L-05-081, Cycle 12 Reload and Core Operating Limits Report

Cycle 12 Reload and Core Operating Limits Report

ML051180167
Person / Time
Site:	Beaver Valley
Issue date:	04/22/2005
From:	Pearce L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-05-081
Download: ML051180167 (12)

Text

FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport. PA 15077-0004 L. William Pearce 724-682-5234 Vice President Fax: 724-643-8069 April 22,2005 L-05-081 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 12 Reload and Core Operating Limits Report Beaver Valley Power Station, Unit No. 2 completed the eleventh cycle of operation on April 3, 2005, with a burnup of 19,538.54 MWD/MTU. This letter describes the Cycle 12 reload design, provides a copy of the Core Operating Limits Report (COLR) in accordance with Technical Specification 6.9.5.d, and documents our review in accordance with 10 CFR 50.59 including our determination that no Technical Specification or license amendment was required for the Cycle 12 reload design.

During the 2R1 I refueling, 1 Region 8A, 20 Region l lA, 12 Region 1 IB, 8 Region 12A, and 20 Region 12B assemblies were discharged and replaced with 33 fresh Region 14A fuel assemblies enriched to 4.20 nominal weight percent and 28 fresh Region 14B fuel assemblies enriched to 4.80 nominal weight percent.

FirstEnergy Nuclear Operating Company has performed a review of this reload core design to determine those parameters affecting the design basis limits and the safety analyses for postulated accidents described in the Updated Final Safety Analysis Report (UFSAR). The analytical methods used to determine the core operating limits meet the criteria specified in Technical Specification 6.9.5.a, b and c. The Cycle 12 reactor core reload evaluation concluded that the implementation of the 17 x 17 RFA core will not adversely affect the safety of the plant. The reload evaluation also concluded that the core design will not require any Technical Specification changes, and will not require a license amendment due to new safety analyses changes, fission product barrier design basis limits, or methods of evaluation as described in the UFSAR, pursuant to 10 CFR 50.59. The Beaver Valley Plant Onsite Review Committee has concurred with the conclusions of the reload evaluation.

Beaver Valley Power Station, Unit No. 2 Cycle 12 Reload and Core Operating Limits Report L-05-081 Page 2 The Core Operating Limits Report (COLR) is enclosed in accordance with Technical Specification 6.9.5.d. The COLR has been updated for this cycle by revising the Fxy and maximum FQT* PJEL criteria.

No newv commitments are contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-4284.

Sincerely, 446e William Pearce Attachment c: Mr. T. G. Colbum, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. L. E. Ryan (BRP/DEP)

I BVPS .

LICENSING REQUIREMENTS MANUAL 4.1 CORE OPERATING LIMiTS REPORT This Core Operating Limits Report provides the cycle specific parameter limits developed in.

accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 6.9.5..

Specification 3.1.3.5 Shutdown Rod Insertion Limits

The Shutdown rods shall be withdrawn to at least 225 steps.(l)

Specification 3.1.3.6 Control Rod Insertion Limits  :

-1

'Control Banks A and B shall be withdrawn to at least 225 steps.l) .

• ' .. I' Control Banks C and D shall be limited in physical insertion as sho'wn in Figure 4.l-l.(')

Specification 3.2.1 Axial Flux Difference NOTE: The target band is +/-7% about the target flux from 0% to 100% RATED THERMAL POWER The indicated Axial Flux Difference:

a. Above 90% RATED THERMAL POWER shall be maintained within the +/-7% target band about the target flux difference.

b. Between 50% and 90% RATED THERMAL POWER is within the limits shown on Figure 4.1-2.

c. .Below 50% RATED THERMAL POWER may deviate outside the target band.

.Specification 3.2.2 FQ(Z) and Fly Limits .

I' C -F .. . . . . .

FQ(Z) < -

• K(Z) for P > 0.5 FQ(Z) <-* K(Z) for P 5 0.5 Where: CFQ = 2.3 P= ' THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 4.1-3.

(1) As indicated by the group demand counter *1 COLR 12

BEAVER VALLEY - UNIT 2

• 4.1-1. Revision 43

BVPS-2 LICENSING REQUIREMENTS MANUAL The Fxy limits [FXy(L)I for RATED THERMAL POWER within specific core planes shall be:

Fxj(L) = Fxy(RTP) (1 + PFxy * (I-P))

Where: For all core planes containing D-Bank:

Fx+(RTP)*<1.71 -

For unrodded core planes:

Fxy(RTP) < 1.75 from 1.8 ft. elevation to 2.3 flt. elevation Fxy(RTP) < 1.79 from 2.3 ft. elevation to 3.7 ft. elevation F1y(RTP) < 1.84 from 3.7 R. elevationto 5.8 ft. elevation FXy(RTP) < 1.85 from 5.8 f. elevation to 7.4 ft. elevation Fxy(RTP) < 1.81 from 7.4 ft. elevation to 9.2 ft. elevation FXy(RTP) < 1.75 from 9.2 ft. elevation to 10.2 ft. elevation

-PF.=0.2 THERMAL POWER.

RATED THERMAL POWER Figure 4.1-4 provides the maximum total peaking factor times relative power (FQT*P) as a function of axial core height during normal core operation.

Specification 3.2.3 FN AH HkCF~ * (I + .PF, (1 _-P)) , '  :

Where: CFAH= 1.62 PPM! = 0.3 THERMAL POWER

= RATED THERMAL POWER COLR 12 BEAVER VALLEY - UNIT 2 4.1-2 . Revision 43

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BVPS-2 LICENSING REQUIREMENTS MANUAL 200

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ut 125 z

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o 100 E.L z

m 75 a

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50 25 0- .~~

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.0 10 20 "30 4o0: 50 60 .70 .80 90 100 ..

PERCENT OF RATED THERMAL POWER FIGURE 4.1-1 CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL COLR 12 BEAVER VALLEY - UNIT 2 4.1-3 Revision 43 -.

..... 2.

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BVPS-2 LICENSING REQUIREMENTS MANUAL

. . . .i 0 1L - -10 ._1: 20 -130. 40

-50 30 -20 -10.:0 - 10 20 30.40 :50:

Flux Difference (Al) %

FIGURE 4.1-2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER COLR 12  : I ..

BEAVER VALLEY - UNIT 2 4.1-4 . Revision 43

- BVPS-2 L. R LICENSING REQUIREMENTS MANUAL 1.2

. I.1 1:'1'1-1 1 1 1:11 1 1.0 ,, =l 101 I-7:7-1;1 I_1

. .8 1 111:11 l l Tr 1 1-0t0-125 ll

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__ T:I I Tl- T-I l 0 .__X :1...:1--1.1 .-1.1.1 0 2 4 :6 8 :10 12 Core Height (feet)

FIGURE 4.1-3 FQT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR 12 BEAVER VALLEY - UNIT 2 .4.1-5 . . . Revision 43 .; t,

BVPS-2 LICENSING REQUIREMENTS MANUAL 2.4 rss jJJ u

2.30 1 AA . . . IA .AA A .4 Z

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.20 A LL - BASIS FXY

.91 .00 FROM 1.8 FT. UP TO 2.3 FT. < 1.75 FROM 2.3 FT. UP TO, 3.7 FT. < 1.79 0.80 A FROM 3.7 FT. UP TO 5.8 FT. < 1.84 L

FROM 5.8 FT. UP TO 7.4 FT. < 1.85 0.60 FROM 7.4 FT. UP TO 9.2 FT. < 1.81

-0.40 FROM .

9.2 FT...-UP TO .

10.2 FT. < 1.75 0 . *20 - ll - t l

1 - 11.i 1.

1 t t l

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l l § I .l . l I 0.0 n 1 I i 7 T I I u L - I - L- L - I - I - .L - - I. - 1. - L - I. -

0 2 4 .6 . 8 10 12 CORE HEIGHT (FT)

FIGURE 4.14 MAXIMUM (FQT*PREL) VS. AXIAL CORE HEIGHT DURING NORMAL OPERATION COLR 12 BEAVER VALLEY - UNIT 2 ..- .4.1-6 - Revision 43 - -.

