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MONTHYEARML0520701182005-08-0303 August 2005 Unit 2 - Closeout Letter for NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. Project stage: Other ML0534603612005-12-14014 December 2005 Letter, Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors Project stage: Other 2005-12-14
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) 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 ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public 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 ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals 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 ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report 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 IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) 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-23-0713, 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-23-0704, 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 IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 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 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter 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 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 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 2024-01-30
[Table view] Category:Memoranda
MONTHYEARML23146A1672023-05-31031 May 2023 Public Meeting Summary2022 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50?348, and 50?364 Meeting Number 20230610 ML22108A1382022-04-18018 April 2022 Annual Assessment Public Meeting Summary ML21280A2962021-10-22022 October 2021 Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150) ML21124A1232021-05-0404 May 2021 April 27, 2021, Public Meeting Summary Joseph M. Farley Nuclear Plant Units 1 and 2, Edwin I. Hatch Nuclear Plant Units 1 and 2, Docket No. 50-348, 50-364, 50-321, 50-366, Meeting Number ML21117A030 ML20154K7242020-06-0202 June 2020 EOC Meeting Summary ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML18337A0422018-12-0303 December 2018 Reissue- Farley 2019 Exam Corporate Notification Letter ML17104A1382017-04-14014 April 2017 Summary of Meeting to Discuss the Annual Assessment of Farley Nuclear Plant, Units 1 and 2 ML16138A6512016-06-0202 June 2016 Audit of Supporting Design, Licensing & Other Documents Related to License Amendment Requests to Support the Adoption of Technical Specification Task Force Traveler 312 ML16126A0812016-05-0505 May 2016 Summary of Public Meeting with Joseph M. Farley, Units 1 and 2 ML16103A5722016-04-21021 April 2016 Transmittal of Final Farley Nuclear Plant Unit 2, Accident Sequence Precursor Analysis ML16097A6022016-04-0808 April 2016 Audit of Supporting Design, Licensing and Other Documents Related to License Amendment Requests to Support Adoption of Technical Specification Task Force Traveler 312 ML15253A4032016-03-11011 March 2016 Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants ML15120A5942015-04-30030 April 2015 Summary of Public Meeting to Discuss 2014 Annual Performance Assessment of the Joseph M. Farley Nuclear Plant ML15055A5622015-02-26026 February 2015 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML14197A5932014-08-0606 August 2014 June 26, 2014, Summary of Category 1 Public Meeting with Southern Nuclear Operating Company to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14133A0392014-06-0303 June 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, and Southern Nuclear Company to Discuss Dam Failure for the Joseph Farley Nuclear Plant ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML14066A0472014-03-0707 March 2014 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742 ML14017A3712014-01-17017 January 2014 Special Inspection Charter to Evaluate the Failure of B Train Solid State Protection System Operability Surveillance Test at Farley Unit 2 ML13067A2692013-03-11011 March 2013 03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML13050A2862013-02-22022 February 2013 3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology ML11208B3162011-07-28028 July 2011 Notice of Closed Meeting with the Southern Nuclear Operating Company, Inc. to Discuss Plant Security Projects and Actions for Upcoming Inspection Activities at the Joseph M. Farley Nuclear Plant ML1108105442011-03-22022 March 2011 Notice of Cancelled Forthcoming Meeting with Southern Nuclear Operating Company, Inc. (Snc), to Discuss NFPA 805 License Amendment for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML1104804052011-03-0707 March 2011 Notice of Forthcoming Meeting with Southern Nuclear Operating Company to Discuss NFPA 805 License Amendment for Farley ML1016704282010-06-17017 June 2010 Meeting Summary Notice ML0929906142009-10-29029 October 2009 Michael Lesar Memo FRN Order (Effective Immediately) Prohibiting Involvement in NRC-Licensed Activities (NRC Office of Investigations Report No. 2-2008-055) ML0917301322009-06-25025 June 2009 06/07-11/2009-Report on Trip to the Institute of Electrical and Electronics Engineers Stationary Battery Committee Meeting in Rohnert Park, CA ML0908607892009-01-16016 January 2009 3. FEMA Response to NRC Regarding Farley TARs Seven Question, FEMA Memo from Burnside, January 16, 2009 ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0730404832007-10-31031 October 2007 Supplemental Augmented Inspection Team Charter to Evaluate a Farley 1B Residual Heat Removal (RHR) Pump 4.16-kV Breaker Failure ML0703002272007-02-0606 February 2007 Facsimile Transmission of Draft Request for Additional Information on Emergency Action Level Revision ML0626902022006-09-20020 September 2006 Facsimile Transmission of Draft Request for Additional Information ML0614505922006-05-26026 May 2006 Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report ML0611602422006-04-26026 April 2006 Special Inspection Charter to Evaluate Farley Unit 1 Main Steam Isolation Valve Failures ML0534901782005-12-0909 December 2005 Safety Evaluation for Proposed Change of Technical Specification to Eliminate the Reactor Coolant Pump Breaker Position Reactor Trip Function. ML0520701182005-08-0303 August 2005 Unit 2 - Closeout Letter for NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0508705022005-03-29029 March 2005 Memo to John a Harris, Correction of License Authority Files (Tac No. MC3231, MC3232) ML0504901422005-02-17017 February 2005 Summary of January 13, 2005, Meeting Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Energy Institute (NEI) on Updating the License Renewal Guidance Documents ML0425402692004-09-15015 September 2004 Memo Issuing Audit and Review Report for Plant Aging Management Reviews and Programs for the Joseph M. Farley Nuclear Plant, Units 1 and 2 ML0415302092004-06-0101 June 2004 Docketing of Questions and Responses Transmitted Electronically or by Facsimile ML0414701282004-05-26026 May 2004 Notice of Meeting with Southern Nuclear Operating Company Re Forthcoming Meeting to Discuss the Staff'S RAIs on LRA for Farley Nuclear Plant, Units 1 & 2 ML0414005382004-05-0707 May 2004 Input to SER for Section 2.4, Scoping and Screening Results: Containments, Structures, and Component Supports, Joseph M. Farley Nuclear Plant LRA ML0335000882003-12-15015 December 2003 Commissioner-District 4 - Acknowledgment of Receipt of Your Letter Supporting the Application for Renewal of the Operating Licenses for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Jason Rudd ML0331604772003-11-12012 November 2003 Email on EOF Relocation ML0323902222003-08-25025 August 2003 Results of the Joseph M. Farley Nuclear Plant Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit ML0828803132002-02-0101 February 2002 Observations Noted from Examination of the Farley-PWR 4.6% Power Uprate: Staff Template for Review of PWR Uprates NRC Generic Letter 1989-111989-06-30030 June 1989 NRC Generic Letter 1989-011: Resolution of Generic Issue 101 Boiling Water Reactor Water Level Redundancy 2023-05-31
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August 3, 2005 MEMORANDUM TO: Evangelos C. Marinos, Section Chief, LPD2-1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: David L. Solorio, Chief /RA/
Balance of Plant Section Plant Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
CLOSEOUT LETTER FOR BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS The Plant Systems Branch (SPLB) has reviewed and evaluated the information provided in responses to Bulletin 2003-01 by the licensee for Farley Unit 1 and Unit 2. SPLB has determined that the licensees actions have been responsive to and meet the intent of Bulletin 2003-01. Attached to this letter is the proposed close-out letter for the above plant. If you have any questions, please contact Leon Whitney or Alan Wang. Please include Alan Wang and Leon Whitney on the distribution list.
Docket Nos: 50-348, 50-364
Attachment:
As stated CONTACTS: Leon Whitney, SPLB/DSSA 415-3081 Alan B. Wang, DLPM, PD IV 415-1445
August 3, 2005 MEMORANDUM TO: Evangelos C. Marinos, Section Chief, LPD2-1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: David L. Solorio, Chief /RA/
Balance of Plant Section Plant Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
CLOSEOUT LETTER FOR BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS The Plant Systems Branch (SPLB) has reviewed and evaluated the information provided in responses to Bulletin 2003-01 by the licensee for the Farley Unit 1 and Unit 2. SPLB has determined that the licensees actions have been responsive to and meet the intent of Bulletin 2003-01. Attached to this letter is the proposed close-out letter for the above plant. If you have any questions, please contact Leon Whitney or Alan Wang. Please include Alan Wang and Leon Whitney on the distribution list.
Docket Nos: 50-348, 50-364
Attachment:
As stated CONTACTS: Leon Whitney, SPLB/DSSA 415-3081 Alan B. Wang, DLPM, PD IV 415-1445 DISTRIBUTION:
LWhitney CGratton AWang DOCUMENT ACCESSION NO:ML052070118 NRR-106 OFFICE DLPM/PDIV-2/PM DSSA/SPLB DSSA/SPLB NAME AWang LWhitney DSolorio DATE 08 / 03 /05 07 / 27 /05 07 / 29 /05 OFFICIAL RECORD COPY
Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway P.O. Box 1295 Birmingham, AL 35201
SUBJECT:
FARLEY UNIT 1 AND UNIT 2 - RESPONSE TO NRC BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED WATER REACTORS (TAC NOS. MB9575 AND MB9576)
Dear Mr. Gasser:
This letter acknowledges receipt of your response dated August 7, 2003, to Nuclear Regulatory Commission (NRC) Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors, dated June 9, 2003. The NRC issued Bulletin 2003-01 to all pressurized-water reactor (PWR) licensees requesting that they provide a response, within 60 days of the date of Bulletin 2003-01, that contains either the information requested in following Option 1 or Option 2 stated in Bulletin 2003-01:
Option 1: State that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in the Discussion section, and are in compliance with all existing applicable regulatory requirements.
Option 2: Describe any interim compensatory measures that have been implemented or that will be implemented to reduce the risk which may be associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete. If any of the interim compensatory measures listed in the Discussion section will not be implemented, provide a justification. Additionally, for any planned interim measures that will not be in place prior to your response to this bulletin, submit an implementation schedule and provide the basis for concluding that their implementation is not practical until a later date.
You provided an Option 2 response.
Bulletin 2003-01 discussed six categories of interim compensatory measures (ICMs):
(1) operator training on indications of and responses to sump clogging; (2) procedural modifications if appropriate, that would delay the switchover to containment sump recirculation ATTACHMENT
Mr. Gasser 2 (e.g., shutting down redundant pumps that are not necessary to provide required flows to cool the containment and reactor core, and operating the CSS intermittently); (3) ensuring that alternative water sources are available to refill the RWST or to otherwise provide inventory to inject into the reactor core and spray into the containment atmosphere; (4) more aggressive containment cleaning and increased foreign material controls; (5) ensuring containment drainage paths are unblocked; (6) ensuring sump screens are free of adverse gaps and breaches.
You stated in your bulletin response of August 7, 2003, that you had implemented the following interim compensatory measures:
(1) initial and continuing operator training including the monitoring of operating ECCS and CSS pumps for indications of pump distress or loss of net-positive suction head (NPSH), operator guidance for the loss of the Safety Injection recirculation function entered in the event of sump blockage, enhancements to the ECCS logs to provide additional detail concerning the recognition and response to ECCS sump suction screen fouling (with annotated actions to be taken upon indications of pump cavitation or signs of sump screen blockage), and job performance measure exercises on the use of ECCS logs - ICM category #1; (2) procedures to add makeup to the refueling water storage tank (RWST) upon loss of emergency coolant recirculation, and a severe accident management guideline detailing potential alternate un-borated sources of RWST makeup - ICM category #3; (3) detailed and extensive procedural guidance for containment inspection to ensure that no loose debris is present in containment, and procedures to inventory and control items carried into containment during non-outage entries - ICM category #4; (4) a procedure which checks that the cavity drain valves are open and their blind flanges removed after completion of refueling activities, double checked by the general containment inspection procedure - ICM category #5; and (5) a procedure performed during refueling outages to ensure that ECCS sump suction screens are not restricted by debris, the sump components (trash racks, screens and inner cages) are properly installed and show no evidence of structural distress or corrosion, the wire mesh on the sump suction screens is not damaged, and gaps greater than 1/8 inch are not present in the mesh - ICM category #6.
