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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217M6061999-10-20020 October 1999 Notification of 991102 Meeting with Util in Port Gibson,Ms to Discuss Bases for Emergency Preparedness Plan Change Submitted in & Supplemented by 990120 & 0715 Ltrs ML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components IR 05000416/19990021999-09-10010 September 1999 Notification of Significant Licensee Meeting with Entergy Operations,Inc on 991018 to Discuss Listed Topics Identified in NRC Insp Repts 50-416/99-02,99-03 & 99-06 ML20211K7171999-09-0202 September 1999 Forwards Ineel Technical Ltr Rept, Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors Dated 990730.Rept Used for Review of BWROG Rept on Revised Source Term Accident Analysis ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20196F0391999-06-23023 June 1999 Notification of 990707 & 08 Meeting with EOI in Conference 1 at GGNS Energy Svc Ctr to Discuss Low Power Shutdown Risk Assessment Methods & Associated Probabilistic Risk Assessment Model ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20207A2551999-05-18018 May 1999 Notification of 990603 Meeting with EOI in Rockville,Md to Discuss EOI Submittal on BWROG Source Term Analysis & Possible Related Future Amend Requests from EOI ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205R8871999-04-20020 April 1999 Notification of 990504 Meeting with Util in Rockville,Md to Discuss Proposal to Submit Consolidated Security Plan for Util Sites ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20204B3041999-03-15015 March 1999 Notification of Licensee Meeting with Util in Energy Svc Ctr,Grand Gulf Site on 990415 to Discuss Plant Performance Review Results.Meeting Open to Public ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195G1121998-11-17017 November 1998 Notification of 981201-02 Meeting with Entergy Operations in Taft,Louisianna to Conduct Joint Workshop for Licensing Personnel from Entergy & Nrc,Project Directorate IV-1 ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl 1999-09-21
[Table view] Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212H2231999-09-24024 September 1999 Summary of 990831-0901 Meeting with STPNOC in Rockville, Maryland Re 990713 Request for 14 risk-informed Exemptions to Exclude safety-related LSSC & non-risk Significant Components from Special Treatment Requirements ML20210Q1841999-08-11011 August 1999 Summary of 990722 Meeting with Util Re Proposed TS for SG Water Level low-top Trip Setpoint.List of Meeting Attendees & Handout Provided by Util Encl ML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20206G4841999-04-30030 April 1999 Summary of 990315 Meeting with STP Nuclear Operating Co Re Util Submittal of Draft Request for Exemption from Special Treatment Requirements for Components That Are Low Safety Significant or non-risk Significant, ML20199D1931999-01-11011 January 1999 Summary of 981208 Meeting with STPNOC Re Status of Current & Future Licensing Actions & Activities.List of Meeting Attendees & Handout Provided by Licensee 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 ML20195G0641998-11-17017 November 1998 Summary of 980915 Meeting with STP Nuclear Operating Co Re Graded Quality Assurance Implementation & Challenges.List of Attendees & Handout Provided by Licensee Encl ML20155E1271998-11-0202 November 1998 Summary of 981008 Conference Call with Util to Discuss Course Action That Would Be Anticipated If Licensee Were to Submit risk-informed Inservice Insp &/Or risk-informed Inservice Testing Program 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 ML20154J7961998-10-13013 October 1998 Summary of 980915 Meeting with Licensee Re risk-informed Operations at Stp.Copies of Slides Presented Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout 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 ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20247L7411998-05-20020 May 1998 Summary of 980506 Meeting W/Util in Re Proposed Merger Between America Electric Power Co,Inc & Central & Southwest Corp (Csw).Meeting Attendees & Handout Provided by Csw Encl ML20217Q6491998-05-0505 May 1998 Summary of 980413 Meeting W/South Texas Project Nuclear Operating Company Re Current South Texas Project Improved TS Schedule.List of Meeting Attendees & Schedule 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 ML20217N0851998-04-0606 April 1998 Summary of 980303 Meeting W/South Texas Project Re long-term Resolution of Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System. Proprietary & non-proprietary Handouts Provided by Licensee 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 ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout 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 ML20199J3371998-02-0202 February 1998 Summary of 980121 Meeting W/Stp Nuclear Operating Co Re Schedule for NRC Review of STPNOC Application for Conversion to Improved Standard Ts.List of Attendees & Handout Provided by Licensee Encl ML20198K4781998-01-0606 January 1998 Summary of 971204 Meeting W/Licensee & Representatives from W Re Proposed 3 Volt Alternate Repair Criteria for Plants Unit 2 Sg.List of Attendees & Handout Encl ML20198G4601997-12-19019 December 1997 Summary of 971210 Meeting W/Licensee Re SG Replacement for Unit 1.List of Attendees & Handout Matls Provided by Licensee Encl ML20199E5771997-11-13013 November 1997 Trip Rept of 971105-06 Visit to Facility for Interviews in Preparation of SALP for Plant ML20212G5041997-10-29029 October 1997 Summary of 971002 Meeting W/Util in Rockville,Md to Discuss Staff Review Schedule for Plant Improved Std TS Conversion Amend.List of Attendees 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 ML20217E0131997-09-29029 September 1997 Trip Rept of 970825-26 Visit to Plant,Unit 1 for Interviews in Preparation of Salp.Agenda for Interviews Encl ML20217E4511997-09-22022 September 1997 Summary of 970911 Meeting W/Util in Rockville,Md Re STP 3-train Design & Improved Std TSs Format ML20198R3481997-09-0404 September 1997 Trip Rept of 961121 Visit to GGNS to Discuss Implementation Methodologies Employed for Graded Aq in Procurement Area ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20141C0811997-05-14014 May 1997 Summary of 970424 Meeting W/Util to Discuss Hl&P Plans Re Incomplete Control Rod Insertion at Stp,Units 1 & 2.Meeting Attendees & Handout Provided by Hl&P,Encl ML20140H7801997-05-0808 May 1997 Summary of 970421 Meeting W/Hl&P to Discuss Hl&P Proposed QA Program Change to Implement Graded QA ML20137Z3651997-04-22022 April 1997 Summary of 970403 Meeting W/Util in Rockville,Md to Discuss Staff Review of Licensee Pilot Submittal for Section 3.5 of Project Conversion Amend.List of Attendees & Staff Handouts Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl ML20137Q8641997-04-0909 April 1997 Summary of 970331 Meeting W/Util Re Util Graded QA Application.List of Attendees Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20133N3821997-01-17017 January 1997 Summary of 970109 Meeting W/Hl&P Re Response to NRC Bulletin 96-01, Control Rod Insertion Problems. List of Attendees & Licensee Handout Encl ML20133M2671997-01-15015 January 1997 Summary of 961212 Meeting W/Util Re Status of Staff Review of Licensee Request to Convert Plant TS to Improved Std TS Format.List of Attendees Encl ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document 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 ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 ML20134L7841996-11-20020 November 1996 Summary of 961114 Meeting W/Hl&P in Rockville,Md to Discuss Status of NRC Review of Licensee Request to Convert STP TSs to Improved STS Format.List of Attendees Encl ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20206R4701996-11-0707 November 1996 Summary of 960821-22 Meetings with Hl&P in Wadsworth,Texas Re Graded Quality Assurance Program at Stp.List of Meeting Attendees for Initial Meeting,List of Meetings Held During Two Day Session & Handouts for Meetings Encl ML20128L2901996-10-0808 October 1996 Summary of 960916 Meeting W/Hl&P to Discuss Plans for SG Replacement at STP-1.List of Attendees & Handout Encl ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents 1999-09-24
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20212H2231999-09-24024 September 1999 Summary of 990831-0901 Meeting with STPNOC in Rockville, Maryland Re 990713 Request for 14 risk-informed Exemptions to Exclude safety-related LSSC & non-risk Significant Components from Special Treatment Requirements ML20210Q1841999-08-11011 August 1999 Summary of 990722 Meeting with Util Re Proposed TS for SG Water Level low-top Trip Setpoint.List of Meeting Attendees & Handout Provided by Util Encl ML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20206G4841999-04-30030 April 1999 Summary of 990315 Meeting with STP Nuclear Operating Co Re Util Submittal of Draft Request for Exemption from Special Treatment Requirements for Components That Are Low Safety Significant or non-risk Significant, ML20199D1931999-01-11011 January 1999 Summary of 981208 Meeting with STPNOC Re Status of Current & Future Licensing Actions & Activities.List of Meeting Attendees & Handout Provided by Licensee 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 ML20195G0641998-11-17017 November 1998 Summary of 980915 Meeting with STP Nuclear Operating Co Re Graded Quality Assurance Implementation & Challenges.List of Attendees & Handout Provided by Licensee Encl ML20155E1271998-11-0202 November 1998 Summary of 981008 Conference Call with Util to Discuss Course Action That Would Be Anticipated If Licensee Were to Submit risk-informed Inservice Insp &/Or risk-informed Inservice Testing Program 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 ML20154J7961998-10-13013 October 1998 Summary of 980915 Meeting with Licensee Re risk-informed Operations at Stp.Copies of Slides Presented Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout 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 ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20247L7411998-05-20020 May 1998 Summary of 980506 Meeting W/Util in Re Proposed Merger Between America Electric Power Co,Inc & Central & Southwest Corp (Csw).Meeting Attendees & Handout Provided by Csw Encl ML20217Q6491998-05-0505 May 1998 Summary of 980413 Meeting W/South Texas Project Nuclear Operating Company Re Current South Texas Project Improved TS Schedule.List of Meeting Attendees & Schedule 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 ML20217N0851998-04-0606 April 1998 Summary of 980303 Meeting W/South Texas Project Re long-term Resolution of Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System. Proprietary & non-proprietary Handouts Provided by Licensee 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 ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout 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 ML20199J3371998-02-0202 February 1998 Summary of 980121 Meeting W/Stp Nuclear Operating Co Re Schedule for NRC Review of STPNOC Application for Conversion to Improved Standard Ts.List of Attendees & Handout Provided by Licensee Encl ML20198K4781998-01-0606 January 1998 Summary of 971204 Meeting W/Licensee & Representatives from W Re Proposed 3 Volt Alternate Repair Criteria for Plants Unit 2 Sg.List of Attendees & Handout Encl ML20198G4601997-12-19019 December 1997 Summary of 971210 Meeting W/Licensee Re SG Replacement for Unit 1.List of Attendees & Handout Matls Provided by Licensee 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 ML20212G5041997-10-29029 October 1997 Summary of 971002 Meeting W/Util in Rockville,Md to Discuss Staff Review Schedule for Plant Improved Std TS Conversion Amend.List of Attendees Encl ML20217E4511997-09-22022 September 1997 Summary of 970911 Meeting W/Util in Rockville,Md Re STP 3-train Design & Improved Std TSs Format ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20141C0811997-05-14014 May 1997 Summary of 970424 Meeting W/Util to Discuss Hl&P Plans Re Incomplete Control Rod Insertion at Stp,Units 1 & 2.Meeting Attendees & Handout Provided by Hl&P,Encl ML20140H7801997-05-0808 May 1997 Summary of 970421 Meeting W/Hl&P to Discuss Hl&P Proposed QA Program Change to Implement Graded QA ML20137Z3651997-04-22022 April 1997 Summary of 970403 Meeting W/Util in Rockville,Md to Discuss Staff Review of Licensee Pilot Submittal for Section 3.5 of Project Conversion Amend.List of Attendees & Staff Handouts Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl ML20137Q8641997-04-0909 April 1997 Summary of 970331 Meeting W/Util Re Util Graded QA Application.List of Attendees Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20133N3821997-01-17017 January 1997 Summary of 970109 Meeting W/Hl&P Re Response to NRC Bulletin 96-01, Control Rod Insertion Problems. List of Attendees & Licensee Handout Encl ML20133M2671997-01-15015 January 1997 Summary of 961212 Meeting W/Util Re Status of Staff Review of Licensee Request to Convert Plant TS to Improved Std TS Format.List of Attendees Encl ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document 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 ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 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 ML20134L7841996-11-20020 November 1996 Summary of 961114 Meeting W/Hl&P in Rockville,Md to Discuss Status of NRC Review of Licensee Request to Convert STP TSs to Improved STS Format.List of Attendees Encl ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20206R4701996-11-0707 November 1996 Summary of 960821-22 Meetings with Hl&P in Wadsworth,Texas Re Graded Quality Assurance Program at Stp.List of Meeting Attendees for Initial Meeting,List of Meetings Held During Two Day Session & Handouts for Meetings Encl ML20128L2901996-10-0808 October 1996 Summary of 960916 Meeting W/Hl&P to Discuss Plans for SG Replacement at STP-1.List of Attendees & Handout Encl ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20059K1731994-01-27027 January 1994 Summary of 940121 Meeting W/Utils Re Results of Operational Readiness Assessment Team Insp at Plant.Various Deficiencies Noted.Media Representatives in Attendance ML20059F3491994-01-0606 January 1994 Summary of 931217 Meeting W/Hl&P Re Analysis Performed on Ecw Sys.W/Attendance List & Meeting Agenda 1999-09-24
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217M6061999-10-20020 October 1999 Notification of 991102 Meeting with Util in Port Gibson,Ms to Discuss Bases for Emergency Preparedness Plan Change Submitted in & Supplemented by 990120 & 0715 Ltrs ML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components IR 05000416/19990021999-09-10010 September 1999 Notification of Significant Licensee Meeting with Entergy Operations,Inc on 991018 to Discuss Listed Topics Identified in NRC Insp Repts 50-416/99-02,99-03 & 99-06 ML20211K7171999-09-0202 September 1999 Forwards Ineel Technical Ltr Rept, Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors Dated 990730.Rept Used for Review of BWROG Rept on Revised Source Term Accident Analysis ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20196F0391999-06-23023 June 1999 Notification of 990707 & 08 Meeting with EOI in