ML021570003

Submittal of Core Operating Limits Report for Oconee Nuclear Site

ML021570003
Person / Time
Site:	Oconee
Issue date:	05/22/2002
From:	Mccollum W Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021570003 (6)

Text

P E Energy Duke Duke Energy Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672 (864) 885-3107 OFFICE W R. McCollum, Jr.

(864) 885-3564 FAX Vice President May 22, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Site Docket No. 50-269 Core Operating Limits Report (COLR)

Gentlemen:

Attached, pursuant to Oconee Technical Specifications 5.6.5, is an information copy of a revision to the Core Operating Limits Report for Oconee Unit 1, Cycle 21, Rev. 18.

Very truly yours, W. R. McCollum, Site Vice President Oconee Nuclear Site Attachment AuCI)

NRC Document Control Desk May 22, 2002 Page 2 xc w/att: Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site

DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 04/23/02 OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK021130046

1) 00813 DOC MGMT EC03C ORIGINAL

2) 06358 ONS REGUL COMPLIANCE ON03RC Duke Power Company QA CONDITION E Yes [ No

3) 06700 ONS MANUAL MASTER FILE ON03DM OTHER ACKNOWLEDGEMENT REQUIRED - Yes DOCUMENT TRANSMITTAL FORM IFQA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P.O. Box 1006 Energy Center EXEMPTION CODE: M-5 EC03C RESP GROUP: N/E Charlotte, N.C OCONEE 1 CYCLE 21 CORE OPERATING LIMITS REPORT Rec'd By Page 1 of 1 Date

• I r--; r-t-----'-T 1-rrT1 r Itl I QA CONC REV #/ DATE DISTR CODE 1 2 3 4 15 6 7 8 9 10 Ill 1 12 113 114 115 TOTAL DOCUMENT NO DOUMNNO - -I~1 FI- -

ONEI-0400-050 1 018 04/23/02 1NOMD-27 X V1 vi z/

FOR IOFORN ATION OIkY

_____________________________________________ - ________ +/- .1_______________ ____ .t ____ J.____ 4 ____ 4..L....L ____ -

REMARKS: DUKE K S CANADY DOCUMENT RELEASE EXEMPT FROM (NUCLEAR) MODIFICATION PROGRAM MANAGER NUCLEAR ENGINEERING BY:

JW SIMMONS JWS/AYB EC08H S-6

ONEI-0400-50 Rev 18 Page 1 of 32 Duke Power Company Oconee I Cycle 21 FOR INFORMATION ONLY Core Operating Limits Report QA Condition I A . . - ama.. n n o,r : ._._t Ina'-

F .-.

nWWWVMMffCWU3 Prepared By: J. D. Forster .iL/ C) 1 4 Date: 2r* AOL-m(ý Checked By: L. D. McClain -A a Date: -2 i*or ,9C.

CDR By: R. Q. Huynh Date: T / 7 Approved By: R. R. St. Clair Date:

ONEI-0400-50 Rev 18 Page 2 of 32 Oconee 1 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 18 This revision is not valid until the end of operation for Oconee I Cycle 20.

Remove these revision 17 pages Insert these revision 18 pages 1, 2 and 4 1, 2 and 4 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 1 Cycle 21 revisions below 18 Apr-02 1, 2, 4 - 32 17 Mar-02 1-31 32 - 32 Oconee 1 Cycle 20 revisions below 16 May-01 1-4 - - 31 15 Nov-00 1-31 - - 31 Oconee 1 Cycle 19 revisions below 14 Oct-00 1,2,3,5 - - 31 13 Feb-00 1,2,3,4 - - 31 12 Jul-99 1,2,3,8, - - 31 10, 13, 31 11 May-99 1-31 - - 31 Oconee 1 Cycle 18 revisions below 10 Mar-99 1 -31 - 32-38 31 9 Feb-98 1,2,3,5,13, - - 38 16,17,32,36 8 Nov-97 1,2,3,5,10, 37 - 38 32 7 Aug-97 1-38 - 38

ONEI-0400-50 Rev 18 Page 4 of 32 Oconee I Cycle 21 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.

Referred to by ITS 3.5.4.

Spent fuel pool boron concentration shall be greater than 2220 ppm and less than 3000 ppm.

Referred to by ITS 3.7.12.

The equivalent of at least 1100 cubic feet of 11,000 ppm boron shall be maintained in the CBAST.

Referred to by ITS SLC 16.5.13.

CFT boron concentration shall be greater than 1835 ppm. The average boron concentration in the CFT's shall be less than 4000 ppm. Referred to by ITS 3.5.1.

RCS and Refueling canal boron concentration shall be greater than 2220 ppm.

Referred to by ITS 3.9.1.

Shutdown Margin (SDM) shall be greater than 1% Ak/k.

Referred to by ITS 3.1.1.

Moderator Temperature Coefficient (MTC) shall be less than: MTC x 10-4 Linear interpolation is valid within the table provided. Ap / 'F  % FP Referred to by ITS 3.1.3. +0.70 0

+0.40 15 0.00 80

-0.125 100

-0.25 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by ITS 3.4.1. 4 RCP: measured hot leg pressure > 2125 psig 3 RCP: measured hot leg pressure > 2125 psig DNB parameter for RCS loop average temperature shall be: Max Loop Tavg (Incl 2°F unc)

Referred to by ITS 3.4.1. ATc, °F 4 RCP Op 3 RCP Op 0 581.0 581.0 The measured Tavg must be less than COLR limits minus 1 581.4 581.2 instrument uncertainty. ATc is the setpoint value selected by 2 581.8 581.4 the operators. Values are expanded by linear interpolation on 3 582.1 581.7 page 32 of this document without instrument uncertainty. 4 582.5 581.9 5 582.9 582.1

• This limit is applied to the loop with the lowest loop average temperature consistent with the NOTE in SR 3.4.1.2. All other temperature limits apply to the maximum loop Tavg.

DNB parameter for RCS loop total flow shall be: 4 RCP: Measured > 108.5 %df Referred to by ITS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.

Referred to by ITS 3.2.1.

Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.

Referred to by ITS 3.2.1.