IR 05000309/1988008
| ML20196C199 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/13/1988 |
| From: | Kirkwood A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20196C197 | List: |
| References | |
| 50-309-88-08, 50-309-88-8, NUDOCS 8807010031 | |
| Download: ML20196C199 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-309/88-08 Docket No.
50-309 License No. OPR-36 Priority Category C
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' Licensee: Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Facility Name: Maine Yankee Atomic Power Station
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Inspection At: Wiscasset,- Maine Inspection Conducted:
May 16-20, 1988
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Inspectors d.N'
/M/Sr0 6 -/3 - G 8 ri A. Kirkwood,4didia' ion Specialist date t
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.date 6 -/P B G J. Kottan, Rad 14 n Laboratory Specialist
. Approved by:
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W.'Tasciak, Chief
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i l-Effluents Radiation Protection Section Inspection Summary:
Inspection on May 16-20, 1988 (Report No. 50-309/88-08)
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+1 Areas Inspected:
Routine, unannounced inspection of: (1) the licensee's radio-chemical measurements program using the NRC:I Mobile Radiological Measurements Laboratory and laboratory assistance provided by the Department of Energy,
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i Radiological and Environmental Sciences Laboratory; and (2) the licensee's whole body counting facility.
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Areas' reviewed included :
Licensee action on previous findings, confirmatory l
measurements, audits, chemistry organization and staffing, and whole body counting.
l Results: With the areas inspected, no violations were identified.
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8807010031 880620 (
PDR ADOCK 05000309 O
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DETAILS 1.
Individuals Contacted 1.1 Principal Licensee Employees
- P. Radsky, Chemistry Section Head
- L. Thornburg, Systems Chemist
- R. Crushy, Licensing
- L. Lawson, Quality Programs Section Head
- J. Brinkler, Assistant Plant Manager
- E. Boulette, Plant Manager D. Day, Radiation Controls Assistant G. Pillsbury, Radiation Controls Section Head P. Dostie, Lead. Plant Specialist J. Stevens, Senior Chemist The inspector also talked with and interviewed other licensee chemistry and radiaton controls individuals.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Inspector Follow-up Item (50-309/85-21-01):
Bias in gamma spectroscopy instrument QC data.
The inspector reviewed the licensee's
- gamma spectrometry QC program. This program consists of daily source, resolution, and gain checks of the gamma spectrometers. The licensee does not plot the data obtained from the checks on control charts, but rather uses vendor supplied software which determines if the values are within plus or minus ten percent. The inspector discussed the use of control charts with the licensee noting that the licensee maintains control charts for the liquid scintillation counter, the gas flow proportional counter, and the gross gamma counter.
The licensee acknowledged the value of control charts and stated that controls charts would be implemented and maintained for the gamma spectrometry system.
The item will remain open until the control charts are in use for the gamma spectrometry system.
(Closed) Inspector Follow-up Item (50-309/85-21-02):
Intercomparison of gas in 33 ml bulb. During this inspection actual effluent gas samples were split between the licensee and the NRC using the 33 ml gas bulb counting geometry. The results were in agreement.
This item is closed.
See Section 3.
3.
Confirmatory Measurements
.3.1 Split Samples During this part of the inspection, liquid, airborne particulate (filter) and iodine (charcoal cartridge), and gas samples were split
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3-between the licensee and the NRC for the purpose of intercomparison.
Where possible', the split samples are actual effluent samples.or inplant samples which duplicate counting geometries used by the
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The samples were analyzed by.
the' licensee using normal methods and equipment, and by the NRC:I Mobile Radiological Measurements Laboratory. Joint analyses of
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effluent samples are used to verify the licensee's capability to measure radioactivity in effluent samples with respect to Technical Specifications and other regulatory requirements.
In addition, a liquid effluent sample was sent to the NRC reference laboratory, Department of Energy, Radiological and Environmental Sciences Laboratory (RESL) for analyses requiring wet chemistry. The analyses to be performed on the sample are:
Sr-89, Sr-90, Fe-55, gross alpha, and tritium. The results will be compared with the licensee's results when received at a later date and will be documented in a subsequent inspection report.
The results of the sample measurements comparison indicated that all of the measurements were in agreement under the criteria used for
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comparing results (see Attachment 1 ) with two exceptions. The Cs-134 value in a liquid sample was in disagreement when the 605 kev photopeak was used for quantifing the results. When the 795 kev photopeak was used for quantifying results the measurements were in
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agreement. The licensee stated stated that the 795 kev photopeak would be used in future measurements to quantify Cs-134. A review of the licensee's interlab QC data also indicated low, although accept-able, Cs-134 results in a recent intercomparison.
The other result disagreement was I-132 on a particulate filter.
The licensee counts the particulate filter on the detector face. This results in a significant (greater than 10%) loss of counts for the I-132 667 kev photopeak due to angular correlation summing.
The inspector discussed this as well as other problems associated with counting filters on l
the face of the detector with the licensee, and the licensee stated l
that, in the future, particulate filter samples would not be counted directly on the face of the detector.
In addition, the inspector noted that the Xe-133 results on detector two for the 33 m1 gas bulb counting geometry were higher than the NRC result and also the l
licensee's result for the same sample on detector three.
The licensee stated that detector two would not be used for the gas bulb counting geometry.
The licensee further stated that resolution problems were l
being experienced with detector two, and this detector would be sent
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back to the vendor within several weeks for refurbishment.
The I
results of the comparisons are listed in Table 1.
3.2 Laboratory QA/QC The inspector reviewed the licensee's radio-analytical measurements QA/QC program.
The QA/QC program is contained in two procedures:
Procedure 7-02-01, Chemistry Quality Assurance / Quality Control Program, and Procedure 7.201, Operational Quality Control Checks of
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4 Laboratory Instruments. Procedure 7-02-01 addresses instrument calibrations;. twining / retraining; intra-laboratory and inter-laboratory sr.iled, split, and duplicate samples; and acceptance criteria for the intra laboratory and inter laboratory programs.
Procedure 7.261 requires daily gain, efficiency and resolution checks for the-gamma spectrometry system; daily standards and backgrounds for all other counting systems including plotting the results on control charts; and calibrations every two years.
The inspector reviewed selected 1987 and 1988 QC data and noted that the licensee was implementing the procedural requirements of the laboratory QA/QC program.
The inspector noted that the licensee
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does not use control charts for the gamma spectrometer system daily QC data, but rather a plus or minus ten percent limit.
The inspector discussed this practice with the licensee, and the licensee stated that control charts would be implemented for the ga,ama spectrometry
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system. The licensee participates in an interlaboratory spike sample program administered by the Yankee Laboratory on a quarterly basis.
This appears to be an excellent interleboratory program and a noted strength of the licensee's laboratory QC p-egram.
The inspector stated that the items discussed above:
the use of the 795 kev photopeak for Cs-134 quantification, moving samples away from the detector face for analyses and refurbishing detector two would be reviewed during a subsequent inspection (50-309/88-08-01).
4.
Audits The inspector reviewed licensee Quality Assurance audits of the chemistry program. Audit-MY-86-02, performed April 28-May 2, 1986 covered the chemistry department chemical and radiochemical activities and Technical Specification requirements. Audit MY-87-02, performed September 28, October 2, 1987 coverad the chemistry department activities including implementation of the Radiological Effluent Technical Specifications-(RETS). The inspector also reviewed the 1988 QA audit schedule and noted that an audit of chemistry department activities was scheduled for 1988.
The inspector observed that the audits appeared to be quite thorough.
Technical Specialists were members of the audit teams. The inclusion of the Technical Specialists appears to have resulted in audit findings which were of excellent technical depth,ufficient to permit assessment of the capabilities and performance of the areas being audited.
5.
Chemistry Organization and Staffing The inspector reviewed the organization and staffing for management control and adequate personnel to administer the chemistry program. The chemistry group is part of the Technica! Support Department.
The Chemistry Section Head reports to the Manager, Technical Support Department.
Under the Chemistry Section Head are four professional level positions:
Senior Chemist, Systems Chemist, Analytic Chemist, and
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Chemistry Specialist.
Reporting to the Senior Chemist are two Laboratory Assistants and one Chemistry / Radiation Cont *)1 technican.
Although the organization appears adequate to administer the chemistry program, two po,itions, Analytic Chemist and Chemistry G;acialist, are currently vacant.
The litansee stated that the Analytic Chemist position should be filled during the summer of 1988.
6.
Whole Body Counting This part of the inspection assessed the capability of the licensee to adequately perform radiological bioassay using a whole body counting system. A whole body counting phantom containing radioactive sources traceable to the National Bureau of Standards (NBS) was submitted to the licensee for analysis.
the phantom duplicated the nuclides and the organ burdens that the licensee might encounter during normal operation, the phantom was. analyzed using the licensee's routine methods and equipment.
