|
|
| Line 24: |
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| ==SUMMARY== | | ==SUMMARY== |
| OF MEETING WITH PHILADELPHIA ELECTRIC COMPANY PROPOSED SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AT THE PEACH BOTTOM FACILITY Introduction On June 14, 1985, the NRC staff met with representatives of Philadelphia Electric Company (the licensee) in Bethesda, Maryland to further discuss the proposed Peach Bottom Safety Parameter Display System (SPDS). The list of participants is included as Enclosure 1. | | OF MEETING WITH PHILADELPHIA ELECTRIC COMPANY PROPOSED SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AT THE PEACH BOTTOM FACILITY Introduction On June 14, 1985, the NRC staff met with representatives of Philadelphia Electric Company (the licensee) in Bethesda, Maryland to further discuss the proposed Peach Bottom Safety Parameter Display System (SPDS). The list of participants is included as Enclosure 1. |
| Discussion By letter dated April 3,1985, the NRC staff sent to the licensee a review of the Peach Bottom proposed SPDS based upon the staff's review of the licensee's submittals of September 28, 1983 and July 17, 1984 and an in-plant audit of the Peach Bottom SPDS. The licensee requested a follow-up meeting to further discuss the staff's findings and conclusions as addressed in the April 3,1985 transmittal and a telephone conference call. The NRC staff agreed to this meeting in order to provide the licensee with an opportunity to more fully describe the proposed SPDS and respond to the April 3,1985 transmittal. | | Discussion By {{letter dated|date=April 3, 1985|text=letter dated April 3,1985}}, the NRC staff sent to the licensee a review of the Peach Bottom proposed SPDS based upon the staff's review of the licensee's submittals of September 28, 1983 and July 17, 1984 and an in-plant audit of the Peach Bottom SPDS. The licensee requested a follow-up meeting to further discuss the staff's findings and conclusions as addressed in the April 3,1985 transmittal and a telephone conference call. The NRC staff agreed to this meeting in order to provide the licensee with an opportunity to more fully describe the proposed SPDS and respond to the April 3,1985 transmittal. |
| A summary of licensce's description of its proposed SPDS and responses to the staff's review is attached as Enclosure 2. | | A summary of licensce's description of its proposed SPDS and responses to the staff's review is attached as Enclosure 2. |
| The licensee's proposed SPDS is based upon the Emergency Procedure Guidelines (EPG) in place at Peach Bottom at the time of the design of the SPDS. Integration of all Nureg 0737, Supplement I goals was basis of the proposed SPDS at Peach Bottom. The proposed SPDS under review by the staff would be replaced in 1990 by an updated SPDS in connection with the installation of upgraded process control computer. | | The licensee's proposed SPDS is based upon the Emergency Procedure Guidelines (EPG) in place at Peach Bottom at the time of the design of the SPDS. Integration of all Nureg 0737, Supplement I goals was basis of the proposed SPDS at Peach Bottom. The proposed SPDS under review by the staff would be replaced in 1990 by an updated SPDS in connection with the installation of upgraded process control computer. |
|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
ML20196A2161988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
IA-88-478, Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting1988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20203M9431986-04-25025 April 1986
Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20203E8051986-04-18018 April 1986
Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20137Y5861986-03-0404 March 1986
Summary of Nrc/Idcor 851210 Meeting Re Preliminary Results & Differences of Risk Analysis for Facilities.Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20141K0981986-01-14014 January 1986
Summary of 851219 Meeting W/Util in Bethesda,Md Re Shroud Head Bolt Cracks & RHR Wear Ring Cracks.List of Meeting Attendees & Viewgraphs Encl
ML20141K0461986-01-0808 January 1986
Summary of 851031 Meeting W/Util in Bethesda,Md Re IGSCC Cracking.List of Meeting Attendees & Viewgraphs Encl. Viewgraphs Withheld
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20205E7101985-10-0909 October 1985
Summary of 851001 Meeting W/Util & GE in Bethesda,Md Re Cracking Identified in 316 L Grade Stainless Steel Recirculation Outlet Safe Ends.Proprietary Viewgraphs Encl. Viewgraphs Withheld (Ref 10CFR2.790)
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
1998-12-15
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20203M9431986-04-25025 April 1986
Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20203E8051986-04-18018 April 1986
Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20137Y5861986-03-0404 March 1986
Summary of Nrc/Idcor 851210 Meeting Re Preliminary Results & Differences of Risk Analysis for Facilities.Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20141K0981986-01-14014 January 1986
Summary of 851219 Meeting W/Util in Bethesda,Md Re Shroud Head Bolt Cracks & RHR Wear Ring Cracks.List of Meeting Attendees & Viewgraphs Encl
ML20141K0461986-01-0808 January 1986
Summary of 851031 Meeting W/Util in Bethesda,Md Re IGSCC Cracking.List of Meeting Attendees & Viewgraphs Encl. Viewgraphs Withheld
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20205E7101985-10-0909 October 1985
Summary of 851001 Meeting W/Util & GE in Bethesda,Md Re Cracking Identified in 316 L Grade Stainless Steel Recirculation Outlet Safe Ends.Proprietary Viewgraphs Encl. Viewgraphs Withheld (Ref 10CFR2.790)
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20133E5661985-10-0303 October 1985
Summary of 850905 & 17 Meetings W/Util in Bethesda,Md Re Recent Detection of IGSCC on Recirculation & RHR Sys Piping & Cracks on Core Spray Line,Respectively.List of Participants & Presentation Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
1998-12-15
[Table view] |
Text
,
' e .. g " 2 1985 M SD(
Dockets Nos. 50-277 and 50-278 LICENSEE: Philadelphia Electric Company FACILITY: Peach Bottom Atomic Power Station, Units 2 and 3
SUBJECT:
SUMMARY
OF MEETING WITH PHILADELPHIA ELECTRIC COMPANY PROPOSED SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AT THE PEACH BOTTOM FACILITY Introduction On June 14, 1985, the NRC staff met with representatives of Philadelphia Electric Company (the licensee) in Bethesda, Maryland to further discuss the proposed Peach Bottom Safety Parameter Display System (SPDS). The list of participants is included as Enclosure 1.
