ML20318A090
ML20318A090 | |
Person / Time | |
---|---|
Site: | Dresden |
Issue date: | 11/05/2020 |
From: | Karaba P Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
20-0054 | |
Download: ML20318A090 (32) | |
Text
{{#Wiki_filter:,, Dresden Nuclear Power Station Exelon Generation -6500 North Dresden Road Morns, IL 60450 SVPLTR # 20-0054 November 5, 2020 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249 Subject; Core Operating Limits Report for Dresden Unit 3 Cycle 27 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Dresden Nuclear Power Station (DNPS) Unit 3 operating cycle 27 (D3C27) in accordance with Technical Specifications Section 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)." There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Mr. Ryan Sprengel, Regulatory Assurance Manager, at (815) 416-2800.
- Respectfully,
~Peter J. Karaba
- Site Vice President Dresden Nuclear Power Station
Attachment:
Core Operating Limits Report for Dresden Unit 3, Revision 17 Cc: Regional Administrator- NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station
COLR Dresden 3 Revision 17 Core Operating Limits Report For Dresden Unit 3 ,Cycle *27
~
lgrtally signed by Hopkins, Ann N: cn=Hopklns, Ann
~ e. 2020.10.21 15:18.-()2 -05'00' Date: -----,---
Maggie Rzepecka/Ann Hopkins - Nuclear Fuels Digrtally SJgned by Malan~ Sanka S j Reviewed By: _________
~-. ) ON m=Malan~ Sanka 5 - ~_0a_2_0_20_10_22_1s_s_s4_1_--0_s'OO'
__ Date: _ _ __ Sarika Malani - Reactor Engineering Reviewed By: S.Imm On S' JOh~.a;~m,~~i~4n n\ ~~rtally s,gned by Simmons, John s, --05'00' Date: ----,---- John Simmons - Engineering Safety Analysis Independent 2020 ..f 0.22 13:10:00 -05'00' Review By: Date: _ _ __ Ryan Pullara - Nuclear Fuels j.( ~ - signed by Kov.c:s, Dtgrtally ll~ Ashley
- qicKovacs, Ashley Approved By: 0ate 20201021120111-osw Date: _ _ __
Ashley Kovacs - NF Senior Manager Degraaf, Brandon )i1grtally signed by Degraaf, randon Michael SQR By: Michael - i)afe:2020.10302i-s3-42-0s*oo* Date: - - - - - Brandon de Graaf - Station Qualified Reviewer Page 1 of 31
COLR Dresden 3 Revision 17 Table of Contents Page Record of Dresden 3 COLR Revisions.. . .. .. . . .. . .. .. .. .. . . ... .. .. .. . . .. .. .. .. .. ... ...... ....... ..... .. .. 3 List of Tables. .... . . .. ..... .. ....... . ................ .. . ........................................................................ 4
- 1. Tenns and Definitions....... . .. . . . .... ..................................................... .. ...... . .... .. ........... 5
- 2. General Information ..... .... .......................... ..... ... ... ............ ..................................................... 6
- 3. Average Planar Linear Heat Generation Rate ................................................................................... 7
- 4. Operating Limit Minimum Critical Power Ratio........ ............ .... . .................................................. 8 4.1. Manual Flow Control MCPR Limits ............ .. . .. .. ..... ... . . .. ................................................. 8 4.1.1. Power-Dependent MCPR ........................................................................................ ........ 8 4 1.2. Flow-Dependent MCPR.. . .. .... .... ... . .. . . ................................................ ... . .. ....... 8 4.2. Scram Time .. .... .. ........................ ..... ......... .. . ...... ...... .. .. ... ... .... ............ ............. ....... ... ....... 9 4.3 Exposure Dependent MCPR Limits... ...... .. . . .. . .... .... .. . .. .. .. .......................................... 10 4.4. Recirculation Pump ASD Settings................................ .. . . ... .. .......................................... 10
- 5. Linear Heat Generation Rate............. ... ... .. .. . .. ............ .. ........................ ............. .... .. ........ 21
- 6. Control Rod Block Setpoints.. .. ....... .... .. .... .... .... .. .. .. ......... .. .... .. ...... .. ......................................... 24
- 7. Stability Protection Setpoints ............. .... .... ..... . ... ......................................... .. ...................... 25
- 8. Modes of Operation......... ... ...................... . ... .................. ....... ........................... ............... . .. ........ 26
- 9. Methodology............. ........... . . ...... .. .. ............................... .. ...... . .. ... ~ ................... 29
- 10. References......... .. ...................................................................................... ...................... 31 Page 2 of 31
COLR Dresden 3 Revision 17 Record of Dresden 3 COLR Revisions Revision Description 17 Initial issuance for D3C27 Page 3 of 31
COLR Dresden 3 Revision 17 List of Tables Page Table 3-1: MAPLHGR SLO Multiplier. . .. ..... ... ....................................... .. . ... . ....... 7 Table 3-2: MAPLHGR for ATRIUM 10XM .... .. ..... .... ............................... ....... 7 Table 4-1: Scram Times..... .... ..... . .. .... . ........... ... .............. . ..... ....... ... ....... ....... ... ................ 9 Table 4-2. Exposure Basis for Transient Analysis ..... .. ... ....... ............................... ... .... .... ........ . . 10 Table 4-3* ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times BOC to EOFPLB (37,536 MWd/MTU Core Average Exposure). . . ..................................... .............. ...... .. .. 11 Table 4-4* ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times BOC to EOFPLB (37,536 MWd/MTU Core Average Exposure) .................................................................................. 12 Table 4-5 ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times BOC to EOFPLB (37,536 MWd/MTU Core Average Exposure) . ... .. ................................. .... ...... .. .. ...... ..... 13 Table 4-6. ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure) ............................................................................................ 14 Table 4-7. ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure)........... . ..................................................................... 15 Table 4-8: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure)..... ....................................................................... 16 Table 4-9. ATRIUM 10XM SLO MCPRp Limits for NSS Insertion Times, All Exposures... ........ ...... 17 Table 4-10* ATRIUM 10XM SLO MCPRp Limits for ISS Insertion Times, All Exposures ....................... 18 Table 4-11: ATRIUM 10XM SLO MCPRp Limits for TSSS Insertion Times, All Exposures ....................... 19 Table 4-12* ATRIUM 10XM MCPRt Limits................ .... ... ............. .. . . .................................... 20 Table 5-1: LHGR Limits for ATRIUM 10XM............. . . .................................................................. 21 Table 5-2 ATRIUM 10XM LHGRFACp Multipliers for All Scram Insertion Times, All Exposures.... ...... 22 Table 5-3* ATRIUM 10XM LHGRFACf Multipliers for All Cycle 27 Exposures, All EOOS ..................... 23 Table 6-1. Rod Block Monitor Upscale Instrumentation Setpomts .............. .. ...... .. . ........ . ... . 24 Table 7-1: OPRM PBDA Trip Settings.............................. ..... ........ .. . ............................................ :25 Table 8-1. Modes of Operation .................. . . ............................................................................. 26 Table 8-2. Core Thermal Power Restnction for EOOS Conditions............................... ... .. ... .. . .. .. 27 Page 4 of 31
COLR Dresden 3 Revision 17
- 1. Terms and Definitions AOO Anticipated operational occurrence ASD AdJustable speed dnve BOC Beginning of cycle CAVEX Core average exposure CRWE Control rod withdrawal error CTP Core thermal power EFPD Effective full power day EFPH Effective full power hour EOCLB End of cycle licensing basis EOFPL End of full power life EOFPLB End of full power licensing basis EOOS Equipment out of service FHOOS Feedwater heater out of service FRV Feedwater regulating valve FWT Feedwater temperature ICF Increased core flow ISS Intermediate scram speed LHGR Linear heat generation rate LHGRFACr Flow dependent linear heat generation rate multiplier LHGRFACp Power dependent linear heat generation rate mult1pller LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MCPR Minimum cntical power ratio MCPRr Flow dependent minimum critical power ratio MCPRp Power dependent minimum cnt1cal power ratio MELLLA Maximum extended load line limit analysis MSIVOOS Main steam isolation valve out of service MWd/MTU Megawatt days per metric ton Uranium NRC Nuclear Regulatory Comm1ss1on NSS Nominal scram speed OLMCPR Operating limit minimum cntical power ratio OOS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm PCOOS Pressure controller out of service PLU Power load unbalance PLUOOS Power load unbalance out of service SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRV Safety/relief valve SRVOOS Safety/relief valve out of service TBV Turbine bypass valve TBVOOS Turbine bypass valves out of service TCV Turbine control valve TCVSLOWC TCV slow closure TIP Traversing in-core probe TLO Two loop operation TMOL Thermal mechanical operating limit TRM Technical Requirements Manual TSSS Technical Specification scram speed TSV Turbine stop valve Page 5 of 31
.
- COLR Dresden 3 Revision 17
- 2. General Information This report is prepared in accordance with Technical Specifi~t1on 5.6 5. The D3C47 rel~d is licensed by Framatome. *
- Licensed rated thermal power is 2957 M\/Vth. Rated core flow is 98 Mlb/hr. Operation up to 108% rated core flow is licensed for .this cycle. For allowed operating regions, see applicable power/flow map.
The licensing analysis supports full power operation to EOC!-B (38,332 MWd/MTl! CAVEX). Note that this value includes *coastdowri, where full power qperation is not expected. The tra'nsient analysis limits* are . prov,1ded for operation up. to specific CAVEX exposures as defined in Section 4.3. Coastdown is defined as operation beyond EOFPL (37,536 MWd/MTU CAVEX) with the plant power*
- gradually reducing as available core reactivity diminishes. The D3C27 reload analyses do not credit this red!,Jced power during coastdown and the EOCL,a limits remain valkt for operation 1,1p to rated power. The minimum allowed coastdown power l1;ivel is 40% rated-CTP per Reference 1.
Power and flow dependent limits are' listed for various power and flow levels. Unear interpolation on *power and flow (as applicable) is to be used to find intermediate values. Linear interpolation is also to be used for table* items intentionally left blank, as indicated by boxes which are grayed out. *
- Only MCPRp varies with scram speed. All other thermal hmrts are analyzed to remain valid with NSS, ISS, andTSSS. . .
LHGRFACt.1s_1r1dependent of feedwatt;3r temperature and*EOOS conditions.- ... For thermal limit monitoring above 100% rated power or 108% rated core flow, the 100% rated power or . the 108% core flaw thermal limit values, r.espectjvely, shall be*used. Steady state operatton is not allowed in this region ..Limits are providecj for transient COl')dit1ons only.
'\
Page 6 of 3~
COLR Dresden 3 Revision 17
/
- 3. Average Planar Linear Heat Generation Rate Technical Specifications Sections 3.2.1 and 3 4.1 Table 3-1 provides the MAPLHGR SLO multiplier for ATRIUM 10XM.
For ATRIUM 10XM fuel, the MAPLHGR values applicable for all lattIces can be found m Table 3-2. During SLO, the limits in Table 3-2 are multiplied by the fuel-specific SLO multiplier listed in Table 3-1. Table 3-1: MAPLHGR SLO Multiplier (Reference 6) Fuel Type Multiplier ATRIUM 10XM 0.80 Table 3-2: MAPLHGR for ATRIUM 10XM (Reference 6) All ATRIUM 1OXM Lattices Average Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 12.20 20,000 12.20 67,000 7 73 Page 7 of 31
COLR Dresden 3 Revision 17
- 4. Operating Limit Minimum Critical Power Ratio Technical Specif1cat1on Sections 3 2 2, 3,4.1. and 3.7.7 The OLMCPRs for D3C27 were established so that less than 0.1 % of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on the Technical Specifications SLMCPR values (Reference 6)
Tables 4-3 through 4-12 include MCPR limrts for various specified EOOS conditions. The EOOS conditions separated by *r in these tables represent single EOOS conditions and not any combination of conditions. Refer to Section 8 for a detailed explanation of allowable combined EOOS conditions 4.1. Manual Flow Control MCPR Limits The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two. 4.1.1. Power-Dependent MCPR The OLMCPR as a function of core thermal power (MCPRp) is shown in Tables 4-3 through 4-11. MCPRp limits are dependent on scram times as described in Section 4 2, exposure as described in Section 4.3, FWT, and whether the plant is in Tl.0 or SLO. TLO limits for ATRIUM 10XM fuel are given in Tables 4-3 through 4-8 and SLO limits for ATRIUM 10XM fuel are given in Tables 4-9 through 4-11. 4.1.2. Flow-Dependent MCPR Table 4-12 gives the OLMCPR limit as a function of the flow (MCPRt) based on the applicable plant condition. These values are applicable to ATRIUM 10XM. Page 8 of 31
COLR Dresden 3 Revision 17 4.2. Scram Time TSSS, ISS, and NSS refer to scram speeds The scram time values associated with these speeds are shown m Table 4-1. The TSSS scram times shown in Table 4-1 are the same as those specified in the Technical Specifications (Reference 2). To utilize the OLMCPR limits for NSS in Tables 4-3, 4-6, and 4-9 the average control rod insertion time at each control rod insertion fraction must be equal to or less than the NSS time shown in Table 4-1 below. To utilize the OLMCPR limits for ISS m Tables 4-4, 4-7, and 4-10, the average control rod insertion time at each control rod insertion fraction must be equal to or less than the ISS time shown 1n Table 4-1 below. The "Average Control Rod Insertion Time" Is defined as the sum of the control rod insertion times of all operable control rods divided by the number of operable control rods. Conservative adjustments to the NSS and ISS scram speeds were made to the analysis inputs to appropriately account for the effects of 1 stuck control rod and one additional control rod that is assumed to fail to scram (Reference 6). To utilize the OLMCPR limits for TSSS in Tables 4-5, 4-8, and 4-11, the control rod insertion time of each operable control rod at each control rod insertion fraction must be equal to or less than the TSSS time shown m Table 4-1 below. The Technical Spec1ficat1ons allow operation with up to 12 "slow' and 1 stuck control rod. One additional control rod is assumed to fail to scram for the system transient analyses performed to establish MCPRµ limits (Reference 6). Conservative adjustments to the TSSS scram speeds were made to the analysis inputs to appropriately account for the effects of the slow and stuck rods on scram reactivity (Reference 6). For cases below 38.5% power (Pt,ypaM), the results are relatively insensitive to scram speed, and only TSSS analyses were performed (Reference 6). Table 4-1: Scram Times (References 2 and 6) Control Rod Insertion NSS (seconds) 155 (seconds) TSSS (seconds) Fraction (%) 5 0 324 0 36 0.48 20 0 700 0.72 0.89 50 1.510 1.58 1.98 90 2.635 2.74 3.44 Page 9 of 31
COLR Dresden 3 Revision 17 4.3. Exposure Dependent MCPR Limits Exposure-dependent MCPRp limrts were established to support operation from BOC to EOFPLB (CAVEX of 37,536 MWd/MTU) and EOFPLB to EOCLB (CAVEX of 38,332 MWd/MTU) as defined by the CAVEX values listed in Table 4-2. The limits at a later exposure range can be used earlier in the cycle as they are the same or more conservative. Table 4-2: Exposure Basis for Transient Analysis (Reference 6) Core Average Exposure (CAVEX) Description (MWd/MTU) Design basis rod patterns to EOFPL 37,536
+ 25 EFPD (EOFPLB)
EOCLB - Maximum licensing core 38,332 exposure includino coastdown 4.4. Recirculation Pump ASD Settings Technical Requirement Manual 2.1.a.1 Dresden 3 Cycle 27 was analyzed with a slow flow excursion event assuming a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically permitted by the equipment, assumed to be 112% of rated core flow (Reference 6), therefore, the recirculation pump ASD must be set to maintain core flow less than 112% (109. 76 Mlb/hr) for all runout events Page 10 of 31
COLR Dresden 3 Revision 17 Table 4-3: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times BOC to EOFPLB (37,536 MWd/MTU Core Average Exposure) (Reference 6) Nominal FWT Core Flow Core Power (% rated) EOOS Condition (% rated) 0 26 S 38.5 > 38.5 76 100 BasefTCV Stuck :s: 60 2.44 2.44 2.14 X'\ :. :-'----': Closed/MSIVOOS > 60 2.61 2 61 2.26 1.89 \t~~s:~:;;~ 1.41 TBVOOS S60 3.36 3.36 2 56 1.97 :~-~~:~-t't '_¥;: 1.45
> 60 3.52 3.52 2.73 ~ < " . . . . -,.. -"\
TCV Slow Closure/ s 60 2.44 244 2.25 PLUOOS/PCOOS 2.25 1.71 1.41
> 60 2.61 2 61 2 26 1 FRV In s 60 2.44 2.44 2.14 Manual Mode*
1.93 ,...~*~, ,..:{-;*f ~.:.:. 1.41
> 60 2.61 2 61 2 26 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 25 :S 38.5 > 38.5 75 100 BasefTCV Stuck s 60 2.61 2.61 2 24 ~~...1~ ::..'~. Closed/MSIVOOS 2.03 ,... j,..,,}1-:i*;r~:...** 1 41
> 60 267 2.67 2.26 s 60 3 48 3.48 2.66 -:**/*J:, *_:y*
TBVOOS 2.03 :lr'),~. ;.../~~ 1 45
> 60 3 63 3.63 2.81 TCV Slow Closure/ I
- s: 60 2.61 2.61 2.25 PLUOOS/PCOOS 2.25 1.71 1.41
> 60 267 2.67 2.26
- EOOS condition 1 FRV in Manual Mode 1s not applicable at power levels below Pbyp,- (.:::.38.5%).
