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| | number = ML14192B031 | | | number = ML14192B031 |
| | issue date = 08/13/2014 | | | issue date = 08/13/2014 |
| | title = Columbia Generating Station - Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows ( | | | title = Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows |
| | author name = George A E | | | author name = George A |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Reddemann M E | | | addressee name = Reddemann M |
| | addressee affiliation = Energy Northwest | | | addressee affiliation = Energy Northwest |
| | docket = 05000397 | | | docket = 05000397 |
| | license number = NPF-021 | | | license number = NPF-021 |
| | contact person = George A E | | | contact person = George A |
| | case reference number = TAC MF3055 | | | case reference number = TAC MF3055 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:OFFICIAL USE ONLY PROPRIIiTARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 August 13, 2014 | | {{#Wiki_filter:OFFICIAL USE ONLY PROPRIIiTARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 13, 2014 Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) |
| | Richland, WA 99352-0968 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COLUMBIA GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (TAC NO. MF3055) | | COLUMBIA GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (TAC NO. MF3055) |
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| ==Dear Mr. Reddemann:== | | ==Dear Mr. Reddemann:== |
| By letter dated October 31, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML 13316A009), as supplemented by letter dated May 29, 2014 (ADAMS Accession No. ML 14163A482), Energy Northwest submitted a license amendment request to revise Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the low pressure core spray and residual heat removal/low pressure coolant injection pump flows. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed requests for additional information (RAis) were provided to L. Williams of your staff on May 29, 2014, and a clarification call was held on June 12, 2014. Please provide a response to the RAis within 30 days of the date of this letter. The NRC staff has determined that the RAis contain proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390. Proprietary information is indicated in the RAI text enclosed within brackets. Accordingly, the NRC staff has also prepared a proprietary, publicly available version of the RAis, which is provided in Enclosure 1. The proprietary version of the RAis is provided in Enclosure 2. Enclosure 2 to this letter contains Proprietary Information. When separated from Enclosure 2, this letter is DECONTROLLED. OFFICIAL USE ONLY PROPRIIiTAR¥ INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov. Docket No. 50-397 | | |
| | By letter dated October 31, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML13316A009), as supplemented by letter dated May 29, 2014 (ADAMS Accession No. ML14163A482), Energy Northwest submitted a license amendment request to revise Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the low pressure core spray and residual heat removal/low pressure coolant injection pump flows. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed requests for additional information (RAis) were provided to L. Williams of your staff on May 29, 2014, and a clarification call was held on June 12, 2014. Please provide a response to the RAis within 30 days of the date of this letter. |
| | The NRC staff has determined that the RAis contain proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390. Proprietary information is indicated in the RAI text enclosed within brackets. Accordingly, the NRC staff has also prepared a non-proprietary, publicly available version of the RAis, which is provided in Enclosure 1. The proprietary version of the RAis is provided in Enclosure 2. to this letter contains Proprietary Information. When separated from Enclosure 2, this letter is DECONTROLLED. |
| | OFFICIAL USE ONLY PROPRIIiTAR¥ INFORMATION |
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| | OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov. |
| | Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 |
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| ==Enclosures:== | | ==Enclosures:== |
| 1. Non-Proprietary RAis 2. Proprietary RAis cc w/encl 1: Distribution via Listserv Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICIAL USE ONLY PROPRIETARY INFORMATION ENCLOSURE 1 REQUESTS FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 Proprietary information pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations has been redacted from this document. Redacted information is identified by blank space enclosed within double brackets. | | : 1. Non-Proprietary RAis |
| OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 In a letter dated October 31, 2013 (Reference 1 ), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (CFR), Energy Northwest submitted a license amendment request to revise the Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the Low Pressure Core Spray (LPCS) and Low Pressure Coolant Injection (LPCI) pump flows. Energy Northwest is requested to provide a response to the following request for additional information (RAI) questions in order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review: SCVB*RAI-1 Reference 2, Table 1, "Key Inputs for the Long-Term Containment Response": The service water temperature input parameter is stated as 85 degrees Fahrenheit (°F) for first 10 hours of loss-of-coolant accident (LOCA) and 90 °F thereafter. However, Reference 3 assumes service water temperature of 90 °F. Please provide justification for using a lower value of the service water temperature for the first 10 hours of the LOCA transient. SCVB-RAI-2 Reference 2, Section 2.1, under heading "Case B: Loss of offsite power-with delayed containment spray" states: "During this time an operational restriction prohibits the activation of containment spray." (a) Please describe the possible operational restrictions that would prevent the initiation of containment sprays. (b) Ten minutes from the initiation of the reactor scram is the normally allowed operator action time for the activation of sprays. Please explain what time was used for the spray initiation for case B. SCVB-RAI-3 Reference 2, Section 2.1, under heading "Case D: All ECCS equipment operating -RHR [residual heat removal] heat exchanger failure". [[ OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY-PROPRIETARY INFORMATION ]] SCVB-RAI-4 Reference 2, Section 4.1.2; please describe the event "Inadvertent RHR Shutdown Cooling." Please provide a further discussion of why it is not adversely affected by a reduction in the RHR flow rate. SCVB-RAI-5 Reference 2, Section 4.1.3; the Final Safety Analysis Report (FSAR) K-value of the two RHR heat exchangers of 578 BTU/s-°F is based on service water temperature of 90°F, and [( ]] Please explain what are the parameters and their FSAR values and new values that resulted in the reduction of the heat exchanger K-value from 578 BTU/s-°F to [( ]] SCVB-RAI-6 Reference 2, Section 4.1.3; please describe the [[ ]] from the FSAR A TWS [anticipated transient without scram] event analysis. SCVB-RAI-7 Please describe the impact of the changes in the LPCS and LPCI flows on the containment wall temperature response analysis under LOCA and main steam line break (MSLB) accident. SCVB-RAI-8 Please provide the following information for the NRC staff review: (a) The value of the required net positive suction head (NPSH) (NPSHR) for the RHR and LPCS pumps while drawing water from the suppression pool. (b) The basis for the NPSHR including the standard on which it is based. As an example, commonly for ECCS and residual heat removal system pumps it is based on the Hydraulic Institute {HI) standard according to which the NPSHR is equal to the available NPSH determined in a factory test at the pump design flow with a 3-percent drop in the total dynamic head. (c) The uncertainty in the factory tested value of NPSHR based on the actual site conditions. (d) The minimum NPSH available (NPSHA) in the proposed analysis at each pump inlet without crediting containment accident pressure, based on maximizing the suppression pool water temperature together with maximizing the suction strainer head loss and maximizing piping head loss. OFFICIAL USE ONLY-PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION (e) The minimum NPSH margin for each pump and its percentage based on NPSHR with uncertainty added. REFERENCES 1. Javorik, Alex L., Energy Northwest letter to U.S. Nuclear Regulatory Commission, "Columbia Generating station. Docket no. 50-397 License Amendment Request for Change to Emergency Core Cooling Systems Surveillance Requirements," dated October 31, 2013 (ADAMS Accession No. ML 13316A009). 2. GE Hitachi Nuclear Energy, NEDC-33813P, Technical Specification Change Support for RHRILPCI and LPCS Flow Rate Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations, Revision 2, September 2013 (Non-Proprietary version available at ADAMS Accession No. ML 13316A010). 3. GE Nuclear Energy, NEDC-32141P, Power Uprate with Extended Load Line Limit Safety Analysis for WNP-2, June 1993. OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov. Docket No. 50-397 | | : 2. Proprietary RAis cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION |
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| | ENCLOSURE 1 REQUESTS FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 Proprietary information pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations has been redacted from this document. |
| | Redacted information is identified by blank space enclosed within double brackets. |
| | |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 In a letter dated October 31, 2013 (Reference 1), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (CFR), Energy Northwest submitted a license amendment request to revise the Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the Low Pressure Core Spray (LPCS) and Low Pressure Coolant Injection (LPCI) pump flows. Energy Northwest is requested to provide a response to the following request for additional information (RAI) questions in order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review: |
| | SCVB*RAI-1 Reference 2, Table 1, "Key Inputs for the Long-Term Containment Response": |
| | The service water temperature input parameter is stated as 85 degrees Fahrenheit (°F) for first 10 hours of loss-of-coolant accident (LOCA) and 90 °F thereafter. However, Reference 3 assumes service water temperature of 90 °F. Please provide justification for using a lower value of the service water temperature for the first 10 hours of the LOCA transient. |
| | SCVB-RAI-2 Reference 2, Section 2.1, under heading "Case B: Loss of offsite power- with delayed containment spray" states: |
| | "During this time an operational restriction prohibits the activation of containment spray." |
| | (a) Please describe the possible operational restrictions that would prevent the initiation of containment sprays. |
| | (b) Ten minutes from the initiation of the reactor scram is the normally allowed operator action time for the activation of sprays. Please explain what time was used for the spray initiation for case B. |
| | SCVB-RAI-3 Reference 2, Section 2.1, under heading "Case D: All ECCS equipment operating - RHR |
| | [residual heat removal] heat exchanger failure". (( |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION |
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| | OFFICIAL USE ONLY- PROPRIETARY INFORMATION |
| | )) |
| | SCVB-RAI-4 Reference 2, Section 4.1.2; please describe the event "Inadvertent RHR Shutdown Cooling." |
| | Please provide a further discussion of why it is not adversely affected by a reduction in the RHR flow rate. |
| | SCVB-RAI-5 Reference 2, Section 4.1.3; the Final Safety Analysis Report (FSAR) K-value of the two RHR heat exchangers of 578 BTU/s-°F is based on service water temperature of 90°F, and [( |
| | )) Please explain what are the parameters and their FSAR values and new values that resulted in the reduction of the heat exchanger K-value from 578 BTU/s-°F to [( )) |
| | SCVB-RAI-6 Reference 2, Section 4.1.3; please describe the (( |
| | )) from the FSAR ATWS [anticipated transient without scram] event analysis. |
| | SCVB-RAI-7 Please describe the impact of the changes in the LPCS and LPCI flows on the containment wall temperature response analysis under LOCA and main steam line break (MSLB) accident. |
| | SCVB-RAI-8 Please provide the following information for the NRC staff review: |
| | (a) The value of the required net positive suction head (NPSH) (NPSHR) for the RHR and LPCS pumps while drawing water from the suppression pool. |
| | (b) The basis for the NPSHR including the standard on which it is based. As an example, commonly for ECCS and residual heat removal system pumps it is based on the Hydraulic Institute {HI) standard according to which the NPSHR is equal to the available NPSH determined in a factory test at the pump design flow with a 3-percent drop in the total dynamic head. |
| | (c) The uncertainty in the factory tested value of NPSHR based on the actual site conditions. |
| | (d) The minimum NPSH available (NPSHA) in the proposed analysis at each pump inlet without crediting containment accident pressure, based on maximizing the suppression pool water temperature together with maximizing the suction strainer head loss and maximizing piping head loss. |
| | OFFICIAL USE ONLY- PROPRIETARY INFORMATION |
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| | OFFICIAL USE ONLY PROPRIETARY INFORMATION (e) The minimum NPSH margin for each pump and its percentage based on NPSHR with uncertainty added. |
| | REFERENCES |
| | : 1. Javorik, Alex L., Energy Northwest letter to U.S. Nuclear Regulatory Commission, "Columbia Generating station. Docket no. 50-397 License Amendment Request for Change to Emergency Core Cooling Systems Surveillance Requirements," dated October 31, 2013 (ADAMS Accession No. ML13316A009). |
| | : 2. GE Hitachi Nuclear Energy, NEDC-33813P, Technical Specification Change Support for RHRILPCI and LPCS Flow Rate Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations, Revision 2, September 2013 (Non-Proprietary version available at ADAMS Accession No. ML13316A010). |
| | : 3. GE Nuclear Energy, NEDC-32141P, Power Uprate with Extended Load Line Limit Safety Analysis for WNP-2, June 1993. |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov. |
| | Sincerely, |
| | /RAJ Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 |
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| ==Enclosures:== | | ==Enclosures:== |
| 1. Non-Proprietary RAis 2. Proprietary RAis cc w/encl 1: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEmcb Resource RidsNrrDeEvib Resource RidsNrrDoriDpr Resource Sincerely, /RAJ Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorllpl4-1 Resource RidsNrrPMColumbia Resource RidsNrrLAJBurkhardt Resource RidsRgn4Mai1Center Resource DHoang, NRRJDE/EMCB CSydnor, NRRIDE/EVIB ADAMS A ccess1on N o.: p . t ML 141928026 ropne ary N p on* . t ML 141928031 ropne ary OFFICE NRRIDORULPL4-1/PM NRR/DORULPL4-1/LA NRRIDSS/SCVB/BC NRR/DORULPL4-1/BC NRRIDORULPL4-1/PM NAME A George J Bu r1<hardt RDennig ( JBettle for) MMarkley A George DATE 7/14/14 7/11/14 7/16/14 8/13/14 8/13/14 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION | | : 1. Non-Proprietary RAis |
| }} | | : 2. Proprietary RAis cc w/encl 1: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrDorllpl4-1 Resource LPL4-1 r/f RidsNrrPMColumbia Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDeEmcb Resource RidsRgn4Mai1Center Resource RidsNrrDeEvib Resource DHoang, NRRJDE/EMCB RidsNrrDoriDpr Resource CSydnor, NRRIDE/EVIB ADAMS A ccess1on No.: p ropne . tary ML141928026 Non* p ropne |
