ML14241A697
| ML14241A697 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/29/2014 |
| From: | Dean E Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LlC-14-0113 | |
| Download: ML14241A697 (2) | |
Text
--~..:...
jjjjjjjj Omaha Public Power Oistrict 444 South 16111 Street Mall Omaha, NE 68102-2247 LlC-14-0113 August29,2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No.1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 10 CFR 50.36(c)(8)
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." Technical Specification 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.
Technical Specification 2.21, Table 2 10, item 3, specifies a minimum of one (1) operable channel for the Main Steam Line Radiation Monitor RM-064.
Footnote (a) of Table 2 10 states:
(a)
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.
The discharge pressure and temperature for Radiation Monitor RM-064, Main Steam Line Radiation Monitor, were found higher than normal due to leakage from the isolation valve HCV-921, the instrument was evaluated, and was declared inoperable on August 21, 2014, at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> Central Daylight Time (CDT). Troubleshooting performed on RM-064 determined that the unit's isolation valve, HCV-921, was not properly seated, allowing steam from Steam Generator A to mix with steam from Steam Generator B during monitoring.
NRC FORM 366 (10-2010)
u.s. Nuclear Regulatory Commission LI C-14-0 113 Page 2 Since the duration of the inoperability of RM-064 has exceeded seven days, this special report is required.
OPPD has implemented a pre-planned alternate method for monitoring the appropriate parameters. Additionally, Radiation Monitor RM-057, Condenser Off Gas Radiation Monitor, is operable and monitoring the condenser's radiation level.
OPPD is coordinating with the vendor and peer stations to repair the monitor. It is expected that RM-064 will be returned to service no later than 10.15.2014.
There are no new commitments being made in this letter. If you should have any questions, please contact Terrence W. Simpkin, Manager, Site Regulatory Assurance, at (402) 533-6263.
EDD/epm Attachment c:
M. L. Dapas, NRC Regional Administrator, Region IV J. K. Rankin, NRC Project Manager S.M. Schneider, NRC Senior Resident Inspector NRC FORM 366 (02*2014)