ML052560211

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Issuance of Core Operating Limits Report for Reload 15, Cycle, 16, Rev 3
ML052560211
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 09/09/2005
From: Cowan P
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052560211 (30)
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Text

Exelon Nuclear www exeloncorp corn Nuclear 2 0 0 Exelon Way Kennett Square, PA 19348 TS 5.6.5.d September 9,2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Peach Bottom Atomic Power Station, Unit 2 Facility Operating License No. DPR-44 NRC h&&

No. 50-377

Subject:

Issuance of the Core Operating Limits Report for Reload 15, Cycle 16, Revision 3 Enclosed is a copy of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Reload 15, Cycle 16, Revision 3. Revision 3 is the result of implementation of revised thermal limits and incorporation of Oscillation Power Range Monitoring (OPRM) set points for Single Recirculation Loop Operation (SLO).

This COLR is being submitted to the NRC in accordance with PBAPS, Unit 2 Technical Specifications (TS) Section 5.6.5.d.

If you have any questions, please do not hesitate to contact Tom Loomis at (610) 765-5510.

Very truly yours, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc:

S. J. Collins, Administrator, Region I, USNRC F. Bower, USNRC Senior Resident Inspector, PBAPS G. Wunder, USNRC Project Manager, PBAPS

Exelon Nuclear - Nuclear Fueis P2C 16 Core Operating Limits Report DM: I& COLR PEACH BO7TOM 2 Page I, Rev. 3 I

CORE OPERATING LIMITS REPORT FOR PEACH BOlTOM ATOMIC POWER STATION UNfT 2 RELOAD 15, CYCLE 16 REVISION 3 Prepared By

/

Engineer Reviewed By:

Date: q/F/m Engineer Date: t--z + QS I

Approved By:

Manager, BWR Design Branch

Exelon Nuclear - Nuclear Fuels P2C16 Core Operathg Limits Report DOC 1D: COLR PEACH BOlTOM 2 Page 2, Rev. 3 I

Revision 3

E x e h Nuclear - Nuclear Fuels PZC14 Core Operating Limits Report Page 3, Rev. 3 I

DOC ID: COLR PEACH WTTOM 2 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 Cycle 16 (Reload 15):

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)

ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Linear Heat Generation Rate (LHGR)

ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multiptiers Rod Block Monitor (RSM) Analytical Limits, Aflowable Values and MCPR Limits Turbine Bypass Valve Parameters EOC Recirculation Pump Trip (02-RPT) Parameters Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints Asymmetric Feedwater Temperature Operation (AFTO) thermal limit penalties These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.

This report provides the means for calculating the Operating Limit MCPR, LHGR, and MAPLHGR thermal limits for the following conditions:

All points in the operating region of the power/flow map including Maximum Extended Load Line limit (MELLL) down to 82.9% of rated core flow during rated thermal power (3514 MWt) operation Increased Core Flow (ICF), up to 110% of rated core flow End-of-Cycle Power Coastdown to a minimum power level of 40%

Feedwater Heaters Out of Service (FWHOOS) to 55" F temperature reduction at any time during the cycle Final Feedwater Temperature Reduction (FWTR) between End-of-Rated (EOR) and End-of-Cycre (EOC) to 90" F temperature reduction maintaining I 100% load line (Reference 1)

Asymmetric Feedwater Temperature Operation (AFTO) - Appendix A The Allowable Values, documented in Reference (l), for feedwater temperature as a function of thermal power for both FWMOOS and FWTR are specified in the appropriate Peach Bottom procedures.

Note that the term 'EOR" refers to the cycle exposure at which operation at "rated conditions" is no longer possible (i.e., the cycle exposure at which cyde extension begins) based on the EOR point as documented in the current revision of the Cycle Management Report.

Exelon Nuclear - Nuclear Fuels P2Cl6 Core Operating Limits Report DOC ID: COLR PEACH BOlTOM 2 Page 4, Rev. 3 I

Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to Mabl-AFTO. A separate description of AFTO limits and their associated ARTS figures are located in Appendix A.

Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is submitted in accordance with Technical Specification 5.6.5 of Reference (2) and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analyses (ARTSIMELLLA) for Peach Bottom Unit 2 Cycle 16.

The MAPLHGR limits (kWIft) obtained from the emergency core cooling system analysis are provided in Figure 1, The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. The MAPLHGR figure is used when hand caiculations are required. All MAPLHGR values for each fuel type as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for the respective fuel and lattice types to be in compliance with Technical Specification 3.2.1. These MAPLHGR limits are specified in References (4) and (5) and the process computer databank. The SLO MAPLHGR multiplier (0.73) is applied as shown in Table 4. This value is based on the GE14 fuel product line. The SLO MAPLHGR multiplier is cramped at 0.73 for any core flow to ensure peak clad temperatures are maintained within the limits of the cycle-specific LQCA analysis for single recirculation loop operation. The MAPLHGR SLO multiplier was obtained from Reference (4). AFTO parameters are addressed in Appendix A.