| | . tary ML141928031 OFFICE NRRIDORULPL4-1/PM NRR/DORULPL4-1/LA NRRIDSS/SCVB/BC NRR/DORULPL4-1/BC NRRIDORULPL4-1/PM NAME AGeorge J Bu r1<hardt RDennig ( JBettle for) MMarkley A George DATE 7/14/14 7/11/14 7/16/14 8/13/14 8/13/14 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION}} |
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MONTHYEARGO2-13-151, NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations.2013-09-30030 September 2013 NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations. Project stage: Other ML13316A0092013-10-31031 October 2013 License Amendment Request for Change to Emergency Core Cooling Systems Surveillance Requirements Project stage: Request ML14038A0262014-02-0707 February 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14056A1202014-03-0505 March 2014 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML14111A0832014-04-29029 April 2014 Request for Additional Information, License Amendment Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows Project stage: RAI ML14163A4822014-05-29029 May 2014 Response to Request for Additional Information Regarding License Amendment Request to Change Emergency Core Cooling Systems Surveillance Requirements Project stage: Response to RAI ML14192B0312014-08-13013 August 2014 Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows Project stage: RAI ML14335A1892015-01-0707 January 2015 Redacted, Issuance of Amendment No. 229, Revise Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows Project stage: Approval 2014-03-05
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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection ML22343A1802022-12-0808 December 2022 February 2023 Emergency Preparedness Program Inspection - Request for Information ML22301A1432022-10-28028 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Adopt TSTF-505 - EPID L-2022-LLA-0023 ML22242A1082022-08-30030 August 2022 Information Request, Information Request, Security IR 2022404 ML22235A1052022-08-22022 August 2022 August 2022 Emergency Preparedness Exercise Inspection Request for Information ML22145A4462022-06-0606 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000397/2022401 ML22144A0342022-05-18018 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22041A4572022-02-10010 February 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000397/2022010) and Request for Information ML21277A3572021-10-12012 October 2021 CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information ML21216A0502021-08-0303 August 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia - License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO EPID L-2021-LLA-0259 ML21209A9792021-07-28028 July 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) - EPID L-2021-LLA-0074 ML21120A1182021-04-30030 April 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - On-Site Cooling System Sediment Disposal Approval Request - EPID L-2020-LLL-0031 ML21068A2842021-03-0404 March 2021 2021002 Inservice Inspection (ISI) Request for Information (RFI) ML20336A1852020-11-30030 November 2020 NRR E-mail Capture - Final - RAI - Columbia - One -Time Exemption from 10 CFR 73, App B, Sect VI, Subsection C.3.(l)(1) Regarding Annual Force-On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20325A0402020-11-19019 November 2020 NRR E-mail Capture - Draft - RAI - Columbia - One -Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force -On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20267A5162020-09-23023 September 2020 NRR E-mail Capture - Columbia Generating Station - Final - Request for Additional Information - Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-09 - EPID L-2020-LLR-0068 ML20245E2822020-08-31031 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20239A9702020-08-26026 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20149K4362020-05-26026 May 2020 NRR E-mail Capture - Formal RAIs for Columbia (COVID-19) QA Plan Change Surveillance, Request Response by Tuesday June 2, 2020 ML20112F4572020-04-21021 April 2020 NRR E-mail Capture - Official Release of NRC RAIs for Columbia Covid Exigent Due Friday April 24, 2020 ML20034E6082020-02-0303 February 2020 NRR E-mail Capture - RAI Formal Release Columbia TSTF 563 LAR, 30 Day Response Period Due March 3, 2020 ML20028E1512020-01-27027 January 2020 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000397/2020002) and Request for Information ML19267A1842019-09-24024 September 2019 Request for Information for Upcoming Open Phase Condition Inspection at Columbia Generating Station ML19232A2282019-08-20020 August 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia Exigent Amendment - One Electrical RAI, ML19183A4752019-07-0202 July 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia HVAC LAR L-2019-LLA-0034 ML18088A0152018-03-29029 March 2018 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans (05000397/2018010) and Request for ML17341B0272017-12-0707 December 2017 NRR E-mail Capture - RAI Associated with Columbia Amendment Request Revise Tech Spec 5.5.12 for Permanent Extension of Type a and Type C Containment Testing Frequencies for MF9469, EPID: L-2017-LLA-0197, ILRT, LLRT LAR - New RAI Response Da ML17292A0572017-10-18018 October 2017 NRR E-mail Capture - New RWCU RAI Due Date Now November 24, 2017 ML17249A6882017-09-0606 September 2017 NRR E-mail Capture - RAIs for Columbia Relief Request RAI (MF8925), 3ISI-19 ML17205A3152017-07-20020 July 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000397/2017004) and Request for Information ML17193A2192017-07-12012 July 2017 NRR E-mail Capture - Columbia RWCU LAR MF8318, Formal Release of RAIs ML17144A1702017-05-24024 May 2017 NRR E-mail Capture - NRC RAIs for Columbia Relief Request MF8922, 3ISI-16 ML17047A7492017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais ML17006A0922017-01-0404 January 2017 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML17006A0902017-01-0404 January 2017 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16356A1382016-12-21021 December 2016 NRR E-mail Capture - Columbia Mur LAR Evib RAIs Non - Proprietary Version - Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML16342C4322016-12-0707 December 2016 NRR E-mail Capture - Columbia Measurement Uncertainty Recapture Power Uprate LAR Rais: Human Performance: MF8060, Formal Release for Response on Monday January 9, 2017 ML16327A1842016-11-22022 November 2016 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16323A1192016-11-16016 November 2016 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML16218A3902016-08-0808 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt) ML16194A3702016-07-11011 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection 05000397/2016003 and Request for Information ML16069A3592016-03-0909 March 2016 NRR E-mail Capture - Second Round Rais: Columbia MF6042 LAR TSTF-425 ML16061A5542016-03-0101 March 2016 Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information ML16061A5662016-03-0101 March 2016 Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information ML15254A2572015-09-16016 September 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Reevaluations ML15215A0432015-08-18018 August 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations ML14262A3412014-09-24024 September 2014 Request for Additional Information, Round 2, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High ML14192B0312014-08-13013 August 2014 Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows ML14206A0112014-07-31031 July 2014 Request for Additional Information, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High 2024-01-10
[Table view] |
Text
OFFICIAL USE ONLY PROPRIIiTARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 13, 2014 Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (TAC NO. MF3055)
Dear Mr. Reddemann:
By letter dated October 31, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML13316A009), as supplemented by letter dated May 29, 2014 (ADAMS Accession No. ML14163A482), Energy Northwest submitted a license amendment request to revise Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the low pressure core spray and residual heat removal/low pressure coolant injection pump flows.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed requests for additional information (RAis) were provided to L. Williams of your staff on May 29, 2014, and a clarification call was held on June 12, 2014. Please provide a response to the RAis within 30 days of the date of this letter.
The NRC staff has determined that the RAis contain proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390. Proprietary information is indicated in the RAI text enclosed within brackets. Accordingly, the NRC staff has also prepared a non-proprietary, publicly available version of the RAis, which is provided in Enclosure 1. The proprietary version of the RAis is provided in Enclosure 2. to this letter contains Proprietary Information. When separated from Enclosure 2, this letter is DECONTROLLED.
OFFICIAL USE ONLY PROPRIIiTAR¥ INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov.
Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Non-Proprietary RAis
- 2. Proprietary RAis cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION
ENCLOSURE 1 REQUESTS FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 Proprietary information pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets.
OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION CHANGE TO EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 In a letter dated October 31, 2013 (Reference 1), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (CFR), Energy Northwest submitted a license amendment request to revise the Columbia Generating Station Technical Specification Surveillance Requirements 3.5.1.4 and 3.5.2.5 for the Low Pressure Core Spray (LPCS) and Low Pressure Coolant Injection (LPCI) pump flows. Energy Northwest is requested to provide a response to the following request for additional information (RAI) questions in order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review:
SCVB*RAI-1 Reference 2, Table 1, "Key Inputs for the Long-Term Containment Response":
The service water temperature input parameter is stated as 85 degrees Fahrenheit (°F) for first 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of loss-of-coolant accident (LOCA) and 90 °F thereafter. However, Reference 3 assumes service water temperature of 90 °F. Please provide justification for using a lower value of the service water temperature for the first 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of the LOCA transient.
