ML023250221

Core Operating Limits Report (COLR)

ML023250221
Person / Time
Site:	Oconee
Issue date:	11/13/2002
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023250221 (10)

Text

Duke R. A JONES EPower Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax November 13, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Site Docket No. 50-270 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 2, Cycle 20, Rev. 18.

Very ly yours, R Jones Site, Vice President Oconee Nuclear Site Attachment ID\

www duke-energy corn

NRC Document Control Desk November 13, 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: 11101102 OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK023050012

1) 00620 DOC MGMT DUKE FILMED MAN EC03C

2) 00813 DOC MGMT EC03C ORIGINAL Duke Power Company QACONDITION N Yes [:] No "13)ý'06358ONSREGULCOMPLIANCE ON03RC DO( ,UMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED [D] Yes

4) 06700 ONS MANUAL MASTER FILE ON03DM IFQA OR OTHER ACKNOWLEDGEMENT REQUIRED. PLEASE

5) 06937 RR ST CLAIR EC08G lit I"* Ip=I==Ill Ip=li.I

• Ip= ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO.

rEFErENCE NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P 0. Box 1006 Energy Center EXEMPTION CODE: M-5 EC03C RESP GROUP: N/E Charlotte, N.C OCONEE UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT Rec'd By -.--

FOR INFORMATION £01N4LY

___________________________________________________ 1 Page 1of 1 Date DOCUMENT NO QA COND REV #/ DATE DISTR CODE 1 2 4 5 16 7 8 9 10 il 1 12 13 114 15 TOTAL ,

+ ____________ _____________ -

ONEI-0400-051 1 018 11/01102 NOMD-27 Vl Vi Vi 4 REMARKS: DUKE K S CANADY DOCUMENT RELEASE EXEMPT FROM (NUCLEAR) MODIFICATION PROGRAM MANAGER NUCLEAR ENGINEERING BY:

J W SIMMONS JWS/AYB ECO8H

ONEI-0400-51 Rev 18 Page 1 of 32 Duke Power Company Oconee 2 Cycle 20

' Core 0 erating Limits Report FOR INFORATIeN ONrY QA Condition I NGrt iXuvte.. . . .,..,J-Yt'U l I LIV d

LIFd.i 3.I RM EWMDANDAPROMWBy 'MM) REMMANDAPPR01YAM, J Prepared By: L. D. McClain !a/ t;" V Date :go d 2 Checked By: D. W. arsOVk Date: 04zsp.' V CDR By: M. E. Henshaw g Date: O: 'oi'L Approved By: R. R. St. Clair 2?11ýv zlzaLý Date :

ONEI-0400-51 Rev 18 iyý C-Iftl/ ;.i Page 2 of 32

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Core Operating Limits Report . No.CO CM .,7E1" Insertion Sheet for Revision 18 This revision is not valid until the end of operation for Oconee 2 Cycle 19.

Remove these revision 17 pages Insert these revision 18 pages 1-3, 14,16, 24,30 1-3, 14,16, 24, 30 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 2 Cycle 20 revisions below 18 Oct 2002 1-3,14,16,24,30 - - 32 17 Oct 2002 1-31 32 - 32 lOconee 2 Cycle 19 revisions below I 16 May 2001 1-31 - 31 Oconee 2 Cycle 18 revisions below 15 Apr2001 1-4 - 31 14 Feb 2000 1-4 31 13 Nov 1999 1-31 31 12 Sep 1999 1-31 - 31 11 Apr 1999 1-4,6 - 31 10 Mar 1999 1-31 - 31

ONEI-0400-51 Rev 18 Page 3 of 32 Oconee 2 Cycle 20 1.0 Error Adjusted Core bperating Limits The Core Operating Umits Report for 02C20 has been prepared in accordance with the requirements of ITS 5.6 5. The core operating limits within this report have been developed using NRC approved methodology identified in references I through 10. The RPS protective limits and maximum allowable setpoints are documented in references 11 through 13. These limits are validated for use in 02C20 by references 14 through 16. The 02C20 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10 OF provided 4 RCPs are in operation and Tavg does not decrease below 569 °F.

The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C20 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 /SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November 23, 1992.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A, Revision 1, SER dated October 1, 1985.

3 Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 5, SER dated December 8, 2000.

4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, Revision 1, SER dated June 23. 2000.

5 Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8,1999.

6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, SER dated April 3,1995

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 1, SER dated May 25, 1999.

8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 2, SER dated October 14, 1998.

9. BAW-10192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.

10 BAW-10227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, SER dated February 4, 2000.

11. Variable Low Pressure Safety Limit, OSC-4048, Revision 3, July 1998.

12. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 1, November 1998.

13. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 0, Duke Power Co., April 2001.

14. 02C20 Maneuvering Analysis, OSC-8082, Revision 2, October 2002.

15. 02C20 Specific DNB Analysis, OSC-8103, Revision 0, May 2002.

16. 02C20 Reload Safety Evaluation, OSC-8182, Revision 0, September 2002.

ONEI-0400-51 Rev 18 Page 14 of 32 Oconee 2 Cycle 20 O'perational Rod Index Setpoints RI Insertion Setpoint RI Withdrawal

%FP No Inop Rod 1 Inop Rod Setpoint 4 Pumps 102.0 263.5 286.5 300 100.0 261.5 284.5 300 90.0 251.5 274.3 300 80.0 246.5 264.1 300 50.0 201.5 233.5 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 237.5 285.2 300 75.0 234.8 281.5 300 50.0 201.5 235.2 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300

Oconee 2 Cycle 20 ONEI-0400-51 Rev 18 Page 16 of 32 Rod Index Setpoints 4 Pump Operation, No Inoperable Rods, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint

%FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 102 100 99.8 24.8 100 100 63.5 101 100 99.0 24.0 100 100 62.5 100 100 98.2 23.2 100 100 61.5 99 100 97.5 22.5 100 100 60.5 98 100 96.7 21.7 100 100 59.5 97 100 95.9 20.9 100 100 58.5 96 100 95.2 20.2 100 100 57.5 95 100 94.4 19.4 100 100 56.5 94 100 93.6 18.6 100 100 55.5 93 100 92.9 17.9 100 100 54.5 92 100 92.1 17.1 100 100 53.5 91 100 91.3 16.3 100 100 52.5 90 100 90.6 15.6 100 100 51.5 89 100 89.8 14.8 100 100 51.0 88 100 89.0 14.0 100 100 50.5 87 100 88.2 13.2 100 100 50.0 86 100 87.5 12.5 100 100 49.5 85 100 86.7 11.7 100 100 49.0 84 100 85.9 10.9 100 100 48.5 83 100 85.2 10.2 100 100 48.0 82 100 84.4 9.4 100 100 47.5 81 100 83.6 8.6 100 100 47.0 80 100 82.9 7.9 100 100 46.5 79 100 -- 82.1 7.1 100 100 45.0 78 100 81.3 6.3 100 100 43.5 77 100 80.6 5.6 100 100 42.0 76 100 79.8 4.8 100 100 40.5 75 100 79.0 4.0 100 100 39.0 74 100 78.2 3.2 100 100 37.5 73 100 77.5 2.5 100 100 36.0 72 100 76.7 1.7 100 100 34.5 71 100 75.9 0.9 100 100 33.0 70 100 75.2 02 100 100 31.5 69.8 100 75.0 0 100 100 31.2 69 100 73.8 0 100 100 30.0 68 100 72.3 0 100 100 28.5 67 100 70.7 0 100 100 27.0 66 100 69.2 0 100 100.0 25.5 65.7 100 68.7 0 100 100.0 25.0 65 100 67.7 0 100 99.5 24.5 64 100 66.1 0 100 98.8 23.8 63 100 64.6 0 100 98.0 23.0 62 100 63.0 0 100 97.2 22.2 61 100 61.5 0 100 96.5 21.5 60 100 60.0 0 100 95.8 20.8 59 100 58.4 0 100 95.0 20.0 58 100 56.9 0 100 94.2 19.2 57 100 " 55.3 0 100 93.5 18.5 56 100 53.8 0 100 92.8 17.8 55 100 52.3 0 100 92.0 17.0 54 100 50.7 0 100 91.2 16.2 53 100 49.2 0 100 90.5 15.5 52 100 47.7 0 100 89.8 14.8 51 100 46.1 0 100 89.0 14.0 50 100 44.6 0 100 88.2 13.2

%FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels. Continued on next page.

ONEI-040OG .ev 18 Page 24 of 32 105 .....

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...... .1.11...105

=*,*: Control Rod Position Setpoints 100 100 No Inoperable Rods, 4 Pump Flow Restricted 95 Operation 90 85 85 80 80 75 75 Unacceptable 70 70i 70 ...... iiiiiiiOperation 65 60 U

55 55 Acceptable 50 0~

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75 85 95 ##0'a 10 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 I Group I I Group 7I Control Rod Position, % WD

ONEI-0400-51 Rev 18 Page 30 of 32 Oconee 2 Cycle 20 Rod Index Limits Referred to by ITS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal

%FP Insertion Limit No inop Rod 1 Inop Rod Limit 4 Pumps 102 262 220 283 300 100 260 300 90 250 300 80 245 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300 3 Pumps 77 236 220 280 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300