ML20217P154

Annual Facility Status & Survey Rept for 970101-1231

ML20217P154
Person / Time
Site:	Humboldt Bay
Issue date:	12/31/1997
From:	PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20217P133	List: HBL-98-006, Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program ML20217P154
References
NUDOCS 9804090331
Download: ML20217P154 (25)

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Enclosure PG&E Letter HBL-98-006 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL FACILITY STATUS AND SURVEY REPORT JANUARY 1 THROUGH DECEMBER 31,1997 2

788" 88n 3!888122 R

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TABLE OF CONTENTS A. FACILITY STATUS...........

.. I 1.

Unit 3 Condition....

......I

2. Caisson Sump Sample Results..

.1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..

.3

1. Summary Description of the Radiological Environmental Monitoring Program..

..........3 Technical Specification Monitoring Requirements................

... 3 a.

2.

EPA Interlaboratory Comparison Program..

.4

3. Monitoring Results.

........5 Radiological Environmental Monitoring Program Annual Summary.

.5 a.

- b. -' Airborne Pathway...

.5 Direct Radiation Pathway.....

..........5 c.

r (1) Onsite Locations...

.5 (2) Offsite Locations.....

.5

d. Waterborne Pathway...

.6 (1) Surface Water.............

......6 (2) Groundwa'er.,

............6 e.

Ingestion Pathway..

.....6 f.

Terrestrial Pathway..

...6 s

-H-i i

r

)

..i LIST OF TABLES bbig Page A-1 Caisson Sump Sample Results..

.2 B-1 HBPP Radiological Emironmental Monitoring Program....

.7 B-2 Distances And Directions to Offsite Emironmental Monitoring Stations.

.8 B-3 TES Participation - EPA Interlaboratory Cross-Check Program Data.

.9 B-4 Radiological Emironmental Monitoring Program Annual Report Summary.

,10 B-5 Onsite Emironmental TLD Stations..

12 B-6 Offsite Environmental TLD Stations.

. 13 B-7 Discharge Canal Sample Results..

.14

\\

B-8 Groundwater Monitoring Well Results.

..,16 LIST OF FIGURES Eigug Page B-1 HBPP Onsite TLD Locations..

18 B-2 HBPP Onsite Monitoring Well Locations..

.19 B-3 HBPP Offsite TLD Locations.

.20 A

B-4 Offsite Environmental Radiation Level Trend _.

.22

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+

.,i PACIFIC GAS AND ELECTRIC COMPANY ANNUAL FACILITY STATUS AND SURVEY REPORT FOR HUMBOLDT BAY POWER PLANT UNIT 3, COVERING THE PERIOD JANUARY I THROUGH DECEMBER 31,1997 This annual report is required by Section VII.H.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 Emironmental Monitoring Program (REMP) for the period

- of January 1 through December 31,1997.

A. FACILITY STATUS

1. Unit 3 Condition The facility remained in SAFSTOR status during the report period.

The rate of groundwater leakage into the caisson sump at the beginning of the report period was approximately 6,000 gallons per day. In September, a caisson inleakage repair project (CIRP) was successfully completed, reducing the groundwater leakage into the caisson ump to approximately 15 gallons per day. The leakage remained at this rate through the end of the report period.

2. Caisson Sump Sample ResultsSection VI.B.I.c of the Technical Specifications requires that the caisson sump water be sampled and analyzed monthly (for total alpha, beta, and gamma activity), and that the average and maximum values for the results be reported annually. This data is reported in Table A-1.

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..s TABLE A-1 CAISSON SUMP SAMPLE RESULTS Alpha Activity Beta Activity Gamma Activity (pCi/l)

Date '

(pCill)

(pCill)

Cs-137 Co-60 1/2/97

<2842 (MDA)

<7125 (MDA) 5.0 5.0

<7.5 (MDA) 1/29/97

<2770 (MDA)

<7266 (MDA) -

8.0 5.2

<5.6 (MDA) 2/26/97

<2403 (MDA)

<744 I (MOA) 9.9

• 6.2

<11.4 (MDA) 3/26/97

<2208 (MDA)

