Letter Sequence Meeting |
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MONTHYEARML20055E9411990-07-0909 July 1990 Summary of 900621 Meeting W/Util Re Proposed Mods for Return to 100% Power.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20059M0441990-09-26026 September 1990 Approves 900809 Request to Withhold 86-1179795-01, ANO-1 HPI Flow Rate Requirements (Ref 10CFR2.790(b)(5)) Project stage: Other ML20058A0811990-10-15015 October 1990 Forwards Questions Re 900808 License Amend Request to Increase Reactor Power to 100% for Response Project stage: Other 1990-07-09
[Table View] |
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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 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 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 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 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 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 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 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 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 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
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UNITED STATES e _q. NUCLEAR REGULATORY COMMISSION M !
, T. ! WASHINGTON, D. C. 20666 s b
%, '...o / auly 9, 1990 Docket No. E0-313 LICENSEE: ENTERGY OPERATIONS. INC.
FACILITY: ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1)'
SUBJECT:
MEETING
SUMMARY
- PROPOSED MODIFICATIONS FOR RETURN TO 100% POWER i (TAC 74894) L On June 21, 1990, the licensee presented to the NRC staff proposed modifications for return to 100% power. Meeting participants are listed in Enc h rJre 1. Slides presented by the licensee are shown in Enclosure 2.
Ah0-1 is currently % ised to 801 power due to a license limit based on their latest Appendix K lut of-coolant accident (LOCA) analysis (a high pressure inje: tion (HPI) lira break scenario). The licensee is also currently using the 80% power limit to provide short-term resolution of a reactor building spray (RBS) pumps net positive suction head (NPSH) issue.
The licensee presented a background and design basis discussion of,the HPI line break and NPSH issues, a description of.the modifications planned, an overview of the operator actions required, and the current status and schedule. .The modifications, all of which are outside containment, include 4 new cross-connect lines with 8 new valves that tap off the existing HPI trains upstream of the splits which eventually inject into the reactor coolant pump loops (the current arrangement is 2 cross-connect lines located downstream of thesplits). The modifications will require no additional operator action to address the HPI line break issue, but it will require the operator to limit HPI flow under certain conditions to address the NPSH issue. The modifications are planned to be installed during the next refueling outage 3 i (October to December 1990), and the supporting license amendment fcr 100% power 1s scheduled for. submittal in August 1990. The licensee also mentioned that they).mightbesubmittingrequestsforrelieffromcertaininservicetesting (IST requirements regarding the 8 new valves in a separate letter.
i'
-The staff inquired about the option to install cavitating venturis, which was unsuccessfully attempted last year. The licensee abandoned this option because the magnitude of the vibrations experienced was not predictable with available theory. The staff also inquired about the class of piping that will be used (Class 2),thespecificISTrequirementsfromwhichreliefmayberequested (possibly the test interval), and some details regarding the operator action needed to address the NPSH issue.
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The staff did not' identify any major concens with the modifications or review schedule proposed by the: licensee. _The staff did; request that the application.
include a description of the post-modification testing to be performed prior-L to start-up from.the refueling-outage.
Original signed by .
Thomas W. Alexion, Project Manager-Project Directorate IV-l'- ;
Division of Reactor Projects . Ill, IV, Y and Special Projects
Enclosures:
i As stated ~ l cc w/ enclosures:
. See next'page l I
DISTRIBUTION-
.N' NRC & Local PDRs FMiraglia 1 JPartlo*:
PD4-1 Reading RDudley
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NRC Participants
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L RBorchardt RII h JClifford,RIII MSlosson,RIV&V g-D' '
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The staff'did not identify any major ~ concerns with the modifications or review [
schedule proposed by the licensee. The staff did request that the application-include a-description of the post-modification testing to be performed prior to start-up from the refueling outage. :
( s !
J .
Thomas W. Alexion, Project anager Project Directorate IV-1 Division of. Reactor Projects - 111
-IV, V and Special Projects
Enclosures:
As stated '
cc w/ enclosures:
See next page t
9
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Mr. Neil S. Carns ;
j ,Entergy Operations, Inc. Arkansas Nuclear One, Unit 1 '
CC: -
Mr. Early Ewing, General Manager Mr. Donald C. Hintz '
Technical Support and Assessment Executive Vice President Arkansas Nuclear One Entergy Operations, Inc.
