Letter Sequence Meeting |
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Results
Other: ML20136J106, ML20137W989, ML20140D589, ML20153D518, ML20153D535, ML20154M151, ML20154N307, ML20203N882, ML20206F544, ML20214L542, ML20214L543, ML20214L552, ML20214L559
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MONTHYEARML20214L5421985-12-26026 December 1985
Confirmatory Action Ltr Re Facility Return to Power Operations.Understands Util Will Conduct Root Cause Analysis of 851226 Reactor Trip & Provide Briefing of Assessment & Justification to Resume Power Operations
Project stage: Other
ML20214L5591985-12-27027 December 1985
Forwards Proposed Plan for Facility Augmented Investigation Team.Comments Requested by 851227.Chronological Sequence of Events Re 851226 Event Also Encl
Project stage: Other
ML20136J1061986-01-0505 January 1986
PNO-IIT-86-001A:on 851226,loss of Integrated Control Sys Occurred.Caused by Simultaneous Deenergizing of All Redundant Dc Power Supplies.Licensee Preparing Action Plans for Systematic Troubleshooting.Sequence of Events Encl
Project stage: Other
ML20137J7271986-01-0606 January 1986
Notifies of 860108 Meeting W/B&W Regulatory Response Group in Bethesda,Md to Discuss 851226 Loss of Integrated Control Sys Power & Generic Implications for Other B&W Plants.Info Confirms NRC 851230 Request
Project stage: Meeting
ML20214L5551986-01-0707 January 1986
Forwards Addl Info for Use in Conjunction W/Meeting W/B&W Regulatory Response Group,Including List of Issues That Rancho Seco Incident Investigation Team Has Identified to Date Associated w/851226 Overcooling Event
Project stage: Meeting
ML20214L5521986-01-20020 January 1986
Package of Two Documents Entitled, Action List,851226 Transient
Project stage: Other
ML20140D5891986-01-24024 January 1986
Forwards Schedule for Return to Power Operations from 851226 Transient.Schedule Consists of Comprehensive Action List & Milestone Schedule.Commencement of Power Operation Scheduled for 860308
Project stage: Other
ML20214L5511986-02-0707 February 1986
Notification of Significant Licensee Meeting on 860210 W/Util in Walnut Creek,Ca to Discuss Review of Plant Restart Actions for Facility Following 851226 Event
Project stage: Meeting
ML20153D5351986-02-19019 February 1986
Description & Resolution of Issues Re 851226 Reactor Trip
Project stage: Other
ML20153D5181986-02-19019 February 1986
Forwards Summary Rept, Description & Resolution of Issues Re 851226 Reactor Trip, Supporting Resumption of Power Operation as Scheduled on 860308.Previous Actions Summarized
Project stage: Other
ML20137W9891986-02-24024 February 1986
Forwards Addendum to 860219 Summary Rept Re Resolution of Issues from 851226 Reactor Trip,Replacing Page 41.Addendum Addresses Remote Isolation Capability for Main Steam Lines, Independent of ICS Power & Controls
Project stage: Other
ML20214E3401986-03-0505 March 1986
Requests Review of Encl Tentative Review Assignments for Action Plan for Restart of Plant by 860307.Requests for Addl Info Re Encl Proposed Resolution of Issues Concerning 851226 Event Requested by 860321.W/o Encls
Project stage: Approval
ML20154M1511986-03-0606 March 1986
Staff Requirements Memo Re 860225 Briefing in Washington,Dc Concerning Incident Investigation Team Rept on 851226 Loss of Power in Integrated Control Sys.Schedules for Followup Plan & Assessment Re Lack of Plant Mods Requested
Project stage: Other
ML20214L5431986-03-10010 March 1986
Viewgraphs Entitled, Smud
Project stage: Other
ML20154N3071986-03-12012 March 1986
Forwards Design Basis Rept for Mods to Facility Based on 851226 Transient
Project stage: Other
ML20199D7561986-03-17017 March 1986
Notification of 860324 & 25 Meetings & Plant Trip W/Util in Herald,Ca to Discuss Proposed Plans for Recovery from 851226 Incident.Agenda Encl
Project stage: Meeting
ML20203H2181986-04-14014 April 1986
Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl
Project stage: Meeting
ML20210R9391986-04-23023 April 1986
Summary of 860324-25 Meetings W/Util Re Plans to Recover from 851226 Overcooling Event.Preparation of Comprehensive Recovery Plan,Demonstrating Safe & Reliable Plant Operation, Needed for NRC Restart Approval.Viewgraphs Encl
Project stage: Meeting
ML20210R9331986-04-23023 April 1986
Forwards Summary of 860324-25 Onsite Meetings W/Util Re Plans for Recovery from 851226 Overcooling Event. Comprehensive Restart Rept,Demonstrating Correction of Plant Design Programmatic & Organizational Deficiencies,Expected
Project stage: Meeting
ML20203N8821986-04-24024 April 1986
Discusses NUREG-1195, Loss of Integrated Control Sys Power & Overcooling Transient at Rancho Seco on 851226. Minor Technical Corrections to & Comments on Misperceptions in Incident Investigation Team Rept Encl
Project stage: Other
ML20210N9891986-04-25025 April 1986
Responds to 860313 Memo Re Identification & Assignment of Responsibilities for Generic & plant-specific Actions Resulting from Investigation of 851226 Incident.Summary of Plans,Schedule,Status & Draft Action Plan Encl
Project stage: Draft Other
ML20198B8301986-05-12012 May 1986
Comments on Adequacy,Scope & Direction of 860418 Meeting W/ Util Re Plant Performance & Mgt Improvement Program Addressing Broad Range of Issues Affecting Restart & Safe & Reliable Operation in Response to 851226 Transient
Project stage: Meeting
ML20198B4341986-05-14014 May 1986
Summary of 860418 Meeting W/Util in Bethesda,Md Re Util Proposed Plant Performance & Mgt Improvement Program in Light of 851226 Transient.List of Attendees & Viewgraphs Encl
Project stage: Meeting
ML20206F5441986-05-29029 May 1986
Forwards List of Open Items,Including 851226 Overcooling Event Concerns,Requiring Util Action Per 860523 Telcon.Items Listed in Areas a & B Should Be Addressed in Restart Rept
Project stage: Other
ML20214L5481987-05-30030 May 1987
Agenda for 860210 Meeting W/Nrc to Discuss Facility 851226 Transient
Project stage: Meeting
1986-03-12
[Table View] |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20211K3471999-08-31031 August 1999
Summary of 990728 Meeting with Util Re Staff 990721 RAI Re Smud Application for ISFSI at Rancho Seco Site.Attendace List Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20055E3451989-05-0404 May 1989
Summary of 890501 Meeting Re Status of Util Effluents & Water Mgt Program & 1988 Annual Radiation Environ Operating Rept.Supporting Info Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20235U4891989-02-0606 February 1989
Public Version of Summary of 890201 Meeting W/Util in Region V Re Licensee Action on Potential Release of Contaminated Resin in Liquid Effluent Waste Stream During 890115-19. Agenda & Outline of Events Encl
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20206A7741988-10-18018 October 1988
Summary of 881012 Meeting W/Util in Region V Ofc Re Licensee Effluents & Water Mgt Project Action Plan .Concern Raised Re Frequent Licensee Reorganizations Resulting in Previous Action Plans Not Being Effectively Implemented
ML20207E2961988-07-28028 July 1988
Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl
ML20148S3821988-03-31031 March 1988
Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl
ML20148H0601987-12-14014 December 1987
Summary of 871207 Meeting W/Util at Plant Site Re Recent Events at Facility,Control Room HVAC & Facility Readiness for Restart.Meeting Agenda & Viewgraphs Encl
ML20148H0221987-12-0303 December 1987
Summary of 871124 Meeting W/Util at Region IV Re Procurement Program,Readiness of Fire Protection Sys for Restart & Current Concerns.Notice of Significant Licensee Meeting & Viewgraphs Encl
ML20215L3041987-06-22022 June 1987
Summary of Meeting W/Util & NUS on 870611 in Bethesda,Md Re Adequacy of Tech Specs.List of Attendees,Viewgraphs & Candidate Tech Specs for Consideration During Finalization of Program Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214L5481987-05-30030 May 1987
Agenda for 860210 Meeting W/Nrc to Discuss Facility 851226 Transient
ML20197D4831987-04-0707 April 1987
Summary of 870303 Meeting W/Util in Bethesda,Md Re Problems Identified W/Facility Liquid Effluent Program & Proposed Corrective Actions.Attendance List Encl
ML20212N2721987-03-0505 March 1987
Summary of Operating Reactor Events Meeting 87-005 on 870302.List of Attendees & Viewgraphs Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20211C1331986-10-0909 October 1986
Summary of 860814 Meeting W/Util,B&W,American Nuclear Insurers & Lrs,Inc in Bethesda,Md Re Detailed Aspects of Action Plan for Performance Improvement at Plant.Viewgraphs Encl
ML20205K2051986-07-21021 July 1986
