ML060530600

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Revision to Core Operating Limits Report for Cycle 14
ML060530600
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/16/2006
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3233
Download: ML060530600 (28)
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Text

FENOCI FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, Ohio 43449 Mark B. Bezila 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Naumber 3233 February 16, 2006 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Davis-Besse Nuclear Power Station Revision to Core Operating Limits Report for Cycle 14 Ladies and Gentlemen:

This letter transmits Revision 1 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)

Core Operating Limits Report (COLR) for the current Cycle 14 operation (Enclosure 1) This revision accommodates additional operational flexibility by allowing the Axial Power Shaping Rods (APSRs) to remain in their normally inserted operating position through the remainder of Cycle 14. Submittal of this revision is in accordance with DBNPS Technical Specification 6.9.1.7.

A list of any regulatory commitments made in this letter is included in Enclosure 2.

If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager - Fleet Licensing, at (330) 315-7243.

MKL Enclosure cc:

Regional Administrator, NRC Region III NRC/NRR Project Manager NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board

-Arto

Docket Number 50-346 License Number NPF-3 Serial Number 3233 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-'BESSE UNIT 1 CYCLE 14 CORE OPERATING LIMITS REPORT REVISION 1 (25 pages follow)

Cycle 14 COLR Page 1 of 25 Revision 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 14 CORE OPERATING LIMITS REPORT Prepared by

/

6 Reviewed by Approved by C

S.. Mw.

Kwper D. S:o iello A.R. urger I

I LIST OF EFFECTIVE PAGES Page C-1 through C-25 Rev. 1 C-l

Cycle 14 COLR Page 2 of 25 Revision 1 Technical Specification/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure 1 a Regulating Group Position and Operating Limits, 0 to 400 3.1.3.8

+/-10 EFPD, Four RC Pumps 3.1.3.6 Figure lb Regulating Group Position and Operating Limits, After 3.1.3.8 400 +/-10 EFPD, Four RC Pumps 3.1.3.6 Figure ic Regulating Group Position and Operating Limits, 0 to 400 +/-10 3.1.3.8 EFPD, Three RC Pumps 3.1.3.6 Figure 1d Regulating Group Position and Operating Limits, After 400 +/-10 3.1.3.8 EFPD, Three RC Pumps 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments 3.1.3.9 Figure 3 APSR Position Operating Limits 3.2.1 Figure 4a AXIAL POWER IMBALANCE Operating Limits, 0 to 300

+/-10 EFPD, Four RC Pumps 3.2.1 Figure 4b AXIAL POWER IMBALANCE Operating Limits, 300 +10 to 654 +20/-10 EFPD, Four RC Pumps 3.2.1 Figure 4c AXIAL POWER IMBALANCE Operating Limits, After 654

+20/-10 EFPD, Four RC Pumps C-2

Cycle 14 COLR Page 3 of 25 Revision 1 3.2.1 Figure 4d AXIAL POWER IMBALANCE Operating Limits, 0 to 300

+/-10 EFPD, Three RC Pumps 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, 300 +10 to 654 +20/-10 EFPD, Three RC Pumps 3.2.1 Figure 4f AXIAL POWER IMBALANCE Operating Limits, After 654 +20/-10 EFPD, Three RC Pumps 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2.2.1 Figure 6 Flux -A Flux/Flow (or Power/

Imbalance/Flow) Allowable Values 3.2.4 Table 1 QUADRANT POWER TILT Limits 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 - FQ (NAS) 3.2.2 Table 4b Nuclear Heat Flux Hot Channel Factor - FQ (FIDMS) 3.2.3.

Table 5 Nuclear Enthalpy Rise Hot Channel Factor - FN H 3.2.3 Figure 7 Allowable Radial Peak for FNH C-3

Cycle 14 COLR Page 4 of 25 Revision 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 14 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 14 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 14 is 736.8 EFPDs (based on a reactor thermal rating of 2772 M4Wt).

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 S etpoints (error adjusted Operating Limits) and Xenon reactivity "power level cuto ff'
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

'3) Negative Moderator Temperature Coefficient limit

9) Nuclear Heat Flux Hot Channel Factor, FQ and N.

LO) Nuclear Enthalpy Rise Hot Channel Factor, FN H 2.0 References (I) BAW-10179P-A, Rev. 4, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses.", August, 2001.

