IR 05000219/1981020
| ML20038C800 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/12/1981 |
| From: | Bores R, Jang J, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20038C793 | List: |
| References | |
| 50-219-81-20, NUDOCS 8112140140 | |
| Download: ML20038C800 (8) | |
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U.S. NUCLEAR REGULATORY LOMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l
Region I Report No.
50-219/81-20 Docket No.
50-219 License No. DPR-16 Priority
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Category C
Licensee:
Jersey Central Power and Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Facility Name:
Oyster Creek Nuclear Generating Station Inspection at:
Forked River, New Jersey Inspection conducted: October 19-22, 1981 Inspectors:
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date signed
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J/S.J. Bores, Chief,IndependentMeasurements date signed
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and Environmental Protection Section, EP&PS Branch Inscection Summary:
Inspection on October 19-22, 1981 (Report No. 50-219/81-20)
Area Inspected:
Routine, unannounced inspection of the licensee's chemical and radiochemical measurements program using NRC:I Mobile Radiological Measurements Laboratory and laboratory assistance provided by DOE Radiological and Environmental Service 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 procedures.
The inspection involved 45 inspector-hours onsite by two NRC regionally based inspectors.
Results: Of the four areas inspected, no items of noncompliance were identified.
Region I Form 12 (Rev. Anril 771 8112140140 811124 PDR ADOCK 05000219
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DETAILS 1.
Individuals Contacted Principal Licensee Employees
- J.
T. Carroll, Acting Director, Oyster Creek
- J. Bachofer, Director - Special Projects
- J.
R. Pelrine, Chemistry Manager
- P. Czaya, Licensing R. L. Stoudnour, Senior Engineer
- R. B. Somers, Group Chemistry Supervisor The inspector also interviewed other licensee employees, including members of the chemistry, health physics and quality assurance staffs.
- denotes those present at exit interview.
2.
Laboratory QC Program The inspector reviewed the licensee's program for the quality control of analytical measurements. The inspector noted that the licensee's 807 Series procedures cover quality control for both reacter coolant chemistry analyses and radiological analyses of effluent samples.
The licensee's effluent radiological analysis QC program consists of quarterly splits with a contracted laboratory.
Also, the operating procedures for the various counting instruments
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specify daily background and source checks and where applicable, gain checks.
The inspector discussed Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring programs (Normal Operations) -Effluent Streams and the Environment, and laboratory quality control in this general area with the licensee.
The inspector had no further questions in this area.
No items of noncompliance were identified.
3.
Audit Results The inspector determined that the licensee's chemistry and effluent monitoring programs were on the Quality Assurance Division audit list.
The inspector reviewed Audit No. 80-09 dated October 7-9, 1980.
The inspector had no further questions in this area.
No items of noncompliance were identified.
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4.
Confirmatory Measurements During the inspection, actual liquid, airborne particulates and charcoal, and gaseous effluent samples were split between the licensee and NRC:I for the purpose of intercomparison.
The effluent samples were analyzed by the licensee using licensee's normal methods and equipment, and by the NRC using the NRC:I Mobile Radiological Measurements Laboratory.
A comparison measurement of a liquid effluent sample was not made during the inspection due to low activity in the sample. A spiked liq.:id sample was presented to the licensee for snalysis.
This spiked sample was prepared by the NRC reference laboratory, Department of Energy, Radiological and Environmental Services Laboratory (RESL).
Joint analyses of actual effluent samples are used to determine the licensee's capability to measure radioactivity in effluent samples.
In addition, a liquid effluent sample was sent to the NRC reference laboratory, 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 results of an effluent sample split between the licensee and NRC:I during a previous inspection on May 13-15, 1980 (Inspection Report 80-20) were also compared during this inspection.
A routine health physics air sample which was analyzed by the licensee's health physics personnel using the health physics gamma ray spectroscopy system was also compared.
The results of the sample measurement intercomparisons indicated that all of the measurements were in agreement or possible agreement under the criteria used for comparing results.
(See Attachment 1).
The results of the comparisons are listed in Table I.
5.
Records and Procedures The inspector reviewed the licensee's records and procedures.
a.
Records (1) Liquid Radioactive Release (January, February, July, September, 1981)
(2) Gaseous Radioactive Release (September 1981 to October 15, 1981)
(3) Stack Gas Marinelli Analysis (February 25, 1981 to April 15, 1981)
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(4) Chemistry Instrument Efficiency and Calibration Log.
(a) Alpha (June 1, 1981 to October 20,1981)
(b) Beta (June 1, 1981 to October 20,1981)
(c) Gamma, Ge(li) (June 1, 1981 to October 20, 1981)
b.