AR nFaT GFNF-The beginning of life (maximum) LHGR values for each fuel type for use in Technical Specification 3.2.3 are provided in Table 3. The LHGR values as a function of peak pellet exposure are provided in References (5) and (47). The bases fur the LHGR values are documented in Reference (3). The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) are provided in Figures 2 and 3. Figure 2 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service with a maximum temperature reduction of 90" F for FWTR operation. Figure 3 is valid for three or more (of nine) TBVs Out-of-Service (00s) or RPTOOS with a maximum FWTR of 90" F. The flowdependent multipliers (LHGRFAC(F)) are provided in Figures 4 and 5 as a function of the number of recirculation loops in operation only.

The SLO LHGR multiplier (0.73) is applied through LH GRFAC(F) as shown in Figure 5. The power-and flow-dependent LHGR multipliers were obtained from References (l), (6), (7),

(9) and (21). AFTO parameters are addressed in Appendix A.

I lucmJmm The Operating Limit MCPR (OLMCPR) for use in Technical Specification 3.2.2 for each fuel type is provided in Table I. These values are determined by the cycle-specific fuel reload analyses in Reference (4). For Single Loop Operation with Turbine Bypass Valve and Recirculation Pump Trip in-service (Option B) from BOC to OR-2300, the OLMCPR is increased to 1.38 to comply with the results of the Single Loop Operation Recirculation Pump Seizure Analysis described in Reference (1 3). This OLMCPR increase is necessary to prevent violating the Reference (13) SLO SLMCPR considering the appropriate ARTS muitiplier for single pump flows. For all other operating domains, the OLMCPR is increased by 0.02 when operating in SLO (due to the 0.02 safety limit MCPR increase for SLO), The Safety Limit MCPRs are documented in Section 2.1.1.2 of Reference (2).

Control rod scram time verification is required as per Technical Specification 3.f.4, "Control Rod Scram Times". Tau, a measure of scram time performance to notch position 36 throughout the

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report MX ID: COLR PEACH BOTTOM 2 Page 5, Rev. 3 1

cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.O (Tau Option A).

Separate OLMCPR values are presented herein (Table 1) for the following domains:

TBVs In-Service (seven or more in-service) and RPT In-Service, maximum FWTR of 90 O f

TBVs Out-of-Service (three or more out-of-sewice) and RPT In-Service, maximum FWTR of 90 OF 0 T8Vs In-Service (seven or more in-service) and RPT Out-of-Service, msimum FWTR of 90 OF The OLMCPR values are documented in Reference (4) for all of the fuel designs.

The ARTS-based powerdependent MCPR limits, OLMCPR(P), for use in Technical Specification 3.2.2 are provided in Figures 6 and 7. Figure 6 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service and a maximurn temperature reduction of 90 OF for FWTR operation. Figure 7 is valid for three or more (of nine)

TBVs Out-of-Service (00s) or RPTOOS with a maximum FWTR of 90 OF. The flow-dependent MCPR limits, OLMCPR(F), are provided in Figure 8. Figure 8 is valid for all operating conditions with symmetric feedwater temperature operation. OLMCPR(P, F) curves were obtained from References (I), (6), (7), (9),

(16) and (21). AFT0 parameters are addressed in Appendix A.

I The Oscillation Power Range Monitor (OPRM) Period Based Detection Algorithm (PBDA) Trip Settings are based, in part, on the cycle specific OLMCPR and the ARTS-based power dependent MCPR limits [K(p) muftiplier] (see OPRM discussion below).

1 I.r-ARTS provides for power-and flowdependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. At any given powerlflow (P/F) state, all four limits are to be determined: LHGRFACtP), LHGRFAC(F), OLMCPR(P), and OLMCPR(F) from Figures 2 through 15, inclusive. The most limiting MCPR and the most limiting LMGR [maximum of OLMCPR(P) and OLMCPR(F) and minimum of LHGRFAC(P) and LHGRFAC(F)] for a given (P,F) condition will be the governing limits. The OLMCPR for each fuel type is determined by the cycle-specific fuel refoad analyses in Reference (4). Rated LHGR values are obtained from the bundle-specific thermaJ-mechanical analysis. Supporting documentation for the ARTS-based limits is provided in References (l), (4), (3, (8), (9) and (21).

I FTPOlMfS The RBM power-biased Analytical Limits, Allowable Vafues and MCPR Limits for use in Technical Specification 3.3.2.1 are provided in Table 2 per Reference (6) with supporting docurnentation in References (4) and (10).

M O P F W I I I q The operabilitv requirements for the steam bvmss svstem are aoverned bv Technical Specification 3.7.6. If the reouirernents cannot be met, the amrooriate Dower dependent limits for Turbine Bvpass Valves Out-of-Service (78VOOS\\ must be used (Table 1 with Fiaures 3 and 7 or Fiaures 10 and 141.

The minimum number of bvpass valves to maintain svstem operabilitv is seven as Der Reference (1 1) and Table 5. Table 5 also includes other Turbine Bypass Valve parameters.

Exefon Nuclear - Nuclear Fuels P2C 16 Core Operating Limits Report DOC ID: COLR PEACH BorrOM 2 Page 6, Rev. 3 1

RF-l ATtpbLeulylP --RRPWFRL\\)31l11t;ll If the EOC-RPT is inoperable, then the OLMCPR (Table I), LHGRFAC(P) (Figure 3), and OLMCPR(P) (Figure 7) values for EOC Recirculation Pump Trip Out-of-Service (RPTOOS), must be used. Appendix A contains LHGRFACfP) and OLMCPR(P) for RPTOOS with AFT0 conditions.

The measured EOC-RPT Response Time as referenced in Technical Specifications Section 3.3.4.2 and as defined in Technical Specifications Section 1.I shall comply with the surveillance requirements in Reference (12) and applicable site procedures for TCV Fast Closure Trip (i.e.

Generator Load Drop) and TSV Fast Closure Trip (Le. Turbine Trip).

A total EOC-RPT system response time acceptance criterion of 0.1 75 seconds is assumed in the safety analysis for both trips and is defined as the time from the turbine vafves (TCV or TSV) start to close until complete arc suppression of the EOC-RPT circuit breakers.

Cycle 16 is not licensed for TBVOOS and RPTOOS to occur concurrently. Therefore, concurrent TBVOOS and RPTOOS is an unanalyzed condition.

The Cycle 16 OPRM Period Based Detection Algorithm (PBOA) Trip Settings are provided in Tables 6 and 7. These values are based on the cycle specific analysis documented in References 18 and 20. The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Reference 19). The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-234 through 237 (Unit-I

2)
  • Table 7 provides alternate PBDA Trip Settings that may be applied during single loop operation (SLO) conditions. These trip settings are applicable when in SLO, with reactor power less than or equal to 65% of rated. The standard two loop operation OPRM Trip Settings specified in Table 6 are bounding for both two loop and SLO conditions. The standard two loop operation OPRM Trip Settings specified in Table 6 must be implemented prior to restarting the idle pump when exiting the SLO condition.

Any change to the OLMCPR values and/or the ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Settings.

REFERENCES

1. "Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 90' F', NEDC-32707PI Supplement 1, May 20, 1998
2. "Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Docket No. 50-277, Appendix A to License No. DPR-44
3. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-14, June 2000; and NEDE-24.01 I-P-A-M-US, June 2000
4. "Supplemental Reload Licensing Report for Peach Bottom 2, Reload 15 Cycle 16", GIobai Nuclear Fuel Document No. 5000-0025-6977-SRLR, Rev. 0, August 2004

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report DOC t o COLR PEACH BOITOM 2 Page 7, Rev. 3 1

5. Fuel Bundle Jnformation Report for Peach Bottom 2, Reload 15 Cycie 16, Gfobal Nuclear Fuel Document No. 0000-0025-6977-FBIR, Revision 0, August 2004
6. Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3, NEDC-32162P, Revision 2, March 1995
7. ARTS Flow-Dependent Limits with TSVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, NEDC-32847P, June 1998
8. Letter, G. V. Kumar to A. M. Olson, PECO Rerate Project, ARTS Thermal Limits, June 27, 1995
9. Peach Bottom Atomic Power Station Units 2 & 3 Plant and Cycle-Independent ARTS Thermal Limits Analyses, NEDC-32162P, Supplement 1, Revision 0, August 2001
10. PECO Energy Calculation PE-0251, Power Range Neutron Monitoring System Setpoint Calculations Peach Bottom Atomic Power Station Units 2 & 3, Revision 1 1 1. Peach Bottom 2 Cycle 16 OPL-3, Gtobal Nuclear Fuels eDRF #0000-0024-7901, Suresh Gupta, August 12,2004
12. PEG0 Calculation PE-0173, Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breaker
13. GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2

& 3, GENE L12-W880-00-01 PI September 2000

14. Safety Review for Peach Bottom Atomic Power Station Units 2 and 3 Asymmetric Feedwater Temperature OperationJ, NEDC - 32691 P, Revision 0, May I997
15. ECR 02-00478, Asymmetric Feedwater Operation Implementation
16. Letter, F. T. Bolger to C. P. Collins, Removal of MCPR(F) Low Flow Correction in NEDC-32847P, February 4, 2002.
17. Letter, Michael P. Galfagher to U. S. Nuclear Regulatory Commission, Peach Bottom Atomic Power Station Units 2 & 3, Facility Operating License Nos. DPR-44 and DPR-56, NRC Docket Nos 50-277 and 50-278, License Amendment Request 01-01 190 Power Uprate Request for Appendix K Measurement Uncertainty Recapture, May 24,2002
18. Peach Bottom 2 Cycle 16 Option lit Stability Analysis, GENE-0000-0031

-5879-RO, January 2005

19. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload
20. EC 356623, Evaluation of PBAPS SLO OPRM Trip Setpoints for Peach Bottom 2 Cycle 16
21. Peach Bottom 2 and 3 Off-Rated Analyses Below the PLU Power Levet, EE-NE-0000-0041-Applications, NED0-32465-A, August 1996.

and Unit 3 Cycle 15 AT 244909-10, July 29,2005.

8205-R0, Revision 0, August 2005.

Exelon Nuclear Nuclear Fuels P2C1 S Core Operating Limits Report:

DOC ID: COLR PEACH BO?TOM 2 Page& Rev. 3 I

FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATtON RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ALL FUEL TYPES 14.00 12.00 iO.OO E

E s *,0° 5

2 3

3 6.00 5

4.00 2.00 0.00

--......_._...I._

\\

^_

0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 Average Planar Exposure, GWdET Avg Plan Exposure MAPLHGR lGWdlSn fkWlftl 14.51 i 2.82 0.0 12.82 19.13 12.82 57.61 8.00 63.50 5.00

Exelon Nuciear - Nuclear Fuels P2C16 tore Operating Limits R e p w t DOC ID: COLR PEACH BOITOM 2 Page 9, Rev. 3 FIGURE 2 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPEClFlCATlON 3.2.3 VALID FOR 7 OR MORE TBVS IN-SERVICE, RPT IN-SERVICE AND MAX 90' F RNTR 1.I 1.a 0.9 0.8 0.7 ii:

0' a Ir. 8

.& I ii 3 0.6 P

'a I

L 8 0.5 a

0.4 0.3 0.2

60%FloW (30,0.600)

[25,0.584)

(25,0.532) :

(85,l.OoO)

(55fJ.798)

For PS 25%: No Thermal Lids knitwing Required No ltrnits specified For 25% 5 P< P(Bypass):

(p(Bypass) = 30% tor PBAFS U n 6 2 8.3)

LHGRFAqp) = 0.60 + 0.0032 * (P30) For Row 2 60%

LHGWAqp) E 0.338 + 0.0072 O ( P 3 0 ) Far Row > 60%

For 30% 5 P < 40%: LHGWAC(p) = 0.798 + 0.0048 (PM)

For 40% 5 Pc 55%: =0.798 For 55% 5 P<65%: LHGRFAC(p) =0.900+0.0102(P65)

For 6570 5 P < 85%: LffiWAC(p) = 1.OM) +0.0050 (P85)

For 85% c p:

LffiRFAap} = I.OM 20 25 30 35 40 45 50 55 60 65 70 75 ao 85 90 95 too Power (%Rated)

Exelon Nuclear - Nuclear Fuels P2C15 Core Operating Limits Report FIGURE 3 DOC 10: CQLR PEACH 30lTOM 2 Page 10, Rev. 3 I

POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3,3.3.4.2 and 3.7.6 1

1

0.
0.

0.;

0.E 0.5 A

P U

0 g -

8.- E s

t 0.4 r

2 0.3 0.2 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 O F FWTR i

z 60% Row LHGR@) = WGRFAC(p)

  • UtGR(sLd)

For P<25%No Tt~rmal limits Monitoring Reqoira No limits specified Far%% SP <P(Bypess):

fP(Bypass)=Whfor PBAPSUlits283)

U-1GRFAClpJ=0572eO.O00~P30) ForFlow s 60%

WGRFAC(p)=0.460+Q.W78(P-30) ForFbw > 6046 For 3% L P ~40%: MGRFAC(p) =0.7oS

+O.WB ( P a )

For 4G% s;P 4 5 % LHGRFACIp)=O.744+0.0025(P-55)

For%% SP 45% MGRFAAC(p)=O.93osO.~(P-85)

For%% sP < W d u.IGRFAC(p)=1~+0.007O(P-95)

For%% 6 P: LHGRFAc(p) = 1W 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (10 Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Qpwattinq Limits Report FIGURE 4 DOC ID: COLR PEACH BO7TOM 2 Page 11, Rev. 3 1

FLOW-DEPENDENT LNGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFCARON 3.2.3 VALID FOR TWO LOOP RECIRC FLOW 1.oo I

I

+

For Two Law Operation, 5 70% WT I

LHGRFAC(F) = The Minimum of EEHER 1.0 OR (0.0268 X ('NT - 70)/10 + 0.9732) 1.oo j

LHGR(F) = LHGFtFAC(F)

I

-t i

For Two Law Operation, 5 70% WT LHGRFAC(F) = The Minimum of EEHER 1.0 OR (0.0268 X ('NT - 70)/10 + 0.9732) 0.3 !-

I i

0.2.+

0.1 7 For Two Loop Operation, 5 70% WT LHGRFAC(F) = (0.6682 x (WdIOO)+ 0.5055}

WT= % Rated Core Flow 1.oc f

10 20 30 44 50 60 70 80 90 100 110 CORE FLOW (% RATED)

Exelon Nuclear - Nuclear Fuels PZC 1 6 Core Operating Limits Repart D M I5 COLR PEACH BOITOM 2 Page 12, Rev. 3 1

FIGURE 5 FLOW-DEPENDENT LHGR MULTIPUER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFEATION 3.2.3 AND 3.4.1 VALID FOR SfNGLE LOOP RECfRC FLOW 1.1 1

0.9 0.8 0

q LL pc a '

0.7 0.6 0.572 0.5 0.4 1,

~... ^_ ___.._,,,,.

'LWGR(F) = LHGRFAC(F) LWGR(std) jLHGR(std) = Standard LHGR Limits

!LHGRFAC(F) = (Af

= 0.73; whichever is lower j

I

~ W T

= YO Rated Core Flow IAf =: 0.6682, Bf = 0.5055 j

...-,,~"....I-___....I 0.73 I

I 1

t I

I I

10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Razed)

Exelon Nuclear - Nuctear Fuels PZC16 Core Operating Limits Report TWO LOOP Operation MWd/ST BOC to EOR -2300 EOR - 2300 MWCUST to EOC BOG to EOR -2300 Single Loop Operation MWUST EOR - 2300 MWd/ST to EOC DOC ID: COLR PEACH BOTTOM 2 Page 13, ~ e v.

3 I

TBV in Service and RPT in Service TBV aut of Service (3 or more TBVOOS)

Option 3 Option A Option B Option A z=o 2 = 1 z=o z=1 i.33 1.36 1.38 1.41 1.38 1.41 1.44 1.47 1.38'3' 1.38 Z.40 1.43 1.40 1.43 1.46 f.49 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)

Opt3on B 2 = 0 Applicable to all fuel types Use in conjunction with Figures 6, 7, and 8 For OLMCPR when in Single Loop Operation, See Note (2).

Option A

%=1 These Tables are referred to by Technical Specification 3.2.2, 3.4.1 and 3.7.6 1.38 1.45 1.40 1.47 J

1.49 1.62 1.51 1.64 RPT 00s NOTES:

1) When Tau does not equal 0 or 1, use linear interpolation.
2) For single-loop operation, the MCPR operating limit is 0.02 greater than the two loap value except when the Two Loop Operation MCPR operating limit is less than 1.36 (consistent with Reference 1 3).
3) OlMCPR limit set by the Single Loop Operation (SLO) - Recirculation Pump Seizure Analysis.

(Reference 13)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Repart DOC ID: COLR PEACH BOTTOM 2 Page 14, Rev. 3 I

FIGURE 6 POWER-DEPENDENT MCPR LIMIT, OLMCPR(P), AND MULTlPllERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR 7 OR MORE TBVS IN-SERVICE, RPT IN-SERVICE AND MAX 90 OF FWTR VALID FOR TWO OR SINGLE LOOP RECIRC FLOW 4.0 3.8 3.6 3.4 3.2 3.0 2.8 (25,2.72)

> 60% ROW P

E 2.4 -

Y v

2.6 -.

s a

. (30, 2.52)

(25,297)

I 6

2.2

60%Row Operating Lirrit MBR (6

= Kp

  • Operetblg L M NICPR (100)

For Fk 25%: No Thermal Urnits fvbnitoring Required No limits speccied For 25% 5 P< p(6ypass):

(Fpypassf

= 30% for WAFS #ts 2 8 3)

OLFXPF~(P)

= 2.38 +o.oja * (30-4 For ROW 5 60%

OLMcpFl(p)

= 2.52 + a.04 * (30-4 For Row z 60%

For30% cPc409b: K(q =1.286+0.0054o(40-~

%r40% 5 Pc55%: K ( 4 = 1.256 +O.WZop (55 - P)

For 55% 5 Pc 65%: K(P) = 1.131.t 0.01250 (65 - Pj For65% CF? K(p)=1.M#)+O.oo375~1oO-q (40.1.286)

(65,1,131) 1.o 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (%Rated)

Exeion Nuclear - Nuclear Fuels P2Ct 6 Core Operating Limits Report FIGURE 7 DOC ID: COLR PEACH BOIOM 2 Page 15, Rev. 3 i

POWER-DEPENDENT MCPR LIMIT, OLMCPR(P), AND MULTIPLIERS THIS FfGURE IS REFERRED TO BY TECHNICAL SPECIFJCATION 3.2.2,3.3.4.2 and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 OF FWTR 4.c 3.t

3.

3.4 3.2 3.0 2.a 2

8 s z

P 0 2.4 2.6 2

2.2 LL a 3

g 2.0

=

a P '

1.8 f

0" 1.6 1.4 1.2 1.o VALID FOR TWO OR SINGLE LOOP RECIRC FLOW

-__I_-

1.440)

Operating Urrit kKX3 (p) = Kp

  • Operating L i d MXA (100)

For p< 25%: No Therml Lnits hrbnitoring Required No lids specified For 25% 5 P < p(Bypass):

(qBypass) = 30% for WAPS &tits 2 8 3)

QLMcpR(p) = 2.72 + 0.098 ' (30-PJ For Flow -< 60%

OLMSR(p) = 3.21 e 0.098 * (30-Pj For Row > 60%

For 30% 5 P c 40%: K(p = 1.440 + 0.0t3W (40- 6 For 40% 5 P c 55%: K(Pf = 1.335 + 0.00700 (55 - 9 For55% cP.:65%:

K(F)=1.131 +0.02040(65-~

For 65% 5 I?

