ML061150273

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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)
v • d • e


Text

FENOC Wirtn 5501 North State Route 2 FirstEnergy Nuclear Operating Company 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 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 _ o(Q25. =//bi/af D. B. Kelley/

Reviewed by _//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 -AFlux/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 FNi11 in Mark-B Fuel Assemblies 3.2.3 Figure 8 Maximum Allowable Radial Peak for FN!11 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 -AFlux/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' Cutoff 100 I LLIIL t l t 1 L I1 l I I IIII 90 [II III! i I I I I I Ti It'll' V7 E Unacceptable 80 Operation

,............

0~ I+ + -4I- I-I I 7il".

-J

-1ThThrI. Operation 4 70 -l

.II _I I -

t Restricted 4 . I.. . ' . I I. ' I-..

Shutdown Ffr1cllI 11 I I I Ii 11 LL l+HI LLI+H L Margin 60 Limit I . . . . . I... .- I

  • n-r l ll ............. z1 r~ I I. .I . nT .I I . . .

Tl I I I I

. +. . . .

0 4I I 50 C:

a) 40 C.)

0) 0~ 30 Acceptable 0)

Operation IL

....

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 u

^

Group 6 A

21 100

,. . P 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 90 or w

0Z: 80 a.

-j 70 w

w LU 60

0) 50 40 a-30 a-20 10 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100

. .

Group 5 0 25 75 100 L

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 inthese 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 90 2r rL 0 80 3:

-L ra-70 w

LU a

60 w

I-50 C

a) 40 0

C1)

.2 30 0

0L 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 90 F

0. 80

-J 70 I-_ 60 a

50 C.

a) 40 (1) 30 0

IL 20 10 0

0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100 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.

C8

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 No. of Rods Function 1 4 Safety 5 12 Control 2 .8 Safety 6 8 Control 3 4 Safety 7 8 Control 4 9 Safety 8 8 APSRs Toteal 61 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 -50 -40 -30 -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 -40 -30 -20 -10 0 10 20- 30 40 50 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE Note 1: Instrument error is accounted for inthese Operating Limits.

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 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. 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 Restricted

- Region I I-"l-444w Region IEstI II JA-1I-1l III[TliIlIlII H-f W

W /tLL °

~v!+IIIIF-Trlr Wgggzu ZL~ermissible H Operating X~tIW4i 30

.--

  • Region -

I

-60 -50 -40 -30 -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 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

, .

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND FULL INCORE Note 1: Instrument error is accounted for inthese Operating Limits.

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 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. 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 70 -60 -50 30 10 0 10 20 30 40 50 60 70 80

. AXIAL POWER IMBALANCE, %

Required Measured Reactor Coolant Flow to Ensure Pumps Operating Flow. aom. Compliance. com 4 380,000 389,500

3. 283,860 290,957 C-17

Cycle 15 COLR Page 18 of 31 Revision 0 Figure 6 Flux-AFlux/Flow (or PowerllmbalancelFlow)

Allowable Values This Figure Isreferred to by Technical Specification 2.2.1 L

% RATED THERMAL POWER UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 120 Curve shows trip

(-17.0,108.0) (17.0,108.0) setpoint for an approximately Ml=+1.00 .25% flow reduc-

,tion for three pump operation

(-30.6,94.4) LIM (283,860 gpm).

The actual set.-

point will be calculated by the Protection (36.6,77.1) Reactor System and will be

(-30.6,67.0) directly propc~r-tional to the I I . j60 actual flow with three DumDs.

IACCEPTABLE OPERATION FOR

.1SPECIFIED RC PUMP (30.6,49.7)

COMBINATION

} l _ -40 I I I

I I 20 I I I I

  • 1 I .I I.

I E . . .

I

.

I

. .

I ,

-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 -3 .7 1x104 Ak/k/ 0F

(@RATED THERMAL POWER)

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) (20 .3)(d) (20.I)

(19.3)(c) (19.3)(e) I (a) Limit for 3 wt% Gd 2O3 rods - Batch 14A1 (b) Limit for 2 wt% Gd2O3 rods - Batch 15 (c) Limit for 8 wt% Gd2O3 rods - Batch 15 (d) Limit for 4 wt% Gd2O3 rods - Batch 16 (e) Limit for 8 wt% Gd 203 rods - Batch 16 (O Limit for 4 wt% Gd2 03 rods - Batch 17 (g) Limit for 8 wt% Gd2O3 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 LHRAVAVG

= 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 0 24,500 52,000 60,000 Segment MWd/mtU MWd/mtU MWd/mtU MWd/mtU I 16.1 16.1 12.0 10.2 2 15.8 15.8 12.0 10.2 3 .15.0 15.0 12.0 10.2 4 15.0 15.0 12.0 10.2 5 15.4 15.4 12.0 10.2 6 15.4 15.4 12.0 10.2 7 14.6 14.6 12.0 10.2 8 14.3 14.3 12.0 10.2 Batch 14AI (Mark-B IOM) - UO, Fuel LHRALLOW kW/ft (a)

Axial 0 35,000 62,000 -

Segment MWd/mtU MWd/mtU MWd/mtU 1I 17.6 16.8 12.8 2 17.5 16.7 12.8 3 17.0 15.6 12.8 4 16.6 15.3 12.8

.5 16.0 15.3 12.8 6 15.3 15.3 12.8 7 14.7 14.7 12.8 8 14.5 14.5 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 15A,B.C2 (Mark-B I OK) - UO, Fuel LHRALLOW kW/ft (a) 0 35,000 58,000 59,000 60,000 62,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 17.6 16.8 14.7 14.4 14.1 13.5 2 17.5 16.7 14.7 14.4 14.1 13.5 3 17.0 15.6 14.6 14.4 14.1 13.5 4 16.6 15.3 14.4 14.4 14.1 13.5 5 16.0 15.3 14.2 14.1 14.1 13.5 6 15.3 15.3 13.7 13.7 13.6 13.5 7 14.7 14.7 13.2 13.1 13.1 13.0 8 14.5 14.5 13.0 12.9 12.9 12.8 Batch 16A-E (Mark-B 12) - UO, Fuel LHRALLOW kWft (a) 0 35,000 58,000 59,000 60,000 62,000 Axial Secment MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 17.6 16.8 14.7 14.4 14.1 13.5 2 17.5 16.7 14.7 14.4 14.1 13.5 3 17.0 15.6 14.6 14.4 14.1 13.5 4 16.6 15.3 14.4 14.4 14.1 13.5 S 16.0 15.3 14.2 14.1 14.1 13.5 6 15.3 15.3 13.7 13.7 13.6 13.5 7 14.7 14.7 13.2 13.1 13.1 13.0 8 14.5 14.5 13.0 12.9 12.9 12.8 Batch 17A-E (Mark-B-HTP) - UO, Fuel LHRALLOW kW/ft (a) 0 40,000 Axial Segment MWd/mtU MWd/mtU I 17.6 17.2 2 17.5 .17.1 3 17.1 16.7 4 17.0 16.7

. 5 16.5 16.2 6 15.9 15.8 7 15.3 15.2 8 15.1 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 1OM 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 0 24,500 52,000 60,000 Elevation (ft) MWd/mtU MWdlmtU MWd/mtU MWd/mtU 0.000 16.3 16.3 12.0 10.2 2.506 15.9. 15.9 12.0 10.2 4.264 15.1 15.1 12.0 10.2 6.021 15.5 15.5 12.0 10.2 7.779 16.0 16.0 12.0 10.2 9.536 15.4 15.4 12.0 10.2 12.000 14.3 14.3 12.0 10.2 Batch 14AI (Mark-BIOM) -UO, Fuel LHRALL°W kW/ft (a)

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

Core 0 35,000 58,000

  • 59,000 60,000 62,000 Elevation MWd/mtU MWdImtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU LfKh 0.000 17.6 16.8 14.7 14.4 14.1 13.5 2.506 17.6 16.8 14.7 14.4 14.1 13.5 4.264 17.1 15.7 14.7 14.4 14.1 13.5 6.021 16.6 15.3 14.4 14.4 14.1 13.5 7.779 16.0 15.8 14.2 14.1 14.1 13.5 9.536 15.3 15.3 13.7 13.7 13.6 13.5 12.000 14.5 14.5 13.0 12.9 12.9 12.8 Batch 17A-E (Mark-B-HTP) - UO, Fuel LHRALLw kW/ft (a)

Core 0 40,000 Elevation MWd/mtU MWd/mtU 0.000 17.6 17.2 2.506 17.6 17.2 4.264 17.2 16.8 6.021 17.0 16.7 7.779 16.5 16.2 9.536 15.9 15.8 12.000 15.1 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 0 35,000 62,000 Elevation (ft) MWd/mtU MWd/mtU MWd/mtU 0.000 16.1 15.4 11.8 2.506 16.1 15.4 11.8 4.264 15.7 14.4 11.8 6.021 15.2 14.0 11.8 7.779 14.7 14.5 11.8 9.536 14.0 14.0 11.8 12.000 13.3 13.3 11.8 Batch 15 (Mark-B I OK) - 2 wt% Gd,03 Fuel LHRALLOW kW/ft (a)

Core 0 35,000 58,000 59,000 60,000 62,000 Elevation (ft) MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.0(0 16.5 15.7 13.9 13.6 13.3 12.8 2.506 16.5 15.7 13.9 13.6 13.3 12.8 4.264 16.0 14.7 13.9 13.6 13.3 12.8 6.021 15.5 14.3 13.6 13.6 13.3 12.:

7.779 15.0 14.8 13.4 13.3 13.3 12.8 9.5 I6 14.3 14.3 13.0 12.9 12.9 12.J 12.030 13.6 13.6 12.4 12.3 12.3 12.2

  • Batch 15 (Mark-BIOK- 8 wt% Gd,0 1 Fuel LHR LOW kW/ft (a)

Core 0 35,000 58,000 59,000 60,000 62,0(10 Elevatic n (ft) MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/ntU 0.000 14.9 14.2 12.4 12.1 11.9 I 1.4 2.506 14.9 14.2 12.4 12.1 11.9 I 1.4 4.264 14.5 13.3 12.4 12.1 11.9 I11.

6.02.1 14.0 12.9 12.2 12.2 11.9 I 1.4 7.779 13.5 13.4 12.0 11.9 11.9 11 A' 9.536 12.9 12.9 11.6 11.5 11.5 I 0A 12.0130 12.2 12.2 11.0 10.9 10.9 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 0 35,000 58,000 59,000 60,000 62,000 Elevation MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtl; (ft) 0.000 15.8 15.1 13.3 13.0 12.7 12.2 2.506 15.8 15.1 13.3 13.0 12.7 12.2 4.264 15.3 14.1 13.3 13.0 12.7 12.2 6.021 14.9 13.7 13.0 13.0 12.7 12.2 7.779 14.3 14.2 12.9 12.8 12.8 12.2 9.536 13.7 13.7 12.4 12.3 12.3 12.2 12.000 13.0 13.0 11.8 11.7 11.7 11.6 Batch 16 (Mark-B 12)- 8 wt% GdO Fuel LHRALLOW kW/ft (a)

Core 0 35,000 58,000 59,000 60,000 62,000 Elevation MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU (f t 0.000 14.9 14.2 12.4 12.1 11.9 11.4 2.506 14.9 14.2 12.4 12.1 11.9 11.4 4.264 14.5 13.3 12.4 12.1 11.9 11.4 6.021 14.0 12.9 12.2 12.2 11.9 11.4 7.779 13.5 13.4 12.0 11.9 11.9 11.4 9.536 12.9 12.9 11.6 11.5 11.5 11.4

.12.000 12.2 12.2 11.0 10.9 10.9 10.8 Batch 17 (Mark-B-HTP)- 4 wt% GdO Fuel LHRALL°W kW/ft (a)

