|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210A6941999-07-16016 July 1999 Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl ML20196J2351999-06-29029 June 1999 Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl ML20207H3531999-06-14014 June 1999 Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl ML20206U9041999-05-19019 May 1999 Summary of 990504 Meeting with EOI in Rockville,Maryland Re Integrated Nuclear Security Plan Being Proposed by EOI for All EOI Sites.List of Meeting Attendees & Copy of Meeting Presentation Matl Encl ML20205J6351999-04-0505 April 1999 Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl ML20207M9251999-03-11011 March 1999 Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20206S8501998-11-13013 November 1998 Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154A0271998-09-25025 September 1998 Summary of 980909-10 Meeting with Entergy Operations,Inc Re Implementation of risk-informed Inservice Insp Program. List of Attendees & Rept Prepared by Structural Integrity Associates,Inc Encl ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E1611998-08-25025 August 1998 Summary of 980728 Meeting W/Util in Rockville,Md Re Replacement of SG at ANO Unit 2.List of Attendees & Handouts Encl ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216B8551998-05-0707 May 1998 Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees ML20216B8511998-05-0606 May 1998 Summary of 980219 Meeting W/Entergy Operations,Inc in Rockville,Maryland Re Spent Fuel Pool Re-Rack & Spent Fuel Pool Cooling at Waterford Steam Electric Station,Unit 3 ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20203A3531998-01-29029 January 1998 Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl ML20199G7121997-11-0606 November 1997 Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20211A0161997-09-16016 September 1997 Summary of 970828 Meeting W/B&Wog Re Mgt of Aging Effects for Reactor Vessel Internals & Activities Related to Baffle Bolting Integrity Issues.List of Attendees & Their Affiliation & Handouts Encl ML20141D0881997-06-24024 June 1997 Summary of 970423 Meeting W/Licensee in Killona,La to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20141C6361997-06-24024 June 1997 Summary of 970321 Meeting W/Licensee in Rockville,Md to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20140H9181997-05-0909 May 1997 Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl ML20137W3311997-04-17017 April 1997 Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G4921996-08-29029 August 1996 Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105 ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058N4851993-12-15015 December 1993 Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl ML20058H0351993-12-0808 December 1993 Summary of 930830 Meeting W/Entergy Operations,Inc Re Operation of ANO-2 W/O SG Exam Until Mar 1994 Scheduled Refueling Outage.List of Attendees & Handouts Encl ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20057D1681993-09-27027 September 1993 Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl ML20056D9881993-08-0202 August 1993 Summary of 930715 Meeting W/Util Re Shutdown Cooling Alternatives During Next Refueling Outage.Attendance List & Handouts Encl ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20128F3481993-02-0202 February 1993 Summary of 920113 Meeting W/Util Re Commercial Grade Dedication at Plant ML20126G0721992-12-22022 December 1992 Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430 ML20126E7521992-12-14014 December 1992 Summary of 921119 Meeting W/Bg&E & SCE Re Document Retrieval Sys Development & Programs.List of Attendees Also Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058D5941990-11-0101 November 1990 Summary of 900912 Meeting W/Util Re Proposed Changes in Security Plan.List of Meeting Attendees Listed IR 05000313/19900081990-08-20020 August 1990 Summary of 900718 Meeting W/Entergy Operations,Inc in Arlington,Tx to Discuss Exercise Weaknesses Identified in Insp Repts 50-313/90-08 & 50-368/90-08 ML20055E9411990-07-0909 July 1990 Summary of 900621 Meeting W/Util Re Proposed Mods for Return to 100% Power.List of Attendees & Viewgraphs Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified 1999-07-16
