NRC 2008-0081, Point Beach, Unit 1, Cycle 32 (U1C32) Core Operating Limits Report.
| ML083010231 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/24/2008 |
| From: | Meyer L Florida Power & Light Energy Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2008-0081, U1C32 | |
| Download: ML083010231 (17) | |
Text
Point Beach N~ilucBeau P8ant October 24,2008 FPL Energy Point Beach, LLC, 6590 IYuclear Road, Two Rivers, Wl54241 NRC 2008-0081 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit I Docket No. 50-266 License No. DPR-24 Unit I Cycle 32 (U1 C32) Core Operatinu Limits Report In accordance with the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.4, "Core Operating Limits Report (COLR)," FPL Energy Point Beach, LLC, is submitting the Core Operating Limits Report for PBNP Unit I Cycle 32 (U 1 C32). The PBNP U1 C32 COLR was issued on October 23,2008. This letter contains no new commitments and no revisions to existing commitments. Very truly yours, FPL Energy Point Beach, LLC Larry Meyer Site Vice President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW An FPL Group company ENCLOSURE CORE OPERATING LIMITS REPORT POINT BEACH NUCLEAR PLANT, UNIT I CYCLE 32 (UlC32)
TRM 2.1 CORE OPERAT T 1 CYCLE 32 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 9 October 23, 2008 CORE OPERATING LIMITS REPORT (COLR) 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Point Beach Nuclear Plant has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.4. A cross-reference between the COLR sections and the PBNP Technical Specifications affected by this report is given below: COLR Section 2. I 2.2 2.12 Figure I Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 PBNP TS - Description Reactor Core Safety Limits Shutdown Margin Rod Group Alignment Limits Shutdown Bank lnsertion Limits Control Bank lnsertion Limits Physics Test Exceptions Moderator Temperature Coefficient Shutdown Bank lnsertion Limit Control Bank lnsertion Limits Nuclear Heat Flux Hot Channel Factor (FQ(Z)) Nuclear Enthalpy Rise Hot Channel Factor (F~~H) Axial Flux Difference (AFD) Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits Curve Required Shutdown Margin Control Bank lnsertion Limits Hot Channel Factor Normalized Operating Envelope (K(Z)) for 0.422V+ Fuel RAOC Summary of W(Z) with HFP AFD Band of -8/+9% Flux Difference Operating Envelope Page 2 of 15 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) TRM 2.1 U1 Revision 9 October 23,2008 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4. 2.1 Reactor Core Safetv Limits (TS 2.1 .I) The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1. Applicability: MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4. 3.1.5, 3.1.6, and 3.1.8) 2.2.1 SDM shall be within the limits provided in Figure 2. Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be 21 % Ak/k. Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3) 2.3.1 The upper MTC limits shall be maintained within the limits. 2.3.2 The maximum upper MTC limits shall be: 55 pcmI0F for power levels <70% RTP SO pcmPF for power levels >70% RTP Applicability: MODE 1 and MODE 2 with bR 21 .O. 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) NOTE: This limit is not applicable while performing SR 3.1.4.2. 2.4.1 Each shutdown bank shall be fully withdrawn. 2.4.2 Fully withdrawn is defined as 2228 steps. Applicability: MODES 1 and 2 2.5 Control Bank Insertion Limits (TS 3.1.6) NOTE: This limit is not applicable while performing SR 3.1.4.2. The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3. Page 3 of 15 POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 9 October 23,2008 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 Applicability: MODE I and MODE 2 with hff 21.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) (TS 3.2.1) The Heat Flux Hot Channel Factor shall be within the following limits: FQ(Z) r CFQ
