ML071090643
| ML071090643 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/19/2007 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| 07-0313 | |
| Download: ML071090643 (22) | |
Text
Dominion Resources Services, Inc.
5000 Dominion Boulevard, Glen Allen. VA L i O ( > O Wcb Address: www.dom.com April 19, 2007 United States Nuclear Regulatory Commission Serial No.: 07-0313 Attention: Document Control Desk NL&OSlvlh Washington, D.C. 20555-001 Docket No.: 50-339 License No.: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTHANNAPOWER STATION UNIT 2 CORE OPERATING LIMITS REPORT Pursuant to North Anna Technical Specification 5.6.5.d) attached is a copy of Dominion's Core Operating Limits Report for North Anna Unit 2 Cycle 19 Pattern ABU, Revision 1.
If you have any questions or require additional information, please contact Mr. Tom Shaub at 8041273-2763.
Very truly yours, C. L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
for Virginia Electric and Power Company Commitments: None Attachment cc: U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. S. P. Lingam U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station
ET-NAF-07-0025, Rev. 0 , Attachment 1 CORE OPERATING LIMITS REPORT Revision 1 North Anna Unit 2 Cycle 19 Pattern APU April 2007 N2C19 COLR, Revision 1 Page 1 of 21
N2C 19 CORE OPERATING LIMITS REPORT INTRODUCTION The Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 19 has been prepared in accordance with North Anna Technical Specification 5.6.5. The technical specifications affected by this report are listed below:
Reactor Core Safety Limits Shutdown Margin (SDM)
Moderator Temperature Coefficient (MTC)
Shutdown Bank Insertion Limit Control Bank Insertion Limits Heat Flux Hot Channel Factor Nuclear Enthalpy Rise Hot Channel Factor ( F * ~ )
Axial Flux Difference (AFD)
Reactor Trip System (RTS) Instrumentation RCS Pressure, Temperature, and Flow DNB Limits Boron Concentration In addition, a technical requirement (TR) in the NAPS Technical Requirements Manual (TRM) refers to the COLR:
TR 3.1.1 Boration Flow Paths - Operating The analytical methods used to determine the core operating limits are those previously approved by the NRC and discussed in the documents listed in the References Section.
Cycle-specific values are presented in bold. Text in italics is provided for information only.
N2C19 COLR, Revision 1 Page 2 of 21
REFERENCES VEP-FRD-42 Rev 2.1-A, Reload Nuclear Design Methodology, August 2003.
(Methodology for TS 3.1.1 - Shutdown Margin, TS 3.1.3 - Moderator Temperature Coefficient, TS 3.1.5 - Shutdown Bank Insertion Limit, TS 3.1.6 - Control Bank Insertion Limits, TS 3.2.1 - Heat Flux Hot Channel Factor, TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and TS 3.9.1- Boron Concentration)
VEP-NE-2-A, Statistical DNBR Evaluation Methodology, June 1987.
(Methodology for TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits)
VEP-NE Rev. 0.1-A, Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications, August 2003.
(Methodology for TS 3.2.1 - Heat Flux Hot Channel Factor and TS 3.2.3 - Axial Flux Difference)
WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions, September 1986.
(Methodology for TS 2.1.1 - Reactor Core Safety Limits and TS 3.3.1 - Reactor Trip System Instrumentation)
WCAP-14483-A, Generic Methodology for Expanded Core Operating Limits Report, January 1999.
(Methodology for TS 2.1.1 - Reactor Core Safety Limits, TS 3.1.1 - Shutdown Margin, TS 3.3.1 - Reactor Trip System Instrumentation, TS 3.4.1 - RCS Pressure, Temperature, and Flow DNB Limits and TS 3.9.1 - Boron Concentration)
BAW-10227P-A, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel."
(Methodology for TS 2.1.1 - Reactor Core Safety Limits, TS 3.2.1 - Heat Flux Hot Channel Factor)
- 7. EMF-2103 (P) (A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors."
(Methodology for TS 3.2.1 - Heat Flux Hot Channel Factor)
- 8. EMF-96-029 (P) (A), "Reactor Analysis System for PWRs."
(Methodology for TS 3.2.1 - Heat Flux Hot Channel Factor)
N2C19 COLR, Revision 1 Page 3 of 21
- 9. BAW-10168P-A, "RSG LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants." Volume I1 only (SBLOCA models).
