L-PI-06-048, Core Operating Limits Report (Colr), Cycle 24, Revision 0
| ML061500395 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/28/2006 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-06-048 | |
| Download: ML061500395 (24) | |
Text
Prairie lsland Nuclear Generatina" Plant
.A Committed to Nucfear ExceNence Operated by Nuclear Management Company, LLC MAY 2 8 2006 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Unit 1 Docket 50-282 License No. DPR-42 Core Operating Limits Report (COLR) for Prairie lsland Unit 1 Cvcle 24, Revision 0 Pursuant to the requirements of Technical Specification 5.6.5.d, the COLR for Prairie lsland Nuclear Generating Plant Unit 1, Cycle 24, Revision 0 is attached. The limits specified in the attached COLR have been established using Nuclear Regulatory Commission (NRC) approved methodologies.
The Unit 1 COLR has been revised for Cycle 24 to incorporate the following changes:
Revised Section 3.1.3.b.ii1Isothermal Temperature Coefficient (ITC) upper limit value from -2.9 pcmI0F at power level = I 00% RTP to -1.5 pcmI0F at power level
=loo% RTP.
Revised the References section to delete the references to the previous 50.59 screenings for Unit 1, Cycle 23 COLR, and added a new reference to include the 50.59 screening for Unit 1, Cycle 24 COLR, Revision 0.
Revised Table 1 to incorporate revised values for Modes 4, 5, and 6 for Unit 1, Cycle 24 COLR, Revision 0.
Revised Table 2 to incorporate revised W(z) Values for Unit 1, Cycle 24 COLR, Revision 0.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
7j-j~-
Thomas J. Palmisano Site Vice President, Prairie lsland Nuclear Generating Plant Nuclear Management Company, LLC Enclosure (1) 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC
ENCLOSURE I PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT I - CYCLE 24 REVISION 0 21 pages to follow
PRAERiE SSLAND NUCLEAR GENERATtPIG RANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 3/22/90 Original Unit 2 Core Operating Limits Report, distributed with Technical Specification Revision 92.
3122190 Original Unit 1 Core Operating Limits Report, distributed with Technical Specification Revision 92.
1 7/27/90 Incarporated expanded V(z) curves.
2 9/27\90 Clarified rod insertion limit curve applicability.
213 1/97 Incorporated revised FQof2.45 as a resuit of NRC approval of Westinghouse Topical Report WCAP-20924-P-A, Volume 1, Addendum 4, October 1990.
14 0 - Not used.
9/27/90 Updated to Unit 2 Cyde 14, incorporated expanded V(z) curves and clarified rod insertion limit curve applicability.
2 212 1/91 Incorporated revised FQof2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-I 0924-P-A, Votume 3, Addendum 4, October 1990.
15 0 6/25/91 Updated to Unit 1 Cycle 15.
15 0 3/9/92 Updated to Unit 2 Cycle 15 and clarified labeling of Figure 4. Clarified the actions to be taken if the nuclear enthalpy rise hot channel factor exceeds the Technical Specification limit.
16 0 12/28/92 Updated to Unit 1 Cycle 16, removed V(Z) curves and replaced them with list of bounding V(z) values fur three ranges of exposures.
16 0 1218193 Updated to Unit 2 Cycle 16. Removed the multiple V(z) curves and replaced them with a single figure with bounding V(z) curves for four ranges of exposures. lncorporated add~tional discussion related to V(z) and K(z).
Page 1 of 5
PRAIRIE lSLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No., Date Remarks I 1/3/94 The table containing the bounding V(z) values and Figure 2 updated to incorporate revised bounding V(z) values for the exposure range of 14-21.5 GWDIMTU. Figures 3 through 6 re-formatted.
6/47/94 Updated to Unit 1 Cycle 17. Removed the list of bounding V(z) values and replaced it with multiple V(z) curves, Incorporated additional discussion related to V(z) and K(z).
2 +7i 0 6/2/95 Updated to Unit 2 Cycte 17. Incorporated Tabfe 1 and expanded Figure 2 with updated bounding V(z) values.
I 18 0 2/7/96 Updated to Unit 1 Cycle 18. Incorporated revised Kx3 limit of 1.77 Incorporated Table 1 and updated Figure 2 with revised bounding V(z) values.
