ML20129K123

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Annual Operations Rept of Texas A&M Univ AGN-201M Training Reactor:Nrc License R-23,June 1984 - May 1985
ML20129K123
Person / Time
Site: Texas A&M University
Issue date: 05/31/1985
From: Erdman C, White R
TEXAS A&M UNIV., COLLEGE STATION, TX
To: Thomas C
Office of Nuclear Reactor Regulation
References
NUDOCS 8507230409
Download: ML20129K123 (10)


Text

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-9 ANNUAL OPERATIONS REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINI!G REACTOR NRC LICENSE R-23 June 1,1984 - May 31,1985 f

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DEPARTENT OF WCLEAR ENGIEERifE Texas A&M University College Station, Texas 77843 f

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ANNUAL OPERATIONS REPORT of the TEXAS A&M UNIVERSITY AGN-20lM TRAINING REACTOR NRC LICENSE R-23 June 1,1984 - May 31,1985 Prepared by:

_ J $b Randall D. White

.. Reactor Supervisor Approved by:

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Carl A. Erdman, Head

  1. UN Nuclear Engineering Dept.

DEPARTENT OF WCLEAR ENGIEERIIG Texas A&M University College Station, Texas 77843 4

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1. SUMi%RY This report details the pertinent activities related to the Texas A&M University AGN-201M training reactor facility operated by the Department of Nuclear _ Engineering during the pe riod June 1, 1984 to May 31, 1985.

Furthermore, it is intended that the contents of this report comply with the requirements of 10 CFR 50 section 50.59 (b), and Appendix A, Technical Specifications, of license R-23.

The utilization of this facility continues to be similar to that of previous years. The general categories of utilization for this past year were support of Nuclear Engineering courses, operator training, preventive

-maintenance, and research for a Master's degree t hesis . Nucle ar Engineering and other courses supported during the past year were:

ENGR 102 Engineering Analysis Il NE 405 Nuclear Engineering Reactor Experiments NE 606 Nuclear Engineering Reactor Experiments

!E 691 Industrial Engineering Research Components replaced as part of preventive and corrective maintenance

- are detailed in Section 4. Components replaced during this period do not involve unreviewed sa fety ques tions and are not expect ed to adversely af fect the safe operation of this facility.

A major facility modification was performed this year. It included moving the reactor control console, construction of an additional security wall, and added shielding for personnel protection. The facility changes

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- did ' require modi fica tions to the Emergency and Securi ty Pla ns . The Emergency plan changes have been approved by the NRC, while the Security Plan changes are still under review. None of these changes are expected to adversely af fect the safe' operation of this facility. These changes were reviewed and approved by the Reactor Safety Board. Following completion of the console move Reactor Safety Board representatives reviewed the work to insure compliance with applicable procedures and specifications.

The results of all major parameter surveillance tests are shown in Table 1.

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TABLE I. REACTOR PARAMETER SURVEILLANCE ffASUREMENTS Date Reactivity Worth Value 18 Apr 85 Safety Rod #1 1.156 % A k/k 18 Apr 85 Safety Rod #2 1.150 % A k/k 18 Apr 85 Course Control Rod 1.163 % A k/k 18 Apr 85 Fine Control Rod 0.3725 % A k/k Rod Drop Times 21 Jan 85 Safety Rod #1 125 msec 21 Jan 85 Safety Rod #2 150 msec 21 Jan 85 Course Control Rod 140 msec Reactivity Insertion Rates 25 Jan 85 Safety Rod #1 0.0515 A x/k/sec 25 Jan 85 Safety Rod #2 0.0517 A k/k/sec 25 Jan 85 Course Control Rod 0.0452 A k/k/sec 25 Jan 85 Fine Control Rod 0.0109 A k/k/sec

.- _ = . _-- . . . - . - . . - - - . . _ . ._

Total Excess Reactivi,ty, 18 Apr 85 Total Excess Reactivity 0.304 % A k/k Corrected to 20 'C

2. OPERATIONAL

SUMMARY

Utilization by Category: Hours (a) Support of Nuclear Engineering Courses 16.37 (b) Operator Training 4.47 (c) Preventive / Corrective Maintenance 8.32 (d) Support of Research 1.02 Total Operating Hours 30.16 Total Watt-hours of Operation 52.53 Average Power Level of Operation 1.74 Number of Reactor Startups 93

3. UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION 8 Feb 85 Hi Level Ch. 3 Student Operator Reinstruct Student error in switching Ope rato r ranges 20 Feb 85 Hi Level Ch. 3 Student Operator Rei ns truct error in switching Student Op3rator ranges 21 Feb 85 lo level Ch. 3 Student Operator Reinstruct Student error in switching Ope rato r ranges
4. MAJOR SAFETY RELATED CORRECTIVE K41NTENANCE Major corrective maintenance and conponent replacement on the AGN-201M reactor during the reporting period are summarized as follows:

(a) 16 Aug 84 - Failure of Console Power On indication. Replaced 1250 ohm current limiting resistor on indicator lamp.

(b) 30 Aug 84 - Holocated C-2 personnel warning device reluired as pirt of i

console relocation.

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(c) 19 Sept 84 - New doors and locks installed as pa rt of console

. rel oca tio n . ,

(d) 20 Sept 84 - Disconnected Console and moved it to new location in reactor room.

(c) 25 Oct 84 - Replaced Ch. 1, 2, 3, detector cables with new detector cables to minimize cable lengths.

