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MONTHYEARML1023006412010-08-16016 August 2010 10 CFR 50.55a Request Number RR-12, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot Leg Nozzle to Safe End Dissimilar Metal Welds Project stage: Request ML1026500132010-09-21021 September 2010 Acceptance Review E-mail, Relief Request RR-12, from Requirements of ASME Code Case N-722 Visual Examination of Reactor Vessel Hot-Leg Nozzle to Safe End Dissimilar Metal Welds for 4th 10-Year Inservice Inspection Interval (ME4541) Project stage: Acceptance Review ML1027801882010-10-0404 October 2010 Email, Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541) Project stage: Draft RAI ML1027801902010-10-0404 October 2010 Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541) Project stage: Draft RAI ML1028600872010-10-25025 October 2010 Request for Additional Information, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval Project stage: RAI ML1029101312010-10-25025 October 2010 Request for Withholding Information from Public Disclosure, 7/30/10 Affidavit Executed by J. Gresham, Westinghouse Project stage: Withholding Request Acceptance LIC-10-0095, Response to Request for Additional Information (RAI) Regarding Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle to Safe End Welds2010-11-0404 November 2010 Response to Request for Additional Information (RAI) Regarding Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle to Safe End Welds Project stage: Response to RAI ML1102001932011-01-14014 January 2011 Withdrawal of Response to Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds Project stage: Withdrawal ML1104705872011-02-16016 February 2011 Request for Additional Information LAR to Revise Technical Specification to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve Project stage: RAI ML1104705882011-02-16016 February 2011 Request for Additional Information Project stage: RAI ML1105404412011-02-23023 February 2011 Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval Project stage: RAI ML1105404492011-02-23023 February 2011 Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval Project stage: RAI ML1106102172011-03-0303 March 2011 Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval Project stage: RAI LIC-11-0016, Response to Second NRC Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds2011-03-0404 March 2011 Response to Second NRC Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds Project stage: Request ML1109103272011-04-0505 April 2011 Verbal Authorization, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot-Leg Nozzle-to-Safe-End Dissimilar Metal Welds, 4th 10-Year Inservice Inspection Interval Project stage: Other ML1108309472011-05-17017 May 2011 Request for Withholding Information from Public Disclosure, Affidavit Dated 7/30/10, Executed by J. Gresham, Westinghouse, Report LTR-PAFM-10-123-P, Revision 0 Project stage: Withholding Request Acceptance ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval Project stage: Other LIC-12-0004, Delay 2012 Refueling Outage and Extend In-service Inspection (ISI) and In-service Test (IST) Intervals2012-01-17017 January 2012 Delay 2012 Refueling Outage and Extend In-service Inspection (ISI) and In-service Test (IST) Intervals Project stage: Other 2011-02-16
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Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 – NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 – Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, SHPO; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commissions Analysis of Omaha Public Power Districts Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
[Table view] Category:Proprietary Information Review
MONTHYEARML17039A6552017-03-0303 March 2017 Request for Withholding Information from Public Disclosure - 12/13/16 Affidavit Executed by G. Elliott, Areva Np; Calculation FC08513; Exemption Request to Reduce Emergency Planning Requirements for Permanently Defueled Condition ML16144A3632016-05-25025 May 2016 Request for Withholding Information from Public Disclosure, 6/1/15 and 6/17/15 Affidavits Executed by J. Gresham, Westinghouse Electric Company LLC, PWROG-14082-P, Revision 0 and PWROG-15030-P, Revision 0 ML14122A2452014-05-22022 May 2014 Request for Withholding Information from Public Disclosure, 3/26/13 Affidavit Executed by C. M. Molnar, Westinghouse, Re.: LTR-RAM-II-10-046, Rev. 3 ML14051A0902014-03-10010 March 2014 Request for Withholding Information from Public Disclosure - 7/23/13 Affidavit Executed by J. Gresham, Westinghouse Regarding WCAP-17262-P, Revision 1 ML14036A0832014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 3/14/12 Affidavit Executed by J. A. Gresham, Westinghouse, Re.: Compact Containing Fire Dynamic Simulator Input ML14036A0682014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 12/9/11 Affidavit Executed by C. M. Molnar, Westinghouse, LTR-RAM-II-10-046, Revision 1, Dated 4/22/2011 ML1108309472011-05-17017 May 2011 Request for Withholding Information from Public Disclosure, Affidavit Dated 7/30/10, Executed by J. Gresham, Westinghouse, Report LTR-PAFM-10-123-P, Revision 0 ML1029101312010-10-25025 October 2010 Request for Withholding