ML20141E074
| ML20141E074 | |
| Person / Time | |
|---|---|
| Issue date: | 04/03/1986 |
| From: | Clark A NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Hannum W ENERGY, DEPT. OF, IDAHO OPERATIONS OFFICE |
| References | |
| REF-PROJ-M-32 NUDOCS 8604080468 | |
| Download: ML20141E074 (18) | |
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ATClark NDavison Project M-32 JRoth, Reg I JKeimig, Reg I RBoyle JJoyner, Reg I Dr. W. H. Hannum, Director West Valley Project Officer Department of Energy _ Idaho Operations Office P.O. Box 191 West Valley, New York 14171
Dear Dr. Hannum:
Enclosed is the report of the NRC Monitoring Team visit to the West Valley Demonstration Project site during the week of September 30, 1985, at which time your measurement systems and the measurement control and environmental moni-toring programs were monitored. Completion of the report was delayed until all analytical results from environmental samples taken by the NRC during the visit were available. The areas covered were as outlined in my letter to you dated May 29, 1985. We appreciate the cooperation extended by the' Department of Energy Project Office and its contractor, West Valley Nuclear Services, Inc., in responding to inquiries and in providing the information requested.
In general, the NRC Monitoring Team found that the measurement systems and the measurement control and the environmental monitoring programs were adequate.
However, several areas were identified which could be improved. Recomenda-tions for improvement in these areas are incorporated into the enclosed report.
Although no response to this letter is requested, we intend to discuss the disposition of the recommendations during future visits to the Project.
Sincerely.
ORIGINAL SIGNED BY:
A. Thomas Clark, Jr.
NRC West Valley Project Manager Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated 0FC: FCAR
- FCA
_______/f_Td________
NAME: ATClark/jl:LCRo"use :
DATE:04/ / /86 :04/9/86 :
/
OFFICIAL RECORD COPY 8604000468 060403 PDR PROJ M-32 PDR
Monitoring Report on Measurement Systems, and the Measurement Control and Environmental Monitoring Programs for the West Valley Demonstration Project - October, 1985 Introduction In accordance with the West Valley Demonstration Project Act, the Nuclear Regulatory Commission (NRC) is required to monitor project activities in the interest of public health and safety. On May 29, 1985, we informed the Depart-ment of Energy (D0E) Project Office of our intention to visit the Project site to monitor the effectiveness the DOE contractor's measurement systems and the measurement control and environmental monitoring programs.
We evaluated those programs in accordance with good laboratory and industry practices. The requirements of DOE Orders 5630, 5820, 5480.1 and 5484.1, were used as the bases for the observations and recommendations made with respect to the measurement systems and the measurement control and environmental moni-toring programs, respectively. The DOE has provided us with information on the contractor's measurement systems, measurement control program and environmental monitoring program since their inception, including the Site Characterization Study, the Environmental Monitoring Plan, and Low Level and TRU Waste Assay Methodology.
In making observations during our visit, we also considered the unique nature of the Project, both with respect to the technical approach taken and the ACTIONTRAK management scheme. We also examined previous audits both of and by the contractor. We note that the effectiveness of these programs has been adequately demonstrated, in that we did not identify any significant deficien-cies which could affect the health and safety of the public.
Section A provides our general observations and recommendations.
In Sections B, C, D and E, a detailed discussion of each topic monitored is presented. As discussed in the detailed sections, we noted that several of our observations and recommendations had been identified in previous audits by others, i.e., DOE and West Valley Nuclear Services (WVNS), and that corrective actions on those items had already been initiated.
A.
Observations - Recommendations In general, the NRC monitoring team found that the measurement systems, measurement control program and the environmental monitoring program were adequate. However, several areas were identified which could be improved.
Our recommendations for improvement in these areas are indicated below:
1.
The contractor should use only approved procedures to perform analyses.
2.
Control charts for all applicable analytical and environmental instruments should be generated to demonstrate trends and systematic biases.
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2 3.
Calibration standard solutions and control standard solutions used for all analytical and environmental measurement systems should be from different stock solutions and stored independently of one another.
4.
Data used to generate calibration curves and control charts should be maintained with the charts in all laboratories.
5.
The contractor should document actions taken to correct out-of-limit analytical results.
6.
The monitoring team determined that despite several constraints in the environmental laboratory (such as old gamma spectrometry equip-ment, limited work areas and limited manpower available) good analy-tical results were being attained.
7.
Copies of vendor laboratory procedures should be obtained, reviewed, approved and maintained current by the contractor.
8.
Americium 241 should be included as part of the calibration curve for the alpha spectrometer so that the Am-241 activity in the environmental samples can be quantified.
9.
Tests of the stack samplers / monitoring system should be conducted
~ prior to hot operation of the Project to assure that the measurement of activity in the exhaust air as measured by the samplers / monitors is accurate or conservative. These tests should include measurement of the stack samplers / monitor line losses.
- 10. The contractor should establish alpha and beta self absorption curves because the actual activity of the sample cannot be calculated due to the high sample residual weight obtained from the quantity of liquid analyzed.
- 11. The high voltage should be increased at smaller increments (currently 50 volt increments) during calibration of proportional counters, in order to more accurately define the plateau.
- 12. Both standard and blank (background) samples should be analyzed along with each batch of environmental samples being analyzed, in order to establish the precision and accuracy of the analyses.
- 13. Lagoon water samples (lagoon 2 and 3) should be distilled prior to analysis for tritium, to avoid potential problems as a result of color and chemical quenching, contribution of other beta emitters, and chemiluminescence.
- 14. The counting efficiency should be determined each time environmental samples are analyzed for tritium, instead of using the instrument counting efficiency for a three month period, in order to assure that corrections are made for the decay of the standard samples.
a.
3
- 15. A strontium carrier calibration procedua.. using the atomic absorption technique for analysis, should be written, reviewed and approved. The strontium carrier calibration frequency and shelf life should be specified in this procedure.
- 16. A trace amount of stable strontium should be added to the secondary' standard solution, in order to keep the radiostrontium in solution.
- 17. The previously established Sr-90 self-absorption curve should be reevaluated, since it was noted that this curve contained an exces-sively wide error band.
- 18. Strontium-90 activity in environmental samples should be recounted two weeks after the initial count, in order to verify the initial Sr-90 determination, since Y-90 should be in equilibrium with Sr-90 after a two week period.
- 19. The contractor should either conduct the tests on TLDs identified in ANSI Standard N545-1975, or obtain the test results from DOE-RESL for review.
B.
West Valley Nuclear Services (WVNS) Measurement Systems and Measurement Control Program 1.
' Program Review The effectiveness of the contractor's (WVNS) measurement systems and control program as they affect analytical laboratory and waste mea-surements was determined by examination, review of records, discus-sions with DOE and WVNS personnel and observations made by the Monitoring Team. The measurement system's quality assurance, quality control and calibration programs were also examined.
Examination of the measurement control program indicated that cali-bration standards were used over the full range of interest, sample analyses were not reported beyond the range of the lowest and highest calibration standards, and most of the analytical measurement systems had control charts with acceptance criteria of 2 sigma. The Moni-toring Team also examined documentation for survey and counting in-strument calibrations in the Analytical and Radiological Control l
Laboratories.
Instrument calibration and control in both labora-tories were found to be excellent. Calibrations of instruments were performed using standards traceable to a national laboratory. At least three concentrations of standards were used for each cali-bra tion. Control standards were used each time the instrument was used in the analysis of samples. The analytical results obtained on these control standards, which were also traceable to a national laboratory, were plotted on control charts. The Monitoring Team also determined that maintenance was well documented for the instruments
o 4
used in each laboratory and that a new calibration curve was generated for each instrument following repair or adjustnent.
The measurement ~ systems reviewed by the Monitoring Team included the following:
a.
Assay 55-Gallon Radiological Waste Drums This system was used to assay all standard 55-gallon drums for various nuclides in order to determine the classification of low level waste. The instrument used was a segmented gamma scanner.
Three drums (called sources or standards) were prepared for the
. instrument calibration. Source A contained microcurie amounts of Am-241, Cd-109, Co-57, Ce-139, Hg-203, Sn-113, Sr-85, Cs-137, Y-88, and Co-60. Source B contained microcurie amounts of Cs-137 in a different concentration than Source A.
Source C contained no radionuclides and was used as a blank. All three sources contained a matrix which was similar to the samples (unknowns) measured with this system. Source A was also used as a control standard and was measured each day that the segmented gamma scanner was used.
If the Am-241 value fell within the 95 percent confidence interval of the known value, the system was considered operational, b.
Atomic Absorption for Metal This system was used to analyze for metals in surface water, saline water, domestic and industrial wastes.
Standard solutions of varying concentrations of the metals were used to calibrate the spectrophotometer. One standard solution was used as the control standard. Analysis results on this standard solution were plotted on a control chart. A control chart was established for each metal analyzed.
c.
Standard Test for Ammonia Nitrogen in Water This test was used to analyze water for ammonia-nitrogen content and would not measure the organic nitrogen content of the water.
Calibration of the specific-ion meter was accomplished by using a minimum of three standard solutions. The calibration curve
'was checked every three hours when a series of samples was analyzed.
b
5 d.
Dionex (Ion-Chromatography)
This analytical method was still under development and will be used to assay the chloride, fluoride, nitrate, nitrite, phosphate, and sulfate content of aqueous solutions.
Data and calibration curves were still being generated during this visit.
e.
Analyses for Gross Alpha and Gross Beta The Radiation Control Laboratory and the Analytical Laboratory analyze contamination smears, air, and liquid samples using either a Tennelec or Canberra proportional alpha-beta counter.
Sr/Y-90 and Pu-239 sources are used to check the instruments daily.
f.
Measurement for Gamma Radiation This measurement technique is used to identify and quantify the gamma radiation present in liquids, filters, and other solid samples. The gamma radiation present in B-25 boxes (low level waste packages) is also measured using this analytical method.
The gamma radiation measured is then correlated to the quantity of individual radionuclides present by means of a series of previously determined calibration curves.
Every six months, the detector, a collimated G-M tube equipped with a single channal analyzer, is calibrated with a Cs-137 source.
Calibration curves are generated for each geometry (type of container or sample) analyzed and the standards used for calibration are traceable to the National Bureau of Standards.
All radiation emitted from the B-25 boxes was assumed to be from the Cs-137 nuclide. The highest radiation dose obtained on each R-25 box measured was used to determine the radionuclide content of the box. Use of the highest dose measurement result in a conservative estimate of the radionuclide content of the box.
2.
Observations and Recommendations The following observations and/or recommendations were communicated to DOE and the contractor (WVNS) personnel in order to improve the measurement systems in use. The recommendations were adopted by the contractor and implementation was initiated while the Monitoring Team was onsite.
e.
6 a.
The contractor should use only approved analytical procedures to perform analyses. Currently, several analytical procedures (e.g. AC-8,14 and 17) were being used and were not approved by all required department heads. While the Monitoring Team was onsite, contractor personnel initiated actions to assure that all procedures in use were properly approved.
b.
A control chart for procedure AC-11 (Assay S5-gal. Radiological Waste Drums) should be generated to demonstrate trends and systematic biases. Contractor personnel immediately initiated actions to develop a control chart for this procedure.
c.
Calibration standard solur. ions and control standard solutions should be from different stock solutions and stored independent-
. ly of one another. Mainte.1ance of two standard stock solutions is required to provide an analytical cross check on the continu-ing quality of the stock solutions.
If only one stock solution is maintained, degradation of that stock solution is not dis-cernible. The contractor initiated action to procure an addi-tional standard solution from another stock.
d.
Data used to generate calibration curves and control charts should be maintained with the charts in the laboratory. This will expedite resolution of questions which may arise concerning the validity of the charts.
e.
The contractor should document actions taken to correct out-of-limit analytical results.
This will provide a record of the actions taken for future use and will also indicate the effectiveness of the laboratory's internal QA/QC program.
C.
West Valley Nuclear Services Environmental Monitoring Program 1.
Program Review The effectiveness of the contractor's (WVNS) enviconmental monitoring program was determined by review of records, discussions with DOE and WVNS personnel, independent measurements and observations made by the NRC Monitoring Team. The contractor's capability to accurately measure radioactive effluent releases was also verifled by examining the adequacy of equipment and calibration procedures. Quality Assurance audits of the environmental monitoring program were also examined and a series of independent environmental monitoring TLD stations were placed around the facility by the Monitoring Team.
The Monitoring Team determined that despite several constraints in the environmental laboratory (such as old gama spectrometry equipment, limited work areas and limited manpower available) good analytical results were being attained.
In addition the
7 environmental laboratory personnel who were interviewed by the Monitoring Team exhibited a good knowledge, expertise and understanding of environmental sample analysis processes and procedures.
The Monitoring Team examined the contractor's procedures, facilities and equipment for implementation of the environmental monitoring program.
It was noted that gross alpha, gross beta, tritium, gamma, and Sr-90 were analyzed on-site. Other radionuclides such as uranium isotopes, plutonium isotopes, and I-29 were analyzed off-site at vendor laboratories.
The Monitoring Team was not able to review the vendors' analytical procedures because the contractor did not maintain copies of those procedures on-site. The Monitoring Team recommended that copies of the vendors' laboratory procedures should be obtained, reviewed, approved and maintained current by the contractor as soon as possible.
Knowledge of the vendors' procedures is required to understand better the analytical results reported.
Procedures, facilities and equipment examined by the Monitoring Team included the following:
a.
Facilities and Equipment The contractor's environmental laboratories including the sample preparation room and counting room were examined. The counting equipment examined consisted of a gas flow proportional counter, a liquid scintillation counter, and an old, computer based, gamma spectroscopy system equipped with a ReGe detector and a shield. The laboratory was also equipped with two 48 inch laboratory hoods, a pH/ISE meter, a chemical balance, and a top loading balance. The sample preparation room was separated from the counting room to avoid possible cross-contamination.
On the basis of the above observations, it appears that the contractor only has limited capability to prepare and process samples containing radionuclides because of the old equipment and limited work space, b.
Gross Alpha and Beta Analysis One liter of well mixed liquid sample is evaporated to dryness on a hot plate. The residue is transferred to a tared planchet, weighed, and counted for alpha and beta activity using Procedure EM-12.
c.
Tritium Analysis Five milliliters of liquid sample is added to 20 ml of scintillation cocktail and the counted for tritium activity in accordance with draft Procedure EM-13. However, since this 4
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8 procedure was in draft form (i.e., had not been completed and through the review and approval process), the contractor personnel were analyzing these samples in accordance with the counting equipment manufacturer's instruction manual.
d.
Strontium-90 Analysis Strontium-90(Sr-90) is extracted from other radionuclides using one of the various chemical precipitation techniques specified in Procedure EM-15. Yttrium-90(Y-90), a daughter product of Sr-90, is separated by iron hydroxide precipitation and the Sr-90 is converted to strontium oxalate. The strontium oxalate is counted within 140 minutes of the Y-90 separation, using a gas flow proportional counter.
e.
Isotopic Gamma Analysis Samples of various types (liquid, vegetation, soil, etc.) are prepared in accordance with the procedures specified in procedure EM-14. The samples are analyzed using the gamma spectrometer.
The Monitoring Team reviewed the calibration data and noted that WVNS used multiple gamma sources to determine the counting efficiency (from Cd-109 to Y-88). However, it was noted that the quantity of Am-241 in a sample was not being determined, since the calibration curve established for the gamma spectrometer did not cover the lower energy spectra associated with the Am-241 peak. As a result, the Monitoring Team recommended that the contractor include analysis of Am-241 as part of the calibration curve, so that the Am-241 activity in the environmental samples could be quantified. Based on the prior fuel processing history of this facility, Am-241 could be present in environmental samples.
f.
Environmental Laboratory QA/QC Procedures The environmental laboratory quality assurance requirements are specified in procedure EM-101.
In addition, each of the environmental measurement procedures specify quality control requirements specific to that activity (e.g., reagent preparation and control and preparation of background count rate control charts). The Monitoring Team noted that the contractor maintained an acceptable environmental laboratory quality assurance program, but improvements to the quality control program were recommended as follows:
1) establish daily (or prior to use) source check and background count control charts for all measuring equipment, a.
9 2) add known amounts of individual isotopes into the quality control samples and compare positive results.
g.
Confirmatory Measurements During this visit, liquid effluent and environmental samples were obtained by the Monitoring Team and split with the contractor (WVNS) for independent analyses. Thesamples(4) were obtained from onsite lagoon No. 2 (process liquid collection lagoon), onsite lagoon No. 3 (decontaminated liquid discharge lagoon), Cattaraugues Creek (downstream from the site discharge), and Buttermilk Creek (upstream from the site discharge). The NRC samples were sent to the NRC reference laboratory, DOE Radiological and Environmental Sciences Laboratory (RESL) located in Idaho Falls, Idaho. The contractor's samples were analyzed at the West Valley site.
The analyses to be performed include: gross alpha, gross beta, tritium, Sr-90 and a gamma scan. Samples indicating gross alpha in excess of 15 pCi/ liter were further analyzed for uranium and plutonium isotopes. The analytical results of these analyses are tabulated in the attached Appendix 1.
Comparison of the NRC and contractnr (WVNS) analytical results indicated reasonable to good agreement (i 1 to 50%) considering the low levels of activity detected.
It was observed that the radioisotopes detected in the process liquid collection lagoon (Lagoon 2) met the NRC and/or DOE limits for release to unre-stricted areas except for gross alpha, gross beta, Sr-90, Cs-137, and U-232.
Following treatment of the process liquid, all radioisotopes detected (Lagoon 3) met the NRC and 00E limits for release to unrestricted areas. The concentrations approach about 95 percent of the limiting values in Table II, Column 2 of 10 CFR Part 20 by the sum of the ratios procedure described in the footnote to Appendix B.
The liquid discharges from Lagoon 3 are infrequent.
It is noted that the gross alpha value in Cattaraugus Creek (at the site boundary) was about 0.5% of the limit. The facility Technical Specifications (T.S. 4.2) require that radio-isotopic concentration in liquid discharges measured at Cattaraugus Creek, shall be less than 2 times the NRC/ DOE limits shown in Appendix 1 as long as the average concentrations over the period of one year are less than the limits shown. As shown above the gross alpha concentration at the site boundary was determined by the NRC Monitoring Team to be about 0.5% of the limit.
h..
Plant Ventilation Exhaust Stack Samplers and Monitors The Monitoring Team examined procedure 50P 15-11 which describes the operating instructions and actions required to properly operate the plant ventilation exhaust stack samplers and monitors. The stack monitor and sampler equipment is housed in o
i 10 an eight-foot by eight-foot insulated building at the south side of the main plant stack base on the Ventilation Exhaust Cell roof. An air sample is continuously drawn via oiless vacuum pumps located in the shelter from two isokinetic multi-nozzle probes, installed at the 80-foot level, in the stack. The sample is transported approximately 80 feet down two stainless' steel heat-traced sample lines to the sampler and monitoring instrumentation.
Flow monitors in both the sampling stream and the monitoring stream indicate the sampling rate, and actuate back-up pumps if the flow rate drops below a preset value. The sample passes through a particulate filter and charcoal cart-ridge before exiting the system. The monitor stream, which is wyed into the on-line and stand-by units, is again split into the separate alpha and beta particulate monitors. One pair of alpha and beta instruments is on line at any given time. During examination of the equipment, the Monitoring Team noted that there were a total of 13 bends in the two stainless steel sample lines leading from the 80-foot level of the stack to the sampler and monitoring instrumentation. Although each bend in the lines was curved sufficiently to preclude extensive particulate holdup, the correlation between the activity released to the environment from the stack and the activity recorded by the stack samplers / monitors could be affected. The contractor apparently had previously attempted to determine this correla-tion, however, the result of these tests were inconclusive.
Therefore, the Monitoring Team recomended that the contractor conduct tests of the stack sampler / monitoring system prior to hot operation of the Project to assure that the measurement of activity in the exhaust air is accurate or conservative. These tests should measure the stack sampler to sampler / monitor line losses.
2.
Observations and Recommendations The following observations and/or recomendations were comunicated to DOE and contractor (WVNS) personnel it an effort to improve the environmental monitoring program. The recommendations made by the Monitoring Team were imediately adopted and implementation was initiated by the contractor, a.
The contractor should establish alpha and beta self absorption curves because the actual activity of the sample cannot be calculated due to the high residual weight obtained from the quantity of liquid analyzed (one liter).
b.
During calibration of the proportienal counters, the high voltage should be increased at smaller increments (currently 50 volt increments) in order to more accurately define the position of the plateau.
f.
L
11 c.
During analyses, both standard and blank (background) samples should be analyzed along with each batch of environmental samples in order to establish the precision and accuracy of the
- analyses, d.
Prior to analysis of lagoon water samples (lagoon 2 and 3) for' tritium, the samples should be distilled to avoid potential problems caused by color and chemical quenching, contribution of other beta emitters, and chemiluminescence.
e.
During analysis of environmental samples for tritium, instead of using the instrument counting efficiency for a three month period, the counting efficiency should be determined each time samples are analyzed in order to assure that corrections are cade for the decay of the standard samples, f.
The strontium carrier calibration procedure using the atomic absorption technique for analysis should be written, reviewed and approved. The strontium carrier calibration frequency and shelf life should be specified in this procedure. Currently, analyses of strontium are being conducted using the atomic absorption instrument in accordance with the instrument manufacturer's instructions, g.
A trace amount of stable strontium should be added to the secondary standard solution in order to keep the radiostrontium in solution.
h.
The previously established Sr-90 self-absorption curve should be reevaluated since it was noted that this curve had an excessively wide error band, i.
Strontium-90 activity in environmental samples should be recounted two weeks after the initial count. This recount will verify the initial Sr-90 determination since Y-90 should be in equilibrium with Sr-90 after the two week period.
J.
Control charts should be established for the proportional counter, liquid scintillation counter and gamma spectroneter used in the environmental laboratory.
D.
Environmental Monitoring Program Quality Assurance Audits 1.
WVNS Internal Audits The Monitoring Team examined contractor (WVNS) records of internal audits of the environmental monitoring program conducted by the WVNS Quality Assurance Department. Audits of this program were conducted annually between September,1982 and January,1985. The audits covered implementation of the Environmental Safety and Health Program o
12 Plan (WVDP-001) and compliance with established procedures.
Corrective actions have been completed on all adverse findings and recommendations identified during these audits.
2.
WVNS External Audits The Monitoring Team examined contractor (WVNS) records of external audits conducted by the WVNS Quality Assurance Department on the environmental monitoring program.
External audits are required since the environmental monitoring prog"am at the West Valley Demonstration Project site is controlled by the Dames and Moore, Chicago, Illinois office, in conjunction with WVNS West Valley personnel. Three audits of the environmental monitoring program administration activities performed by Dames and Moore were conducted between December, 1983 and August, 1985. The activities audited included proper use of computer programs, training programs, instrument calibration records, and Dames and Moore surveillance activities. Corrective actions have been completed on all adverse findings and recommendations identified.
3.
DOE - Idaho Audits Audits of the West Valley Demonstration Project Environmental Moni-toring Program were conducted by DOE - Idaho and DOE - Headquarters personnel during May, 1983, and May, 1985. Effluent and environ-mental monitos ing activities at the site were reviewed for compliance witt DOE requirements, specifically DOE and ID Order 5480.1, Chapter XII and 5484.1, Chapter III. The results of these audits indicated that "WVNS has made continuing improvements to the monitoring program since assuming responsibility for the site" (in February,1982).
Several areas for improvement of the monitoring program were iden-tified during the May,1985 audit.
These included assurance that program plans are reviewed annually and that the quality assurance program for environmental samples was operating properly. Corrective actions on the items identified had been initiated but not completed prior to this monitoring visit.
E.
Environmental TLD Program The contractor's (WVNS) environmental monitoring program has been enhanced
+hrough the placement of thermolurainescent dosimeters (TLD's) on and around the West Valley Demonstration project site. The Monitoring Team examined this program in detail and established independent TLD stations on and around the site.
In general, the Monitoring Team determined that the environmental TLD program established by the contractor was sound and good techniques were used to assure proper calibration and quality control of the TLD chips.
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P 33 1.
WVMS TLD Program The environmental TLDs placed on and around the site are used to i
measure ambient and background radiation in the vicinity of the site.
The environmental TLD package placed at each location consisted of five thermoluminescent chips (Harshaw TL-700 LiF, supplied by the '
DOE ~- Radiological and Environmental Services Laboratory (RESL))
laminated in a thick card. Each card was stamped with an j
identification code which identified the location of placement. The TLD packages are collected and analyzed quarterly. Analyses are i
conducted onsite by MVNS personnel. During July and August 1985, WVNS personnel performed a comparison study between high pressure ion chamber measurements and TLD measurements placed at the same locations. The results of this comparison indicated excellent l~
agreement between the two measurements (average ratio = 1.009).
l' -
During examination of the WVMS environmental TLD program, the Monitoring Team noted that tests of the TLDs identified in ANSI Standard N545-1975 had not been performed by the contractor prior to use of the Harshaw TL-700 chips. These tests are required to understand the behavior. of the TL-700 chips. Therefore, the Monitoring Team recomended that the contractor should either conduct the tests or obtain the test results from DOE-RESL for review.
- 2. ' NRC TLD Program Prior to this monitoring visit, the NRC decided to place NPC TLDs around the West Valley site as an independent overcheck. These TLDs j
will be analyzed periodically and compared with the contractor's resul ts. During this monitoring visit a total of twelve TLDs t
(calcium sulfate - Tm) were placed on and around the site at the locations described in Appendix 2.
Several of the NRC TLDs are co-located with either WVMS or New York State TLDs or both. The NRC TLDs will be collected quarterly by New York State personnel, sent to j
the NRC and analyzed in the NRC Region I laboratory.
Shown in Appendix 3 are the TLD Monitoring results for the TLDs placed on and around the West Valley site for the period September 26, 1985 to January 22, 1986. The column identified as Net Exposure Rate gives the exposure in millf rem per 90 day period as adjusted from the gross exposure values. Stations 10, 11 and 12 are located l
onsite and were expected to have somewhat higher exposure rates.
L The value for Station 11, 2404 millirem /90 days was higher than expected but is similar in value to the TLDs placed in the area by the DOE contractor (WVMS). According to contractor personnel, the high value was caused by radiation from a radioactive material storage building which was located within 100 yards of the fenceline.
The contractor identified the unexpectedly high values during December 1985, imediately ordered additional shielding for the storage building and completed installation of the shielding during ta i
I
14 the week of February 17, 1986. Station No. 9, also found to be somewhat elevated, was located just outside the West Valley site.
7 This elevated radiation level was also caused by proximity to the storage building. Although somewhat elevated, the radiation level at Station 9 was still well within the E00 millirem per year limit for exposure to the public. Additional shielding around the
- storage building should reduce the radiation level at Station No. 9 to about background levels.
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1.441C.10i-7 2 E-6 2 E-6 Th-110 3 s 2 E-9
~-
2 E-6 2 E-6 Th-232 3 2 2 E-9
-~
0-132 2.4810.07E-6
- E-5 8 E-7 3.5020.10E-7 3.9620.5 F-7 3 E-1 4E6 i
0-134/*23 1.11to.04E-t 1.63to.C5E-7 1.8220.3 E-7
-~
3 E-1 4 E-0 l
U-235 L 5
- 3.45 6 5.3 r 0.EE-9 e.1920.7 E-9
~.
