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| {{#Wiki_filter:The following table was developed using the current Model of Record (MOR), which is documented in the Peach Bottom Atomic Power Station (PBAPS) PRA Summary Notebook (PB-PRA-013, Revision 4). The table was developed using the EPRI R&R Workstation SysImp Computer code. It shows the top systems/groups of equipment to the overall CDF by Fussell-Vesely. SYSIMP Key System/Equipment Contribution to CDF System/Equipment Tag F-V High Pressure Coolant Injection HPCI 15.8% Condenser Vacuum TCV 11.8% Reactor Core Isolation Cooling RCIC 10.9% DC Power DC 10.1% AC Power AC 10.1% Emergency Diesel Generators EDG 7.9% Feedwater FW 7.1% Reactor Protection System RPS 5.7% High Pressure Service Water HPSW 4.8% Main Steam Isolation Valves MSIV 3.8% Emergency Cooling Tower/ Emergency Cooling Water ECT/ECW 2.2%}} | | {{#Wiki_filter:The following table was developed using the current Model of Record (MOR), which is documented in the Peach Bottom Atomic Power Station (PBAPS) PRA Summary Notebook (PB-PRA-013, Revision 4). The table was developed using the EPRI R&R Workstation SysImp Computer code. It shows the top systems/groups of equipment to the overall CDF by Fussell-Vesely. |
| | SYSIMP Key System/Equipment Contribution to CDF System/Equipment Tag F-V High Pressure Coolant Injection HPCI 15.8% |
| | Condenser Vacuum TCV 11.8% |
| | Reactor Core Isolation Cooling RCIC 10.9% |
| | DC Power DC 10.1% |
| | AC Power AC 10.1% |
| | Emergency Diesel Generators EDG 7.9% |
| | Feedwater FW 7.1% |
| | Reactor Protection System RPS 5.7% |
| | High Pressure Service Water HPSW 4.8% |
| | Main Steam Isolation Valves MSIV 3.8% |
| | Emergency Cooling Tower/ |
| | Emergency Cooling Water ECT/ECW 2.2%}} |
Latest revision as of 13:50, 20 October 2019
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Category:- No Document Type Applies
MONTHYEARML23192A1212023-07-0606 July 2023
FAQ 23-03 - Peach Bottom Unit 1 Unplanned Scram with Complications Interpretation
ML23136A6052023-05-12012 May 2023
FAQ 23-02 Peach Bottom Performance Indicator Interpretation Request
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(PBAPS) Unit 2, ISI Owner'S Activity Report for the 24th Refueling Cycle Covering ISI Activities Associated with the First Period of the 5th ISI Inspection Interval for Unit 2
RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020
Proposed Changes to Decommissioning Trust Agreements
ML20008D2232020-01-0808 January 2020
NRC Region I Twitter Feeds 10-1 to 12-31-2019
ML19247D2872019-09-0404 September 2019
Fws to NRC, Concurrence That Peach Bottom License Renewal Is Not Likely to Adversely Affect the Indiana Bat or Northern Long-eared Bat
ML18283B2782018-10-15015 October 2018
PBAPS PRA System Importance List
ML17128A0162017-05-0808 May 2017
May 3, 2017 Peach Bottom Attendance List for Public Meeting
ML16102A1152016-04-0606 April 2016
Aam Attendance List
ML15113A2982015-04-23023 April 2015
Aam Attendance List, April 2015
ML15097A1142015-04-0707 April 2015
Soarca Peach Bottom 2006 Meteorological File
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2015-03-0202 March 2015
Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML15071A1192015-03-0202 March 2015
Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML14153A5352014-05-29029 May 2014
May 29, 2014 Aam, Attendance List
ML15120A2292014-03-11011 March 2014
NRC Comments on Fpra FAQ 14-0007, Transient Fire Frequency Likelihood (4/30/2015)
ML13364A2832013-12-30030 December 2013
Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013
ML13211A4032013-07-30030 July 2013
EPU LAR Supplement 6 Attachment 2 - Response to Request for Additional Information - Snpb
