ENS 48395
ENS Event | |
|---|---|
01:15 Oct 4, 2012 | |
| Title | Unanalyzed Fire Protection Deficiencies |
| Event Description | On 10/9/12, at 16:30 PDT control room operators were questioned whether recently identified fire protection program deficiencies should have been reported to the NRC.
On October 3 and October 8, 2012, DCPP [Diablo Canyon Power Plant] staff reviewing NFPA 805 Nuclear Safety Capability Assessment (NSCA) Variance From Deterministic Requirements (VFDRs) identified fire areas that neither conformed to Appendix R requirements nor had established, proceduralized and practiced compensatory measures in place. The issues were identified in the DCPP corrective action program and compensatory measures were established in accordance with the DCPP fire protection program requirements. Event: 10/3/12 Fire areas containing cables associated with startup transformers 1-2 and 2-2 could result in loss of startup power and also prevent the emergency diesels from performing their Appendix R safe shutdown function. Event: 10/8/12 Fire areas containing reactor coolant pump (RCP) breakers could result in loss of RCP seal cooling and prevent the credited local manual trip of the RCPs, contrary to the specified method of performing the Appendix R safe shutdown function. Event: 10/8/12 Fire areas containing cables for the ventilation systems of the 480V switchgear, DC panels, and battery chargers could require unproceduralized use of portable fans to maintain adequate cooling of the electrical equipment necessary to perform the Appendix R safe shutdown function. Operators established fire watches as compensatory measures as required by the DCPP fire protection program requirements. The above late notification of discovery of the unanalyzed conditions has been entered into the DCPP corrective action program. NRC Resident Inspector has been notified.
This is an update to EN #48395 reported on October 10, 2012, at 0032 EDT. During the NRC's Fire Protection Triennial Inspection the NRC identified that several Alternate Compensatory Measures (ACMs) were not in the current post-fire procedure CP M-10. The ACMs address potential Appendix R non-conformance issues identified via the initiative to convert the DCPP fire protection program to NFPA 805. PG&E has established compensatory measures for all the identified areas in accordance with the DCPP fire protection program requirements. [The] NRC Resident Inspector has been notified. Notified R4DO (Deese).
This is an update to EN #48395 reported on October 9, 2012, at 2132 PST. During the ongoing evaluation of the issues previously identified in this event notification, PG&E [Pacific Gas & Electric] has concluded that a fire in the fire areas containing cables associated with startup transformers 1-2 and 2-2 would not result in loss of startup power or prevent the emergency diesels from performing their Appendix R safe shutdown function. This issue was reported as an unanalyzed condition. However, it is analyzed and controlled in plant procedure CP M-10, 'Fire Protection of Safe Shutdown Equipment.' PG&E retracts the initial event documented on October 3, 2012, thus making the date on which the first unanalyzed condition was discovered October 8, 2012. Therefore, PG&E will submit the 60-day Licensee Event Report by December 7, 2012. The NRC Resident Inspector has been notified. Notified the R4DO(Whitten).
This is an update to EN #48395 reported on October 9, 2012, at 2132 PDT. On October 31, 2012, at 2128 PDT, PG&E provided an update to this event notification identifying that several alternate compensatory measures (ACMs) were not in plant procedure, CP M-10, 'Fire Protection of Safe Shutdown Equipment.' PG&E has evaluated this further and concluded that ACMs had been adequately implemented in CP M-10, and therefore retracts the EN update of [November 1, 2012 at 0028 EDT]. NRC resident inspector has been notified. Notified R4DO (Walker). |
| Where | |
|---|---|
Diablo Canyon  California (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+143.28 h5.97 days <br />0.853 weeks <br />0.196 months <br />) | |
| Opened: | John Whetsler 00:32 Oct 10, 2012 |
| NRC Officer: | Dong Park |
| Last Updated: | Jan 30, 2013 |
| 48395 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 544172019-11-30T19:00:00030 November 2019 19:00:00
[Table view]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 Both Trains of Containment Spray Removed from Service ENS 522602016-09-21T03:47:00021 September 2016 03:47:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Steam Line Pipe Whip Restraint Coupling Sleeve Found Not Engaged ENS 503342014-08-01T00:29:0001 August 2014 00:29:00 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)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Unanalyzed Condition ENS 498792014-03-06T17:06:0006 March 2014 17:06:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Regarding Potential Tornado Missile Damage to Emergency Diesel Exhaust Plenum ENS 496632013-12-19T15:52:00019 December 2013 15:52:00 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 Two of Three Emergencey Diesel Generators Inoperable at the Same Time ENS 496342013-12-14T23:03:00014 December 2013 23:03:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Affecting Unit 1 Emergency Diesel Generator ENS 491482013-06-26T04:58:00026 June 2013 04:58:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 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, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required Due to Rhr System Socket Weld Leak ENS 491472013-06-24T23:15:00024 June 2013 23:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Emergency Diesel Generators Unavailable for Auto-Start ENS 487262013-02-06T23:24:0006 February 2013 23:24:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Control Room Ventilation ENS 483952012-10-04T01:15:0004 October 2012 01:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Fire Protection Deficiencies ENS 482462012-08-29T00:00:00029 August 2012 00:00:00 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 Mitigating Actions Implemented for Inoperable Control Room Envelope ENS 475642011-12-31T10:00:00031 December 2011 10:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Barrier Rating of Vital Swtichgear Walls May Not Meet Standards ENS 474142011-11-03T22:50:0003 November 2011 22:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Control Room Ventilation Single Point Vulnerability ENS 472582011-09-13T00:45:00013 September 2011 00:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Control Room Envelope Declared Inoperable ENS 472232011-08-30T00:24:00030 August 2011 00:24:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Maintenance Inadvertently Renders Control Room Ventilation System Inoperable ENS 465312011-01-10T21:21:00010 January 2011 21:21:00 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 Both Trains of Auxiliary Building Ventilation Became Inoperable ENS 457542010-03-10T03:16:00010 March 2010 03:16:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Loss of 1E Pumps Due to Degraded Voltage During Postulated Accidents ENS 454612009-10-23T15:00:00023 October 2009 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Post Loca Recirculation Valve Position Interlocks ENS 449272009-03-22T20:34:00022 March 2009 20:34:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unit 1 Steam Generator Found in an Unanalyzed Condition Related to Gaps on Seismic Washer Plates 2019-11-30T19:00:00 | |