ML20087J744
| ML20087J744 | |
| Person / Time | |
|---|---|
| Site: | 05000538 |
| Issue date: | 12/31/1983 |
| From: | Dietz R, David Jones MEMPHIS STATE UNIV., MEMPHIS, TN |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8403230060 | |
| Download: ML20087J744 (18) | |
Text
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i Center for Nuclear Studies Memphis State University 1983 Annual Report Nuclear Reactor Operations License R-127, Docket 50-538 AGN-201 Nuclear Reactor, Serial 108 1 ATE MARCH,1984 h
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e Center for Nuclear Studies Memphis State University 1983 ANNUAL REPORT of NUCLEAR REACTOR OPERATIONS AGN-201 Nuclear Reactor, Serial 108 Facility Operating License R-127, Docket 50-538 March 1, 1984
/
R. L. Diet:z SupervisoV
. W. Jones Nuclear O'perations irector
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ABSTRACT The 1983 Annual Report of Nuclear Reactor Operations is prepared in compliance with Technical Specification 6.9 of Appendix A to Memphis State University Facility Operating License R-127, Docket No. 50-538.
The report includes facility operation from January 1 through December 31, 1983.
Reactor operations during 1983 were primarily for purposes of operator training.
New or previously untried experiments were not conducted.
A total of 563 startups were performed, 215.63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br /> of critical opera-tions were accumulated, and the maximum steady state power level achieved was 54 milliwatts. Ten unscheduled shutdowns are described in Section B of the report and an additional 19 training scrams were experienced throughout the operating year. One of the shutdowns was a reportable occurrence and a copy of the followup report for this event is contained in Appendix A.
The reactor did not require any Safety-related Maintenance.
Routine, annual reactivity measurements of core parameters were made in December,1983, and do not significantly differ from data contained in previous reports of AGN-201 performance.
Radiation exposure rates measured during reactor operation do not exceed maximum permissible levels specified in 10 CFR 20 and-the highest cumulative dose-equivalent received by an individual was.087 Rem for the operating year.
A statistical summary pursuant to 10 CFR 20.407 is provided in Section K of this report.
A total of eight independent audits were performed in various areas of facility operation and are listed in Section L.
ii
TABLE OF CONTENTS Page Number TITLE PAGE..........................
i ABSTRACT...........................
11 TABLE OF CONTENTS...................... iii A.
REACTOR OPERATING EXPERIENCE,..............
1 B.
UNSCHEDULED REACTOR SHUTDOWNS 2
C.
PREVENTIVE AND CORRECTIVE MAINTENANCE 3
1.
Major Safety Related Corrective Maintenance 2.
Results of Major Surveillance Tests D.
CHANGES IN FACILITY DESIGN, PERFORMANCE CHARACTERISTICS, OR PROCEDURES RELATED TO REACTOR SAFETY 4
E.
CHANGES WHICH WOULD AFFECT THE FACILITY DESCRIPTION 5
F.
CHANGES TO ADMINISTRATIVE PROCEDURES 5
G.
NEW OR UNTRIED EXPERIMENTS................
5 H.
RADI0 ACTIVE EFFLUENTS 5
I.
ENVIRONMENTAL RADIOLOGICAL SURVEYS PERFORMED OUTSIDE THE FACILITY 6
J.
RADIATION EXPOSURES GREATER THAN 100 MILLIREM 6
K.
PERSONNEL EXPOSURES AND MONITORING 6
L.
4UDITS AND INSPECTIONS '..................
7-APPENDICES l
A.
FOLLOW-UP REPORT TO REPORTABLE OCCURRENCE 83-1 1
111
A.
REACTOR OPERATING EXPERIENCE 1.
Student Training Programs Forty-three power plant employees participated in training exercises designed by Memphis State University (MSU) to provide research reactor startup experience for cold license candidates.
In addition, 28 students from MSU's specialized on-campus Nuclear Skills Training Program performed reactor startups and related training exercises as part of the program's normal curriculum.
A total of 531 reactor startups were conducted for purposes of student training.
2.
Staff Operator Training Eleven reactor startups were conducted for purposes of main-taining and evaluating licensed operator proficiency. As of December 31, 1983, the MSU Center for Nuclear Studies Staff held two Senior Operator and two Operator Licenses for the AGN-201 Reactor.
3.
Additional reactor operations were conducted for purposes of satisfying surveillance requirements, routine tests, and calibrations.
4.
Operations - Summary Hours Max. Power hours' Max. Power Month Critical (Milliwatts)
Month Critical (Milliwatts)
Jan 50.27 54 Jul 42.72.
43
,Feb 16.77 44 Aug 22.87 45 Mar 0
0 Sep.
0.88-
'50 Apr 0
0.
Oct
'17.82 48 May 3.97 52 Nov 28.02 49-Jun 16.63 52 Dec 15.68 50 TOTAL NUMBER OF REACTOR STARTUPS DURING 1983: 563 TOTAL HOURS OF CRITICAL OPERATION DURING 1983: 215.63 1
B.
UNSCHEDULED REACTOR SHUTDOWNS Ten unscheduled (non-training) reactor scrams were experienced during 1983. Operating limitations were not exceeded nor were any conditions achieved that would have required reactor shutdown, operation of safety systems, or other protective measures required by Technical Specifica-tions. However, one of the shutdowns was considered to be a reportable occurrence as defined in the facility license and a copy of the follow-e up report for that event is contained in Appendix A.
CHANNEL 1 HIG'. LEVEL TRIP (2).
On February 17 and again on December 16, 1983, high level trips occurred on the Channel 1 Neutron Flux Monitor due to operators not properly upranging the instrument while increasing reactor power.
This channel employs an eight-step range switch and has a High Level Trip set at 90-95% of full-scale indication to prevent over-ranging the instrument. The highest power level corresponding to the maximum setting of this trip point is approximately 53 milliwatts.
CHANNEL 1 LOW LEVEL TRIP (3).
On January 4, January 26, and August 4,1983, low level trips occurred on the Channel i Neutron Flux Monitor.
The Low Level Trip for this instrument is set at 12-15% of full scale indication to ensure that an adequate source level is observed for reactor startup.
Two of the trips resulted from setpoint' drift (upscale to 17-20% fs) and the other resulted from vacuum tube failure in the high voltage supply tc, the Channel 1 Neutron Detector.
CHANNEL 3 LOW LEVEL TRIP (3).
On February 25 and twice on October 25, 1983, low level trips occurred on the Channel 3 Neutron Flux Monitor due to spurious electrical noise transients. The low level trip for this instrument is set at 5-10% of 2
i
full scale indication to ensure that an adequate source level is observed for reactor startup.
The spurious noise transients were eliminated by thoroughly cleaning and drying the electrical con-tactor for the 20-step range switch used in Channel 3.
REACTOR PERIOD TRIP (1).
On October 21, 1983, a reactor period trip occurred from an elec-trical noise transient of unknown origin.
The reactor was at a subcritical power level of less.than one milliwatt in preparation for a training startup at the time of the transient.
Attempts to reproduce the noise transient were unsuccessful and the ceriod circuit and trip function tested satisfactorily.
LOSS OF ELECTRICAL POWER (1).
This unscheduled scram is described in Appendix A.
TRAINING.
Nineteen additional scrams were caused by trainees during the con-duct of student training programs. Most of these trips resulted from improperly positioned instrument range switches during power level transients.
C.
PREVENTIVE AND CORRECTIVE MAINTENANCE.
1.
Safety Related Corrective Maintenance: None required.
2.
Results of Major Surveillance Tests and Inspections:
a.
Control Rod Drive Assembly Inspe. tion and Lubrication.
