L-08-028, Core Operating Limits Reports for Cycle 16, Revision 0
ML080280310 | |
Person / Time | |
---|---|
Site: | Davis Besse ![]() |
Issue date: | 01/24/2008 |
From: | Bezilla M FirstEnergy Nuclear Operating Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
L-08-028 | |
Download: ML080280310 (32) | |
Text
SFENOC 1EI4J 'c 5501 North State Route 2 FirstEnergyNuclearOperating Company Oak Harbor,Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 January 24, 2008 L-08-028 Davis-Besse Nuclear Power Station, Unit 1 Technical Specification 6.9.1.7 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License No. NPF-3 Core Operatinq Limits Report for Cycle 16 Enclosed, please find the Davis-Besse Nuclear Power Station, Unit 1 Core Operating Limits Report for Cycle 16, Revision 0. Submittal of this report is in accordance with Davis-Besse Nuclear Power Station, Unit 1 Technical Specification 6.9.1.7.
There are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.
Sincerely, Mark B. Bezilla
Enclosure:
FirstEnergy Nuclear Operating Company, Davis-Besse Unit 1, Cycle 16, Core Operating Limits Report, Revision 0 cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Review Board OD-
Cycle 16 COLR Page 1 of 31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 16 CORE OPERATING LIMITS REPORT Prepared by T1e. ie,, /
D. B. Kelle*
Reviewed by . , "
Approved by 7' d LIST OF EFFECTIVE PAGES Page C-1 through C-31 Rev. 0 C-1
Cycle 16 COLR Page 2 of 31 Revision 0 Technical Specification/COLR Cross-Reference Technical Specification COLR Figure/Table 3.1.3.6 Figure la Regulating Group Position Operating Limits, and 0 to 300 +/-10 EFPD, Four RC Pumps, 2772 3.1.3.8 MWt 3.1.3.6 Figure lb Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Four RC Pumps, 2772 3.1.3.8 MWt 3.1.3.6 Figure Ic Regulating Group Position Operating Limits, and 0 to 300 +/-10 EFPD, Three RC Pumps, 2772 3.1.3.8 MWt 3.1.3.6 Figure ild Regulating Group Position Operating Limits, and After 300 +/-10 EFPD, Three RC Pumps, 3.1.3.8 2772 MWt 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments 3.1.3.9 Figure 3 APSR Position Operating Limits, 2772 MWt 3.2.1 Figure 4a AXIAL POWER IMBALANCE Operating Limits, 0 to 350 +/-10 EFPD, Four RC Pumps, 2772 MWt 3.2.1 Figure 4b AXIAL POWER IMBALANCE Operating Limits, 350 +/-10 to 600 +/-10 EFPD, Four RC Pumps, 2772 MWt 3.2.1 Figure 4c AXIAL POWER IMBALANCE Operating Limits, After 600 +/-10 EFPD, Four RC Pumps, 2772 MWt 3.2.1 Figure 4d AXIAL POWER IMBALANCE Operating Limits, 0 to 350 +/-10 EFPD, Three RC Pumps, 2772 MWt 3.2.1 Figure 4e AXIAL POWER IMBALANCE Operating Limits, 350 +/-10 to 600 +/-10 EFPD, Three RC Pumps, 2772 MWt C-2
Cycle 16 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 MWt 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits, 2772 MWt 2.2.1 Figure 6 Flux -A Flux/Flow (or Power/Imbalance/Flow) Allowable Values, 2772 MWt 3.2.4 Table 1 QUADRANT POWER TILT Limits, 2772 MWt 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), 2772 MWt 3.2.2 Table 4b Nuclear Heat Flux Hot Channel Factor - FQ (FIDMS), 2772 MWt 3.2.3 Table 5 Nuclear Enthalpy Rise Hot Channel Factor -
FNH F AH 3.2.3 Figure 7, Maximum Allowable Radial Peak for FNAH in Mark-B Fuel Assemblies 3.2.3 Figure 8 Maximum Allowable Radial Peak for FNAH in Mark-BHTP Fuel Assemblies 3.2.3 Table 6 Maximum Allowable Radial Peak for FNAH in Mark-B Fuel Assemblies 3.2.3 Table 7 Maximum Allowable Radial Peak for FNAH in Mark-BHTP Fuel Assemblies C-3
Cycle 16 COLR Page 4 of 31 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 16 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 16 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 16 is 741.8 EFPDs (based on a reactor thermal rating of 2772 MWt which is equivalent to 730 EFPDs at 2817 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, FNAH 2.0 References
- 1) BAW-10179P-A, Rev. 6, "Safety Criteria and Methodology For Acceptable Cycle Reload Analyses", August, 2001. _
- 2) BAW-10164P-A, Rev. 6, "RELAP5/MOD2-B&W -An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis",
June, 2007.
C-4
Cycle 16 COLR Page 5 of 31 Revision 0
- 3) BAW-10243P-A, "Statistical Fuel Assembly Hold Down Methodology",
September, 2005.
C-5
Cycle 16 COLR Page 6 of 31 Revision 0 Figure la Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Four RC Pumps--2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 III I I I Power Level I I iI ii T41+
100 Cutoff = 100%
1.11 1 1 1 1 1 1 1 90 Operation u2J Unacceptable 0
80 0~ i i i i -i -j H4fl4+ 1 'I-+4-
-J f- Operation 70 Shutdown Restricted ll Margin 60 Limit 4)- l-I I-50 (D
40 C.,
()
0~
0 30 Acceptable E)
O~ Operation 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 75 100 P I Group 5 01 25 75 100 I
I I I I Group 6 01 Zb I 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 Limits.
C-6
Cycle 16 COLR Page 7 of 31 Revision 0 Figure lb Regulating Group Position Operating Limits After 300 +10 EFPD, Four RC Pumps --2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 ' P0ower'L'ev'el'
'Cutoff=100%
90 0~
80 Unacceptable:
1-J Operation -
I I 70 All!l 1111IN1111111111 Operation
-H-i-H-H-I-V 60 Restricted Shutdown #4t Margin M, I I I I I I I I ,-
I 0 50 Limit 40 CD a) 0~ 30 Acceptable IL Operation 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0
1 75 100 I.
Group 5 0 25 75 100 1 1 I Group 6 0I 25 100 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 Limits.
C-7
Cycle 16 COLR Page 8 of 31 Revision 0 Figure lc Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level -
Cutoff = 75%
I I I I 90 80 0~ a 70 + Unacceptable --11i
- Operation
-LJ I I I I I i I I 60 Operation Shutdown Restricted ::
50 _ Margin I I I II i Ii Limit 40 0
(L 30 20
[ i l; . ... : IIJ' ii: Acceptable -i iII 1 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0 75 100 1 I Group 5 01 25 75 100 I
Group 6 0 25 100 1 1 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 Limits.
C-8
Cycle 16 COLR Page 9 of 31 Revision 0 Figure ld Regulating Group Position Operating Limits After 300 +10 EFPD, Three RC Pumps --2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 90 W
w:
0 80 CL 70 w
I 60 0-50 0 40 a.
30 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 10 75 100 I
Group 5 0 25 75 100 1 1 I Group 6 01 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 Limits.
C-9
Cycle 16 COLR Page 10 of 31 Revision 0 Figure 2 Control Rod Core Locations and Group-Assignments Davis-Besse 1, Cycle 16 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 1 11 1 1 1 1 I 1 1 1 A
B C
D E
F G
(W) H (Y)
K L
M N
0 P
R
=--Group Number (Z)
Group No. of Rods Function 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 Tot*al 61 C-iO
Cycle 16 COLR Page 11 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 675 +/- 10 EFPD, Three or Four RC pumps operation Lower Limit: 0 %WD Upper Limit: 100 %WD After APSR Pull: 675 +/- 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-1I
Cycle 16 COLR Page 12 of 31 Revision 0 Figure 4a AXIAL POWER IMBALANCE Operating Limits 0 to 350 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specification 3.2.1 I 1111111 Irl l iiil IIi iii I I I I I II
-I Restricted I I I ill Restricted Region Region 91) 80 iT
-40 Permissible Operating Region III InJ
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for inthese operating Limits. FULL INCORE EXCORE C-12
Cycle 16 COLR Page 13 of 31 Revision 0 Figure 4b AXIAL POWER IMBALANCE Operating Limits 350 +10 to 600 +10 EFPD, Four RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 16 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 C-13
Cycle 16 COLR Page 14 of 31 Revision 0 Figure 4c AXIAL POWER IMBALANCE Operating Limits After 600 +/-10 EFPD, Four RC Pumps-2772 MWt RTP Davls-Besse 1, Cycle 16 This Figure Is referred to by Technical Specification 3.2.1
-r'M I I I I 1 1110 1 1 1 1 1 1 1 1 1 T7 110 Restrictedon Restricrted Region Region II
-o
.n LL
-14ý I
- 0 Permissible 44-4T-4 Operating Region
- w nI.-
-a)
-0
-I
-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 C-14
Cycle 16 COLR Page 15 of 31 Revision 0 Figure 4d AXIAL POWER IMBALANCE Operating Limits 0 to 350 +10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Specification 3.2.1 Rreicted Region Region
.4 ý7oi 6
.w
"- 40.
