ML12128A170

Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18

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 PASSPORT DOCUMENT To CHIEF PROJECT BRANCH E Facility FC Department : TRANSMITTAL Address USNRC CHIEF PROJECT BRANCH E 1600 EAST LAMAR BOULEVARD ARLINGTON TX 76011-4511 Page: 1 From Address DOCCON FC-2-3 Attention: Doc Management Distribution 1llIIfllNllI N 11 City Fort Calhoun State: Postal Code:

Country UNITED STATES Email Contact Kristi Horn 402-533-6714 6714 Date/Time 04/12/2012 1 3:01 Transmittal Group Id: 041212-2 Trans No. 000135176

Title:

04-12-12 ISSUE #2 Total Items: 00001 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).

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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