IR 05000131/1987001
ML20214G916 | |
Person / Time | |
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Site: | 05000131 |
Issue date: | 05/13/1987 |
From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | |
Shared Package | |
ML20214G875 | List: |
References | |
50-131-87-01, 50-131-87-1, NUDOCS 8705270218 | |
Download: ML20214G916 (9) | |
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSTION
REGION IV
'NRC Inspection Report: 50-131/87-01 License:
R-57 Docket:
50-131 Licensee: Omaha Veterans Administration Hospital (OVAH)
4101 Woolworth Avenue Omaha, Nebraska 68105 Facility Name: Omaha Veterans Administration Medical Center (OVAMC) TRIGA Research Reactor Inspection At: OVAMC Site, Omaha, Nebraska Inspection Conducted: April 13-17, 1987 Inspector:
A-3 87 R./E. Bae'r, Radiation Specialist, Facilities Date Radiological Protection Section Approved:
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B. Mtirray, Chief, Facil s Radiological
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Protection Section
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Inspection Summary Inspection Conducted April 13-17, 1987-(Report 50-131/87-01)
I Areas Inspected: Routine, unannounced inspection of the licensee's program
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including:
reactor operations, physical security, safeguards, transportation
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of radioactive materials, and emergency planning.
I Results: Within the areas inspected, two violations were identified (operator l
requalification program, see paragraph 4a and Technical Specification (
Surveillances, see paragraph 4b). No deviations were identified.
L 8705270218 870520:.
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-2-DETAILS 1.
Persons Contacted OVAH
- R.
L. Turcotte, Hospital Director
- A. J. Blotcky, Reactor Supervisor, Senior Reactor Operator
- G. T. Hansen, Research Chemist, Senior Reactor Operator C. L. McClellan, Chief of Security
- J. J. Phillips, Associate Hospital Director The NRC inspector also interviewed several other licensee emplovees including operatioiis and administrative personnel.
- Denotes those present during the exit interview on April 17, 1987.
2.
Facility Status An active program continues to exist concerning operation of the reactor.
The reactor is mainly used to support research work performed by other departments at the hospital. The reactor use involves the irradiation of biological and chemical samples. The reactor is operated about 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> per week. The reactor operated 777 hours0.00899 days <br />0.216 hours <br />0.00128 weeks <br />2.956485e-4 months <br /> in 1984, 801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br /> in 1985, 1328 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.05304e-4 months <br /> -in 1986, and 344 hours0.00398 days <br />0.0956 hours <br />5.687831e-4 weeks <br />1.30892e-4 months <br /> for the period ending April 16, 1987.
When in use, the reactor operates at a steady-state power level of 18 kw.
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3.
Program Areas Inspected The following program areas were inspected.
Unless otherwise noted, the inspection was completed and revealed no violations, deviations, unresolved items, or open items. Notations after a specific inspection item are used to identify the following:
I = item not inspected or only partially inspected; V = violation; D = deviation; U = unresolved item; and 0 = open item.
Procedure Inspection Requirements 40750 Class II Research and Test Reactors Operations Procedures 02.01 - Initial Interview 02.02 - Initial Walkthrough or Site Tour 02.03 - Records a.
Logs and Records b.
Procedures c.
Requalification Training-V (see paragraph 4)
d.
Surveillance-V (see paragraph 4)
e.
Experiments
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Health' Physics g.
Design Changes, Audits, and Committees h.
Emergency Planning-02.04 - Observations 81401 Physical Security Program 02.01 - Plan Revisions 02.02 - Unapproved Revisions 02.03 - Records of Revisions 02.04 - Procedures
02.05 - Security Plan Review 02.06 - Continoency Plan Review
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81402 Reports of Safeguard Events 02.01 - Trace Investigation of Shipments 02.02 - Incidents 02.03 - Events
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02.04 - Quality of Reports 81431 Fixed Site Physical Protection of Special Nuclear Material of Low Strategic Significance 02.01 - Use ar.d Storage 02.02 - Detection and Surveillance 02.03 - Acr.ess Control 02.04 - Response 02.05 - Testing and Maintenance
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81810 Safeguards Information 02.01 - Safeguards Information Identification 02.02 - Marking of Safeguards Information
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02.03 -- Control o', Access to Safeguards Information 02.04 - Pnysica.1 Protection of Safeguards Information i
02.05 - Controls Over Disclosure of Safeguards Information 02.06 - Controls Over Data Processing System 02.07 - Removal of Safeguards Information 85102 Material Control and Accounting
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02.01 - Possession and Use of SNM 02.02 - Control and Accounting of SNM 86740 Transportation Activities 02.01 - Management Controls 02.02 - Indoctrination and Training Programs 02.03 - Audit Program
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.4-4-02.04 - Quality Assurance Program 02.05 - Procurement and Selection of Packagings 02.06 - Preparation of Packages for Shipment 02.07 - Delivery of Completed Packages to Carriers
'02.08 - Receipt of Packages 02.09 - Periodic Maintenance of Packagings 02.10 - Records and Reports 4.
Violations a.
40750 Item 02.03c Requalification Training 10 CFR Part 50.54(1-1) requires the licensee to have in effect an operator requalification program which as a minimum meets the requirements of Appendix A of 10 CFR Part 55. The licensee's operator requalification program is described in Chapter 5 of the application for renewal of License No. R-57 for the Omaha Veterans Administration Medical Center, dated May 10, 1979. The requalification program included planned lectures, an annual evaluation of the licensed operator's knowledge and performance, and records for each individual and that contain the following information:
' Current copy of either the individual's reactor operator or C
senior reactor operator license.
Copies of all written examinations administered to the
individual and correct answers given to the individual during the requalification period.
The annual evaluations of the individuals documented in a memorandum for record.
The individual's -requalification program progress checklist.
The summary of additional training received by the individual documented in a memorandum for record and any additional documentation.
The NRC inspector determined on April 17, 1987, that the licensee had not implemented a formal, documented operator requalification program since November 1985. The licensee stated they had held informal tutoring sessions for the f.enior reactor operator during reactor operations between November 1985 and April 16, 1987, but had not documented the contents or dates of these sessions.
The failure to conduct an operator requalification program is an apparent violation of 10 CFR Part 50.54(1-1).
(313/8701-01)
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40750 Item 02.03d Surveillances
. Technical Specification (TS) Appendix A requires that the licensee perform specific safety system surveillances/ calibrations.
Section 4.4. " Primary Coolant Conditions" states that the conductivity and pH of the primary coolant water shall be measured at least once every 2 weeks.
The NRC inspector determined on April 17, 1987, that the licensee had not performed the primary coolant water pH surveillances during the periods: January 23 and February 14, 1986; February 20 and March 20, 1986; May 9, 'and June 3,1986; July 3 and July 23, 1986; and December 18, 1986, and February 2, 1987.
The NRC inspector noted that the pH measurements before and after each period listed above were within the acceptable range specified in T.S. 4.4(2).
The failure to perform the required surveillance within the specified time period is considered an apparent violation of TS Section 4.4.
(131/8701-02).
5.
Exit Interview The NRC inspector met with the personnel identified in paragraph 1 at the conclusion of the inspection on April 17, 1987.
The.NRC inspector summarized the scope and findings of the inspection.
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