Letter Sequence RAI |
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Results
Other: ML19259A913, ML20032B746, ML20093E104, ML20126K501, ML20127J035, ML20128L456, ML20128L477, ML20133A189, ML20133C210, ML20147B795, ML20147B900, ML20149H307
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MONTHYEARML20149G9741977-11-10010 November 1977 Summary of 771025 Meeting W/Util in Silver Spring,Md Re Storage of Oconee Nuclear Station Spent Fuel at McGuire Nuclear Station.List of Attendees Encl Project stage: Meeting ML20149H7251977-12-29029 December 1977 Forwards Request for Addl Info Re Rev 24 to FSAR Re Storage of Oconee Fuel at McGuire Facility Project stage: RAI ML20149H7111978-01-0404 January 1978 Forwards Request for Addl Info Re Rev 24 to FSAR Concerning Storage of Oconee Spent Fuel at McGuire Facility Project stage: RAI ML20149H5791978-03-0909 March 1978 Application for Amend to License SNM-1773,authorizing Storage of Oconee Spent Fuel at McGuire Facility Prior to Issuance of McGuire OL Project stage: Request ML20147B9001978-04-19019 April 1978 Confirms 780418 Conversation Re Site Visit on 780425-27 by NRC & Contractor Personnel.Areas of Interest to Be Reviewed for Both McGuire & Oconee Sites Are Listed Project stage: Other ML20147B7951978-05-0808 May 1978 Discusses 780425-27 Site Visit Made to Familiarize Proj Manager & Contractors W/Spent Fuel Facil Project stage: Other ML20149H1011978-05-19019 May 1978 Forwards Request for Addl Info Re Application for Amend to License SNM-1773,including Licensing of Spent Fuel Pool as Isfsi.Meeting W/Util Requested to Resolve Matter.Response to Encl Questions Needed by 780605 Project stage: RAI ML20147C7361978-05-23023 May 1978 Notification of 780602 Meeting Re Proposed Transport of 120 Day Old Vice 1 Year Old Spent Fuel from Oconee Nuc Station to McGuire Nuc Station for Interim Storage Project stage: Meeting ML20149H8721978-07-21021 July 1978 Forwards Request for Addl Info Re Application for Amend to License SNM-1773 Re Storage of Oconee Spent Fuel at McGuire Facility.Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20149H3071978-08-0202 August 1978 Forwards Schedule Used by NRC to Insure Timely Review Process.Dates Shown Reflect Best Practical Estimate Which Can Be Made at This Time.Date of Completion & Final Decision on Licensing Action Will Depend on Result of Hearings Held Project stage: Other ML20150A6631978-09-26026 September 1978 Forwards Review of Draft EIS for Transshipment & Storage of Irradiated Oconee Fuel at Subj Facil.Requests Review for Consistency W/Nrr Review of McGuire Appl.Meeting W/Pacific Nw Lab 781002 ML19259A9131978-12-31031 December 1978 Eia Re Spent Fuel Storage of Oconee Spent Fuel at McGuire Station-Unit 1 Spent Fuel Pool. Concludes There Will Be No Significant Environ Impact & That No EIS Need Be Prepared Project stage: Other ML20032B7461981-10-27027 October 1981 Amend 8 to License NPF-9,revising Tech Specs to Authorize Receipt,Possession & Storage of 300 Irradiated Fuel Assemblies Project stage: Other ML20080P8411984-02-17017 February 1984 Application for Amend to Licenses NPF-9 & NPF-17,allowing Spent Fuel Pool Storage Capacity Expansion from 500 to 1,463 Spaces for Each Spent Fuel Pool.Supporting Documentation Encl Project stage: Request ML20093E1171984-09-24024 September 1984 Safety Evaluation Supporting Amends 35 & 16 to Licenses NPF-9 & NPF-17,respectively Project stage: Approval ML20093E1041984-09-24024 September 1984 Amend 35 & 16 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs to Permit Expansion of Spent Fuel Pool Storage Capacity Project stage: Other ML20100G4641985-04-0303 April 1985 Application for Amends to Licenses NPF-9 & NPF-17, Incorporating Into Unit 2 License Authority to Receive, Possess & Store Irradiated Oconee Fuel Assemblies Under Same Conditions as Presently Authorized by Unit 1.Fee Paid Project stage: Request ML20127H6421985-05-14014 May 1985 Application for Amend to Licenses NPF-9 & NPF-17, Incorporating Into Unit 2 License Authority to Receive, Possess & Store Irradiated Oconee Fuel Assemblies Under Conditions Authorized by Unit 1 License Project stage: Request ML20127J0351985-05-14014 May 1985 Proposed Tech Specs,Incorporating Into Unit 2 License Authority to Receive,Possess & Store Irradiated Oconee Fuel Assemblies Under Conditions Authorized by Unit 1 License Project stage: Other ML20128L4771985-05-16016 May 1985 Notice of Consideration of Issuance of Amend to Licenses NPF-9 & NPF-17 & Proposed NSHC Determination & Opportunity for Hearing Re Util 850403 Request to Store Oconee Spent Fuel at Unit 2 Project stage: Other ML20128L4561985-05-20020 May 1985 Forwards Notice of Consideration of Issuance of Amend to Licenses NPF-9 & NPF-17 & Proposed NSHC Determination & Opportunity for Hearing Re Util 850403 Request to Store Oconee Spent Fuel at Unit 2 Project stage: Other ML20126K5011985-06-12012 June 1985 Submits Addl Info Further Clarifying Util Position on Receiving,Possessing & Storing Irradiated Oconee Nuclear Station Fuel Assemblies Under Current License NPF-9 Conditions,Per 850403 & 850514 Proposed License Amends Project stage: Other ML20133A1891985-07-26026 July 1985 Forwards Unexecuted Amend 8 to Indemnity Agreement B-83 for Signature Project stage: Other ML20133C2181985-07-26026 July 1985 Safety Evaluation Supporting Amends 44 & 25 to Licenses NPF-9 & NPF-17,respectively Project stage: Approval ML20133C2101985-07-26026 July 1985 Amends 44 & 25 to Licenses NPF-9 & NPF-17,respectively, Incorporating License Authority to Receive,Possess & Store Irradiated Fuel Assemblies from Oconee Nuclear Station Project stage: Other 1978-08-02
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SICJECT:
STO?Mr OF OCC EE SPERT TUEL AT THE MCCUIRE lVCLEAR STAT 101l In Revision ?4 of the FSliR for the lic0uire fluclear Station, you proposed 1
the stcrap of Oconee scent fuel at the !!cCuire Station.
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thic see? oral and have deter.'iii.ed that we n.ed additional infornation to co:plete our evaluation.
The enclosure desertins the required information.
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tle would annrecicte an early response in order to continue our review
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l Sincerely, o
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ENCLOSURE JAN 04 ma AUXILIARY SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORitATION MCGUIRE NUCLEAR STATION, UNITS l&2 DOCKET NOS. 50-369/370 10.24 a.
Demonstrate that the insertion of the proposed spacer (9.1.4) in the storage rack will not block or restrict the fluid flow necessary for spent fuel decay heat removal.
b.
Demonstrate that the location and method of attaching the 5-1/2" spacers in the McGuire fuel racks do not
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nullify the McGuire fuel rack seismic Category I design.
The effect of gaps, sloshing water, and increase of effective mass and damping due to submergence in water should be considered.
Provide drawings to show the location and means of attaching the spacer in the storage rack.
c.
Describe the measures that will be taken to assure that only Oconee fuel assemblies can be stored in the storage rack locations where the 5-1/2" spacers are inserted, and how to prevent McCuire fuel being stored in such loca-tions inadvertently.
l d.
Discuss the adverse consaquences of storing the McGuire fuel assemblies in location which are allocated for Oconee fuels, i.e., locatiens where 5-l/2" spaters are at'. ached.
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. #N04 M8 10.24 Discuss the consequences if one or more of the 5-1/2" spacers were not in place when the Oconee fuel bundle is inserted _into a spent fuel rack.
e.
Indicate the maximum quantity of Oconee spent fuel (RSP) assemblies that will be stored in the McGuire facility.
Will there be sufficient storage space for emergency unloading of an entire McGuire cone following i ts startup?
f.
Demonstrate that the special fuel handling tool for Oconee fuel will have the same seismic and quality group classification as McGuire fuel handling equipment.
In addition, demonstrate that the special handling tool is capable of holding its load during a seismic event.
g.
Describe the hoist which will be used to handle Oconee spent fuel assemblies. Demonstrate that the maximum uplift force of the hoist will not exceed the design limit of the McGuire spent fuel storage rack or the Oconee spent fuel essembly, h.
You indicate that a portion of the Oconee fuel assembly would extend above the fuel rack when stored in the l
l McGuire facility) Provide the results of an analysis
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e,
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3-JBN 01 M8 indicating the expected amount of fuel damage as a result of dropping either a McGuire or Oconee fuel bundle onto the portion of the Oconee fuel bundle extending above the fuel racks in the spent fuel.
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