IR 05000262/1980002
| ML19337B159 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 08/15/1980 |
| From: | Dean S, Gagliardo J, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19337B145 | List: |
| References | |
| 50-262-80-02, 50-262-80-2, NUDOCS 8010010344 | |
| Download: ML19337B159 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-262/80-02 License No. R-109 Licensee:
Brigham Young University (BYU)
Docket No.
50-262 Provo, Utah Category H
Facility:
L-77 Reactor (10 Watts)
Inspection Condu ted: July 21-23, 1980 Inspector: h'*
I O 3 1 % R. Dean, Reactor Inspector Dare
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O Reviewed by:, y I
J.(E.Gagiardo, Chief,NuclearSupportSection Date N[C du -~-
rP5 /iJ Approved by:
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i G. L. Madsen, Chief, Reactor Operations and Date
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Nuclear Support Branch Inspection Summary Inspection on July 21-23, 1980 (Report No. 50-262/80-02)
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Areas Inspected: Routine, unannounced inspection of the licensee's organization,
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operations and maintenance logs, licensee's internal review and audit program, operator requalification program, operating procedures, surveillance require-ments, experiment review, radiation protection, environmental protection, and emergency planning programs.
The inspection involved 14 on site inspection
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hours by one NRC inspector, i
Results: Of the ten areas inspected no items of noncompliance were identified in nine areas.
One item of noncompliance was identified in the remaining area.
(infraction - failure to demonstrate knowledge and understanding of the facility after exceeding four months inactivity by a licensed SRO, paragraph 8.)
801001086
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DETAILS 1.
Persons Contacted
- Dr. Dwight Dixon, Reactor Facility Chief Wallis Hansen, Campus Safety Officer
- Dr. Max Hill, Chairman Reactor Safety Committee
- Dr. Gary Jensen, Reactor Supervisor Fred Nelson, Canpus Radiation Safety Officer
- Denotes those present during the exit interview.
2.
Licensee Action on IE Bulletin No. 79-19
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IE Bulletin 79-19, dated August 10, 1979, provided information, recommenda-tions and contained a request for data of the licensee.
The inspector reviewed the licensee's response dated October 4, 1979.
In discussion with the inspector, the licensee committed to implement the following bulletin recommendations:
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a.
Establish detailed instructions and operating procedures for all personnel involved in the transfer, packaging, and transport of low level radioactive material, b.
Provide training and periodic retraining in DOT and NRC regulatory requirements, the v trial ense requirements, in their instruc-tions and operr. tin
__aures.
c.
Maintain a record of training, dates, attendees, and subject material.
d.
Establish and implement a management controlled audit of all transfer, packaging and transfer activities to ensure safety and compliance with regulatory requirements.
This item will remain open until tl.e actions taken are reviewed in a future inspection.
(262/8002-01)
3.
Plant Status
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During this inspection the reactor was operated at power.
The inspector observed the following:
a.
Reactor pre-startup checkout," Console Operation Check List."
b.
Reactor-start up and approach to criticality, c.
Reactor power operation and control of power changes.
d.
Reactor experiment, " Irradiation of Silver."
e.
Reactor shutdown.
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No items of noncompliance or deviations were noted.
4.
Organization The inspector reviewed the operational and administrative organization regarding the reactor to determine compliance with Technical Specification requirements.
Such items as membership and meetings of Reactor Safety Committee, minimum staffing composition for operation, and supervision of the reactor facility were examined.
No items of noncompliance or deviations were noted.
5.
Plant Tour The inspector toured the facility on July 22, 1980.
Attention was given to the following:
Conditions within the facility
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Access Control Posting and Labeling Availability of Radiation Survey Equipment Emergency Equipment No items of noncompliance or deviations vere noted.
Logs and Records
The inspector reviewed the following logs for the period June 1978 to July 1980 to determine that operations and maintenance activities had been prope.cly conducted.
Daily Log
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Facility Log Reactor Maintenance Log All maintenance and operations activities appear to have been conducted in a manner consistent with Technical Specifications and Administrative Procedures.
The inspector selected the pumping of gas from the reactor core for a detailed analysis. The operation was detailed in the licensee's Facility Log. The vacuum had degraded gradually from 24.4" of Hg to near the scram setpoint of 21" of Hg.
A temporary apparatus was designed utilizing a hand pump and gas line connected to a bell jar.
The vacuum
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was gradually lowered to 24.7" of Hg and the apparatus removed.
The operation was performed on July 17, 1979, and reviewed by the Reactor Safety Committee on July 31, 1979.
No items of noncompliance or deviations were identified.
