IR 05000333/1981008
| ML20011A360 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/09/1981 |
| From: | Bores R, Jang J, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20011A354 | List: |
| References | |
| 50-333-81-08, 50-333-81-8, NUDOCS 8110090353 | |
| Download: ML20011A360 (7) | |
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U. S. NUCLEAR REGULATORY-COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
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Report No.
50-333/81-08 Docket'No.
50-333 License No. DPR-59-Priority Category C
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Licensee:
Power Authority of. the State of New York 10 Columbus Circle New York, New York' 10019 Facility Name:
James A. FitzPattick Nuclear Power Plant Inspection At:
Scriba, New York Inspection Conducted:
March 25-27, 1981 Inspectors: 7
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J. J. Kottan Radiation Laboratory Specialist date'
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C.Jang,RpationSpecialist date
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date Approved b : b, (I -
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R. J. Bores,' Chief, Independent Measurements date
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and Environmental Protection Section Inspection Summary:
Inspection on March 25-27, 1981 (Report No. 50-333/81-08)
Areas Inspected: Routine, unannounced inspection of the licensee's chemical and radiochemical measurements program uslng NRC:I Mobile Radiological Measure-ments_ Laboratory..and labortory assistance provided by DOE Radiological and Environmental Services Laboratory. Areas reviewed included:
program for quality control of analytical measurements, audit results, performance on radiological analyses of split actual effluent samples, and effluent control records and procedures. The inspection involved 40 inspector-hours onsite by two NRC region based inspectors.
Results: Of the four areas inspected, no items of noncompliance were identified.
Region I Form 12 (Rev. April 1977)
8110090353 810910
' PDR ADOCK 05000333
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DETAILS
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' Persons Contacted
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Principal Licensee Employees
- R..Pasternak, Resident Manager
- V. Childs, Assistant Resident Manager
- E. Mulcahey, Radiological and Environmental-Services Superintendent
- A.-McKeen, Assistant Radiological and Environmental Services Superintendent
- B. Gorman, Environmental-Supervisor
- P. Smalley, Senior Radiation and Environmental Technician
'*D. Zimmerman, Senior Radiation and Environmental Technician M. Cosgrove, QA Superintendent E. Salvetti, Radiation'and Environmental' Technician B. Abbotts, Radiation and Environmental Technician The inspector also interviewed other licensee employees including members of the chemistry and health physics staffs.
- denotes those present at the exit interview.
2.
-Laboratory QC Program
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The inspector reviewed the licensee's program for the quality control of analytical amea'surements. The licensee's QC program is detailed in'the Radiological and Environmental Service Department QA/QC Program.
The
program includes the frequency of the calibration, source check and back-
. ground checks of the different radiation measurement detectors and monitors. The licensee's QC program also includes a radiological and non-radiological program for split, spiked, auplicate, and
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interlaboratory QC sample analyses.
The inspector reviewed the implementation of the licensee's QC program and noted the licensee was
following the QC sample analyses and equipment check schedules.
The inspector noted the results of chemical analyses and equipment checks were reviewed and acknowledged by the Radiological and Environmental Services Superintendent as required.
No items of noncompliance were identified.
3.
Audit Results
'The inspector determined that the licensee's effluent monitoring program was-on the Corporate QA Audit list. The inspector reviewed the PASNY
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QA/QC Audit File 4.0.6.
The last Corporate QA/QC Audit which was i
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. performedlin the effluent monitoring. area was dated March 17 and 18, 1981 and otherf items were scheduled for 1901.
The inspector had no further questior; in this area.
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Confirmatory Measurements -
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During the inspection,. actual ' liquid and gaseous effluent samples were split between the licensee and NRC:I for the purpose of intercomparison.
-The-eff kcnt. samples were analyzed by the licensee using his normal methods and equipment, and the NRC using the NRC:I Mobile Radiological Measurements Laboratory. Joint analyses of actual effluent u yles determine the icensee's capabilility to measure radioactiv.. in effluent samples.
'In addition, a liquid effluent sample was sent to the NRC reference
' laboratory, Department of Energy, Radiological and Environmental-Services Labortory (RESL), for analyses requiring wet chemistry. The analyses to be performed on the samples are:
Sr-89, Sr-90, gross alpha, gross beta and tritium.
These 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 comparison of the licensee's measurements with those of the NRC indicated that,iise of the measurements were in agreement or possible acreement under the criteria used by tha Office of Inspection and Enforcement for comparing test results (see Attachment 1), and two p
measurements were in disagreement.
The two measurements in' disagreement were I-131 analyses of charcoal cartridges using face loaded geometries.
The inspector noted that the licensee used a face loaded standard which does not duplicate the geometry in which the iodine is actually collected on the charcoal cartridge.
This results in the licensee using a lower counting efficiency than would be obtained from counting a standard which duplicates the actual geometry.
The licensee's results were higher than the NRC's results and, therefore, were in a conservative direction and would not result in the licensee exceeding any effluent release limits.
In addition, the charcoal cartridges were counted by the NRC assuming a uniform distribution and the results were in agreement. The results of the comparisons are listed in Table 1.
The licensee stated that the licensee would review licensee's charcoal cartridge calibration.
5.
Records and Procedures
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The inspector reviewed the following records and procedures:
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Gaseous effluent analysis data (January 1980 to February 1981).
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Liquid effluent analysis data (January 1980 to February 1981).
c Counter calibration and check records.
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L6 oratory QC sample analyses (November 1980 to February 1981).
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The follusing procedures:
(1) PSP-5, Radioactive Airbourne Sampling, Analysis and Equipment Calibration (2) PSP-4, Waste Water Sampling and Analysis 6.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on March 27, 1981.
The inspector summarized the purpose and scope of the inspection and the inspection findings.
The licensee agreed to perform the analyses listed in paragraph 4 and report the results to the NR 'i
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TABLE 1 fITZPATRICK VERIFICATION - TEST _RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICROCURIES PER MILLILITER Reactor Tc-99m (1.10910.009)E-2 (1.129'O.017)E-2 Ag reement Wator C r-51 (6.110.6)E-3 (7.810.7)E-3 Ag reement j
1305 1-132 (6.210.2)E-3 (5.710.3)E-3 Ag reement 3/25/81 1-134 (1.9510.07)E-2 (1.5210.08)E-2 Ag reement I-135 (5.210.4)E-3 (3.710.4)E-3 Ag reement Co-60 (2.310.7)E-4 (3.510.8)E-4 Ag reement Na-24 (1.5610.03)E-2 (1.5510.04)E-2 Ag reement Reactor 1-131 (1.010.4)E-4 (8.7 1.1)E-5 Ag reement Water 1-132 (5.2110.15)E-3 (5.7110.06)E-3 Agreement todine 1-133 (1.7310.05)E-3 (1.5010.02)E-3 Ag reement 1000 l-134 (1.4410.04)E-2 (1.04910.007)E-2 Possible Agreement 3/26/81 1-135 (3.910.2)E-3 (4.0910.08)E-3 Ag reement
"B" Li_ quid Laund ry Tank Mn-54 (1.510.3)E-6 (1.410.4)E-6 Ag reement 0815 Co-60 (7.310.5)E-6 (8.411.0)E-6 Ag reemen t 3/26/81 Cs-134 (!.110.3)E-6 (1.910.6)E-6 Ag reement Cs-137 (2.210.3)E-6 (1.410.4)E-6 Ag reement Fi a tor Mn-54 (3.5710.12)E-6 (4.210.3)E-6 Ag reement 2H Co-60 (1.6810.03)E-5 (2.2510.08)E-5 Ag reement Feedwater Co-141 (9.010.5)E-10 (1.0510.09)E-9 Ag reemen t Pa rt i cu I a to Cr-51 (5.610.6)E-9 (6.610.8)E-9 Ag reemen.
Filter Co-58 (8.110.2)E-9 (1.0810.03)E-8 Ag reemen '
0800 Mn-54 (1.7310.03)E-8 (2.1310.04)E-8 Ag reco- -
3/24/81 Zn-65 (2.310.3)E-9 (2.610.4)E-9 Ag rer aent Fe-59 (9.010.4)E-9 (1.1510.06)E-8 Agreement Co-60 (3.4410.07)E-8 (4.6510.08)E-8 Possible Agreement Sb-124 (2.210.3)E-9 (2.810.3)E-9 Aq + eemer.t
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TABLE 1
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FITZPATRICK VERIFICATION - TEST RESULTS SAMPLE ISOTOPE NRC VALUE LlCENSEE VALUE COM PAR I SON RESULTS IN MICROCURIES PER MILLILITER Orr Cas Xe-133 (9.0310.15)E-3 (1.0210.01)E-2 Ag reement 1425 Xe-135 (2.8310.02)E-2 (2.8910.01)E-2 Ag reement 3/25/81 Kr-88 (2.1310.05)E-2 (1.6210.02)E-2 Possible Agreement Aliquot =33ml Kr-8.
(1.7710.05)E-2 (1.2810.02)E-2 Possible Agreement K r-85m (7.1910.15)E-3 (7.110.3)E-3 Ag reement O f f Ca s Xe-133 (6.?10.5]E-3 (9.h 0.1)E-2 Ag reement
0655 Xe-135 (3.0710.04)E-2 (2.7410.01)E-2 Ag reement 3/26/81 Ki-88 (2.40!O.11)E-2 (1.6210.02(E-2 Possible Agreement Aliquot =15 ml K r-87 (2.3910.10)E-2 (1.5910.02]E-2 Possible Agreement K r-85m (7.510.3)E-3 (6.610.3)E-3 Agreement Main Stack k r-85 (1.1010.09)E-4 (1.4010.02)f-4 Ag reement Cas Xe-133 (2.210.2)E-4 (2.25510.011)E-4 Ag reement 1:45 Xe-135 (4.4410.14)E-4 (6.06110.012)E-4 Possible Ag reement 3/26/81 Kr-88 (2.610.3)E-4 (3.08710.016)E-4 Ag reement Main Stack Ba-140 (6.410.2)E-12 (7.510.5)E-12 Ag reement Pa r t icu l a te La-140 (6.310.2)E-12 (5.410.4)E-12 Ag reement 0715 Cs-137 (4.310.3)E-13 (5.911.0)E-13 Ag reement 3/24/81 Turbine Bldg.
1-131 (9.8t0.6)E-13 (1.610.2)E-12 Possible Agreement Pa r t i cu l a te I-133 (1.3010.09)E-11 (1.4310,12)E-11 Ag reement filter Ba-140 (4.210.2)E-12 (3.210.5)E-12 Ag reement 1535-0730 3/17-3/24/81 lurbine Bldg.
Uniform Distribution Vent Cha rcoa t 1-131
..410.2)E-12 (6.810.3)E-12 Ag reement 1535-0730 1-133 (4.210.3)E-11 (4.3410.16)E-11 Ag reement 3/17-3/24/81 face Loade_d_
I-131 (3.8010.08)E-12 (6.810.3)E-12 Di sag reement 4-133 (3.010.2tE-11 (4.3410.16)E-11 Ag reement Ma in Stack Uni f o rm Di st ribut ion Cha rcoa l 1-131 (1.7310.03)E-10 (1.8510.015)E-10 Ag reement 1620-0715 l-133 (1.4810.03)E-9 (1.40510.015)E-9 Ag reement 3/17-3/24/81 Face Loaded 1-131 (1.22610.012)E-10 (1.85610.015)E-10 Di sa g reemen t 1-133 (1.07710.011)E-9 (1.40510.015)E-9 Possible Agreement t
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Attachment 1
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Criteria _for Comparing Analytical !%asurements This atiachment 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.
LICENSEE VALUE PATIO = NRC' REFERENCE VALUE Possible Possible Resolution Agreement A reement A Agreement _B_
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<3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 60 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.60 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Key.
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Tritium analyses of liquid samples.
Iodine on absorbers
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"B" criteria are appliad to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and 903r Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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