IR 05000285/1979014
| ML19254E612 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/19/1979 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19254E608 | List: |
| References | |
| 50-285-79-14, NUDOCS 7911010577 | |
| Download: ML19254E612 (11) | |
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U. S. NUCLEAR REGUL/. TORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/79-14 License No. DPR-40 Docket No. 50-285 Licensee: Omaha Public Power District (OPPD)
Category C 1623 Harney Street Omaha, Nebraska Facility:
Ft. Calhoun (FC)
Inspection Conducted: August 30-31, 1979 Inspector:
N
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915ineMurray',RadipionSpecialist
/Datd Approved by:
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//M. D. Brown, Chief, Fugl Facility and Material natf
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G Safety Branch
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Inspection Summary Inspection Conducted during August 30-31, 1979 (Report No. 50-285/79-14)
Areas Inspected: Routine unannounced inspection of the licensee's Radioactive Waste Systems and Analytical Measurements programs including:
liquid and gaseous effluent releases; procedures for controlling effluent releases; training and qualifications of radiochemistry personnel; radiochemistry samnling and analyses procedures; radiochemistry laboratory QA program; and confirmatory measurement results. The inspection involved 16 onsite hours t, r one NRC inspector.
Results: No items of noncompliance or deviations were noted.
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DETAILQ 1.
Persons Contacted (L '"D)
- R. L. Andrews, Plant Manager
' 's Supervisor
- F. F. Franco, Chemistry and Health Pb
- J. Gass, Training Coordinator
- J. B. Nicholas, Chemist M. F. Cassada, Health Physicist
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- Denotes those present during the exit interview. The inspector also interviewed several other licensee personnel during the inspection.
2.
Status of Previous Inspection Findings (0 pen) Open Item 78-05/ Sampling Procedures: This item was discussed in Inspection Report No. 50-285/78-05 and involved the lack of sample collection procedures for certm.a samples. Procedures have not been completed to cover all samples. This item remains open.
(0 pen) Open Item 78-05/ Containment Sampler: This item was discussed in Inspection Report No. 50-285/78-05 and involved installation of a remote containment air sampling system.
Installation of this system has not been completed.
This item remains open.
3.
Open Itens this insp ction (Open) Open Item 79-14/ Training Records: The training records for several technicians assigned to work in the radiochemistry laboratory were not up-to-date.
(See paragraph 5.)
4.
Scope of Inspection The purpose of this inspection was to review the licensee's Analytical Measurements program and a partial review of the Radioactive Waste Systems program for the period May 8,1978 through August 30, 1979.
5.
Ra'iochemistry Staff The inspector reviewed the organization, staffing, training, and qualifications for the radiochemistry staff. The li'ensee has established a program of rotating Health Physics Technicians through the Radiochemistry Department at various intervals to assist with radiochemistry activities.
It was noted that the training records for several technicians were not current.
Supervisory personnel had not signed the training record approval forms for some techicians to indicate ; hat the technicans
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are approved to perform certain procedures. The Chemistry and Health Physics Supervisor stated that delinquent training records would be brought up-to-date.
This item is considered open pending further review.
No other problems were identified.
6.
Radioactive Effluent Releases a.
liquid The inspector examined liquid releases made between May 1, 1978 and August 30, 1979 to determine compliance with Technical Specifications 2.9.(1),3.12.(1) and Table 3-11.
The following procedures and data forms were examined:
Standing Order No. T-2, " Waste Liquid Releases"
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Surveillance Form, "ST-Chem 1.F.1 Weekly" Surveillance Form, "ST-Chem 1.F.2 Monthly"
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Surveillance Form, "ST-Chem 1.F.3 Quarterly"
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Form FC-211, " Waste Liquid Release"
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Form FC-222, " Waste Release Batch Summary"
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Form FC-326, " Monitor Tank Releases" Form FC-327, " Steam Generator Releases"
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Form FC-287, " Steam Generator Release Summary"
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No items of noncompliance or deviations were identified.
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b.
Gaseous The inspector reviewed gaseous releases made between May 1, 1978 and August 30, 1979 to determine compliance with Technical Specifications 2.9.(2),3.12.(2), and Table 3-12.
