ML20078B504

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Rev 2 to MCEI-0400-47, McGuire Unit 2 Cycle 9 Colr
ML20078B504
Person / Time
Site: Mcguire
Issue date: 10/18/1994
From: Bortz D, Clark R
DUKE POWER CO.
To:
Shared Package
ML20078B501 List:
References
MCEI-0400-47, MCEI-0400-47-R02, MCEI-400-47, MCEI-400-47-R2, NUDOCS 9410250294
Download: ML20078B504 (7)


Text

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DOCUMENT CONTROL NO. MCEI 0400 47 REVISION NO. (HM)2 PAGE NO. 1 OF 153 l

l TITLE MCGUIRE UNIT 2 CYCLE 9 CORE OPERATING LIMITS REPORT SIGNOFF DATE PREPARED BY #])&JJ f Me f a f f y/g <f i

CHECKED BY ) /80C[7f L/

APPROVED BY [ %/ 1 /u f o /ggy 1

9410250294 941019 PDR ADDCK 05000370 P PDR

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MCEl-0400-47 Page 2 0f 153 Revision 2 McGuire Nuclear Station COLR McGuire Unit 2 Cycle 9 Core Operating Limits Report October 1994 Revision 2 Duke Power Company l

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1 NOTE The contents of this document have been reviewed to verify that no material herein either directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 M2C9 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0210)

. MCEI-0400-47 Page 3 of 153 l

Revision 2 l

l McGuire 2 Cycle 9 Core Operating Lirnits Report i

I REVISION LOG l

Revision Effective Date Effective Paces OriginalIssue August 25,1993 Pages 6, 8, 9,12,13,15-153 Revision 1 June 20,1994 Pages 5,5A,58, 7,10,11,14,14 A Revision 2 October 18,1994 Pages 1-3,3A,4,7A,14B l

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MCEl-0$CD47 Page 3 A of 153 Revision 2 McGuire 2 Cycle 9 Core Operating Limits Report INSERTION SHEET FOR REVISION 2 Remove pages Insert Rev. 2 pages Pages 1-3,3A,4,7A Pages 1-3,3A,4,7A,14B

. MCEl-04CD-47 ,

Page 4 of 153 Revision 2 McGuire 2 Cycle 9 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report, (COLR), for McGuire, Unit 2, Cycle 9 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

The Technical Specifications affected by this report are listed below:

2.2.1 Reactor Trip System Instrumentation Setpoints 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.2.5 Borated Water Source - Shutdown 3/4.1.2.6 Borated Water Source - Operating 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limit 3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4.5.1.1 Accumulators 3/4.5.5 Refueling Water Storage Tank 3/4.9.1 Refueling Operations - Boron Concentrations 3/4.9.12 Fuel Storage - Spent Fuel Storage Pool I

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Page 7A of 153 l

Revision 2 i

l McGuire 2 Cycle 9 Core Operating Limits Report

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3.2 Tech Spec 3/4.1.2.6 - Horated Water Source - Operating 3.2.1 Volume and boron concentrations for the Horic Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4:

Parameter Limit Boric Acid Storage System minimum contained 20,453 gallons l

borated water volume for LCO 3.1.2.6a Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 372,100 gallons borated water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank maximum boron 2,275 ppm concentration for LCO 3.5.5b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,175 ppm 4

3.3 Tech Spec 3/4.1.3.5 - Shutdown Rod Insertion Limit 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.

3.4 Tech Spec 3/4.1.3.6 - Control Rod Insertion Limits 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.

3.5 Tech Spec 3/4.2.1 - Axial Flux Difference 3.5.1 The Axial Flux Difference (AFD) Limits are provided in Figure 3.

MCEl-0400-47 Page 14B of 153 Revision 2 McGuire 2 Cycle 9 Core Operating Limits Report 3.10 Refueling Operations - Boron Concentration (Specification 3/4.9.1) 3.10.1 Minimum boron concentrations for the filled portions of the Reactor Coolant System and refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.

i Parameter Linnt Refueling boron concentration for the filled portions of the 2175 ppm Reactor Coolant System and refueling canal for LCO l 3.9.1.b.

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3.11 Fuel Storage - Spent Fuel Storage' Pool (Specification 3/4.9.12) ,

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i l 3.11.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel is stored in the spent fuel pool.

Parameter Limit i

Spent fuel pool minimum boron concentration for LCO 2175 ppm '

l 3.9.12.a.

t l Spent fuel pool minimum boron concentration for 2175 ppm surveillance 4.9.12b.

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