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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20199J6751997-11-20020 November 1997 Rev 1 to Vogtle Unit 1 Boral Replacement Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20216D3061997-09-0404 September 1997 Mod Rept for Increased SFP Storage Capacity ML20217H9241997-08-0808 August 1997 Spent Fuel Pool Boron Dilution Assessment ML20128H0281996-10-0404 October 1996 Applicability of WCAP-14181 PRA Results to Vogtle ML20097B9451996-01-31031 January 1996 GL 89-10 Close-Out Submittal Vol 1 Program Summary Rept ML20097B9531996-01-31031 January 1996 GL 89-10 Close-Out Submittal Vol 2 Design-Basis Capability Verification Rept ML20100B9171996-01-23023 January 1996 Unit 1 Pressure & Temp Limits Rept ML20100B9341996-01-23023 January 1996 Rev 0 to Vogtle Electric Generating Plant - Unit 2 Pressure & Temp Limits Rept ML20094D4651995-11-0101 November 1995 IPEEE, Vols 1 & 2 ML20087C3031995-08-0303 August 1995 Rev 0 to VEGP Unit 1 Presure & Temperature Limits Rept ML20078A1351995-01-13013 January 1995 Plant Vogtle Training Simulator 4-Yr Certification Update ML20058J0101993-09-30030 September 1993 Nonproprietary Probability of Missile Generation in GE Nuclear Turbines Suppl Rept:Steam Valve Surveillance Test Interval Extension ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20082T3551991-01-31031 January 1991 Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Aw Vogtle Nuclear Plant Units 1 & 2 ML20028H7341991-01-17017 January 1991 Simulator Certification Rept 1991. ML20059C3251990-08-20020 August 1990 Rev 0 to Core Operating Limits Rept, for Cycle 3 ML20246H8531989-05-0101 May 1989 Status of Control Room Design Review,Human Engineering Discrepancies & Similarity Review Remaining Issues ML20244D5631989-03-31031 March 1989 Criticality Analysis of Vogtle Unit 1 Spent Fuel Racks ELV-00511, Criticality Analysis of Vogtle Fresh Fuel Racks1989-01-31031 January 1989 Criticality Analysis of Vogtle Fresh Fuel Racks ML20196A0021988-11-30030 November 1988 Design Evaluation of West Jersey Mfg/Piping Supplies,Inc Fittings & Flanges W/Estimated Strength Below 66 Ksi for Plant Vogtle,Unit 2 ML20207G8601988-08-12012 August 1988 to Criticality Safety Analyses for Vogtle Electric Generating Plant Spent Fuel Storage Racks ML20155C0471988-06-0101 June 1988 Rev 0 to Branch Technical Position Cmeb 9.5-1, Fire Event Safe Shutdown Evaluation Summary Rept ML20155C0711988-06-0101 June 1988 Rev 4 to Branch Technical Position Cmeb 9.5-1, Control Room Fire Alternate Shutdown Evaluation (Spurious Actuation Study) ML20154G2511988-05-20020 May 1988 Vols 1-5 to Seismic Qualification of Safety-Related Equipment Vogtle Electric Generating Station Unit 2 ML20154H8571988-04-30030 April 1988 Positive Moderator Temp Coefficient & Refueling Water Storage Tank/Accumulator Boron Concentration Increase Licensing Rept for Vogtle Electric Generating Plant Units 1 & 2 ML20155C0351988-04-0101 April 1988 Rev 1 to Fire Event Safe Shutdown Evaluation Rept (Per Branch Technical Position Cmeb 9.5-1) ML20196G3701988-02-29029 February 1988 Dcrdr Supplemental Summary Rept ML20150E7151987-12-31031 December 1987 ECCS Outage Data Rept for 1987 ML20246D9121987-12-31031 December 1987 Georgia Power Supply Methodology Rept ML20238D5801987-07-31031 July 1987 Digital Metal Impact Monitoring Sys Baseline Data Acquisition Summary for Vogtle Unit 1 ML20236C7311987-07-22022 July 1987 Special Rept on Initial Operating History of Plant ML20214S6281987-06-30030 June 1987 Verification & Validation:Final Rept for Plant Safety Monitoring Sys ML20235A5141987-06-30030 June 1987 Evaluation of RCS for Steam Generator Upper Support Redesign ML20214T5881987-05-26026 May 1987 Long Term Support of Cables in Vertical Cable Trays ML20147D3141987-02-28028 February 1987 Steam Generator Tube Rupture Event