LIC-02-0046, Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring

Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring

ML021210450
Person / Time
Site:	Fort Calhoun
Issue date:	04/16/2002
From:	Bannister D Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-02-0046
Download: ML021210450 (2)

Text

UHHU Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 April 16, 2002 LIC-02-0046 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring The Omaha Public Power District (OPPD) submits this report pursuant to the requirements of Fort Calhoun Station (FCS) Technical Specification (TS) 2.21, "Post-Accident Monitoring Instrumentation." TS 2.21, Table 2-10, specifies the minimum operable channels for several post accident monitoring instruments. If the required instrumentation is not operable, then the appropriate actions specified in Table 2-10 are to be taken.

Table 2-10, Item 3, specifies a minimum of one operable channel for the Main Steam Line Radiation Monitor RM-064. Footnote (a) of Table 2-10 indicates that "With the number of OPERABLE channels less than required by the minimum channels operable requirements, initiate the pre-planned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

1. either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or

2. prepare and submit a special report to the Commission pursuant to specification 5.9.3 within 14 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedules for restoring the system to OPERABLE status."

On April 2, 2002, at 0155 the Main Steam Line Radiation Monitor, RM-064, was declared inoperable due to an equipment failure. As required, FCS has initiated the pre-planned alternate method of monitoring main steam line dose rates using procedure EPIP-EOF-06, "Dose Assessment," and an operations memorandum.

Employment with Equal Opportunity 4171

U. S. Nuclear Regulatory Commission LIC-02-0046 Page 2 An initial attempt to repair the monitor failed and the vendor was contacted. Troubleshooting and investigation of the failure continues. Additional parts to repair the monitor have been ordered and delivery is anticipated on April 16, 2002. The monitor will be repaired and placed in service as soon as repairs and post-maintenance testing is completed. It is currently anticipated that repairs will be completed by April 19, 2002. Should additional time be required to repair the monitor the NRC resident inspectors will be kept informed of the revised schedule.

The pre-planned alternate method of monitoring main steam line dose rates mentioned above will continue to be used until the monitor is repaired.

If you have any questions regarding this, please contact Erick Matzke at (402) 533-6855.

Sincerely, D. J. Bannister Plant Manger Fort Calhoun Station DJB/EPM/epm Enclosures 7 c: E. W. Merschoff, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector Winston & Strawn