
(2) Onsite Environmental Monitoring (a) Direct Radiation The SAFSTOR ODCM requires sixteen onsite emironmental monitoring stations, and one background (offsite) environment-l manitoring station, equipped with TLDs to monitor gamma exposure. The TLDs are to be exchanged quarterly. The stations selected to satisfy this requirement are Stations Tl through T16 (onsite) and Station T17 (ofTsite).
(b) Surface Water The SAFSTOR ODCM requires that the discharge canal effluent be monitored by gamma isotopic analysis and by tritium analysis. Samples are normally to be composites collected weekly from a continuous sampler, with dip samples to be collected if the sampler is inoperable.
(c) Groundwater The SAFSTOR ODCM requires that five groundwater wells be momtored by gamma isotopic analysis and by tritium analysis, as discussed in section B.I.a.(2)(c) of this report. Samples are to be collected quarterly. The monitoring wells seL:ted to satisfy this requirement are identified as MW-1, MW-2, MW-4. MW-6 and MW-11.
- 2. EPA Iv+ rlaboratory Comparison Program PG#fs Technical and Ecological Services participates in the EPA's Environmental Laboratorv Performance Evaluation Study (Interlaboratory Cross-Check Program). This participation includes sufficient determinations (sample medium radionuclide combmatird to ensure independent checks on the precision and accuracy of the measurement.; o.~iadioactive materials in the REMP samples. Results of the 1998 participation in the Interlaboratory Cross-Check Program are presented in Table B-3.
- 3. Monitoring Results
- n. Radiological Environmental Monitoring Program Annual Summary Results of the REMP sampling and analysis are summarized in Table B-4 in the fomtat of the BTP Table 3.
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- b. Airborne Pathway Airborne pathway monitoring is not required by the Technical Specifications. The Environmental Report, sulcmitted to the NRC as Attachment 6 to the SAFSTOR license amendment reque.ct, establisned baseline conditions for the airborne pathway. In accordance with the NRC approved SAFSTOR Decommissioning Plan, these baseline conditions will only need to be reestablished prior to fmal decommissioning if a significant release occurs during SAFSTOR as the result of an accident.
- c. Direct Radiation Pathway (1) Onsite Locations Onsite monitoring of the direct radiation pathway is performed at 16 locations near the facility fenceline. Monitoring is performed using TLDs which are changed out quarterly.
Detailed results of the onsite monitoring are provided in Table B-5. Variations in quanerly dose measurements at the onsite locations are attributed to in-plant sources and low-level waste packaging and shipping activities. All measurements were comparable to the ranges observed at these locations since entering SAFSTOR decommissioning.
All sampling and analysis for the onsite locations of the direct radiation pathway required during this reporting period was puformed successfully.
(2) Offsite Locations OtTsite monitoring of the direct radiation pathway is performed at 4 locations m the vicinity of the facility. Monitoring is performed using TLDs which are changed out quarterly. Detailed results of the offsite monitoring are provided in Ta' ale B-6. All measurements were comparable to the ranges observed at these locations smce entering SAFSTOR decommissioning. Station No. 2, which served as a background monitoring location during plant operation, continued to show slightly higher readings than the 3 stations located within 1.3 miles of the facility. Therefore, it is concluded that all four locations are reporting naturally occurring background radioactivity. A plot of the radiation level trends for the four locations is shown in Figure B-4, OfTsite Environmental Radiation Level Trends.
All sampling and analysis for the offsite locations of the direct radiation pathway required during this reporting period was performed successfully.
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- d. Waterborne Pathway (1) Suiface Water Surface water sampling of the waterborne pathway is performed by sampling the discharge canal effluent. Sampling is nonnal:v performed by collecting a weekly sample from a discharge canal continuous comporite sampler. If the composite sampler is found to be inoperable. dip samples from the discharge canal are taken. Dip sample analysis results are not used in determination of average and maximum concentrations. Detailed results of the discharge cenal monitoring are provided in Table B-7.
(2) Groundwater Groundwater sampling of the waterborne pathway is performed by sampling five monitoring wells located to monitor for leakage from the spent fuel pool. Sampling of these monitoring wells is performed quarterly. Detailed results of groundwater monitoring are provided in Table B-8.
The Tritium samples collected 2/17/98 were analyzed with longer than nonnal counting times to achieve detection levels much lower than normal, in order to confimi that the trace levels .of Tritium found by 1997 sampling in wells number I and i 1 were unchanged Pecause the sampling on 2/17/98 detected Cs 137 in well number 11, a non-routine set of samples was collected on 2/26/98.
