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Category:Regulatory Guide
MONTHYEARML22276A1542022-10-0303 October 2022 Pre-decisional DG Seismic Isolation Ver 7 ML22276A1492022-10-0303 October 2022 Pre-decisional DG Seismic Design Ver 7 ML22157A3662022-05-27027 May 2022 Draft NRC Regulatory Issue Summary 2022-XX Personnel Access Authorization Requirements for Non-Immigrant Foreign Nationals Working at Nuclear Power Plants ML21280A3592021-10-26026 October 2021 Watermarked for ACRS - RG 1.244 - Control of Heavy Loads -10-7.docx ML20287A1992021-01-31031 January 2021 Regulatory Guide (RG) 1.191, Rev 1, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20287A4232021-01-31031 January 2021 Draft Regulatory Guide DG-1377, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste ML20142A4892020-08-31031 August 2020 DG-1351 Rev 1 - Licensee Actions to Address Nonconservative Technical Specifications_FY20 ML20078K9272020-08-0606 August 2020 FRN for DG-1370 for Revision 1 of RG 1.191 Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown ML19291D4372019-10-17017 October 2019 RITF Public Meeting Talking Points on Regulatory Guide Reviews (October 17, 2019) Regulatory Guide 1.2262019-06-30030 June 2019 Rev. 0, Flexible Mitigation Strategies for Beyond-Design-Basis Events Regulatory Guide 1.2272019-06-30030 June 2019 Rev. 0, Wide-Range Spent Fuel Pool Level Instrumentation ML18129A0802018-06-30030 June 2018 Draft Regulatory Guide (DG)-1336, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. ML16312A0022017-08-0202 August 2017 Rulemaking: Final Rule: Office of Management and Budget Supporting Statement for Information Collections American Society of Mechanical Engineers Code Cases ML15294A4902017-03-10010 March 2017 Rulemaking: Being Made Public to Support the Regulatory Information Conference - Draft Preliminary Regulatory Basis - Regulatory Improvements for Power Reactors Transitioning to Decommissioning ML16035A4762017-02-28028 February 2017 Draft Regulatory Guide (DG)-2004, Emergency Planning for Research and Test Reactors and Other Non-Power Production and Utilization Facilities ML16211A1672016-11-30030 November 2016 Rev. 0 - Wide-Range Spent Fuel Pool Level Instrumentation Dated November 2016 ML16218A2362016-11-30030 November 2016 Rev. 0 - Integrated Response Capabilities for Beyond-Design-Basis Events Dated November 2016 SECY-16-0048, : Enclosure 3 - Proposed Rulemaking: Non-Power Production or Utilization Facility License Renewal (RIN-350-AI96)2016-04-0707 April 2016 SECY-16-0048: Enclosure 3 - Proposed Rulemaking: Non-Power Production or Utilization Facility License Renewal (RIN-350-AI96) ML16005A1332016-01-19019 January 2016 2/4/2016 ACRS Subcommittee Meeting: Regulatory Guide 1 224 - Establishing Analytical Limits for Zirconium-Alloy Cladding Material ML16005A1342016-01-19019 January 2016 2/4/2016 ACRS Subcommittee Meeting: Regulatory Guide 1.223 - Determining Post Quench Ductility ML16005A1352016-01-19019 January 2016 2/4/2016 ACRS Subcommittee Meeting: Regulatory Guide 1.222 - Measuring Breakaway Oxidation Behavior ML15259A4722015-09-16016 September 2015 Results of Periodic Review of Regulatory Guide 8.35 ML15068A3282015-03-10010 March 2015 ACRS Pre-Decisional DG-1319 Integrated Response Capabilities for Beyond-Design-Basis Events ML15068A3252015-03-10010 March 2015 ACRS Pre-Decisional DG-1317, Wide Range Spent Fuel Pool Level Instrumentation SECY-11-0124, Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 32013-07-17017 July 2013 Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3 ML1104201332011-04-30030 April 2011 Regulatory Analysis, Revision 4 of Regulatory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements ML1034000082011-01-31031 January 2011 Draft Regulatory Guide, DG-1229, Assuring the Availability of Funds for Decommissioning Nuclear Reactors ML0909705302009-09-30030 September 2009 Draft Regulatory Guide DG-1225, Instrument Lines Penetrating the Primary Reactor Containment ML0916204092009-07-31031 July 2009 DG-4015, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications ML0812005932008-04-10010 April 2008 Enclosure 9 - Proposed Guidance to MC0305 to Address Protracted PI Results - NEI, Draft ML0808801432008-03-27027 March 2008 Nesc Reference for the Purpose of TMI License Renewal Environmental Review ML0625404082006-10-11011 October 2006 Draft Regulatory Guide DG-1164, Meteorological Monitoring Programs for Nuclear Power Plants (Proposed Revision 1 of Regulatory Guide 1.23) ML0615202332006-05-29029 May 2006 DG-1145 Section C.I.1 Introduction on and General Description of Plant Regulatory Guide 1.12005-09-0606 September 2005 Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps ML0424600382004-11-0808 November 2004 SECY-040-0211Atch2 - Regulatory Guide 1.101, Revision 5 ML0413400872004-06-30030 June 2004 SECY-04-0109 - Attachment 6 - Regulatory Guide 1.201, Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance ML0320305282003-06-23023 June 2003 Debris Generation Methodology Guidance, Draft Guide, Attachment 3 ML0320305352003-06-21021 