Letter Sequence Other |
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Results
Other: 05000344/LER-1980-006, Forwards LER 80-006/01T-0, 05000344/LER-1980-006-01, /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap, ML19309C391, ML19323C628, ML19323C633, ML19341A169, ML19341A172, ML19341A175, ML19345F215, ML19345F217, ML19347F033, ML19347F037, ML20003D352, ML20005A518
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MONTHYEARML19309C3911980-04-0404 April 1980 Provides Schedule for 800426-0505 Fuel Insps During Cycle 2 Refueling Outage.Insps Will Be Performed by Westinghouse & Util in Spent Fuel Pool Area.Preliminary Oral Rept Will Be Made Prior to Return to Operation Project stage: Other 05000344/LER-1980-006-01, /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap1980-05-0808 May 1980 /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap Project stage: Other 05000344/LER-1980-006, Forwards LER 80-006/01T-01980-05-0808 May 1980 Forwards LER 80-006/01T-0 Project stage: Other ML19323C6281980-05-12012 May 1980 Forwards License Change Application 61 Requesting Amend to License NPF-1 Project stage: Other ML19323C6331980-05-12012 May 1980 License Change Application 61 Requesting Amend to License NPF-1,adding License Condition Re Fuel Assemblies.Waives Requirement That Each Fuel Assembly Contain 264 Fuel Rods. Outer Zircaloy-4 Clad Fuel Rods May Be Replaced Project stage: Other ML19320C1701980-06-27027 June 1980 Forwards Amend 45 to License NPF-1,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19341A1751981-01-0707 January 1981 Requests That Util Startup & Power Escalation Testing Rept Be Withheld from Public Disclosure Per 10CFR2.790.Original Affidavit AW-76-31 Encl Project stage: Other ML19341A1691981-01-13013 January 1981 Forwards Proprietary & Nonproprietary Versions of Improved Bol,Hzp,Power Distribution Prediction, Per 801118 Request. Requests Withholding (Ref 10CFR2.790) Project stage: Other ML19341A1721981-01-13013 January 1981 Nonproprietary Version of Improved Bol,Hzp Power Distribution Prediction Project stage: Other ML19345F2151981-02-0505 February 1981 Forwards License Change Application 70,amending License NPF-1 to Waive Requirement Re Fuel Assembly Rods.Fuel Assemblies in Core Contain Three Stainless Steel Dummy Fuel Rods.W/Class III Amend Fee & Certificate of Svc Project stage: Other ML19345F2171981-02-0505 February 1981 License Change Application 70,amending License NPF-1 to Waive Tech Spec 5.3.1 Requirement Re Fuel Assembly Rods.Fuel Assemblies in Core Contain Three Stainless Steel Dummy Fuel Rods.Westinghouse Evaluation Encl Project stage: Other ML20003D3521981-03-20020 March 1981 Responds to NRC 810310 Telcon Requesting Addl Info Re License Change Application 70.Updated Table 2 Reflecting Final Cycle 4 Design Encl.Prompt Approval Requested to Avoid Impacting Spring Refueling Outage Project stage: Other ML19347F0331981-05-0808 May 1981 Amend 60 to License NPF-1,approving Use of Two Modified Fuel Assemblies Containing Three Stainless Steel Rods for Fuel Cycle 4 & One Subsequent Fuel Cycle Project stage: Other ML19347F0371981-05-0808 May 1981 Notice of Issuance & Availability of Amend 60 to License NPF-1 Project stage: Other ML19347F0361981-05-0808 May 1981 Safety Evaluation Supporting Amend 60 to License NPF-1 Project stage: Approval ML19347F0311981-05-0808 May 1981 Forwards Amend 60 to License NPF-1,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML20005A5181981-06-25025 June 1981 Forwards Preliminary Results of Insp of Fuel Assemblies Subj to cross-flow Baffle Jetting Per Paragraph 2.C(11) of License NPF-1 & FSAR Project stage: Other 1981-01-13
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V 7590-01 UNITED STATES NUCLEAR REGULATORY COMM SSION DOCKET NO. 50-344 PORTLAND GENERAL ELECTRIC COMPANY, ET AL.
NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 60 to Facilit/ Operating License No. NPF-1, issued to Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee), which revised the license for operation of Trojan Nuclear Plant (the facility) located in Columbia County, Oregon. The amendment is effective as of the date of issuance.
The amendment approves the use of two modified fuel assemblies containing three stainless steel rods for fuel cycle 4 and one
~
subsequent fuel cycle.
The application for the amendment complies with the standards and requirements of tne Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, wh1
'e set forth in the license amendment. Prior public notice of this amendment was not required since this amendment does not involve a significant hazards consideration.
l 8105150l05
7590-01
. The Commission has determined 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 fmpact statement or negative declaration and environmental impact appraisal need not se prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application for amendment dated February 5,1981, as supplemented March 20,1981,(2) Amendment No. 60 to Licar.se No. NPF-1 and (3) the Commission's related~ Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the local public document room located at the Multnomah County Library, Social Science and Science Department, 801 S.W.10th Avenue, Portland, Oregon 9'/205. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 8th day of May,1981.
FOR THE NUCLEAR REGULATORY COMMISSION (w[
h Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
__.