ML15174A242
| ML15174A242 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/23/2015 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-269/15-301, 50-270/15-301, 50-287/15-301 50-269/15-301, 50-270/15-301, 50-287/15-301 | |
| Download: ML15174A242 (205) | |
Text
Oconee Nuclear Station Question: 1 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor trip has just occurred from 100% power CR GP 5 Rod 5 remained fully withdrawn Reactor power is less than 1 percent and decreasing
- 1) As the remainder of the control rods fully inserted, the startup rate would have been
____(1)____ before stabilizing at - 1/3 DPM while power decreases towards the source range.
- 2) EOP subsequent actions ____(2)____ direct boration from the BWST.
Which ONE of the following completes the statements above?
A. 1. greater than -1/3 DPM (more negative)
- 2. does B. 1. greater than -1/3 DPM (more negative)
- 2. does NOT C. 1. less than -1/3 DPM (less negative)
- 2. does D. 1. less than -1/3 DPM (less negative)
- 2. does NOT Page 1 of 75
Oconee Nuclear Station Question: 2 ILT 47 ONS RO NRC Examination (1 point)
Unit 1 plant conditions:
Reactor Power =100%
1SA-18, A/1 PRESSURIZER RELIEF VALVE FLOW alarms RCS pressure = 2200 psig decreasing 1RC-66 indicates partially open 1RC-4 will not close from the control room
____(1)____ will be entered which will dispatch an operator to open 1DIB Breaker # 24 to fail ____(2)____ closed.
Which ONE of the following completes the statement above?
A. 1. AP/2, (Excessive RCS Leakage)
- 2. 1RC-4 C. 1. AP/44, (Abnormal Pressurizer Pressure Control)
- 2. 1RC-66 D. 1. AP/44, (Abnormal Pressurizer Pressure Control)
- 2. 1RC-4 Page 2 of 75
Oconee Nuclear Station Question: 3 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0400 Reactor Trip from 100%
SBLOCA has occurred Rule 2 (Loss of SCM) in progress 1A and 1B MD EFDWPs are operating Time = 0410 Rule 7 (SG Feed Control) in progress RCS temperature = 470°F slowly decreasing EFW flow = 100 gpm to each SG 1A and 1B SG levels = 85 XSUR stable
- 1) At 0400, in accordance with Rule 2, __ (1) __ gpm EFDW flow will initially be established to each SG.
- 2) At 0410, in accordance with Rule 7 (SG Feed Control), EFDW flow should be
__ (2) __.
Which ONE of the following completes the statements above?
A. 1. 300
- 2. decreased B. 1. 300
- 2. increased C. 1. 450
- 2. decreased D. 1. 450
- 2. increased Page 3 of 75
Oconee Nuclear Station Question: 4 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0800:
Reactor power = 100%
LBLOCA occurs Time = 0810:
RCS Pressure = 200 psig decreasing HPI Flow in 1A Header = 750 gpm HPI Flow in 1B Header = 490 gpm Which ONE of the following describes the required operator actions per Rule 6 HPI PUMP THROTTLING LIMITS, to protect the HPI pumps?
A. Throttle each HPI pump flow to <475 gpm B. Throttle HPI flow in ONLY 1A header to <750 gpm C. Throttle HPI flows in BOTH 1A & 1B headers to <950 gpm combined D. Throttle HPI flow in ONLY 1B header to <475 gpm Page 4 of 75
Oconee Nuclear Station Question: 5 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial Conditions Core Thermal Power = 100%.
Current conditions:
A Station Blackout occurs at 0600.
AP/0/A/1700/025 (Standby Shutdown Facility Emergency Operating Procedure) has been initiated.
1XSF is being powered from 0XSF.
- 1) In accordance with station Time Critical Actions, SSF RCMU flow must be established to Unit 1 RCP seals no later than ___(1)___.
Which ONE of the following completes the statements above?
A. 1. 0614
- 2. can B. 1. 0620
- 2. can C. 1. 0614
- 2. cannot D. 1. 0620
- 2. cannot Page 5 of 75
Oconee Nuclear Station Question: 6 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 1200 Reactor power = 80%
1HP-120 (RC VOLUME CONTROL) FAILED CLOSED Makeup flow has been re-established in accordance with AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection)
Time = 1215 Pressurizer level is 220 stable
- 1) In accordance with AP/14, ____(1)____ was throttled first to maintain Pzr level.
- 2) If 1RC-1 subsequently fails open at Time = 1220, prior to any Operator actions RCS makeup flow will ____(2)____.
Which ONE of the following completes the statements above?
A. 1. 1HP-26 (1A HP INJECTION)
- 2. decrease C. 1. 1HP-122 (RC VOLUME CONTROL BYPASS)
- 2. increase D. 1. 1HP-122 (RC VOLUME CONTROL BYPASS)
- 2. decrease Page 6 of 75
Oconee Nuclear Station Question: 7 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions Reactor power = 100%
The running CC pump trips AP/20 LOSS OF COMPONENT COOLING has been entered 2 minutes have elapsed CC Surge Tank level = 10 NO automatic actions occur
- 1) Assuming that no operator actions are taken during the first 2 minutes of the event,
____(1)____.
- 2) Based on the above plant conditions, AP/20 ____(2)____ direct the operator to start the standby CC pump.
Which ONE of the following completes the statements above?
A. 1. CRDM temperatures will have increased to the point at which damage has occurred to the stator windings
- 2. will B. 1. CRDM temperatures will have increased to the point at which damage has occurred to the stator windings
- 2. will NOT C. 1. Demineralizer temperatures will have increased to the point at which damage has occurred to the demineralizer resin
- 2. will D. 1. Demineralizer temperatures will have increased to the point at which damage has occurred to the demineralizer resin
- 2. will NOT Page 7 of 75
Oconee Nuclear Station Question: 8 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
RCS pressure = 2360 psig increasing Current conditions:
Reactor power = 7% decreasing
- 1) With Reactor power decreasing, the MINIMUM power level at which Rule 1 (ATWS/UNPP) is required to be performed to address Emergency Boration is
__(1)__.
- 2) The reason this power level is chosen is so the Boron will reduce reactor power to
__ (2) __.
Which ONE of the following completes the statements above?
A. 1. 1%
- 2. below the point of adding heat B. 1. 1%
- 2. within the capacity of the EFDW system C. 1. 5%
- 2. below the point of adding heat D. 1. 5%
- 2. to within the capacity of the EFDW system Page 8 of 75
Oconee Nuclear Station Question: 9 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
SGTR tab in progress 1B SG isolated 1B1 RCP secured 1A loop Tcold = 440°F decreasing 1B S/G TUBE/SHELL DT = (-)72°F
- 1) The reason the SGTR tab directs minimizing core SCM during cooldown is to minimize__(1)__.
- 2) The initial method that will be used to reduce the SCM is __(2)__.
Which ONE of the following completes the statements above?
A. 1. primary to secondary leak rate
- 2. de-energizing Pzr heaters and cycling Pzr spray B. 1. primary to secondary leak rate
- 2. de-energizing Pzr heaters and cycling Pzr spray D. 1. compressive stresses in the 1B SG
- 2. cycling the PORV Page 9 of 75
Oconee Nuclear Station Question: 10 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0800:00 Reactor power = 90%
Control Rod Gp 7 position = 90%
The PI panel is selected to Relative Steam line break on the 1A SG occurs inside containment Time = 0801:00 Reactor trip occurs
- 1) At Time = 0800:30 ____(1)____ SG pressure(s) will be decreasing.
- 2) The MINIMUM requirement for Relative Position Indication (RPI) to AUTOMATICALLY reset to 0% is to have ____(2)____.
Which ONE of the following completes the statements above?
A. 1. ONLY 1A
- 2. a Trip Confirmed signal generated B. 1. ONLY 1A
- 2. ALL Regulating Rod Group IN LIMITs satisfied C. 1. BOTH 1A and 1B
- 2. a Trip Confirmed signal generated D. 1. BOTH 1A and 1B
- 2. ALL Regulating Rod Group IN LIMITs satisfied Page 10 of 75
Oconee Nuclear Station Question: 11 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Both Main FDW pumps trip 1A and 1B MDEFDW pumps did NOT start TDEFWP did NOT start Current conditions:
Tave = 566ºF stable Recovery from CBP feed with the TDEFDW pump is in progress TDEFWP is running and flow has been verified Which ONE of the following describes how Tave and SG levels will be controlled INITIALLY during the recovery from CBP feed?
Tave will INITIALLY be controlled by throttling ____(1)____ and INITIALLY a SG level
____(2)____ be established.
A. 1. EFDW flow
- 2. will NOT B. 1. the TBVs
- 2. will NOT C. 1. EFDW flow
- 2. will D. 1. the TBVs
- 2. will Page 11 of 75
Oconee Nuclear Station Question: 12 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial Conditions:
Reactor power = 100%
1A HPI pump switch in ON 1B HPI pump switch in AUTO SBLOCA occurs The reactor trips on variable low RCS pressure Current conditions 1A HPI pump switch in ON 1B HPI pump switch in AUTO A Switchyard Isolation occurs CT-1 locks out RCS pressure has decreased to 1500 psig Following the CT-1 lockout, when the 4160 VAC busses re-energize:
- 1) there will be ____(1)____ HPIP(s) operating.
- 2) If 1HP-26 fails to open the operator will ____(2)____.
Which ONE of the following completes the statements above?
A. 1. 2
- 2. open 1HP-410 B. 1. 3
- 2. open 1HP-410 C. 1. 2
- 2. dispatch an operator to manually open 1HP-26 D. 1. 3
- 2. dispatch an operator to manually open 1HP-26 Page 12 of 75
Oconee Nuclear Station Question: 13 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
A loss of both MFW pumps occurs from 100% power Rule 3 (Loss of Main or Emergency FDW) is in progress 1FDW-315 and 1FDW-316 are maintaining SG levels at 30 XSUR Current conditions:
1KVIB is de-energized Assuming no additional operator actions, which ONE of the following will be directed by the EOP and why?
A. Take manual control of 1FDW-315 since its Moore controller will automatically swap to its alternate power supply B. Take manual control of 1FDW-316 since its Moore controller will automatically swap to its alternate power supply C. Feed the 1A SG through 1FDW-35 (1A STARTUP FDW CONTROL) since 1FDW-315 will fail open D. Feed the 1A SG through 1FDW-35 (1A STARTUP FDW CONTROL) since 1FDW-316 will fail open Page 13 of 75
Oconee Nuclear Station Question: 14 ILT 47 ONS RO NRC Examination (1 point)
Given the following Plant conditions:
1CA Battery Charger fails - output voltage = 0 VDC 1CA Battery voltage = 126 VDC 1DCB Bus voltage = 123 VDC Unit 2 DCA/DCB Bus voltage = 124 VDC Unit 3 DCA/DCB Bus voltage = 127 VDC Which ONE of the following will be supplying power to 1DIA panelboard?
A. 1DCB Bus B. 1CA Battery C. Unit 2 DC Bus D. Unit 3 DC Bus Page 14 of 75
Oconee Nuclear Station Question: 15 ILT 47 ONS RO NRC Examination (1 point)
Given the following plant conditions:
Time = 0800:
Unit 1 = 100% power Unit 2 = Mode 5 Unit 3 = 100% power A, B and C LPSW pumps are operating Time = 0805:
C LPSW pump trips AP/24, Loss of LPSW is initiated LPSW header pressure = 65 psig stable
- 1) The LCO for TS 3.7.7 Low Pressure Service Water (LPSW) System ____(1)____
met for Unit 1.
be directed.
Which ONE of the following completes the statements above?
A. 1. is
- 2. will B. 1. is
- 2. will NOT C. 1. is NOT
- 2. will D. 1. is NOT
- 2. will NOT Page 15 of 75
Oconee Nuclear Station Question: 16 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
A complete loss of Instrument Air (IA) and Auxiliary Instrument Air (AIA) occurs.
Which ONE of the following describes RCP seal cooling and Pressurizer level response?
RCP Seal cooling will be maintained by ____(1)____ and pressurizer level will
____(2)____
ASSUME NO OPERATOR ACTIONS A. 1. Component Cooling
- 2. decrease B. 1. Component Cooling
- 2. increase C. 1. HPI Seal Injection
- 2. decrease D. 1. HPI Seal Injection
- 2. increase Page 16 of 75
Oconee Nuclear Station Question: 17 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Both Main Feedwater pumps tripped EFDW NOT available 1TD de-energized RCS pressure = 2217 psig slowly increasing
- 1) The pumps that will be aligned first to provide decay heat removal in accordance with the EOP are the __(1)__?
- 2) AP/11 (Recovery from Loss of Power) entry conditions __(2)__ met?
A. 1. HPI Pumps
- 2. are B. 1. HPI Pumps
- 2. are NOT C. 1. Condensate Booster Pumps
- 2. are D. 1. Condensate Booster Pumps
- 2. are NOT Page 17 of 75
Oconee Nuclear Station Question: 18 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0800:
Reactor power = 100%
Grid voltage oscillating Generator Parameters:
o MWe = 950 o Vars = -350 MVAR o H2 Pressure = 45 psig AP/34 (Degraded Grid) has been initiated Time = 0805:
Reactor power = 60%
Generator Parameters o MWe = 550 o Vars = -450 MVAR o H2 Pressure = 45 psig
- 1) At 0805, AP/34 directs the operator to ____(1)____.
- 2) The reason this action is taken is to protect the generator from excessive
____(2)____.
Which ONE of the following competes the statements above?
REFERENCE PROVIDED A. 1. OPEN PCB 20 and PCB 21
- 2. armature core end heating B. 1. OPEN PCB 20 and PCB 21
- 2. field heating C. 1. Trip the reactor
- 2. armature core end heating D. 1. Trip the reactor
- 2. field heating Page 18 of 75
Oconee Nuclear Station Question: 19 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 90%
Controlling Tave fails low Plant Transient Response is performed Appropriate ICS stations are placed in MANUAL
- 1) Feedwater flow will ____(1)____ due to the failure.
- 2) Control rods are moved to ____(1)____.
Which ONE of the following completes the statements above?
A. 1. increase
- 2. the pre-transient rod height B. 1. increase
- 2. match current feedwater demand C. 1. decrease
- 2. the pre-transient rod height D. 1. decrease
- 2. match current feedwater demand Page 19 of 75
Oconee Nuclear Station Question: 20 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Reactor in MODE 6 Core offload in progress MP/0/A/1500/029, Reactor Bridge Operation is in progress Main Fuel Bridge is withdrawing a fuel assembly that appears to be binding The __(1)__ interlock will stop the withdrawal of the fuel assembly to prevent fuel Damage. The load setpoint for this interlock is __(2)__.
Which ONE of the following completes the statement above?