<7326 (MDA) 11.0

• 6.2

<11.3 (MDA) 4/23/97

<2208 (MDA)

<7454 (MDA) 8.3 4.P

<9.1 (MDA) 5/21/97

<1757 (MDA)

<7421 (MDA) 9.0 5.3

<6.1 (MDA) 6/18/97

<2270 (MDA)

<7396 (MDA) 10.1 5.5

<6.4 (MDA) 7/16/97

<2334 (MDA)

<7443 (MDA) 13.7 6.6

<l l.7 (MDA) 8/13/97

<l252 (MDA)

<7214 (MDA) 11.6 5.9

<7.5 (MDA) 9/10/97

<2193 (MDA)

<7160 (MDA) 8.7 A 5.0

<7.0 (MDA) i 10/8/97

<l158 (MDA)

<7196 (MDA) 7.1

• 3.3

<4.5 (MDA) 11/5/97

<1452 (MDA)

<7112 (MDA) 4.4

• 3.2

<3.7 (MDA) l 12/3/97

<1403 (MDA)

<7085 (MDA)

<5.6 (MDA)

<3.4 (MDA) 12/31/97

<l440 (MDA)

<7127 (MDA)

<9.4 (MDA)

<8.9 (MDA)

Calculated Alphe Activity Beta Activity Gamma Activity (pCi/l)

Parameters (pCi/l)

(pCi/l)

Cs-137 Co-60 Average Note 4 Note 4 8.9

• 1.5 Note 4

)

Maximum Note 4 Note 4 13.7 6.6 Note 4 Notes:

1.

Alpha and Beta analyses are performed on a measured aliquot of sample. The typical LLDs for the analyses with I ml aliquots are approximately 2,000 pCU! for Alpha and 10,000 pCi/l for Beta. The MDA for the analyses ranged from 1,160 to 2,842 pCi/l for Alpha and from 7,080 to 7,450 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 1

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 3.6 to 9.4 pCi/l for Cs-137 and from 3.4 to 11.7 pCill for Co-60.

2.

For purposes of this report, LLD is defined as the a priori (before the fact) lower lir.it of detection which represents the desired capability of the measnement system. MDA is defined as the a l

posteriori (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.

.?

2-

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B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Summary Description of the Radiological Emironmental Monitoring Program The NRC Radiological Assessment Branch issued a Branch Techaical Position (BTP) on environmental monitoring in March 1978. Revision 1 of the BTP was issued as Generic Letter 79-65 and sets forth an example of an acceptable minimum radiological monitoring program. He 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 t'.ne 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 Emironmental Report as discussed below. In addition, the nuclides specified for analysis by the BTP have been revised to reflect the available source term at a nuclear power plant which has been shut down since July 2,1976.

The Emironmental Report, submitted to the NRC as Attachment 6 to the SAFSTOR license amendment request, established baseline conditions for soil, biota and sediments. 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 recalt of an accident.

The Emironmental Report also contains a description of the demography and human actisities within the environs surrounding the site.

The REMP consists of the collection and analysis of both onsite and offsite emironmental samples.

Sample collection is performed by HBPP personnel and sample analysis is performed by PG&E's Tecimical 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.

I Sample collection for the REMP is performed at the sampling stations defined by Table B-2, j

Distances and Directions to Environmental 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.

a.

Technical Specification Monitoring Requirements (1) Offsite Environmental Monitoring Stations ne Technical Specifications (Section V.A.4) require four offsite environmental monitoring stations (Stations 1, 2,14 and 25) to be maintained through the SAFSTOR period. These stations are required to be equipped with dosimetry devices that can be compared with those used onsite.

The Technical Specifications (Section V.B.4) require tilat if TLDs are the dosimetry devices used, they shall be monitored at least quarterly, with average and maximum values reported annually.

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Section V.B.4 also requires that if the results from any station indicate that the total

' radiation dose would be 25 mr/yr or more above background, an investigation shall be l

conducted and necessary mitigative actions taken.

(2) Onsite Environmenal Monitoring Stations The Technical Specifications (Section V.A.6) establish rquirements for onsite environmental monitoring stations.

(a) A continuous sampler shall be provided for monitoring water in th: discharge canal.

