ML020160524

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Revision to Core Operating Report for Cycle 13
ML020160524
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/11/2002
From:
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2755
Download: ML020160524 (27)
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Text

FENOC FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Ohio 43449-9760 Howard W. Bergendahl 419-321-8588 Vice President - Nuclear Fax: 419-321-8337 Docket Number 50-346 License Number NPF-3 Serial Number 2755 January 11, 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001

Subject:

Revision to Core Operating Limits Report for Cycle 13 Ladies and Gentlemen:

Enclosed is a copy of Revision 1 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)

Core Operating Limits Report (COLR) for the current Cycle 13 operation. This revision to the COLR is being submitted in accordance with DBNPS Technical Specification 6.9.1.7.

Revision 1 to the COLR reflects a core average temperature reduction of 8°F and a shortened operating cycle length. The temperature reduction and shortened operating cycle length are the result of actions taken in response to NRC Bulletin 2001-01, "Circumferential Cracking of Pressure Vessel Head Penetration Nozzles," dated August 3, 2001.

Should you have any questions or require additional information, please contact Mr. David H.

Lockwood, Manager - Regulatory Affairs, at (419) 321-8450.

Very MKIJlaj cc:

J. E. Dyer, Regional Administrator, NRC Region m1I S. P. Sands, DB-1 NRC/NRR Project Manager D. S. Simpkins, DB-1 NRC Resident Inspector Utility Radiological Safety Board V

0\\

Docket Number 50-346 License Number NPF-3 Serial Number 2755 Enclosure COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE 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 - REGULATORY AFFAIRS (419-321-8450) AT THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE Not Applicable None

COLR Page 1 of 25 Revision I FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT I CYCLE 13 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page C-1 through C-4, C-10, C-12, C-13, C-15, C-16 Page C-5 through C-9, C-Il, C-14, C-17 through 25 Rev. I Rev. 0 C-1

COLR Page 2 of 25 Revision 1 Technical Specification/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure la Regulating Group Position and Operating Limits, 0 to 300 3.1.3.8

+/-10 EFPD, Four RC Pumps 3.1.3.6 Figure lb Regulating Group Position and Operating Limits, After 3.1.3.8 300 +/-10 EFPD, Four RC Pumps 3.1.3.6 Figure Ic Regulating Group Position and Operating Limits, 0 to 300 +/-10 3.1.3.8 EFPD, Three RC Pumps 3.1.3.6 Figure Id Regulating Group Position and Operating Limits, After300 +/-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 EFPD to 300

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

+/-10 EFPD, Four RC Pumps 3.2.1 Figure 4c

[Deleted]

C-2

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

+/-10 EFPD, Three RC Pumps 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, After 300 +/-10 EFPD, Three RC Pumps 3.2.1 Figure 4f

[Deleted]

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-1 3.2.3 Figure 7 Allowable Radial Peak for FNm C-3

COLR Page 4 of 25 Revision 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 13 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 13 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 13 is 635 EFPDs.

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, FNm 2.0 References (1) BAW-10179P-A, Revision 4, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses.", dated August 2001.

(2) BAW-10227P-A, Revision 0, "Evaluation of Advanced Cladding and Structural Material (M5TM) in PWR Reactor Fuel, dated February 2000.

C-4

COLR Page 5 of 25 Revision 0 Figure la Regulating Group Position Operating Umits 0 to 300 +/-10 EFPD, Four RC Pumps Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 0

25 50 75 100 125 150 175 200 Rod Index, %Withdrawn 90 80 70 60 50 40 30 20 10 0

0 75 100 I

I I

Group 5 0

25 75 100 o

I 100 Group 6 0

25 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 acoounted for In these Operating Umlts.

C-5 0Y "1

I=

tI 0

U.

a).

I 1C.

225 250 275 300

COLR Page 6 of 25 Revision 0 Figure lb Regulating Group Position Operating Umits After 300 +/-10 EFPD, Four RC Pumps Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 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 75 100 I

I 75 100 I 0

25 100 G u I I

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 Umlts.

C-6 0~

a.

i 0

a u0 o

0 0 1 Group 5 0 1 25 1 Group 6 I

J

COLR Page 7 of 25 Revision 0 Figure ic Regulating Group Position Operating Umits 0 to 300 +/-10 EFPD, Three RC Pumps Davis-Besse 1, Cycle 13 This Figure Is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level Cutoff = 75%

Unacceptable Operation I I I I I I I I Shutdown Margin Limit Acceptable Operation I I I 1I I III 0

25 50 75 100 125 150 175 200 225 250 275 300 0 1 Group 5 75 I 0 1 Rod Index, %Withdrawn 100 I 25 1 75 1 Group 6 100 I 25 1 100 I 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 Umits.

C-7 90 80 70 60 50 0

aJ 0

LI "F

.4-"

0 2

Operation Restricted 40 30 20 10 0

I I

I I

COLR Page 8 of 25 Revision 0 Figure id Regulating Group Position Operating Limits After 300 +/-10 EFPD, Three RC Pumps Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 1 100 Power Level Cutoff = 75%

90 80 70 60 50 40 30 20 10 0

- Unacceptable 111 11 1 1 111 1I-I1 1 1 1 I 1 1" Operation I

I I I A. I I I II I

I I

I II I

I I zl I I I I I¥!

2L Operation

_--Restrictedý Shutdown I, 1.. 11,.,

Margin, n,;

Limit n,

-"Acceptable ':

SOperationi TI I I III I

1.I 1:

I I

I I I I I

I I

0 25 50 75 100 125 150 175 200 225 250 275 300 75 1 Group 5 Rod Index, %Withdrawn 100 I 25 1 Group 6 75 1 0 1 100 I 25 1 100 I 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 Uimits.

C-8

0.

(L

-J W

0 Il I-S.

0-0 I I

I I

I I

I

COLR Page 9 of 25 Revision 0 Figure 2Control Rod Core Locations and Group Assignments Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specification 3.1.3.7 4-N (x) 6 1 4

8 6

3 6

8 4

7 5

5 8

6 7

3 4

3 7

6 jroup Number (Z)

Group No. of Rods Function 1

4 Safety 2

8 Safety 3

4 Safety 4

9 Safety.

9 10 11 12 13 14 15 i

I 4

a 7

5 2

6 8

4 1

5 3

7 6

5 6

84 5

2 8

7 5

2 4

A B

C

'D E

-F

-G

-H (Y)

-K

-L P

R Group No. of Rods Function 5

12 Control 6

8 Control 7

8 Control 8

8 APSRs Total 61 C-9 2

3 2

S 5

2 2

5 7

8 7

8 7

(W) 4 6

4 2

2

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 0 EFPD to 635 EFPD Three or Four RC pumps operation*

Lower Limit: 0 %WD Upper Limit: 100 9oWD

  • Power restricted to 77% for three pump operation C-10 I

COLR Page 11 of 25 Revision 0 Figure 4a AXIAL POWER IMBALANCE Operating Limits 0 to 300 +10 EFPD, Four RC Pumps Davis-Besse 1, Cycle 13 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 EXCORE Note 1: Instrument error Is accounted for in these Operating Umits.

C-1I

Figure 4b AXIAL POWER IMBALANCE Operating Limits After 300 +/-10 EFPD, Four RC Pumps -

Davis-Besse 1, Cycle 13 COLR Page 12 of 25 Revision 1 110 II II I

II.

H I I II

- Restricted Region 11 00 I I I

ri III liii I I01 I.

Thu I I I

N+hHzU Restricted -1 Region El:

III::

II II*I 111111 I

iw I

I ;

I,

I Il Vi I 11111 1 11111111 111111111 IlI I I I

I. i

..1...

I i i i I I.II I.

.I..

I I I..

I.

I I.

I

.I

1.

