ML061150273: Difference between revisions

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| number = ML061150273
| number = ML061150273
| issue date = 04/21/2006
| issue date = 04/21/2006
| title = Davis-Besse Nuclear Power Station Core Operating Limits Report for Cycle 15
| title = Core Operating Limits Report for Cycle 15
| author name = Bezilla M B
| author name = Bezilla M
| author affiliation = FirstEnergy Nuclear Operating Co
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =  
| addressee name =  
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This letter transmits Revision 0 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)Core Operating Limits Report (COLR) for Cycle 15 operation (Enclosure 1). Submittal of this revision is in accordance with DBNPS Technical Specification 6.9.1.7.Attachment 1, Commitment List, identifies that there are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at (330) 315-7243.Sincerely, MKL Enclosures cc: Regional Administrator, NRC Region III NRC/NRR Project Manager DB-1 Senior Resident Inspector, NRC Region III Utility Radiological Safety Board Aoo Docket Number 50-346 License Number NPF-3 Serial Number 3252 Enclosure 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 0 (31 pages follow)
This letter transmits Revision 0 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)Core Operating Limits Report (COLR) for Cycle 15 operation (Enclosure 1). Submittal of this revision is in accordance with DBNPS Technical Specification 6.9.1.7.Attachment 1, Commitment List, identifies that there are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at (330) 315-7243.Sincerely, MKL Enclosures cc: Regional Administrator, NRC Region III NRC/NRR Project Manager DB-1 Senior Resident Inspector, NRC Region III Utility Radiological Safety Board Aoo Docket Number 50-346 License Number NPF-3 Serial Number 3252 Enclosure 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 0 (31 pages follow)
Cycle 15 COLR%Page 1 of 31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT I CYCLE 15 CORE OPERATING LIMITS REPORT Prepared by _Reviewed by o(Q25. =//bi/af D. B. Kelley/_ //z / , X-" S. M. 16r Approved by AR. R Bau rgse RPer 'Iii v A.R. Burger al mg, a'LIST OF EFFECTIVE PAGES Page C-I through C-31 Rev. 0 C-l Cycle 15 COLE Page 2 of 31 Revision 0 Technical Specificationl/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure la Regulating Group Position Operating Liraits, 0-and to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure lb Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Four RC Pumps, 2772 3.1.3.8 MWth 3.1.3.6 .Figure lc Regulating Group Position Operating Limits, 0 and to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure id Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Three RC Pumps, 2772 3.1.3.8 MWth 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments 3.1.3.9 Figure 3 APSR Position Operating Limits, 2772 Mv[Wth 3.2.1 Figure 4a. AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4b AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-1 0 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4c AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4d AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps, 2772 MWth C-2 Cycle 15 COLR Page 3 of 31 Revision 0 3.2.1 Figure 4f AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Three RC Pumps, 2772 MWth 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits, 2772 MWth 2.2.1 Figure 6 Flux -A Flux/Flow (or Power/Imbalance/Flow)
Cycle 15 COLR%Page 1 of 31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT I CYCLE 15 CORE OPERATING LIMITS REPORT Prepared by _Reviewed by o(Q25. =//bi/af D. B. Kelley/_ //z / , X-" S. M. 16r Approved by AR. R Bau rgse RPer 'Iii v A.R. Burger al mg, a'LIST OF EFFECTIVE PAGES Page C-I through C-31 Rev. 0 C-l Cycle 15 COLE Page 2 of 31 Revision 0 Technical Specificationl/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure la Regulating Group Position Operating Liraits, 0-and to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure lb Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Four RC Pumps, 2772 3.1.3.8 MWth 3.1.3.6 .Figure lc Regulating Group Position Operating Limits, 0 and to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure id Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Three RC Pumps, 2772 3.1.3.8 MWth 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments 3.1.3.9 Figure 3 APSR Position Operating Limits, 2772 Mv[Wth 3.2.1 Figure 4a. AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4b AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-1 0 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4c AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4d AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps, 2772 MWth C-2 Cycle 15 COLR Page 3 of 31 Revision 0 3.2.1 Figure 4f AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Three RC Pumps, 2772 MWth 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits, 2772 MWth 2.2.1 Figure 6 Flux -A Flux/Flow (or Power/Imbalance/Flow)
Allowable Values, 2772 MWth 3.2.4 Table 1 QUADRANT POWER TILT Limits, 2772 MWth 3.1.1.3c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits 3.2.2 Table 4a Nuclear Heat Flux Hot Channel Factor -F]Q (NAS), 2772 MWth 3.2.2 Table 4b Nuclear Heat Flux Hot Channel Factor -FQ (FIDMS), 2772 MWth 3.2.3 Table 5 Nuclear Enthalpy Rise Hot Channel Factor -FN AH, 2772 MWth 3.2.3 Figure 7 Maximum Allowable Radial Peak for FNi 1 1 in Mark-B Fuel Assemblies
Allowable Values, 2772 MWth 3.2.4 Table 1 QUADRANT POWER TILT Limits, 2772 MWth 3.1.1.3c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits 3.2.2 Table 4a Nuclear Heat Flux Hot Channel Factor -F]Q (NAS), 2772 MWth 3.2.2 Table 4b Nuclear Heat Flux Hot Channel Factor -FQ (FIDMS), 2772 MWth 3.2.3 Table 5 Nuclear Enthalpy Rise Hot Channel Factor -FN AH, 2772 MWth 3.2.3 Figure 7 Maximum Allowable Radial Peak for FNi 1 1 in Mark-B Fuel Assemblies 3.2.3 Figure 8 Maximum Allowable Radial Peak for FN!1 1 in Mark-BHTP Fuel Assemblies 3.2.3 Table 6 Maximum Allowable Radial Peak for FN6, in Mark-B Fuel Assemblies 3.2.3 Table 7 Maximum Allowable Radial Peak for FNAH in Mark-BHTP Fuel Assemblies C-3 Cycle 15 COLR Page 4 of31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The Core Operating Limits have been developed using the methodology provided in reference 2.0 (1). The licensed length of Cycle 15 is 711.36 EFPDs (based on a reactor thermal rating of 2772 MWt).The following cycle-specific core Operating Limits, Protective Limit and Flux -A Flux/Flow Reactor Protection System Allowable Values are included in this report: 1) Regulating Group Position Alarm Setpoints (error adjusted Operating Limits) and Xenon reactivity "power level cutoff'2) Rod program group positions (Control Rod Core locations and group assignments)
 
====3.2.3 Figure====
8 Maximum Allowable Radial Peak for FN!1 1 in Mark-BHTP Fuel Assemblies
 
====3.2.3 Table====
6 Maximum Allowable Radial Peak for FN6, in Mark-B Fuel Assemblies
 