You further stated in your response, including justifications, that you would not be implementing the following interim compensatory measure: procedural modifications, if appropriate, that would delay the switchover to containment pump recirculation, In an October 29, 2004, response to an August 30, 2004, NRC request for additional information (RAI) you stated that Southern Nuclear Company (SNC) would provide its response regarding Westinghouse Owners Group (WOG) Bulletin 2003-01 operational guidance (potential interim compensatory measures) by November 30, 2004. In a letter dated November 30, 2004 you stated that SNC had received Westinghouse report WCAP-16204, Revision 1, Evaluation of Potential ERG and EPG Changes to Address NRC Bulletin 2003-01 Recommendations (PA-SEE-0085), and you provided the results of your evaluation of this document and its Candidate Operator Actions (COAs) with respect to Farley as follows:
Mr. Gasser 3 (1) COA 1A, Operator Action to Secure One Containment Spray Pump Before Recirculation Alignment, concluding that because Farley Unit 1 A train and Unit 2 A and B trains of containment spray and residual heat removal (RHR) have separate, independent sumps, but Unit 1 B train core spray and RHR pumps share a common sump screen, SNC would implement COA for Unit 1 B train to reduce differential pressure across that sump - ICM category #2; (2) COA 1B, Operator Action to Secure Both Containment Spray Pumps Before Recirculation Alignment, concluding that for reasons of maintaining appropriate containment pH and providing required containment pressure and dose control during the injection and recirculation phases, this COA would not be implemented; (3) COA 2, Manually Establish One Train of Containment Sump Recirculation Prior to Automatic Recirculation Swapover, concluding that, for reasons of inadequate NPSH, establishing recirculation prior to reaching the current swap-over criteria would not be implemented; (4) COA 3, Terminate One Train of Safety Injection After Recirculation Alignment, concluding that, if the remaining operating train were to fail (single failure), peak cladding temperatures would rise rapidly and there would not be sufficient time for operators to perform effective mitigative actions, and that therefore this COA would not be implemented; (5) COA 4, Early Termination of One RHR Pump Prior to Recirculation Alignment, concluding that this COA, analyzed for CE designed plants, does not apply to Westinghouse designed plants such as Farley; (6) COA 5, Refill of RWST, concluding that current guidance exists at Farley to refill the RWST upon loss of emergency sump recirculation, ensuring that alternate water sources are available to refill the RWST (see below) - ICM category #3; (7) COA 6, Injection of More Than One RWST Volume or Alternate Water Source Bypassing the RWST, concluding that the former interim compensatory measure is addressed in Severe Accident Management Guidelines (SAMGs) and that the latter is in a current Farley emergency procedure - ICM category #3; (8) COA 7, More Aggressive Cooldown and Depressurization Guidance for Small Break LOCA, concluding that, as a Westinghouse plant, Farley currently has aggressive cooldown guidance up to the limits of Technical Specifications - ICM category #2; (9) COA 8, Provide Guidance on Symptoms and Identification of Containment Sump Blockage, concluding that specific indications of sump blockage will be added to three recirculation related emergency procedures (including pump flow, discharge pressure and motor amps), and that local monitoring of containment spray pump parameters would be directed as conditions allow during a LOCA event - ICM category #1; (10) COA 9, Develop Contingency Actions to Be Taken in Response to Containment Sump Blockage, concluding that explicit contingency action guidance will be included in new ECP-1.3, Recirculation Sump Blockage - ICM category #1;
Mr. Gasser 4 (11) COA 10, Termination of One Train of HPSI Prior to Recirculation Alignment, concluding that this COA is applicable only to CE designed plants, unlike Farleys Westinghouse design; and (12) COA 11, Prevent or Delay Containment Spray for Small Break LOCAs, concluding that this COA is not applicable to non-ice condenser containment designed plants such as Farley.
In a July 22, 2005, letter SNC stated that in regards to COA 5, Refill of RWST at Farley, ESP 1.3, Transfer to Cold Leg Recirculation, guidance had been added to start filling the RWST when transfer to cold leg recirculation is complete.
The NRC staff has considered your Option 2 response for compensatory measures that were or were to have been implemented to reduce the interim risk associated with potentially degraded or nonconforming ECCS and CSS recirculation functions. Based on your response, the NRC staff considers your actions to be responsive to and meet the intent of Bulletin 2003-01. Please retain any records of your actions in response to Bulletin 2003-01, as the NRC staff may conduct subsequent inspection activities regarding this issue.
Should you have any questions, please contact me at 301-415-[xxxx] or the lead PM for this issue, Alan Wang at 301-415-1445.
Sincerely,
[Name], Project Manager, Section [1 or 2]
Project Directorate [I, II, III, or IV]
Division of Licensing Project Management Office of Nuclear Reactor Regulation cc: See next page [Plant Mailing List]
ADD TO DISTRIBUTION: AWang, RArchitzel, DSolorio, MKowal, LWhitney