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MONTHYEARML0816905942008-07-0808 July 2008 GL-08-001, Managing Gas Accumulation in Emergency Core Cooling Decay Heat Removal Project stage: Other ML0825405162008-09-25025 September 2008 Generic Letter 2008-01. Managing Gas Accumulation in Emergency Core Cooling Decay Heat Removal and Containment Spray Project stage: Other ML1023600532010-08-25025 August 2010 Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information (RAI) Project stage: RAI ML1104603882011-02-23023 February 2011 Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information Project stage: RAI 2008-09-25
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Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23156A2452023-06-0505 June 2023 Audit Summary and RAI-RCI - Revised Enclosure ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23095A0052023-04-0404 April 2023 002 Radiation Safety Baseline Inspection Information Request ML23086C0362023-03-27027 March 2023 Request for Additional Information Steam Generator Tube Inspection Report (03R31) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final ML22251A2902022-09-0808 September 2022 Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9 ML22234A0052022-08-30030 August 2022 SLRA - Feedback for RAI B2.1.7-4a to Duke - August 16, 2022 ML22157A0042022-06-0606 June 2022 10 CFR 50.59 Inspection Initial Information Request ML22157A0012022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a ML22154A2122022-06-0101 June 2022 SLRA - 2nd Round RAI B2.1.7-4b ML22124A1632022-05-0303 May 2022 (Public) Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22124A1612022-05-0303 May 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22122A0182022-04-28028 April 2022 Attachment: Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A0192022-04-28028 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A1312022-04-27027 April 2022 (Public) Oconee SLRA - 2nd Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 Redacted ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22113A0092022-04-20020 April 2022 Attachment: Oconee SLRA - Final RAI 3.1.2-1 ML22112A0072022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L ML22081A0062022-03-21021 March 2022 Attachment: Oconee SLRA - 2nd Round RAI B4.1-3 ML22081A0052022-03-21021 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3 ML22080A0772022-03-16016 March 2022 SLRA - RAI Set 4 (2nd Round Rais) ML22069A0012022-03-0808 March 2022 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 4 ML22063A4502022-03-0404 March 2022 Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump RA-22-0036, Responses to NRC Request for Additional Information Set 22022-02-14014 February 2022 Responses to NRC Request for Additional Information Set 2 ML22019A1042022-01-18018 January 2022 Attachment: Oconee SLRA - Final Requests for Additional Information - Set 3 ML22019A2442022-01-18018 January 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI) ML22019A1032022-01-18018 January 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3 ML22012A0422022-01-11011 January 2022 SLRA - Final Requests for Additional Information - Set 2 ML22010A1132022-01-0505 January 2022 SLRA - RCIs - Set 3 ML21333A0392021-11-29029 November 2021 RP Inspection Document Request ML21330A0192021-11-23023 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 2 ML21327A2782021-11-23023 November 2021 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Final RAIs (Set 1 and 2nd Round RAI B2.1.27-1a) ML21327A2792021-11-23023 November 2021 SLRA - Final Requests for Additional Information - Set 1 ML21327A2802021-11-23023 November 2021 SLRA - Final 2nd Round RAI - RAI B2.1.27-1a ML21313A2342021-11-0404 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 1 ML21274A0682021-10-0101 October 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria ML21273A0492021-09-30030 September 2021 Request for Additional Information Alternative Request (ON-RPI-OMN-28) to Use Code Case OMN-28 ML21271A5892021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Draft) ML21271A5902021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Final) ML21271A5882021-09-22022 September 2021 SLRA - Request for Additional Information B2.1.27-1 - Email from Angela Wu (NRC) to Steve Snider (Duke) ML21217A1912021-08-0505 August 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria ML21190A0172021-07-0808 July 2021 NRR E-mail Capture - Oconee Nuclear Station, Units 1, 2, and 3 - Request for Additional Information Alternative for ISI RPV Weld Examination from 10 to 20 Years (EPID-L-2021-LLR-0004) ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) 2023-07-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 2.5, 2010 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS," REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. MD7852, MD7853, AND MD7854)
Dear Mr. Baxter:
Generic Letter (GL) 2008-01, "Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal, And Containment Spray Systems," requests licensees to submit information to demonstrate that the emergency core cooling, decay heat removal, and containment spray systems are in compliance with the applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance.
The l\Iuclear Regulatory Commission (NRC) has concluded that additional information is required to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01. The NRC staff's RAI is enclosed. Unless otherwise agreed to, please submit all responses to these RAI questions within 30 days.
If you have any questions, please call me at 301-415-1345.
Si erelY~
hn Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
RAls cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION (RA!)
GENERIC LEITER (GL) 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3
- 1. Provide a discussion of the methods used to determine the volume of voids for both venting and ultrasonic testing. Discuss follow up actions such as trending the volume of voids.
