ML073320591
| ML073320591 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/15/2007 |
| From: | Laughlin G Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| COLR2-11, Rev 1 | |
| Download: ML073320591 (23) | |
Text
P.O. Box 63 Lycoming, NY 13093 Constellation Nine Mile Point Nuclear Station Energy-November 15, 2007 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Core Operating Limits Report, COLR2-11 Revision 1 Attached is a copy of the Core Operating Limits Report, COLR2-11 Revision 1, for Nine Mile Point Unit 2 (NMP2). This report is being submitted pursuant to NMP2 Improved Technical Specification 5.6.5.d.
Should you have any questions regarding the information in this submittal, please contact T. F. Syrell, Director Licensing, at (315) 349-5219.
Verytrl rs/,
Manager, Engineering Services GJL/MHS/
Attachment:
(1) Core Operating Limits Report, COLR2-11 Revision I cc: S. J. Collins, NRC M. J. David, NRR Senior Resident Inspector, NRC ko'o I
ATTACHMENT (1)
NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT COLR2-11 REVISION 1 Nine Mile Point Nuclear Station, LLC November 15,2007
NINEMILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT Document No.: COLR2-11 Controlled Document Copy ForLatest Information Check CDS Revision 1, Cycle 11 Name Title Date Prepared by:
C. W. Lepine(/ Fuel Engineer Reviewed by:
R. S. Close.. Fuel Engineer Independently
-viewed by: ~A (IL Pbz T~Z4~Cc~L) //-hY-o 7 W. J. Carter Fuel Engineer Approved by: /I -/ 3-,r?
P. I. Wengloski Supervisor, Nuclear Fuels Services Approved by: I~ i731o4 J. N. Darweesh Supervisor, Reactor Engineering Approved by: 11-13 -a r P. 1.Wen~oski General Supervisor, Nuclear Fuels Services This Controlled Document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point TTnit 2 Technical Specifications. Document pages may only be changed through a reissue of the entire document.
Revision 1
-Cycle il NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT Table of Contents.
Pagee 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........... 1 1.1 Limits for Technical Specification 3.2.1 ........ ............. ..... ..... .............................. 1 2.0 MINIMUM CRITICAL POWER RATIO (ODYh OPTION B) ................................ 3 2.1 Limits for Technical Specification 3.2.2.................................................................. 3 3.0 LINEAR HEAT GENERATION RATE (LHGR) .............. 11 3.1 Limits for Technical Specifications 3.2.3 .................................................... ...... 11 4.0ý AVERAGE POWER RANGE MONITOR SETPOINTS .................... 14 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) .......... 14 5.0 ROD BLOCK MONITOR (RBM) ............. ................................................ .. ...... 15 5.1 Allowable Value for Technical Specification Table 3.3.2.1-1 ......................... 15
6.0 REFERENCES
FOR TECHNICAL SPECIFICATIONS ............................... 16
7.0 REFERENCES
FOR TECHNICAL SPECIFICATION BASES.............................. 17 8.0 SOURCE DOCUM ENTS ............................................................................................... 18 Page i
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1.1 Limits for Technical Specification 3.2.1 The APLHGR(s) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown inTable 1.
The limits of Table I shall be reduced to a value of.78 times the two recirculation loop operation limit when in single recirculation loop operation.
Page 1 of 19
NINE MILE POINT UNIT 2 COLR2-11, Revision 1 Table 1 Cycle 11 MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Average Planar Exposure MAPLHGR Limits (kw/ft)
GWd/ST GEll GE14 Bundles Bundles 0.00 13.42 12.82 14.51 - 12.82 19.13 - 12.82 19.72 13.42-27.22 12.29 -
57.61 - 8.00 63.50 8.90 5.00
-NOTE: (1) A "-" indicates that there is no entry for this box and the limit can be determined by linearly ifiterpolating between the previous and next point in each column. MAPLHGRs are interpolated between exposure points for which explicit values are given.
NOTE: (2) These MAPLHGR are not lattice dependent. The values shown also correspond to the limiting value for the most limiting latticefor use when hand calculations are required.
Page 2 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B) 2.1 Limits for Technical Specification 3.2.2 The Minimum Critical Power Ratio, (MCPR) shall be equal to or greater than the appropriate MCPR limit from Figures 2a-14 and 2b-14 for GE14 and Figures 2a-11 and 2b- 11 for GEl 1 times the K(f) shown in Figure 2c with tau (or "T")
defined as follows:
TA 0.866 seconds; control rod average scram insertion time limit to notch 39 per Specification 3.1.4.
n TB =. 6 72 + 1.6 5 *[ N1 /Z Ni ]" 2 .016 n n Tave= i j) /N(EN i n = number of surveillance tests performed in cycle Ni= number of active control rods measured in the ih surveillance test
=i average scram time to notch 39 of all rods measured in the ith surveillance test N1 = total number of active rods measured in Specification 3.1.4.1.
NOTES: 1. The MCPR Operating Limits in Figures 2a- 11, 2a-14, 2b- 11 and 2b-14 are based on a 1.07 Safety Limit MCPR (SLMCPR) for two recirculation loop operation and a 1.09 Safety Limit MCPRfor single loop operation.
- 2. T= 1.0 prior to performance of-the initial scram time measurements for the cycle.
- 3. The Operating Limit MCPR values for Turbine Bypass Out of Service and EOC-RPT Out of Service are higher (more limiting) than for the standard normal operation case, and are therefore specifically identified in Figures 2a-14, 2b-14, 2a-1 1, and 2b-1 l.The OLMCPR values for all other analyzed EOOS transient events are bounded by the Normal Operation limits.
- 4. For operation between 30% and 90% RTP with a backup pressure regulator out of service, additional MCPR limit requirements have been established in Figures 2d and 2e.
- 5. EOR on Figures 2a-14, 2b-14, 2a- 11, and 2b-1 1 is the End of Rated exposure as defined in the Cycle Management Report Page 3 of 19
Figure 2a-14 Nine Mile Point 2 Cycle 11 GE14 MCPR Operating Limits (Beginning Of Cycle to EOR-1140 MWd/ST) 1.54-1.52 (1,1.521
. . . Turbine Bypass Inoperable (,.1
-1.5 -o
- 1.48 I (0,1.48)
I-° o 1.46 1.442
._.1.42. 1' Normal Operation 1.4 -
(0,1.39) 1.38 0 0.2 0.4 0.6 0.8 Tau Page 4 of 19
Figure 2b-14.
Nine Mile Point 2 Cycle 11 GE14 MCPR Operating Limits (EOR-1 140 MWd/ST to End Of Cycle) 1.66 1.64 1.62-1.6 -
C. 1.58-EOC-RPT Inoperable 1.56 I 1.54 1.52 1.48 (0,1.48)
~1.441 1.46' 1 Turbin ByNormal Operation (0,1.44) 1.42 0 0.2 0.4 0.6 0.8 I Tau Page 5 of 19
Figure 2a-11 Nine Mile Point 2 Cycle 11 GEII MCPR Operating Limits (Beginning Of Cycle to EOR-1140 MWdlST) 1.46 1.44 1.42
, ,;:(1, 1.41)
- 1.4 -i (1, 1.40)
,oo'm Turbine Bypass Inoperable C 1*3.
a (0,1.38)
1.36 1.34 1.34- 0z* (1,1.34) 11('0o, 1.33)
Normal Operation 1.32 (0, 1.31) 1.3 0 0.2 0.4 0.6 0.8 Tau Page 6 of 19
Figure 2b-11 Nine Mile Point 2 Cycle 1.1 GEl1 MCPR Operating Limits (EOR-1 140 MWdIST to End Of Cycle) 1.5 1(1, 1.49) 1.48 1.44-EOC-RPT Inoperable S1.44-0~
C. 1.42 E
.0 1.4'1
.E Turbine Bypass Inoperable 1.38 Is (1, 1.38)
(N, Oeai)
~Normal Operattion 1.36-(0, 1.35) 1.34 0 0.2 0.4 0.6 0.8 Tau Page 7 of 19
NINE MILE POINT UNIT 2 Figure 2c COLR2-11, Revision 1 Cycle 11 Kf vs Core Flow 1.4 1.3 1.2
'4-1.1 0.9 20 30 40 50 60 70 80 90 100 110 Core Flow, % of rated Page 8 of 19
NINE MILE POINT UNIT 2 COLR2-11, Revision 1 Cycle 11 Figure 2d GE1I MCPR Limits for Operation Without a Backup Pressure Regulator 2.2 For operation >70% but <90% RTP maintain MCPR > normal operation MCPR limit from Figures 2a-1 1.or 2b-1 1 dividedby the fraction of rated thermal power.
