ENS 47810: Difference between revisions
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ENS Event | |
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02:38 Apr 6, 2012 | |
| Title | Standby Shutdown Facility (Ssf) Not Analyzed For All Operating Conditions |
| Event Description | On 3/29/2012 Duke Energy identified that unanalyzed conditions exist for SSF mitigated events since associated thermal and hydraulic analyses do not consider all initial operating conditions, especially lower operating modes and lower decay heat. Specifically there are four (4) conditions where the SSF is not currently analyzed:
1. SSF operating at less than 525 degrees F and less than normal operating pressure (approximately 2155 psig), 2. SSF operation before four (4) Effective Full Power Days (EFPDs), 3. SSF reactor coolant make up at low Reactor Coolant System (RCS) pressure. 4. A reactor trip from less than 85 percent power and less than 579 degrees F. On 4/4/2012, an immediate determination of operability concluded that for the first three (3) conditions the SSF was operable but degraded/nonconforming (OBDN). For the 4th issue, there was reasonable assurance that 1% delta k/k shutdown margin would be maintained if T average. remained above 500 degrees F. Based on a lack of analysis and an increased likelihood of reducing T average. below 525 degrees F during a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> event, the SSF was declared OBDN with a separate operability determination required to validate the Unit 3 power coastdown and end of life T average. reduction analysis. Until additional analysis is performed, the SSF is inoperable on any unit where the power level is reduced below 85 percent. A second operability determination for Unit 3 concluded that the SSF will maintain greater than or equal to 525 degrees F with an initial power level of 70 percent and a 570 degree F T average. The SSF will be declared inoperable on Unit 3 if power is reduced to less than 70 percent. Seventy percent was chosen as a conservative value to ensure the unit stayed inside the bounds of existing analyses. Unit 3 is currently at approximately 85 percent power and reducing power at approximately 1 percent per day in preparation for the Unit 2 end of core 26 refueling outage. For Unit 3, the SSF is OBDN based on preliminary calculation results. On 4/5/2012, due to a worsening component cooling water system leak on Unit 2, it was necessary to bring the unit down to Mode 3 to implement repairs. Upon down power, when Unit 2 transitioned below 85 percent power, the ability of the SSF to perform its design function, in consideration of the information above, could not be confirmed and the SSF was declared inoperable for Unit 2. Currently, there is no conclusive information that would support SSF operability while Unit 2 is below 85 percent power. As such, this event is being conservatively reported under 50.72(b)(3)(ii)(B), 'The nuclear plant being in an unanalyzed condition that significantly degrades plant safety.' Due to their current power levels, this condition does not affect Units 1 and 3. Initial Safety Significance: Until confirmed by analysis, the lack of decay heat may result in an initial over cooling of the RCS and potentially an interruption of natural circulation or inadequate shutdown margin. Consequently, the SSF was declared inoperable. Corrective Action(s): Additional analyses are being completed to reestablish SSF operability to bound the unanalyzed entry conditions. The NRC Resident Inspector has been informed.
Update to ENS Notification Number 47810: ENS Notification 47810 identified an unanalyzed condition for Oconee Unit 2. This update includes Oconee Units 1, 2 and 3 because the condition of the SSF affects all three units during certain plant conditions. The Standby Shutdown Facility (SSF) serves as a backup for existing safety systems. Currently the events that rely upon the SSF for mitigation are unanalyzed on Units 1 and 2 when the power level is reduced below 85 percent and on Unit 3 when the power level is reduced below 70 percent, or for any unit operating with less than 4 Effective Full Power Days (EFPDs) at 100% full power since its most recent shutdown. Since the SSF events are unanalyzed for these conditions and until further analysis and evaluation can be completed, Duke Energy is conservatively calling the SSF inoperable when in these conditions. For these conditions, this event is being reported for Oconee Units I, 2, and 3 under 50. 72(b )(3)(ii)(B), that is, the nuclear plant being in an unanalyzed condition that significantly degrades plant safety. Based on current analyses, the SSF will be declared inoperable, and action statements entered on Units 1 or 2 if power is reduced below 85% power and on Unit 3 if power is reduced below 70% power, or for any unit operating with less than 4 EFPDs since its most recent shutdown. Initial Safety Significance: Until confirmed by analysis or evaluation, the lack of decay heat may result in an initial over cooling of the RCS and potentially fail the various acceptance criteria of the events required to be augmented by the SSF. Consequently, the SSF will be declared inoperable for the conditions stated above. Unit 3 is being shut down for a routine refueling outage. Units 1 and 2 continue to operate at 100% power with no problems. Corrective Action(s): Additional evaluations are being completed to establish whether the existing analyses are applicable to the conditions outside of which they were performed and, if not, there is a reasonable assurance that successful mitigation can be accomplished with the existing procedure. If not, further licensing action may be required. These evaluations were initiated on April 4, 2012, and are ongoing. The licensee has notified the NRC Resident Inspector. Notified the R2DO (Kathleen O'Donohue). |
| Where | |
|---|---|
Oconee  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+1.32 h0.055 days <br />0.00786 weeks <br />0.00181 months <br />) | |
| Opened: | Stephen Newman 03:57 Apr 6, 2012 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Apr 13, 2012 |
| 47810 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (85 %) |
WEEKMONTHYEARENS 506402014-11-25T17:12:00025 November 2014 17:12:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Deficiency in Methodology Used for Emergency Core Cooling System Performance Requirements ENS 499682014-03-28T17:00:00028 March 2014 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Keowee Emergency Power System 13.8Kv Cable May Not Comply with Licensing Basis ENS 490682013-05-24T18:00:00024 May 2013 18:00:00 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 Heating Ventilation and Air Condition System Inadequately Analyzed for Heat Load ENS 478102012-04-06T02:38:0006 April 2012 02:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Standby Shutdown Facility (Ssf) Not Analyzed for All Operating Conditions ENS 423182006-02-07T01:50:0007 February 2006 01:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Non-Conforming Fire Barriers ENS 418502005-07-18T15:30:00018 July 2005 15:30:00 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 Electrical Alignment Results in Single Failure Vulnerability ENS 417282005-05-24T17:50:00024 May 2005 17:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Emergency Backup Power Generators ENS 407242004-05-04T20:55:0004 May 2004 20:55:00 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 Unanalyzed Condition and Potential Loss of Containment Safety Function ENS 401922003-09-23T08:00:00023 September 2003 08:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Potential Rcs Leakage at Oconee 1 2014-03-28T17:00:00 | |