SCVB-RAI-2 Reference 2, Section 2.1, under heading "Case B: Loss of offsite power- with delayed containment spray" states:
"During this time an operational restriction prohibits the activation of containment spray."
(a) Please describe the possible operational restrictions that would prevent the initiation of containment sprays.
(b) Ten minutes from the initiation of the reactor scram is the normally allowed operator action time for the activation of sprays. Please explain what time was used for the spray initiation for case B.
SCVB-RAI-3 Reference 2, Section 2.1, under heading "Case D: All ECCS equipment operating - RHR
[residual heat removal] heat exchanger failure". ((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
))
SCVB-RAI-4 Reference 2, Section 4.1.2; please describe the event "Inadvertent RHR Shutdown Cooling."
Please provide a further discussion of why it is not adversely affected by a reduction in the RHR flow rate.
SCVB-RAI-5 Reference 2, Section 4.1.3; the Final Safety Analysis Report (FSAR) K-value of the two RHR heat exchangers of 578 BTU/s-°F is based on service water temperature of 90°F, and [(
)) Please explain what are the parameters and their FSAR values and new values that resulted in the reduction of the heat exchanger K-value from 578 BTU/s-°F to [( ))
SCVB-RAI-6 Reference 2, Section 4.1.3; please describe the ((
)) from the FSAR ATWS [anticipated transient without scram] event analysis.
SCVB-RAI-7 Please describe the impact of the changes in the LPCS and LPCI flows on the containment wall temperature response analysis under LOCA and main steam line break (MSLB) accident.
SCVB-RAI-8 Please provide the following information for the NRC staff review:
(a) The value of the required net positive suction head (NPSH) (NPSHR) for the RHR and LPCS pumps while drawing water from the suppression pool.
(b) The basis for the NPSHR including the standard on which it is based. As an example, commonly for ECCS and residual heat removal system pumps it is based on the Hydraulic Institute {HI) standard according to which the NPSHR is equal to the available NPSH determined in a factory test at the pump design flow with a 3-percent drop in the total dynamic head.
(c) The uncertainty in the factory tested value of NPSHR based on the actual site conditions.
(d) The minimum NPSH available (NPSHA) in the proposed analysis at each pump inlet without crediting containment accident pressure, based on maximizing the suppression pool water temperature together with maximizing the suction strainer head loss and maximizing piping head loss.
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION (e) The minimum NPSH margin for each pump and its percentage based on NPSHR with uncertainty added.
REFERENCES
- 1. Javorik, Alex L., Energy Northwest letter to U.S. Nuclear Regulatory Commission, "Columbia Generating station. Docket no. 50-397 License Amendment Request for Change to Emergency Core Cooling Systems Surveillance Requirements," dated October 31, 2013 (ADAMS Accession No. ML13316A009).
- 2. GE Hitachi Nuclear Energy, NEDC-33813P, Technical Specification Change Support for RHRILPCI and LPCS Flow Rate Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations, Revision 2, September 2013 (Non-Proprietary version available at ADAMS Accession No. ML13316A010).
- 3. GE Nuclear Energy, NEDC-32141P, Power Uprate with Extended Load Line Limit Safety Analysis for WNP-2, June 1993.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION M. Reddemann If you have any questions regarding these RAis or will have difficulties meeting the agreed-upon schedule, please contact me at (301) 415-1081 or by email at andrea.george@nrc.gov.
Sincerely,
/RAJ Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Non-Proprietary RAis
- 2. Proprietary RAis cc w/encl 1: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorllpl4-1 Resource LPL4-1 r/f RidsNrrPMColumbia Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDeEmcb Resource RidsRgn4Mai1Center Resource RidsNrrDeEvib Resource DHoang, NRRJDE/EMCB RidsNrrDoriDpr Resource CSydnor, NRRIDE/EVIB ADAMS A ccess1on No.: p ropne . tary ML141928026 Non* p ropne
. tary ML141928031 OFFICE NRRIDORULPL4-1/PM NRR/DORULPL4-1/LA NRRIDSS/SCVB/BC NRR/DORULPL4-1/BC NRRIDORULPL4-1/PM NAME AGeorge J Bu r1<hardt RDennig ( JBettle for) MMarkley A George DATE 7/14/14 7/11/14 7/16/14 8/13/14 8/13/14 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION