|
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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
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i e .o
[p ato 'c UNITED STATES
, l' , , c (',j NUCLEAR REGULATORY COMMISSION
- "/ g WASHINGTON, D. C. 20555 k [ September 24, 1987 Docket No. 50-313 LICENSEE: Arkansas Power and Light Company (AP&L)
FACILITY: Arkansas Nuclear One, Unit 1 (ANO-1)
SUBJECT:
SUMMARY
OF MEETING BETWEEN THE STAFF AND ARKANSAS POWER AND LIGHT (AP&L) REGARDING THE JUSTIFICATION FOR CONTINUED OPERATION (JCO) WITH HIGH CONTAINMENT TEMPERATURES, AUGUST 28, 1987.
BACKGROUND In early August 1987, it was determined that ANO-1 was operating with contain-ment temperatures ranging from 103 F to 183 F, with an average of about 140 F.
This compares with a normal average temperature of 110 assumed in the FSAR, and an equipment qualification temperature of 120 F. Following a r. umber of discussions between the staff and licensee (see Meeting Summary dated August 28, 1987), the staff requested the licensee to submit a JC0 on August 28, 1987.
Pending staff review of the JC0, a decision would be made concerning continued plant operation.
SUMMARY
An initial meeting was held between AP&L and NRC management to discuss the general approach and bases for the JCO. An attendance list is included in Enclosure 1. AP&L stated that they had made a review of the effect of high containment temperatures and concluded that the plant is safe to continue to operate until the scheduled mid-cycle outage. AP&L indicated that they had brought a number of technical and support personnel with them and were prepared to sit with the NRC staff to answer questions and provide any additional information that the staff needed. In response to NRC questions, AP&L stated that they believed that they had addressed all critical areas that might have been affected by the temperatures.
AP&L summarized the scope of the JC0 by reviewing with the NRC the JC0 Table of Contents (Enclosure 2). AP&L was asked about the accuracy of containment tempera-ture profile; they responded that there are RTD data which were supplemented by infra-red measurements taken during containment entry on August 26, 1987. The actual values were compared to the calculated ones and found to be slightly lower. l 1
In response to a question about a specific cable failure, AP&L stated that the l cable in question was in an area of localized high temperature (pressurizer j vent block valve). The damaged cable was replaced with an improved type. AP&L 1
was asked if there were plans to go into containment to look at specific items, for example penetrations. AP&L stated that the preventative maintenance program was a major element in the program to continually assess the condition of critical equipment items.
8709300278 870924 PDR ADOCK 05000313 P PDR
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-2 AP&L stated that they had taken several steps to avoid being in,similar situa-tions in the future. They initiated a review of all discrepancies identified {
during the ANO-1 start-up and the disposition of each discrepancy. Further, j AP&L is requalifying 50.59 reviewers, assessing the effectiveness of the j Safety Review Committee, and assigning additional technical people to the i plant.
l 1
The NRC stated that in addition to the effects of the harsh environment on com-ponents and structures, the higher temperatures made it difficult for personnel to enter containment. AP&L was told that the NRC wants to see the root cause fixed. AP&L indicated that an evaluation was underway to determine what long term actions should be taken. The evaluation is to be com pleted by January )
1988 after which a course of action will be set. At this point however, it !
appears that there are three major factors that affect containment temperature. l They are chiller capacity, insulation, and air circulation within the building. {
At the end of the meeting AP&L was informed that the NRC would perform a l preliminary review of the JC0 during the afternoon. Following the technical review, the staff would caucus, reach a conclusion, and the conclusions and/or 1 com ments would be conveyed to AP&L management.
Following completion of the management meeting, the technical staff received copies of the JCO. It was reviewed by the following branches; Mechanical Engineering, Structural and Geosciences, Instrumentation and Control Systems, i Electrical Systems, Plant Systems, and Reactor Systems. In addition to review-l ing the JC0, the staff met with AP&L staff and their consultants. At the l j
conclusion of the meetings and reviews with AP&L, the staff reconvened. The i staff concluded that the JC0 was acceptable. It was agreed that the staff l would issue a Safety Evaluation documenting its conclusions and any licensee j commitments for actions or confirmatory information. J After the NRC meeting, AP&L management was informed by telephone of the staff's decisions.
l5l George F. Dick, Jr., Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
Enclosures:
As stated l cc w/ enclosures:
See next page Docket File NRC PDR Local PDR PD4 Reading T. Murley/J. Sniezek F. Miraglia F. Schroeder D. Crutchfield P. Noonan G. Dick OGC-Beth W. Lanning E. Jordan J. Partlow Receptionist (Phillips) l NRC Participants ACRS (10) GPA/PA l V. Wilson B. Kolostyak l LTR NAME: ' MEETING SUMMAR AN01 9/9 i APM PD4/D I y- '
PD4/LATk.
PNoon' a6 -
k:al JCalvo 96t/87 9/J4/87 9/af/87 L__________________
x -
'Mr. G. Campbell T Arkansas Power & Light Company Arkansas Nuclear One, Unit 1 Cc:
Mr. J. Ted Enos, Manager Nuclear Engineering and. Licensing
' Arkansas Power & Light Company P. O., Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine, Director.
Site Nuclear Operations-Arkansas Nuclear One P. O. Box-608 Russellville, Arkansas ~72801 Mr. Nicholas.S. Reynolds Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street,'.N.W.
Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector
'U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Regional' Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations i 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County '
Pope County Courthouse
-Russellville, Arkansas 72801 1
7 Enclosure 1 NRC/AP&L MANAGEMENT MEETING ATTENDANCE AUGUST 28, 1987 NRC AP&L J. Sniezek T.G. Campbell F. Miraglia J. Levine R. Starostecki J.T. Enos L. Shao R. Lane I l
F-. Schroeder J. Calvo G. Dick l l
Tenera H. Levin Middle South Utilities /SSI l W. Cottle l
1 i
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l l
1 l
L l
i l
ENCLOSURE 2
't ELEVATED REACTOR BUILDING TEMPERATURE ARKANSAS NUCLEAR ONE - UNIT i l
JUSTIFICATION '
FOR CONTINUED OPERATION i i
l' AUGUST 28, 1987 l ARKANSAS POWER S LIGHT COMPANY
)
33
. TABLE OF CONTENTS 4
Section Title Page i f'
EXECUTIVE
SUMMARY
I. ANO REACTOR BUILDING AIR TEMPERATURE HISTORY ....... 1-1
]
I.A REACTOR' BUILDING AIR TEMPERATURE HISTORY ............. 1-1 1
1.B EQUIPMENT PROBLEMS RELATED T0 REACTOR BUILDING )
ELEVATED AIR TEMPERATURE ............................. 1-2 )
I.C. BASES FOR SAR REACTOR BUILDING AIR TEMPERATURE VALUE ................................................ I-3 1.0 REACTOR BUILDING STRUCTURAL DESIGN ................... I-6 1.E PLANT OPERATING HISTORY .............................. I-6 I.F INVESTIGATION OF CURRENT REACTOR BUILDING TEMPERATURES ......................................... I-7 II. SAFETY ANALYSESE..................................... 11-1 II.A REANALYSIS OF ANO-1 TO CONSIDER ELEVATED REACTOR BUILDING TEMPERATURES ........................ 11-1 II.A.1 Safety Analysis Report, Operating License and Associated Technical Specifications, and Safety Evaluation Report Review ..... ... ............ 11-1 II.A.2 Regulatory Correspondence Review ..................... 11-8 II.A.3 Additional Reactor Building Pressure /
Temperature Response Analyses ........................ II-11 II.A.4 Chapter 14 Analyses .................................. 11-14 II.B REACTOR BUILDING STRUCTURAL INTEGRITY II.B.1 Introduction II.B.2 Internal structure Impacts II.B.3 Equipment Support and Anchorages II.B.4 Piping Systems II.B.5 Cranes and Fuel Handling Equipment Inside Containment !
II.B.6 Auxiliary Systems
f t-- .
TABLE OF CONTENTS Section Titig Pa2' II.B.7- Sump Debris
, II.C ENVIRONMENTAL QUALIFICATION 11.0 EVALUATION OF NON-EQ EQUIPMf.HT INSIDE THE REACTOR BUILDING II.D 1 Mechanical Equioment 11.0.2 Electrical Equipment II.D.3 Instrumentation and Controls II.D.4 Maintenance Program II.D.5 Conclusion II.E. EVALUATION OF~ ELEVATED TEMPERATURE EFFECTS ON EQUIPMENT AND SYSTEMS OUTSIDE REACTOR BUILDING II.E.1 Methodology II.E.2 General Design Requirements II.E.3 System Overview II.E.4 Survey Results II.E.5 Heat Gain Evaluation II.E.6 Conclusions III. EVALUATION OF POTENTIAL IMPACTS ON ANO-2
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III.A DESIGN CONDITIONS .................................... III-1 III.B SAFETY ANALYSES AND TECHNICAL SPECIFICATIONS . . . . . . . . . III-2 III.C PERFORMANCE OF THE ANO-2 CONTAINMENT ................. III-2 l 1
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11.0 CONCLUSION
........................................... III-4 IV. ACTIONS IV.A ANO-1 ................................................ IV-1 IV.A.1 Immediate Actions ....................... .............. IV-1 IV.A.2 N e a r Te rm A c t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-3
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TABLE OF CONTENTS I
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Section Title Long Term Actions .................................... IV-7 IV.A.3 1
IV-9 j Iv.B ANO-2 ................................................
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SUWARY AND CONC LUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1 !
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