This annual surveillance procedure was completed on December 2, 1983. The drive assemblies were found in satisfactory condition with no evidence of abnormal wear or deterioration.
3-
b.
Measurement of Safety and Control Rod Scram and Insertion Times.
This annual surveillance procedure was completed on December 8,1983, with the following results:
Insertion (cm/sec)
Scram (m sec)
Safety Rod No.1 0.446 122 Safety Rod No. 2 0.471 104 Coarse Control Rod 0.397 120 Fine Control Rod 0.441 N/A c.
Reactivity Measurements: This annual surveillance pro-cedure was completed on December 16, 1984, with the following results:
Parameter
% Reactivity Control Rod Integral Worth:
Fine 0.322 Coarse 1.24 Reactivity Insertion Rate:
Safety Rod No.1
.033/sec Safety Rod No. 2
.034/sec Coarse Control Rod
.029/sec Fine Control Rod
.01/sec Excess Reactivity (Glory Hole empty, 20 C, all rods IN) 0.198 Shutdown Margin (Most reactive rod IN) 2.69 D.
CHANGES IN FACILITY DESIGN, PERFORMANCE CHARACTERISTICS, OR PROCEDURES RELATED TO REACTOR SAFETY None.
4
E.
CHANGES WHICH WOULD AFFECT THE FACILITY DESCRIPTION None.
F.
CHANGES TO ADMINISTRATIVE PROCEDURES 1.
Revision 7 (2/83) to the AGN-201 Nuclear Reactor Facility Organization and Regulations Manual was approved and issued on February 25, 1983.
This revision updated the Emergency Plan Notification List to reflect proper phone contacts and numbers.
2.
Revision 3(3/83) to the AGN-201' Reactor Operations Manual l
was approved and issued on March 24, 1983.
This revision incorporated editorial changes to Part I of the Manual (Description of the Reactor and Systems) and provided clarification of procedural steps and stat {ments contained in:
Operating Procedure No. 3, Reactor Startup Operating Procedure No. 4, Critical Operation Operating Procedure No. 8, Radiation Monitoring Equipment Emergency Procedure No. 4, Reactivity Excursions The revisions were reviewed and approved by the Reactor Safety Committee and do not involve a change to the Facility Technical Specifications nor do they involve an unreviewed safety question as defined in 10 CFR 50.59.
G.
NEW CR UNTRIED EXPERIMENTS None.
H.
RADI0 ACTIVE EFFLUENTS 1.
Liquid: None 2.
Airborne: None 3.
Solid: None 5
I.
ENVIRONMENTAL RADIOLOGICAL SURVEYS PERFORMED OUTSIDE THE FACILITY Areas of unrestricted access begin at the outside walls of the Reactor Room. A general area radiation survey conducted December 19, 1983, revealed the maximum level of gamma radiation to be 0.2 mR/hr measured upon contact with the outside east wall. The maximum level of neutron radiation measured < 0.1 mrem /hr at the same location. The reactor was operating at a steady power level of 50 milliwatts for the duration of the survey.
l l
Random wipes / smears of surfaces both inside and outside the reactor facility did not reveal any loose surface contamination above natural background levels.
The reactor was not operated at steady-state power levels above 54 milliwatts during 1983.
Therefore, full power radiation survey results are not available.
J.
RADIATION EXPOSURES GREATER THAN 100 MILLIREM (50 MILLIREM FOR PERSONS UNDER 18 YEARS OF AGE)
None K.
PERSONNEL EXPOSURE AND MONITORING:
10 CFR 20. Part 407 (a) (2) and Part 407 (b) 1.
Personnel monitoring was provided for a total of 105 persons during 1983. The highest cumulative exposure for an individual was.087 Rem.
The average exposure for the 105 individuals monitored was.0042 Rem.
6
)
2.