Information from Public Disclosure, 7/30/10 Affidavit Executed by J. Gresham, Westinghouse ML0733903722007-12-18018 December 2007 Request for Withholding Information from Public Disclosure Containment Spray System Actuation Logic (Tac No. MD6204) ML0702200092007-02-23023 February 2007 Withholding Letter License Amendment Request to Support Use of Areva Realistic Large Break Loss-of-Coolant Accident Methodology ML0633901582006-12-11011 December 2006 Request for Withholding Information from Public Disclosure Engineering Information Record 51-9004433-01, FCS RSG - Afas Verification - RAI Responses ML0625404872006-10-0303 October 2006 Request for Withholding Information from Public Disclosure ML0618104582006-06-28028 June 2006 Request for Withholding Information from Public Disclosure, TAC MC8946 ML0534703412005-12-0707 December 2005 12/7/05 Fort Calhoun Station, Unit 1 - Request for Withholding Information from Public Disclosure (Tac. MC8946) ML0513801842005-05-17017 May 2005 Withholding from Public Disclosure, Framatome Anp Proprietary Drawings, MC3220 ML0506902422005-03-0909 March 2005 Westinghouse, (Vendor) Letter to J. Gresham Request for Withholding Information from Public Disclosure for Ft. Calhoun Station #1 (CAW-05-1962) ML0506703562005-03-0303 March 2005 Withholding from Public Disclosure, Information in the Draft Presentation Materials to Be Used at Meeting with NRC Staff on March 3, 2005, MC6024 ML0504105342005-02-0808 February 2005 Withholding from Public Disclosure, Calculation Note Number CN-CI-02-74, Revision 2, MC0196 ML0501803112005-01-19019 January 2005 1/19/05, Fort Calhoun Station, Unit 1, Withholding from Public Disclosure, Information in the Final Presentation Materials Used at a Meeting with the NRC Staff on January 10, 2005 ML0500602432005-01-0606 January 2005 1/6/05, Fort Calhoun - Request for Withholding Information from Public Disclosure - Requesting That Draft Presentation Materials to Be Used at a Meeting with the Staff Be Withheld from the Public ML0405405352004-02-18018 February 2004 Framatome, Request for Withholding Information from Pubic Disclosure, Report 54-PQ-189-01 and Procedure Number 54-ISI-189-00 ML0328703942003-10-14014 October 2003 Withholding from Public Disclosure, Calculation Number FC-6896-P, Secondary Calorimetric Uncertainty Analysis 2017-03-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 May 17, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
SUBJECT:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE FOR FORT CALHOUN STATION, UNIT NO.1 (TAC NO. ME4541)
Dear Mr. Bannister:
By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102300641). Omaha Public Power District (the licensee) submitted an affidavit dated July 30, 2010, executed by J. A. Gresham, Westinghouse Electric Company LLC (Westinghouse), requesting that the information contained in the following document be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 2, Section 2.390:
LTR-PAFM-10-123-P, Revision 0, "Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds," July 2010 A nonproprietary copy of this document, designated as LTR-PAFM-10-123-NP, has been placed in the Nuclear Regulatory Commission's (NRC's) Public Document Room and added to the ADAMS Public Electronic Reading Room under ADAMS Accession No. ML102300642.
The licensee stated in its affidavit and submittal that the submitted information should be considered exempt from mandatory public disclosure for the following reasons:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
D. Bannister -2 We have reviewed your application and the material in accordance with the requirements of 10 CFR 2.390 and, on the basis of the statements in the affidavit, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure.
Therefore, LTR-PAFM-10-123-P, Revision 0, "Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds," July 2010, marked as proprietary, will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Sincerely, Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: J. A. Gresham, Manager Regulatory Compliance and Plant Licensing Westinghouse Electric Company LLC Nuclear Services P.O. Box 355 Pittsburgh, PA 15230-0355 Additional distribution via Listserv
D. Bannister -2 We have reviewed your application and the material in accordance with the requirements of 10 CFR 2.390 and, on the basis of the statements in the affidavit, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure.
Therefore, LTR-PAFM-10-123-P, Revision 0, "Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds," July 2010, marked as proprietary, will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wi Ikins@nrc.gov.
Sincerely, IRAI Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: J. A Gresham, Manager Regulatory Compliance and Plant Licensing Westinghouse Electric Company LLC Nuclear Services P.O. Box 355 Pittsburgh, PA 15230-0355 Additional distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDciCpnb Resource RidsNrrPMFortCalhoun Resource LPLIV r/f RidsNrrDorlLpl4 Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurkhardt Resource RidsRgn4MailCenter Resource NRR/DCI/CPNB/BC NRR/LPL4/BC NRR/LPL4/PM LWllkins JBurkhardt TLupold Markley LWllkins 3/25/11 3/25/11 4/5111 5/17/11 5/17/11