|
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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 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 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 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 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 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 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 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 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 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 ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20195J4291988-11-29029 November 1988 Summary of 881118 Meeting W/Util in Rockville,Md Re Four Plant Startup Issues Including:Dhr Sys Shutdown Cooling Mode of Operation,Operability of Penetration Room Ventilation Sys & Operability of Nozzles in safety-related Piping Sys ML20206L9831988-11-25025 November 1988 Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl ML20205P2201988-10-26026 October 1988 Summary of 881018 Meeting W/Util in Rockville,Md Re Results of Inservice Insp of Casings of Reactor Coolant Pumps a & B & Request for Relief from ASME Code Requirements for Inspecting Reactor Coolant Pumps.Related Info Encl ML20204G4391988-10-12012 October 1988 Summary of 880908 Meeting W/Util in Arlington,Tx Re Previous Violation in Area of Contingency Response.Util Expressed Basis for Denial in Insp Rept 50-313/86-34.No New Requirements Imposed But Requirement Already in Place ML20151Q8131988-08-0303 August 1988 Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20150F2451988-06-29029 June 1988 Summary of 880607 Meeting W/Util in Little Rock,Ar Re B&W Owners Group Safety & Performance Improvement Program at Plant ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants ML20154S0341988-05-27027 May 1988 Summary of 880519 Meeting W/Middle South Utils Representatives Re Proposed Establishment & Licensing of Middle South Utils Nuclear Operating Co.Agenda Encl ML20154K9611988-02-0505 February 1988 Summary of 880204 Meeting Re Presentation Made by Allegheny Ludlum on Ferritic Stainless Steel E-Brite ML20237E0391987-12-0909 December 1987 Summary of 871026 Meeting W/Util Re Permanent Repairs to Pressurizer.List of Attendees & Licensee Handouts Encl ML20237B4671987-12-0909 December 1987 Summary of 871117 & 18 Meetings W/Util at Plant Site Re Licensee Inservice Testing Program.Licensee Committed to Resubmit Inservice Testing Program in May 1988,pending Closure of Open Items by 880101.List of Attendees Encl ML20237B4791987-12-0202 December 1987 Trip Rept of 871117 & 18 Visit to Plant Site Near Russellville,Ar Re Pump & Valve Inservice Testing Program. Program Changes Indicated in Response to Questions ML20236B0861987-10-15015 October 1987 Summary of 871007 Meeting W/Util Re Midcycle Outage on Facility.List of Attendees & Outline of Licensee Presentation Encl 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 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 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 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 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 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 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 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 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 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 ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20195J4291988-11-29029 November 1988 Summary of 881118 Meeting W/Util in Rockville,Md Re Four Plant Startup Issues Including:Dhr Sys Shutdown Cooling Mode of Operation,Operability of Penetration Room Ventilation Sys & Operability of Nozzles in safety-related Piping Sys ML20206L9831988-11-25025 November 1988 Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl ML20205P2201988-10-26026 October 1988 Summary of 881018 Meeting W/Util in Rockville,Md Re Results of Inservice Insp of Casings of Reactor Coolant Pumps a & B & Request for Relief from ASME Code Requirements for Inspecting Reactor Coolant Pumps.Related Info Encl ML20204G4391988-10-12012 October 1988 Summary of 880908 Meeting W/Util in Arlington,Tx Re Previous Violation in Area of Contingency Response.Util Expressed Basis for Denial in Insp Rept 50-313/86-34.No New Requirements Imposed But Requirement Already in Place ML20151Q8131988-08-0303 August 1988 Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20150F2451988-06-29029 June 1988 Summary of 880607 Meeting W/Util in Little Rock,Ar Re B&W Owners Group Safety & Performance Improvement Program at Plant ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants ML20154S0341988-05-27027 May 1988 Summary of 880519 Meeting W/Middle South Utils Representatives Re Proposed Establishment & Licensing of Middle South Utils Nuclear Operating Co.Agenda Encl ML20154K9611988-02-0505 February 1988 Summary of 880204 Meeting Re Presentation Made by Allegheny Ludlum on Ferritic Stainless Steel E-Brite ML20237E0391987-12-0909 December 1987 Summary of 871026 Meeting W/Util Re Permanent Repairs to Pressurizer.List of Attendees & Licensee Handouts Encl ML20237B4671987-12-0909 December 1987 Summary of 871117 & 18 Meetings W/Util at Plant Site Re Licensee Inservice Testing Program.Licensee Committed to Resubmit Inservice Testing Program in May 1988,pending Closure of Open Items by 880101.List of Attendees Encl ML20236B0861987-10-15015 October 1987 Summary of 871007 Meeting W/Util Re Midcycle Outage on Facility.List of Attendees & Outline of Licensee Presentation Encl ML20235G8921987-09-24024 September 1987 Summary of 870828 Meeting W/Util Re Justification for Continued Operation W/High Containment Temps.List of Attendees & Table of Contents from 870828 Justification for Continued Operation Encl ML20234B0731987-08-28028 August 1987 Summary of 870821 Meeting W/Util in Bethesda,Md Re Issue of High Temp in Reactor Containment Bldg.Vendor Branch Questions & Attendance List Encl 1999-07-16
[Table view] |
Text
-
,(g nogfg UNITED STATES y NUCLEAR REGULATORY COMMISSION
)s g 5{
aj WASHINGTON, D. C. 20555 g July 1, 1987 Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)
FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELIABILITY OF THE ANO-2 EMERGENCY FEEDWATER SYSTEM (EFWS) -
INTRODUCTION At the request of the NRC staff, a meeting was hel:1 on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and control, environment, and accessibility of operation recovery actions following any potential malfunctions, associated with the ANO-2 EFWS to assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary findings which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed. A summary of the meeting follows.
SUMMARY
The NRC staff noted that the staff's preliminary evaluation indicates that an additional source of feedwater ta steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee commented that it believes the I current ANO-2 EFWS is sufficiently reliable as a result of various reliablity related modifications and meets the all applicable regulatory requirements. l The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee ;
noted that condensate pumps can be used to feed steam generators in place of !
the EFWS and AN0-2 has a feed and bleed capability utilizing a 6 inch ECCS l l
vent.
The NRC staff indicated that the licensee's comments would be considered in the preparation of the assessment report related to the AN0-2 EFWS. The staff, however, noted that it is difficult to show a high reliability with a two pump EFWS.
l 8707130173 870701 PDR ADOCK 05000369 P PDR
V g.
FUTURE WORK The NRC t;taff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibility and/or potential alternatives to the potential backfit action in the latter part of July 1987.
l l
15, Rober# S. Lee, Project Manager Project Directorate IV !
Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:
See-next page DIST1(IBUTION
@ cket File NRC PDR Local PDR P. Norian T. Enos PD4 Reading S. Diab S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. C lvo R. Giardina I R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)
W. Minners ,
D. Howard i o a o 07/ / /87 07// /87 07/}/87 0
1 l
l I
[ .' .,
Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light' Company Unit No. 2 cc:
Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Rock, Arkansas 72203 Suite 1310 Bethesda, Maryland 20814 Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Nicholas S. Reynolds, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, H.W.
Suite 700 ,
Washington, D.C. 20036 Regiorici Administrator, Region IV U.S. Nuclear Regulatory Connission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 L
Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 3- 7910 Woodmont' Avenue Bethesda, Maryland 20814
4 Enclosure
>= ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L S. Quinnoz AP&L
k [N'
/ 'o
- ,,c UNITED STAT ES
!" NUCLEAR REGULATORY COMMISSION 1
W ASHNGTON, D. C. 2n555 f ; ~;
July 1, 1987
j Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)
FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELI ABILITY OF THE AND-2 EMERGENCY FEEDWATER SYSTEM (EFWS)
INTRODUCTION At the request of the NRC staff, a meeting was held on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and .
control, environment, and accessibility of operation recovery actions following' any potential malfunctions, associated with the AN0-2 EFWS to assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary findings which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed.. A summary of the meeting follows.