(2) BAW-10164P-A, Rev. 4, " RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis," November, 2002.

C4

Cycle 14 COLR Page 5 of 25 Revision 1 Figure la Regulating Group Position Operating Limits 0 to 400+/-+10 EFPD, Four RC Pumps -2772 MWt Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 1110 I I I I I:

1I 1 L L 1(0 ower Level Cutoff = 100%

F-90 0S'}

-J c~

02 7'0 w

M I-o a0

-40 0

C U)

C.

4.0 a-L-o) 30 0a-20 Unacceptable Operation Operation Restricted

- Shutdown Margin Limit C

LAUepJLdUI Iperation 10 _ r llsr 1

1 1 11 r 11 1 1 Ir O( y I I I I _-

I 0

2 0

25 50 75 1 00 125 150 175 200 225 250 275 300 0

75 i

Rod Index, %Withdrawn 1gO0 Group 5 0

25 75 100 Group 6 0

15 Group 7 Note 1: A Rod Group overlap of 25 +5% between sequeintial 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 14 COLR Page 6 of 25 Revision I Figure lb Regulating Group Position Operating Limits After 400+10 EFPD, Four RC Pumps -- 2772 MWt Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100

Power Level Cutoff= 100%

F 90 w

°o E;0 2

70 a~ 60 LU w

I W:

510 4-o0 r-0 tL 0

a-20 Unaccepl:able Operation

.Operation

. 0

-6 tcj l 11 1 1 1 1 1 1 1 4 -

Shutdown Margin Limit Acceptable Operation lV 1

S AL III I I I I I I 10 -

e J - l--

IIIIII 1 I 1. 1

.. I

0 L I I I 1 0

2 0

25 50 75 100 125 150 175 200 225 250 275 300 P

75 Rod Index, %Withdrawn 1(0 Group 5 0

25 75 100 Group 6 0

Group 7 25 100 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: Instbument error is accounted for in these Operating Limits.

C-6

Cycle 14 COLR Page 7 of 25 Revision I Figure 1c Regulating Group Position Operating Limits 0 to 400+10 EFPD, Three RC Pumps -- 2772 MWt Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 1110 10 IT]' T er ; ILW I~r 1 K Power Level Cutoff = 75%

Ew 0

2t Ego

-j 2

7'0 w

Iu-o 60 w

I-C

0) 40 2

a-,- n 0

0 2:.0 b

Unacceptable Operation F.l I I Ch "t.6 I I I I Operation Restricted

%J11UIIU JVV Margin Limit Acceptable -

Operation 10 0

25 50 75 100 125 150 175 200 225 250 275 300 P

Rod Index, %Withdrawn 75 170 Group 5 0

25 75 100 Group 6 0

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 14 COLR Page 8 of 25 Revision 1 Figure Id Regulating Group Position Operating Limits After 400+/-+10 EFPD, Three RC Pumps -- 2772 MWt Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 1 10 100 _ _ -

Power Level Cutoff = 75%

LU 0a-

-J w

I az w

0 C

a).

(1) 0 a-.

90 80 t)

O, I I I I II

/

XX jLl I

I II I I I I

_ I I T

I I

I TFlT

' 0 Unacceptable 60 _

Operation

'iO

.Operation

~ Restricted 40 Shutdown Margin Limit 30 210 Acceptable -

Operation -

10 AI 0

25 50 75 100 125 150 175 200 225 250 275 300 P

Rod Index, %Withdrawn 75 1t0 I

Group 5 0

25 75 100 Group 6 0

25 100 Group 7 Note 1: A RDd 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 14 COLR Page 9 of 25 Revision 1 Figure 2 Control Rod Core Locations and Group Assignments Davis-Besse 1, Cycle 14 This ure is referred to by Technical Specification 3.1.3.7 N

(X)

"w-1 2

3 4

5 6

I-7 8

9 10 11 12 13 14 15 I

I I

I I

I I

I I

. -I 1 I I

I 1-I

,I I 4

6 4

A B

C 2

5 5

2 2

8 1

1 5

1 8 1 7 2 L D

2 5

5 2

E (W) 4 8

6 3

6 18 4

5 1

1 5

6 7

3 4

3 7

6 5

1 1

1 4 8

6 3

6 4

.I F

G H (Y)

K L

2 5

5 2

I_

_8 I

8 1 11 7

1 H~

N~

2 5

5 2

0 4

6 4

6 4

P I

R

[jjGroup Number (Z)