A. 1. TS-1 (Overload Bypass)
- 2. 2500 lb B. 1. TS-1 (Overload Bypass)
- 2. 3000 lb C. 1. TS-2 (Hoist Interlock Bypass)
- 2. 2500 lb D. 1. TS-2 (Hoist Interlock Bypass)
- 2. 3000 lb Page 20 of 75
Oconee Nuclear Station Question: 21 ILT 47 ONS RO NRC Examination (1 point)
Given the following Plant conditions:
All Units Reactor power = 100%
1SA3/B-6 (Fire Alarm) actuated AO reports flames and heavy smoke spreading to equipment and cable trays Fire location = Near the LPSW pumps, Column G30 Which ONE of the following locations is the affected SSF Risk Area(s) and the required action in accordance with AP/25 (Standby Shutdown Facility Emergency Operating Procedure)?
REFERENCE PROVIDED A. ALL Three Units are affected therefore trip ALL Three Units B. ONLY Unit 2 is affected therefore trip Unit 2 ONLY C. ALL Three Units are affected therefore perform a rapid shutdown on all three units D. ONLY Unit 2 is affected therefore perform a rapid shutdown on Unit 2 ONLY Page 21 of 75
Oconee Nuclear Station Question: 22 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
The reactor was tripped Unit 1 & 2 Control Room was evacuated prior to any additional actions being taken The crew has proceeded to the Auxiliary Shutdown Panel (ASP)
AP/8 (Loss Of Control Room) is in progress LDST level at the ASP = 47 inches decreasing In accordance with AP/8:
- 1) LDST level will be maintained by aligning HPIP suction to the BWST____(1)____
- 2) If no action is taken, 1HP-24 and 1HP-25 will automatically open when LDST level decreases to a setpoint value of ____(2)____ inches.
Which ONE of the following completes the statement above?
A. 1. at the ASP
- 2. 40 B. 1. at the ASP
- 2. 45 C. 1. locally at the valve(s)
- 2. 40 D. 1. locally at the valve(s)
- 2. 45 Page 22 of 75
Oconee Nuclear Station Question: 23 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0800:
Reactor power = 100%
Auxiliary Steam header being supplied by Unit 2 Large Break LOCA occurs Time = 0804:
Transition to the ICC tab is made The step to reduce SG pressure is initiated Which ONE of the following describes the guidance provided by the ICC tab?
A. SGs depressurization will be limited to 100 OF / hr cooldown rate and will stop at 250 psig.
B. SGs depressurization will be limited to 100 OF / hr cooldown rate and will continue until SGs are completely depressurized.
C. SGs depressurization will occur as rapidly as possible and will stop at 250 psig.
D. SGs depressurization will occur as rapidly as possible and will continue until SGs are completely depressurized.
Page 23 of 75
Oconee Nuclear Station Question: 24 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 80% stable Tc Controller is in HAND 1B1 RCP trips Crew performs Plant Transient Response Crew enters AP/1 (Unit Runback)
Tc = +1.2 and becoming more positive The operator will have to manually re-ratio feedwater such that feed to the __(1)__ SG will increase because the ___(2)___.
Which ONE of the following completes the above statement?
A. 1. 1A
- 2. RC Flow Ratio circuit has failed B. 1. 1A
- 2. RC Flow Ratio circuit is blocked when the Delta Tc controller is in HAND C. 1. 1B
- 2. RC Flow Ratio circuit has failed D. 1. 1B
- 2. RC Flow Ratio circuit is blocked when the Delta Tc controller is in HAND Page 24 of 75
Oconee Nuclear Station Question: 25 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 1200 Reactor power = 40%
PCB 20 and PCB 21, Generator Output Breakers open A plant runback initiates Time = 1202 Reactor power = 30% decreasing Main Turbine trips At Time = 1204, the SGs will be fed from ____(1)____ feedwater and heat removal from the reactor will be by ____(2)____circulation.
Which ONE of the following completest the statements above?
A. 1. Main
- 2. Natural B. 1. Main
- 2. Forced C. 1. Emergency
- 2. Natural D. 1. Emergency
- 2. Forced Page 25 of 75
Oconee Nuclear Station Question: 26 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
A SB LOCA has occurred LOCA CD tab in progress 1A LPI Pump operating in the Piggyback alignment Which ONE of the following describes the:
- 2) pump(s) being protected by the above limitation?
A. 1. Maximized to < 3100 gpm
- 2. LPI B. 1. Maximized to < 3100 gpm
- 2. HPI C. 1. Maximized to < 2900 gpm
- 2. LPI D. 1. Maximized to < 2900 gpm
- 2. HPI Page 26 of 75
Oconee Nuclear Station Question: 27 ILT 47 ONS RO NRC Examination (1 point) 1SA-1 1 2 3 4 5 6 7 8 9 10 11 12 ICS A 1 A RPS TRIP 1A LO PRESS TRIP 1A FLUX/ IMB/ FLOW TRIP 1A HI TEMP TRIP 1A VAR LO PRESS TRIP 1A HI PRESS 1A RCP / FLUX 1A HI FLUX 1A R.B. HI PRESS ES 1 TRIP ES 5 TRIP LOSS OF ACS POWER FUSE TRIP TRIP TRIP TRIP BLOWN 1B 1B 1B ICS B 1 B RPS TRIP 1B LO PRESS TRIP FLUX/IMB/ FLOW TRIP HI TEMP TRIP 1B VAR LO PRESS TRIP HI PRESS TRIP 1B RCP / FLUX TRIP 1B HI FLUX TRIP 1B R.B. HI PRESS TRIP ES 2 TRIP ES 6 TRIP AUTO/ HAND POWER FUSE BLOWN 1C C 1 C RPS TRIP 1C LO PRESS TRIP 1C FLUX/IMB/ FLOW TRIP HI TEMP TRIP 1C VAR LO PRESS 1C HI PRESS 1C RCP / FLUX 1C HI FLUX 1C R.B. HI PRESS ES 3 TRIP ES 7 TRIP LP INJECTION PUMP A DIFF. PRESS TRIP TRIP TRIP TRIP TRIP LOW 1D 1D 1D D 1 DRPS TRIP LO PRESS TRIP FLUX/ IMB/ FLOW TRIP HI TEMP TRIP 1A VAR LO PRESS 1D HI PRESS 1D RCP / FLUX 1D HI FLUX 1D R.B. HI PRESS ES 4 TRIP ES 8 TRIP LP INJECTION PUMP B DIFF. PRESS TRIP TRIP TRIP TRIP TRIP LOW CRD CRD CRD E SEQUENCE FAULT TRIP BKR A TRIP TRIP BKR B TRIP CRD TRIP BKR C TRIP CRD TRIP BKR D TRIP CRD ELECTRONIC CRD ELECTRONIC TRIP E TRIP F DIVERSE HPI BYP DIVERSE HPI TRIP DIVERSE LPI BYP DIVERSE LPI TRIP LP INJECTION PUMP C DIFF. PRESS LOW Given the following Unit 1 conditions Initial conditions:
Reactor power = 45% stable Current conditions:
Reactor power = <1% WR decreasing Core SCM = 0°F stable RCS pressure = 140 psig decreasing Reactor Building pressure = 16.4 psig increasing 1SA-1 alarms as indicated above Which ONE of the following describes actions required by the EOP?
A. Secure running LPI pumps B. Manually actuate ES Digital Channels 7 & 8 C. Dispatch AO to open CRD breakers C & D D. Feed to LOSCM setpoint with Emergency Feedwater Page 27 of 75
Oconee Nuclear Station Question: 28 ILT 47 ONS RO NRC Examination (1 point)
Plant conditions:
It is desired to perform a manual start of KHU-1 from the Unit 1/2 Control Room The MASTER TRANSFER switch for KHU-1 is positioned to REMOTE UNIT 1 MASTER SELECTOR is placed in MAN UNIT 1 SYNC 230 KV selector is placed in MAN UNIT 1 LOCAL MASTER switch is placed in START and held in position for
> 10 seconds until KHU-1 starts In the above starting sequence, which ONE of the following is correct regarding generator cooling water flow?
A. When the MASTER SELECTOR switch is placed in MAN, the generator cooling water pump will start to provide water to the cooler.
B. When the MASTER SELECTOR switch is placed in MAN, the generator cooling water valve will open to provide water to the cooler.
C. When the LOCAL MASTER switch is placed in START, the generator cooling water pump will start to provide water to the cooler.
D. When the LOCAL MASTER switch is placed in START, the generator cooling water valve will open to provide water to the cooler.
Page 28 of 75
Oconee Nuclear Station Question: 29 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 1200 Reactor power = 65% stable 1LPSW-6 (UNIT 1 RCP COOLERS SUPPLY) fails closed Time = 1205 AP/16 (Abnormal RCP Operation) in progress RCP Temperatures:
1A1 1A2 1B1 1B2 Upper Guide 182ºF 197ºF 188ºF 185ºF Bearing Temp Seal Return 169ºF 174ºF 227ºF 187ºF Temp Which ONE of the following is required per AP/16 at Time = 1205?
A. Trend affected RCP temperatures since no RCP immediate trip criteria has been reached B. Manually trip the Reactor and stop RCPs 1A2 & 1B1 ONLY C. Stop RCP 1A2 ONLY and verify FDW re-ratios properly D. Stop RCP 1B1 ONLY and verify FDW re-ratios properly Page 29 of 75
Oconee Nuclear Station Question: 30 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
LDST level = 90 Stable Current conditions:
1HP-14 fails to the Bleed position
- 1) Over the next 5 minutes, 1HP-120 will __ (1) __ to maintain Pzr level constant.
- 2) __ (2) __ will be entered to mitigate this event.
Which ONE of the following completes the statements above?
A. 1. open
- 2. AP/02 (Excessive Leakage)
B. 1. open
- 2. AP/32 (Loss of Letdown)
C. 1. remain in its current position
- 2. AP/02 (Excessive Leakage)
D. 1. remain in its current position
- 2. AP/32 (Loss of Letdown)
Page 30 of 75
Oconee Nuclear Station Question: 31 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
A LOCA occurs Rule 2 (Loss of SCM) is initiated RCS pressure = 1500 psig slowly decreasing 1HP-24 and 1HP-25 fail to open When the Piggyback lineup is complete, there will be ____(1)____ LPI pump(s) and
____(2)____ HPI pumps operating.
Which ONE of the following completes the statement above?
A. 1. one
- 2. two B. 1. one
- 2. three C. 1. two
- 2. two D. 1. two
- 2. three Page 31 of 75
Oconee Nuclear Station Question: 32 ILT 47 ONS RO NRC Examination (1 point)
Which ONE of the following states the power supply for 3LP-18?
A. 3XS-1 B. 3XS-2 C. 3XS-3 D. 3XS-4 Page 32 of 75
Oconee Nuclear Station Question: 33 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Loss of all Feedwater HPI forced cooling initiated Quench Tank pressure = 50 psig increasing RCS activity indicates no fuel failures present Current conditions:
Quench Tank pressure = 3 psig stable Which ONE of the following describes the containment response?
A. RB Normal sump level rises and 1RIA-47 radiation level increases B. RB Normal sump level rises and 1RIA-47 radiation level remains constant C. RB Normal sump level remains constant and 1RIA-47 radiation level increases D. RB Normal sump level remains constant and 1RIA-47 radiation level remains constant Page 33 of 75
Oconee Nuclear Station Question: 34 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
OP/1/A/1103/002, (Filling and Venting RCS) Enclosure 4.14 (Establishing Pzr Steam Bubble And RCS Final Vent) in progress The Pressurizer is vented to the Quench Tank for 30 minutes
- 1) In accordance with OP/1/A/1103/002, Quench Tank level should increase a minimum of ____(1)____ to indicate that Pzr Steam Bubble Formation is complete?
- 2) A consequence of incomplete Pzr bubble formation is that ____(2)____.
Which ONE of the following completes the statements above?
A. 1. 0.2 inches
- 2. Pzr spray will NOT effectively control RCS pressure on an insurge B. 1. 0.2 inches
- 2. Pzr heaters will NOT effectively control RCS pressure on an outsurge C. 1. 2.0 inches
- 2. Pzr spray will NOT effectively control RCS pressure on an insurge D. 1. 2.0 inches
- 2. Pzr heaters will NOT effectively control RCS pressure on an outsurge Page 34 of 75
Oconee Nuclear Station Question: 35 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 Conditions:
Reactor power = 100%
- 1) ___(1)___ would result in an increase in CC Cooler outlet temperature ºF.
- 2) The Component Cooling water temperature exiting the Letdown Cooler is monitored by ___(2)___.
Which ONE of the following completes the statements above?
A. 1. Throttling open 1HP-7
- 2. OAC indication ONLY B. 1. Throttling open 1HP-7
- 2. OAC indication AND Control Room temperature gage C. 1. Placing 1HP-14 in BLEED
- 2. OAC indication ONLY D. 1. Placing 1HP-14 in BLEED
- 2. OAC indication AND Control Room temperature gage Page 35 of 75
Oconee Nuclear Station Question: 36 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Initial conditions:
Reactor power = 100%
Switchyard Isolation occurs Current Conditions:
Natural Circulation established RCS pressure = 2155 psig Tcold = 550°F stable Pressurizer level = 220 stable Pressurizer temperature = 628°F
- 1) The Pressurizer is __(1)__.
- 2) Pressurizer Heater Bank #2 (Groups B & D) heaters are __(2)__.
Which ONE of the following completes the statements above?
A. 1. saturated
- 2. energized B. 1. subcooled
- 2. energized C. 1. saturated
- 2. NOT energized D. 1. subcooled
- 2. NOT energized Page 36 of 75
Oconee Nuclear Station Question: 37 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Mode 5 Pzr bubble has just been established PT/1/A/0201/004 (RC-66 Stroke Test) is being performed Pzr pressure = 40 psig Quench Tank pressure = 0 psig When RC-66 is opened QT pressure will ____(1)____ and the temperature downstream of the PORV will increase to ____(2)____.
Which ONE of the following completes the statement above?
A. 1. remain approximately the same
- 2. 252 OF B. 1. remain approximately the same
- 2. 265 OF C. 1. increase
- 2. 252 OF D. 1. increase
- 2. 265 OF Page 37 of 75
Oconee Nuclear Station Question: 38 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
1A RPS Thot RTD power supply is lost Which ONE of the following describes:
- 1) ALL RPS trips affected by the failure?
- 2) the actions preferred in accordance with OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)?
A. 1. RCS High Outlet Temperature ONLY
- 2. Place MANUAL TRIP Keyswitch in "TRIP".
B. 1. RCS High Outlet Temperature ONLY
C. 1. RCS High Outlet Temperature and RCS Variable Low Pressure
- 2. Place MANUAL TRIP Keyswitch in "TRIP".
D. 1. RCS High Outlet Temperature and RCS Variable Low Pressure
Page 38 of 75
Oconee Nuclear Station Question: 39 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 50% stable Power to ES Channel 1 VOTERS is lost
- 1) The loss of power above ___(1)___ actuate ES Channel 1.
- 2) In accordance with TS 3.3.7 (ESPS Automatic Actuation Output Logic Channels) the Completion Time for placing the associated ES Ch 1 components in their ES configuration is ___(2)___.
Which ONE of the following completes the statements above?
A. 1. will
- 2. immediately B. 1. will
- 2. one hour C. 1. will NOT
- 2. immediately D. 1. will NOT
- 2. one hour Page 39 of 75
Oconee Nuclear Station Question: 40 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Time = 1200 Reactor Power = 100%
1A MSLB inside the Reactor Building Current conditions:
Time = 1201 Reactor Building Pressure = 3 psig increasing Which ONE of the following describes the operation of 1A RBCU OUTLET, 1LPSW-18?
A. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1201 B. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1201 C. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1204 D. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1204 Page 40 of 75
Oconee Nuclear Station Question: 41 ILT 47 ONS RO NRC Examination (1 point)
Which ONE of the following is the power supply for Reactor Building Cooling Unit (RBCU) 1A?
A. 1XS2 B. 1XS3 C. 1X8 D. 1X9 Page 41 of 75
Oconee Nuclear Station Question: 42 ILT 47 ONS RO NRC Examination (1 point)
Which ONE of the following is the power supply to Building Spray Pump 1A discharge valve, 1BS-1?
A. 1XS-2 B. 1XS-3 C. 1XS-4 D. 1XS-5 Page 42 of 75
Oconee Nuclear Station Question: 43 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
1RIA-40 (CSAE Off-Gas Monitor) reading is rising slowly 1RIA-54 (Turbine Building (TB) Sump Monitor) is inoperable The operating crew has just entered AP/31 (Primary To Secondary Leakage) due to a 6 gpm leak in the 1A SG
- 1) In accordance with AP/31 an AO is required to __ (1) __.
- 2) Emergency Dose Limits __ (2) __ in affect.
A. 1. open and white tag the TB Sump Pump breakers
- 2. are NOT Page 43 of 75
Oconee Nuclear Station Question: 44 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Unit startup in progress Turbine heatup has been initiated Turbine Bypass Lines Pumping Trap has malfunctioned and is not removing moisture
- 1) Plant damage, as a result of the malfunctioning pumping trap is a concern due to the potential of__ (1) __.
- 2) The Turbine Bypass Lines Pumping Trap is aligned to the __ (2) __.
Which ONE of the following completes the statements above?
A. 1. a water hammer
- 2. Condenser B. 1. a water hammer
- 2. Condensate Storage Tank C. 1. moisture impingement on the turbine blades
- 2. Condenser D. 1. moisture impingement on the turbine blades
- 2. Condensate Storage Tank Page 44 of 75
Oconee Nuclear Station Question: 45 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 40%
Loop B FDW valve P selected to 1B2 Current conditions:
1B2 Loop B FDW valve P fails LOW
- 1) Feedwater Flow will initially __ (1) __.
- 2) AP/28 (ICS Instrument Failures) will ensure BOTH __ (2) __ are in HAND to stabilize the plant.
Which ONE of the following completes the statements above?
A. 1. decrease
- 2. FDW Masters B. 1. decrease
- 2. Main FDW Pumps C. 1. increase
- 2. FDW Masters D. 1. increase
- 2. Main FDW Pumps Page 45 of 75
Oconee Nuclear Station Question: 46 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Condenser vacuum = 18.5 inches Hg stable 1TA and 1TB de-energized SG levels will be automatically controlled at ________.
Which ONE of the following completes the statement above?
A. 25 inches SUR B. 30 inches XSUR C. 50% OR D. 240 inches XSUR Page 46 of 75
Oconee Nuclear Station Question: 47 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 1200 Reactor power = 100%
Unit 1 TDEFWP unavailable Time = 1230 Both Main FDW pumps trip 1B MDEFWP fails to start Which ONE of the following:
- 1) describes actions directed by the EOP to remove core decay heat?
- 2) states the maximum flow rate (gpm) that can be supplied by the 1A MDEFWP at Time = 1230 in accordance with Rule 7 (SG Feed Control).
A. 1. cross connect with an alternate unit to supply the 1B Steam Generator
- 2. 440 B. 1. cross connect with an alternate unit to supply the 1B Steam Generator
- 2. 600 C. 1. feed both SGs with 1A MDEFWP
- 2. 440 D. 1. feed both SGs with 1A MDEFWP
- 2. 600 Page 47 of 75
Oconee Nuclear Station Question: 48 ILT 47 ONS RO NRC Examination (1 point)
Given the following plant conditions:
ACB-2 (Keowee 2 Generator BKR) CLOSED ACB-3 (Keowee 1 Emergency Feeder BKR) CLOSED A LOOP (Switchyard Isolation) causes ALL 4160 V switchgear (1TC, 1TD, and 1TE) to de-energize.
Which ONE of the following describes the response of Keowee switchgear power supplies?
A. 1X switchgear de-energizes and then is restored 15 seconds later B. 1X switchgear de-energizes and then is restored 36 seconds later C. 2X switchgear de-energizes and then is restored 15 seconds later D. 2X switchgear de-energizes and then is restored 36 seconds later Page 48 of 75
Oconee Nuclear Station Question: 49 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
1SA-04/E-6 (125 Volt Ground Trouble) actuates
- 1) 1SA-04/E-6 ARG directs the Operator to __ (1) __ to determine if the ground is on the battery or the Bus.
- 2) 1SA-04/E-6 actuating indicates that the ground is located on __ (2) __.
Which ONE of the following completes the statements above?
A. 1. rotate the Ground Relay Selector Switch
- 2. Unit 1 ONLY B. 1. rotate the Ground Relay Selector Switch
- 2. any Unit C. 1. isolate the battery from the Bus
- 2. Unit 1 ONLY D. 1. isolate the battery from the Bus
- 2. any Unit Page 49 of 75
Oconee Nuclear Station Question: 50 ILT 47 ONS RO NRC Examination (1 point)
Given the following plant conditions:
Operators are preparing to synchronize KHU-2 to the grid OP/0/A/1106/019, (Keowee Hydro At Oconee) in progress Grid Frequency = 60.3 cycles Keowee Frequency = 59.9cycles Keowee 2 Line Volts = 13.8 kV Keowee 2 Output Volts = 13.8 kV
- 1) KHU Unit 2 __ (1) __ must be adjusted prior to closing ACB-2 .
- 2) Procedural requirements for Keowee Output Volts are provided to ensure acceptable
__(2)__ when ACB-2 is closed.
Which ONE of the following completes the statements above?
A. 1. Auto Voltage Adjuster
- 2. MVARs B. 1. Speed Changer Motor
- 2. MVARs C. 1. Auto Voltage Adjuster
- 2. MWs D. 1. Speed Changer Motor
- 2. MWs Page 50 of 75
Oconee Nuclear Station Question: 51 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor in MODE 5 RB Purge is in progress Reactor Building Airborne activity is increasing .
RM Reactor BLDG Purge Disch RAD Inhibit will occur ____(1)____ and will close
____(2)____.
Which ONE of the following completes the statement above?
A. 1. prior to the switchover from 1RIA-45 to 1RIA-46 occurring
Oconee Nuclear Station Question: 52 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Time = 1200 Reactor power = 100%
3B MDEFWP switch in AUTO 2 3A MDEFWP switch in AUTO 1 for testing Time = 1201 BOTH Main Feedwater pumps trip 3MS-87 (MS to TDEFDWP Control) fails closed
- 1) The 3A MD EFDW pump ____(1)____ be operating.
- 2) The TD EFDW pump ____(2)____ be operating.
Which ONE of the following completes the statements above at time = 1202 assuming NO operator actions?
A. 1. will
- 2. will B. 1. will
- 2. will NOT C. 1. will NOT
- 2. will D. 1. will NOT
- 2. will NOT Page 52 of 75
Oconee Nuclear Station Question: 53 ILT 47 ONS RO NRC Examination (1 point)
During normal operation of the CC system
- 1) CC flow through each letdown cooler is maintained at ____(1)____ gpm.
- 2) If letdown flow were increased, CC outlet temperature on the in-service CC cooler would be maintained by ____(2)____ operation of the associated LPSW valve.
Which ONE of the following completes the statements above?
A. 1. 200 gpm
- 2. manual B. 1. 200 gpm
- 2. automatic C. 1. 400 gpm
- 2. manual D. 1. 400 gpm
- 2. automatic Page 53 of 75
Oconee Nuclear Station Question: 54 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
Instrument Air Pressure decreasing AP/22 (Loss of Instrument Air) initiated Current conditions:
Instrument Air pressure = 63 psig decreasing
- 1) A reactor trip ____(1)____required at this time per AP/22.
- 2) When air is lost to the Main Feedwater Control valves, they fail ____(2)____.
Which ONE of the following completes the statements above?
A. 1. is
- 2. open B. 1. is
- 2. as is C. 1. is NOT
- 2. open D. 1. is NOT
- 2. as is Page 54 of 75
Oconee Nuclear Station Question: 55 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0805 Reactor in MODE 6 Fuel offload is in progress Reactor Building Normal Sump (RBNS) is being pumped A fuel assembly is dropped Time = 0809 A High Radiation Annunciator in the Control Room alarms The Reactor Building Normal Sump has failed to isolate AP/9 SPENT FUEL DAMAGE is initiated
- 1) 1RIA __(1)__ in HIGH alarm should have caused the RBNS isolation.
- 2) If the RB Normal sump isolation valves are the last open penetrations to be closed and are closed at 0830, the criteria for isolating open penetrations per AP/9 __(2)__
been met.
Which ONE of the following completes the statements above?
A. 1. 4 (Reactor Building Entrance)
- 2. has B. 1. 4 (Reactor Building Entrance)
- 2. has NOT C. 1. 49 (RB Gas)
- 2. has D. 1. 49 (RB Gas)
- 2. has NOT Page 55 of 75
Oconee Nuclear Station Question: 56 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 80%
1B1 RCP trips
- 1) The ICS will initiate a unit runback at __ (1) __%/minute.
- 2) When the runback is complete, reactor power will be approximately __ (2) _%.
Which ONE of the following completes the statements above?
A. 1. 20
- 2. 65 B. 1. 20
- 2. 74 C. 1. 25
- 2. 65 D. 1. 25
- 2. 74 Page 56 of 75
Oconee Nuclear Station Question: 57 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 0800 Reactor power = 100%
NR RCS pressure Channel B has failed high Time = 0801 NR RCS pressure Channel E fails high
- 2) The reactor ____(2)____ receive a High RCS Pressure trip signal.
Based on the plant conditions at 0801, complete the above statements.
(Assume NO operator actions)
A. 1. will
- 2. will B. 1. will
- 2. will NOT C. 1. will NOT
- 2. will D. 1. will NOT
- 2. will NOT Page 57 of 75
Oconee Nuclear Station Question: 58 ILT 47 ONS RO NRC Examination (1 point)
The C LPSW Pump is normally powered from __(1)__ and it __(2)__ have an alternate supply from another unit.
A. 1. 1TC
- 2. does B. 1. 1TC
- 2. does NOT C. 1. 2TC
- 2. does D. 1. 2TC
- 2. does NOT Page 58 of 75
Oconee Nuclear Station Question: 59 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 80%
1A TBVs (1MS-22 and 1MS-19) fail open When the plant stabilizes from the event, the 1A SG level will be __(1)__ the pre-transient level and the plant MWe output will be __(2)__ the initial output .
Which ONE of the following completes the statement above?
A. 1. the same as
- 2. the same as B. 1. the same as
- 2. lower than C. 1. higher than
- 2. the same as D. 1. higher than
- 2. lower than Page 59 of 75
Oconee Nuclear Station Question: 60 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
The operating CSAE malfunctions Condenser vacuum = 24.5 slowly decreasing AP/27 (Loss Of Condenser Vacuum) has been initiated Vacuum Pumps have been started In accordance with AP/27, which ONE of the following states:
- 1) the MINIMUM vacuum that the Main Vacuum Pump must be pulling prior to opening its inlet valves?
- 2) the consequences if the above criteria is violated?
A. 1. 20 Hg Vacuum
- 2. The loss of vacuum may worsen B. 1. 20 Hg Vacuum
- 2. The vacuum pump seal may be lost resulting in damage to the pump C. 1. 24 Hg Vacuum
- 2. The loss of vacuum may worsen D. 1. 24 Hg Vacuum
- 2. The vacuum pump seal may be lost resulting in damage to the pump Page 60 of 75
Oconee Nuclear Station Question: 61 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Time = 1200:00 Reactor power = 80% stable 1A and 1B CBP operating Time = 1201:00 1A CBP trips Feedwater Pump suction pressure = 225 psig slowly decreasing Time = 1203:00 Feedwater Pump suction pressure = 220 slowly increasing Which ONE of the following describes the:
- 1) runback rate (%/min) inserted at Time = 1201:00 to ICS?
- 2) procedure that will be directed by the CRS at Time = 1203:00?
A. 1. 15
- 2. AP/1/A/1700/001 (Unit Runback)
B. 1. 15
- 2. EOP C. 1. 20
- 2. AP/1/A/1700/001 (Unit Runback)
D. 1. 20
- 2. EOP Page 61 of 75
Oconee Nuclear Station Question: 62 ILT 47 ONS RO NRC Examination (1 point)
Unit 1 plant conditions:
A gaseous waste release at 1/3 station limit is being performed
- 1) The Alert and High setpoints for ____(1)____ are based on this limit.
- 2) If the High alarm setpoint is reached on ____(2)____, the gaseous waste release will be automatically terminated.
Which ONE of the following completes the statements above?
A. 1. 1RIA-38
- 2. 1RIA-45 Page 62 of 75
Oconee Nuclear Station Question: 63 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
An area radiation monitor is being checked per PT/0/A/0230/001 When performing the source check, the RIA reading ____(1)____ increase and the Process Monitor Fault Alarm ____(2)____be received.
Which ONE of the following completes the statements above?
A. 1. should
- 2. should B. 1. should
- 2. should NOT C. 1. should NOT
- 2. should D. 1. should NOT
- 2. should NOT Page 63 of 75
Oconee Nuclear Station Question: 64 ILT 47 ONS RO NRC Examination (1 point)
Given the following conditions:
Time = 0400 IA header develops a leak The maximum IA header pressure where SA-141, SA to IA Controller will be open is
____psig .
Which ONE of the following completes the statement above?
A. 95 B. 93 C. 90 D. 85 Page 64 of 75
Oconee Nuclear Station Question: 65 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial Conditions:
Time = 1200 Power escalation in progress Core Thermal Power = 50% slowly increasing NI Power = 52% slowly increasing Current Conditions:
Time = 1400 Core Thermal Power = 60% slowly increasing
- 1) At Time = 1200 NIs are considered __(1)__.
- 2) As a result of changes in RCS temperature, at Time = 1400 NIs will be __(2)__
than 2% different than Core Thermal Power.
Which ONE of the following completes the statements above?
A. 1. conservative
- 2. less B. 1. conservative
- 2. greater C. 1. non-conservative
- 2. less D. 1. non-conservative
- 2. greater Page 65 of 75
Oconee Nuclear Station Question: 66 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 plant conditions:
0800:
Reactor Power = 100%
1SA2/A12, ICS TRACKING is received Plant transient response is performed ICS is taken to HAND 0804:
The plant is declared stable Exiting Transient Annunciator Response is announced by the CRS In accordance with AD-OP-ALL-1000 (Conduct of Operations)
- 1) At 0800, the CRS __(1)__ required to announce Implementing Transient Annunciator Response in order to suspend normal annunciator response protocol.
- 2) At 0804, ARGs for ____(2)____ are required to be reviewed.
Which ONE of the following completes the statements above?
A. 1. is
- 2. ONLY statalarms that remain lit B. 1. is
- 2. ALL statalarms that were received during the transient C. 1. is NOT
- 2. ONLY statalarms that remain lit D. 1. is NOT
- 2. ALL statalarms that were received during the transient Page 66 of 75
Oconee Nuclear Station Question: 67 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Time = 1200 LDST level = 75 inches decreasing LDST pressure = 35 psig slowly decreasing Which ONE of the following describes the:
- 1) status of the HPI system at Time = 1200?
- 2) required action in accordance with OP/1108/001 (Curves and General Information)?
REFERENCE PROVIDED A. 1. Operable
- 2. Initiate makeup to LDST B. 1. Operable
- 2. Depressurize LDST C. 1. Inoperable
- 2. Initiate makeup to LDST D. 1. Inoperable
- 2. Depressurize LDST Page 67 of 75
Oconee Nuclear Station Question: 68 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
RCS pressure = 525 psig stable An attempt is made to open 1LP-1 (LPI RETURN BLOCK FROM RCS)
- 1) 1LP-1 __ (1) __ open.
- 2) The reason 1LP-1 has an interlock is to __ (2) __.
Which ONE of the following completes the statements above?
A. 1. will
- 2. prevent over pressurizing LPI suction piping B. 1. will
- 2. ensure delta p across 1LP-1 will allow it to open C. 1. will NOT
- 2. prevent over pressurizing LPI suction piping D. 1. will NOT
- 2. ensure delta p across 1LP-1 will allow it to open Page 68 of 75
Oconee Nuclear Station Question: 69 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 3 conditions:
Reactor power = 100%
3RC-1 has failed OPEN 3RC-3 will NOT close RCS pressure continues to decrease Which ONE of the following describes the Reactor Coolant Pump(s) that will be INITIALLY secured after the Reactor has been Manually tripped in accordance with AP/3/A/1700/044 (Abnormal Pressurizer Pressure Control)?
A. 3B1 ONLY B. 3B1 AND 3B2 C. 3A1 ONLY D. 3A1 AND 3A2 Page 69 of 75
Oconee Nuclear Station Question: 70 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power is being reduced from 100% to 88% in order to perform surveillance testing OP/1/A/1102/004 (Operation at Power), Enclosure 4.2 (Power Reduction) is in progress
- 1) The SOC ____(1)____ required to be notified.
- 2) The E Heater Drain Pumps ____(2)____ required to be secured.
Which ONE of the following completes the above statements for the power reduction?
A. 1. is
- 2. are B. 1. is
- 2. are NOT C. 1. is NOT
- 2. are D. 1. is NOT
- 2. are NOT Page 70 of 75
Oconee Nuclear Station Question: 71 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
An AO is to valve out the 1A Seal Supply filter Anticipated dose rate alarms were briefed by RP
- 1) Based on the RWP and the Plan View, the maximum time below that can be taken to perform this task per PD-RP-ALL-0001, Radiation Worker Responsibilities before the AO is expected to exit the area is __ (1) __ minutes.
- 2) Upon receipt of a second dose rate alarm that was anticipated and previously briefed, the AO __ (2) __.
Which ONE of the following completes the statement above?
REFERENCE PROVIDED A. 1. 21
- 2. may continue to work B. 1. 21
- 2. must immediately exit the area C. 1. 27
- 2. may continue to work D. 1. 27
- 2. must immediately exit the area Page 71 of 75
Oconee Nuclear Station Question: 72 ILT 47 ONS RO NRC Examination (1 point)
Given the following Plant conditions:
Spent Fuel Storage Cask has been dropped in Unit 1&2 SFP Spent Fuel damage is visible RIA-6 and RIA-41 HIGH alarm actuates Spent Fuel Pool level = -3.5 feet decreasing Which ONE of the following describes the
- 1) RB Purge filters that will be used to reduce off site releases
- 2) status of any SF Pumps that were in operation at the time of the event?
A. 1. Unit 1
- 2. ON B. 1. Unit 1
- 2. OFF C. 1. Unit 2
- 2. ON D. 1. Unit 2
- 2. OFF Page 72 of 75
Oconee Nuclear Station Question: 73 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Both Main Feedwater pumps trip Current conditions:
REACTOR TRIP pushbutton has been depressed Reactor power = 4% slowly decreasing Which ONE of the following describes the NEXT action required in accordance with EOP Immediate Manual Actions?
A. Perform Rule 1 (ATWS)
B. Manually insert control rods C. Verify RCP seal injection available D. Depress the Turbine TRIP pushbutton Page 73 of 75
Oconee Nuclear Station Question: 74 ILT 47 ONS RO NRC Examination (1 point)
Given the following Unit 1 conditions:
Reactor power = 100%
1SA3/B6 (FIRE ALARM) actuated Fire Alarm panel indication o point 0202071 (Unit 1 pipe trench room 348 North End) actuated o point 0202072 (Unit 1 pipe trench room 348 East Side) actuated RP/0/A/1000/029 Fire Brigade Response is in progress
- 1) MERT will be dispatched to the area ____(1)____.
- 2) Per RP/0/A/1000/029, if water is to be used for extinguishing the fire, a transformer mulsifyre is activated or a fire hydrant is opened to ____(2)____.
Which ONE of the following completes the statements above?
A. 1. at the same time as the fire brigade
- 2. ensure HPSW pump minimum flow requirements are met B. 1. at the same time as the fire brigade
- 2. mitigate the pressure surge from any water hammer event that occurs upon HPSW pump start C. 1. ONLY after the fire is confirmed
- 2. ensure HPSW pump minimum flow requirements are met D. 1. ONLY after the fire is confirmed
- 2. mitigate the pressure surge from any water hammer event that occurs upon HPSW pump start Page 74 of 75
Oconee Nuclear Station Question: 75 ILT 47 ONS RO NRC Examination (1 point)
- 1) The on-site emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated is the __ (1) __.
- 2) The minimum level of emergency classification that always requires activation of the TSC and OSC is a(n) __ (2) __
Which ONE of the following completes the statements above?
A. 1. Technical Support Center (TSC)
- 2. Alert B. 1. Technical Support Center (TSC)
- 2. Unusual Event C. 1. Operations Support Center (OSC)
- 2. Alert D. 1. Operations Support Center (OSC)
- 2. Unusual Event Page 75 of 75
Examination KEY for: ILT 47 ONS RO NRC Examin Question Answer Number 1 A 2 C 3 B 4 D 5 D 6 A 7 D 8 D 9 A 10 C 11 A 12 B 13 A 14 B 15 D 16 D 17 D 18 C 19 D 20 A 21 B 22 C 23 D 24 A 25 D Printed 5/14/2015 10:10:12 AM Page 1 of 3
Examination KEY for: ILT 47 ONS RO NRC Examin Question Answer Number 26 A 27 B 28 B 29 C 30 C 31 B 32 B 33 A 34 C 35 A 36 B 37 B 38 D 39 D 40 B 41 C 42 C 43 B 44 A 45 D 46 D 47 D 48 A or C 49 D 50 B Printed 5/14/2015 10:10:14 AM Page 2 of 3
Examination KEY for: ILT 47 ONS RO NRC Examin Question Answer Number 51 A 52 C 53 B 54 B 55 C 56 D 57 B 58 D 59 B 60 C 61 D 62 A or C 63 D 64 D 65 A 66 C 67 D 68 C 69 B 70 B 71 A 72 D 73 D 74 A 75 A Printed 5/14/2015 10:10:14 AM Page 3 of 3
Reference List for: ILT 47 ONS RO NRC Examination AP 43 Encl 5.1 Generator Capability Curve OP/0/A/1108/001 .39 (page 1 only with action notes removed)
Plan View RWP 23 Printed 5/14/2015 10:16:44 AM
Page 1 of 1 Enclosure 5.1 AP/0/A/1700/043 SSF Risk Areas Page 1 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. __ Determine from dispatched operator if fire is in SSF RISK AREA by using table below:
SSF Risk Area Affected Units Cross-Hatched Areas in TB Refer to Page 3 of this 3rd Floor enclosure.
Cross-Hatched Areas in TB Refer to Page 5 of this Basement enclosure.
Enclosure 5.1 AP/0/A/1700/043 SSF Risk Areas Page 2 of 5 THIS PAGE INTENTIONALLY BLANK
Enclosure 5.1 AP/0/A/1700/043 SSF Risk Areas Page 3 of 5 Turbine Building 3rd Floor NORTH 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 B B C C D D E E F F G G H H J J K K L L M M 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 LEGEND SSF RISK AREA SSF RISK AREA ALL 3 UNITS UNIT 3 Fire plan 796.des Rev. 0 11/18/06 RTR 7312
Enclosure 5.1 AP/0/A/1700/043 SSF Risk Areas Page 4 of 5 THIS PAGE INTENTIONALLY BLANK
Enclosure 5.1 AP/0/A/1700/043 SSF Risk Areas Page 5 of 5 Turbine Building Basement NORTH B HPSW PUMP ROOM (NOT PART OF U2 SSF RISK AREA)
Enclosure 5.1 AP/1/A/1700/034 Generator Capability Page 1 of 3 Curve
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Duke Energy Procedure No.
Oconee Nuclear Station 0 OP/ /A/1108/001 CURVES AND GENERAL INFORMATION Revision No.
109 Electronic Reference No.
OX002VHZ Reference Use PERFORMANCE
- * * * * * * * *
- UNCONTROLLED FOR PRINT * * * * * * * * * *
(ISSUED) - PDF Format
OP/0/A/1108/001 Page 2 of 4
- 1. Purpose 1.1 To provide various tank, system, and concentration curves along with general information necessary for the efficient operation of the plant.
- 2. Limits and Precautions 2.1 None
- 3. Procedure 3.1 Refer to various listed enclosures as required.
- 4. Enclosures 4.1 BHUT Volume Vs. Level Curve {31}
4.2 CBAST Volume Vs. Level Curve (All Units) 4.3 GWD Tank Volume Vs. Pressure Curve (A, B, 3A, 3B) 4.4 GWD Tank Volume Vs. Pressure Curve (C, D, 3C) 4.5 HAWT Volume Vs. Level Curve (Unit 1&2 And Unit 3) 4.6 LAWT Volume Vs. Level Curve (Unit 1&2 And Unit 3) 4.7 Unit 1&2 MWHUT Volume Vs. Level Curve 4.8 Unit 3 MWHUT Volume Vs. Level Curve 4.9 Hotwell Volume Vs. Level Curve (All Units) 4.10 UST Volume Vs. Level Curve (All Units) 4.11 Unit 1&2 RCW Storage Tank Volume Vs. Level Curve 4.12 Unit 3 RCW Storage Tank Volume Vs. Level Curve 4.13 Turbine Oil Storage Tank Volume Vs. Level Curve (All Units) 4.14 Boric Acid Solubility In Water Curve 4.15 CBAST Concentration Vs. Level Curve (All Units) 4.16 Laundry And Hot Shower Tank Volume Vs. Level Curve (All Units) 4.17 Evaluation For Removal Of Statalarms/Control Room Indications {28}
4.18 CSAE Blower Head Curve
OP/0/A/1108/001 Page 3 of 4 4.19 Deborating IX Capacity For Saturation Of Demineralizer 4.20 Compartment Identification Of 600/208 VAC Motor Control Centers 4.21 ICS Schematic 4.22 SG Level Ranges 4.23 Unit 1 Mechanical RB Penetrations (East And West) 4.24 Unit 2&3 Mechanical RB Penetrations (East And West) 4.25 Expected Feedwater Flow Per Header Vs. Reactor Power 4.26 Miscellaneous Data 4.27 Instructions For Adjusting Alarm Setpoints On The NI Recorder 4.28 Unit 1 Core Map 4.29 Unit 2 Core Map 4.30 Unit 3 Core Map 4.31 Unit 1 RCS Heatup/Cooldown Curves 4.32 Unit 2 RCS Heatup/Cooldown Curves 4.33 Unit 3 RCS Heatup/Cooldown Curves 4.34 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve (DELETED- moved to OP/0/A/1108/001 B (Spent Fuel Pool Level Vs. Temperature Curves) 4.35 Combined Inventory For Emergency Feedwater Curve 4.36 Site Assembly Alarm Test 4.37 Emergency Power Switching Logic (EPSL) 4.38 Condenser Flow And Temperature Data 4.39 LDST Pressure Vs. Level (All Units) 4.40 ESV System Vacuum Requirements 4.41 CCW Discharge Local Temperature Data 4.42 Not Used 4.43 Not Used 4.44 RCS Boron Changes Due To Letdown Temperature Changes
OP/0/A/1108/001 Page 4 of 4 4.45 RCS Instrumentation 4.46 Total Loss Of DHR Time To Boil (DELETED- moved to OP/0/A/1108/001 A (Reactor Core And SFP Loss Of Cooling Heatup Tables) 4.47 Maximum SFP Temperature Vs. Total SFC System Flow 4.48 Appendix
Enclosure 4.1 OP/0/A/1108/001 BHUT Volume Vs. Level Curve Page 1 of 1 90,000 80,000 70,000 Volume of Liquid in Tank (VBHUT) [gal]
60,000 50,000 NOTE: Bleed Transfer Pump trips at 15" 40,000 indicated level (29" actual level). {10}
30,000 20,000 10,000 0
0 20 40 60 80 100 120 140 160 180 200 Indicated Level of Liquid in Tank (LBHUT) [in]
BHUT Rev 4 (Final).xlsx (OSC-7129 Rev. 4)
Enclosure 4.2 OP/0/A/1108/001 CBAST Volume Vs. Level Curve (All Units) {30} Page 1 of 1 CBAST Volume Vs. Level 23 22 21 20 19 18 17 16 15 14 13 GALLONS 12 (THOUSANDS) 11 10 9
8 7
6 5
4 3
2 1
0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 LEVEL (INCHES)
CBAST lvl vs vol curve rev 0.xlsx
Enclosure 4.3 OP/0/A/1108/001 GWD Tank Volume Vs. Pressure Curve (A, B, 3A, 3B) Page 1 of 1 Gwd tank 1.des
Enclosure 4.4 OP/0/A/1108/001 GWD Tank Volume Vs. Pressure Curve (C, D, 3C) Page 1 of 1 Gwd tank 2.des
Enclosure 4.5 OP/0/A/1108/001 HAWT Volume Vs. Level Curve (Unit 1&2 And Unit 3) Page 1 of 1 HAWT rev 1.des rtr7312 4 23 13
Enclosure 4.6 OP/0/A/1108/001 LAWT Volume Vs. Level Curve (Unit 1&2 And Unit 3) Page 1 of 1 LAWT rev 1.des rtr7312 4 23 13
Enclosure 4.7 OP/0/A/1108/001 Unit 1&2 MWHUT Volume Vs. Level Curve Page 1 of 1 1_2 mwhut.des
Enclosure 4.8 OP/0/A/1108/001 Unit 3 MWHUT Volume Vs. Level Curve Page 1 of 1 3 mwhut.des
Enclosure 4.9 OP/0/A/1108/001 Hotwell Volume Vs. Level Curve (All Units) Page 1 of 1 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 70 70 60 60 50 50 LEVEL, INCHES (COMPUTER READOUT) 40 40 30 30 20 20 10 10 HOTWELL MAY CONTAIN AS MUCH AS 14,000 GALLONS WHEN COMPUTER READOUT INDICATES "0" INCHES 0 0
-6 -6 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 VOLUME, GALLONS X 1000 Hotwell Lvl vs Volume rev 2.des 05/21/08 rtr7312
Enclosure 4.10 OP/0/A/1108/001 UST Volume Vs. Level Curve (All Units) Page 1 of 1 0 1 2 3 4 5 6 7 8 9 10 11 12 80,000 80,000 70,000 70,000 60,000 60,000 COMBINED VOLUME OF BOTH USTs, ONE UNIT 50,000 50,000 VOLUME, GALLONS 40,000 40,000 30,000 30,000 20,000 20,000 10,000 10,000 0 0 0 1 2 3 4 5 6 7 8 9 10 11 12 LEVEL, FEET USTCRV.TCW
Enclosure 4.11 OP/0/A/1108/001 Unit 1&2 RCW Storage Tank Volume Vs. Level Curve Page 1 of 1 1_ 2 rcw tnk.des
Enclosure 4.12 OP/0/A/1108/001 Unit 3 RCW Storage Tank Volume Vs. Level Curve Page 1 of 1 3 rcw tnk.des
Enclosure 4.13 OP/0/A/1108/001 Turbine Oil Storage Tank Volume Vs. Level Curve (All Units) Page 1 of 1 to stg tnk.des
Enclosure 4.14 OP/0/A/1108/001 Boric Acid Solubility In Water Curve Page 1 of 1 ba sol.bmp
Enclosure 4.15 OP/0/A/1108/001 CBAST Concentration Vs. Level Curve (All Units) Page 1 of 1 CBAST Concentration vs Level Curve - All Units 16000 15500 15000 14500 14000 13500 CBAST Concentration, ppm boron Operable Range 13000 Operating Guidelines:
10,000 - 14,500 ppm boron, normally 12500 >13,000 ppm boron prior to RFO {6}
Inoperable Range 12000 11500 11000 10500 10000 9500 9000 8500 8000 0 10 20 30 40 50 60 70 80 90 100 110 120 130 CBAST Level, inches Source: ONTC-0-106A-001-001 rev.0
Enclosure 4.16 OP/0/A/1108/001 Laundry And Hot Shower Tank Volume Vs. Level Curve (All Units) Page 1 of 1 LAUNDRY & HOT SHOWER TANKS A & B LEVEL VS. VOLUME UNITS 1,2,3 6000 FULL CAPACITY = 5,513 GAL OR 101.75 INCHES OF TANK HEIGHT 5000 VOLUME OF TANK (GALLONS) [GAL]
4000 3000 2000 1000 0
0 10 20 30 40 50 60 70 80 90 100 110 LEVEL OF TANK (INCHES) [IN]
Enclosure 4.17 OP/0/A/1108/001 Evaluation For Removal Of Page 1 of 4 Statalarms/Control Room Indications {28}
- 1. Initial Conditions 1.1 Plant component failure or plant conditions have occurred such that it is necessary to remove a Statalarm window from service, or identify a Control Room indication as out of service.
- 2. Limits And Precautions 2.1 The implications of loss of alarm and Control Room indication functions must be fully evaluated and understood by Control Room personnel.
2.2 EACH alarm card in BETALARM panel (3SA-19 and all alarm panels in the SSF Control Room) powers two (2) alarm windows. An alarm test must be performed to verify which two alarms will be silenced by pulling the card. Both alarms should be evaluated for safety impact before leaving the card pulled. {27}
- 3. Procedure (Removal) 3.1 Complete the following steps for the Statalarm/Control Room indication to be removed from service:
_____ 3.1.1 Name of Statalarm/Control Room Indicator:
_____ 3.1.2 Identify the reason for removal (equipment malfunction, nuisance alarm, multiple inputs with no reflash, etc.):
_____ 3.1.3 List any safety-related equipment affected by the removal of this statalarm/indicator:
_____ 3.1.4 List any applicable TS and/or SLCs:
_____ 3.1.5 List alternate monitoring (if required):
_____ 3.1.6 IF applicable generate a WR for equipment being removed from service:
WR # : ________________ (For Control Room statalarms, designate as CRIP)
_____ 3.1.7 Perform a review of the statalarm/Control Room indicator to determine the CRS acceptability of removal from service. Resources may include, but are not limited to, the following: TS, SLC, ARG, OP, AP, EOP, and Ops Guides.
Enclosure 4.17 OP/0/A/1108/001 Evaluation For Removal Of Page 2 of 4 Statalarms/Control Room Indications {28}
_____ 3.1.8 Determine if evaluation is needed by Engineering and/or Operations CRS Procedures Group for the affected component; generate PIP as required.
Engineering Contact (if applicable): ________________________________
OPS Procedure Group Contact_____________________________________
3.1.9 Removal prepared by:
________________________ _____/_____
(CRS/RO) Date Time 3.1.10 Removal approved by:
________________________ _____/_____
(CRS) Date Time NOTE: EACH alarm card in BETALARM panel (3SA-19 and all alarm panels in the SSF Control Room) powers two (2) alarm windows. An alarm test must be performed to verify which two alarms will be silenced by pulling the card. Both alarms should be evaluated for safety impact before leaving the card pulled. {27}
CAUTION: While Statalarm panel is open, energized electrical conductors that supply alarm lights are exposed.
3.2 Complete the following removal steps for the affected Statalarm/Control Room Indicator:
_____ 3.2.1 IF removal of a Statalarm requires pulling a statalarm card, perform the following:
_____ A. Identify statalarm card number and record: _______________
_____ B. Remove all jewelry and watches and wear safety glasses before removing statalarm card.
_____ C. Make determination as to which alarm card is to be pulled, and pull selected card.
_____ D. Perform statalarm panel test on affected panel to verify correct card has been pulled.
Enclosure 4.17 OP/0/A/1108/001 Evaluation For Removal Of Page 3 of 4 Statalarms/Control Room Indications {28}
3.2.2 IF a statalarm card is pulled, OR a multiple input statalarm with no reflash capability is "Locked In" perform the following:
_____ Add removed statalarm to the "Out of Normal Alarms" section of the Unit Turnover Sheet or AO Turnover Sheet.
_____ Place a "T/O Sheet" or "CBWO" status label on the statalarm window.
3.2.3 IF removing a Control Room indication from service perform the following for _______________________________ (identify Control Room indication):
_____ A. Add the Out Of Service indicator to the "Equipment Deficiencies" section of Unit Turnover Sheet.
_____ B. Place an "OOS/I&E" plant status label on the indicator.
_____ 3.3 IF alternate monitoring is required:
_____ Add affected statalarm/indication to "Additional Monitoring" section of Unit Turnover Sheet or AO Turnover Sheet.
_____ IF not performed in Step 3.2.2, place a "T/O Sheet" plant status label on the statalarm window.
_____ 3.4 Place this enclosure in the "Alarm Status" section of respective unit "PT/600/001 Working Copy" notebook.
Enclosure 4.17 OP/0/A/1108/001 Evaluation For Removal Of Page 4 of 4 Statalarms/Control Room Indications {28}
- 4. Restoration CAUTION: While Statalarm panel is open, energized electrical conductors that supply alarm lights are exposed.
4.1 WHEN notified that the statalarm/Control Room indicator is ready to be returned to service, perform the following:
_____ 4.1.1 IF restoring a statalarm to service requires reinserting a statalarm card, perform the following:
_____ A. Identify statalarm card number and record: _______________
_____ B. Remove all jewelry and watches and wear safety glasses before installing cards.
_____ C. Make determination as to which alarm card is to be inserted, and insert selected card.
_____ D. Perform statalarm panel test on affected panel to verify the statalarm has been returned to service.
_____ 4.1.2 IF Step 3.2.2 was performed, perform the following as required:
_____ A. Delete restored statalarm from the "Out of Normal Alarms" section of the Unit Turnover Sheet or AO Turnover Sheet.
_____ B. Remove the "T/O Sheet" or "CBWO" status label from the statalarm window.
_____ 4.1.3 IF restoring a Control Room indication to service perform the following for
_____________________________ (identify Control Room indication):
_____ A. Delete the Out Of Service indicator from the "Equipment Deficiencies" section of Unit Turnover Sheet
_____ B. Remove the "OOS/I&E" plant status label from the indicator.
_____ 4.2 IF alternate monitoring was required:
_____ Delete the affected statalarm/indication from the "Additional Monitoring" section of Unit Turnover Sheet or AO Turnover Sheet.
_____ Remove the "T/O Sheet" plant status label from the statalarm window.
_____ 4.3 Complete the enclosure coversheet and forward to Shift Clerk for processing.
Enclosure 4.18 OP/0/A/1108/001 CSAE Blower Head Curve Page 1 of 1 60 59 58 57 56 55 54 Inches of H 2O 53 52 51 50 49 48 47 46 45 100 150 200 250 300 350 SCFM
Enclosure 4.19 OP/0/A/1108/001 Deborating IX Capacity For Saturation Of Demineralizer {29} Page 1 of 1 Curve file located at \\onsfs00\dwgs\Boron curves for op 0 a 1108 001 rev. 107.doc
Enclosure 4.20 OP/0/A/1108/001 Compartment Identification Of 600/208 VAC Page 1 of 1 Motor Control Centers Notes:
- 1. Front of MCC is 600 VAC side; determined by location of incoming feeder breaker. Compartments are numbered from left to right, lettered vertically, one letter for each breaker.
- 2. Rear of MCC is 208 VAC side; compartments are numbered from right to left, lettered vertically, one letter for each breaker.
FRONT, 600 VAC (TYPICAL)
REAR, 208 VAC (TYPICAL)
ELECPNL.TCW Rev. 1 11/15/99 rtr
Enclosure 4.21 OP/0/A/1108/001 ICS Schematic Page 1 of 3 Unit 1 TRACKING INPUTS TAVE CTP ERROR LOAD LIMITS FDW FLOW GEN MWe THP ERROR T10 RC FLOW (variable) NI FLUX 1.2 RC PUMPS (74%) CTP TAVE ERROR CTP BEST BEST < >
FDW PUMPS (65%)
ASY ROD (55%)
BOTH GEN BKRS OPEN (20%) T3 SP CTP CTP MAXIMUM RUNBACK (15%) DEMAND 2250#
RX TRIP (0%) SETPOINT DEMAND RCS OPERATOR S/G PRESS T1 T2 d/dt f(g) MASTER DEMAND H/A
>101%
MANEUVERING RATES THP ERROR FDW RX LOW LEVEL LIMITS 1%/MIN* X f(g) TEMP TAVE ASY ROD 1%/MIN* SP MASTER MAXIMUM RB 20%/MIN H/A SP TRACKING 20%/MIN 2250#
RX CROSS LIMITS RC FLOW 20%/MIN RCS T11 NEUTRON LOW CBP/MFP SUCT PRESS 20%/MIN ERROR +/- 5% NI PRESS BOTH GEN BKRS OPEN 20%/MIN LOSS OF ONE RCP 25%/MIN LOSS OF ONE FWP 25%/MIN X DIAMONDPANEL REACTOR TRIP 600%/MIN IN OUT RC RC CRDMS THP ERROR 1A FDW FLOW FLOW 1B FDW THP SETPOINT A B MASTER RATIO MASTER S/G S/G H/A H/A THP PRESS PRESS TOTAL FDW FLOW TO SP A B T2 Tc 2250# FDW TC FDW H/A SP FLOW FLOW THPERROR RCS SP SP PRESS T7 T7 OPER OPER LEVEL LEVEL TURBINE 125psig Tc FDW VALVE LOAD/UNLOAD SP P SP CONTROLLER 50 psig T8 25" 25" 0 psig SP SU 35 # SU LEVEL T4 T5 LEVEL TURBINE COMPOSITE COMPOSITE THP VALVE DEMAND VALVE DEMAND MASTER CONTROLLER CONTROLLER SP H/A SEQ SEQ SP SP BIAS BIAS EHC 1035# 1035#
SP SP TRANSFERFUNCTIONS T1 LOAD LIMITS OPER OPER LEVEL T6 T6 LEVEL T2 TRACKING T3 FDW CONTROL CORRECTION SELECTOR T4 LO LEVEL LIMIT SELECTOR S/G 'A' 1ATBV 7" Hg 1B TBV 1A MFDW 1A S/U 1A MFWP BIAS 1B S/U FDW 1B MFDW T5 LO LEVEL LIMIT SELECTOR S/G 'B' H/A Vac H/A CONTROL FDW 1B MFWP CONTROL CONTROL CONTROL H/A T6 SU FDW VALVES CONTROL 50% OP LVL H/A H/A H/A H/A H/A T7 TBV CONTROL ERROR SELECTOR T9 T9 T8 TBV OPERATING BIAS MFWP 1A MGU MFWP 1B MGU T9 7" Hg VAC SHUTS TBVs 1A TBV 1B TBV AUX S/DPANEL 1A S/U FDW 1B S/U FDW T10 REACTOR CONTROL CORRECTION SELECTOR H/A H/A CONTROL CONTROL T11 MANEUVERING RATE SELECTION (ASP) (ASP) H/A(ASP) H/A (ASP) U1 ICS.des Rev. 1 rtr 2/15/05
Enclosure 4.21 OP/0/A/1108/001 ICS Schematic Page 2 of 3 Unit 2 TAVE TRACKING INPUTS CTP ERROR LOAD LIMITS FDW FLOW GEN MWe THP ERROR T10 RC FLOW (variable) NI FLUX 1.2 RC PUMPS (74%) CTP TAVE ERROR CTP BEST BEST < >
FDW PUMPS (65%)
ASY ROD (55%)
BOTH GEN BKRS OPEN (20%) T3 SP CTP CTP MAXIMUM RUNBACK (15%) DEMAND 2250#
RX TRIP (0%) SETPOINT DEMAND RCS OPERATOR S/G PRESS T1 T2 d/dt f(g) MASTER DEMAND H/A
>101%
MANEUVERING RATES THP ERROR FDW RX LOW LEVEL LIMITS 1%/MIN* X f(g) TEMP TAVE SP MASTER ASY ROD 1%/MIN* H/A SP MAXIMUM RB 20%/MIN 2250#
TRACKING 20%/MIN RX CROSS LIMITS RC FLOW 20%/MIN T11 RCS NEUTRON LOW CBP/MFP SUCT. PRESS. 20%/MIN PRESS ERROR +/- 5% NI BOTH GEN BKRS OPEN 20%/MIN LOSS OF ONE RCP 25%/MIN X DIAMONDPANEL LOSS OF ONE FWP 25%/MIN REACTOR TRIP 600%/MIN IN OUT RC RC CRDMS THP ERROR A FDW FLOW FLOW B FDW THP SETPOINT A B MASTER RATIO MASTER S/G S/G H/A H/A THP PRESS PRESS TOTAL FDW FLOW TO SP A B T2 Tc 2250# FDW TC FDW H/A SP FLOW FLOW THPERROR RCS SP SP PRESS T7 T7 OPER OPER LEVEL LEVEL TURBINE 125psig Tc FDW VALVE LOAD/UNLOAD SP P SP CONTROLLER 50 psig T8 25" 25" 0 psig SP SU 35 # SU LEVEL T4 T5 LEVEL TURBINE COMPOSITE COMPOSITE THP VALVE DEMAND VALVE DEMAND MASTER CONTROLLER CONTROLLER SP H/A SEQ SEQ SP SP BIAS BIAS EHC 1035# 1035#
SP SP TRANSFERFUNCTIONS T1 LOAD LIMITS OPER OPER LEVEL T6 T6 LEVEL T2 TRACKING T3 FDW CONTROL CORRECTION SELECTOR T4 LO LEVEL LIMIT SELECTOR S/G 'A' A TBV 7" Hg B TBV A MFDW A S/U A MFWP BIAS B S/U FDW B MFDW T5 LO LEVEL LIMIT SELECTOR S/G 'B' H/A Vac H/A CONTROL FDW B MFWP CONTROL CONTROL CONTROL H/A T6 SU FDW VALVES CONTROL 50% OP LVL H/A H/A H/A H/A H/A T7 TBV CONTROL ERROR SELECTOR T9 T9 T8 TBV OPERATING BIAS MFWP A MGU MFWP B MGU T9 7" Hg VAC SHUTS TBVs A TBV B TBV AUX S/DPANEL A S/U FDW B S/U FDW T10 REACTOR CONTROL CORRECTION SELECTOR H/A CONTROL Unit 2 ICS Schematic H/A CONTROL O2ICS0001.des T11 MANEUVERING RATE SELECTION (ASP) (ASP) H/A(ASP) H/A (ASP) rtr 10/26/05 Rev. 1
Enclosure 4.21 OP/0/A/1108/001 ICS Schematic Page 3 of 3 Unit 3 TAVE TRACKING INPUTS CTP ERROR LOAD LIMITS FDW FLOW GEN MWe THP ERROR T10 RC FLOW (variable) NI FLUX 1.2 RC PUMPS (74%) CTP TAVE ERROR CTP BEST BEST < >
FDW PUMPS (65%)
ASY ROD (55%)
BOTH GEN BKRS OPEN (20%) T3 SP CTP CTP MAXIMUM RUNBACK (15%) DEMAND 2250#
RX TRIP (0%) SETPOINT DEMAND RCS OPERATOR S/G PRESS T1 T2 d/dt f(g) MASTER DEMAND H/A
>101%
MANEUVERING RATES THP ERROR FDW RX LOW LEVEL LIMITS 1%/MIN* X f(g) TEMP TAVE SP MASTER ASY ROD 1%/MIN* H/A SP MAXIMUM RB 20%/MIN 2250#
TRACKING 20%/MIN RX CROSS LIMITS RC FLOW 20%/MIN T11 RCS NEUTRON LOW CBP/MFP SUCT. PRESS. 20%/MIN PRESS ERROR +/- 5% NI BOTH GEN BKRS OPEN 20%/MIN LOSS OF ONE RCP 25%/MIN X DIAMONDPANEL LOSS OF ONE FWP 25%/MIN REACTOR TRIP 600%/MIN IN OUT RC RC CRDMS THP ERROR A FDW FLOW FLOW B FDW THP SETPOINT A B MASTER RATIO MASTER S/G S/G H/A H/A THP PRESS PRESS TOTAL FDW FLOW TO SP A B T2 Tc 2250# FDW TC FDW H/A SP FLOW FLOW THP ERROR RCS SP SP PRESS T7 T7 OPER OPER LEVEL LEVEL TURBINE 125psig Tc FDW VALVE LOAD/UNLOAD SP P SP CONTROLLER 50 psig T8 25" 25" 0 psig SP SU 35 # SU LEVEL T4 T5 LEVEL TURBINE COMPOSITE COMPOSITE THP VALVE DEMAND VALVE DEMAND MASTER CONTROLLER CONTROLLER SP H/A SEQ SEQ SP SP BIAS BIAS EHC 1035# 1035#
SP SP TRANSFERFUNCTIONS T1 LOAD LIMITS OPER OPER LEVEL T6 T6 LEVEL T2 TRACKING T3 FDW CONTROL CORRECTION SELECTOR T4 LO LEVEL LIMIT SELECTOR S/G 'A' A TBV 7" Hg B TBV A MFDW A S/U A MFWP BIAS B S/U FDW B MFDW T5 LO LEVEL LIMIT SELECTOR S/G 'B' H/A Vac H/A CONTROL FDW B MFWP CONTROL CONTROL CONTROL H/A T6 SU FDW VALVES CONTROL 50% OP LVL H/A H/A H/A H/A H/A T7 TBV CONTROL ERROR SELECTOR T9 T9 T8 TBV OPERATING BIAS MFWP A MGU MFWP B MGU T9 7" Hg VAC SHUTS TBVs A TBV B TBV AUX S/DPANEL A S/U FDW B S/U FDW T10 REACTOR CONTROL CORRECTION SELECTOR H/A CONTROL Unit 3 ICS Schematic H/A CONTROL O3ICS0001.des T11 MANEUVERING RATE SELECTION (ASP) (ASP) H/A(ASP) H/A (ASP) rtr 4/30/06 Rev. 2
Enclosure 4.22 OP/0/A/1108/001 SG Level Ranges Page 1 of 1 NOTE: SG secondary side contains approximately 41.46 Gal./Inch FORMULAS Full Range (Inches)=Full Range (%) X 6.50 Full Range (%)=Full Range (Inches) 6.50 100% 650" 621" (Upper Tube Sheet) 600" 90%
540" 80%
480" 70%
420" 60% 100% 388" 388" FULL RANGE (%)
360" 90%
80%
50%
EXTENDED STARTUP RANGE OPERATING RANGE 300" 70% 300" 60%
40%
50% 250" 240" 40%
30% 200" 200" 30%
180" STARTUP RANGE 20%
20% 10%
120" 0% 96" 100" 100" 10% 60" 0% 0" 0" 0" NOTE: Lower tap for Full Range, Startup Range, and Extended Startup Range (0" reference level) is 8" above lower tube sheet.
SGLVL RV2.des rtr 1/26/05
Enclosure 4.23 OP/0/A/1108/001 Unit 1 Mechanical RB Penetrations (East And West) {13} Page 1 of 4 (INSIDE RB LOOKING TOWARD E. PENT. RM.)
EMV-1 EMV-2 20 42 41 27 25 45 44 43 El. 828' - 0" (2F)
El. 827' - 0" (2F) 30 60 El. 824' - 0" (2G) 61 46 34 33 32 49 48 3 47 El. 820' - 0" (2G) 31 35 24 23 22 21 15 50 38 El. 816' - 0" (1G) 13 18 9 8 7 6 2 1 El. 812' - 0" (1G) u1 rb east pen.tcw Rev. 1 rtr 2/23/01
Enclosure 4.23 OP/0/A/1108/001 Unit 1 Mechanical RB Penetrations (East And West) {13} Page 2 of 4 (INSIDE E. PENT. RM. LOOKING TOWARD RB)
EMV-2 EMV-1 20 41 42 27 25 43 44 45 El. 828'-0" El. 827'-0" 60 30 61 El. 824'-0" 46 47 3 48 49 32 33 34 El. 820'-0" 31 38 50 21 22 23 24 35 15 El. 816'-0" 1 2 6 7 8 9 18 13 El. 812'-0" Note: 1. Pent. #63 & 64 are not shown on this drawing, u1 east pent Rev 2.tcw but are located near Col. Qa-65 in E. Pent. Rm. rtr 2/6/06
- 2. Changes to this graphic may require changes to AP/1/A/1700/026.
Enclosure 4.23 OP/0/A/1108/001 Unit 1 Mechanical RB Penetrations (East And West) {13} Page 3 of 4 (INSIDE RB LOOKING TOWARD W. PENT. RM.)
19 51 17 16 WMV1 WMV2 El. 816' - 6" El. 816' - 0" El. 816' - 0" (1G)
(1G) 57 39 56 55 4 54 10 14 53 52 El. 812' - 0" 59 58 El. 811' - 6" u1 rb west pen.tcw Rev. 1 rtr 2/23/01
Enclosure 4.23 OP/0/A/1108/001 Unit 1 Mechanical RB Penetrations (East And West) {13} Page 4 of 4 (INSIDE W. PENT. RM. LOOKING TOWARD RB) 16 17 51 19 WMV2 WMV1 El. 816' - 6" El. 816' - 0" El. 816' - 0" 52 53 14 10 54 4 55 56 39 57 El. 812' - 0" 58 59 El. 811' - 6" u1 west pen.tcw Rev. 1 rtr 2/23/01
Enclosure 4.24 OP/0/A/1108/001 Unit 2&3 Mechanical RB Penetrations (East And West) {13} Page 1 of 4 EMV-2 EMV-1 (INSIDE RB LOOKING TOWARD E. PENT. RM.)
20 41 42 25 27 43 44 45 El. 828' - 0" (2F)
El. 827' - 0" (2F) 60 30 61 El. 824' - 0" (2G) 46 47 3 48 49 32 33 34 31 El. 820' - 0" (2G) 38 50 15 21 22 23 24 35 El. 816' - 0" (1G) 1 2 6 7 8 9 18 13 El. 812' - 0" (1G) u2&3 rb east pen.tcw Rev. 1 rtr 2/23/01
Enclosure 4.24 OP/0/A/1108/001 Unit 2&3 Mechanical RB Penetrations (East And West) {13} Page 2 of 4 EMV-1 EMV-2 (INSIDE E. PENT. RM. LOOKING TOWARD RB) 20 42 41 27 25 45 44 43 EL. 828'-0" EL. 827'-0" 30 60 EL. 824'-0" 61 46 34 33 32 49 48 3 47 EL. 820'-0" 31 35 24 23 22 21 15 50 38 EL. 816'-0" 13 18 9 8 7 6 2 1 EL. 812'-0" Note: 1. Pent. #63 & 64 are not shown on this drawing, U2&3 east pen Rev 2.tcw but are located near Col. Qa-81 in U2 E. Pent. Rm. rtr 2/6/06 and near Col. Qa-96 in U3 E. Pent. Rm.
- 2. Changes to this graphic may require changes to AP/2,3/A/1700/026.
Enclosure 4.24 OP/0/A/1108/001 Unit 2&3 Mechanical RB Penetrations (East And West) {13} Page 3 of 4 (INSIDE RB LOOKING TOWARD W. PENT. RM.)
16 17 51 19 WMV2 WMV1 El. 816' - 6" El. 816' - 0" El. 816' - 0" (1G) 52 53 14 10 54 4 55 56 39 57 (1G)
El. 812' - 0" 58 59 El. 811' - 6" u2&3 rb west pen.tcw Rev. 1 rtr 2/23/01
Enclosure 4.24 OP/0/A/1108/001 Unit 2&3 Mechanical RB Penetrations (East And West) {13} Page 4 of 4 (INSIDE W. PENT. RM. LOOKING TOWARD RB) 19 51 17 16 WMV1 WMV2 El. 816' - 6" El. 816' - 0" El. 816' - 0" 57 39 56 55 4 54 10 14 53 52 El. 812' - 0" 59 58 El. 811' - 6" u2&3 west pen.tcw Rev. 0 rtr 2/23/01
Enclosure 4.25 OP/0/A/1108/001 Expected Feedwater Flow Per Header Vs. Reactor Power Page 1 of 1 Fdw flow.des
Enclosure 4.26 OP/0/A/1108/001 Miscellaneous Data Page 1 of 3 NOTE: The values in this enclosure are approximations only. Do not use these numbers to perform calculations other than estimates.
- 1. Lake Keowee Elevation Calculation From Keowee Forebay Elevation Indication (2AB3) {14}
FOREBAY ELEV + 700' = Lake Keowee Level (level above sea level in feet)
- 2. Volume Vs. Level For Various Tanks And SFP Pressurizer 23.94 gal/inch Quench Tank 34.94 gal/inch BWST 7608 gal/foot SFP (Unit 1&2) 1512 gal/ 0.1 foot; 544,000 gal. total at 0 feet (1)
(Unit 3) 1041 gal/ 0.1 foot; 376,000 gal. total at 0 feet (2)
SFP/FTC (Unit 1&2) 2300 gal/inch (3)
(Unit 3) 1907 gal/inch (3)
FTC Deep End 261.8 gal/inch Core Flood Tank 5 gal/ 0.01 foot RB Normal Sump 15 gal/inch BAMT (All Units) 400 gallons + 40 gal/inch; tank contains 400 gallons when level indication is at 0 inches. {5}
LDST (All Units) 677 gallons + 31.3 gal/inch; tank contains 677 gallons when level indication is at 0 inches. (4)
CC Surge Tank Level (All Units) 7.8 gal/inch
References:
- 1. OSC-4998 and drawing 0-155G
- 2. OSC-4776 and drawing 0-2155G
- 3. Drawing 0-58A
- 4. OSC-7129
Enclosure 4.26 OP/0/A/1108/001 Miscellaneous Data Page 2 of 3
- 3. Volume For Various Plant Components {8}
Component Volume (gal)* Reference Letdown Coolers 60 Letdown Filters 60 1,2,3 'A' Seal Return Coolers 36 OM-1201-3217, O-436D, O-436G, O-1436A, O-1436C, 1,2,3 'B' Seal Return Coolers 43 O-2436D, O-2436J Seal Return Filter Bypass 1 Seal Supply Filters 5 Seal Supply Filter Bypass 1 Pzr at 0" 718 OSC 7129 {11}
Pzr Surge Line 163 Total volume with Pzr at 0" 881 U1 and U3 HPI Pump A 75 U1 and U3 HPI Pump B 75 U1 HPI Pump C 136 U3 HPI Pump C 128 2A HPI Pump 113 PIP 10-7606 {25}
2B HPI Pump 105 PIP 10-7606 {25}
2C HPI Pump 132 PIP 10-7606 {25}
U1 Purification IX Bypass Line 12 O-435E & O-435L {9}
U2 Purification IX Bypass Line 4 O-435D & O-435L {9}
Piping between 1CS-89 and 57 3CS-89
- If original volume information provided had fractional value, Volume is rounded up to next whole gallon.
Enclosure 4.26 OP/0/A/1108/001 Miscellaneous Data Page 3 of 3
- 4. Volume For Various Plant Demineralizers Component Volume- Resin Volume- Water Reference (ft3) (gallons)
Unit 1 Purification and Spare 35 650 OP/1/A/1103/004 B Purification IXs Unit 1 Deborating and Spare 60 1200 OP/1/A/1103/004 C Deborating IXs Unit 2 Purification and Spare 35 650 OP/2/A/1103/004 B Purification IXs Unit 2 Deborating and Spare 60 1200 OP/2/A/1103/004 C Deborating IXs Unit 3A and 3B Purification 50 650 OP/3/A/1103/004 B IXs Unit 3A and 3B Deborating 60 1200 OP/3/A/1103/004 C IXs
Enclosure 4.27 OP/0/A/1108/001 Instructions For Adjusting Alarm Setpoints Page 1 of 4 On The NI Recorder
- 1. Procedure 1.1 Setting Chart Alarm Setpoints (Unit 1 & Unit 3; see next page for Unit 2)
- 1. Depress the "Root" key.
- 2. Select "Operator".
- 3. Select "Config".
- 4. Select "Channels" to adjust PR alarms, or "Maths" to adjust SR or WR alarms.
- 5. Select appropriate channel number using combo box.
- 6. Select appropriate alarm number (typically alarm 1 is the high alarm, alarm 2 is the low alarm).
- 7. Select the white threshold box.
- 8. Enter the specified threshold.
- 9. Select "OK".
- 10. Repeat Steps 5 through 9 for all alarm functions as necessary.
- 11. Select "Apply".
- 12. Select "Root" key.
- 13. Using "Goto Group" and "Goto Display", navigate to appropriate group as necessary.
Enclosure 4.27 OP/0/A/1108/001 Instructions For Adjusting Alarm Setpoints Page 2 of 4 On The NI Recorder NOTE: Selection of Source Range and Wide Range NI signals to be viewed on Unit 2 NI recorder will be via switches mounted to left of recorder.
1.2 Setting Chart Alarm Setpoints (Unit 2) {26}
- 1. IF Unit 2 NI Recorder Current Access Level is "Logged Out" as indicated in the top left corner of the display, perform the following:
> Select "Current Access Level Key" (top left corner of chart).
> Select "Operator" from the resulting pick list.
- 2. Depress the "Root" key.
- 3. Select "Operator".
- 4. Select "Config".
- 5. Select "Channels" to adjust PR alarms, or "Maths" to adjust SR or WR alarms.
- 6. Select appropriate channel number using combo box.
- 7. Select appropriate alarm number (typically alarm 1 is the high alarm, alarm 2 is the low alarm).
- 8. Select the white threshold box.
- 9. Enter the specified threshold.
- 10. Select "OK".
- 11. Repeat Steps 5 through 9 for all alarm functions as necessary.
- 12. Select "Apply".
- 13. Select "Root" key.
- 14. Using "Goto Group" and "Goto Display", navigate to appropriate group as necessary.
Enclosure 4.27 OP/0/A/1108/001 Instructions For Adjusting Alarm Setpoints Page 3 of 4 On The NI Recorder 1.3 Changing Chart Scale/Speed
- 1. Select "Root Menu" key.
- 2. Select "Go To View".
- 3. Select "Unit _ NI Flux".
- 4. The top chart is SR and WR on a logarithmic scale.
- 5. The bottom chart is WR and PR on a linear scale.
- 6. The remaining displays show the current value of each channel.
NOTE: Grid decades/divisions are set for the Hi Set. Toggling the Hi/Lo Set may mean the decades/divisions do not match the scale (i.e. the zoomed in span may be three decades, where normal scale is ten decades).
- 7. Select the Hi/Lo Set key at bottom left of chart as desired to toggle between chart scale/speeds for the entire recorder.
Enclosure 4.27 OP/0/A/1108/001 Instructions For Adjusting Alarm Setpoints Page 4 of 4 On The NI Recorder 1.4 History Trend
- 1. Select "Options" key.
- 2. Select "Enter History"-
- Use Slider and Page buttons to scroll in time.
- Note- BLACK background indicates that screen is showing history.
- 3. Select "Options" key.
- 4. Select "Exit History" or select "Root" key to return NI chart.
Enclosure 4.28 OP/0/A/1108/001 Unit 1 Core Map Page 1 of 1 North X
1NI-3 1NI-5 1NI-6 1A HOT 1NI-1 1A 2 CO 1 1A D LD L CO W Y 1 1B 1B D CO 2 L LD CO 1B HOT 1NI-8 1NI-2 1NI-4 1NI-7 Z Unit 1 Core Map Rev 1.des rtr 3/21/11
Enclosure 4.29 OP/0/A/1108/001 Unit 2 Core Map Page 1 of 1 North X
2NI-4 2NI-7 2B HOT 2NI-8 2NI-2 2B 2 CO 1 2B D LD L CO W Y 1 2A 2A D CO 2 L LD CO 2NI-1 2A HOT 2NI-5 2NI-6 2NI-3 Z Unit 2 Core Map Rev 1.des
.rtr 7312 08/20/13
Enclosure 4.30 OP/0/A/1108/001 Unit 3 Core Map Page 1 of 1 North X
3NI-4 3NI-7 3B HOT 3NI-8 3NI-2 3B 2 CO 1 3B D L
LD CO W Y 1 3A 3A D CO 2 L LD CO 3NI-1 3A HOT 3NI-5 3NI-6 3NI-3 Z Unit 3 Core Map Rev 1.des rtr 2/13/12
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 1 of 9 NOTE: If changes are required to curves in this enclosure, the OAC curves must be updated at the same time or the OAC curves must be considered not valid. {1}
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 2 of 9 Notes For Unit 1 Wide Range Cooldown Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When any number of RCPs are running, maintain RCS P/T above and to the left of the 4 RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. When a single RCP in a loop is operating, minimize operating time below the < 4 RC Pump NPSH curve. This limits cumulative damage to the single operating pump caused by cavitation due to required NPSH at high flows.
- 5. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
- 6. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 3 of 9 Unit 1 Wide Range Cooldown Curve Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 4 of 9 Notes For Unit 1 Wide Range Heatup Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When any number of RCPs are running, maintain RCS P/T above and to the left of the 4 RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. When a single RCP in a loop is operating, minimize operating time below the < 4 RC Pump NPSH curve. This limits cumulative damage to operating pump caused by cavitation due to required NPSH needed at high flows.
- 5. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 5 of 9 Unit 1 Wide Range Heatup Curve Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 6 of 9 Notes For Unit 1 Low Range Cooldown Curve
- 1. Curve #1- RCS cooldown limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
- 5. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
< 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 7 of 9 Unit 1 Low Range Cooldown Curve
Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 8 of 9 Notes For Unit 1 Low Range Heatup Curve
- 1. Curve #1- RCS heatup limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
< 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.31 OP/0/A/1108/001 Unit 1 RCS Heatup/Cooldown Curves Page 9 of 9 Unit 1 Low Range Heatup Curve
Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 1 of 9 NOTE: If changes are required to curves in this enclosure, the OAC curves must be updated at the same time or the OAC curves must be considered not valid. {1}
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 2 of 9 Notes For Unit 2 Wide Range Cooldown Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When RCPs are running, maintain RCS P/T above and to the left of the RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
- 5. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 3 of 9 Unit 2 Wide Range Cooldown Curve Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 4 of 9 Notes For Unit 2 Wide Range Heatup Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When RCPs are running, maintain RCS P/T above and to the left of the RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 5 of 9 Unit 2 Wide Range Heatup Curve Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 6 of 9 Notes For Unit 2 Low Range Cooldown Curve
- 1. Curve #1- RCS cooldown limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
- 5. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
- 6. Briefly operating above the LPI pressure curve (#4) or below the RCP NPSH curve (#2) by < 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 7 of 9 Unit 2 Low Range Cooldown Curve
Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 8 of 9 Notes For Unit 2 Low Range Heatup Curve
- 1. Curve #1- RCS heatup limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
- 5. Briefly operating above the LPI pressure curve (#4) or below the RCP NPSH curve (#2) by < 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.32 OP/0/A/1108/001 Unit 2 RCS Heatup/Cooldown Curves Page 9 of 9 Unit 2 Low Range Heatup Curve
- PZR level restricted to < 380 inches when RCS temperature is < 160°F, < 100 psig AND NO HPIPs operating.
Note: PT/2/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 1 of 9 NOTE: If changes are required to curves in this enclosure, the OAC curves must be updated at the same time or the OAC curves must be considered not valid. {1}
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 2 of 9 Notes For Unit 3 Wide Range Cooldown Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When RCPs are running, maintain RCS P/T above and to the left of the RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
- 5. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 3 of 9 Unit 3 Wide Range Cooldown Curve Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 4 of 9 Notes For Unit 3 Wide Range Heatup Curve
- 1. Maintain RCS P/T below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.
- 2. Maintain RCS P/T above and to the left of the 20°F Subcooled curve.
- 3. When RCPs are running, maintain RCS P/T above and to the left of the RCP NPSH curve. (See EOP curves for abnormal containment conditions).
- 4. Use Low Range Curves when either of the following exist:
RCS pressure is < 550 psig RCS temperature is <350°F Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 5 of 9 Unit 3 Wide Range Heatup Curve Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 6 of 9 Notes For Unit 3 Low Range Cooldown Curve
- 1. Curve #1- RCS cooldown limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
- 5. RCS is considered depressurized when all of the following conditions exist:
RCS temperature < 200°F RCS pressure < 50 psig All RCPs off
- 6. Briefly operating above the LPI pressure curve (#4) or below the RCP NPSH curve (#2) by < 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate RCS Temp Max Heatup Rate {22}
T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 7 of 9 Unit 3 Low Range Cooldown Curve
Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 8 of 9 Notes For Unit 3 Low Range Heatup Curve
- 1. Curve #1- RCS heatup limitations.
- 3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating pump caused by cavitation.
- 5. Briefly operating above the LPI pressure curve (#4) or below the RCP NPSH curve (#2) by < 40 psig is acceptable while swapping RCPs.
Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Heatup Rate T > 270°F < 45°F in any 1/2 hour period T < 270°F < 25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T > 270°F < 45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized < 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.33 OP/0/A/1108/001 Unit 3 RCS Heatup/Cooldown Curves Page 9 of 9 Unit 3 Low Range Heatup Curve
- PZR level restricted to < 380 inches when RCS temperature is < 160°F, < 100 psig AND NO HPIPs operating.
Note: PT/3/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.
Enclosure 4.34 OP/0/A/1108/001 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve (DELETED- moved to Page 1 of 1 OP/0/A/1108/001 B (Spent Fuel Pool Level Vs. Temperature Curves))
Enclosure 4.35 OP/0/A/1108/001 Combined Inventory For Emergency Feedwater Curve Page 1 of 1 COMBINED INVENTORY FOR EFW 12 11 10 Acceptable Operation
(>155,000 gal.)
UST LEVEL (FEET) 9 8
Unacceptable Operation 7 (<155,000 gal.)
6 40 45 50 55 60 HOTWELL (INCHES)
Enclosure 4.36 OP/0/A/1108/001 Site Assembly Alarm Test Page 1 of 1
- 1. Initial Conditions 1.1 None.
- 2. Procedure NOTE: IF the CR phone cannot access the PA system, the CR "gray" phone may be tried as an alternate.
2.1 Ensure "PAGE OVERRIDE" switch in "up" position.
2.2 Dial 70 on CR phone.
2.3 Announce
- "THIS IS A TEST OF THE SITE ASSEMBLY ALARM."
- "THIS IS A TEST OF THE SITE ASSEMBLY ALARM."
2.4 Hang-up CR phone.
2.5 Activate alarm as follows:
2.5.1 Place "SITE ASSEMBLY ALARM" to "ON".
2.5.2 After 5 seconds, place "SITE ASSEMBLY ALARM" to "OFF".
2.6 Repeat Step 2.5 one time (for a total of two alarm activations).
2.7 Dial 70 on CR phone.
2.8 Announce
- "THIS CONCLUDES TEST OF THE SITE ASSEMBLY ALARM."
- "THIS CONCLUDES TEST OF THE SITE ASSEMBLY ALARM."
2.9 Hang-up CR phone.
2.10 Ensure "PAGE OVERRIDE" switch in "down" position.
Enclosure 4.37 OP/0/A/1108/001 Emergency Power Switching Logic (EPSL) Page 1 of 2 Manual:
Keowee Emergency Emergency Start switches in each Control Room Emergency Start switches in each Cable Room Automatic:
ES 1 or 2 Start MFBMP actuation Grid Protection (SY Isolate) 1 Load Shed AND Startup Source UV (10 Sec TD)
Standby Breaker Close Initiation (SBCI) 2 Load Shed AND STAR Relay (no Time Delay) 3 Load Shed and E1 and E2 Bkr Tripped OR NOT in Operate Position AND MFB1 AND MFB2 UV AND Retransfer to SU CH1 and CH2 NOT actuated (10 Sec TD) 4 Load Shed and S1 Closed and Standby Bus 1 not Locked out (no Time Delay) 5 Load Shed and S2 Closed and Standby Bus 2 not Locked out (no Time Delay) 6 Seal-in: Load Shed and SBCI signal already satisfied AND No Retransfer to Startup Ch. 1 or 2 signal SBCI Retransfer to AND ES-1(2) OR MFBMP (either one satisfies RX relay)
AND Standby Bus 1 and 2 UV Startup Source AND Startup Source NOT UV (5 Sec TD)
UNDERVOLTAGE UV (62% - 164KV) on same 2 of 3 phases of BOTH Switchyard Isolate the Red and Yellow Bus.
UNDERFREQUENCY UF (57 Hz for 15 cycles - .25 seconds) on same 2 of 3 phases of BOTH the Red and Yellow Bus.
(any one of three)
DEGRADED GRID VOLTAGE UV (227.468KV) on 2 of 3 phases of the YELLOW Bus for >9 Seconds AND ES-1 or 2 on ANY Unit.
Enclosure 4.37 OP/0/A/1108/001 Emergency Power Switching Logic (EPSL) Page 2 of 2 Initiation Main Feeder Bus Monitor UV for 20 seconds on 2 of 3 phases of BOTH MFB's After Initiation:
Provides input to SK Breaker logic AND Retransfer to Startup logic Keowee Emergency Start Panel Initiates a Load Shed signal.
Load Shed signal provides seal-in to prevent loss
- of MFBMP signal.
Starts 'A' & 'B' HPIP's and CC Pumps STAR Relay energizes when:
2 of 3 phases of Startup Source UV detected AND a second UV detected on startup bus within 1 minute of voltage returning STAR to normal from initial UV.
