|
---|
Category:Letter type:ONS
MONTHYEARONS-2018-025, 2017 Annual Radiological Environmental Operating Report (AREOR)2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report (AREOR) ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)2018-04-30030 April 2018 2017 Annual Radioactive Effluent Release Report (ARERR) ONS-2018-032, Ufsar/Selected Licensee Commitment Changes2018-04-17017 April 2018 Ufsar/Selected Licensee Commitment Changes ONS-2018-029, Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 32018-04-0404 April 2018 Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3 ONS-2018-027, Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-0022018-03-28028 March 2018 Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-002 ONS-2018-023, Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency2018-03-20020 March 2018 Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency ONS-2018-017, Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan2018-03-15015 March 2018 Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan ONS-2018-021, ISFSI - Submittal of 2017 Annual Effluent Release Report2018-03-0101 March 2018 ISFSI - Submittal of 2017 Annual Effluent Release Report ONS-2018-020, Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2018-02-26026 February 2018 Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes ONS-2018-015, Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cabl2018-02-19019 February 2018 Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cables i ONS-2018-014, License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-012018-02-12012 February 2018 License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-01 ONS-2018-019, Submittal of Emergency Plan, Section B2018-02-0505 February 2018 Submittal of Emergency Plan, Section B ONS-2018-011, Ufsar/Selected Licensee Commitment Changes2018-01-25025 January 2018 Ufsar/Selected Licensee Commitment Changes ONS-2017-087, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2017-12-0404 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ONS-2017-083, Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 02017-11-21021 November 2017 Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 0 ONS-2017-041, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments2017-11-15015 November 2017 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments ONS-2017-085, Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR)2017-11-15015 November 2017 Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR) ONS-2017-079, Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-11-13013 November 2017 Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-078, Emergency Plan Revision 2017-0042017-11-0909 November 2017 Emergency Plan Revision 2017-004 ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 ONS-2017-067, Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 22017-10-16016 October 2017 Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 2 ONS-2017-069, (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement2017-10-13013 October 2017 (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement ONS-2017-070, Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0022017-10-0505 October 2017 Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-002 ONS-2017-072, Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-10-0303 October 2017 Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-066, Registration for Use of General License Spent Fuel Cask Numbers 147 and 1482017-09-20020 September 2017 Registration for Use of General License Spent Fuel Cask Numbers 147 and 148 ONS-2017-061, Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations2017-08-10010 August 2017 Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations ONS-2017-060, Registration for Use of General License Spent Fuel Cask Numbers 145 and 1462017-08-0303 August 2017 Registration for Use of General License Spent Fuel Cask Numbers 145 and 146 ONS-2017-059, Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary2017-07-31031 July 2017 Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 ONS-2017-047, Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 1442017-06-27027 June 2017 Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 144 ONS-2017-042, Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 22017-06-0101 June 2017 Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 2 ONS-2017-040, Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0032017-05-22022 May 2017 Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-003 ONS-2017-037, 2016 Annual Radiological Environmental Operating Report2017-05-15015 May 2017 2016 Annual Radiological Environmental Operating Report ONS-2017-026, Submittal of Ufsar/Selected Licensee Commitment Change2017-04-11011 April 2017 Submittal of Ufsar/Selected Licensee Commitment Change ONS-2017-024, Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program2017-03-16016 March 2017 Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program ONS-2017-001, Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 0452017-03-0202 March 2017 Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 045 ONS-2017-017, Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-001 ONS-2017-018, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-001 ONS-2017-015, End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2017-02-24024 February 2017 End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 ONS-2017-011, Emergency Plan Revised Evaluation2017-02-0202 February 2017 Emergency Plan Revised Evaluation ONS-2017-009, Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events.2017-02-0101 February 2017 Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events. ONS-2017-004, Submittal of Core Operating Limits Report2017-01-12012 January 2017 Submittal of Core Operating Limits Report ONS-2017-006, Emergency Plan Revision 2016-0032017-01-12012 January 2017 Emergency Plan Revision 2016-003 ONS-2016-097, Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S)2016-11-17017 November 2016 Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S) ONS-2016-098, Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors2016-11-14014 November 2016 Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors ONS-2016-096, Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations2016-11-10010 November 2016 Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations 2018-05-15
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARRA-18-129, Technical Specification 5.6.6 Special Report, Inoperability of Post Accident Monitoring Instrument; Containment Sump Wide Range Water Level (CR 02218964)2018-08-23023 August 2018 Technical Specification 5.6.6 Special Report, Inoperability of Post Accident Monitoring Instrument; Containment Sump Wide Range Water Level (CR 02218964) ONS-2016-098, Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors2016-11-14014 November 2016 Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors ONS-2015-085, Special Report in Accordance with Selected Licensee Commitment (SLC) 16.7.4, Hydrogen Analyzers2015-07-10010 July 2015 Special Report in Accordance with Selected Licensee Commitment (SLC) 16.7.4, Hydrogen Analyzers ONS-2014-159, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to Protected Service Water System - Revision 32015-02-0909 February 2015 Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to Protected Service Water System - Revision 3 RA-14-0032, CFR 50.46 - 30-Day Report for Estimated Impacts to Peak Cladding Temperature Due to Fuel Pellet Thermal Conductivity Degradation2014-12-17017 December 2014 CFR 50.46 - 30-Day Report for Estimated Impacts to Peak Cladding Temperature Due to Fuel Pellet Thermal Conductivity Degradation ML12073A3542012-03-0909 March 2012 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model ML11347A1932011-12-0808 December 2011 Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model ML1007005562010-03-0303 March 2010 LER, Oconee, Units 1, 2, & 3, Submittal of 30-Day Report Pursuant to Ground Water Protection Initiative and Ground Water Monitoring Wells GM-7R and GM-7DR ML0823208842008-08-13013 August 2008 Site, Independent Spent Fuel Storage Instillation (ISFSI) General License Cask Certificate of Compliance, 30-Day Report Due to Higher Canister Heat Loading ML0517304632005-06-13013 June 2005 Steam Generator Inservice Inspection lEOC22, Steam Generator Tube Plugging and Repair 30-day Report ML0509703152005-03-31031 March 2005 Special Report Per Technical Specification 5.6.6 Problem Investigation Process No.: 0-05-1567, 0-05-1401 2018-08-23
[Table view] |
Text
e1_.,ouKE Thomas D. Ray Vice President
~ ENERGY Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.5016
- f. 864.873. 4208 Tom.Ray@duke-energy.com ONS-2016-098 November 14, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station (ONS), Units 1, 2 and 3 Docket Nos. 50-269, 50-270, and 50-287 Renewed License Nos. DPR-38, DPR-47, and DPR-55 Special Report per Technical Specification 5.6.6 Action Request No.: 02069527
Subject:
Special Report per Technical Specification 5.6.6, lnoperability of Unit 1, 2 and 3 Post Accident Monitoring Containment High Range Radiation Monitors Pursuant to ONS Technical Specification 3.3.8, Condition I and Technical Specification 5.6.6, enclosed is a special report regarding the inoperability of the Containment High Range Radiation Monitors (CHRRMs) for all 3 Units.
This Special Report is being submitted due to CHRRMs RIA-57 and RIA-58, for each Unit, being inoperable for greater than 7 days. The information required by this Special Report is enclosed.
There are no regulatory commitments contained in this report.
If you have any questions regarding this submittal, please contact Sam Adams, Oconee Regulatory Affairs, at 864-873-3348.
~~
Thomas D. Ray
Enclosure:
Oconee Nuclear Station, Units, 1, 2, and 3 Special Report per Technical Specification 5.6.6
ONS-2016-098 November 14, 2016 Page 2 cc:
Ms. Catherine Haney Administrator Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall Senior Project Manager (by electronic mail only)
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2746 Mr. Eddy Crowe NRG Senior Resident Inspector Oconee Nuclear Station
Enclosure:
Oconee Nuclear Station, Units 1, 2, and 3 Special Report per Technical Specification 5.6.6 lnoperabilitv of Post-Accident Monitoring Instrument Containment High Range Radiation Monitors Description of Condition On October 25, 2016, Containment High Range Radiation Monitors (CHRRMs) RIA-57 and RIA-58 were declared inoperable on all three ONS Units due to the potential for Thermally Induced Currents (TIC) to affect the accuracy of the radiation monitor readings during a High Energy Line Break (HELB) event in the associated Unit's East or West Penetration Room. The TIC effect could give a short-lived (less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) false high radiation reading, potentially resulting in improper actions, including a misclassification of the actual event, if other monitored plant parameters are not considered. A HELB event in either the East or West Penetration Rooms could affect both RIAs. During a subsequent investigation and walkdown, it was identified that some of the connectors for the CHRRMs were not sealed with environmentally qualified shrink tubing, thereby making them susceptible to moisture intrusion and potential failure during a HELB event in the East or West Penetration Room.
The aforementioned TIC and moisture intrusion issues are only a concern for a HELB in either Penetration Room. It is worth noting that it is beyond the ONS design and licensing basis to have a HELB outside of Containment that would result in an actual high containment radiation condition. Thus, although inoperable, RIA-57 and RIA-58 are considered available to fully perform their intended function under all conditions with the exception of a HELB in the East or West Penetration rooms and, as such, provide reliable assessment capability for design basis events involving the failure of the RCS and/or fuel barriers and their potential to contribute to a release of radioactivity to the outside atmosphere.
