04-11-2016 | On February 13 through 15, 2016, February 15 through 16, 2016, and February 17 through 18, 2016 operations with the potential to drain the reactor vessel ( OPDRV) activities were performed while Unit 1 remained in Refueling Mode (Mode 5) without an operable secondary containment. These activities are prohibited by Technical Specifications (TS) 3.6.4.1. However, recent NRC guidance provided in Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 and in Regulatory Issue Summary ( RIS) 2012-11 allowed the implementation of interim actions as an alternative to full compliance. These actions are compiled in the operating procedure for the OPDRV activities performed during the 2016 Hatch Unit 1 Refueling Outage in February.
The performance of OPDRV activities were planned activities that were completed under the guidance of plant procedures and confirmed to have low safety significance based on interim actions taken. Since these actions were deliberate, no cause determination was necessary. A licensee amendment request ( LAR) will be submitted following NRC approval of the Technical Specification Task Force ( TSTF) Traveler associated with generic resolution of this issue ( TSTF-542). |
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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] |
(02-2014) Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> ".0 RCN,.
f ,1 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 ) LICENSEE EVENT REPORT (LER) ChgovmmandtohirDeshil79 OthlfiCen DCr Offic2BB5e of Inform hratirn iBntemeht ge--m5:153to)infot HectsNuclear Regourceula:nryrc.
, / CONTINUATION SHEET and Regulatory Affairs, NEOB-10202, (3150-0194), 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.
Edwin I. Hatch Nuclear Plant Unit 1 05000 321
PLANT AND SYSTEM IDENTIFICATION
General Electric- Boiling Water Reactor (BWR) Energy Industry Identification System codes appear in the text as (EIIS Code XX)
DESCRIPTION OF EVENT
In February 2016, with Unit 1 at 0 percent rated thermal power due to a scheduled refueling outage, operations with the potential to drain the reactor vessel (OPDRV) activities were performed while in Mode 5 (Refueling Mode) contrary to Technical Specification (TS) 3.6.4.1. The NRC recognizes that such activities need to be performed during refueling outages. Activities are underway to formulate acceptable generic changes to BWR Technical Specifications. NRC Regulatory Issue Summary (RIS) 2012-11 communicated this guidance to the industry. Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 currently provides enforcement discretion for licensee noncompliance with TS containment requirements during OPDRV activities until December 31, 2017 while the NRC staff and Boiling Water Reactor Owner's Group finalize a generic solution for TS changes. The required interim actions specified in the EGM were incorporated into plant procedure 31GO-OPS-025-0 "Operations With The Potential To Drain The Reactor Vessel".
This procedure was utilized during the following three occasions during the 2016 Unit 1 Refueling Outage:
Table 1: Hatch Unit 1 OPDRVs Performed February 2016 OPDRV Activity Start End LPRM replacement activity 02/13/2016, 2130 EST 02/15/2016, 0149 EST CRD push-pull activity 02/15/2016, 1213 EST 02/16/2016, 0740 EST CRD insert / re-couple activity 02/17/2016, 1547 EST 02/18/2016, 1038 EST
CAUSE OF EVENT
Implementation of the required EGM 11-003, Revision 3 interim actions during the 2016 Unit 1 Refueling Outage was a planned activity. As such, no cause determination was performed for the events.
REPORT ABILITY AND SAFETY ASSESSMENT
This event is reportable per 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by Technical Specifications (TS) 3.6.4.1.C.3, which prohibits performing activities identified as OPDRVs in Mode 5 while secondary containment is inoperable.
The OPDRVs discussed in this report performed during the Unit 2 Refueling Outage were accomplished using interim actions provided by the NRC in EGM 11-003, Revision 3. Hatch adhered to the NRC plain language meaning of OPDRV activities that could potentially result in draining or siphoning the reactor pressure vessel (RPV) water level below the top of the fuel. Hatch also met the requirements which specify the minimum makeup flow rate and water inventory based on OPDRV activities with long drain down times.
Furthermore, an adequate defense in depth was maintained to minimize the potential for the release of fission products with secondary containment not operable by (a) monitoring RPV level to identify the onset of a loss of inventory event, (b) maintaining the capability to isolate the potential leakage paths, (c) prohibiting Mode 4 (cold shutdown) OPDRV activities, and (d) prohibiting movement of irradiated fuel with the spent fuel storage pool gates removed in Mode 5.
All other Mode 5 Technical Specifications requirements for OPDRV activities were followed. Since these compensatory measures were properly implemented, an adequate level of safety was provided during the performance of the OPDVR activities described in this report Based on this information, the performance of these OPDRV activities were determined to have a very low safety significance.
CORRECTIVE ACTIONS
Consistent with the guidance given in EGM 11-003 Revision 3, Hatch will submit a licensee amendment request (LAR) following NRC approval of the Technical Specifications Task Force (TSTF) Traveler associated with generic resolution of this issue within the time restraints given in the EGM.
ADDITIONAL INFORMATION
Other Systems Affected: None.
Failed Components Information: None.
Commitment Information: This report does not created any new licensing commitments.
Previous Similar Events:
On February 16, 2015, February 20, February 18 through 19, 2015, and February 23 through 24, 2015, OPDRV activities were performed while Unit 2 was in Refueling Mode (Mode 5) without an operable secondary containment These activities are prohibited by Technical Specifications (TS) 3.6.4.1. However, NRC guidance provided in Regulatory Issue Summary (RIS) 2012-11 and in Enforcement Guidance Memorandum (EGM) 11-003, Revision 2 allowed the implementation of interim actions as an alternative to full compliance. An adequate defensed in depth was maintained to minimize the potential for the release of fission products with secondary containment not operable by (a) monitoring RPV level to identify the onset of a loss of inventory event, (b) maintaining the capability to isolate the potential leakage paths, (c) prohibiting Mode 4 (cold shutdown) OPDRV activities, and (d) prohibiting the movement of irradiated fuel with the spent fuel storage pool gates removed in Mode 5. The associated Technical Specification Task Force (TSTF) Traveler is not yet available as a Technical Specification consolidated line item improvement process (CLIIP) for use by licensees. For that reason, the corrective actions from this event would not be expected to have prevented the condition reported in this LER.
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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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