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| | number = ML12236A243 | | | number = ML12236A243 |
| | issue date = 08/31/2012 | | | issue date = 08/31/2012 |
| | title = Fort Calhoun Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation (TAC ME8038) | | | title = Request for Additional Information Regarding License Amendment Request to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Bannister D J | | | addressee name = Bannister D |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
| | license number = DPR-040 | | | license number = DPR-040 |
| | contact person = Wilkins L E | | | contact person = Wilkins L |
| | case reference number = TAC ME8038 | | | case reference number = TAC ME8038 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME8038 | | | project = TAC:ME8038 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 August 31, 2012 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT NO.1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038) Dear Mr. Bannister: By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML 12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems." The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail on July 13, 2012. During a teleconference on August 14, 2012, Ms. Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter. If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. 2 1Y , Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 Enclosure: As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL LICENSE AMENDMENT REQUEST FOR FORT CALHOUN STATION TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO.1 DOCKET NO. 50-285 By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML 12046A838), Omaha Public Power District (OPPD, the licensee) requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system (RPS) actuation circuits in Technical Specification (TS) 2.15, "Instrumentation and Control Systems." The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and has determined that the following information is needed in order to complete its review. 1. Please provide technical information and manufacturer data for the RPS M2 contactor. 2. The current TS for FCS identifies the following operating modes: a) Power Operation Condition (Operating Mode b) Hot Standby Condition (Operating Mode c) Hot Shutdown Condition (Operating Mode d) Cold Shutdown Condition (Operating Mode e) Refueling Shutdown Condition (Operating Mode To support the NRC staff review, please provide the following information: Please explain how the FCS Operating Modes line up with the Operating Modes in NURG-1432, "Standard Technical Specifications [STSs] Combustion Engineering Plants." In particular, please explain how FCS Operating Mode 2 compares to NUREG-1432, LCO 3.3.3, "Reactor Protective System (RPS) Logic and Trip Initiation (Analog)." License Amendment Request (LAR), Enclosure 2, Section 3, "Applicability," describes the applicability for when the RPS logic and trip initiation channels are required to be operable. Please identify the FCS operating modes when the proposed LCO 2.15.2 is applicable. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 31, 2012 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 |
| -2 LCD 2.15.2 states that it is applicable for FCS Operating Modes 1 and 2; and when reactor coolant temperature (Tcold) is greater than 210° For FCS Operating Mode 4 with more than one control element assembly (CEA) rod capable of being withdrawn and RCS boron concentration less than REFUELING BORON CONCENTRATION. Please clarify the operating modes applicable for LCD 2.15.2 using the definitions provided in FCS TS. One of the applicable modes identified in the proposed LCD 2.15.2 is "when reactor coolant temperature (Tcold) is greater than 2100 F." Please explain if this description corresponds to FCS operating Mode 3. NUREG-1432, STSs, identifies the applicability for LCD 3.3.3 to be STS operating Modes 1 and 2; or Modes 3, 4, and 5 with any reactor trip circuit breakers closed and any CEAs capable of being withdrawn. Please clarify how the operating modes for the proposed LCD 2.15.2 compare with this description. LAR, Enclosure, Section 2.0, states that the RPS manual trip functional unit included in Table 2-2, "Instrument Operatillg Requirements for Reactor Protective System," will be removed, and that this function will be included in the proposed LCD 2.15.2. The LAR Enclosure Section 3.0, Technical Evaluation, does not state that the manual function would be moved to the new LCD 2.15.2, instead this section states that requiring restoration of the inoperable channel is consistent with the current TS requirement contained in TS Table 2-2, item 1. Please clarify. Current TS requirement in LCD 2.15 (2) states that if a channel of a particular system (Table 2-2) is inoperable, this channel must be placed in the tripped position. Further, if the inoperable channel has not been restored to operable status after 48 hours, the reactor should be placed in a Hot Shutdown Condition (mode 3) within the following 12 hours based on this information, it is not clear why the proposed LCD 2.15.2 (3) is requiring that with one inoperable RPS manual trip channel to restore the status to OPERABLE prior to entering Mode 2 from Mode 3. Please clarify. The LAR Enclosure 2, Section 3.0, Technical Evaluation, states that the current TS 2.15(5), Alternate Shutdown and Auxiliary Feedwater Panel, will be incorporated into a new LCD 2.15.3 with the list of components being included into a new Table 2-6. Further, Section 3 states that no changes are proposed for the requirements, other than formatting. Please clarify the relationship between required actions 1 and 2 in the proposed TS 2.1.5.3. | | |
| August 31,2012 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT NO.1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038) Dear Mr. Bannister: By letter dated February 10, 2012 (Agencywide Documents Access and ManC\gement System Accession No. ML 12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems." The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail onJuly13.2012.DuringateleconferenceonAugust14.2012.Ms. Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter. If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov. Sincerely, IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 Enclosure: As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun RAlvarado.. NRR/DEIEICB LPLIV Reading RidsNrrDorlDpr Resource Resource KBucholtz, RidsAcrsAcnw_MailCTR RidsNrrLAJBurkhardt RidsOgcRp Resource NRR/DSS/STSB Resource Resource RidsRgn4MailCenter RidsNrrDeEicb Resource Resource ADAMS Accession No ML*via memo dated I OFFICE NRRlDORULPL4/PM NRRlDORUlPl4/LA NRRlDE/EICB !BC NRRlDORUlPl4/BC NRRlDORUlPl4/PM JBurkhardt NAME LWilkins (BClayton for) JThorpe* MMarkley LWilkins DATE 8/30/12 8/28/12 6/21/12 8/31/12 8/31/12 OFFICIAL RECORD COpy | | ==SUBJECT:== |
| }} | | FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038) |
| | |
| | ==Dear Mr. Bannister:== |
| | |
| | By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems." |
| | The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. |
| | A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail on July 13, 2012. During a teleconference on August 14, 2012, Ms. |
| | Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter. |
| | If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. |
| | 2 1Y Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR FORT CALHOUN STATION TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO.1 DOCKET NO. 50-285 By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML12046A838), Omaha Public Power District (OPPD, the licensee) requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system (RPS) actuation circuits in Technical Specification (TS) 2.15, "Instrumentation and Control Systems." |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and has determined that the following information is needed in order to complete its review. |
| | : 1. Please provide technical information and manufacturer data for the RPS M2 contactor. |
| | : 2. The current TS for FCS identifies the following operating modes: |
| | a) Power Operation Condition (Operating Mode 1) b) Hot Standby Condition (Operating Mode 2) c) Hot Shutdown Condition (Operating Mode 3) d) Cold Shutdown Condition (Operating Mode 4) e) Refueling Shutdown Condition (Operating Mode 5) |
| | To support the NRC staff review, please provide the following information: |
| | a) Please explain how the FCS Operating Modes line up with the Operating Modes in NURG-1432, "Standard Technical Specifications [STSs] Combustion Engineering Plants." In particular, please explain how FCS Operating Mode 2 compares to NUREG-1432, LCO 3.3.3, "Reactor Protective System (RPS) Logic and Trip Initiation (Analog)." |
| | b) License Amendment Request (LAR), Enclosure 2, Section 3, "Applicability," describes the applicability for when the RPS logic and trip initiation channels are required to be operable. Please identify the FCS operating modes when the proposed LCO 2.15.2 is applicable. |
| | |
| | -2 |
| | : 3. LCD 2.15.2 states that it is applicable for FCS Operating Modes 1 and 2; and when reactor coolant temperature (Tcold) is greater than 210° For FCS Operating Mode 4 with more than one control element assembly (CEA) rod capable of being withdrawn and RCS boron concentration less than REFUELING BORON CONCENTRATION. |
| | a) Please clarify the operating modes applicable for LCD 2.15.2 using the definitions provided in FCS TS. |
| | b) One of the applicable modes identified in the proposed LCD 2.15.2 is "when reactor coolant temperature (Tcold) is greater than 210 F." Please explain if this description 0 |
| | corresponds to FCS operating Mode 3. |
| | c) NUREG-1432, STSs, identifies the applicability for LCD 3.3.3 to be STS operating Modes 1 and 2; or Modes 3, 4, and 5 with any reactor trip circuit breakers closed and any CEAs capable of being withdrawn. Please clarify how the operating modes for the proposed LCD 2.15.2 compare with this description. |
| | : 4. LAR, Enclosure, Section 2.0, states that the RPS manual trip functional unit included in Table 2-2, "Instrument Operatillg Requirements for Reactor Protective System," will be removed, and that this function will be included in the proposed LCD 2.15.2. The LAR Enclosure Section 3.0, Technical Evaluation, does not state that the manual function would be moved to the new LCD 2.15.2, instead this section states that requiring restoration of the inoperable channel is consistent with the current TS requirement contained in TS Table 2-2, item 1. Please clarify. |
| | : 5. Current TS requirement in LCD 2.15 (2) states that if a channel of a particular system (Table 2-2) is inoperable, this channel must be placed in the tripped position. Further, if the inoperable channel has not been restored to operable status after 48 hours, the reactor should be placed in a Hot Shutdown Condition (mode 3) within the following 12 hours based on this information, it is not clear why the proposed LCD 2.15.2 (3) is requiring that with one inoperable RPS manual trip channel to restore the status to OPERABLE prior to entering Mode 2 from Mode 3. Please clarify. |
| | : 6. The LAR Enclosure 2, Section 3.0, Technical Evaluation, states that the current TS 2.15(5), Alternate Shutdown and Auxiliary Feedwater Panel, will be incorporated into a new LCD 2.15.3 with the list of components being included into a new Table 2-6. Further, Section 3 states that no changes are proposed for the requirements, other than formatting. |
| | Please clarify the relationship between required actions 1 and 2 in the proposed TS 2.1.5.3. |
| | |
| | August 31,2012 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:== |
| | FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038) |
| | |
| | ==Dear Mr. Bannister:== |
| | |
| | By letter dated February 10, 2012 (Agencywide Documents Access and ManC\gement System Accession No. ML12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems." |
| | The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. |
| | A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail onJuly13.2012.DuringateleconferenceonAugust14.2012.Ms. |
| | Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter. |
| | If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov. |
| | Sincerely, IRA! |
| | Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun RAlvarado.. NRR/DEIEICB LPLIV Reading RidsNrrDorlDpr Resource Resource KBucholtz, RidsAcrsAcnw_MailCTR RidsNrrLAJBurkhardt RidsOgcRp Resource NRR/DSS/STSB Resource Resource RidsRgn4MailCenter RidsNrrDeEicb Resource Resource ADAMS Accession No ML12236A243 *via memo dated I OFFICE NRRlDORULPL4/PM NRRlDORUlPl4/LA NRRlDE/EICB !BC NRRlDORUlPl4/BC NRRlDORUlPl4/PM JBurkhardt NAME LWilkins (BClayton for) JThorpe* MMarkley LWilkins DATE 8/30/12 8/28/12 6/21/12 8/31/12 8/31/12 OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
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MONTHYEARLIC-12-0006, License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)2012-02-10010 February 2012
License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)
Project stage: Request
ML1208303282012-03-23023 March 2012
Email License Amendment Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
Project stage: Other
ML12198A2342012-07-13013 July 2012
Email, Draft Requests for Additional Information, License Amendment Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
Project stage: Draft RAI
ML12236A2432012-08-31031 August 2012
Request for Additional Information Regarding License Amendment Request to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation
Project stage: RAI
LIC-12-0136, Responses to Request for Additional Information License Amendment Request to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation2012-10-0101 October 2012
Responses to Request for Additional Information License Amendment Request to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation
Project stage: Response to RAI
ML12306A3572012-10-31031 October 2012
Email, Draft Request for Additional Information, Round 2, Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
Project stage: Draft RAI
LIC-12-0178, Responses to Second Request for Additional Information License Amendment Request for Fort Calhoun Station to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation2013-01-22022 January 2013
Responses to Second Request for Additional Information License Amendment Request for Fort Calhoun Station to Establish the Reactor Protective System Actuation Circuits Limiting Condition for Operation
Project stage: Request
ML13043A6612013-02-28028 February 2013
Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
Project stage: Approval
2012-03-23
[Table View] |
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Category:Letter
MONTHYEARLIC-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
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)
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Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256)
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
ML23234A2392023-08-18018 August 2023
Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf
ML23234A2412023-08-18018 August 2023
Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request
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
IR 05000285/20230022023-06-0505 June 2023
NRC Inspection Report 05000285/2023002
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
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 Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285)
IR 05000285/20220042022-09-14014 September 2022
NRC Inspection Report 05000285/2022004
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
ML22138A1242022-08-0303 August 2022
Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106
ML22101A1092022-08-0303 August 2022
Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106
ML22138A1212022-08-0303 August 2022
Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106
2024-09-18
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24243A1042024-09-12012 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)
ML24180A2062024-07-0808 July 2024
Phase 1 Final Status Survey Reports Request for Additional Information
ML23151A0042023-06-0606 June 2023
Second Set RAIs Rev 4
ML22357A0672022-12-30030 December 2022
Enclosure RAI Re Approval of License Termination Plan
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
ML20111A2162020-05-20020 May 2020
Revised PSDAR Request for Additional Information - RAI
ML19241A1812019-08-21021 August 2019
Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status
ML18067A1432018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to M. J. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI)
ML17236A3462017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567)
ML17236A3442017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)
ML17234A4692017-08-22022 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831)
ML17194A9732017-07-13013 July 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
ML17112A0362017-04-20020 April 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR
ML17090A3942017-03-31031 March 2017
NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437)
ML17082A0022017-03-22022 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption
ML17081A0192017-03-21021 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption
ML17067A3862017-03-15015 March 2017
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17033A9692017-02-0202 February 2017
NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment
ML16263A0492016-09-20020 September 2016
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML16174A1502016-06-27027 June 2016
Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML16146A1782016-05-27027 May 2016
Request for Additional Information, Round 2, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16106A0232016-04-29029 April 2016
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML16104A2872016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML16048A1542016-02-23023 February 2016
Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16048A0242016-02-23023 February 2016
Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML15343A1082015-12-15015 December 2015
Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML15323A0362015-11-24024 November 2015
Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval
ML15194A2722015-07-14014 July 2015
Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML15057A0152015-03-0303 March 2015
Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review
ML15043A0612015-02-25025 February 2015
Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14353A0512014-12-22022 December 2014
Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra
ML14259A3652014-09-24024 September 2014
Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14195A0862014-07-16016 July 2014
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
ML13317A5832013-11-25025 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13290A0022013-10-0909 October 2013
Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks
ML13282A5362013-10-0909 October 2013
Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13270A2872013-09-27027 September 2013
Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13261A2122013-09-18018 September 2013
Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13233A2482013-08-26026 August 2013
Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7)
ML13235A1682013-08-23023 August 2013
Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
ML13234A4352013-08-22022 August 2013
Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source
ML13226A1222013-08-14014 August 2013
Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13212A0092013-07-30030 July 2013
Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source
ML13205A1252013-07-24024 July 2013
Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact
ML13205A0182013-07-23023 July 2013
Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact
ML13144A4822013-05-23023 May 2013
Request for Additional Information Email, Decommissioning Funding Status Report
ML13100A1752013-04-10010 April 2013
Request for Additional Information Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup
ML13086A4732013-03-27027 March 2013
Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML13120A0842013-03-22022 March 2013
Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660)
2024-09-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 31, 2012 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:
FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038)
Dear Mr. Bannister:
By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems."
The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review.
A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail on July 13, 2012. During a teleconference on August 14, 2012, Ms.
Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
2 1Y Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR FORT CALHOUN STATION TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO.1 DOCKET NO. 50-285 By letter dated February 10, 2012 (Agencywide Documents Access and Management System Accession No. ML12046A838), Omaha Public Power District (OPPD, the licensee) requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system (RPS) actuation circuits in Technical Specification (TS) 2.15, "Instrumentation and Control Systems."
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and has determined that the following information is needed in order to complete its review.
- 1. Please provide technical information and manufacturer data for the RPS M2 contactor.
- 2. The current TS for FCS identifies the following operating modes:
a) Power Operation Condition (Operating Mode 1) b) Hot Standby Condition (Operating Mode 2) c) Hot Shutdown Condition (Operating Mode 3) d) Cold Shutdown Condition (Operating Mode 4) e) Refueling Shutdown Condition (Operating Mode 5)
To support the NRC staff review, please provide the following information:
a) Please explain how the FCS Operating Modes line up with the Operating Modes in NURG-1432, "Standard Technical Specifications [STSs] Combustion Engineering Plants." In particular, please explain how FCS Operating Mode 2 compares to NUREG-1432, LCO 3.3.3, "Reactor Protective System (RPS) Logic and Trip Initiation (Analog)."
b) License Amendment Request (LAR), Enclosure 2, Section 3, "Applicability," describes the applicability for when the RPS logic and trip initiation channels are required to be operable. Please identify the FCS operating modes when the proposed LCO 2.15.2 is applicable.
