|
|
Line 31: |
Line 31: |
| * 10% rated core flow: SLs 2.0 MCPR shall be <! 1. 09 for two recirculation loop operation or<! 1.12 for single recirculation loop operation. 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. HATCH UNIT 2 2.0-1 Amendment No. 218 | | * 10% rated core flow: SLs 2.0 MCPR shall be <! 1. 09 for two recirculation loop operation or<! 1.12 for single recirculation loop operation. 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. HATCH UNIT 2 2.0-1 Amendment No. 218 |
|
| |
|
| ML 16312A244 Sincerely, IRA/ Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME MOrenak LRonewicz MMarkley MOrenak DATE 11/21/16 11/14/16 11/21/16 11/22/16 | | ML 16312A244 Sincerely, IRA/ Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME MOrenak LRonewicz MMarkley MOrenak DATE 11/21/16 11/14/16 11/21/16 11/22/16}} |
| }} | |
Revision as of 03:37, 19 May 2018
Similar Documents at Hatch |
---|
Category:Letter
MONTHYEARIR 05000321/20240102024-11-0606 November 2024 NRC Inspection Report 05000321/2024010 and 05000366/2024010 ML24299A2222024-10-31031 October 2024 Audit Summary for License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components IR 05000321/20240032024-10-30030 October 2024 Edwin I Hatch, Units 1 and 2 - Integrated Inspection Report 05000321/2024003 and 05000366/2024003 NL-24-0357, Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines2024-10-30030 October 2024 Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines ML24292A1602024-10-22022 October 2024 Request for Withholding Information from Public Disclosure License Amendment Request to Revise Technical Specification Surveillance Requirements to Increase Safety/Relief Valve Setpoints ML24290A0792024-10-18018 October 2024 SLR Environmental Preapplication Meeting Summary ML24303A4102024-10-17017 October 2024 Dir Results Letter to NRC - Hatch - Hurricane Helene IR 05000321/20244012024-10-10010 October 2024 Security Baseline Inspection Report 05000321-2024401 and 05000366-2024401 ML24256A0282024-09-12012 September 2024 2024 Hatch Requal Inspection Corporate Notification Letter NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc IR 05000321/20240912024-08-27027 August 2024 NRC Investigation Report 2-2023-003 and NOV - NRC Inspection Report 05000321/2024091 and 05000366/2024091 IR 05000321/20240052024-08-26026 August 2024 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Report 05000321/2024005 and 05000366/2024005 NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information IR 05000321/20240022024-08-0808 August 2024 Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24198A1252024-07-16016 July 2024 Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 05000321/LER-2024-003, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024 Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link 05000321/LER-2024-002-01, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024 Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 ML24163A0532024-06-14014 June 2024 Audit Plan - Alternative Seismic Method LAR NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations IR 05000321/20240902024-05-15015 May 2024 NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024 Manual Reactor Trip Due to Loss of Feedwater NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000032/20240112024-04-25025 April 2024 Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011 05000366/LER-2024-002, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024 Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications IR 05000321/20240012024-04-22022 April 2024 Integrated Inspection Report 05000321/2024001 and 05000366/2024001 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint 05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-0909 April 2024 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML23275A2402024-03-22022 March 2024 SNC Fleet - Issuance of Environmental Assessment and Finding of No Significant Impact Regarding Exemption from the Requirements of 10 CFR Part 73, Section 73.2, Definitions (EPID Nos. L-2023-LLE-0018 & L-2023-LLE-0021) - Letter NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML24047A0362024-03-0404 March 2024 Response to Hatch and Vogtle FOF Dates Change Request (2025) NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 IR 05000321/20230062024-02-28028 February 2024 Annual Assessment Letter Edwin I. Hatch Nuclear Plant Units 1 and 2 - Nrc Inspection Report 05000321/2023006 and 05000366/2023006 2024-09-09
[Table view] |
Text
Mr. Charles R. Pierce Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 22, 2016 Southern Nu.clear Operating Company, Inc. P.O. Box 1295 /Bin 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 -CORRECTION FOR AMENDMENTS REGARDING REACTOR CORE SAFETY LIMITS (CAC NO. MF4588)
Dear Mr. Pierce:
On October 20, 2014, the U.S. Nuclear Regulatory Commission (NRC) issued License Amendment No. 213 to Renewed Facility Operating License (RFOL) No. NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit No. 2 (HNP-2), changing the reactor steam dome pressure safety limit (SL) in TS Section 2.1.1, "Reactor Core SLs" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14276A634). On February 18, 2015, the NRC issued License Amendment No. 218 to RFOL No. NPF-5 for HNP-2, changing the minimum critical power ratio (MCPR) SL in TS Section 2.1.1 (ADAMS Accession No. ML 15020A434). The SLs in TS Section 2.1.1, TS page 2.0-1, include limits on both reactor steam dome pressure and MCPR. On February 24, 2015 (ADAMS Accession No. ML 15054A400), a correction letter was issued to correct TS page 2.0-1 to reflect the earlier change that the NRC approved for the steam dome pressure SL. Unfortunately, this corrected page contained a numbering error that listed the TS section on "SLs" as TS 2.2, instead of the correct TS 2.1, and the TS section on "SL Violations" as TS 2.3, instead of the correct TS 2.2. This letter corrects these two numbering errors.
C. Pierce Enclosed is corrected TS page 2.0-1, which includes the correct numbering for TSs 2.2 and 2.3. These TS changes are administrative errors. Accordingly, the NRC safety evaluations and Federal Register notices for each license amendment are independent of those developed for the other amendment. There is no change to the regulatory basis for the issuance of both License Amendment Nos. 213 and 218 for HNP-2. Docket No. 50-366
Enclosure:
Corrected TS page 2.0-1 to License Amendment No. 218 to NPF-5 cc w/enclosure: Distribution via Listserv Sincerely, Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENCLOSURE Corrected TS page 2.0-1 to License Amendment No. 218 to NPF-5 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 685 psig or core flow < 10% rated core flow: THERMAL POWER shall bes 24% RTP. 2.1.1.2 With the reactor steam dome pressure <! 685 psig and core flow <!
- 10% rated core flow: SLs 2.0 MCPR shall be <! 1. 09 for two recirculation loop operation or<! 1.12 for single recirculation loop operation. 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. HATCH UNIT 2 2.0-1 Amendment No. 218
ML 16312A244 Sincerely, IRA/ Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME MOrenak LRonewicz MMarkley MOrenak DATE 11/21/16 11/14/16 11/21/16 11/22/16