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| | issue date = 12/19/2011 | | | issue date = 12/19/2011 |
| | title = Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration | | | title = Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration |
| | author name = Wiebe J S | | | author name = Wiebe J |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000254, 05000265 | | | docket = 05000254, 05000265 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| | ==SUBJECT:== |
| | QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613) |
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. | | |
| By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information. | | By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information. |
| The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter. 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. | | The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter. |
| M. Pacilio If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. | | 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. |
| Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND DOCKET NOS. 50-254 AND In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML 111590206, ML 112650386, ML 113070426, and ML 113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A. | | |
| Provide a complete listing of computer codes used in the implementation of 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications. During the conference call on November 18, 2011, your staff stated that you were evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. | | M. Pacilio -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. |
| Describe how you are establishing this threshold. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation. | | Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111590206, ML112650386, ML113070426, and ML113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: |
| | : 1. CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A. |
| | Provide a complete listing of computer codes used in the implementation of CENPD 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications. |
| | : 2. During the conference call on November 18, 2011, your staff stated that you were re evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. Describe how you are establishing this threshold. |
| | : 3. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation. |
| Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal. | | Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal. |
| M. Pacilio -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. | | |
| Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via LPL3-2 RidsNrrDorlLpl3-2 RidsNrrLASRohrer RidsAcrsAcnw_MailCTR RidsNrrPMQuadCities Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssSrxb Resource ADAMS Accession No. ML 113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC NAME JWiebe SRohrer TUlses JZimmerman DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy}}
| | M. Pacilio - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. |
| | Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsOgcRp Resource LPL3-2 RlF RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrLASRohrer Resource RidsNrrDssSrxb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMQuadCities Resource ADAMS Accession No. ML113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC SRohrer TUlses JZimmerman NAME JWiebe DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy}} |
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Category:Request for Additional Information (RAI)
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R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17353A9492018-01-0909 January 2018 Supplemental Information Needed for Acceptance of License Amendment Request to Revise Technical Specification Requirements for Secondary Containment ML17355A0112017-12-20020 December 2017 NRR E-mail Capture - Request for Additional Information Regarding Relief Request I5R-11, Revision 2 ML17333A0822017-11-28028 November 2017 17 Quad Cities Nuclear Plant, Unit 2 - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000265/2018001 (DRS-M.Domke) ML17262A0892017-09-19019 September 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies (RS-17-051) ML17198A2292017-07-17017 July 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Set No. 2 (Cac. 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[Table view] Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - 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Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station 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 ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 2024-02-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613)
Dear Mr. Pacilio:
By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information.
The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter.
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.
M. Pacilio -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.
Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111590206, ML112650386, ML113070426, and ML113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review:
- 1. CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A.
Provide a complete listing of computer codes used in the implementation of CENPD 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications.
- 2. During the conference call on November 18, 2011, your staff stated that you were re evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. Describe how you are establishing this threshold.
- 3. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation.
Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal.
M. Pacilio - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.
Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource LPL3-2 RlF RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrLASRohrer Resource RidsNrrDssSrxb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMQuadCities Resource ADAMS Accession No. ML113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC SRohrer TUlses JZimmerman NAME JWiebe DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy