Letter Sequence RAI |
---|
|
|
MONTHYEARNL-14-1250, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.02014-09-19019 September 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 Project stage: Request NL-14-1821, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information2014-11-13013 November 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information Project stage: Request NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package Project stage: Request ML15005A2702015-01-13013 January 2015 Request for Additional Information Project stage: RAI ML15035A6802015-02-0505 February 2015 Request for Additional Information Project stage: RAI NL-15-0331, Response to Request for Additional Information from Mechanical and Civil Branch Regarding High Density Polyethylene (Hdpe) Piping Replacement2015-02-19019 February 2015 Response to Request for Additional Information from Mechanical and Civil Branch Regarding High Density Polyethylene (Hdpe) Piping Replacement Project stage: Response to RAI ML15191A4872015-07-13013 July 2015 Unit 2: Plant Service Water Piping Replacement Using High Density Polyethylene (Hdpe) Piping Nrc/Snc Meeting July 13, 2015 Project stage: Meeting ML15195A4812015-08-31031 August 2015 July 13, 2015, Summary of Meeting with SNC on High Density Polyethylene Piping for HNP-2 Project stage: Meeting 2015-01-13
[Table View] |
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-24-0290, 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-24-0276, 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-24-0261, 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-2024-002-01, 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 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 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 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 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 ML23032A3322024-04-24024 April 2024 Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes 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 NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission 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) 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 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24278A0052024-10-0303 October 2024 Document Request for Hatch Nuclear Plant - IP 92702 Follow-Up Radiation Protection Inspection - Inspection Report 2024-04 ML24211A0162024-07-26026 July 2024 NRR E-mail Capture - Request for Additional Information - Hatch, Units 1 and 2, Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase SRV Setpoints LAR ML24208A1742024-07-26026 July 2024 Request for Additional Information Regarding License Amendment Request to Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase S/Rv Setpoints ML24193A1182024-07-10010 July 2024 Email to SNC with RAI for Hatch Exemption Request ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23354A2032023-12-18018 December 2023 Document Request for Hatch Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-01 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 ML23264A0142023-09-14014 September 2023 NRR E-mail Capture - (External_Sender) Draft Round-2 RAI - Hatch, Units 1 and 2, Revise TS 1.1-1 Modes LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23018A1872023-01-17017 January 2023 2023 HNP CGD Inspection Information Request ML22355A2082022-12-21021 December 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, Reactor Pressure Vessel RPV Head Studs LAR ML23026A2372022-11-16016 November 2022 2023001 Hatch RP RFI Final ML22208A1332022-07-26026 July 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-208 LAR ML22157A3542022-06-0606 June 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-505 LAR ML22140A1192022-05-20020 May 2022 NRR E-mail Capture - RAIs - Hatch, Units 1 and 2, TSTF-505 LAR ML22073A0842022-03-21021 March 2022 An NRC Fire Protection Team Inspection (NRC Inspection Report Nos. 05000321/2022011 and 05000366/2022011) and Request for Information ML22025A2142022-01-21021 January 2022 Plant Hatch 2022001 RP Baseline Inspection Information Request ML21265A3402021-09-22022 September 2021 NRR E-mail Capture - Request for Additional Information - Hatch, Unit 1, Emergency TS 3.7.2 LAR ML21111A3032021-04-21021 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21110A6842021-04-20020 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21013A4112021-01-13013 January 2021 Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010 ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20253A2732020-09-0909 September 2020 Requalification Program Inspection Hatch Nuclear Station ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests NL-19-1532, Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors2019-12-18018 December 2019 Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors ML19336A0142019-12-0101 December 2019 NRR E-mail Capture - RAI: Hatch Emergency TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LAR ML19280A0082019-10-0404 October 2019 NRR E-mail Capture - Request for Additional Information (RAI) - Hatch TSTF-51 LAR (L-2019-LLA-0091) ML19224C0552019-08-12012 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Degraded Voltage (L-2019-LLA-0108) ML19220A0362019-08-0808 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Adoption of NFPA 805, Request for Additional Information, EPID L-2018-LLA-0107 ML19164A2582019-06-13013 June 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19107A4962019-04-17017 April 2019 NRR E-mail Capture - Request for Additional Information - Hatch 1 & 2 Application to Adopt Title 10 of Code of Federal Regulations 50.69 RISK-INFORMED Categorization and Treatment of Structures, Systems and Components for Power Reactors ML19088A0092019-03-29029 March 2019 NRR E-mail Capture - Hatch 1 and 2 - LAR to Adopt NFPA 805 Fire Protection Standard, EPID L-2018-LLA-0107, Request for Additional Information