June 2003 PWR Sump Performance Evaluation Methodology: Velocity Calculation, Draft, Attachment 4 ML0037671122000-11-0707 November 2000 Guide for Processing License Amendments ML0037681442000-11-0101 November 2000 G20000453/LTR-00-0600 - Enclosure to Rep. Sue Kelly Policy on Request for Additional Information When Processing License Amendments ML0037604692000-10-25025 October 2000 SECY-00-0212-Attachment 1 - Regulatory Guide 1.186 - Guidance and Examples for Idenfitying 10 CFR 50.2 Design Bases ML0037360972000-08-24024 August 2000 Draft Regulatory Guide DG-1104, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses ML0734102491978-03-0707 March 1978 Transmittal of Revision 1 to Regulatory Guide 1.97, a Clearer Basis for Development Initial Response ML0124202911976-01-0707 January 1976 License Amendment, Reporting Requirements According to Regulatory Guides 1.10 and 1.16 ML0127703911976-01-0707 January 1976 Amendments 14, Incorporating Technical Specifications Changes to the Reporting Requirements ML0119300121975-12-22022 December 1975 Letter Informing of Issuance of Amendment No. 16, Technical Specification Change No.26 for License No DPR-38 ML0133304361975-11-26026 November 1975 Issuance of Amendments 13 and 12, Incorporating Into Turkey Point Nuclear Generating Units 3 and 4 TS Changes to Reporting Requirements ML0118700651975-11-0101 November 1975 License DPR-35, Amendment 13 ML19283D5761971-03-10010 March 1971 Safety Guide 8 (Regulatory Guide 1.8) Personnel Selection and Training 2022-05-27
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SAFETY GUIDE 1 REGULATORY GUIDE 1.1 NET POSITIVE SUCTION HEAD FOR
EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL SYSTEM PUMPS*
A. Introduction possible accident conditions. For example, if Proposed General Design Criterion 41 re- proper operation of the emergency core cooling quires that the emergency cooling and contain- system depends upon maintaining the contain- ment heat removal systems be capable of ac- ment pressure above a specified minimum complishing their required safety functions as- amount, then too low an internal pressure (re- suming partial loss of installed capacity. In cur- sulting from impaired containment integrity rent designs the ability to accomplish these or operation of the containment heat removal safety functions reliably depends in part on the systems at too high a rate) could significantly proper performance of system pumps which, affect the ability of this system to accomplish in turn, depends on the conditions under which its safety functions by causing pump cavita- the pumps must operate. One of these condi- tion. In addition, the deliberate continuation of tions is suction pressure. This guide describes a high containment pressure to maintain an a suitable relationship between increases in adequate pump NPSH would result in greater containment pressure caused by postulated loss leakage of fission products from the contain- of coolant accidents and the net positive suc- ment and higher potential offsite doses under tion head (NPSH) of emergency core cooling accident conditions than would.otherwise result.
and containment heat removal system pumps Changes in NPSH for emergency core cool- which may be used to implement General De- ing and containment heat removal system sign Criterion 41. pumps caused by increases in temperature of the pumped fluid under loss of coolant accident B. Discussion conditions can be accommodated without reli- A significant consideration related to emer- ance on the calculated increase in containment gency core cooling and containment heat re- pressure. Adequate NPSH can be assured by moval systems is the potential for degraded locating pumps at-suitable elevations with re- pump performance which could be caused by a spect to the storage volumes connected to their number of factors, including inadequate NPSH. suction sides, by using multistage or booster If the NPSH available to a pump is not suffi- pumps, by a combination of these methods, or cient, cavitation of the pumped fluid can occur. by other techniques.
This cavitation may reduce significantly the capability of the system to accomplish its safety C. Regulatory Position functions. Emergency core cooling and containment heat removal systems should be designed so It is important that the proper performance that adequate net positive suction head (NPSH)
of emergency core cooling and containment is provided to system pumps assuming maxi heat removal systems be independent of calcu- mum expected temperatures of pumped fluids lated increases in containment pressure caused and no increase in containment pressure from by postulated loss of coolant accidents in order that present prior to postulated loss of coolant to assure reliable operation under a variety of accidents.
1.1
- This regulatory guide has been superseded by Regulatory Guide 1.82 Revision 4. However, this regulatory guide may continue to be used if it is part of a plants licensing basis on the date of issuance of Regulatory Guide 1.82 Revision 4.
ATTACHMENT 2