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210A6941999-07-16016 July 1999 Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl ML20196J2351999-06-29029 June 1999 Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl ML20207H3531999-06-14014 June 1999 Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl ML20206U9041999-05-19019 May 1999 Summary of 990504 Meeting with EOI in Rockville,Maryland Re Integrated Nuclear Security Plan Being Proposed by EOI for All EOI Sites.List of Meeting Attendees & Copy of Meeting Presentation Matl Encl ML20205J6351999-04-0505 April 1999 Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl ML20207M9251999-03-11011 March 1999 Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20206S8501998-11-13013 November 1998 Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154A0271998-09-25025 September 1998 Summary of 980909-10 Meeting with Entergy Operations,Inc Re Implementation of risk-informed Inservice Insp Program. List of Attendees & Rept Prepared by Structural Integrity Associates,Inc Encl ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E1611998-08-25025 August 1998 Summary of 980728 Meeting W/Util in Rockville,Md Re Replacement of SG at ANO Unit 2.List of Attendees & Handouts Encl ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216B8551998-05-0707 May 1998 Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees ML20216B8511998-05-0606 May 1998 Summary of 980219 Meeting W/Entergy Operations,Inc in Rockville,Maryland Re Spent Fuel Pool Re-Rack & Spent Fuel Pool Cooling at Waterford Steam Electric Station,Unit 3 ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20203A3531998-01-29029 January 1998 Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl ML20199G7121997-11-0606 November 1997 Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20211A0161997-09-16016 September 1997 Summary of 970828 Meeting W/B&Wog Re Mgt of Aging Effects for Reactor Vessel Internals & Activities Related to Baffle Bolting Integrity Issues.List of Attendees & Their Affiliation & Handouts Encl ML20141D0881997-06-24024 June 1997 Summary of 970423 Meeting W/Licensee in Killona,La to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20141C6361997-06-24024 June 1997 Summary of 970321 Meeting W/Licensee in Rockville,Md to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20137W3311997-04-17017 April 1997 Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G4921996-08-29029 August 1996 Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105 ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058N4851993-12-15015 December 1993 Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl ML20058H0351993-12-0808 December 1993 Summary of 930830 Meeting W/Entergy Operations,Inc Re Operation of ANO-2 W/O SG Exam Until Mar 1994 Scheduled Refueling Outage.List of Attendees & Handouts Encl ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20057D1681993-09-27027 September 1993 Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl ML20056D9881993-08-0202 August 1993 Summary of 930715 Meeting W/Util Re Shutdown Cooling Alternatives During Next Refueling Outage.Attendance List & Handouts Encl ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20128F3481993-02-0202 February 1993 Summary of 920113 Meeting W/Util Re Commercial Grade Dedication at Plant ML20126G0721992-12-22022 December 1992 Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430 ML20126E7521992-12-14014 December 1992 Summary of 921119 Meeting W/Bg&E & SCE Re Document Retrieval Sys Development & Programs.List of Attendees Also Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058D5941990-11-0101 November 1990 Summary of 900912 Meeting W/Util Re Proposed Changes in Security Plan.List of Meeting Attendees Listed IR 05000313/19900081990-08-20020 August 1990 Summary of 900718 Meeting W/Entergy Operations,Inc in Arlington,Tx to Discuss Exercise Weaknesses Identified in Insp Repts 50-313/90-08 & 50-368/90-08 ML20055E9411990-07-0909 July 1990 Summary of 900621 Meeting W/Util Re Proposed Mods for Return to 100% Power.List of Attendees & Viewgraphs Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson 1999-07-16
[Table view] |
Text
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/ o UNITED STATES 6 !" '
% NUCLEAR REGULATORY COMMISSION
.( ,$. WASHINGTON, D. C. 20555
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MAY J g Lagg item 0RANDUM FOR: Scott Newberry, Chief Instrumentation & Control Systems Branch Division of Engineering & Systems Technology THRU: Jerry L. Mauck, Section Chief Instrumentation & Control Systems Branch Division of Engineering & Systems Technology FROM: Hulbert C. Li Instrumentation & Control Systems Branch Division of Engineering & Systems Technology
SUBJECT:
SUMMARY
OF MEETING WITH CE0G ON DIVERSE EMERGENCY FEEDWATER ACTUATION SYSTEM DESIGN IN ACCORDANCE WITH 10CFR50.62 REQUIREMENTS At the request of the CE Owners Group (ANO-2, Waterford 3, San Onofre 2&3), a meeting was held on May 1, 1989 in Rockville, Maryland. The purpose of the meeting was to discuss a conceptual design of the diverse emergency feedwater actuation system in accordance with 10CFR50.62 requirements. The CE0G's presentation outline is shown in Attachment 1. A list of attendees is shown in Attachment 2.
