Letter Sequence Other |
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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 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 ML20093E1171984-09-24024 September 1984 Safety Evaluation Supporting Amends 35 & 16 to Licenses NPF-9 & NPF-17,respectively Project stage: Approval 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 ML20100G4881985-04-0303 April 1985 Proposed Tech Specs Re Possession & Storage of Irradiated Oconee Fuel Assemblies Containing SNM Project stage: Other 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 ML20133C2181985-07-26026 July 1985 Safety Evaluation Supporting Amends 44 & 25 to Licenses NPF-9 & NPF-17,respectively Project stage: Approval ML20133A1891985-07-26026 July 1985 Forwards Unexecuted Amend 8 to Indemnity Agreement B-83 for Signature Project stage: Other 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 ML17219A6301987-06-12012 June 1987 Proposed Tech Specs,Permitting Replacement of Spent Fuel Racks to Increase Capacity to 1,706 Spent Fuel Assemblies Project stage: Request ML13319A8041987-12-24024 December 1987 Forwards Transshipment of San Onofre Unit 1 Spent Fuel for Review & Approval,Per NRC Request at 870925 Meeting.Proposed Method for Transshipment of Spent Fuel to Units 2 & 3 Will Not Include Air Pallet Sys.Fee Paid Project stage: Meeting ML13319A8061987-12-31031 December 1987 Transshipment of San Onofre Unit 1 Spent Fuel Project stage: Other ML20196H1381988-02-0808 February 1988 Notice of Consideration of Issuance of Amends to Licenses NPF-10 & NPF-15 & Proposed NSHC Determination & Opportunity for Hearing on 871230 Request Re Possession of Byproduct & SNMs Produced by Unit 1 Project stage: Other ML20149L8001988-02-22022 February 1988 Proposed Tech Specs 3/4.7.1.1, Safety Valves, 3.0.4, 3/4.3.2, ESF Actuation Sys Instrumentation, & 3/4.4.4, Steam Generators & Surveillance Requirements 4.0.3 & 4.0.4 Project stage: Other ML17221A6341988-02-22022 February 1988 Environ Assessment & Finding of No Significant Hazard, Supporting Proposed Amend to License NPF-16,permitting Transfer of Unit 1 Spent Fuel Pool to Unit 2 Spent Fuel Pool Project stage: Other ML13303A8341988-02-26026 February 1988 Requests Addl Info Re Util 871231 Proposed Change to Licenses NPF-10 & NPF-15 to Allow Storage of Spent Fuel. Application for Amend to Licenses Must Be Received Before NRC Makes Final Determination on Issue Project stage: Other ML13303B8931988-03-0808 March 1988 Notification of Registration as User of Certificate of Compliance 9001 in Response to 880111 Request Project stage: Other ML13330B2941988-04-25025 April 1988 Forwards Transshipment of San Onofre Unit 1 Spent Fuel, .Rept Supercedes 871224 Rept Transmitted to NRC Project stage: Other ML13331B0391988-04-28028 April 1988 Application for Amend to License DPR-13,consisting of Proposed Change 181 to Amend Application 148,revising License Condition 3.C & Deleting Tech Spec 4.13, Turbine Deck Load Bearing Test & Visual Insp Project stage: Request ML13331B0371988-04-28028 April 1988 Forwards Amend Application 148,consisting of Proposed Change 181 to License DPR-13,revising License Condition 3.C & Deleting Tech Spec 4.13, Turbine Deck Load Bearing Test & Visual Insp Project stage: Request ML13331B0401988-04-28028 April 1988 Tech Spec 4.13 Requiring Performance of Turbine Deck Load Bearing Test Every 4 Yrs W/Use of Air Pallet Sys.Air Pallet Sys Will Not Be Used as Part of Proposed Method for Spent Fuel Shipment.Tech Spec Not Applicable Project stage: Other ML13330B2961988-04-30030 April 1988 Transshipment of San Onofre Unit 1 Spent Fuel Project stage: Other ML20196B7941988-06-22022 June 1988 Safety Evaluation Supporting Amends 63 & 52 to Licenses NPF-10 & NPF-15,respectively Project stage: Approval 1985-04-03
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l DISTPIBUTION:
sDocli~et:Nos:n50-369/370 m July 26, 1985 e
NRC FDR local PDR Docket Nos: 50-369 PRC System and 50-370 LB #4 r/f EAdensam DHood MDuncan Mr. H. B. Tucker, Vice President JSaltzman, OSP Nuclear Production Department Attorney, OELD Duke Power Company JPartlow 422 South Church Street EJordan Charlotte, North Carolina 28242 BGrimes ACRS (16)
Dear Mr. Tucker:
Subject:
Indemnity Agreement Amendment Two signed copies of Amendment No. 8 to Indemnity Agreement No. B-83 which covers the activities authorized under Facility Operating license NPF-9 and NPF-17 are enclosed.
Please sign both copies and return one copy to this office.
The Indemnity Agreement has been amended to incorporate changes authorized by license amendment nos. 44 and 25 issued this date.
Sincerely, Darl S.
El*
. Adensam, Chief AcensingBranchNo.4 Division of Licensing j
Enclosure:
Amendment No. 8 to Indemnity Agreement B-83 cc: See next page 3>5H 33If bl.
LA:p,( B #4 DL:LB #4 DL:lB #4 MDurfcd /hmc DHood EAdensam 7/,2(/85 7/ 4/85 7/2c/85 7
8500050370 850726 PDR ADOCK 05000369 i
PDR
'o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 7;
%.....);E WASHINGTON. D. C. 20555 Docket 50-369 50-370 AMENDMENT TO INDEMNITY AGREEMENT N0. B-83 AMENDMENT NO. 8 Effective July 26, 1985
, Indemnity Agreement No. B-83, between Duke Power Company and the Nuclear Regulatory Commission, dated February 28, 1978, as amended, is hereby further amended by modifying Article I, paragraph 9 to read as follows:
"The radioactive material means source, special nuclear and byproduct material which (1) is used, was used or will be used in, or is irradiated, was irradiated or will be irradiated b the nuclear reactors licensed under NPF-9 and NPF-17 or (2) y, was used in, or was irradiated in the nuclear reactors licensed under DPR-38, DPR-47, and DPR-55 and subsequently is transported to the site of the nuclear reactors licensed under NPF-9 and NPF-17 for the purpose of storage or (3) which is produced as a result of operation of the nuclear reactors licensed under NPF-9 and NPF-17."
FOR THE U.S. NUCLEAR REGULATORY COMMISSION f
<T y y, ',:
erome Saltzma'n, Assi ant Direc or State and License Kelations Office of State ograms Accepted
, 1985 By DUKE POWER COMPANY