- K(Z) / Pfor P > 0.5 FQ(Z) r CFQ
- K(Z) 1 0.5 for P r 0.5 Where P is the fraction of Rated Power at which the core is operating. FQ(Z) is both: Steady State FQ'(Z) = FQ(Z)
- 1.08 Transient F~~(z) = FQc(z)
- W(Z) CFQ = 2.60 (422V+ Fuel) K(Z) is the function in Figure 4. W(Z) is the function in Figure 5. The following FQ penalty factors are applicable to Cycle 32. Applicability: MODE 1 Cycle Burnup (MWDIMTU) Beginning-of-Cycle to End-of- Cycle 2.7 Nuclear Enthalpv Rise Hot Channel Factor (FNU) (TS 3.2.2) The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: FWa(z) Penalty Factors 1.02 2.7.1 F~~H 5% RTP per minute; or 2) THERMAL POWER step >I 0% RTP. 2.1 1.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 21 82,400 gpm. Applicability: MODE 1 2.1 2 Refueling Boron Concentration (TS 3.9.1) Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained 22200 ppm. Applicability: MODE 6 Page 6 of 15 POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 9 October 23, 2008 CORE OPERATING LIMITS REPORT (COLR) FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V + fuel) 680 Unacceptable Operation Acceptable Operation 560 -- 54O1*"i"'i"'~"'~'"! 0 0 2 0.4 0.6 0.8 1 1.2 1.4 Core Power (fraction of 1540 MWt) Page 7 of 15 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 9 October 23, 2008 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 FIGURE 2 REQUIRED SHUTDOWN MARGIN 0.0% 0 10 20 30 40 50 60 Core Burnup (%) Page 8 of 15 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Ul Revision 9 October 23, 2008 CORE OPERATING LIMITS REPORT (COLR) FIGURE 3 CONTROL BANK INSERTION LIMITS NOTE: The "fully withdrawn" parking position ranger 225 steps can be used without violating this Figure. Page 9 of 15 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 9 October 23,2008 CORE OPERATING LIMITS REPORT (COLR) FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) FOR 0.422V+ FUEL 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE ~IG~ @I) Page 10 of I5 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 TRM 2.1 U1 Revision 9 October 23, 2008 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9% (Top 15% and Bottom 12% Excluded) Page 11 of 15 HEi$lt (f-1 o.a 0.2 0.4 0.8 0.8 1 .ID 1.2 1 -4 a -8 3 -8 2.101 2.2 2-4 2-6 2.8 3-10 3.2 3.4 3.8 3.8 4.1n( . 4-2 4.4 4-43 4.8 5.dll 5.2 5.4 5-13 5.8 6 -0 6.2 6.4 6.6 6.8 1 SClt lUR%m!&m I .an ~cr I .uaao 1 .UQ DTJ '1 -00 D0 1 .on eo I .anocr I -0QCIO 1 .UO DO I -2288 1.2133 1.1965 1 -3 989 1 .lrii?il I -3 435 1 -1263 4 -1 109 1 -3 1137 1 -313313 1-BUD8 t.09 82 I .ar 54 I .u~Q@ 1 -08 84 1 .a874 1 -0883 1 -08 93 I -09 84 1 -09134 1 -09 84 1-il~36 I -1CIB8 1.3178 1.1257 1 -13313 1.3393 2000 B,T&~~&JUU I -nlntao I ~~~[ltuo 1 .uJBRO 4 .Q~DRDI I .QOUO I .nmm I .Q000 1 .rJ00Q I -1726 1.1594 1.1482 1.1383 I -1278 1-1175 1 -1 lU173 1 .Q983 1 .Q94Q 1.0934 1 -13193 7 I -a597 .I .Q.EE 1 A844 I Al822 1.0548 1 -Q1E75 .l -OE96 1 -rJi935 1 .Q930 1 .Q952 1-lalln 1 -14364 1.1157 1-1223 1.13R9 1-1382 T&r[a SQOO MWmj&flU 3 .a a00 a .a nos Q .Q ~00 4 A DOID Q ,Q cro~ T DOID ID^ Q -a ~01~1 % -0 DOln* 2 :I 743 Q -1 624 1.1491Uf Q -1 363 9.1 258 a-~aci~ 1.1 D62 1 -0 998 2 -0970 Q -0952 %A938 a -0949 "II .a967 1.Q980 "1 .Q 99 1 2 .a 9Q9 .ii -1 004 3.1 004 % .I QOB 41 -1 038 11 .4 Q3B .li :I 0187 "ti .I 367 -li -1 255 .I :I 337 21.1432 % -1477 141DO8 &f II%?J~~%IW 3 .IDTJ~ a 1 .OUQ a 1 .lDBQ Cl 1 -00Q O 3.~431 Q l .00~ a 1 .a011 O 3 .lo011 ll 3.1756 3-1 649 11532 1.141317 3 .I 284 - 1.1 3~3~ 1.1 03.0 1.10193 2 t.OY83 l .a19 84 1.dl198Q I-la975 3.095 8 3 -095 7 l .Q98 3 1.1 U1 a 1.1 048 1.1089 3.1 $28 7l.1352 1 :I 21 5 1.1339 9:1479 3 :I 609 1.1 728 3 :I 838 3.1 935 POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 9 October 23, 2008 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 FIGURE 5 (con't) RAOC Summary of W(Z) with HFP AFD Band of -81+9% (Top 15% and Bottom 12% Excluded) Page 12 of 15 Height [f&t) 7. D 7.2 7.4 7.6 7.8 8.0 8.2 8.4 8.6 8.8 91. D 9.2 91.4 9.6 9.9; a s,o 3 0-2 3 0.4 ~lclr.~i 3 0-8 3 1.0 11-2 3 I -4 11.8 3 1 .i3 12.0 '150 I '8 ,14451 1 .I489 1 ."I528 "0.1 563 .I . 9 586 .Ti .I 595 .I :I 590 "0.1 568 f .I 531 11 .I 530 1 .I 596 ?I .I TST 1 :I 905 11.2D7?5 2.2242 11 -2398 % .2541 1 .omno 'l .aiDnat 1.8D08 9 .0DQ8 ?i .@DO0 1 .31iDO411 $ -8DQal 11 .~DCKlflc 4 .0DQ41( 14CJO40 EYLV~'LS~Y~~FZ~ %.2D37 Z -2Di34 2 -2% 33 .I -29 85 2-2.177 3 -2% 68 % -2% 38 3.2DSB %.2DDB 1.1947 .1i - I 938 .11.1957 'li.ZD4'1 %.2D35 2.2?48 I -233% 1 -2 543 T.QDUO ili.oclolnr 1 -0 1508 % .OD00 4 -Q DUO 4 .OD00 1 -0 D0lnl '~l .O DO0 'tr.rJD00 T~9T(2;1 2800 MVCliItiTriT 1.1447 I ."jD4 .l.Z158 I .?tED6 I .I1643 l.3 1666 I -3 674 4 -3 668 1 -3 1550 1 -3 655 1 .a 729 1.3911 1 1.2Uijr3 1.2238 I -24DO 1.2556 I .2702 I .UQDQ I .OODO 1.04l!D0 1.931iDO 1 -08DQ I .OODO I .Ufl*DQ I -031iDO 1 .OII~DQ 8000 ?kI~JfD/ITU 1 :I 529 1.1578 I -3 627 1-1662 1 .lX382 1 -3 6 88 1.2678 -.I 653 1.3627 1.1638 1 ,?853 1 -11 7617 1 .l!882 1-201 6 1-2146 I -2267 12373 1 .DQ o01 I .DODO 1 .DQ BO 1 .DQ DO 1 .DQ D0 I .DrJ DR 1 .DQ 00 1 .DUD0 I o0 POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 9 October 23,2008 CORE OPERATING LIMITS REPORT (COLR) FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE -35.00 -30.00 -25.00 -20.00 -15.00 -10.00 -5.00 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 Delta I (%) NOTE: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure 2 of ROD 1.2 for administrative limit. Page 13 of 15 POINT BEACH NUCLEAR PLANT TRM 2.1 Ul TECHNICAL REQUIREMENTS MANUAL Revision 9 October 23,2008 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS GULK Section 2.1 2.2 1 2.3 WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision I, October 1999 (cores containing 422V + fuel) 2.4 2.5 2.6 WCAP-10924-P-A, "Large Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addenda, December 1988 (cores not containing 422V + fuel) Parameter Reactor Core Safety Limits Shutdown Margin 1 Moderator Tem~erature Coefficient WCAP-10924-P-A, "LBLOCA Best Estimate Methodology: Model Description and Validation: Model Revisions," Volume 1, Addendum 4, August 1990 (cores not containing 422V + fuel) NRC Approved Methodology --- WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 , WCAP-9272-P-A, "Westinghouse Reload Shutdown Bank Insertion Limit Control Bank Insertion Limits Height Dependent Heat Flux Hot Channel Factor (Fa) WCAP-I 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 Safety Evaluation Method6logy," July 1985 WCAP-9272-P-A, "Westing house Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control Fo Surveillance Technical Specification," February 1994 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSl Condensation Model," July 1997 Page 14 of 1 5 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 9 October 23,2008 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 32 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Page 15 of 15 NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-I 0216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986 WCAP-11397-P-A, "Revised Thermal Design Procedure," April 1989, for those events analyzed using RTDP WCAP-1 4787-PI Rev. 2, "Westing house Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-MSSS Power with LEFM on Feedwater Header)", October 2002. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 COLR Section 2.7 2.8 2.9 2.10 2.1 1 2.12 Parameter Nuclear Enthalpy Rise Hot Channel Factor (F~~H) Axial Flux Difference (AFD) Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration