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| ==Subject:== | | ==Subject:== |
| Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2 Docket No. 50-270 Special Report per Technical Specification | | Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2 Docket No. 50-270 Special Report per Technical Specification 5.6.6 Problem Investigation Process Nos.: 0-11-13855, 0-11-14092 Pursuant to Oconee Nuclear Station (ONS) Technical Specification 3.3.8, Condition B and Technical Specification 5.6.6, enclosed is a special report regarding the inoperability of the ONS, Unit 2, Post Accident Monitoring System Containment Water Wide Range Level Transmitter 2PAMLT0090. |
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| ====5.6.6 Problem====
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| Investigation Process Nos.: 0-11-13855, 0-11-14092 Pursuant to Oconee Nuclear Station (ONS) Technical Specification 3.3.8, Condition B and Technical Specification 5.6.6, enclosed is a special report regarding the inoperability of the ONS, Unit 2, Post Accident Monitoring System Containment Water Wide Range Level Transmitter 2PAMLT0090. | |
| This transmitter performs a post-accident monitoring function per the Duke Energy Carolinas, LLC response to Regulatory Guide 1.97.The apparent cause of the failure was the failure of a switch internal to the transmitter. | | This transmitter performs a post-accident monitoring function per the Duke Energy Carolinas, LLC response to Regulatory Guide 1.97.The apparent cause of the failure was the failure of a switch internal to the transmitter. |
| This transmitter is located in containment and is inaccessible during normal operations. | | This transmitter is located in containment and is inaccessible during normal operations. |
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Category:Letter
MONTHYEARML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure IR 05000269/20243012024-09-23023 September 2024 NRC Operator License Examination Report 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) ML24220A1092024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 2024-09-23
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation RA-24-0072, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee RA-24-0071, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications 05000287/LER-2017-0012017-09-20020 September 2017 Unit 3 Reactor Protection System Actuation - Reactor Trip due to Turbine Trip from Generator Lockout, LER 17-001-00 for Oconee Nuclear Station, Unit 3, Regarding Reactor Protection System Actuation - Reactor Trip due to Turbine Trip from Generator Lockout 05000287/LER-2016-0012016-08-26026 August 2016 1 of 3, LER 16-001-00 for Oconee, Unit 3, Regarding Reactor Building Cooling Unit Inoperability Exceeds Technical Specification Completion Time 05000269/LER-2016-0012016-05-0505 May 2016 1 of 3, LER 16-001-00 for Oconee Nuclear Station, Unit 1, Regarding RPS Actuation - Unit 1 Reactor Trip Initiated by a Generator Lockout/Turbine Trip ML11364A0462011-12-23023 December 2011 Special Report Per Technical Specification 5.6.6, Problem Investigation Process Nos.: 0-11-13855, 0-11-14092 ML12006A1922011-12-19019 December 2011 LER 11-03-001 for Oconee, Units 1, 2, and 3 Regarding Inoperability of the Standby Shutdown Facility Diesel Generator ML0932902002009-11-18018 November 2009 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance USA/9319/B(U)F-96, Revision, for the Model No. MAP-12/MAP-13 Package ML0534104592005-12-0101 December 2005 Special Report Per Selected Licensee Commitment 16.9.9, Problem Investigation Process No.: O-05-7215 for Oconee Regarding the Inoperability of the Station Auxiliary Service Water (Asw) System and the Stand-by Shutdown Facility (Ssf) Asw Sys ML0426503832004-09-0909 September 2004 LER 04-02-001 for Oconee Nuclear Station Re Main Steam Line Break Mitigation Design/Analysis Deficiency ML0313204452003-04-24024 April 2003 LER 03-S01-00 for Oconee, Units 1, 2 & 3 Re Security Access Revoked for Falsification of Criminal Record ML0232303392002-11-12012 November 2002 LER 02-S02-00 for Oconee Nuclear Station Regarding Uncontrolled Safeguards Information ML0215802872002-05-28028 May 2002 LER 2002-02-00 Re Potential for Fire to Indirectly Damage Mitigation Component for Oconee Nuclear Station Unit 1 ML0211201432002-04-0909 April 2002 LER 02-01-00 for Oconee Nuclear Station Unit 1 Re Security Access Revoked for Falsification of Criminal Record 2024-08-02
[Table view] |
Text
Duke T. PRESTON GILLESPIE, JR.Vice President hEnergy Oconee Nuclear Station Duke Energy ON0I VP / 7800 Rochester Hwy.Seneca, SC 29672 864-873-4478 864-873-4208 fax T. Gillespie@duke-energy.
com December 23, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2 Docket No. 50-270 Special Report per Technical Specification 5.6.6 Problem Investigation Process Nos.: 0-11-13855, 0-11-14092 Pursuant to Oconee Nuclear Station (ONS) Technical Specification 3.3.8, Condition B and Technical Specification 5.6.6, enclosed is a special report regarding the inoperability of the ONS, Unit 2, Post Accident Monitoring System Containment Water Wide Range Level Transmitter 2PAMLT0090.
This transmitter performs a post-accident monitoring function per the Duke Energy Carolinas, LLC response to Regulatory Guide 1.97.The apparent cause of the failure was the failure of a switch internal to the transmitter.
This transmitter is located in containment and is inaccessible during normal operations.
Repairs will be made during the next reasonable opportunity, and no later than the next ONS, Unit 2 refueling outage.This event is considered to be of no significance with respect to the health and safety of the public.There are no regulatory commitments contained in this report. Any questions regarding the content of this report should be directed to Corey Gray, Oconee Regulatory Compliance at 864-873-6325.
Sincerely, T. Preston Gillespie, Jr.Vice President Oconee Nuclear Site Enclosure E MPJL www. duke-energy.
com Document Control Desk December 23, 2011 Page 2 cc: Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Stang Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Mr. Andrew Sabisch NRC Senior Resident Inspector Oconee Nuclear Station INPO (Word File via E-mail)
ENCLOSURE OCONEE NUCLEAR STATION, UNIT 2 SPECIAL REPORT 2011-01 Description of Condition:
On November 14, 2011, during startup from the 2EOC25 Refueling Outage, the Post Accident Monitoring (PAM) System Containment Water Wide Range Level Transmitter 2PAMLT0090 could not be calibrated and was determined to be inoperable.
Troubleshooting determined that an internal switch was open and was not functioning.
Following discovery of the transmitter inoperability, the available replacement level transmitter was determined to not be qualified to perform its function for the specified mission time.Subsequent evaluation determined that the replacement transmitter could be installed but would be operable but degraded/nonconforming (OBDN). However, the plant was in a configuration (Mode 2) that would not permit replacement by the time the determination was made. The opposite channel wide range level transmitter was declared OBDN since it is the same type of transmitter.
Both narrow range level transmitter channels are operable.Background The primary purpose of PAM instrumentation is to display unit variables that provide information required by the control room operators during accident situations.
This information provides the necessary support for the operator to take the manual actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for Design Basis Events.The OPERABILITY of the PAM instrumentation ensures that there is sufficient information available on selected unit parameters to monitor and to assess unit status and behavior following an accident.The availability of PAM instrumentation is important so that responses to corrective actions can be observed, and so that the need for and magnitude of further actions can be determined.
These essential instruments are identified by the ONS specific Regulatory Guide 1.97 analysis, Updated Final Safety Analysis Report (UFSAR), Section 7.5, and the NRC's Safety Evaluation Report for the ONS Regulatory Guide 1.97 analysis which address the recommendations of Regulatory Guide 1.97, as required by Supplement 1 to NUREG-0737.
PAM variables are the key variables deemed risk significant because they are needed to:* Determine whether systems important to safety are performing their intended functions;" Provide information to the operators that will enable them to determine the potential for causing a gross breach of the barriers to radioactivity release; and" Provide information regarding the release of radioactive materials to allow for early indication of the need to initiate action necessary to protect the public and to estimate the magnitude of any impending threat.1 Containment Water Level Wide Range instrumentation is a Type B, Category 1 variable provided for verification and long term surveillance of Reactor Coolant System (RCS)integrity.
The Containment Water Level Wide Range instrumentation consists of two channels (2PAMLT0090 and 2PAMLT0091) with readout on two indicators and one recorder.
The indicated range is 0 to 15 feet. Additionally, the sump has two narrow range transmitters with an indication range of 0 to 3 feet.Cause of Inoperability The cause of the inoperable transmitter was equipment failure. The cause of the failure to return the transmitter to service within 30 days is inability to safely access the transmitter location while the plant is in operation.
Preplanned Alternate Method of Monitoring The opposite train PAM System Containment Water Wide Level Transmitter 2PAMLT0091 was determined to be operable but degraded/nonconforming and both trains of the Containment Sump Water Narrow Level Transmitter were determined to be operable.Plans and Schedule for Restoring Operability The failed 2PAMLT0090 will be replaced during the next reasonable opportunity, and no later than the next scheduled Unit 2 refueling outage.2