The CHRRMs are post-accident monitoring (PAM) instrumentation specifically designed to detect radiation levels in the containment building of their associated unit to allow for assessment of conditions related to fission product barrier status (RCS and fuel barriers) and to assess the potential for a radioactive release to the public when one or more of these barriers are failed, along with a release path from the containment building to the outside atmosphere.
The primary purpose of PAM instrumentation is to provide control room indication of selected unit parameters during accident conditions. Operability of the PAM instrumentation ensures that there is sufficient information available to monitor and assess unit status during and following an accident. The PAM 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. The CHRRMs are identified as Type C and Type E Category 1 variables. Other than an alarm in the Control Room, there are no automatic functions provided by the CHRRMs.
The CHRRMs are addressed by Technical Specifications (TS) Table 3.3.8-1, Function 9. TS Limiting Condition for Operation (LCO) 3.3.8 requires that the Post-Accident Monitoring (PAM) instrumentation for each function in Table 3.3.8-1 be operable. Condition C of TS 3.3.8 states that with two inoperable Containment Area Radiation (High Range) monitoring channels, one must be restored to operable status within 7 days. If this indication is not restored within 7 days, Condition G and Table 3.3.8-1 lead to Condition I which requires initiating action in accordance with TS 5.6.6. TS 5.6.6 requires the submittal of a Special Report within the following 14 days and states that the report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channel to operable status.
Enclosure Page 1 of2
Enclosure:
Oconee Nuclear Station, Units 1, 2, and 3 Special Report per Technical Specification 5.6.6 Cause of lnoperability The CHRRMs on all three units (1 ,2,3RIA-57 and 1,2,3RIA-58) are considered inoperable since a HELB in either penetration room could cause the CHRRMs to experience spurious indication spikes due to TIC and could cause moisture intrusion and/or failure of the CHRRMs connectors due to not having environmentally qualified heat shrink tubing on connectors. The indication spikes would likely result in exceeding the RG 1.97 accuracy requirements for these post-accident monitors. Since incorrect CHRRMs indication information could be provided to the operators, this deficiency does not allow for the CHRRMs to accurately monitor the effluent discharge paths to ascertain if there have been significant releases (planned or unplanned) of radioactive materials and to continually assess such releases, as required by UFSAR Section 7.5.1.3.2 for RG 1.97 Type E Instrumentation.
Preplanned Alternate Method of Monitoring The CHRRMs are functioning at this time and are providing valid data. Although functional, these radiation monitors have been declared inoperable until changes are implemented that resolve the potential impacts of TIC on the credited functions of the CHRRMs. On October 13, 2016 the concern with TIC effects was communicated with licensed operators, along with the distribution of an Operations Guide to each ONS Control Room, directing that an evaluation of the conditions in the East and West Penetration Rooms should be made prior to making E-plan declarations based on the indications provided by 1,2,3RIA-57 and/or 1,2,3RIA-58 during a HELB event affecting the penetration rooms. Additionally, the OPS Guide directs that operators must validate conditions using alternate indications. The CHRRMs are used as one of several diverse methods for evaluating emergency action levels (EALs) for the Loss of RCS Barrier, Loss of Fuel Clad Barrier and for the Potential Loss of Primary Containment Barrier in the Emergency Plan. The specific alternate indications that can be used to assess conditions related to a potential offsite release following an accident are:
Containment Normal and Emergency Sump levels (PAM) - redundant method for loss of coolant accidents; Containment water level (above sump levels) (PAM) - redundant method for loss of coolant accidents; Containment pressure (PAM) - redundant method for loss of coolant accidents; Reactor Coolant System Sub-Cooling Margin (PAM) - redundant method for loss of coolant accidents; Reactor Vessel Head Level and RCS Hot Leg Level (PAM) - redundant method for loss of coolant accidents; RCS Pressure (Wide Range) (PAM) - redundant method for loss of coolant accidents; Pressurizer Level (PAM) - redundant method for loss of coolant accidents; RCS Core Exit Thermocouples (PAM) - redundant method for loss of coolant accidents and fuel barrier losses.
Plans and Schedule for Restoring Operability Replacement of the non-EQ heat shrink tubing is already in progress. Preliminary reviews indicate that replacing the coaxial cable for the CHRRMs will not completely resolve the TIC concern. Further research into fleet and industry operating experience will be conducted to consider other viable options, including potential licensing changes. Based on the findings of the additional research, an implementation schedule will be developed and the operability of the CHRRMs will be restored within the next two refueling outages for each unit.
Enclosure Page 2 of2