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Category:Report
MONTHYEARML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 ML23325A1612023-10-26026 October 2023 Relief Request 70 - Proposed Alternatives in Accordance with 10 CFR 50.55a(z)(1) for Pressurizer Lower Shell Temperature Nozzle ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study ML21077A2562021-03-18018 March 2021 El Paso Electric Co., Application for Approval of Indirect Transfer of Control of Licenses Pursuant to 10 C.F.R. 50.80 and 72.50 ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML19136A4092019-05-16016 May 2019 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2018 ML19046A3512019-02-15015 February 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R21 ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML17181A5152017-06-29029 June 2017 Flooding Focused Evaluation Summary ML17248A5262017-05-30030 May 2017 3INT-ISI-3, Revision 4, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 3, Enclosure 3 to 102-07551-MDD/MSC ML17006A2172017-01-0505 January 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R19 ML16306A4442016-11-14014 November 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML16321A0032016-10-31031 October 2016 WCAP-18030-NP, Revision 1, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3. ML16221A6042016-09-13013 September 2016 Staff Assessment of Information Provided Under Title 10 of Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of Near-Term Task Force Review of Insights from . ML16120A3892016-04-28028 April 2016 1-SR-2016-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML15336A0842015-11-30030 November 2015 NET-300047-07 Revision 1, Material Qualification Report of Maxus for Spent Fuel Storage. ML15188A0492015-06-30030 June 2015 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R18 ML15111A4302015-04-17017 April 2015 Attachments 2 & 3: Flaw Fracture Mechanics, Corrosion & Loose Parts Evaluations for One Cycle Relief (DAR-MRCDA-15-6-NP) and APS Response to NRC Request for Additional Information Dated April 14, 2015 ML15076A0732015-03-10010 March 2015 Seismic Hazard and Screening Report ML15012A4462015-01-0606 January 2015 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R18 ML15027A1222014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61 ML14184B3822014-06-27027 June 2014 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R18 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14126A6362014-04-30030 April 2014 APS Supplement to the Seismic Walkdown Report Requested by the NRC Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1, 2.3, and 9.3 of the Near-Term Task Force. ML14087A1882014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML14034A1472014-01-24024 January 2014 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U3R17 ML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. ML13252A1112013-08-31031 August 2013 WCAP-17680-NP, Supplement 1, Rev. 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information. CY-12-009, Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance ML13120A5032013-04-10010 April 2013 Technical Requirements Manual, Revision 57 ML1307003422013-02-28028 February 2013 APS Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML13022A4072013-01-14014 January 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report for Unit 2 Refueling Outage 17 (U2R17) ML12355A7482012-12-31031 December 2012 Evacuation Time Estimate Study; Cover Through Section 4 ML12355A7512012-12-14014 December 2012 Evacuation Time Estimate Study; Section 5 Through 12 ML12355A7522012-12-14014 December 2012 Evacuation Time Estimate Study; Appendix a Through H ML12278A1002012-09-0707 September 2012 Pressurized Water Reactor (PWR) Internals Aging Management Program Plan ML12229A1192012-08-0303 August 2012 Attachment 4, PVNGS Engineering Study 13-ES-A037, Revision 0, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS) ML12229A1202012-08-0303 August 2012 Attachment 5, PVNGS Engineering Study 13-NS-C089, Revision 0, PRA Evaluation of LPSI Pump Failing to Trip on RAS 2024-04-12
[Table view] Category:Technical
MONTHYEARML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML23325A1612023-10-26026 October 2023 Relief Request 70 - Proposed Alternatives in Accordance with 10 CFR 50.55a(z)(1) for Pressurizer Lower Shell Temperature Nozzle ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML17248A5262017-05-30030 May 2017 3INT-ISI-3, Revision 4, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 3, Enclosure 3 to 102-07551-MDD/MSC ML16321A0032016-10-31031 October 2016 WCAP-18030-NP, Revision 1, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3. ML15336A0842015-11-30030 November 2015 NET-300047-07 Revision 1, Material Qualification Report of Maxus for Spent Fuel Storage. ML15076A0732015-03-10010 March 2015 Seismic Hazard and Screening Report ML15027A1222014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request ML14126A6362014-04-30030 April 2014 APS Supplement to the Seismic Walkdown Report Requested by the NRC Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1, 2.3, and 9.3 of the Near-Term Task Force. ML14087A1882014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. ML13120A5032013-04-10010 April 2013 Technical Requirements Manual, Revision 57 ML12355A7482012-12-31031 December 2012 Evacuation Time Estimate Study; Cover Through Section 4 ML12355A7512012-12-14014 December 2012 Evacuation Time Estimate Study; Section 5 Through 12 ML12355A7522012-12-14014 December 2012 Evacuation Time Estimate Study; Appendix a Through H ML12278A1002012-09-0707 September 2012 Pressurized Water Reactor (PWR) Internals Aging Management Program Plan ML12229A1192012-08-0303 August 2012 Attachment 4, PVNGS Engineering Study 13-ES-A037, Revision 0, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS) ML12229A1202012-08-0303 August 2012 Attachment 5, PVNGS Engineering Study 13-NS-C089, Revision 0, PRA Evaluation of LPSI Pump Failing to Trip on RAS ML1106107572011-01-26026 January 2011 PVNGS Technical Requirements Manual, Revision 54. List of Effective Pages ML1106107582011-01-26026 January 2011 Technical Requirements Manual, Revision 54 ML1021500372010-07-22022 July 2010 Engineering Study 13-MS-B094, Revision 0 ML1016607492009-05-0101 May 2009 Adeq 2009a Palo Verde Aquifer Protection Permit (Area Wide) No. P-100388. Issued by Arizona Dept of Environmental Quality. May 2009 ML0828200292008-10-0101 October 2008 Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0906410162008-06-30030 June 2008 WCAP-16835-NP, Rev. 0, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Basis for RCS Pressure and Temperature Limits Report. ML0810801162008-04-10010 April 2008 Request for Amendment to Technical Specification 3.5.5, Refueling Water Tank (RWT) to Increase the RWT Minimum Water Level Under Exigent Circumstances ML0719303162007-03-12012 March 2007 Chemical Effect Head Loss Test Specification ML0719303652007-03-0707 March 2007 CCI Chemical Laboratory Bench Top Test Rev 0 ML0626301802006-08-16016 August 2006 Request for Amendment to Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.9, 3.8.1.10, & 3.8.1.14 ML0617804692006-04-30030 April 2006 Enclosure 2D, Non-Proprietary, Redacted Westinghouse Response to NRC Request for Additional Information Regarding Technical Specification Improvement and Tubesheet Inspection Depth for Steam Generator Tubes ML0602005772006-01-13013 January 2006 Revised Redacted Version of Response to Information Request Dated February 24, 2005 ML0602005752006-01-13013 January 2006 Revised Redacted Version of Recirculation Sump Void Testing and Probabilistic Risk Assessment Preliminary Results Dated December 27, 2004 ML0534802032005-12-0505 December 2005 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0531203902005-10-28028 October 2005 Revised Station Blackout Evaluation ML0525601382005-07-0505 July 2005 Redacted Version of Proprietary Submittal Dated February 15, 2005 Regarding Safety Significance Evaluation of ECCS Containment Sump Voided Piping ML0517903492005-06-21021 June 2005 List of References Associated with ASME Code Case N-499 to Support NRC Review of Inservice Inspection (ISI) Program Relief Request No. 33 for Pressurizer Base Material Heating ML0519404732005-02-28028 February 2005 Attachment 2-E, DAR-OA-05-3, Revision 0, Report of SBLOCA Analyses with Degraded ECCS Flow After RAS Performed for Arizona Public Service in Support of Palo Verde Nuclear-Generating Station Units 1, 2, and 3 ML0505402582005-02-15015 February 2005 Attachment 2-F, 13-NS-C074, Rev 0, Significance Determination of Containment Sump Air Entrainment. ML0504503532005-02-0404 February 2005 Submittal of Redacted Version of Recirculation Sump Void Testing and Probabilistic Risk Assessment Preliminary Results ML0429603662004-07-0202 July 2004 Discussion and Proposed Resolution of NRC AIT URI (Unresolved Issue) Relating to MSIS Impact on AF-A Operability (6/14/04 Three Unit LOOP Trip). ML0424500452004-06-30030 June 2004 Reformatted Technical Report SIR-04-045, Revision 0, Supporting the Palo Verde Pressurizer Heater Sleeve Mid-Wall Repair ML0429603432004-06-28028 June 2004 Evaluation of CVCS Soft Parts Due to High Temperature Letdown Event. ML0412102272004-04-15015 April 2004 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report ML0316201772003-06-0404 June 2003 ISFSI, Registration of Dry Spent Fuel Transportable Storage Canister Identification No. AMZDFX003 & Report of Cask Performance ML0309806332003-04-0202 April 2003 Response to Request for Additional Information Regarding Relaxation Request to NRC Order EA-03-009 ML0233004122002-11-21021 November 2002 Supplement to Request for a License Amendment to Support Replacement of Steam Generators & Uprated Power Operations 2024-04-12
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Enclosure Response to Request for Additional Information, Review of Single Failure Analysis of Low Pressure Safety Injection Pumps for Minimum Required Refueling Water Tank Transfer Volume Attachment 5 PVNGS Engineering Study 13-NS-C089, Revision 0 PRA Evaluation of LPSI Pump Failing to Trip on RAS PALO VERDE NUCLEAR GENERATING STATION DOCUMENT TITLE SHEET Title /
Description:
PRA Evaluation of LPSI Pump Failing to Trip on RAS-. r I T T T 7 r T 7 r V 4 4 t 4- 4 4- 4 4 4 + + + + + 4 Original Issue LqUio ..ui" .N/A N/A N/A N/A N/A Hulet Mark N/A..........
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Document Electronically Available X Yes D No Cii le.I C Independent Other REV. REVISION Preparer RE Checker Mech. Civil Elec. I & C Verification (Specify Org.)NO. DESCRIPTION Date Date Date Date Date Date Date Date Date_CROSS DISCIPLINE REVIEW PRA Evaluation of LPSI Pump Failing to Trip on RAS Executive Summary The purpose of this study is to determine the potential additional risk posed by the failure of a Low Pressure Safety Injection Pump to trip on a Recirculation Actuation Signal, which may result in enough air drawn into the suction of the Emergency Core Cooling and Containment Spray Pumps to render them unavailable.
This is done in support of CRDR 2835132, which will change the licensing basis regarding the Refueling Water Tank design basis. The results of the analysis show that even a conservative estimation yields additional risk well below acceptance guideline values.No operator action is credited to close the RWT supply valves to the ECCS and CS headers.10 CFR 50.59 Applicability Determination A 10 CFR 50.59 Screening is not required for this study since it does not constitute a credited evaluation or method of evaluation as defined in NEI 96-07 Rev 1, Guidelines for IOCFR50.59 Implementation, Section 3.10, "Methods of Evaluation", in accordance with 93DP-OLC17 Rev 5 10 CFR 50.59 and 72.48 Guidance Manual, Section 2.1.6,"Qualifying Changes to Studies, Calculations and Analyses".
This document does not result in a change to a design output of any Engineering/NFM design basis analysis or calculation.
As a result of this evaluation, no design output document or design process documents will be changed. This study is not intended for alteration, impact or change of any design functions as stated in the Licensing Basis. This study is not intended to be used as design output, design input or design process documentation.
As such, there is no impact to the design functions stated in the Licensing Basis. Therefore, a 10CFR 50.59 screening and evaluation are not necessary.
This screening was performed by R.C. Lindquist.
13-NS-C089 Rev 0 Page 2 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS Table of Contents Executive Sum m ary .............................................................................................................
2 Table of Contents ............................................................................................................................
3 1.0 Introduction
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4 2.0 Requirem ents ....................................................................................................
4 3.0 Methodology
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5 4.0 Results and Conclusions
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5 5.0 References
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6 13-NS-C089 Rev 0 Page 3 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS 1.0 Introduction PRA performed a risk analysis to support a license amendment regarding a statement in the UFSAR regarding single failures associated with Recirculation Actuation Signal (RAS). Of concern is the induction of air due to vortexing at the entrance to the headers supplying Emergency Core Cooling System (ECCS) and Containment Spray (CS)pumps. Specifically, a concern arose that if a Low Pressure Safety Injection (LPSI)pump failed to trip upon RAS, RWT level could be drawn down enough to result in air entrainment in the pump suction before the available head from the containment sump would result in closure of the check valve in the RW-T headers (CHAV306 and CHBV305).
In 2005 Westinghouse, with support from Fauske Associates, performed a hydraulic analysis showing that with just the HPSI and CS pumps operating after RAS (per design), insufficient air gets far enough into the header to have any effect on the pumps (Ref. 5.1) for the full spectrum of LOCA break sizes and even down to -3 psig in the containment.
Though the analysis did not examine the LPSI pump failing to trip, it can be inferred that there is a higher potential for air induction due to the higher velocity of fluid in the RWT suction headers. However, failure of a LPSI pump to trip is a train-specific failure mechanism; there is no cross-train effect, since there is no communication between the two trains. Although operator action could be credited to close the RWT supply valves to the ECCS and CS suction headers before air is drawn in, it is conservatively neglected in this analysis.
Additionally, this failure mechanism is not of concern in the Small Break LOCA range, since RCS pressure remains high enough that sub-cooling is not lost, which means that there is no flow from LPSI.This study supports CRDR 2835132 and was done under ACT 3361768.2.0 Requirements A contractor (Exponent) performed a fault tree analysis to determine the probability of a LPSI pump failing to trip on RAS. Their report (Ref. 5.2) used failure data from the PRA data study, Ref. 5.3. Their analysis of the control circuit was thorough and includes all contacts and relays that need to function properly to achieve LPSI pump trip. There is a slight difference in Train A vs. Train B values, because the control circuit for Train B includes the additional Control Room remote disconnect switch for 1OCFR50 Appendix R compliance.
The 95th percentile values were determined in the Exponent study:* LPSI-A 2.98E-3* LPSI-B 3.13E-3 The range of break size of concern from (Ref. 5.4) is less than 0.5 sq-ft. However, as mentioned in Section 1, it also is of no concern in the Small Break LOCA range, because there will be no LPSI flow to the RCS, and even minimum flow recirculation is stopped on RAS. Therefore, the failure will be modeled as only applying to Medium and Large LOCAs.13-NS-C089 Rev 0 Page 4 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS The Rev. 16 combined internal events and fire model was used.3.0 Methodology To estimate the additional potential risk associated with a LPSI pump failing to trip, a new basic event was added to fail a train of ECCS and CS in the recirculation mode.Conservatively, the 9 5 th percentile value, rounded up to 3.2E-3, was used.In addition a common-cause failure was added using a conservative 0.1 screening value. The common-cause failure probability is then 3.2E-4.A new parameter, MP-FT, was created having a probability of 3.2E-3 (rounding up the 95th percentile failure probabilities determined by Exponent).
A new parameter, MP-FT-CC was created with a probability of 3.2E-4.New basic events, both of which use the parameter MP-FT were created: 4SIAP01 ---- MP-FT, 4SIBP01 ---- MP-FT A third basic event for common-cause failure is 4SIXPO1-CC-MP-FT using the parameter MP-FT-CC.Fault trees SUMPA1 and SUMPB1 were modified as shown in Figures 1 and 2. House event IE-LMLOCA causes the additional fault only to be applied for Medium and Large LOCAs.4.0 Results and Conclusions CDF1 = 4.979E-6/yr LERF1 = 2.282E-7/yr CDFO = 4.952E-6/yr LERFO = 2.282E-7/yr Delta CDF = 2.7E-8/yr Delta LERF = 0 Where CDF1 and LERF1 are the calculated values resulting from the changes above, and CDFO and LERFO are the documented combined internal event and fire CDF and LERF from the current PRA model, Rev. 16.Since this is associated with a change to the licensing basis, the guidance in Ref. 5.5 can be used to judge the significance of this additional failure mechanism.
It states that a change in CDF of less than 1 E-6/yr and a change in LERF of less than 1 E-7/yr are acceptable.
Therefore, this potential additional risk is not significant, even without crediting operator action to close the RWT supply valve (CHAHV531 or CHBHV530).
13-NS-C089 Rev 0 Page 5 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS 5.0 References 5.1 FAI-05/107, The Potential for Air Intrusion Following RAS 5.2 Engineering Study 13-EN-A037, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS)5.3 Engineering Study 13-NS-B063, PVNGS At-Power PRA Study for.Generic and Bayesian Updated Reliability Data Analysis 5.4 Westinghouse evaluation DAR-OA-07-2 (SDOC N001-1501-00008), Emergency Operating Procedure (EOP) Report to Support Early Termination of One Containment Spray Train 5.5 Regulatory Guide 1.174 Rev. 1, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis 13-NS-C089 Rev 0 Page 6 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS Figure I -Train A Sump CSA4 HR1 -1 LR1 7 13-NS-C089 Rev 0 Page 7 of 8 PRA Evaluation of LPSI Pump Failing to Trip on RAS Figure 2 -Train B Sump Insufficient Flow From CSB4 ESF Sump B HR2-1-\LR27 GSUK/FB1 13-NS-C089 Rev 0 Page 8 of 8