(Methodology for TS 3.2.1 - Heat Flux Hot Channel Factor)
- 10. DOM-NAF-2-A, "Reactor Core Thermal-HydraulicsUsing the VIPRE-D Computer Code,"
including Appendix A, "Qualification of the F-ANP BWU CHF Correlations in the VIPRE-D Computer Code."
(Methodology for TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits)
N2C19 COLR, Revision 1 Page 4 of 21
2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in COLR Figure 2.1-1; and the following SLs shall not be exceeded.
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNBR criterion for the DNB correlations and methodologies specified in the References Section.
2.1.1.2 The peak fuel centerline temperature shall be maintained < 5 173"F, decreasing by 65°F per 10,000 MWDIMTU of burnup.
N2C19 COLR, Revision 1 Page 5 of 21
COLR Figure 2.1-1 NORTH ANNA REACTOR CORE SAFETY LIMITS
\ 2400 psia 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 POWER (fraction of nominal)
N2C19 COLR, Revision 1 Page 6 of 21
3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
LC0 3.1.1 SDM shall be 2 1.77 % Aklk.
3.1.3 Moderator Temperature Coefficient (MTC)
LC0 3.1.3 The MTC shall be maintained within the limits specified below. The upper limit of MTC is +0.6 x AWF, when < 70% RTP, and 0.0 AWW°F when > 70%
RTP.
The BOCIARO-MTC shall be I+0.6 x W ° F (upper limit), when < 70%
RTP, and < 0.0 Ak/k/"F when 2: 70% RTP.
The EOCIAROIRTP-MTC shall be less negative than -5.0 x loe4AkM°F (lower limit).
The MTC surveillance limits are:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to
-4.0 x Ak/W°F [Note 21.
The 60 pprnlARO1RTP-MTC should be less negative than or equal to
-4.7 x AWW°F [Note 31.
SR 3.1.3.2 Verify MTC is within -5.0 x AklW°F (lower limit).
Note 2: If the MTC is more negative than -4.0 x W ° F , SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.
Note 3: SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than -4.7 x 10" W ° F .
3.1.4 Rod Group Alignment Limits Required Action A. 1.1 Verify SDM to be 2 1.77 % Aklk.
Required Action B. 1.1 Verify SDM to be 2 1.77 % Akk.
Required Action D. 1.1 Verify SDM to be 2 1.77 % AWk.
N2C19 COLR, Revision 1 Page 7 of 21
3.1.5 Shutdown Bank Insertion Limits LC0 3.1.5 Each shutdown bank shall be withdrawn to at least 227 steps.
Required Action A.l.l Verify SDM to be 2 1.77 % A k k .
Required Action B. 1 Verify SDM to be 2 1.77 % A k k .
SR 3.1.5.1 Verify each shutdown bank is withdrawn to at least 227 steps.
3.1.6 ControlBankInsertionLimits LC0 3.1.6 Control banks shall be limited in physical insertion as shown in COLR Figure 3.1-1. Sequence of withdrawal shall be A, B, C and D, in that order; and the overlap limit during withdrawal shall be 99 steps.
Required Action A. 1.1 Verify SDM to be 2 1.77 % A k k .
Required Action B. 1.1 Verify SDM to be 2 1.77 % AWk.
Required Action C. 1 Verify SDM to be 2 1.77 % A k k .
SR 3.1.6.1 Verify estimated critical control bank position is within the insertion limits specified in COLR Figure 3.1-1.
SR 3.1.6.2 Verify each control bank is within the insertion limits specified in COLR Figure 3.1-1.
SR 3.1.6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in L C 0 3.1.6 above.
3.1.9 PHYSICS TESTS Exceptions - MODE 2 LC0 3.1.9.b SDM is 2 1.77 % AWk.
SR 3.1.9.4 Verify SDM to be 2 1.77 % Ak/k.
N2C19 COLR, Revision 1 Page 8 of 21
COLR Figure 3.1-1 North Anna 2 Cycle 19 Control Rod Bank Insertion Limits Fully wld po 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Fraction of Rated Thermal Power N2C19 COLR, Revision 1 Page 9 of 21
3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
LC0 3.2.1 Fa(Z), as approximated by F ~ ~ ( z shall
) , be within the limits specified below.
