ML20211B729
| ML20211B729 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/16/1999 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20211B719 | List: |
| References | |
| NUDOCS 9908250069 | |
| Download: ML20211B729 (28) | |
Text
1 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 i
ATTACHMENT CORE OPERATING LIMITS REPORT CYCLE 11, REVISION 2 l
9908250069 990818 PDR ADOCK 05000302-P PDR
L Florida Power Corporation Crystal River Unit 3 4
Cycle 11 Core Operating Limits Report Revision 2 l
l l
i 1
I Referencing Improved Technical Specifications i
I
7 Crystal River Unit 3, Cycle 11 1.0 Cor: Cperating Limits This Core Operating Limits Report for CR3 Cycle 11 has been prepared in accordance with the requirements of Technical Specification Section 1.1 and 5.6.2.18. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.
These methods are documented in BAW-10179PA, Rev.1 " Safety Critera and Methodology for Acceptable Cycle Reload Analyses", NRC Letter R. Jones to J.H. Willoughby dated January 22, 1996. The Cycle 11 limits generated using this methodology above are documented in BAW-2262,
" Crystal River Unit 3 Cycle 11 Reload Report", dated January 1996, BAW-2262, Rev. I dated December 1997, and BAW-2262 Rev. 3 dated June 1999.
Note that BAW-2262 Rev. 2 examined the impact of an error in accounting for Gadolinium (Gd) pins on the Cycle 11 Linear Heat Rate-to-Centerline Fuel Melt limits. FCF did not apply the proper uncertainty to account for Gd pin loading. However, by taking advantage of margin in
]
l the maneuvering analyses, the existing limits were found to remain bounding. The revision did I
not require a change to the COLR.
The following limits are included in this report.
l SL 2.1.1.1 AXIAL POWER IMBALANCE PROTECTIVE LIMITS SL 2.1.1.2 AXIAL POWER IMBALANCE PROTECTIVE LIMITS LCO 3.1.1 SHUTDOWN MARGIN i
LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT l
SR 3.1.7.1 API /RPI POSITION INDICATION AGREEMENT LCO 3.2.1 REGULATING ROD INSERTION LIMITS LCO 3.2.2 AXIAL POWER SHAPING ROD INSERTION LIMITS LCO 3.2.3 AXIAL POWER IMBALANCE OPERATING LIMITS LCO 3.2.4 QUADRANT POWER TILT LCO 3.2.5 POWER PEAKING FACTORS LCO 3.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LCO 3.9.1 REFUELING BORON CONCENTRATION I
Page 2 l
l Crystol River Unit 3, Cycle 11 Axial Power Imbalance Protective Limits 1
i l.
120 -
(-44.13,112)
(
110 4 100 -
Acceptable 4 Pump Operation
__i
(-44.13,90.56)
(44.14,90.56)
< (-73.87,80.
80 ~
(.89,80.58)
Acceptable 3 and 4 Pump Operation 70 -
a (.73.87,59.16) 60 -
(73.89,59.14) lThis Figure is referred to by T.S. SL 2.1.1.1 l 50 -
lThis Figure is referred to by T.S. SL 2.1.1.2 l
% Rated Thermal Power 30 -
l 20 -
10 O
o-4 t-o
+
-80
-60
-40
-20 0
20 40 60 80 Axial Power Imbalance %
1 1
l l
l i
Page 3 1
L.
Crystal River Unit 3, Cycle 11 Shutdown Margin (SDM)
Operating procedures require RCS boration to 1.0%Ak/k Subcritical at 73*F prior to bypassing EFIC actuation on low steam generator pressure, therefore Mode 1,2,3,4,5 SDM 21.0% Ak/k These limits are referred to by Technical Specification LCO 3.1.1 l
}
4 Page 4
a l'
' Crystal River Unit 3, Cycle 11 Moderator Temperature Coefficient Limit
' Lower Limit MTC at HFP >'-3.58x104 A k/k/oF l
Upper Limit MTC s 0.9x104 A k/k/oF when Thermal Power < 95% RTP MTC s 0.0 when Thermal Power 2 95% RTP l
These limits are referred to by Technical l
Specification l
1
{
i i
l l-l u
Page5
)
Crystal River Unit 3, Cycle 11 Absolute Position Indicator / Relative Position Indicator Agreement Limits 2.7% when the comparison is performed using the plant computer, or I
3.5 % when the comparison is performed using the panel meters on the main control board.
These limits are referred to by Technical Specification SR 3.1.7.1 I
l i
Page 6 l.
I L
Crystcl River Unit 3, Cycle 11 Regulating Rod Group Insertion Umits Four Pump Operation 0 to 250110 EFPD 110 (300,102)
(90,102)
(265,102)-
Unacceptable (255'92) 90 -
Restricted Operation Operation 80 -
(245,80) 70 -
Ic.
T l
60 -
(49.60)
(225,60)
{
t
$c 50 -
g Acceptable l
c f
Operation
. a.
40 +
30 -
lThis figure is referred to by Technical Specification LCO 3.2.1 l l
W 20 (20,20) 10 - (0,8.7)
Note 1: A rod group overlap of 25 5% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained t
0+
0 50 100 150 200 250 300 Rod index, % Withdrawn Page 7
Crystal River Unit 3, Cycle 11 Regulating Rod Group insertion Limits Four Pump Operation after 250110 EFPD to 600110 EFPD 110 (300,102)
(196,102)
(265,102) -
0 Unacceptable (255,92) 90 Operation Restricted 80 (245,80) 70 -
15 60 (119,60)
(225,60) 5
?
50 -
Acceptable X
J Operation 40
[This figure is referred to by Technical Specification LCO 3.2.1 l 30 --
20 1 (84,20) 10 -
Note 1: A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained
,5.8) 0 0
50 100 150 200 250 300 Rod index, % Withdrawn Page 8
o Crystal Rivcr Unit 3, Cycle 11 l
Regulating Rod Group Insertion Limits Four Pump Operation after 600110 EFPD 110 l
(200,102)
(265,102) -(300,102):
100 -
(255,92) 90 Unacceptable Operation 80 +
(245,80)
Restricted adon 70 -
i E 60 --
(140,60)
(225,60) 5 h
Acceptable 5
50 -
Operation a
40 (This figure is referred to by Technical Specification LCO 3.2.1 l 30-20 (87,20)
Note 1: A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 10 _
and 7 shall be maintained
- 3) Note 2: This figure shall be used up to, during, after APSR withdrawal per LCO 3.2.2 01, 0
50 100 150 200 250 300 Rod index, % Withdrawn Page 9
Crystal River Unit 3, Cycle 11 Regulating Rod Group Insertion Limits Three Pump Operation 0 to 250110 EFPD 110,
100 -
90 4 80 -
(265,77)_ (300,77)f Unacceptable (90,77)
Operation I
)
Operation Restricted l
60 (245,60) i k
50 e
(49,45.5)
(225,45)
Ic.
40 t Acceptable Operation This figure is referred to by Technical Specification LCO 3.2.1 20 -
(20,15.5) 10 -
(0,7) Note 1: A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained 04 i
0 50 100 150 200 250 300 Rod Indwx, % Withdrawn Page 10
F 1
l Crystal River Unit 3, Cycle 11 l
l Regulating Rod Group insertion Limits Three Pump Operation 250110 to 600110 EFPD H0 100 -
90 +
Unacceptable 80 -
(196,77)
(265,77) -(300,77),
5 Operation
)
70 -
2 (255,69)
E 5
60 -
M aed (245,60)
I"
]
Operation j
50 -
e}
(119,45.5)
(225,45)
$ 40 -
E Acceptable
^
Operation 20 (84,15.5) 10 -
This figure is referrsd to by Technical Specification LCO 3.2.1
.(0,4.9 Note 1: A rod group ovedap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained 0
O 50 100 g
200 250 300 Page11
Crystal River Unit 3, Cycle 11 Regulating Rod Group Insertion Limits Three Pump Operation after 600110 EFPD 110 100 90 -
80 -
(300,77)
(200,77)
(265,77)-
na cepWe 70 -
(255,69) a Operation 2
Restricted l
60 -
(246,60)
Operation I
k 50 -
kte (140,45.5)
(225,45)
Q.
