01-04-2017 | On November 7, 2016 at 2355 EST, while performing a main control board panel walkdown, it was d'scovered that the High Pressure Coolant Injection ( HPCI) vacuum breaker motor operated isolation valve 2E41F111 had been left in the open position with its breaker turned off. Upon further review of the associated tagout, it was determined that this primary containment isolation valve ( PCIV) had been in this inoperable configuration greater than allowed LCO time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 2E41F111 was then declared inoperable and the 2E41F104 redundant Technical Specifications (TS) LCO 3.6.1.3, Condition A.1.
The inoperable as-found condition of the 2E41F111 PCIV was due to supervision failing to recognize that the tagout preparer did not possess the proper skill set to perform the task. Although the 2E41F111 was left in the open position with its breaker turned off, the manual HPCI turbine exhaust valve 2E41F021 was tagged in the closed position per the tagout instructions. Therefore, closure of the 2E41F021 ensured the affected piping was isolated such that primary containment boundary functions were maintained. Expectations were instituted to ensure individuals assigned with preparing tagouts associated with TS equipment are trained on the basics of TS. |
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Category:Letter
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[Table view] Category:Licensee Event Report (LER)
MONTHYEARNL-20-0230, Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2020-03-0202 March 2020 Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 05000366/LER-2020-0012020-03-0202 March 2020 LER 2020-001-00 for Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 05000321/LER-2017-0042017-08-24024 August 2017 Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications, LER 17-004-00 for Edwin I. Hatch Regarding Safety Relief Valves' as Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria 05000366/LER-2017-0022017-04-13013 April 2017 Emergency Diesel Generator Start Due to Inadvertent Electrical Bus De-Energization, LER 17-002-00 for Edwin I. Hatch, Unit 2, Regarding Emergency Diesel Generator Start Due to Inadvertent Electrical Bus De-Energization 05000366/LER-2017-0032017-04-13013 April 2017 LER 17-003-00 for Edwin I. Hatch, Unit 2, Regarding Primary Containment Isolation Penetration Exceeded Overall Allowable Technical Specification Leakage Limits 05000321/LER-2017-0022017-04-0707 April 2017 High Pressure Coolant Injection System Declared Inoperable Due to Degraded Inverter, LER 17-002-00 for Edwin I. Hatch, Unit 1, Regarding High Pressure Coolant Injection System Declared Inoperable Due to Degraded Inverter 05000366/LER-2016-0042017-01-0303 January 2017 Condition Prohibited by Technical Specifications Due to Inoperable PCIV, LER 16-004-00 for Edwin I. Hatch Nuclear Plant, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to Inoperable PCIV 05000366/LER-2016-0022016-07-13013 July 2016 Group I Isolation Received During Turbine Testing, LER 16-002-00 for Edwin I. Hatch, Unit 2, Regarding Group 1 Isolation Received During Turbine Testing 05000366/LER-2016-0012016-06-0808 June 2016 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability, LER 16-001-00 for E.I. Hatch, Unit 2, Regarding 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability 05000321/LER-2016-0042016-05-26026 May 2016 Safety Relief Valves As Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria, LER 16-004-00 for Edwin I. Hatch Nuclear Plant Unit 1 RE: Safety Relief Valves as Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria 05000321/LER-2016-0032016-04-14014 April 2016 Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage, LER 16-003-00 for E.I. Hatch, Unit 1, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage 05000321/LER-2016-0022016-04-11011 April 2016 Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment, LER 16-002-00 for E.I Hatch, Unit 1, Regarding Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment 05000321/LER-2016-0012016-04-0808 April 2016 Performance of Fuel Movement with Inoperable Rod Position Indication System in Violation of Technical Specifications, LER 16-001-00 for Edwin I. Hatch, Unit 1, Regarding Performance of Fuel Movement With Inoperable Rod Position Indication System in Violation of Technical Specifications NL-08-1906, LER 08-S01-00, for Edwin I. Hatch, Failure to Report Arrest Results in Inappropriate Access to Protected and Vital Areas2008-12-19019 December 2008 LER 08-S01-00, for Edwin I. Hatch, Failure to Report Arrest Results in Inappropriate Access to Protected and Vital Areas ML1019404552008-05-0808 May 2008 Southern Nuclear Plant E. I. Hatch - Actions for Potential Groundwater Contamination Events NL-06-2726, LER 06-S01-00 for Edwin I. Hatch Nuclear Plant, Re Contract Employee Failure to Self-Disclose Material Information for Unescorted Access2006-12-0505 December 2006 LER 06-S01-00 for Edwin I. Hatch Nuclear Plant, Re Contract Employee Failure to Self-Disclose Material Information for Unescorted Access ML17252B4401976-04-15015 April 1976 LER 76-026-00 for Hatch, Unit 1 Regarding an Occurrence of Open Links in Panel H11-P601 Defeating the Starting of All RHR Pumps After They Had Been Stopped 2020-03-02
[Table view] |
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150.0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
PLANT AND SYSTEM IDENTIFICATION
General Electric — Boiling Water Reactor Energy Industry Identification System codes appear in the text as (EIIS Code XX).
DESCRIPTION OF EVENT
On November 7, 2016 at 2355 EST, with Unit 2 at 100 percent rated thermal power (RTP), while performing a main control board panel walkdown, it was discovered that the High Pressure Coolant Injection (HPCI) vacuum breaker motor operated isolation valve 2E41F111 (EIIS Code ISV) had been left in the open position with its breaker turned off. Upon subsequent investigation, it was determined that since the valve provides a primary containment isolation function, it is required for operation in the current plant condition. The 2E41F111 was then declared inoperable and the 2E41F104 redundant penetration motor operated isolation valve was closed and deactivated to meet the required action per Unit 2 Technical Specifications (TS) LCO 3.6.1.3, Condition A.1.
CAUSE OF EVENT
The unacceptable as-found condition of the 2E41 F111 primary containment isolation valve (PCIV) was due to supervision failing to recognize that the tagout preparer did not possess the proper skill set to perform the task. This led to assigning an individual to prepare the tag out who did not have the appropriate knowledge of basic TS. Additionally, invalid assumptions were made by the tag out reviewer concerning the PCIV TS Bases when rendering a PCIV inoperable.
REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT
This event is reportable per 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. Upon review of the tagout, it was determined that the valve had been in a condition prohibited by TS for greater than the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LCO completion time.
Although the 2E41F111 was left in the open position with its breaker turned off, the manual HPCI turbine exhaust valve 2E41F021 was tagged in the closed position per the tagout instructions. This allowed the associated piping to be isolated such that primary containment boundary functions as assumed in the safety analyses were maintained. However, because the valve is Appendix J, Type A tested instead of being Appendix J, Type C tested this is a condition prohibited by TS per the Unit 2 Hatch TS Bases LCO 3.6.1.3, Condition A.1 which states that the device used to isolate a penetration must be subjected to leakage testing requirements equivalent to the inoperable valve. Therefore, if the inoperable valve is Appendix J, Type C tested, the device used to isolate the associated penetration flow path must also be Appendix J, Type C tested per current Hatch TS Bases. TS required actions were met once the 2E41F104 isolation valve was closed since this valve is also Appendix J, Type C tested. Based on this information, the event is considered to have very low safety significance.
CORRECTIVE ACTIONS
Expectations were instituted to ensure individuals assigned with preparing tagouts associated with TS equipment are trained on the basics of TS. Enhancement actions were also taken to label all PCIV equipment in the clearance and tagging database as containment related components. In addition, guidance will be provided to determine when a pre-job brief is required to be conducted before developing a tagout.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.ResourceOnrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
ADDITIONAL INFORMATION
Other Systems Affected: None.
Failed Components Information:
Master Parts List Number: 2E41F111 Manufacturer: Dresser Industries Model Number: Hancock Type 950 W Motor Operated Gate Valve Type: Isolation Valve Manufacturer Code: D245 EIIS System Code: BJ Reportable to EPIX: Yes Root Cause Code: A EIIS Component Code: ISV Commitment Information: This report does not create any licensing commitments.
PREVIOUS SIMILAR EVENTS:
None.
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05000366/LER-2016-001 | 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability LER 16-001-00 for E.I. Hatch, Unit 2, Regarding 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000321/LER-2016-001 | Performance of Fuel Movement with Inoperable Rod Position Indication System in Violation of Technical Specifications LER 16-001-00 for Edwin I. Hatch, Unit 1, Regarding Performance of Fuel Movement With Inoperable Rod Position Indication System in Violation of Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000366/LER-2016-002 | Group I Isolation Received During Turbine Testing LER 16-002-00 for Edwin I. Hatch, Unit 2, Regarding Group 1 Isolation Received During Turbine Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000321/LER-2016-002 | Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment LER 16-002-00 for E.I Hatch, Unit 1, Regarding Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000366/LER-2016-003 | 2C Emergency Diesel Generator Inoperable Due to Low Lube Oil Pressure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000321/LER-2016-003 | Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage LER 16-003-00 for E.I. Hatch, Unit 1, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000366/LER-2016-004 | Condition Prohibited by Technical Specifications Due to Inoperable PCIV LER 16-004-00 for Edwin I. Hatch Nuclear Plant, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to Inoperable PCIV | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000321/LER-2016-004 | Safety Relief Valves As Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria LER 16-004-00 for Edwin I. Hatch Nuclear Plant Unit 1 RE: Safety Relief Valves as Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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