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MONTHYEARML23117A3742023-05-0202 May 2023 Northstar Lessons Learned Meeting Slides, May 2, 2023 ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML19248C2302019-09-10010 September 2019 Final NEIMA Meeting Slides - Vermont Yankee ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML17160A1952017-06-12012 June 2017 Meeting Slides for Pre-Submittal Meeting with Entergy Regarding the Plan for Decommissioning Licensing Actions ML17193A7562017-05-25025 May 2017 NRC Presentation ML17192A6032017-05-25025 May 2017 Entergy Presentation ML17193A7392017-05-25025 May 2017 Entergy/Northstar Presentation ML17024A1062017-01-24024 January 2017 Decommissioning Reactor License Transfer Review Process ML17019A1452017-01-24024 January 2017 Presentation by Northstar and Entergy for January 24, 2017 Public Meeting on the Proposed License Transfer of Vermont Yankee for Decommissioning ML15057A4242015-02-19019 February 2015 NRC Slides Vermont Yankee PSDAR Public Meeting February 19 2015 ML15057A4432015-02-19019 February 2015 Entergy Slides, Vermont Yankee PSDAR Public Meeting, February 19, 2015 ML15036A4682015-02-0505 February 2015 Webinar Meeting to Discuss the Decommissioning Process for Nuclear Power Reactors and How It Relates to Vermont Yankee Nuclear Power Station - Slide Presentation ML15030A2742015-01-28028 January 2015 the NRC Reactor Decommissioning Process Presented at Vyndcap Meeting 1/28/2015 ML14204A3442014-06-26026 June 2014 Decommissioning - FEMA Meeting, June 26, 2014 ML14154A2522014-05-28028 May 2014 5/28/14 - Vermont Yankee 2013 EOC Aam NRC Presentation ML1118105622011-06-30030 June 2011 Aam NRC Slides, June 30, 2011 ML1021600822010-08-0404 August 2010 Annual Assessment Meeting Slides ML0810504132008-04-14014 April 2008 Slides for the Vermont Yankee 2007 Annual Assessment Meeting ML0801002822008-01-0808 January 2008 Presentation to NRC by Vermont Yankee Regarding Environmental Fatigue Analyses for License Renewal ML0731902202007-11-0707 November 2007 Meeting Handout Fitzpatrick GNF2 Introduction at Entergy ML0729000982007-08-16016 August 2007 E-mail from K. Toukatly of USNRC to Various, Regarding Bridge Call: Today (August 16) 12:15 Pm - 1:30 Pm (3 Pages) / Exemption 2 ML0715704482007-05-24024 May 2007 Slides - 5/24/07 (Final) ML0711502692007-04-25025 April 2007 NRC Annual Performance Assessment of Vermont Yankee, 2006 Reactor Oversight Process ML0707000032007-02-27027 February 2007 VY Dseis Presentation for VT Legislature 02/27/2007 ML0705405272007-01-31031 January 2007 Meeting Slides, Preliminary Results of Environmental Review Vermont Yankee Nuclear Power Station, from VYNPS Draft SEIS Public Meeting - Presentation ML0617904762006-06-0707 June 2006 2006/06/07-Slides Used During the Scoping Meeting for VYNPS License Renewal ML0609402092006-04-0404 April 2006 NRC Slides for 04/20/2006 VY Annual Assessment Meeting ML0615901582006-03-0707 March 2006 03/07/2006 - RIC 2006 Presentation - T1E - John F. Mccann - License Renewal ML0615902322006-03-0707 March 2006 2006/03/07- - RIC 2006 Presentation - T1F - Garry G. Young - License Renewal ML0617802712006-03-0707 March 2006 RIC 2006 Presentation - T2E - Vincent Coulehan - Use of Operating Experience (Regulator/Operator/Licensee) ML0602605762006-01-18018 January 2006 E-mail, Lobel, NRR, to Ennis, NRR, VY EPU Rg 1.82 Slides ML0533202252005-12-0101 December 2005 Ri Schedule 05- Mcmurtray; Lessons Learned from Security-Based Table Top Drills ML0527904952005-08-16016 August 2005 Mantg Conference, 8/16/05 - Breakout - Breakout Session Outline by NRC (Todd Fish, Peter Presby) and Entergy Nuclear Vermont Yankee (John Taylor) ML0506901392005-03-10010 March 2005 Presentation Slides for Vermont Yankee Annual Assessment Meeting BVY 04-113, Vermont Yankee Nuclear Power Station - Proposed Technical Specification Change No. 263 - Supplement No. 20 Extended Power Uprate - Meeting on Steam Dryer Analysis Meeting Presentation Slides2004-09-29029 September 2004 Vermont Yankee Nuclear Power Station - Proposed Technical Specification Change No. 263 - Supplement No. 20 Extended Power Uprate - Meeting on Steam Dryer Analysis Meeting Presentation Slides ML0425103952004-09-0202 September 2004 Attachments 1 Through 4 of 07/21/2004 & 07/22/2004 Summary of Meeting with Entergy Nuclear Operations, Inc., on Steam Dryer Analysis ML0430302692004-06-29029 June 2004 Briefing Slides: Credit for Accident Pressure in Calculated NPSH for ECCS and Containment Heat Removal Pumps ML0430302742004-06-29029 June 2004 Briefing Slides: Credit for Accident Pressure in Calculated NPSH for ECCS and Containment Heat Removal Pumps ML0430302772004-06-29029 June 2004 Briefing Slides: Credit for Accident Pressure in Calculated NPSH for ECCS and Containment Heat Removal Pumps ML0430204972004-06-0909 June 2004 Briefing Slides: Credit for Accident Pressure in Calculated NPSH for ECCS and Containment Heat Removal Pumps ML0411203682004-05-17017 May 2004 Enclosure 14, 03/31/2004 Meeting Summary for Vermont Yankee. Slides Presentation Proposed Power Uprate ML0411100212004-03-31031 March 2004 NRC Region I Slides for the Vermont Yankee Annual Assessment Meeting ML0533300492004-03-26026 March 2004 E-Mail from Skay to Holian, Et. Al., Slides for VY Public Meeting ML0528000192004-03-16016 March 2004 E-mail from D. Florek, USNRC, to A. Mcmurtray, B. Holian, C. Anderson, D. Pelton, D. Florek, N. Sheehan, R. Ennis, and W. Ruland, USNRC, Re VY Annual Assessment Strategy Meeting 2023-05-02
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CREDIT FOR ACCIDENT PRESSURE IN CALCULATED NPSH FOR ECCS AND CONTAINMENT HEAT REMOVAL PUMPS Richard Lobel June 29, 2004 v7
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Definition of Available NPSH NPSH AVAILABLE = hATM + hSTATIC - hLOSSES - hVAPOR where hATM = pressure of containment atmosphere hSTATIc = pressure due to height of water above pump suction hLOSSES = pressure losses in piping, fittings, and screens hVApoR = vapor pressure of pumped fluid NRC Guidance On NPSH 1970 Regulatory Guide 1.1 Guidance on NPSH
....adequate NPSH is provided to system pumps assuming maximum expected temperatures of pumped fluids and no increase in containment pressure from that present prior to postulated LOCAs.
1974 Regulatory Guide 1.82 Guidance on PWR Sump Design The available surface area in determining the design coolant velocity [at the entrance to the sump screen] should be based on one-half of the free surface area of the ... inner screen...
NRC Guidance On NPSH (CONT.)
1981 SRP 6.2.2 Rev 4 Containment Heat Removal Systems for BWRs: hatm =0 for PWRs: hatm = hvAPoR, or, hatm 0 NPSH analysis will be acceptable if it is done in accordance with ...Regulatory Guide 1.1, i.e., is based on maximum expected temperature of the pumped fluid and with atmospheric pressure in containment.
SRP 6.2.2 allows overpressure credit for subatmospheric containments during the first hour following a LOCA.
NRC Guidance On NPSH (CONT.)
1985 GL 85-22 (GSI A-43) LOCA Debris Guidance h,0SS increases No backfit; consider for modifications Regulatory Guide 1.82 Rev 1 Issued.
Fibrous insulation debris should be considered as uniformly distributed over the available debris screen area Did not address containment conditions assumed in determining NPSH, only design of sumps and ECCS suction strainers NRC Guidance On NPSH (CONT.)
1996 BULLETIN 96-03 BWR ECCS STRAINER BLOCKAGE hlss increases Result of the 1992 Barseback event (strainer blockage).
BWRs should Install Suction Strainers. Results in greater pressure losses Increased suction losses due to larger strainers and consideration of debris NRC Guidance On NPSH (CONT.)
1997 GL 97-04 Request for information on NPSH Calculations for containment heat removal and ECCS pumps including credit for containment overpressure.
BWRs and PWRs.
Prompted by credit for overpressure w/o prior NRC review and approval.
Reviews of all operating reactors performed.
Criteria developed for the review allowed credit for containment overpressure. These criteria were not documented at this time.
NRC Guidance On NPSH (CONT.)
All BWR NPSH calculations revised as a result of Bulletin 96-03. Some BWRs received credit for overpressure. Some BWRs licensed with credit for overpressure and the credit for overpressure was increased. Some BWRs did not need overpresssure in order to comply with Bulletin 96-03.
2003 Bulletin 2001-03 Guidance on PWR Sump Blockage Some PWR licensees may request credit for containment overpressure to compensate for higher head losses RG 1.82 Rev 3 Guidance ECCS and containment heat removal systems should be designed so that sufficient available NPSH is provided to system pumps assuming maximum expected temperature and no increase in containment pressure from that present prior to LOCA For certain operating reactors for which the design cannot be practicably altered, conformance with the previous position may not be possible. In these cases, no additional containment pressure should be included in NPSH analyses than necessary to preclude pump cavitation.
For certain operating reactors for which the design cannot be practicably altered, credit may be taken for pump tests which demonstrate that a cavitating pump will continue to deliver the design basis flow rate. The time period is no longer than that of the test.
Risk Consideration A risk calculation is performed using realistic input values and assumptions.
Vermont Yankee personnel indicate that when using realistic input and assumptions, no credit for containment overpressure is required.
Therefore, risk increase is negligible.
Risk Consideration (Cont)
A staff calculation using the VY IPE and SPAR model calculated the probability of the loss of containment accident pressure This was determined as (LOCA probability)(Probability of failure of containment isolation)
It was assumed that loss of overpressure is equivalent to loss of ECCS pumps and therefore core damage.
ACDF = 1.3E-07 = lALERF THIS IS SMALL AND ACCEPTABLE ACCORDING TO RG 1.174 Proposed Modified Position Credit for overpressure is allowed when a conservative calculation demonstrates that sufficient containment pressure is available No test of "necessity" or specific cause of the NPSH deficiency is part of the criteria for allowing credit for containment overpressure.
No limit is placed on the amount of pressure that may be assumed available as long as the pressure is determined conservatively.
Plan For Re-evaluating Credit For Containment Accident Pressure
- 1. Withdraw RG 1.1
- 2. Modify RG 1.82 Rev 3 to reflect the modified position
- 3. Modify SRP 6.2.2 to reflect modified position