Statistical Suninary:
Estimated Whole Body Number of Individuals Exposure (Rems)
In Each Range No measureable exposure 90 Measureable exposure less than 0.1 15 0.1 to 0.25 0
0.25 to 0.5 0
0.5 to 0.75 0
0.75 to 1.0 0
I to 2 0
2 to 3 0
3 to 4 0
4 to 5 0
5 to 6 0
6 to 7 0
7 to 8 0
8 to 9 0
9 to 10 0
10 to 11 0
11 to 12 0
12 +
0 L.
AUDITS AND INSPECTIONS Audits and inspections of the AGN-201 Reactor Facility were conducted by the following agencies during 1983.
Copies of the written reports documenting the results of each audit / inspection are retained on file at the facility.
1.
MSU Reactor Safety Committee (RSC) a.
Review of the Facility Emergency Plan (6-27-83) b.
Review of the Facility Radiological Controls Program and records (3-15-83) c.
Review of the Facility Security Plan (1-14-83) d.
An evaluation.of the' conformance of facility operation to the Technical Specifications. (1-12-83) 7
(
e.
Review of the performance, qualifications, and training of the facility staff (1-11-83) f.
Review of the results of actions taken to correct deficiencies that affect reactor safety (1-10-83) 2.
American Nuclear Insurers (ANI)
Nuclear liability inspection including a review of various aspects of the f4SU Safety Committee, Radiation Protection Program, Operations Program, Training Programs, and Emergency Planning Programs (6-8-83).
3.
U.S. Nuclear Regulatory Commission (USNRC) - Region II A rovtine, unannounced, safety inspection in the areas of Organization; Logs and Records; Review and Audit; Requalification Training; Procedures; Surveillance; Experiments; Followup on Previously Cited Noncompliance and Previous Unresolved Items (f4ay 24-26, 1983.
USNRC Region II Inspection Report 50-538/83-01).
1 8
APPENDIX A FOLLOW-UP REr0RT TO REPORTABLE OCCURRENCE NO. 83-1 APPENDIX A (4pps)
@^TE}h MEMPHIS STATE UNIVERSITY p' g' e r E g
MEMPHIS, TENNESSEE 35152
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January 5, 1983 w
Centerfor Nuclear Studies Offce of the Director (901) 434-2687 Director Region II, USilRC Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, GA 30303
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 January 3, 1983. The report is submitted in accordance with section 6.9.2 of Appendix A to Facility Operating License R-127, Docket No.
50-538.
An unscheduled momentary power outage occurred during reactor operation which directly caused reactor shutdown.
Restoration of electric power service was completed in approximately 30-45 seconds and conditions re-turned to normal.
Initial notification was made to your office by telephone and confirmed by mailgram on January 4,1983.
Sincerely,
$W D.W[ Jones Director RLD/mm
Enclosures:
Follow-up Report to Reportable Occurrence #83-1 cc: Mr. A. Hardin, USNRC, Region II Dr. V. N. Oliphant, MSU Dr. D. K. Holmes, CNS/RSC Mr. R. L. Dietz, MSU/CNS Mr. J. R. Caves, CNS Mr. C. V. Holm, CNS Mr. J. P. Williams, CNS The Nation'sprst Regional Centerfor Nuclear Manpower Development An EqualOpportunity University 1.
i
MEMPHIS STATE UNIVERSITY AGN-201 NUCLEAR REACTOR FACILITY LICENSE R-127, DOCKET N0. 50-538 FOLLOW-UP REPORT TO REPORTABLE OCCURRENCE NO. 83-1 Date of Report:
January 5, 1983.
Date of Occurrence:
January 3, 1983.
Date of HRC Notification:
January 4,1983.
1.
Reactor.
AGN-201, Serial 108. Located at the Center for. Nuclear Studies, Memphis State University, Memphis, Tennessee.
Facility Operating License R-127, Docket No. 50-538.
2.
Reportable Occurrence.
Electric power service to the Memphis State University 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.
3.
Conditions at Time of Occurrence.
a.
