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
, h@b f"%,4 fr-Spq
.pe UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINoToN, D.c. 20066 0001 k..../ June 17, 1998 FACILITY: Maine Yankee Atomic Power Station
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 9,1998, TO DISCUSS SPENT FUEL HEATUP ANALYSIS PERFORMED BY MAINE YANKEE ATOMIC POWER STATION On June 9,1998, the NRC staff met at Rockville, Maryland, with staff of Maine Yankee Atomic Power Company (MYAPC or the licensee) and its contractor, Scientech, Inc., to discuss the spent fuel heatup analysis that MYAPC performed in support of exemption requests that it has submitted related to emergency preparedness and financial protection.
A list of attendees is included as Enclosure 1.
MYAPC provided certifications of permanent cessation of operation and permanent removal of fuel from the reactor vessel on August 7,1997. On November 6,1997, MYAPC submitted an exemption request to discontinue certain aspects of offsite emergency preparedness to reflect the permanently defueled status of the plant. On January 20, 1998, MYAPC submitted exemption requests from certain insurance coverage and financial protection requirement limits related to onsite and offsite liability coverage due to the reduced potential risk that the shutdown plant presents to public health and safety. An analysis by Brookhaven National Laboratory indicated that a potential hazard, a zircaloy cladding failure due to spent fuel heatup in the event of a loss of spent fuel pool water, could occur for some time after a reactor nas been shut down. MYAPC performed a spent fuel decay heat analysis to demonstrate to the NRC staff that the Maine Yankee spent fuel had cooled sufficiently that in the event of a complete loss of spent fuel pool water, the fuel temperature would not exceed 565"C, the temperature below which fuel cladding integrity is rnaintained, in its presentation, the licensee stated that its purpose was to discuss the basis and results of the MYAPC heatup analysis and to demonstrate that the Maine Yankee fuel is no longer capable of sustaining an uncontrolled heatup resulting in fuel clad damage and offsite release. The licensee provided an overview of the Maine Yankee spent fuel and a comparison to the generic PWR analysis, and a description of the development of the MYAPC analysis.
A representative from Scientech then presented a detailed discussion of the MYAPC analysis. Although the meeting was open to public observation, this portion of the meeting .
wes closed.to the public due to the proprietary material that Scientech presented. The t handout used by MYAPC during the non-proprietary portion of the meeting is included as 0[y
/
Enclosure 2.
1 990dn240274 17 PDR ADOCK 0 4 . _ ~ ~%s F PDR .
{ nn enat,
2 June 17,1998 The NRC staff stated that it would contact MYAPC in the near future with a determination as to whether the analysis that MYAPC had conducted provides an adequate basis upon which the staff could base its determination regarding the exemptions or if additional information or staff review was required.
ORIGINAL SIGNED BY:
Michael K. Webb, Project Manager Non-Power Reactors and Decommissioning i Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosures:
As stated cc w/ enclosures: See next page DISTRIBUTION:
E-MAIL HARD COPY SCollins/FMira0lia (SJC1/FJM) Docket File 50-309 BBoger (BAB2) PUBLIC JRoe (JWR) EHylton SWeiss (SHW) PDND r/f TMartin (SLM3) MMasnik Region 1 MWebb
- PDND (NPRs staff) OGC (015-B18)
BMcCabe (BCM)
PDND:PM PDN 7 h
hD:D MWebb w 6//6 /98.
on PDND:(A)[SC MMasnik SWeiss 6 /98 6/) /98 6/; $98 OFFICIAL RECORD COPY
- DOCUMENT NAME: G:\SECY\MTG_NOTC\MY9JUNMT l
L t
L 2
-The NRC staff stated that it would contact MYAPC in the near future with a determination I as to whether the analysis that MYAPC had conducted provides an adequate basis upon l ' which the staff could base its determination regarding the exemptions or if additional information or staff review was required.