For operation >30% and <70% RTP the additional requirements are as shown in this
2.1 Figure
Operating Limit MCPR (P) = OLMCPR(P) = [1.58+0.0080(70%-P)].
There are no additional MCPR limits required for operation <30% and >90% RTP with a backup pressure regulator out of service.
2 1.9 ACCEPTA3LE REGION 1.8 SOperating MCPR shall be _ MCPR limit line 1.7 1.6 RISTR CTE REGION Enter T:Dch. pec. 3.2.2 1.5 1.4 30 35 40 45 50 55 60 65 70 Core Thermal Power (P) in units of % Rated Thermal Power (%RTP)
Page 9 of 19
NINE MILE POINT UNIT 2 COLR2-11, Revision 1
.. Cycle 11 Figure 2e GE14C MCPR Limits for Operation Without a Backup Pressure Regulator 2.3
! I For operation >70% but <90% RTP maintain MCPR > normal operation MCPR limit from Figures 2a-14 or 2b-14 divided by the fraction of rated thermal power.
For operation >30% and <70% RTP the additional requirements are as shown in this figure:
2.2 Operating Limit MCPR .(P) = OLMCPR(P) = [1.72+0.00825(70%-P.)]
There are no additional MCPR limits required for operation <30% and >90% RTP with a backup pressure regulator out of service.
A4 N..MOP, 2.1 2
ACC PTA LE R GIO Operating MCPR shall be >_MCPR limit line o 1.9 1.8 1.7 REST CTEREGIN
____ ~ E~ter T ch. pec 4:.2.2 ___ __
1.6 1.5 30 ) 35 40 45 50 55 60 65 70 Core Thermal Power (P) in units-of % Rated Thermal Power (%RTP)
Page 10 of 19
Revision I Cycle 11 17- NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 3.0 LINEAR HEAT GENERATION RATE (LHGR) 3.1 Limits for Technical Specification 3.2.3 During power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the limiting values shown in RSLD-10, Revision 1, "Nine Mile Point Unit 2 Reload 10, Reload Specific Lattice Data". This document contains the LHGR limits for both U02 rods (which contain no gadolinium) and the most limiting gadolinium-bearing rods. Other gadolinium-bearing rods have LHGR limits which lie between these two curves.
Compliance with these limits will be monitored by the plant's process computer.
NOTE: For operation >30% and <90% RTP with a backup pressure regulator out of service, additional LHGR limit requirements have been established as shown in Figure 3-11 and 3-14. There are no additional LHGR limits required for operation
<30% and >90% RTP for operation with a backup pressure regulator out of service.
Page 11 of 19
Figure 3-11 LHGR Limit for Operation Between 30% and 90% RTP Without a Backup Pressure Regulator for GEl 1 0.95
EnterT TED RE .5.2.3r/
SIpe(;. N 0,9 0.85 0.8 a.
,.J L-0.75 0.7 rACCEPTABLE REGI DN Operating MFLPD shall be < MFLPD limit line MFLPD Limit =
For 30%:g P < 70%
0.65 MFLPD = [0.80-0.00225(70%-P)]
For 70% < P< 90 %:
MFLPD = FRTP
-\P P 0.6 30 35 40 45 50 55 60 65 70 75 80 85 90 Core Thermal Power (P) in units of % Rated Thermal Power (%RTP)
Page 12 of 19
Figure 3-14 LHGR Limit for Operation Between 30% and 90% RTP Without a Backup Pressure Regulator for GE14C 0.95 DES
- nterTRI(,#T Tech. Spe. : GI3.23 0.9 0.85 0.8 a
,-J U.