An operator training program was in progress for the purpose of providing reactor startup experience.for students from the Public Service Electric and Gas Company of New Jersey.
b.
.The reactor was suberitical and a 1/M approach to critical was in progress.
ity Rods were fully inserted (24 cm). Fine Control Rod at _ cm, and the Coarse Rod was being inserted to increase the subcritical neutron level.
Estimated margin' to critical was approximately.03% reactivity at 19.1'0C.
1 1
4.
Narrative.
A momentary loss of electrical power to the Center for Nuclear 7
Studies Facilities occurred at 4:34 p.m. (CST) on January 3, 1983.
The AGN-201 Reactor was being operated by a student under the direct supervision of licensed facility operators.
At the time of the un-scheduled event, the operator was insertino the Coarse Control Rod to increase the subcritical neutron level as part of a reactor training startup procedure using a 1/M approach to criticality.
The reactor was subcritical by approximately.03% reactivity.
The reactor scrammed, as designed and required by the Facility Technical Specifications, due to loss of Reactor Control Power which interrupted electrical current to the Control Rod Holding Magnets.
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.
Approximately 30-45 seconds later, at 4:35 p.m. (CST), the electric distribution feeder system was restored to normal.
The Senior Operator reenergized Reactor Control Power to allow the Fine Control Rod and the Holding Magnet Assemblies to be returned to their fully withdrawn positions. The reactor was secured at 4:44 p.m. (CST). Subsequent control and instrumentation checks revealed no abnormalities as a result of the power failure.
The Reactor Supervisor and. the Facility Director were notified.
The event was reported to the USNRC Region II Office of Inspection and Enforcement (Mr. A. Hardin) via telephone and confirmed by_ mail-gram on January 4,1983, in compliance with section 6.9.2 of the MSU Facility Technical Specifications.
2 l'
L c-
- a
i 5.
Safety Significance of the Occurrence.
None. A loss of electrical power de-energizes the Safety and Coarse Control Rod Holding liagnets causing.a reactor scram and thus assures safe and immediate shutdown in case of a power outage. Re-actor systems performed as designed and as required by technical specification 3.3.
6.
Cause of Failure.
The momentary interruption of electrical power was caused by a power perturbation of unknown origin on the main distribution feeder to the Center for fluclear Studies which is maintained by the Memphis Light, Gas and Water Company.
7.
Corrective Action.
None. Corrective action to restore and maintain the South Campus electric service feeder is under the cognizance and control of organi-zations outside the Center for Nuclear Studies and the AGil-201 P,eactor Facility.
8.
!!easures to Prevent Recurrence.'
None. !!easures to prevent recurrence of an electric power outage of the nature described in this report are not within the capabilities of the Center for fluclear Studies or AGil-201 Reactor Facility staff.
9.
Similar Reportable Occurrences.
MSU Follow-up Reports: #79-1 (1/29/79), #79-2 (3/10/79), #81-1.
(6/11/81),
.F '
i Prepared by:
fe' Reactor-Super 01sor i
l 3
a L
'h "MEhkPHIS STATE UNIVERSITY k
gg MEMPillS, TENNESSEE 38152 g
March 19, 1984 Centerfor Nuclear Studies Office of the Director (901) 454-2687 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk (DCD)
Gentlemen:
Subject:
Facility Operating License R-127, Docket 50-538 Copies of the Memphis State University 1983 Annual Report of Nuclear Reactor Operations are transmitted herewith for your review and records.
The report is provided in compliance with Facility Operating License R-127, Docket 50-538.
Information contained in the report is considered by the licenses to be non-proprietary.
Sincerely,
/sw D. W.
ones Dir tor DWJ:RLD/mrm Enclosures - (12 copies) cc: Mr. R. t.. Dietz IV The Nation'sfirst Regional Centerfor Nuclear Manpower Development An Equal Opportu sity Ur:lversity
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