- p& W'7)!b Michael K. Webb, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosures:
As stated cc w/ enclosures: See next page j
Maine Yankee Atomic Power Station Docket No. 50-309 cc:
Mr. Charles B. Brinkman Friends of the Coast Manager - Washington Nuclear P.O. Box 98 Operations Edgecomb, ME 04556 ABB Combustion Engineering 12300 Twinbrook Parkway, Suite 330 Mr. William O' Dell Rockville, MD 20852 Operations Director Maine Yankee Atomic Power Company Thomas G. Dignan, Jr., Esquire P.O. Box 408 Ropes & Gray Wiscasset, ME 04578 One International Place Boston, MA 02110-2L .4 Mr. George Zinke, Director Nuclear Safety and Regulatory Affairs Mr. Uldis Vanags Maine Yankee Atomic Power Company State Nuclear Safety Advisor P.O. Box 408 State Planning Office Wiscasset, ME 04578 State House Station #38 Augusta, ME 04333 Mr. Jonathan M. Block Attorney at Law Mr. P. L. Anderson, Project Manager P.O. Box 566 Yankee Atomic Electric Company Putney, VT 05346-0566 580 Main Street Bolton, MA 01740-1398 Mr. Michael J. Meisner, President Main Yankee Atomic Power Company Regional Administrator, Region l P.O. Box 408 U.S. Nuclear Regulatory Commission Wiscasset, ME 04578 475 Allendale Road King of Prussia, PA 19406 Mr. Robert Fraser, Director Engineering First Selectman of Wiscasset Maine Yankee Atomic Power Company Municipal Building P.O. Box 408 U.S. Route 1 Wiscasset, ME 04578 Wiscasset, ME 04578 Mr. Patrick J. Dostie Mr. Richard Rasmussen State of Maine Nuclear Safety Senior Resident inspector Inspector Maine Yankee Atomic Power Company Maine Yankee Atomic Power Company U.S. Nuclear Regulatory Commission P.O. Box 408 P.O. Box E Wiseasset, ME 04578 Wiscasset. ME 04578 Mr. Mark Ferri Mary Ann Lynch, Esquire Decommissioning Director
, Maine Yankee Atomic Power Company Maine Yankee Atomic Power Company P.O. Box 408 P.O. Box 408 Wiscasset, ME 04578 Wiscasset, ME 04578
Maine Yankee Atomic Power Station .
Spent Fuel Heatup Analysis Meeting June 9,1998 Attendees NAME ORGANIZATION Michael Meisner MYAPC George Zinke.- - MYAPC Robert Jordan - MYAPC l Jack Dallman . Scientech, Inc.
Uldis Vanags State of Maine Russ Mellor - Connecticut Yankee l Edward Mullarkey Connecticut Yankee Gerry VanNoordennen Connecticut Yankee Jack Roe NRC Seymour Weiss NRC Michael Masnik NRC Ron Burrows NRC Ralph Caruso NRC Tom Fredrichs NRC
- Chris Gratton NRC Michelle Hart NRC George Hubbard NRC Diane Jackson NRC Anthony Markley NRC !
Vonna Ordaz NRC -1 Joseph Staudenmeier NRC Michael Webb NRC Ray Ng (non-proprietary portion only) Bechtel l
ENCLOSURE 1.
i
l f(
~
\
~
N r s,h ~
)lAINE YANKEE SPENT FUEL $
4EATUP ANALYSIS V g; .y l
PRESENTATION TO THE _
NUCLEAT! REGULATORY COMMISSION JUNE 9,1998 j ew. .
\
% / N I
+ IMMEDIATE. cceptance of MY Beyond Design Basis Zirc Fi _ Supportinh Submittec !