2 18 0 2127/97 Updated to Unit 2 Cycle 18. Revised F , limit to 1.77. Updated Table I and Figures 2a through 2e with revised bounding V(z) values.
lncorporated new Figures 2f and 2g with additional bounding V(z) values.
1 19 0 9/25/97 Updated to Unit 1 Cycle 19. Updated Tabfe 1 and Figures 2a through 2f with revised bounding Vfz) values.
2 19 0 12/17/98 Updated to Unit 2 Cycle 19. Updated Table 1 and Figures 2a through 2d with revised bounding V(z) values. Deleted Figures 2e, 2f and 29.
1 20 0 511 3/99 Updated to Unit 1 Cycle 20. Updated Table 1 and Figures 2a through 2f with revised bounding V(Z) values.
1 8/4/00 Technical Specification Amendment 151:
Relocate shutdown margin (SOM) requirements from Tech Specs and incorporate additional SDM requirements for Modes 3-6 from rev~sed analysis of Uncontrolled Dilut~onevent.
Page 2 of 5
PRAIRIE ISLAND NUCLEAR GENERATtNG PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks Updated to Unit 2 Cycle 20. Updated Tabte ?
and Figures 2a through 2d with revised bounding V(z) values. Added new Table 2 and Figures Ze, 2f and 213with additional bounding V(z) values.
Added references to Tables 1 and 2 and to Figures 2e, 2f and 2g to discussion of heat flux hot channel factor limits, Added discussion clarifying applicability of axial flux difference limits when using Tables 1 and 2 and Figures 2a through 29. Added discussion of two tier V(z) curve presented in Table 2 and Figure 29.
Technical Specification Amendment 142:
Relocate shutdown margin (SDM) requirements from Tech Specs and incorporate additional SDM requirements for Modes 3-6 from revised analysis of Uncontrolled Dilution event.
Revised to change axial flux difference target band.
Updated to support refueling activities associated with Unit ICycle 21. Revision 0 of the Unit 1 Cycle 21 COLR had to be issued prior to confirming the applicability of the LOCA analysis.
Therefore, Revision 0 of the Unit ICycle 21 COLR does not contain all of the operating limits necessary to support operation of Unit 1 Cycle 21.
Updated to Unit 1 Cycle 21. Updated Tables 1 and 2 and Figures 2a through Zf with revised bounding V(z) values.
Revised to support License Amendment 158 changes. including revision of at! references to TS, revision of Fa symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations Updated to Unit 2 Cycle 21.
2 21 1 10/02/02 Revised to support License Amendment 149 Page 3 of 5
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks changes, including revision of all references to TS, revision of Fa symbols, addition of Table 4, ITC fimits, DNB limits and fueling boron concentrations. Also revised to include an additional V(z) curve to give greater Fo margin between 13.0 and 16.0 GWdtNITU.
Updated to Unit 1 Cycle 22. Updated Tables 1 and 2 and Figures 2a through Zf with revised bounding V(z) values. Incorporated new Figure 29 with additional bounding V(z) values.
Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.
Updated to Unit 2 Cycle 22. Updated Tables 1 and 2. A reduced number of exposure ranges were calculated in Table I, therefore new Figures 2a through 2e with revised bounding V(z) values replaced Figures 2a through Zf. New Figure 2f replaced Figure 29 for the 2 tier band bounding V(z) values. Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.
Revision to incorporate Westinghouse Safety Analysis Transition per LA 1621153. Revision 1 contains transitional values for the OP/OT AT Trip setpoints that will be used while the physical changes are implemented.
Revision to incorporate Westinghouse Safety Analysis transition per LA 162/153. Revision 1 contains transitional values for the OP/OT AT Trip setpoints that wilt be used while the physical changes are implemented.
Revised Fq limit from 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.
Revised Fq limit form 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC Page 4 of 5
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record d Revision Revision Approval Unit Cycle No. Date Remarks methodology and replaced with Westinghouse developed setpoints.
1 23 0 10120i04 Updated to Unit 1 Cyde 23.
2 23 0 - Not used due to core redesign.
2 23 1 5119105 Updated to Unit 2 Cyde 23 and to support redesign of Unit 2 Cycle 23 core.
