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| | issue date = 03/31/2006 | | | issue date = 03/31/2006 |
| | title = IR 05000321-03-009 and 05000366-03-009, on February 14, 2006, E. I. Hatch Nuclear Plant, Units 1 and 2 | | | title = IR 05000321-03-009 and 05000366-03-009, on February 14, 2006, E. I. Hatch Nuclear Plant, Units 1 and 2 |
| | author name = Payne D C | | | author name = Payne D |
| | author affiliation = NRC/RGN-II/DRS/EB2 | | | author affiliation = NRC/RGN-II/DRS/EB2 |
| | addressee name = Sumner H L | | | addressee name = Sumner H |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:rch 31, 2006 |
| [[Issue date::March 31, 2006]]
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| Southern Nuclear Operating Company, Inc.ATTN:Mr. H. L. Sumner, Jr.Vice President P. O. Box 1295 Birmingham, AL 35201-1295
| | ==SUBJECT:== |
| | EDWIN I. HATCH NUCLEAR POWER PLANT - NRC INSPECTION REPORT NOS. 05000321/2003009 AND 05000366/2003009 |
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| SUBJECT: EDWIN I. HATCH NUCLEAR POWER PLANT - NRC INSPECTION REPORT NOS. 05000321/2003009 AND 05000366/2003009
| | ==Dear Mr. Sumner:== |
| | On February 14, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an in-office review related to an unresolved item identified during the Triennial Fire Protection Inspection of 2003. A meeting was held in the Region II office with regional staff and Mr. R. Baker and Mr. D. Parker on December 7, 2005, to discuss the status of SNC's proposed resolutions for protecting the affected cables of eleven safety-relief valves and to clarify the staffs position regarding the use of local operator actions in lieu of circuit protection as required by NRC regulations. Following completion of additional review in the Region II office, a final exit was held by telephone with Mr. D. Madison and other members of your staff on March 31, 2006. |
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| | The in-office review consisted of evaluating the safety significance of particular spurious valve operations and reviewing your compensatory measures and various proposed final resolutions. |
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| | The issue remains unresolved for reasons described in the enclosed report. |
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| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| ==Dear Mr. Sumner:==
| | Should you have any questions concerning this letter, please contact us. |
| On February 14, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an in-officereview related to an unresolved item identified during the Triennial Fire Protection Inspection of 2003. A meeting was held in the Region II office with regional staff and Mr. R. Baker and Mr. D. Parker on December 7, 2005, to discuss the status of SNC's proposed resolutions for protecting the affected cables of eleven safety-relief valves and to clarify the staff's position regarding the use of local operator actions in lieu of circuit protection as required by NRC regulations. Following completion of additional review in the Region II office, a final exit was held by telephone with Mr. D. Madison and other members of your staff on March 31, 2006.The in-office review consisted of evaluating the safety significance of particular spurious valveoperations and reviewing your compensatory measures and various proposed final resolutions.
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| The issue remains unresolved for reasons described in the enclosed report.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system(ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Should you have any questions concerning this letter, please contact us.