6.1 Comparison of Results The licensee's whole body counting system consists of two shielded chairs with aach chair containing a 3' x 3' NaI(T1) detector for body
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counting and a 1.5' x 0.5' Nal (TI) detector for thyroid counting.
The detectors are coupled to a multichannel analyzer which is interfaced to a computer. The system softwv.e is supplied by a vendor.
The comparison of results for the lung are based on an average of five measurements and the GI tract results are based on an average of two messurements.
Based on.these results, no violations were identified in this area.
Results of the comparison are listed in Table II.
The phantom was first submitted to the licensee with the sources in the lungs. With the detector in the whole body counting position no radioactivity was detected. The whole body counting position is used for routine counting. The lung results of Table II were obtained during the lung counting position.
The GI tract results were obtained using the whole body counting position.
The inspector discussed with the licensee the failure of the whole body counter to detect the radioactivity in the lungs with the detector in the routine counting position.
The licensee stated that this area would be reviewed and evaluated in order to ensure that the radioactivity in the lung would be detected during routine whole body counting.
The inspector stated that this area would be reviewed during a subsequent inspection.
(50-390/88-08-02).
During the remainder of the inspec-tion the licensee ran several tests using the NRC phantom.
The results of these tests indicated that activity in either the lung or
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GI tract was readily detected with the whole body counter in the scan counting position.
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/l 6.2 Procedures and Data
/l The following procedures for operation and calibration of the whole
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body counting system were reviewed:
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Procedue No. 9.334, Calibration of the Whole Body Counter
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Procedue No. 9.1.26, Whole Body Counting
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The procedures include periodic source and background checks, and
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the maintenance of control charts to trend changes in detector response and background respectively. Annual calibrations are I
performed with semiannual calibration checks with acceptance criteria.
The inspector reviewed selected 1988 QC data.
The inspector discussed the construction and use of control charts with the licensee, and also provideC a copy of a publication to the licensee which discusses the use of control charts. Within the scope of this review, no violations were identified.
7.
Exit Interview The inspector met with the licensee representatives (denoted in Section 1)
at the conclusion of the inspection on May 20, 1988.
Th; inspector summarized the scope and findine s of the inspection.
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TABLE I Maine Yankee Atomic Power Station Verification Test Results Sample Isotope NRC Value Licensee Value Comparison Results in Microcuries per Milliliter Containment Xe-133 (1.91 0.02)E-4 (2.31 0.07)E-4 Agreement Gas Xe-135 (5.3 0.6)E-6 (5.0 0.4)E-6 Agreement 1200 hrs 5-19-88 Detector 2
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(33 ml counting geometry)
Containment Gas Xe-133 (1.91 0.02)E-4 (2.0 0.2)E-4 Agreement 1200 hrs Xe-135 (5.3 0.6)E-6 (5.4 0.8)E-6 Agreement 5-19-88 Detector 3 (33 ml counting geometry)
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TABLE I (continued)
Maine Yankee Atomic Power Station Verification Test Results Sample Isotope NRC Value Licensee Value Camparison Results in Microcuries per Milliliter Containment Gas Xe-133 (2.622 0.009)E-4 (2.9 0.3)E-4 Agreement 1230 hrs Xe-133m (3.0 0.3)E-6 (2.9 0.6)E-6 Agreement 5-19-88 Xe-135 (7.03 0.11)E-6 (7.3 0.7)E-6 Agreement Detector 2 (Marinelli beaker
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counting geometry)
Containment Gas Xe-133 (2.622 0.009)E-4 (2.8 0.3)E-4 Agreement 1230 hrs Xe-133m (3.0 0.3)E-6 (2.8 0.4)E-6 Agreement 5-19-88 Xe-135 (7.03 0.11)E-6 (7.3 0.7)E-6 Agreement Detector 3 (Marineili beaker counting geometry)
Test Tank Ag-110m (7.2 0.4)E-7 (5.9 0.8)E-7 Agreement 1345 hrs Co-60 (5.2 0.5)E-7 (6.1 1.2)E-7 Agreement
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Q TABLE I (continued)
Maine Yankee Atomic Power Station Verification Test Results Sample Isotope NRC Value Licensee Value Comparison Results in Microcuries per Milliliter PC Coolant I-131 (7.4 0.5)E-7 (6.2 0.7)E-7 Agreement 0800 hrs 1-133 ( 1. 0 b 15)E-6 (1.01 0.11)E-6 Agreement 5-18-88 Cs-134 (1.40:0.08)E-6 (9.0 1.0)E-7 Disagreement Detector 2
- (1,18 0.12)E-6 Agreement Cs-137 (2.39 0.08)E-6 (2.4 0.2)E-6 Agreement PC Coolant I-131 (7.4 0.5)E-7 (5.1 0.7)E-7 Agreement 0800 hrs I-133 (1.03 0.05)E-6 (8.17 0.14)E-7 Agreement 5-18-88 Cs-134 (1,40 0.08)E-6 (1.16 0.14)E-6 Agreement
- (1.24 0.14)E-6 Detector 3 Cs-137 (2.39 0.08)E-6 (2.0 0.2)E-6 Agreement Reactor I-131 (5.6 0.3)E-3 (5.6 0.5)E-3 Agreement Coolant I-132 (3.84 0.08)E-2 (3.7 0.3)E-2 Agreement 1321 hrs I-133 (6.06 0.05)E-2 (5.8 0.5)E-2 Agreement 5-18-88 I-134 (1.1 0.2)E-2 (8.6 1.0)E-3 Agreement Detector 2 1-135 (9.8 0.2)E-2 (9.0 0.6)E-2 Agreement
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Recalculated value using 795 kev photopeak
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TABLE I (continued)
Maine Yankee Atomic Power Station Verification Test Results Sample Isotope NRC Value Licensee Value Comparison Results in Microcuries per Milliliter Containment I-131 (5.3 0.3)E-10 (4.8 0.3)E-10 Agreement Charcoal Cartridge I-133 (1,14 0.06)E-9 (9.1 0.5)E-10 Agreement 5-18-88 Detector 3 Reactor I-131 (1.41 0.13)E-3 (1.22 0.13)E-3 Agreement Coolant Filter I-132 (1.25 0.05)E-2 (9.0 0.7)E-3 Disagreement 1200 hrs I-133 (1.35 0.03)E-2 (1.24 0.12)E-2 Agreement 5-19-88 I-135 (2.36 0.14)E-2 (2.1 0.2)E-2 Agreement Detector 3 Na-24 (2.9 0.3)E-3 (2.4 0.2)E-3 Agreement Reactor I-131 (1.41 0.13)E-3 (1,14 0.05)E-3 Agreement Coolant Filter I-132 (1.25 0.05)E-2 (9.2 0.3)E-3 Disagreement 1200 hrs I-133 (1.35 0.03)E-2 (1.29 0.03)E-2 Agreement 5-19-88 I-135 (2.36 0.14)E-2 (2.21 0.07)E-2 Agreement Detector 2 Na-24 (2.9 0.3)E-3 (2.92 0.13)E-3 Agreement
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TABLE II
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WHOLE BODY COUNTING PHANTOM TEST RESULTS NRC Licensee *
Ratio Isotope Organ Known Value *
Result (Licensee:NRC)
Results From Chair Number One Co-60(1173 kev)
Lung 57 7 50 5 0.8810.14 Co-60(1332 kev)
Lung 57 7 50 3 0.8810.12 Cs-137 Lung 90 12 83.4 1.1 0.9310.13 Co-60(1173 kev)
G1 tract 51 6 147 7 2.9 0.4 Co-60(1132 kev)
GI tract 51 6 144 4 2.8 0.3 Cs-137 GI tract 81 11 202 13 2.5 0.2 Results From Chair Number Two Co-60(1173 kev)
Lung 57 7 58 3 1.0210.14 Co-60(1332 kev)
Lung 5717 59.6 1.1 1.05 0.13 Cs-137 Lung 90 12 99 3 1.10 0.15
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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS
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'Ulis attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an' empirical relationship which combines prior experience and the accuracy:needs of this program.
In these criteria, the judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value-to its associated uncertainty. As that ratio, referred to in this program as "Resolution",
increases the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.
Resolution Ratio For Agreement 2
<3 0.4 - 2.5
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'0.5 - 2.0
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0.6 - 1,66
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50 0.75 - 1.33
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200 0.80 - 1.25
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>200 0.85 - 1.18 1Resolution = (NRC Reference Value/ Reference Value Uncertainty)
2 Ratio = (License Value/NRC Reference Value)
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