GrouD No. of Rods F'unction Group 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 Total 61 C-9

Cycle 14 COLR Page 10 of 25 Revision 1 Figure 3 APSR Position Operating Limits This Figure is referred to by Technical Specification 3.1.3.9 Before APSR Pull: 0 ]EFPD to 654 +20/-10 EFPD, Three or Four RC pumps operation I

Lower Limit:

0 %WD Upper Limit:

100 %WD After APSR Pull: 654 +20/-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 I

c-lo

Cycle 14 COLR Page 11 of 25 Revision 1 Figure 4a AXIAL POWER. IMBALANCE Operabng Lirmits o to 300 +10 EFPD, Four RC Pumps - 2772 MWt RTP Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specification 3.2.1

  • -60

-50

-40

-30

-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 EMORE

-- 0--

C-il

Cycle 14 COLR Page 12 of 25 Revision 1 Figure 4b AXIAL POWER IMBALANCE Operating Limits 300 +10 to 654 +20/-10 EFPD, Four RC Pumps - 2772 MWt RTP Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specification 3.2.1 I

I.

  • 1111i 0()0

_ _1-Restricted Region T

,1 1 1 11 1_ _ _- _

Restricted -

Region _

I III I

_0 At I I I I IrxI I

T IlLIl H-nI I1 10fT1XrrIITTIrr Du 1 1 + rl ' a ril IslIvL lS1lll At I {I:

II If J

I A I[

I I

I I

I\\V

_w

-Ir

-F

_ a

" 0

- C-La.

_ -I I I I I

I I-I.

.I I + H I,

I..

40, T§°

  • Permissible Operating Region a) 20 Ii ITI I

I I,,

I, r

I I I I IL I

I I I I 1

-50

-40

-30

-20

-10 0

10 20 AXIAL POWER IMBALANCE %

Note 1: Instrument error is accounted for in these Operating Limits.

30 40 50 LEGEND FULL INCORE EXCORE

-0 C-12

Cycle 14 COLR Page 13 of 25 Revision 1 Figure 4c AXIAL POWER IMBALANCE Operating Limits After 654 +20/-10 EFPD, Four RC Pumps - 2772 MWt RTP Davis-Besse 1. Cycle 14 I

This Fig ure is referred to by Technical Specification 3.2.1

-.60

-50

-40

-30

-20

-10 0

AXIAL POWER IMB/

Note 1: Instrument error is accounted for in these Operating Limits.

10 20 30 40 50 60 kLANCE %

LEGEND FULL INCORE EXCORE C-13

Cycle 14 COLR Page 14 of 25 Revision 1 Figure 4d AXIAL POWER IMBALANCE Operating Limits 0 to 300 +10 EFPD, Three RC Pumps -- 2772 MWt RTP Davis-Besse 1, Cycle 14 This Figure is referred to by Technical Specification 3.2.1

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 AXIAL PO'NER IMBALANCE %

Note 1: Instrument error is accounted for in these Operating Limits.

LEGEND FULL INCORE EXCORE -C.

C-14

Cycle 14 COLR Page 15 of 25 Revision 1 Figure 4e AXIAL POWER IMBALANCE Operating Limits 300 +10 to 654 d+20/-10 EFPD, Three RC Pumps - 2772 MWt RTP Davis-Besse 1, Cycle 14 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 %

Note 1: Insirument error is accounted for in these Operating Limits.

LEGEND FULL INCORE EXCORE C-i5

Cycle 14 COLR Page 16 of 25 Revision 1 Figure 4f AXIAL POWER IMBALANCE Operating Limits After 654 +20/-10 EFPD, Three RC Pumps - 2772 MWt RTP Davis-Besse 1, Cycle 14 I

I This Figure is-referred to by Technical Specification 3.2.1

  • 11CI.....

,,I i,

I -

I I

II T llTI l II II I I I I I I I I11u 100 I

[1-

.I I

Arn,.

_j on

%Jl Restricted Region

+ I

.-LL

. _C JI Li'.

S 47i 5

2 i l ll l l lRestnicted J '1111ll 1 I2NiRegionllllm 1

'I I

I 1 1 11 11 11 11 i

.50-

]

T t.71-t44 6-

,4 I I I I I I3 0

t~1

.o 31 1

1 I

I I I I I I I

I I I I I Permissible Operating ll Region I

I l 1 1 1 I a) a ).

