IR 05000298/1979008
| ML19241B569 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/30/1979 |
| From: | Brown G, Cain C, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19241B564 | List: |
| References | |
| 50-298-79-08, 50-298-79-8, NUDOCS 7907190049 | |
| Download: ML19241B569 (9) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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IE Inspection Report No. 50-:98/79-08 License No. DPR-46 Licensee: Nebraska Public Power District (NPPD)
Docket No. 50-298 Facility:
Cooper Nuclear Station (CNS)
Inspection Conducted: April 30 - May 4, 1979 Inspectors:
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Blaine Murray, Radiati6'n Sp hialist IDatel aM4 s bM 5/27[77 Charles Cain, Radiation Specialist Date Approved by: /
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' Glen D. Browri, Chief, Yu'el Facility and
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Material Safety Branch Inspection Summary Inspection on April 30 - May 4, 1979 (Report No. 50-298/79-08)
Areas Inspected:
(1) Routine, announced Radiation Protection inspection during refueling activities includ:ng radiation protection procedures, advanced planning and preparation, radiological training, exposure control, respirat ry protection program,.. posting and controls, audits performed by the licensee, survey results, plant tours, independent measurements made by the inspector, radioactive and contaminated material control, follow-up action on previously identified items; and (2) analytical measurement results.
The inspection inve'"ed sixty-four (64) hours by two (2) NRC inspectors.
Results: No items of noncompliance or deviation were identified.
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Details 1.
Persons Contacted (NPPD)
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C. Lessor, Station Superintendent J. V.
Sayer, Chemistry and Health Physics Supervisor R. W. Seir, QA Specialist R. J. Mcdonald, Health Physicist J. R. Warren, Radiochemist W. F. Gilbert, Training Coordinator R. Brungardt, Shift Supervisor
- Denotes those attending the exit interview.
2.
Scope.of Inspection The purpose of this inspection was to review the lic. nsee's Radiation Protection Program, including refueling activities, for the period April 1, 1978, through April 30, 1979, and documentation of the analytical measure-ment results.
3.
Advanced Planning and Preparation The inspectors examined the licensee's program for providing advanced planning and preparation by the Health Physics staff.
The Chemistry and Health Physics Supervisor stated that he is provided sufficient advanced information regarding work involving radiation control to enable proper planning and preparation by the Health Physics staff.
The inspectors also examined the inventory of supplies and equipment.
No items of noncompliance or deviations we re noted.
4.
Radiological Training The inspectors reviewed the licensee's radiological training program to determine compliance with 10 CFR 19.12 and the FSAR.
Attention was given to training of non-regular personnel involved with the refueling.
The following areas were examined:
Scope and content of training Initial training Refresher training Training of the Health Physics Staff
. Documentation of training The inspectors interviewed five (5) new contract employees regarding material covered during the training sessions.
In additions, training q{u U
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records were examined for six (6) new plant employees, eighteen (18)
contract personcel, and fifteen (15) regular plaut employees.
See paragraph 11.b for comments regarding training procedures.
No items of noncompliance or deviations were noted.
5.
Exposure Control The inspectors reviewed exposure records for permanent plant employees, transient workers, visitors, and terminated personnel to determine compliance with 10 CFR 20 reqairements.
No items of noncompliance or deviations were identified.
6.
Respiratory Protection Program The inspectors examined the licensee's respiratory protection program to determine compliance with 10 CFR 20.103.
No items of noncompliance or deviations were identified.
7.
Posting and Control The inspectors made several visits to various plant areas during April 30 -
May 4,1979, to observe work activities. Attention was given to the following items:
Special Work Permit (SWP) areas
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Housekeeping Visitor control Acctss control into restricted areas Identification and control of contaminated areas Radioactive materials storage areas
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Laundry facilities Health Physics supplit, and equipment Respirator cleaning and storage areas Health physics counting room First Aid supplies
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Radioactive waste handling and storage areas
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Independent measurements made by the inspectors The above visits included a review of the licensee's program to determine compliance with the following requirements:
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10 CFR 20.203 10 CFR 20.207
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Special Work Permit (SWP) requirements
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No items of noncompliance or deviations were noted.
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8.
Radioactive and Contaminated Material Control The inspectors examined the licensee's program for controlling contaminated tools and equipment.
No items of noncompliance or deviation were identified.
9.
Su rveys The inspectors reviewed the licensee's survey program to determine compliance with established procedures, 10 CFR 20.201 and 10 CFR 20.401.b.
No items of noncompliance or deviations were identified.
10.
Instruments and Equipment The inspectors examined the inventory, response tests, and calibrations regarding Health Physics instruments and equipment to determine compliance with established procedures and Technical Specification requirements. This involved a review of the following types of instruments and equipment:
Portable survey instruments Fixed perconnel monitoring equipment (e.g. portal monitors, friskers,
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hand and foot counters; Constant air monitors
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Portable air samplers
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Pocket dosimeters Area radiation monitors
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Personnel monitoring devices
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Whole body counters
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See paragraph 11.a for comments regarding calibration procedures for the whole body counter.
No items of ndncompliance or deviations were noted.
11.
Procedures The inspectors reviewed selected Health Physics procedures regarding scope and content.
In addition, the inspectors also reviewed changes and revisions made to existing radiological procedures between June 1, 1978, and May 1, 1979.
It was noted that changes to the procedures were properly reviewed and approved by designated licensee personnel.
The following items were discussed with the licensee regarding scope and content of certain procedures:
a.
Whole Body Counter Calibration H. P. Procedure 9.1.8
" Bio-Assay and Whole Body Counting" contains only rather limited details regarding the calibration of the whole
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body counter.
The licensee stated that the above procedure will be expanded to cover such items as:
Acceptance limits
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Activity of calibration sources
. Radionuclides
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Phantom Arrangement Evaluation of Body Btrdens versus MPC hours b.
Training Outline ADM Procedure 1.5
" Training Program" contains basic guidelines regarding radiological training requirements.
However, the licensee has not d veloped a formal outline for the subjects to be covered during training sessions.
Presently, each Health Physicist assigned to conduct a particular training session has developed an individual draft outline.
The licensee state that single formal outline will be written to ensure that uniform training is provided.
12.
Notifications and Reports The inspectors examined record of notifications and reports to determine compliance with 10 CER 19 and 20 requirements.
No items of noncompliance or deviations were noted.
13.
H. P. Logs and Radiological Incident Reports The inspectors examined radiological activities documented in the Health Physics Logs and Radiological Incident Reports for the period June 1, 1978, thru May 1, 1979.
It was noted that timely follow-up action was either completed or initiated for those items requiring such action.
No items of noncompliance or deviation. were noted.
Miscellaneous Radioactive Material Sources The inspectors reviewed the licensee's program regarding miscellaneous sources to deterrine compliance with plant procedures, Technical Specifica-tions 3.8 and 4.8, and 10 CFR 71.
No items cf noncompliance or deviations were identitied.
15.
Audits The inspectors examined audits performed by the licensee of the radiation protection progra -
The licensee's records indicated that an audit was performed during July, 1978. The eport was reviewed for scope and timely follow-up action for items identified during tie audit.
No items of noncompliance or deviations were identified.
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16.
Analytical Measurements a.
Confirmatory Measurements Program Confirmatory measurements were performed on the following samples:
(1) Liquid waste (2) Off gas (3) Stack charcoal cartridge (4) Stack particulate filter The confirmatory measurements consist of comparing measurements made by the licensee and NRC's reference laboratory, Idaho Health Services Laboratory (IHSL).
IHSL's measurements are referenced to the National Bureau of Standards by laboratory intercamparisons.
Confirmatory measurements are only made for those radionuclides identified by IHSL as being present in concentrations greater than 10% of the respective MPC's for liquid and gas samples and above an established Lower Limit of Detection (LLD) for stack samples.
Attachment hm-1 contains the criteria used to compare results.
Attachment No. 2 lists the LLDs for stack samples.
b.