| | Sincerely, |
| | \\RA\\ |
| | D. Charles Payne, Chief Engineering Branch 2 Division of Reactor Safety cc w/encl - See next page |
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| Sincerely,\\RA\\D. Charles Payne, ChiefEngineering Branch 2 Division of Reactor Safetycc w/encl - See next page SNC2Docket Nos.: 50-321, 50-366License Nos.: DPR-57, NPF-5
| | SNC 2 Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| NRC Triennial Fire Protection Inspection Report Nos. 05000366/2003009,05000321/2003009 | | NRC Triennial Fire Protection Inspection Report Nos. 05000366/2003009, 05000321/2003009 w/Attachment: Supplemental Information |
| | |
| | REGION II== |
| | Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5 Report No.: 05000321/2003009 and 05000366/2003009 Licensee: Southern Nuclear Operating Company Facility: Edwin I. Hatch Nuclear Plant, Units 1 and 2 Location: P. O. Box 2010 Baxley, GA. 31513 Dates: February 14, 2006 Inspector: N. Staples, Reactor Inspector Approved by: D. Charles Payne, Chief Engineering Branch 2 Division of Reactor Safety Summary of Findings IR 05000366/2003-009, 05000321/2003-009; 02/14/2006; E. I. Hatch Nuclear Plant, Units 1 and 2. |
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| | Enclosure |
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| | The report covered an in-office review of an unresolved item related to fire protection by a Regional Inspector. The NRC*s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000. |
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| | A. NRC-Identified and Self-Revealing Findings None B. Licensee-Identified Violations None Enclosure |
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| | REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Other (Discussed) URI 05000366/2003006-01: Concerns Associated with Potential Opening of SRVs Introduction: The Inspector reviewed an unresolved item (URI) involving the failure to protect circuits against fire which could lead to spurious opening of all eleven safety relief valves (SRV). The team had found instrumentation cables, that could cause maloperation of safe shutdown equipment, in FA 2104 without adequate spatial separation or fire barriers. The finding remains unresolved pending review of proposed corrective actions for the circuit design of the eleven SRVs. |
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| | Description: During the 2003 Triennial Fire Protection Inspection, the inspection team performed a circuit analysis of Group A safety relief valves for which the licensee took safe shutdown credit for fires in Fire Area 2104, Unit 2 East Cableway. The requirements of 10 CFR 50, Appendix R, Section III.G.2, apply to this fire area. The team identified that two reactor pressure instrument cables (for circuits ABE019C08 and ABE019C09) were located in the same cable tray and thereby exposed to the same heating rate which could potentially cause both circuits to simultaneously fail high and result in all eleven SRVs spuriously opening. Each cable consisted of a single twisted pair of insulated conductors, an uninsulated drain wire that was wound around the twisted pair of conductors, and a foil shield. The conductor insulation and jacket material of each cable was cross-linked polyethylene (XLPE). A thermal assault on instrument cables could result in (false high) signals, generated as a result of leakage current in each damaged cable. These undesired false high signals could actuate the SRV electrical backup scheme and cause all eleven SRVs to open. In addition, this failure mode would defeat the capability to manually control these SRVs. Normally, whenever a SRV lifted, it would remain open until nuclear boiler pressure was reduced to about 85% of its overpressure lift setpoint. However, if the instrument loops have failed high, the trip unit master relays and the trip unit slave relays would continue to energize the pilot valve of the individual SRV and maintain the SRV open. As a result, this failure mode could result in spurious actuation of all eleven SRVs with the eleven SRVs subsequently remaining open. |
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| ===w/Attachment:===
| | In response to this finding, the licensee initiated Condition Report 2003008203 and promptly revised AOP 34AB-X43-001-2, Fire Procedure, Version 10.8 dated May 28, 2003. The procedure change enabled the local operator actions to prevent all eleven SRVs from opening simultaneously to be accomplished earlier during a fire in the Unit 2 East Cableway, or in other fire areas that were vulnerable to the potential for spuriously opening all eleven safety relief valves. While, the revised procedure was an acceptable interim compensatory measure, it was not a permanent resolution to the circuit damage issue because Appendix R, Section III.G.2 does not allow use of local operator actions in lieu of circuit protection to ensure safe shutdown. On December 7, 2005, NRC staff met with the licensee to discuss proposed options for protecting cables from a fire in FA 2104 and to clarify the staffs position on regulation regarding the use of local operator actions in lieu of circuit protection. While various options were presented by the licensee, the licensee had not yet determined a final resolution. This URI will remain open pending the licensees final resolution. |
| Supplemental Informationcc w/encl:J. T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
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| Electronic Mail DistributionGeorge R. FrederickGeneral Manager, Plant Hatch Southern Nuclear Operating Company, Inc.
| | 4OA6 Meetings, Including Exit Exit meeting Summary On March 31, 2006, the regional staff presented the status results to Dennis Madison and other members of his staff, who acknowledged the findings. The inspectors asked the licensee whether any of the material examined during the inspection should be considered proprietary. |
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| Electronic Mail DistributionRaymond D. BakerManager Licensing - Hatch Southern Nuclear Operating Company, Inc.
| | No proprietary information was identified. |
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| Electronic Mail DistributionArthur H. Domby, Esq.Troutman Sanders Electronic Mail DistributionLaurence BergenOglethorpe Power Corporation Electronic Mail DistributionBentina C. TerrySouthern Nuclear Operating Company, Inc.
| | Enclosure |
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| Bin B-022 P. O. Box 1295 Birmingham, AL 35201-1295DirectorDepartment of Natural Resources 205 Butler Street, SE, Suite 1252 Atlanta, GA 30334Manager, Radioactive Materials ProgramDepartment of Natural Resources Electronic Mail DistributionChairmanAppling County Commissioners County Courthouse Baxley, GA 31513Resident ManagerOglethorpe Power Corporation Edwin I. Hatch Nuclear Plant Electronic Mail DistributionSenior Engineer - Power SupplyMunicipal Electric Authority of Georgia Electronic Mail DistributionReece McAlisterExecutive Secretary Georgia Public Service Commission 244 Washington Street, SW Atlanta, GA 30334 EnclosureU. S. NUCLEAR REGULATORY COMMISSIONREGION IIDocket Nos.:50-321, 50-366License Nos.: DPR-57, NPF-5Report No.:05000321/2003009 and 05000366/2003009Licensee:Southern Nuclear Operating Company Facility:Edwin I. Hatch Nuclear Plant, Units 1 and 2Location:P. O. Box 2010 Baxley, GA. 31513 Dates:February 14, 2006Inspector:N. Staples, Reactor InspectorApproved by:D. Charles Payne, ChiefEngineering Branch 2Division of Reactor SafetySummary of FindingsIR 05000366/2003-009, 05000321/2003-009; 02/14/2006; E. I. Hatch Nuclear Plant, Units 1 and 2.
| | SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee Personnel: |
| | R. Baker, Licensing Supervisor (Corporate) |
| | I. Luker, Senior Engineer, Licensing D. Madison, General Manager for Plant Hatch D. Parker, Senior Engineer, Electrical K. Underwood, Performance Analysis Supervisor J. Vance, Senior Engineer, Mechanical & Civil O. Vidal, Principal Engineer, Licensing P. Wells, Plant Support General Manager LIST OF ITEMS DISCUSSED Discussed 05000366/2003006-01 URI Concerns Associated with Potential Opening of SRVs LIST OF DOCUMENTS REVIEWED Procedure: |
| | AOP 34AB-X43-001-2, Fire Procedure, Version 10.8 Drawings H-11821, Fire Hazards Analysis, Turbine Bldg. El. 130=-0@, Rev. 0 H-26014, R.H.R. System P&ID Sheet 1, Rev. 49 H-26015, R.H.R. System P&ID Sheet 2, Rev. 46 H-26018, Core Spray System P&ID, Rev. 29 H-11821, Fire Hazards Analysis Drawing, Turbine Building, Rev. 11 Calculations, Analyses, and Evaluations E. I. Hatch Nuclear Plant Units 1 and 2 Safe Shutdown Analysis Report, Rev. 20. |
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| EnclosureThe report covered an in-office review of an unresolved item related to fire protection by a RegionalInspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactorsis described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.NRC-Identified and Self-Revealing Findings NoneB.Licensee-Identified Violations None EnclosureREPORT DETAILS4.OTHER ACTIVITIES4OA5Other(Discussed) URI 05000366/2003006-01: Concerns Associated with Potential Opening of SRVsIntroduction: The Inspector reviewed an unresolved item (URI) involving the failure to protect circuitsagainst fire which could lead to spurious opening of all eleven safety relief valves (SRV). The team hadfound instrumentation cables, that could cause maloperation of safe shutdown equipment, in FA 2104without adequate spatial separation or fire barriers. The finding remains unresolved pending review ofproposed corrective actions for the circuit design of the eleven SRVs. Description: During the 2003 Triennial Fire Protection Inspection, the inspection team performed acircuit analysis of Group A safety relief valves for which