Similar Documents at Maine Yankee |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212D1631999-09-20020 September 1999 Summary of 990908 Meeting with Myap in Rockville,Md Re Plant License Termination Plan.List of Attendees & Licensee Handouts Encl ML20212A3101999-09-14014 September 1999 Summary of 990823 Meeting with Util in Rockville,Md to Discuss License Termination Plan.List of Attendees Encl ML20210G2711999-07-28028 July 1999 Summary of 990707 Meeting with Util in Rockville,Md to Discuss Licensee Termination Plan.List of Attendance & Handouts Encl ML20210B7521999-07-21021 July 1999 Summary,For Docket 7200030,of 990707 Meeting with Myap,S&W & NAC Intl Re Util Plans to Store Spent Fuel Using NAC-UMS Dry Storage Sys.Attendance List,Meeting Handouts & Util Rulemaking Handout,Encl ML20207G2401999-06-0707 June 1999 Summary of 990525 Meeting with Util in Rockville,Md to Discuss Maine Yankee Atomic Power Station License Termination ML20196C3251998-11-23023 November 1998 Summary of 981109 Meeting with Util & SWEC Re Decommissioning Activities & Schedule at Maine Yankee Atomic Power Station.List of Attendees Enclosed ML20236S9811998-07-22022 July 1998 Summary of 980710 Meeting W/Util in Rockville,Md Re Plant Backfit Appeal.Appeal Submitted Per NRC Determination Re Plant Emergency Preparedness Exemption ML20249B8251998-06-17017 June 1998 Summary of 980609 Meeting W/Util in Rockville,Md to Discuss Sf Heatup Analysis That Util Performed in Support of Exemption Requests Submitted Re Emergency Preparedness & Financial Protection ML20202F4691997-12-0101 December 1997 Summary of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Defueled TSs for Plant.List of Attendees & Handouts Used by Licensee Encl ML20202G8591997-12-0101 December 1997 Summary of 971125 Meeting W/Employees of Myap in Rockville, Maryland Re Proposed Defueled Emergency Plan for Myap Station.List of Attendees Encl ML20211P3801997-10-0808 October 1997 Summary of 970911 Meeting W/Myapco Re Options Available for Storage of Spent Fuel Currently at Site.Meeting Attendee List & Meeting Handouts Encl ML20197F7631997-08-14014 August 1997 Summary of 960429 Public Meeting in Wiscasset,Maine Re Licensee New small-break loss-of-coolant Analysis & Licensee Reanalysis of Potential Containment Pressures Under Postulated Accident Conditions ML20140H5731997-04-0404 April 1997 Summary of 439th Meeting of ACRS on 970306-08 Re Release of AP600 Test Data from Rosa Test Facility,Rept Entitled, Recommendations to Improve Senior Mgt Meeting Process & Independent Safety Assessment of Myaps ML20137L3531997-03-27027 March 1997 Summary of 970320 Meeting W/Util in Rockville,Md Re Outage Activities Identified in Attachment Four & Proposed TS Change 194, Reactor Coolant Flow Rate Requirements. W/List of Attendees & Viewgraphs ML20134P0531997-02-20020 February 1997 Summary of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Mgt Svcs Agreement Between Licensee & Entergy Nuclear,Inc.Meeting Closed Due to Proprietary Nature of Info to Be Discussed ML20129E6321996-10-0707 October 1996 Summary of 960730 Meeting W/Myap in Rockville,Md Re Lessons Learned Related to RELAP5YA.Transcript Encl ML20127L7631993-01-21021 January 1993 Summary of 921028 Meeting to Review Licensee Proposed Fuel Pool Reracking ML20127J6121993-01-15015 January 1993 Summary of 921217 Meeting W/Licensee to Discuss Fuel Pool Reracking ML20198D6241992-05-12012 May 1992 Summary of 920507 Meeting W/Util in King of Prussia,Pa Re Current Status of Physical Security Program Being Implemented at Facility ML20055E2491990-07-0505 July 1990 Summary of 900625 Meeting W/Util & C-E Re Control Element Assembly Failures & Corrective Actions.Major Topics Presented Listed,Including Visual Exam Results & Fuel Insp Activity & Results.List of Attendees & Briefing Matls Encl ML20153C1861988-08-23023 August 1988 Summary of Operating Reactors Events Meeting 88-34 on 880823 ML20207F6541988-08-17017 August 1988 Summary of 