IR 05000029/1976016
| ML19343A504 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/18/1976 |
| From: | Kottan J, Paperiello C, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19343A503 | List: |
| References | |
| 50-029-76-16, 50-29-76-16, NUDOCS 8011140154 | |
| Download: ML19343A504 (11) | |
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U. S. NUCLEAR REGUL\\ TORY CO CiISSION
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0FFICE OF INSPECTION AND ENFORCCJEMT
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REGION I
50-29 50-29/76-16 Docket No:
IE Inspection Report No:
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DPR-3 Yankee Atomic Electric Company License No:
Licensee:
20 Turnpike Road Priority:
Westborough, Massachusetts 01581 C
Cam,
Safeguards Group:
Yankee Aconic Power Station, Rowe, Massachusetts PWR (600 MWe)
Type of Licensee:
Independent Measurements, Announced Th c of Inspection:
Dates of Inspection:
August 10-12, 1976 July 19-23,1976 Dates of Previous Inspection:
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>1-Reporting Inspectot: T.T kd./O vd> -
0/7 7 /.
s J. J. Kottan, Radiation Specialist
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DATE Actonpanying Inspcetcrs:
o F cme-t, r*
l-Dr.C.J.Paheriello,RadiationSpecialist DATE
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DATE DATE Other Accompanying Personnel:
None
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DATE
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Reviewed By:
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J. P. Stoh, Chief, Environmental and, Special Projects
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Section, FF&MS Branch
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SUMMARY OF FINDINGS Enforcement Action A.
Violations None B.
Infractions
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None
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C.
Deficiencies None Licensee Action on Previous 1v Identified Enforcement Items (Independent Measurements)
None Unusual Occurrences N ne -
o Other Significar.t Findings A.
General This report summarizes the results of an Independent Measurements-Inspection conducted to evaluate the capability of the licensee to measure radioactivity in effluent samples and to evaluate the ade-quacy of the licensee's management controls for maintaining the quality of measurements of radioactivity in effluent samples. The results of the actual effluent sample analyses and the capability test standards analyses indicate that 95% of the analyses were in agreement with the NRC reference laboratory and five percent were not in agreement.
(Details, Paragraph 3)
B.
Unresolved Items 1.
Xe-133 Measurements.
(Details, Paragraph 3)
2.
Cr-51 Measurements.
(Details, Paragraph 3)
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Infractions and Deficiencies Identified by the Licensee None D.
Deviation None Management Interview The following individuals attended the management interview at the conclusion of the inspection.
Mr. N. N. St. Laurent, Assistant Plant Superintendent, YAS Mr. L. L. Reed, QC cnd Audit Coordinator, YAS Mr. J. L. Staub, Technical Assistant to Plant Superintendent, YAS Mr. W. D. Billings, Chemistry and Health Physics Supervisor, YAS Mr. J. S. Gedutis, Technical Assistant Chemistry, YAS Mr. M. W. Thise11, Chemist, YAS Dr. C. J. Paperiello, Radiation Specialist, NRC :I Mr. J. J. Kottan, Radiation Specialist, NRC:1 The inspector discussed his inspection findings in the following areas.
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A.
Scope of the Inscection The inspector stated the purpose of the inspection. He stated there were no items of noncompliance.
B.
Results of Verification Test Samples The inspector stated that 20 of the 21 measurements to test the licensee's capability to measure radioactivity in effluent samples were in agreement. The inspector stated that the only measurement in disagreement was a filter-paper analysis for Cr-51.
The inspector stated that this would be considered an Unresolved Iten pending the results of Cr-51 analysis of the filter by the NRC reference labora-tory, Idaho Health Services Laboratory (IHSL). The inspector also stated that the Xe-133 measurements would be considered an Unre-solved Item pending the analysis of a gas sample by the NRC refer-ence laboratory, IHSL. The inspector stated that the results of the IHSL analyses would be documented in.a subsequent inspection
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report.
(Details, Paragraph 3)
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C.
Additional Analyses on Verification Samoles The inspector stated that the NRC reference laboratory, IHSL, would perform Strontium-89, Strontium-90, gross beta, gross alpha, and tritium analyses on the split liquid Waste Hold Up Tank sample; and tritium and Carbon-14 analyses on the split liquid Test Tank Sample.
The licensee staced that he will perform the same analyses of the samples for the comparisen of results. The inspector stated that the results of the comparison would be documented in a subsequent inspection report.
(Details, Paragraph 2)
D.
Procedures The inspector noted that the licensee had implemented an internal laboratory QC Proceedure. The inspector also noted that the licen-see had procedures for compositing liquid samples and performing proper radiation =enitoring while taking gas samples.
(Details,
Paragraph 4)
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s DETAILS 1.
Persons Contacted Mr. H. A. Autio, Plant Superintendent, YAS Mr. N. N. St. Laurent, Assistant Plant Superintendent, YAS Mr. J. L. Staub, Technical Assistant to Plant Superintendent, YAS Mr. L. L. Reed, QC and Audit Coordinator, YAS Mr. W. D. Billings, Chemistry and Health Physics Supervisor, YAS Mr. J. S. Gedutis, Technical Assistant. Chemistry, YAS Mr. R. A. Mellor, Technical Assistant Health Physics, YAS Mr. M. W. Thisell, Chemist, YAS 2.
General (
This inspection consisted of a review of the licensee's effluent collection and analysis procedures, effluent records, quality
?ssurance recotis, certain monitoring and counting equipment, and gerformance on actasi af fluent samples split between the licensee and the NRC:I. The actual effluent samples were analyzed by the licensee using his norsal methods and equipment; the NRC:I using the NRC:I mobile laboratory at the sise; and the NRC reference laboratory, Idaho Health Services Laboratory (IHSL). Results of the sample analyses were compared. Joint analyses of the actual effluent samples and subsequent comparison of the results deter-mines the licensee's capability to measure radioactivity in effluent
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samples.
In addition, certain capability test standards, prepared The 11cen-by IHSL, were submitted to the licensee for analysis.
see's performance in these samples were also reviewed.
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An actual liquid effluent sample was sent to IHSL for analysis re-quiring wet chemistry. These results will be cocpared with the licensee's results when received at a later date and will be docu-mented in a subsequent inspection report.
3.
Results of Verification Test Samples The comparison of the licensee's analyses with those of the NRC:I mobile laboratory and the Idaho Health Services Laboratory (IHSL)
indicated that 20 of the licensee's measurements were in agreement under the test criteria used for comparing test results (See Attach-ment 1) and one of the licensee's measurements was not in agreement.
The samples analyred consisted of splits of actual effluents and test standards prepared by IHSL. The results of the measurement comparisons are listed in Table 1.
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TABLE I
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YANKEE ROWE - VERIFICATION TEST RdSULTS SAMPLE ISOTOPE NC VALUE LICENSEE VALUE COMPARISON RESULTS IN HICROCURIES PER MILLILI'lER llSL Sr-89 3.3410.07 E-5 6.110.8 E-5 Possible Agreement B Sr-4 Sr-90 4.7910.14 E-6 6.611.3 E-6 Possible Agreement A 12/1/75 i
Waste lloid I-131 3.4510.10 E-5 3.711? E-5 Agreement Up Tank Cs-134 2.5410.13 E-5 2.8217 E-5 Agreement 1000 lirs.
'Cs-137 3.5510.12 E-5 3.6817 E-5 Agreement 8/10/76 Co-58 3.0810.71 E-5 4.2917 E-5 Possible Agre'ement A
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Mn-54 2.0010.02 E-4 2.6517 E-4 Possible Agreement A Co-60 1.0510.02 E-4 1.181? E-4 Agreement
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T_ABLE I
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YANKEE ROWE - VERIFICATION TEST RESULTS
SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICR0 CURIES PER MILLILITER
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Filter Paper Ce-144 4.110.8 E-6 3.27i7 E-6
~ Agreement 1200 Hrs.
Cr-51 1.2410.02 E-4 2.7317 E-4 Disagreement 8/4/76 Ag-110m 2.210.3 E-6 2.41t? E-6 Agreement'
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.Zr-95 3.3110.09 E-5 4.41? E-3 Possible Agreement A Co-58 6.3910.06 E-5 7.31? E-5 Agreement Mn-54 5.5110.06 E-5 7.211? E-5 Possible Agreement A Fe-59, 5.6910.11 E-5 6.331? E-5 LAgreement
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Co-60 2.8510.01 E-4 3.3417 E-4 Agreement Sb-124 1.910.3 E-6 2.1917 E-6 Agreement
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Low Pressure Xe-133 3.4610.17 E-1 5.481? E-1 Possible Agreement B Surge Tank Xe-135 4.2510.21 E-3 3.3517 E-3 Agreement 0845 lirs.
Xe-133m 3.S40.5 E-3 5.05+? E-3 Agreement 8/11/76
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Waste cas Xe-133 2.84+0.08 E-4 5.26+? E-4 Possible Agreement B Surge Drum 1120 !!rs.
8/10/76
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The inspector noted that the only measurement in disagreement was
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the Cr-51 c-asurement of the filter paper. The filter paper was
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recounted by the licensee and the NRC inspector. The inspector reviewed the licensee's calibration and the use of the proper branching ratio. The licensee checked the computer program used to
analyze the gamma ray spectrum of the filter paper. The cause of the disagreement, however,' could not be determined. The inspector
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stated.that this would be considered an Unresolved Item pending the l
analysis of.the filter paper by the NRC reference laboratory, IESL.
The inspector also noted that the licensee's Xe-133 measurements, although meeting Possible Agreement Criteria B, were significantly higher than those of the NRC mobile laboratory. The inspector-
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reviewed the licensee's gaseous calibration procedures and the use of the proper branching ratio. The inspector stated thac this would be considered an Unresolved. Item pending the analysis of the
. gas sample by the NRC reference laboratory, IHSL. The inspector noted -that the licensee's measurements of both Xe133 and Cr51 were higher than those of the NRC, and this would not result in the licensee exceeding any technical specification effluent release limits. The inspector stated that the results of the IHSL analyses will be documented in a subsequent inspection report.
4.
Procedures The inspector noted that the licensee had implemented Procedure AP-9004, Laboratory Quality. Control Program. The inspector also noted that Procedure OP-9415, Radioactive Gas Sampling, contained provis-
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ions for radiation monitoring while taking radioactive gas samples.
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In addition, the inspector witnessed a radioactive gas sample being taken and observed that radiation monitoring was performed while
sampling. The inspector noted that Procedure OP-9246, Radioactive
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Liquid Releases and Reports, contained steps to prevent the loss of radioactivity in liquid composite samples.
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The following procedures were reviewed by the inspector:
AP-9000 - Training of Chemistry & Health Physics Department Personnel AP-9001 - Primary Chemistry Test Frequencies & Specifications AP-9003 -' Chemistry Instruction, Reports & Records AP-9004 - Laboratory Quality Control Program AP-9009 - Calibration Schedule for Chemistry Laboratory Instruments DP-9100 - Preparation of' Secondary Standards OP-9102 - QC Checks of Laboratory Counting Equipment
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RP-9105 - Detection and Calculation' of Primary-to-Secondary Leakage DP-9112 - QC Tests for Ion Exchange Resins OP-9200 - Iodice Analysis DP-9219 - Crud Concentration & Radionuclide Analysis
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OP-9220 - Determination of Gross Beta Radioactivity OP-9221 - Main Coolant Caseous Radionu'clide Analysis & Gaseous E Determinatien DP-9222 - Alpha Emitter Analyses DP-9225 - Radionuclide Analysis by Gamma Spectroscopy (Sodium Iodine Scintillation Detector)
DP-9226 - Radionuclide Analysis by Gamma Spectroscopy (Germanium - Lithuis Detector)
OP-9237 - Determination of Gross Gamma Radioactivity OP-9240 - Tritium Analysis by Liquid Scintillation Counting DP-9241 - Carbon-14 Analysis
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DP-9242 - Radiochemical Separation & Analysis of Strontium-89 and Strontium-90 DP-9244 - Radionuclide Analysis of the Primary Coolant OP-9245 - Primary Vent Stack Sampling and Monitoring OP-9246 - Radioactive Liquid Releases and Reports DP-9247 - Analysis of Radioactive Airborne Releases DP-9248 - Analysis of Low Level Radiciodines Using Anion Ion
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Exchange Resin OP-9404 - Split Sample Program OP-9415 - Radioactive Gas Sanpling D2-9501 - Operation & Calibration of the KHC PCC-llT/DS-2 Internal Proportional Counter DP-9502 - Calibration of the Germanium Lithium Detector and D
Camberra Model 8100 Multichannel Analyzer System DP-9503 - Operation of the Model 8100 Multichannel Analyzer and PDP-ll/05 Ccoputer DP-9504 - Operation and Calibration of Liquid Scintillation Spectrometer DP-9512 - Efficiency Calibration of the Multichannel Analyzer and the Sodium Iodine Scintillation Detector The inspector had no additional questions in this area.
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-Records The inspector reviewed the plant logs and records in the following areas:
Gaseous Discharge Release Permits (January,1975 to August, a.
1976).
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Liquid Discharge Release Permits (January,1975 to August, 1976),
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Counter Calibration Records (1974 throrgh 1976).
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Daily Counter Check Logs and Graphs (June,1979, August, 1976).
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Internal Laboratory QC Records (1975 through 1976).
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The inspector had no additional questions in this area.
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Attachment 1 Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience anu the accuracy needs of this program.
In these criteria, the judgement limits are variable in relation to _ the comparison of the :RC 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 RATIO = NRC REFERENCE VALUE Possible Possible Resolution Agreement Agreement A Agreement B
<3 0.4 - 2.5 0.3 - 3.0
'o 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 - 50 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 0.80 - 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 Kev.
Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and 90Sr Determinations.
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Cross Bets where samples are counced on the same date using the same reference nuclide.
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