-2
- 3. LCD 2.15.2 states that it is applicable for FCS Operating Modes 1 and 2; and when reactor coolant temperature (Tcold) is greater than 210° For FCS Operating Mode 4 with more than one control element assembly (CEA) rod capable of being withdrawn and RCS boron concentration less than REFUELING BORON CONCENTRATION.
a) Please clarify the operating modes applicable for LCD 2.15.2 using the definitions provided in FCS TS.
b) One of the applicable modes identified in the proposed LCD 2.15.2 is "when reactor coolant temperature (Tcold) is greater than 210 F." Please explain if this description 0
corresponds to FCS operating Mode 3.
c) NUREG-1432, STSs, identifies the applicability for LCD 3.3.3 to be STS operating Modes 1 and 2; or Modes 3, 4, and 5 with any reactor trip circuit breakers closed and any CEAs capable of being withdrawn. Please clarify how the operating modes for the proposed LCD 2.15.2 compare with this description.
- 4. LAR, Enclosure, Section 2.0, states that the RPS manual trip functional unit included in Table 2-2, "Instrument Operatillg Requirements for Reactor Protective System," will be removed, and that this function will be included in the proposed LCD 2.15.2. The LAR Enclosure Section 3.0, Technical Evaluation, does not state that the manual function would be moved to the new LCD 2.15.2, instead this section states that requiring restoration of the inoperable channel is consistent with the current TS requirement contained in TS Table 2-2, item 1. Please clarify.
- 5. Current TS requirement in LCD 2.15 (2) states that if a channel of a particular system (Table 2-2) is inoperable, this channel must be placed in the tripped position. Further, if the inoperable channel has not been restored to operable status after 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor should be placed in a Hot Shutdown Condition (mode 3) within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> based on this information, it is not clear why the proposed LCD 2.15.2 (3) is requiring that with one inoperable RPS manual trip channel to restore the status to OPERABLE prior to entering Mode 2 from Mode 3. Please clarify.
- 6. The LAR Enclosure 2, Section 3.0, Technical Evaluation, states that the current TS 2.15(5), Alternate Shutdown and Auxiliary Feedwater Panel, will be incorporated into a new LCD 2.15.3 with the list of components being included into a new Table 2-6. Further, Section 3 states that no changes are proposed for the requirements, other than formatting.
Please clarify the relationship between required actions 1 and 2 in the proposed TS 2.1.5.3.
August 31,2012 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:
FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ESTABLISH THE REACTOR PROTECTIVE SYSTEM ACTUATION CIRCUITS LIMITING CONDITION FOR OPERATION (TAC ME8038)
Dear Mr. Bannister:
By letter dated February 10, 2012 (Agencywide Documents Access and ManC\gement System Accession No. ML12046A838), Omaha Public Power District requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation requirements for the reactor protective system actuation circuits in Technical Specification 2.15, "Instrumentation and Control Systems."
The Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review.
A draft copy of the enclosed request for additional information was provided to Mr. Bill Hansher of your staff via e-mail onJuly13.2012.DuringateleconferenceonAugust14.2012.Ms.
Donna Lippy of your staff indicated that the response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov.
Sincerely, IRA!
Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun RAlvarado.. NRR/DEIEICB LPLIV Reading RidsNrrDorlDpr Resource Resource KBucholtz, RidsAcrsAcnw_MailCTR RidsNrrLAJBurkhardt RidsOgcRp Resource NRR/DSS/STSB Resource Resource RidsRgn4MailCenter RidsNrrDeEicb Resource Resource ADAMS Accession No ML12236A243 *via memo dated I OFFICE NRRlDORULPL4/PM NRRlDORUlPl4/LA NRRlDE/EICB !BC NRRlDORUlPl4/BC NRRlDORUlPl4/PM JBurkhardt NAME LWilkins (BClayton for) JThorpe* MMarkley LWilkins DATE 8/30/12 8/28/12 6/21/12 8/31/12 8/31/12 OFFICIAL RECORD COpy