I I.i i i II l

l1 1111111 I I I I I I A I I I I I I I 6011111 111 IAi liii I Iii ii

III:....

zumziznzm I

I:

I I I I I I U I I I I I I I I I I I I I.z I

I I

I I

  • I I

I III I

11111 II III** I 130 Permissible Operating SRegion I

l l II I

1 I 1

LIZE II I~

I IN I I I I

II I

I FT111 iii...

.J.-I

'U' 111111 i ii ii i ii i i i

.,,-,' i ii i i ii ii 112 IIIIII4 I I 11111 liii liii I liii I 1111 I

1111:11111 I III iii::

I

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE EXCORE --

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

C-12 This Figure is referred to by Technical Specification 3.2.1 I I I I I 111111111 I I :;,,,.,,

zmzluz I

I I I I I I 111 I I I I I I t-I I IJ

]T]Tfffl I I J i

i d

t

=

lin LHIi I

I

' J i I i -ii i !

a

  • I i

Ill SR 1 -

V ii!!

.. i i i iii:

i i

Id i

I I i I

I 1 el i

1 I

I I

IF I

-=

FF ELii I

lJill 60 0*

4oH I

COLR Page 13 of 25 Revision 1 Figure 4c

[ Deleted I C-13

COLR Page 14 of 25 Revision 0 Figure 4d AXIAL POWER IMBALANCE Operating Limits 0 to 300 +10 EFPD, Three RC Pumps Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specification 3.2.1

-50

-40 LEGEND FULL INCORE EXCORE G

-30

-20

-10 0

10 20 30 40 50 AXIAL POWER IMBALANCE %

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

C-14

COLR Page 15 of 25 Revision 1 Figure 4e AXIAL POWER IMBALANCE Operating Limits After 300 +10 EFPD, Three RC Pumps -

Davis-Besse 1, Cycle 13 This Figure is referred to by Technical Specification 3.2.1 100 II

-t9-1 I'l Restricted Region 0

III IIV J

Restricted t Region J Permissible Operating Region

_0 1 I I I I I I 1 1 1 1 1 I It 1 i

-50

-40

-30

-20

-10 0

10 20 30 40 50 LEGEND FULL INCORE AXIAL POWER IMBALANCE %

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

C-15 iii ii: 1111111 liii I C0-110] -I-I I

I l l

i

! i t

% i i i

,t I10 rr1-kC I

COLR Page 16 of 25 Revision 1 Figure 4f

[Deleted I C-16

COLR Page 17 of 25 Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective ULmits This Figure is referred to by Technical Specification 2.1.2 120O

(-43.1,112.0)

(-50.8, 100.0)

(-50.8, 78.9)

UNACCEPTABLE OPERATION

-80

-70

-60

/

I 110 +

100+

(-43.1, 90.9) 4 70+

wt

0.

I-1 C

0W I6 60+

5o0-i 40+

304-20+

104

-50 c Pumps Operating 4

3 (46.0,112.0) 4 PUMP LIMIT (46.0, 90.9) 3 PUMP LIMIT,MI ACCEPTABLE OPERATION FOR SPECIFIED RC PUMP COMBINATION 50

-20

-10 0

10 20 30 40 50 60 70 80 (53.4,100.0)

(53.4, 78.9)

UNACCEPTABLE OPERATION AXIAL POWER IMBALANCE. %

Required Measured Reactor Coolant Flow to Ensure

Flow, rpmC 380,000 389,500 283.860 290,957 C-17 60 70 80 1

l 110+-

w-50

COLR Page 18 of 25 Revision 0 Flux-AFlux/Flow (or Power/Imbalance/Flow)

Allowable Values This Figure Is referred to by Technical Specification 2.2.1

% RATED THERMAL POWER UNACCEPTABLE OPERATION

(-17.0,108.0 MI=+1.00

/

4

(-30.6,94.4)

LI I

I

(-17.0,80.6) 1 IA

(-30.6,67.0)

EX E

I

-60 AMPLE

+60 IACCEPTABLE OPERAT ISPECIFIED RC PUMP 1COMBINATION 40 I

I

-20 I I I

I i

-40

-20 0.-

120 UNACCEPTABLE OPERATION (17.0,108.0)

(30.6,77.1)

ION FOR 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 pumps.

