ML20129E264
| ML20129E264 | |
| Person / Time | |
|---|---|
| Site: | 05000131 |
| Issue date: | 09/23/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20129E231 | List: |
| References | |
| 50-131-96-01, 50-131-96-1, NUDOCS 9610010027 | |
| Download: ML20129E264 (12) | |
See also: IR 05000131/1996001
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ENCLOSURE 2
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.: 50-131
License No.: R-57 i
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Report No.: 50-131/96-01 l
Licensee: Omaha Veterans Administration Medical Center
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Facility: TRIGA Mark 1 Nuclear Reactor
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Location: 4101 Woolworth Avenue
Omaha, Nebraska
Dates: August 26-29,1996 ;
Inspector: L. T. Ricketson, P.E., Senior Radiation Specialist
Plant Support Branch
, Approved By: Blaine Murray, Chief, Plant Support Branch
Division of Reactor Safety
Attachment: Partial List of Persons Contacted
List of Inspection Procedures Used
List of items Opened and Closed ,
List of Procedures Reviewed
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9610010027 960923
PDR ADOCK 05000131
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EXECUTIVE SUMMARY
Omaha Veterans Administration Medical Center
NRC Inspection Report 50-131/96-01
This routine, announced inspection reviewed the reactor operations, reactor maintenance,
surveillance testing, experiments, reactor oversight, reporting, reactor operator
requalification, radiation protection, emergency preparedness, and security programs.
Operations
- Reactor operations were conducted well. The reactor operator was knowledgeable
of routine operating procedures. No safety limits or limiting conditions for operation
of the reactor were exceeded. Experiments were reviewed appropriately and
performed safely (Sections 01, and 04).
- Standard operating procedures generally provided adequate guidance to ensure that
operations and surveillances were conducted properly and consistently. However, a
violation was identified involving the lack of written standard operating procedures
for some surveillance activities (Section 03).
- A Non-Cited Violation was identified involving the failure to include all required i
topics in the annual operating reports (Section 01).
- The operator requalification program was conducted as required (Section 05).
- Adequate oversight of reactor operations was provided by the Reactor Safeguards
Committee (Section 07).
Facility Suncort
- Appropriate radiation protection practices were implemented. Minimal radiation
hazards were present with the reactor operated as observed (Section R1).
- A good emergency preparedness program was maintained and the physical security
plan was properly implemented (Sections P1 and S1).
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Report Details I
1. Operations ,
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01 Conduct of Operations
a. Scope of Inspection
The inspector interviewed a senior reactor operator and reviewed the following: '
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- Reactor logs
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- Annual operating reports for 1993-1995.
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b. Observations and Findinos
The reactor normelly operated at a steady-state power level of approximately 18 kilowatts.
Reactor power levels did not exceed the limiting condition of Technical Specification 3.1.
Reactor use declined steadily since 1993. r
Seven unscheduled reactor shutdowns occurred in 1993, three in 1994, and two in 1995. l
The majority of the unscheduled shutdowns were caused by electrical noise or electrical
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power interruptions.
The major maintenance activity involved a repair of the pneumatic sample transfer system.
A new fuel element was installed in the reactor in October 1995.
The required technical specification surveillance tests were conducted.
Four new experiments were added since the previous inspection. Experiments 94-1
through 94-4, were reviewed and approved by the Reactor Safeguards Committee, in
accordance with Technical Specification 6.8. The reactivity worth of the experiments did
not exceed the limit of Technical Specification 3.6. Samples which were irradiated met the
requirements of Technical Specification 3.7. No unreviewed safety questions were
identified.
Technical Specification 6.9.1.2 requires, in part, that each annual operating report include
a brief narrative summary of major surveillance tests and inspections. The only
surveillance test discussed in the 1994 and 1995 Annual Operating Reports was the fuel
inspection surveillance. Other surveillances were not discussed. Technical
Specification 6.9.1.2 also requires that each annual operating report include a brief
description of any new or untried experiments or tests performed during the reporting
period that are not described in the Safety Analysis Report. The 1994 annual report did
not include a discussion of the Experiments 94-1 through 94-4. The inspector identified
the omission of these items from the annual operating reports as a violation of Technical
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Specification 6.9.1.2 (131/9601-01). This failure constitutes a violation of minor
significance and is being treated as a Non-Cited Violation, consistent with Section IV of the
NRC Enforcement Policy. The licensee acknowledged the inspector's comments and
stated that the requirements would be reviewed to ensure all necessary inforrnation was ;
included. ;
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c. Conclusions '
Reactor operations were conducted well No safety limits or limiting conditions for
opvation of the reactor were exceeded and required surveillances were performed.
Experiments were reviewed appropriately and performed safely. The annual operating
reports did not comply with all documentation requirements.
O3 Operatior.s Procedures and Documentation
a. Inspection Scope
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The procedures listed in the attachment were reviewed.
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b. Observations and Findinas '
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Procedure 16, " Conduct of Irradiations and Experiments" was the only procedure added ,
since the previous inspection. The procedure was approved by the reactor supervisor, as l
required.