Although Alpha and Beta analysis was not required by the ODCM after S/7/98, both the 5/19/98 and the 8/18/95 sample sets were analyzed for gross alpha and beta. These !
samples, as well as the 2/26/98 samples, are identified as non-routine in Table B-4. l 1
All samphng and analysis for the five monitoring wells of the waterborne pathway required i during this reporting period was performed successfully.
- e. Ingestion Pathway ingestion pathway monitoring is not required by the Technical Specifications. The Environmental Report established baseline conditions for tne ingestion pathway. In accordance with the NRC approved SAFSTOR Decommissioning Plan, these baseline conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR as the result of an accident.
- f. Terrestrial Pathway Terrestrial pathway monitoring is not requireG by the Technical Specifications. The Environmental Report established baseline conditions for the terrestrial pathway. In accordance with the NRC approved SAFSTOR Decommissioning Plan, these baseline conditens will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR as the result of an accident.
TABLE B-1 IIBPP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 -
Exposure Pathway Number of Samples Sampling and Collection Type of Analysis and/or Sample and Locations Frequency DIRECT RADIATION _1_6_onsite sta,tions with TL_D_s____IL_Ds ex_ changed guarterly_ _ _ __ Gan1nla_exposur_e_ _ _ _ _ _
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l 4 offsite stations with TLDs TLDs exchanged quarterly Ganuna exposure WATERBORNE I Surface Water Dischr:ge canal effluent Continuous simipler operation Gamma isotopic
- and i with sample collection weekly Tritium analysis of weekly Dip samples if sampler sample inoperable Groundwater 5 groundwater monitoring wells Quarterly Alpha, Beta, Tritium and gamma isotopic" analysis
'* Gross Alpha and Beta analysis were discontinued aner the third quarter samples were collected. as discussed in section B.I.a.(2)(c) of this report.
- Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the scility.
l TABLE B-2 DISTANCES AND DIRECTIONS TO OFFSITE ENVIRONMENTAL MONITORING STATIONS Radial Direction Radial Distance Station Uy from Plant No. Station Name Sector Degrees (Miles) 1 King Salmon Picnic Area W 270 0.3 2 1742 Wood, Fortuna SPE 158 11.2 l 14 South Bay School Parking Lot S 180 0.4 l
l 25 Irving Drive, Humboldt Hill SSE 175 1.3 l
TABLE B-3 I TES PARTICIPATION - EPA INTERLABORATORY CROSS-CIIECK PROGRAM DATA Sample Type Measurement Month EPA Standard
- TES Results* Participant Average **
Water H-3 March 2155.0 2081.7 2159.5 Sr-89 January 8.0 3.0 9.3 July 21.0 23.3 20.5 Sr-90 January 32.0 33.3 29.5 July 7.0 6.0 6.8 j 1-131 February 104.9 105.3 105.7 j Co-60 June 12.0 12.0 12.7 {
November 38 0 36 7 38.2 )
Zn-65 June 104.0 105.7 108.5
, November 131.0 137.3 137.2 Ba-133 June 40.0 38.3 38.1 November 56.0 59.0 53:1 Cs-134 June 31.0 28.7 28.4 November 105.0 105.3 97.1 Cs-137 lune 35.0 35.7 36.2 November i l 1.0 121.0 113.4 m.
Blind P s Alpha April 54.4 49.5 53.3
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Sample A & B October 30.1 24.5 30.0 l Gross Beta April 94.7 90.0 97,7 October 94.0 90.1 94.2 ;
Sr-89 April 6.0 4.7 6.2 October 19.0 21.0 18.3 {
Sr-90 April 18.0 17.1 17.3 October 8.0 7.0 7.2 I Co-60 April 50.0 47.7 49.7 l October 21.0 19.7 21.8 Cs-134 April 22.0 19.7 20.7 October 6.0 6.7 6.4 Cs-137 April 10.0 10.7 10.I' October 50.0 50.0 50.9 Table Notation l Measurement units vary. As all values are relative to EPA standard, units are not shown in table.
Grand average of submitted results from all program participants, excluding values considered by EPA to be outliers.