The CEOG submitted a report CEN-384 " Design for a Diverse Emergency Feedwater Actuation System " dated April 1989 on the Docket Nos. 50-361, 50-362, 50-368 and 50-382. This report was submitted in response to the NRC's previous denial on exemption requests with respect to 10CFR50.62 diversity requirements. The report describes a Non-Class 1E Diverse Emergency Feedwater Actuation System (DEFAS) that addresses the conformance to the requirements of 10CFR50.62.
A key design basis of the DEFAS is that the DEFAS would be required only upon failureoftheexistingPlantProtectionSystem(PPS)demandsforEmergency Feedwater and the initiation of the Diverse Scram system (DSS). The DEFAS would not interfere with accident mitigation function by the PPS.
The staff acknowledges the need for the PPS to override the DEFAS, however, the staff is questioning the timing of Emergency Feedwater under an ATWS event due to this adoitional DSS interlock in the DEFAS system. The staff needs further investigation on this subject.
The conceptual design will be applicable to ANO-2 and Sin Onofre 2 and 3.
The Waterford plant DEFAS, which is diverse from the PPS, will employ a 2-out-of-2 logic Class 1E subsystem added in the existing EFAS cabinets.
The DEFAS logic will also incorporate a steam generator (SG) high level S
gowoioD n %p
b Scott Newberry i input to protect the SG and the turbine from damage. The staff finds that the Waterford conceptual design is a valid ,npproach. However, the information in' Appendix B of the CEN-384 report is not sufficient to make a final e determination. .The Waterford licensee has agreed to provide more detailed -
information on their design in the near future.
'A key concern that was presented by CE0G was'their continual belief that the implementation of DEFAS could have a negative impact on plant safety. This was discussed at length but the concern was not resolved. The staff indicated that we would not accept any system design that would negatively impact safety ;
however the staff did not share the CEOG belief that DEFAS would have a negative <
safety impact. This will be the subject of continuing discussions in the near future.
A*J[ed
/
Cb Hulbert C. Li Instrumentation & Control Systems Branch Division of Engineering & Systems Technology
Enclosures:
As stated cc w/ enclosures:
A. Thadani W. Hodges J. Calvo-G. Knighton D. Lynch V. Thomas D. Hickman C. Poslusny D. Wigginton T. Chan A.Nolan(INEL) I i DISTRIBUTION: i l :ContralEFiles2 l l SICB RF PDR l LPDR l SNewberry l JMauck HLi SICB: DEST SICB: DESTf gg ,
HLi /ft fjy JMauck I Sh f/89 5////89 E________----___--__--___--- . _ - - - - - - - . - _ - - - - - - - - - - -J
Athchment- I ,
i' p
l' 1 L
C-E OWNERS GROUP (ANO-2, WATERFORD 3, SAN ONOFRE 2&3)
MEETING WITH THE NRC STAFF ON DIVERSE EMERGENCY FEEDWATER ACTUATION SYSTEM (DEFAS)
DESIGN IN ACCORDANCE WITH 10CFR50.62 l
MONDAY, MAY 1, 1989 I
4
. i TOPICS SECTION TITLE I. OVERVIEW II. EXISTING PPS EFAS DESIGN III. DIVERSE EFAS SYSTEM IV. DEFAS 10CFR50.62 COMPLIANCE V. REQUESTED AREAS OF NRC CONCURRENCE S
6
4 I. OVERVIEW INTENT OF THE MEETING IS TO DISCUSS THE TECHNICAL ISSUES ON THE DESIGN FOR A DIVERSE EMERGENCY FEEDWATER ACTUATION SYSTEM-(DEFAS) TO COMPLY WITH 10CFR50.62 ADDITIONAL DEFAS DESIGN DETAILS ARE PROVIDED IN CEOG DRAFT REPORT (CE-NPSD-384)
GOALS OF THE MEETING INCLUDE PROVIDING THE NRC STAFF WITH' ADDITIONAL INSIGHT INTO THE PROPOSED DEFAS IMPLEMENTATION, COMPLIANCE AND AREAS OF REQUESTED NRC CONCURRENCE b
'4 ..
