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MONTHYEARML24159A6372024-06-0707 June 2024 Non-Possessing Standard Practice Procedures Plan ML22223A0232022-09-0101 September 2022 SA 2022-07 Decom Rx and ISFSI Unga 77 Public Summary ML22223A0262022-09-0101 September 2022 SA 2022-06 Part 37 Unga 77 Public Summary ML21301A1992021-10-0606 October 2021 EN55511 Report to INES Diamond Technical Services Had a Worker Exceed the Annual Whole Body Dose Limit in Pittsburgh, PA ML21244A4272021-07-28028 July 2021 FAQ 21-03 R1 ANS Guidance Following IPAWS - Final Approved ML21091A2272021-03-0808 March 2021 Dave Nelson Consent Form - Speaker RIC 2021 ML20350B4632020-12-22022 December 2020 OIG-19-A-13-Status of Recommendations: Audit of Nrc'S Cyber Security Inspections at Nuclear Power Plants Dated December 3, 2019 Enclosure to NSIR Response ML20302A4632020-11-0909 November 2020 Enclosure - Completed Preparations for Incident Response Program Transition ML20238C0502020-08-25025 August 2020 Completed Version of EPFAQ 2019-04, Clarification Based on the Impact of Implementation of BWROG EPG-SAG Revision 4 on Various EALs ML20206K9852020-08-18018 August 2020 EPFAQ 2020-02 Clarification of Emergency Preparedness Communication Equipment Relative to Extended Loss of All Power Communication Equipment ML20206L1272020-08-18018 August 2020 EPFAQ 2020-01 Relief from Annual Evacuation Time Estimate (ETE) Update When Performing a Census Baseline ETE Study ML20170B1532020-07-18018 July 2020 EPFAQ 2019-04 BWROG EPG-SAG Revision 4 Impact on Eals Public Comment ML19339H4352019-12-0505 December 2019 NEI Reactor Oversight Process Whitepaper - Counting of DEP Opportunities from an Actual Emergency Following a Retraction of the Emergency Declaration ML19318G3402019-12-0303 December 2019 EPFAQ 2019-04 Clarification Based on Implementation of the Impact of BWROG Epg/Sag Revision 4 on Various Emergency Action Levels ML19296B0312019-10-24024 October 2019 EPFAQ 2019-02 Clarification of Initiating Conditions CU1 (15 Minutes) and CA1 (Significance) ML19172A3032019-07-0303 July 2019 OEDO-19-00273-OEDO Ticket - Audit of Nrc'S Cyber Security Inspections at Nuclear Power Plants (OIG-19-A-13): Enclosure to NSIR Memo ML18295A5692018-11-27027 November 2018 Transformative Change to 50-54(q) - RL-SO Version ML18295A5702018-11-27027 November 2018 Transformative Change to 50-54(q) - Clean Version ML18171A3262018-08-13013 August 2018 Encl 2 - Emergency Planning and Security Inspection Reports at San Onofre Nuclear Generating Station ML17031A2892017-05-0505 May 2017 Notice of Safeguards (SGI) Document Availability: NSIR Safety Evaluation Report Related to Kewaunee Power Stations Physical Security Plan (Rev. 0) and Revised Answer to NRC Order for Additional Security Measures (EA-07-195); Cac# L53093/L53 ML15344A4522015-12-14014 December 2015 50 54(p) Review for Grand Gulf ML15322A0252015-11-18018 November 2015 50 54(p) Review for Indian Point ML15278A0302015-10-0505 October 2015 50 54(p) Review for Ginna ML14078A6212014-04-0101 April 2014 Enclosure 3 - RASCAL 4.3 Inputs for Site Boundary Dose Projections ML12263A3092012-09-13013 September 2012 TMI Alert Presentation Notes Sept 13 2012 NUREG-0654 Public Mtg ML1118700982011-09-14014 September 2011 Enclosure 1: Sf 312 Classified Information Nondisclosure Agreement ML1105907182011-02-28028 February 2011 Staff Discussion Items for NEI 10-05 (Rev. 0) Related to On-Shift Emergency Response Organization Staffing Analysis Process ML0934106152009-12-0707 December 2009 Evacuation Time Estimate Analysis ML0532604592005-11-16016 November 2005 Meeting Attendance List for Nrc/Dhs/Fema Meeting with Entergy Nuclear Operations, Inc., on the Status of the Alert and Notification System (Siren System) for the Indian Point Energy Center SECY-05-0010, Atch - Background Information in Support of Staff Recommendations2005-01-10010 January 2005 SECY-05-0010Atch - Background Information in Support of Staff Recommendations ML0323202372003-08-22022 August 2003 August 2003 Irradiated Reactor Fuel Route Summary National Institute of Standards and Technology, Gaithersburg, MD to DOE Savannah River Site, Sc (187) 2024-06-07
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NRC Staff Discussion Items Related to the On-Shift Emergency Response Organization Staffing Analysis Process (NEI 10-05, Revision 0) # Page Section Discussion Item 1 ThroughoutThroughout Licensees should perform analysis for events provided in the Interim Staff Guidance, NSIR/DPR-ISG-01, "EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS." 2 4 2.3 At a minimum, the number and composition of the on-shift staff credited in the staffing analysis must be reflect ed in the commitments within each site's emergency plan. 3 4 2.5 Section IV.A.9 of Appendix E to 10 CFR 50 requires licensees to perform the detailed analysis to determine if on-shift staff may be assigned additional responsibilities that would prevent the timely performance of their emergency response functions delineated in the emergency plan. Any changes to the on-shift staffing, augmented staffing or augmentation staffing timing are subject to the requirements of 10 CFR 50.54(q) and related guidance.
4 6 3.1.3 The on-shift personnel complement is limited to the minimum required number and composition as reflected in the commitments within the site's emergency plan. Licensees may have other personnel on shift required by other commitments (i.e,, Appendix R), these personnel may be included in the analysis only if they are reflected as on shift in the site's emergency plan. 5 7 3.1.5 -assigned actions. For DBT events, licensees should evaluate the effects of station Security/Operation's procedures upon the response times of the on-shift personnel, i.e., movement of personnel secured or "two-man rule." Licensees should-. 6 8 3.1.10 -enforcement. This does not include off-site notifications as provided in Table 5. 7 8 3.1.12 Repair and Corrective Actions: -controls to complete. Examples of Repair and Corrective actions may include:(1) Electrician: Responsible for providing electrical support for ECCS equipment, event mitigation, and equipment repair. (2) Mechanic: Responsible for providing mechanical support for ECCS equipment, event mitigation, and equipment repair.
NRC Staff Discussion Items Related to the On-Shift Emergency Response Organization Staffing Analysis Process (NEI 10-05, Revision 0) (3) I&C Technician: Responsible for providing assist with logic manipulation, for providing I&C support for event mitigation and equipment repair, and for support of digital I&C if applicable. (4) Rad Waste Operator: Responsible for Rad Waste Operations required by applicable site procedures, e.g., EOP, AOP, EPIPs, etc. 8 8 3.1.12 Licensees should review applicable site procedures, e.g., EOP, AOP, EPIPs, etc, to determine if support/actions by Mechanical/Electrical/I&C are required under the Major Functional Area of "Repair or Corrective Actions." 9 8 3.2.1 Complete Appendix A for events identified in Interim Staff Guidance NSIR/DPR-ISG-01, "Emergency Planning For Nuclear Power Plants." 10 10 3.2.2.2.c Maintenance/Electrical/I&C personnel if identified in Step 3.1.12.
11 11 3.2.2.5.a -emergency plan implementing procedures. 12 12 3.2.2.5.b -Chemistry Technician (as indicated in Table 5)-. 13 13 3.2.2.6.a.12 It should be noted that the NRC may request an open, continuous communication channel IAW 10 CFR 50.72.(a)(3). 14 15 3.2.3.2 Table An additional notification block should be added for DBT events. Perform NRC abbreviated notification for DBT events. 15 15 3.2.3.2 Table Perform NRC communications (It should be noted that the NRC may request an open, continuous communication channel) 16 B-6 Table 4 Offsite Radiological Assessment (as indicated in Table
- 5) 17 B-7 Table 5 An additional notification block should be added for DBT events. Perform NRC abbreviated notification for DBT events. 18 B-7 Table 5 Perform NRC communications (It should be noted that the NRC may request an open, continuous communication channel)