ML12128A170
| ML12128A170 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 04/12/2012 |
| From: | Omaha Public Power District |
| To: | Horn K Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 000135176, TSBC-12, Rev 01 | |
| Download: ML12128A170 (3) | |
Text
T-01 To Facility Address From Address City Country Email Contact Date/Time Trans No.
Total Items:
CHIEF PROJECT BRANCH E FC Department USNRC CHIEF PROJECT BRANCH E 1600 EAST LAMAR BOULEVARD ARLINGTON TX 76011-4511 PASSPORT DOCUMENT TRANSMITTAL Page:
1 1ll IIfllNllI N1 11 DOCCON FC-2-3 Fort Calhoun UNITED STATES Kristi Horn 04/12/2012 1
000135176 00001 Attention:
Doc Management Distribution State:
Postal Code:
402-533-6714 6714 3:01 Transmittal Group Id:
Title:
04-12-12 ISSUE #2 041212-2 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy #
Media Cpys 0001 FC MANL TEC TSBC-12 ACTIVE 001 16 P
01 If a document was not received or is no longer required check the response below and return to sender.
Documents noted above not received (identify those not received).
I no longer require distribution of these documents (identify those no longer required).
Date:
Signature:
c5
OMAHA PUBLIC POWER DISTRICT TECHNICAL SPECIFICATION BASIS CHANGE INDEX TSBC No.
Page No.
Date 09-006-0 2.8 - Page 20, 28 and 29 10-06-09 09-007-0 2.0 - Page 3 11-12-09 09-008-0 3.6 - Page 6 and 7 10-15-09 09-009-0 2.15 - Page 6a 12-14-09 10-001-0 2.16-Page 1 03-18-10 10-002-0 2.0 - Pages 2 and 3 Pages 4 and 5 deleted 09-09-10 2.7 - Pages 7, and 8 - New Page 9 10-003-0 2.16 - Page 1 08-10-10 10-004-0 2.1 - Page 21 10-19-10 10-005-0 2.6 - Page 3 09-30-10 11-002-0 2.7 - Page 7 10-25-11 11-003-0 2.8 - Page 18 04-28-11 11-006-0 2.15 - Page 6 and 3.1 - Page 2 02-24-12 12-001-0 2.10 - Page 18 04-12-12 Page 2 of 2 April 12, 2012 (11:01AM)
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.10 Reactor Core (Continued) 2.10.4 Power Distribution Limits (Continued)
(5)
DNBR Margin During Power Operation Above 15% of Rated Power (a) The following limits on DNB-related parameters shall be maintained:
(i)
Cold Leg Temperature as specified in the COLR (Core Inlet Temperature)
(ii)
Pressurizer Pressure
_> 2075 psia(1)
(iii)
Reactor Coolant Flow rate
> 202,500 gpm indicated (iv)
Axial Shape Index as specified in the COLR (b) With any of the above parameters exceeding the limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce power to less than 15% of rated power within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Basis The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System or the Incore Detector Monitoring System, provides adequate monitoring of the core power distribution and is capable of verifying that the linear heat rate does not exceed its limit. The Excore Detector Monitoring System performs this function by continuously monitoring the axial shape index (ASI) with the operable quadrant symmetric excore neutron flux detectors. The axial shape index is maintained within the allowable limits of the Limiting Condition for Operation for Excore Monitoring of LHR Figure provided in the COLR. This ASI is adjusted by Specification 2.10.4(1)(c) for the allowed linear heat rate of the Allowable Peak Linear Heat Rate vs.
Burnup Figure provided in the COLR and the FRT and Core Power Limitations Figure provided in the COLR. In conjunction with the use of the excore monitoring system and in establishing the axial shape index limits, the following assumptions are made:
(1) the CEA insertion limits of Specification 2.10.2(6) and long term insertion limits of f
Specification 2.10.2(7) are satisfied, and (2) the flux peaking augmentation factors are as shown in Figure 2-8.
(1) Limit not applicable during either a thermal power ramp in excess of 5% of rated thermal power per minute or a thermal power step of greater than 10% of rated thermal power.
- SEE TDB-VIII 2.10 - Page 18 Amendment No. 32**,57,70-,
77,92,109,117,141,156, 193,196,209, 249 TSBC 12-001-0