Conference 1 at GGNS Energy Svc Ctr to Discuss Low Power Shutdown Risk Assessment Methods & Associated Probabilistic Risk Assessment Model ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20207A2551999-05-18018 May 1999 Notification of 990603 Meeting with EOI in Rockville,Md to Discuss EOI Submittal on BWROG Source Term Analysis & Possible Related Future Amend Requests from EOI ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205R8871999-04-20020 April 1999 Notification of 990504 Meeting with Util in Rockville,Md to Discuss Proposal to Submit Consolidated Security Plan for Util Sites ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20204B3041999-03-15015 March 1999 Notification of Licensee Meeting with Util in Energy Svc Ctr,Grand Gulf Site on 990415 to Discuss Plant Performance Review Results.Meeting Open to Public ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195G1121998-11-17017 November 1998 Notification of 981201-02 Meeting with Entergy Operations in Taft,Louisianna to Conduct Joint Workshop for Licensing Personnel from Entergy & Nrc,Project Directorate IV-1 ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl 1999-09-21
[Table view] |
Text
_ _
~
e nau j* t UNITED STATES g
2 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001
'+,,.....p March 24, 1997 MEMORANDUM TO: David B. Matthews, Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management [
Office of Nuclear Reactor Regulation FROM: Melinda Malloy, Project Manager Generic issues and Environmenta Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING WITH THE NUCLEAR ENERGY INSTITUTE (NEI) AND LICENSEE REPRESENTATIVES ON QUALITY-ASSURANCE-RELATED TOPICS On February 7,1997, representatives of the U.S. Nuclear Regulatory Commission (NRC) met with representatives of the Nuclear Energy Institute (NEI), Arizona Public Service Company's Palo Verde Nuclear Generating Station (PVNGS), and Houston Lighting &
Power Company's South Texas Project (STP) at the NRC's offices in Rockville, Maryland.
The purpose of the meeting was to discuss NEl's concems related to graded quality assurance (GOA) activities with volunteer plants (Grand Gulf Nuclear Station, PVNGS, and STP), performance-based QA activities, the potential impact on the volunteer plants of the draft regulatory guide (RG) on GOA, and the status of the staff's review of the petition for rulemaking on 10 CFR 50.54(a) which was filed by NEl on' behalf of the nuclear utilities.
These concerns were articulated in an October 10,1996, letter from Ralph Beedle to Ashok Thadani (NRC) (see Accession No. 9610230003 for this lett'er). The list of meeting attendees is provided in Attachment 1.
- 1. Performance-Based Reaulations and Graded QA NEl presented an outline of what the industry co1siders are necessary steps to improve the regulatory process for QA (Attachment 2). MI reiterated its concurrence with the staff position on policy issues discussed in SECY 96-218,=" Quarterly Status Update for the Probabilistic Risk Assessment (PRA) lmplementation Plan, including a Discussion of Four Emerging Policy issues Associated with Risk-informed Performance-Based Regulation," dated October 11,1996, as well as with the associated staff requirements memorandum from the Commission, dated January 22,1997. NEl stated that probabilistic safety assessment (PSA) techniques constitute an invaluable tool for implementing the maintenance rule. NEl also stated that while the risk-informed ,
approaches are similar for in-service testing (IST) and GOA, it acknowledged limitations I' in modeling the effect of GOA changes in the PRA model. Ofg 310048 NRC HLE CENTHi Wh
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D. Matthews -2 March 24, 1997 :
L j
The staff emphasized its continuing commitment to resolving the risk-informed,
. performance-based regulatory issues discussed in SECY-96-218. The staff indicated i that there are certain concerns related to PSA which must be addressed. Specifically, the staff is concemed that the industry has not yet developed or demonstrated a .
sufficiently sound process (i.e., scrutable and repeatable) that would guide the j consistent implementation of PSA technology in all suitable regulatory areas, while at l the same time maintaining the necessary regulatory and safety margins. Another .
remaining area of concem for the staff is the quality of the PRA models and the scope of their modeling. Despite these concems, the staff continues to encourage industry in ,
using PSA techniques for GQA; as well as for other regulatory applications (e.g., IST, '
Improved Standard Technical Specifications (iSTS), etc.). ;
Although it intends to proceed cautiously with a risk-informed, performance-based ,
regulatory regime until all safety and regulatory implications are fully understood, the staff does not share the industry's perception that little progress has been made in !
agency efforts aimed at increasing the use of PSA tools in regulatory decision-making l processes. As an example of progress in this area, the staff cited the amendment to !
the STP Technical Specifications. !
I NEl emphasized that in its opinion, the GQA initiative is a prime candidate to pursue for
- performance-based regulatory improvements. NEl outlined its conceptual framework for a performance-based monitoring approach. NEl also expressed its intent to meet i again with the staff in April 1997 to further discuss the approach and to develop plans !
for a pilot implementation. '
i
- 2. Staff Activities with Graded QA Volunteer Plants l
The Houston Lighting and Power (HL&P) Company representatives presented a brief synopsis of GOA activities at the STP site (Attachment 3). The presentation included i an historical summary, a description of the QA program changes needed to implement '
a GQA program at the STP, the status of current activities, and an account of safety :
significance categorization of the first two systems. The HL&P representatives !
expressed concems about their planned GQA approach in light of the uncertainties !
associated with their perceptions on upcoming guidance from the draft RG on GQA. ,
The Arizona Public Service (APS) Company representatives discussed the GQA efforts at the PVNGS. Their presentation slides are provided in Attachment 4. Functional areas that the licensee has selected for application of GQA include procurement and ;
audits. Other areas that have been identified for potential application include j environmental equipment qualification, commodities, and the critical vendors list. The l
APS representatives expressed an interest in continuing the dialogue with the staff in '
trying to resolve previous comments and concerns identified during past staff site visits.
l
l March 24, 1997 D. Matthews The representatives from NEl and the GOA volunteer plants present at the meeting stated that the staff's expectations on the level of detail needed for an acceptable risk-ranking process for GOA remains unclear. Specifically, they stated they were unaware of the need to include quantitative PRA sensitivity analyses as part of the structures, systems, and components (SSCs) safety significant categorization process. The staff's initial thoughts on needed studies was discussed during the February 21,1997, briefing on the draft RG on GOA to the Advisory Committee on Reactor Safeguards (ACRS). The staff identified two types of studies; one involving changes in the PRA model to reduce the categorization dependence on highly uncertain PRA models (e.g.,
operator recovery and common-cause failures); and the other to investigate the aggregate risk impact of implementing GOA by simultaneously varying the failure probability of alllow-safety-significant SSCs.
The staff clarified that these were not new staff concerns and that requests for additional information (RAls) sent to HL&P (on the STP), as a graded QA volunteer, included questions regarding'such studies. HL&P's response to the RAls was that some model sensitivity studies were planned, but that the identified aggregate risk sensitivity issue would be controlled by the performance monitoring feedback loop.
Similar responses to similar RAls were also received from Entergy for Grand Gulf and the APS for the PVNGS. The staff reiterated the importance of satisfying technical issues in this area.
NEl stated that the industry remains concerned about staff expectations on GOA which it believes to be contained in the draft RG and which remain unknown to the volunteers plants. The staff acknowledged the concems and stated that in keeping with its commitments to the Commission, its goal is to issue all risk-informed RGs for public comment no later than April 1997.
- 3. Petition for Rulemakina on 10 CFR 50.54(a) and Performance-Based QA NEl emphasized that while the industry does not believe that changes in the provisions of Appendix B to 10 CFR Part 50 are necessary, a change to the provisions of 10 CFR 50.54(a) is needed if the industry is to be allowed to move forward on performance-
- based approaches to implementing OA programs. NEl presented its early concept of performance-based QA indicators (see Attachment 2) which would provide monitoring and trending data for utilities to identify degrading conditions and to take corrective actions as necessary. Such an approach rests on the assumption that licensees would have flexibility (not currently available under 10 CFR 50.54(a)) to change or re-arrange their QA program implementation without prior NRC approval. NEl reiterated its belief that the current GA program change process is too cumbersome and that more balance is needed.
l The staff agreed that it is appropriate to evaluate the 10 CFR 50.54(a) OA program {
change process to find objectively acceptable alternatives to the threshold for reporting l QA program changes requiring prior approval by the NRC. The staff emphasized, l i
j
- - . . _ _ - - _ = . . _ _ . . . . . . . . - - - . . - . - - . . . - . - . - . . . - . - . - -.. . . . - .
i . j D. Matthews 4 March 24, 1997 {
I 1
however, that the outcome of the NEl petition should not prevent or inhibit progress in GQA activities at the volunteer plants. l At the conclusion of the meeting, both NEl and the staff agreed that progress can be made j; towards a more performance-based regulatory framework and agreed to meet to continue I the dialogue once the risk-informed RGs are issued for public comment.
j This summary was prepared with input provided by the staff of the Quality Assurance and ,
. Maintenance Branch, Division of Reactor Controls and Human Factors, Office of Nuclear i 1
- Reactor Regulation (NRR) and the staff of the Probabilistic Safety Assessment Branch l
- Division of Systems Safety and Analysis, NRR. ,
i Attachments:
- 1. List of Attendees i
- 2. NEl's Briefing Slides :
- 3. - HL&P's Briefing Slides
- 4. APS's Briefing Slides l l
Project No. 689 )
l l
cc w/atts: See next page 1
- .. . =. - -- - .. - - _- -. . -_ ~_.-.
D. Matthews 4 March 24, 1997 however, that the outcome of the Nt:1 petition should not prevent or inhibit progress in GOA activities at the volunteer plants.
At the conclusion of the meeting, both NEl and the staff agreed that progress can be made towards a more performance-based regulatory framework and agreed to meet to continue the dialogue once the risk-informed RGs are issued for public comment.
This summary was prepared with input provided by the staff of the Quality Assurance and Maintenance Branch, Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation (NRR) and the staff of the Probabilistic Safety Assessment Branch, Division of Systems Safety and Analysis, NRR.
Attachments:
- 1. List of Attendees
- 2. NEl's Briefing Slides
- 3. HL&P's Briefing Slides
- 4. APS's Briefing Slides Project No. 689 cc w/atts: See next page DISTRIBUTION: See attached page i
l I
1 Document Name: g:\mxm\MSUM0227.97
- SEE PREylOpS COrKUhRENCES OFFICE PGEB:DRPM BC:HQMB:DRCH BC:SPSB:DSSA SC:PGEB:1 C:PGh: PM 1
l NAME MMalloy:sw' SBlack' MRubin' FAkst icz DMatt DATE 03/11/97 03/14/97 o3/17/97 03p97 o3dh 97 i
OFFICIAL RECORD COPY l
1
4 1
NRC-NEl MEETING ON QA-RELATED TOPICS February 27,1997 >
List of Attendees Name Oroanization Ralph Beedle Nuclear Energy institute MaryAnn Biamonte NRC/EDO Suzanne Black NRC/NRR/HOMB Larry Campbell NRC/NRR/HOMB Mike Cheok NRC/NRR/SPSB Stephen Dinsmore NRC/NRR/SPSB Jack Donohew NRC/NRR/DRPW Ed Ford NRC/NRR/HOMB Rosemary Fullner Arizona Public Service Co./Palo Verde Robert Gramm NRC/NRR/HOMB Owen Gormley NRC/RES/GSIB Dale Harmon Westinghouse Energy Systems Walter P. Haass NRC/NRR/HOMB Adrian Heymer Nuclear Energy Institute Lee Higgins NRC/OlG ,
Gary Holahan NRC/NRR/DSSA l Robert Jones NRC/NRR/SPSB Michael Knapik McGraw-Hill Donald Lamontagne Arizona Public Service Co./Palo Verde Robert M. Latta NRC/NRR/HOMB Richard P. Lynskey Tennessee Valley Authority Mark McBurnett Houston Lighting & Power Co./ STP Juan Peralta NRC/NRR/HOMB Tony Pietrangelo Nuclear Energy Institute Mike Polak Baltimore Gas & Electric Co.
Roy Rehkugler Houston Lighting & Power Co./ STP Mark Rubin NRC/DSSA/SPSB R. Lee Spessard NRC/NRR/DRCH l Donald Taylor NRC/NRR/HOMB l Ashok Thadani NRR/ADT ]
l 1
I 1
1 Attachment 1
- . - .- -. . .- . . ~ - . . .-.-. .__ . . . -
i List of Attendees i Name Organization Roger D. Walker TU Electric H. Roy Woods NRC/RES/PRAB Altheia Wyche SERCH Licensing /Bechtel Abbreviations ADT- Associate Director for Technical Assessment Co. Company DRPW Division of Reactor Projects lli & IV DRCH Division of Reactor Controle end Human Factore DSSA Division of Systems Safety and Analysis EDO Office of the Executive Director for Operations GSIB Generic Safety leeues Branch HOMB Quality Assurance end Maintenance Branch NRC U.S. Nuclear Reguletory Commission '
NRR Office of Nuclear Reactor Regulation OlG Office of the inspector General PRAB Probabilistic Riek Analysis Branch RES Office of Nuclear Regulatory Research SPSB Probabilistic Safety Assessment Branch STP South Texas Project List of Attendees l
IMPROVING THE REGULATORY PROCESS FOR QA i
NRC - NEl Meeting February 27,1997 4
Attachment 2
..l l
IMPROVING THE REGULATORY PROCESS FOR QA Clarify statements made in NEl letter 10/10/96
- -Use of PSA
-QA Program for low safety significant SSCs Improved approach needed for assessing QA program effectiveness -- performance-based
-Monitoring plant (equipment, personnel, process)
- Precursors for declining plant performance Graded QA Draft Reg. Guide
- Uncertainty
-Status b'
--_j
. .l i
NEl LETTER ON GRADED QA 10/10/96 Industry uncertainty ,
- progress & industrywide benefit NRC - pilot project meetings
- RAls
-Industry perce ations Uncertainty over adequacy of QA program for low safety significant SSCs l ACRS briefings
- Apparent convergence at Nov.1996 briefing
-Uncertainty in Feb.1997 briefing e .g.