Core 0 40,000 Elevation MWd/mtU MWd/mtU 0.000 15.8 15.7 2.506 15.8 15.7 4.264 15.4 15.2 6.021 15.2 15.1 7.779 14.8 14.7 9.536 14.2 - 14.3 12.000 13.5 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% GdxO1 Fuel LHRALLOW kW/ft (a)

Core 0 40,000 Elevation (ft) MWd/mtU MWd/mtU 0.000 14.9 14.9 2.506 14.9 14.9 4.264 14.5 14.6 6.021 14.4 14.5 7.779 13.9 14.0 9.536 13.4 13.7 12.000 12.7 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 ,

114 4. -I L. -I - I I - I t I I I I -L L-C.)

I._ - A _I r---

- - _-J---I--J --- - L J

": 1.8 - -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-- - - - ~ I - ~ I J-L. J.. LL. JLL4 .LJ.L.L J.IL .J..LJ. L J.-L cu 1.7 -

II II I I I I - 1 - +- I I I-I-I I -I I I I I I I I JI IL-III- I- J I I I L I I I IL I I L I T IIII 1 r ii L r ~ -- r1-1-I II- I

£ 1.75-

,2 1.6 - I, 1

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 2r1 _ - r -T - C-i- r -r i - r -r -n-iT r 1--r7 r rir
  • 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

_ -1IJ L _L _I_ J L _l- J1_ - - L -J - .4 _- - L- J - A - I_ J L - I_- J

L::~:2:~~:~~ , J_

_'__L I-- lI_-_J __ L~-4-.-44-L-4.-~-4 I L -e__1-_ L _'_ J_- L _' x/L...

-*-x/L=(1.14- -

2 -- i -r-i-T-- -' - - r--- -r-r- _-

, - -r-r-I- - - - r- - xL- .2 0xIL -

- I ... J-r:L t -.. -r-I_ - -I -; -I_ L 1.0 -

rr 4 '-- r -xJL= 0.r

' L0.6

.2 1.6 - J+/-L.IJ.L-'---'-

-t- - - -- l-J.J.. J-

.L.. IJ W.L...LJ-

-t-$-n--x-t o

-t-l

=..SS 1

1. _4

_

-- - -sL- ;-1

-$_14 -W14;1 _ ,- 41.

-

-o I-

.L1.L-L-l-

--

-

O,-XI- 0.88

-- -r--- J: s-r-r- L--r- -L J-r-r r-- -r -r-r J--IL- -u-r- r -

_s 1.1 1 .2L T.V 1.6 I L I 1.7Is J a 1. TheI 1.9 I L -I

-1 t I--+

- -i t-FI-q -- qFF---

i-t-F 1 ARvaluieI_ Tbased

- Lr __J, T-ar I L -I- J-ativ

- LT-hL __J- - _L - r14.7 o_-L inches.1 L -1_ L- j _1 _ 1_L 1 l____ 'JLl___

w~~~~~~~~~~~~~~~~~~ ~ Ll__'_~_'J __I '__' -

1. 1II. 1I I 1II I I I I I I I 1.6 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 Axial Axial Height MAP MARP Axial Height MAP MARP Peak x/L (inches) Limit Limit Peak x/L (inches) Limit Limit 0.0 0.000 2.03286 1.91828 0.0 0.000 2.79510 1.81332 0.1 14.275 2.03375 1.91912 0.1 14.275 2.66285 1.72752 0.14 19.985 2.03379 1.91916 0.14 19.985 2.63106 1.70690 0.2 28.550 2.03355 1.91893 0.2 28.550 2.69787 1.75024 0.4 57.100 2.03179 1.91727 0.4 57.100 2.75779 1.78912

1.1' 0.5 71.375 2.03107 1.91659 1.6 0.5 71.375 2.79658 1.81428 0.6 85.650 2.03099 1.91652 0.6 85.650 2.71189 1.75934 0.8 114.200 2.03178 1.91726 0.8 114.200 2.46394 1.59848 0.88 125.620 1.98623 1.87428 0.88 125.620 2.36299 1.53299 0.9 128.475 1.98774 1.87570 0.9 128.475 2.37234 1.53906 1.0 142.750 1.86518 1.76005 1.0 142.750 2.21845 1.43922 0.0 0.000 2.33414 2.01903 0.0 0.000 2.81571 1.71924 0.1 14.275 2.33416 2.01905 0.1 14.275 2.66718 1.62855 0.14 19.985 2.33413 2.01902 0.14 19.985 2.63022 1.60598 0.2 28.550 2.33248 2.01760 0.2 28.550 2.69195 1.64367 0.4 57.100 2.33024 2.01566 0.4 57.100 2.76735 1.68971 1.2 0.5 71.375 2.32955 2.01506 1.7 0.5 71.375 2.80468 1.71250 0.6 85.650 2.32916 2.01472 0.6 85.650 2.77165 1.69234 0.8 114.200 2.15618 1.86510 0.8 114.200 2.52074 1.53913 0.88 125.620 2.07666 1.79631 0.88 125.620 2.42051 1.47793 0.9 128.475 2.07869 1.79807 0.9 128.475 2.43041 1.48398 1.0 142.750 1.95649 1.69236 1.0 142.750 2.27373 1.38831 0.0 0.000 2.66591 2.12863 0.0 0.000 2.83401 1.63428 0.1 14.275 2.64485 2.11181 0.1 14.275 2.66992 1.53965 0.14 19.985 2.62777 2.09817 0.14 19.985 2.62789 1.51542 0.2 28.550 2.66761 2.12998 0.2 28.550 2.68772 1.54992 0.4 57.100 2.65903 2.12313 0.4 57.100 2.7774 1.60163 1.3 0.5 71.375 2.58224 2.06182 1.8 0.5 71.375 2.80694 1.61867 0.6 85.650 2.46978 1.97202 0.6 85.650 2.82218 1.62746 0.8 114.200 2.24712 1.79424 0.8 114.200 2.57398 1.48433 0.88 125.620 2.15963 1.72438 0.88 125.620 2.47403 1.42669 0.9 128.475 2.16184 1.72615 0.9 128.475 2.48254 1.43160 1.0 142.750 2.02976 1.62069 1.0 142.750 2.32589 1.34126 0.0 0.000 2.74599 2.03596 0.0 0.000 2.85122 1.55767 0.1 14.275 2.65413 1.96785 0.1 14.275 2.67423 1.46097 0.14 19.985 2.63176 1.95126 0.14 19.985 2.62778 1.43560 0.2 28.550 2.69213 1.99602 0.2 28.550 2.68609 1.46745 0.4 57.100 2.74771 2.03723 0.4 57.100 2.78418 1.52104 1.4 0.5 71.375 2.68391 1.98993 1.9 0.5 71.375 2.80567 1.53278 0.6 85.650 2.56032 1.89829 0.6 8S.650 2.83113 1.54669 0.8 114.200 2.33307 1.72980 0.8 114.200 2.62225 1.43258 0.88 125.620 2.23716 1.65869 0.88 125.620 2.52166 1.37762 0.9 128.475 2.24237 1.66256 0.9 128.475 2.53147 1.38298 1.0 142.750 2.09699 1.55477 1.0 142.750 2.37605 1.29807 0.0 0.000 2.77184 1.91811 0.1 14.275 2.66225 1.84228 0.14 19.985 2.63504 1.82345 0.2 28.550 2.69706 1.86637 0.4 57.100 2.75139 1.90396 1.5 0.5 71.375 2.75241 1.90467 0.6 85.650 2.64282 1.82883 0.8 114.200 2.39919 1.66024 0.88 125.620 2.30027 1.59179 0.9 128.475 2.30907 1.59788 1.0 142.750 2.15988 1.49464 C-31

Docket Number 50-346 License Number NPF-3 Serial Number 3252 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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