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MONTHYEARML11236A1342011-07-31031 July 2011 Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 Project stage: Request L-2011-409, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts2011-10-14014 October 2011 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts Project stage: Request ML1125602172011-10-25025 October 2011 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance ML1206203892012-03-20020 March 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-2012-132, Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References2012-03-31031 March 2012 Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References Project stage: Supplement L-PI-12-038, Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.2012-05-0303 May 2012 Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389. Project stage: Other ML12139A1982012-05-16016 May 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME69851) Project stage: Response to RAI ML12215A2522012-08-0707 August 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-12-066, Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure2012-08-27027 August 2012 Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML12249A0692012-09-0404 September 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13011A3162013-01-22022 January 2013 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-13-002, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-02-0808 February 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13197A3972013-06-25025 June 2013 NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI Project stage: Draft Other L-PI-13-067, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-07-17017 July 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13241A3832013-08-29029 August 2013 Issuance of Amendments Spent Fuel Pool Criticality Changes Project stage: Approval 2012-08-27
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Category:Request for Additional Information (RAI)
MONTHYEARML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23096A3082023-04-0707 April 2023 Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 ML23053A1432023-02-22022 February 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22145A4152022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21147A5232021-06-0303 June 2021 Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21131A0752021-05-10010 May 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004 ML21099A0972021-04-0909 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012 ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant ML21033A6112021-02-0101 February 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010 ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 ML20133K0692020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20077K6242020-04-13013 April 2020 License Amendment Request - Request for Additional Information ML20052F4102020-02-21021 February 2020 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18264A1912018-09-19019 September 2018 NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg) ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18169A4202018-06-25025 June 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18025C0152018-01-24024 January 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop) ML17277B3332017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) ML17235A9982017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change ML17221A3892017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17219A0762017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17038A5132017-02-0707 February 2017 NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01 ML17018A4272017-01-18018 January 2017 NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action ML16326A3532016-11-18018 November 2016 NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) ML16189A2052016-07-0707 July 2016 Notification of NRC Inspection and Request for Information ML16113A1612016-04-21021 April 2016 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2 ML16075A0802016-03-15015 March 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 Request for Additional Information Related to License Amendment Request to Adopt TSTF-523, GL 2008-01, Managing Gas Accumulation ML16008A1092016-01-0808 January 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Requests for Additional Information (Afpb) License Amendment Request to Adopt NFPA 805 ML15195A6562015-07-10010 July 2015 Prairie Island Notification of NRC Inspection and Request for Information ML15149A1662015-05-28028 May 2015 Plan - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15121A6512015-04-29029 April 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen) 2023-09-05
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MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985) Dear Mr. Molden: By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML 12139A 198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
J. Molden -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. Sincerely, Docket Nos. 50-282 and 50-306 Enclosure: Request for Additional Information cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION (RAI) PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML 12139A 198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review. This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response"). Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading. A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading. NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis. RAI-SRXB-2: The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G. Enclosure
-2 The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh What is the basis for 4 percent 235U assumption? What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis? RAI-SRX8-4 (Axial blankets): Show that neglecting the hollow annular pellets in the blankets is always conservative. RAI-SRX8-5 (Axial Provide the analysis results that support the selection of the axial burnup profiles used in analysis (e.g., k-effective results and corresponding "shape depletion RAI-SRX8-6 (Operation with control In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design cases and the "Rodded" RAI-SRX8-7 (Criticality code validation fission product The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance.
J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 Enclosure: Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 RtF RidsNrrPMPrairielsland Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsNrrDorlDpr Resource TNakanishi, NRR KWood, NRR ADAMS Accession Number: ML 12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A) BTully/SRohrer IfI SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy