ENS 48814
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ENS Event | |
|---|---|
02:21 Mar 9, 2013 | |
| Title | Spent Fuel Pool Criticality Analysis of Record Not Revised Following Power Uprate |
| Event Description | During review of industry operating experience, engineering personnel determined the Palo Verde Nuclear Generating Station (PVNGS) analysis of record (AOR) for Spent Fuel Pool (SFP) criticality was not revised to support a license amendment to allow power uprate to 3990 MW thermal. The power uprate impacted the reactivity of fuel discharged to the SFP but the SFP criticality AOR was not revised to account for the impact to fuel reactivity. At 1921 [MST] on March 8, 2013, PVNGS received preliminary analysis from Westinghouse that indicates the current AOR for SFP criticality is nonconservative due to the impact of the power uprate. However, significant margin is maintained to SFP criticality at the current Technical Specification minimum SFP boron concentration requirement of 2150 parts per million (ppm) and additional margin is provided by procedure requirements which maintain SFP boron concentration greater than 4000 ppm. Margin also exists due to the maximum fuel enrichment used at PVNGS being less than the fuel enrichment assumed in the AOR.
The SFP criticality analysis supports Technical Specification (TS) LCOs 3.7.15 (Fuel Storage Pool Boron Concentration) and 3.7.17 (Spent Fuel Assembly Storage) as well as TS Design Features 4.3.1 (Fuel Storage Criticality). This notification is being made pursuant to the reporting requirements of 10CFR50.72 (b)(3)(ii)(B) to describe an unanalyzed condition. The NRC Resident Inspector has been notified of this condition. |
| Where | |
|---|---|
Palo Verde  Arizona (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+2.6 h0.108 days <br />0.0155 weeks <br />0.00356 months <br />) | |
| Opened: | Sean Davison 04:57 Mar 9, 2013 |
| NRC Officer: | Dong Park |
| Last Updated: | Mar 9, 2013 |
| 48814 - 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 %) |
Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 539682019-04-01T03:06:0001 April 2019 03:06:00
[Table view]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 Due to Eccs Leakage ENS 520832016-07-12T20:00:00012 July 2016 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Degraded Fire Barrier ENS 494112013-10-04T16:46:0004 October 2013 16:46:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Fire Event Could Result in a Hot Short That Could Adversely Impact Safe Shutdown Equipment ENS 488142013-03-09T02:21:0009 March 2013 02:21:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Spent Fuel Pool Criticality Analysis of Record Not Revised Following Power Uprate ENS 474592011-11-19T15:28:00019 November 2011 15:28:00 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 the Low Pressure Safety Injection System Was Subjected to High Pressure Resulting in Both Trains Being Declared Inoperable ENS 448462009-02-11T20:18:00011 February 2009 20:18:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Possibly Inadequate Backup Nitrogen Supply for Atmospheric Dump Operation ENS 431402007-02-03T19:32:0003 February 2007 19:32:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Technical Specification 3.0.3 Entered During Routine Surveillance Testing of Control Element Assemblies (Cea'S) ENS 428472006-09-19T08:05:00019 September 2006 08:05:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Pressurizer Heater Capacity Less than Tech Spec Limit ENS 427322006-07-27T02:00:00027 July 2006 02:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Limiting Condition for Operation 3.7.4 Deemed to Be Nonconservative ENS 420502005-10-11T23:02:00011 October 2005 23:02:00 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, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown of Both Unit 2 and 3 ENS 417892005-06-23T15:23:00023 June 2005 15:23:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unit 2 Aux Feedwater Train Separation Not Maintained During Operation 2019-04-01T03:06:00 | |
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