II. EXISTING PPS EFAS DESIGN
~
PLANT PROTECTION SYSTEM (PPS) CONSISTS OF'
. REACTOR PROTECTIVE SYSTEM (RPS) AND ENGINEERED-SAFETY FEATURES ACTUATION SYSTEM (ESFAS)
THE EMERGENCY FEEDWATER ACTUATION SYSTEM (EFAS)
IS ONE'0F THE ESFAS SYSTEMS AND IS THE BASIS FOR THIS DESIGN EFFORT.
THE EFAS INITIATES EMERGENCY (AUXILIARY)
FEEDWATER TO THE INTACT STEAM GENERATOR (5)
FOLLOWING A LOW INVENTORY FOR WHATEVER REASON
- EFAS INITIATES USING A 2/4 LOGIC WHEN EITHER;
'SETPOINT 4
O_j
0 II. EXISTING PPS EFAS DESIGN (CONT.)
- THE INITIATING SIGNAL INTERFACES WITH THE AUXILIARY RELAY CABINETS (ARC) WHICH IN TURN INTERFACE AND ACTUATE THE VARIOUS EFAS COMPONENTS e
C
..y e4
, c F - -~ -- - -' - - - - 7 l OGGG l I
l _y v v v I l l Process l CABINET 5 l ,
l i Area 1 L _ __ _ _ _ ______J u
PPS CABINET (4CHAmEL5) r - -- p -----7
1 l AUXILIARY RELAY e I CABINETS I i 3 I Aree 2 L _ _. _ _ . -___--J v
POTOR CONTICL CENTElt PLDP5 VALVES
Title:
PPS GENERAL BLOCK DIAGRAM
o,.
[
SG-1 PitES$URE SG-2 PRE 551stE SG-! LEVEL SG 2 LEVEL TRANSMITTERS TRAIGNITTElts SEN50ft5 SEN505 I A I B IC 101 I A IB IC 101 IAIBICl01 I A IB IC lo l (l l t w 2 a A A PPS CABINET , l 4, Bt5 TABLES B15 TABLES 81 STABLES B15 TABLES
, , F F F e 3 i, l o o ) o o i )}q p }< ,<,,
2/4 LOGIC 2/4 LOGIC 2/4 LOGIC 2/4 LOGIC l INITIATION lELAY) ___n--i l
I INITIAT!:pf M Y I! T 1 r' g
g- '#- as.:g IQ1 i u+i ras-a I ras a pas-a a c m !ON as. ' I uns l ssata is ! I sans ssass I l ssaan ssaas l l ssana. ssus l g estrac1 act I i stact tortact 8 l tostact contac1 l lgg contac1 g
. . .J L _ - _ _ _ .I s. _ ___ J L. . --_ _.
