ML16343A970
| ML16343A970 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/24/2016 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16336A263 | List:
|
| References | |
| AEP-NRC-2016-42 | |
| Download: ML16343A970 (4) | |
Text
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
19.1 Table: 14.1.0-2 Page:
1 of 4 Unit 2
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED REACTIVITY COEFFICIENTS ASSUMED Fault Conditions Computer Codes Utilized Moderator Temperature (pcm/°F)
Moderator Density (K/gm/cc)
Doppler DNB Correlation Revised Thermal Design Procedure Initial NSSS Thermal Power Output 1 (MWt)
Reactor Vessel Coolant Flow (GPM)
Vessel Average Temperature
(°F)
Pressurizer Pressure (PSIA)
Uncontrolled RCCA Bank Withdrawal from a Subcritical Condition TWINKLE FACTRAN THINC See Section 14.1.1.2 N/A2 3
W-3 ANF WRB-2 and W-3 V-5 No 0
162,840 547.0 2037.0 4 RCCA Misalignment LOFTRAN THINC N/A N/A N/A W-3 ANF WRB-2 V-5 Yes 3600 366,400 581.3 2100.0 5 1 Includes reactor coolant pump heat, if applicable.
2 N/A - Not Applicable 3 Zero Power Doppler Power Defect at BOL assumed to be - 1000 pcm.
4 Core Pressure 5 For transition cycles, pressurizer pressure is 2250 psia.
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
19.1 Table: 14.1.0-2 Page:
2 of 4 Unit 2
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED REACTIVITY COEFFICIENTS ASSUMED Fault Conditions Computer Codes Utilized Moderator Temperature (pcm/°F)
Moderator Density (K/gm/cc)
Doppler DNB Correlation Revised Thermal Design Procedure Initial NSSS Thermal Power Output 1 (MWt)
Reactor Vessel Coolant Flow (GPM)
Vessel Average Temperature
(°F)
Pressurizer Pressure (PSIA)
Uncontrolled Boron Dilution N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 3600 0
N/A N/A N/A N/A N/A N/A Loss of Forced Reactor Coolant Flow LOFTRAN FACTRAN THINC
+5 N/A Max 6 W-3 ANF WRB-2 V-5 Yes 3608 366,400 581.3 7 2100.0 (5)
Locked Rotor (Peak Pressure)
LOFTRAN
+5 N/A Max (6)
N/A N/A 3680 354,000 585.4 2312.6 Locked Rotor (Peak Clad Temp)
LOFTRAN FACTRAN
+5 N/A Max (6)
N/A N/A 3680 354,000 585.4 2037.4 6 Maximum Doppler power coefficient (pcm/%power) = -19.4 + 0.002Q, where Q is in MWt (see Figure 14.1.0-1) 7 For Transition Cycles, Vessel Average Temperature is 576°F.
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
19.1 Table: 14.1.0-2 Page:
3 of 4 Unit 2
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED REACTIVITY COEFFICIENTS ASSUMED Fault Conditions Computer Codes Utilized Moderator Temperature (pcm/°F)
Moderator Density (K/gm/cc)
Doppler DNB Correlation Revised Thermal Design Procedure Initial NSSS Thermal Power Output 1 (MWt)
Reactor Vessel Coolant Flow (GPM)
Vessel Average Temperature
(°F)
Pressurizer Pressure (PSIA)
Locked Rotor (Rods-in-DNB)
LOFTRAN FACTRAN THINC
+5 N/A Max (6)
WRB-2 Yes 3608 366,400 581.3 2100.0 Loss of Normal Feedwater LOFTRAN 0
N/A Max (6)
N/A N/A 3680 354,000 585.4 2312.6 Loss of Offsite Power (LOOP) to the Station Auxiliaries LOFTRAN 0
N/A Max (6)
N/A N/A 3680 354,000 541.4 2312.6 Rupture of a Steam Pipe LOFTRAN THINC See Figure 14.2.5-1 N/A See Figure 14.2.5-2 W-3 ANF W-3 V-5 NO 0
354,000 547.0 2100.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
19.1 Table: 14.1.0-2 Page:
4 of 4 Unit 2
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED REACTIVITY COEFFICIENTS ASSUMED Fault Conditions Computer Codes Utilized Moderator Temperature (pcm/°F)
Moderator Density (K/gm/cc)
Doppler DNB Correlation Revised Thermal Design Procedure Initial NSSS Thermal Power Output 1 (MWt)
Reactor Vessel Coolant Flow (GPM)
Vessel Average Temperature
(°F)
Pressurizer Pressure (PSIA)
Rupture of a Control Rod Drive Mechanism Housing TWINKLE FACTRAN See Section 14.2.6 N/A 8, 9 N/A N/A 3660 10 0
354, 000 162, 840 585.4 547.0 2037.4 (4)
Rupture of Feedwater Pipe LOFTRAN N/A
.54 Max (6)
N/A N/A 3680 354, 000 585.4 2162.6 8 Full Power Doppler Power defect at BOL and EOL assumed to be -966 pcm and -893 pcm respectively.
9 Zero Power Doppler only Power defect at BOL and EOL assumed to be -965 pcm and -849 pcm, respective.
10 Core thermal power.