Summary of ACRS 315th Meeting on 860710-12 in Washington,Dc Re Loss of Feedwater Event at Davis Besse Nuclear Power Station,Unit 1 & Review of Proposed Commission Policy Statement on Tech Specs
ML20206S8071986-07-0101 July 1986
Summary of ACRS Subcommittee on B&W Reactor Plants 860625 Meeting in Washington,Dc Re Review of Loss of Integrated Control Sys Power & Overcooling Transient.Fr Notice & Supporting Matl Encl
ML20202G4981986-05-22022 May 1986
Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl
ML20198B4341986-05-14014 May 1986
Summary of 860418 Meeting W/Util in Bethesda,Md Re Util Proposed Plant Performance & Mgt Improvement Program in Light of 851226 Transient.List of Attendees & Viewgraphs Encl
ML20210R9391986-04-23023 April 1986
Summary of 860324-25 Meetings W/Util Re Plans to Recover from 851226 Overcooling Event.Preparation of Comprehensive Recovery Plan,Demonstrating Safe & Reliable Plant Operation, Needed for NRC Restart Approval.Viewgraphs Encl
ML20205J9221986-04-18018 April 1986
Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations
ML20203H2181986-04-14014 April 1986
Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl
ML20214L9801986-04-0101 April 1986
Summary of 860325 Meeting W/Epa Re Offsite Contamination Problems & Requirements of 40CFR190
ML20137Y7821986-02-25025 February 1986
Summary of 860108 Meeting W/B&W Owners Group Regulatory Response Group in Bethesda,Md Re Generic Implications of 851226 Loss of Integrated Control Sys Power Event.List of Attendees & Viewgraphs Encl
ML20205J3851986-01-23023 January 1986
Summary of ACRS 309th Meeting on 860109-11 in Washington,Dc Re Final Design Approval for Gessar II Design & Proposed Rev 3 to Reg Guide 1.63, Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20138M4151985-10-17017 October 1985
Summary of 851004 Meeting W/B&W Owners Group Transient Assessment & Availability Committees in Bethesda,Md Re Operating Experience of Operating Reactors & Plans to Improve Experience.Viewgraphs Encl
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20128K7491985-07-12012 July 1985
Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20198G6931975-06-0303 June 1975
Summary of ACRS Subcommittee Meeting on 750516 to Discuss Application.List of Attendees Encl
1999-08-31
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20211K3471999-08-31031 August 1999
Summary of 990728 Meeting with Util Re Staff 990721 RAI Re Smud Application for ISFSI at Rancho Seco Site.Attendace List Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20055E3451989-05-0404 May 1989
Summary of 890501 Meeting Re Status of Util Effluents & Water Mgt Program & 1988 Annual Radiation Environ Operating Rept.Supporting Info Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20235U4891989-02-0606 February 1989
Public Version of Summary of 890201 Meeting W/Util in Region V Re Licensee Action on Potential Release of Contaminated Resin in Liquid Effluent Waste Stream During 890115-19. Agenda & Outline of Events Encl
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20206A7741988-10-18018 October 1988
Summary of 881012 Meeting W/Util in Region V Ofc Re Licensee Effluents & Water Mgt Project Action Plan .Concern Raised Re Frequent Licensee Reorganizations Resulting in Previous Action Plans Not Being Effectively Implemented
ML20207E2961988-07-28028 July 1988
Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl
ML20148S3821988-03-31031 March 1988
Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl
ML20148H0601987-12-14014 December 1987
Summary of 871207 Meeting W/Util at Plant Site Re Recent Events at Facility,Control Room HVAC & Facility Readiness for Restart.Meeting Agenda & Viewgraphs Encl
ML20148H0221987-12-0303 December 1987
Summary of 871124 Meeting W/Util at Region IV Re Procurement Program,Readiness of Fire Protection Sys for Restart & Current Concerns.Notice of Significant Licensee Meeting & Viewgraphs Encl
ML20215L3041987-06-22022 June 1987
Summary of Meeting W/Util & NUS on 870611 in Bethesda,Md Re Adequacy of Tech Specs.List of Attendees,Viewgraphs & Candidate Tech Specs for Consideration During Finalization of Program Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20197D4831987-04-0707 April 1987
Summary of 870303 Meeting W/Util in Bethesda,Md Re Problems Identified W/Facility Liquid Effluent Program & Proposed Corrective Actions.Attendance List Encl
