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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Text
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[p Rtcq UNITED STATES NUCLEAR REGUL A. TORY COMMISSION es 4
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Docket Nos.:
50-369 50-370 MEMORANDUM FOR:
Olan D. Parr, Chief, Light Water Reactors Branch, DPM FROM:
Victor Benaroya, Chief. Auxiliary Systems Branch, DSS
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - STORAGE OF OCONEE SPENT FUEL IN MCGUIRE FACILI~.Y Plant Name:
McGuire Nuclear Station, Units 1 & 2 Licensing Stage:
0L Docket Numbers:
50-369/370 Milestone Number:
N/A Responsible Branch:
LWR No. 2 Project Manager:
R. Birkel Requested Completion Date:
N/A In their Revision 24 of the FSAR, the applicant proposed to store the Oconee spent fuel in the McGuire facility and use a special tool to handle the Oconee fuel. We have examined those portions of the FSAR for which ASB has primary review responsibilities and conclude that we need additional informatior. to complete our evaluation. The attached request for additional infomation also includes a request (item b) from SEB and AAB, which have secondary review responsibility.
\\
' 'ho} W Victor Benaroya, Chief Auxiliary Systems Branch Division of Systems Safety
Enclosure:
As stated cc:
S. Hanauer R. Mattson R. Boyd J. Glynn R. Birkel R. Hartfield D. Bunch I. Sihweil G. Chipman C. Tan D. Fischer P. Matthews Leuna 8802220075 780104 PDR ADOCK 05000369 i
P PDR
AUXILIARY SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 182 DOCKET NOS. 50-369/370 l
l 10.24 a.
Ocmonstrate that the insertion of the proposed spacer
=--
(9.1.4) in the storage rack will not block or restrict the l
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 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 McGuire fuel being stored in such loca-tions inadvertently.
d.
Discuss the adverse consequences of storitig the McGuire fuel assemblies in location which are allocated for Oconee
'8 fuels, i.e., locations where 5-1/2" spacers are attached.
s%
6
4 -
10.24 Discuss the consequences if one or more of the 5-1/2" l
l 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 spec m 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 l
Cconee spent fuel assembly.
h.
You indicate that a portion of the Oconee fuel assembly would extend above the fuel rack when stored in the McGuire facility.
Frevide the results of en analysis
- a..
indicating the expected amount of fuel damage as a l
result of dropping either a McGuire or Oconee fuel 1
bundle onto the portion of the Oconee fuel bundle extending above the fuel racks in the spent fuel.
l k
y
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