Similar Documents at Maine Yankee |
|---|
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
-. - . _ _ _- _ _ _ _ _ __ _ _ _ _ _ _ . _ _ _ _ __ . . . __
/ - 64 , j t
-f 4 s g. 'f 4
n+ 7 1;,;bei%IN j .DecernDer 1,1997 '
- u la
,j q -
't
,7 y jfyf .
4 3 ,
hy sFACILITY: Maine Yankee Atomic Power Station: _
1 l 9[ ;
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 20 1997, TO DISCUSS THE
' PROPOSED DEFUELED TECHNICAL SPECIFICATIONS FOR MAINE YANKEE 1
L 3$
4- ATOMIC POWER STATION -
,: J: '
2 On November 20,1997, NRC staff members met at Rockville, Maryland, with employees of:
Maine Yankee Atomic Power Company (MYAPC or the licensee) to discuss the proposed defueled technical specifications for the Maine Yankee Atomic Power Station (Maine Yankee).- A list of attendees is included as Enclosure 1. The handout used by MYAPC at -
the meeting is included as Enclosure 2. -
MYAPC provided certifications of permanent cessation of operation and permanent removal
- of fuel from the reactor vessel on August 7,1997. On October 20,1997, MYAPC
. submitted an application to amend the Technical Specifications to reflect the permanently defueled status of the plant.
-In its presentation, the licensee provided an overview of the regulatory and analytical framework that it used to develop the Maine Yankee defueled Technical Specifications. The-licensee also provided an item-by item comparison of the current Maine Yankee Technical
. Specifications with the improved Standard Technical Specifications and the proposed defueled Technical Specifications.
ORIGINAL SIGNED BY:
Michael K. Webb, Project Manager Non Power Reaciors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulau n -
Docket No. 50-309 ,
4
Enclosures:
, . As stated hn hh h( {!{'jl e t
. - cc w/ enclosures: ~
See next page DISTRIBUTION: w/o enclosure 2 s . .
E-M AIL s HARD COPY , .
. SCollins/FMiraglia RRasmussen' ~ Docket No. 50-309 MWebb y +
1 RZimmerman TJohnson PUBLIC EHylton l 'v.
C *
. JRoeL SWeiss ,
LPittiglio TMartin'(SLM3)
PDND r/f.
OGC w' f ~
3 MMasnik . BMcCabe ACRS e
,= ,
- (z
.-_y7 _x _
m '
PDND:PM PDND:LA PDND:(A)SC PDND:D -
4 , s ' MWebb .w EHylton' MMasnik /k SWeiss g- _
11/d/97 1$/l/97 12/(197 '
9:
J 15/ // /97 ,
, , ( " ~, OFFICIAL RECORD COPY DOCUMENT NAME: A:\S-112097 ,
.,3 '
9712090091 971201 PDR ADOCK 05000309 I.B.E.,I,M..M. '
N .PDR .
e ,
98AIOp y t UNITED STATES s* }f NUCLEAR REGULATORY COMMISSION WASHH '10 ton, D.C. 2006H001
% # December 1, 1997 FACILITY: Maine Yankee Atomic Power Station
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 20,1997, TO DISCUSS THE PROPOSED DEFUELED TECHNICAL SPECIFICATIONS FOR MAINE YANKEE ATOMIC POWER STATION On November 20,1997, NRC staff members met at Rockville, Maryland, with employees of Maine Yankee Atomic Power Company (MYAPC or the licensee) to discuss the proposed defueled technical specifications for the Maine Yankee Atomic Power Station (Maine Yankee). A list of attendees is included as Enclosure 1. The handout used by MYAPC at the meeting is included as Enclosure 2.
MYAPC provided certifications of permanent cessation of operation and permanent removal of fuel from the reactor vessel on August 7,1997. On October 20,1997, MYAPC submitted an application to amend the Technical Specifications to reflect the permanently defueled status of the plant.
In its presentation, the licenseo provided an overview of the regulatory and analytical framework that it used to develop the Maine Yankee defueled Technical Specifications. The licensee also provided an item-by-item comparison of the current Maine Yankee Technical Specifications with the improved Standard Technical Specifications and the proposed defueled Technical Specifications.