Technical Specification 6.7 requires, in part, that there shall be written procedures that
cover the surveillance, testing, and calibration of instruments, components, and systems !
involving nuclear safety. The inspector identified that standard operating procedures were
available to provide guidance for conducting some surveillances, but not others. Although
the surveillance activities were conducted correctly at the proper frequencies, no
procedures were available to provide guidance and ensure consistency for nuclear safety
systems involving the measurement of scram times (required by Technical Specification 4.2.2(1)), testing of pool level channel operability (required by Technical Specification 4.2.2(2)), and verification of ventilation system operability (required by Technical
Specification 4.2.4). The inspector identified the lack of written testing and surveillance
procedures as a violation of Technical Specification 6.7 (131/9601-02).
c. Conclusions _
Standard operating procedures generally provided adequate guidance to ensure that l
operations and surveillances were conducted properly and consistently. However, this was
not true in all cases, and a violation was identified because standard operating procedures
were not implemented to provide guidance for some surveillance activities involving nuclear
safety systems.
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04- Operator Knowledge and Performance
j a. Inspection Scone
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The inspector interviewed a senior reactor operator and observed a reactor startup and l
showdown. Standard operating procedures were reviewed as the senior operator I
conducted reactor operations. l
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- b. Observations and Findinas ,
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c. Conclusions
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. The reactor operator was knowledgeable of routine operating procedures. >
05 Operator Training and Qualificaticn '
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a. Insoection Scoce ,
Documentation of the following was reviewed: {
- Lectures ;
- Observations of manipulation of controls and understanding of operations and
procedures
- Discussions of f acility design, changes, procedures changes, and facility license ,
changes
- Reviews of abnormal emergency procedures
- Annual written examinations
b. Observations and Findinas
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Lectures were conducted as required. Observations of operator manipulations were
documented. The last observation was June 1996.
Section 3.c. of the licensee's Requalification Program for Licensed Reactor Operators
stated that information should be included in on-the-job training so that each licensed
operator and senior operator is cognizant of facility design changes, procedure changes,
and facility license changes. There was no documentation of a discussion concerning the
implementation of Standard Operating Procedure 16. The procedure was implemented
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since the previous inspection. However, the senior operator was knowledgeable of the. ,
procedure, so the inspector concluded that the on-the-job training functioned appropriately. ,
A review of the abnormal / emergency procedures was conducted. Annual written
examinations for 1994,1995, and 1996 were given and successfully passed by the senior
reactor operator.
c. Conclusions
The operator requalification program was conducted as required.
06 Operations Organization and Administration
The inspector reviewed the licensee's organization and determined that no changes had
been made in the structure of the organization, and it continued to be as described in
Technical Specification 6.2. Since the previous inspection, the only personnel change
involved the radiation safety officer. A new individual was hired to fill the position. The
licensee had two senior reactor operators, one of whom was the reactor supervisor. There
were no reactor operators.
O7 Quality Assurance in Operations
a. Scope of Inspecti_o_n
Minutes of the Retctor Safeguards Committee meetings from December 22,1993 to June-
28,1996 were res iewed.
b. Observations and Findinas
The inspector verified the licensee's review and audit program implemented by the Reactor
Safeguards Committee included approval for facility changes, changes in operating and '
maintenance procedures, and design changes as required by Technical Specification 6.5. ,
The Reactor Safeguards Committee met on a quarterly basis, as required by Technical ,
Specifications. Annual audits were conducted on June 29,1994, June 23,1995, and '
July 7,1996, by a Reactor Safeguards Committee member who was not part of the
reactor staff. The audits reviewed the areas specified in the Technical Specifications.
Biennial reviews of the emergency plan were conducted June 24,1994, and July 8,1996.
A biennial review of the security plan was last conducted on May 25,1995.
c. Conclusions
Adequate oversight of reactor operations was provided by the Reactor Safeguards ,
Committee. 1
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11. Maintenance
M1 Conduct of Maintenance
Other than the addition a fuel element and the repair of the pneumatic sample transfer
system, there had been no major maintenance on the reactor since the previous inspection.
Minor maintenance items were recorded in the reactor log.
Ill Enaineerina
E2 Engineering Support of Facilities and Equipment
There were no reactor design changes since the previous inspection.
IV. Facility Support
R1 Radiological Protection and Chemistry (RP&C) Controls
a. Scope of Inspection
The following documents were reviewed:
Annual review of radiation protection program
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Annual radiation dose summaries for 1993 1995.
Radiation surveys in reactor log books
Weekly contamination surveys
Instrument calibration records
b. Observations and Findinas
Annual reviews of the radiation protection program, in accordance with 10 CFR
20.1101(c), were performed in conjunction with the annual reviews of the medical center
broad license radiation protection program.
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Reactor operators used extremity monitoring in addition to whole body dosimetry. The
extremity monitoring was used to record the dose accrued by the operators when they
handled irradiated samples. Most dosimetry results were minimal. The limits of 10 CFR
20.1201 were not exceeded.
The inspector performed area radiation surveys and confirmed that radiation levels in
unrestricted areas did not exceed the limits of 10 CFR 20.1302(a)(2)while the reactor was
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operating at a power level of 18 kilowatts. The licensee had survey records and area
dosimetry monitoring results as documentation of its radiation measurements. Restricted
areas were posted in accordance with 10 CFR 20.1902. The licensee also performed :
general area contamination monitoring weekly.
Calibrations of the instruments used to perform radiation surveys were performed with
radioactive sources traceable to national standards. Calibrated instruments were available
at the time of inspection.
Workers were provided radiation safety instruction by the reactor supervicor in accordance I
with 10 CFR 19.12.
The inspector determined that the licensee had not transported radioactive materials since
the previous inspection.
The inspector reviewed the licensee's program of material control and accountability to
determine compliance with license conditions and 10 CFR Part 70.
The inspector reviewed material balance and inventory records and determined that the
records were properly maintained in accordance with the requirernents of 10 CFR Part 70
and that the licensee did not exceed the uranium-235 possession limits of License
Condition 2.B.(2). There had been one receipt of fuel since the previous inspection.
Receipt of the material was properly documented. The material was properly stored,
c. Conclusions
Appropriate radiation protection practices were implemented. Minimal radiation hazards
were present with the reactor operated as observed.
P1 Conduct of EP Activities
a. Scoce of Inspection
The following documentation was reviewed:
- Letters of agreement from local offsite support organizations
- Emergency call lists
- Training records
- Exercise and drill scenarios
- Contents of the emergency equipment cart
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b. Observations and Findinas
l Letters of agreement with the Omaha Police Department, Omaha Fire Department, and the
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state of Nebraska were maintained and current.
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The inspector verified that emergency call lists were accurate and provided in the proper
j places. Inventories of the emergency equipment located on the licensee's emergency cart
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were performed at the proper frequency. However, the inspector noted that the radiation
survey instrument (an ion chamber) did not function. The reactor operator stated that the
a instrument was not routinely response tested during the equipment inventories, but this
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would be considered as a possible addition to the inventory.
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Appropriate orientation and training were provided to onsite and offsite emergency
response personnelin accordance with the emergency plan. The inspector confirmed that l
, exercises or drills were conducted November 30,1994 and November 21,1995. The
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frequency was in accordance with the commitments of the emergency plan.
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c. Conclusions
A good emergency preparedness program was maintained.
S1 Conduct of Security and Safeguards Activities
a. Insoection Scope
The inspector interviewed the head of the hospital security force and a senior reactor
operator. Additionally, the inspector compared the facility and equipment with the
description and commitments in the physical security plan.
b. Observations and Findinas
The inspector verified that the site and facilities were as described in the security plan.
There had been no revisions to the security plan since the previous inspection. The
licensee stored and used material only within the controlled access area. Through
interviews with licensee personnel and reviews of logs, the inspector determined that
security for the facility was implemented as specified in the security plan. There had been
no security problems or safeguards events since the previous inspection.
c. Conclusions
The physical security plan was properly implemented.
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V. Manaaement Meetinos
X1 Exit Meeting Summary
The inspector presented the inspection results to the licensee management on August 29,
1996. Licensee management acknowledged the findings presented. The licensee
identified the physical security plan as proprietary information.
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ATTACHMENT
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PARTIAL LIST OF PERSONS CONTACTED
Licensee l
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J. Claassen, Senior Reactor Operator I
M. Christensen, Radiation Safety Officer
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J. Phillips, Director, Veterans Affairs Medical Center '
A. Pribble, Chief, Veterans Affairs Medical Center
D. Shoop, Research Chemist
LIST OF INSPECTION PROCEDURES USED
40750 Class ll Research and Test Reactors Operations Procedure
81401 Plans, Procedures, and Reviews
81403 Receipt of New Fuel at Reactor Facilities
81431 Fix Site Physical Protection of Special Nuclear Material of Luw Strategic
Significance
85102 Material Control and Accounting - Reactors
86740 Inspection of Transportation Activities j
LIST OF ITEMS OPENED AND CLOSED l
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Opened I
131/9601-01 NCV Annual Operating Report Omissions
131/9601-02 VIO Lack of Standard Operating Procedures for Some
Surveillances
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131/9601-01 NCV Annual Operating Report Omissions
LIST OF PROCEDURES REVIEWED
Check Out and Calibration of Reactor Operating instrumentation and Controls
Reactor Start Up
Reactor Shut Down
Cont:ol Rod Calibration
Emergency and Abnormal Conditions
Fuel Loading, Unloading, Storage, and inspection
Control Rod Removal or Replacement
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Maintenance Operations Which May Affect Reactor Safety
Criteria for Evaluating Experiments
Reactor Power Calibration ,
Radiation Monitor Calibration Procedure !
Review and Approval of Changes to Procedures ,
Personnel Radiation Protection l
Administrative Control of Operations and Maintenance
Filling Reactor Tank With Makeup Water
Conduct of Irradiations and Experiments
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