NL-10-034, Revised Core Operating Limits Report, Cycle 20
| ML101310393 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/03/2010 |
| From: | Robert Walpole Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-10-034 | |
| Download: ML101310393 (15) | |
Text
-Entergy Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Licensing Manager NL-10-034 May 3, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Revised Core Operating Limits Report for Indian Point Unit 2 Docket No. 50-247 License No. DPR-26
Dear Sir or Madam:
Please find attached Core Operating Limits Report (COLR) for Indian Point Unit 2 Cycle 20 in accordance with the Indian Point 2 Technical Specifications 5.6.5.d. Enclosure 1 provides the cycle-specific operating limits for the operation of Indian Point Unit 2.
There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact my office at (914) 734-6710.
Sincerely,
Enclosure:
- 1. Indian Point 2 COLR - Cycle 20 cc:
Mr. John Boska, NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, NRC Region I IPEC NRC Resident Inspector's Office (w/o enclosure)
Mr. Paul Eddy, New York State Department of Public Service (w/o enclosure)
Mr. Francis J. Murray, President and CEO, NYSERDA (w/o enclosure) k-i CLK
ENCLOSURE 1 TO NL-10-034 Indian Point 2 COLR - Cycle 20 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 LICENSE NO. DPR-26
Enutergy Nuclear Northeast Procedure Use Is:
03 Continuous IJ Reference R1 Information Control Copy:
Effective Date: 3/ ]/
Page 1 of 13 2-GRAPIH-RPC'4, ReVision: 13 CORE OPERATING LIMITS REPORT (COLR)
Approved By:
id Sonsor, RPOi*
i Des i~i~iii!!*iiigne j
,,a e,
~iiii~
I W'Osii~~iii-i Team Staff l
A Procedure Owner GENERAL REVISION
REVISION
SUMMARY
(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 20 changes per NF-IP-09-30 2.0
SUMMARY
OF CHANGES 2.1 Added TS 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))" to the Table of Contents. [Editorial 4.6.6]
2.2 Added parentheses around "FAH" in the Table of Contents, TS 3.2.2. [Editorial 4.6.1]
2.3 Changed "RPS Instrumentation" to "Reactor Protection System (RPS)
Instrumentation" in the Table of Contents, TS 3.3.1. [Editorial 4.6.9]
2.4 Separated Attachment 1 into Attachments 1 and 2 in the Table of Contents.
[Editorial 4.6.2]
2.5 Deleted the note at the top of page 3, as it is no longer needed. [Editorial 4.6.12]
2.6 Deleted "Reference Graph RV-12 for cycle specific predicted MTC" in TS 3.1.3, as Westinghouse cannot validate that statement. [Editorial 4.6.13]
2.7 Added the statement "Each Control Bank shall be considered fully withdrawn at 2! 223 steps" to TS 3.1.6 for consistency with the Unit 3 COLR wording, but quoting the correct number of steps for Unit 2. [Editorial 4.6.13]
2.8 Added the definition of "P" to the Note in TS 3.2.1. [Editorial 4.6.11]
2.9 Added parentheses around "FNH "in the title of TS 3.2.2. [Editorial 4.6.1]
2.10 Replaced "Refer to Attachment 1" with "Refer to Attachment 2" in TS 3.3.1, Item
- 2. [Editorial 4.6.2]
2.11 Changed "Refuel" to "Refueling" in TS 3.9.1.. [Editorial 4.6.9]
2.12 Changed "(page 1 of 2)" to "(page 1 of 1)" in Attachment 1, "Overtemperature AT Allowable Value" (see page 5 of 11).. [Editorial 4.6.7]
2.13 Changed "Overtemperature AT" in Attachment 1 to "Overtemperature AT Allowable Value" (see page 5 of 11).. [Editorial 4.6.9]
2.14 Specified 5720F in the definition of T' in Attachment 1.. [Editorial 4.6.9]
(Page 2 of 2) 2.15 Changed "(page 2 of 2)" to "(page 1 of 1 )" in Attachment 2, "Overpower AT Allowable Value" (see page 6 of 11).. [Editorial 4.6.7]
2.16 Changed "Overpower AT" in Attachment 2 to "Overpower AT Allowable Value" (see page 6 of 11). [Editorial 4.6.9]
2.17 Specified 5720F in the definition of T" in Attachment 2. [Editorial 4.6.9]
2.18 Changed "Operation" to "Consequences" in two places on Figure 1. [Editorial 4.6.1]
2.19 Added "(Page 1 of 1)" to Figures 1 through 4. [Editorial 4.6.7]
Indian Point Unit 2 Cycle 20 COLR Page 4 of 13 TABLE OF CONTENTS SECTION PAGE TS 2.1.1 R eactor C ore S Ls.......................................................................................
5 TS 3.1.1 Shutdown Margin (SDM).............................................................................
5 TS 3.1.3 Moderator Temperature Coefficient (MTC).................................................
5 TS 3.1.5 Shutdown Bank Insertion Limits.................................................................
5 TS 3.1.6 Control Bank Insertion Limits....................................................................
6 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))........................................................
6 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH)......................................... 6 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
M ethodology)..........................................................................................
... 6 TS 3.3.1 Reactor Protection System (RPS) Instrumentation.....................................
7 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (D N B ) Lim its...................................................................................
7 TS 3.9.1 Refueling Boron Concentration......................................
I
............................ 7 Attachments:
Overtemperature AT Allowable Value........................................
8 Overpower AT Allowable Value.................................................
9 Figures:
Figure 1 Reactor Core Safety Limit - Four Loops in Operation..............
