ML20099L891

Annual Operating Rept for 1984 for Westinghouse Nuclear Training Reactor

ML20099L891
Person / Time
Site:	05000087
Issue date:	12/31/1984
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20099L870	List: ML20099L869 ML20099L891 ML20099L924
References
NUDOCS 8503210158
Download: ML20099L891 (3)

Text

F AfWUAL OPERATING REPORT FOR 1984 AS REQUIRED BY TECFNICAL SPECIFICATIONS FOR THE WESTINGHOUSE NUCLEAR TRAINING REACTOR FACILITY LICENSE NO. R-119 DOCKET NO. 50-87

1. NARRATIVE SLfftARY The Westinghouse Nuclear Training Reactor was operated in accordance with conditions, requirements and Technical Specifications incorporated into the Facl11ty License during 1984. Routine operations included training for utility customers, training for licensed operator candidates and reactivity manipulations in support of the Facility's Licensed Operator Requalification Program.

No changes were made in the facility design or performance characteristics relating to reactor safety.

During 1984, the WNTR License No. R-119 was renewed for twenty years. The renewal documents required major changes in the Technical Specifications and Final Safety Analysis Report. Minor revisions to the Operator Requalification Program and Security Plan were also submitted and approved. A revised Emergency Plan was also approved and implemented during 1984.

2. ENERGY GENERATED AND HOURS OPERATIONAL The reactor generated 32,438 watt-hours of energy and was operational for 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> during 1984.

3. INADVERTENT REACTOR TRIPS There were a total of 159 inadvertent reactor trips during 1984. One hundred thirty-eight of these trips were due to tralnee error and 21 were due to equipment malfunctions. The number of inadvertent -

trips depends directly on the number of trainees utilizing the traininng reactor.

4. SUPNARY OF MAJOR MAINTENANCE OPERATIONS Significant maintenance / surveillance during 1984 were the annual control rod and fuel inspections, repainting and preservation of the I-beam reactor tank supports, replacement of C-2 gamma detector, and the design, building and installation of an electronic 8503210158 850204 PDR ADOCK 05000087 R PDR

compensating voltage network for the CIC's. Results of the annual surveillance compared satisfactorily with previous examinations. Repaired and replaced equipment tested satisfactority prior to use during operations.

The remaining maintenance was routine and was both scheduled and unscheduled in nature. The maintencnce consisted of removing, replacing or repairing worn or failed system components. In no case were safety system functions for the reactor impaired or

/ Jeopardized. The maintenance is summarized as follows:

a. inspected and cleaned dump and reactor tanks b., fuel elevator pully repaired

c. 15 volt power supply in spare log N Amp replaced

d. refurbished domineralizer pump

e. calibrated moderator temperature and level detectors

f. repaired emergency power supply for NTR Emergency Alarm

g. rebuilt 10" dump valve solenoid

h. replace B1-A count rate-cutout meter

1. Installed Run Time meter J. replaced 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock on reactor

k. replaced B-2 Source range channel Amp

1. replaced kinked source cable

, m. repaired and calibrated reactivi ty computer

n. refurbished count rate cut-out relays

o. repaired con trol rod stop plate

p. repaired sump pump

.4. StM%RY OF RADI0 ACTIVE EFFLUENT DISCHARGES s During the 1984 calendar year two discharges of radioactive effluents were made to the sanitary sewer system. Table 1 describes each discharge.

TABLE 1 Liquid Radioactive Effluent Releases i to Sanitary Sewer System Total Date a 8 Value Activity Released 4/10/84 < 2.98x10-Ilmci/ml 4x10-9 mci /ml 37 gallons 5.64x10-4 mci 10/17/84 8.2x10-10 mci /ml 9.2x10-8 mci /ml 50 gallons 1.76x10-2 mci 4

, . . _ ._4-. . , - _ _ - ._. _ _ . _ _ ,

The releases were moderator / shield water from the dump tank. For all releases, the requirements and limits of 10CFR 20.303 were satisfied.

7. Stkt%RY OF REPORTABLE OCCURENCES There were no reportable occurences at the bNTR during 1984.

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