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TABLE B-5 ONSITE ENVIRONMENTAL TLD STATIONS l I
Station TLD Exposure Measurements (mR) l Number First Qurrier Second Quarter Third Quarter Tl. 14.3 0.2 14.0
- 0.6 Fourth Quarter )
14.1
- 0.4 13.4
- 0.6 T2 13.1 0.2 12.6 0.5 13.3
- 0.4 12.4 0.4 j T3 12.9 0.4 12.2 0.3 12.1 0.3 11.8
- 0.2 {
T4 12.5 + 0.2 12.2
- 0.4 12.8 0.4 Il.7 i 0.5 !
T5 12.7 0.3 12.7
- 0.5 12.6 + 0.3 11.8 0.3 T6 13.0 + 0.3 12.5 + 0.6 Ii7*O6
[ 12.5 0.7 T7 12.9
- 0.4 11.9
- 0.4 12.3 0.6 11.3 0.4 T8 12.3 0.3 11.2 0.6 12.8 i 0.3 11.4 + 0.6 1 T9 13.0 0.4 12.0 0.5 12.8
- 0.5 11.7 0.5 Tl0 12.1* 0.4 11.0
- 0.4 12.5 0.6 11.5 0.4 Tl1 12.9 0.4 11.9 0.6 13.9 1.3 11.9 0.5 T12 i4.2t0.3 13.6
- 0.3 14.4 0.4 13.0 0.6 T13 14.0 0.6 13.2
- 0.5 13.9
- 0.5 12.8 0.4 T14 14.1
- 0.4 13.4 0.4 13.9 0.7 12.8
- 0.4 TI5 13.9 0.5 14.0
- 0.4 13.9
- 0.5 13.0 0.5
. T16 13.6 0.3 12.0 0.5 12.8 0.5 12.3
- 0.5 f T17 12.8 0.2 12.8 0.5 12.5 0.4 12.2
- 0.5 l I Calculated Parameters (mR)
Parameter First Quarter Second Quarter Third Quarter Fourth Quarter
- Average 13.22 0.09 12.53
- 0.12 13.16
- 0.14 12.16
- 0.12 j Maximum 14.3 i 0.2 14.0 0.6 14.4 0.4 13.4 + 0.6 l
l Notes:
l
- 1. These exposures are reported for a . standardized period of 90 days.
- 2. Station T17 is an of&ite background station. Its results are not included in the calculated parameters.
&^
1 TABLE B-6 l OFFSITE ENVIRONMENTAL TL0 STATIONS l Station TLD Exposure Measurements (mR) l Number First Quarter Second Quarter Third Quarter Fourth Quarter l 1 12.6 0.3 12.2
- 0.5 12.0 0.6 12.0
- 0.4 )
l 2 13.5 A 0.4 12.9 0.5 13.7 0.4 12.6 i 0.8 4 l , 14 11.7 i 0.4 10.8
- 0.4 11.6 0.3 10.6 i 0.5 I 25 12.0
- 0.4 l 11.5
- 0.4 11.3 0.4 11.2
- 0.6
( l l
Calculated Parameters (mR) l Parameter First Quarter Second Quar *er Third Quarter Fourth Quarter l Average 12.45
- 0.19 11.85
- 0.23 12.15 0.22 11.60 0.30 Maximum 13.5 0.4 12.9 0.5 13.7
- 0.4 12.6
- 0.8 Note:
- 1. These exposures are reported for a standardized period of 90 days.