ML13143A3312013-06-0606 June 2013
Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2
ML13133A1482013-03-0404 March 2013
Attendee List for Peach Bottom Aam on April 18, 2013
ML12056A0522012-03-12012 March 2012
Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML1127100332011-09-28028 September 2011
ROP Tabletop Examples and Results
ML11255A3402011-08-25025 August 2011
State-of-the-Art Reactor Consequence Analyses (Soarca), Peach Bottom Initial Information Needs
ML1117502192011-06-22022 June 2011
NRC Inspection Findings Related to Closed Cooling Water Systems (1/1/2004 to 6/22/2011)
ML1110801202011-04-13013 April 2011
Public Meeting Attendance List, April 13, 2011
ML1011100692010-04-20020 April 2010
PBAPS Aam Sign-in Sheets, April 19, 2010
ML1019304602010-03-25025 March 2010
List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants
ML1021103752010-03-0202 March 2010
Action Request Number: 00939717, Elevated Tritium Identified in New Sample Point
ML12024A0732009-03-31031 March 2009
Don Dube Comments; Soarca Secy and Associated Enclosures
ML12024A0742009-03-0909 March 2009
RES Response Comments; Don Dube Comments: Soarca Secy and Associated Enclosures
ML0903500432009-02-0303 February 2009
Peter Stockton Comments to NRC Public Meeting, 2/3/09
ML0816503082008-06-0909 June 2008
Annual Assessment Meeting, Sign-In Sheet
ML0815003772008-04-29029 April 2008
Summary of Enhanced Monitoring of Security, Regarding Peach Bottom'S Security Officers
ML0815003782008-04-29029 April 2008
Allegation Receipt Report, Regarding Allegation
ML0812702892008-03-24024 March 2008
Sign-in Sheet, Pb, Security Deviation Memo, 3/24/08
ML0806704192008-03-0707 March 2008
CDBI Findings
ML0804603992008-02-13013 February 2008
Power Reactor Inattentive Officer Findings 2004-Present
ML0803602952008-01-23023 January 2008
Talking Points on Transition from Wackenhut/Wcbs
ML0803600752008-01-23023 January 2008
Pennsylvania Senate Standing Committee Hearing Prep Book
ML0803600522008-01-23023 January 2008
AR 00673505 Report, Aff Fac: Peach Bottom, AR Type: CR
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0726303192007-09-14014 September 2007
P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List
ML0726301142007-09-14014 September 2007
/ P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170
ML0703000342007-01-12012 January 2007
Public Comments Submitted by E-mail: Eric Epstein, Three Mile Island Alert, Inc
ML0615101792006-05-30030 May 2006
FOL Pages Associated W/License Transfer DPR-44
ML0516401312005-05-27027 May 2005
Advisory Committee Reports to AEC on Safety Aspects of Two Reactor Projects
ML0516402382005-05-27027 May 2005
Paper Subject: Consultant to Dl&R, Graphite for Gas Cooled Reactors
ML0505404642004-02-0909 February 2004
Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants
ML0309304702003-03-18018 March 2003
Comments on Peach Bottom SER
2023-07-06
[Table view] |
Text
The following table was developed using the current Model of Record (MOR), which is documented in the Peach Bottom Atomic Power Station (PBAPS) PRA Summary Notebook (PB-PRA-013, Revision 4). The table was developed using the EPRI R&R Workstation SysImp Computer code. It shows the top systems/groups of equipment to the overall CDF by Fussell-Vesely.
SYSIMP Key System/Equipment Contribution to CDF System/Equipment Tag F-V High Pressure Coolant Injection HPCI 15.8%
Condenser Vacuum TCV 11.8%
Reactor Core Isolation Cooling RCIC 10.9%
DC Power DC 10.1%
AC Power AC 10.1%
Emergency Diesel Generators EDG 7.9%
Feedwater FW 7.1%
Reactor Protection System RPS 5.7%
High Pressure Service Water HPSW 4.8%
Main Steam Isolation Valves MSIV 3.8%
Emergency Cooling Tower/
Emergency Cooling Water ECT/ECW 2.2%
