NL-10-070, Revised Core Operating Limits Report, Mid-Cycle Revision
| ML101950040 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/07/2010 |
| From: | Robert Walpole Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-10-070 | |
| Download: ML101950040 (14) | |
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 N L-10-070 L
July 7, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Revised Core Operating Limits Report for Indian Point Unit 3 -
Mid-Cycle Revision Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
Please find attached Core Operating Limits Report (COLR) for Indian Point Unit 3 in accordance with the Indian Point 3 Technical Specifications 5.6.5.d. Enclosure 1 provides a mid-cycle revision to the Cycle 16 COLR.
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, RW/dmt
Enclosure:
- 1. Indian Point 3 COLR - Mid-Cycle Revision for Cycle 16 cc:
Mr. John Boska, NRR Senior Project Manager Mr. Marc Dapas, Acting Regional Administrator, NRC Region I IPEC NRC Resident Inspector's Office Mr. Paul Eddy, New York State Department of Public Service (w/o enclosure)
Mr. Francis J. Murray, President and CEO, NYSERDA (w/o enclosure)
~bL4
ENCLOSURE 1 TO NL-10-070 Indian Point 3 COLR - Mid-Cycle Revision for Cycle 16 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 LICENSE NO. DPR-64
En tergv Nuclear Northeast 00o0 Ta Procedure Use-Is:
E0 Continuous 0 Reference O3 Information Control Copy:
Effective Date: 0/'13 0
- / o Page 1 of 12 3-C
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)n: 2 EPORT cc IATING LIM PO.
Approved By:
s' g-n t
/ 61-Procedure Sponsor, DM/Des Team 3B erat~.o Procedure Owner EDITORIAL REVISION
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 2 of 12 REVISION
SUMMARY
(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 This revision corrects an editorial error in COLR.
2.0
SUMMARY
OF CHANGES 2.1 This revision corrects an editorial error in the COLR. The Indian Point Unit 3 Cycle 16 COLR text for "TS 2.1.1 Reactor Core SLs" has been revised for consistency with "Figure 1 Reactor Core Safety Limit - Four Loops in Operation" in COLR, as well as the Indian Point Unit 3 Technical Specifications. This revision is not considered a significant safety concern. The guidance that was presented in the COLR text would have resulted in a conservative determination of a safety limit being exceeded when applied to the COLR Figure 1 since Reactor Vessel average temperatures would have been compared to limits on Reactor Vessel inlet temperatures.
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 3 of 12 TABLE OF CONTENTS SECTION PAGE TS 2.1.1 Reactor Core SLs...............................................................................................
4 TS 3.1.1 Shutdown Margin (SDM)....................................................................................
4 TS 3.1.3 Moderator Temperature Coefficient (MTC)........................................................
4 TS 3.1.5 Shutdown Bank Insertion Limits.........................................................................
5 TS 3.1.6 Control Bank Insertion Limits.............................................................................
5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))................................................................
5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F$NH.................................................
5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology). 6 TS 3.3.1 RPS Instrumentation...........................................................................................
6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
L im its.......................................................................................................................................
6 TS 3.9.1 Refueling Boron Concentration...........................................................................
6 ATTACHMENTS OVERTEMPERATURE AT.........................................................................
7 OVERPOWER AT......................................................................................
8 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation........................................
9 Figure 2 Rod Bank Insertion Limits..................................................................................
10 Figure 3 Hot Channel Factor Normalized Operating Envelope.........................................
11 Figure 4 Axial Flux Difference Envelope Limits...............................................................
12
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 4 of 12 NOTE The Technical Specification references shown next to each Factor OR Limit in this COLR are there to identify the corresponding sections in the Technical Specifications that refer to the COLR.
" The COLR, including any midcycle revisions or supplements, shall be provided for each reload cycle to the NRC. {T.S. 5.6.5d.)
" The data presented in this report applies to Cycle 16 ONLY and may NOT be used for other cycles of operation. Also, it applies only to operation at a maximum power level of 3188.4 MWt. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10CFR50.59.
TS 2.1.1 Reactor Core SLs In MODE 1 and 2, the combination of thermal power level, pressurizer pressure, and Reactor Vessel inlet temperature SHALL not exceed the limits shown in Figure 1. The safety limit is exceeded if the point defined by the combination of Reactor Vessel inlet 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:
-38.0 pcm/-°F
-44.5 pcm/QF
-47.0 pcm/-°F 300 ppm 60 ppm 0 ppm
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 5 of 12 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 _> 225 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.
TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with keff > 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 > 230 steps.
TS 3.2.1 Heat Flux Hot Channel Factor (FQ(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 FQ, IF P >.5, FQ(Z) <! (2.50 /P) x K(Z)
I F P <ý.5, FQ(Z) < (5. 00) x K(Z)
TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FAH NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FNH< 1.70 {1 +0.3(1 -P)}
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 6 of 12 TS'3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
Methodoloyv)
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.
- 1. Overtemperature 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
- 2. Overpower AT 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 loop Tavg < 576.70F for full-power Tavg 572.0°F
- b.
Pressurizer Pressure > 2204 psig
- c.
Reactor Coolant System Total Flow Rate > 364,700 gpm TS 3.9.1 Refuelinq Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either Ž> 2050 ppm or that which is sufficient to provide a shutdown margin _> 5% Ak/k.
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 7 of 12 OVERTEMPERATURE AT The Overtemperature AT Function Allowable Value SHALL not exceed the following:
Note: For limitations on the maximum trip Setpoint, see Technical Specification 3.3.1.
AT < AT, [K1 - K2 [(1 + TIs)/(1 + t2s)J (T - T') + K3 (P - P') - f1(AI)]
Where:
AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec-1.
T is the measured RCS average temperature, OF.
T' is the loop specific indicated T at RTP, °F < 572.0°F.
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure, _> 2235 psig.
K, *1.26 ti > 25.0 sec K2 > 0.022/-F t:2 < 3.0 sec K3 > 0.00070/psi fl(Al) =
4.00[ -15.75 - (qt - qb)]
0% of RTP
+3.33[(qt - qb) - 6.911 when qt - qb _ - 15.75% RTP when -15.75% RTP < qt - qb
- 6.9% RTP when qt - qb > 6.9% 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.
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 8 of 12 OVERPOWER AT The Overpower AT Function Allowable Value SHALL not exceed the following:
Note:
For limitations on the maximum trip Setpoint, see Technical Specification 3.3.1.
AT < ATo [K4 - K5 [(t3S)/(1 + t 3s)](T) - K6(T - T") - f2(AI)]
Where:
AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
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 T at RTP, 0F < 572.0°F.
K4 < 1.10 K5 > 0.01 75/°F for increasing T K6 > 0.0015/0F when T > T" 01/F for decreasing T 0/°F when T < T" T3 > 10 sec f2(AI) = 0
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation 68W U.
4)
CL 0.
0 10 20 30 40 50 s0 70 80 90 180 110 Reactor Power (Percent of 3216 MWt)
(Conservative relative to 3188.4 MWt; use as-is for operation at 3188.4 MWt]
120
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 104 Step Overlap CD
-o 0.
0)
CC 230 220 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 Power (Percent of 3188.4 MWt) 80 90 100
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 11 of 12 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)
1.2 1
t.0.8 0C.
C" L.
0.6 0Z
,0.4 0.2 0
0 2
4 6
8 Core Elevation (feet) 10 12
No: 3-GRAPH-RPC-16 Rev: 2 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits cv, 0
0(L
-40
-30
-20
-10 0
10 20 30 40 Axial Flux Difference