40 -
Acceptable
/
)
/
30 --
Operation This figure is referred to by Technical Specification LCO 3.2.1 20 --
(87,15.5)
Note 1: A rod group overlap of 2515% between sequential 10 withdrawn groups 5 and 6, and 6 and 7 shall be maintained
,4.5)
Note 2: This figure shall be used up to, during.and after APSR l
withdrawal per LCO 3.2.2 04 0
50 100 150 200 250 300 Rod index, % Withdrawn t
Page 12
Crystal River Unit 3, Cycle 11 Axial Power Shaping Rod Insertion Limits Up to 640 EFPD the APSRs may be positioned as necessary. The APSRs shall be completely withdrawn (100%) by 660 EFPD. Once withdrawn during this period,640EFPD to 660EFPD the APSRs shall not be reinserted for the remainer of the cycle.
These limits are referred to by Technical l
Specification LCO 3.2.2 L
t-Page 13 E
Crystal River Unit 3, Cycle 11 Axial Power imbalance Operating Umits Four Pump Operation 0 to 250110 EFPD 110-l
(-24,102)
- (25,102) 100 -
l
(-27.6,92)
(28.5,92) 90 -
(35.2,80) i (-32.8,80) 80 --
i Acceptable Operation Acceptable Operation f
70 -
l ll (-33,60) 60 --
l(36,60) lThis Figure is referred to by T.S. LCO 3.2.3 l 50 +
40 -
l i
30 -
% Rated Thermal Power 20 10 l
t l
l si 0-t 11 l
-40
-30
-20
-10 0
10 20 30 40 Axial Power imbalance %
Page 14 i
Crystal River Unit 3, Cycle 11 Axial PowerIntstance Emelope FourRnpOperation 250i10b50&t10EFPD 110 j
~('
}
(-21,102) 100 --
(-23.9,92)
(24B,92) 90 y i (32,m) m.
(256,80)
Aa:eptadeOperaton AxxpadeOperaton 70 o (aeo) 00-i(m.m)
This Figtse is referred b by T.S. LOO 32.3 1
4 30.
% Rated Themal Power 20 4 10 0
i i
n F
n 40
-30
-20
-10 0
10 20 30 40 Axial Powerimbalance %
Page 15
Crystal River Unit 3, Cycle 11 Axial Powerimbalance Envelope Four Pump Operation 500110 to 600110 EFPD 110 -
(-24,102)
- (-20,102)
(-27.6,92) i(24.8,92) y 1 (-35.2,80) 80 -
l (25.6,80)
Acceptable Operation Acceptable Operation 70 -
ll (-36,60) 60 -
II (36,60)
This Figure is referred to by T.S. LCO 3.2.3l 40 -
30 -
% Rated Thermal Power 20 1 10 -
si
+
O ll
-40
-30
-20
-10 0
10 20 30 40 Axial Powerimbalance %
Page 16
i Crystal River Unit 3, Cycle 11 Axial PowerInhalance Envelope
)
Fotr RnpOperdion dier600110EFPD 110 T
(-24,102)
(24,102)
,gg
(-29.4,92)
I(24.8,92) gg,
i (-35.2,80) m-i(25.e,80) 3 Axwiecp.sion AmtweOpersion i
70 iI(-36,60) 60 -
l(36,60) 50 - TMs FKpe is referTed to by T.S. LOO 3.23l 40 +
30 7
%RatedThommi Pour 20 }
10 -
1-il 0
ll
-40
-30
-20
-10 0
10 20 30 40 Axial Pcwsrkrbelance%
Page 17
1 Crystal River Unit 3, Cycle 11 Axial Power Imbalance Envelope Three Pump Operation 0 - 250110 EFPD 110 --
100 -
90 -
(-24,77) -
~
- (25,77) 70 -
(-27.6,69)
(28.5,69)
Acceptable Operation I
(-32.8,60) 60 +
(35.2,60) 50 11(-33,45)
(
This Figure is referred to by T.S. LCO 3.2.3 l
ll(36,45) 40 -
% Rated Thermal Power 30 -
2 T
10 -
ii
-+
0 ei
~40 -
-30 20
-10 0
10 20 30 40 i
Axial Power Imbalance %
i I
l Page 18 L-
Crystal River Unit 3, Cycle 11 Axial Powerimbalance Envelope Three Pump Operation l
250110to500110 EFPD 110 T 100-90 --
(-21,77)
~
- (19,77) 70 -
(-23.9,69)
(24.8,69)
Acceptable Operation
-32,60) 60 -
(25.6,60) 50 -
ii(-33,45) lThis Figure is referred to by T.S. LCO 3.2.3 i(36,45) 40 --
30 1
% Rated Thermal Power l
20 -
10 -
F si
+
0 si
-40
-30
-20
-10 0
10 20 30 40 Axial Powerimbalance %
l t
Page 19 t.