Section V.B.6.a requires 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 requires that the composite samples shall be analyzed weekly when -

l the sampler has been operating.

Section V.B.6.a also requires that average and maximum activity and concentrations shall be reponed annually. Dip samples shall not be used in determination of average and maximum ' concentrations.

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(b) A total of 16 onsite dosimeters are required to be located within the site perimeter

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fence line at locations specified on Technical Specification Figure V-2.

l S' ection _V.B.6.b requires that the onsite dosimeter stations be monitored at least

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quanerly and that average and maximum dosimetry values shall be reported annually.

(c) 'Ihe onsite groundwater monitoring program consists of five wells constructed in the j

vicinity of Unit 3.

l Section V.B.6.c requires that the wells shall be sampled quarterly for total gros i-alpha, total gross beta, total gamma activity and tritium and that average and maximum sample results shall be prepared annually.

2. EPA Interlaboratory Comparison Program 1-L PG&E's Technical and Ecological Semees participates in the EPA's Environmental Laboratory l.

Performance Evaluation Study (Interlaboratory Cross-Check Program).

This participation includes sufficient determinations (sample nrfum radionuclide combination) to ensure independent checks on the precision and accuracy of the measurements of radioactive materials in the REMP samples. Results of the 1997 participation in the Interlaboratory Cross-Check Program are presented in Table B-3.

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3. Monitoring Results Radiological Emironmental Monitoring Program Annual Summary a.

Results of the REMP sampling and analysis are summarized in Table B-4 in the format of the BTP Table 3.

b. Airborne Pathway Airborne pathway monitoring is not required by the Technical Specifications.

The Environmental Report, submbed to the NRC as Attachment 6 to the SAFSTOR license j

amendment request, establisk baseline conditions for the airborne pathway. In accordance with the NRC approved SAF 50R Decommissioning Plan, these baseline conditions will only need to be reestablished priw to final decommissioning if a significant release occurs during 1

SAFSTOR as the result of an accident.

Direct Radiation Pathway c.

t (1) Onsite Locations j

Onsite monitoring of the direct radiation pathway is performed at 16 locations near the facility fenceline. Monitoring is perfonned using TLDs which are changed out quarterly.

Detailed results of the onsite monitoring are provided in Table B-5.

Variations in quarterly 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 s>nce entering SAFSTOR decommissioning.

All sampling and analysis for the onsite locations of the direct radiation pathway required during this reporting period was performed successfully.

(2) Offsite Locations Offsite monitoring of the direct radiation pathway is performed at 4 locations in the vicinity of the facility. Monitoring is performed using TLDs which are changed out quarterly. Detailed results of the offsite monitoring are provided in Table B-6. All measurements were comparable to the ranges observed at these locations since 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, Offsite Environmental Radiation LevelTrends.

All sampling and analysis for the offsite locations of the direct radiation pathway required during this reporting period was performed successfully.

d. Waterbome Pathway (1) Surface Water Surface water sampling of the waterborne pathway is performed by sampling the discharge canal eflicent. Sampling is ncrmally peiformed by collecting a weekly sample from a discharge canal continuous composite sampler. If the composite sampler is found to be inoperable, dip samples from the discharge canal are taken in accordance with Technical Specification V.B.6.a.

Dip sample analysis results are not used in determination of average and maximum concentrations. Detailed results of the discharge canal monitoring are provided in Table B During the reporting period,54 discharge canal samples were obtained. Two samples (on 10/10/97 and 10/24/97) were dip samples required to be taken due to an inoperable composite rampler. Although the sample was not operating on 10/24/97, there was sufficient composite sample for analysis, so both the dip sample and the partial composite sample were sent to TES for analysis.

(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 pertbnned quarterly. Detailed results of groundwater monitoring are provided in Table B-8.

The esults for 8/19/97 were the first since 1984 to D01 indicate detectable Tritium in well

{

1. 11, ari the first since 1984 to detect Tritium in well #1. Accordingly, a non-routine y

sample was collected (on 10/24/97) from each of these wells to confirm these results.

All sampling and analysis for the five monitormg wells of the waterborne pathway required during this reporting period was performed successfully.

Ingestion Pathway e.

Ingestion patlnvay monitoring is not required by the Technical Specifications.

The Emironmental Report established baseline conditior.e for the ingestion pathway.

In accordance with the NRC approved SAFSTOR Decommissioning Plan, these baseline conditions will only need to b: reestablished prior to final decommissionin3 if a significant j

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release occurs during SAFSTOR as tho result of an accident.

f.

Terrestrial Pathway Terrestrial patnway monitoring is not required 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 i

conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR as the resu t of an accident.

TABLE B-1 IIBPP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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 TLD_s___,RDs exciganged, quarterly __ ___ Gam _ma_exyosure 4 offsite stations with TLDs TLDs exchanged quarterly Gamma exposure WATERBORNE Surface Water Discharge canal efiluent Continuous sampler operation Gamma isotopic (*) and with sample collection weekly Tritium analysis of weekly Dip samples if sampler sample inoperable Groundwater 5 groundwater monitoring wells Quarterly Alpha, Beta, Tritiam and gamma isotopic (') analysis

(*) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the elliuents from the facility.

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TABLE B-2

' DISTANCES AND DIRECTIONS TO OFFSITE ENVIRONMENTAL MONITORING l

STATIONS l

Radial Direction Radial Distance Station By from Plant No.

Station Name Sector Degrees (M:les) 1 King Salmon Picnic Area W

270 0.3

~

2 1742 Wood, Fortuna SSE 158 l 1.2 14 South Bay School Parking Lot S

180 0.4 25 Irving Drive, Humboldt Hill SSE 175 1.3 l

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TABLE B-3 TES PARTICIPATION - EPA INTERLABORATORY CROSS-CllECK PROGRAM DATA Sample Type Radionuclide Month EPA Standard TES Results Participant Average

• pCill pCi/l pCill Wate-H-3 March 7900.00 7876.67 7730.31

^

__ u3us.t __ijgt0pp_ ___ _ i.0_96M7_ _ _ __ _ _ _ j Q868 J6 _ _ _ _

Sr-89 January 12.00 12.43 11.78

__Julx__ -___4439__.-___.R33___.- _ _ _ _ _.4L5 2_ _ _.

Sr-90 January 25.00 22.50 23.52

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-_ _J_ul_v 1-131 February __

- _ - _16_.0_0

---_ _14._67_ _ _.- _ _ _ _ _ _1_5._2 8--__.

l 86.00 89.00 87.71

_S_ent_em_ber

____L0pp_______jl.33_____ _ _ _ _ _ 19 92 _ _ _ _

Co-60 June 18.00 18.67 18.77 N-27.00

-- -- _2_6.67 _ _ - - _ _ _ _ _2_7.5 5 _ _ _ -

-_ov_em_ber--

June 100.00 101.67--

Zn-65 103.33 No

-- _v_em_b_e_r

- - _ __7_5_.0_0_ _.- _ _ _ _7_2._67_ _ _.

- _ _ _7_8.1_1 _ _ _ _

Ba-133 June 25.00 24.33 23.74 i

-_o_vemb_er-_ _ _9_9_.0_0_ _.- _ _ _ _93._3 3_ _ _

_9_4._5 6_ _ _ _ -

N 3

Cs-134 June 22.00 21.67 20.17 i

N-June 49.00 48.67 49.97

-_ov_em_ber--- _ _ _10._.0_0_ -.-- _ _ _10.00_ _ -- _ - - _ -- 9._5 1 _ _ --

Cs-137 N-

-_ov_em_b_e_r

--- 7_4_.0_0_ --- _ _ _ _7 9._3 3_ _ _.- - - _ -- _7_6._16_ - - _ -

Gross Alpha January 5.20 6.97 6.02 July 3.10 5.43 4.13

-_Octo_ber

_ _ _1_4_.70_ _- _ _ - 14.03_ _ --- _ _ -_ - 12._26 Gross Beta January 14.70 11.50 15.66 July 15.10 11.87 15.42 October 48.90 48.53 48.88 Blind Gross Alpha April 48.00 45.70 46.90 Sample A & B

_ _0_ctober__ _ _ _4 9_90_ _ __ _ _ _,' 9_. 00_ _ _ __ _ _ _ _ _ _4 7.2 7_ _ _ _ _

Gross Beta April 102.10 99.67 97.27

-_O_ctobe_r_- _ _ _14_3_.4_0 _- - _ _12_9._3 7_ _ _.- _ _ _ _. 1_3_4._2 7 _ _ _.