- b & X W O 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
l l
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 Station Thomas G. Dignan, Jr., s.nuire P.O. Box 408 Ropes & Gray Wiscasset, ME 04578 One Internationa'. Place Boston, MA 02110-2624 Mr. Michael J. Meisner Vice President Mr. Ul:lis Vanags Licensing and Regulatory Compliance State Nuclear Safety Advisor Maine Yankee Atomic Power Company State Planning Of fice 329 Bath Road State House Station #38 Brunswick, ME 04011 Augusta, ME 04333 Mr. Jonathan M. Block Mr. P. L. Anderson, Project Manager Attorney at Law Yankee Atomic Electric Company P.O. Box 566 580 Main Street Putney, VT 05346-0566 Bolton, MA 01740-1398 Mr. Michael B. Sellman, President Regional Administrator, Region 1 Main Yankee Atomic Power U.S. Nuclear Regulatory Commission 329 Bath Road 475 Allendale Road Brunswick, ME 04011 King of Prussia, PA 19406 Mr. Robert Fraser, Director First Selectman of Wiscasset Engineering Municipal Building Maine Yankee Atomic Power Company U.S. l'oute 1 329 Bath Road Wiscasset, ME 04578 Brunswick, ME 04011 Mr. Richard Rasmussen Mr. Patrick J. Dostie Senior Resident inspector State of Maine Nuclear Safety Maine Yankee Atamic Power Station inspector U.S. Nuclear Regulatory Commission Maine Yankee Atomic Power Station P.O. Box E P.O. Box 408 Wiscasset, Sid 04578 Wiscasset, ME 04578 Mary Ann Lynch, Esquire Mr. Mark Ferri Maine Yankee Atomic Power Company Decommissioning Director 329 Bath Road Maine Yankee Atomic Power Station Brunswick, ME 04011 P.O. Box 408 Wiscasset, ME 04578 Mr. George Zinke, Manager Regulatory Aff airs Maine Yankee Atomic Powe- Company 329 Bath Road Brunswick, ME 04011
ENCLOSURE 1 Maine Yantee Atomic Power Station Proposed Defueled Tech Spec Meeting November 20,1997 ATTENDEES NAME ORGANIZATION Michael Meisner MYAPC George Zinke MYAPC Michael Whitney MYAPC Rick Rasmussen NRC/ Senior Resident inspector Seymour Weiss NRC/NRR Michael Masnik NRC/NRR Michael Webb NRC/NRR Tim Johnson NRC/NMSS Larry Pittiglio NRC/NMSS Peter Wiley State of Maine Ray Ng Bechtel W. P. Gammill LMITCO (INEEL)
Sam Bryan Quality Services Associates I
Ir i ' -
e MAINE YASKEE DEFELED i TECHXICAL .
SPECIFICATIONS i
i Overview Presentation to Nuclear
! Regulatory Commission m t November 20,1997 l 5
M i
i
4 s
Regulatory Framework Defueled
~
i j l
Teclinical Speci5 cations 10CFR50.82(aX2) - Certifications docketed
! for permanent cessation of operations and permanent removal of fuel from the reactor vessel
- 10CFR50.36 " Technical Specifications" bEREG-1432 " Standard Technical I Specification, Combustion Engineering l Plants" .
i .
l-
, - n.. -
n , , .... -., . -
l l
~
i l Analytical Framework
- Current FSAR analyses (no changes)
- Amendment 144 (Fuel Pool Rerack)
- Spent Fuel Pool Cooling Thermal / Hydraulic
- - Fuel Handling Accident
! - Spent Fuel Criticality
L p
Improved Standard Technical l:
Specification Methodology
- Applicable to all modes of" operation"
- power operation
- - shutdown
- defueled t
- Conversion Process i l - Evaluated to 10CFR 50.36(cX2Xii) criterion :
1
- - Relocated information/ requirements to i
- appropriate controlled programs / documents I i 4
i i !
- i
a i
Impact of 10CFR50.82 -l
! Certifications I
? !
I Most specifications not applicable i -
Most specifications will never become
- applicable
- t
- i l
4 i l
)
L Major Changes i
L l Removes specifications not applicable to a permanently defueled condition
- j. Relocates information/ requirements to J FSAR, QA Program, ODCM, and
- Radioactivity Effluents Controls Program.
i Two specifications added per ISTS
- Fuel Pool Boron Concentration l
i .
- Fuel Pool Level L
i
Major Changes -
l
- Administrative Controls changes t
I - Oversight review committees-
- structure and responsibilities relocation
- Cleanup of 10CFR20 items
- Relocation of audit subjects and frequencies i
- Relocation of procedure change process l - Relocation of record retention requirements
- - Design Features relocations 1
. - - - . . . .__.___._._______.J
Comparison with Trojan -l Technical Specifications L Submitted prior to finalization ofImproved l Standard Technical Specifications and Maintenance Rule l Fuel Pool Temperature Specification .
L Chemistry Program i
! Fuel Pool Cooling Monitoring Program
! Fuel Pool Load Restrictions Specification
- i R
- - - . -__o
e e 1
Submittal -
j i
Background and Description of Changes i
- Significant Hazards Evaluation Permanently Defueled Technical .
r Specifications i Technical Specification Bases PORC/NSARC Relocation and Restructure
! i i
- PDTS Submittal- 10/20/97 i - FR N otice - next available period
!' - OGC Review - 1/15/98
- NRC Approval- 1/31/98
- Maine Yankee Implementation - ASAP after 1/31/98 1
4
- - - _ .. .. . _ . _ _ _ - _ _ _ ___________!