Page 11 of 31
COLR Dresden 3 Revision 17 Table 4-4: ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times BOC to EOFPLB (37,536 MWd/MTU Core Average Exposure) (Reference 6) Nomlnal FWT Core Flow Core Power (% rated) EOOS Condition (% rated) 0 25 S 38.5 > 38.5 75 100 s 60 Base/TCV Stuck Closed/MSIVOOS > 60 2.44 2 61 2.44 2.61 2 14 2 26 1.90 ~
~,\:-?~i ~-'.:,*;~ */, ,_ 1.41 s 60 2 56 TBVOOS > 60 3.36 3 52 3.36 3.52 2.73 1.97 .{~~'~i; ~;,~: 1.45 TCV Slow Closure/ s 60 2 44 2.44 2.25 2.25 1.72 1.41 PLUOOS/PCOOS > 60 2.61 2.61 2.26 s; 60 244 244 '.:;- ~ . ,.
1 FRV in 2.14 1.93 ~,:f;*~-~~2 ~~ 1.41 Manual Mode* > 60 2 61 2 61 2.26
,J FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 25 S38.5 > 38.5 76 100 Base/TCV Stuck s 60 2.61 2 61 2 24 .-{ .... ,: *;. Closed/MSIVOOS 2.04 :' :i --'.~. ~:(. 1 41
> 60 2.67 2.67 2 26 *~,.* " : *c-1..r,,;...'
TBVOOS s 60 3.48 348 2 66 If t~ I~* * ~
- 2.04 1.45
> 60 3.63 3.63 2 81 ,*:~~-' .:* ;:1. ~
TCV Slow Closure/ S60 2.61 2 61 225 2.25 1.72 1.41 PLUOOS/PCOOS > 60 2.67 2 67 2 26
- EOOS condition 1 FRV in Manual Mode i$ not applicable at power levels below Pbyp..,.. ~38.5%).
COLR Dresden 3 Revision 17 Table 4-5: ATRIUM 10XM TLC MCPRi, Limits for TSSS Insertion Times BOC to EOFPLB (37,636 MWd/MTU Core Average Exposure) (Reference 6) Nominal FWT EOOS Condition Core Flow Core Power (% rated) (% rated) 0 25 S 38.5 > 38.5 75 100 s 60
*,a_ ... , .
2.44 2 44 2.14 r BasefTCV Stuck Closed/MSIVOOS > 60 2.61 2 61 2 26 1 97 ,.:\~*_;\ 1 41 TBVOOS S 60 3.36 3 36 2.56 1.98 1.45
> 60 3.52 3.52 2.73 TCV Slow Closure/ - - - -s-60 2.44 2 44 2 26 -+-----+----+------< 2.26 1.74 1.41 PLUOOS/PCOOS > 60 2.61 2 61 2.26 1 FRV In s 60 2.44 2.44 2.14 1.97 1.43 Manual Mode* > 60 2.61 2.61 2.26 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) O 25 S 38.5 > 38.5 75 100 BasefTCV Stuck s 60 2.61 2.61 2.24 2.11 \\,,-,:;::~ 1.41 Closed/MSIVOOS > 60 2 67 2.67 2.26 ~. ,.,.,,. TBVOOS S 60 3 48 3.48 2.66 1.45
> 60 3 63 3.63 2.81 TCV Slow Closure/ t - - -s-60 2.61 2.61 2.26 - - - + - - - - - + - - - l - - - - - - n 2.26 1 74 1 41 PLUOOS/PCOOS > 60 2 67 2.67 2.26
- EOOS condition 1 FRV in Manual Mode is not applicable at power levels below Pbypass ~38.5%).
Page 13 of 31
COLR Dresden 3 Revision 17 Table 4-6: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure) (Reference 6) Nomlnal FWT Core Flow Core Power (% rated) EOOS Condition (% rated) 0 25 S 38.5 > 38.5 75 100 Base/TCV Stuck s 60 2.44 2.44 2.14 1.89
- ~- y?. i**~t( :
;;,.,.. *.-,.,.(-, 1 41 Closed/MSIVOOS > 60 2.61 2.61 2.26 X; *- -t_ ...
S60 3 36 3 36 2.56 TBVOOS
> 60 3 52 3 52 2 73 1.97 {?/{? 1 45 TCV Slow Closure/ s 60 2.44 2.44 2.25 PLUOOS/PCOOS > 60 2.25 1.71 1.41 2.61 2.61 226 1 FRV in s 60 2.44 2.44 2.14 ..
Manual Mode* 1 93 <~I.; .:~/~: 1 41
> 60 2 61 2.61 2.26 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 25 S 38.5 > 38.5 75 100 Base/TCV Stuck s 60 2.61 2.61 2.24
\I.,.'* '~-~ ,;- f Closed/MSIVOOS > 60 2 67 2 67 2.26 2.03 ~ ;;*i '-, ~~-~ 1.41 ,. '1~*1" -
S60 3.48 348 2 66 ~ ~ '/ ,. , TBVOOS 2.03 1 45
> 60 3.63 3.63 2.81 -~;. :*:.*. ~:.). -~
TCV Slow Closure/ s 60 2 61 2.61 2.25 PLUOOS/PCOOS > 60 2 67 2.25 1.71 1.41 2.67 2.26
- EOOS condrt1on 1 FRV in Manual Mode is not applicable at power levels below Pbypina ~38 5%).
Page 14 of 31
COLR Dresden 3 Revision 17 Table 4-7: ATRIUM 10XM TLC MCPRp Limits for ISS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure) (Reference 6) Nominal FWT Core Flow Core Power (% rated) EOOS Condition (% rated) 0 26 :S 38.5 > 38.5 75 100 Base/TCV Stuck :;; 60 2.44 2.44 2.14 1.90 ' 1.41 Closed/MSIVOOS > 60 2.61 2.61 2.26
- 60 3.36 3.36 2.56 TBVOOS 1.97 1.45
> 60 3.52 3.52 2.73 TCV Slow Closure/ ::; 60 2.44 2.44 2.25 2 25 1.72 1.41 PLUOOS/PCOOS > 60 2.61 2 61 2.26 1 FRV in :;; 60 2.44 2.44 2.14 1.93 : 1.41 Manual Mode* > 60 2.61 2.61 2.26 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 26 :S 38.5 > 38.5 75 100 Base/TCV Stuck :;; 60 2.61 2 61 2.24 .' \ 2.04 1.41 Closed/MSIVOOS > 60 2.67 2.67 2.26
- 60 3 48 3.48 2.66 TBVOOS 2.04 1.45
> 60 3.63 3.63 2.81 TCV Slow Closure/ :;; 60 2 61 2.61 2.25 2 25 1.72 1.41 PLUOOS/PCOOS > 60 2.67 2.67 2.26
- EOOS condition 1 FRV in Manual Mode is not applicable at power levels below Pt,ypasa 0:38 5%).
Page 15 of 31
COLR Dresden 3 Revision 17 Table 4-8: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times EOFPLB to EOCLB (38,332 MWd/MTU Core Average Exposure) (Reference 6) Nominal FWT Core Flow Core Power (% rated) EOOS Condition (% rated) 0 25 S 38.5 > 38.5 75 100 Base/TCV Stuck s 60 244 2.44 2.14 1.97 1.41 Closed/MSIVOOS > 60 2.61 2.61 2.26 '- ~:
- TBVOOS s 60 3.36 3.36 2.56 1.98 1.45
> 60 3.52 3.52 2.73 TCV Slow Closure/ s 60 244 2.44 2.26 2.26 1.74 1.41 PLUOOS/PCOOS > 60 2.61 2.61 2.26 1 FRV in s 60 2.44 2.44 2 14 1.97 1.43 Manual Mode" > 60 2 61 2 61 2.26 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 25 :S 38.5 > 38.5 75 100 Base/TCV Stuck s 60 2.61 2.61 2.24 2.11 1.41 Closed/MSIVOOS > 60 2.67 2.67 2.26 TBVOOS s 60 3.48 3.48 2.66 2.11
/,' 1, 1.45 > 60 3.63 3.63 2.81 TCV Slow Closure/ s 60 2.61 2.61 2.26 2.26 1.74 1.41 PLUOOS/PCOOS > 60 2.67 2.67 2.26
- EOOS condition 1 FRV in Manual Mode is not applicable at power levels below P ~ (:::.38.5%).
Page 16 of 31
COLR Dresden 3 Revision 17 Table 4-9: ATRIUM 10XM SLO MCPRp Limits for NSS Insertion Times, All Exposures (Reference 6) Nominal FWf EOOS Condition Core Power (% rated) (all Include SLO) 0 25 S 38.5 > 38.6 60 BasefTCV Stuck 2.46 2.46 2.16 2.06 2.06 Closed/MSIVOOS TBVOOS 3 38 3.38 2.58 2.06 2.06 TCV Slow Closure/ 2.46 2.46 2.27 2.27 2.10 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated) (all include SLO) 0 26 S 38.5 > 38.5 60 Base/TCV Stuck 2 63 2.63 2 26 2.06 2.06 Closed/MSIVOOS TBVOOS 3 50 3.50 2 68 2.06 2.06 TCV Slow Closure/ 2 63 2.63 2.27 2.27 2.10 PLUOOS/PCOOS Page 17 of 31
COLR Dresden 3 Revision 17 Table 4-10: ATRIUM 10XM SLO MCPRp Limits for ISS Insertion Times, All Exposures (Reference 6) Nomlnal FWT
\
EOOS Condition Core Power (% rated) (all include SLO) 0 26 S 38.6 > 38.5 50 I Base/TCV Stuck 2.46 2.46 2.16 2.06 2.06 Closed/MSIVOOS TBVOOS 3.38 3.38 2.58 2.06 2.06 TCV Slow Closure/ 2.46 246 2.27 2.27 2.11 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated) (all include SLO) 0 25 S 38.6 > 38.5 50 Base/TCV Stuck 2 63 2 63 2.26 2.06 2.06 Closed/MSIVOOS TBVOOS 3.50 3.50 2.68 2 06 2.06 TCV Slow Closure/ 2.63 2.63 2.27 2.27 2 11 PLUOOS/PCOOS Page 18 of31
COLR Dresden 3 Revision 17 Table 4-11: ATRIUM 1OXM SLO MCPRp Limits for TSSS Insertion Times, All Exposures (Reference 6) Nominal FWT EOOS Condition Core Power (% rated) (all include SLO) 0 25 S38.5 > 38.5 50 BasefTCV Stuck 2.46 2.46 2.16 2.06 2.06 Closed/MSIVOOS TBVOOS 3.38 3 38 2.58 2.06 2.06 TCV Slow Closure/ 2.46 2.46 2.28 2.28 2.12 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated) (all include SLO) 0 26 S 38.5 > 38.5 50 BasefTCV Stuck 2.63 2.63 2.26 2.13 2.06 Closed/MSIVOOS TBVOOS 3 50 3.50 2 68 213 2.06 TCV Slow Closure/ 2 63 2.63 2.28 2.28 2.12 PLUOOS/PCOOS Page 19 of 31
COLR Dresden 3 Revision 17 Table 4-12: ATRIUM 1 OXM MCPRt Limits (Reference 6) EOOS Condition" Core Flow (% rated) MCPRtLimit Base Case / FHOOS / PCOOS I PLUOOS / 0 1.64 TCV Slow Closure/ PLUOOS + PCOOS In 35 1.64 TLO and SLO / 1 FRV in Manual Mode In TLO 108 1.20 0 1.82 Any Scenario- with One MSIVOOS 35 1.82 108 1 20 0 1.88 Any Scenario- with TBVOOS 35 1.88 108 1.35 0 1.64 Any Scenario,... with 1 Stuck Closed 35 1 64 TCV/TSV 108 1.20
- See Section 8 for further operating restnctions.
- "Any Scenario" implies any other combination of allowable EOOS conditions that is not otherwise covered by this table.
Note that the MCPRt limits for any scenario with 1 stuck closed TCV/TSV are identlcal to base case MCPRt llmits. This Is reflected in the thennal limit sets presented in Table 8-1. Page 20 of 31
COLR Dresden 3 Revision 17
- 5. Linear Heat Generation Rate Technical Specification Sections 3.2 3, 3.4.1, and 3.7.7 The TMOL at rated conditions for the ATRIUM 1OXM fuel is established in terms of the maximum LHGR as a function of peak pellet (rod nodal) exposure. The LHGR limits for ATRIUM 10XM fuel are presented in Table 5-1.
The power- and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACt) are applied directly to the LHGR limits to protect against fuel melting and overstraining of the cladding during an AOO (Reference 6) In all conditions, the margin to the LHGR limits is determined by applying the lowest multiplier from the applicable LHGRFACp and LHGRFAC, multipliers for the power/flow statepoint of interest to the steady state LHGR limit (Reference 6). LHGRFACp and LHGRFACt multipliers were established to support base case and all EOOS conditions for all Cycle 27 exposures and scram speeds. The LHGRFACp multJpliers for ATRIUM 10XM are presented in Table 5-2. The LHGRFACt multipliers for ATRIUM 10XM are presented m Table 5-3. Table 6-1: LHGR Limits for ATRIUM 10XM (Reference 6) Peak Pellet Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 14.1 18,900 14.1 74,400 7.4 Page 21 of 31
COLR Dresden 3 Revision 17 Table 5-2: ATRIUM 10XM LHGRFACp Multipliers for All Scram Insertion Times, All Exposures (Reference 6) Nominal FWT Core Flow Core Power (% rated) EOOS Condition (% rated} 0 25 S 38.5 > 38.5 60 90 100 Base/TCV Stuck S60 0.54 0 54 0.58 Closed/MSIVOOS 0.61 0.68 0.89 1.00
> 60 0.54 0.54 0.58
- 5 60 0 40 0.40 0.54 TBVOOS 0.61 0 68 0.89 1 00
> 60 0 36 0.36 0.48 TCV Slow Closure/ s 60 0.54 0.54 0.58 0.61 0.68 0.89 1.00 PLUOOS/PCOOS > 60 0.54 0.54 0.58 1 FRV In :5 60 0 54 0.54 0.58 0.59 0.63 0.87 0.98 Manual Mode"' > 60 0.54 0.54 0.58 FHOOS Core Flow Core Power (% rated)
EOOS Condition (% rated) 0 25 S 38.5 > 38.6 60 90 100 Base/TCV Stuck :5 60 , 0 50 0 50 0.54 0.61 0.68 0.89 1 00 Closed/MSIVOOS > 60 0.48 048 0.54
- 5 60 0 36 0 36 0.48 TBVOOS 0.61 0.68 0.89 1.00
> 60 0.34 0.34 0.46 TCV Slow Closure/ :5 60 \ 0.50 0.50 0.54 PLUOOS/PCOOS ' 0.61 0.68 0.89 1 00 > 60 0.48 0.48 0.54
- EOOS condition 1 FRV in Manual Mode is not applicable at power levels below Pbypass ~38.5%)
Page 22 of 31
COLR Dresden 3 Revision 17 Table 6-3: ATRIUM 10XM LHGRFACt Multipliers for All Cycle 27 Exposures, All EOOS (Reference 6) Core Flow (% rated) LHGRFACt 0.0 0.57 35.0 0.57 80.0 1.00 108.0 1.00 Page 23 of 31
COLR Dresden 3 Revision 17
- 6. Control Rod Block Setpoints Technical Specification Sections 3 3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are detennined from the relationships shown in Table 6-1.
Table 6-1: Rod Block Monitor Upscale Instrumentation Setpolnts
* (Reference 3)
ROD BLOCK MONITOR UPSCALET~PFUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.65Wd + 55% Operation Single Recirculation Loop 0.65 Wd + 51% Operation Wd - percent of recirculation loop drive flow required to produce a rated core flow of 98.0 Mlbfllr. The setpoint may be lowerflligher and will still comply with the CRWE analysis because CRWE Is analyzed unblocked (Reference 6). Page 24 of 31
COLR Dresden 3 Rev1s1on 17
- 7. Stability Protection Setpoints Technical Specification Section 3.3.1.3 The OPRM PBDA Tnp Settings are provided in Table 7-1.
Table 7-1: OPRM PBDA Trip Settings (Reference 6) Corresponding Maximum PBDA Trip Amplitude Setpolnt (Sp) Confirmation Count Setpoint (Np) 1.11 14 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Methodology 2). The OPRM PBDA trip settings are based, in part, on the cycle specific OLMCPR and the power/flow dependent MCPR limits. Any change to the OLMCPR values and/or the power/flow dependent MCPR limrts should be evaluated for potential impact on the OPRM PBDA trip settings. The OPRM PBDA trip settings are applicable when the OPRM system is declared operable and the associated Technical Specifications are implemented. Page 25 of 31
COLR Dresden 3 Revision 17
- 8. Modes of Operation The allowed modes of operation with combinations of EOOS are as descnbed in Table 8-1. The EOOS conditions separated by *r in these tables represent single EOOS conditions and not combinations of conditions Note that the following EOOS options have operational restrictions: all SLO, all EOOS options with 1 TCV/TSV stuck closed, 1 MSIVOOS, and 1 FRV In Manual Mode. See Table 8-2 for specific restrictions.
Table 8-1: Modes of Operation (Reference 6) EOOS I Option Thermal Limit Set BASE CASE Base Case TLO orSLO Nominal FWT or FHOOS TBVOOS TBVOOS TLO orSLO Nominal FWT or FHOOS BASE CASE 1 TCV/TSV Stuck Closed TLO orSLO Nominal FWT or FHOOS MSIVOOS One MSIVOOS TLO orSLO Nominal FWT or FHOOS PLUOOS/TCV SLOW C TCV Slow Closure TLO orSLO Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS TLO orSLO Nominal FWT or FHOOS PLUOOS/TCV SLOW C PCOOS TLO or SLO Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS and 1 TCV/TSV Stuck Closed no for Nominal FWT or FHOOS SLO for Nominal FWP PLUOOS/TCV SLOW C PCOOS and PLUOOS no for Nominal FWT or FHOOS SLO for Nominal FWT" PLUOOS/TCV SLOW C PCOOS and 1 TCV/TSV Stuck Closed no for Nominal FWT or FHOOS SLO for Nominal FWT" 1 MANUAL FRV ALL POSITIONS 1 FRV in Manual Mode TLO for Nominal FW'P""
- FHOOS cannot be applied to SLO for the cases of PLUOOS and 1 TCV/TSV Stuck Closed, PCOOS and PLUOOS, and PCOOS and 1 TCV/TSV Stuck Closed.
- SLO and FHOOS cannot be applied for the case of 1 FRV in Manual Mode.
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COLR Dresden 3 Revision 17 Table 8-2: Core Thennal Power Restriction for EOOS Conditions (Reference 6) Core Flow (% of Core Thermal Power (% EOOS Condition Rod Line(%) Rated) of Rated Power) 1 Tcvrrsv stuck Closed Pcoos and 1 Tcvrrsv Stuck Closed NIA < 75 < 80 PLUOOS and 1 Tcvrrsv stuck Closed One MSIVOOS NIA < 75 N/A SLO < 51 < 50 NIA 1 FRV m Manual Mode NIA > 38 5 (Pbypass) NIA All requirements for all applicable conditions listed in Table 8-2 MUST be met. Page 27 of 31
COLR Dresden 3 Revision 17 Common Notes
- 1. Base case operation assumes:
a 1 TBV OOS (only 8 of the 9 bypass valves are available) per Reference 6.
- b. Between 25% and 50% rated power, the PLU will not actuate per Reference 8.
- c. The limrting relief, safety, or SRV is out-of-service per Reference 6.
d Both dome pressure and throttle pressure control are supported per Reference 6.
- e. Operation wrth a feedwater temperature band of +10/-30°F relative to the nominal feedwater temperature presented in Reference 7, Item 2.4.2.
- f. Operation for dome pressures between the minimum and maximum bands per Reference 7, Item 2.4.5.
- 2. All modes are allowed for operation at MELLLA, ICF (up to 108% rated core flow), and coastdown subject to the power restrictions in Table 8-2 (Reference 6). The licensing analysis supports full power operation to EOCLB (38,332 MWd/MTU CAVEX) Note that this value includes coastdown, where full power operation Is not expected The minimum allowed coastdown power level is 40% rated CTP per Reference 1. Each OOS Option may be combined with each of the following conditions (Reference 6):
- a. Up to 40% of the TIP channels OOS or the equivalent number of TIP channels, using the guidance in Reference 4 for startup with TIP machines OOS
- b. Up to 50% of the LPRMs OOS c An LPRM calibration frequency of up to 2500 EFPH
- 3. Nominal FWT results are valid for application within a +10°F/-30°F temperature band around the nominal FWT curve (Reference 6) For operation outside of nominal FWT, a FWT reduction of between 30°F and 120°F Is supported for all FHOOS conditions listed in Table 8-1 for cycle operation through EOCLB (Reference 6). At lower power levels, the feedwater temperature reduction is less (Reference 6) Per Reference 5, there is a restriction which requires that for a FWT reduction greater than 100°F, operation needs to be restricted to less than the 100% rod line. For a feedwater temperature reduction of between 3D°F and 120°F, the FHOOS limits should be applied.
