|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20206U9041999-05-19019 May 1999 Summary of 990504 Meeting with EOI in Rockville,Maryland Re Integrated Nuclear Security Plan Being Proposed by EOI for All EOI Sites.List of Meeting Attendees & Copy of Meeting Presentation Matl Encl 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 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 ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees 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 ML20216B8511998-05-0606 May 1998 Summary of 980219 Meeting W/Entergy Operations,Inc in Rockville,Maryland Re Spent Fuel Pool Re-Rack & Spent Fuel Pool Cooling at Waterford Steam Electric Station,Unit 3 ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl 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 ML20141C6361997-06-24024 June 1997 Summary of 970321 Meeting W/Licensee in Rockville,Md to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20141D0881997-06-24024 June 1997 Summary of 970423 Meeting W/Licensee in Killona,La to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl 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 ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) 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 ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20056D9881993-08-0202 August 1993 Summary of 930715 Meeting W/Util Re Shutdown Cooling Alternatives During Next Refueling Outage.Attendance List & Handouts Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058D5941990-11-0101 November 1990 Summary of 900912 Meeting W/Util Re Proposed Changes in Security Plan.List of Meeting Attendees Listed 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 ML20245C7201989-04-20020 April 1989 Summary of 890320 Meeting W/Util to Discuss Difference of Understanding on Intent & Operation of Plant,Per 890103 Order Imposing Civil Penalty Concerning 880512 Event ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams Encl 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 ML20215M1961987-04-28028 April 1987 Summary of 870318 & 19 Mgt Conference W/Util,Ebasco & BNL in Bethesda,Md Re Final Rept of Basemat Confirmatory Analyses Program.List of Attendees Encl ML20215M6631987-04-28028 April 1987 Summary of 870414 Audit at Ebasco to Review Calculational Results Proposed by Util/Ebasco Raised at 870330 Conference. List of Attendees Encl ML20215M3361987-04-27027 April 1987 Summary of 870330 & 31 Mgt Discussions W/Util,Bnl & Ebasco in Bethesda,Md Re Basemat Summary Rept.List of Attendees & Draft Outline of Summary Rept on Basemate Design & Analyses Encl ML20210C2061986-09-11011 September 1986 Trip Rept of Attendance at 860829 Basemat Confirmatory Analyses Audit in New York,Ny W/Bnl,Util & Ebasco Re Calculations & Results for Horizontal Analysis.List of Attendees Encl ML20206Q0241986-08-22022 August 1986 Summary of 860731 Site Visit W/Util & BNL Re Previously Unmapped Cracks in Common Foundation Basement.List of Attendees Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20211J0191986-06-10010 June 1986 Summary of 860603 Meeting W/Util & C-E in Bethesda,Md to Discuss Fuel Cycle Design,Tech Spec Amends & Other Licensing Actions Needed to Support Cycle 2 Operations.Viewgraphs & Attendance List Encl ML20198G8931986-05-21021 May 1986 Summary of 860513 Meeting W/Util in Bethesda,Md Re Design & Implementation of Spds.List of Attendees Encl ML20141F0461985-12-30030 December 1985 Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl ML20151N3021985-12-19019 December 1985 Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl ML20210A2641985-11-0505 November 1985 Summary of 851012-24 Meeting W/Util & BNL at Site Re Surveillance Program for Common Foundation Basemat.List of Attendees & Rev 1 to Procedure PE-5-033, Nuclear Plant Island Structure Foundation Basemat..., Encl ML20133P0971985-10-16016 October 1985 Summary of 851002 Meeting W/Util in Arlington,Tx Re General Plant Status,Including Recent Major Events & Milestones Achieved & Recent Main Turbine Generator Outage. Attendance List & Related Info Encl ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20135J0071985-09-13013 September 1985 Summary of 850905 Meeting W/Util,Bnl & Ebasco in New York,Ny Re Progress to Date in Confirmatory Analyses for Common Foundation Basemat.List of Attendees & Viewgraphs Encl ML20127G2061984-09-27027 September 1984 Trip Rept of 840910 & 13 Visits to Taft,La to Review Program Being Utilized to Resolve Issues Stated in ML20127G1721984-08-15015 August 1984 Trip Rept of 840809 & 10 Visits to Taft,La Re Review of Verification Program for Qa/Qc Personnel Qualifications, Qualifications of Reviewers & Qualifications of Third Party Performing Overview of NRC Task Force Findings ML20054J0271982-06-21021 June 1982 Summary of 820615 Meeting W/Util,Ebasco & C-E in Bethesda,Md Re Util Proposal for Verifying That Plant Designed & Built Per NRC Requirements ML20127A1441982-02-18018 February 1982 Summary of 820210 Meeting W/Util Re Open SER Item Concerning Flooding in Cooling Tower Areas ML20062K1401980-11-20020 November 1980 Summary of 800930-1003 Meeting W/Util & Consultants in New York,Ny Re Mechanical Engineering Branch Review of Open Items in Initial Draft SER ML20062D4281978-11-0808 November 1978 Summary of 780918 Meeting of Caseload Forecast Panel to Obtain Info to Predict Subj Facil Fuel Load Date.Disscussion Items Incl:Plant Staff,Need for Plant,Turnaround Time for Design Engr Work,& Startup Organization 1999-05-19
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20206U9041999-05-19019 May 1999 Summary of 990504 Meeting with EOI in Rockville,Maryland Re Integrated Nuclear Security Plan Being Proposed by EOI for All EOI Sites.List of Meeting Attendees & Copy of Meeting Presentation Matl Encl 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 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 ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees 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 ML20216B8511998-05-0606 May 1998 Summary of 980219 Meeting W/Entergy Operations,Inc in Rockville,Maryland Re Spent Fuel Pool Re-Rack & Spent Fuel Pool Cooling at Waterford Steam Electric Station,Unit 3 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 ML20141C6361997-06-24024 June 1997 Summary of 970321 Meeting W/Licensee in Rockville,Md to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl ML20141D0881997-06-24024 June 1997 Summary of 970423 Meeting W/Licensee in Killona,La to Discuss Design & Licensing Basis of Certain Essential Containment Isolation Sys at Plant.List of Attendees & Licensee Presentation Encl 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 ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) 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 ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20056D9881993-08-0202 August 1993 Summary of 930715 Meeting W/Util Re Shutdown Cooling Alternatives During Next Refueling Outage.Attendance List & Handouts Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058D5941990-11-0101 November 1990 Summary of 900912 Meeting W/Util Re Proposed Changes in Security Plan.List of Meeting Attendees Listed 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 ML20245C7201989-04-20020 April 1989 Summary of 890320 Meeting W/Util to Discuss Difference of Understanding on Intent & Operation of Plant,Per 890103 Order Imposing Civil Penalty Concerning 880512 Event ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams Encl 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 ML20215M1961987-04-28028 April 1987 Summary of 870318 & 19 Mgt Conference W/Util,Ebasco & BNL in Bethesda,Md Re Final Rept of Basemat Confirmatory Analyses Program.List of Attendees Encl ML20215M6631987-04-28028 April 1987 Summary of 870414 Audit at Ebasco to Review Calculational Results Proposed by Util/Ebasco Raised at 870330 Conference. List of Attendees Encl ML20215M3361987-04-27027 April 1987 Summary of 870330 & 31 Mgt Discussions W/Util,Bnl & Ebasco in Bethesda,Md Re Basemat Summary Rept.List of Attendees & Draft Outline of Summary Rept on Basemate Design & Analyses Encl ML20206Q0241986-08-22022 August 1986 Summary of 860731 Site Visit W/Util & BNL Re Previously Unmapped Cracks in Common Foundation Basement.List of Attendees Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20211J0191986-06-10010 June 1986 Summary of 860603 Meeting W/Util & C-E in Bethesda,Md to Discuss Fuel Cycle Design,Tech Spec Amends & Other Licensing Actions Needed to Support Cycle 2 Operations.Viewgraphs & Attendance List Encl ML20198G8931986-05-21021 May 1986 Summary of 860513 Meeting W/Util in Bethesda,Md Re Design & Implementation of Spds.List of Attendees Encl ML20141F0461985-12-30030 December 1985 Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl ML20151N3021985-12-19019 December 1985 Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl ML20210A2641985-11-0505 November 1985 Summary of 851012-24 Meeting W/Util & BNL at Site Re Surveillance Program for Common Foundation Basemat.List of Attendees & Rev 1 to Procedure PE-5-033, Nuclear Plant Island Structure Foundation Basemat..., Encl ML20133P0971985-10-16016 October 1985 Summary of 851002 Meeting W/Util in Arlington,Tx Re General Plant Status,Including Recent Major Events & Milestones Achieved & Recent Main Turbine Generator Outage. Attendance List & Related Info Encl ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20135J0071985-09-13013 September 1985 Summary of 850905 Meeting W/Util,Bnl & Ebasco in New York,Ny Re Progress to Date in Confirmatory Analyses for Common Foundation Basemat.List of Attendees & Viewgraphs Encl ML20054J0271982-06-21021 June 1982 Summary of 820615 Meeting W/Util,Ebasco & C-E in Bethesda,Md Re Util Proposal for Verifying That Plant Designed & Built Per NRC Requirements ML20127A1441982-02-18018 February 1982 Summary of 820210 Meeting W/Util Re Open SER Item Concerning Flooding in Cooling Tower Areas ML20062K1401980-11-20020 November 1980 Summary of 800930-1003 Meeting W/Util & Consultants in New York,Ny Re Mechanical Engineering Branch Review of Open Items in Initial Draft SER ML20062D4281978-11-0808 November 1978 Summary of 780918 Meeting of Caseload Forecast Panel to Obtain Info to Predict Subj Facil Fuel Load Date.Disscussion Items Incl:Plant Staff,Need for Plant,Turnaround Time for Design Engr Work,& Startup Organization 1999-05-19
[Table view] |
Text
_ _ _ _ _ _ _ . _ . _ _. ..-. _ _.. _ . _ _ _ _ __ _ _ . _ _ . _ _ _ _~
LICENSEE: ENTERGY OPERATIONS, INC.
i FACILITY: Waterford Steam Electric Station, Unit 3
SUBJECT:
SUMMARY
OF MEETING WITH ENTERGY OPERATIONS, INC. ON THE CONTAINMENT ISOLATION SYSTEMS DESIGN I
On April 23, 1997, members of the Nuclear Regulatory Commission (NRC) staff met with representatives of Entergy Operations, Inc. (E0I) at Waterford Steam 4
Electric Station, Unit 3 (Waterford 3), at Killona,~ Louisiana to discuss the design and licensing basis of certain essential containment isolation systems
- at Waterford 3. This was a follow-up meeting from the meeting on March 21, 1997. E01 provided a detailed planning to resolve the containment isolation
! issues for certain essential systems at Waterford 3. The short term and long -
, term resolutions for the Containment Spray (Penetration 34 and 35), Component Cooling Water to the Containment Fan Coolers, and Chemical and Volume Control
! System (Penetration 27) were discussed. The NRC staff provided its generic
. interpretation of the requirements for the containment isolation systems. The staff requested E01 to provide a detail submittal describing its approach in
! resolving the containment isolation issue for each system in question. E0I j- indicated that it will submit a written response for each system in question.
! A list of Attendees is provided in Enclosure 1. A copy of E0I's presentation
- is provided in Enclosure 2.
Orig. signed by l Chandu P. Patel, Project Manager
- Project Directorate IV-1 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation l
Docket No. 50-382
Enclosures:
- 1. List of Attendees
- 2. E01's Presentation i cc w/encls: See next page DISTRIBUTION: /
HARD COPl E-MAIL Docket File SCollins/FMiraglia (SJC1/FJM) RZimmerman (RPZ)
- PUBLIC JRoe (JWR) EAdensam (EGAl)
- '- PD4-1 r/f CPatel (CPP) CHawes (CMH2)
OGC JClifford (JWC) PGwynn (TPG)
ACRS JKudrick (JAKl) TPruett (TWP)
GPick (GAP)
! Document Name: WAT42397.MTS 1
+
OFC PM/PD4-1 a LA/PD4-1 I NAME CPatel/vw CHawes 0/UN DATE 6/M97 [/X//97 I
COPY /YE3/N0 YES/N0 0FFICIAL RECORD COPY l
-l 9706260276 970624 PDR ADOCK 05000382 P
PDR i . .- - - _
/ p 4%g% UNITED STATES I 3
- r } NUCLEAR REOULATORY COMMISSION ]
- WASHINGTCN, D.C. 30566 4 001 l 2
\ ,o8 June 24, 1997 I
LICENSEE: ENTERGY OPERATIONS, INC.
FACILITY: Waterford Steam Electric Station, Unit 3
SUBJECT:
SUMMARY
OF MEETING WITH ENTERGY OPERATIONS, INC. ON THE l CONTAINMENT ISOLATION SYSTEMS DESIGN j l On April 23, 1997, nembers of the Nuclear Regulatory Commission (NRC) staff met witn representative of Entergy Operations, I- (E01) at Waterford Steam Electric Station, Unit 3 (Waterford 3), at Killes.4 )uisiana to discuss the design and licensing basis of certain essential :.cainment isolation systems at Waterford 3. This was a follow-up meeting from the meeting on March 21, 1997. E01 provided a detciled planning W resolve the containment isolation issues for certain essentfal systems at katerford 3. The short term and long term resolutions for the Containment Spray (Penetration 34 and 35), Component Cooling Water to the Containment Fan Coolers, and Chemical at;d Volume Control System (Penetration 27) were discussed. The NRC staff provided its generic interpretation of the requirements for the cortainment isolation systems. The staff rec;uetted E01 to provide a detail submittal describing its approach in resolving the containment isolation issue for och system in question. E01 indicated that it will submit a written response for each system in question.
A list of Attendees is provided in Enclosure 1. A copy of E01's presentation is provided in Enclosure 2.
wh 0 f Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. List of Attendees
- 2. E01's Presentation cc w/entis: See next page l
l l
l
- e. A 4 a =a--,u , -- -. A 4 ,- # . Fnx n W 4A _ m- a Entergy Operations, Inc. Waterford 3 I !
cc:
Administrator Regional Administrator, Region IV Louisiana Radiation Protection Division U.S. Nuclear Regulatory Commission Post Office Box 82135 611 Ryan Plaza Drive, Suite 1000
, Baton Rouge, LA 70884-2135 Arlington, TX 76011 i Vice President, Operations Resident Inspector /Waterford NPS Support Post Office Box B22 Entergy Operations, Inc. Killona, LA 70066
, P. O. Box 31995
- Jackson, MS 39286 Parish President Coun. 1 i' St. Charles Parish Director P. O. Box 302 Nuclear Safety & Regulatory Affairs Hahnville, LA 70057 Entergy Operations, Inc.
P. O. Box B Executive Vice-Prrsident
- Killona, LA 70066 and Chief Operating Officer Entergy Operations, Inc.
1 Wise,. Carter, Child & Caraway P. O. Box 31995 i P. O. Box 651 Jackson, MS 39286-1995 Jackson, MS 39205 4
Chairman General Manager Plant Operations Louisiana Public Service Commission
- Entergy Operations, Inc. One American Place, Suite 1630 P. O. Box B Baton Rouge, LA 70825-1697 i Killona, LA 70066 Licensing Manager Vice President Operations Entergy Operations, Inc. Entergy Operations, Inc.
i P. O. Box B P. 0.' Box B Killona, LA 70066 Killona, LA 70066 1 l 4
Winston & Strawn i 1400 L Street, N.W.
j Wachington, DC 20005-3502 ,
l J
4 i 1 5
1 Y
l I
l
MEETING ATTENDEES APRIL 23. 1997 MEETING WITH E01 l CONTAINMENT ISOLATION SYSTEM AT WATERFORD 3 4
5 E 101 C. Patel A. J. Wrape, III - E0I G. Pick L. Rushing - E01
- T. Pruett P. L. Caropino - E01 J. Kudrick K. Walsh -E01 l D. Ortego - E01 l D. Gamble - E01 ,
M. A. Groome - E01 l G. S. Matharu - E0I i' R. Weicks - EDI D. Viener - E01 E. C. Ewing, III - E0I P. V. Prasankumar - E01 P. M. Melancon - E01
1
- PENETRATIONS 34 & 35 - CONTAINMENT SPRAY 1
DESIGN / LICENSING BASIS- 1 i
i
+ GDC 56 PENETRATION e
Check Valve inside Containment (CS-128A&B)
- e Solenoid Valve inside Containment (CS-129A&B, parallel to CS-128) ,
AOV Outside Containment (CS-125A&B) i -
auto open on CSAS j -
remote manual to close l j -
air accumulator capable of maintaining closure for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (minimum) i :
! + CLOSED WATER FILLED SYSTEM OUTSIDE CONTAINMENT (not credited as iaolation barrier in meeting GDC 56) l . CS system does not communicate with the outside atmosphere Sl-107A&B, RWSP outlet check valves are a leak tested boundary valve CS piping outside contairiment is located within the Controlled Ventilation Area System (CVAS) boundary piping will be water filled post-accident safety class 2 shutoff valves isolate CS system branch piping ,
f
' e designed to Safety Class (SC) 2 requirements all CS piping outside of containment designed to SC 2 appropriate class breaks taken on branch lines
]
j e designed for iriternal pressure and temperature greater than 1 1 containment design conditions minimum design conditions,300 psig @ 190*F j e can withstand lossv i :oolant accident transient and environment j -
ESF system desiw.ad to operate post-LOCA i
- . designed to Seismic Category i requirements j -
all CS piping outside of containment designed seismic cat. l l
appropriate class breaks taken on branch lines
! . not susceptible to overpressurization from thermal expansion when
! isolated ref. design guide AMEC-D-007 for analysis (T <150*F) i 4 . is protected against a high energy line break outside of containment j -
analysis documented in FSAR 3.6.A.2 b
(Note: the above design meets the criteda for a closed system Wside ntainment per ANSI N271-1976, which is endorsed by Reg. *iu dc : 141.)
l ENCLOSURE 2 1
I 4
. PENETRATIONS 34 & 35 - CONTAINMENT SPRAY l l
DESIGN / LICENSING BASIS (cont.): I i
i e
l + APPENDIX J TYPE C TEST NOT REQUIRED
! . closed water filled system outside containment
- . system included {n the TMI leak reduction program
- . loop seal exists after RAS l
- ISSUES IDENTIFIED:
+ OUTSIDE CIV's, CS-125A&B
- e cannot override CSAS l . fall open AOV with < 30 day air supply l
i
! CORRECTIVE ACTIONS:
l l
+ PROVIDE REMOTE MANUAL OVERRIDE CAPABILITY TO.CS-125A&B i . DC-3523
! . will be implemented during this refueling outage (RFE) *
+ PROVIDE CS-125A&B WITH SAFETY RELATED CLOSURE CAPABILITY FOR 30 DAY.9
. DC-3523 (phase 11)
. to be implemented during next refueling outage (RFC)
t PENETRATIONS 34 & 35 - CONTAINMENT SPRAY COMPENSATORY ACTIONS (cont.):
i
+ ADMINISTRATIVE CONTROLS TO CLOSE CS-117A&B (if required)
. CS-117 is located upstream of CS-125
. CS-117 is a stop check valve
. accessible after 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post-accident JUSTIFICATION FOR COMPENSATORY ACTIONS:
+ ACTIONS DO NOT COMPROMISE CONTAINMENT INTEGRITY e containment integrity is maintained after a single active failure
+ TWO ISOLATION BARRIERS EXIST WITH CS-125 FAILED OPEN e closed water filled system outside containment e inside containment isolation valves, CS-128A&B, CS-129A&B
. + ADDITIONAL BARRIERS OUTSIDE CONTAINMENT
. Shutdown Cooling HX Outlet Stop Check, CS-117A&B
. Shutdown Cooling HX Outlet isolation to RWSP, CS-118A&B
. CS Pump Discharge Stop Check, CS-111 A&B
. RWSP Outlet Header Check, SI-107A&B
+ PROCEDURES EXIST TO RESTORE INSTRUMENT AIR POST-ACCIDENT e ability to close CS-125 may be restored (when power is available)
W3F1-96-0207 .
EflCLOSURE 1
- CONTAINMENT SPRAY SYSTEM - PENETRATIONS 34 cnd 35
- (CSASIRAS' Alignment Shown)
I _
- M
- RWSP
- ,
swi7aae
- ?
I, .
1 CVAS BOUNDARY ,,,,; pg
! Dh_,nmem
+
staanse Eg 2] storage cs.1toNun }Z 9
From SISump > : E-1 h
cs.ittA8e l SDCHX ' ] 34 4cs.tasA y To CS Header es.117 Ace es.sasA p Ik CS A(8) a: E4 {; pg 1I Typical for'Penskelon 35 To Safetyinjection Shutdown Coohng Headers Notes:
- 1) Prior to a RAS, communication with the containment atmosphere will not occur by ensunng the system is water filled downstream of a CS-117A(B) assuming a smole faalure of a Containment Spray Pump.
' 2) After a RAS, communscation with the containment atmosphere will not occur sece a loop seal will exist between the Safety injection Swn, ano me conia.nm ni Spear ne.o., ensunna me system is FIGURE 1 water hiled.
, . _ , _ , , , . - . . , . , .-._,,,,,,,.m,,.,4 .,.,,_,,,.w,,,,,.,3., ,,3,
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7_
ll PENETRATION 27 - CHARGING i
e i
DESIGN / LICENSING BASIS:
1
) + GDC 55 PENETRATION i
j . Inside Containment (parallel valves)
} -
Solenoid Valves, CVC-218A&B for RCS Loops 1 A and 2A post-accident position is open remote manual to close l
Solenoid Valves, CVC-216A&B f or Aux. Spray l
locked closed i
- - Check Valve, CVC-219 provides overpressure protection when CIVs are closed i
AOV Outside Containment (CVC-209) normally locked open i post-accident position is open !
remote manual to close 1 no air accumulator, non-1E power i
j + CLOSED WATER FILLED SYSTEM OUTSIDE CONTAINMENT (not credited j as an isolation barrier in meeting GDC 55)
- . does not communicate with the outside atmosphere j -
piping will be water filled post-accident j -
multiple barriers (safety class 2) exist to prevent through system leakage,
, including positive displacement pumps safety class 2 shutoff valves isolate CVC system branch piping i
. designed to Safety Class (SC) 2 requirements entire loop (letdown and charging) designed to SC 2 e designed for internal pressure and temperature greater than containment design conditions charging design conditions,3125 psig @ 250 F
. can withstand loss-of coolant accident transient and environment ESF system designed to operate post-LOCA
' l l PENETRATION 27 - CHARGING DESIGN / LICENSING BASIS (cont.):
I . designed to Seismic Category I requirements entire loop (letdown and charging) designed seismic cat. l
. not susceptible to overpressurization from thermal expansion when isolated ref. design guide AMEC-D-007 for analysis (Te <150 F) e is protected against a high energy line break outside of containment analysis documented in FSAR 3.6.A.2 (Note: the above design meets the criteria for a closed system outside containment per ANSI N271-1976, which is endorsed by Reg. Guide 1.141.)
+ APPENDIX J TYPE C TEST NOT REQUIRED e closed water filled system outside containment
. CVC-209 stem leakage included in the TMI leak reduction program ISSUES IDENTIFIED:
+ OUTSIDE CIV CVC-209
. air required to close e non-1E solenoid in air supply to actuator e fall open AOV with no accumulator CORRECTIVE ACTIONS:
+ PROVIDE CVC-209 WITH SAFETY RELATED CLOSURE CAPABILITY FOR 30 DAYS
. DC-3529 (to be implemented during RF9)
7 _._ ._. _ .__ _ _ _ -
, PENETRATION 27 - CHARGING' COMPENSATORY ACTIONS:
I
+ ADMINISTRATIVE CONTROLS TO CLOSE CVC-208 (if required) '
i
) . CVC-208 is located upstream of CVC-209 l l 1 i i i
JUSTIFICATION FOR COMPENSATORY ACTIONS:
l + ACTIONS DO NOT COMPROMISE CONTAINMENT INTEGRITY i
j . containment integrity is maintained after a single active failure t
j + TWO ISOLATION BARRIERS EXIST WITH CVC-209 FAILED OPEN f
! . closed system outside containment j e inside containment isolation valves, CVC-218A&B,216A&B,219
+ ADDITIONAL BARRIERS INSIDE CONTAINMENT 1
. CParging to RC Loop 1 A & 2A Check Valves, CVC-221 A&B
+ ADDITIONAL BARRIERS OUTSIDE CONTAINMENT
. CVC-208 can be manually closed (accessible area)
. Charging Pump Discharge Check Valves, CVC-194A,B,A/B e Charging Pumps (positive displacement pumps)
. RWSP to Charging Suction isolation Valve, CVC-507
. RWSP to Charging Suction Check Valve, CVC-508
. Emergency Boration Header Check Valve, BAM-135
+ PROCEDURES EXIST TO RESTORE INSTRUMENT AIR POST-ACCIDENT
. ability to close CVC-209 may be restored (if power is available) e can restore power to valve operator (A/B sups)
i i W3F1-96-0207 CHEMICAL cnd VOLUME CONTROL - CHARGING SYSTEM ENCLOSURE $
i PENETRATION 27
! RWSP {SIASINo RAS Alignment Shown) i From BAMT -
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[ h S,
n v% -
N
- k 9 X 27 4
- * ** Cm16 . C w m C m 200 cm2m
- cvc nexAS)" *
+ -
! Rx From VCT CVc-180]b.. p ,
m,
- cvc-= 23
................................. . . .. cve.221e CVAS BOUNDARY m ,,, /
To HPSI Header cwana
,, 5 > To AuxSpray cm2am t
f FIGURE 4
Proposed Alternate Fill for Containment Isolation Vavles DC 3429 ;
RAB NORMAL I HOT TOOL ROOM " " ~. t WING AREA I t
b Sh 8 %
9F 1P EL +21 1 r 1 r -
JL JL J L JL I i
dL jb qt jh CVAS AREA I
-4 WING AREA r
CC-807A CC-808B CC-808A CC-807B i
CC-823A CC-822 B CC-822A CC-823B t
CC-710 CC-713 CC-641 INSIDE CONTAINMENT I
i
- ' Proposed Alternate Fill for i Containment Isolation Vavles RAB NORMAL HOT TOOL ROOM DC 3429 WinlG AREA j c5 A EL +21
, M_ ) IA Containment Building A=
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- . Proposed Alternate Fill for i
- Containment Isolation Vavles DC 3429 RAB NORMAL SWITCHGEAR "B' 2
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u v JL JL i
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TO CC-710 CC-822A _.y, SEE PAGE 3 IA r
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- Proposed Alternate Fill for Containment Isolation Vavles 1 DC 3429 RAB NORMAL SWITCHGEAR *B" i
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- C I Containment Building l
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