P. O. Box 608 P. O. Box 31995 '
Russellville, Arkansas 72801 Jackson, Mississippi 39286 Mr. Jerry Yelverton. Mr. Gerald Muench ;
Director Nuclear Operations Vice President Operations Support '
Arkansas Nuclear One - Entergy Operations, Inc. l Route 3 Box 137G P. O. Box 31995
-Russellville, Arkansas 72801 Jackson, Mississippi 39286 '
Mr. Nicholas S. Reynolds Mr. Robert B. McGehee, Esquire Bishop, Cook, Purcell & Reynolds Wise, Carter, Child & Caraway 1400 L Street, N.W. P. O. Box 651 Washington, D.C. 20005-3502 Jackson, Mississippi 39205 1
Mr. Robert B. Dorsum
- Babcock & Wilcox l
Nuclear Power Generation Division 1700 Rockville Pike,-Suite 525
- Rockville, Maryland 20852
- i. Senior Resident Inspector i L U.S. Nuclear Regulatory Comission 1 Nuclear Plant Road . i Russellville, Arkansas 72801 -
l 1
-Regional Administrator, Region IV i U.S. Nuclear Regulatory Commission l l Office of Executive Director for Operations h 611 Ryan Plaza Drive, Suite 1000 1 Arlington, Texas 76011- I l
l' Honorable Joe W. Phillips 1 County Judge of Pope County i p Pope County Courthouse
- l. Russellville, Arkansas 72203 L
j Ms. Greta Dicus, Director i Div.ision of Environmental Health l Protection l Arkansas Department of Health j 4815 West Markam Street l Little Rock, Arkansas 72201 l
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= n y c .: . . ENCLOSVRE 1= ;
5.1 '
ARKANSAS NUCLEAR ONE, UNIT 1 PROPOSED MODIFICATIONS FOR RETURN TO 100*/ POWER JUNE 21. 1990 NAME ORGANIZATION-Thomas Alexion NRC/PD IV-1 Chester Poslusny NRC/PD IV-1 Dale James Entergy/ Licensing
- Bill Eaton Entergy/MCS Design James 1Fisicaro Entergy/ Licensing George Jones Entergy/ Engineering Ed Jacks Entergy/Nuc.' Stand.
John Richardson Entergy/ Design Eng.
George Woerner III Entergy/MCS Design Darrell Williams Entergy/Nuc. Eng.
Kenneth Dempsey NRC/EMEB Vincent: Thomas NRC/SICB Jesse Arildsen NRC/LHFB Linh Tran NRC/PD IV-1 John Miller, Jr. Entergy/Nuc. Eng.
Randy Ellison BWNS James Pulsipher NRC/EbLB Walton Jensen .NRC/OEAB Richard Dudley NRC/PD IV-1 Mark Caruso NRC/SRXB Thomas Stetka NRC/ Region IV David Terao- NRC/EMEB Thomas Westerman
- NRC/ Region IV Clay Warren
1 l
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- - tied-in via speaker phone
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. le MODIFICATIONS .
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[? June 21 1990 I
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~ ENTERGY OPERATIONS
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ANO-1 RETURN TO 100% POWER MODIFICATIONS 4
. INTRODUCTION
- B'ACKGROUND OF ISSUES
-- HIGH PRESSURE INJECTION (HPI) LINE BREAK SCENARIO LOW PRESSURE INJECTION (LPI) AND i REACTOR BUILDING SPRAY (RBS) PUMPS l NET POSITIVE SUCTION HEAD (NPSH) i L . EMERGENCY CORE COOLING SYSTEM (ECCS) & RBS DESIGN BASIS i OVERVIEW r !- 1R9 MODIFICATIONS SCOPE '
d I'
- HPI LINE BREAK RESOLUTION - VALVES /
INSTRUMENTATION
- NPSH RESOLUTION - INSTRUMENTATION i
REQUIRED OPERATOR ACTION OVERVIEW l'.