k ( 2 EFAS-2 EFAS-1 EFAS-1 EFAS-2 AUX llELAY U i AUX ft[ LAY I' I' CABINET A CABINET B SELECT!yg SELECTIVE 2/4 L Ele 2/4 LOGIC e 4 ACTUATION ACTUATION RELAYS RELAYS
. o o MOTOR CONTROL CENTER #CTOR CONTROL CENTER TRAIN A TRAIN 8 4 4 I 4 EFAS TRAIN A EFAS TRAIN A EFAS 78ULIN 8 EFAS TRAIN 8 VALVE 5 PtAf5 YALVES PupF
Title:
PPS SYSTEM BLOCK DIAGRAM L
m-56-1 $G.2 $G-1 SG-2 fRl55 PRE 55 LEVEL LEVEL allih4L SfGhAL !GRAL IGNAL L 1r h p E o o u SG-1 LW $6-2 LW $G-3 > SG 2 SG-2 >$8 1 5G-3 Ubi $G-2 LW PRES $UE PRE 55URE PES $UM PK55uRE LEVEL LEVEL (s 750 PSI) (s 150 P51; (a P > 90) (aP>90) = 255 ' < 255 9 8 MMi uMM AND AND
%) %)
B B C C I I U4 U4 1r 1' EFAS-1 RELAY [FAS-2 RELAV TRfJN A TRAIN B TRAIN A TRAIN 8 CONTACT CONTACT CONTACT CONTACT lf 1f TO AAC TO ARC 70 ARC TO ARC A 8 A B
Title:
PPS EFAS SIGNAL LOGIC DIAGRAM - CHAMEL e
_____.___m-.__----------- - - - - - - - - - - - - - - - - - - - -
- c -
en I
l l
i l
l PPS TRIP PATM INITIATION RELAY CONTACTS y DC SUPPLY DC SUPPLY m, ,
tw n
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Title:
ESFAS AUX, RELAY CABINET EXISTING FUNCTIONAL LOGIC DIAGRAM
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III. DIVERSE EFAS SYSTEM A. PURPOSE THE PURPOSE OF THE DIVERSE EMERGENCY FEEDWATER ACTUATION SYSTEM (DEFAS) IS TO PROVIDE EQUIPMENT THAT COMPLIES'WITH THE REQUIREMENTS OF THE ATWS RULE, 10CFR50.62 THE DEFAS PROVIDES'FOR THE ACTUATION OF THE EMERGENCY FEEDWATER DURING AN ANTICIPATED OPERATIONAL OCCURRENCE (A00) REQUIRING EMERGENCY.FEEDWATER COINCIDENT WITH A FAILURE OF THE PLANT PROTECTION SYSTEM (PPS) AND -
INDICATION OF THE DIVERSE SCRAM SYSTEM (DSS) i
III. DIVERSE EFAS SYSTEM B. FUNCTIONAL REQUIREMENTS
- DEFAS MUST INITIATE EMERGENCY FEEDWATER FLOW FOR CONDITIONS INDICATIVE OF AN ATWS WHERE THE EFAS HAS FAILED.
THE DEFAS WILL NOT BE REQUIRED TO PROVIDE ACCIDENT MITIGATION SUCH AS ISOLATION FEED TO A RUPTURED STEAM GENERATOR.
DEFAS WILL SECURE FEEDING THE AFFECTED STEAM GENERATOR (S) UPON REACHING A PREDETERMINED LEVEL SETPOINT (APPROXIMATELY 30 MINUTES AFTER ACTUATION) FOLLOWING WHICH MANUAL OPERATOR INTERVENTION WILL CONTROL SYSTEM.
DEFAS WILL UTILIZE LOGIC AND REDUNDANCY TO ACHIEVE A 2-0UT-0F-2 INITIATION, AS A MINIMUM.
- DEFAS WILL UTILIZE STEAM GENERATOR LEVEL AS THE PARAMETER INDICATIVE OF THE NEED FOR EFAS ACTUATION.
III. DIV RSE EFAS SYSTEM B. FUNCTIONAL REQUIREMENTS (CONT.)
DEFAS WILL INTERFACE TO THE ACTUATED CGMPONENTS~
VIA THE EXISTING AUXILIARY RELAY CABINET (ARC)
RELAYS.
-- DEFAS WILL BE BLOCKED BY THE EFAS TO PREVENT CONTROL / SAFETY INTERACTIONS AND TO DISABLE DEFAS WHEN THE EFAS SYSTEM ACTUATES.
DEFAS WILL BE BLOCKED BY THE MSIS SIGNAL TO PREVENT CONTROL / SAFETY INTERACTIONS AND TO .
DISABLE THE DEFAS WHEN CONDITIONS FOR MSIS EXISTS.
4
- DEFAS WILL BE ENABLED BY AN ENABLE SIGNAL, INDICATING DSS ACTUATION, FROM THE DIVERSE l SCRAM SYSTEM (DSS).