7.
Review and Audit The minutes of the Reactor Safety Committee were examined by the inspector.
The Committee met quarterly as required by the Technical Specifications and routinely made the following reviews:
Technical Specification Requirements
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Experiments Maintenance and Operations Logs i
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Radiation Surveys i
No items of noncompliance or deviations were noted.
8.
Operator Requalification Program The inspector reviewed activities conducted under the BYU " Operator Requali-fication Program," approved by the NRC on November 24, 1974, and Technical Specification requirements.
Two members of the facility staff were licensed Senior Reactor Operators.
The Chairman of the Reactor Safety Committee chose not to renew his license i
as Senior Reactor Operator upon expiration September 9,1979.
I It was noted that one licensed senior reactor operator, had exceeded a
four month period of activity supervising reactor operations.
The Facility l
Log indicated that the operator had supervised the reactor on the following
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dates:
October 23, 1978 March 16, 1979 September 13, 1979 The period between each operation was greater than four months.
No records were available to indicate that the senior reactor operator had demonstrated to the Commission that his knowledge and understanding of the facility was satisfactor, s o.
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10 CFR 55.31(e) " Conditions of the Licenses," states in part that, "If a licensee has not been actively performing the functions of an operator or senior operator for a period of four months or longer, he shall, prior to resuming activities licensed to this part, demonstrate to the Commission that his knowlege and understanding of facility operation and administra-tion are satisfactory." Section J of tne BYU, " Operator Requalification Program," November 6, 1974, requires that:
"Recertification.
If an operator has not been actively performing operator function for four months or longer, he shall demonstrate his knowledge and understanding of facility operations, including changes in operational procedures, license require-ments or facility design and also all abnormal or emergency procedures, to an authorized facility officer before resuming activities.
For all operators except the facility chief, this recertifying officer is the facility chief; for the facility chief, it is the chairman of the Reactor Safety Committee.
The recertifying officer shall, after obtaining a demonstration of the operator's proficiency, certify the same to the U. S.
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Atomic Energy Commission."
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The failure of a senior reactor operator, prior to resuming activities of his license, to demonstrate that his knowledge and understanding of facility operation were satisfactory to the Commission constitutes an apparent item of noncompliance at the infraction level.
(262/8002-02)
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9.
Procedures The inspector reviewed operating procedures to determine compliance with Technical Specifications.
Most of the procedures associated with the reactor are found in the BYU L-77 Reactor Facility Procedures Manual, Revision 1, dated November 1974.
The manual contains procedures covering such items as:
Organization
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Training Written Instructions and Documents Records Keys, Access, and Security Operation Health Physics Emergency Preparedness
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No items of noncompliance or deviations were noted.
10.
Surveillance The inspector reviewed Technical Specification requirements for surveillance tests, reactor core limits, and control and instrumentation systems.
The licensee's records indicated that limits regarding excess reactivity, control and safety rod worths, core tank, scram and safety systems were not exceeded.
The inspector did not identify any surveillance tests which were not per-formed as specified in Technical Specifications.
The surveillance test results records did not indicate any unusual conditions.
No items of noncompliance or deviations were noted.
11.
Experiments The inspector examined records of experiments placed in the reaccor to
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determine compliance with Technical SpecificationsSection II, Item E.
The licensee's records indicated that no new experiments have been placed in the reactor since the previous inspection.
No items of noncompliance or deviation were identified.
12.
Rajiological Control The inspector examined the licensee's program to determine compliance with 10 CFR 20 requirements.
The inspector performed a radiation survey utilizing the licensee's Thyrac III radiation instrument and found those areas surveyed to be at background levels, with the reactor shutdown.
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No items of noncompliance or deviation were noted.
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13.
Environmental Protection
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The licensee does not maintain a detailed environmental surveillance program (e.g., collection and analysis of water, soil, vegetation samples).
There are no specific license requirements that such a program be implemented.
A licensee representative stated that no liquid effluent releases have been made since the last inspection.
Reactor operating data indicates that airborne effluents have been within 10 CFR 20 limits.
No items of noncompliance or deviation were noted.
14.
Emergency Planning
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Procedure BYU-NUC-003 titled, " Procedures for Emergency Evaluation and Recovery," outlines the licensee's emergency procedures.
It was noted
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that an emergency drill was conducted annually.
No items of noncompliance or deviations were noted.
15.
Exit Interview An exit interview was held with representatives of the license on July 23, 1980, at the conclusion of this inspection. The findings noted in the previous paragraphs were di cussed with and acknowledged by these repre-sentatives.
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