L-03-051, Cycle 16 Reload and Core Operating Limits Report

Cycle 16 Reload and Core Operating Limits Report

ML031120073
Person / Time
Site:	Beaver Valley
Issue date:	04/17/2003
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-03-051
Download: ML031120073 (11)

Text

FENOC _______

Beaver Valley Power Station Route 168 PO Box4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 Mark B. Bezilla 724-682-5234 Site Vice President Fax: 724-643-8069 April 17, 2003 L-03-051 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Cycle 16 Reload and Core Operating Limits Report Beaver Valley Power Station, Unit No. 1 completed the fifteenth cycle of operation on March 7, 2003, with a burnup of 17,997.33 MWD/MTU. This letter describes the Cycle 16 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 is required for the Cycle 16 reload design.

The Beaver Valley Power Station Unit No. 1 reactor core features a low leakage pattern.

During 1RI5 refueling, 1 Region 13A, 12 Region 15A, 24 Region 15B, 32 Region 16A, 8 Region 16B and 4 Region 17A fuel assemblies were discharged and replaced with 9 reinserted Region 13A fuel assemblies, 12 reinserted Region 13B fuel assemblies, 44 fresh Region 18A fuel assemblies enriched to 4.4 nominal weight percent, and 16 fresh Region 18B fuel assemblies enriched to 4.95 nominal weight percent. Cycle 16 is the second cycle with Robust Fuel Assemblies (RFA) in the core. In addition, all 48 control rods were replaced with new control rods.

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. This core reload has been designed using the Positive Moderator Temperature Coefficient approved by Technical Specification Amendment No. 251. The Cycle 16 reactor core reload evaluation concluded that the implementation of the 17 x 17 core will not adversely affect the safety of the plant. The reload evaluation also concluded that the core design did not require any Technical Specification changes, and did not require a license amendment pursuant to 10 CFR 50.59 due to no new safety analyses changes, no new fission product barrier design basis limits, or no new methods of evaluation as described in the UFSAR. The A-

Beaver Valley Power Station, Unit No. 1 Cycle 16 Reload and Core Operating Limits Report L-03-051 Page 2 Beaver Valley Plant Operations Review Committee has concurred with the conclusions of the reload evaluation.

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* PREL criteria.

No regulatory commitments are contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Performance Improvement at 724-682-5284.

Sincerely, Mark B. Bezill c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. D. M. Kern, NRC Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. L. E. Ryan (BRP/DEP)

BVPS-1 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.*

Specification 3.1.3.6 Control Rod Insertion Limits Control Banks A and B shall be withdrawn to at least 225 steps.*

Control Banks C and D shall be limited in physical insertion as shown in Figure 4.1-1.*

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 F0 (Z) and FyLimits FQ(Z) < _F" K(Z) for P > 0.5 P

FQ(Z) < C.* K(Z) forP <0.5

0.5 Where

CFQ = 2.3 P= THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 4.1-3.

• As indicated by the group demand counter BEAVER VALLEY - UNIT 1 4.1-1 COLR 16 Revision 31

BVPS-1 LICENSING REQUIREMENTS MANUAL The FXY limits [Fy(L)] for RATED THERMAL POWER within specific core planes shall be:

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

Where: For all core planes containing D-Bank:

FXy(RTP) < 1.71 For unrodded core planes:

FXy(RTP) < 1.75 from 1.8 ft. elevation to 2.3 ft. elevation FXy(RTP) < 1.80 from 2.3 ft. elevation to 3.7 ft. elevation FXy(RTP) < 1.83 from 3.7 ft. elevation to 7.4 ft. elevation FXy(RTP) < 1.79 from 7.4 ft. elevation to 9.2 ft. elevation FXy(RTP) < 1.74 from 9.2 ft. elevation to 10.2 ft. elevation PFy = 0.2 P= THERMAL POWER RATED THERMAL POWER Figure 4.1-4 provides the maximum total peaking factor times relative power (FQT*PreI) as a function of axial core height during normal core operation.