Discussion By letter dated April 3,1985, the NRC staff sent to the licensee a review of the Peach Bottom proposed SPDS based upon the staff's review of the licensee's submittals of September 28, 1983 and July 17, 1984 and an in-plant audit of the Peach Bottom SPDS. The licensee requested a follow-up meeting to further discuss the staff's findings and conclusions as addressed in the April 3,1985 transmittal and a telephone conference call. The NRC staff agreed to this meeting in order to provide the licensee with an opportunity to more fully describe the proposed SPDS and respond to the April 3,1985 transmittal.
A summary of licensce's description of its proposed SPDS and responses to the staff's review is attached as Enclosure 2.
The licensee's proposed SPDS is based upon the Emergency Procedure Guidelines (EPG) in place at Peach Bottom at the time of the design of the SPDS. Integration of all Nureg 0737, Supplement I goals was basis of the proposed SPDS at Peach Bottom. The proposed SPDS under review by the staff would be replaced in 1990 by an updated SPDS in connection with the installation of upgraded process control computer.
The NRC staff agreed that further review of the Peach Bottom SPDS was warranted based upon the licensee's presentation and the fact that the licensee was in the planning stages to install a new process control ccmputer and associated computer assisted SPDS. The licensee was asked to respond to the the staff's April 3,1985 transmittal as well as include documentation on the status of the new process computer (e.g., time frame, costs, individual SPDS versus integrated SPDS with new process computer etc.).
8507190422 850702 PDR ADOCK 05000277 F PDR-
~
^*
The licensee agreed to submit the above information in support of its proposed SPDS as interim compliance to Nureg-0737, Supplement 1 prior to the installation of a new process control computer and associated SPDS.
%'..wi ;.I: :.
Gerald E. Gears, Project Manager Operating Reactors Branch #4 Division of Licensing
Enclosures:
- 1. List of Attendees
- 2. The Licensee's Sumary cc w/ enclosures:
See next page i
f
MEETING
SUMMARY
DISTRIBUTION Licensee: Philadelphia Electric Company
" Copies also sent to those people or service (cc) list for subject plant (s).
kE ket @
fl R C P D R L PDR ORB #4 Rdp Project Manager - G Gears JStolz B Grimes (Emerg. Preparedness only)
OELD EJordan, IE A C R S-10 P Morriette N R C Meetinc
Participants:
L Beltracchi SWeiss 11Regan JMazetis illicC oy 11 Ken nedy
Enclosure 1
(
SPDS MEETING JUN 14, 1985 Name O roa nization Telep hone Gerald Gears Project Manager /N RC/DL 301-492-8362 Wes Bowers Supervising Engr./PEco 215-841-4602 W. T. Ullrich Supervising /Nucl. Generat. Divis. 215-841-5593 L. Beltracchi NRC/DHFS 301-492-4879 S. Weiss NRC/DHFS 301-492-4875 i
l U. Regan N R C/D H FS 301-492-4813 Jerry Mazetis NRC/DHFS 301-497-7254 fiike McCoy NRC/DHFS 301-492-9692 l W. Kennedy NRC/DHFS 301-492-4578 W. Birley PECo-Licensing Engineer 215-P41-5048 l
l l
l l
l l i i
l l
I
F- .
PEACH BOTTOM APS UNITB 2 AND 3 SAFETY PARAMETER D I SPL. AY SYSTEM
f- .
AGENDA LICENSING STATUS DISCUSSION OF EPG IMPLEMENTATION REVIEW OF PEACH BOTTOM DESIGN DISCUSSION OF ISSUES
-RELIABILITY VS. VALIDATION
-PARAMETER SELECTION
-OPERATOR USE OF SPDS FUTURE ACTION
F -
l I
i 1
l l
LICENSING STATUS I
- NUREG-0737, SUPPLEMENT 1 I
ISSUED 12/82
- SAFETY EVALUATION SUBMITTED
- NRC REQUESTED ADDITIONAL INFORMATION 5/B4 l
- ADDITIONAL INFORMATION BUBMITTED 7/B4
- RESPONSE TO FINDINGS PREPARED BUT NOT ISSUED i
i
NRC FINDINGS
- MONITOR ADDITIONAL VARIABLES
- PROVIDE MORE EFFECTIVE VALIDATION
- INCORPORATE HUMAN FACTORS PRINCIPLES
- JUSTIFY ISOLATION BETWEEN CLASS 1E AND NON-CLASS 1E CIRCUITS
F -
REQUIREMENTS IN NUREG-0737
- COMMERCIAL SRADE EQUIPMENT ACCEPTABLE
- OPERATORS TRAINED TO RESPOND WITH OR WITHOUT SPDS
- HUMAN FACTORS PRINCIPLES APPLIED TO DISPLAY
- PROMPT IMPLEMENTATION DESIRED
F .
-REACTIVITY CONTROL
-CORE COOLING AND HEAT REMOVAL
-REACTOR COOLANT SYSTEM INTEGRITY
-RADIOACTIVITY CONTROL
-CONTAINMENT CONDITIONS
- ~
- SPECIFIC PARAMETERS SELECTED a
BY LICENSEE
- ANALYSIS REQUIRED TO JUSTIFY SELECTED PARAMETERS I
SPDS AT PEACH BOTTOM
- USES STRIP-CHART RECORDERS AND VALVE POSITION LIGHTS AT TWO LOCATIONS
- HIGHLY RELIABLE INDICATION
- VARIABLES BELECTED ARE TRIP ENTRY CONDITIONS
- FULLY OPERATIONAL AFTER REACTOR PRESSURE INDICATION ADDED
- CRDR TO PROVIDE ENHANCEMENTS
-NEW LABLES
-ZNDICATORS COLOR CODED
-OUT-OF-NORMAL LIMITS COLOR CODED I
- OPERATORS TRAINED AS PART OF TRIP TRAINING i
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FIGURE 1 SPDS ARRANGEMENT ( .og) 1
< 67" #
i A
Wi 5 1~ 2,3,4,5 6 90" l
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CORE CORE PCIS SPRMr RHR MSIV ADS CAD CAD RCIC HPCI RHR REAY 1
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V Approximate Scale 1" =25" SPDS Indicators
- 1. Drywell Temperature Recorder (0 to 240 F). l
- 2. Suppression Pool Level Recorder (1 to 21 feet) .
- 3. Suppression Pool Temperature Recorder (30 to 230 F).
- 4. Drywell Pressure Recorder (5 to 25 psia and 0 to 225 psig).
- 5. Reactor Water Level Recorder (-165 to +50 inches and -325 to 0 inches).
- 6. Group I Isolation Valve Position Lights (Open/Close).
- 7. Reactor Pressure (0 to 1500 psig).
i
-. . - . - .- . - . . . _ . - . . . _ - . . = . _ - - _
- _.. . . . _ . - . - _ _ - _ _ ~ . .- .. -. - - - .. ..
r SPDS Design and Qualification j i
Safety Quality Periodically on-site Sensor Qualification Variable Related Assured Tested Power Seismic Environmental 1
Deactor water level Yes Yes Yes Yes Yes Yes Reactor pressure '.*e s Yes Yes Yes Yes Yes Drywell pressure Yes Yes Yes Yes Yes Yes .
I Drywell Temperature No No Yes Yes Yes Yes ,
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Suppression pool temperature Yes Yes Yes Yes Yes Yes !
i Suppression pool level Yes Yes Yes Yes Yes Yes j Group I isolation valve position Yes Yes Yes Yes Yes Yes l Neutron flux Note 1 Note 1 Yes Yes Yes Yes !
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NOTES l
- 1. All portions of the loop are safety related and quality assured except for the recorder.
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i i
DISCUSSION ITEMS PECO BELIEVES SPDS MEETS NUREG-0737 REQUIREMENTS PECO BELIEVES NRC REVIEW DONE WITHOUT CONSIDERING ALL SUBMITTALS
-NEUTRON FLUX MONITORED > +
-HUMAN FACTORS REVIEW INTEGRATED WITH CRDR
-ISOLATION INFORMATION PROVIDED
-PLANT-UNIQUE PROCEDURES USED IT APPEARS THAT GUIDANCE UPGRADED TO REQUIREMENTS
-VALIDATION IT APPEARS THAT NEW
{
REQUIREMENTS WERE IMPOSED
-SHIFT SUPERVISOR IS ONLY USER
-OFFSITE RELEASES MUST BE MONITORED
-SINGLE FAILURE CRITERIA I M P O S E D'.
RELIABILITY OF SPDS
- NUREG-0737 REQUIRES RELIABLE DISPLAY
- RELIABILITY REQUIREMENT MET
-SELECTED SAFETY-GRADE CRITERIA
-ALL PARAMETERS VALIDATED ON l
REDUNDANT DISPLAY
-ADDITIONAL VALIDATION POSSIBLE
- SRP 18.2 SUGGESTS USE OF ON-LINE VALIDATION TO MEET RELIABILITY REQUIREMENT
-NO CREDIT FOR " PEDIGREED" INSTRUMENTS
-APPEARS TO ELEVATE VALIDATION GUIDANCE TO A REQUIREMENT
-REDUNDANT DISPLAYS IN ONE FIELD OF VIEW
-APPEARS TO IMPOSE BINGLE FAILURE CRITERIA
SPDS PARAMETER SELECTION
- BASED ON ENTRY CONDITIONS FOR EMERGENCY PROCEDURES
-PLANT-UNIQUE TRIP PROCEDURES
-REVISION 2 OF EPGs
-REACTOR CONTROL
-CONTAINMENT CONTROL
- RADIATION RELEASE GUIDELINES NOT INCLUDED
-NOT PART OF TRIP PROCEDURES
-NUREG-0737 SAYS SPDS USED BY OPERATORS RESPONSIBLE FOR AVOIDANCE OF DEGRADED AND DAMAGED CORE EVENTS
-NUREG-0737 SAYS SPDS USED TO DETERMINE SAFETY STATUS OF PLANT AND ASSESS WHETHER ABNORMAL CONDITIONS WARRANT CORRECTIVE ACTION TO AVOID A DEGRADED CORE
PARAMETER SELECTION CCONT.)
-ADDITIONAL PARAMETERS REQUIRED APRM SRM AREA RADIATION CCONTAINMENT7)
PLANT VENT RADIATION CONTAINMENT HYDROGEN CFUTURE)
CONTAINMENT OXYGEN CFUTURE)
-APPEARS TO IMPOSE NEW REQUIREMENTS i
O OPERATOR USE OF SPDS
- NUREG-0737 SAYS USED BY OPERATORS RESPONSIBLE FOR AVOIDANCE OF DEGRADED AND DAMAGED CORE EVENTS
-SHIFT SUPERVISOR
-SENIOR REACTOR OPERATOR
-SHIFT TECHNICAL ADVISOR
-ONE REACTOR- OPERATOR
- PLANT UNIQUE IMPLEMENTATION
-OPERATOR AT PANEL COSA CONTROLLING REACTIVITY
-OPERATOR AT PANELS CO4B AND C, CO3, C484A AND B CONTROLLING ECCS
-SHIFT SUPERVISOR IN MIDDLE OF ROOM RECEIVING DATA AND LOOKING AT PROCEDURES
-STA HAS ACCESS TO DATA
-DISPLAYS ARE CONCISE FOR USER
-SIMULATOR EXPERIENCE SHOWS THIS WORKS WELL
USE OF SPDS CCONT-)
-REGIUIRES MORE CONCISE DISPt_AY
-REQUIRES SHIFT SUPERVISOR TO GATHER DATA
-APPEARS TO IMPOSE NEW REQUIREMENT I
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4I
_h
' o N O -
/ _,
-- op .
1
- f
' SHIFT SUPERVISOR WORKSTATION DURING EMERGENCIES
, h co3 ,
SPDS VARIABLES
- 1. DRYWELL PRESSURE
- 2. DRYWELL TEMPERATURE
- 3. SUPPRESSION POOL
> TEMPERATURE
- 4. SUPPRESSION POOL LEVEL F. REACTOR WATER LEVEL
- 6. REACTOR PRESSURE x
- 7. GROUP 1 CONTAINMENT ISOLATION VALVE POSITION
- 8. NEUTRON FLUX fAPRM)
BOTTOM --UNIT 2_ SPDS LAVOUT PEACH
F- . ,
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TABLE 1 1 Revised SPDS Parameter List Function Reactor Reactivity Reactor Core Coolant Radioact .vity Containment Control Cooling And System Control Conditions
'ISriable Heat Removal Integrity R rctor Water Level X X R rctor Pressure X X Drywall Pressure X X X X Drywall Temperature X Suppr aalon Pool Tcmpers,ture X Suppraccion Pool Lcval X Group I Containment Isolation Valva Position X X X NOutron Flux (APRM) X
