|
---|
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
[Table view] |
Text
-
Duim. PowEu CoxpAxy
- l'owru Heimasu 422 SouT s Cittrucu STuncET, CitAin.orTE, N. C, coau WILLI AM O PAH M E R. J R TELtpoeONE; ARE A 704 wr Passitrat su .- e- " " '" "'
August 19, 1981 Mr. Harold R. Denton, Director ' '
Office of Nuclear Reactor Regulation ,V U. S. Nuclear Regulatory Commission Washington, D. C. 20555 )
~
Attention: Mr. J. F. Stolz, Chief , g\9 #
2 Operating Reactors Branch No. 4 8 , .4 *' O b -
Re: Oconee Nuclear Station, Unit 2 g M' ,
M Docket No. 50-270 g
\P)'s
Dear Sir:
Pursuant to 10 CFR 50, 5 50.90, please find attached a proposed amendment to the Oconee Nuclear Station Facility Operating License and revision to the Technical Specifications. This proposed change extends the Oconec Unit 2, Cycle 5 operating ler gth to 390 EFPD.
Oconee Technical Specification 3.5.2.9 requires that an evaluation be performed to verify that operationa) limit curves are valid for operation beyvnd the nominal design cycle length. This evaluation has been performed and has confirmed that the existing Oconee 2 operating limit Technical Specifications are valid. The current Oconee 2 Technical Specifications state that the operational limits are valid to 360 I 10 EFPD. This pro-posal revised the title block of each affected Specification to state that the limits are valid to 390 + 10, - 30 EFPD. As a consequence, the Cycle 6 length of Oconee 2 will have a nominal design length somewhat shorter than previously planned (N400 EFPD).
With the current burnup of Oconee 2, Cycle 5, the current Technical Specifi-cation will expire September 12, 1981, assuming a 100 percent capacity factor for the Unit. The prcposed extension would allow continued opera-tion of Unit 2 until its scheduled refueling shutdown in early October.
In order to allow continued operation of Unit 2 beyond the above date, prompt approval by the Staff is requecced.
Pursuant to 10 CFR 170, S 170.22, this amendment request is deemed to consist of one Class II license fee, in that the evaluation has been per-formed by Babcock & Wilcox, the Oconee NSSS vendor, on behalf of Duke Power Company and it is an administrative matter to revise the affected Technical Specifications. As such, please find a el ek in the amount of $1,200.
ry truly yours,
\
\
n /j, y >
b William O. Parker , Jr.
RLG/php 6 D,0 Attachments 8108240098 810819 I .n PDR ADOCK 05000270 PDR DV P
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 thereia are true and correct to the best ,f his knowledge.
/
w a . /m de, .
William O. Parker, Jr., V(ce) President Subscribed and sworn to before me this August 17, 1981 a f. ~
Notary Public My Commission Expires:
September 20, 1984 l
l l
t b