ML20246N054
| ML20246N054 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1989 |
| From: | Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-772, NUDOCS 8909080025 | |
| Download: ML20246N054 (2) | |
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 August-31, 1989 LIC-89-772' U. S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station PI-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter OPPD (K. J. Morris) to NRC (Document Control Desk) dated February 7, 1989 (LIC-89-161) 3.
Letter OPPD (K. J. Morris) to NRC (Document Control Desk) dated February 23, 1989 (LIC-89-227) 4.
Letter OPPD (K. J. Morris) to NRC (Document Control Desk) dated March 17,1989.(t.IC-89-246) 5.
Letter OPPD (K. J. Morris) to NRC (Document Control Desk) dated May 23, 1989 (LIC-89-447)
Gentlemen:
SUBJECT:
Special Report on Inoperability of Wide ~ Range Noble Gas Stack Monitors RM-063L, RM-063M and RM-063H for Post-Accident Monitoring Omaha Public Power District (OPPD) submits this report pursuant to the require-
~ ments of Fort Calhoun Station Technical Specification'.2.21, " Post-Accident Monitoring Instrumentation." Table 2-10, Item 2,3 requires that a minimum of one channel for each wide range noble gas stack monitor RM-063L, RM-063M and RM-063H be operable in Modes 1, 2 and 3.
If the number of operable channels is less than the minimum operable channels requirement, OPPD must either restore
-the inoperable channels to operable status within seven days of the event, or prepare and submit a special report to the Commission pursuant to Technical J
Specification 5.9.3 within 14 days following the event.
)
Reference 5 discussed the inoperability of monitors RM-063L, RM-063M and RM-063H due to a malfunctioning flow controller. The flow controller was repaired and a calibration was started to return the monitors to, service.
During this calibration, RM-063H did not respond as designed to radioactive sources. OPPD is currently investigating the cause of this problem.
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.-.4 U. S. Nuclear Regulatory Commission LIC-89-772 Page 2 During this investigation, a leak was identified in RM-063H process stream tubing which was subsequently repaired.
Investigation of the response problem noted above is continuing.
RM-063H is now undergoing a primary calibration to determine the proper sensitivity of the monitor. The primary calibration will take approximately one month to complete.
Following the primary calibration, an electronic calibration of RM-063K must be performed.
The flow control circuit must then be calibrated in order to return RM-063L, RM-063M and RM-063H to service. Due to the unforeseen problems with RM-063H discussed above, the revised schedule for returning RM-063L, RM-063M and RM-063H to service is December 15, 1989.
If you have any questions, please contact us.
Sincerely,
/
K orris D vision Manager Nuclear Operations Division KJM/jms cc: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector
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