K(p) = 1.ooO + O.OO375 (100- p)

(55,1.335) 20 25 30 35 40 45 50 55 60 65 70 75 ao 85 90 95 100 Power (%Rated)

DOC ID: COLR PEACH BOTTOM 2 Page 16, Rev. 3 1

Exelan Nuclear - Nuclear Fuels P2C16 Care Operating Limits Report FIGURE 8 FLOW-DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3,2.2 VALID FOR ALL CONDITIONS 2.M 1.9 1.a I.7c n

& 1.N pc 8 3 0

1.50 1.40 1.30 1.20 1.10 MCPR(F) = The Maximum of EITHER 1.25 OR { -0.5784 x (WT/IOO)+ 1.7073)

WT= O h Rated Core Flow 0

10 20 30 MI 50 80 70 80 90 100 110 Core Flow (% Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report Doc ID: COLR PEACH WITOM 2 Page 17, Rev. 3 1

ROD BLOCK MONITOR ANALYTICAL LIMITS, ALLOWASLE VALUES, AND MCPR LIMITS THIS TABLE IS REFERRED TO BY TECHNICAL SPEClFiCATlON 3.3.2.1 Applicability:

BOC to EOC High Power Range - Upscale (1)

These Trip Level Settings (with RBM filter time constant between 0.1 and 0.55 secands) are based on a cyclespecific rated RWE MCPR limit of 1.30 which is less than the minimum cycle OLMCPR (References (4), (6) and (10))

(2)

This is the MCPR limit (given THERMAL POWER 2 28.4% and c 90% RTP) below which the RBM is required to be OPERABLE (References (4) and (6) and TS Table 3.3.2.1-1).

(3)

This is the MCPR Limit (given THERMAL POWER 2 90% RTP) below which the RBM is required to be OPERABLE (References (4) and (6) and TS Tabie 3.3.2.1-1).

Exelon Nuclear - Nuclear Fuels PPCI 6 Core Operating Limits Report DOC ID: COLR PEACH BOTTOM 2 Page 18, Rev. 3 u a E 3 DESIGN LiNEAR HEAT GENERATION RATE (LHGR) LIM1TS FuEuxE GE14

-Ltum&u 13.4 kW/ft rAB.LA SINGLE LOOP AhAPLHGR MULTIPLIER GE14 jVrUlTrPLlEa 0.73 The LHGR Limits provided above are the beginning of life (maximum) vatues. The 1HCR limits as a function of peak pellet exposure are provided in References (5) and (17).

Ekelon Nuclear - Nuclear Fuels PPC16 Core Operating Limits Report DOC ID: COLR PEACH Bo?TOM 2 Page 19, ~ e v.

3 I

TURBINE BYPASS VALVE PARAMETERS Maximum detay time before start of bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above defay time)

Minimum required number of bypass valves to maintain system operability 0.10 sec 0.30 sec.

7

Exelon Nuclear - Nuclear Fuels P2Cl6 Cote Operating Limits Report DOC 10: CQLR PEACH BOTTOM 2 Page 20, Rev. 3 I

Oscillation Power Range Monitor (OPRM)

Period Based Detection Algorithm (PBDA) Trip Settings*

Valid For All Conditions Corresponding Maximum 15 Oscillation Power Range Monitor (OPRM) - SLO**

Period Based Detection Algorithm (PBDA) Trip Settings*

Valid For SLO Conditions Only With Reactor Power s 65%

1.16 Corresponding Maximum t Trin 17

  • The PBDA is the onfy OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system. The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPIDs) G-080-VC-234 through 237 (Unit-2).
    • The standard two loop operation OPRM Trip Settings specified in Table 6 must be implemented prior to restarting the idle pump when exiting the SLO condition.

Exelon Nuclear - Nuclear Fuels P2Cl6 Core Operating Limits RepMt D M ID: COLR PEACH BOTTOM 2 page 21, Rev. 3 I

ASYMMETRK FEEDWATER TEMPERATURE OPERATION Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating either the ' A or the 'C' heater strings wilt result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel.

Asymmetric feedwater temperature operation (AFTO) is defined as operation in a feedwater heatedstring configuration which results in a specified threshold temperature difference. This threshold is a function of power and flow. The curve of the threshold values is incorporated in the station procedures that govern A m 0 (Reference 15).

As a result of analyses documented in Reference (141, a 4% penalty has been applied to the MCPR ARTS curves and a 7% penalty has been applied to the LHGR ARTS curves and MAPLHGR to ensure that sufficient thermal margin exists during anticipated operational occurrences while in AFTO.

l9kmumm The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) for asymmetric feedwater temperature operation are provided in Appendix A, Figures 9 and 10. Figure 9 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service, maximum 90 OF FWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. Figure 10 is valid for three or more (of nine) T6Vs Out-of-Service (00s) or RPTOOS, maximum 90 OF FWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. The flow-dependent multipliers (LHGRFAC(F)) for AFT0 are provided in Appendix A, Figures 11 and 12 as a function of the number of recirculation loops in operation only.

The SLO LHGR multiplier (0.73) is applied, with a 7% penalty, through LHGRFAC(F) as shown in Figure 12. LHGRFAQF) is clamped at 0.679 starting at 33.6% of rated core flow for single recirculation loop and asymmetric feedwater temperature operation. The power-and flow-dependent LHGR multipliers were obtained from References (l), (4), (6), (7), (9) and (21) and were adjusted with a 7% penalty as per Reference (14).

I v

The ARTS-based power-dependent MCPR limits, OLMCPR(P), for use in Technical Specification 3.2.2 during asymmetric feedwater temperature operation are provided in Appendix A, Figures 13 and 14. Figure 13 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service, maximum 90 OF FWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. Figure 14 is valid for three or more (of nine) TBVs Out-of-Service (00s) or RPTOOS, maximum 90 OF FWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. The flow-dependent MCPR limits, OLMCPR(F), for AFT0 are provided in Appendix A, Figure 15. Figure 15 is valid for ail operating conditions with AFTO. The power-and flow-dependent OLMCPR curves were obtained from References (I), (4), (6),

(7), (9), (16) and (21) and were adjusted with a 4% penalty as per Reference (14).

I

Exelon Nuclear - Nuclear Fuels P2Cl6 Core Operating Limits Report DOC tD: COLR PEACH BOTTOM 2 Page 22, Rev, 3 I

MAPLHGALLMrrS A 7% penalty is applied to all MAPLHGR limits for all conditions under asymmetric feedwater temperature operation (AFTO) as per Reference (14). The penalty is being applied as a 0-930 multiplier for all conditions, except single-loop operation (SLO), in Table 8. For single-loop operation, 1 the AFT0 multiplier is also applied to the MAPLHGR limits. The SlO multiplier (0.73) from Reference (4) is multiplied by the AFTO multiplier (0.93) in Table 8. Therefore, the SLO MAPLHGR multiplier is clamped at 0.679 as shown in Table 9 to ensure peak clad temperatures are maintained within the limits of the cycle-specific LOCA analysis for single recirculation loop and asymmetric feedwater temperature operation.

I AFTO MAPLHGR MULTIPLIER (EXCEPT SINGLE LOOP OPERATION)

FUEL.IYPE GE14 0.93 I A B l m AFT0 SINGLE LOOP MAPLHGR MULTIPLIER FUELTYPE GE14 NlULTlPLlER 0.679

Do(: iD: COLR PEACH BOITOM 2 Page 23, Rev. 3 I

Exelon Nuclear - Nuclear Fuels P2C 16 Core Operating Limits Report flGUREg POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FfGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 VALID FOR 7 OR MORE TBVS IN-SERVICE. RPT IN-SERVICE, MAX 90 "E FWTR, WfTH MAX 55 "F TEMPERATURE DIFFERENTIAL BE~WEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.o 0.9 0.8 0.7 h

P 2

k 3

8 3 3 0.6 3 '

0.5 f:

t if!

0.4 0.3 0.2 (85.0.930)

(100,0.93(

(40.0.742)

(55.0.742)

(30,0.698)

LHGRp) = LHGRFAqp) x LffiRfStd)

For P< 25%: No TnerrrPit Lids M i r i n g Required b b kits specified For 25% 5 Pc P(8ypass):

(&Bypass) = 30% for WAF5 hits 2 & 3)

LHGRFAcfp) = 0.558 i O.M)30 x (P-30) For Row 5 W/O LHGAFAqp) = 0.528 + 0.0053 x (P30) For Row > 60%

For 30?& 5 P 40%: LHGRFAqp) = 0.742 t 0.0044 x (P40j For 40% 5 P < 55%: LffiFFAC(p) = 0.742 For 55% 5 P < 85%: LHGRFAC(p) = 0.837 + 0.00% x (Pa;)

For 65% 5 P e 85%: LffiRFAcfp) = 0.930 t 0.00465 x (P-85)

For 85% 5 P: LffiRFAQp) = 0.930 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (%Rated)

Exelon Nuctear - Nuclear Fuels P2C16 Core Operating Limits Report Page 24, Rev. 3 f

DOC ID: CQLR PEACH BOITOM 2 E l a R u Q POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED 70 BY TECHNICAL SPEClFiCATlON 3.2.3,3.3.4.2, and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 OF FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEQWATER SPARGER LINES (AFTO) 1.I I.o 0.9 0.8 0.7 n

5 iz 3

K Q 3 0.6 n

E -

0.5

0. t 0.4 0.3 0.2 For Pc 25%: No Thermal tiMs Monitoring Required No iirrits specified For 25% 2 P < &Bypass):

(FyBypass) = 30% for PBAFS Wits 2 ti 3) ttlGWAqp) = 0.532 + 0.0120 x (P-30) For Flow 2 60%

LffiRFAC(p) = 0.428 + 0.0072 x (P-30) For Flow > 60%

For 30% 5 P < 40%:

Fcrf 55% 5 P < 85%:

LffiRFAC(p) = 0.657 + 0.00080 x (P-40)

For 40% 5 P < 55%:

LffiRFAC(p) = 0.692 + 0.03233 x (P-55)

For 85% 5 P< 95%:

LHGRFAC(pJ = 0.930 + 0.00650 x (P-95)

LHGRFAC(p) = 0.865 + 0.00577 x (P-85)

For 95% 5 P: LHGRFAQp) = 0.930 20 25 30 35 40 45 50 55 60 65 70 75 80 a5 90 95 100 Power (%Rated)

