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
~ _ _ . _ _ . _ _ _ _ _ _ _ . . _ _ _ _ . _ ~__
l l
. October 8, 1997
. MEMORANDUM T0: Charles J. Haughney. Acting Director Spent fuel Project Office. NMSS FROM: Michael G. Raddatz. Sr. Project Manager Spent Fuel Licensing Section Spent Fuel Pro,1ect Office. NMSS
SUBJECT:
MEETING WITH MAINE YANKEE A10MIC POWER COMPANY On September 11. 1997, a meeting was held between representatives of the Nuclear Regulatory Commission and Maine Yankee Atomic Power Company (Maine Yankee) to discuss the options available for storage of its spent fuel.
Attachment 1 is a list of attendees. Attachment 2 is a copy of the meeting handout. The meeting was noticed on September 3. 1997.
The meeting, requested by Maine Yankee, was an information gathering session fausing on options for the storage of the spent fuel currently at the site.
NRC staff presented a brief overview of the licensing process for independent spent fuel storage installations under both the site specific and general license processes. Maine Yankee informed NRC of its intent to continue discussions with various vendors and will decide on future milestones in fall 1997. The Maine Yankee reactor shutdown in December 1996 and commenced core offloading in June 1997. By 2003 Maine Yankee intends to empty the fuel pool and complete the initial decommissioning.
No proprietary information was disseminated or presented at this meeting. No regulatory decisions were requested or made.
Docket 50-309 Attachments: 1. Attendee List
- 2. Meeting Handout Di st ribution-Inctot __ NR Fil -PUBlic, NMSS R/F sFP0 R/f SfLs R/F i sshankman HbG1TTgattiACenter_
s PEng EEaston fsturz WReamer. 0GC l REaton DDorman JYerokun CAnderson. R1 SGaoner, nPA l lOFC SFP0 .t E SFPQk (( SFP0 E/
lNAME MRadhatY:dd V pe fJLeed [
i lDATE' 10/$ /97 10/o } /97 10kEd97
! C = COVER E = COVE 1 & LNCLO5URL N = NO COPi G:\MAINEY\9 29 97.mtg -
OfgCIALRECORDcoPY I
can ll l.l! .Ill .I!.I' 1llll pn p q p-ym pgpf 9710200178 971008 PDR ADOCK 05000309 W PDR
. ATTENDANCE LIST i MEETING BETWEEN U.S. NUCLEAR REGULATORY COMMISSION AND MAINE YANKEE ATOMIC POWER COMPANY-SEPTEMBER 11. 1997
&Lme Oraanization Fritz Sturz NRC/NMSS/SFP0-Eric Leeds NRC/NHSS/SFP0 David Tang NRC/NMSS/SFP0 l Kim Gruss NRC/NMSS/SFP0__
Sherry Wu NRC/NMSS/SFP0 Rick Rasmussen -
NRC/RGN-1 Paul Harris NRC/NRR/DRPM Michael.Webb NRC/NRR/DRPM Dan Dorman NRC/NRR Sue Gagner NRC/0PA .
R. P. Jordan Maine Yankee Paul J. Plante- Maine Yankee David A. Rivard Maine Yankee Pat Dostie (by telephone) State of Maine Uldis Vanags (by telephone) State of Maine Steve Schulin The IBEX Group James Doman Booz Allen (DOE)
Ray N Bechtel Power Corp.
Alan elson NEI ATTACHMENT 1
\
- - I l
i Licensing of Independent
!' l l
! Spent Fuel Storage
- Installations I, !
l Michael G. Raddatz, Senior Project Manager Licensing i
j j Spent Fuel Licensing Section Spent Fuel Project Office l United States iJuclear Regulatory Commission w
j _
i 3
i l
f j ATTACHMENT 2
i 1
10 CFR Part 72 1
3 Regulations l
- = Technical Requirements l l 4 !
- I i
! - Design Basis Accidents l
l
L i
i 1
a
'I 4
i ,
- I 10 CFR Part 72 l Procedural Aspects i i
= One-Step Licensing i
= 20 Years !
= 40 Years
= Licensing Terms
= Environmental Review
n '
l 10 CFR Part 72 '
l The Regulations Consider l
l I
2
= Accidents l i
i f
!
- = Sabotage i
i i
A 4
i l
e g-v, ,,- w + w w= +
w -- w -w - - - vw--'m- -~
"-w-- " w ,-
I General Li.;ense '
I
= Advantages
- Pre-Approval of Designs a Disadvantages
- Reliance upon vendors L i N
- . - _ . - w - -.,.%. . - _ ,_
D The General License
= Safety requirements of 10 CFR Part 72 remain in effect
= Current safeguards requirements for 10 CFR Part 73 for fixed sites remain applicable
= Ruie approved several cask designs
- New Casks are added by rulemaking em
l \
Licensee Requirements
- Under the General License
= NRC Notifications:
i
- 90 days prior to first storage under the General l License
- Register use of a cask design within 30 days of use
- Provide a preoperational test report at least 30 days !
prior to receipt of spent fuel j
- Maintain a copy of the Certificate of Compliance and other vendor supplied documents l l J
_-wM N
i Site Specific Licensing '
i
= Direct Review of an Application
= Approval of a Storage System's Topical Safety Analysis Report
- or - '
= Combination of the Above t_ I
l l
Site Specific Licensing '
l Review of the Application ,
= Review of the Environmental Report
- Prepare an Environmental Assessment
= Review Safety Analysis Report
- Supplementary Information
- Confirmatory Calculations
= Publish a Safety Evaluation Report 1 J
9H M W
l l The Safety Review '
Major Areas of a Review l
= Confinement Barriers a Criticality
= Testing & Maintenance
4
. r i :
, i l-Certificate of Compliance '
I i What do you get ?
! = 20 year renewable certificate !
l
= Casks must be manufactured per a l Certificate of Compliance j
- = Description of cask and references to l
! appropriate drawings l
\
. = Technical Specifications !
t
~
i 4 h l
4
c Certificate of Compliance !
4 What does it Contain ?
l
= Functional and Operating Limits
- Surveillance / maintenance requirements ;
-Inert gas pressure I
- Leak tightness ! !
- Surface dose rates and contamination limits !
l = Type of fuel !
- Cooling time
- Burnup / heat loads :
-Initial Enrichment
= Lift height restrictions
& hm - - -
M ape -
M
- m
I !
l' NRC Expectations '
= Utilities .
- Frequent communications with NRC and Public l !
- Early notification essential !
, - Aggressive QA oversight l
- Aggressive self assessments '
= Fabricators ;
l
- Adhere strictly to QA program i
- Document all deviations thoroughly
- Justify all changes in detail
- Communicate often with vendor and utility 4
a f
i 4
(
T
Dry Storage issues
= Overall inconsistent performance ,
= Utility oversight essential l
= QA programs and principles not observed
= Engineering safety evaluations
= NRC expectations not clearly communicated
= Public Confidence Jeooardized i
.