Letter Sequence Other |
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Results
Other: 05000302/LER-1978-037, Forwards LER 78-037/01T-1, 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined, ML19308D758, ML19317G782, ML19317G791, ML19319D197, ML19340A474, ML19340A475, ML20062C376
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MONTHYEARML19319D9191978-08-0202 August 1978 Proposed Amend 59 to License DPR-54,revising Tech Specs Re Pressurization,Heatup & Cooldowm Limitations Per App 6 10CFR50.Class III Fee Encl Project stage: Request 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined1978-08-11011 August 1978 /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined Project stage: Other ML19308D7581978-08-14014 August 1978 Confirms 780814 Telcon Re Possible Use of Atypical Weld Filler Wire.Requests Info Re Interim Measures,Operational Safety Assessment & Commitment to Maintain Interim Measures Pending Resolution of Issue Project stage: Other ML19317G7821978-08-16016 August 1978 Amend 22 to License DPR-54,revises Tech Specs Re RCS Pressure Temp.Tech Specs Encl Project stage: Other ML19317G7761978-08-16016 August 1978 Forwards Amend 22 to License DPR-54,safety Evaluation & Notice of Issuance Project stage: Approval ML19317G7871978-08-16016 August 1978 Safety Evaluation Supporting Amend 22 to License DPR-54 Project stage: Approval ML19317G7911978-08-16016 August 1978 Notice of Issuance & Availability of Amend 22 to License DPR-54 Project stage: Other ML19340A4721978-08-18018 August 1978 Responds to NRC 780814 Request for Info Re Possibility That Atypical Weld Wire Used in Mfg of Reactor Vessel.Until Determination Is Made,Util Will Operate on Assumption That Wire Was Used & Start Corrective Action Project stage: Request ML19308D9381978-08-18018 August 1978 Forwards Response to NRC 780517 Request for Addl Info Re Movement of Heavy Loads Near Spent Fuel Project stage: Request ML19340A4741978-08-22022 August 1978 Forwards Revised Operating Curves,Tech Specs Promised in Util Re Reactor Vessel Atypical Weld Matl & Bases for Tech Specs Project stage: Other ML19340A4751978-08-22022 August 1978 Revised Tech Specs 3/4.4.9 Re Operating Curves.Curve Diagrams & Bases for Tech Specs Encl Project stage: Other ML19319D1971978-08-31031 August 1978 Notifies of 781101 Possible Completion Date for B&W Chemical Analysis of Reactor Vessel Surveillance Matl to Determine Whether Atypical Weld Matl Used.Outlines Action to Be Taken on Results Project stage: Other 05000302/LER-1978-037, Forwards LER 78-037/01T-11978-09-0101 September 1978 Forwards LER 78-037/01T-1 Project stage: Other ML19308D8331978-09-0101 September 1978 Provides Review of Revised pressure-temp Operating Limits & Finds Them Acceptable.Amend Classification Form Encl Project stage: Approval ML20062C3761978-10-31031 October 1978 Forwards Tech Spec Change Requests 27 & 34,requesting Amend to App a of License DPR-72.Changes Concern Reactor Coolant Pump Power Monitors & Revisions to Heatup,Cooldown & Inservice Leak & Hydrostatic pressure-temp Curves Project stage: Other ML19257C7951980-01-28028 January 1980 Requests Withdrawal of 781031 Tech Spec Change Request 34 & Licensing Fee,Due to NRC Approval of BAW-1566, Evaluation of Atypical Weldment. Certificate of Svc & Affidavit Encl Project stage: Withdrawal 1978-08-18
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7590-01 UNITED STATES NUCLEAR REGULATORY COPHISSION 00CXET NO.
50-312 O
SACRANENTO MUNICIPAL UTILITY DISTRICT NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE
-~
The U. S. Nuclear Regulatory Comission (the Comission) has issued Amendment No. 22 to Facility Operating License No. OPR-54 issued to Sacramento Municipal Utility District, which revised Technical Specifications for operation of the Rancho Seco Nuclear Genw"ing Station, located in Sacramento County, California.
H The i
amendment is effective as of its date of issuance.
The amendment to the Technical Specifications revises the pressure-temperature limitations appitcable to the reactor coolant systen to cover operation up to five effective full power years.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
8004010 l
7590-01 The Comission has detemined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be i
i prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the 5
application for amencrent dated August 2,1978, as revised August 11,1978,(2) Amendment Ne. 22 to License No. DPR-54, and (3) the Comission's related Safety E /aluation. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Business and Municipal Department, Sacramento City-County Library, 828 I Street, Sacramento, California. A copy of items (2) and (3) my be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D.C.
20555, Attention: Ofrector, Division of Operating -
Reactors.
Dated at Bethesda, Maryland, this 16th day of August 1978.
i FOR THE NUCLEAR REGU TORY COMISSION
(,les bN&
Robert W. Reid, Chief Operating Reactors Branch !4 Division of Operating Reactors
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