880816 Operating Reactors Events Meeting 88-33 in Rockville,Md Re Briefing of Senior Managers from Nrr,Osp, AEOD & Regional Ofcs on Events Which Occurred Since Last Meeting on 880809.List of Attendees Encl ML20154J8011988-05-16016 May 1988 Summary Rept of 880427 Meeting W/Util in King of Prussia,Pa Re Licensee Planning & Preparation for Upcoming Outage & Station Performance in Area of Radiological Controls ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted ML20214P6121987-05-27027 May 1987 Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl ML20205Q9121987-03-20020 March 1987 Summary of 870306 Meeting W/Util in Bethesda,Md Re Low Level Waste Mgt.List of Attendees,Viewgraphs & APTR-42, Maine Yankee Atomic Power Station In-Situ Decommissioning/Low Level Waste Mgt, Encl ML20211B9491987-02-0909 February 1987 Summary of 870205 Meeting W/Util in Bethesda,Md Re RELAP5YA Computer Code & Use in Small Break LOCA Analysis Pertmi Action Plan Item II.K.3.30.List of Attendees & Presentation Matl Used by Util Encl ML20212G4991987-01-12012 January 1987 Summary of 861216 Meeting W/Util & Intermountain Technologies,Inc in Bethesda,Md Re Large Break LOCA Analysis Axial Power Shape.List of Attendees & Presentation Outline on Steam Cooling Model Rev Encl ML20207J7881987-01-0707 January 1987 Trip Rept of 861218-19 Visit to Framingham,Ma to Examine Plant Spent Fuel Pool Masonry Wall Failure Consequence Analysis.Conclusions Listed 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 ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20207A7551986-11-0404 November 1986 Summary of 861022 Meeting W/Util in Bethesda,Md Re Selection of Axial Power Shape for Large Break LOCA Analysis.List of Attendees & Supporting Documentation Encl ML20215N5521986-11-0404 November 1986 Summary of 860930 Second Peer Review Group Meeting in San Francisco,Ca Re Facility Seismic Design Margin Program ML20210G8611986-09-22022 September 1986 Summary of 860909 Meeting W/Util in Bethesda,Md Re Util Large Break LOCA Analysis Axial Power Shape.List of Attendees & Viewgraphs Encl ML20205E2901986-08-13013 August 1986 Summary of 860721-25 Meetings W/Util & Consultants Re Seismic Design Margin Program.Peer Review Group Meeting Scheduled for 860930.Attendee List,Agenda & Contractor Presentation Outline Encl ML20198C6991986-05-19019 May 1986 Summary of 860507-08 Meetings W/Util & Consultants Re Seismic Design Margin Program Activities,Schedules & Manpower Requirements.Attendance List,Viewgraphs & Supporting Documentation Encl ML20205J0421985-11-21021 November 1985 Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants 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 ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20128M0751985-05-21021 May 1985 Summary of 850508 Meeting W/Util in Bethesda,Md Re Testing of Offsite Power Supplies ML20216H9751985-04-0303 April 1985 Summary of 850311 Meeting W/Util Re Alternative Approach to 10CFR50,App R,Section Iii.O Requirements.W/List of Attendees ML20140C8561984-06-0404 June 1984 Summary of 840424 Meeting W/Utils & Eqe,Inc Re Update of Seismic Design Review Project 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 ML20148G8601976-11-15015 November 1976 Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl 1999-09-20
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20212D1631999-09-20020 September 1999 Summary of 990908 Meeting with Myap in Rockville,Md Re Plant License Termination Plan.List of Attendees & Licensee Handouts Encl ML20212A3101999-09-14014 September 1999 Summary of 990823 Meeting with Util in Rockville,Md to Discuss License Termination Plan.List of Attendees Encl ML20210G2711999-07-28028 July 1999 Summary of 990707 Meeting with Util in Rockville,Md to Discuss Licensee Termination Plan.List of Attendance & Handouts Encl ML20210B7521999-07-21021 July 1999 Summary,For Docket 7200030,of 990707 Meeting with Myap,S&W & NAC Intl Re Util Plans to Store Spent Fuel Using NAC-UMS Dry Storage Sys.Attendance List,Meeting Handouts & Util Rulemaking Handout,Encl ML20207G2401999-06-0707 June 1999 Summary of 990525 Meeting with Util in Rockville,Md to Discuss Maine Yankee Atomic Power Station License Termination ML20196C3251998-11-23023 November 1998 Summary of 981109 Meeting with Util & SWEC Re Decommissioning Activities & Schedule at Maine Yankee Atomic Power Station.List of Attendees Enclosed ML20236S9811998-07-22022 July 1998 Summary of 980710 Meeting W/Util in Rockville,Md Re Plant Backfit Appeal.Appeal Submitted Per NRC Determination Re Plant Emergency Preparedness Exemption ML20249B8251998-06-17017 June 1998 Summary of 980609 Meeting W/Util in Rockville,Md to Discuss Sf Heatup Analysis That Util Performed in Support of Exemption Requests Submitted Re Emergency Preparedness & Financial Protection ML20202F4691997-12-0101 December 1997 Summary of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Defueled TSs for Plant.List of Attendees & Handouts Used by Licensee Encl ML20202G8591997-12-0101 December 1997 Summary of 971125 Meeting W/Employees of Myap in Rockville, Maryland Re Proposed Defueled Emergency Plan for Myap Station.List of Attendees Encl ML20211P3801997-10-0808 October 1997 Summary of 970911 Meeting W/Myapco Re Options Available for Storage of Spent Fuel Currently at Site.Meeting Attendee List & Meeting Handouts Encl ML20197F7631997-08-14014 August 1997 Summary of 960429 Public Meeting in Wiscasset,Maine Re Licensee New small-break loss-of-coolant Analysis & Licensee Reanalysis of Potential Containment Pressures Under Postulated Accident Conditions ML20140H5731997-04-0404 April 1997 Summary of 439th Meeting of ACRS on 970306-08 Re Release of AP600 Test Data from Rosa Test Facility,Rept Entitled, Recommendations to Improve Senior Mgt Meeting Process & Independent Safety Assessment of Myaps ML20137L3531997-03-27027 March 1997 Summary of 970320 Meeting W/Util in Rockville,Md Re Outage Activities Identified in Attachment Four & Proposed TS Change 194, Reactor Coolant Flow Rate Requirements. W/List of Attendees & Viewgraphs ML20134P0531997-02-20020 February 1997 Summary of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Mgt Svcs Agreement Between Licensee & Entergy Nuclear,Inc.Meeting Closed Due to Proprietary Nature of Info to Be Discussed ML20129E6321996-10-0707 October 1996 Summary of 960730 Meeting W/Myap in Rockville,Md Re Lessons Learned Related to RELAP5YA.Transcript Encl ML20127L7631993-01-21021 January 1993 Summary of 921028 Meeting to Review Licensee Proposed Fuel Pool Reracking ML20127J6121993-01-15015 January 1993 Summary of 921217 Meeting W/Licensee to Discuss Fuel Pool Reracking ML20198D6241992-05-12012 May 1992 Summary of 920507 Meeting W/Util in King of Prussia,Pa Re Current Status of Physical Security Program Being Implemented at Facility ML20055E2491990-07-0505 July 1990 Summary of 900625 Meeting W/Util & C-E Re Control Element Assembly Failures & Corrective Actions.Major Topics Presented Listed,Including Visual Exam Results & Fuel Insp Activity & Results.List of Attendees & Briefing Matls Encl ML20153C1861988-08-23023 August 1988 Summary of Operating Reactors Events Meeting 88-34 on 880823 ML20207F6541988-08-17017 August 1988 Summary of 880816 Operating Reactors Events Meeting 88-33 in Rockville,Md Re Briefing of Senior Managers from Nrr,Osp, AEOD & Regional Ofcs on Events Which Occurred Since Last Meeting on 880809.List of Attendees Encl ML20154J8011988-05-16016 May 1988 Summary Rept of 880427 Meeting W/Util in King of Prussia,Pa Re Licensee Planning & Preparation for Upcoming Outage & Station Performance in Area of Radiological Controls ML20214P6121987-05-27027 May 1987 Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl ML20205Q9121987-03-20020 March 1987 Summary of 870306 Meeting W/Util in Bethesda,Md Re Low Level Waste Mgt.List of Attendees,Viewgraphs & APTR-42, Maine Yankee Atomic Power Station In-Situ Decommissioning/Low Level Waste Mgt, Encl ML20211B9491987-02-0909 February 1987 Summary of 870205 Meeting W/Util in Bethesda,Md Re RELAP5YA Computer Code & Use in Small Break LOCA Analysis Pertmi Action Plan Item II.K.3.30.List of Attendees & Presentation Matl Used by Util Encl ML20212G4991987-01-12012 January 1987 Summary of 861216 Meeting W/Util & Intermountain Technologies,Inc in Bethesda,Md Re Large Break LOCA Analysis Axial Power Shape.List of Attendees & Presentation Outline on Steam Cooling Model Rev 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 ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20207A7551986-11-0404 November 1986 Summary of 861022 Meeting W/Util in Bethesda,Md Re Selection of Axial Power Shape for Large Break LOCA Analysis.List of Attendees & Supporting Documentation Encl ML20215N5521986-11-0404 November 1986 Summary of 860930 Second Peer Review Group Meeting in San Francisco,Ca Re Facility Seismic Design Margin Program ML20210G8611986-09-22022 September 1986 Summary of 860909 Meeting W/Util in Bethesda,Md Re Util Large Break LOCA Analysis Axial Power Shape.List of Attendees & Viewgraphs Encl ML20205E2901986-08-13013 August 1986 Summary of 860721-25 Meetings W/Util & Consultants Re Seismic Design Margin Program.Peer Review Group Meeting Scheduled for 860930.Attendee List,Agenda & Contractor Presentation Outline Encl ML20198C6991986-05-19019 May 1986 Summary of 860507-08 Meetings W/Util & Consultants Re Seismic Design Margin Program Activities,Schedules & Manpower Requirements.Attendance List,Viewgraphs & Supporting Documentation Encl ML20205J0421985-11-21021 November 1985 Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants 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 ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20128M0751985-05-21021 May 1985 Summary of 850508 Meeting W/Util in Bethesda,Md Re Testing of Offsite Power Supplies ML20216H9751985-04-0303 April 1985 Summary of 850311 Meeting W/Util Re Alternative Approach to 10CFR50,App R,Section Iii.O Requirements.W/List of Attendees ML20140C8561984-06-0404 June 1984 Summary of 840424 Meeting W/Utils & Eqe,Inc Re Update of Seismic Design Review Project 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 ML20148G8601976-11-15015 November 1976 Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl 1999-09-20
[Table view] |
Text
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AUG 171998 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Of fice of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING August 16, 1988 - MEETING 88-33 On August 16, 1988 an Operating Reactors Events meeting (88-331 was held to brief senior managers from NRR, OSP, AE00, Commission Staff, and Regional Offices on events which occurred since our last meeting on August 9, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a summary of reactor scrams. No signif-icant events were identified for input to NRC's Performance Indicator Program.
Mtinal Signert th-Pd W. Bwa nows ky fw Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Of fice of Nuclear Reactor Regulation
Enclosures:
As stated cc w/Enclo.:
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0FFICIAL RECORD COPY
2 ENCLOSURE 1 b
LIST OF ATTENDEES OPERATING PEACTORS EVENTS BRIEFING (88-33-)
August 16, 1988 NAME ORGANIZATION NAME ORGANIZATION R. Scholl NRR/00EA A. Vietti-Cook OCM/LZ
- 0. Crutchfield NRR/0RSP M.L. Reardon NRR/00EA 0.C. Fischer NRR/00EA J. Kelly , OSP/TVA S. Israel AE00 P. Baranowsky NRR/00EA V. Benaroya AE00/DSP P. Sears NRR/P01-3 W.E. Holland SRI (Surry) C. Patel NRR/ORP W. Hodges NRR/ DEST C. Thomas NRR/PMAS H.N. Pastis NRR/P02-3 0.B. Matthews NRR/P02-3 B. Boger NRR/ADR-1 T. Martin NRR/ADT S. Varga NRR/ORP W. Minners RES/0RPS C.J. Haughney NRR/ORIS J. Sniezek 00:NRR o
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- - ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-33 EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT TUESDAY, AUGUST 16, 1988, 11:00 A.M.
MAINE YANKEE GENERATOR / REACTOR' TRIP AND FAILURE TO CLOSE "RESERVE" BREAKERS GENERIC ISSUE INADE00 ATE NET POSITIVE SUCTION HEAD IN THE HIGH/ LOW PRESSURE SAFETY SYSTEMS
~ - - . . _ . . . _ . _ , . - . . _ , . , . . _ _ _ . , . . _ , - , - _ , . . . . , _ _ , , - _ , _ . . - - , . . _ , _ _ , , , , - , . _ _ _ _ , , , - - - . -
88-33 MAINE YANKEE GENERATOR / REACTOR TRIP AND FAILURE TO CLOSE "RESERVE" BREAKERS AUGUST 13, 1988 PROBLEM FAILURE TO AUTOMATICALLY TRANSFER STATION AUXILIARY LOADS (6.9KV AND 4.16KV BUSES) FROM THE MAIN GENERATOR TO THE "RESERVE" 0FFSITE SOURCES FOLLOWING MAIN GENERATOR, TURBINE AND REACTOR TRIP DUE TO MAIN TRANSFORMER FAULT.
CAUSE '
TRANSFER TO THE "RESERVE" SOURCES WILL NOT OCCUR IF RESERVE SOURCE LOW V0LTAGE IS SENSED, IT IS SUSPECTED THAT THE MAIN TRANSFORMER FAULT CAUSED A M0MENTARY GRID DISTURBANCE (LOW VOLTAGE) THAT PREVENTED TRANSFER.
SAFETY SIGNIFICANCE o FAILURE TO AUTOMATICALLY TRANSFER POWER TO 6.9KV BUSES RESULTS IN LOSS OF REACTOR COOLANT PUMPS (RCP) AND CONDENSER CIRCULATING WATER PUMPS (CCWP),
o LOSS OF POWER TO THE 4.16KV BUSES REQUIRES DIESEL GENERATOR AUTOMATIC START TO PROVIDE POWER TO SAFETY-RELATED LOADS.
DISCUSSION o ON AUGUST 13, 1988, WHILE OPERATING AT 98% POWER, A FAULT OCCURRED ON MAIN TRANSFORMER X1A (SEE FIGURE 1, ATTACHED) CAUSING 4 MAIN GENERATOR, TURBINE AND REACTOR TRIP.
o GENERATOR TRIP RESULTED IN THE LOSS OF THE NORMAL SOURCE OF POWER TO 6.9KV BUSES 1 8 2 AND 4.16KV BUSES 3, 4, 5, 8 6 (SEE FIGURE 2, ATTACHED),
o FAILURE TO AUTOMATICALLY TRANSFER 6.9KV AND 4.16KV LOADS TO THE "RESERVE" (OFFSITE) SOURCES PER DESIGN RESULT,ED IN LOSS OF THE RCPs AND CCWPs, o DIESEL GENERATOR (DG) BACKED BUSES WERE ISOLATED AND THE DGs AUTOMATICALLY STARTED AND SUPPLIED BUS LOADS AS DESIGNED.
CONTACT: R. KENDALL
REFERENCE:
50.72 # 13187
.- MAINE-YANKEE 88-33 o PRIMARY SYSTEM WAS COOLED VIA NATURAL CIRCULATION FOR 20-25 MINUTES UNTil "RESERVE" POWER WAS MANUALLY RESTORED TO ONE 6.9KV BUS, ALLOWING RESTART OF ONE RCP, o LOSS OF CCWPs RESULTED IN CONDENSER OVERPRESSURE AND RUPTURE OF A LOW PRESSURE TURBINE RUPTURE DISC, ADDITIONAL CONCERNS o GROUP 5B RODS ("NON-TRIPPABLE" GROUP; 4 RODS) COULD NOT BE MANUALLY INSERTED BY THE OPERATORS FOLLOWING REACTOR TRIP DUE TO PCWER SUPPLY PROBLEMS.
o ONE MAIN STEAM LINE EXCESS FLOW CHECK VALVE FAILED TO CLOSE MANUALLY DUE TO FAILED SOLEN 01D (STEAM LINE #3), MAIN YANKEE IS A 3-LOOP CE PLANT, o ONE SERVICE WATER PUMP FAILED TO AUTOMATICALLY START CONCURRENT WITH '
THE DG AUTOMATIC START / LOAD SEQUENCE, FOLLOWUP REGION I HAS SENT ADDITIONAL INSPECTORS TO THE SITE AND IS CONTINUING TO FOLLOWUP,
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. 88-33 GENERIC ISSUE INADEQUATE NET POSITIVE SUCTION HEAD IN THE HIGH/ LOW PRESSURE SAFETY SYSTEMS MAY 12, 1988 PROBLEM .
THE NPSH FOR THE HIGH PRESSURE INJECTION PUMPS COULD BE INADEQUATE DURING THE RECIRCULATION MODE FOLLOWING A SMALL BREAK LOCA, CAUSE FLAWED DESIGN ANALYSIS LED TO UNDERSIZED PIPING. TYPICAL LOCA ANALYSIS DOES NOT ANALYZE ECCS FLOW SCENARIOS FOR THE RECIRCULATION PHASE, SAFETY SIGNIFICANCE CAVITATION CAUSED BY INADEQl' ATE NPSH COULD RESULT IN PUMP FAILURE AND LOSS OF LONG TERM COOLING FOR CERTAIN SMALL BREAK LOCAs, O
DISCUSSION o TURKEY PT, - MAY 12, 1988 - LICENSEE DISCOVERED A THROTTLE VALVE IN THE RHR DISCHARGE LINE IS NORMALLY 30% OPENED, EVALUATION SHOWED THAT THE VALVE SHOULD BE IN THE FULLY OPEN POSITION, o OCONEE 1, 2, AND 3 - MAY 19, 1988 - DURING A ECCS DESIGN REVIEW, THE LICENSEE DISCOVERED THAT A CERTAIN SET OF CONDITIONS COUPLED WITH INADE00 ATE GUIDANCE TO THE OPERATORS COULD CAUSE THE HPSI PUMPS TO HAVE INADEQUATE NPSH FOLLOWING A SMALL BREAK LOCA, o CONTAINMENT SPRAY AND HIGH PRESSURE INJECTION ARE BOTH PIGGYBACKED OFF THE LPSI (RHR) PUMPS IN THE RECIRCULATION MODE FOLLOWING A SMALL BREAK LOCA (PROCEDURES ALLOWED SIMULTANE0US USE OF LPSl/HPSI AND CS PUMPS, o ORIGINAL 6 INCH LINE TO CROSSTIE LPSI TO HPSI WAS REDUCED TO 3 INCHES BASED ON B8W CALCULATIONS BACK IN THE SIXTIES (OCONEE),
o EMERGENCY PROCEDURES REVISED AT OCONEE TO REDUCE FLOW AND MAINTAIN PRESSURE IN THE HPSI TRAINS AND/0R THE CONTAINMENT SPRAY TRAINS TO ACHIEVE ADEQUATE NPSH CONDITIONS DURING THE RECIRCULATION PHASE, CONTACT: J, THOMPSON
REFERENCE:
50,72 # 12326 AND MORNING REPORT 08/00"
GENERIC.lSSUE 88-33 o THIS PROBLEM POTENTIALLY EXISTS FOR OTHER PWR's.
FOLLOWUP o AEOD ENGINEERING EVALUATION REPORT (AUGUST 1988) SUGGESTED A SUPPLEMENT TO AN EARLIER INFORMATION NOTICE ON INJDEQUATE NPSH IN LPSI IN PWRs (IN 87-63, INADEQUATE NET POSITION SUCTION HEAD IN LOW PRESSURE SAFETY SYSTEMS),
o B&W IS LOOKING AT GENERIC IMPl? CATIONS TO OTHER B8W PLANTS, o EAB IS WORKING WITH RSB AND AEOD TO FACillTATE PROPER GENERIC REGULATORY RESPONSE (1.E., INFORMATION NOTICE OR BULLETIN),
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. , ENCLOSURE 3 REACTOR SCRAM
SUMMARY
NEEKENDING 08/14/88 ,
- l. PLANT SPECIFIC DATA DATE SITE UNIT PONER SIGNI4 CAUSE COMPL1- YTD fiD YTD CATIONS ABOVE DELON TOTAL 151 151 08/11/88 BRAIDN000 1 100 A PERSONNEL No 1 0 1 08/12/88 TURKEY POINT 4 0A EQUIPMENT NO 0 1 1 08/13/88 MINE YANKEE 1 98 A E00!PMENT YES 2 0 2 SUMARY OF COMPLICAi!ONS SITE UNIT COMPLICAi!DNS MINE YANKEE 1 SERVICE NATER PUMP FAILED TO START AUTOMTICALLY AND LOAD ONTO D/6 AS EIPECTED .
ONE MIN STEAM LINE EICESS FLON CHECK VALVE CollLD NOT BE CLOSED MNUALLY FROM THE CCNTROL R00M .
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