ML020580466
| ML020580466 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/11/2002 |
| From: | Vonsuskil J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW020014, TS 5.6.5 | |
| Download: ML020580466 (17) | |
Text
Exelkn Exlo Generation Company, LLC www.exelonfcolp.corn Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-458-2801 February 11,2002 BW020014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License Nos. NPF-77 NRC Docket No. STN 50-457
Subject:
Core Operating Limits Report, Braidwood Unit 2 Cycle 9A Sequence Number 1 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 9A Sequence Number 1, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." This revision of the COLR was recently implemented and provides additional information and clarification.
If you have any questions regarding this matter, please contact Ms. A. Ferko, Regulatory Assurance Manager at (815) 417-2699.
Respectfully, A
"mesD. von Suskil Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 9A Sequence Number 1 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station 4,C)CI
ATTACHMENT I Core Operating Limits Report Braidwood Unit 2, Cycle 9A, Sequence Number I
NUCLEAR FUEL MANAGEMENT DEPARTMENT TRANSMITTAL OF DESIGN INFORMATION
[ SAFETY RELATED Originating Organization TODI No. NFM0100053 0 NON-SAFETY RELATED 0 Nuclear Fuel Management Seq. No. I E] REGULATORY RELATED fi Other (specify) Page I of 14 Station Braidwood Unit 2 Cycle 9A Generic To: Lonnie K. Kepley - Braidwood Subject Braidwood Unit 2 Cycle 9A Core Operating Limits Report in ITS Formnpt and W(z) Function P. Moravek A59 // 3P Preparer Preparer's Signature Date T. Stevens A AA/..
Reviewer Rvf iDate D.Redden It 3
,WFM Supervisor NFM Superi' i ature Date N.
Status of Information: 0 Verified E5 Unverified E0 Engineering Judgement Method and Schedule of Verification for Unverified TODls:
Description of Information:
Attached is the Braidwood Unit 2 Cycle 9A Core Operating Limits Report (COLR) in the ITS format and W(z) function. The Sequence I of this TODI supersedes Sequence 0.
Purpose of Information:
The attached Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 9A, with uprate values, has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS). In this sequence, the following COLR Sections were revised:
- Section 2.2.2; the SDM limits for MODE 5, applicable for LCO 3. 1. 1,
- Section 2.3.4, the EOL/ARO/HFP-MTC Surveillance limit at 60 ppm, applicable for LCO 3.1.3,
- Section 2.5.1, the control bank insertion limits, applicable for LCO 3.1.6.
- Section 2.5.4, the control bank overlap limits, applicable for LCO 3.1.6.
- Section 2. 13.2, the Reactor Coolant System boron concentration, applicable to TLCO 3.1 .k.2)
Braidwood Station is requested to perform a plant review of this document. Upon completion of the plant review, Braidwood Station is to transmit the COLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 5.6.5. Please provide NFM (Tyrone L.
Stevens) with a copy of Braidwood Station's completed plant review and COLR submittal to the NRC.
Source of Information: .
Westinghouse Letter CAC-01-131, "Braidwood 2 Cycle 9A COLR data for 3586.6 MWt Operation, "dated April 12, 2001.
NFMO100054, "RCS Average Temperature DNB Limit, "Seq. 0, dated April 14, 2001.
Supplemental Distribution: A. Ferko I L. S. Dworakowski (BR)
TODI NFM0100053 Seq. I Page 2 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 1.0 CORE OPERATING LIMITS- REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 9A has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specifications affected by this report- are listed below: --...
SL 2.1.1 Reactor Core Safety Limits (SLs)
LCO....31 .----Sh-ttdown-M-argin-(SDM) .-. .......
"bLco 3.1,3 -Modeirator Temperat'ure Coefficient LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 Physics Tests Exceptions - Mode 2 LCO 3.2.1 Heat Flux Hot Channel Factor (FO(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)
LCO 3.2.3 Axial Flux Difference (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) DNB Parameters LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:
TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1 .g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff > 1.0 TRM TLCO 3.1A Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1 .k Position Indication System - Shutdown (Special Test Exception)
TODI NFMO100053 Seq. I Page 3 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
2.1 Reactor Core Limits (SL 2.1.1) 2.1.1 In Modes 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.
680 2471 p.61 660 a_
640
-- 620 600 580 Froction of Nominol Power Figure 2.1.1: Reactor Core Limits
TODI NFM0100053 Seq. 1 Page of 14 4
CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 2.2 Shutdown Marqin (SDM)
The SDM limit for MODES 1, 2, 3, and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).
The SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1 .i and 3.1 .j).
2.3 Moderator Temperature Coefficient (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOLJARO/HZP-MTC upper limit shall be +4.1 x 10-5 Ak/k/OF.
2.3.2 The EOLIARO/HFP-MTC lower limit shall be -4.6 x 10-4 Ak/k/ 0F.
2.3.3 The EOLJARO/HFP-MTC Surveillance limit at 300 ppm shall be
-3.7 x 104 Ak/k/°F.
2.3.4 The EOLJARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1 0 -4 Ak/k/°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limit (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with the Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Limit (step) 225 110 226 111 227 112 228 113 229 114 231 116
TODI NFMO100053 Seq. 1 Page 5 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Figure 2.5.1:
Control Bank Insertion-Limits Versus Percent Rated Thermal Power 224 220 200 180 (100%, 161) 160 5
140 0.
U)
"00 120 Z
0 o 100 03.
0 W
V 80 0n 60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
TODI NFMO100053 Seq. 1 Page 6 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 2.6 Heat Flux Hot Channel Factor (F_(Zfl (LCO 3.2.1) 2.6.1 F RTP FQ(Z) <Q xK(Z) forP<0.5 0.5 F. RTP FQ (Z) 0.5 P
where: P--the ratio of THERMAL POWER to RATED THERMAL POWER FQr = 2.60 K(Z) is provided in Figure 2.6.1.
2.6.2 W(Z) Values:
.a-)-When-PDMS-is .OPERABLE_-W(Z-) .00000. for all. axial-points.... ..
b) When PDMS is Inoperable, W(Z) is provided in Figures 2.6.2.a through 2.6.2.c The normal operation W(Z) values have been determined at burnups of 7901, 14000, and-18000 MWD/MTU.
For this cycle, the Fco(z) penalty factors are equal to 2% per 31 Effective Full Power-Dbi§ (EFPD)_7:These values shall be used to increase the FwQ(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups.
Multiplication Factor = 1.02
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula:
UFQ = Uq. U1 where:
Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is Inoperable Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FQ(Z) Warning Setpoint > 2% of FQ(Z) Margin FQ(Z) Alarm Setpoint > 0% of FQ(Z) Margin
TODI NFM0100053 Seq. I Page 7 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Figure 2.6.1: K(Z) - Normalized FQ(Z) as a Function of Core Height 1.1
.924) 0.9 0.8
-0..7.
IL aN 0.6 z
" 0.4 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
TODI NFM0100053 Seq. I Page 8 of 14 CORE OPERATTNG LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Heigt MAXW(D Ek*Jod b2*2 Cyc bA O.00 1.0000 am 1.0000 am 1.6ooo om0 1.0000 Snmmuy OFWCD RDfon art701 MWD/MlU 0.0 1.0000 (lap and m 15%IEluded perWCfCAP-1W1 1OO 1.0000
- i. 1.0000 t10 1.0000 1.W0 1.0000 1.80 1.1722 2.m0 1.1596 2.0 1.1476 2.45 1.1410 2.10 1.1351
- 2. 1.1320
&W 1.1280 3&0 1.1229 3A10 1.1195 3&00 1.1156
&W0 1.1121 4.0 1.1102
- 4. 1.1120 4AIO 1.1128 4.0 1.1123 Aw 1.1117
&W 1.1107 sm 1.1078 5m 1.1058
&0 1.1033
. A1.1068 am 1.1183 6.a0 1.1354 6AO 1.1513 6.w 1.1659 6.95 1.1783. ..
7.00 1.1891 7.20 1.1987 7AD 1.2083 7.M0 1.2178 7.S0 1.2265 80 1.2325 a2D 1.2361 am0 1.2397 aW 1.2414 8.00 1.2415 9.00 1.2401 am 1.2455 9A4 1.2537
- 9. 1.2618 9.80 1.2699 v.0 1.2796 1020 1.2864 0m 1.0000 law 1.0000 1080 1.0000 11.00 1.0000 1120 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 I.40 1.0000 CORE HEIGHT (FEET) 11.0 1.0000 110. 1.0000 M0 1.0000
TODI NFMOIOOO53 Seq. I Page 9 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Heagi MAX WCD Ekakh~mod tW*2Cvw~eI am 1.0004 U21) 1.0001
&W 3.0004 9anwrqyoFWW0Rmton at 14000MWD/WM 1.00 1.0001 (lb and Ebicm 1150/60hnied per WCAP1401Q am4 1.00(m 1.0 1.000(
2.00 1.227ý 2.40 1.202',
2m0 1.1881 iso 3761 1_
3M4 1. 541~
3.4 1.1501 3.00 1.1SW 3.40 1.35(M 4.w 1.149(
4M4 1.147!
- 40. 13574 4m4 1.162C 5.4 1-1645
TODI NFM0100053 Seq. I Page 10 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Heit MAXW(D Feeta hinmdWtU*2 Cycle 9A 0.0 1.0000 am 1.0000 Agwe 2X" 0.80 1.0000 S.ummya W(Z FuRcton at 1800 MWD/MWU 0.10 1.0000 Ilhp and BEm 15%lWEluded perVWCW*1P.1 1.00 1.0000 1.80 1.0000 1.40 1.0000 1.8 1.0000 1.40 180 1.2532
.0 1.2338 "2.80 1.2055 2M , -1881
- 2. 1.1776
- 2. 1.1677 3.0 1.1578 3.0 1.1482 1.35 -- 7 7 3AD 1.1489
._&8O 1.1507
&0 1.1588 40* 1.1659
- -am0 1.17/41 4A4 1.1812 4.8 1.1868
.80 1.1904 1.30 sm 1.1931 S.80 1.1929 SAO 1.1928 38 1.2093 I
.8 1.2248 0 6.a0 1.2364 P am 1.2459 0 1 6.a0 12541 .2 6.80 1.2553 -
7.A0 1.2557 7.M0 1.2533 7-A0 1.2481 1 7.AO 1.2377
--- 7.80 1.2292 1.20
".0 1.2173 am 112033 8.40 1.1919 8.80 1.1844 m 1.1846 --
9am 1.1837 9m 1.1810 9m 1.2120 1.15 9.8 1.2640 9.80 1.3080 10.00 1.3470 10.20 1.3830 lam0 1.0000 "m 1.0000 1080 1.0000 11.00 1.0000 1.10 I1t.0 11.80 1.0000 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET) 11.m0 1.0000 1280 1.0000
TODI NFM0100053 Seq. I Page 11 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7.1 FNH, FRTP[1.0 + PFAH(1.0- P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER MTP = 1.70 PFAH = 0.3 2.7.2 Uncertainty when PDMS is inoperable:
The uncertainty, UFm, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F HN shall be calculated by the following formula:
UFAH = UFAHm where:
UFHj, = Base FN&H measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNAH Warning Setpoint Ž 2% of FNAH Margin F N Alarm Setpoint Ž 0% of FN AHMargin 2.8 Axial Flux Difference (AFD) (LCO 3.2.3) 2.8.1 When PDMS is Inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boilingq Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAsL > 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER
Ž 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint Ž 2% of DNBR Margin DNBR Alarm Setpoint _>0% of DNBR Margin
TODI NFMO100053 Seq. 1 Page 12 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power
TODI NFM0100053 Seq. I CORE OPERATING LIMITS REPORT Page 13 of 14 (COLR) for BRA]DWOOD UNIT 2 CYCLE 9A 2.10 Reactor Trip System Overtemperature AT Setpoint Parameter Values (LCO 3.3.1) 2.10.1 The Overtemperature AT reactor trip setpoint K, shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient 1K2 shall be equal to 0.0297 / OF.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient 1(3 shall be equal to 0.00181 / psig.
2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 OF.
2.10.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.
2.10.6 The measured reactor vessel AT lead/lag time constant -r shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r shall be equal to 3 2
sec. ------
2.10.8 The measured reactor vessel AT lag time constant r3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant "4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant Ts shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant "rshall be 6
less than or equal to 2 sec.
2.10.12-The-fi-(Al) "positive' breakpoint shall be +10% Al.
2.10.13 The f1 (Al) "negative" breakpoint shall be -18% Al.
2.10.14 The f, (Al) "positive" slope shall be +3.47% / % Al.
2.10.15 The f, (Al) "negative" slope shall be -2.61% / % Al.
2.11 Reactor Trip System Overpower AT Setpoint Parameter Values (LCO 3.3.1) 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / OF for increasing Tavg..
2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / OF for decreasing Tavg..
TODI NFM0100053 Seq. 1 Page 14 of 14 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 9A 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K shall be equal 6
to 0.00245 / °F when T > T".
2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K shall be equal 6
to 0 / OF when T < T".
2.11.6 The nominal Tag at RTP (indicated) T"-shall be less than or equal to 588.0 OF.
2.11.7 The measured reactor vessel AT lead/lag time constant "* shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant r shall be equal to 3 2
sec.
2.11.9 The measured reactor vessel AT lag time constant "r3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant T6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant "r 7
shall be equal to 10 sec.
2.11.12 The f2 (AI) "positive" breakpoint shall be 0 for all Al.
2.11.13 The f2 (AI) "negative" breakpoi-nt-sh-al be 0 for all Al.
2.11.14 The f2 (AI) "positive" slope shall be 0 for all Al.
2.11.15 The f2 (Al) "negative" slope shall be 0 for all Al.
2.12.__ Reactor Coolant System (RCS) DNB Parameter Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.
2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 OF.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 2000 ppm (LCO 3.9.1).
2.13.2 The Reactor Coolant System boron concentration, with all shutdown and control rods fully withdrawn, shall be greater than or equal to 2143 ppm to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TLCO 3.1.g and TLCO 3.1.k.2).
TIMM104 TASK DOCUMENT REFERENCES 02/08/02 11:00 W/O Task: 99222769 01 Status: READY 02/08/02 Desc : EM 2AFOlEA-1 BATTERY CHGR CLEAN & INSPECT PM
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