e--
PermissIble Operating
,,.t Region III 0
-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 Umits. FULL INCORE EXCORE C-15
Cycle 16 COLR Page 16 of 31 Revision 0 Figure 4e AXIAL POWER IMBALANCE Operating Limits 350 +10 to 600 +/-10 EFPD, Three RC Pumps-2772 MWt RTP Davis-Besse 1, Cycle 16 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 0
C-16
Cycle 16 COLR Page 17 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 16 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 % .EGENQ Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE
-8 C-17
Cycle 16 COLR Page 18 of 31 Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2772 MWt RTP This Figure is referred to by Technical Specification 2.1.2 120-(-37.22, 112.0) (35.29, 112.0) 4
/
110+
4 PUMP LIMIT
(-45.54, 100.0) 100+ (45.88, 100.0)
(-37.22, 90.7) (35.29, 90.7)
-nfl. 4-
- U 3 PUMP LIMIT \
(-45.54, 78.7) 80+ (45.88, 78.7) 70+
UNACCEPTABLE w UNACCEPTABLE OPERATION 03.. OPERATION 60+
a 1- 50+
I--
I-2 0 40+ ACCEPTABLE wl OPERATION 0 FOR SPECIFIED 30+ RC C
PUMP COMBINATION 20+
10+
fl~j * .1~
-80 -70 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 AXIAL POWER IMBALANCE, %
Required Measured Reactor Coolant Flow to Ensure -
Pumps Operating Flow, qpm Compliance, qpm 4 380,000 389,500 3 283,860 290,957 C-18
Cycle 16 COLR Page 19 of 31 Revision 0 Figure 6 Flux-AFlux/Flow (or Power/Imbalance/Flow)
Allowable Values This Figure Is referred to by Technical Specification 2.2.1
% RATED THERMAL POWER UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION Curve shows trip
(-17.0,108.0). (17.0,108.0) setpoint for an approximately M1=+1 .00 .25% flow reduc-
,tion for three pump operation
(-30.6,94.4) (283,860 gpm).
The actual set-point will be
(-17, calculated by the Reactor Protection
.System and will be 30.6,67.0) directly propor-tional to the I l. rI . 1 60 I actual flow with three DumDs.
IACCEPTABLE OPERATION FOR ISPECIFIED RC PUMP 0 (30.6,49.7) 1COMBINATION 40 i I
,I 20 I I .I I II I I __
-80 -60 -40 -20 0 - 20 40 60 80 AXIAL POWER IMBALANCE, %
C-19
Cycle 16 COLR Page 20 of 31 Revision 0 Table 1 QUADRANT POWER TILT Limits N
2772 MWt RTP This Table is referred to by Technical Specification 3.2.4 From 0 EFPD to EOC-16 Steady-state Limit for THERMAL Steady-state Limit POWER > 60% Transient Limit QUADRANT for THERMAL POWER TILT POWER < 60% Maximum Limit as measured by: (%) (%) (%) (%)
Symmetric Incore 7.90 4.25 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 -3.76x10_4 Ak/k/0F
(@ RATED THERMAL POWER)
C-20
Cycle 16 COLR Page 21 of 31 Revision 0 Table 3 Power To Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9K Batch 15 Batch 16 Batch 17 Batch 18 Fuel Assembly Type Mark-B8A Mark-B1OK Mark-B12 Mark-B-HTP Mark-B-HTP Minimum linear heat 20.5 22.1 22.1 22.1 22.1 rate to melt, kW/ft (21.1 )(a) (20.3)(c) (20.1 )(e) (20.1 )(e)
(19. 3 )(b) ( 1 9 .3 )(d) (19.1 )(M (19.1 )(f)
(a) Limit for 2 wt% Gd 20 3 rods - Batch 15 (b) Limit for 8 wt% Gd2 0 3 rods - Batch 15 (c) Limit for 4 wt% Gd 2 0 3 rods - Batch 16 (d) Limit for 8 wt% Gd 20 3 rods - Batch 16 (e) Limit for 4 wt% Gd 2 0 3 rods - Batches 17 and 18
( Limit for 8 wt% Gd 2 0 3 rods - Batches 17 and 18 C-21
Cycle 16 COLR Page 22 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 FQ FQ shall be limited by the following relationships:
F0 < LHRALLIw (Bu) / [LHRAVG
- P] (for P *1.0)
LHR allw (Bu) = See the following tables LHR av = 6.3095 kW/ft at 2772 MWt for Batch 9K Mark-B8A fuel LHRavg = 6.3183 kW/ft at 2772 MWt for Batches 15C3 and 15E Mark-B1 OK fuel LHRavg= 6.3183 kW/ft at 2772 MWt for Batches 16C2, 16D2 and 16E2 Mark-B12 fuel LHRavg = 6.3294 kW/ft at 2772 MWt for Batch 17A-E Mark-B-HTP fuel LHRavg = 6.3183 kW/ft at 2772 MWt for Batch 18A-C Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = fuel burnup (MWd/mtU)
Batch 9K U02 Fuel(Mark-B8A) LHRALL-w kW/ftu 0 24,500 52,000 60,000 Axial Seqment 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 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-22
Cycle 16 COLR Page 23 of 31 Revision 0 Table 4a, (Continued)
Batch 15C3 and 15E U02 Fuel (Mark-B10K) LHRAkk~w kW/ftu 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 16C2, 16D2, and 16E2 U02 Fuel (Mark-B12) LHR ALLw kW/ft*
0 35,000 58,000 59,000 60,000 62,000 Axial Segqment 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 17A-17E U02 Fuel (Mark-B-HTP) LHRALLkw kW/ftP 0 40,000 62,000 Axial Segqment MWd/mtU MWd/mtU MWd/mtU' 1 17.6 17.2 13.6 2 17.5 17.1 13.5 3 17.1 16.7 13.2 4 17.0 16.7 13.2 5 16.5 16.2 13.1 6 15.9 16.0 13.1 7 15.3 15.4 12.8 8 15.1 15.2 12.6 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-23
Cycle 16 COLR Page 24 of 31 Revision 0 Table 4a , (Continued)
Batch 18A-18C U02 Fuel (Mark-B-HTP) LHR AL"w kW/ftw 0 40,000 62,000 Axial Secqment MWd/mtU MWd/mtU MWd/mtU 1 17.6 17.2 13.6 2 17.5 17.1 13.5 3 17.1 16.7 13.2 4 17.0 16.7 13.2 5 16.5 16.2 13.1 6 15.9 16.0 13.1 7 15.3 15.4 12.8 8 15.1 15.2 12.6 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-24
Cycle 16 COLR Page 25 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 F-FQ shall be limited by the following relationships:
FQ < LHR (Bu) / [LHRAvG
- P] (for P < 1.0)
LHRallw (Bu) = See the following tables LHRavg = 6.3095 kW/ft at 2772 MWt for Batch 9K Mark-B8A fuel LHR-vg = 6.3183 kW/ft at 2772 MWt for Batches 15C3 and 15E Mark-B1OK fuel LHRvg = 6.3183 kW/ft at 2772 MWt for Batches 16C2, 16D2 and 16E2 Mark-B12 fuel LHRavg = 6.3294 kW/ft at 2772 MWt for Batch 17A-E Mark-B-HTP fuel LHRa,, = 6.3183 kW/ft at 2772 MWt for Batch 18A-C Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = fuel burnup (MWd/mtU)