4 E-5 6 E-7 0-238 2.4720.142-1 3.9 2 0.2E-4 3.3 2 0. 5 E-E
- Lagoon 214.44 is g;$ released to the e.$cirnet.ent. prf o'r to treatze-t (1) NRC IC CF7 23 Apper*,ta S Tonle U liatts pravf deo for enspartsan only (2) NEC uncerteln'y valuu a
- 1 s1W; %"A$ uncertainty valuas a 2 2 sigsa (3) ocE/ wies limits an,1y to tne site toursary (u,restricte tree) resuits anc est to tsann 2 or 3 re.utts
]
APFENDIX 2 NRC TLD DIRECT RADIATION ENVIRONMFNTAL MONITGRING LOCA110NS AT WCS1 VALLEY STA.
D16T(m )
D!R DESCRIPTION T
40
' 350 5prir.gvi11 R owntown M.ing let 2
f.3 144
. Pine c1TTFRd, West valley (utility
~
PoleAAD3)
T
. l.5,
~
' 92 Heinz Road at the Site Boundary
~
~
4 1.?
51 7effer Farm, Route 240 5
2.1 ID Emerson Farm, Thomas Corner Rd.
T 1.7 319 Rock Spring and Dutch Hill Rd.
7 1.2 262 Outch Hill & ' Head Row (lltility Pole 20)
~
8 1.4
' 234 Outch iiill & Pine (Utility Pole 78)
T 0,3 300 Rock Spring at Quarry Creek 10 on-site 43 Switch Gear Fence 11 cn-site 334 BWE fence Line (about 107TTrom i
~
the Fence) 12 on-s'ite
^
83 Utility Ditch at Security Fence
+
r g.3 5
,j 7 ev y r,, -
' i/.
t APPENDIX 3 TLD DIREC1 RADIATION ENVIRONMENTAL MONITORING RESULTS For the Period: 9/26/85 - 1/22/86, 118 Days Field Time:
104 Days Gross NET Exposure Rate STA.
TLD DIST(mi)
DIR Exposure (mR) mR/90 Days 1
3101 4.0 350 TLD MISSING Z
3102 3.6 144 21.5 2 0.4; 3.2*
17.6 1 0.4; 3.9*
3 3103 1.5 92 26.810.5;4.0 22.2 1 0.5; 4.4 4
3104 1.2 51 20.4 1 0.2; 3.1 19.2 1 0.3; 3.9 5
3105 2.1 10 25.6 1 0.1; 3.8 21.1 1 0.3; 4.3 6.
1106
._l. 7 319 23.2 2 0.4; 3.5 19.0 2 0.4; 3.9
?
r,
~
22.2 1 0.6; 3.3 18.2 1 0.6; 4.0 7
,;' 31D7 '_
1.2 262 3108 1.4 234 22.7 1 0.2; 3.4 18.6 2 0.3; 4.0 8
4 9,
3109 0.3 50'0 66.0 1 4.6; 9.9 56.1 2 4.0; 9.0 p., -
10 ij 3110 on-site (3
43.2 1 0.2; 6.5 36.3 1 0.3; 6.3 11 l,,,311 f-~
on-site 334 2779 1 159; 417 2404 i 138; 361 l
l Y2
-~3112 on-site
~83 116.8 1 8.8; 17.5 100.0 1 7.6; 1574~
l Transtt Dose:
1.2 1 0.3; 3.2 l
l i
- Me)asurement = Random Error; Systeaatic Error t
4 I
l i
Cf
'I.
i5
['
I l
i l
~
NiinWS ^Hf',ycle Mstdd FCUF
,,V...,--
. nee gw.
,..u....
b Y
y y
I!'-
.'M.m.3E Olho. _.
PDR LPDR _._
Ef. x~o.,so -- j na,.
n SS 398
.