the licensee took safe shutdown credit for firesin Fire Area 2104, Unit 2 East Cableway. The requirements of 10 CFR 50, Appendix R, Section III.G.2,apply to this fire area. The team identified that two reactor pressure instrument cables (for circuitsABE019C08 and ABE019C09) were located in the same cable tray and thereby exposed to the sameheating rate which could potentially cause both circuits to simultaneously fail high and result in all elevenSRVs spuriously opening. Each cable consisted of a single twisted pair of insulated conductors, anuninsulated drain wire that was wound around the twisted pair of conductors, and a foil shield. Theconductor insulation and jacket material of each cable was cross-linked polyethylene (XLPE). A thermalassault on instrument cables could result in (false high) signals, generated as a result of leakage currentin each damaged cable. These undesired false high signals could actuate the SRV electrical backupscheme and cause all eleven SRVs to open. In addition, this failure mode would defeat the capability tomanually control these SRVs. Normally, whenever a SRV lifted, it would remain open until nuclear boilerpressure was reduced to about 85% of its overpressure lift setpoint. However, if the instrument loopshave failed high, the trip unit master relays and the trip unit slave relays would continue to energize thepilot valve of the individual SRV and maintain the SRV open. As a result, this failure mode could resultin spurious actuation of all eleven SRVs with the eleven SRVs subsequently remaining open.In response to this finding, the licensee initiated Condition Report 2003008203 and promptly revisedAOP 34AB-X43-001-2, Fire Procedure, Version 10.8 dated May 28, 2003. The procedure changeenabled the local operator actions to prevent all eleven SRVs from opening simultaneously to beaccomplished earlier during a fire in the Unit 2 East Cableway, or in other fire areas that were vulnerableto the potential for spuriously opening all eleven safety relief valves. While, the revised procedure wasan acceptable interim compensatory measure, it was not a permanent resolution to the circuit damageissue because Appendix R, Section III.G.2 does not allow use of local operator actions in lieu of circuitprotection to ensure safe shutdown. On December 7, 2005, NRC staff met with the licensee to discussproposed options for protecting cables from a fire in FA 2104 and to clarify the staff's position onregulation regarding the use of local operator actions in lieu of circuit protection. While various optionswere presented by the licensee, the licensee had not yet determined a final resolution. This URI willremain open pending the licensee's final resolution.4OA6Meetings, Including ExitExit meeting SummaryOn March 31, 2006, the regional staff presented the status results to Dennis Madison and othermembers of his staff, who acknowledged the findings. The inspectors asked the licenseewhether any of the material examined during the inspection should be considered proprietary. No proprietary information was identified.
| | Edwin I. Hatch Nuclear Plant Fire Hazards Analysis and Fire Protection Program, Rev. 20 Corrective Action Reviewed CR 2003008203, Safety relief valves Manual Action Steps in Fire Procedure Attachment |
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| AttachmentSUPPLEMENTAL INFORMATIONKEY POINTS OF CONTACTLicensee Personnel
| | License Basis Documents Hatch UFSAR Section 6.3, Emergency Core Cooling System, Rev. 21 Safe Shutdown Analysis Report for E.I. Hatch Nuclear Plant Units 1 and 2, Rev. 26 Fire Hazards Analysis for E. I. Hatch Nuclear Plant Units 1 and 2, Rev.18 C, dated 7/00 Attachment |