(f) 5 Dec 84 - Al l major modifications associ ated with console move completed, including cable connections to the console, console wall construction, reactor room concrete wall partition, partial rewiring within the consolo, and panel re-arrangement on the console. The changes improve ,

utilization of available space in the reactor roon, provide radi ation i shielding for operating personnel, increase reliability of console wiring, and provide more accessible arrangement of instruments on the console.

(9) 7 Dec 84 - Initial console energization af ter relocation. All rods on test stand. Initial rod testing failed due to wiring errors, errors in some schematics, and bad solder joints on the control rois and in the console. Pe rformed extensive continuity checks and visual wire verifications, corrected schematics to reflect procedural cmpliance, ard resoldered suspect solder joints.

(h) 20 Dec 84 - Replaced rod top micro-switch for Safety Rod #2. The switch may have failed as a result of initial reenergization problems.

(1) 11 Jan 85 - Removed two external resistors on CRIM panel which limit magnet current. Removal of the resistors allows better current control using existing potentiometers. Potentiometers were adjusted to stardard 90 mA with no degradation in rod drop times. Also resoldered several wires inside CRIM panel .

(j ) 21 Jan 85 - Reinstalled Rods in reactor. All rods operational .

(k) 1 Feb 85 - Resoldered connectors for startup source drive cable.

Cable was replaced at this time.

(1) 25 Feb 85 - Radiation survey performed at various power levels.

Indications show that operator exposure at console during full power (5 w) ,

operations is within safe levels (approximately 2.5 mrem /hr).

(m) 22 Mar 85 - Failure to receive Ch. 2 high trip during prestartup check. Replaced vacuum tubes V4, V5 and V16 in the instrument at:1 tic relay in trip assembly 4103.

(n) 29 Mar 85 - Failure of SR2 rod control switch. Re-wired switch to utilize an unused bank of contacts on the same switch.

(o) 4 Apr 85 - Failure of SR2 relay K-12. This relay was replaced with an electrically equivalent relay f rom another manuf acturer. The replacement relay failed. The failed relay was replaced with an original type r elay.

(p) 15 May 85 - Re-wired connectors for Rod Position Indicator lamps to better facilitate lamp changes.

The corrective maintenance and conponent replacement perfonned during this reporting period do not involve unreviewed safety questions.

5. (a) FACILITY CHANGES Facility changes this year included moving the reactor control console from room 60C to the reactor room (room 61). A solid concrete half-wall was constructed between the reactor and the console for operator radiation protection. A removable wall of solid concrete blocks was constructed '

around the skirt of the reactor to reduce neutron and gamma levels in the room. A solid concrete wall was built to divide room 61 into a reactor area (including the control console) and a laboratory area. Access fran the laboratory area to the reactor area is provided via locked doors.

(b) CHANGES TO PLANS AND PROCEDURES The Emergency and Security Plans and Procedures were changed to reflect the facili ty modi fication in 5(a), in pa rt icula r , facili ty drawings and access routes were af fected. It is our interpretation that none of these changes decreased the of fectiveness of the Pla ns or Procedures. The NRC has reviewed and approved of changes to the Emergency Plan and is currently reviewing the Securtly Plan.

(c) NEW EXPERIMENTS OR TESTS No new experiments or tests were pe rf o nned during this report ing period.

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6.

SUMMARY

OF SAFETY EVALUATIONS No changes, tests, or experiments were performed during this reporting i period which meet the criteria of 10 CFR 50 paragraph 50.59 requiring a safety evaluation.

7.

SUMMARY

OF RADI0 ACTIVE EFFLUENT RELEASES No liquid or solid radioactive waste was released during thi s reporting period.

8. ENVIRONMENTAL RADIOLOGICAL SURVEYS No environmental radiological surveys were pe rf onned outside the facility during this reporting period.
9. RA0!ATION EXPOSURE One individual received a total radiation exposure of between 100 mrem and 250 mrem for the calendar year 19M.

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O 10 . MISCELLANEOUS The following pe rsonnel pa rt icipa ted satisfactorily in the AGN requalification program.

Carl Erdman SOP-4136 Gerald Schlapper SOP-4210 Randy White 50P-43026 Art Flores 50P-43027 Barry Willits SOP-4472 Mr. Barry Willits obtained re-certi fication effective 13 Sept 84. Mr.

David Carpenter (SOP-4471) resigned as Reactor Supervisor ef fective 31 Dec

84. Mr. Randy White was named the Reactor Supervisor for the AGN-201M facility ef fective 1 Jan 85.

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D TEXAS A&M UNIVERSITY COLLEGE OF ENGINEERING COLLEGE STATION TEXAS 778411135 DEPARTMENT OF NUCLEAR ENQuNECRtNO (409)845 4169 11 July 85 Cecil 0. Thomas, Chief Standardization and Special Proj. Branch Division of Licensing U.S. NRC Washington, DC 20555

Dear Mr. Thomas:

Please find enclosed five copies of the most recently completed annual operating report dated 1 June 84 to 31 May 85, for the AGN-201M, docket no. 50-59.

If you nave any questions concerning the report please call me at (409)845-498d or (409)845-4161.

Sincer y, 8 d<) 'i Randall D. White Reactor Supervisor, AGN 201-M Nuclear Engineering Department R0W/kis kh N COLLt0E 0!ENGINrtnING : TEACHINQ MtstAMCM . ExtENst0N

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