ML20212N2721987-03-0505 March 1987
Summary of Operating Reactor Events Meeting 87-005 on 870302.List of Attendees & Viewgraphs Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20211C1331986-10-0909 October 1986
Summary of 860814 Meeting W/Util,B&W,American Nuclear Insurers & Lrs,Inc in Bethesda,Md Re Detailed Aspects of Action Plan for Performance Improvement at Plant.Viewgraphs Encl
ML20205K2051986-07-21021 July 1986
Summary of ACRS 315th Meeting on 860710-12 in Washington,Dc Re Loss of Feedwater Event at Davis Besse Nuclear Power Station,Unit 1 & Review of Proposed Commission Policy Statement on Tech Specs
ML20206S8071986-07-0101 July 1986
Summary of ACRS Subcommittee on B&W Reactor Plants 860625 Meeting in Washington,Dc Re Review of Loss of Integrated Control Sys Power & Overcooling Transient.Fr Notice & Supporting Matl Encl
ML20202G4981986-05-22022 May 1986
Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl
ML20198B4341986-05-14014 May 1986
Summary of 860418 Meeting W/Util in Bethesda,Md Re Util Proposed Plant Performance & Mgt Improvement Program in Light of 851226 Transient.List of Attendees & Viewgraphs Encl
ML20210R9391986-04-23023 April 1986
Summary of 860324-25 Meetings W/Util Re Plans to Recover from 851226 Overcooling Event.Preparation of Comprehensive Recovery Plan,Demonstrating Safe & Reliable Plant Operation, Needed for NRC Restart Approval.Viewgraphs Encl
ML20205J9221986-04-18018 April 1986
Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations
ML20203H2181986-04-14014 April 1986
Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl
ML20214L9801986-04-0101 April 1986
Summary of 860325 Meeting W/Epa Re Offsite Contamination Problems & Requirements of 40CFR190
ML20137Y7821986-02-25025 February 1986
Summary of 860108 Meeting W/B&W Owners Group Regulatory Response Group in Bethesda,Md Re Generic Implications of 851226 Loss of Integrated Control Sys Power Event.List of Attendees & Viewgraphs Encl
ML20205J3851986-01-23023 January 1986
Summary of ACRS 309th Meeting on 860109-11 in Washington,Dc Re Final Design Approval for Gessar II Design & Proposed Rev 3 to Reg Guide 1.63, Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20138M4151985-10-17017 October 1985
Summary of 851004 Meeting W/B&W Owners Group Transient Assessment & Availability Committees in Bethesda,Md Re Operating Experience of Operating Reactors & Plans to Improve Experience.Viewgraphs Encl
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20128K7491985-07-12012 July 1985
Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20198G6931975-06-0303 June 1975
Summary of ACRS Subcommittee Meeting on 750516 to Discuss Application.List of Attendees Encl
1999-08-31
[Table view] |
Text
, L,
.b 6 - o I &
d' May 14, 1986 y $9 - 3d 1 LICENSEE - Sacramento Municipal Utility District FACILITY - Rancho Seco Nuclear Generating Station SUBJECT - Summary of Meeting on April 18, 1986 with Sacramento Municipal Utility District (SMUD)
On April 18, 1986, the Sacramento Municipal Utility District (SMUD) met with the NRC staff in Bethesda to review SMUD's proposed plant performance and management improvement program for the Rancho Seco plant. This presentation was a follow-up to the meeting held between SMUD and senior NRC management on March 24-25, 1986 where SMUD was requested to take a broader perspective regarding the issues affecting the safe and reliable operation of the Rancho Seco plant beyond the narrow focus of responding to the December 26, 1985 transient. Enclosure 1 is a list of the attendees. Enclosure 2 is a copy of the material presented by SMUD at the meeting.
SMUD presented an outline of its program to improve its management organization, systems and procedures, communications, and plant performance.
The organization is being restructured to include six departments vs the present three, with new management personnel being brought in from outside SMUD. Management systems and procedures, functional interfaces and information flow (dissemination and feedback) will be evaluated. From the evaluation, recommendation for change or improvement will be made for implementation to improve overall management performance. The plan has been reviewed and approved by management.
The performance indicators SMUD will use to judge management performance are (1) plant availability, (2) forced outage rate, (3) reactor trips, (4) NRC violation, (5) NRC SALP ratings, (6) INp0 findings, (7) low level solid radio-active waste, (8) personnel radiation exposure and (9) lost time accidents. Their near term goal is to have a better than 60% plant availability, no greater than 10% forced outage rate and less than 3 reactor trips per year.
The licensee has organized a performance analysis group to develop a program beyond that currently established to respond to the December 26, 1986 transient to improve the overall plant performance of Rancho Seco. The program will incorporate a short term element requiring resolution prior to restart and a longer term element. The licensee will do a deterministic failure consequences analysis primarily on motive power systems to determine whether system failures could (1) cause a reactor trip, (2) challenge safety systems and/or impact the ability to stay in the " Post-Trip Window" (predicted reactor coolant pressure and temperature and steam outlet temperature and pressure). Equipment and or system whose failures will result in one or more on these conditions will be evaluated for modificatinn, enhanced procedures, enhanced training and possible testing. In addition, SMUD stated they will conduct interviews with their staff to obtain issues and concerns regarding plant design and operations. They will also factor into their restart program precursor documents referenced in the NUREG-1195 report (IIT Report) and such things as I&E Bulletins and Notices, LER's, Trip Reports, etc.
N s
$$ h2
The licensee indicated that some of the items will be implemented in parallel with the analysis and evaluation portion of the program. They expect the analysis and evaluation part of the program will be completed in June to support-issuance of the Rancho Seco startup report for NRC review early in July 1986.
The NRC staff had the following major comments:
- 1. The staff suggested that, in addition to low level solid radioactive waste, radioactive liquid waste (releases) should be considered as a performance indicator.
- 2. The startup program should be comprehensive enough to provide reasonable assurance that when restarted the plant can be safely and reliably operated. It is not necessary that the program be like the Davis-Besse program. However, they should be prepared to justify their program when it is compared to what appears to be a more comprehensive test program being conducted at Davis-Besse.
- 3. The staff questioned whether the deterministic failure consequences analysis program limited to only the motive systems will result in a sufficiently comprehensive start-up program to demonstrate reasonable assurance of reliable and safe operation.
- 4. The staff also noted that the test program described appeared rather limited. l
. In conclusion, SMUD indicated that it will consider all of the staff's comments made during the meeting in developing its restart program and report.
% %te ,y Sydney Miner, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
Enclosures:
As Stated cc w/ enclosures: See next page PBD#6 SMiner, k 5/g./86
MEETING
SUMMARY
DISTRIBUTION Licensee: Sacramento Municipal Utility District
- Copies also sent to those people on service (cc) list for subject plant (s).
Docket File NRC PDR L PDR P8D-6 Rdg JStolz SMiner 0CLD EJordan BGrimes ACRS-10 NRC Participants DCrutchfield JSWermiel RWeller GKalman CMcCracken KWichman NLauben DFieno JTBeard GEdison FSchroeder RJones WRegan RWright JCalvo
o I
'[ Enclosure 1 RANCHO SECO MEETING
. APRIL 18, 1986 L
. NAME' ORGANIZATION
~
Sydney 111ner NRR/PWR-B Lew Miller RV Dennis Crutchfield NRR/PWR-B J.S. Wenniel NRR/PWR-B Rick Weller NRR/PWR-B
- George Kalman NRR/PWR-B
! Conrad McCracken NRR/PWR-B Keith Wichman NRR/PWR-B
- l. Norm Lauben NRR/PWR-B Daniel Fieno NRR/PWR-B J.T. Beard NRR/0 RAS J.L. Crews' RV Henry Bailey IE/EAB Gordon E. Edison NRR/PWR-B John F. Stolz NRR/PWR-B Frank Schroeder NRR/PWR-B l Robert Jones NRR/PWR-B l RC De Young Consultant to SMUD
( Wm. H. Regan- NRR/PWR-B
! Robert Wright NRR/PWR-B Jose A. Calvo NRR/PWR-B i
i l
l l
I l
l l
PLANT PERFORMANCE e AND MANAGEMENT IMPROVEMENT PROGRAM improvement = General Manager Program Overview Panel Asst. General Manager, Nuclear i
Nuclear Dept.
____ Performance . _ _ _
Review Panel Managers improvement independent Manager e rJuclear Plant
. Quatit y
. Engineering Asst.
. ucensino improvement -
Manager l l Mgmt. Process Performance Resource / Schedule Review Group Analysis Group Monitoring e Organization
- Performance . nesources improvement Plan e Psocurement
. Management systems
& Procedures
- Procedures e schedule e Functional inter f aces .
& Interface
. information Dissemination
& Feedback . FinC Interf ace
. Performance Indicators 5
N
~
ORGANIZATION oCHANGEO .ORGANIZA TIONAL STRUCTURE .A T .SEVERAL LGVELS h
- SIX DEPARTMENTS VS THREE
- REORGANIZA TION A T DEPARTMENT LEVEL .
ONEW MANAGEMENT PERSONNEL IN PLACE
- PERSONNEL FROM .OUTSIDE SMUD
- PERSONNEL WITH PROVEN RECORDS j
= s
~
! . c mr5 $ ~
l
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MANAGEMENT SYSTEMS AND PROCEDURES .
- ARE ADEQUA TE MANAGEMENT SYSTEMS .IN PLACE TO:
- PLAN
- ORGANIZE _
- S TA FF
- DIRECT
- CONTROL e DO PROCEDURES ADEQUhTELY ADDRESS THE .
MANAGEMENT SYSTEMS THEY ARE INTENDED TO IMPLEMENT
- RECOMMEND CHANGES OR IMPROVEMENTS ,
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18231 FUNCTIONAL INTERFACES
- DETERMINE PRESENT FUNCTIONAL INTERFACES
- RECOMMEND . CHANGES .OR .lMPRO VEMENTS I
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INFORMATION DISSEMINATION AND FEEDBACK
- VERTICAL COMMUNIOA TION METHOLbS'-
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- HORIZONTAL COMMUNICATION METHODS e FEEDBACK METHODS -
e RECOMMENDA TIONS FOR . CHANGE OR IMPROVEMENTS
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-PERFORMANCE INDICATORS
- 9. REACTOR TRIP
- LOW LEVEL SOLID RAD WASTE
- PERSONNEL RADIATION EXPOSURE -
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4 RANCHO SECO PERFORMANCE IMPROVEMEt1T PROGRAM PERFORAfANCE ANAL YSIS GROUP e Deterministic Failure *
- Reduce Challenges Consequences , gg,pagggjon to Safety Systems ' ,
- Plant Staff Interviews , p,gorggy e Enhance Plant Reliability e Precursor Review INPUT e implementation ESULTS e Reinforced Procedures
- Event-related Actioins e Restart Report
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- Test Program Definition LONG TERAf BENEFITS
o Morale Improvemerst i e Project Management Program OSMUD_ , _ , , _ , , , , _ , ,
flANCHO SFCO NUCL F A4 ClNf R Af *tG STAfmM
- Enhanced Quality Program 9
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PLANT PERFORMANCE IMPROVEMENT e SITUA TION:
Rel! ability suffers due to specific component failures
\ History suggests that causes are rectified only after event History shows that safety systems work '
e A C TION PL AN:
i Improve reliability by reducing challenge's Review Effect of Process System malfunctions Identify precursors to transients Implement effective compensatory measures l
i Cause a reactor trip?
Challenge a safety system? '
I impact ability to stay in post-trip window?
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Appropriateness of procedural guidance Implement corrective action
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PERFORhfANCE lh1PROVEhfENT PROGRAh1 IN T .
Selected Deterministic Profocts Failure Consequences Precursor BWOG Stop-Trip '
R e vie w Program Plant Staff f 1 - G Event &
Intervic ws NUREG 1195 Action List u
E VA L UA TION Recommendations A ssign Review & Resolution ~
Dispositioning Board Organization i i Plan & In vestigation Budget '
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Proposed Disposition DISPOSITION '
Feed bacl< Disposition by Programmatic to RRRB Performance ~
Analysis Group . Trend Analynis I I e o y CLOSE A C TION A C TION No furthe, r Non-Startup to o action required required for startup Living Scheduto or CCL thfPLEMENTA TION v I
Implementation l
using approved ECN/DCN, Operations,
' Procedurcs, Engincaring, Training Programs Test Program I
l784l PERFORMANCE ANAL YSIS GROUP 1
FOCUS EFFORTS OF ALL NUCLEAR DEPARTMENTS -
DIRECTED B Y NUCLEAR PROJECTS MANA GER COMBINES RESOURCES OF: .
l Operations including Maintenance & Technical Support Engineering l
Quality
- Training ,,
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Licensing l
Scheduling e A CTIVITIES
Resource Commitment
- l Prioritization Budgeting .
