UNITED STATES NUCLEAR REGULATORY COMMISSION REGION Iv 1600 E. LAMAR BLVD ARLINGTON, Tx 76011-4511 March 30, 2015 Mr. Lou Cortopassi, Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 PO. Box 550 Fort Calhoun, NE 68023-0550 SUBJECT: CLOSURE OF NRC INSPECTION MANUAL CHAPTER 0350 OVERSIGHT AND TRANSITION TO THE ROUTINE REACTOR OVERSIGHT PROCESS FOR FORT CALHOUN STATION Dear Mr. Cortopassi: This letter is to notify you of the transition of regulatory oversight of Fort Calhoun Station (FCS) from the US. Nuclear Regulatory Commission (NRC) Inspection Manual Chapter (IMC) 0350, ?Oversight of Operating Reactor Facilities in an Extended Shutdown as a Result of Significant Performance Problems,? process to the IMC 0305, "Operating Reactor Assessment Program process. This transition will become effective on April 1, 2015. Based on current plant performance, FCS will be placed in the Licensee Response Column of the ROP Action Matrix. This letter provides the schedule for inspections that will be conducted at the facility through June 30, 2016. addition, NRC inspections to monitor your continuing efforts to sustain improved plant performance and comply with the commitments identi?ed in our December 17, 2013, Confirmatory Action Letter (CAL) EA-13-243 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13351A395) will be conducted for the remaining CAL open items in coordination with their completion. Background By letter dated December 13, 2011, (ADAMS Accession No. ML113470721), the NRC informed Omaha Public Power District (OPPD) that FCS transitioned to increased regulatory oversight as prescribed by NC 0350 based on the plant being in an extended shutdown with significant performance problems and a significant operational event involving a fire in safety-related electrical switchgear on June 7, 2011. In accordance with IMC 0350, an NRC Oversight Panel was chartered to coordinate and oversee NRC activities needed to verify proper station safety performance prior to and following plant restart, and to ensure that agency focus and resources supported the review of OPPD improvement initiatives. Under the direction of the Oversight Panel, NRC staff completed inspection, assessment, and licensing activities and evaluated the effectiveness of OPPD's L. Cortopassi - 2 - actions to address the issues that resulted in the extended plant shutdown. The Oversight Panel assessed the effectiveness of corrective actions based on inspection results. The Oversight Panel determined that there was no safety concern with restart of FCS and recommended closure of CAL EA-020 dated February 26, 2013 (ADAMS Accession No. ML13057A287). The Oversight Panel also recommended issuing a post-restart CAL in support of continuing performance improvement in a number of areas including the corrective action process (CAP). The decision to lift its restrictions on the restart of FCS, and basis for the decision, were described in a December 17, 2013, letter to OPPD (ADAMS Accession No. ML13351A423). The letter addressed the CAL closure, Restart Checklist closure, coordination of the restart decision with other federal agencies, OPPD commitments, and continuation of enhanced NRC regulatory oversight of FCS after restart. The NRC issued post-restart CAL EA-13-243 (ADAMS Accession No. ML13351A395) on December 17, 2013. This letter confirmed the commitments by OPPD in its report, "Integrated Report to Support Restart of Fort Calhoun Station and Post-Restart Commitments for Sustained Improvement," dated December 20, 2013 (ADAMS Accession No. ML13336A785). In the report, OPPD committed to take actions following restart of FCS to ensure the improvements initiated during the extended outage remain in place and performance continues to improve at the facility. After the NRC lifted the CAL restriction on the restart of FCS, OPPD commenced startup and the unit reached criticality on December 18, 2013. Generator output breakers were closed on December 21 and the unit reached 100 percent power on December 26, 2013. After startup, the NRC continued to implement its inspection program at FCS as directed by the IMC 0350 Oversight Panel. In addition to ROP baseline inspections performed by the residents and regional based inspectors, two NRC team inspections were conducted to assess the effectiveness of OPPD actions for implementing the CAL commitments and the effectiveness of the FCS CAP in identifying and resolving station problems. These post-restart inspection activities did not result in the identification of any Greater-than-Green safety or security issues. At the time of restart, several of the ROP performance indicators (Pls) did not afford sufficient insight into plant performance because of the extended shutdown. Specifically, the Mitigating Systems Performance Indicators for Unplanned Scrams, Unplanned Power Changes, Emergency AC Power System Unavailability, High Pressure Injection System Unavailability, Heat Removal System Unavailability, Residual Heat Removal System Unavailability, and Cooling Water Systems Unavailability were affected. In the second caiendar quarter of 2014, the for both Unplanned Scrams and Unplanned Power Changes became valid. High Pressure Injection System Unavailability, Heat Removal System Unavailability, and Cooling Water Systems Unavailability became valid in the fourth calendar quarter of 2014. Emergency AC Power System Unavailability and Residual Heat Removal System Unavailability became valid starting in the first calendar quarter of 2015. Based on two unplanned scrams in the first quarter of 2014, the Unplanned Scrams Pl turned White in the second calendar quarter of 2014. The NRC completed a supplemental inspection in accordance with NRC Inspection Procedure 95001, ?Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area,? in January of 2015. Based on the results of this inspection, the NRC determined that OPPD had effectively evaluated L. Cortopassi - 3 - the cause and extent of condition for the scrams and implemented appropriate corrective actions. As a result, the Oversight Panel concluded that this item is closed. The results of the 95001 supplemental inspection were documented in NRC Inspection Report (IR) 05000285l2015008 issued on March 12, 2015 (ADAMS Accession No. ML15071A115). Two issues of low to moderate safety significance (White) were dispositioned since plant restart in December of 2013. The issues involved the failure to provide adequate tornado missile protection for plant structures, systems, and components; and the failure to properly implement high energy line break and environmental qualification design requirements. For both of these issues, OPPD either modified the plant or implemented compensatory measures that adequately addressed all the identified deficiencies prior to plant restart in December of 2013. The Oversight Panel determined that since these issues were identified and resolved by OPPD during the extended shutdown, under increased NRC oversight per the IMC 0350 process, that these issues would not be used for future plant performance assessment inputs and, as such, they are considered closed. The tornado missile protection issue was dispositioned on April 25, 2014, in NRC IR 0500028512013017, (ADAMS Accession No. ML14115A41 1). The high energy line break and environmental qualification issues were dispositioned on November 25, 2014, in NRC IR 05000285l2013018, (ADAMS Accession No. ML143293361). Since plant restart, the Oversight Panel has continued conducting periodic public meetings with OPPD to discuss licensee performance and NRC inspection and assessment results. During each of these meetings, members of the public were given an opportunity to ask questions and provide comments. In addition, each of these meetings was video-taped, transcribed, or documented in public meeting summaries and placed on the Public Web site. The following public meetings between the NRC and OPPD were conducted: a February 27, 2014, in Blair, Nebraska (Meeting Summary, ADAMS Accession No. ML14065A253) 0 May 13, 2014, in Omaha, Nebraska (Meeting Summary, ADAMS Accession No. ML14143A289) 0 June 3, 2014, Commission briefing in RockviIIe, Maryland (Meeting Transcripts, ADAMS Accession No. ML14156A005) - September 25, 2014, in Omaha, Nebraska (Meeting Summary, ADAMS Accession No. ML14276A543) - October 1, 2014, in RockviIIe, Maryland (Meeting Transcripts, ADAMS Accession No. ML14297A383) 0 December 2, 2014, in RockviIIe, Maryland (Meeting Summary, ADAMS Accession No. ML14344A087) The next public meeting is currently scheduled to be conducted in Omaha, Nebraska, on April 9, 2015. L. Cortopassi -4- Basis for the Transition of Fort Calhoun Station to the Routine Reactor Oversight Proce?_s_ In accordance with the NC 0350 process, the Oversight Panel assessed the transfer of FCS oversight to the routine ROP using the following criteria: Veri?cation that established an effective long-range improvement program, OPPD is suf?ciently implementing its corrective action program, OPPD has demonstrated safe plant operation, and OPPD has adequate controls in place to address the plant-speci?c issues that caused the significant performance decline which led to invoking the 0350 process. On March 18, 2015, the Oversight Panel concluded that OPPD had satis?ed these four transition criteria. The following provides a summary of key items considered by the Oversight PaneL Verification that OPPD has established an effective long-range improvement program On December 17, 2013, the NRC authorized plant restart and issued post-restart CAL EA-13-243 detailing commitments that OPPD made to ensure improvements realized during the extended shutdown remain in place, and performance continues to improve at the facility. The NRC has conducted a signi?cant number of inspections with respect to the various CAL items and has concluded that OPPD has been effectively implementing its performance improvement initiatives. Additionally, OPPD has developed long-term actions to sustain performance improvement focused in the areas of configuration control, risk management, refueling outage activities, backlog reduction, system health, work management, fundamentals and behaviors, corrective action program, and workforce development. Currently, the NRC has reviewed and closed 146 of the 166 items associated with the post-restart CAL, resulting in 7 of the 10 performance improvement areas being considered closed. The following provides the status of these improvement areas: - Organizational Effectiveness, Safety Culture, and Safety Conscious Work Environment is closed 8 of 8 items completed) 0 Problem Identi?cation and Resolution is closed (14l14) 0 Performance Improvement and Learning Programs is closed (11/11) 0 Design and Licensing Basis Control and Use is open (5/15) 0 Site Operational Focus is closed L. Cortopassi - 5 - 0 Procedures is closed (10/10) 0 Equipment Performance is open (25/34) Programs is open (66/67) 0 Nuclear Oversight is closed 0 Transition to the Exelon Nuclear Management Model and Integration into the Exelon Nuclear Fleet is closed Although not all of the post-restart CAL items are closed, the Oversight Panel concluded that completion of the remaining items should not delay transfer of FCS to the routine ROP under IMC 0305. The few items currently open pertain to long-term actions such as performing a design basis reconstitution that is scheduled for completion in 2018. The NRC will continue to perform CAL follow-up inspections as the licensee completes these improvement initiatives. OPPD is sufficiently implementing its corrective action program In July of 2014, an NRC team performed an inspection to assess the effectiveness of OPPD actions to address CAL commitments, and to assess the effectiveness of CAP implementation. Overall, the team concluded that OPPD had effectively implemented several of the improvement initiatives described in the December 17, 2013, however, a significant number of deficiencies were identified involving the licensee staff?s ability to evaluate and resolve problems effectively and consistently using its CAP. The results of this inspection were documented in NRC IR 05000285l2014009 issued on September 18, 2014, (ADAMS Accession No. ML14361A455). Based on the results of NRC inspection activities, the Oversight Panel unanimously concluded on September 4, 2014, that OPPD was not sufficiently implementing its CAP and should remain under the IMC 0350 oversight process. Specifically, the Oversight Panel concluded that the ability of the licensee to effectively evaluate and resolve problems in a consistent manner was of concern. The Oversight Panel recommended that OPPD remain under the IMC 0350 process until such time the licensee fully evaluated the areas of concern, identified and implemented corrective actions for program improvements, and had measures in place that adequately monitor and manage the effectiveness of program improvement initiatives. OPPD conducted a number of self and external assessments to determine the causes of inconsistent implementation of the CAP. These assessments resulted in OPPD taking immediate and long-term actions to improve CAP performance. An NRC team inspection in January 2015 assessed the effectiveness of OPPD actions to improve performance of the CAP. Overall, the team concluded that the licensee had made significant progress in improving station CAP performance. Station management has adopted a new set of standards for CAP implementation and is L. Cortopassi - 6 - holding the staff accountable to the standards. Station processes for communicating, tracking, reviewing, and resolving issues placed in the CAP have been improved. In addition, the inspection team noted that FCS management and staff are more aligned on the importance of the CAP. The results of this inspection are documented in NRC IR 05000285l2015008, dated March 12, 2015. OPPD has demonstrated safe plant Operation Since the December 2013 plant restart, control room operators have consistently demonstrated safe plant operation. Operators have effectively controlled the plant during transient conditions and reduced power or shutdown the plant on a number of occasions based on conservative decisions to place the unit in a safe condition. In each of the following examples, plant operators performed without error or incident: 0 On January 9, 2014, control room operators declared the raw water system inoperable after identifying a stuck open intake structure sluice gate resulting in a Technical Speci?cation required shutdown. On January 12, 2014, during a reactor start up, control room operators inserted a manual scram to shutdown the reactor due to a control rod that failed to move properly. - On March 17, 2014, control room operators responded effectively to an automatic reactor scram following a loss of main turbine generator stator water cooling. 0 On April 15, 2014, control room operators declared the control room air conditioning system inoperable resulting in a Technical Speci?cation required shutdown. Plant shutdown was halted at 36 percent power when air conditioning was restored to service. 0 On June 20, 2014, control room operators reduced power to 30 percent "in response to potential Missouri River flooding conditions. a On December 17, 2014, control room operators responded effectively to an automatic reactor scram following the failure of an auxiliary transformer sudden pressure trip relay. OPPD has adeguate controls in place to address the plant-specific issues that caused the significant performance decline which led to invoking the 0350 process On December 17, 2013, the NRC issued a letter, ?Fort Calhoun Station Closure of Confirmatory Action Letter,? (ADAMS Accession No. ML13351A423) documenting the basis for the NRC's determination that it had completed the necessary inspection, assessment, and licensing activities to thoroughly evaluate the issues identified'as contributors to the longstanding degradation in overall station performance as described in CAL EA-13-020, dated February 26, 2013. This assessment of actions was based on resident, region-based, and headquarters inspections, supplemented by L. Cortopassi - 7 - review and input from headquarters technical staff. The NRC inspections were performed individually and by teams, with results documented in reports that are publicly available. These reports include: 0 NRC INTEGRATED INSPECTION REPORTS (issued every 6 weeks since entry into MC 0350) NRC IMC 0350 SECURITY IR 05000285l2013405 issued on April 24, 2013, ADAMS Accession No. ML13115A087 (associated with Greater-than-Green security ?ndings) 0 NRC SPECIAL IR 05000285l2013-012 issued on May 24, 2013, ADAMS Accession No. ML13144A772 (associated with the improper design speci?cations involving the raw water pump anchor bolts) - MANUAL CHAPTER 0350 TEAM IR 05000285l2013008 issued on July 16, 2013, ADAMS Accession No. ML13197A26 (focused in the areas of safety culture, corrective action program, engineering programs, regulatory processes, and nuclear oversight) NRC IMC 0350 IR 05000285l2013010 issued on July 11, 2013, ADAMS Accession No. ML13192A501 (focused in the areas of operations and emergency preparedness) NRC IMC 0350 SECURITY TEAM IR 05000285l2013407 issued on August 1, 2013, ADAMS Accession No. ML13213A498 (associated with follow-up inspections for the Greater-than-Green security findings) 0 MANUAL CHAPTER 0350 TEAM IR 0500028512013013 issued on April 3, 2014, ADAMS Accession No. ML14094A052 (focused in the areas of signi?cant performance deficiencies, engineering and maintenance programs, and operability process) MANUAL CHAPTER 0350 TEAM INSPECTION AND FINAL SIGNIFICANCE DETERMINATION OF WHITE FINDING AND NOTICE OF VIOLATION REPORT 05000285l2013017 issued on April 25, 2014, ADAMS Accession No. ML14115A411, (focused on resolution of tornado missile protection de?ciencies) MANUAL CHAPTER 0350 TEAM INSPECTION AND FINAL SIGNIFICANCE DETERMINATION OF WHITE FINDING AND NOTICE OF VIOLATION REPORT 05000285l2013018 issued on November 25, 2014, ADAMS Accession No. ML143298361, (focused on resolution of high energy line break and environmental qualification deficiencies) L. Cortopassi - 8 - After startup, NRC inspection activities under IMC 0350 oversight continued. Overall results of these inspections indicate that OPPD's performance continues to improve. No Greater-than-Green safety or security findings were identified. The results of these inspections are documented in the following reports: - NRC INTEGRATED INSPECTION REPORTS - IR 05000285l2014002 issued on March 19, 2014, ADAMS Accession No. IR 05000285001400? issued on May 14, 2014, ADAMS Accession No. IR 05000285l2014003 issued on July 29, 2014, ADAMS Accession No. IR 05000285l2014004 issued on November 13, 2014, ADAMS Accession No. and IR 05000285l2014005 issued on February 12, 2015, ADAMS Accession No. ML15043A423 0 SECURITY BASELINE INSPECTION REPORTS IR 05000285l2014404 issued on May 2, 2014, ADAMS Accession No. and IR 05000285l2014403 issued on July 17, 2014, ADAMS Accession No. ML14198A184 TEMPORARY INSTRUCTION 2515/186, OF PROCEDURES AND PROCESS FOR RESPONDING TO POTENTIAL AIRCRAFT REPORT 05000285l2014406 issued May 21, 2014, ADAMS Accession No. ML14141A336 . NRC POST-APPROVAL LICENSE RENEWAL IR 0500028512014008 issued on June 13, 2014, ADAMS Accession No. ML14164A638 TEMPORARY INSTRUCTION 2201/004, OF IMPLEMENTATION OF INTERIM CYBER SECURITY MILESTONES REPORT 05000285l2014405 issued on June 25, 2014, ADAMS Accession No. ML14176B202 NRC CONFIRMATORY ACTION LETTER FOLLOWUP INSPECTION AND PROBLEM IDENTIFICATION AND RESOLUTION TEAM IR 0500028512014009 issued on September 18, 2014, ADAMS Accession No. ML14261A455 I NRC CONFIRMATORY ACTION LETTER FOLLOWUP INSPECTION AND PROBLEM IDENTIFICATION AND RESOLUTION TEAM IR 05000285l2015008 issued on March 12, 2015, ADAMS Accession No ML15071A115 Transition of Fort Calhoun Station to the Routine Re_actor Oversight Process After evaluating station performance in the areas discussed above, the Oversight Panel concluded that your staff?s performance with respect to each area, was acceptable and further increased regulatory oversight under the IMC 0350 process was no longer necessary. As such, on March 19, 2015, the Oversight Panel issued a memorandum to me and the L. Cortopassi - 9 - Director of the NRC's Of?ce of Nuclear Reactor Regulation (NRR) recommending termination of the IMC 0350 process for FCS. On the basis of this recommendation, I have consulted with the Director of NRR and the Deputy Executive Director for Reactor and Preparedness Programs and determined that termination of increased regulatory oversight under the IMC 0350 process is warranted and that regulatory oversight of FCS should return to the routine ROP. Based on no Greater-than-Green Findings or Performance Indicators currently in effect, FCS will transition to the Licensee Response Column (Column I) of the ROP Action Matrix consistent with IMC 0305 effective April 1, 2015. Cross-cutting aspects assigned to inspection ?ndings will be assessed consistent with the normal process in IMC 0305 to identify the presence of substantive cross-cutting issues at the station. For example, during the 2015 mid-cycle review, the staff would assess cross-cutting aspects assigned to inspection findings over the previous four quarters. Based on OPPD improvement initiatives in the cross-cutting areas of human performance, problem identification and resolution, and safety conscious work environment, no substantive cross-cutting issues are being identi?ed. Additionally, inspection planning and routine public meetings will be conducted as described in the ROP Action Matrix. Inspection Schedule Under the Reactor Oversight Process The enclosed 18 month inspection schedule is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. Follow-up inspections for the remainder of the open items associated with the post-restart CAL will be conducted in coordination with your completion of those activities! improvement initiatives specific to each item. Inspection Manual Chapter 0305 recognizes that up to 200 hours of direct inspection may be required for licensees which are transitioning out of the IMC 0350 process. If circumstances arise which cause us to change the inspection plan, we will contact you to discuss the change as soon as possible. Please contact Michael C. Hay, Chief, Reactor Projects Branch D, Division of Reactor Projects, at 817-200-1147 with any questions you may have regarding this letter or the inspection plan. Summary In summary, this letter is to inform you of the following four actions: - Termination of the IMC 0350 process at FCS and the disbandment of the IMC 0350 Oversight Panel, 0 Transition of FCS oversight to the routine ROP under the Licensee Response Column of the Action Matrix, starting on April 1, 2015, Cross-cutting aspects assigned to inspection findings will be assessed using the normal process outlined in IMC 0305 during future mid-cycle and end-of?cycle review meetings to assess for potential substantive cross-cutting issues, and L. Cortopassi - 10 - NRC follow-up inspections will be implemented for the remaining open items associated with CAL EA-13-243, dated December 17, 2013. Sincerely, Wax/2% Marc L. Dapas Regional Administrator Docket No. 50-285 License No. DPR-40 Enclosure cc: Electronic Distribution Page 1 of 2 0313012015 Report 22 07:41 :27 Unit Number 1111612015 1211412015 04121 1201 5 04127120 1 5 041271201 5 0412712015 0412 71201 5 0810312015 0810312015 0810312015 0810312015 0810312015 0910112015 1011912015 1110212015 1111612015 1111612015 111161201 5 1210712015 0711812016 0711812016 0711812016 0711612016 Planned Dates 1112012015 1211812015 051021201 5 0510112015 0510112015 0510112015 0510112015 0810712015 0810712015 0810712015 0810712015 0810712015 091301201 5 1012312015 1110612015 1112012015 1112012015 1112012015 1211112015 0712212016 0712212016 0712212016 0712212016 Fort Calhoun Inspection IActivity Plan 0410112015 - 0913012016 EXAM X02544 X02544 71111.08 IP RS 13 PI IP 71124.01 IP 71124.03 IP 71151-OR01 IP 71151-PR01 EP-2 IP 7111404 IP 7111407 EP-3 IP 71151-EP01 IP 71151-EP02 IP 71151-EP03 ISFSI IP 60855 EBZ-OST IP 7111105X IP 7111105X R524 IP 711 24.02 IP 71124.04 TSB 528 711523 IP 711523 RS 5678 IP 