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| | issue date = 07/14/2008 | | | issue date = 07/14/2008 |
| | title = Response to Request for Additional Information Fourth Ten-Year Interval Inservice Testing Program Update | | | title = Response to Request for Additional Information Fourth Ten-Year Interval Inservice Testing Program Update |
| | author name = Ajluni M J | | | author name = Ajluni M |
| | author affiliation = Southern Nuclear Operating Co, Inc | | | author affiliation = Southern Nuclear Operating Co, Inc |
| | addressee name = | | | addressee name = |
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| | document type = Graphics incl Charts and Tables, Letter type:NL | | | document type = Graphics incl Charts and Tables, Letter type:NL |
| | page count = 6 | | | page count = 6 |
| | | project = |
| | | stage = Response to RAI |
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| {{#Wiki_filter:Southern Nuclear Operating Company, Inc. Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 2059925000 SOUTHERN A COMPANY July 14, 2008 Energy to Serve Your World'* Docket 50-348 NL-08-1033 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant -Units 1 and Response to Request for Additional Information Regarding Fourth Ten-Year Intervallnservice Testing Program Ladies and Gentlemen: | | {{#Wiki_filter:Southern Nuclear Operating Company, Inc. |
| In letter dated August 14, 2007, Southern Nuclear Company (SNC) submitted the Fourth 10-Year Intervallnservice Testing (1ST) Program for Farley Nuclear Plant (FNP) Units 1 and 2 for NRC review and approval. | | Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 2059925000 SOUTHERN COMPANY A |
| In accordance with 10 CFR SO.5Sa(f)(4)(ii), the updated 1ST program was written to meet the requirements of the ASME OM Code 2001 edition though 2003 addenda, except where proposed requests for alternatives and/or proposed requests for relief are documented in the Farley 1ST Program. The Fourth 1ST Interval began on December 1, 2007 and ends on November 30,2017. On June 11, 2008, a NRC Request for Additional Information (RAI) was received regarding the proposed program. This RAI was discussed in a telecon with the NRC Staff on June 23,2008. SNC is withdrawing relief requests RR-P-1 and RR-V-1 since SNC will comply with the appropriate 1ST requirements for the associated components. | | July 14, 2008 Energy to Serve Your World'* |
| SNC is requesting interim approval for RR-P-3 until July 1, 2009 to allow additional testing be performed for the motor driven auxiliary feedwater pumps to determine if a substantial flow rate can be achieved for 1ST. The SNC response to the requested information is provided in Enclosure | | Docket Nos.: 50-348 NL-08-1033 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update Ladies and Gentlemen: |
| : 1. A SNC commitment made in this response is listed in Enclosure
| | In letter dated August 14, 2007, Southern Nuclear Company (SNC) submitted the Fourth 10-Year Intervallnservice Testing (1ST) Program for Farley Nuclear Plant (FNP) Units 1 and 2 for NRC review and approval. In accordance with 10 CFR SO.5Sa(f)(4)(ii), the updated 1ST program was written to meet the requirements of the ASME OM Code 2001 edition though 2003 addenda, except where proposed requests for alternatives and/or proposed requests for relief are documented in the Farley 1ST Program. The Fourth 1ST Interval began on December 1, 2007 and ends on November 30,2017. |
| : 2. If you have any questions, please advise. Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJAlBDM/phr U. S. Nuclear Regulatory Commission Nl-08-1033 Page 2
| | On June 11, 2008, a NRC Request for Additional Information (RAI) was received regarding the proposed program. This RAI was discussed in a telecon with the NRC Staff on June 23,2008. SNC is withdrawing relief requests RR-P-1 and RR-V-1 since SNC will comply with the appropriate 1ST requirements for the associated components. SNC is requesting interim approval for RR-P-3 until July 1, 2009 to allow additional testing be performed for the motor driven auxiliary feedwater pumps to determine if a substantial flow rate can be achieved for 1ST. |
| | The SNC response to the requested information is provided in Enclosure 1. A SNC commitment made in this response is listed in Enclosure 2. |
| | If you have any questions, please advise. |
| | Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJAlBDM/phr |
| | |
| | U. S. Nuclear Regulatory Commission Nl-08-1033 Page 2 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1) Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update 2) Commitment Table Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President | | : 1) Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update |
| -Farley Mr. D. H. Jones, Vice President | | : 2) Commitment Table cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; lC# 14793 U. S. Nuclear Regulatory Commission Mr. l. A. Reyes, Regional Administrator Mr. R. A. Jervey, NRR Project Manager - Farley Mr. E. l. Crowe, Senior Resident Inspector - Farley |
| - | | |
| RTYPE: CFA04.054; lC# U. S. Nuclear Regulatory Mr. l. A. Reyes, Regional Mr. R. A. Jervey, NRR Project Manager -Mr. E. l. Crowe, Senior Resident Inspector | | Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure 1 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update |
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| Joseph M. Farley Nuclear Plant -Units 1 and Enclosure Response to Request for Additional Information Regarding Fourth Ten-Year Intervallnservice Testing Program Enclosure Response to Request for Additional Information Regarding Fourth Ten-Year Intervallnservice Testing Program NRC Question RR-P-3-01 The relief request states that the 2 inch minimum flow fixed resistance line limits flow to 50 gpm which provides only minimal data for determining pump operational readiness. | | Enclosure 1 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update NRC Question RR-P-3-01 The relief request states that the 2 inch minimum flow fixed resistance line limits flow to 50 gpm which provides only minimal data for determining pump operational readiness. The relief request also states that each pump is provided with a 4 inch return line to the condensate storage tank but that significant piping vibration was experienced when attempts were made to utilize the piping for full flow testing of the Auxiliary Feedwater (AFW) pumps. Please discuss the ramifications of using the 4 inch return line at flow rates greater than 50 gpm but less than 350 gpm for the quarterly Group A test. |
| The relief request also states that each pump is provided with a 4 inch return line to the condensate storage tank but that significant piping vibration was experienced when attempts were made to utilize the piping for full flow testing of the Auxiliary Feedwater (AFW) pumps. Please discuss the ramifications of using the 4 inch return line at flow rates greater than 50 gpm but less than 350 gpm for the quarterly Group A test. SNC Response Additional evaluation and testing will be required to address this question. FNP will perform additional testing utilizing the 4-inch return line and determine if a substantial flow rate can be achieved for 1ST. A flow rate of 280 gpm (80% of accident flow rate) would satisfy the code requirement for the Group A Test. FNP will conduct this additional testing and evaluation and provide the results to the NRC no later than jUly 1, 2009 which allows for testing during a refueling outage on each unit, if necessary. FNP's final response will include either a revised relief request justifying any flow rate < 280 gpm or withdrawal of the relief request if testing in accordance with the Code is achievable. Therefore, FNP requests interim approval for RR-P-3 until July 1,2009. E1-1 Joseph M. Farley Nuclear Plant -Units 1 and Enclosure Commitment Enclosure Commitment Commitment Type Scheduled Completion Date (If Required) | | SNC Response Additional evaluation and testing will be required to address this question. |
| One-Time Action Continuing Compliance Test MDAFW pumps to determine if >50 gpm flow can be achieved and provide the results to the NRC. X prior to July 01 , 2009 E2 -1}}
| | : 1. FNP will perform additional testing utilizing the 4-inch return line and determine if a substantial flow rate can be achieved for 1ST. A flow rate of |
| | ~ 280 gpm (80% of accident flow rate) would satisfy the code requirement for the Group A Test. |
| | : 2. FNP will conduct this additional testing and evaluation and provide the results to the NRC no later than jUly 1, 2009 which allows for testing during a refueling outage on each unit, if necessary. |
| | : 3. FNP's final response will include either a revised relief request justifying any flow rate < 280 gpm or withdrawal of the relief request if testing in accordance with the Code is achievable. |
| | : 4. Therefore, FNP requests interim approval for RR-P-3 until July 1,2009. |
| | E1- 1 |
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| | Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure 2 Commitment Table |
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| | Enclosure 2 Commitment Table Type Scheduled Commitment Completion Date One-Time Continuing (If Required) |
| | Action Compliance Test MDAFW pumps to determine if >50 prior to July 01 , |
| | gpm flow can be achieved and provide the X 2009 results to the NRC. |
| | E2 -1}} |
Letter Sequence Response to RAI |
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Category:Graphics incl Charts and Tables
MONTHYEARML18312A0712018-10-30030 October 2018 Revision 28 to Updated Final Safety Analysis Report, Chapter 3, Part 2 ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15343A4182015-12-10010 December 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML15106A3612015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Example Vogtle 1 and 2, Change Justification Matrix ML14135A1732014-02-26026 February 2014 May 16, 2014, J.M. Farley Category 1 Meeting Handout, Duration for Completion of the Flood Hazard Re-evaluation. ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 NL-08-1033, Response to Request for Additional Information Fourth Ten-Year Interval Inservice Testing Program Update2008-07-14014 July 2008 Response to Request for Additional Information Fourth Ten-Year Interval Inservice Testing Program Update ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0519603252005-07-15015 July 2005 Attachment 3 - Recommendation and Action Item Cross Reference Table 2005-025 2018-10-30