ML19029B3402019-01-23023 January 2019 Southern Nuclear Operating Company, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 Draft Request for Additional Information for the License Amendment Requests to Adopt the Risk-Informed Provisions of Title 10 of the Code of Federal Regulat ML19016A3422019-01-10010 January 2019 U2 ISI 2019001 RFI - Bcc ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18085A0132018-03-0808 March 2018 Draft Request for Additional Information on Alternative RR-V-11, Proposed Extension to Main Steam Safety Relief Valve Testing Requirements ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17284A3542017-11-0707 November 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools ML17270A1402017-09-27027 September 2017 PIR Notification Letter 2017 ML17290A3172017-09-19019 September 2017 NRR E-mail Capture - Hatch 1 and 2 - Draft Request for Additional Information Request for Alternative No. HNP-ISI-ALT-05-05 ML17111A5792017-04-26026 April 2017 Request for Additional Information, Fourth 10-Year ISI Interval Relief Requests ML17110A2112017-04-24024 April 2017 Request for Additional Information ML16330A1282016-12-0505 December 2016 Request for Additional Information ML16307A1842016-11-0202 November 2016 Request for Additional Information (Non-Proprietary) ML16271A1692016-10-17017 October 2016 Request for Additional Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16205A0012016-07-22022 July 2016 Requalification Program Inspection - Plant Hatch 2024-07-26
[Table view] |
Text
!_
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2015 Mr. C. R'. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P. 0. Box 1295/Bin- 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT 2- REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MF4860)
Dear Mr. Pierce:
By letter dated September 19, 2014, the Southern Nuclear Operating Company, Inc. (SNC),
submitted request for relief HNP-ISI-ALT-HDPE-01, which requests authorization to replace buried steel Plant Service Water piping with High Density Polyethylene piping for the duration of the license at Hatch Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission staff has determined that additional information in the mechanical engineering area is needed as discussed in the Enclosure. We request that SNC respond by February 20, 2015.
~~~~
~obert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-366 cc: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION PROPOSED INSERVICE INSPECTION ALTERNATIVE HNP-ISI-ALT-HDPE-01, REV. 2 HATCH NUCLEAR PLANT, UNIT 2 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NO. 50-366 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Southern Nuclear Operating Company, Inc. (SNC), relief request HNP-ISI-ALT-HDPE-01, dated September 19, 2014, as supplemented on November 14, and November 24, 2014 (References 1, 2 and 3 below)
(Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML14266A183, ML14317A261 and ML15028A518), which requests authorization to replace buried steel Plant Service Water (PSW) piping with High Density Polyethylene (HOPE) piping for the duration of the license at Hatch Nuclear Plant, Unit 2. The NRC staff has reviewed the request and determined that additional information is necessary in the mechanical engineering area to continue the review.
References:
- 1. Letter No. NL-14-1250, From C. R. Pierce, Regulatory Affairs Director, Southern Nuclear Operating Company (SNC), to U. S. Nuclear Regulatory Commission, Document Control Desk, "Edwin I. Hatch Nuclear Plant Unit 2 Proposed lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01 Version 2.0," September 19, 2014.
(ML14266A183)
- 2. Letter No. NL-14-1821, From C. R. Pierce, Regulatory Affairs Director, Southern Nuclear Operating Company (SNC), to U. S. Nuclear Regulatory Commission, Document Control Desk, "Edwin I. Hatch Nuclear Plant Unit 2 Proposed lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01 Version 2.0 Supplementary Information," November 14, 2014.
(ML14317A261t
- 3. Letter No. NL-14-1876, From C. R. Pierce, Regulatory Affairs Director, Southern Nuclear Operating Company (SNC), to U. S. Nuclear Regulatory Commission, Document Control Desk, "Edwin I. Hatch Nuclear Plant Unit 2 Proposed lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01 Version 2.0 Conceptual Design Information Package,"
November 24, 2014. (ML15028A518)
-1. Section 1.0, Calculation SMNH-14-013, Enclosure 3 (Calculation of Minimum Wall Thickness for PSW HOPE Piping) to NL-14-1876 (Conceptual Design information Package, Reference 3):
It was noted that minimum wall thickness calculation does not apply to fittings and components. However, the PSW replacement by HOPE includes some fittings, e.g.
90 degree mitered elbows, 45 degree mitered elbows, and flange adaptors. The licensee is requested to address minimum required wall thickness for these components.
Enclosure
- 2. Section 1.0, Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Conceptual Design information Package, Reference 3):
Section 3.1 of Enclosure 3 of Reference 3 includes design pressure and design temperature for PSW Header HOPE pipe but does not provide normal and maximum operating pressures and temperatures. It was not identified whether the design values are for PSW supply or PSW return system. The licensee is requested to provide a table showing normal operating, and maximum operating pressures and temperatures for the HOPE piping (PSW Supply, and PSW Return portions as applicable).
3.a In Section 6220 of Enclosure 2 to NL-14-1250 (Reference 1) it was stated that the system will be hydrostatically tested at not less than 1.5times the design pressure
+ 10 psi. Please supplement Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE) to NL-14-1876 (Conceptual Design information Package, Reference 3) to include stresses in HOPE piping for the initial hydrotest based on 1.5 times design pressure+ 10 psi, along with allowable stress limit.