F0)

IC-P-10 I I I II I lltLL 1p-c r,.

-60

-50

-40

-30

-20

-10 0

10 20 30 AXIAL POWER IMBALANCE %

Note 1: Instrument error is accounted for in these Operaling Limits.

40 50 60 LEGEND FULL INCORE EXCORE C-16

Cycle 14 COLR Page 17 of 25 Revision 1 Figure 5 AXIAL POWER IWIBALANCE Protective Limits 2772 MWt RTP r

This Figunr is referred to by Technical specification 2.1.2 120 -

(-42.6, 112.0)

(36.6, 112.0)

-I10 -.

/

'110 -1.

(47.2,100.0)

(47.2, 79.0)

UNACCEPTABLE OPERATION

'100 +

(-42.6, 91.0) 4 PUMP LIMIT (36.6, 91.0) 3 PUMP LIMIT (45.6,100.0)

(45.6, 79.0)

UNACCEPTABLE OPERATION 80 +

70 -

w 0a.

-j 0w 0) 20 U

a.

60 -

50 40 ACCEPTABLE OPERATION FOR SPECIFIED RC PUMP COMBINATION 30 -

20 -

10 -

n w

-80

-70

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 70 80 Pumps Operating 4

3 AXIAL POWER IMBALANCE, %

Required Measured Reactor Coolant Flow to Ensure Flow, cor Compliance. gpm 380,000 389,500 283,860 290,957 c-17

Cycle 14 COLR Page 18 of 25 Revision 1 Figure 6 Fm u:--AlFlu ow (or PowernmbalancelFiow)

Ailcwable Values This Figure Is referred to by Technical Specification 2.2.1

% RATED THERMAL POWER UNACCEPTABLE OPERATION UNACCEPTABLE OPERATION 120 (17.0,108.0)

(-17.0,108.0) m1=+1.00

(-30.6,94.4)

(36.6,77.1)

(-30.6,67.0)

I I

i 1ACCEPTABLE OPEI ISPECIFIED RC PI

-60 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 propor-tional to the.

actual flow with three pumos.

i0 80' ICOMBINATION I

I I

I I

lI I

.I II RATION FOR iMP

-40 I

-20 I

1.

I I

I I

I I

I I

(30.6,49.7) l

-80

-60

-40

-20 0 -

20 40 6

AXIAL POWER IMBALANCE, %

C-18

Cycle 14 COLR Page 19 of 25 Revision 1 Table 1 QUADRANT POWER TILT Limits This Table is referred to by Technical Specification 3.2.4 From 0 EFPD to EOC-14 QUADRANT Steady-state Steady-state Transient Maximum POWER TILT as Limit for Limit for Limit Limit P eaur TILT as THERMAL POWER 1HERMAL POWER measured by:

< 60%

> 60%

(%)

(%)

(%)

(%)

Symmetrical Incore detector system 77.90 4.00 10.03 20.0 Table 2 Negative Moderator TemDerature Coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature Coefficirnt Limit (at RATED THERMAL POWER)

-3.83x10 4 Ak/k/ 0F C-19

Cycle 14 COLR Page 20 of 25 Revision 1 Table 3 Power To Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9H Batch 14 Batch 15 Batch 16 Fuel Assembly Type Mark-B8A Minimum linear heat rate to melt, kW/ft 20.5 Mark-BIOM 22.3 (20.8)(a)

(19.9)°1)

Mark-B IOK Mark-B 12 22.1 (21.1)(c)

(20.7)(d)

(19.3)(c) 22.1 (20.3)(f

-(19.3)(g)

(a)

Limit for 3 wt% Gd rods - Batch 14 (b) imit for 6 wt% Gd rods - Batch 14 (c)

Limit for 2 wt% Gd rods - Batch 15 (d)

Limit for 3 wt% Gd rods - Batch 15 (e)

Limit for 8 wt% Gd rods - Batch 15 (f

Limit for 4 wt% Gd rods - Batch 16

(

Limit for 8 wt% Gd rods - Batch 16 C-20

Cycle 14 COLR Page 21 of 25 Revision 1 Table 4a Nuclear Heat Flux Hot Channel Factor - FQ (NAS) 2 772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor FQ FQ shall be limited by the following relationships:

FQ < LHRAU-0W(Bu)/[LHRA"G

  • P] (for P < 1.0)

