ML20009F422
| ML20009F422 | |
| Person / Time | |
|---|---|
| Site: | 05000538 |
| Issue date: | 06/11/1981 |
| From: | David Jones MEMPHIS STATE UNIV., MEMPHIS, TN |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8107310131 | |
| Download: ML20009F422 (4) | |
Text
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' l'" * ' June 11, 1981 .
Center for Nus leur Sturlues Offsce of the 1) erector (9t)!) 45446AI h Q e'\ ' ,
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[1L $ t Director
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Region II, USNRC gm I' Office of Inspection and Enforcement b 101 Marietta Street, Suite 3100 Lx e Atlanta, GA 30303 'g
Dear Sir,
Enclosed is the follow-up report to a reportable event that occurred at the Memphis State University AGN-201 Nuclear Reactor Facility on June 8, 1981. The report is submitted in accordance with section 6.9.2 of Appendix A to Facility Operating License R-127, Docket lia. 50-538.
An unscheduled power outage occurred during reactor operation which directly caused reactor shutdown. Restoration of electric power service was completed and conditions returned to normal after approximately fifty minutes. Initial notification was made to your office by telephone and confirmed by mailgram on June 9,1981.
Sincerely, D. . Jones Director RLD/sf
Enclosures:
Follow-up Report to Reportable Occurrence #81-1 cc: Mr. C. Julian, USNRC Region II Dr. J. A. Rhodes, MSU Dr. D. W. Cooke, MSU/RSC Mr. R. E. Horn, MSU/RCSC Mr. R. L. ?ietz, MSU/CNS Mr. M. M. Martin, MSU/CNS Mr. D. K. Baer, MSU/CNS
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The Nation's first Regional Center for Nuclear Manpou er Development B1073to131 B10b11 An Equal Opportunity University PDR ADOCK 0500053B S PDR
MEMPHIS STATE UNIVERSITY AGN-201 NUCLEAR REACTOR FACILITY LICENS2 R-127, DOCKET N0. 50-538 FOLLOW-UP REPORT TO REPORTABLE OCCURRENCE NO. 81 Date of Report: June 11, 1981 Date of Occurrence: June 8, 1981 Date of NRC Notification: June 9, 1981
- 1. Reactor.
AGN-201, Serial 108. Located at the Center for Nuclear Studies, Meaphis State University, Memphis, Tennessee. Facility Operating License R-127, Docket No. 50-538.
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- 2. Reportable Occurrence.
Electric power service to the Memphis State Universitv Center for Nuclear Studies Facilities was unexpectedly interrupted. The unscheduled power outage occurred during AGN-201 reactor operation and, as a direct result of the event, caused reactor shutdown.
- Item 6.9.2.a.(7) of the Facility Technical Specifications applies, j
- 3. Conditions at Time of Occurrence.
- a. An operator training program was in progress for the purpose of providing reactor startup experience for students in Memphis State University's Nuclear Skills Related Training Program (NSRT).
- b. Tne reactor was subcritical and at a steady state neutron level.
A startup was in progress with the Safety Rods fully inserted (24 cm), Coarse Control Rod at 17.86 cm, Fine Control Rod at 15 cm, ard with an estimated margin of 0.14% reactivity from criticality. The reactor temperature was 21 C.
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- 4. _Narra ti ve. l A partial loss of electrical power to the Center for Nuclear Studies Facilities occurred at 3:12 p.m. (CST) on June 8,1981.
The AGN-201 Reactor was being operated by a student under the direct supervision of licensed Senior Operators. At the time of the unscheJuled event, the operator was evaluating data to be used for an estimate of the critical rod positions as part of a reactor training startup procedure using a 1/M approach to criticality.
The reactor was ct a sub-critical, steady state neutron level.
The reactor scrammed, as designed and as required by the Facility Technical Specifications, due to los: cf Reactor Control Power which interrupted electrical current to the Control Red Holding Magnets. Electrical circuits to the neutron flux monitoring instruments, which are connected to a different phase of the power source, remained energized and the reactor power level decay was monitored unti? normal shutdown readings were obtained. t The fine Control Rod (no scram function) remained inserted to 15 cm and the Safety and Coarse Rod Magnet Assemblies remained
- at the pre-scram positions. The normal shutdowr. checkoff was completed at 3
- 27 p.m. (CST) in accordance with OP-S with the
- exception that the Fine Rod remained at the 15. cm position. At l
3:40 p.m. (CST), a complete in,terruption of electric power occurred wnich deenergized all console instrumentation, alarms, and safety 1 circuits.
l The fault was apparently corrected and the electric
! distribution feeder system was restored to normal at 4:58 p.m. (CST).
! Three minutes later the Reactor Supervisor reenergized Reactor Control Power to allow the Fine Control Rod and the Holding Magnet l Assemblies to be returned to their fully withdrawn positiou. The reactor was secured at 4:02 p.m. (CST). Subsequent control and i instrumentation checks revealed no abnormalities as a result of
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the power failure.
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The Reactor Supervisor was in the control room at the time that the unplanned event occurred. The Facility Director was -
notified. The event was reported to the USNRC Region II Office of Inspection and Enforcement (Mr. C. Julian) via telephone and confirmed by mailgram to the Director on June 9,1981, in corpliance with section 6.9.2 of the MSil Facility Technical Specifications.
- 5. Safety Sionificance of the _0ccurrence.
None. A loss of electrical power de-energizes the Safety and Coarse Control Rod Holding Magnets causing a reactor scram and thus assures safe and immediate shutdown in case of a power cut;ge.
Reactor systems performed as designed and as required by tecanical specification 3.3. .
- 6. Cause of Failure.
The interruption of electrical power was apparently caused by a power overload or imbalance of unknown origin on the main distribution feeder to the Center for Nuclear Studies located on the MSU South Campus.
- 7. Corrective Action.
None. Corrective action to restore and maintain the South Campus electric service feeder is under the cognizance and control of organizations outside the Center for Nuclear Studies and the AGN-201 Reactor Facility.
- 8. Measur,es_to Prevent Recurrence.
None. Measures to prevent recurrence of an electric power outage of the nature described in this report are not within the capabilities of the Center for Nuclear Studies or AGN-201 Reactor Facility staff.
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