L-03-158, Cycle 11 Reload and Core Operating Limits Report

Cycle 11 Reload and Core Operating Limits Report

ML032880404
Person / Time
Site:	Beaver Valley
Issue date:	10/09/2003
From:	Pearce L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-03-158
Download: ML032880404 (12)

Text

Beaver Valley Power Station

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Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. Williant Pearce 724-682-5234 Site Vice President Fax: 724-643-8069 October 9, 2003 L-03-158 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 11 Reload and Core Operating Limits Report Beaver Valley Power Station, Unit No. 2 completed the tenth cycle of operation on September 12, 2003, with a bumup of 20,307.76 MWD/MTU. This letter describes the Cycle 11 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 11 reload design.

The Beaver Valley Power Station Unit No. 2 reactor core features a low leakage pattern.

During the 2R10 refueling, 1 Region 8B, 12 Region 10A, 20 Region 10B and 28 Region 1lA assemblies were discharged and replaced with 1 reinserted Region 8A, 36 fresh Region 13A fuel assemblies enriched to 4.40 nominal weight percent and 24 fresh Region 13B fuel assemblies enriched to 4.95 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 11 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.

-OD

Beaver Valley Power Station, Unit No. 2 Cycle 11 Reload and Core Operating Limits Report L-03-158 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 FQ T* PUL criteria.

No new 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, L. William Pearce Attachment c:

Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. L. E. Ryan (BRP/DEP)

BVPS-2 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 FQ(Z) and Y Limits FQ(Z) < CFQ

• K(Z) forP>0.5 P

FQ(Z) < CFQ

• 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 COLR 11 BEAVER VALLEY - UNIT 2

- 4.1-1 Revision 34

BVPS-2 LICENSING REQUIREMENTS MANUAL The Fy limits [F,~(L)] for RATED THERMAL POWER within specific core planes shall be:

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

Where: For all core planes containing D-Bank:

FXy(RTP) < 1.71 For unrodded core planes:

FXy(RTP)

• 1.76 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 5.8 ft. elevation FXy(RTP) < 1.84 from 5.8 ft. elevation to 7.4 ft. elevation FXy(RTP) < 1.81 from 7.4 ft. elevation to 9.0 ft. elevation FXy(RTP) < 1.72 from 9.0 ft. elevation to 10.2 ft. elevation PFXY = 0.2 THERMAL POWER

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

Specification 3.2.3 FNAH N

F2jH CFM * (1 + PFH (1 -

P))

Where:

CFH= 1.62 PFH = 0.3 THERMAL POWER

= RATED THERMAL POWER COLR 11 BEAVER VALLEY - UNIT 2 4.1-2 Revision 34

BVPS-2 LICENSING REQUIREMENTS MANUAL 225 200 C

')

S

• 0 U) co 0.co

.4 z

m 0

cz 0o 175 150 125 100 75 50 25 0

20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER FIGURE 4.1-1 CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL BEAVER VALLEY - UNIT 2 4.1-3 COLR 11 Revision 34

BVPS-2 LICENSING REQUIREMENTS MANUAL a) 0 a3-0) 4-4'a 0)

.10 0-100 90 80 70 60 50 40 30 20 10 0 -50

-40

-30

-20

-10 0

10 20 30 40 50 Flux Difference (AM) %

FIGURE 4.1-2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER COLR 11 BEAVER VALLEY - UNIT 2 4.1-4 Revision 34

BVPS-2 LICENSING REQUIREMENTS MANUAL 1.2 1.0 0.8

..-N 0.6 0.4 0.2 0

0.0, 1.00 I I

3

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12_0 0__2 10Xt~~~~~~~~~~~~~~ff~~~

0 2

4 6

8 Core Height (feet) 10 12 FIGURE 4.1-3 FQT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR 11 Revision 34 BEAVER VALLEY - UNIT 2 4.1-5

BVPS-2 LICENSING REQUIREMENTS MANUAL 240 220 200 1.80 1.60 L 0.0, 2.301

0.

2. 12751

- I - -- - - - -

I Al LI I

I I

i

' I I

I I I

I I

M 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 BASIS Fxy From 1.8 R. up to 2.3 R. 1.76 From 2.3 R. up to 3.7 R.; 1.80 From 3.7 R. up to 5.8 Ft.E 1.83 From 5.8 R. up to 7A R. 1.84 From 7A Ft. up to 9.0 Ft.; 1.81 From 9.0 Ft. up to 10.2 Ft. 1.72

-, 9 l

0 2

4 6

8 10 12 Core Height (Ft)

FIGURE 4.14 MAXIMUM (FQT*Prel) VS. AXIAL CORE HEIGHT DURING NORMAL OPERATION COLR 11 Revision 34 BEAVER VALLEY - UNIT 2 4.1-6

BVPS-2 LICENSING REQUIREMENTS MANUAL Specification 3.3.1.1 Reactor Trip System Instrumentation Setoints. Table 3.3-1 Table Notations A and B Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint KI < 1.311 Overtemperature AT reactor trip setpoint Tavg coefficient K2 0.01 83/0F Overtemperature AT reactor trip setpoint pressure coefficient K3 2 0.00082/psia Tavg at RATED THERMAL POWER T' < 576.20F Nominal pressurizer pressure P'

2250 psia Measured reactor vessel AT lead/lag time constants Tr 2 8 sec T2 < 3 sec Measured reactor vessel AT lag time constant r3 < 0 sec Measured reactor vessel average temperature lead/lag time constants T4 2 30 sec T5 < 4 sec Measured reactor vessel average temperature lag time constant T6 < 0 sec f (Al) 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(AI) = 0, where qt and qbare 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 -32%, the AT Trip Setpoint shall be automatically reduced by 1.46% of its value at RATED THERMAL POWER; and (iii)

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

COLR 11 Revision 34 BEAVER VALLEY - UNIT 2 4.1-7

BVPS-2 LICENSING REQUIREMENTS MANUAL Overpower AT Setpoint Parameter Values:

Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel AT lead/lag time constants Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant Value K4 < 1.094 K5 0.00/0F for increasing average temperature K5 = O/F for decreasing average temperature K6 2 0.0012/OF for T > T" K6 = O/0F for T < T" T" < 576.20F T, 2 8 sec T2 < 3 sec T3 <0 sec T6 <0 sec r7 Ž0 sec COLR 1 Revision 34 BEAVER VALLEY - UNIT 2 4.1-8

BVPS-2 LICENSING REQUIREMENTS MANUAL Specification 3.2.5 DNB Parameters Parameter Indicated Value Reactor Coolant System Tavg Pressurizer Pressure Tavg < 579.90F(I)

Pressure 2 2214 psia(4 2

Flow 267,200 gpm(3)

Reactor Coolant System Total Flow Rate (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 plant process computer.

If periodic verification of flow rate is performed via the process computer, the required flow value is 2 267,200 gpm.

COLR 11 BEAVER VALLEY - UNIT 2 4.1-9 Revision 34 I

BVPS-2 LICENSING REQUIREMENTS MANUAL 670 660 650 640 U-630 0a i!

620 610 600 590 580 2420 PSIA UNICCEPT BLE OPERTION ACC PTAE PEA

\\IO 1920 PShi ACCI PTABLE OPERAT ION\\\\

==~~

==

==

0 0.2 0.4 0.6 0.8 1

FRACTION OF RATED THERMAL POWER 1.2 1.4 Figure 4.1-5 REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR 11 Revision 34 BEAVER VALLEY - UNIT 2 4.1-10