ML20133J058

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Forwards Annual Operations Rept of Texas A&M Univ AGN-201M Training Reactor, for June 1984 - May 1985
ML20133J058
Person / Time
Site: Texas A&M University
Issue date: 07/11/1985
From: White R
TEXAS A&M UNIV., COLLEGE STATION, TX
To: Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8508090636
Download: ML20133J058 (1)


Text

E T E X A S A & M U N IV E llSITY COLLEGE OF ENGINEERING COLLEGE STATION TE AAS 77Mi-11B DEPARTMENT OF NUCLCAR ENGINEERING (409) 84S-4161 Q 11 July 85 '-

Robert Martin '- 'O Regional Administrator U.S. NRC Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011

Dear Mr. Martin:

Please fi nd enclosed the original pl us three copi es 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 have any questions concerning the report please call meat (409)845-4988 or (409)845-4161.

Sincer ly, h

Randall D. White Reactor Supervisor, AGN 201-M Nuclear Engineering Department RDW/kls of l) k 6o 8508090636 850711 b PDR R

ADOCK 05000059 PDR 6th i

COLLEGE OF ENGINEERING : TEACHING RESEARCH EXTENSION

y ANNUAL OPERATIONS REPORT of t he TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 June 1,1984 - May 31,1985 9

DEPARTMENT OF NUCLEAR ENGIEERItG Texas A&M University College Station, Texas 77843 H

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m ANNUAL OPERATIONS REPORT t of the TEXAS A&M UNIVERSITY AGN-201M TRAINIfG REACTOR NRC LICENSE R-23 June 1,1984 - May 31,1985 Prepared by:

.c $b Randall D. White Reactor Supervisor Approved by: <;

4 /WW Carl A. Erdman, Head Nuclear Engineering Dept.

l DEPARTMENT OF t0 CLEAR ENGIEERIPG I Texas A&M University College Station, Texas 77843 l

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1. SUtFARY l

Tiiis report details the pertinent activities related to the Texas A&M University AGN-201M training reactor facility operated by the Department of Nuclear Engineering duri ng 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 tresis. Nucle ar Engineering and other courses supported during the past year were:

ENGR 102 Engineering Analysis II 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 questions and are not ex pect ed to ad ve rsel y 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 securi ty wall, and added shielding for personnel protection. The f acili ty changes u

m did requi re modifications to the Emergency and Securi ty Pl a ns . The Emergency plan changes have been approved by the NRC, while the Securi ty 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 reviewec 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 1. REACTOR PARAMETER SURVEILLANCE MEASUREMENTS 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 Tires 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 k/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 Reactivity 18 Apr 85 Total Excess Reactivity 0.304 % A k/k Corrected to 20 C 9

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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 ra tor ranges 20 Feb 85 Hi Level Ch. 3 Student Operator Rei ns truct error in switching Student Operator ra nges 21 Feb 85 Lo Level Ch. 3 Student Operator Reinstruct Student error in switching Ope ra to r ranges i

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4. MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE Major corrective maintenance and coaponent 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 - Relocated C-2 personnel warning device required as part of console relocation, i.

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rm (c) 19 Sept 84 - New doors and locks ins tal led as pa rt of console rel oca tio n .

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

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

(f) 5 Dec 84 - All major modifications as soci ated with console move completed, including cable connections to the console, console wall construction, reactor room concrete wall partition, partial rewiring within the console, and panel re-arrangement on the console. The changes improve utilization of available space in the reacto r roon, provide radi ation shielding for operating personnel, increase reliability of console wiring, and provide more accessible arrangement of instruments on the console.

(g) 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 rods and in the console. Performed extensive continui ty checks and visual wire verifications, corrected schematics to reflect procedural conpli ance, and resoldered suspect solder joints.

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

11 Jan 85 - Removed two external resistors on CRTM panel which limit (i) magnet current. Removal of the resistors allows better current control

- using existing potentiometers. Potentiometers were adjusted to standard 90 mA with no degradation in rod drop times. Also resoldered several wires inside CRTM panel .

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

(k) 1 Feb 85 - Resoldered connecto rs for startup source drive ca b le .

Cable was replaced at this time.

(1) 25 Feb 85 - Radiation survey pe rf ormed at various power level s .

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 a nd V16 in the ins trument and the relay in trip assembly 4103.

(n) 29 Mar 85 - Failure of SR2 rod control switch. Re-wired swi tch 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 from another manufacturer. The replacement relay failed. The failed relay was replaced with an original type relay, i

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

The corrective maintenance and canponent 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 roan (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 fica tion 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 t he ef fectiveness of the Pla ns or Procedures. The NRC has reviewed and approved of changes to the Emergency Plan and is currently reviewing the Security Plan.

(c) NEW EXPERIMENTS OR TESTS

. No new expe riment s or tests were pe rf onned duri ng this repo rt ing period.

6.

SUMMARY

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

7.

SUMMARY

OF RADIO.iCTIVE EFFLUENT RELEASES No liquid or solid radioacti ve waste was released du ri ng Chis report ing period.

8. ENVIRONMENTAL RADIOLOGICAL SURVEYS No environment al radiological surveys were pa rf onned outside t he f acility during this reporting period.
9. RADIATION EXPOSURE One individual received a total radiation exposure of between 100 mrem an1250 mrem for the calendar year 1981 e

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10 . MISCELLANEOUS The following pe rsonnel pa rt icipated satisfactorily in the AGN requalification program.

Carl Erdnan S0P-4136 Gerald Schiapper S0P-4210 Randy White SOP-43026 Art Flores 50P-43027 Barry Willits 50P-4472 Mr. Barry Willits obtained re-certification ef fective 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 of fective 1 Jan 85.

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