10 Figure 2 Rod Bank Insertion Limits........................................................
11 Figure 3 Hot Channel Factor Normalized Operating Envelope............... 12 Figure 4 Axial Flux Difference Envelope Limits......................................
13
Indian Point Unit 2 Cycle 20 COLR Page 5 of 13 The data presented in this report applies to Cycle 20 ONLY and may NOT be used for other cycles of operation.
Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10 CFR 50.59.
TS 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL not exceed the limits shown in Figure 1.
The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.
TS 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than or equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/°F at hot zero power.
The MTC lower limit SHALL be less negative than or equal to:
-36.5 pcm/°F@ 300 ppm
-43.0 pcm/°F@
60 ppm
-45.5 pcm/°F@
0 ppm TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position > 223 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.
Indian Point Unit 2 Cycle 20 COLR Page 6 of 13 TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with kef > 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
Each Control Bank shall be considered fully withdrawn at Ž_ 223 steps.
TS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
K(Z) is the fraction given in Figure 3 AND Z is the core height location of Fa.
IF P >.5, FQ(Z) < (2.50 /P) x K(Z)
IF P <.5, FQ(Z) < (5.00) x K(Z)
TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH)
NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FNH<1.70 {1 +0.3(1 -P)}
TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
Methodology)
The Indicated limit is the Target Band; i.e., the Target +/- 5%
The AFD SHALL be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.
Indian Point Unit 2 Cycle 20 COLR Page 7 of 13 TS 3.3.1 Reactor Protection System (RPS) Instrumentation
- 1. Overtemperature AT
- 2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.
Refer to Attachment 1.
Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2.
Refer to Attachment 2.
TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:
- a.
Reactor Coolant System average TAVG < 568.10F and highest loop TAVG < 571.1 0F for full power TAVG of 565.0°F
- b.
Pressurizer Pressure _> 2216 psia
- c.
Reactor Coolant System Total Flow Rate > 348,300 gpm TS 3.9.1 Refuelinq Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refueling Canal, and Reactor Cavity SHALL be the more restrictive of either
> 2050 ppm or that which is sufficient to provide a shutdown margin 2! 5% Ak/k.
Indian Point Unit 2 Cycle 20 COLR Page 8 of 13 (Page 1 of 1)
Overtemperature AT Allowable Value The Overtemperature AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 1 value.
The following provides the computed value:
AT (I+Z1S) [T-T']+K (P-P')-f,(AI)}
AT <AT0KI-K~('+ 172S)
Where:
AT is measured RCS AT, 'F (measured by hot leg and cold leg RTDs).
AT 0 is the loop specific indicated AT at RTP, °F.
s is the Laplace transform operator, sec-'.
T is the measured RCS average temperature, OF.
T' is the loop specific indicated Tavg at RTP, < 572 OF.
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure, _> 2235 psig.
K1,
1.22 K2 -> 0.020/1F K 3 > 0.00070/psi
, >25 sec T2 *< 3 sec f1(AI) = -1.97 {30 + (qt - qb)}
when qt - qb:< -30% RTP 0% of RTP when -30% RTP < qt - qb <7% RTP 2.25 {(qt - qb) - 7}
when qt - qb > 7% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
Indian Point Unit 2 Cycle 20 COLR Page 9 of 13 (Page 1 of 1)
Overpower AT Allowable Value The Overpower AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 2 value.
The following provides the computed value:
SToK 4 -
S T -K6 (T-T")-f2(A
<-Aro K4 Ks + Zý,' )
Where:
AT is measured RCS AT, OF.
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1.
T is the measured RCS average temperature, OF.
T" is the loop specific indicated Tavg at RTP, < 572 OF.
K4 < 1.074 K5 > 0.01 88/0 F for increasing Tavg K6 > 0.0015/°F when T > T 0/0F for decreasing Tavg 0/OF when T _ T T3 > 10 sec f2(AI) = 0
Indian Point Unit 2 Cycle 20 COLR Page 10 of 13 Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page 1 of 1) 680 2440 psla UNACCEPTABLE 660 CONSEQUENCES 640-620 p.>
2250 psia 600
~2000 psla 1860 psla 580 ACCEPTABLE 560 CONSEQUENCES 540 I '
I I
FRACTION OF RATED POWER
Indian Point Unit 2 Cycle 20 COLR Page 11 of 13 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page 1 of 1) 0 I-(n 0
0.
z 225 200 175 150 125 r..
3il i i(:4.9:,223) 223)r
=
i i
- I 1
100,1 11 0
17
)
1~~
12 ie J BA I
- +J I?
'---T ff OF!F l
ogi 001---
.0 1
f,-
lull I..............................9.
75 50 25 IiIlIlLiO I I ijý 1A
- 1 ILL
-L I
I I F I....I
'00' i
l I.00:
Ii L 0
0 10 20 30 40 50 60 70 Power Level (Percent of Rated Power) 80 90 100
Indian Point Unit 2 Cycle 20 COLR Page 12 of 13 Figure 3 Hot Channel FaCtOrlNormalized Operating Envelope (For S. G. Tube Plugging up to 10%)
(Page 1 of 1) 1.2 1.0 N
0 Cu CL 0.
V 0z 0.8 0.6 0.4 0.2
-0.oOo--
F 60, 100 J,
J I *....,.... -......
i 12.0, 0.925 1 FQ 2.50 2
kz)
Elev (ft) 2.50 1.0
-0.0 2.50 1.0 6.0 2.31 0.925 12.0 i
I 0
0 2
4 6
8 10 12 Core Height (ft)
Indian Point Unit 2 Cycle 20 COLR Page 13 of 13 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1)
I 95 90 85
.R so 0a.7.
70 65 60 55 50
-40
-30
-20
-10 0
10 20 30 40 Axial Flux Difference