LBVPS-2

- . LICENSING RE UIREMENTS MANUAL :

Specification 3.3.1.1 Reactor Trip' System Instrumeniation Setnoints. Table 3.3-1 Table Notations A antlA ,

Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reacfortrip setpoint' -. "' (1'* 01.31 ' '

Overtemperature AT reactor trip setpoint Tavg coefficient K2Ž20.01S3/0 F .'

Overtemperature AT. reactor trip setpoint pressure coefficient . K3 2 0.00082/psia

-Tavg at RATED THERMAL POWER . T` -<576.2*F Nominal pressunzer pressure  ; P' Ž2250 psia .

Measured reactor vessel AT lead/lag time constants T 2 8 sec .

T2 < 3 sec Measured reactor vessel AT lag time constant .73

• sec Measured reactor vessel average temperature lead/lag time constants ;r4 Ž30sec

.r 5<4sec

'MeaLsured reactor vessel average temperature lag time constant tr6 < 0'sec f(&I) is a function of the indicated difference between top and bottom detectors of the power-range:

nuclear ion chambers; with gains to be selected based on measured instrument response'during plant startup tests such that:

'(i) For q, - qb between -32% and +11%, f 1(AI) 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is tota THERMAL POWER in percent of RATED THERMAL POWER; '

,..(ii) For each'percent that the magnitude of qt- 'qexceed -32%,"the AT Trip Setp oi strhoabe' :'

automatically reduced by 146% of its Value at RATED THERMAL POWER, and'...

.(iii] )For each'percent that the magnitude of q1 - qb exceeds +11%, the AT Trip Setpoint shall be automatically reduced by 1.56% of its value at RATED THERMAL POWER.

COLR12 . ..I BEAVER VALLEY - UNIT 2 .. 4.1-7 .:,Revision 43

' '. LICE G BVPS-2 .

< s...  : .. ......... LICENSING REQUIRMENTS MANUAL ............... ..-.- :

Overpower AT Setpoint Parameter Values:

-Parameter - Value

,Overpower AT reactor trip setpoint K4 < 1.094 Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 2 0.00/°F for increasing ... .

. . -::-. average0 temper e K5 0/ Ffor

- - . decreasing average temperature OverowerAT reactor tripsetpointeTavg he cofficient K6Ž 0.0012/F forT>.  :-

. . - K6 = Ffor'T <T Tavg at RATED THERMAL POWER .':.. < T" 5i62 0 F

.- . Mea'ured reactor vessel AT lead/ ag time constants' '. >-8 sec -.

-2 *3.sec Measured reactor vessel AT lag time constant T3 < 0 sec Measured reactor vessel average temperature lag time constant -6 *.0 sec Measured reactor vessel average temperature rate/lag time constant s.ec" '..0 T<rs

,1

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.COLR12 ' . . -1. - - --.:,

..BEAVER VALLEY - UNIT 2 4.1-8, Revision 43*

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. . BVPS-2'

'LICENSING REQUIREMENTS MAINUAL Soecification 3.2.5 DNB Parameters Parameter 'Indicated Value Reactor CCoolant System Tavg Tavg < 579.9oF(1)

.Pressuriz' er Pressure Pressure 2 2214 psia..

Reactor CCoolant System Total Flow Rate 'Flow 2 267,200 gprn( 3 )

.I (1) The Reactor Coolant Sy-stem (RCS) T'gvalue includes allowances for rod control opelation' and verification via control board indication.

(2) Thle pressurizer precssure valuecincludesiallowanlces forpr'essurizer pressure control operation a'nd" verification via control board indication.

(3) The RCS total -flowrate includes' allowances for normalization' of the cold leg elbow taps with a beginning of cycle precision RCS floiw calorimcetric measurement atndverification on a periodic basis via plant -proces's computer. If periodic verification of flow rate is performed via the process computer, the required flow value'is Ž267,200 g'pm.

COLR 12 BEAVER VALLEY - UNIT-2 . .4.1-9 Revision 43

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BVPS-2 LICENSING REQUIREMENTS MANUAL U1.

0

..t I.g I

.590

... . . 1 . .. - .

8.0....

. 580

0. 0.2 0.4 0.6 :- 0.8 1 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 4.1-5 REACTOR'CORE SAFETY LIMiT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR 12 BEAVER VALLEY - UNIT 2 4.1-10' Revision 43 1I

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