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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARM990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20203D6651997-12-0909 December 1997 Rev 2 to 970044, Operating Limits Rept (Olr) for Braidwood Unit 1 Cycle 7 ML20203D7531997-12-0909 December 1997 Rev 2 to Ndit 970160, Operating Limits Rept (Olr) for Braidwood Unit 2,Cycle 7 ML20203D7721997-12-0909 December 1997 Rev 3 to Ndit 970160, Operating Limits Rept (Olr) for Braidwood Unit 2,Cycle 7 ML20212G7161997-10-13013 October 1997 Rev 1 of Ndit 970160, Braidwood Unit 2 Cycle 7 Operating Limits Rept ML20140H1451997-04-22022 April 1997 Rev 1 to Ndit 97044, Braidwood Unit 1 Cycle 7 Operating Limits Rept ML20140H1501997-04-22022 April 1997 Rev 1 to Ndit 960028, Braidwood Unit 2 Cycle Operating Limits Rept ML20108D8671996-03-11011 March 1996 Unit Cycle 6 Operating Limits Rept ML20094H0061995-11-0808 November 1995 Cycle 6 Operating Limits Rept ML20091L0261995-08-25025 August 1995 Rev 1 to Braidwood Unit 2 Cycle 5 Operating Limits Rept ML20091L0791995-08-25025 August 1995 Rev 2 to Braidwood Unit 1 Cycle 5A Operating Limits Rept ML20080U5111995-03-0909 March 1995 Rev 1 of Braidwood Unit 1,Cycle 5A Operating Limit Rept - Fxy Portion ML20078G8631994-11-0808 November 1994 BW2C5 Core Operating Limits Rept ML20029E4691994-05-0606 May 1994 Cycle 5 Colr. ML20116F2801992-11-0505 November 1992 Cycle 4 Core Operating Limits Rept ML20086E2071991-11-21021 November 1991 Core Operating Limits Rept for Cycle 3 1999-07-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
[Table view] |
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{{#Wiki_filter:__ . _ _ - _ _. _ .. _ . _ . _ _ . - . . _ _ . __,__m_ __
t NUCLEAR FUELSERVICES DEPARTMENT NUCIIAR DESIGN INFORMATION 11tANSMTITAL Originating Organization NDTT No. 960028 S SAFETY RELATED ,
E NuclearFuelServices Rev. No. I O NON. SAFETY RELATED 0 Other(specify) Page 1 of 9 O REGULATORY RELATED I
Station Hraidwood Unit 2 Cycle 6 _ Generic i
To: James R. Meister, Braidwood Site Engineering Manager Subiect Braidwood Unit 2 Cycle 6 Operatine LJmits Report
-r,ev Preparer
- s. A /
Pwimrer's Signature al2,1n Dite '/
J Nmsen ___r' Reuewer si Date j D Redden p' NFS Supemsor 1@S Supervisor's Signatuie Date i
Status of informanon: E Venfied O Unvenfied O EngmeeringJudgement ,
Meinod and Schedule of Venfication for Unverified i NDi f- l Dewnptmn ut Information: Attached is the Braidwood Umt 2. Cycle 6 Operaung 12mits Report (OLR).
Purnv of informanon:This Revision e ua A Revtston 0. Reymon I incorporates changes due to Techmcal Specificanon Amendment '
78 tirmd anod Stauon is requested to perform an On-Site ReYiew (OSR) of this document. Upon completion of the OSR. Braidwood Station is to irr.n mii the OLR porton to the Nuclear Regulatory Commission pursuant to Technical Specificauon 6.9.1.9. Please provide NFS (Jeff Guna i w iih a copy of Braidwood Station's completed OSR ad OLR submittal to the NRC. ;
Source or informauon: PWR Nuclear Design.
Suppemental Distnbunon: M. Lesmak L Kepicy / O. Gosbec/D. Lawson P. Boyle E. Young /M. Kim H. S. Kim/J. Dunlap Braidwood Central File l
9705120351 970501 PDR ADOCK 05000456 P PDR
NDIT 960028 Rev.1
- Page 2 of 9 4 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 6 i
l 1.0 OPERATING LIMITS REPORT I
This Operating Limits Report (OLR) for Braidwood Station Unit 2 Cycle 6 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:
3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit i 3/4.1.3.6 Control Rod Insertion Limits 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 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.1.9.
2.1 Moderator Temoerature Coefficient (Specification 3/4.1.1.3)
I 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
- a. The BOL/ARO/HZP-MTC baall be less positive than +4.0 x 10 Ak/k/ F.
- b. The EOUARO/RTP-MTC shall be less negative than -4.1 x 10" Ak/kFF.
2.1.2 The EOUARO/RTP-MTC Surveillance limit is:
d The 300 ppm /ARO/RTP-MTC should be less negative than or equal to -3.2 x 10 Ak/krF.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER
. . - - . - - - - . - . _ _ - - _ _ . . . . _ _ - . . . . . . -~ . - _ .
.' NDIT 960028 Rev.1
. . Page 3 of 9 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 6 j i
l 2.2 Shutdown Rod insertion Limit (Specification 3/4.1.3.5) 2.2.1 All shutdown banks shall be withdrawn to at least 231 steps.
2.3 Control Rod Insertion Limits (Specification 3/4.1.3.6) ;
i 2.3.1 The control banks shall be limited in physicalinsertion as shown in Figure 1.
2.4 Axial Flux Difference (Specification 3/4.2.1) !
2.4.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +3,-12% of the target flux l difference. 1 2.4.2 The AFD Acceptable Operation Limits are provided in Figure 2. !
2.5 Heat Flux Hot Channel Factor (Specification 3/4.2.2) l 1
2.5.1 Fo(Z) s(FEP/P)[K(Z)) for P > 0.5 i Fo(Z) s (Fo /0.5][K(Z)] for P s 0.5 l
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FE" = 2.50 K(Z) is provided in Figure 3.
I 2.5.2 F'y
, = F"[(1 + 0.2(1 - P)] j F"[ limits within specified core planes shall be:
- a. For the lower core region from greater than or equal to 0% to less than or equal to 50%:
- 1) F"[ s 2.803 for all core planes containing bank "D" control rods j
- 2) F7P s 1.729 for all unrodded Core planes
- b. For the upper core region from greater than 50% to less than or equal to 100%:
- 1) F"[ s 2.103 for all core planes containing bank "D" control rods
- 2) F@" 51.810 for all unrodded core planes 2.5.3 A plot of (Fo(z)
- Pu] vs Axial Core Height is provided in Figure 4 and Table 1 contains the data plotted in Figure 4.
__. ._ ..._.m._ _ _ _ _ _ . _ . . _. ._ _ . . _ _ _ . . . - _ _ . _ _ . _ _ _ -
NDIT 960028 Rev.1
*
- Page 4 of 9 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 6 2.6 Nuclear Enthalov Rise Hot Channel Factor (Specification 3/4.2.3)
F5 s F"d[1.0 + PFm(1.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F8 = 1.65 PF, = 0.3
. . bbow 960028 ~1
~
Rev.1 .
Page 5 of 9 l OPERATINO LIMITS REPORT (OIR) for BRAIDWOOD UNIT 2 CYCLE 6 1
Figure 1- l Control Bank Insertion Limits Versus Percent Rated Thermal Power (29%,228) ' (79 %,228)
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OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 6 1- l a i FIGURE 2: Axial Flux Difference Limits As A Function of Rated Thermal Power i
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. Page 9 of 9 'l 4
OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 6 Table 1: [Fdz)
- Pu] vs. Axial Co.e Height Fq SPIL Core Height Max Fq x P UMIT
- J ..
i
,f y
1.8778 2.4999 2.5000
- 2.1282 2.2956 2.5000 2.3786 2.3666 2.5000
- 2.6289 2.3276 2.5000
- 2.8793 2.3561 2.5000 ,
2.5000 l
' 3.1297 2.3792 3.3801 2.3948 2.5000 3.6305 2.4087 2.5000 3.8808 2.2272 2.5000 4.1312 2.4099 2.5000 i
- 4.3816 2.4126 2.5000 4.6320 2.4044 2.5000 4.8823 2.3915 2.5000 l
l 5.1327 2.3743 2.5000 5.3831 2.3905 2.5000 5.6335 2.2404 2.f000 l 5.8838 2.4268 2.5000 6.1342 2.4648 2.4957 ,
2.4878 2.4878 l 6.3846 6.6350 2.4582 2.4799 l l 2.4457 2.4720 1 6.8853 2.4196 2.4640 l
- 7.1357 7.3861 2.3648 2.4561 2 7.6365 2.4273 2.4482 7.8868 2.4195 2.4402 8.1372 2.4039 2.4323
' 8.3876 2.3792 2.4244 8.6380 2.3479 2.4165 8.8883 2.3011 2.4085 9.1387 2.2127 2.4006 9.3891 2.3076 2.3927 i 2.3847
! 9.6395 2.3110 i 9.8899 2.3407 2.3768 10.1400 2.3681 2.3689 i t..u:
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Unshaded area shows surveillance region.
Shaded area (top and bouom 15%)is ignored.
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