Specification 3.2.3 FNAN F AH < CFAH * (1 + PFAH (I-P))

Where: CFAH = 1.62 PFAH = 0.3 P= THERMAL POWER RATED THERMAL POWER BEAVER VALLEY - UNIT 1 4.1-2 COLR 16 Revision 31

BVPS- I LICENSING REQUIREMENTS MANUAL 200 100,18 C

co 150 CL I8 I I0 a')

a:

to D-0._

C 0

100 U)

I,1 0

a_

C:

m

-0 0

50 0

0 20 40 60 80 100 Relative Power (Percent)

FIGURE 4.1-1 CONTROL ROD INSERTION LIMITS BEAVER VALLEY - UNIT 1 4.1-3 COLR 16 Revision 31

BVPS-I LICENSING REQUIREMENTS MANUAL 100 90 80 a) 0: 70 0~

0) 75- 60 E

-0 50 C

a) 40 a_

30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (A I)

FIGURE 4.1-2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER BEAVER VALLEY - UNIT 1 4.1-4 COLR 16 I Revision 31

BVPS-1 LICENSING REQUIREMENTS MANUAL 1.2 10 - - -f- "-

12.0. 0.925 0.8

-, 0.6 N

0.4 0.2 00 0 2 4 6 8 10 12 Core Height (feet)

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

BEAVER VALLEY - UNIT 1 4.1-5 COLR 16 Revision 31

BVPS-1 LICENSING REQUIREMENTS MANUAL 2.40 2.20 2.00 1.80 1.60 0-a 0.

1.40 I-LL x

1.20 1.00 0.80 0.60 0.40 0.20 0.00 0 2 4 6 8 10 12 Core Height (Ft)

FIGURE 4.1-4 MAXIMUM (FoT*PREL) VS AXIAL CORE HEIGHT DURING NORMAL OPERATION BEAVER VALLEY - UNIT 1 4.1-6 COLR 16 Revision 31

BVPS-1 LICENSING REQUIREMENTS MANUAL Specification 3.3.1.1 Reactor Trip System Instrumentation Setpoints, Table 3.3-1 Table Notations A and B Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint KI

• 1.259 Overtemperature AT reactor trip setpoint Tavg coefficient K2 2 0.01655/0 F Overtemperature AT reactor trip setpoint pressure coefficient K3 2 0.000801/psia Tavg at RATED THERMAL POWER T'

• 576.2 0 F Nominal Pressurizer Pressure P' 2 2250 psia Measured reactor vessel average temperature lead/lag time constants tl 2 30 secs T2

• 4 secs f (AI) 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:

(1) for qt - qb between -36 percent and +15 percent, f (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 total THERMAL POWER in percent of RATED THERMAL POWER).

(ii) for each percent that the magnitude of (qt - qb) exceeds -36 percent, the AT trip setpoint shall be automatically reduced by 2.08 percent of its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (q, - qb) exceeds +15 percent, the AT trip setpoint shall be automatically reduced by 1.59 percent of its value at RATED THERMAL POWER.

Overpower AT Setpoint Parameter Values:

Parameter Value Overpower AT reactor tnp setpoint K4 S 1.0916 Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 2 0.02/°F for increasing average temperature BEAVER VALLEY - UNIT 1 4.1-7 COLR 16 Revision 31

BVPS-l BVPS-I LICENSING REQUIREMENTS MANUAL Overpower AT Setpoint Parameter Values (continued):

Parameter Value Overpower AT reactor trip setpoint Tavg heatup coefficient K6 > 0.00128/1F for T >T" K6 = 0/F for T < T" Tavg at RATED THERMAL POWER T" < 576.2 0 F Measured reactor vessel average temperature rate/lag time constant T3 2 0 seCs Specification 3.2.5 DNB Parameters Parameter Indicated Value Reactor Coolant System Tavg Tavg < 580.OOF(I)

Pressurizer Pressure Pressure > 2215 psia(2)

Reactor Coolant System Total Flow Rate Flow > 267,400 gpm(3)

(1) The Reactor Coolant System (RCS) Tavg value includes allowances for rod control operation and verification via control board indication.

(2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

BEAVER VALLEY - UNIT 1 4.1-8 COLR 16 Revision 31

BVPS-1 LICENSING REQUIREMENTS MANUAL FE7rs 660 2420 PSIA UNi kCCEPTA BLE OPERATION 650 ] 4 - t 2250 PSIA 6404 1 C 630 0)

C) \ <)20 PSIA X 0

1 620 610 600 ACCEPTABLEI OPERAT ION 590

=1= = XI 580 0.2 04 06 08 1 12 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)

BEAVER VALLEY - UNIT 1 4.1-9 COLR 16 I Revision 31