Procedures (1) 807.1 Laboratory QA and QC - General Scope (2) 807.6 QA Analyses by Contractor Laboratories (3) 807'.7 Laboratory QA and QC Standard, Spiked and Blind Samples (4) 809.2 Calibration of the Beckman LS100 Liquid Scintillation Counter (5) 809.3 Calioration of the Beckman Widebeta Counting System (6) 809.4 Calibration of the Princeton Gamma - Tech Ge(li) Detector (7) 810.5 Preparation Procedure for Radioactive Calibration Standards (8) 806.1 Gross Alpha and Beta Activity in Water (9) 806.5 Tritium (10) 806.6 Radiciodine from Incore Fuel Sipping
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(11) 806.7 Gross Gamma Radioactivity Offgas 2hr/24hr Ratio (12) 804.15 Tritium in Offgas and Gland Seal Exhaust l
Since a new filing system was instituted recently and is being processed, the licensee was not able to retrieve Liquid and Gaseous Radioactive Release Records in a timely manner at the Document Control Center.
The inspector stated this would be considered as a follow-up item.
The irspector had no further questions in this are.
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6.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on October 22, 1981. The inspector summarized the purpose and scope of the inspection and the inspector findings.
The licensee agreed to perform the analyses listed in Paragraph 5 and report the results to the NR TABLE 1.
THE RESULTS OF THE COMPARIS0NS (NRC VS OYSTER CREEK)
SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARIS0N RESULTS IN MICR0 CURIES PER MILLILITER Stack I-131 (2.72 1 0.11) E-11 (2.29 1 0.11) E-11 Agreement Charcoal I-133 (2.84 1 0.03) E-10 (2.59 1 0.03) E-10 Agreement 08:05 I-135 (2.24 1 0.10) E-10 (2.19 1 0.08) E-10 Agreement 10-20-81 Stack Particuiate Sr-91 (1.15 1 0.06) E-10 (1.10 1 0.09) E-10 Agreement Filter Cs-137 (1.35 1 0.08) E-11 (1.26 1 0.07) E-11 Agreement 08:05 Ba-140 (2.14 1 0.06) E-10 (1.99 1 0.05) E-10 Agreement 10-20-81 Offgas Kr-85m (8.1 1 0.3) E-3 (8.3 1 0.4) E-3 Agreement 07:50 Kr-87 (5.56 1 0.15) E-2 (4.8 1 0.3) E-2 Agreement 10-21-81 Kr-88 (2.9 1 0.2) E-2 (2.8 1 0.3) E-2 Agreement Xe-135m (2.0 1 0.2) E-1 (1.36 1 0.03) E-1 Agreement Xe-135 (3.44 1 0.06) E-2 (2.71 1 0.06) E-2 Possible Agreement Xe-138 (1.40 1 0.10) E-2 (7.89 1 0.15) E-1 Possible Agreement
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TABLE 1.
THE RESULTS OF THE COMPARISONS (CONTINUED)
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SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARIS0N RESULTS IN MICR0 CURIES PER MILLILITER Health Physics Air Sample "A" Co-60 (4.7 1 0.7) E-10 (5.3 1 0.4) E-10 Agreement Pump Room 14:57 Cs-137 (2.6 1 0.9) E-11 (3.2 1 1.5) E-11 Agreement 10-19-81 Reactor Water I-131 (3.33 1 0.07) E-4 (4.6 1 1.2) E-4 Possible Agreement 02:40 10-20-81 I-132 (1.42 1 0.05) E-2 (1.62 1 0.07) E-2 Agreement I-133 (4.21 1 0.03) E-3 (5.0 1 0.2) E-3 Agreement I-135 (4.77 1 0.15) E-3 (4.7 1 0.4) E-3 Agreement Simulated Liquid Co-57 (3.88 1 0.04) E-5 (3.98 1 0.47) E-5 Agreement Rad Waste Std. DG0-2 Co-60 (1.94 1 0.02) E-4 (1.96 1 0.04) E-4 Agreement Cs-137 (1.68 1 0.02) E-4 (1.99 1 0.05) E-4 Agreement Y-88 (3.77 1 0.08) E-4 (4.17 1 1.4) E-4 Agreement Waste Sample H-3 (6.78 1 0.02) E-3 (6.61 1 0.66) E-3 Agreement Tank B WS-877-80 Sr-90 (4.6 1 0.5) E-8 (3.7 1 0.7) E-8 Agreement 14:30 5-13-80 Gross Alpha (0 1 2) E-9 (3.6 1 4.0) E-7 No Comparison Gross Beta (3.5 1 0.2) E-6 (4.96 1 0.80) E-6 Possible Agreement
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l 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 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 RATIO = NRC REFERENCE VALUE Possible Possible Resolution Agreement Agreement A Agreement B
<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 - 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
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"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
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Tritium analyses of liquid samples.
Iodine on absorbers I
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
895r and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same i
reference nuclide.
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