F l
l l
Crystal River Unit 3, Cycle 1i l
Axial PowerImbalance Envelope Three Pinp Operation 1
l 500i10to600i10 EFPD 110 -
l l
100-90 -
80 -
(-24,77) _
- (20,77)
(-27.6,69) 70 -
(24.8,69) weoperation 1 -35.2,60) 60 -
(25.6,60) l 50 -
1I(-36,45)
[This Figure is referred to by T.S. LCO 3.2.3) l (36,45) 40 _
i 30 -
% Rated 1hermalPower 20 -
10 -
F - il 0-
-+
ll
-40
-30
-20
-10 0
10 20 30 40 Axial Powerintialance%
4 Page 20 IL
r:
Crystal River Unit 3. Cycle 11 i
t Axial Power Imbalance Envelope l
Three Pump Operation after600110 EFPD 110 100 -
90 -
(-24,77) 80 -
- (24,77) 70
(-29.4,69) i (24.8,69)
Acceptable Operation I (-35.2,60) 60 --
(25.6,60) 50 -
" (~
}
l (36,45) fhis Figure is referred to by T.S. LCO 3.2.3 l 40 -
l 30 -
% Rated Thermal Power l
20 -
10 -
F-n 0
n ---i
-40
-30
-20
-10 0
10 20 30 40 Axial Power imbalance %
l i
i i
f Page 21 l
Crystal River Unit 3, Cycle 11 Quadrant Power Tilt Limits For Operation from 0 EFPD to EOC Thermal Power s 60% RTP Steady State Transient Maximum Symmetrical Incore Detector System 7.50 10.03 20.00 Power Range Channels 4.94 6.%
20.00 Minimum Incore Detector System 3.07 4.40 20.00 Measurement System Independent 8.58 11.07 20.00 Thermal Power > 60% RTP Steady State Transient Maximum Symmetrical Incore Detector System 4.49 10.03 20.00 Power Range Channels 1.%
6.%
20.00 Minimum Incore Detector System 1.90 4.40 20.00 Measurement System Independent 4.92 11.07 20.00 These limits are referred to by Technical Specification LCO 3.2.4 I
p Page 22 l
l l
L-n
e Crystal River Unit 3, Cycle 11 Power Peaking Factors This Liinit is r'eferred to by Technical Specfication LCO 3.2.5 Heat Flux Hot Channel Factor FQ FQ shall be limited by the following relationships:
FQ s LHRallow (Bu)/ [LHRavg
- P] (for Ps LO)
LHRallow(Bu) = See the following Table LHRavg
= 5.79 kW/ft for Mk-B9,B10ZL, B101, B10E fuel LHRavg
-= 5.74 kW/ft for Mk-B4Z fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = Fuel Burnup (mwd /mtU)
Mk-B101/Mk-B10E LHRallow kW/ft*
Core 0
10650 33000 l
Elevation, ft Mwd /mtU Mwd /mtU Mwd /mtU 2
15.5 16.0 16.0 i
4 17.5 16.5 16.5 6
17.0 16.3 16.3 8
17.0 16.5 16.5 10 17.0 16.5 16.5 Mk-B9/Mk-B10ZL LHRallow kW/ft*
Core 0
1 % 50 40000 44000 44667 45667 57000 Elevationd Mwd /mtU Mwd /mtU Mwd /mtU mwd /mtU mwd /mtU Mwd /mtU mwd /mtU 2
15.5 16.0 16.0 15.7 15.6-15.5 11.3 4
17.5 16.5 16.5 16.2 15.9 15.5 11.3 l
6 17.0 16.3 16.3 16.0 15.9 15.5 11.3 8
17.0 16.5 16.5 16.2 15.9 15.5 11.3 10 17.0 16.5 16.5 16.2 15.9 15.5 11.3 1
Mk-B4Z LHRallow kw/ft*
_ Core 0.