Exelon Nudear - Nuclear Fuels P2C 16 Core Operating Limits Report DOC ID: COLR PEACH BOTT'OM 2 Page 25, Rev. 3 I

EwLmEu FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE tS REFERRED TO BY TECHNICAL SPECiFfCATlON 3.2.3 VALID FOR 2 LOOP RECIRC FLOW WITH MAX 55 O F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARCER LINES (AFlO) 1.c O"9 0.8 0.7 0.6 n 5

u. 0.5 rx (II 5 0.4 0.3 0.2 0.1 0.0 LHGR(F) = LHGRFAC(F) x LHGR(std)

For TWO Loop Operation, > 70% WT LHGRFAC(F) = The Minimum of EITHER 0.930 OR {0.0250 X (WT -70)/10 +.9050]

For Two Loop Operation, 5 70% WT LHGflFAC(F) = (0.6217 X (WT/lOO)+ 0.4701)

W p % Rated Core Ftow 10 20 40 50 60 70 80 90 loo CORE FLOW (% RATED) 0.9:

110

Exeton Nuclear - Nuclear Fuels P2C16 Cwe Operating Limits Report DOC ID: COLR PEACH BOTTOM 2 Page 26, Rev. 3 FtGURE12 FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPEClFlCATlON 3.2,3 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW WITH MAX 55 O F TEMPERATURE DIFFERENTIAL BENVEEN FEEDWATER SPARGER LINES (AFTO) 0.679 0.67!

0 3

a 3

2 0.5 -

c) 0.4 0.3 -

0.2 0.1.I LHGR(F) = LHGRFAC(F)

Li-tGR(std) = Standard LHGR Limits LHGRFAC(F) = MIN(0.679, Af*W$IOO t Bf);

where, WT = % Rated Core Flow Af = 0.6217, Bf = 0.4701 0.0 !

1 f0 20 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)

xelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report Page 27, RW. 3 I

ElmmA3 POWER-DEPENDENT MCPR LIMIT, OLMCPR(P), AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPEClFlCATlON 3.2.2 DOC ID: COUZ PEACH BOTTOM 2 VALID FOR 7 OR MORE TBVS IN-SERVICE, RPT IN-SERVICE, MAX 90 OF FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LIMES (ARO)

VALID FOR TWO OR SINGLE LOOP RECIRC FLOW 3.0 2.8 2.6 2 4 c9 2 L

3 A

v P 2.2 E

IL 0

3 0 2.0 1.8 1.6 h

a 1.4 Y

.O

< 50% Flow i FORM% 2 PC 55% :

fDR55%5 PC 65% :

tQ = 1.306 + O.oQ207' ( 55% f l')

Kp = 1.176+0.013O '( 65% ~ P) 30,248)

FOR65%5 P: Kp = 1.040 +0.00389 '( loQ% - F)

I 0

10 20 30 40 50 60 70 80 90 100 Power {% Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report Page 28, Rev. 3 I

DOC 10: COLR PEACH BO7TOM 2 E l w E E s POWER-DEPENDENT MCPR LlMlT, OLMCPR(P), AND MULTIPLIERS THIS FIGURE tS REFERRED TO BY TECHNICAL SPEClFICATfON 3.2.2, 3.3.4.27 and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 O F FWTR, WITH MAXiMUM 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGEA LINES (AFTO) 3.8 3.6 VALID FOR TWO OR SINGLE LOOP RECIRC FLOW 4.0 I 3.4 3.2 3.0 FOR 25% 5 P < 30%:

otMcpR(p) =2.83+0.102 ' (30%

~ P, FOR R.OWj6O%

I 3.34 + 0.102 * (30%. Pj FOR Row > 60%

m30%

5 P<40% :

FOR 40% 5 P < 55% :

FOfl55%5 Pc65% :

Kp = 1.498 +0.01350' ( 40%. pl Kp = 1.388 + 0.00733 ' ( 55% ~ P) t@ = 1.176 t0.0212

  • ( 65% - p)

FOR 65% 5 P: Kp I 1.040 + 0.00388 * ( 100% - 9

^ "

t P 1.0 s 2.8 Q

P 2.6 0

h Y

P 0

0 2.2 2.4 3

2.0 0

10 20 30 40

!XI

$0 70 so 90 fM)

Power ("7 Rated)

I.

1.6 P s

,& 1.4 a

2t.-

a I 1.2.r

Exeion Nuciear - Nudear Fuels P2C16 Core Operating Limits Repart DOC If): COLR PEACH BOTTOM 2 Page 29, R ~ V. 3 i

FLOW-DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FfGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 AND 3.4.1 VALID FOR ALL CONOiTlONS WflH MAXIMUM 55 O F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 200 1.W 1.80 1.70 g 1.60 4

3 e

1.50 1.40 1.30 1.20 1.10 MCPR(F) = The Maximum of ElTHER 1.30 OR { -0.60i 6 x (Wd1 OO)+ 1.7756)

W,.= % Rated Core Flow 1

J 1.300 1.300 Core Flow (% Rated)

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