ML18192A932
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Oconee Nuclear Station UFSAR Appendix 7A. Tables Appendix 7A. Tables
Oconee Nuclear Station UFSAR Table 7-1 (Page 1 of 1)
Table 7-1. Reactor Trip Summary Steady-State Trip Value or Condition for Trip Variable No. of Sensors Normal Range Trip Over Power4 4 Flux Sensors 0-100% 105.5 percent of rated thermal power4 (RTP) with four RC pumps operating 80.5 percent of RTP when reset for three RC pumps operating Nuclear Over 4 Two-Section Flux NA 109.4 percent RTP times flow Power Based on Sensors 8 P Flow minus reduction due to Flow and imbalance Imbalance2 Power/RC Pumps2 4 Pump Monitors 3 to 4 Pumps Loss of any two operating reactor coolant pumps with the reactor at power operation Reactor Outlet 4 Temperature 532-604 F 618 F Temperature Sensors Pressure/ 4 Pressure NA (11.14Thot-4706) P Temperature2 Sensors 4 Temperature Sensors Reactor Coolant 4 Pressure 2,090-2,220 psig 2,355 psig (high)3 Pressure Sensors 1,800 psig (low)2 Reactor Building 4 Pressure 0 psig 4 psig Pressure Sensors Main Turbine Trip 4 Pressure NA Turbine Trip Sensors Loss of Main 4 Pressure NA Loss of both Main Feedwater Feedwater Trip Sensors /pump (8 Pump Turbines total)
Note:
- 1. Trip condition bypassed at predetermined low power setpoints.
- 2. Bypassed by shutdown bypass.
- 3. Reset to 1720 psig by shutdown bypass.
- 4. Administratively reset to 5 percent during reactor shutdown.
(31 DEC 2016)
Oconee Nuclear Station UFSAR Table 7-2 (Page 1 of 1)
Table 7-2. Engineered Safeguards Actuation Conditions Channel Steady State No. Action Trip Condition Normal Value Trip Point1 1,22 High Pressure Low Reactor Coolant 2,120-2,250 psig 1,600 psig4 Injection and Pressure or Reactor Building Non- High Reactor Building Atmospheric 3 psig Essential Pressure Isolation 3,43 Low-Pressure Very Low Reactor 2,120-2,250 psig 550 psig Injection Coolant Pressure or High Reactor Building Atmospheric 3 psig Pressure 5,6 Reactor High Reactor Building Atmospheric 3 psig Building Pressure Cooling &
Reactor Building Essential Isolation 7,8 Reactor Very High Reactor Atmospheric 10 psig Building Spray Building Pressure Note:
- 1. Typical values and conditions. Refer to Technical specifications for current allowable value requirements.
- 2. May be bypassed below 1750 psig and is automatically reinstated above the removal setpoint value.
- 3. May be bypassed below 900 psig and is automatically reinstated above the removal setpoint value.
- 4. Based on the analyses presented in BAW-1976, SBLOCA Analyses for B&W 177-FA Lowered-Loop Plants in Response to NUREG-0737, Item II.K.3.31, and the measurement uncertainty associated with wide range RCS pressure, 1600 psig is the minimum allowable setpoint for low RCS pressure.
(31 DEC 2012)
Oconee Nuclear Station UFSAR Table 7-3 (Page 1 of 1)
Table 7-3. Engineered Safeguards Actuated Devices Channel 1 Channel 2 Channels 1 & Channel 3 Channel 4 Channels 3 & 4 2
3 HP-P1A HP-P1C HP-P1B LP-P1A LP-P1B LPSW-P1C ( )
HP-24 HP-25 LP-17 LP-18 1 2 HP-26 HP-27 LPSW-PIA( ) LPSW-PIB( )
HP-3 HP-5 HP-4 HP-21 HP-20 KEOWEE KEOWEE START START (Channel B)
(Channel A) LOAD SHED &
LOAD SHED STBY. BRK. 2
& STBY. BKR. Standby BUS 1 Standby FEED BKR. 2 BUS FEED RC-7 BKR. 1 RC-5 FDW-106 RC-6 FDW-108 FDW-105 GWD-13 FDW-107 LWD-2 GWD-12 CS-6 (7)
LWD-1 PR-2 (7)
CS-5 PR-3 (7) (7)
PR-1 PR-4 (7) (7)
PR-6 PR-5 PR-7 PR-8 PR-9 PR-10 FDW-103 FDW-104 Channel 5 Channel 6 Channels 5 & 6 Channel 7 Channel 8 CC-7 CC-8 LPSW-15 BS-1 BS-2 LPSW-18 LPSW-24 LPSW-6 BS-P1A BS-P1B RBCU-F1A RBCU-F1C LPSW-21 PR-E1A PR-E1B RBCU-F1B LPSW-1055 LPSW-1054 LPSW-1061 LPSW-1062 NOTES:
- 1. LPSW-P1C for Unit 2 LPSW-P3A for Unit 3
- 2. LPSW-P1B for Unit 2 LPSW-P3B for Unit 3
- 3. LPSW-P1A for Unit 2
- 4. Deleted per 2012 update
- 5. Deleted per 2012 update
- 6. Deleted per 2006 update
- 7. Maintained in ES position (closed) in accordance with the requirements of NUREG 0737, Item II.E.4.2.6 in any mode where ES is required operable.