| :R. Baker, Licensing Supervisor (Corporate)I. Luker, Senior Engineer, LicensingD. Madison, General Manager for Plant HatchD. Parker, Senior Engineer, ElectricalK. Underwood, Performance Analysis SupervisorJ. Vance, Senior Engineer, Mechanical & CivilO. Vidal, Principal Engineer, LicensingP. Wells, Plant Support General ManagerLIST OF ITEMS DISCUSSEDDiscussed05000366/2003006-01URIConcerns Associated with Potential Opening of SRVsLIST OF DOCUMENTS REVIEWEDProcedure:AOP 34AB-X43-001-2, Fire Procedure, Version 10.8 DrawingsH-11821, Fire Hazards Analysis, Turbine Bldg. El. 130
| |
| =-0@, Rev. 0H-26014, R.H.R. System P&ID Sheet 1, Rev. 49H-26015, R.H.R. System P&ID Sheet 2, Rev. 46 H-26018, Core Spray System P&ID, Rev. 29H-11821, Fire Hazards Analysis Drawing, Turbine Building, Rev. 11Calculations, Analyses, and EvaluationsE. I. Hatch Nuclear Plant Units 1 and 2 Safe Shutdown Analysis Report, Rev. 20.Edwin I. Hatch Nuclear Plant Fire Hazards Analysis and Fire Protection Program, Rev. 20Corrective Action ReviewedCR 2003008203, Safety relief valves Manual Action Steps in Fire Procedure 2AttachmentLicense Basis DocumentsHatch UFSAR Section 6.3, Emergency Core Cooling System, Rev. 21Safe Shutdown Analysis Report for E.I. Hatch Nuclear Plant Units 1 and 2, Rev. 26Fire Hazards Analysis for E. I. Hatch Nuclear Plant Units 1 and 2, Rev.18 C, dated 7/00
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| _________________________OFFICERII:DRSRII:DRSRII:DRPRII:DRSSIGNATURENLS2PJFCWR1DCPNAMENStaplesPFillionCRappDPayneDATE3/17/20063/20/20063/21/20063/31/20064/ /20064/ /20064/ /2006 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO
| | _________________________ |
| | OFFICE RII:DRS RII:DRS RII:DRP RII:DRS SIGNATURE NLS2 PJF CWR1 DCP NAME NStaples PFillion CRapp DPayne DATE 3/17/2006 3/20/2006 3/21/2006 3/31/2006 4/ /2006 4/ /2006 4/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO |
| }} | | }} |
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ML23250A0472023-09-20020 September 2023
Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes
ML23241B0212023-09-12012 September 2023
Review of Quality Assurance Topical Report
IR 05000321/20230052023-08-27027 August 2023
Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005
NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023
Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal
NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023
CFR 50.46 ECCS Evaluation Model Annual Report for 2022
IR 05000321/20230022023-08-0808 August 2023
Integrated Inspection Report 07200036/2023001, 05000321/2023002, and 05000366/2023002
NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023
Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis
ML23202A1122023-08-0202 August 2023
Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML23201A0292023-07-20020 July 2023
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023
ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use
NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023
Request for Exemption from Physical Barrier Requirement
ML23178A0012023-06-27027 June 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000321 2023403 and 05000366 2023403
NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023
Quality Assurance Topical Report Submittal
NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023
ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use
IR 05000321/20230102023-06-0909 June 2023
Focused Engineering Inspection Report 05000321 2023010 and 05000366 2023010
NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023
Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27
NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023
SNC Response to Regulatory Issue Summary 2023-01:Preparation And.