[Table view] Category:Letter type:NL
MONTHYEARNL-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) 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-24-0230, Plants Units 1&2, 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 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, 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-24-0201, 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) 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 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 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 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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. NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update 2024-07-03
[Table view] |
Text
Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 2059925000 SOUTHERN COMPANY A
July 14, 2008 Energy to Serve Your World'*
Docket Nos.: 50-348 NL-08-1033 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update Ladies and Gentlemen:
In letter dated August 14, 2007, Southern Nuclear Company (SNC) submitted the Fourth 10-Year Intervallnservice Testing (1ST) Program for Farley Nuclear Plant (FNP) Units 1 and 2 for NRC review and approval. In accordance with 10 CFR SO.5Sa(f)(4)(ii), the updated 1ST program was written to meet the requirements of the ASME OM Code 2001 edition though 2003 addenda, except where proposed requests for alternatives and/or proposed requests for relief are documented in the Farley 1ST Program. The Fourth 1ST Interval began on December 1, 2007 and ends on November 30,2017.
On June 11, 2008, a NRC Request for Additional Information (RAI) was received regarding the proposed program. This RAI was discussed in a telecon with the NRC Staff on June 23,2008. SNC is withdrawing relief requests RR-P-1 and RR-V-1 since SNC will comply with the appropriate 1ST requirements for the associated components. SNC is requesting interim approval for RR-P-3 until July 1, 2009 to allow additional testing be performed for the motor driven auxiliary feedwater pumps to determine if a substantial flow rate can be achieved for 1ST.
The SNC response to the requested information is provided in Enclosure 1. A SNC commitment made in this response is listed in Enclosure 2.
If you have any questions, please advise.
Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJAlBDM/phr
U. S. Nuclear Regulatory Commission Nl-08-1033 Page 2
Enclosures:
- 1) Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update
- 2) Commitment Table cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; lC# 14793 U. S. Nuclear Regulatory Commission Mr. l. A. Reyes, Regional Administrator Mr. R. A. Jervey, NRR Project Manager - Farley Mr. E. l. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure 1 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update
Enclosure 1 Response to Request for Additional Information Regarding the Fourth Ten-Year Intervallnservice Testing Program Update NRC Question RR-P-3-01 The relief request states that the 2 inch minimum flow fixed resistance line limits flow to 50 gpm which provides only minimal data for determining pump operational readiness. The relief request also states that each pump is provided with a 4 inch return line to the condensate storage tank but that significant piping vibration was experienced when attempts were made to utilize the piping for full flow testing of the Auxiliary Feedwater (AFW) pumps. Please discuss the ramifications of using the 4 inch return line at flow rates greater than 50 gpm but less than 350 gpm for the quarterly Group A test.
SNC Response Additional evaluation and testing will be required to address this question.
- 1. FNP will perform additional testing utilizing the 4-inch return line and determine if a substantial flow rate can be achieved for 1ST. A flow rate of
~ 280 gpm (80% of accident flow rate) would satisfy the code requirement for the Group A Test.
- 2. FNP will conduct this additional testing and evaluation and provide the results to the NRC no later than jUly 1, 2009 which allows for testing during a refueling outage on each unit, if necessary.
- 3. FNP's final response will include either a revised relief request justifying any flow rate < 280 gpm or withdrawal of the relief request if testing in accordance with the Code is achievable.
- 4. Therefore, FNP requests interim approval for RR-P-3 until July 1,2009.
E1- 1
Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure 2 Commitment Table
Enclosure 2 Commitment Table Type Scheduled Commitment Completion Date One-Time Continuing (If Required)
Action Compliance Test MDAFW pumps to determine if >50 prior to July 01 ,
gpm flow can be achieved and provide the X 2009 results to the NRC.
E2 -1