ML20214G916
| ML20214G916 | |
| Person / Time | |
|---|---|
| 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) | |
See also: IR 05000131/1987001
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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:
/
/l.d8Il
/3!
B. Mtirray, Chief, Facil
s Radiological
- Date'
Protection Section
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Inspection Summary
Inspection Conducted April 13-17, 1987-(Report 50-131/87-01)
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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.
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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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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.
,
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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f.
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
,
81402
Reports of Safeguard Events
02.01 - Trace Investigation of Shipments
02.02 - Incidents
02.03 - Events
,
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
!
02.03 -- Control
o', Access to Safeguards Information
02.04 - Pnysica.1 Protection of Safeguards Information
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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
,
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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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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b.
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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