) .:
GRADED APPROACH TO IMPLEMENTING .
QUALITY
- A A High Safety-Significant (safety related &
non-safety related) Company Quality Regulatory Program meets !
Scope -- App. B req'ts as Maint. Rule + necessary --
Low .
Safety-Significant Graded per i safety i (safety related & significance non-safety related) t V
l:
Other SSCs i u !
Reg. Scope = Maint. Rule Scope + Other SSCs from Other Regs.
6
. . t
.l PERFORMANCE-BASED QA_
i SCOPE ! CATEGORIZATION i QA ELEMENTS i EFFECTIVENESS n n JL l
High Safety Significance (safety related &
non-safety related) Company Quality Regulatory Program - Assessment of Scope + Graded per program effectiveness safety via monitoring i Low Safety significance plant condition or Significance (Meets Regs) Performance (safety related &
non-safety related) !
if ...... .............. .. .......... ............... ..... .......
1f ........
Other SSCs 1r
+ Reg. Scope = Maint. Rule SSCs + Other SSCs from Other Regs.
6 .
i
PERFORMANCE-BASED APPROACH TO ASSESS QA PROGRAM EFFECTIVENESS Current assessment -- programmatic compliance
- Focus is on literal program implementation
-Limited focus on safety significance, results Improved approach -- performance-based
- Prime focus on results -- organizational functions
- Enhances feedback for graded QA
-Improved tool for management oversight e .g;.
1
PERFORMANCE-BASED REGULATION ;
1/22/97 SRM on SECY 96-218 recommendations on performance-based implementation of the regulations '
-Measurable parameters
-Objective criteria
-Licensee flexibility on how to meet criteria ,
-Fai ure to meet criteria will not result in an intolerable outcome QA - Plant management process
- Regulatory aspect -- provides reasonable assurance that safety functions will be performed z .g.
.l PERFORMANCE-BASED QA ASSESSMENT Monitoring plant { equipment, people, process}
Equipment -- level of monitoring very similar to that of the maintenance rule Process & people -- level of monitoring similar to that established in licensee management monitonng programs Performance-Based QA indicators provide earlier identification of declining plant performance
- Developing leading indicators
PERFORMANCE-BASED QA ,
Monitoring & trending indicators Failure to meet criteria ,
-Perform a cause determination ;
-Focus on cause and correction before criteria are i violated --if necessary, through QA program changes Significant incentive to meet indicators
- Assures protection of public health & safety while focusing resources more effectively
-Consistent process for licensee /NRC assessment of plant performance l i 6
- 1. .
A EFFECTIVENESS ASSESSMENT PERFORMANCE-BASED QA LICENSEE (REGULATORY) CRITERIA .
CORRECTIVE ACTION MONITORING & TRhNDING PROGRAMS (e.g., plant, system, organizational,..)
A A A A
- - h- - - - :-SUPPORTiNO-PROGRAMS-Y .
PLANT PROGRAMS & CRITERIA ;
I (Vibration, oil analysis, erosion / corrosion, organizational functions, water chemistry, design, testing, procurement, calibration, ;
employee concerns, industry guidelines, standards, etc..)
i 10 i
REGULATORY CHANGES TO lMPLEMENT IMPROVED APPROACH 10 CFR 50.54(a)
Compatibility with SRM on SECY 96-218
-Licensee flexibility in meeting the criteria (Appendix B & monitoring criteria)
Options to NEl petition
-Discussed in April 30,1996 NEl - NRC meeting
-Summarized in NEl May 30,1996 letter to NRC .
Further dialogue would be beneficial
.g.
DRAFT PERFORMANCE-BASED QA PLAN Amend and improve the regulatory change process for QA programs - @50.54(a)
NRC involvement and endorsement of industry i guideline for the development of:
-indicators
-criteria
-assessment process Licensees implement performance-based QA per
! guideline recommendations
,2
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GRADED QUALITY ASSURANCE AT STP
~
HISTORY April 1995 -
Entered into agreement with NRC staff as volunteer (Pilot) plant March 1996 -
Sobinitted revised QA plan depicting Graded QA August 1996 -
Received NRC comments / questions i
January 1997 -
Submitted draft QA Plan revision (major format) i
GRADED QUALITY ASSURANCE AT STP SITE STATUS
- Implementing procedures, Expert Panel, GQA Working Group in place and '
working
- Two system reviews (essential cooling water, radiation monitoring) are completed and approved by Expert Panel t
- Third system (Emergency Diesel Generators) nearly completed Reviews of 24 additional systems will occur in 1997 i
. The GQA process has been frozen past the point of Expert Panel review / approval of system review packages
7 GRADED QUALITY ASSURANCE AT STP THREE LEVELS OF PROGRAM CONTROLS FULL: Highest possible levels of control / oversight - applied to safety related, high important items BASIC: Lesser levels of control / oversight - applied to other safety related items TARGETED: Select levels of control / oversight - applied to non-safety related, risk important items l
l l
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GRADED QUALITY ASSURANCE AT STP FIRST TWO SYSTEMS REVIEW RESULTS ESSENTIAL COOLING WATER COMPONENTS Full QA - 6 Basic QA - 1,050 Targeted QA - 307 No QA - 43 I
RADIATION MONITORING COMPONENTS Full QA - 0 Basic QA - 388 Targeted QA - 1,131 No QA 303
GRADED QUALITY ASSURANCE AT STP GQA BENEFITS
- Increased Nuclear Safety
. Increased cost effectiveness (STP anticipates approximately $1.5 million '
savings per year in procurement costs alone) i i
t I
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GRADED QUALITY ASSURANCE AT STP STP plans to proceed with GQA Program implementation June 1,1997 i
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i
Palo Verde Nuclear Generating Station 4
Graded Quality Assurance Presented by Donald Lamontagne February 27,1997 Attachment 4 i
,e Graded Quality Assurance Functional Areas l
+ Procurement l
l i
l
+ QA Audits and Evaluations
. . . ,w
- Graded Quality Assurance Procurement Improvements Made In 1996
+ Selection and Documentation of Critical Verification Attributes
, + Post-Installation Testing
+ Equipment Failure Feedback Mechanisms 4
+ Seismic Qualification Si&L
~
i Graded Quality Assurance 1997 Procurement Initiatives i
1 i
+ Emphasize Increased Use of Graded QA i
l
+ Equipment Qualification
- + Commodities
+ CriticalVendors List i
- m..o.,.,, - , m ,
I 4
E ;
, l NEl Project No. 689 cc: Mr. Ralph Beedle Mr. Thomas Tipton, Vice President i Senior Vice President Operations j and Chief Nuclear Officer Nuclear Energy Institute j Nuclear Energy Institute Suite 400 1 Suite 400 1776 l Street, NW l 17761 Street, NW Washington, DC 20006-3708 i
- Washington, DC 20006-3708 )
Mr. Alex Marion, Director Mr. Jim Davis, Director .
Programs Operations i
Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suite 400 1 1776 i Street, NW 1776 I Street, NW l Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. David Modeen, Director Ms. Lynnette Hendricks, Director Engineering Plant Support Nuclear Energy Institute Nuclear Energy Institute J Suite 400 Suite 400 1776 i Street, NW 1776 l Street, NW ,
Washington, DC 20006-3708 Washington, DC 20006-3708 ;
Mr. Anthony Pietrangelo, Director '
Licensing Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Ronald Simard, Director :
Advanced Technology l Nuclear Energy Institute l Suite 400 1 1776 i Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 i
j
r l-lI Distribution for Summary of Meeting w/ NEl on QA-Related Topics dated March 24, 1997 Hard Cooy Central Files PUBLIC PGEB r/f MMalloy SMagruder ACRS i E-Mail l
SCollins - l l FMiraglia RZimmerman '
JDonohew RAuluck TAlexion FGillespie AThadani BBoger LSpessard SBlack RGramm EFord LCampbell l WHaass !'
RLatta JPeralta DTaylor i GHolahan '
j RJones 4 MRubin !
MCheok SDinsmore TTMartin ,
MSlosson DMatthews FAkstulewicz SMagruder MMalloy BSheron TOMartin, RES PKadambi, RES l OGormley, RES )
MCunningham, RES i HWoods, RES I ARamey-Smith, RES HBell, OlG LHiggins, OlG JMoore, OGC l
BBordenick, OGC MBismonte, EDO l WDean, EDO 1
l l
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