SUMMARY
The NRC staff noted that the staff's preliminary evaluation indicates that an additional source of feedwater to steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee cc.mmented that it believes the current ANO-2 EFWS is sufficiently reliable as a result of various reliablity related modifications and meets the all applicable regulatory requirements.
The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee ,
noted that condensate pumps can be used to feed steam generators in place of l the EFWS and AND-2 has a feed and bleed capability utilizing a 6 inch ECCS vent.
The NRC staff indicated that the licensee's comments would be considered in the preparation of the assessment report related to the ANO-2 EFWS. The staff, however, noted that it is difficult to show a high reliability with a two pump EFWS.
1
. . . . . . I
1
- FUTURE WORK The NRC staff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibility .
and/or potential alternatives to the potential backfit action in the latter part of July 1987.
IS Robert S. Lee, Project Manager Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:
See next page DISTRIBUTION DojcetFile WRC PDR Local PDR P. Norian T. Er.os PD4 Reading
- 5. Diab S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. Calvo R. Giardina R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)
W. Minners D. Howarc PD-4 e -4 PNoo l JCalvo 07///87 07/I /87 07/c )/87
I 1 Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 CC*
Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Rock, Arkansas 72203 Suite 1310 Bethesda, Maryland 20814 Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. C. Box 608 Russellville, Arkansas 72801 Nicholas S. Reynolds, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Suite 700 Washington, D.C. 20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan, Plaza Drive, Suite 1000
. Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 7910 Woodmont Avenue _
Bethesda, Maryland 20814
e s
Enclosure
\
ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB ,
i i
G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L
- 5. Quinnoz AP&L
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+ pcp Mcg'S UNITED STATES
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~h NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 r,,
~l July 1, 1987 g
=..o Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)
FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELIABILITY OF THE AND-2 EMERGENCY FEEDWATER SYSTEM (EFWS)
INTRODUCTION At the request of the NRC staff, a meeting was held on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and control, environment, and accessibility of operation recovery actions following any potential malfunctions, associated with the ANO-2 EFWS t'o assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary finding:5 which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed. A summary of the meeting f9llows.
SUMMARY
The NRC staff noted that the staff's preliminary evaluation indicat.es that an additional source of feedwater to steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee connented that it believes the current ANO-2 EFWS is suf fic$ently reliaMe as a result of various reliablity related modificat. ions and meets the all applicable regulatory requirements.
The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee noted that condensatt pumps can be used to feed steam generators in piece of the EFWS and ANO-2 has a feed and bleed capability utilizing a 6 inch ECC5 vent.
The NRC staff indicated that the licensee's conarents would be considered in the preparation of the assessment report related to the ANO-2 EFWS. The staff, however, ncted that it is difficult to show a high reliability with a two pump
'EFWS.
{
q.. 2 FUTURE WORK The NRC staff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibili',y and/or potential alternatives to the potential backfit action in the latter part of July 1987.
15 Robert 5. Lee, Project Manager Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:
See next page DISTRIBUTION Ifocket File NRC PDR
@ (al PDR P. Norian T. Enos PD4 Reading
- 5. Diad S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. Calvo R. Giardina R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)
W. Minners D. Howard '
nw ;M 07/ / /87 07// /87 ho 07/g}/87
( Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 cc:
Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Ror.k, Arkansas 72203 Suite 1310 !
Bethesda, Maryland 20814 !
Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Nicholas 5. Reynolds, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Suite 700 Washington, D.C. 20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 7910 Woodmont Avenue Bethesda, Maryland 20814
'Y Enclosure ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L AP&L S. Quinnoz