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Category:Letter type:NLS
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station NLS2022031, Licensee Guarantees of Payment of Deferred Premiums2022-07-19019 July 2022 Licensee Guarantees of Payment of Deferred Premiums NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-06-16016 June 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements NLS2022025, Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring2022-06-0606 June 2022 Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring NLS2022016, Annual Radiological Environmental Report2022-05-10010 May 2022 Annual Radiological Environmental Report NLS2022020, Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report2022-05-0202 May 2022 Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report NLS2022014, Annual Radioactive Effluent Release Report2022-04-27027 April 2022 Annual Radioactive Effluent Release Report NLS2022010, Annual Report of Individual Exposure Monitoring2022-04-0505 April 2022 Annual Report of Individual Exposure Monitoring NLS2022009, Property Insurance Coverage2022-03-23023 March 2022 Property Insurance Coverage NLS2022011, Preparation and Scheduling of Operator Licensing Examinations2022-03-18018 March 2022 Preparation and Scheduling of Operator Licensing Examinations NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 NLS2021067, ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan2021-12-16016 December 2021 ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan NLS2021069, Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-12-15015 December 2021 Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 2024-01-25
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021058, Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-10-12012 October 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2020051, Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change2020-08-25025 August 2020 Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change ML18311A1862018-11-0505 November 2018 Email (11-5-18) RR RFI Responses for Review NLS2018029, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-032018-05-16016 May 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-03 NLS2018017, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station Independent Spent Fuel Storage Installation2018-04-11011 April 2018 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station Independent Spent Fuel Storage Installation ML18241A3822018-03-23023 March 2018 CNS Email to Beaulieu, George, Kumana: Response to CNS Fan Coil Unit Questions NLS2018012, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-032018-03-14014 March 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-03 NLS2018011, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Requests RR5-02 and RR5-032018-03-0808 March 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Requests RR5-02 and RR5-03 NLS2017095, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI-21, Revision 12017-11-30030 November 2017 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI-21, Revision 1 NLS2017072, Nebraska Public Power District'S Seismic High Frequency Confirmation - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from2017-08-24024 August 2017 Nebraska Public Power District'S Seismic High Frequency Confirmation - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from t ML17244A2812017-05-0808 May 2017 16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation. NLS2017012, Response to NRC Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report2017-02-0808 February 2017 Response to NRC Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report NLS2016067, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 32016-12-0707 December 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3 NLS2016075, Response to Nuclear Regulatory Commission RAI Regarding License Amendment Request to Adopt TSTF-425, Rev 32016-12-0707 December 2016 Response to Nuclear Regulatory Commission RAI Regarding License Amendment Request to Adopt TSTF-425, Rev 3 ML16258A3732016-11-16016 November 2016 Cooper Nuclear Station - Response Regarding Phase 2 Staffing Submittals Associated with Near-Term Task Force Recommendation 9.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (CAC No. MF7776) NLS2016053, Nebraska Public Power District'S Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information2016-09-14014 September 2016 Nebraska Public Power District'S Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information ML16252A2232016-08-29029 August 2016 Response to NRC Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016045, Nebraska, Final Six-Month Status Report and Response to Request for Additional Information in Response to Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-08-22022 August 2016 Nebraska, Final Six-Month Status Report and Response to Request for Additional Information in Response to Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) NLS2016029, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 9.3, Emergency Preparedness - Staffing, Requested Information Items 1,2, and 6 - Phase 2 Staffing Assessment2016-05-18018 May 2016 Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 9.3, Emergency Preparedness - Staffing, Requested Information Items 1,2, and 6 - Phase 2 Staffing Assessment ML16084A1822016-03-17017 March 2016 Response to Nuclear Regulatory Commission Request for Additional Information (RAI) Regarding Proposed Changes to the Technical Specifications for Implementation of a New Pressure-Temperature Limits Report NLS2015133, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-022015-12-21021 December 2015 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-02 NLS2015123, Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, RP5-012015-11-0909 November 2015 Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, RP5-01 NLS2015112, Response to NRC Requests for Additional Information for Relief Request No. RR5-01, Alternate Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap2015-10-29029 October 2015 Response to NRC Requests for Additional Information for Relief Request No. RR5-01, Alternate Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap NLS2015113, Response to NRC Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-022015-10-21021 October 2015 Response to NRC Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-02 NLS2015086, Response to Nuclear Regulatory Commission Additional Requests for Additional Information for License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water2015-07-13013 July 2015 Response to Nuclear Regulatory Commission Additional Requests for Additional Information for License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water NLS2015080, Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program2015-06-30030 June 2015 Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program NLS2015068, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2. 1, Seismic Hazard and Screening Report2015-06-22022 June 2015 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2. 1, Seismic Hazard and Screening Report 2024-01-25
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H Nebraska Public Power District AlwaJs theTe when JOU need us NLS2017012 February 8, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Response to Nuclear Regulatory Commission Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. NPPD Letter to NRC, "Nebraska Public Power District's Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated September 14, 2016
- 2. NRC letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2), and 9.3, of the Near-Term Task Force Review oflnsights from the Fukushima Dai-ichi Accident," dated March 12, 2012
- 3. Email from Frankie Vega, NRC, to Brenda Kirkpatrick, NPPD, "Rec 2.1 Seismic: Cooper's SFP Evaluation," dated December 15, 2016
Dear Sir or Madam:
In Reference 1, Nebraska Public Power District (NPPD) submitted the Spent Fuel Pool (SFP)
Evaluation Report in response to the seismic aspects of Recommendation 2.1 in Reference 2.
In Reference 3, the Nuclear Regulatory Commission (NRC) requested information/clarification regarding the piping evaluation documented in the SFP evaluation. The attachment to this letter provides NPPD's response to Reference 3.
There are no new regulatory commitments contained in this correspondence.
Should you have any questions or require additional information, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
COOPER NUCLEAR STATION P.O. Box 98 I Brownville, NE 68327-0098 Telephone: (402) 825-3877 /Fax: (402) 825-5211 www.nppd.com
NLS2017012 Page 2 of2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on: _ _ ;;__,./'-~::...,0;._1_,.7'-----
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Kenn:~tham Vice President - Nuclear and Chief Nuclear Officer
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Attachment:
Response to Nuclear Regulatory Commission Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report cc: Regional Administrator, w/attachment USNRC - Region IV Director, w/attachment USNRC - Office of Nuclear Reactor Regulation Cooper Project Manager, w/attachment USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector, w/attachment USNRC-CNS NPG Distribution, w/attachment CNS Records, w/attachment
NLS2017012 Attachment Page 1 of2 ATTACHMENT Response to Nuclear Regulatory Commission Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report Cooper Nuclear Station, Docket No. 50-298, DPR-46 By letter dated September 14, 2016, Nebraska Public Power District (NPPD) submitted the Spent Fuel Pool Evaluation Report for Cooper Nuclear Station (CNS). In an email dated December 15, 2016, the Nuclear Regulatory Commission (NRC) transmitted the following request for information/clarification:
NRC Request:
The piping evaluation section states that piping attached to the SFP could not be confirmed to have been evaluated to the SSE. In addition, this section states that piping is attached such that drain-down is possible to 10' above top offuel, which is a "safe storage depth. "
However, analyses in EPRl's SFP Seismic Evaluation Guidance (EPRI 3002007148) considered initial SFP water losses only from seismically induced sloshing, and did not consider additional water losses such as from a potential SFP pipe-break located 10' above the top of the spent fuel.
Additional information is needed to evaluate the potential for boil-offand uncovering the top third of the spent fuel within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ofa seismically induced pipe-break that resulted in unm.itigated water loss to 10' above the top of the spent fuel, which is the event sequence outlined in the SPID (EPRI 1025287).
NPPD Response:
The piping evaluation within the "Non-Structural Parameters" section of the Spent Fuel.Pool (SFP) Evaluation Report reiterates an Updated Safety Analysis Report statement that describes the SFP "safe storage level" as 10 feet above the top of the fuel and that there are no penetrations below the "safe storage level."
Furthermore, this section states that there are two lines (6" FC-1 S and 4" FC-2) designated as seismic Class IIS. Class IIS piping may be required for the operation of the station, but are not required for a safe shutdown. Based on a review of CNS drawings, the4" FC-2 line does not penetrate the SFP liner. The 4" FC-2 line is part of the SFP skimmer that branches off to the 2" FC-2 lines connected to the skimmer around the pool at elevation 1000'-0", approximately 5.5" above the SFP norinal water level; therefore the 4" FC-2 lines cannot cause a rapid drain-down of the SFP leading to uncovering more than one third of the fuel in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The 6" FC-lS lines enter the SFP at elevation 997'-10". Outside the SFP, the lines are connected to check valves at elevation 999'-4" and the check valves are approximately 2'-10" from the
NLS2017012 Attachment Page 2 of2 outside face of the SFP wall. These check valves prevent backflow out of the pool in the event of a pipe break upstream of the check valve below the water level in the pool.
Furthermore, there are anti-siphoning devices on the 6" FC-1 S lines at elevation 996'-1 O". If the check valves in the 6" FC-1 S line were to fail during a break of the upstream piping, or in the event of a pipe break on the short section of piping between the check valve and the fuel pool, these devices limit the potential loss due to siphoning to 2'-11 Yz (i.e., 35.5 inches), the SFP remains within the range of the EPRI analyzed plants.
The potential loss due to siphoning is: (999'-9Yz") - (996'-10") = 2'-11Yz"=35.5 inches.
SFP sloshing and siphoning losses are not accumulative; therefore, any loss due to SFP sloshing would reduce the potential loss due to siphoning. Hence, given the potential losses due to siphoning, the remaining water inventory above the top elevation of fuel assemblies is 37.54 ft. -
2.96 ft. - 15.2 ft. (height ofracks) = 19.38 ft., which is within the range of the EPRI analyzed plants (i.e., 16.8 ft. to 29.2 ft.). Accounting for allowed inventory losses down to one third the height of the fuel assemblies in accordance with the Screening, Prioritization, and Implementation Details report (EPRI 1025287), the increased inventory height is 19.38 ft.+ (1/3)
(height of racks) = 24.45 ft~, which is within the range of the EPRI analyzed plants (i.e., 21.8 ft.
to 34.2 ft.).
Finally, Table 3-4 of the EPRI Guidelines (EPRI 3002007148) summarizes the SFP non-,'.
structural evaluation criteria with the following statement for sloshing:
"Site-specific sloshing analyses show that inventory losses are minor. For plants with peak Sa less than 0.8g, a conservative estimate ofSFP inventory lost to sloshing is 3 feet.
This lost inventory is accounted for in estimating evaporative losses (below)."
Since the maximum potential loss due to siphoning, (i.e. 2'-11 Yz), is less than the. estimates of SFP inventory loss due to sloshing/evaporation, (i.e. 3'); any potential loss due to siphoning has already been accounted for in EPRI's evaporation loss analysis.
Given the aforementioned justification, the potential losses due to siphoning from the 6" FC-1 S lines are within the bounds of the EPRI analyzed plants; therefore there will not be a rapid drain-down of the SFP leading to uncovering more than one third of the fuel in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.