.HPI LINE BREAK - IMMEDIATE ACTION RBS AND LPI ACTIONS
.i-
- LONG TERM RECOVERY SCENARIOS
- CURRENT STATUS & SCHEDULES
- MODIFICATIONS
- LICENSE AMENDMENT REQUEST
- CONCLUDING REMARKS
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I INTRODUCTlON i
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1 HPl BACKGROUND
. JANUARY 1989 REVIEW OF ECCS ANALYSIS REVEALED SPECIFIC SMALL .
BREAK NOT ENVELOPED BY . ANALYSIS BREAK OF AN HPI INJECTION LINE UPSTREAM OF THE COLD LEG CONNECTION AND l DOWNSTREAM OF THE FIRST RCS/HPi .;
SYSTEM BOUNDARY CHECK VALVE l
i - MARCH 1989 LICENSE AMENDMENT l SUBMITTED AND ISSUED LIMITING l
. POWER OPERATION TO 50%
l 11 . APRIL & MAY 1989 SUPPLEMENTuL INFORMATION PROVIDED JUSTIFYING :
7 i 80% POWER OPERATION
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- l. MAY 1989 AMENDMENT ISSUED ALLOW '
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80% POWER' OPERATION
. DECEMBER 1989 CAVITATING VENTURI ADDED DURING 1M89 TO ADDRESS HPI LINE BREAK SCENARIO
! -- VENTURI REMOVED FOLLOWING POST i MODIFICATION TESTING WHICH SHOWED l EXCESSIVE VIBRATION l ,
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ENTERGY OPERATIONS
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it li RBS/LPI NPSH BACKGROUND
. DECEMBER 1989 DESIGN CONFIGURATION DOCUMENTATION (DCD) PROJECT REVIEW OF ANO-1 DECAY HEAT REMOVAL SYSTEM IDENTIFIED CALCULATIONS ERRORS AND INCONSISTENCIES.
-- CONTAINMENT WATER LEVEL BWST AVAILABLE VOLUME WATER DENSITY i -- AVAILABILITY OF TRAPPED WATER
- j. --
OTHERS
- COLLECTIVELY MAY HAVE RESULTED i
IN CAVITATION IN THE- LPI & RBS '
PUMPS.
- EOP GUIDANCE RF, VISED TO THROTTLE
! PUMP DISCHARGE TO ASSURE THE NPSH REQUIREMENTS COULD BE SATISFIED.
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ENTERGY
~~ OPERATIONS
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. EMERGENCY CORE COOLING
>: SYSTEM (ECCS)
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AND F. RBS DESIGN BASIS -
OVERVIEW .
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2 M~' ENTERGY OPERATIONS
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ECCS & RBS DESIGN BASIS OVERVIEW THE ECCS & RBS SYSTEMS, ALONG WITH OTHER ENGINEERED SAFEGUARDS, ACT TO SATISFY THE REQUIREMENTS OF GDC 35, 38, & 41 BY:
-. PROVIDING COOLANT TO ASSURE CORE STRUCTURAL lNTEGRITY F
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- . MAINTAINING THE INTEGRITY OF THE REACTOR BUILDING
. REDUCING THE FISSION PRODUCTS 1 RELEASED TO AND EXPELLED FROM.
i THE REACTOR BUILDING 1 :
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L O h RA ONS
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THESE SYSTEMS OPERATE IN THE FOLLOWING MODES:.
INJECTION OF BORATED WATER TO l c THE RCS FROM THE BWST BY THE HPI j SYSTEM. :
l
. INJECTION OF BORATED WATER TO THE RCS FROM THE BWST BY THE LPI l SYSTEM.
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'. INJECTION OF BORATED WATER TO- "
THE RCS FROM THE CORE FLOODING SYSTEM. ;
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. SPRAY OF- BORATED WATER TO THE L
,1 REACTOR BUILDING ATMOSPHERE FROM THE BWST BY THE REACTOR L BUILDING. SPRAY SYSTEM.
[" . RECIRCULATION OF BORATED WATER TO THE RCS FROM THE. REACTOR !
"j BUILDING SUMP BY THE LPI SYSTEM (HPI PIGGYBACK FOR VERY SMALL 1 B.R E A KS). l
. -- RECIRCULATION OF BORATED WATER TO THE REACTOR BUILDING
. ATMOSPHERE 'FROM THE REACTOR BUILDING SUMP BY- THE REACTOR BUILDING SPRAY SYSTEM.
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~ ENTERGY OPERATIONS 4
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-THE ACCIDENTS CREDITING THESE r SYSTEMS INCLUDE: i l
t . LARGE BREAK LOCA
. SMALL BREAK LOCA
. LPI LINE BREAK LOCA o
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HPI LINE BREAK LOCA J
- MAIN STEAM LINE BREAK- 1 it l l '
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- STEAM GENERATOR TUBE RUPTURE N.'
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1R9 MODIFICATIONS SCOPE i
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- 1M89 VENTURI MODIFICATION l 1 e
L . - OPTIONS CONSIDERED:
1 1)' VALVE ADDITIONS TO BALANCE FLOW OPERATOR ACTION REQUIRED [
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- 2) 'CAVITATING VENTURIS PASSIVE - IMMEDIATE BALANCE NO- OPERATOR- ACTION REQUIRED ADDITION OF CAVITATING VENTURIS J
q PERFERRED SOLUTION - i CAVITATING VENTURIS INSTALLED DURING 1M89 u L' VENTURIS WERE INSTALLED INTO THE SYSTEM AND TESTED FOR PERFORMANCE l-n -
SIGNIFICANT NOISE OBSERVED-- LARGE L AMPLITUDE VlBRATION. IN . VENT STACKS [
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VENTURIS REMOVED AND UNIT RETURNED TO !
80% POWER -
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HIGH PRESSUREJ
- 'l Isi LINJECTION N
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cvins PUMP:-(HPIP)
REACTOR .g g y HPIP. ,A, m,
COOLANT t, PUMP (RCP) 5l
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'A' ,,,,,, _ q mia. ,,,,,,s tviza ARRANGEMENT PRIOR TO. IM89 :
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POST 1M89 ACTIVITIES
. TASK FORCE MET TO REVISIT OPTIONS
- -TASK FORCE RECOMMENDED RECONSIDERATION OF SAME TWO OPTIONS
- CRITERIA ESTABLISHED FOR 7
l REINSTALLATION OF VENTURIS l- .
! - INDUSTRY EXPERTS CONTRACTED TO' l INVESTIGATE FLOW INDUCED VIBRATIONS 1 i
! - NSSS VENDOR CONTRACTED TO ANALYZE f i j.
SYSTEM RESPONSE WITH REDUNDANT INJECTION LINES AND DETERMINE j OPERATOR ACTION REQUIRED L ! . RESULTS I - VIBRATION UNAVOIDABLE - MAGNITUDE NOT
[ PREDICTABLE WITH AVAILABLE THEORY l
- INDUSTRY EXPERIENCE DOES NOT l ENVELOPE' OUR APPLICATION .
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- WITH REDUNDANT-INJECTION LINES, l'
ADEQUATE FLOW POSSIBLE WITH NO
! OPERATOR ACTION i - ADDITIONAL MARGIN CAN BE OBTAINED WITH MINIMAL OPERATOR ACTION m i A ONS
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RECIRCULATION MODE NPSH -
INADEQUACY RESOLUTIQH THE CHANGES IDENTIFIED TO PROVIDE ADEQUATE' ECCS AND RBS PUMP NPSH
' lNCLUDE:
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THROTTLE RBS FLOW PRIOR TO
- ; SWITCHING TO THE RB SUMP -
L REQUIRES THE FLOW INDICATION TO g l BE UPGRADED TO REG. GUIDE 1.97 CATEGORY 1 TYPE A I .
MOVE THE RBS FLOW TRANSMITTERS
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TO REMOVE RADIATION INDUCED l
ERROR -
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INCREASE THE BWST LOW LEVEL 1 TECHNICAL SPECIFICATION LIMIT I i I
(APPROXIMATELY 2.5 TO 3.5 FEET).
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$Ed$SIONS 1
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THE ANALYSES BEING REASSESSED DUE TO THE CHANGES TO PROVIDE ADEQUATE ECCS AND RBS PUMP NPSH INCLUDE:
. LPI AND RBS PUMP NPSH DURING RB SUMP RECIRCULATION ii .- POST-LOCA RB SUMP WATER LEVEL L
i . POST-LOCA EQ SUBMERGENCE 1 QUALIFICATIONS l
t i . BWST SEISMIC QUALIFICATION
' . POST-LOCA RB PRESSURE AND te TEMPERATURE PROFILES L i
. POST-LOCA OFFSITE DOSE-y
.t l- POST-LOCA -RB SUMP pH i
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~ OPERATIONS '
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REQUIRED OPERATOR ACTION OVERVIEW EOP ACTIONS DEVELOPED TO ADDRESS AN HPI LINE BREAK CURRENT GUIDANCE REQUIRES THE OPERATOR, IN THE EVENT OF AN ESAS, TO:
'l - VERIFY- EXPECTED HPI, LPI &
i RBS FLOW RATES i
. ' THROTTLE THE HIGHER LOOP A (B) HPI FLOW TO.WITHIN 30-GPM OF THE OTHER LOOP A (B) HPl .
i FLOW .
[ j PLANNED GUIDANCE WILL REQUIRE THE OPERATOR, IN THE EVENT OF AN p ESAS, TO:
- VERIFY EXPECTED HPI, LPI &
' l-RBS FLOW RATES r . IF ONLY ONE HPI TRAIN
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ACTUATES, THROTTLE THE
, HIGHEST FLOW INJECTION LINE m TO WITHIN 20 GPM OF THE i
NEXT HIGHEST INJECTION lj FLOW LINE i
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a EOP. ACTIONS DEVELOPED TO ADDRESS ECCS AND RBS PUMP NPSH
-CURRENT GUIDANCE REQUIRES THE OPERATOR, PRIOR TO REALIGNMENT FOR RB SUMP SUCTION TO:
. THROTTLE RBS PLOW TO BETWEEN 1100 AND 1300 GPM PER TRAIN e l
. THROTTLE COMBINED LPI AND HPl
. l FLOW TO BETWEEN 2800 GPM AND L 3200 GPM PER TRAIN
- i i i PLANNED GUIDANCE WILL REQUIRE THE OPERATOR TO:
! . THROTTLE RBS FLOW TO BETWEEN J ! 1050 GPM AND 1200 GPM PER i
TRAIN
. IF HPi FLOW HAS NOT BEEN 1 SECURED' AND LPI FLOW > 3300 GPM, LIMIT HPl FLOW TO APPROXIMATELY 100 GPM UNTIL THE 20 MINUTE HPl TERMINATION CRITERIA IS MET L
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L CURRENT STATUS .
AND L SCHEDULES ,
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1 CURRENT STATUS & SCHEDULE -
1 L . HPl MODIFICATIONS ARE PLANNED FOR 1R9, AS
!- ARE THE NPSH MODIFICATlONS l
l PLANNED RESOLUTIONS AME WELL UNDERWAY.
L- THE TWO MAJOR CONCERNS OF RESOLVING '
THE TECHNICAL ISSUES ~ AND OPERATOR o RESPONSES, .WE BELIE'/E, ARE ADDRESSED.
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' i OPERATOR ACTION REQUIRED ARE A i
i: ' REDUCTION WITH RESPECT TO CURRENT EOP
! REQUIREMENTS.
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THE LICENSE AMENDMENT WILL BE SUBMITTED-IN EARLY AUGUST 1990 UPON COMPLETION 'OF AN ALYSIS.
MODIFICATIONS ARE ANTICIPATED TO FALL -
WITHIN THE FRAMEWORK OF 50.59 -AND' ALONG
':' WITH ANALYSIS RESULTS WILL SUPPORT A >
l LICENSE AMENDMENT TO RETURN TO 100%
!.., POWER.
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