====3.2.3 Table====
7 Maximum Allowable Radial Peak for FNAH in Mark-BHTP Fuel Assemblies C-3 Cycle 15 COLR Page 4 of31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The Core Operating Limits have been developed using the methodology provided in reference 2.0 (1). The licensed length of Cycle 15 is 711.36 EFPDs (based on a reactor thermal rating of 2772 MWt).The following cycle-specific core Operating Limits, Protective Limit and Flux -A Flux/Flow Reactor Protection System Allowable Values are included in this report: 1) Regulating Group Position Alarm Setpoints (error adjusted Operating Limits) and Xenon reactivity "power level cutoff'2) Rod program group positions (Control Rod Core locations and group assignments)
: 3) Axial Power Shaping Rod Alarm Setpoints (error adjusted Operating Limits)4) AXIAL POWER IMBALANCE Alarm Setpoints (error adjusted Operating Limits)5) AXIAL POWER IMBALANCE Protective Limits 6) Flux-AFlux/Flow (or Power/Imbalance/Flow)
: 3) Axial Power Shaping Rod Alarm Setpoints (error adjusted Operating Limits)4) AXIAL POWER IMBALANCE Alarm Setpoints (error adjusted Operating Limits)5) AXIAL POWER IMBALANCE Protective Limits 6) Flux-AFlux/Flow (or Power/Imbalance/Flow)
Allowable Values.7) QUADRANT POWER TILT limits 8) Negative Moderator Temperature Coefficient limit 9) Nuclear Heat Flux Hot Channel Factor, FQ and 10) Nuclear Enthalpy Rise Hot Channel Factor, FN,, 2.0 References
Allowable Values.7) QUADRANT POWER TILT limits 8) Negative Moderator Temperature Coefficient limit 9) Nuclear Heat Flux Hot Channel Factor, FQ and 10) Nuclear Enthalpy Rise Hot Channel Factor, FN,, 2.0 References
: 1) BAW-10179P-A, Rev. 6, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses", August, 2001.C4 Cycle 15 COLR Page S of 31 Revision 0 Figure Ia Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level' t l t 1 1 l Cutoff 100 I LLIIL L I[II II! III It'll'V 7 E 0~-J 0 C: a)C.)0)0~0)90 80 70 60 50 I I I I i I I I I I Ti Unacceptable Operation ,............
: 1) BAW-10179P-A, Rev. 6, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses", August, 2001.C4 Cycle 15 COLR Page S of 31 Revision 0 Figure Ia Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level' t l t 1 1 l Cutoff 100 I LLIIL L I[II II! III It'll'V 7 E 0~-J 0 C: a)C.)0)0~0)90 80 70 60 50 I I I I i I I I I I Ti Unacceptable Operation ,............
7il".I+ + -4I- I- I I-1ThThrI Operation 4 t Restricted 4..II _I I -' .I.. .I .I. ' I- ..Shutdown Margin Limit I .....I...-l Ffr1 11 cllI I I I Ii 11 LL l+HI LLI+H L*n-r l ll .............
7il".I+ + -4I- I- I I-1ThThrI Operation 4 t Restricted 4..II _I I -' .I.. .I .I. ' I- ..Shutdown Margin Limit I .....I...-l Ffr1 11 cllI I I I Ii 11 LL l+HI LLI+H L*n-r l ll .............
z1 r~ I I. .I .nT I .Tl I I I I.-I I ........+4 I I 40 30 Acceptable Operation  
z1 r~ I I. .I .nT I .Tl I I I I.-I I ........+4 I I 40 30 Acceptable Operation
: I L .... II I!20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 1 75 100 Group 5 0 25 75 100 ,. .P A ^Group 6 u 21 100 Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6. and 6 and 7. shall be maintained.
: I L .... II I!20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 1 75 100 Group 5 0 25 75 100 ,. .P A ^Group 6 u 21 100 Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6. and 6 and 7. shall be maintained.
Note 2: Instrument error is accounted for in these Operating Limits.C-5 Cycle 15 COLR.Page 6 of31 Revision 0 Figure lb Regulating Group Position Operating Limits After 300 +/-10 EFPD, Four RC Pumps -2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 or w Z: 0 a.-j w w 0)LU a-a-90 80 70 60 50 40 30 20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100..Group 5 0 L 25 75 100 Group 6 0 25 100 Group 7 NoBe 1: A Rod Group overlap of 25 +/-5% between sequential withdrawn groups 5 and 6, and 6 and 7. shall be maintained.
Note 2: Instrument error is accounted for in these Operating Limits.C-5 Cycle 15 COLR.Page 6 of31 Revision 0 Figure lb Regulating Group Position Operating Limits After 300 +/-10 EFPD, Four RC Pumps -2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 or w Z: 0 a.-j w w 0)LU a-a-90 80 70 60 50 40 30 20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100..Group 5 0 L 25 75 100 Group 6 0 25 100 Group 7 NoBe 1: A Rod Group overlap of 25 +/-5% between sequential withdrawn groups 5 and 6, and 6 and 7. shall be maintained.
Line 54: Line 45:
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE E)C-14 Cycle 15 COLR Page 15 of 31 Revision 0 Figure 4e AXIAL POWER IMBALANCE Operating Limits 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15* This Figure is referred to by Technical Specification 3.2.1 , .-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE  
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE E)C-14 Cycle 15 COLR Page 15 of 31 Revision 0 Figure 4e AXIAL POWER IMBALANCE Operating Limits 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15* This Figure is referred to by Technical Specification 3.2.1 , .-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE  
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE ED C-15 Cycle 15 COLF.Page 16 of 31 Revision 0 Figure 4f AXIAL POWER IMBALANCE Operating Limits After 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 l-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE  
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE ED C-15 Cycle 15 COLF.Page 16 of 31 Revision 0 Figure 4f AXIAL POWER IMBALANCE Operating Limits After 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 l-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE  
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE Go C-16 Cycle 15 COLR.Page 17 of 31 Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2772 MWt RTP This Figure is referred to by Technical Specification  
%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE Go C-16 Cycle 15 COLR.Page 17 of 31 Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2772 MWt RTP This Figure is referred to by Technical Specification 2.1.2 UNACCEPTABLE OPERATION-80 60 40 20 -10 0 10 20 30 40 50 60 70 80.AXIAL POWER IMBALANCE, %Pumps Operating 4 3.Reactor Coolant Flow. aom.380,000 283,860 Required Measured Flow to Ensure Compliance.
 
====2.1.2 UNACCEPTABLE====
OPERATION-80 60 40 20 -10 0 10 20 30 40 50 60 70 80.AXIAL POWER IMBALANCE, %Pumps Operating 4 3.Reactor Coolant Flow. aom.380,000 283,860 Required Measured Flow to Ensure Compliance.
com 389,500 290,957 C-17 Cycle 15 COLR Page 18 of 31 Revision 0 Figure 6 Flux-AFlux/Flow (or PowerllmbalancelFlow)
com 389,500 290,957 C-17 Cycle 15 COLR Page 18 of 31 Revision 0 Figure 6 Flux-AFlux/Flow (or PowerllmbalancelFlow)
Allowable Values L This Figure Is referred to by Technical Specification 2.2.1% RATED THERMAL POWER UNACCEPTABLE OPERATION (-17.0,108.0)
Allowable Values L This Figure Is referred to by Technical Specification 2.2.1% RATED THERMAL POWER UNACCEPTABLE OPERATION (-17.0,108.0)
Line 67: Line 55:
I I .j60 IACCEPTABLE OPERATION.1SPECIFIED RC PUMP COMBINATION
I I .j60 IACCEPTABLE OPERATION.1SPECIFIED RC PUMP COMBINATION
} l _ -40 I 20 I I* 1 I .I FOR I I I I I I I.(30.6,49.7)
} l _ -40 I 20 I I* 1 I .I FOR I I I I I I I.(30.6,49.7)
I I I I , E......-8 .-60-40-20 0o 20 40 60 80 AXIAL POWER IMBALANCE, %C-18 Cycle 15 COLR Page 19 of 31 Revision 0 Table 1 QUADRANT POWER TILT Limits 2772 MWt RTP l This Table is referred to by Technical Specification 3.2.4 From 0 EFPD to EOC-15 Steady-state Limit for THERMAL Steady-state Limit for POWER > 60% Transient Limit QUADRANT THERMAL POWER POWER TILT < 60% Maximum Limit as measured by: (%) (%) (%)Symmetric Incore 7.90 4.31 10.03 20.00 Detector System Table 2 Negative Moderator Temperature Coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature Coefficient Limit (@RATED THERMAL POWER)-3.7 1x104 Ak/k/0 F C-19 Cycle 15 COLE" Page 20 of 31 Revision 0 Table 3 Power To Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9J Batch 14AI Batch 15 Batch 16 Batch 17 Fuel Assembly Type Mark-B8A Mark-B IOM Mark-B 1OK Mark-B12 Mark-B-HTP Minimum linear heat 20.5 22.3 22.1 22.1 22.1 rate to melt, kW/ft (20.8)(a)  
I I I I , E......-8 .-60-40-20 0o 20 40 60 80 AXIAL POWER IMBALANCE, %C-18 Cycle 15 COLR Page 19 of 31 Revision 0 Table 1 QUADRANT POWER TILT Limits 2772 MWt RTP l This Table is referred to by Technical Specification 3.2.4 From 0 EFPD to EOC-15 Steady-state Limit for THERMAL Steady-state Limit for POWER > 60% Transient Limit QUADRANT THERMAL POWER POWER TILT < 60% Maximum Limit as measured by: (%) (%) (%)Symmetric Incore 7.90 4.31 10.03 20.00 Detector System Table 2 Negative Moderator Temperature Coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature Coefficient Limit (@RATED THERMAL POWER)-3.7 1x104 Ak/k/0 F C-19 Cycle 15 COLE" Page 20 of 31 Revision 0 Table 3 Power To Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9J Batch 14AI Batch 15 Batch 16 Batch 17 Fuel Assembly Type Mark-B8A Mark-B IOM Mark-B 1OK Mark-B12 Mark-B-HTP Minimum linear heat 20.5 22.3 22.1 22.1 22.1 rate to melt, kW/ft (20.8)(a)
(2 1.1)(b) (2 0.3)(d) (20.I)(19.3)(c)  
(2 1.1)(b) (2 0.3)(d) (20.I)(19.3)(c)
(19.3)(e)
(19.3)(e)
I (a) Limit for 3 wt% Gd 2 O 3 rods -Batch 14A1 (b) Limit for 2 wt% Gd 2 O 3 rods -Batch 15 (c) Limit for 8 wt% Gd 2 O 3 rods -Batch 15 (d) Limit for 4 wt% Gd 2 O 3 rods -Batch 16 (e) Limit for 8 wt% Gd 2 0 3 rods -Batch 16 (O Limit for 4 wt% Gd 2 0 3 rods -Batch 17 (g) Limit for 8 wt% Gd 2 O 3 rods -Batch 17 C-20 Cycle 15 COLR Page 21 of 31 Revision 0 Table 4a Nuclear Heat Flux Hot Channel Factor -FQ (NAS)2772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor FO FQ shall be limited by the following relationships:
I (a) Limit for 3 wt% Gd 2 O 3 rods -Batch 14A1 (b) Limit for 2 wt% Gd 2 O 3 rods -Batch 15 (c) Limit for 8 wt% Gd 2 O 3 rods -Batch 15 (d) Limit for 4 wt% Gd 2 O 3 rods -Batch 16 (e) Limit for 8 wt% Gd 2 0 3 rods -Batch 16 (O Limit for 4 wt% Gd 2 0 3 rods -Batch 17 (g) Limit for 8 wt% Gd 2 O 3 rods -Batch 17 C-20 Cycle 15 COLR Page 21 of 31 Revision 0 Table 4a Nuclear Heat Flux Hot Channel Factor -FQ (NAS)2772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor FO FQ shall be limited by the following relationships:
Line 85: Line 73:
4 wt% GdO Fuel LHRALL&deg;W kW/ft (a)Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.8 15.8 15.4 15.2 14.8 14.2 13.5 40,000 MWd/mtU 15.7 15.7 15.2 15.1 14.7-14.3 13.6 (a) L1inear interpolation for allowable LHR between specified burnup points is valid for these tables.C-26 Cycle 15 COLR Page 27 of 31 Revision 0 Table 4b, (Continued)
4 wt% GdO Fuel LHRALL&deg;W kW/ft (a)Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.8 15.8 15.4 15.2 14.8 14.2 13.5 40,000 MWd/mtU 15.7 15.7 15.2 15.1 14.7-14.3 13.6 (a) L1inear interpolation for allowable LHR between specified burnup points is valid for these tables.C-26 Cycle 15 COLR Page 27 of 31 Revision 0 Table 4b, (Continued)
Batch 17 (Mark-B-HTP)-
Batch 17 (Mark-B-HTP)-
8 wt% GdxO 1 Fuel LHRALLOW kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 40,000 MWd/mtU MWd/mtU 14.9 14.9 14.5 14.4 13.9 13.4 12.7 14.9 14.9 14.6 14.5 14.0 13.7 13.0 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-27 Cycle 15 COLR Page 28 of 31 Revision 0 Table 5 Nuclear Enthalpv Rise Hot Channel Factor -F, This Table is referred to by Technical Specification  
8 wt% GdxO 1 Fuel LHRALLOW kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 40,000 MWd/mtU MWd/mtU 14.9 14.9 14.5 14.4 13.9 13.4 12.7 14.9 14.9 14.6 14.5 14.0 13.7 13.0 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-27 Cycle 15 COLR Page 28 of 31 Revision 0 Table 5 Nuclear Enthalpv Rise Hot Channel Factor -F, This Table is referred to by Technical Specification 3.2.3 Enthalpy Rise Hot Channel Factor F 11 FNAH < MARP [I + 0.3 (1 -P/Pm)]MARP = Maximum Allowable Radial Peak, see MARP Figures and data Tables P = THERMAL POWER / RATED THERMAL POWER and P < 1.0 Pm = 1.0 for 4-RCP operation Pm = 0.75 for 3-RCP operation Figure 7 Maximum Allowable Radial Peak for FAH in Mark-B Fuel Assemblies 2.1 -..-2.0-*Y 1.9 , C.)114 I._": 1.8 -cu 1.7 -&#xa3; 1.6 -1 ,2 1.75-4. -I L. -I -I I -I t I I -L L- I I A -_I- r--- --_-J- --I--J --- -L J-1 L I i I -L -I- -1 L -I I I I JI: L I I L I- I I L I T FI I I I I I I I I I- I- -i- ~- f- _-I- ------4-~ I -~ I J-L J.. .LL. JLL4 .LJ.L.L J.I L .J..LJ. L J.-L I I I I I I I -I 1 -+- I I I I I-I-I -I I I I I I J L-II I I I I- I- J I I I I I I I L IL I I L I IIII T 1 r ii L r ~ --r1-1-I II- I I, I 1.4 -Il 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak* This figure is applicable to all Mark-B fuel in the core. Linear interpolation and extrapolation above x/L of 0.8 are acceptable.
 
====3.2.3 Enthalpy====
Rise Hot Channel Factor F 11 FNAH < MARP [I + 0.3 (1 -P/Pm)]MARP = Maximum Allowable Radial Peak, see MARP Figures and data Tables P = THERMAL POWER / RATED THERMAL POWER and P < 1.0 Pm = 1.0 for 4-RCP operation Pm = 0.75 for 3-RCP operation Figure 7 Maximum Allowable Radial Peak for FAH in Mark-B Fuel Assemblies 2.1 -..-2.0-*Y 1.9 , C.)114 I._": 1.8 -cu 1.7 -&#xa3; 1.6 -1 ,2 1.75-4. -I L. -I -I I -I t I I -L L- I I A -_I- r--- --_-J- --I--J --- -L J-1 L I i I -L -I- -1 L -I I I I JI: L I I L I- I I L I T FI I I I I I I I I I- I- -i- ~- f- _-I- ------4-~ I -~ I J-L J.. .LL. JLL4 .LJ.L.L J.I L .J..LJ. L J.-L I I I I I I I -I 1 -+- I I I I I-I-I -I I I I I I J L-II I I I I- I- J I I I I I I I L IL I I L I IIII T 1 r ii L r ~ --r1-1-I II- I I, I 1.4 -Il 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak* This figure is applicable to all Mark-B fuel in the core. Linear interpolation and extrapolation above x/L of 0.8 are acceptable.
For axial heights < x/L of 0.2, the value at x/L 0.2 will be used.C-28  
For axial heights < x/L of 0.2, the value at x/L 0.2 will be used.C-28  
*a Cycle 15 COLR Page 29 of 31 Revision 0 Figure 8 Maximum Allowable Radial Peak for FrNi in Mark-BHTP Fuel Assemblies
*a Cycle 15 COLR Page 29 of 31 Revision 0 Figure 8 Maximum Allowable Radial Peak for FrNi in Mark-BHTP Fuel Assemblies

Revision as of 19:34, 13 July 2019

Core Operating Limits Report for Cycle 15
ML061150273
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/21/2006
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3252
Download: ML061150273 (34)
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Text

FENOC Wirtn FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Hzrbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President

-Nuclear Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 3252 April 21, 2006 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Davis-Besse Nuclear Power Station Core Operating Limits Report for Cycle 15 Ladies and Gentlemen:

This letter transmits Revision 0 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)Core Operating Limits Report (COLR) for Cycle 15 operation (Enclosure 1). Submittal of this revision is in accordance with DBNPS Technical Specification 6.9.1.7.Attachment 1, Commitment List, identifies that there are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at (330) 315-7243.Sincerely, MKL Enclosures cc: Regional Administrator, NRC Region III NRC/NRR Project Manager DB-1 Senior Resident Inspector, NRC Region III Utility Radiological Safety Board Aoo Docket Number 50-346 License Number NPF-3 Serial Number 3252 Enclosure 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 0 (31 pages follow)

Cycle 15 COLR%Page 1 of 31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT I CYCLE 15 CORE OPERATING LIMITS REPORT Prepared by _Reviewed by o(Q25. =//bi/af D. B. Kelley/_ //z / , X-" S. M. 16r Approved by AR. R Bau rgse RPer 'Iii v A.R. Burger al mg, a'LIST OF EFFECTIVE PAGES Page C-I through C-31 Rev. 0 C-l Cycle 15 COLE Page 2 of 31 Revision 0 Technical Specificationl/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure la Regulating Group Position Operating Liraits, 0-and to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure lb Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Four RC Pumps, 2772 3.1.3.8 MWth 3.1.3.6 .Figure lc Regulating Group Position Operating Limits, 0 and to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.1.3.8 3.1.3.6 Figure id Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Three RC Pumps, 2772 3.1.3.8 MWth 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments 3.1.3.9 Figure 3 APSR Position Operating Limits, 2772 Mv[Wth 3.2.1 Figure 4a. AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4b AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-1 0 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4c AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Four RC Pumps, 2772 MWth 3.2.1 Figure 4d AXIAL POWER IMBALANCE Operating Limits, 0 to 300 +/-10 EFPD, Three RC Pumps, 2772 MWth 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps, 2772 MWth C-2 Cycle 15 COLR Page 3 of 31 Revision 0 3.2.1 Figure 4f AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Three RC Pumps, 2772 MWth 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits, 2772 MWth 2.2.1 Figure 6 Flux -A Flux/Flow (or Power/Imbalance/Flow)

Allowable Values, 2772 MWth 3.2.4 Table 1 QUADRANT POWER TILT Limits, 2772 MWth 3.1.1.3c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits 3.2.2 Table 4a Nuclear Heat Flux Hot Channel Factor -F]Q (NAS), 2772 MWth 3.2.2 Table 4b Nuclear Heat Flux Hot Channel Factor -FQ (FIDMS), 2772 MWth 3.2.3 Table 5 Nuclear Enthalpy Rise Hot Channel Factor -FN AH, 2772 MWth 3.2.3 Figure 7 Maximum Allowable Radial Peak for FNi 1 1 in Mark-B Fuel Assemblies 3.2.3 Figure 8 Maximum Allowable Radial Peak for FN!1 1 in Mark-BHTP Fuel Assemblies 3.2.3 Table 6 Maximum Allowable Radial Peak for FN6, in Mark-B Fuel Assemblies 3.2.3 Table 7 Maximum Allowable Radial Peak for FNAH in Mark-BHTP Fuel Assemblies C-3 Cycle 15 COLR Page 4 of31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 15 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The Core Operating Limits have been developed using the methodology provided in reference 2.0 (1). The licensed length of Cycle 15 is 711.36 EFPDs (based on a reactor thermal rating of 2772 MWt).The following cycle-specific core Operating Limits, Protective Limit and Flux -A Flux/Flow Reactor Protection System Allowable Values are included in this report: 1) Regulating Group Position Alarm Setpoints (error adjusted Operating Limits) and Xenon reactivity "power level cutoff'2) Rod program group positions (Control Rod Core locations and group assignments)

3) Axial Power Shaping Rod Alarm Setpoints (error adjusted Operating Limits)4) AXIAL POWER IMBALANCE Alarm Setpoints (error adjusted Operating Limits)5) AXIAL POWER IMBALANCE Protective Limits 6) Flux-AFlux/Flow (or Power/Imbalance/Flow)

Allowable Values.7) QUADRANT POWER TILT limits 8) Negative Moderator Temperature Coefficient limit 9) Nuclear Heat Flux Hot Channel Factor, FQ and 10) Nuclear Enthalpy Rise Hot Channel Factor, FN,, 2.0 References

1) BAW-10179P-A, Rev. 6, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses", August, 2001.C4 Cycle 15 COLR Page S of 31 Revision 0 Figure Ia Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level' t l t 1 1 l Cutoff 100 I LLIIL L I[II II! III It'll'V 7 E 0~-J 0 C: a)C.)0)0~0)90 80 70 60 50 I I I I i I I I I I Ti Unacceptable Operation ,............

7il".I+ + -4I- I- I I-1ThThrI Operation 4 t Restricted 4..II _I I -' .I.. .I .I. ' I- ..Shutdown Margin Limit I .....I...-l Ffr1 11 cllI I I I Ii 11 LL l+HI LLI+H L*n-r l ll .............

z1 r~ I I. .I .nT I .Tl I I I I.-I I ........+4 I I 40 30 Acceptable Operation

I L .... II I!20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 1 75 100 Group 5 0 25 75 100 ,. .P A ^Group 6 u 21 100 Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6. and 6 and 7. shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.C-5 Cycle 15 COLR.Page 6 of31 Revision 0 Figure lb Regulating Group Position Operating Limits After 300 +/-10 EFPD, Four RC Pumps -2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 or w Z: 0 a.-j w w 0)LU a-a-90 80 70 60 50 40 30 20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100..Group 5 0 L 25 75 100 Group 6 0 25 100 Group 7 NoBe 1: A Rod Group overlap of 25 +/-5% between sequential withdrawn groups 5 and 6, and 6 and 7. shall be maintained.

No :e 2: Instrument error is accounted for in these Operating Limits.C-6 Cycle 15 COLR.Page 7 of31 Revision 0 Figure 1c Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 2r rL 3: 0 ra--L LU w I-a w 0.2 C a)C1)0 0L 90 80 70 60 50 40 30 20 10 0 0 25 50 -75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100 I I I Group 5 0 25 75 100.^ i, Group (i u 25)100 Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.C-7 Cycle 15 COLR Page 8 of3l Revision 0 Figure ld Regulating Group Position Operating Limits After 300 +10 EFPD, Three RC Pumps -2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 F 0.-J I-_a C.a)(1)0 IL 90 80 70 60 50 40 30 20 10 0 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 100 0 75 Group 5 0 25 75 100., 1i, Group b u 25b 100 Group 7 Note 1: A Rod Group overlap of 25 +5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.C 8 Cycle 15 COLR.Page 9 of31 Revision 0 Figure 2 Control Rod Core Locations and Group Assignments Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.1.3.7 N (X)1 2 3 4 5 6 7 8 9 10 11 12 13 14 .15 A B C D E F.1 (XV)K Id ED W Group Number (Z)Group No. of Rods Function Groun 1 4 Safety 5 2 .8 Safety 6 3 4 Safety 7 4 9 Safety 8 No. of Rods 12 8 8 8 al 61 Function Control Control Control APSRs Tote C-9

.Cycle 15 COLF.Page 10 of 31 Revision 0 Figure 3 APSR Position Operating Limits-2772 MWt RTP This Figure is referred to by Technical Specification 3.1.3.9 Before APSR Pull: 0 EFPD to 620 4 10 EFPD, Three or Four RC pumps operation*

Lower Limit: 0 %WD Upper Limit: 100 %WD After APSR Pull: 620 + 10 EFPD to End-of-Cycle Three or Four RC pumps operation*

Insertion Prohibited (maintain

> 99%WD)* :Power restricted to 77% for 3-pump operation.

c-lo Cycle 15 COLR.Page 11 of 31 Revision 0 Figure 4a AXIAL POWER IMBALANCE Operating Limits 0 to 300 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 i-60 40 20 -10 0 10 20 30 40 50 60 AXIAL POWER IMBALANCE

% LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE Go C-li Cycle 15 COLRE Page 12 of 31 Revision 0 Figure 4b AXIAL POWER IMBALANCE Operating Limits 300 +/-10 to 600 +/-10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1-50 30 10 0 10 20- 30 40 50 AXIAL POWER IMBALANCE

%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE To C-12 Cycle 15 COLP.Page 13 of 31 Revision 0 Figure 4c AXIAL POWER IMBALANCE Operating Limits After 600 +/-10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 , .-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE

%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE Go C-13 Cycle 15 COLR.Page 14 of 31 Revision 0 Figure 4d AXIAL POWER IMBALANCE Operating Limits 0 to 300 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 110 100 90 fflO.- Restricted

-Region IEstI II I I I -"l-444w JA-1I-1l Restricted Region III[ TliIlIlII H-f W W /tLL °Trlr ~v!+IIIIF-Wgggzu X~tIW4i ZL~ ermissible H Operating* Region -.-3 0-I-60 40 20 -10 0 10 20 30 40 50 60 AXIAL POWER IMBALANCE

%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE E)C-14 Cycle 15 COLR Page 15 of 31 Revision 0 Figure 4e AXIAL POWER IMBALANCE Operating Limits 300 +/-10 to 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15* This Figure is referred to by Technical Specification 3.2.1 , .-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE

%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE ED C-15 Cycle 15 COLF.Page 16 of 31 Revision 0 Figure 4f AXIAL POWER IMBALANCE Operating Limits After 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 15 This Figure is referred to by Technical Specification 3.2.1 l-50 30 10 0 10 20 30 40 50 AXIAL POWER IMBALANCE

%Note 1: Instrument error is accounted for in these Operating Limits.LEGEND FULL INCORE EXCORE Go C-16 Cycle 15 COLR.Page 17 of 31 Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2772 MWt RTP This Figure is referred to by Technical Specification 2.1.2 UNACCEPTABLE OPERATION-80 60 40 20 -10 0 10 20 30 40 50 60 70 80.AXIAL POWER IMBALANCE, %Pumps Operating 4 3.Reactor Coolant Flow. aom.380,000 283,860 Required Measured Flow to Ensure Compliance.

com 389,500 290,957 C-17 Cycle 15 COLR Page 18 of 31 Revision 0 Figure 6 Flux-AFlux/Flow (or PowerllmbalancelFlow)

Allowable Values L This Figure Is referred to by Technical Specification 2.2.1% RATED THERMAL POWER UNACCEPTABLE OPERATION (-17.0,108.0)

Ml=+1.00 (-30.6,94.4)

LIM UNACCEPTABLE OPERATION 120 (17.0,108.0)

Curve shows trip setpoint for an approximately

.25% flow reduc-,tion for three pump operation (283,860 gpm).The actual set.-point will be calculated by the Reactor Protection System and will be directly propc~r-tional to the actual flow with three DumDs.(36.6,77.1)

(-30.6,67.0)

I I .j60 IACCEPTABLE OPERATION.1SPECIFIED RC PUMP COMBINATION

} l _ -40 I 20 I I* 1 I .I FOR I I I I I I I.(30.6,49.7)

I I I I , E......-8 .-60-40-20 0o 20 40 60 80 AXIAL POWER IMBALANCE, %C-18 Cycle 15 COLR Page 19 of 31 Revision 0 Table 1 QUADRANT POWER TILT Limits 2772 MWt RTP l This Table is referred to by Technical Specification 3.2.4 From 0 EFPD to EOC-15 Steady-state Limit for THERMAL Steady-state Limit for POWER > 60% Transient Limit QUADRANT THERMAL POWER POWER TILT < 60% Maximum Limit as measured by: (%) (%) (%)Symmetric Incore 7.90 4.31 10.03 20.00 Detector System Table 2 Negative Moderator Temperature Coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature Coefficient Limit (@RATED THERMAL POWER)-3.7 1x104 Ak/k/0 F C-19 Cycle 15 COLE" Page 20 of 31 Revision 0 Table 3 Power To Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9J Batch 14AI Batch 15 Batch 16 Batch 17 Fuel Assembly Type Mark-B8A Mark-B IOM Mark-B 1OK Mark-B12 Mark-B-HTP Minimum linear heat 20.5 22.3 22.1 22.1 22.1 rate to melt, kW/ft (20.8)(a)

(2 1.1)(b) (2 0.3)(d) (20.I)(19.3)(c)

(19.3)(e)

I (a) Limit for 3 wt% Gd 2 O 3 rods -Batch 14A1 (b) Limit for 2 wt% Gd 2 O 3 rods -Batch 15 (c) Limit for 8 wt% Gd 2 O 3 rods -Batch 15 (d) Limit for 4 wt% Gd 2 O 3 rods -Batch 16 (e) Limit for 8 wt% Gd 2 0 3 rods -Batch 16 (O Limit for 4 wt% Gd 2 0 3 rods -Batch 17 (g) Limit for 8 wt% Gd 2 O 3 rods -Batch 17 C-20 Cycle 15 COLR Page 21 of 31 Revision 0 Table 4a Nuclear Heat Flux Hot Channel Factor -FQ (NAS)2772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor FO FQ shall be limited by the following relationships:

FQ < LHRALLOW (Bu) / [LHRAVG

  • P] (for P < 1.0)LHRALLOW (Bu): See Tables below AVG LHRAV = 6.3095 kW/ft for Mark-B8A fuel LHRvG = 6.4201 kW/ft for Mark-BIOM fuel LHRAVG LHRAG = 6.3183 kW/ft for Mark-BIOK fuel LHRAVG =6.3 183 kW/ft for Mark-B 12 fulel LHRAVG = 6.3294 kW/ft for Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = Fuel Burnup (MWd/mtU)Batch 9J (Mark-B8A)

-UO, Fuel LHRALLOW kW/ft (a)Axial Segment I 2 3 4 5 6 7 8 0 MWd/mtU 16.1 15.8.15.0 15.0 15.4 15.4 14.6 14.3 24,500 MWd/mtU 16.1 15.8 15.0 15.0 15.4 15.4 14.6 14.3 52,000 MWd/mtU 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 60,000 MWd/mtU 10.2 10.2 10.2 10.2 10.2 10.2 10.2 10.2 Batch 14AI (Mark-B IOM) -UO, Fuel LHRALLOW kW/ft (a)Axial Segment 1I 2 3 4.5 6 7 8 0 MWd/mtU 17.6 17.5 17.0 16.6 16.0 15.3 14.7 14.5 35,000 MWd/mtU 16.8 16.7 15.6 15.3 15.3 15.3 14.7 14.5 62,000 -MWd/mtU 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-21 Cycle 15 COLF.Page 22 of 31 Revision 0 Table 4a, (Continued)

Batch 1 5A,B.C2 (Mark-B I OK) -UO, Fuel LHRALLOW kW/ft (a)Axial Segment 1 2 3 4 5 6 7 8 0 MWd/mtU 17.6 17.5 17.0 16.6 16.0 15.3 14.7 14.5 35,000 MWd/mtU 16.8 16.7 15.6 15.3 15.3 15.3 14.7 14.5 58,000 MWd/mtU 14.7 14.7 14.6 14.4 14.2 13.7 13.2 13.0 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.1 13.7 13.1 12.9 60,000 MWd/mtU 14.1 14.1 14.1 14.1 14.1 13.6 13.1 12.9 62,000 MWd/mtU 13.5 13.5 13.5 13.5 13.5 13.5 13.0 12.8 Batch 16A-E (Mark-B 12) -UO, Fuel LHRALLOW kWft (a)Axial Secment 2 3 4 S 6 7 8 0 MWd/mtU 17.6 17.5 17.0 16.6 16.0 15.3 14.7 14.5 35,000 MWd/mtU 16.8 16.7 15.6 15.3 15.3 15.3 14.7 14.5 58,000 MWd/mtU 14.7 14.7 14.6 14.4 14.2 13.7 13.2 13.0 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.1 13.7 13.1 12.9 60,000 MWd/mtU 14.1 14.1 14.1 14.1 14.1 13.6 13.1 12.9 62,000 MWd/mtU 13.5 13.5 13.5 13.5 13.5 13.5 13.0 12.8 Batch 17A-E (Mark-B-HTP)

-UO, Fuel LHRALLOW kW/ft (a)Axial Segment I 2 3 4.5 6 7 8 0 MWd/mtU 17.6 17.5 17.1 17.0 16.5 15.9 15.3 15.1 40,000 MWd/mtU 17.2.17.1 16.7 16.7 16.2 15.8 15.2 15.0 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-22 Cycle 15 COLR.Page 23 of 31 Revision 0 Table 4b Nuclear Heat Flux Hot Channel Factor -Fq (FIDMS)2772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor Fn FQ shall be limited by the following relationships:

FQ < LHR-OW (Bu) / [LHRAVG

  • p] (for P 1.0)LHRALLOW (Bu): See the Tables below LHRAVG = 6.3095 kW/ft for Mark-B8A fuel LHRAVG = 6.4201 kW/ft for Mark-B 1 OM fuel LHRAVG = 6.3183 kW/ft for Mark-BlOK fuel LHRAVG = 6.3183 kW/ft for Mark-B 12 fuel LHRAvG = 6.3294 kW/ft for Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = Fuel Burnup (MWd/mtU)Batch 9J (Mark-B8A)

-UO, Fuel LHRALL°W kWfft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 16.3 15.9.15.1 15.5 16.0 15.4 14.3 24,500 MWdlmtU 16.3 15.9 15.1 15.5 16.0 15.4 14.3 52,000 MWd/mtU 12.0 12.0 12.0 12.0 12.0 12.0 12.0 60,000 MWd/mtU 10.2 10.2 10.2 10.2 10.2 10.2 10.2 Batch 14AI (Mark-BIOM) -UO, Fuel LHRALL°W kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 17.6 17.6 17.1 16.6 16.0 15.3 14.5 35,000 MWd/mtU 16.8 16.8 15.7 15.3 15.8 15.3 14.5 62,000 MWd/mtU 12.8 12.8 12.8 12.8 12.8 12.8 12.8 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-23 Cycle 15 COLP.Page 24 of 31 Revision 0 Table 4b, (Continued)

Batch 15AB.C2 (Mark-B IOK) -UO, Fuel LHRALLOW kWMft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 17.6 17.6 17.1 16.6 16.0 15.3 14.5 35,000 MWd/mtU 16.8 16.8 15.7 15.3 15.8 15.3 14.5 58,000 MWd/mtU 14.7 14.7 14.7 14.4 14.2 13.7 13.0 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.1 13.7 12.9 60,000 MWd/mtU 14.1 14.1 14.1 14.1 14.1 13.6 12.9 62,000* MWd/mtU 13.5 13.5 13.5 13.5 13.5 13.5 12.8 Batch 16A-E (Mark-B 12) -UO, Fuel LHRALOW kW/ft (a)Core Elevation LfKh 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 17.6 17.6 17.1 16.6 16.0 15.3 14.5 35,000 MWdImtU 16.8 16.8 15.7 15.3 15.8 15.3 14.5 58,000 MWd/mtU 14.7 14.7 14.7 14.4 14.2 13.7 13.0* 59,000 60,000 62,000 MWd/mtU MWd/mtU MWd/mtU 14.4 14.1 13.5 14.4 14.1 13.5 14.4 14.1 13.5 14.4 14.1 13.5 14.1 14.1 13.5 13.7 13.6 13.5 12.9 12.9 12.8 Batch 17A-E (Mark-B-HTP)

-UO, Fuel LHRALLw kW/ft (a)Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 17.6 17.6 17.2 17.0 16.5 15.9 15.1 40,000 MWd/mtU 17.2 17.2 16.8 16.7 16.2 15.8 15.0 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-24 Cycle 15 COLR Page 25 of 31 Revision 0 Table 4b. (Continued)

Batch 14A1 (Mark BIOMY- 3 wt% GdO, Fuel LHRALLoW kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 16.1 16.1 15.7 15.2 14.7 14.0 13.3 35,000 MWd/mtU 15.4 15.4 14.4 14.0 14.5 14.0 13.3 62,000 MWd/mtU 11.8 11.8 11.8 11.8 11.8 11.8 11.8 Batch 15 (Mark-B I OK) -2 wt% Gd,03 Fuel LHRALLOW kW/ft (a)Core Elevation (ft)0.0(0 2.506 4.264 6.021 7.779 9.5 I6 12.030 0 MWd/mtU 16.5 16.5 16.0 15.5 15.0 14.3 13.6 35,000 MWd/mtU 15.7 15.7 14.7 14.3 14.8 14.3 13.6 58,000 MWd/mtU 13.9 13.9 13.9 13.6 13.4 13.0 12.4 59,000 MWd/mtU 13.6 13.6 13.6 13.6 13.3 12.9 12.3 60,000 MWd/mtU 13.3 13.3 13.3 13.3 13.3 12.9 12.3 62,000 MWd/mtU 12.8 12.8 12.8 12.: 12.8 12.J 12.2* Batch 15 (Mark-BIOK-8 wt% Gd,0 1 Fuel LHR LOW kW/ft (a)Core Elevatic n (ft)0.000 2.506 4.264 6.02.1 7.779 9.536 12.0130 0 MWd/mtU 14.9 14.9 14.5 14.0 13.5 12.9 12.2 35,000 58,000 59,000 60,000 MWd/mtU MWd/mtU MWd/mtU MWd/mtU 14.2 12.4 12.1 11.9 14.2 13.3 12.9 13.4 12.9 12.2 12.4 12.4 12.2 12.0 11.6 11.0 12.1 12.1 12.2 11.9 11.5 10.9 11.9 11.9 11.9 11.9 11.5 10.9 62,0(10 MWd/ntU I 1.4 I 1.4 I11.I 1.4 11 A'I 0A 10.8 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-25 Cycle 15 COLF.Page 26 of 31 Revision 0 Table 4b. (Continued)

Batch 16 (Mark-B 12)- 4 wt% GdO, Fuel LHRALLOW kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 35,000 58,000 59,000 60,000 62,000 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtl;15.8 15.8 15.3 14.9 14.3 13.7 13.0 15.1 15.1 14.1 13.7 14.2 13.7 13.0 13.3 13.3 13.3 13.0 12.9 12.4 11.8 13.0 13.0 13.0 13.0 12.8 12.3 11.7 12.7 12.7 12.7 12.7 12.8 12.3 11.7 12.2 12.2 12.2 12.2 12.2 12.2 11.6 Batch 16 (Mark-B 12)- 8 wt% GdO Fuel LHRALLOW kW/ft (a)Core Elevation (f t 0.000 2.506 4.264 6.021 7.779 9.536.12.000 0 35,000 58,000 59,000 60,000 62,000 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 14.9 14.9 14.5 14.0 13.5 12.9 12.2 14.2 14.2 13.3 12.9 13.4 12.9 12.2 12.4 12.4 12.4 12.2 12.0 11.6 11.0 12.1 12.1 12.1 12.2 11.9 11.5 10.9 11.9 11.9 11.9 11.9 11.9 11.5 10.9 11.4 11.4 11.4 11.4 11.4 11.4 10.8 Batch 17 (Mark-B-HTP)-

4 wt% GdO Fuel LHRALL°W kW/ft (a)Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.8 15.8 15.4 15.2 14.8 14.2 13.5 40,000 MWd/mtU 15.7 15.7 15.2 15.1 14.7-14.3 13.6 (a) L1inear interpolation for allowable LHR between specified burnup points is valid for these tables.C-26 Cycle 15 COLR Page 27 of 31 Revision 0 Table 4b, (Continued)

Batch 17 (Mark-B-HTP)-

8 wt% GdxO 1 Fuel LHRALLOW kW/ft (a)Core Elevation (ft)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 40,000 MWd/mtU MWd/mtU 14.9 14.9 14.5 14.4 13.9 13.4 12.7 14.9 14.9 14.6 14.5 14.0 13.7 13.0 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.C-27 Cycle 15 COLR Page 28 of 31 Revision 0 Table 5 Nuclear Enthalpv Rise Hot Channel Factor -F, This Table is referred to by Technical Specification 3.2.3 Enthalpy Rise Hot Channel Factor F 11 FNAH < MARP [I + 0.3 (1 -P/Pm)]MARP = Maximum Allowable Radial Peak, see MARP Figures and data Tables P = THERMAL POWER / RATED THERMAL POWER and P < 1.0 Pm = 1.0 for 4-RCP operation Pm = 0.75 for 3-RCP operation Figure 7 Maximum Allowable Radial Peak for FAH in Mark-B Fuel Assemblies 2.1 -..-2.0-*Y 1.9 , C.)114 I._": 1.8 -cu 1.7 -£ 1.6 -1 ,2 1.75-4. -I L. -I -I I -I t I I -L L- I I A -_I- r--- --_-J- --I--J --- -L J-1 L I i I -L -I- -1 L -I I I I JI: L I I L I- I I L I T FI I I I I I I I I I- I- -i- ~- f- _-I- ------4-~ I -~ I J-L J.. .LL. JLL4 .LJ.L.L J.I L .J..LJ. L J.-L I I I I I I I -I 1 -+- I I I I I-I-I -I I I I I I J L-II I I I I- I- J I I I I I I I L IL I I L I IIII T 1 r ii L r ~ --r1-1-I II- I I, I 1.4 -Il 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak* This figure is applicable to all Mark-B fuel in the core. Linear interpolation and extrapolation above x/L of 0.8 are acceptable.