CFQ = 2.32 The Measured Heat Flux Hot Channel Factor, FQM(z),shall be limited by the following relationships:
CFQ K G )
F:(z)~-- for P10.5 0.5 N(Z)
THERMAL POWER where: p= ;and RATED THERMAL POWER K(Z) is provided in COLR Figure 3.2-1, N(Z) is a cycle-specific non-equilibrium multiplier on FQM(z)to account for power distribution transients during normal operation, provided in COLR Table 3.2-1.
The discussion in the Bases Section B 3.2.1 for this LC0 requires the application of a cycle dependent non-equilibrium multiplier, N o , to the measured peaking factor, F~"(Z), before comparing it to the limit. N(Z) uccounts for power distribution transients encountered during normal operation. As finction N(Z) is dependent on the predicted equilibrium FQ(Z) and is sensitive to the axial power distribution, it is typically generated from the actual EOC burnup distribution that can only be obtained after the shutdown of the previous cycle. The cycle-specific N(Z)&nction is presented in COLR Table 3.2-1.
N2C19 COLR, Revision 1 Page 10 of 21
COLR Table 3.2-1 N2C19 Normal Operation N(Z)
NODE HEIGHT 0 to 1000 1000 to 3000 5000 to 7000 7000 to 9000 (FEET) MWDIMTU MWDIMTU MWDlMTU MWDIMTU 10 10.2 1.092 1.095 1.119 1.130 11 10.0 1.099 1.103 1.118 12 9.8 1.108 1.112 1.I21 13 9.6 1.117 1.120 1.I26 14 9.4 1.122 1.124 1.125 15 9.2 1.I26 1.129 1.127 16 9.0 1.138 1.I43 1.143 17 8.8 1.149 1.156 1.160 18 8.6 1.151 1.I63 1.167 19 8.4 1.151 1.166 1.171 20 8.2 1.154 1.171 1.178 21 8.0 1.I55 1.173 1.182 22 7.8 1.156 1.173 1.184 23 7.6 1.156 1.171 1.184 24 7.4 1.156 1.167 1.184 25 7.2 1.153 1.163 1.183 26 7.0 1.150 1.159 1.180 27 6.8 1.149 1.157 1.179 28 6.6 1.147 1.152 1.176 29 6.4 30 6.2 31 6.0 32 5.8 33 5.6 34 5.4 35 5.2 36 5.0 37 4.8 38 4.6 39 4.4 40 4.2 41 4.0 42 3.8 43 3.6 44 3.4 45 3.2 46 3.0 47 2.8 48 2.6 49 2.4 50 2.2 51 2.0 52 1.8 N2C19 COLR, Revision 1 Page 1 1 of 21
COLR Table 3.2-1 (cont.)
N2C19 Normal Operation N(Z)
NODE HEIGHT 9000 to 11000 1 1000 to 13000 13000 to 15000 15000 to 17000 17000 to EOR (FEET) MWDIMTU MWDIMTU MWDIMTU MWDIMTU MWDIMTU 10.2 1.130 1.I33 1.133 1.108 1.114 10.0 1.129 1.131 1.131 1.107 1.114 9.8 1.134 1.128 1.128 1.107 1.112 9.6 1.142 1.126 1.126 1.110 1.111 9.4 1.144 1.122 1.122 1.109 1.105 9.2 1.146 1.I24 1.124 1.115 1.108 9.0 1.151 1.I37 1.139 1.135 1.130 8.8 1.159 1.154 1.158 1.158 1.157 8.6 1.164 1.159 1.163 1.164 1.I64 8.4 1.170 1.164 1.168 1.169 1.169 8.2 1.178 1.173 1.178 1.182 1.182 8.0 1.183 1.I78 1.185 1.191 1.191 7.8 1.185 1.I80 1.186 1.193 1.193 7.6 1.I86 1.180 1.190 1.195 1.197 7.4 1.181 1.204 7.2 1.183 1.208 7.0 1.185 1.209 6.8 1.187 1.211 6.6 1.I87 1.211 6.4 1.I86 1.211 6.2 1.182 1.207 6.0 1.I83 1.207 5.8 1.178 1.199 5.6 1.163 1.182 5.4 1.148 1.164 5.2 1.143 1.158 5.0 1.134 1.153 4.8 1.119 1.146 4.6 1.110 1.139 4.4 1.111 1.134 4.2 1.115 1.133 4.0 1.120 1.135 3.8 1.126 1.136 3.6 1.133 1.138 3.4 1.139 1.142 3.2 1.143 1.147 3.0 1.146 1.151 2.8 1.148 1.155 2.6 1.147 1.153 2.4 1.151 1.158 2.2 1.162 1.172 2.0 1.171 1.184 1.8 1.172 1.189 These decks were generated for normal operation flux maps that are typically taken at full power ARO. Additional N(z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical. EOR is defined as Hot Full Power End of Reactivity.