ML23136B2942023-05-19019 May 2023
Summary of May 02, 2023, Observation Public Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a LAR for the Reactor Pressure Vessel Head Closure Bolts for Edwin I. Hatch Nuclear Plant, Units 1 and 2
NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023
Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022
ML23123A2222023-05-0101 May 2023
Notification of Licensed Operator Initial Examination 05000321/2023301, and 05000366/2023301
IR 05000321/20230012023-04-26026 April 2023
Integrated Inspection Report 05000321/2023001 and 05000366/2023001
NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023
Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022
NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023
GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023
Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report
NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023
Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding
NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023
Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update
NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023
Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)
NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023
National Pollutant Discharge Elimination System (NPDES) Permit Renewal
ML23065A1092023-03-0808 March 2023
Correction of Relief Request HNP-ISI-RR-05-02 Allowing to Continue Operation with a Flaw Indication on One Reactor Pressure Vessel Closure Bolt Until December 31, 2025
ML23053A2182023-03-0303 March 2023
Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program
IR 05000321/20220062023-03-0101 March 2023
Annual Assessment Letter Edwin I. Hatch Nuclear Plant, Units 1 and 2 - NRC Inspection Report 05000321/2022006 and 05000366/2022006
NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023
Cycle 28 Core Operating Limits Report Version 1
ML23034A2462023-02-21021 February 2023
Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs
ML22363A3932023-02-15015 February 2023
Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program
ML22346A1482023-02-0909 February 2023
Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10
2024-01-31
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Inspection Report - Hatch - 2003009 |
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Text
rch 31, 2006
SUBJECT:
EDWIN I. HATCH NUCLEAR POWER PLANT - NRC INSPECTION REPORT NOS. 05000321/2003009 AND 05000366/2003009
Dear Mr. Sumner:
On February 14, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an in-office review related to an unresolved item identified during the Triennial Fire Protection Inspection of 2003. A meeting was held in the Region II office with regional staff and Mr. R. Baker and Mr. D. Parker on December 7, 2005, to discuss the status of SNC's proposed resolutions for protecting the affected cables of eleven safety-relief valves and to clarify the staffs position regarding the use of local operator actions in lieu of circuit protection as required by NRC regulations. Following completion of additional review in the Region II office, a final exit was held by telephone with Mr. D. Madison and other members of your staff on March 31, 2006.
The in-office review consisted of evaluating the safety significance of particular spurious valve operations and reviewing your compensatory measures and various proposed final resolutions.
The issue remains unresolved for reasons described in the enclosed report.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this letter, please contact us.
Sincerely,
\\RA\\
D. Charles Payne, Chief Engineering Branch 2 Division of Reactor Safety cc w/encl - See next page
SNC 2 Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5
Enclosure:
NRC Triennial Fire Protection Inspection Report Nos. 05000366/2003009, 05000321/2003009 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5 Report No.: 05000321/2003009 and 05000366/2003009 Licensee: Southern Nuclear Operating Company Facility: Edwin I. Hatch Nuclear Plant, Units 1 and 2 Location: P. O. Box 2010 Baxley, GA. 31513 Dates: February 14, 2006 Inspector: N. Staples, Reactor Inspector Approved by: D. Charles Payne, Chief Engineering Branch 2 Division of Reactor Safety Summary of Findings IR 05000366/2003-009, 05000321/2003-009; 02/14/2006; E. I. Hatch Nuclear Plant, Units 1 and 2.
Enclosure
The report covered an in-office review of an unresolved item related to fire protection by a Regional Inspector. The NRC*s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A. NRC-Identified and Self-Revealing Findings None B. Licensee-Identified Violations None Enclosure
REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Other (Discussed) URI 05000366/2003006-01: Concerns Associated with Potential Opening of SRVs Introduction: The Inspector reviewed an unresolved item (URI) involving the failure to protect circuits against fire which could lead to spurious opening of all eleven safety relief valves (SRV). The team had found instrumentation cables, that could cause maloperation of safe shutdown equipment, in FA 2104 without adequate spatial separation or fire barriers. The finding remains unresolved pending review of proposed corrective actions for the circuit design of the eleven SRVs.
Description: During the 2003 Triennial Fire Protection Inspection, the inspection team performed a circuit analysis of Group A safety relief valves for which the licensee took safe shutdown credit for fires in Fire Area 2104, Unit 2 East Cableway. The requirements of 10 CFR 50, Appendix R, Section III.G.2, apply to this fire area. The team identified that two reactor pressure instrument cables (for circuits ABE019C08 and ABE019C09) were located in the same cable tray and thereby exposed to the same heating rate which could potentially cause both circuits to simultaneously fail high and result in all eleven SRVs spuriously opening. Each cable consisted of a single twisted pair of insulated conductors, an uninsulated drain wire that was wound around the twisted pair of conductors, and a foil shield. The conductor insulation and jacket material of each cable was cross-linked polyethylene (XLPE). A thermal assault on instrument cables could result in (false high) signals, generated as a result of leakage current in each damaged cable. These undesired false high signals could actuate the SRV electrical backup scheme and cause all eleven SRVs to open. In addition, this failure mode would defeat the capability to manually control these SRVs. Normally, whenever a SRV lifted, it would remain open until nuclear boiler pressure was reduced to about 85% of its overpressure lift setpoint. However, if the instrument loops have failed high, the trip unit master relays and the trip unit slave relays would continue to energize the pilot valve of the individual SRV and maintain the SRV open. As a result, this failure mode could result in spurious actuation of all eleven SRVs with the eleven SRVs subsequently remaining open.
In response to this finding, the licensee initiated Condition Report 2003008203 and promptly revised AOP 34AB-X43-001-2, Fire Procedure, Version 10.8 dated May 28, 2003. The procedure change enabled the local operator actions to prevent all eleven SRVs from opening simultaneously to be accomplished earlier during a fire in the Unit 2 East Cableway, or in other fire areas that were vulnerable to the potential for spuriously opening all eleven safety relief valves. While, the revised procedure was an acceptable interim compensatory measure, it was not a permanent resolution to the circuit damage issue because Appendix R,Section III.G.2 does not allow use of local operator actions in lieu of circuit protection to ensure safe shutdown. On December 7, 2005, NRC staff met with the licensee to discuss proposed options for protecting cables from a fire in FA 2104 and to clarify the staffs position on regulation regarding the use of local operator actions in lieu of circuit protection. While various options were presented by the licensee, the licensee had not yet determined a final resolution. This URI will remain open pending the licensees final resolution.
4OA6 Meetings, Including Exit Exit meeting Summary On March 31, 2006, the regional staff presented the status results to Dennis Madison and other members of his staff, who acknowledged the findings. The inspectors asked the licensee whether any of the material examined during the inspection should be considered proprietary.
No proprietary information was identified.
Enclosure
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee Personnel:
R. Baker, Licensing Supervisor (Corporate)
I. Luker, Senior Engineer, Licensing D. Madison, General Manager for Plant Hatch D. Parker, Senior Engineer, Electrical K. Underwood, Performance Analysis Supervisor J. Vance, Senior Engineer, Mechanical & Civil O. Vidal, Principal Engineer, Licensing P. Wells, Plant Support General Manager LIST OF ITEMS DISCUSSED Discussed 05000366/2003006-01 URI Concerns Associated with Potential Opening of SRVs LIST OF DOCUMENTS REVIEWED Procedure:
AOP 34AB-X43-001-2, Fire Procedure, Version 10.8 Drawings H-11821, Fire Hazards Analysis, Turbine Bldg. El. 130=-0@, Rev. 0 H-26014, R.H.R. System P&ID Sheet 1, Rev. 49 H-26015, R.H.R. System P&ID Sheet 2, Rev. 46 H-26018, Core Spray System P&ID, Rev. 29 H-11821, Fire Hazards Analysis Drawing, Turbine Building, Rev. 11 Calculations, Analyses, and Evaluations E. I. Hatch Nuclear Plant Units 1 and 2 Safe Shutdown Analysis Report, Rev. 20.
Edwin I. Hatch Nuclear Plant Fire Hazards Analysis and Fire Protection Program, Rev. 20 Corrective Action Reviewed CR 2003008203, Safety relief valves Manual Action Steps in Fire Procedure Attachment
License Basis Documents Hatch UFSAR Section 6.3, Emergency Core Cooling System, Rev. 21 Safe Shutdown Analysis Report for E.I. Hatch Nuclear Plant Units 1 and 2, Rev. 26 Fire Hazards Analysis for E. I. Hatch Nuclear Plant Units 1 and 2, Rev.18 C, dated 7/00 Attachment
_________________________
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS SIGNATURE NLS2 PJF CWR1 DCP NAME NStaples PFillion CRapp DPayne DATE 3/17/2006 3/20/2006 3/21/2006 3/31/2006 4/ /2006 4/ /2006 4/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
