Rev 5 to MCEI-0400-46, McGuire Unit 1 Cycle 10 Colr| ML20078B478 |
| Person / Time |
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| Site: |
McGuire  |
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| Issue date: |
10/18/1994 |
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| From: |
Bortz D, Ray C
DUKE POWER CO. |
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| To: |
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| Shared Package |
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| ML20078B473 |
List: |
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| References |
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| MCEI-0400-46, MCEI-0400-46-R05, MCEI-400-46, MCEI-400-46-R5, NUDOCS 9410250274 |
| Download: ML20078B478 (6) |
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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20217F3661999-09-22022 September 1999
Rev 18 to McGuire Unit 1 Cycle 14 Colr
ML20196G0761998-11-0606 November 1998
Rev 15 to COLR Cycle 12 for McGuire Unit 2
ML20196G0581998-11-0606 November 1998
Rev 17 to COLR Cycle 13 for McGuire Unit 1
ML20249C7031998-05-27027 May 1998
Rev 16 to MCEI-0400-46, McGuire Unit 1 Cycle 13 Colr
ML20217R2711998-03-12012 March 1998
Rev 15 to McGuire Unit 1 Cycle 12 Colr
ML20217L7471997-07-0808 July 1997
Rev 14 to McGuire Unit 1 Cycle 12 COLR for July 1997
ML20137M9581997-02-13013 February 1997
Cycle 12 COLR, Feb 1997
ML20113C4881996-06-24024 June 1996
Rev 11 to McGuire Unit 1 Cycle 11 Colr
ML20101F3821996-03-12012 March 1996
Cycle 11 Colr
ML20095J3791995-12-31031 December 1995
Rev 9 to McGuire Unit 1 Cycle 11,Core Operating Limits Rept, for Dec 1995
ML20094Q5771995-11-28028 November 1995
Cycle 10 Colr
ML20086B9071995-06-26026 June 1995
Rev 3 to McGuire Unit 1 Cycle 10,Core Operating Limits Rept, June 1995
ML20076K9761994-10-25025 October 1994
Rev 2 to MCEI-0400-46, McGuire Unit 1 Cycle 10 Core Operating Limits Rept, Oct 1994
ML20078B4781994-10-18018 October 1994
Rev 5 to MCEI-0400-46, McGuire Unit 1 Cycle 10 Colr
ML20073C3431994-09-14014 September 1994
Rev 4 to MCEI-0400-46, McGuire Unit 1 Cycle 10 Colr
ML20063L6731994-02-24024 February 1994
Rev 2 to MCEI-0400-46, McGuire Unit 1 Cycle 9 Core Operating Limits Rept
ML20046A0941993-07-13013 July 1993
Cycle 9 Reload Rept.
ML20044H3391993-05-28028 May 1993
Rev 1 to MCEI-0400-46, McGuire Unit 1,Cycle 9 Colr.
ML20044G7381993-05-24024 May 1993
Cycle 9 Colr.
ML20125D2451992-12-31031 December 1992
Rev 3 to McGuire Unit 1 Cycle 8 Core Operating Limits Rept
ML20106B6991992-09-25025 September 1992
Rev 2 to McGuire Unit 1,Cycle 8,COLR
ML20141M2961992-07-31031 July 1992
Rev 1 to MCEI-0400-05, McGuire Unit 1,Cycle 8 Core Operating Limits Rept
ML20094K7471992-03-11011 March 1992
Rev 1 to McGuire Nuclear Station Unit 1 Cycle 8 Startup Rept
ML20092J5551991-11-30030 November 1991
Cycle 8 Core Operating Limits Rept
ML20086H7231991-11-27027 November 1991
End-of-Cycle 7 Refueling Outage Steam Generator Rept
ML20086A3561991-11-0707 November 1991
Rev to McGuire Unit 1,Cycle 8 Reload Rept
ML20077H0651991-06-26026 June 1991
Cycle 8 Reload Rept
ML20065M9521990-11-30030 November 1990
Rev 0 to Core Operating Limits Rept for Cycle 7
ML20237B1061987-12-11011 December 1987
Peaking Factor Limit Rept for Mcguire Unit 1 Cycle 5:RAOC & Base Load Operation
ML20204H6551986-07-31031 July 1986
Rev 1 to Reload Safety Evaluation,Mcguire Nuclear Station, Unit 1 Cycle 4
ML20113H6371984-12-31031 December 1984
Reload Safety Evaluation,Mcguire Nuclear Station Unit 1 Cycle 3
1999-09-22
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2
ML20217F3661999-09-22022 September 1999
Rev 18 to McGuire Unit 1 Cycle 14 Colr
ML20212D1911999-09-20020 September 1999
SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20216E8851999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20217G8101999-08-31031 August 1999
Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2
ML20211G5261999-08-24024 August 1999
SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20210S2371999-07-31031 July 1999
Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20216E8951999-07-31031 July 1999
Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20209H1631999-06-30030 June 1999
Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20210S2491999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209H1731999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
ML20195K3691999-05-31031 May 1999
Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206N3511999-05-11011 May 1999
Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs
ML20195K3761999-04-30030 April 1999
Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206R0891999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205L2341999-04-0505 April 1999
SFP Criticality Analysis
ML20206R0931999-03-31031 March 1999
Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205P8991999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205C4171999-03-25025 March 1999
Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed
ML20207K2051999-03-0505 March 1999
Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed
ML20204C8911999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205P9021999-02-28028 February 1999
Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20204C8961999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2
ML20199E0301998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2
ML20216F9931998-12-31031 December 1998
Piedmont Municipal Power Agency 1998 Annual Rept
ML20198A4481998-12-11011 December 1998
Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted
ML20198D7561998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2
ML20199E0491998-11-30030 November 1998
Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure
ML20199E9651998-11-24024 November 1998
Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility
ML20196D4171998-11-24024 November 1998
Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress
ML20196G0581998-11-0606 November 1998
Rev 17 to COLR Cycle 13 for McGuire Unit 1
ML20196G0761998-11-0606 November 1998
Rev 15 to COLR Cycle 12 for McGuire Unit 2
ML20198D7771998-10-31031 October 1998
Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2
ML20195E5961998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2
ML20154L6251998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2
ML20195E6021998-09-30030 September 1998
Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2
ML20154B4131998-09-22022 September 1998
Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage
ML20151W3521998-09-0808 September 1998
Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc
ML20154L6321998-08-31031 August 1998
Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1
ML20153B3741998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2
ML20236U1601998-07-31031 July 1998
Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept
ML20237B2381998-07-31031 July 1998
Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2
ML20153B3931998-07-31031 July 1998
Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2
ML20236P0451998-07-0808 July 1998
Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days
1999-09-30
[Table view] |
Text
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9 MCEl-0400-46 Page 1 of 19 Revision 5 McGuire Unit I Cycle 10 Core Operating Limits Report October 1994 I
(rev.1)
Duke Power Company Date Prepared By: Nc/ 8 ff<r/ /c/fy/vy Cheeked By: '
/SQfTI L/
Checked By: $t Xh lo //t /9+
Approved By: / 2/ ((h/v h////M QA Condition 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 MIC10 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0245).
9410250274 94101g PDR ADOCK 05000369 PDR
MCEl-0400-46 Page 2 of 19 Revision 5
\
McGuire 1 Cycle 10 Core Operating Limits Report 1
REVISION LOG Revision Effective Date Effective Paces COLR ;
Original Issue May 24,1993 Pages 6,12,13,15-153 MIC09 j Revision 1 May 27,1993 Page 9 MIC09 Revision 2 February 24,1994 Page 8 MIC09 Revision 3 June 20,1994 Pages 1-3,3A,4,5,5A,5B, M1C09 7,7A,10,11,14,14 A Revision 4 September 13,1994 Pages 5 -9,11 -18 MlC10 l
l Revision 5 October 18,1994 Pages 1 - 4,10,19 MIC10 l
l
MCEl-04C046 Page 3 of 19 Revision 5 McGuire 1 C3cle 10 Core Operating Limits Report INSERTION SIIEET Remove pages Insert. pages Pages 1- 4,10 and 19 (rev. 4) Pages 1- 4,10 and 19 (rev. 5) 4
MCEl-04GO-46 Page 4 of 19 Revision 5 McGuire 1 Cycle 10 Core Operating Limits Report 1.0 Core Oneratino Limits Renort The Core Operating Limits Report,(COLR) for McGuire Unit 1, Cycle 10 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, along with the location of the affected Technical Specification within this report.
