ENS 50213
ENS Event | |
|---|---|
20:28 Jun 19, 2014 | |
| Title | |
| Event Description | A review of industry operating experience regarding the impact of unfused Direct Current (DC) circuits has determined the described condition to be applicable to the Perry Nuclear Power Plant (PNPP) resulting in an unanalyzed condition with respect to fire safe shutdown requirements.
In the postulated event, a fire induced hot short could adversely impact safe shutdown equipment. The potential exists for a secondary fire to occur due to unfused DC control circuits associated with the Turbine Emergency Bearing Oil Pump, Reactor Feed Pump Turbine 'A' Emergency Lube Oil Pump, Turbine Emergency Seal Oil Pump, and Reactor Feed Pump Turbine 'B' Emergency Lube Oil Pump. These circuits are routed from the respective equipment to other plant areas including the Unit 1 Control Room, Division 1 Cable Spreading, and Division 1 Cable Chase. Without overcurrent protection for these circuits, the potential exists that an initial fire event affecting these circuits could cause short circuits without protection that would cause excessive current through the circuit beyond the capacity rating of the conductors. This could lead to a secondary fire in another plant area where these circuits are routed challenging the ability to achieve and maintain safe shutdown. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-3.37 h-0.14 days <br />-0.0201 weeks <br />-0.00462 months <br />) | |
| Opened: | Thomas Morse 17:06 Jun 19, 2014 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Jun 19, 2014 |
| 50213 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 564552023-04-06T20:46:0006 April 2023 20:46:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Main Steam Line 'B' Leakage in Excess of Tech Spec Limits ENS 536752018-10-19T04:00:00019 October 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot-Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 536442018-10-04T04:00:0004 October 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 502132014-06-19T20:28:00019 June 2014 20:28:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to a Postulated Hot Short That Could Affect Safe Shutdown Equipment ENS 494462013-10-17T17:00:00017 October 2013 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 475452011-12-21T18:59:00021 December 2011 18:59:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Groundwater Level May Exceed Design Assumptions ENS 475082011-11-17T01:00:00017 November 2011 01:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Flooding Scenario Results in Unanalyzed Condition ENS 470242011-07-05T22:15:0005 July 2011 22:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Two Appendix R Wiring Issues That Could Potentially Affect the Ability to Shutdown ENS 436032007-08-27T20:45:00027 August 2007 20:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Grating Inside Containment Found Unsecured ENS 420722005-10-21T13:00:00021 October 2005 13:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Relocation of a Fire Door Boundary ENS 414172005-02-17T22:30:00017 February 2005 22:30:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Emergency Diesel Generators Declared Inoperable Due to Unanalyzed Condition ENS 413442005-01-19T07:37:00019 January 2005 07:37:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Emergency Diesel Generators Declared Inoperable Due to an Unanalyzed Condition ENS 404042003-12-22T01:21:00022 December 2003 01:21:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Impact to Safe Shutdown Due to Control Complex Ventilation Inoperability 2023-04-06T20:46:00 | |