1000 6000 38125 40000 40312 40750 42937 60000 Elevation, ft mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU 2
14.8 14.8 15.5 15.5 15.5 15.4 15.4 15.2 10.1 4
16.1 16.6 16.6 16.6 16.1 16.0 15.9 15.2 10.1 6
16.1" 16.1 16.1
-16.1 16.1 16.0 15.9 15.2 10.1 l
8
~17.0 17.0 17.0 16.6 16.1 16.0 15.9 15.2 10.1 c10 16.0 16.0 16.0 16.0 16.0 15.9 15.9 15.2 10.1 l
- Linear interpolation is used to calculate the LHR limit to maintain the internal pin pressure less than l
or equal to the limit based on NRC approved fuel rod gas pressure criterion.
l Page 23 E
[
Crystal River Unit 3, Cycle 11 Power Peaking Factors j
This Li'mit is referred to by Technical Specfication LCO 3.2.5 N
Enthalpy Rise Hot Channel Factor. _ F g FL < ARP [1 + (1/RH)(1 - P/P )]
APR = Allowable Radial Peak, See the following table P = THERMAL POWER / RATED THERMAL POWER and P < 1.0 P, = 1.0 for 4-RCP operation i
P = 0.75 for 3-RCP operation RH = 3.34 l
Cycle 11 Maximum Allowable Radial Peaks (MARP)
Axial Peak X/L' MARP -
1.1 0.2 1.9156 1.1 0.4 1.9071 1.1 0.6 1.8929 1.1 0.8 1.8655 1.3 0.2 1.9898 1.3 0.4
- 1. % 74 1.3 0.6 1.9283 1.3 0.8 1.8141 1.5 0.2 2.0462 1.5 0.4 1.9480 1.5 0.6 1.8234 1.5 0.8 1.7009 1.7 0.2 1.9337 1.7 0.4 1.8232 1.7 0.6 1.7023 1.7 0.8 1.5936 l
1.9 0.2 1.7837 1.9 0.4 1.6821 1.9 0.6 1.5799 1.9 0.8 1.4876
- Based on an active core height of 140.6 inches. Linear interpolation is acceptable; extrapolation above 112.48 inches and below 28,12 inches i:: acceptable.
Page 24 i
I
Crystal River Unit 3, Cycle 11 Nuclear Overpower and Axial Power Imbalance Maximum Allowable Trip Setpoint T
( 34.0,108u
- (34.0.108) 100 --
Acceptable 4 Pump Operation 90 -
(-34.0,80.6 ^
- (34.0,80.68 ou Acceptable 3 and 4 Pump Operation
< (-62.5,71.11 70 (62.5,71.0 8
60 -
lThis Figure is referred to by T.S. LCO 3.3.1 l 50 -
< (-62.5,43.79)
(62.5,43.7 P
40 -
% Rated Thermal Power 30 --
20 -
10 -
<H-O l
- < > -H
-70
-60 50
-40
-30
-20
-10 0
10 20 30 40 50 60 70 Axial Powor imbalance %
i Page 25
Crystal River Unit 3, Cycle 11 Refueling Boron Concentration The boron concentration must be greater than 3013 ppmb Note: The refueling boron concentration must be increased by 2 ppmb for every EFPD the final Cycle 10 burnup is less than 610 EFPD. The refueling boron concentration can be reduced 2.0 ppmb for every EFPD that the final Cycle 10 burnup exceeds 610 EFPD. The 610 EFPD refueling concentration is 2%7. The actual end of cycle 10 was 592.790 EFPD @ 2544 MWt or 587.25 @
2568 MWt. Using this value and the equation above the refueling boron increases to 3013 ppmb.
3 This limit is referred to by Technical Specification LCO 3.9.1 l
Page 26
4 Crystal River Unit 3, Cycle 11 Revision History Revision 0 - Original Cycle 11 Release Approved 3/21/96 PRC Meeting #96-12 Revision 1 - Revised to include nuclear enthalpy rise hot channel factor limits and added
. information to shutdown margin discussion. An ITS Basis change relative to the rod insertion limits in the COLR was made, but did not affect the rod insertion data in the COLR.
Revision 2 - Revised to include new Lower Limit (End of Cycle 11) for Moderator Temperature Coefficient. To correct a minor formatting deficiency in Revision 1, the column width of the Mark B4Z Linear Heat Rate Limits was adjusted to more fully show the LHR data for the high burnup limit (60GWD/MT).
l l
i Page.27 L.