Operator Action Times Using Vogtle Simulator ML20211A4531987-02-0909 February 1987 Nuclear Svc Cooling Water Welding Concern ML20214D4381986-11-30030 November 1986 Rev 4 to Vogtle Environ Qualification Rept ML20213C7951986-10-31031 October 1986 Verification & Validation Program Summary Rept for Georgia Power Co,Vogtle Electric Generating Plant Emergency Response Facilities Computer Sys ML20210A9841986-08-31031 August 1986 Rept on Settlement. W/34 Oversize Drawings ML20199K1501986-07-0202 July 1986 Info & Control Characteristics Basis Document ML20206P5751986-06-25025 June 1986 Thermal Analysis of Safety-Related Valves Exposed to Vogtle Electric Generating Plant Control & Auxiliary Bldg Steam Line Breaks ML20203G1461986-06-10010 June 1986 Nuclear Operations, Crdr Summary Rept ML20203L6891986-04-30030 April 1986 Rev 2 to Tdi Diesel Generator Design Review & Quality Revalidation Rept ML20203B4441986-04-30030 April 1986 Vols 1-5 to Seismic Qualification of Safety-Related Equipment,Vogtle Electric Generating Plant Unit 1 ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20205J6971986-02-14014 February 1986 Evaluation of Chlorine Concentration in Vogtle Electric Generating Plant Control Room. W/13 Oversize Drawings ML20137K4871985-11-25025 November 1985 Evaluation of Chlorine Concentration at Vogtle Electric Generating Plant Control Bldg Air Intake ML20211E8611985-10-31031 October 1985 Suppl 1 to Rev 1 to Exhaust Manifold Piping (Large Bore Scope Only) Component Part 02-380A ML20137Y3551985-10-0202 October 1985 Cathodic Protection for Fuel Oil Storage Tanks & Associated Pipes 1997-09-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
[Table view] |
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i V0GTLE ELECTRIC GENERATING PLANT (VEGP) tiNIT 1 CYCLE 3 P i
CORE OPERATING LIMITS REPORT REVISION O i
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1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNIT 1 CYCLE 3 has been prepared -in accordance with the requirements of Technical Specification 6.8.1.6.
L- The Technical Specifications affected by this repert are listed b2 low:
3/4.1.1.1 SHUTDOWN MARGIN - MODES 1 and 2 SHUTDOWN MARGIN - MODES 3, 4 and 5 3/4.1.1.2 . !
3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 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 - FQ(2) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F$g REV. O PAGE 1 of 9 h /
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COLR for VEGP UNIT 1 CYCLE 3 2.0 OPERATING LIMITS :
The cycle specific parameter limits for the specifications listed 'n Section 1.0 are presented in the fo119 wing subsections. These limits have been developed r using the NRC approved methodologies specified in Technical Specific: tion '
6.8.1.6 .
2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (Specification 3/4.1.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k.
i 2.2 SHUTDOWN MARGIN - MODES 3. 4 AND 5 (Specification 3/4.1.1.2) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures I and 2.
2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.3) ;
2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL/ARO/HZP - MTC shall be less positive than +0.7 x 10-4 ok/k/0F for power levels er to 70% RTP with a linear ramp to 0 ok/k/0F at 100% RTP.
The EOL/AR0/RTP MTC shall be less negative than -4.0 x 10 4 '
hk/k/0F. .
2.3.2 The MTC Surveillance limit is:
The 300 ppm /AR0/RTP MTC should be less negative than or equal to 3.1 x 10 4 ok/k/0F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out ;
HZP stands for Hot Zero THERMAL POWER EOL stands for Fnd of Cycle Life RTP stands for RATED THERMAL POWER ,
2.4 Shutdown Rod Insertion Limit (Specification 3/4 1.3.5) ,
2 1 All shutdown rods shall be withdraw to a position greater than or ;
equal to 222 steps. ,
2.5 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.
REV. O PAGE 2 of 9 1
COLR for VEGP UNIT 1 CYCLE 3 1
2.6 Axial Flux Difference (Specification 3/4.2.1) l
{CAOC methodology)
The AXIAL FLUX DIFFERENCE (AFD) target band is +5%, -5% for core I 2.6.1 average accumulated burnup 5 3000 MWD /MTV.
f.6.2 The AFD target band is +3%, 12% for core average accumulated burnup > 3000 MWD /MTV.
where: MWD /MTV stands for megawatt days / metric ton of initial uranium metal.
2.6.3 The AFD Acceptable Operation Limits are provided in Figure 4.
2.7 Heat Flux Hot Channel Factor - Fy(Z) (Specification 3/4.2.2)
(Fxy methodology)
RTP F0 2.7.1 Fg(Z) s
RTP F0 FQ (Z) 5 m __ *K(Z) for P s 0.5
0.5 where
P - THERMAL POWER RATED THERMAL POWER .
RTP 2.7.2 Fg - 2.30 .
1 l
2.7.3 K(2) is provided in Figure 5. r REV. O PAGE 3 of 9 l
__ - ~ , . .
__4-, . . ...
COLR for VEGP UNIT 1 CYCLE 3 L RTP 2.7.4 Fxy - Fxy * (1 + PFxy * (1 P))
RTP where: 1. F is less than or sgJal to 1.775 for all Core pI5nes containing Bank "D" control rods
- 2. For all unrodded core planes:
RTP F is less than or equal to 1.705 for core eievationsbelow3.7ft.
RTP F is less than or equal to 1.660 for core eI5vationsbetween3.7ft.and8.1ft.
RTP F is less than or equal to 1.765 for core eI5vationsabove8.1ft.
2.7.5 PFxy = 0.2 Nuclear Enthalov Rise Hot Channel Factor - F$g (Specification 3/4.2.3)
E.8 RTP F5HsFag * (1 + PFAH * (1-P))
where: P = THERMAL POWER 1 RATED THERMAL POWER RTP 2.8.1 FAH
- 1.55 2.8.2 PFAH
= 0.3
, REY O PAGE 4 of 9 1
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COLR FOR VEGP UNIT 1 CYCLE 3 I Q
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COLR FOR VEGP UNIT 1 CYtLE 3
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COLR FOR VEGP UN8T 1 CYCLE 3
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, O PAGE 7 of 9
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.- COLR FOR YEGP UNIT 1 CYCLE 3 l
140 120 UNACCEPTABLE l 100 i OPERATION l ( 11.90) (11.90) t
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ACCEPTABLE OPERATION ig /
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FIGURE 4 AX1AL FLUX DIFFERENCE LIMITS AS A FUf4CTIOff 0F RATED THERMAL POWER REV. O PAGE 8 of 9 m__ . _ _ , . , _, _
i COLR FDP, VEGP UN17 1 CYCLE 3 1 1
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1.25-1.00 mummmmmmmmmmu-mummmmmmmmmme
$ 0.75 0.50 CORE HEIGHT K(2) i 0.000 1.000 6.000 1.000 10.835 0.939 0.25 12.000 0.652 0
4.0 6.0 8.0 10.0 12.0 2C 0
CORE HEIGHT (ft)
FIGURE 5 .
K(2) - NORMAll2ED FQ(2) AS A FUNCTION OF CORE HEIGHT REV. O PAGE 9 of 9 ,
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V0GTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 1 CORE OPERATING LIMITS hiPORT AiVISION 0 l
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COLR for VEGP UNIT 2 CYCLE 1 s
1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNIT 2 CYCLE 1 has been prepared in accordance with the requirements of Technical Specification 6.8.1.6 The Technical Specifications affected by this report are listed below:
3/4.1.1.1 SHUTDOWN MARGIN - MODES 1 and 2 3/4.1.1.2 SHUTDOWN MARGIN - MODES 3, 4 and 5 3/4.1.1.3 Moderator Te.nerature Coefficient 3/4.1.3.5 Shutdown Rod insert.on 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 - FQ(Z)
N 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAH l 4
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REV. O PAGE 1 of 9 I
ll
COLR for VEGP UNIT 2 CYCLE 1 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 6.8.1.6.
2.1 SHUTDOWN MARGIN - MODES I AND 2 (Specification 3/4.1.1.1)
I 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k.
2.2 SHUTDOWN MARGIN - MODES 3. 4 AND 5 (Specification 3/4.1.1.2) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.
2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL/ARO/HZP - MTC shall be less positive than 0 Ak/k/0F.
The EOL/ARO/RTP MTC shall be less negative than -4.0 x 10 4 ok/k/0F.
2.3.2 The MTC Surveillance limit is:
The300 3.1 x 10*ppg /AR0/RTPMTCshouldbelessnegativethanorequalto Ak/k/0F, 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 2.4 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 2.4.1 All shutdown rods shall be withdrawn to a position greater than or equal to 222 steoc.
2.5 Control Rod Insertion limits (Specification 3/4.1.3.6) 2.5.1 The control rod banks shall be limited in physical insertion as l shown in Figure 3.
REY. O PAGE 2 of 9
COLR for VEGP UNIT 2 CYCLE 1 2.6 Axial Flux Difference (Specification 3/4.2.1)
(CAOC methodology) 2.6.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +5%, -5% for core average accumulated burnup 5 3000 MWD /MTV.
2.6.2 The AFD target band is +3%, -12% for core average accunulated burnup > 3000 MWD /MTV, where: MWD /MTV stands for megawatt days / metric ton of initial uranium metal.
2.6.3 The AFD Acceptable Operation Limits are provided in Figure 4.
2.7 Heat Flux Hot Channel Factor - F Q (Z) (Specification 3/A.2.2)
(Fxy methodology)
RTP Fg 2.7.1 FQ (Z) s
RTP FQ (Z) s
0.5 where
P - THERMAL POWER RATED THERMAL POWER RTP 2.7.2 Fg - 2.30 l '
2.7.3 K(Z) is provided in Figure 5.
REV. O PAGE 3 of 9
, COLR for VEGP UNIT 2 CYCLE 1 L RTP 2.7.4 Fxy - Fxy * (1 + PFxy * (1-P))
RTP where: 1. F is less than' or equal to *. 71 for all core pi5nescontainingBank"D"controlrods
- 2. For all unrodded core planes:
RTP F is less than or equal to 1.54 for core eievationsuptoandincluding5.5ft.
RTP F is less than or equal to 1,62 for core eievationsabove5.5ft.
2.7.5 PFxy = 0.2 2.8 Nuclear Enthalov Rise Hot Channel Factor - F$g (Specification 3/4.2.3)
. RTP F5HsFAH * (1 + PFAH * (1 P))
where: P = _ THERMAL P,0WER RATED THERMAL POWER RTP 2.8.1 FAH
= 1.55 2.8.2 Ii AH = 0.3 REV. O PAGE 4 of 9
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RELATIVE POWER (PariCENT) l l
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, .' . COLR FOR VEGP UN1V 2 CYCLE 1 140 -
'i20 UNACCEPTABLE 100 OPERATION
( 11,90) (11,90) t Jb i" ,
r T I
f O
ACCEPTABLE OPERATION N (31.50) g ( 31,50) 40 20 l 0 -
50 -40 30 20 10 0 10 20 30 40 50 FLUX DIFFERENCE, el (percent)
I FIGURE 4 Axl AL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER l
REV. O PAGE 8 of 9 e
m__--____.__ __-_._____________m_______._- -
__ _._m. -___.m____ _ -__.___ - m_.______._
. 1
' ' ' i COLR FOR VEGP UNIT 2 CYCLE 1
. . i I
l 8 l
\
l' l l 1.60 1
1 1.25 .,
l 1.00 sumummmmmmmmmes '-
l l
l g 0.75 h
0.50 CORE ,
HEIGHT K(Z) 0.000 1.000 6.000 1.000
- 0.25 10.835 0.939 12.000 0.652 0
0 2.0 4.0 6.0 6.0 10.0 12.0 CORE HEIGHT (ft)
FIGURE 5 K(Z) - NORMALIZED ig(2) AS A FUNCTION OF CORE HEIGHT REV. O PAGE 9 of 9
-