(30.6,49.7)

I,

1 I.

20 40 60 80 AXIAL POWER IMBALANCE, C-18 Figure 6

U U

-80 I

I I

I

COLR Page 19 of 25 Revision 0 Table 1 QUADRANT POWER TILT Limits This Table is referred to by Technical Specification 3.2.4 QUADRANT POWER TILT as measured by:

Steady-state Limit for THERMAL POWER

< 60%

(%)

From 0 EFPD to EOC-13 Steady-state Limit for THERMAL POWER

> 60%

(M)

_____7 Transient Maximum Transient Limit (M) symmetrical Incore 7.90 4.00 10.03 20.0 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 (at RATED THERMAL POWER)

-4.00xlO-4 Ak/k/fF C-19 Maximum Limit (M)

COLR Page 20 of 25 Revision 0 Table 3 Power to Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9G Batch 1OA2 Fuel Assembly Mark-B8A Type Minimum linear heat rate to melt, kW/ft (a) Limit for 3 wt%

(b) Limit for 6 wt%

(c) Limit for 2 wt%

(d) Limit for 3 wt%

(e) Limit for 8 wt%

20.5 Gd Gd Gd Gd Gd rods rods rods rods rods Batch 13 Mark-B8A Mark-BlOA 20.5 Batch Batch Batch Batch Batch 22.3 Batch 14 Mark-BlOM 22.3 (20.8) (a)

(20.8) (b) 14 14 15 15 15 C-20 Batch 15 Mark-BlOK 22.1 (21.11) (C)

(20.7) (d)

(20.3)(e)

COLR Page 21 of 25 Revision 0 Table 4 auuclear Heat Flux Hot Channel Factor -

FO NASI This Table is referred to by Technical Specification 3.2.2 Nuclear Heat Flux Hot Channel Factor - F2 FQ shall be limited by the following relationships:

FQ < LHRALLOW(Bu)/[LHRAVG

  • P]

(for P < 1.0)

LHRALLOW(Bu):

See Tables below LHRAVG - 6.139 kW/ft for Mark-B8A fuel LHRAVG = 6.426 kW/ft for Mark-B10A fuel LHRAVG = 6.420 kW/ft for Mark-BlOM fuel LHRAVG = 6.318 kW/ft for Mark-BlOK fuel P

ratio of THERMAL POWER/RATED THERMAL POWER Bu Fuel Burnup (MWd/mtU)

Batch 9G (Mark-B8AI LHRALLOW kWfft(a) 0 24,500 52,000 60,000 Axial Seament MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1

15.6 15.6 11.8 10.3 2

15.3 15.3 11.8 10.3 3

14.5 14.5 11.8 10.3 4

14.5 14.5 11.8 10.3 5

14.9 14.9 11.8 10.3 6

14.9 14.9 11.8 10.3 7

14.2 14.2 11.4 9.9 8

13.9 13.9 11.2 9.7 Batch 10A2 (Mark-B8A)

LHRALLOW kW/ft(a) 0 24,500 52,000 Axial Seament MWd/mtU MWd/mtU MWd/mtU 1

15.6 15.6 11.8 2

15.3 15.3 11.8 3

14.5 14.5 11.8 4

14.5 14.5 11.8 5

14.9 14.9 11.8 6

14.9 14.9 11.8 7

14.2 14.2 11.4 8

13.9 13.9 11.2 C-21

COLR Page 22 of 25 Revision 0 TABLE 4a continued Batch 13 (Mark-BiOA}

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 14Wd/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 Batch 14 (Mark-BIOM)

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 62,000 MWd/mtU 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 Batch 15 (Mark-BlOK)

LHRALLOW kW/ft(a)

Axial Seciment 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 (a) Linear interpolation for allowable linear heat rate between specified burnup points is valid for these tables.