71124.05 IP 71124.06 IP 71124.07 IP 71124.08 - INI11AL OPERATOR EXAM INITIAL EXAM INITIAL EXAM - INSERVICE INSPECTION Inservice Inspection Activities - PWR RADIATION SAFETY Radiological Hazard Assessment and Exposure Controls In-Plant Airborne Radioactivity Control and Mitigation Occupational Exposure Control Effectiveness RETSIODCM Radiological Ef?uent Occurrences - HAB EXERCISE INSPECTION Emergency Action Level and Emergency Plan Changes Exercise Evaluation - Hostile Action (HA) Event - EP PERFORMANCE INDICATORS Drill/Exercise Performance ERO Readiness Alert 8: Noti?cation System Reliability - ROUTINE INSPECTION (1 WEEK IN THE MONTH) Operation Of An ISFSI - TRIENNIAL FIRE PROTECTION INSPECTION Fire Protection - NFPA 805 (Triennial) Fire Protection - NFPA 805 (Triennial) - RADIATION SAFETY Occupational ALARA Planning and Controls Occupational Dose Assessment - BIENNIAL INSPECTION Problem Identi?cation and Resolution Problem Identi?cation and Resolution - RADIATION SAFETY - TEAM Radiation Monitoring Instrumentation Radioactive Gaseous and Liquid Ef?uent Treatment Radiologlcal Environmental Monitoring Program Radioactive Solid Waste Processing and Radioactive Material Handling. Storage, and Transportation No. of Staff his report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures. page 2 of 2 Fort Calhoun 03130I2015 07:41:27 Inspection [Activity Plan 22 041011201 5 - 09I3012016 Unit Number No. of Staff on Site a Title EB1-17T - FCS PERM PLANT MODS 8: 50.59 INSPECTION 1 07/25/2016 0811212016 IP 7111117T Evaluations of Changes. Tests. and Experiments and Permanent Plant Modi?cations if. I is report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures. L. Cortopassi - 10 - NRC follow-up inspections will be implemented for the remaining open items associated with CAL EA-13-243, dated December 17, 2013. Sincerely, WW Marc L. Dapas Regional Administrator Docket No. 50-285 License No. DPR-4O cc: Electronic Distribution DISTRIBUTION: See next page DOCUMENT NAME: orts to ROP 2015.docx ADAMS ACCESSION NUMBER: ML1508 A085 SUNSI Review ADAMS Publicly Available Non-Sensitive KeywordNon-Publicly Available El Sensitive NRC-002 OFFICE DDRP DDRS RA NAME TWPruett LLund AVegel SIGNATURE Mil DATE 3/18/15 3/18/15 3/18/15 03/19/15 36W OFFICIAL RECORD COPY Letter to Lou Cortopassi from Marc L. Dapas, dated March 30, 2015 SUBJECT: CLOSURE OF NRC INSPECTION MANUAL CHAPTER 0350 OVERSIGHT AND TRANSITION TO THE REACTOR OVERSIGHT PROCESS FOR FORT CALHOUN STATION Executive Director for Operations (Mark.Satorius@nrc.gov) Deputy Executive Director, Reactor Preparedness Programs (Michael.Johnson@nrc.gov) Director, Of?ce of NRR (Bill.Dean@nrc.gov) Regional Administrator (Marc.Dapas@nrc.gov) Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) Director, Division of Inspection and Regional Support (Scott.Morris@nrc.gov) Director, NSIR (Jim.Wiggins@nrc.gov) Deputy Director for Reactor Safety Programs (Jennifer.Uhle@nrc.gov) DRP Director (Troy.Pruett@nrc.gov) DRP Deputy Director (Ryan.Lantz@nrc.gov) DRS Director (Tony.Vegel@nrc.gov) DRS Deputy Director (Jeff.Clark@nrc.gov) Senior Resident Inspector (Max.Schneider@nrc.gov) Resident Inspector (Brian.Cummings@nrc.gov) Administrative Assistant (Janise.Schwee@nrc.gov) Branch Chief, (Michael.Hay@nrc.gov) Senior Project Engineer, (Robert.Hagar@nrc.gov) Project Engineer, (Jan.Tice@nrc.gov) Project Engineer, (Brian.Parks@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov) Branch Chief, SB (Geoffrey.Miller@nrc.gov) Project Manager (Fred.Lyon@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) ACES Regional Counsel (Karla.Fuller@nrc.gov) Technical Support Assistant (Loretta.Williams@nrc.gov) Congressional Affairs Of?cer (Angel.Moreno@nrc.gov) RIVIETA: OEDO (Michael.Waters@nrc.gov) MC 0350 Panel Chairman (Anton.Vegel@nrc.gov) MC 0350 Panel Vice Chairman (Louise.Lund@nrc.gov) MC 0350 Panel Member (Nathan.Sanfilippo@nrc.gov) MC 0350 Panel Member (Michael.Markley@nrc.gov) MC 0350 Panel Member (Joseph.Sebrosky@nrc.gov) MC 0350 Panel Member (John.Kirkland@nrc.gov) ROPreports