LHRALLW(Bu): See Tables below LHRAVG = 6.3095 kW/ft for Mark-B8A fuel LHRAVG = 6.4201 kW/ft for Mark-B lOM fuel LHRAVI = 6.3183 kW/ft for Mark-BlOK fuel LHRAVG = 6.3 183 kW/ft for Mark-B 12 fuel P = ratio of THERMAL POWNER/RATED THERMAL POWER Bu = Fuel Burnup (MWd/mtU)

Batch 9H (Mark-B8A) LHRALLOW kW/ft(a) 0 24,500 52,000 60,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1

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 14 (Mark-B10M) LHRALLOW kWlft(a) 0 35,000 62,000 Axial Seament M\\l/d/mtU MWd/mtU MWd/mtU 1

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 C-21

Cycle 14 COLR Page 22 of 25 Revision 1 Table 4a, continued Batch 15 (Mark-B110K) LHRALLOW kW/ft(a)

Axial Seament 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 13.8 13.3 13.1 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.2 13.7 13.2 13.0 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 16 (Mark-EI12) 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 13.8 13.3 13.1 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.2 13.7 13.2 13.0 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 (a) Linear interpolation for allowable linear heat rate between specified burnup points is-alid for these tables.

C-22

Cycle 14 COLR Page 23 of 25 Revision I Table 4b Nuclear Heat Flux Hot Channel Factor - Fn (FIDMS) 2772 MWt RTP This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor LQ FQ shall be limited by the following relationships:

FQ < LHRALLow(BuVl/[ 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 IOM fuel LHRAVG = 6.3183 kW/ft for Mark-B 10K fuel LHRAVG = 6.3183 kW/ft for Mark-B 12 fuel P = ratio of THERMAL POWER/RATED THERMAL POWER Bu = Fuel Burnup (MWd/mtU)

Batch 911 (Mark-B8A) LHRALLOW kW/ft (a)

Core Elevation 0

24,500 52,000 60,000 (feet' MWd/mtU MWd/mtU 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 14 (Mark-Bl OM) LHRALLOW kW/ft (a)

Core Elevation 0

35,000 62,000 (feet)

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 C-23

Cycle 14 COLR Page 24 of 25 Revision 1 Table 4b. continued Batch 15 (Mark-B 1 OK) LHR'Low kW/ft (a)

Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0

35,000 MWd/mtU MWd/mtU 17.6 16.8 17.6 16.8 17.1 15.7 16.6 15.3 16.0 15.8 15.3 15.3 14.5 14.5 58,000 MWd/mtU 14.7 14.7 14.7 14.4 14.2 13.8 13.1 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.2 13.7 13.0 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 16 (Mlark-B 12) LHRALLOW kW/ft (a) 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 13.8 13.1 59,000 MWd/mtU 14.4 14.4 14.4 14.4 14.2 13.7 13.0 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 (a) Linear interpolation for allowable linear heat rate between specified burnup points is valid for these tables.

C-24

Cycle 14 COLR Page 25 of 25 Revision 1 Table 5 Nuclear Enl:halnv Rise Hot Channel Factor-F-A This Table is referred to by Technical Specification 3.2.3 Enthalpv Rise Hot Channel Factor F&H FSH < ARP [I + 0.3(1 -P/P.)]

ARP = Allowable Radial Peak, see Figure 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* Al'owable Radial Peak for FAH 2.1 m

W 2

m

) 1.9 Q

m 1.7

.0 3 I-:.7

=

E

= 11.6 E

E 1.5 l

I[III I I II3111111111 11 I IIIIIII l

l l

l 1

ll

_os

=2_

_l 00 ll

_~~~~~~~~~~~~~~~~2.

=2 1

f

__,e o = _ _ _ _= s = I II I I '5I I4 I

I 1 11 1 1 11 1 I I II I I II4.36I

!1>

SS11 1

Jil ItI11-11I1 1 It t1l til It tI II Ii 2 1 til I I 2 1 t I I I I -

1F 1481" 1.4 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 fuel in the core. Linear interpolation and extrapolation above 112.48 inches are acceptable. For axial heights <28.12 inches, the value at 28.12 inches will be used.

C-25

Docket Number 50-346 License Number NPF-3 Serial Number 3233 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-]3ESSE NUCLEAR POWER STATION (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 THE MANAGER - FLEET LICENSING (330-315-7243) OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE None N/A

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