The following procedures and data forms were examined:
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Standing Order T-3, " Waste Gas Release"
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Surveillance Form, ST-Chem 1.F.1 Weekly"
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Surveillance Form, ST-Chem 1.F.2 Montuly"
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Surveillance Form, "ST-Chem 1.F.3 Quarterly"
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Form FC-213, " Waste Gaseous Release Permits"
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Form FC-212, " Containment Purge Release Permits"
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Form FC-253, " Weekly Chemical Analysis"
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Form FC-252, " Gaseous Release Requirements"
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Form FC-302, " Waste Gas Release Summary - Containment"
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Form FC-300, " Continuous Gas Release Summary - RM-060"
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Form FC-303, " Waste Gas Release Summary - Gas Decay Tanks" Form FC-293, "RM-060 Weekly"
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Form FC-261, "RM-057 Monthly"
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Form FC-263, "RM-062 Quarterly" No items of noncompliance or deviations were identified.
7.
Procedures For Controlling The Release of Gaseous and Liquid Effluents The inspector reviewed release procedures to determine compliance with Technical Specifications 2.9.(1),2.9.(2),3.12.(1),3.12.(2),'and 5.8.1.
The following procedures were reviewed:
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Standing Order No. T-2, " Waste Liquid Release" Standing Order No. T-3, " Waste Gas Release"
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Standing Order No. T-12, " Containment Purge Release"
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Form FC-211, " Liquid Waste Release Permit"
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Form FC-212, " Containment Purge Release Permit" Forra FC-213, " Waste Gas Release Permit"
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The above procedures are designed to indicate such data as:
Radiochemistry analyses results
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Technical Specification limits Function Test of Gas / Liquid monitors 2b
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Function test of isolation valve
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Allowable release rate
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Dilution flow
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Valve line-up Total volume released
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Total activity released
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Authorization signatures
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No items of noncompliance or deviations were identified.
8.
Analytical Measurements a.
Sampling and Analyses Procedures The inspector examined the following analyses and sampling procedures:
Procedure CMP 2.0 " Sample Collection" Procedure CMP 3.2 " Determination of Radioactive Iodine" Procedure CMP 3.3 " Radioactive Cesium in Liquid Sample" Procedure CMP 3.5 " Determination of Isotopic Specific Activity in Primary Coolant Gas and Waste Gas" Procedure CMP 3.9 " Determination of Tritium In plant Atmosphere" Procedure CMP 3.10 " Determination of Radioactive Particulate and Radioactive Iodine In Air Samples" Procedure CMP 3.12 " Determination of Barium-139 and Barium-140 in Primary Coolant" Procedure CMP 3.13 " Determination of Tritium by Liquid Scintillation" Procedure CMP 3.14 " Determination of 5 in Reactor Coolant" Procedure CMP 3.17 " Gases Activity in Water" Standing Order T-30, " Composite Sample Collection."
Procedure OI-SL-SP " General Sampling Procedures"
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Procedure 0I-WDG-1, " Waste Gas System" Procedure OI-SL-1, " Primary Sampling System" Procedure OI-SS-1, " Secondary Sampling System
Procedure OI-WDL-1, " Collection and Transfer of Liquid Waste" Procedure OI-WDL-1, " Liquid Waste Disposal" Detailed, written procedures have not been completed to cover the collection of various liquid and gas samples. This same item was discussed in Inspection Report No. 50-285/78-05.
General sampling procedures and portions of certain analyses procedures briefly mention some aspects of sample collection. However, step-by-step procedures have not been written to provide guidance in the proper techniques for collection of specific samples.
A licensee representative stated that the necessary sampling procedures will be completed.
b.
Calibration and Quality Control Program The inspector reviewed the calibration and quality control program associated with the laboratory counting instrumentation. The following procedures were reviewed:
Standing Order T-13, " Quality Control Program For Chemistry and Radiation Protection Equipment:
Procedure FCP-LAB-6, " Function Check - GM"
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Procedure FCP-LAB-7, " Function Check - IPC" Procedure FCP-LAB-8, " Function Check - Liquid Scintillation" Procedure FCP-LAB-10, " Function Check - Packard NaI Spectrometer" Procedure FCP-LAB-15, " Function Check - TN-11" Procedure FCP-LAB-16, " Function Check - Wide Beta II" Procedure FCP-LAB-19, " Function Check - Canberra GeLi System" Procedure CP-LAB-6, " Calibration Procedure - GM" Procedure CP-LAB 7, " Calibration Procedure - IPC"
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Procedure CP-LAB-8, " Calibration Procedure - Liquid Scintillation" Procedure CP-LAB-10, " Calibration Procedure - NaI Spectrometer" Procedure CP-LAB-15, " Calibration Procedure - TN-11" Procedure CP-LAB 16, " Calibration Procedure - Wide Beta II" Procedure CP-LAB-19, " Calibration Procedure - Canberra GeLi System" In general, the above procedures require that each instrument be functional tested daily or prior to use if the instrument is not operated on a routine basis.
