ML19310A345: Difference between revisions
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l scram is required to be,s 125 F. It is actually set at 124 F. The 0.6 F | l scram is required to be,s 125 F. It is actually set at 124 F. The 0.6 F | ||
, error noted above means that on April 14, 1980, the trip point was 124.6 F, Q | , error noted above means that on April 14, 1980, the trip point was 124.6 F, Q | ||
still below the 125oF limit. | still below the 125oF limit. | ||
s | s | ||
^ | ^ | ||
A am | A am 8006110 $ | ||
8006110 $ | |||
U.S. Nuclear Regulatory Commission, Region II Page 2 May 26, 1980 The following steps have been taken to prevent a recurrence of an incident of this kind in the future. | U.S. Nuclear Regulatory Commission, Region II Page 2 May 26, 1980 The following steps have been taken to prevent a recurrence of an incident of this kind in the future. | ||
: 1. Re-instruct all operating and maintenance personnel in the need and importance of calibrating any safety-related instrument following any maintenance, repair etc. on the instrument. | : 1. Re-instruct all operating and maintenance personnel in the need and importance of calibrating any safety-related instrument following any maintenance, repair etc. on the instrument. | ||
Status: Completed , | Status: Completed , | ||
: 2. Strengthen our program that documents all special repairs, surveillance and checks of the reactor instruments by requiring a second review of the documentation. We would expect the overlooked calibration noted | : 2. Strengthen our program that documents all special repairs, surveillance and checks of the reactor instruments by requiring a second review of the documentation. We would expect the overlooked calibration noted above to be recognized by such a review. | ||
above to be recognized by such a review. | |||
Status: ' Completed Should you require any additional information on this matter, please advise me. | Status: ' Completed Should you require any additional information on this matter, please advise me. | ||
Sincerely yours | Sincerely yours | ||
'. I Robert S. Kirkland Associate Director RSK:lrm cc: Members, Nuclear Safeguards Committee L.E. Weaver L.D. McDowell M.E. Mercer J.M. Burke | '. I Robert S. Kirkland Associate Director RSK:lrm cc: Members, Nuclear Safeguards Committee L.E. Weaver L.D. McDowell M.E. Mercer J.M. Burke O}} | ||
O}} | |||
Latest revision as of 10:36, 1 February 2020
| ML19310A345 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 05/23/1980 |
| From: | Kirkland R Neely Research Reactor, ATLANTA, GA |
| To: | |
| References | |
| NUDOCS 8006110118 | |
| Download: ML19310A345 (2) | |
Text
6
= .4 GEORGIA INSTITUTE OF TECHNOLOGY SCHOOt. OF NUCLEAR ENGINEERING ATLANTA, GEdRGI A 30332'. .* 3 (,
F R AN K H. N EELY NUCLE AR RESE ARCH CENTER TE LE P'10 N E: (404)894 3600 May 23, 1980 U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W., Suite 3100 Atlanta, Georgia 30303 Gentlemen:
Reference:
Docket 50-160; License R-97
Subject:
Licensee Event Report LER 80-3 During the preparation for reactor startup on April 10, 1980, a " Low D,30 Temperature" alarm was received from the D 0 temperature recorder TRA-D1 2
when the pen drive cable broke. A spare cable was installed and the re-corder TRA-D1 was calibrated. During reactor operation later in the day, it was observed that the indicated temperature was exhibiting an erratic behavior. At apparently random intervals, point No. 1 (Reactor outlet) would print about 10 0F high for one or two cycles then return to normal.
The reactor was shutdown to investigate the problem. As a result of the investigation, a Inir of sliding contacts on one of the two scanner select switches was replaced due to excessive wear. The recorder then appeared to be operating normally but, contrary to established procedures, it was not recalibrated.
The reactor was operated for two brief periods on April 10, 1980 and April 11, 1980. In both cases the power level was <500 KW. On April 14, 1980, the reactor was scheduled to operate at 1000 KW. The power was increased in several increments because a replacement neutron detector has been in-stalled and its performance was being closely monitored. The power was stabilized when the nuclear instrumentation indicated approximately 1000 KW.
A thermal balance at this time gave a value of 933 KW. On April 15, 1980, the recorder TRA-D1 was calibrated. -The results indicated that the two monitored temperatures (reactor inlet and outlet) differed by approximately 0.50 F and the indicated reactor outlet temperature was 0.60F low. The dif-ference error is equivalent to 145 KW so the operating power on April 14, 1980 was approximately 933 + 145 or 1078 KW. The trip point for the High D 20 Temp.
l scram is required to be,s 125 F. It is actually set at 124 F. The 0.6 F
, error noted above means that on April 14, 1980, the trip point was 124.6 F, Q
still below the 125oF limit.
s
^
A am 8006110 $
U.S. Nuclear Regulatory Commission, Region II Page 2 May 26, 1980 The following steps have been taken to prevent a recurrence of an incident of this kind in the future.
- 1. Re-instruct all operating and maintenance personnel in the need and importance of calibrating any safety-related instrument following any maintenance, repair etc. on the instrument.
Status: Completed ,
- 2. Strengthen our program that documents all special repairs, surveillance and checks of the reactor instruments by requiring a second review of the documentation. We would expect the overlooked calibration noted above to be recognized by such a review.
Status: ' Completed Should you require any additional information on this matter, please advise me.
Sincerely yours
'. I Robert S. Kirkland Associate Director RSK:lrm cc: Members, Nuclear Safeguards Committee L.E. Weaver L.D. McDowell M.E. Mercer J.M. Burke O