Technical Specifications Section Page 2.2.1 - Reactor Trip System Instrumentation Setpoint 2.0 5 l 3/4.1.1.3 - Moderator Temperature Coefficient 3.0 7 3.1 9 3/4.1.2.5 - Borated Water Source - Shutdown 3/4.1.2.6 - Borated Water Source - Operating 3.2 10 3.3 10 3/4.1.3.5 - Shutdown Rod Insertion Limit 3.4 10 3/4.1.3.6 - Control Rod Insertion Limit 3.5 10 3/4.2.1 - Axial Flux Difference 3/4.2.2 - Heat Flux Hot Channel Factor 3.6 13 3/4.2.3 - Nuclear Enthalpy Rise Hot Channel Factor 3.7 16 3.8 18 3/4.5.1.1 - Accumulators 3/4.5.5 - Refueling Water Storage Tank 3.9 18 3/4.9.1 - Refueling Operations Boron Concentration 3.10 19 3/4.9.12 - Fuel Storage - Spent Fuel Storage Pool 3.11 19 l
l l
.-p -.--r .. , , ,
s MCEI4M00-46 j Page 10 of 19 Revision 5 McGuire 1 Cycle 10 Core Operating Limits Report ,
3.2 Tech Spec 3/4.1.2.6 - Horated Water Source - Operating 3.2.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4: ,
Parameter Linut t
l Boric Acid Storage System minimum contained 20,453 gallons burateu water volume for LCO 3.1.2.6a l
a c
l i Boric Acid Storage System minimum boron 7,000 ppm
{
! concentration for LCO 3.1.2.6a J Boric Acid Storage System minimum water volume 9,851 gallons ,
j' required to maintain SDM at 7,000 ppm l
Refueling 6 ater Storage Tank minimum contained 91,000 gallons l
- borated water volume for LCO 3.1.2.6b li t
j Refueling Water Storage Tank minimum boron 2,175 ppm l
concentration for LCO 3.1.2.6b i
j Refueling Water Storage Tank maximum boron 2,275 ppm l l concentration for LCO 3.5.5b l Refueling Water Storage Tank minimum water 57,107 gallons j volume required to maintain SDM at 2,175 ppm !
i
{ 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.
- j
! 3.4 Tech Spec 3/4.1.3.6 - Control Rod Insertion Limits j 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.
l 3.5 Tech Spec 3/4.2.1 - Axial Flux Difference i
i 3.5.1 The Axial Flux Difference (AFD) Limits are provided in Figure 3.
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i i 4
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MCEl-0400-46 Page 19 of 19 Revision 5 McGuire 1 Cycle 10 Core Operating Limits Report 3.10 Tech Spec 3.4.9.1 - Refueling Operations - Boron Concentration 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.
Parameter Limit Refueling boron concentration for the filled portions of the 2175 ppm Reactor Coolant System and refueling canal for LCO 3.9.1.b.
3.11 Tech Spec 3/4.9.12 - Fuel Storage - Spent Fuel Storage Pool 3.11.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuelis stored in the spent fuel pool.
Parameter Listi Spent fuel pool minimum boron concentration for LCO 2175 ppm 3.9.12.a.
Spent fuel pool minimum boron concentration for 2175 ppm surveillance 4.9.12b.
4 Note:
Data contained in Tables in the Appendix to this document were generated in the McGuire 1 Cycle 10 Maneuvering Analysis calculational file (MCC-1553.05-00-0119.) The McGuire Reactor Engineering Group will control this information via computer file (s) and should be contacted if there is a need to access this information.