-26.67 24.18-j-

Sr-89 April 24.00

-_O_cto_be_r_--_ 3 6.0_0_ _.- _ _- _3 7.17.. _ --- _ _ _ _ _ _3_5._3 0_ - - - -

Sr-90 April 13.00 1!.67 12.52 Oct -

--- _obe_r_ --- 2_2_.00 _.

_ _ _ _2_1._5 3_ _ _.- _ _ _ _ _2_1.5 3_ - _ _ -

Co-60 April 21.00 21.00 21.87

-_ October _._ _ _ _10.00_ _.-_ __10.33 _ _ - _ - _ _ _ 10.4 6 _ _ _..

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-_O_ctobe_r_- _ - _4_1_. 0_0_ - -- _ - _ _4 0.00 Cs-137 April 22.00 21.67- - - - -.- _ _ - _ - _3_7._8 22.75 October 34.00 38.00 35.51

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..l-j TABLE B-5 ONSITE' ENVIRONMENTAL TLD STAilONS Station TLD Exposure Measurements (mR)

Number First Quarter Second Quarter Third Quarter Fourth Quarter Tl 14.0

• 0.4 14.3 0.3 14.4

• 0.5 14.6 0.6 T2 13.0 0.4 13.6

• 0.5 13.2 0.4 12.9 i 0.6 T3 13.2 0.3 12.9

• 0.5 12.9 0.4 12.9

• 0.2 T4 12.7 A 0.4 12.9 0.4 12.8 i 0.4 12.6 t 0.4 T5 13.8 i 0.5 13.8

• 0.5 13.4 0.4 13.2 0.5 T6 15.8

• 0.4 15.2

• 0.6 14.0 0.3 13.0

• 0.6 T7 17.5

• 0.4 15.3 0.2 14.8

• 0.4 13.8

• 0.3 T8 13.0

• 0.5 12.1 0.4 13.3

• 0.5 12.2

• 0.4 T9 12.8 0.4 12.9

• 0.6 13.6 0.5 12.9 0.4 T10 12.6 0.3 11.8 0.3 13.1 0.4 12.2 0.5 Tl1 12.7 0.4 12.9 0.4 13.8 0.4 12.8

• 0.2 T12 14 5 0.4 13.9 0.4 14.3

• 0.5 14.0

• 0.7 Tl3 13.7

• 0.6 14.5

• 0.3 13.9 0.5 13.6

• 0.4 T14 13.9

• 0.3 14.9

• 0.6 13.7

• 0.6 13.5

• 0.5 T15 13.5

• 0.4 14.1

• 0.5 14.1

• 0.6 13.6 A 0.3 T16 13.2

• 0.3 14.8

• 0.5 13.3

• 0.3 13.0

• 0.3 T17 12.9 0.4 12.6 0.6 12.9 0.7 12.5 0.4 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 13.74 i 0.10 13.74 0.11 13.66 0.11 13.18

• 0.11 Maximum 17.5

• 0.4 15.3

• 0.2 14.8

• 0.4 14.6 0.6 Notes:

1.

These exposures are reponed for a standardized period of 90 days.

2.

Station T17 is an offsite background station. Its results are not included in the calculated parameters.

• s,

O TABLE B-6 OFFSITE ENVIRONMENTAL TLD STATIONS Station TLD Exposure Measurements (mR)

Number First Quarter Second Quarter Third Quarter Fourth Quarter 1

12.8

• 0.6 12.1 0.6 13.2 0.4 13.0 0.4 2

13.3

• 0.5 13.2

• 0.4 13.8 i 0.7 13.5 0.3 14 11.6 0.3 11.3 A 0.3 12.0 0.6 11.6 0.3 25 11.7

• 0.4 11.6

• 0.6 11.7

• 0.5 11.7 0.3 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 12.35

• 0.05 12.05

• 0.06 12.68 0.07 12.45 0.04 Maximum 13.3 0.5 13.2

• 0.4 13.8

• 0.7 13.5 0.3 _

Note:

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

i l

I

, M

i TABLE B-7 DISCIIARGE CANAL SAMPLE RESULTS Gamma Activity (pCill)

Sample Date Cs-137 Co-60 Tritium Activity (pCill) 1/4/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 1/10/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 1/17/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 1/24/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 1/31/97

<!8 (MDA)

<l5 (MDA)

<500 (MDA) 2/7/97

<18 (MDA)

<15 (MDA)

<500 (MDA) 2/14/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 2/21/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 2/28/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 3/7/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 3/14/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 3/21/97

<l 8 (MDA)

<l5 (MDA)

<500 (MDA) 3/28/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 4/4/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 4/11/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 4/17/97

<l 8 (MDA)

<l5 (MDA)

<500 (MDA) 4/25/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

~

5/2/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 5/9/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 5/16/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 5/23/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 5/30/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 6/6/97

<18 (MDA)

<15 (MDA)

<500 (MDA) 6/13/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 6/20/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 6/27/97

<l 8 (MDA)

<15 (MDA)

<500 (MDA) 7/3/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 7/l1/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 7/18/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 7/25/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 8/1/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

I 8/8/97

<l 8 (MDA)

<15 (MDA)

<500 (MDA) 8/15/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 8/22/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 8/29/97

<18 (MDA)

<5 (MDA)

<500 (MDA) 9/5/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) l i

I TABLE B-7 (CONTINUED)

DISCIIARGE CANAL SAMPLE RESULTS Gamma Activity (pCill)

Sample Date Cs-137 Co-60 Tritium Activity (pCill) 9/12/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 9/19/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 9/26/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) l 10/3/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 10/10/97 (grab)

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 10/17/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 10/24/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 10/24/97 (grab)

<18 (MDA)

<l5 (MDA)

<500 (MDA) 10/31/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 11/7/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 11/14/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 11/21/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 11/26/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 12/3/97

<l8 (MDA)

<15 (MDA)

<500 (MDA) 12/5/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 12/12/97

<l8 (MDA)

<l5 (MDA)

<500 (MDA) 12/23/97

<18 (MDA)

<l5 (MDA)

<500 (MDA) 12/26/97

<18 (MDA)

<l5 (MDA)

<500 (MDA)

Calculated Parameters Gamma Activity (pCill)

Tritium Activity (pCi/l)

Cs-137 Co-60 Average Note 4 Note 4 Note 4 Maximum Note 4 Note 4 Note 4 l

Notes:

l

1. Gamma measurements are performed on the original sample, with results corrected to the time of sampling. Naturally occurring isotopes are not reported. The maximum lower limits of detection (LLDs) for Co-60 and Cs-137 are 15 and 18 pCi/1, respectively. The MDA for these analyses was at or below the LLD.

2.

For purposes of this report, LLD is defmed as the a nriori (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 sample.

3.

Tritium analysis is performed on a measured aliquot of distilled sample. The reponed values are net measurements above instrument background. Results that are at or below the typical MDA of 500 pCi/l are reponed as "<MDA".

4.

Results for grab samples and/or results identified as "<MDA" are not included in the calculation of average and maximum values.

I TABLE B-8

)

GROUNDWATER MONITORING WELL RESULTS Monitor Alpha Beta Gamma Tritium Well Sample Activity Activity Activity Activity Number Date (pCill)

(pCi/l)

(pCi/l)

(pCill) l Cs-137 Co-60 MW-1 02/18/97

<3 (MDA) 4*5

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-2 02/18/97

<3 (MDA)

<4 (MDA)

<l 8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-4 02/18/97

<3 (MDA) 4*3

<18 (MDA)

<l5 (MDA)

<500 (MDA)

MW-6 02/18/97

<3 (MDA)

<4 (MDA)

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-il 02/18/97

<4 (MDA) 7 6

<l8 (MDA)

<l5 (MDA) 500 228 MW-1 05/21/97

<3 (MDA)

<4 (MDA)

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-2 05/21/97

<3 (MDA)