Exemption R fit)
+ PROMPT g mergency Plan Exempt
+ PROMPT" royal of Pend n urance Exemptions )
s 1
l 1
ENCLOSURE 2 i
KGROUND
+ 4/89 - NUREd'13 " Regulatory A alysis for tie \
Resolution of G ond Desicn Basis Accidents in Sp, _ , suools'82, 'B , d Issue
+ 4/89 - Generic Id LVED - NO NEW REQUIREMENTS
^
+ 6/89 - Rancho Sdc$ Stiutdoh
+ 1/91 - Rancho Seco insurance Exemp 'on Gra ited (no zite fire analysis; 588 jays after sh )
x xy C GROUND
\
+ 2/91 - Ranchh E-Plan Exemp ons Granted (no zire fire ana1Y ys after s utdown)
+ 11/92 - Trojag
+ 6/93 - E-Plan'E d d irc fire analysis -
325 days aftaiir7
+ 12/96 - MainEYankee Sh oSE's s
+ 11/97 - MY Requests E-Plan Exe s
~,E w
2
Nf
/
) ~BICKGROUND -
M E
$$ .ll#
+ 1/16/98 Zirc FirhEvent No Longer ossible - Maine \
Yankee / Scientec lysis (406 c lays after shutdown) 'q
+ 1/20/9E MY Req ~ e Exemptions
+ 5/6/98 Generic W ., _ , . . . ded (NUREG-1353, SECY 96-256' 17 months)' ^
+ 6/9/98 NRC Reviews and Analysis Sti Pending (550 days after shutdown) x Nf
+ NO SAFETYI ^ E EXISTS 550 DAYS '
AFTER MAINE YAN,K TDOWN
+ NRC Impositi uirements Conceming Zirc Fire inconsist
+ Acceptanc[ ,,. , ,.,.
+ Analysis Validation Process '-
+ Beyond Design Basis Event S significance ,-
n -
3
4 7
nam # .
NAINE YANKEE SPENT FUE $m gONIUM HEATUP ANALYSIS f -
p Robert P, Jordan
~j Manager, Engineering Analysis
_ 4 6498 -
t
~
.=
/\
ion Purpose
+ Discuss the N nd results of th Maine Yankee zirconium h sis following a loss of water l inventory in' ool.
+ Share Main $( n i' e zirconiurn heatup transi
+ Demonstrate that aine Yanke spent fuelis no longer capable of susta!ning an un o rolled heatup resulting in fuel clad damage and releases, x
4 J
I "
%, l sion Topics
+ Overview I# ration of Spent uel Pool
-Et
+ Key Compan enen PWR Ana ysis j.
+ Maine Yankbe ysis De o ment
+ Detailed Analysis Discussion ?
J-N l
\f uei status N
+ Last core c,, 12/6/96 folio ving a ~10 month operating
+ Core offloa'd) pool complete E/6/97.
+ Cessation of, rtified on 8/7/97.
+ Minimum spent s (547 dtys) as of 6/6/98.
x 5
Fuel Pool Overview
+ Nominal Op'e r ting Conditions: '\
+ Level - 36.5 feet (nsnimum)
.
+ Boron C ,
ppm
+ Technical Spect
' tion on
(
ns:
- Level > 23 feet above 'rradiated fuel when i moving spent f E
- Boron Concentration > 1000 g.,pm (( y
- ti 4 .
3 N\ r !
Spent Fuel Pool Kev Ele h yy ,
Ew7.- _ . . . . . . _ . .
umam y
s
... ,....... ... a
\
Elh'TAIi~ ..... _
i! ,,...,,...ii. ,,,.......
,2 l $i >...- -
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R;;> G,
.$pm%g,.s.
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-- g ges. ,,,,,]
...r... ...r..,
6 i
I
Fuel PoolInventory S ma x.
+ 1432 spent fue) mblies from 1 operating cycles.
+ Standard CE; d 14 x 14 fuci
+ Supplied byf xon (Siemens), W
+ Controls r I
{
+ 2 consolidatedYsse demonstration proje' t circeQ1986-1'garray) fro m
c 9.
+ 2 failed rod baskets partially full.
+ Trash baskets .
x NV Analysis of Spent F IHe N
+ NUREG/CR-645 \
afety and Regulat ry Assessm9nt of Generic BWR ermanently Sh .itdown Nucle ar Power Plants" 4'
+ NUREG-1353, I t Resolution of Generic issue 82, Beyond n Spent Fudi Pools" g,,, ~.wgp tvn x
7
'Nf l WF yLKilCom)arisons with Gen alrica Ar <
g..sJCR-6451; j
+ Reactor Dati \
+ Generic PW.., 1130 MWe 193 Fuel Assemblies
+ Maine Yan ' 870 MWe 217 Fuel Assemblies
- Significant'e.' e has a lower initial enrichments and power de toar decay heat levels.