(31 DEC 2012)
Oconee Nuclear Station UFSAR Table 7-4 (Page 1 of 1)
Table 7-4. Characteristics of Out-of-Core Neutron Detector Assemblies Characteristic Source/Wide Power Type Tube Sensitivity FC Gamma - Metrics UCIC1 900217-101 Thermal Neutron Flux 20 CPS/nv Note 2 Gamma Flux NA 1.5x10-10 A/R/hr Maximum Ratings External Pressure 70 psig (QTR 010) 150 psig Temperature 420 F (DBE QTR 212 F 010)
Thermal Neutron Flux Operating 1x1010 nv 1.5x1010 nv Non-Operating 1x1010 nv 2.5x1011 nv Gamma Flux 1x106 R/hr 5x105 R/hr Integrated Exposure Before 10% Reduction in Sensitivity Neutron 1020 nvt 1019 nvt Gamma N/A 3x109 R Note:
- 1. WL23636, WL23636A, and WL23636B Type Detectors are installed in various locations in Oconee Units (For Safety Related RPS Inputs); WL23675 is only installed in unit 1, a non-safety application (Unit 1 NI-9 abandoned in place per EC100792). Unit 2 NI-9 was abandoned in place per EC100793 and Unit 3 NI-9 was abandoned in place per EC100794. The original Qualification Test Report is for a WL23675 detector. All applicable data is the same for the WL23636 series except for Thermal Neutron Sensitivity. WL23636B is available replacement for all applications.
- 2. Approximate Thermal Neutron Sensitivity for Each Section WL-23675 3.75 x 10-13 A/nv WL-23636 3.75 x 10-13 A/nv WL-23636A 3.75 x 10-13 A/nv WL-23636B 2.15 x 10-13 A/nv (spec. for new detector)
(31 DEC 2013)
Oconee Nuclear Station UFSAR Table 7-5 (Page 1 of 2)
Table 7-5. NNI Inputs to Engineered Safeguards Reactor Outlet Reactor Building Reactor Building Characteristics Pressure (WR)(1) Pressure (WR) Pressure (NR)
Component Item RC3A-PT3 BS4-PS1 & 2 BS4-PT1 Number RC3A-PT4 BS4-PS3 & 4 BS4-PT2 RC3B-PT3 BS4-PS5 & 6 BS4-PT3 ESPS Channel A,B,C A,B,C A,B,C Sensor Type Pressure Transmitter Pressure Switch Pressure Transmitter Type Readout all indicating NA all indicating Power Required external none external Sensors Connected Note (3) BS4-PS2 & BS4-PT1 All separate building to Common Taps penetrations BS4-PS4 & BS4-PT2 BS4-PS6 & BS4-PT3 NNI Inputs to RPS Reactor Outlet Reactor Reactor Outlet Temperature Reactor Building Characteristics Pressure (NR)(1) (NR) Coolant Flow Pressure (NR)
Component Item RC3A-PT1 RC4A-TE1 RC14A-dPT1 BS4-PS7 Number RC3A-PT2 RC4A-TE4 RC14A-dPT2 BS4-PS8 RC3B-PT1 RC4B-TE1 RC14A-dPT3 BS4-PS9 RC3B-PT2 RC4B-TE4 RC14A-dPT4 BS4-PS10 RC14B-dPT1 RC14B-dPT2 RC14B-dPT3 RC14B-dPT4 Reactor A,B,C,D A,B,C,D A,B,C,D(2) A,B,C,D Protective Channel Sensor Type Press. RTD Differential Pressure Switch Transmitter Pressure Transmitter Type Readout all indicating all indicating all indicating NA Power Required external external external none (31 DEC 2006)
Oconee Nuclear Station UFSAR Table 7-5 (Page 2 of 2)
NNI Inputs to RPS Reactor Outlet Reactor Reactor Outlet Temperature Reactor Building Characteristics Pressure (NR)(1) (NR) Coolant Flow Pressure (NR)
Sensors RC3A-PT1 (3) & All sensors have All sensors for All sensors have Connected to separate taps. same loop are separate taps.
RC3A-PT3 Common Taps connected to RC3A-PT2 & common taps.
RC3A-PT4 RC3B-PT1 &
RC3B-PT3 Note:
- 1. NR = Narrow Range, WR = Wide Range
- 2. Each channel has an input from each loop.
- 3. Pressure taps for each RPS channel are independent. A RPS channel and an ESPS channel may have common pressure sensing taps.
- 4. Deleted per 2006 Update.
(31 DEC 2006)
Oconee Nuclear Station UFSAR Table 7-6 (Page 1 of 1)
Table 7-6. ICS Transient Limits Ramp Range Ramp Input Transient (% Full Power) Limit (% Power/min)
Power Increase 2-15 1 15-20 5 20-95 9.9 95-100 5 Power Decrease 100-95 9.9 95-20 9.9 20-15 5 15-2 1 High Limit Ramp Input Limit Runback (% Full Power) (% Power/min)
RC Flow 20 RCP 74 25 Feedwater Pump Limit 65 25 Asymmetric Rod 55 1 Generator Breakers 20 20 Maximum Runback 15 20 Condensate/Feedwater 15 20 Pump Low Suction Pressure Reactor Trip 0 600 (31 DEC 2005)