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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20134L3001997-02-10010 February 1997 Application for Amends to Licenses DPR-38,DPR-47 & DPR-55, Revising TS to Reduce Allowable RB Vol Leakage Rate Per Day Limit to Permit Relaxation of Certain Requirements for Operability of Prvs Sys ML16134A6741982-08-11011 August 1982 Application for Amend to License DPR-47,changing Tech Specs Re Reload Design Calculations for Cycle 7 ML20052F2401982-05-0303 May 1982 Application for Amend to DPR-55,changing Core Protection Safety Limits,Protective Sys Max Allowable Setpoints & Rod Position Limits.Proposed Tech Specs, Cycle 7 Reload Rept & Fee Encl ML15223A7651982-01-12012 January 1982 Application to Amend Licenses DPR-38,DPR-47 & DPR-55, Changing Tech Spec Section 3.1.2 Re Heatup,Cooldown & Inservice Test Limitations for Rcs.W/Class I & II Fees ML16148A4401981-11-13013 November 1981 Application to Amend OL Changing Tech Specs Required to Support Operation at Full Rated Power During Cycle 6.Changes Concern Core Protection Safety Limits,Protective Sys Max Allowable Setpoints & Rod Position Limits ML20010D2051981-08-19019 August 1981 Application for Amend to OL Revising Tech Specs to Extend Cycle 5 Operating Length to 390 Effective Full Power Days Allowing Continued Operation of Facility Until Scheduled Refueling Shutdown in Early Oct ML15223A7301981-05-29029 May 1981 Application for Amend of Licenses DPR-38,DPR-47 & DPR-55, Revising Tech Specs Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits.Replacement for Core Symmetry Test & Amend Fees Encl ML19320D4911980-07-16016 July 1980 Application for Amend to OL Revising Tech Spec 3.3.1.c Allowing Continued Operation of Unit 2 at Full Rated Power, While Maint Continues on HPI Pump Until 800718 ML19312B8011978-07-0505 July 1978 Proposed Amend of Condition 2 to Licenses DPR-38,DPR-47 & DRP-55,allowing Receipt & Possession of Up to Four Fuel Assemblies Irradiated in Crystal River Unit 3 1997-02-10
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML15261A4641998-09-0404 September 1998 Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Current TSs Re Electrical Distribution Sys & Incorporate New Requirements for Sys Operation, Limiting Conditions for Operation & SR ML20198S2021998-01-19019 January 1998 Application for License Amend Request for Oconee Nuclear Station Isfsi,Changing Corporate Name of Licensee from Duke Power Co to Duke Energy Corp ML20134L3001997-02-10010 February 1997 Application for Amends to Licenses DPR-38,DPR-47 & DPR-55, Revising TS to Reduce Allowable RB Vol Leakage Rate Per Day Limit to Permit Relaxation of Certain Requirements for Operability of Prvs Sys ML16134A6741982-08-11011 August 1982 Application for Amend to License DPR-47,changing Tech Specs Re Reload Design Calculations for Cycle 7 ML20052F2401982-05-0303 May 1982 Application for Amend to DPR-55,changing Core Protection Safety Limits,Protective Sys Max Allowable Setpoints & Rod Position Limits.Proposed Tech Specs, Cycle 7 Reload Rept & Fee Encl ML15223A7651982-01-12012 January 1982 Application to Amend Licenses DPR-38,DPR-47 & DPR-55, Changing Tech Spec Section 3.1.2 Re Heatup,Cooldown & Inservice Test Limitations for Rcs.W/Class I & II Fees ML16148A4401981-11-13013 November 1981 Application to Amend OL Changing Tech Specs Required to Support Operation at Full Rated Power During Cycle 6.Changes Concern Core Protection Safety Limits,Protective Sys Max Allowable Setpoints & Rod Position Limits ML20010D2051981-08-19019 August 1981 Application for Amend to OL Revising Tech Specs to Extend Cycle 5 Operating Length to 390 Effective Full Power Days Allowing Continued Operation of Facility Until Scheduled Refueling Shutdown in Early Oct ML15223A7301981-05-29029 May 1981 Application for Amend of Licenses DPR-38,DPR-47 & DPR-55, Revising Tech Specs Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits.Replacement for Core Symmetry Test & Amend Fees Encl ML19320D4911980-07-16016 July 1980 Application for Amend to OL Revising Tech Spec 3.3.1.c Allowing Continued Operation of Unit 2 at Full Rated Power, While Maint Continues on HPI Pump Until 800718 ML19312B8011978-07-0505 July 1978 Proposed Amend of Condition 2 to Licenses DPR-38,DPR-47 & DRP-55,allowing Receipt & Possession of Up to Four Fuel Assemblies Irradiated in Crystal River Unit 3 1998-09-04
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May 3, 1982 3 "- a w $
cb Mr. Harold R. Denton, Director r9 office of Nucicar Reactor Regulation 4N U. S. Nuclear Regulatory Commission # gs
'4a s hi ng t on , D. C. 20555 ,
NECElyED - \'
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Attention: Mr. J. F. Stolz, Chief ; g MAy
- g. A 1 I9325 g Operating Reactors Branch No. 4 exam y ,
/
Subject:
Geonee Nuclear Station Unit 3 Docket No. 50-287 4 vs
Dear Sir:
Pursuant to 10 CFR 50, 550.90, please find attached proposed changes to the Oconee Nuclear Station (ONS) Technical Specifications which are required to support the operation of Oconee Unit 3 at full rated power during Cycle 7.-
This proposal contains changes which concern the following:
- 1. Core Protection Safety Limits of Specification 2.1; [
- 2. Protective Fystem Maximum Aflowahle Setpoints of Specification 2.3;
- 3. Rod Position Limits of Specification 3.5.2.
Also at tached is DPC -RD-2001, Oconee Uni t 3, Cycle 7 Reload Report. This report includes a summary of Cycle 7 operating parameters and contairs the safety analyseu supporting the operation of Oconee 3 Cycle 7 core at rated power in accordance with the Terhnical Specifications provided.
Oconee Unit 3 was shut dovn to begin the refuelin; cycle after 349 EFPD which is 17 EFPD short of the Cycle 7 window as included in this report. A reanalysis is underway, but changes to this ~ubmittal are expected to be minor due to the minor difference in actual EFPD versus those assumed in this analy-sis. An amendment will be submitted by apprexinately July 31, 1982 containing the required changes. Your review of this submittal at this time is requested to ensure a timely respanse after the amendinent submittal as this refueling outage is currently in progress.
Startup testing of Oconee Unit 3, Cycle 7 will be performed in accordance with the report entitled, "Oconee Nuclear Station Generic Startup Physics Test Program", initially ap;iroved by NRC Ictter dated March 23, 1981 and as modifled by boke letter dated Mty 29, 1981.
This proposed 11cene,e amendment concerning the reload design calculations for 1
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Mr. Ilarold R. Denton, Director May 3,1982 Page 2 Oconee 3, Cycle 7 was conducted consistent with Duke Technical Report NFS-1001, "Oconee Nuclear Station Reload Design Methodology" which was reviewed and accepted by the Staff in a 1ctter dated July 29, 1981. As such, it is considered that this proposed revision to the Oconee Technical Specifications is a Class III licensing action. Therefore, pursuant to 10 CFR 170, 5170.12, please find enclosed a check in the amount of $4000.
Ver truly yours, j 1
- N
CO . / g', ,.
William O. Parker, Jr.
JFN/php Attachments cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II j 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station
Mr. liarold R. Denton, Director May 3, 1982 Page 3 WILLIAM 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, DPR-47 and DPR-55; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
7 0LL*u U- % _r - r William O. Parker, Jr., \ @ President Subscribed and sworn to before me this 3rd day of May, 1982.
i',C Notary Public C Qw h
My Commission Expires:
September 20, 1984 l
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