1 23 1 711 7/05 Revised ITC upper limit from < 0 pcmf0Ffor power levels > 70% R I P to less than a line that slopes linearly from 0 pcrnl'F at 70% RTP to -2.9 pcmf'F at 100% RTP. Revised the title of Figure 3 to reference T.S.3.1.4 Condition B and revised the title of Figure 4 to reference T.S. 3.1.4 Condition A. Added references 24 and 25 to include the 50.59 screenings written to issue revision 1.
5110106 Updated to Unit 1 Cycle 24.
Page 5 of 5
Core Operating Limits Report Unit 1, Gyck 24 Revision O PRAIRIE ISLAND NUCLEAR GENERATING PLANT C O W OPERATING LIMITS REPORT UNIT 1 - CYCLE 24 REVISION 0 Reviewed Ry: Date: 3-% - e z l b Supervisor; NSSS Reviewed By:
Ed Mercier Supervisor, P W Analyses
~
Approved By
- Steve Bmwn Director, Site Engineering Note: This report is not part of the Technical Specifications This report is referenced in the Technical Specifications Page 1 of 16
Core Operating Limits ReporZ Unit I,Cycle 24
- vision 0 PRAIRIE ISLAND NUCXEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT I CYCLE 24 IZ_EVISION 0 This report provides the values of the limits for Unit 1 Cycle 24 as required by Technical Specification Section 5.6.5. These values have been established u s i ~ ~NRC g approved methodology and are established such that all applicable limits of the plant safety andysis are met. The Technical Specifications affected by this report are listed below:
Reactor Core SLs Shutdown Margin (SDM)
Isothermal Tenlperahrre Coefficient (ITC)
Shutdom Bank Insertion Limits Control Bank Insertion Limits Physics Tests Exceptions - MODE 2 Heat Flux Hot Channel Factor (Fct(z))
Nuclear Enthalpy Rise Hot Channel Fmtor (F,~)
Axial Flux Difference ( A D )
Reacror Trip System (RTS)Instrumentation Ovcrtemperaturc AT and Overpotver AT Parameter Values for Table 3.3.1-1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits Boron Concentration
- 1. 2.1.1 Rcactor Core Safetv Limits Reactor Core Safely Limits are shown in Figure I .
Reference Technical Specification section 2.1.1.
3 3.1 .I Shutdon.11h.lar$in Reuziircments I\.li~~imum Shutdown Margin requirements are shown in Table 1 .
Kefere~rceTechnical Specification section 3.1 . 1 Page 2 of 16
Core Operating Limits Report Unit I, Cycle 24 Revision O
- 3. 3.1.3 Isothermal Tem~eratureCoefficient GTCJ ITC Upper limit:
- a. < 5 pcd°F for power levels < 70% RTP; and
- b. Iess than a line which slopes linearly from i) 0 pcnlf'F at power level = 70% RTP to ii) -1. S p c d F at power level = 100%, RTP ITC Lower limit:
- a. -32.7 pcnf"F Reference Technical Specification section 3.1.3.
- 4. 3.1.5 Shutdown Bank Insertion Limits The shutdown rods shall be fulfy withdrawn.
Reference Tcchriical Specification section 3.1.5.
- 5. 3.1.6 Control Bank Insertjon Limits The control rod banks shalt be limited in physical insertion as shown in Figures 2, 3, and 4.
The controi rod banks withdrawal sequence shall be Bank A, Bank B7Bank C.
and finally Bank D.
The conlrol rod bmks sllall be withdrawn maintaining 128 step tip-to-tip distance.
Reference Tech~~ical Specification section 3.1.6.
- 6. 3.1.8 Phvsics Tests Exceptions - MODE 2 M i n i m ~ i ~Shutdotvn li Margin requirements during pl~ysicstesting are shown in Table 1.
Reference Technical Specification section 3.1.5.
Page 3 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0 3.2.1 Heat Flux Hut Channel Factor (Fg(Z)Z The Heat Flux Hot Charnel Factor shall be within the following limits:
CFQ = 2.50 K(Z) is a constant value = 1.0 at all elevations.
W(Z) values are provided in Table 2.
F" t$Z) Penalty Factors are provided in Table 3.
Applicability: MODE 1.
Reference Technical Specification section 3.2.1
- 5. 3.2.2 Nuclear Er~thaluvRise Hot C h a ~ ~ nFactor el IF^^
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
F ~ f<i f .77 x [I + 0.3(1- P)]
\vl~ere: P is the fraction of RATED THERMAL POWER at \vhich the core is operating.
Applicability: MODE I .
Reference Technical Specification section 3.2.2 9 32 . 3 Axial Flus Difference (AFD)
Tt~cindicated axial flux difference, in 94, flux difference units. sl~aflbe rnainiaixled within tile allo\iect operational space defined by Figure 5.
Applicability: MODE 1 with RATED TIiER&IAL POWER 50°'6 RTP.
Iiofi.rencc Technical Specification sectioi~s3.2.3.
Page 4 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0
- 10. 3.3.1 Reactor Trip System (RTS) btmmentation Overtemperature AT and Overpower AT Parameter Values for Table 3.3.1 -1 ;
Overtemperature AT setpoint parameter values:
Indicated AT at RATED THERMAL POWER, %
Average temperamre, "F 560.0 'F Pressurizer Pressure, psig 2235 psig 1.17 0.014 / O F 0.00100 /psi 30 seconds 4 seconds A function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where q, and q b are the percent power in the top and bottom halves of the core respectively, and q, + qb is total core power in percent of RATED THERMAL POWER, such that (a) For q, - q b within --I 3, +8 % qAI) = O (b) -
For each percent that the magnitude of qt q b exceeds +8%
the AT trip setpoint shall be automatically reduced by an equivalent of 1.73 % of RATED THEFWAL POWER.
(c) For cacfl percent that the magnitude of q, - q b exceeds - I3 ?4 the AT trip setpoint shall be automatically reduced by an eql~ivalertt of 3.845 % of RATED THERMAL POIVER.
Overpower AT setpoint parameter values:
AT0 T
'r'
=
=
Indicated AT at RATED THERMAL POWER, %
Average ttemperaturc, "F 560.0 "F Kt K: - 1.11 0.0275i°F for increasing T; O for decreasing T Kt, = 0.0D2iQFfor T 3 T' : 0 for T < T' 7;: - 10 secotlds Page 5 of I 6
Cwe Operating Limits Report Unit 1, Cycle 24 Revisin O
- 11. 3.4.1 RCS Pressure, Temperature, and Flaw - De~artwt:frcun Nucleate Boiling (DM31 Limits Pressurizer pressure limit = 2205 psia RCS average temperature limit = 564'F RCS total flow rate limit = 178,000 gpm Reference Technical Specification section 3.4.1 .
1 2. 3.9.1 Refueling Boron Concentration.
The boron concentration of the reactor coolant system and the refueling cavity shall be sufficient to ensure that the more restrictive ofthe foilowi~zgconditions i s met:
af < 0.95 b) 2000ppm C) The Shutdown Margin specified in Table 1 Reference Technical Specification section 3.9.1.
Page 6 of 16
Core Operating Limits R w r t Unit 1, Cyda 24 Revisian 0 REFERENCES NSPNAD-8 101-A, "Qualification of Reactor Physics Methods for Application to Prairie Island," Revision 2, October 2000.
NSPNAD-8102-PA, "Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Unirs," Revision 7, July 1999.
NSPNAD-97002-PA, "Northern States Power Company's "Stem Line Break
-Methodology," Revision I , October 2000.
IVCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July, 1985.
W CAP- 10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUllfP Code," August, 1985.
IVCAP- 10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTR UiMP Code," Addendum 2 Revision 1, July 1997.
WCAP-10924-P-A, "Westinghouse Large Break LOCA Best Estimate Methodology,'"
Revision 1 . Volume I Addendum 1,2,3>December f 988.
WCAP-10924-P-A, "Westingi~ouseLarge Break LOCA Best Estimate Methodology,"
Revision 2 ,Volume 2 Addendum 1, December 1988, WCAP-10924-P-A, "Westinghouse Large Break LOCA Best Esrimate Methodolo$y,"
Ret isinn 1. Voltirne 1 Addelldurn 3. March 1991.
XN-NF-77-57-(A), XN-NF-77-57, Supplement I (A), "Exxon Nuclear Power Distrrbutio~iControl for Pressurized Water Reactors Phase 11," May 1981, W f AP- 13677-P-A, " 10 CFR 50.46 Evaluation Model Report: W-COBItcLITRAC 2-Loop Upper Plenum Injection Model Update to Support z I R L o ~Cladding~ Options,"
February 1994.