- DEFAS WILL INCLUDE TESTING CAPABILITIES THAT ALLOW TESTING TO OCCUR AT POWER.
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III. DIVERSE EFAS SYSTEM B. FUNCTIONAL REQUIREMENTS- (CONT.)
DEFAS WILL INCLUDE FEATURES THAT PROVIDE ANNUNCIATOR, PLANT COMPUTER AND OPERATOR INTERFACE TO ALLOW FOR SYSTEM STATUS AND OPERABILITY REQUIREMENTS.
DEFAS SETPOINTS WILL BE LOWER THAT THE PPS SETF0INTS S0 THAT A RACE CONDITION BETWEEN THE PPS AND DEFAS MAY BE PREVENTED.
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--- - _ _ . - . _ _ - - _ _ . - - ____. _____________________________________1
4 III.DIVIRSEEFASSYSTEM-C. SYSTEM INTERFACES SENSORS
- EXISTING NARROW RANGE SENSORS
- EXISTING POWER IN PROCESS CABINETS TO -
POWER FIBER-OPTIC ISOLATORS DEFAS HARDWARE
- CONTROL GRADE EQUIPMENT l
- TWO (2) PLC's RECEIVE IDENTICAL SIGNALS
- UNINTERRUPTABLE POWER SUPPLY
- III. DIVERSE EFAS SYSTEM C. . SYSTEM INTERFACES (CONT.)
- DEFAS HARDWARE (CONT.)
- FIBER-OPTIC COMMUNICATION WITH AUXILIARY RELAY CABINET DISTRIBUTED I/O SYSTEM DEFAS LOGIC
- PLC #1 TRIPS ARC TRIP LEG 1 - 3
- PLC #2 TRIPS ARC TRIP LEG 2 - 4
- TESTING AT POWER CAPABILITIES
- EACH PLC GENERATES TWO OUTPUTS:
DEFAS 1 AND DEFAS 2
- TRANSMISSION OF DEFAS 1 AND DEFAS 2 OVER SERIAL FIBER-OPTIC LINKS TO ARC 4
9
- - - - _ . _ _ _ _ _ _- _ _ _ _ _ _ - - _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ - - - - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
III. DIVERSE EFAS SYSTEM C. SYSTEM INTERFACES (CONT.)
- AUXILIARY RELAY CABINET
- DEFAS RELAYS CONTROL CYCLING RELAY TRIP LEGS i
- INDICATOR PANEL FOR TESTING AND RELAY INDICATION
- BLOCKING LOGIC TO DISABLE DEFAS WHEN PPS FUNCTIONING NORMALLY S
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DEFAS/PPS GENERAL BLOCK DIAGRAM
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Title:
l ESFAS AUX RELAY CABINET SIMPLIFIED FUNCTIONAL DIAGRAM
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- - - - - - - -________--__________________________L
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III.DIVkRSEEFASSYSTEM D. . WATERFORD 3 PLANT SPECIFIC EFAS DESIGN 1
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IV. DEFAS'10CFR50.62 COMPLIANCE THE DEFAS HAS BEEN DESIGNED IN ACCORDANCE'WITH THE GUIDELINES SET FORTH IN 10CFR50.62
' GUIDELINE COMPLIANCE INCLUDES; A. SAFETY CLASSIFICATION
- DEFAS IS A NON-SAFETY RELATED CONTROL GRADE SYSTEM THAT INTERFACES WITH'OTHER SAFETY RELATED SYSTEMS THROUGH QUALIFIED ISOLATORS B. REDUNDANCY
- DEFAS IS NOT REQUIRED TO CONTAIN REDUNDANCY -
C. SEPARATION FROM EXISTING REACTOR TRIP SYSTEM ;
- DEFAS IS ISOLATED THROUGH QUALIFIED ISOLATORS AND IS ELECTRICALLY AND PHYSICALLY SEPARATED FROM THE EXISTING REACTOR TRIP SYSTEM D. ENVIRONMENTAL QUALIFICATION
- DEFAS IS ENVIRONMENTALLY QUALIFIED FOR A00 CONDITIONS 9
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IV. DEFAS IOCFR50.62 COMPLIANCE (CONT.)