+ Spent Fuel Chara enz W, s
+ Generic PWR ' 20-60 GWD TU '
7x17 Design
+ Maine Yankee 3-49.3 GW U -
4x14 Desi
+ Slanificance: Maine Yankee has ompa :t design a -
lower decay heat levels. '
\'w l
\[
mparisons with Gene ic Ar al
/ .
+ Spent Fuel.S,t t x
- Generic _ 2 Region S2P (1460 assemblies)
)
N(f .4" Storage Cell Pitch P IFlo Hole ,
l- i 7g St elConstruclion
+ Maine Y (1434 assepblies)
- %$E 3 +J w'10.5" & 9.08 Storage Cell Pitch 4" Cell Flow H e - i Stainless nstruction
+ Slanificance: Same basic stora ers 1
s
1 l
[ Comparisons with Gene ic Ar a$bR4451) $
a.
+ Analysis Acceptance Criteria N
+ Generic PWR .,
- 5650 as ipient clad fc ilure
+ 671C as. ed clad ailure.
+ Maine Yankees. '
+ 565C as _ . ,e,
+ Zirconium cladding oxidation heat ad ion:
+ 565C adds -0% heat addition from idation
)
+ 671C adds <0.1% heat additio idatiol
+ Significance: Conservative analys pt qce criteria. .
N\ 7 mpansons with Gene ic Ar
+ Analytical d : \
+ Generic Critical Dec. y Time of 17 months jgf No cladding failures
+ Maine . al Dec y Time of 13 months
?h; ing failures
+ Consistent' lations, ww . .~ ...r
+ By January 1998, Maine Yankee ad passed the point of cladding damage due .
nt fuel heatup. ;
+ Reliance on the generic analy lo Staff to close this issue for Maine Yankee.
e
t e
Yankee Analysis Deve e
+ Analysis does.
'N ead to safety re ated actioris or
\
requirements fo. nt mitigaticin.
+ Accident consid. nd Des gn Basis" per Generic issue
+ Analysis desigrl . con . p nt in time at which fuel clad failures are not possible.
+ Justifies use of a realistically bas lytical assumptions and methodologies. s v
N\r N
ankee Analysis Deve pmen C. ,
N
+ Scenario Defin
- $7a
'A,
+ Non-mec. " t initiator resulting in u, controlled and ins of the spent fuel pcol.
.ys
\~II .
+ Complete. ..
na - I cooling by natural
" '^
circulation'of alr/
v i0
~
4 1
\y[
Yankee Analysis Deve
+ Key Assumption N N
+ No credit fo" recovery ac9 ions.
+ No credit fo( d or NNS equipment.
+ No credit fof ' 1e.
+ Adiabatic , . . - __, _ _ j_y ly (Region 11 racks).
l
+ Realistic decay heat based testin .
E 1 N
gr ;
jYankee Analysis Deve pmi
+ Decay heatI' \
+ Calcula t loading in the SFP.
+ Accounts . to conduc: ion, evaporation, and cony l
)
+ Compa AN 1971 Stand,1rd.
+ Results 3
+ ASB 9-2'$herpre'd icts decay heat by factor of - 30%.
(1971/1973 ANS Standart +25% -50% unce nty for decay times >
~
1 07 seconds.) .
+ Realistic decay heat loadings wit its ' ell w thin published uncertainties l1 l
4r Yankee Analysis Deve 3 N
+ Performed real fly based anal sis with a number of known consef s and simp:ifications.
+ Results are con - both the generic a,nalysis and within publi e certainties.
+ Results show cbne #k v , e, irconium 1eatup issue at Maine Yankee cannot resu in cladding breach and off site releases.
E 3 x~
l nh[iankee 3 iled n.a.
Analysis Discussion ;
i
+ Scientech, I
\
R. J. Dall hnical Dire . tor ,
s Ltl
- r. 3: #; r T ? f ~ * . ,%
I N t l-( 12
< _ _ -_---__-_--____a
LUSION 7s N
+ NO SAFETY iS EXISTS 550 l AYS AFTER MAINE YANKE, DOWN '
+ PROMPT Ap ng En ergency Plan Exemptions W5
+ PROMPT Approva o ,.
(
sarance Exemptions Warranted E R R
13