- 2. In Reference 4, the licensee states that "Surveillance procedures have a low threshold for as found gas" and "The Corrective Action Program is entered if the vented volume exceeds a predetermined threshold." Clarify what the threshold volume is, how it was determined, and if it takes into account both water hammers and gas injection limits for pumps.
- 3. In Reference 4, the licensee states that "the consequences of the gas were evaluated to be acceptable." Please provide a brief description of the criteria and methodology used to determine acceptability.
- 4. In Reference 4, the licensee states that "Approximately 20 new vent valves will be needed on each unit." What is the status of these valves? Please justify any cancellations of installation.
- 5. In Reference 4, the licensee states that "Effective transport velocities when dynamic venting is credited (Froude number of > 0.55 for horizontal piping runs and> 1.0 for vertical piping runs)." Justify that dynamic venting under these conditions is able to remove voids.
- 6. Describe the monitoring of appropriate plant parameters during normal and shutdown operation, including reduced inventory and mid-loop operation, such as monitoring level indicators, including the level of the volume control tank and accumulator and piping pressures. Clarify how often the accumulator water make-ups and water make-up rates are monitored and trended as part of the Engineering Support Program. For reduced inventory and mid-loop operations justify that the water level is sufficient to prevent vortexing due to suction from the residual heat removal system.
- 7. Training was not identified in the GL (Reference 3) but is considered to be a necessary part of applying procedures and other activities when addressing the issues identified in GL. 2008-01. Provide a brief description of training.
-2 REFERENCES
- 1. Ruland, William H., "Preliminary Assessment of Responses to Generic Letter 2008-01,
'Managing Gas Accumulation in emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,' and Future NRC Staff Review Plans," NRC letter to James H. Riley, Nuclear Energy Institute, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091390637), May 28, 2009.Riley, James H., "Generic Letter (GL) 2008-01, 'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems' Evaluation and 3 Month Response Template," Letter to Administrative Points of Contact from Director, Engineering, Nuclear Generation Division, Nuclear Energy Institute, Enclosure 2, "Generic Letter 2008-01 Response Guidance," lVIarch 20, 2008.
- 2. Case, Michael J., "NRC Generic Letter 2008-01: Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," Letter from Director, Division of Policy and Rulemaking, Office of Nuclear Regulation, NRC, January 11, 2008 (ADAMS Accession No. ML072910759).
- 3. Harrall, T., "Duke Energy Carolinas, LLC (Duke); Oconee Nuclear Station, Units 1, 2 & 3, Docket Nos. 50-269, 50-270, 50-287; McGuire Nuclear Station, Units 1 & 2, Docket Nos.
50-369,50-370; Catawba Nuclear Station, Units 1 & 2, Docket Nos. 50-413, 50-414; Generic Letter 2008-01, 9-Month Response," Letter to Document Control Desk, NRC, from Vice President, Plant Support, Duke Energy Carolinas, LLC, October 13, 2008 (ADAMS Accession No. ML082900490).
- 4. Morris, J., "Duke Energy Carolinas, LLC (Duke); Catawba Nuclear Station - Unit 2; Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 (10CFR50.54f)," Letter to Document Control Desk, NRC, from Vice President, Catawba Nuclear Site, Duke Energy Carolinas, LLC July 15, 2009 (ADAMS Accession No. ML092010132).
- 5. Warren C. Lyon, U.S. Nuclear Regulatory Commission, "Revision 2 to NRC Staff Criteria for Gas Movement in Suction Lines and Pump Response to Gas," March 26, 2009 (ADAMS Accession No. ML090900136).
August 25, 2010 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB~IECT: OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS," REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. MD7852, MD7853, AND MD7854)
Dear Mr. Baxter:
Generic Letter (GL) 2008-01, "Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal, And Containment Spray Systems," requests licensees to submit information to demonstrate that the emergency core cooling, decay heat removal, and containment spray systems are in compliance with the applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance.
The Nuclear Regulatory Commission (NRC) has concluded that additional information is required to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable desjgn, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01. The NRC staff's RAI is enclosed. Unless otherwise agreed to, please submit all responses to these RAI questions within 30 days.
If you have any questions, please call me at 301-415-1345.
Sincerely, IRA!
John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
RAls cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLlI-1 R/F RidsNrrDorlLp2-1 Resource RidsSrxbReasource RidsAcrsAcnw_MailCtr Resource RidsNrrLAMOBrien Resource (hard copy) RidsRgn2MailCenter Resource RidsNrrDorlDpr Resource RidsNrrPMOconee Resource (hard copy)
ADAMS Accession No. ML102360053 'Bv M O ae erno ld OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA NRRlSRXB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME JStang MO'Brien AUlses' GKulesa JSlang DATE 08/24/10 08/24/10 07/16/10 08/25/10 08/25/10 OFFICIAL RECORD COpy