TREND ANAL YSIS ON RECOMMENDA TIONS
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17 87l RECOMMENDA TIONS REVIEW AND RESOLUTION BOARD _
- ' Chairman from Recovery Management Group
- Review, Resolve, . Propose Priority
- Assigns Dispositioning Responsibility e Determines Adequacy and Appropriateness of Proposed Dispositions
- Processes Recommendations per Procedure
- Multidiscipline RRR Board Maintenance HP/ Chemistry Operations
- Tech Support
- Nuclear Engineering
- Licensing Quality Training 9
[71/l 1 DETERMINISTIC FAILURE CONSEQUENCES e IDENTIFY EFFECT OF PROCESS SYSTEM FAILURES EVALUA TION CRITERIA:
-Cause Reactor Trip
-Challenge To Safet'y System
- -Impact Ability To Stay In " Post-Trip" Window e APPL Y PROCESS TO
-Motive Power Systems -
- Electrical Power Supplies
-Both " Primary" & "Secortdary" Systems e ANTICIPA TES "REAL" EVENTS Verfiles That Procedures,. Training & Hardware Are Appropriate
- DOES NOT ASSUME THA T ONL Y " HISTORIC # OR " DESIGN" ,
EVENTS CAN OR WILL OCCl)R.
- ANAL YSIS B Y TEAMS,. COMPOSED OF:
-Operations & Design Engineers
-Op era t ors
-Plant Techn'icians
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\ PLANT STAFF INTERVIEWS .
- Obtain Issues and Concerns of Knowledgeable Staff Reguarding Plant Design and Operations .
Identification of "Near Misses" & Potential Problems ,
- Systematic Interview Process e Goal:
Interview Majority of Staff Members Consider Ongoing Program
Operators Plant Engineers Technicians '
Mechanics Inspectors / Auditors Instructors Design Engineers
- Broadens Scope Beyond 12-26 Event
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PRECURSOR REVIEW
NUREG 073 7
I&E Bulletins I&E Notices SOER 's .
Rancho Seco: .
Trip Reports t l
ODR 's LER 's ,
e REVIEW WILL CONSIDER Likelihood as Pre ~ cursor Event .
" Narrowness" of Previous Reviews Scope of Response , ,
. Effect of Plant Configuration Changes
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x-l 789l BWOG STOP-TRIP PROGRAM Objective and Goals j Program Objectives
'l e . Reduce number of trips / transients on B&W i Owners Group Plants '
l o Ensure acceptable plant response dbring trips and transients WhiCh occur.
Program Goals
- 1. By the end of 1990 the average plant trip frequency will be less than two per year.
- 2. Severe transients as classified by measureable .
parameters will be reduced.
- 3. SMUD will be active in program.
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. . - - ._ - . . . ~ - - - - . - . -
2 '
E SELECTED PHOJECTS
- ANTICIPATE DETERMINISTIC FAILURE CONSEQUENCE REVIEW
- PROCEED DIRECTLY TO DISPOSITION *
Instrument Air Syste'm Startup Transformer #2 Makeup Pump Interlocks E&F Bus DC Bus ICS/NNI
, . MSLF Logic l ' Component Cooling Water System
- DETERMIAISTIC FAILURE CONSEQUENCE WILL ALSO BE DONE
~~ - - , -
lmi TEST PROGRAM PURPOSE Insure Modifications & Changes Accomplish Purpose Demonstrate Interface Between e Trained Operators -
e Operating Procedures e Plant & Control Room Hardware SPECIFIC ISSUES Demonstrate Satisfactory Response on:
e Loss of ICS Loss of NNI Loss .of Instrument Air .
l OTHER TESTING .
- As Identified by Performance ,
improve
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SUMMARY
PERFORMANCE IMPROVEMENT PROGRAM: '
- e evelops Confidence that Future Events will not Challenge Plant Design Basis i
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- Provides for Systematic Review of Transient Response
- Provides " Broad Perspective" to issues which i
may have been Viewed Narrowly -
- Gnhances Plant Reliability i
- Reduces Challenges.to Safety Systems
~e Develops Confidbnce for Restart Decision
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