- 4. The base case and EOOS limits and multipliers support operation with 8 of 9 turbine bypass valves operational (i.e., one bypass valve out of service) with the exception of the TBVOOS condition in which all bypass valves are inoperable (Reference 6). Use of the response curve in TRM Appendix H supports operation wrth any single TBV OOS. TRM Appendix H facilitates analysis with one valve OOS in that the capacity at 0.5 seconds from start of TSV closure Is equivalent to the total capacity with eight out of the nine valves in service (Reference 7). The analyses also support Turbine Bypass flow of 29.8% of vessel rated steam flow (Reference 7), equivalent to one TBV OOS (or partially closed TBVs equivalent to one closed TBV), if the assumed opening profile for the remaining TBVs is met. If the opening profile Is NOT met, or if the TBV system CANNOT pass an equivalent of 29.8% of vessel rated steam flow, utilize the TBVOOS condition.
- 5. TBVOOS assumes that ALL the TBVs do .!lQ! trip open on TCV fast closure or TSV closure and that ALL the TBVs are not capable of opening via the pressure control system (Reference 8). Steam relief capacity is defined in Reference 7.
6 Between 25% and 50% of rated thermal power, the PLUOOS/TCV Slow Closure thermal limit set ensures that the AOO acceptance criteria are met for a load reJection event if the 86 Device is OOS (Reference 6). Therefore, use the PLUOOS/TCV Slow Closure thermal limit set between 25% and 50% of rated thermal power if the 86 Device is OOS.
- 7. Operating restrictions apply when one Feedwater Regulating Valve is placed in manual mode, per Reference 6 Additional EOOS cond1t1ons that are supported with 1 FRV in Manual Mode consist of 40% of TIP channels OOS and 50% of the LPRMs out-of-service. Other conditions associated with base case conditions, such as the feedwater temperature band, the pressure band, single and three-element level control, dome and turbine pressure control, operation with 1 SRVOOS, and operation wrth 1 TBV OOS, are supported as discussed in Section 5.1 of Reference 6.
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COLR Dresden 3 Revision 17
- 9. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specrfically those described in the following documents:
- 1. GE Topical Report NEDE-24011-P-A, Revision 15, "General Electric Standard Application for Reactor Fuel (GESTAR)," September 2005.
- 2. GE Topical Report NEDO-32465-A, Revision 0, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 3. Exxon Nuclear Company Report XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," March 1984.
- 4. Advanced Nuclear Fuels Corporation Report ANF-89-98(P)(A), Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," May 1995.
5 Siemens Power Corporation Report EMF-85-74(P), Revision O Supplement 1 (P)(A) and Supplement 2 (P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998. 6 AREVA NP Topical Report BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," February 2008.
- 7. Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 1 Revision O and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1983.
8 Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 4 Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology for BWR Reloads," June 1986 *
- 9. Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 3 Revision 2, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," January 1987.
- 10. Siemens Power Corporation Topical Report EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2," October 1999.
- 11. AREVA Topical Report ANP-10298P-A, Revision 1, "ACE/ATRIUM 1OXM Critical Power Correlation,"
March 2014.
- 12. AREVA NP Topical Report ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," June 2011.
13 Exxon Nuclear Company Report XN-NF-84-105(P)(A), Volume 1 Revision O and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," February 1987.
- 14. Advanced Nuclear Fuels Corporation Report ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, "COTRANSA2* A Computer Program for Boiling Water Reactor Transient Analyses," August 1990.
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COLR Dresden 3 Revision 17
- 15. Framatome ANP Report EMF-2361 (P)(A), Revision 0, "EX.EM BWR-2000 ECCS Evaluation Model,"
May 2001. 16 Siemens Power Corporation Report EMF-2292(P)(A), Revision 0, "ATRIUM'-10. AppendlX K Spray Heat Transfer Coefficients," September 2000.
- 17. Framatome ANP Topical Report ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," September 2005.
- 18. Siemens Power Corporation Topical Report EMF-CC-074(P)(A), Volume 4 Revision 0, "BWR Stability Analysis. Assessment of STAIF with Input from MICROBURN-82," August 2000.
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j COLR Dresden 3 Revision 17
- 10. References
- 1. Exelon Generation Company, LLC, Docket No 50-249, Dresden Nuclear Power Station, Unit 3, Renewed Facility Operating License No DPR-25. '
- 2. Exelon Technical Specifications for Dresden 2 and 3, Table 3.1.4-1, "Control Rod Scram Times."
- 3. Exelon Design Analysis GE DRF C51-00217-01, "Instrument Setpoint Calculation Nuclear Instrumentation Rod Block Monitor," July 30, 2012.
- 4. FANP Letter, NJC:04*031/FAB04-496, "Startup with TIP Equipment Out of Service," April 20, 2004.
(Exelon EC 348897-000)
- 5. Exelon Letter, NF-MW:02-0081, "Approval of GE Evaluation of Dresden and Quad Crties Extended Final Feedwater Temperature Reduction," Carlos de la Hoz to Doug Wise and Alex Misak, August 27, 2002.
(The GE Evaluation can be found in EDMS as GE-NE-A 13-00487-00-01 P.)
- 6. Framatome Report ANP-3863P, Revision 0, "Dresden Unit 3 Cycle 27 Reload Safety Analysis," August 2020.
7 Exelon TODI ES2000003, Revision 0, "Dresden Unit 3 Cycle 27 Plant Parameters Document (PPD)," February 12, 2020.
- 8. Exelon TODI ES1500011, Revision 0, _"Equipment Out of Service Description for Transition to AREVA Fuel - Dresden," May 20, 2015.
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