0.75
' _ _ I -_ _ "_
0.7 ACCEP ABLE ýEG ON Operating MFLPD shall be < MFLPD limit MFLPD Limit =
For 30% f P < 70%
MFLPD = [0.85-0.0035(70%-P)]
0.65 For 70% P < 90 %:
MFLPD =FRTP 0.6 30 35 40 45 50 55 60 65 70 75 80 85 90 Core Thermal Power (P) in units of % Rated Thermal Power (%RTP)
Page 13 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2, CORE OPERA TING LIMITS REPORT 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)
ALLOWABLE VALUE < 1.13
.Page 14 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 5.0 ROD BLOCK MONITOR (RBM) 5.1 Allowable Value for Technical Specification Table 3.3.2.1-1 Function Allowable Value RBM Upscale _0.66 (W - AW) + 47%
with a maximum of 113%
NOTE: W = Loop Recirculation Flow as a percentage of the loop recirculation flow which produces a rated core flow of 108.5 MLB/HR. AW is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow. AW = 0 for two loop operation. AW = 5% for single loop-op6eration.
Page 15 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT
6.0 REFERENCES
FOR TECHNICAL SPECIFICATION Technical Specification 5.6.5.b.1:
General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A- 15 and NEDE 24011-P-A-15-US (September 2005).
Page 16 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT
7.0 REFERENCES
FOR TECHNICAL SPECIFICATION BASES 2.1.1 BASES REFERENCE 3:
General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-15 and NEDE 24011-P-A-I5-US (September 2005).
2.1.1 BASES REFERENCE 4:
Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-0023-4708-SRLR, Rev. 0, February 2006.
3.1.1 BASES REFERENCE 7:
General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-15 and NEDE 24011 -P-A- 15-US (September 2005).
3.1.6 BASES REFERENCE 1:
Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle .11, 0000-0023-4708-SRLR, Rev. 0, February 2006.
3.2.1 BASES REFERENCE 1:
General Electric Standard Application for Reactor Fuel, NEDE 2401 1-P-A-15 and NEDE 24011-P-A-I5-US (September 2005).
3.2.2 BASES REFERENCE 2:
General Electric Standard Application for Reactor Fuel, NEDE 2401 1-P-A-15 and NEDE 24011 -P-A- 15-US (September 2005).
3.2.2 BASES REFERENCE 3:
Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-0023-4708-SRLR, Rev. 0, February 2006.
3.2.3 BASES REFERENCE 1:
General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-15 and NEDE 24011-P-A-i 5-US (September 2005).
3.2.3 BASES REFERENCE 2:
Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-0023-4708-SRLR, Rev. 0, February 2006.
3.2.4 BASES REFERENCE 3:
General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-15 and NEDE 24011-P-A- 15-US (September 2005).
Page 17 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 8.0 SOURCE DOCUMENTS The Core Operating Limits contained in this report were obtained from the following docitments:
CORE OPERATING LIMIT ,REFERENCE Section 1.0 - APLHGR LIMITS "Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11", 0000-0050-1550-ER, Rev 0, March 2006 "NMP2 CYCLE, 11 GESTAR II COMPLIANCE ASSESSMENT", JAR-NMP-KG1-07-019, November 9, 2007 Section 2.0 - MCPR LIMITS "Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11", 0000-0050-1550-ER, Rev 0, March 2006 "NMP2 CYCLE 11 GESTAR II COMPLIANCE ASSESSMENT", JAR-NMP-KG1-07-019, November 9, 2007 Section 3.0 - LHGR LIMITS "Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11", 0000-0050-1550-ER, Rev 0, March 2006 "NMP2 CYCLE 11 GESTAR II COMPLIANCE ASSESSMENT", JAR-NMP-KG1-07-019, November 9, 2007 Page 18 of 19
Revision 1 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 8.0 SOURCE DOCUMENTS (Cont)
CORE OPERATING LIMIT REFERENCE Section 4.0 - APRM SETPOINTS Limits for Technical Specification "Engineering Report for Nine Mile Point Table 3.3.1.1-1 (OPRM Upscale) Nuclear Station Unit 2, Reload 10, Cycle 11", 0000-0050-1550-ER, Rev 0, March 2006 Section 5.0 - RBM SETPOINTS GE Engineering Report for Nine Mile Point Nuclear Station Unit 2 Reload 2 Cycle 3, NFD92-016 January 1992 Page 19 of 19