C-22

COLR Page 23 of 25 Revision 0 Table b Nuclear Heat Flux Hot Channel Factor -

F2 (FIDMS)

This Table is referred to by Technical Specification 3.2.2 Nuclear Heat Flux Hot Channel Factor - FQ FQ shall be limited by the following relationships:

FQ 5 LHRALLOW(Bu)/[LHRAVG

  • P]

(for P < 1.0)

LHRALLOW(Bu):

See Tables below LHRAVG = 6.377 kW/ft P = ratio of THERMAL POWER/RATED THERMAL POWER Bu = Fuel Burnup (MWd/mtU)

Batch 9G (Mark-BSA)

LHRALLOW kW/ft(a)

Core Elevation 0

24,500 52,000 60,000 ft.

MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 16.2 16.2 12.1 10.6 2.506 15.8 15.8 12.1 10.6 4.264 15.0 15.0 12.1 10.6 6.021 15.4 15.4 12.1 10.6 7.779 15.9 15.9 12.1 10.6 9.536 15.3 15.3 12.1 10.6 12.000 14.3 14.3 11.5 10.0 Batch 10A2 (Mark-B8A)

LHRALLOW kW/ft(a)

Core Elevation 0

24,500 52,000 ft.

MWd/mtU MWd/mtU MWd/mtU 0.000 16.2 16.2 12.1 2.506 15.8 15.8 12.1 4.264 15.0 15.0 12.1 6.021 15.4 15.4 12.1 7.779 15.9 15.9 12.1 9.536 15.3 15.3 12.1 12.000 14.3 14.3 11.5 C-23

COLR Page 24 of 25 Revision 0 TABLE 4b continued Batch 13 (Mark-BlOA}

LHRALLOW kW/ft(a)

Core Elevation 0

35,000 62,000 ft.

MWd/mtU MWd/mtU MWd/mtU 0.000 17.6 1"6.8 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 Batch 14 (Mark-BlOMI LHRALLOW kW/ft(a)

Core Elevation 0

35,000 62,000 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 Batch 15 (Mark-BlOK)

LHRALLOW kW/ft(a)

Core Elevation 0

35,000 ft.

MWd/mtU MWd/mtU 0.000-17.6 16.8 2.506 17.6 16.8 4.264 17.1 15.7 6.021 16.6 15.3 7.779 16.0 15.8 9.536 15.3 15.3 12.000 14.5 14.5 (a) Linear interpolation for allowable linear heat rate between specified burnup points is valid for these tables.

C-24

COLR Page 25 of 25 Revision 0 Table 5 Nuclear Enthalpy Rise Hot Channel Factor -

FAH This Table is referred to by Technical Specification 3.2.3 Enthalpy Rise Hot Channel Factor F'IH FIH :S ARP (1 + 0.3(1 -

P/Pm)]

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

  • Allowable Radial Peak for FN&H

..4 JL..J-..

4 4-..J-.4-4-. 44



 



  • 44-111 tILL
ii 4-I I1 -4 izrnzmzrzm 4-4-4 4-4

4-4-4-4-4-4-4-4 4-4 I

I 4

I 4 .-4 4-4 4---4---4-

I 4---I---4-- 4-4-4-4

-.4-4--4-.4-4 -

-I I

i 4-4 4-44

-4 1....,.

tiiiThiiizttLLLLUitlizlIzliU2IIz 121 WI 11 I'll

"'It Iii 4 A L.L.Lii.L.L11i.....L.L..LLL.1....LJ....LL1..I..lJL4Ll.

ThTh

91 9"lI I

JI 156.24" I

I I

-84.36-ir II lII II I I 1.1 1.2 1.3 1.4 1.5 Axial Peak 1.6 1.7 1.8 1.9

  • 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 2.1 2

S1.9 4'

5 1.8 j1.7 E

=M1.6 1.5 iii i i i i i.......... 114&

1 1

"*LNIIO I

i I

I

.'._'.2. "*

i k

4

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