E. SEISMIC QUALIFICATION
- DEFAS IS NOT REQUIRED TO BE SEISMICALLY QUALIFIED F. QUALITY ASSURANCE
- DEFAS WILL BE DESIGNED AND MANUFACTURED
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CONSISTENT WITH SUITABLE QUALITY ASSURANCE PROCEDURES G. SAFETY RELATED POWER SUPPLY
- DEFAS LOGIC IS POWERED BY BATTERY BACKED NON-SAFETY RELATED POWER SUPPLIES -
H. TESTABILITY AT POWER
- DEFAS DESIGN SUPPORTS TESTING AT POWER I. DIVERSITY FROM EXISTING REACTOR TRIP SYSTEM
- DEFAS IS DIVERSE FROM THE EXISTING REACTOR TRIP SYSTEM CONSISTENT WITH THE IOCFR50.62 GUIDANCE i
i 4
IV. ' DEFAS 10CFR50.62 COMPLIANCE (CONT.)
J. ELECTRICAL INDEPENDENCE
- DEFAS IS ELECTRICALLY INDEPENDENT FROM THE EXISTING REACTOR TRIP SYSTEM I. INADVERTENT ACTUATION
- DEFAS IS DESIGNED TO MINIMIZED INADVERTENT ACTUATIONS W
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4 V. REQUESTEDAREASOFNRCCONCURRENCE SEVERAL SAFETY RELATED IMPLICATIONS HAVE BEEN IDENTIFIED DURING THE DESIGN OF THE DEFAS THAT NEED TO BE ADDRESSED BASED ON THE PRESENT STATE OF DESIGN THE FOLLOWING IMPLICATIONS HAVE BEEN DEVELOPED; CONTROL SYSTEM INTERACTIONS FUNCTIONAL DUPLICATION ISOLATION OF RUPTURED STEAM GENERATOR OPERATOR ACTION
-/ POWER SOURCES n;;-
INADVERTENT ACTUATION -
SEPARATION FROM EXISTING SYSTEM
-/ TECHNICAL SPECIFICATIONS l THESE AND POSSIBILITY OTHER AREAS OF THE DEFAS DESIGN i
WILL REQUIRE NRC FLEXIBILITY IN THE REVIEW PROCESS PRIOR TO THE INSTALLATION OF A DEFAS I
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l IS01.ATION OF A RUPTURED STEAM GENERATOR ,
DEFAS HAS NO ISOLATION LOGIC STEAMLINE BREAK INSIDE CONTAINMENT INADVERTENT ACTUATION JUST PRIOR TO STEAMLINE BREAK DURING A STEAM GENERATOR TUBE RUPTURE BEST ESTIMATE ANALYSIS CEPAC COMPUTER CODE USED ON PC STEAMLINE BREAK INSIDE CONTAINMENT WITH AND WITHOUT DEFAS ACTUATION SGTR WITH DEFAS MISOPERATION
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STEAMLINE BREAK RESULTS MORE RAPID C00LDOWN OF PRIMARY 0 MODERATOR FEEDBACK 0 DNB CONCERNS 0 RETURN TO POWER 0 INCREASE IN CONTAIMENT PRESSURE ESTIMATED APPROXIMATELY 2 PSI 4
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I STEAM GENERATOR TUBE RUPTURE RESULTS LOSS OF LEVEL INDICATION BEFORE 30 MINUTES SG NEARLY FULL AT 30 MINUTES (1 TUBE)
MULTIPLE TUBES FILL GENERATOR BEFORE 30 MINUTES WATER IN STEAM LINE - SLB POSSIBLE l'
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v CONCLUSIONS ON DEFAS MISOPERATION 0 STEAMLINE BREAK IS WORSE O CONTAINMENT PRESSURE IS HIGHER 0 POSSIBILITY OF SG OVERFILL INCREASED I
0 INADVERTENT ACTUATION PRIOR TO SLB WORSENS CONTAINMENT PRESSURE
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