Results The following tables show the comparison results:
(1) Liquid Waste (Collected December 19, 1978, ac
'iay 3, 1979)
Radionuclide NRC Measurement NPPD Measurement Decision
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r 1.45+0.35E-05 uCi/ml 3.8+0.32E-05 uCi/ml Disagreement I
4.62+0.17E-05 uCi/ml 4.3810.05E-05 uCi/ml Agreement 134 10.2H-M uG/ml W10.0005 uG/d
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s 137 Cs 8.3210.24E-05 uCi/ml 7.710.08E-05 uCi/ml
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13g
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Cs 4.12+0.67E-06 uCi/ml 4.77+0.6E-06 uCi/ml
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n 5.5+0.17E-05 uCi/ml 6.79i0.07E-05 uCi/ml
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"Ag 3.44+0.53E-06 uCi/ml 1.12E-06 uCi/ml Disagreement Fe 6.92+0.89E-06 uCi/ml 1.08+0.05E-05 uCi/ml
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Zn 1.0+0.08E-05 uCi/ml 4.48{0.9E-06uCi/ml
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0Co 1.3210.038E-04 uCi/ml 1.5910.02E-04 uCi/ml
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ggSr 1.8+0.3E-07 uCi/ml 3.49+0.09E-07 uCi/ml
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90Sr 1.4i0.7E-08 uCi/ml 1.88io.3E-08 uCi/ml
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gross beta 3.5{0.1E-05u,i/ml 3.95[0.11E-05uCi/ml
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H 1.36+0.02E-03 uCi/ir 1.5710.01E-03 uCi/ml
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(2) Off Gas (Collected December 19, 1978)
Radionuclide NRC Measurement NPPD Measurement Decision Xe 1.3010.07E-02 uCi/ml 2.1010.01E-02 uCi/ml Agreement (3) Stac Charcoal Cartridge (Collected December 18, 1978)
Radionuclide NRC Measurement NPPD Measurement Decision 131 I
8.0810.27E-03 uCi/ sample 8.0910.11E-03 uCi/ sample Agreement (4) Stack Particular Filter (Collected April 30, 1979)
Radionuclide NRC Measurement NPPD Measurement Decision Cs 9.610.3E-04 uCi/ sample 1.1210.02E-03 uCi/ sample Agreement
I 6.610.3E-04 uCi/saeple 8.6410.09E-04 uCi/ sample
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134Cs 9.710.3E-04 uCi/ sample 1.1410.13E-03 uCi/ sample
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136Cs 5.410.1E-05 uCi/ sample 5.2710.58E-05 uCi/ sample 58Co 8.610.9E-05 uCi/ sample 7.110.8E-05 uCi/ sample
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60 2.410.1E-04 uCi/ sample 2.410.1E-04 uCi/ sample
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Mn 14g 2.110.1E-04 uCi/ sample 2.910.09E-04 uCi/ sample
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La 2.510.6E-05 uCi/ sample 6.3210.8E-05 uCi/ sample
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No items of noncompliance or deviations were noted.
17.
Exit Interview At the conclusion of the inspection on May 4, 13/9, the inspection findings were discussed with the individual denoted in paragraph 1.
The inspector summarized the scope of the inspection and the inspection findings.
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ATTACHMENT NO. 1 Criteria for Comparing Analytical Measureme, s 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 Uncertainly Ratio = Licensee Value NRC Value Comparisons are rade by first determining the resclutica and then reading across the same line to the corresponding ratio. Trie 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 0.5 - 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 adso-bers.
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
90 Sr and Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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ATTACIDIENT NO. 2
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LLDs for Nuclides on Particulate and Charcoal Filters htclide LLD (uCi/ sample)
Cr 1E-04 54Mn 1.5E-05
}8Co 1.5E-05 39Fe 3E-05 57Co 2E-05 60Co 3E-05 65 Zn 3E-05 89Sr IE-05 904 2E-07 137. r I
2E-05 134Cs 2E-05 137 Cs 2E-05 140Ba 2E-05 140 La 4E-05 141 Ce 2E-05 100Ce IE-04
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