I i
l 1
I
1 TABLE B-7 DISCIIARGE CANAL SAMPLE RESULTS Gamma Activity (pCill) j Sample Date Cs-137 Co-60 Tritium Activity (pCill) 1/2/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 1/9/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 1/16/98 <l8 (MD/ y <l5 (MDA) <500 (MDA) i 1/23/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 1/30/98 <l8 (MDA) <l5 (MDA) <500 (MDA) )
2/6/98 <!8 (MDA) <l5 (MDA) <500 (MDA) 2/13/98_
<l 8 (Mb A)
_ <l5 (MDA) <500 (MDA) 2/20/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 2/27/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 3/6/98 <18 (MDA) <l5 (MDA) <500 (M DA) 3/13/98 <l8 (MDA) <l5 (MD A) <500 (MDA) 3/20/98 <l" (MDA) (15 (MDA) <500 (MDA) 3/27/98 <l 8 (MDA) <l5 (MDA) <500 (MDA) 4/3/98 <l 8 (MDA) <l5 (MDA) <500 (MDA) 4/10/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 4/16/98 <l 8 (MDA) <l5 (MDA) <500 (MDA) 4/24/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 5/1/98 <l8 (MDA) <l5 (MDA) <500 (M DA) 5/8/98 <l8 (MDA) <l5 (MDA) <500 (MDA) i 5/15/98 10*2 6 2 <500 (M DA) 5/22/98 <!8 (MDA) <l5 (MDA) <500 (M DA) 5/29/98 <18 (MDA) <l5 (MDA) <500 (MDA) 6/5/98 <l8 (MDA) <l5 (MDA) <;i00 (MDA) 6/12/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 6/19/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 6/26/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 7/3/98 <l 8 (MDA) <l5 (MDA) <5,00 (M DA) 7/10!98 <l8 (MDA) <l5 (MDA) <500 (MDA) 7/17/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 7/24/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 7/31/98 <18 (MDA) <l5 (MDA) <500 (MDA) 8/7/98 <18 (MDA) <l5 (MDA) <500 (MDA) 8/14/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 8/21/98 <l8 (MDA) <l5 (MDA) <500 (M DA) 8/28/98 <18 (MDA) <l5 (MDA) <500 (MDA) 9/4/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 15-
~-
r
)
i 1
TABLE B-7 (CONTINUED) i DISCilARGE CANAL SAMPLE RESULTS i 1
1 Gamma Activity (pCill) l Sample Date Cs-137 Co-60 Tritium Activity (pCill) l l 9/11/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 9/18/98 <l 8 (MDA) <l5 (MDA) <500 (MDA) 9/25/98 <l8 (MDA) <l5 (MDA) <500 (M DA) i 10/2/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 10/9/98 <l8 (MDA) <l5 (MDA) <500 (M DA) I 10/16/98 <l8 (MDA) <l5 (MD i (500 (M DA) 10/23/98 <l8 (MDA) <l5 (MDA) <500 (M DA) I 10/30/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 11/6/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 11/13/98 <l8 (MDA) <l5 (MDA) <500 (M DA) l 11/20/98 <l8 (MDA) <l5 (MDA) <500 (M DA) i1/25/98 <!8 (MDA) <l5 (MDA) <500 (MDA) ~
12/3/98 <!8 (MDA) <l5 (MDA) <500 (M DA) i 12/9/98 <l8 (MDA) <l5 (MDA) <500 (MDA) 12/16/98 <l8 (MDA) <l5 (MDA) <500 (M DA) I 12/23/98 <l8 (MDA) <l5 (MDA) <500 (M DA) l 12/30/98 <l 8 (MDA) <l5 (MDA) <500 (MDA)
, Calculated Parameters Gamma Activity (pCill) Tritium Activity (pCill) l Cs-137 Co-60 l Average 10 + 2 6*2 Note 4 l l Maximum 10 2 6 2 Note 4 Notes:
- 1. Gamma measurements are performed on the original sample, with results corrected to the time of l
sampling. Naturally occurring isotopes are not reported. The maximum lower limits of detection (LLDs) for Co-60 and Cs-137 are 15 and 18 pCi/l, respectively. The MDA for these analyses was at or below the LLD.
- 2. For purposes of this report, LLD is defmed as the a priori (before the fact) lower limit of detection which represents the capability of the measurement system. MDA is defmed as the a_posteriori (after the fact) limit of detection capability considering a given instrument, procedure and type of cample.
- 3. Tritium analysis is performed on a measured aliquot of distilled sample. The reported values are net measurements above instrument background. Results that are at or below the typical MDA of 500 pCill are reported as "<MDA"
- 4. Results for grab samples and/or results identified as "<MDA" are not included in the calculation of average and maximum values.
b
TABLE B-8 GROUNDWATER MONITORING WELL RESULTS Monitor Alpha Beta j Gamma Tritium Well Sample Activity Activity Activity Activity Number Date (pCill) (pCill) (pCill) (pCill)
_Cs-137 Co-60 MW-1 02/17/98 <3 (MDA) 4 6 <l 8 (MDA) <l5 (MDA) 447* 131 MW-2 02/17/98 <3 (MDA) <4 (MDA) <l8 (MDA) <l5 (MDA) <200 (M DA)
MW-4 02/17/98 <3 (MDA) <4 (MDA) <!8 (MDA) <l5 (MDA) <200 (MDA)
MW-6 02/17/98 <3 (MDA) <4 (MDA) <!8 (MDA) <l5 (MDA) <200 (MDA)
MW-11 02/17/98 <3 (MDA) 24 8 12.6
MW-2 02/26/98 <3 (MDA) 5*4 <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-4 02/26/98 <3 (MDA) 6 5 <l8 (MDA) <15 (MDA) <500 (M DA)
MW-6 62/26/98 <3 (MDA) 4*4 <!8 (MDA) <l5 (MDA) <500 (MDA)
M W-11 02/26/98 <3 (MDA) 10
MW-1 05/19/98 <3 (MDA) 6 5 3.7 0.5 2.0 0.4 <500 (MDA)
MW-2 05/19/98 <3 (MDA) 7*4 <18 (MDA) <l5 (MDA) <500 (MDA)
MW-4 05/19/98 <3 (l\.;:>A) 5*4 <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-6 05/19/98 <3 (MDA) 5 4 <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-11 05/19/98 <3 (MDA) <4 (MDA) <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-1 08/18/98 <3 (MDA) <4 (MDA) <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-2 08/18/98 <3 (MDA) . <4 (MDA) <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-4 08/18/98 <3 (MDA) 14 6 <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-6 08/18/98 <3 (MDA) <4 (MDA) <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-11 08/18/98 <3 (MDA) <4 (MDA) <! 8 (MDA) <l5 (MDA) <500 (MDA)
MW-1 11/17/98 Note 5 Note 5 <!8 (MDA) <l5 (MDA) <500 (MDA)
MW-2 II/17/Rd Note 5 Note 5 <l8 (MDA) <i5 (MDA) <500 (MDA) ;
MW-4 11/17/98 Note 5 Note 5 <l8 (MDA) <l5 (MDA) <500 (MDA) l MW-6 11/17/98 Note 5 Note 5 <18 (MDA) <l5 (MDA) <500 (MDA)
MW-11 11/17/98 Note 5 Note 5 <l8 (MDA) <l5 (MDA) <500 (MDA)
MW-l l 11/17/98 Note 5 Note 5 <l8 (MDA) <l5 (MDA) <500 (MDA) l l
l i
t_ 1
4 e l
. 1 4 s TABLE B-8 KONTINUED)
GROUNDWATER MONITORING WELL RESULTS Calculated Parameters Alpha Beta Gamma Tritium l (By Monitor Well Activity Activity Activity Activity l Nianber) (pCill) (pCill) (pCi/l) (pCill)
)
Average: MW-1 Note 4 6 3 3.7
- 0.5 2.0
- 0.4 447 131 Average: MW-2 Note 4 6*3 Note 4 Note 4 Nc'. 4 Average: MW-4 Note 4 8*3 Note 4 Note 4 NoA4 i Average: MW-6 Note 4 4*3 Note 4 Note 4 Note 4 l Average: MW-11 Note 4 17
- 5 12.6 2.3 Note 4 274
- i I 8_
Maximum: MW-1 Note 4 7 5 3.7
- 0.5 2.0 0.4 447 A i3l _ - -
Maximum: MW-2 Note 4 7*4 Note 4 Note 4 Note 4 Maximum: MW-4 Note 4 14
- 6 Note 4 Note 4 Note 4 Maximum: MW-6 Note 4 5 4 Note 4 Note 4 Note 4 I 1 Maximum: MW-11 Note 4 24
- 8 12.6 2.3 Note 4 274 118 Notes: ,
J l Reported values are net measurements (above instrument background). The normal minimum I detectable activities foe the analyses for gross alpha, gross beta, and tritium are approximately 3,4, and 500 pCi/1, respectively.
- 2. Gamma activity meacarements are performed on the original sample, with results corrected to the time of sampling Naturally occurring isotopes are not reported. The maximum lower limits of detection (LLDs) for Co-60 and Cs-137 are 15 and 18 pCi/1, respectively. The actual MDAs for these analyses were at or below the LLD.
- 3. For purposes of this report, LLD is dermed as the a priori (before the fact) lower limit of detection ;
which represents the capability of the measurement system. MDA is dermed as the _a posteriori (after {
the fact) limit of detection capability considering a given instrument, procedure and type of sample.
- 4. Results identihed as "<MDA" are not included in the calculation of average and maximum values
- 5. Gross Alpha and Beta analysis discontinued, as discussed in section B.I.a.(2)(c) of this report. l i
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4 O FIGURE B-1 IIBPP ONSITE TLD LOCATIONS
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