ENS 40503
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ENS Event | |
|---|---|
22:35 Feb 3, 2004 | |
| Title | Technical Specification Required Shutdown Due to Rcs Pressure Boundary Leakage |
| Event Description | The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
On February 3, 2004 at approximately 14:18 MST, Palo Verde Nuclear Generating Station (PVNGS) Unit 1 identified reactor coolant system (RCS) pressure boundary leakage. PVNGS Unit 1 was in Mode 1 (Power Operation) at 99% power with normal RCS temperature and pressure at the time of discovery. A normal reactor shutdown was commenced at 15:35. Technical Specification Limiting Condition for Operation 3.4.14 (RCS Operational Leakage) allows no pressure boundary leakage and requires the plant to be in Mode 3 (Hot Shutdown) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 (Cold Shutdown) within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and TLCO 3.14.103 (Structural Integrity). The leakage was discovered on a High Pressure Safety Injection Drain Valve (SIA-V056) with is connected to the RCS loop 1 hot leg and is non isolable. The location of the leak is at a weld on the valve socket weld and is estimated at 10 drops per second. No automatic or manual reactor protection system or engineered safety features actuations occurred and none were required. There were no other component failures, testing or work in progress that contributed to the leak. The leak is located within the containment building, therefore there is no release of radioactivity to the environment and no impact to the health and safety of the public. There is no elevated RCS activity and heat removal is via normal steaming to the main turbine condenser, The electric grid is stable. The licensee has notified the NRC resident Inspector. |
| Where | |
|---|---|
Palo Verde  Arizona (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000528/LER-2004-001 |
| Time - Person (Reporting Time:+-3.72 h-0.155 days <br />-0.0221 weeks <br />-0.0051 months <br />) | |
| Opened: | Dan Autala 18:52 Feb 3, 2004 |
| NRC Officer: | Mike Ripley |
| Last Updated: | Feb 3, 2004 |
| 40503 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (99 %) |
| After | Power Operation (45 %) |
Palo Verde with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 567852023-10-09T22:07:0009 October 2023 22:07:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 523092016-10-20T01:30:00020 October 2016 01:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Safety Injection Piping Weld Flaw ENS 519102016-05-05T12:00:0005 May 2016 12:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded High Pressure Safety Injection Valve Bonnet Leakage Identified During Refueling Outage ENS 518612016-04-11T12:35:00011 April 2016 12:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Bounday Leakage ENS 509682015-04-08T10:30:0008 April 2015 10:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage Identified ENS 506002014-11-06T18:16:0006 November 2014 18:16:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Dropped Control Element Assembly ENS 496012013-12-03T06:24:0003 December 2013 06:24:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Dropped Control Element Assembly ENS 494162013-10-07T09:19:0007 October 2013 09:19:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Coolant System Pressure Boundary Leakage Identified ENS 442742008-06-06T06:56:0006 June 2008 06:56:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Leak in Safety Injection Tank Vent Line ENS 438042007-11-24T05:26:00024 November 2007 05:26:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Plant Shutdown Due to Inoperable Load Sequencer ENS 437362007-10-22T10:11:00022 October 2007 10:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Due to Inoperable Steam Driven Auxiliary Feedwater Pump ENS 431732007-02-19T21:57:00019 February 2007 21:57:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit 2 Performed a Ts Required Shutdown ENS 428862006-10-07T18:40:0007 October 2006 18:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Axial Indications Identified on Pressure Boundry 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 424872006-04-10T19:33:00010 April 2006 19:33:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit 2 Entered a Ts Required Shutdown Due to Inoperable Auxiliary Feedwater Pumps 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 419392005-08-22T23:05:00022 August 2005 23:05:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Core Protection Calculator System (Cpcs) Software Not Consistent with System Design Requirements. ENS 419132005-08-12T07:19:00012 August 2005 07:19:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Entered Lco Action Statement 3.8.1 to Be in Mode 5 Due to Unit 1 "B" Diesel Gen. Being Declared Inoperable ENS 417832005-06-17T18:00:00017 June 2005 18:00:00 10 CFR 21.21, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Degraded Condition Due to Pressurizer Heater Element Non-Conformance ENS 416292005-04-23T07:00:00023 April 2005 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovered Two Axial Indications on Inside Diameter of Reactor Vessel Head Penetration ENS 415022005-03-18T22:00:00018 March 2005 22:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Diesel Generator ENS 413892005-02-09T08:04:0009 February 2005 08:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Shutdown Due to Loss of Normal and Alternate Power to Safety Bus ENS 405562004-02-29T07:00:00029 February 2004 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boric Acid Residue Found on Pressurizer Heater Sleeve ENS 405032004-02-03T22:35:0003 February 2004 22:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Rcs Pressure Boundary Leakage ENS 397142003-03-29T11:00:00029 March 2003 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 2023-10-09T22:07:00 | |
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