3.b In Supplement 5 (Section XI In-service Inspection) of Enclosure 2 to NL-14-1250 (Reference 1), it was mentioned that the periodic pressure test will be performed using a test pressure of maximum normal operating pressure. Please provide the value for maximum normal operating pressure. *
- 4. In Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE) to NL-14-1876 (Conceptual Design information Package, Reference 3),
(a) Include exerpts from the stress analysis computer program .(i) input, and (ii) output corresponding to the maximum reported stress locations.
(b) Provide a description of the stress analysis model termination boundaries; hour much of the piping and supports beyond the buried HOPE piping is included.
(c) Include a summary of stresses, and loadings (forces and moments) at the interface (metallic pip to HOPE pipe) adapter flange from all applicable load cases, and discuss the acceptability of these loadings.
- 5. On page 1 of 2 of Enclosure 1 (Conceptual Design Scope description) to NL-14-1876 (Conceptual Design information Package, Reference 3), it was mentioned that Valve 2P41-F380B and its operator are relocated in the existing Unit 2 Division II vault, and new stainless steel piping is added. Additional pipe supports will be added to the metallic piping. The licensee is requested to:
(a) Provide loads on metallic piping supports included in the buried HOPE piping model.
(b) Also include valve accelearations for any valves included in the stress analysis model along with their acceptance limits.
(c) Address the impact of these changes on above ground piping stress analysis models, and the qualification of valves and pipe supports in the vicinity of the metallic and HOPE piping interface.
- 6. Page E2-22, Section 3312 of Enclosure 2 to NL-14-1250 (Reference 1) provides allowable stress limit as 2S for c6mputed stresses from non-repeated anchor movements, where Sis Long-Term Allowable Stress for Polyethylene listed in Table 3131-1 (Page E2-22).
7 Page 3 of Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Reference 3) computed non-repeated anchor movement stress based on % inch assumed building settlement and used allowable stress limit of 1S only in margin factor calculation. Please provide the following information.
(a) Technical basis or a justification for% inch settlement used in conceptual design.
(b) Explain if 1S limit instead of 2S limit is used for conservatism only.
- 7. Page 2 of Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Reference 3) provides a tai;Jie containing computed longitudinal stresses for service levels A, B, and D. Please include the load cases and load combinations used for the above three service levels.
- 8. Page 3 of Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Reference 3) provides a table containing seismically induced stresses for straight pipe and miter elbow. Please include the seismic input values used such as soil strains caused by seismic wave passage, seismic soil movement, and seismic anchor motion. Briefly describe the applicable load cases and load combinations used.
- 9. Page 3 of Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Reference 3) provides a table containing stresses from thermal expansion and thermal contraction and combined stress. Please include the corresponding temperatures for all of the thermal modes applicable to the PSW system.
- 10. Page 3 of Section 2.0 of Enclosure 5 (Summary Report on Stress Analysis for PSW Buried HOPE Piping) to NL-14-1876 (Reference 3) provides a table containing stresses
- from alternative thermal expansion and contraction evaluation. Please describe if these stresses are thermal range stresses and include the corresponding temperatures for the applicable thermal cases used in this evaluation.
- 11. Item (e) Page E2-34, Section 4520 of Enclosure 2 to NL-14-1250 (Reference 1) discusses flanged joints at the transition flange. It is mentioned here that in assembling flanged joints, the gaskets, if used, will be uniformly compressed to the proper design loading.
The licensee is requested to clarify whether the transition flanged joints in Hatch, Unit 2, existing service water sub-grade vault 2B and in new service water sub-grade vault
. (page 1 of 2 of Enclosure 1 to NL-14-1876 (Reference 3) contain gaskets or not. Please discuss if leak tight joints can be achieved without a gasket, citing any precedents or operating experience. If gaskets will be used, please provide applicable gasket details (Gasket Material, Gasket Factor, Seating Stress, and Seating Width) .
- 12. As discussed in Enclosure 1 to NL-14-1876 (Reference 3) the majority of the HOPE.
piping is buried with some non-buried portions in an existing vault and in a new vault, which contain transition flanged joints and some valves. The licensee's submittal does not address moderate energy crack postulation assessments for non-buried sections of
HOPE piping. The licensee is requested to address the Moderate Energy Crack postulation assessments for non-buried sections of moderate energy piping and any impact on safety-related commodities in the vicinity. The evaluations should include computed stresses and crack postulation threshold limits to determine if moderate energy cracks need to be postulated or can be excluded.
- 13. Provide a brief discussion related to the fire hazard of the non-buried sections of the HOPE piping located in the existing service water vault 28 and the new service water vault and the impact on any safety-related commodities in the vicinity from the fire hazard. Please also address fire resistance characteristics of the insulation and any.
wrapping used on the HOPE piping.
ML15035A680 OFFICE NRR/LPLII-1/PM NRR/LPLII-1/LA NRR/LPLII-1/BC NRR/LPLII-1/PM NAME RMartin SFigueroa RPascarelli RMartin DATE 01/30/15 02/05/15 02/05/15 02/05/15