N2C19 COLR, Revision 1 Page 12 of 21
c
.-0
.-( I )
a, u
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F ~ A H )
LC0 3.2.2 F~~~shall be within the limits specified below.
F~~ I 1.587{1 + 0.3(1- P))
THERMAL POWER where: p=
RATED THERMAL POWER SR 3.2.2.1 Verify F ~ A His within limits specified above.
3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LC0 3.2.3 The AFD in 9% flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.
N2C19 COLR, Revision 1 Page 14 of 21
COLR Figure 3.2-2 North Anna 2 Cycle 19 Axial Flux Difference Limits ccel per,
/
27, Percent Flux Difference (Delta-I)
N2C19 COLR, Revision 1 Page 15 of 21
3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.
where: AT is measured RCS AT, OF.
ATo is the indicated AT at RTP, OF.
s is the Laplace transform operator, sec-'.
T is the measured RCS average temperature, OF.
T' is the nominal T,,, at RTP, 1586.8 O F .
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure, 2 2235 psig.
'1, 2 = time constants utilized in the lead-lag controller for T,,,
21 2 23.75 sec 2 2 1 4.4 sec
( I + qs)/(l+q s ) = function generated by the lead-lag controller for Ta,, dynamic compensation Where q, and ql, are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
N2C19 COLR, Revision 1 Page 16 of 21
TS Table 3.3.1-1 Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.
where: AT is measured RCS AT, OF.
ATo is the indicated AT at RTP, OF.
s is the Laplace transform operator, sec-I.
T is the measured RCS average temperature, OF.
T' is the nominal T,,, at RTP, 1586.8 O F .
I(4 I 1.0865 Kg 2 0.0197 /OF for increasing T,,, K6 2 0.00162 /OF when T > T' 0 1°F for decreasing T,,, 0 1°F when T I T'
~7 = time constant utilized in the rate lag controller for T,,,,
z3 2 9.5 sec qs/(l+q s ) = function generated by the rate lag controller for TaVsdynamic cornpensation f2(AI)= 0, for all AI.
N2C19 COLR, Revision 1 Page 17 of 21
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LC0 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
- a. Pressurizer pressure is greater than or equal to 2205 psig;
- b. RCS average temperature is less than or equal to 591 OF; and
- c. RCS total flow rate is greater than or equal to 295,000 gpm.
SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to 2205 psig.
SR 3.4.1.2 Verify RCS average temperature is less than or equal to 591 OF.
SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to 295,000 gpm.
SR 3.4.1.4 ------------------------------NOTE--------------------------------------------
Not required to be performed until 30 days after 2 90% RTP.
Verify by precision heat balance that RCS total flow rate is 2 295,000 gpm.
N2C19 COLR, Revision 1 Page 18 of 21
3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 Boron Injection Tank (BIT)
Required Action B.2 Borate to an SDM 2 1.77 % A k k at 200 O F .
N2C19 COLR, Revision 1 Page 19 of 21
3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LC0 3.9.1 Boron concentrations of the Reactor Coolant System (RCS), the refueling canal, and the refueling cavity shall be maintained 2.2600 ppm.
Note: The refueling boron concentration satisfies the more restrictive of the following conditions: ( a )kef (0.95, or ( b )boron concentration 22600 pprn.
SR 3.9.1.1 Verify boron concentration is within the limit specified above.
N2C19 COLR, Revision 1 Page 20 of 21
NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 REACTIVEY CONTROL SYSTEMS TR 3.1.1 Boration Flow Paths - Operating Required Action D.2 Borate to a SHUTDOWN MARGIN 2 1.77 % Akk at 200 O F ,
after xenon decay.
N2C19 COLR, Revision 1 Page 21 of 21