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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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R EG ~1.IRY INF~ORM*ATION DISTr'IBUTIOSYSTEM4(RIDS) c C ES SI ON.. 'B3 3201230031f OC!, AT E 5 2O1/ 12 VT lrR.Z E0 : ESDOCKET FACIL.:50-2b9 )tovee 'Ju 1eaIr. Station:, lThit I., Duke Popoer, Co,.. 05000269 Jnii~r St to,U~ t 2,D kae Ii ~ er Co.0 00 7 50:27,0 ),-olie~ Unit 3f, D'Uke Po~ser Co.,. 0500)0287 5287, J'onae Ni1.fealr-,Staltion, PARKERP4.0. Duk e? oer Cb!,
RECIP.NAM-El -REiIlEN*r' AFF1tPPIAT ION1 DE4N T-N H.R. lffi-e oifi 4urear Reactoir Regula!tion:, Director S~rLZ J a~eratingq Reactors, Blrainch4 SUBJECT : Aootliication: toi amnrd Licenses DPRm38,DR.-4 -7 & DPR-55:,
ch an[i ng TIech Spe?- S'ec-tjon 3.1. 2 re heatuotfcoioildown: & %
irmseriice test; li iTitations fo~r RCS.fN/Cl'as I & II fees.. .' (2 DISTRIB-JTI)Ni 0),OZ A001S. COPI1ES RECEIVED: rR J..WENCUI . SIZEI:a~"
TITLE; General' f~sr'uii or' alfter Issuahce a,f, 0O',eratingULcen-se NJOTS:AOD/Dr,~ei n; 1c.D5,000269 AEOD/Or'stei ml licc, 05000270 AEOD/lrmstai ni: Icc. 050 00 287, RCIEll T CPlIES REClP 11 VM COPIE'S ID] .ITTV~IrR, ENCL 10' CO DE!N54MEI LTTR ENCLI ACTION: ORB #4: 3C 01, 113. 13, INTERNALI: ELID. 1 0 IE; 06' 2 2 lVRR/D-jF'S DEPYD8 05 I. NRR/DUf DIRl 1: 1 11: 01 NRR/DSI/RA31 1. 1.
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DUKE POWER COMPANY POWER BUILDING 422 SOUTH CHURCH STREET, CHARLOTTE, N. C. 28242 WILLIAM 0. PARKERJR.
VICE PRESIDENT TELEPHONE: AREA 704 STEAM PRODUCTION January 12, 1982373-4083 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. J. F. Stolz, Chief Operating Reactors Branch No. 4
Dear Sir:
Pursuant to 10 CFR 50, §50.90 and Oconee Technical Specification 3.1.2.7.,
please find attached a proposed amendment to the Oconee Facility Operating License and revision to the Technical Specifications which concern heatup, cooldown, and inservice test limitations for the reactor coolant systems of each Oconee unit.
Attachment 1 provides the proposed changes to the Oconee TechnicalSpecifica tions. The supporting technical .justification is provided in Attachment 2 which contains two capsule analysis reports. As noted in the proposed Bases, because of the similarity between Oconee Unit 1 and Oconee Units 2, 3, the Oconee Unit 1 operating limits have been extended through 15 EFPY based on the surveillance capsule evaluation of Oconee Units 2 and 3.
As of January 1, 1982, Oconee 1 has 5,03EFPY of service life, Oconee 2 has 4.82 EFPY, and Oconee 3 has 4.86 EFPY. NRC review and approval of these new curves is requested prior to the expiration of the current curves.
Pursuant to 10 CFR 170, §170.22 this request.is considered to consist of one Class III and two Class I license amendments.. Therefore, please find attached a check in the amount of $4,800.
Ve y truly yours, William 0. Parker, Jr. Z/E/1I RLG/php 1AD6/w AA Attachment 8201250081 820112 PDR ADOCK 05000269 P PDR S
Mr. Harold R. Denton, Director January 12, 1982 Page 2 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 is knowledge.
William 0. Parker, Jr., Vi President Subscribed and sworn to before me this 12th day of January, 1982, Notary Public My Commission Expires:
September 20, 1984