<4 (MDA)

<18 (MDA)

<l5 (MDA)

<500 (MDA)

MW-4 05/21/97

<3 (MDA)

<4 (MDA)

<18 (MDA)

<l5 (MDA)

<500 (MDA)

MW-6 05/21/97

<3 (MDA)

<4 (MDA)

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-i l 05/21/97

<3 (MDA)

<4 (MDA)

<18 (MDA)

<l5 (MDA) 601 211 MW-1 08/19/97

<3 (MDA) 11 5

<l8 (MDA)

<l5 (MDA) 589

• 225 MW-2 08/19/97

<3 (MDA)

<4 (MDA)

<18 (MDA)

<l5 (MDA)

<500 (MDA)

MW-4 08/19/97

<3 (MDA)

<4 (MDA)

<l8 (MDA)

<l5 (MDA)

<500 (MDA)

MW-6 08/19/97

<3 (MDA)

<4 (MDA)

<18 (MD 6

<l5 (MDA)

<500 (MDA)

MW-ll 08/19/97

<3 (MDA) 8 6

<l8 (MD. )

<l5 (MDA)

<500 (MDA)

MW-1 10/24/97

<3 (MDA)

<4 (MDA)

<18 (MDA)

<l5 (MDA) 453

• 118 j

MW-ll 10/24/97

<3 (MDA)

<4 (MDA)

<l 8 (MDA)

<l5 (MDA) 299

• 113 MW-1 11/18_/97

<3 (MDA) 8 7

<l8 (MDA)

<l5 (MDA) 409 121 MW-2 11/18/97

<3 (MDA)

<4 (MDA)

<l8 (MDA)

<l5 (MDA)

<200 (MDA)

MW-4 11/18/97 7i6 12 8

<18 (MDA)

<l5 (MDA)

<200 (MDA)

MW-6 11/18/97

<3 (MDA) 4 7

<l8 (MDA)

<l5 (MDA)

<200 (MDA)

MW-ll 11/18/97

<3 (MDA) 15

• 8

<l8 (MDA)

<l5 (MDA) 376 A 120 l

l

[

t I

l t

e,;

TABLE B-8 (CONTINUED).

GROUNDWATER MONITORING WELL RESULTS l

Calculated Parameters Alpha Beta Gamma Tritium (By Monitor Well Activity Activity Activity Activity Number)

(pCill)

(pCill)

(pCill)

(pCi/l)

Cs-137 Co-60 Average: MW-1 Note 5 8 3 Note 5 Note 5 484 94 Average: MW-2 Note 5 Note 5 Note 5 Note 5 Note 5 Average: MW-4 7*6 8 4 Note 5 Note 5 Note 5 Average: MW-6 Note 5 4*7 Note 5 Note 5 Note 5 Average: MW-11 Note 5 10 6 Note 5 Note 5 444 88 Maximum: MW-1 Note 5 11 5 Note 5 Note 5 589 225 Maximum: MW-2 Note 5 Note 5 Note 5 Note 5 Note 5 Maximum: MW-4 7 6 12

• 8 Note 5 Note 5 Note 5 Maximum: MW-6 Note 5 4*7 Note 5 Note 5 Note 5 Maximum: MW-11 Note 5 15

• 8 Note 5 Note 5 601 211 i

Notes:

1.

Reported values are net measurements (above instrument background). The normal minimum detectable activities for the analyses for gross alpha, gross beta, and tritium are approximately 3,4, and 500 pCi/1, respectively.

2.

Gamma activity measurements are perfonned 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 defined as the a orio_d (before the fact) lower limit of detection which represents the capability of the measurement system. MDA is defined as the a nosteriori (after j

the fact) limit of detection capability considering a given instrument, procedure and type of sample.

4.

The results for 8/19/97 were the first since 1984 to indicate no detectable Tritium in well #11, and the first since 1984 to detect Tritium in well #1. Accordingly, extra samples were collected (10/24/97) to confirm these results. The Tritium analysis of samples collected 10/24/97 and 11/18/97 used longer than normal counting times to achieve a minimum detectable tritium activity of approximately 200 pCi/1.

5.

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

]

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