Calibration frequencies are specified in Standing Order T-13.
No items of noncompliance or deviations were identified.
c.
Confirmatory Measurements Confirmatory measurements were performed on the following samples:
(1) Liquid Waste (2) Gaseous Waste (3) Stack Charcoal Cartridge
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(4) Stack Particulate Filter The confirmatory measurements tests consist of comparing measurements made by the licensee and NRC's reference laboratory, Radiogical and Environmental Sciences Laboratory (RESL) - DOE Idaho Falls.
RESL's measurements are referenced to the National Bureau of Standards by laboratory intercomparisons. Confirmatory measur.:ments are only made for those nuclides identified by RESL as being present in concentrations greater than 10% of the respective MPC's for liquid and gas samples and above the Lower Limits of Detection (LLD) for stack samples.
Stack charcoal cartridge and particulate filter comparisons are based on established LLDs for total activity per sample.
Attachment No. I contains the criteria used to compare results.
Attachment No. 2 lists the LLDs for stack samples.
The following tables show the comparison results:
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(1) Liquid Waste (Hold-up Tank-Collected December 19,1978)
Nuclide NRC Measurement OPPD Measurement Decision
5.71 0.02 E-03 uCi/ml 5.91[0.01E-03uCi/ml Agreement H
beta 8.8 * 0.3 E-03 uCi/ml 1.44[0.02E-02uCi/ml Agreement
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134 3.87[0.11E-03uCi/ml 3.72[0.03E-03uCi/ml Agreement Cs 137 5.69[0.16E-03uCi/ml 5.69[0.03E-03uCi/ml Agreement Cs
3.29 * 0.09 E-03 uCi/ml 3.07[0.03E-03uCi/ml Agreement C0
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1.54[0.06E-04uCi/ml 1.68[0.08E-04uCi/ml Agreement Co 124Sb 2.3[0.3E-05uCi/ml 3.73[0.66E-05uCi/ml Agreement (2) Gaseous Waste (Gas Decay Tank - Collected December 19, 1978)
Nuclide NRC Measurement OPPD Measurement Decision
3.8 + 0.2 E-05 uCi/ml 7.92[0.37E-05uCi/ml Disagreement *
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1.61[0.38E-05uCi/ml 3.66[0.38E-03uCi/ml Disagreement *
Kr
- Possible problems regarding sample split. New sample collected on August 31, 1979; Results will be reported after analyses are completed.
(3) Stack Charcoal CartriJge (Collected December 19, 1978)
Nuclide NRC Measurement OPPD Measurement Decision 131 4.03[0.15E-03uCi/ sample 3.55[0.1E-03uCi/sampleAgreement I
3.34[0.75E-05uCi/ sample 2.8[0.58E-05uCi/sampleAgreement Co (4) Stack Particulate Filter (Collected December 19, 1978)
Nuclide NRC Heasurement OPPD Measurement Decision 137 If1[2.3E-05uCi/ sample 1.58 3.8 E-05 uCi/ sample Agreement Cs No items of noncompliance or deviations were identified.
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9.
Exit Interview -
At the conclusion of the inspection on August 31, 1979, the inspection findings were discussed with those individuals identified in paragraph 1.
The inspector sumarized the scope of the inspection and the inspection findings.
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ATTACHMENT NO. 1 Criteria for Comparing Analytical Measurements The following are the criteria used in comparing the results of capability tests and verification measurements.
The criteria are based on an empirical relationship established through prior experience and this program's analytical requirements.
In these criteria, the judgement limits vary in relation to the comparison of the resolution.
Resolution = NRC Value NRC escertainly Ratio = Licensee Value NRC Value Comparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio.
The following table shows the acceptance values.
RESOLUTION RATIO Possible Possible Agreement Agreement A Agreement B
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 - 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.
Iodine on adsorbers.
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
O Sr and Sr Determinations.
Gross Beta where samples are counted on'the same date using the same reference nuclide.
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ATTACIDfENT NO. 2 LLDs for Nuclides on Particulate and Charcoal Filters
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livelide LLD (uCi/ sample)
jjCr IE-04 Mn
1.5E-05 Co
1.5E-05 Fe
3E-05 Co
2E-05 Co
3E-05 Zn
3E-05 90{Sr IE-05 r
2E-07 I
134 2E-05 Cs 137 2E-05 Cs 140 2E-05 Ba 140 2E-05 La 141 4E-05 C
144 e 2E-05 Ce IE-04 1283 218
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