NSPN AD-93003-A, "Prairie lslaiid Units 1 and 2 Transient Poww Distribution h.lct11odolog.y." Revisiu~~ 0, -4pril 1993.
\%'TAP-1 02 16-P-A, Re\ lsion 1A. "Relaxation of Constant Axiaf Offset ControI~FQ Surincillance Technical Specification," Februa~y1994.
il~C~%P-8745-P-A, "Design Bases for the Thernlal 0vctrpo~-er :ZT and Thrr~nal 01cr-tc~npcrature A?' Trip F ~ ~ ~ ~ c t i oSeplerilber ns," 1986.
\b C' A P- t 1397-P-A, "Re~isebThemal Design Proccdure." April 1989.
Page 7 of 16
Core Operating Limits Report Cycle 24 Unit I, Revision 0 WCAP-14483-A, "Generic Methodoiogy for Expanded Core Operating Limits Report,"
J m u q 1 999.
WCAP-7588 Rev. 1-A, "An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods," January 1975.
WCAP-7908-A, "F-4CTRAP-J- A FORTRAN 1V Code for Thermal Transients in a UO:!
Fuel Rod," December 1989.
'#CAP-7907-P-A, "LOFTRAN Code Description," April 1984.
WCAP-7979-P-A, "TWINKLE - A Multidimensional Neutron Kinetics Computer Code," January 1975.
WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code,"
December 198.5.
WCAP- 1 1394-P--4,"Methodology for the Analysis of the Dropped Rod Event," January 1990.
%'CAP-I 1596-P-A, "Qualification of the PHOENIX-PIANC Nuclear Design System for Psessurjzcd Water Reactor Cores," June 1988.
W C A P - t 291 0 Rev. I-A, "Pressurizer Safety Valve Set Pressure Shift," May 1993.
WCAP- 14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurizcd Water Reactor Non- LOCA Thermal-Hydraulic Safety Analysis," October t 999.
WCAP- 14882-P-A, "RETR4N-02 Modeling and Qualification for Westinghouse Pressurized Jliater Reactor Nun-LOCA Safety Analyses," April 1999.
50.59 Evalrration 1054, "Unit 1 Cycte 24 Core Reload."
Page 8 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0 Table 1 Minimum Required Shutdown Margin I Physics Testing in Mode 2 1 0.5% I 0.5% 1 0.5% 1 Operational Mode Definitions, as per TS Table I. 1-1.
- For Mode 1 and Mode 2 with Keff l 1 .O. the minimum shutdown margin requirements are provided by the Rod Insertiotl Limits.
- Charging purnpfs) in service only pertains to steady state operations. It does not include transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column,
- These values are also applicable for the Unit 1 Cycle 23 end of cycle.
Page 9 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revbim 0 Page 10 of 16
Core Operating t i i t s Report Unit 1, Cycle 24 Revlsion O Table 3 F ~ ~ (Penalty z) Factor t
Exposure Range F"~(z)
Penalty Factor I
I BOC EOC 1.02 t Page 11 01 16
Core Operating Limits Report Unit 1, Cyde 24 Revision 0 Figure 1 Reactor Core Safety Limits 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of Rated Thermal Power Page 12 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0 Figure 2 Rod Insertion Limit, 128 Step Tip-&Tip 0 20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Positions Given By:
UOTT' The top nf the active fuel height corresponds to 224 steps. The ARO parking position tnay 17e any positron abo\.e 224 steps.
Page 13of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0 Figure 3 Rod Insertion Limit, 128 Step Tipto-Tip, One Bottomed Rod (Technical Specification 3.1.4 Condition B)
Power Level, % of Rated Thermal Power Bank Positions Giveii By:
SOTE; The top of the active fuel 1.ieigI.itcot-rcspondsto 224 steps. The ARO parking position may be any positlo11above 224 steps.
Page 14 of 16
Core Operating Limits Report Unit 1, Cycle 24 Revision 0 Figure 4 Rod insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4 Condition A) 0 0 20 40 60 80 2 00 Power Level, % of Rated Thermal Power Bank Positions Given By:
N O T E The top of the actit e fuel height correspot~dsto 224 steps. The ARO parking position may nc any position above 224 steps.
Page 15 of 16
Care Operating Limits Report Unit 1, Cyde 24 Revision 0 Figure 5 Flux Difference Operating Envelope Page 16 of 16