For axial heights < x/L of 0.2, the value at x/L 0.2 will be used.C-28

  • a Cycle 15 COLR Page 29 of 31 Revision 0 Figure 8 Maximum Allowable Radial Peak for FrNi in Mark-BHTP Fuel Assemblies
L::~:2:~~:~~

-L~-4-.-44-L-4.-~-4 x/L... -2r1 _ -r -T -C-i -r -r rir i -r -r -n-iT r 1--r7 r *xL0.t_ -1...4 .-J ...I.4.I.L. t-4-l -l-I t-- -- -l-fl.L -. l -LIt- .J *x/L=(I. I-1 _ IJ L _L _I_ J L _l -J1 _ --L -J -.4 _- -L- J -A -I_ J L -I_- J I- l _-_ I J __ , J_ _L _'_ I L -e__1- _ L _'_ J_ -L _' -*-x/L=(1.14-2 --i -' -r-i-T-- --r-- -_- , -r-r- --r-r-I- --r --- - - -xL- 0xIL .2 --I ... t -..J-r:L -r-I_ --I -; -I _ L 1.0 -rr 4 '-- r - -xJL= 0.r.2 1.6 -J+/-L.IJ.L-'---'-

J.J.. .L.. W.L...LJ-J- o IJ =..SS-t -----l- ---- -t-$-n--x-t -t-l ' L0.6 1 _ -.L1.L-L-l-

-I-J: --L--r- -r--- s-r-r- -L J-r-r r-- -r -r-r J--IL- -u-r- r -I L -I 1. --_4 -$_14 --sL --W14;1 ;-1 _ ,- 41. -o --O,-XI- 0.88 1.1 1 .2L 1.6 1.7 J 1. 1.9_ s T.V I L I I Is a The AR valuie T -r based T -ar -ativ -T -h --o -r14.7 inches.-1 t -- ----I- -+ --1 --i t-FI- q -- FF--- q i-t-F 1 I_ L __J, I L -I- J L L __J _L _-L L -1_ 1 L- j _1 _ 1_L 1 w~~~~~~~~~~~~~~~~~~

~ -__I '__' l____ 'JLl___ Ll__'_~_'J

1. 1I 1I 1I I. 1.6 I I I I I I I I I 1.7 1 .1 1 1 .9 Axial Peak*This figure is applicable to all Mark-B-HTP fuel in the core. Line ar interpolation is acceptable.

The MIARP values are based on an active fiiel height of 142.75 inches.C-29 a Cycle 15 COLF.Page 30 of 31 Revision 0 N Table 6 Maximum Allowable Radial Peak for FAH in Mark-B Fuel Assemblies Axial Peak x/L Axial Heicht (inches) MAP Limit MARP Lirmit 0.2 28.12 2.0415 1.9264 0.4 56.24 2.0345 1.9198 0.6 84.36 2.0221 1.9081 0.8 112.48 1.9934 1.8810 0.2 28.12 2.2918 1.9824 0.4 56.24' 2.2749 1.9678 1.2 0.6 84.36 2.2470 1.9437 0.8 112.48 2.1601 1.8685 0.2 28.12 2.5521 2.0378 0.4 56.24 2.5197 2.0119 1.3 0.6 84.36 2.4387 1.9472 0.8 112.48 2.2719 1.8140 0.2 28.12 3.0022 2.0775 I 0.4 56.24 2.8272 1.9564 15 0.6 84.36 2.6367 1.8246 0.8 112.48 2.4553 1.6991 0.2 28.12 3.1839 1.9441 0.4 56.24 2.9911 1.8263 1.7 0.6 84.36 2.7902 1.7037 0.8 112.48 2.6084 1.5927 0.2 28.12 3.2865 1.7955 0.4 56.24 3.0945 1.6906 1.9 0.6 84.36 2.9062 1.5877 0.8 112.48 2.7279 1.4903 C-30

.Cycle 15 COLT, Page 31 of 31 Revision 0 Table 7 Maximum Allowable Radial Peak for FAH in Mark-BHTP Fuel Assemblies Axial Peak Axial Height MAP x/L (inches) Limit MARP Axial Limit Peak Axial Height MAP x/L (inches) Limit 0.0 0.1 0.14 0.2 0.4:1.1' 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.2 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.3 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.4 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.5 0.5 0.6 0.8 0.88 0.9 1.0 0.000 2.03286 14.275 2.03375 19.985 2.03379 28.550 2.03355 57.100 2.03179 71.375 2.03107 85.650 2.03099 114.200 2.03178 125.620 1.98623 128.475 1.98774 142.750 1.86518 0.000 2.33414 14.275 2.33416 19.985 2.33413 28.550 2.33248 57.100 2.33024 71.375 2.32955 85.650 2.32916 114.200 2.15618 125.620 2.07666 128.475 2.07869 142.750 1.95649 0.000 2.66591 14.275 2.64485 19.985 2.62777 28.550 2.66761 57.100 2.65903 71.375 2.58224 85.650 2.46978 114.200 2.24712 125.620 2.15963 128.475 2.16184 142.750 2.02976 0.000 2.74599 14.275 2.65413 19.985 2.63176 28.550 2.69213 57.100 2.74771 71.375 2.68391 85.650 2.56032 114.200 2.33307 125.620 2.23716 128.475 2.24237 142.750 2.09699 0.000 2.77184 14.275 2.66225 19.985 2.63504 28.550 2.69706 57.100 2.75139 71.375 2.75241 85.650 2.64282 114.200 2.39919 125.620 2.30027 128.475 2.30907 142.750 2.15988 1.91828 1.91912 1.91916 1.91893 1.91727 1.91659 1.91652 1.91726 1.87428 1.87570 1.76005 2.01903 2.01905 2.01902 2.01760 2.01566 2.01506 2.01472 1.86510 1.79631 1.79807 1.69236 2.12863 2.11181 2.09817 2.12998 2.12313 2.06182 1.97202 1.79424 1.72438 1.72615 1.62069 2.03596 1.96785 1.95126 1.99602 2.03723 1.98993 1.89829 1.72980 1.65869 1.66256 1.55477 1.91811 1.84228 1.82345 1.86637 1.90396 1.90467 1.82883 1.66024 1.59179 1.59788 1.49464 0.0 0.1 0.14 0.2 0.4 1.6 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.7 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.8 0.5 0.6 0.8 0.88 0.9 1.0 0.0 0.1 0.14 0.2 0.4 1.9 0.5 0.6 0.8 0.88 0.9 1.0 0.000 2.79510 14.275 2.66285 19.985 2.63106 28.550 2.69787 57.100 2.75779 71.375 2.79658 85.650 2.71189 114.200 2.46394 125.620 2.36299 128.475 2.37234 142.750 2.21845 0.000 2.81571 14.275 2.66718 19.985 2.63022 28.550 2.69195 57.100 2.76735 71.375 2.80468 85.650 2.77165 114.200 2.52074 125.620 2.42051 128.475 2.43041 142.750 2.27373 0.000 2.83401 14.275 2.66992 19.985 2.62789 28.550 2.68772 57.100 2.7774 71.375 2.80694 85.650 2.82218 114.200 2.57398 125.620 2.47403 128.475 2.48254 142.750 2.32589 0.000 2.85122 14.275 2.67423 19.985 2.62778 28.550 2.68609 57.100 2.78418 71.375 2.80567 8S.650 2.83113 114.200 2.62225 125.620 2.52166 128.475 2.53147 142.750 2.37605 MARP Limit 1.81332 1.72752 1.70690 1.75024 1.78912 1.81428 1.75934 1.59848 1.53299 1.53906 1.43922 1.71924 1.62855 1.60598 1.64367 1.68971 1.71250 1.69234 1.53913 1.47793 1.48398 1.38831 1.63428 1.53965 1.51542 1.54992 1.60163 1.61867 1.62746 1.48433 1.42669 1.43160 1.34126 1.55767 1.46097 1.43560 1.46745 1.52104 1.53278 1.54669 1.43258 1.37762 1.38298 1.29807 C-31 Docket Number 50-346 License Number NPF-3 Serial Number 3252 Attachment 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station, Unit Number 1, (DBNPS) in this document.

Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments.

Please notify Gregory A. Dunn, Manager -FENOC Fleet Licensing (330-315-7243) of any questions regarding this document or associated regulatory commitments.

COMMITMENTS DUE DATE None N/A

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