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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
1
. MCEl-0400-46 Page 1 of 19 Revision 11 McGuire Unit 1 Cycle 11 Core Operating Limits Report June 1996 l
l Duke Power Company l l l
I l l l Date Prepamd By: -
6[2N[96 6( i j Checked By: /,ou,&M.buuo bf24f 9lo u
! Checked By: Umdv/.@y 6/M/f/r l
Approved By: ,
[ M[M_ ded{ 4 l
l QA Condition I i NOTE The contents of this document have been reviewed to verify that no material herein either i directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 M1C11 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0258).
9607010266 960624
, PDR ADOCK 05000369 l P PM
MCEl-0400-46 Page 2 of 19 Revision iI McGuire 1 Cycle 11 Core Operating Limits Report REVISION LOG I
Revision Effective Date Effective Pages _ COLE Original Issue May 24,1993 N/A MIC09 Revision 1 May 27,1993 N/A M IC09, Rev.1 Revision 2 February 24,1994 N/A M1C09, Rev. 2 Revision 3 June 20,1994 N/A M IC09, Rev. 3
! Revision 4 September 13,1994 N/A MIC10 Revision 5 October 18,1994 N/A M 1C10, Rev.1 Revision 6 October 24,1994 N/A M1C10, Rev. 2 Revision 7 June 26,1995 N/A MIC10, Rev. 3 Revision 8 November 28,1995 N/A M IC10, Rev. 4 l Revision 9 December 14,1995 Pages 4-8,12,14,15,16-19 MlCll Revision 10 March 11,1996 N/A M1Cl 1, Rev.1 Revision 11 June 24,1996 Pages 1-3,9-11,13,15a M1Cl1, Rev. 2 l
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._ ._ = _ _ _ _ _ _
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. ,, MCEl-0400-46 Page 3 of 19 Revision 11 l McGuire 1 Cycle 11 Core Operating Limits Report i
INSERTION SHEET FOR REVISION 11 j
i Remove pages Insert Rev. I1 pages Pages 1-3,9-11,13 Pages 1-3,9-11,13,15a
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.. MCEl-0400-46 Page 9 of 19 Revision 11 McGuire 1 Cycle 11 Core Operating Limits Report 3.1 Tech Spec 3/4.1.2.5 - Horated Water Source - Shutdown 3.1.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 5 & 6:
Parameter Linut Boric Acid Storage System minimum contained 8,884 gallons borated water volume for LCO 3.1.2.5a 10.0% level Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum water volume 585 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 26,000 gallons borated water volume for LCO 3.1.2.5h 13.3 inches .
Refueling Water Storage Tank minimum boron 2,475 ppm I concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,475 ppm 1
.. MCEI-0400-46 ;
Page 10 of 19 '
Revision 11 McGuire 1 Cycle 11 Core Operating Limits Report 3.2 Tech Spec 3/4.1.2.6 - Horated Water Source - Operating 3.2.1 Volume and baron concentrations for the Boric Acid Storage System and the Refueling i Water Storage Tank (RWST) during modes 1,2,3, & 4:
Parameter Limit Boric Acid Storage System minimum contained 20,520 gallons borated water volume for LCO 3.1.2.6a 34.8% level Boric Acid Storage System minimum baron 7,000 ppm concentration for LCO 3.1.2.6a l
Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 91,000 gallons borated water volume for LCO 3.1.2.6b 96.4 inches Refueling Water Storage Tank minimum baron 2,475 ppm i concentration for LCO 3.1.2.6b j l
Refueling Water Storage Tank maximum boron 2,575 ppm concentration for LCO 3.5.5b l Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,475 ppm 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 lirnited 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-0400-46 Page 1I of 19 1
Revision 11 McGuire 1 Cycle 11 Core Operating Limits Report
]
(Fully Withdrawn min - 222, max - 231) 240
- (29.6%.231) , (80.0.231 j 220 , ,
/ ,. , l 200 / ,
f 1
, Bank E f 80 ,
' / (100%,161) l 160 - ,/
RM
]
' (tr/c.163)!
140 Insertion s'- e' Position 120 ,
Bank c ,f (Steps ,
/ ,
/
Withdrawn) ,
80 1 1
,s ,
/ Bank D c' ,
i 40 -j (og,47) l ,
/
20 ,'
, l (30%,0) l 0
O 10 20 30 40 50 60 70 80 90 100 (FullyInserted)
Relative Power (Percent)
Figure 2 Control Rod Bank Insertion Limits Versus Percent Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.1.3 may require rod withdrawal limits.
Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
[
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l . .. ., MCEl-040046 j Page 13 of 19 Revision i1 McGuire 1 Cycle 11 Core Operating Limits Report 3.6 Tech Spec 3/4.2.2 - Heat Flux Hot Channel Factor, FQ (X,Y,Z)
RTP l 3.6.1 Fg = 2.32 x K(BU) 3.6.2 K(Z) and K(BU) are provided in Figures 4 and 5, respectively, for MkBW fuel. I The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.2:
D 3.6.3 [F (X,Y,Z)]OP = p g (X,Y,Z) x Mg(X,Y,Z)/(UMT x MT x TILT) where:
[ g(X,Y,Z))OP = cycle dependent maximum allowable design peaking factor which ensures that the FQ(X,Y,Z) limit will be preserved for operation within the LCO limits [F (X,Y,Z)]OP. !F (X,Y,Z)JOP includes allowances for calculational and measurement uncertainties, F (X,Y,Z) = the design power distribution for FQ. F (X,Y,Z) is provided in l Table 1, Appendix A, for normal operating conditions and in {
Table 2, Appendix A for power escalation testing during initial !
startup operation.
I MQ(X,Y,Z) = the margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z)is provided in Table 1, Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operation.
UMT= Measurement Uncertainty, = 1.05.
MT= Engineering Hot Channel Factor, = 1.03.
TILT = Poaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) l _1 MAX j NOTE: [F9(X,Y,Z)]OP is the parameter identified as Fq (X,Y,Z) in DPC-NE-20l lPA.
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o . . . .
. MCEl-0400-46 Page 15a of 19 Revision iI McGuire 1 Cycle 11 Core Operating Limits Report 1.00 : -
- (46M ,1.0) 0.90 --
0.80 -~ (60,000 ,0.8233)
O.70 -- l 3
6 0.60 --
W
] 0.50 --
=
! 0.40 --
2 l 0.30 --
O.20 --
1 0.10 -- I 0.00 -- l l l l l ::
]
0 10000 20000 30000 40000 50000 60000 Hurnup (MWD /MTU)
Figure 5 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MkBW Fuel l 1
l I
