05000387/FIN-2011004-03: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 12: | Line 12: | ||
| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.15 | | Inspection procedure = IP 71111.15 | ||
| Inspector = A Rosebrook, C Crisden, D Schroeder, E Miller, J Furia, J Greives, J Noggle, K Modes, P Finney, P Krohn, R Fuhrmeister, S Ibarrola, T Fish, W Schmidta, | | Inspector = A Rosebrook, C Crisden, D Schroeder, E Miller, J Furia, J Greives, J Noggle, K Modes, P Finney, P Krohn, R Fuhrmeister, S Ibarrola, T Fish, W Schmidta, Rosebrooke Burket, J Greives, M Orr, P Finney, P Krohn, S Pindale | ||
| CCA = P.2 | | CCA = P.2 | ||
| INPO aspect = PI.2 | | INPO aspect = PI.2 | ||
| description = On June 29, 2011, Unit 2 RCIC was declared inoperable after it tripped on over speed in automatic flow control when initiated for SR 3.5.3.3 between 920 and 1060 psig reactor pressure. RCIC had previously been operated in manual flow control for SR 3.5.3.4 with reactor pressure less than 165 psig reactor pressure. The failure was attributed to the ramp generator signal converter (RGSC) prior to the end of the refueling outage. The completion of SR 3.5.3.4 did not identify the issue with the RGSC. PPL entered this issue into their CAP as CR 1430270. At the end of this inspection period, PPL was conducting an apparent cause evaluation, a root cause analysis (RCA), and post-mortem investigation of the RGSC. This issue will be tracked as an URI pending inspection and review of PPL\'s completed ACE, RCA, and RGSC investigation | | description = On June 29, 2011, Unit 2 RCIC was declared inoperable after it tripped on over speed in automatic flow control when initiated for SR 3.5.3.3 between 920 and 1060 psig reactor pressure. RCIC had previously been operated in manual flow control for SR 3.5.3.4 with reactor pressure less than 165 psig reactor pressure. The failure was attributed to the ramp generator signal converter (RGSC) prior to the end of the refueling outage. The completion of SR 3.5.3.4 did not identify the issue with the RGSC. PPL entered this issue into their CAP as CR 1430270. At the end of this inspection period, PPL was conducting an apparent cause evaluation, a root cause analysis (RCA), and post-mortem investigation of the RGSC. This issue will be tracked as an URI pending inspection and review of PPL\\\'s completed ACE, RCA, and RGSC investigation | ||
}} | }} |
Latest revision as of 19:43, 20 February 2018
Site: | Susquehanna |
---|---|
Report | IR 05000387/2011004 Section 1R15 |
Date counted | Sep 30, 2011 (2011Q3) |
Type: | URI: Green |
cornerstone | Mitigating Systems |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.15 |
Inspectors (proximate) | A Rosebrook C Crisden D Schroeder E Miller J Furia J Greives J Noggle K Modes P Finney P Krohn R Fuhrmeister S Ibarrola T Fish W Schmidta Rosebrooke Burket J Greives M Orr P Finney P Krohn S Pindale |
CCA | P.2, Evaluation |
INPO aspect | PI.2 |
' | |