Batch 9K - U02 Fuel LHRALLow kW/ft*
Core Elevation 24,500 52,000 60,000 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 16.3 16.3 12.0 10.2 I
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 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batches 15C3 and 15E - U02 Fuel LHRALLOw kW/ft*
Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 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 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-25
Cycle 16 COLR Page 26 of 31 Revision 0 Table 4b, (Continued)
Batch 16C2, 16D2, and' 16E2 - U02 Fuel LHR ALLOw kW/ft*
Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 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 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batch 17A-E - U02 Fuel LHRALLOw kW/ft*
Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 17.6 17.2 13.6 2.506 17.6 17.2 13.6 4.264 17.2 16.8 13.3 6.021 17.0 16.7 13.2 7.779 16.5 16.2 13.1 9.536 15.9 16.0 13.3 12.000 15.1 15.2 12.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batch 18A-C - U02 Fuel LHRALLw kW/ft*
Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 17.6 17.2 13.6 2.506 17.6 17.2 13.6 4.264 17.2 16.8 13.3 6.021 17.0 16.7 13.2 7.779 16.5 16.2 13.1 9.536 15.9 16.0 13.3 12.000 15.1 15.2 12.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batch 15 - 2 wt% Gadolinia Fuel LHRALL~w kW/ft*
Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 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 12.8 7.779 15.0 14.8 13.4 13.3 13.3 12.8 9.536 14.3 14.3 13.0 12.9 12.9 12.8 12.000 13.6 13.6 12.4 12.3 12.3 12.2 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-26
Cycle 16 COLR Page 27 of 31 Revision 0 Table 4b, (Continued)
Batch 16- 4 wt% Gadolinia Fuel LHR LL kW/ft*
Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 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 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batches 15 and 16 - 8 wt% Gadolinia Fuel LHRALLOw kW/ft*
Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 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 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batches 17 and 18 -4 wt% Gadolinia Fuel LHRALLOw kW/ft*
Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 15.8 15.7 12.3 2.506 15.8 15.7 12.3 4.264 15.4 15.2 12.0 6.021 15.2 15.1 11.9 7.779 14.8 14.7 11.8 9.536 14.3 14.5 12.0 12.000 13.6 13.8 11.4 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
Batches 17 and 18 - 8 wt% Gadolinia Fuel LHRALLOw kW/ft*
Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 14.9 14.9 11.5 2.506 14.9 14.9 11.5 4.264 14.5 14.6 11.2 6.021 14.4 14.5 11.1 7.779 13.9 14.0 11.0 9.536 13.4 13.9 11.2 12.000 12.7 13.2 10.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.
C-27 r
Cycle 16 COLR Page 28 of 31 Revision 0 Table 5 Nuclear Enthalpy Rise Hot Channel Factor - F-NH This Table is referred to by Technical Specification 3.2.3 Enthalpv Rise Hot Channel Factor FUH FNH < MARP [1 + 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 FNH in Mark-B Fuel Assemblies SI I_ L 1 L ii 7 I I - - I I L J I L 1 1 I I I
. .. 7. . T -F - - -1 - - T i F - i T -- - F -
1.4 1' 1 T -I - - - - - -- -- r----- I -- -- T r- I- 7 -- - -
I I" It i *"I I -"* , 1 - - I i TI- - - - - F- - *
- 1. 1-7 T r I T -r -1 1- -- 7 - i-i-rr
-r -- -- L - s-- r - -r -
I- 1.2- . I- 1 .1 1.7 1. 1.
I- I L- 1I L I I 1 .NI L L . .
V-I - -- - -- -I I 7 - --
A
- -I- ia Peak - - - --- 1I - - -" -- - -r --
S I I-- -I0.I - - T Ir I I Iv I I t I I II I " I" " I J*
" I- L I Je L L" -L i -I" -I 1 -1 I- - L L -I I -I- .. - L .
- 17~ . .. . . . . . . . T T . F.. .
Thfrspa taM-ui o Lin terpolattraaio in i L j1 I I I I I- I I I I I I I L
" -I-7 T --- 7 - T - r I-7 T F-i i 7 7 r- I T F/ I I -* T .... .. 4 - -rI r 1.6 -I 17 - r I- T - r -I- - T - -F- :-6. - -I - - - -1
-- I-- --
r - - -i - rI-r,- - - -4
- ,- t- r- - 1 I--7Ir-r- -- 17 1 I- - - 71 -
- - N-I x/L =U, 0. 1' -- _ I + L II I J L L I J L I. L -I- J -L. L-
"**-II 1L,- 0.4 T 'r I- " T " I 1 - 11 -1"- IT 1 I 71 - r i - r 1I -I- r - . . .
- ~~~-k-IL = 0.6 -- - - f-q- - ---4 -- 1- I-1--- -t- 4 -- l -- -- I I
... L l J I L- J'1 L J - J- - L I k . .. I L JL -I I - LL . *Jt *I. L _
" -- I1- 1 - 0. * *1 L - I -- -" -
T L j"
- 1 L -j
--I F LT abv of 0. ar acetbe
-I T - I- -I-7 T L/ Fo aiL hegt <L of 0.2 the vau at xIL0.2 wL r 1i T r IF i 1 T 1 I" 71 1 1 I T - J - 11 T I " ] r I - - r' ]
be- used.
I I - -
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
Cycle 16 COLR Page 29 of 31 Revision 0 Figure 8 Maximum Allowable Radial Peak for FAH in Mark-BHTP Fuel Assemblies 2.1 -
--*-x/L-0.14 2.0 F- i I F 7 T -4l-x/L = 0.2 I -&-x/L = 0.4
-- O-x/L = 0.5 1.9 7 T -7 F T 7 7 T n T T - r -I- I T r 1 1 7 r -x/L = 0.6 1 4
+
I Lt -,6-x/L = 0.8 1 1.8 t F i T I L- -- --*-./L = 0.88 I T
-1 t -,X-- x/L = 0.9
-- I.-X/L = 1.0
.2 1.7 - - - - - --- - - - T - - -I I- I I -i -TI 11- 4 F 1 7 - F 4- 4 1.6 L -L L -1 1 L -1 -1 L -I-i T r -i- -I- I T-1.5 L L
L -1 I- - - - - L - - -
L L 1I T T - -1 T.
II1.4 T
T F I T F 7 7 'T LI r q r I
- -- - - - - - --- - - - - . T. . I. - I 1.3 . . . . . . . . . . . . .
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-HTP fuel in the core. Linear interpolation is acceptable.
The MARP values are based on an active fuel height of 142.75 inches.
C-29
Cycle 16 COLR Page 30 of 31 Revision 0 Table 6 Maximum Allowable Radial Peak for FAH in Mark-B Fuel Assemblies Axial Peak x/L Axial Height (inches) MAP Limit MARP Limit 0.2 28.12 2.0415 1.9264 0.4 56.24 2.0345 1.9198 1.1 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 0.4 56.24 2.8272 1.9564 1.5 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 16 COLR Page 31 of 31 Revision 0 Table 7 Maximum Allowable Radial Peak for F'AH in Mark-BHTP Fuel Assemblies Axial Axial Axial Height MARP Axial Height MARP Peak x/L (inches) MAP Limit Limit ,Peak XIL (inches) MAP Limit .Limit 0.0 0.000 2.03286 1.91828 0.0 0.000 2.79510 1.81 332 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 1.71 924 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 2.691 95 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 1.71 250 0.6 85.650 2.32916 2.01472 0.6 85.650 2.771 65 1.69234 0.8 114.200 2.15618 1.86510 0.8 114.200 2.52074 1.539 13 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 1.51 542 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 1.61 867 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 2.851 22 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 85.650 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 2.521 66 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 1.918 11 0.1 14.275 2.66225 .1.84228 0.14 19.985 2.63504 1.82345 0.2 28.550 2.69706 1.86637 y0.4 57.100 2.751 39 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 1.59 179 0.9 128.475 2.30907 1.59788 1.0 142.750 2.15988 1.49464 C-31I