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Category:Inspection Plan
MONTHYEARIR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20230062024-02-28028 February 2024 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2023006 and 05000364/2023006 ML24037A1362024-02-0606 February 2024 RP DLR Feb. 2024 ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML23335A0112023-12-0101 December 2023 IP 95001 Inspection Notification and Request for Information (EA-23-080) ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 ML22347A0882022-12-13013 December 2022 Final Farley Pi_R Initial RFI (2023) IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22101A2862022-04-0101 April 2022 RQ Inspection Corporate Notification Letter IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) ML20302A0002020-10-28028 October 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20175A1992020-06-23023 June 2020 Emergency Preparedness Program Inspection Request for Information ML20094H5182020-04-0303 April 2020 Plant Reference Simulator Inspection Request for Information IR 05000348/20190062020-03-0303 March 2020 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000348/2019006 and 05000364/2019006 ML19274D2092019-09-23023 September 2019 ISI Request for Information IR 05000348/20190052019-08-28028 August 2019 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Reports 05000348/2019005 and 05000364/2019005 ML19100A0072019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000348/20190132019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000364/20180062019-03-0404 March 2019 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000346 and 05000364/2018006 ML19063B8902019-03-0404 March 2019 ISI Sgisi 2019002 RFI - Bcc ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18360A2312018-12-21021 December 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000348/20180052018-08-23023 August 2018 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Reports 05000348/2018005 and 05000364/2018005 ML18094A7822018-04-0303 April 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2018011 and 05000364/2018011 ML18059A1532018-02-28028 February 2018 EOC Assessment Letter ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML18053A0942018-02-22022 February 2018 Baseline In-Service Inspection Initial Information Request ISI 2018002 Rpc IR 05000348/20170052017-08-28028 August 2017 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2, NRC Report 05000348/2017005 and 05000364/2017005 ML17156A1032017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000348/20160062017-03-0101 March 2017 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2016006 and 05000364/2016006) IR 05000348/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Report 05000348/2016005 and 05000364/2016005 ML16244A3102016-08-29029 August 2016 Notification of Inspection and Request for Information ML16062A1522016-03-0202 March 2016 Final Annual Assessment Letter ML15260A9022015-09-17017 September 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2015005 and 05000364/2015005) ML14245A1752014-09-0202 September 2014 Mid-cycle Ltr 2014 ML14121A5042014-05-0101 May 2014 Notification of Triennial Fire Protection Baseline Inspection and Request for Information IR 050000348-14-009 and 05000364-14-009 ML14063A1442014-03-0404 March 2014 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 IR 05000348/20140012014-03-0404 March 2014 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2014001 and 05000364/2014001) ML13354B9722013-12-20020 December 2013 Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 ML13253A3662013-09-10010 September 2013 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML13246A1102013-09-0303 September 2013 Mid-Cycle Assessment Letter ML13070A4622013-03-0808 March 2013 Notification of Inspection and Request for Information IR 05000348/20120012013-03-0404 March 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2012001 and 364/2012001) 2024-08-26
[Table view] Category:Letter
MONTHYEARIR 05000348/20240032024-11-13013 November 2024 Integrated Inspection Report 05000348/2024003, 05000364/2024003 and 07200042/2024001 IR 05000348/20244032024-11-13013 November 2024 – Security Baseline Inspection Report 05000348/2024403 & 05000364/2024403 NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter 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 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown 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 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal 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, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions 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 NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 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-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report 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 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 June 2, 2017 Mr. Dennis Madison Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319
SUBJECT:
FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Madison:
The NRC will perform the baseline heat sink (HS) inspection at the Farley Nuclear Plant, Units 1 and 2, from July 17 - 21, 2017. Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group (Section A of the enclosure) identifies information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (Section B of the enclosure) identifies the information the inspectors will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
We discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Julie Collier of your organization. Our inspection dates are subject to change based on your updated schedule of activities. If there are any questions about this inspection or the material requested, please contact the lead inspector, Brendan Collins, at (404) 997-4420 (Brendan.Collins@nrc.gov).
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Agency Rules of Practice and Procedure," 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 the NRC's Agencywide Document Access and Management System (ADAMS).
D. Madison 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Shakur A. Walker, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-348, 50-364 License Nos.: NPF-2, NPF-8
Enclosure:
Pre-Inspection Document Request cc: Distribution via Listserv
D. Madison 3
SUBJECT:
FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION DATED: June 2, 2017 DISTRIBUTION:
S. Sandal, RII, DRP C. Kontz, SPE D. Mas- Peneranda, PE P. Niebaum, SRI K. Miller, RI S. Price, ORA/RC K. Sloan, RII, EICS RIDSNRRDIRS PUBLIC
- See previous page for concurrence X PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE X NON-SENSITIVE ADAMS: X Yes ACCESSION NUMBER: ___________ x SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII/DRS RII/DRS SIGNATURE BCC2 SAW4 NAME B. Collins S. Walker DATE 6/1/2017 6/2/2017 E-MAIL COPY YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRS NEW\ENG BRANCH 3\INSPECTIONS\WORKING DOCUMENTS\RFIS\HEAT SINK REQUEST FOR INFORMATION LETTERS\2017\Farley HS RFI 2017003 - BCC.DOCX
HEAT SINK PERFORMANCE DOCUMENT REQUEST Inspection Dates: July 17 - 21, 2017 Inspection Procedures: IP 71111.17, Heat Sink Performance Inspectors: Brendan Collins, Reactor Inspector (Lead Inspector)
A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (preferred), in care of Brendan Collins by June 30, 2017, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week (Section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.
A.1 Heat Exchangers and Service Water Equipment a) List of heat exchangers (HXs) or equipment cooled by service water (SW) directly or indirectly
- Include the risk ranking from the site specific risk assessment for each listed HX
- Detail whether any cleaning or inspection activities are planned during the proposed onsite inspection period for any of the listed HXs
- For HXs directly cooled by SW, provide the testing, inspection, maintenance, and monitoring of biotic fouling and macrofouling program documents b) Detail the HX performance inspection methods for HXs that are inspected/cleaned c) Response to Generic Letter 89-13 including any regulatory commitments made d) Design Basis documents associated with the SW system e) Design Basis documents associated with the Ultimate Heat Sink (UHS) f) SW system flow diagrams g) Recent Health Reports associated with the SW System and systems that are cooled by SW h) List of SW system related corrective action documents (with a brief description) which have received a Root Cause Analysis or an elevated severity level in the last three years i) Recent Operating Experience Events (2014-2017)
Enclosure
2 j) List of applicable Codes and Industry Guidelines k) List of findings in the heat sink/heat exchanger performance area for the last 3 years l) List of redundant or infrequently used HXs m) Chemistry Program for safety-related HXs n) Detail whether the UHS is above ground encapsulated by embankments, weirs or excavated side slopes; underwater weir or excavation; or forced draft cooling tower or spray pond o) Provide a list of buried or inaccessible piping and the piping test program, inspection or monitoring program p) List of safety-related and non-safety related valve interfaces q) Most recent self-assessment reports performed on the UHS and SW systems B. Information to be provided on-site to the inspector at the entrance meeting (July 17, 2017):
B.1 Heat Exchangers and Service Water Equipment The inspector will select two to four heat exchangers and/or heat sink samples as required by the inspection procedure during the in-office preparation. The following items will be requested when the selections are made:
a) Updated list of System Engineers b) List of any through-wall leaks including completed or planned corrective actions and structural evaluations c) Provide a copy of the corrective actions and supporting documentation d) For the HXs that have Visual and/or Eddy Current Testing performed, provide a copy of the written procedures used, examination records, examiner qualification records, and associated corrective action documents e) Heat transfer calculations f) Evaluations for the potential of water hammer g) Documentation for controls and operational limits for excessive flow induced vibrations h) Periodic flow test results at/or near maximum design flow i) For an UHS that is encapsulated by embankments, weirs of excavated side slopes provide: (1) third party dam inspection results, and (2) documentation showing that there is sufficient reservoir capacity
3 j) For an UHS that is an underwater weir or excavation provide documentation showing:
- Periodic monitoring and trending of sediment build-up
- Sufficient reservoir capacity
- Considerations for adjacent non-seismic and/or non-safety related structures of possible degradation or blocking of safety-related flow paths due to severe weather or seismic events
- Performance monitoring of heat transfer capabilities
- Performance monitoring of UHS structural integrity
- SW flow balance test results Inspector Contact Information:
Brendan Collins Reactor Inspector 404-997-4420 Brendan Collins@nrc.gov Mailing Address:
US NRC Region 2 Attn: Robert Williams Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303