L-05-077, Cycle 17 Core Operating Limits Report Mid-Cycle Revision
| ML051150171 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/19/2005 |
| From: | Pearce L FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-05-077 | |
| Download: ML051150171 (13) | |
Text
FENOC Beaver Valley Power Station PO. B~ox 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. William Pearce 724-682-5234 Vice President Fax: 724-643-8069 April 19, 2005 L-05-077 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. I Docket No. 50-334, License No. DPR-66 Cycle 17 Core Operating Limits Report Mid-Cycle Revision The Beaver Valley Power Station (BVPS) Unit I Core Operating Limits Report (COLR) was revised on April 7, 2005. Pursuant to BVPS Unit I Technical Specification 6.9.5.d, attached is a copy of this mid-cycle revision to the BVPS Unit I COLR (Revision 45).
As identified in the previous FirstEnergy Nuclear Operating Company (FENOC) letter L-04-144 dated November 19, 2004, titled "10 CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models," the BVPS Unit 1 containment metal mass had' been previously under-estimated, which resulted in increased Loss of Coolant Accident (LOCA) peak clad temperature (PCT) effects.
A compensatory measure taken by FENOC to address this newly identified LOCA analysis effect was to reduce the core design limit, FQ, from 2.30 to 2.20 for the BVPS Unit I Cycle 17 fuel, which had already been designed and manufactured when this LOCA analysis discrepancy was identified.
The reduction in FQ improved the LOCA analysis PCT results. This reduction in FQ, however, causes a reduction in available margin for meeting the required periodic Fxy surveillances performed during BVPS Unit I operation in Cycle 17.
The initial Cycle 17 COLR (previously submitted to the NRC by FENOC letter L 147, dated November 5, 2004) provided a single set of Fxy limits which were applicable throughout the whole BVPS Unit 1 Cycle 17 operation. This mid-cycle revision splits the current Fxy limits into two parts: for core burnups < 8000 MWD/MTU and for core burnups > 8000 MWD/MTU.
By splitting the Fxy limits into two parts, additional margin could be obtained for meeting Fxy surveillance limits during BVPS Unit I plant operation when core burnup is < 8000 MWD/MTU.
An additional action is being considered to improve the Fxy surveillance margin for BVPS Unit 1 operation for core bumups > 8000 MWD/MTU, which may lead to another BVPS Unit 1 COLR mid-cycle revision. Any further COLR revisions will be provided to the NRC as required by BVPS Unit 1 Technical Specification 6.9.5.d.
Beaver Valley Power Station, Unit No. 1 Cycle 17 Core Operating Limits Report Mid-Cycle Revision L-05-077 Page 2 No regulatory 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, 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)
-Beaver Valley Power Station, Unit No. I Cycle 17 Core Operating Limits Report Mid-Cycle Revision L-05-077 Page 3 bc: R. W. Fedin R. W. Huston D. J. Schwer J. J. Hagan D. W. Jenkins Central File - Keywords: COLR
BVPS-1 LICENSING REQUIREMENTS MANUAL
- j) 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 Fo(Z) and F,, Limits FQ(Z)< CF-*K(Z) forP>0.5 P
CFQ Fo(Z) <
.5* K(Z) for P < 0.5 Where:
CFQ = 2.20 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 17 Revision 41
BVPS-1 LICENSING REQUIREMENTS MANUAL The Fy limits [Fy,(L)] for RATED THERMAL POWER within specific core planes shall be:
Fx(L) = F2y(RTP)(l + PFxy * (I-P))
Where: For all core planes containing D-Bank:
FZy(RTP) < 1.71 For unrodded core planes with core burnup < 8000 MWD/MTU:
FXy(RTP) < 1.75 from 1.8 ft. elevation to 2.3 ft. elevation FXy(RTP) < 1.75 from 2.3 ft. elevation to 3.7 ft. elevation FXy(RTP) < 1.79 from 3.7 ft. elevation to 5.8 ft. elevation FXA(RTP) < 1.81 from 5.8 ft. elevation to'7. ft. elevation FXy(RTP) < 1.75 from 7.4 ft. elevation to 8.9 ft. elevation FXy(RTP) < 1.74 from 8.9 ft. elevation to 10.2 ft. elevation For unrodded core planes with core burnup > 8000 MWD/MTU:
Fxy(RTP) < 1.68 from 1.8 ft. elevation to 2.3 ft. elevation Fxy(RTP) < 1.73 from 2.3 ft. elevation to 3.7 ft elevation
.FXy(RTP) < 1.79 from 3.7 ft. elevation to 5.8 ft. elevation FIy(RTP) < 1.81 from 5.8 ft. elevation to 7.4 ft. elevation FXy(RTP) < 1.74 from 7.4 ft elevation to 8.9 R. elevation Fy(RTP) < 1.60 from 8.9 ft. elevation to 10.2 ft. elevation PFxy = 02 P = THERMAL POWER RATED THERMAL POWER BEAVER VALLEY - UNIT 1 4.1-2 COLR 17 Revision 45
.5.
BVPS-1 LICENSING REQUIREMENTS MANUAL Figure 4.1-4 provides the mraximum 'total peaking factor times relative power (FQT*Pj) as a function of axial core height during normal core operation.
Specification 3.2.3 FNAiI FNA < CFj * (1 + PFAH (I-P))
Where:
CFAH = 1.62 PFAH = 0.3 P =
THERMAL POWER RATED THERMAL POWER BEAVER VALLEY - UNIT 1 4.1-2a COLR 17 Revision 45
BVPS-1 LICENSING REQUIREMENTS MANUAL 200 C
-3 co 0.
CD CO 0
U)
-0n a-C 0m i0 150 100
- 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 17 Revision 41
BVPS-I LICENSING REQUIREMENTS MANUAL 100 90 80 I.-w 0a.
-i E4 0
.0 0~
70
.60 50 40 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 COLR17 Revision 41 I
BVPS-I LICENSING REQUIREMENTS MANUAL 1.2 1.0 0.8
__ 0.6 N
)
0.4 0.2 0.0 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 17 Revision 41 I
BVPS-I LICENSING REQUIREMENTS MANUAL v-I-I-I r
2.40 2.2 2.00 1.80 1.60 4 1.40 t.0
- p. 1.20 0.8S 0.0, 2.201 I
I I 6.0, 2.20I....4........
a-.
- 2. 0 3 5 1 I
A I
~I
~
)
u.ul 0.41 n.2 0
2 4
6 Core Height (Ft) 8 10 12 FIGURE 4.1-4 MAXIM (FoT*PREL) VS AXIAL CORE HEIGHT DURING NORMAL OPERATION
)
BEAVER VALLEY - UNIT I 4.1-6 COLR 17 Revision 45
BVPS-I LICENSING REQUIREMENTS MANUAL Specification 3.3.1.1 Reactor Trip System Instrumentation Setpoints. Table 3.3-1 Table Notations AandB Overtemperature AT Setpoint Parameter Values:
Parameter Value Overtemperature AT reactor trip setpoint KI
- 1.259 Overtemperature AT reactor trip setpoint Tavg coefficient K2 2 0.0 1655/0F Overtemperature AT reactor trip setpoint pressure coefficient K3 2 0.000801/psia Tavg at RATED THERMAL POWER.
r 5 57620F Nominal Pressurizer Pressure P' 22250 psia Measured reactor vessel average temperature lead/lag time constants r1 2 30 secs T2
- 4 secs 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:
F)
(i) 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 (qt - 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 Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Value K4 S 1.0916 K5 2 0.02/F for increasing average temperature COLR 17 Revision 41
)
BEAVER VALLEY - UNIT 1 4.1-7 I
BVPS-1 LICENSING REQUIREMENTS MANUAL Overpower AT Setpoint Parameter Values (continued):
Parameter Value Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER K6 2 0.00128/0F for T >T" K6 = 0/0F for T < T" T" < 576.20F Measured reactor vessel average temperature rate/lag time constant r3 2 0 secs Specification 3.2.5 DNB Parameters Parameter Indicated Value Reactor Coolant System Tavg Pressurizer Pressure Tavg
- 580.OOF(I)
Pressure2 2215 psia(2)
Flow 2 267,400 gpm(3 Reactor Coolant System Total Flow Rate I)
(1) The Reactor Coolant System (RCS) Ta.g 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 17 Revision 41
BVPS-l LICENSING REQUIREMENTS MANUAL
.'S U.
.a
_042 PSIAIO UN CCEPTABLEOPE TION 2255P01 630 620 6101 ACC¶EPTABLE OPERAI ION N:
580 4
- I
+
0 0.2 0.4 0.6 0.8 12 1.4
- FRACTION OF RATED THERMAL POWER Figue 4.1-5 REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
BEAVER VALLEY - UNIT I 41-9 COLR 17 Revision 41