STAR will:
Trip 'E' breakers and block their closure Input to 'Transfer to Standby' logic Input to 'Load Shed' logic Load Shed Logic Path # 1 (1 sec TD after logic satisfied)
- UV on 2 of 3 phases of Startup Source AND
- UV on 2 of 3 phases of Normal Source AND
- ES or STAR Load Shed Logic Path # 2 (1 sec TD after logic satisfied)
- Breaker N1 open AND
- Breaker E1 open AND
- UV on MFB # 1 Z phase AND Load Shed
- ES-1 or STAR-'A' Load Shed Logic Path # 3 (1 sec TD after logic satisfied)
MFBMP (Ch. 1 OR 2): Channel initiates when BOTH
- MFB's UV >20 secs Load Shed Logic Path # 4
- Seal-in (as long as ES or STAR still present)
Load Shed Logic Path # 2a (1 sec TD after logic satisfied)
- Breaker N2 open AND
- Breaker E2 open AND
- UV on MFB # 2 Z phase AND
- ES-2 or STAR-'B' Under voltage Protection SL1 and SL2 Auto-Select switches in "AUTO" AND SL1 and SL2 UV on BOTH Standby Buses.
Degraded Voltage Protection TRIP INTERLOCK DEFEAT switch in "CENTRAL" AND 1st Level 100KV DEGRADED VOLTAGE reached for 9 seconds AND 2nd Level 100KV DEGRADED VOLTAGE reached.
Enclosure 4.38 OP/0/A/1108/001 Condenser Flow And Temperature Data Page 1 of 2
- 1. Initial Conditions NOTE: Manual logging of CCW data is no longer required when affected Unit's CCW checks can be performed per OP/1,2,3/A/1105/014 (Control Room Instrumentation Operation And Information).
_____ 1.1 Manual logging of CCW flow and temperature data is required.
- 2. Procedure 2.1 Log data as required in Table 1 below.
_____ 2.1.1 IF data cannot be gathered as required for Table 1, go to Step 2.2.
_____ 2.1.2 IF Average CCW Outlet Temperature is 100°F OR Station T > 22°F, notify Unit 1 CRS that CCW temperature limits in OP/1,2,3/A/1105/014 could be affected.
_____ 2.1.3 WHEN this enclosure is completed, forward copy to ONS Environmental Chemistry (mail code ON03EN).
Table 1 CCW Flow (A) (1) (2) (3) (4)
For Running Date Performed: {19} Pumps Lowest Available Unit 1 CCW Unit 2 CCW Unit 3 CCW Average CCW Station T (GPM X Station CCW Inlet Discharge Discharge Discharge Outlet 1000) Temperature From Temperature Temperature Temperature Temperature:
Unaffected Units' Affected Unit: _______
OAC Data # CCW Pumps 1 246 OAC points: From Unit 1 From Unit 2 From Unit 3 Data from Data column Running On 2 465 O1P0761, Process Control Process Control Process Control columns (4)-(A)
Time Taker Affected Unit 3 609 O2P0761 or Panel Screen Panel Screen Panel Screen (1)+(2)+(3)/3 4 708 O3P0761
Enclosure 4.38 OP/0/A/1108/001 Condenser Flow And Temperature Data Page 2 of 2 2.2 Log data as required in Table 2 below.
_____ 2.2.1 IF Average CCW Outlet Temperature is 100°F OR Station T > 22°F, notify Unit 1 CRS that CCW temperature limits in OP/1,2,3/A/1105/014 could be affected.
_____ 2.2.2 WHEN this enclosure is completed, forward copy to ONS Environmental Chemistry (mail code ON03EN).
Table 2 CCW Flow Condenser __A Condenser __B Condenser __C Condenser __A Condenser __B Condenser __C For Running Date Performed: {19} Pumps Inlet Temp. Inlet Temp. Inlet Temp. Outlet Temp. Outlet Temp. Outlet Temp.
______________ (GPM X 1000)
Avg.
Affected Unit: _______
Data # CCW 1 246 __A1 __A2 __B1 __B2 __C1 __C2 __A1 __A2 __B1 __B2 __C1 __C2 Outlet 2 465 (TH14) (TH15) (TH16) (TH17) (TH18) (TH19) (TH20) (TH21) (TH22) (TH23) (TH24) (TH25) Temp.
Time Taker Pumps 3 609 On 4 708
Enclosure 4.39 OP/0/A/1108/001 LDST Pressure Vs. Level (All Units) Page 1 of 2 (Instrument Error Included) 100 90 80 LDST Pressure (psig) 70 60 50 Operation above and to the left of Curve 1 NOT PERMITTED: declare BOTH trains of HPI INOPERABLE.
40 30 Re gi on Op.
issibl 20 Pe e
rm 1
rve Cu 10 Operation below and to the right of Curve 2 requires the 2 compensatory actions listed ve Cur on Page 2 of this enclosure.
0 0 10 20 30 40 50 60 70 80 90 100 LDST Indicated Level (inches) LDST lvl vs press.des Rev. 6 RTR 3/01/05
Enclosure 4.39 OP/0/A/1108/001 LDST Pressure Vs. Level (All Units) Page 2 of 2
Reference:
Curve information comes from drawing #ONTC-0-101A-0005-01. {15}
NOTE: If LDST pressure is < 30 psig, leakage from BWST into HPI System may occur.
- 1. When HPI Pumps are operating: {3}
1.1 LDST pressure and level should remain within "Permissible Op. Region" of "LDST Pressure Vs. Level" curves.
- If system operation leaves the "Permissible Op. Region", but is still between Curve 1 and Curve 2, actions should be taken immediately to restore system to acceptable operating region.
- "LDST Pressure Vs. Level" curves are also located on OAC.
NOTE: If LDST Pressure Vs. Level is above and to the left of Curve 1 and HPI emergency injection initiates, gas may be drawn into HPI Pump suctions resulting in HPI Pump damage.
- 2. If LDST Pressure Vs. Level is above and to the left of Curve 1, then declare BOTH trains of HPI INOPERABLE.
2.1 Immediately depressurize LDST below Curve 1.
2.2 Refer to TS 3.0.3 for shutdown requirements.
2.3 Make notifications as required by OMP 1-14 (Notifications).
NOTE: If LDST Pressure Vs. Level is below and to the right of Curve 2, it may be possible to draw a vacuum in LDST resulting in HPI Pump damage due to inadequate NPSH. This could occur even though sufficient LDST level exists.
- 3. If LDST Pressure Vs. Level is below and the right of Curve 2, then perform the following:
3.1 Pressurize LDST back into "Permissible Op. Region" of "LDST Pressure Vs. Level" curve unless LDST is being depressurized intentionally by an approved procedure.
3.2 Carry a note on the Turnover Sheet to the effect that if a transient occurs which requires additional HPI flow, immediately open (1)(2)(3)HP-24 and (1)(2)(3)HP-25 to provide an adequate suction source to HPI Pumps.
3.3 IF LDST pressure CANNOT be maintained 0 psig, a LDST vent path must be established.
- (1)(2)(3)GWD-19 (LDST VENT) AND (1)(2)(3)GWD-20 (LDST Vent Blk) (LDST Hatch Area) must be open.
Enclosure 4.40 OP/0/A/1108/001 ESV System Vacuum Requirements Page 1 of 1 0
5 Tank Pressure (in Hg vacuum) 10 Unacceptable 15 20 Acceptable 25 30 782 784 786 788 790 792 794 796 798 800 Lake Level (Feet)
Esv_vacsp.xls Rev. 5 9/15/99
Enclosure 4.41 OP/0/A/1108/001 CCW Discharge Local Temperature Data Page 1 of 1 Date Performed:______________
- 1. Initial Conditions
_____ 1.1 Logging of CCW discharge local temperature data required.
- 2. Procedure NOTE: Metal cabinet that houses the local CCW discharge digital temperature instruments is located at fence on NE side of CCW discharge structure. Metal cabinet latches are slot headed screws and will need a flat blade screw driver (or other suitable object) to operate.
_____ 2.1 Open metal cabinet and log data as required on chart below.
_____ 2.1.1 IF any Unit discharge temperature OR the average CCW discharge temperature is 100°F, perform the following:
A. Notify Unit 1 CRS that CCW temperature limits in OP/1,2,3/A/1105/014 could be affected.
_____ 2.2 WHEN this enclosure is completed, forward copy to ONS Environmental Chemistry (mail code ON03EN).
Time Data Unit 1 CCW Unit 2 CCW Unit 3 CCW Average CCW Taker Discharge Discharge Discharge Discharge Temperature Temperature Temperature Temperature
.42 OP/0/A/1108/001 (Not Used) Page 1 of 1
.43 OP/0/A/1108/001 (Not Used) Page 1 of 1
Enclosure 4.44 OP/0/A/1108/001 RCS Boron Changes Due To Letdown Temperature Changes {29} Page 1 of 4 NOTE: Information below curve title line denotes resin mix that curves are applicable for; Chemistry Group can verify this information.
Curve file located at \\onsfs00\dwgs\1108 001 rev 107 boron curves
Enclosure 4.44 OP/0/A/1108/001 RCS Boron Changes Due To Letdown Temperature Changes {29} Page 2 of 4 NOTE: Information below curve title line denotes resin mix that curves are applicable for; Chemistry Group can verify this information.
Curve file located at \\onsfs00\dwgs\1108 001 rev 107 boron curves
Enclosure 4.44 OP/0/A/1108/001 RCS Boron Changes Due To Letdown Temperature Changes {29} Page 3 of 4 NOTE: Information below curve title line denotes resin mix that curves are applicable for; Chemistry Group can verify this information.
Curve file located at \\onsfs00\dwgs\1108 001 rev 107 boron curves
Enclosure 4.44 OP/0/A/1108/001 RCS Boron Changes Due To Letdown Temperature Changes {29} Page 4 of 4 Curve file located at \\onsfs00\dwgs\1108 001 rev 107 boron curves
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 1 of 16
- 1. Temperature Measuring Devices 1.1 RCS Temperature is measured using either Resistance Temperature Detectors (RTDs) OR Thermocouples.
1.2 RTDs work by correlating a change in electrical resistance with a change in temperature. As the temperature of the wire increases, its resistance increases. This resistance change is measured and displayed as temperature.
1.2.1 Failure modes are as follows:
- Shorted RTDs will display lower than actual temperature since the resistance of a short is essentially zero.
- Open RTDs will display higher than actual temperature since an open circuit is read as infinite resistance.
- Failure of the RTD bridge source will cause the indication to fail to its minimum nominal value.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 2 of 16 1.2.2 RTDs are powered as follows:
RTD # Description Power Supply RD1A RPS Ch A Th A KVIA RD1B ICS NR A1 Th KI or KU from Auctioneering circuit RD2A ICS NR A2 Th KI or KU from Auctioneering circuit RD2B RPS Ch B Th A KVIB RD3A RPS Ch C Th B KVIC RD3B ICS NR B1 Th KI or KU from Auctioneering circuit RD4A ICS NR B2 Th KI or KU from Auctioneering circuit RD4B RPS Ch D Th B KVID RD5A ICS NR A2 Tc KI or KU from Auctioneering circuit RD5B ICS WR A2 Tc KI or KU from Auctioneering circuit RD6A ICS WR A1 Tc KI or KU from Auctioneering circuit RD6B ICS NR A1 Tc KI or KU from Auctioneering circuit RD7A ICS NR B2 Tc KI or KU from Auctioneering circuit RD7B ICS WR B2 Tc KI or KU from Auctioneering circuit RD8A ICS WR B1 Tc KI or KU from Auctioneering circuit RD8B ICS NR B1 Tc KI or KU from Auctioneering circuit RD84A ICS WR A Th KI or KU from Auctioneering circuit RD84B ICCM WR A Th KVIA RD85A ICS WR B Th KI or KU from Auctioneering circuit RD85B ICCM WR B Th KVIB
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 3 of 16 1.3 Thermocouples work by creating a potential (or voltage) at the junction of two dissimilar metals. Low potential at the contact corresponds to low temperatures, while high contact potential corresponds to high temperatures.
- Shorted thermocouples where the short occurs between the element and well will NOT change the indication, since the potential across the junction does NOT change.
- Shorted thermocouples where the short occurs between the leads and outside the well will cause the indication to read ambient, since the leads are made of the same material as the junction.
- Shorts to ground will cause the thermocouple indication to fail low since the potential across the junction goes to zero.
- Open circuits result in a lower than actual indication due to the decrease in potential across the junction.
1.3.1 Type "J" thermocouples use Iron-Constantine and have a range of 0 - 700°F.
These are typically used to measure the temperature of the pressurizer and its associated piping and connections. (RC-66, RC-67, and RC-68 tailpipes; Pressurizer Surge Line; Pressurizer Spray Line) 1.3.2 Type "K" thermocouples use Chromel-Alumel and have a range of 0 - 2500°F.
Typical applications for these thermocouples are incore temperature measurements. Each core has 52 incore thermocouples (ICTCs); 47 input to various calculations, indications and the OAC. Five are used for SSF indication only. ICCM trains A and B each have 12 ICTCs feeding them. The ICCM indications also feed the OAC. The remainder of the ICTCs feed the OAC but, are NOT considered environmentally qualified.
1.4 Hot Leg Control Room Temperature Indications 1.4.1 Narrow Range Temperatures are used between 520°F - 620°F.
1.4.2 Narrow Range Thot feeds each RPS channels High Temperature AND Variable Low Pressure Trip functions. Channels A and B are measured from Loop A, while Channels C and D are measured from Loop B.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 4 of 16 1.4.3 Median Select signal OR the average of the two NR Thot RTDs feed:
- High Temperature Alarm Circuit
- Loop A and Loop B NR Thot Dixon meter
- Unit Thot NR recorder (the position switch allows the selected Loop A Thot, the selected Loop B Thot, or the average of both Loops Thot to be displayed)
- NR Tave Circuit
- Loop T Circuit
- ICS (Both loop Thot signals will feed)
- Aux Shutdown Panel (Loop B only) 1.4.4 Wide Range Temperatures indicate from 50°F - 650°F.
1.4.5 Two WR Thot are located on each hot leg. One feeds ICCM, the other ICS.
1.4.6 ICCM WR Thot feeds:
- Digital LED meters. Off-scale low indicate LO. Off-scale high indicates HI.
- ICCM Loop Subcooled Margin Monitors.
- Median select circuit.
- OAC Loop Subcooled Margin Monitors.
1.5 Cold Leg and Average Temperature Control Room Indications 1.5.1 Output of the median select circuit OR average of the two NR Tcold feeds:
- Loop A and Loop B NR Tcold meter.
- Loop A and Loop B T meter.
- Loop A and Loop B Tave meter.
- Tc meter.
- Controlling Tave digital meter (green LED).
- Tave Recorder.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 5 of 16 1.5.2 Tave Select Schemes:
- IF RCS flow is normal ( 70E6 lbm/hr) in both loops, the Unit Tave output feeds the Tave control circuit.
- IF RCS flow is normal ( 70E6 lbm/hr) in one loop and low (< 62E6 lbm/hr )
in the other loop, the Loop Tave in the high flow loop becomes the controlling Tave.
- IF RCS flow in both loops is low (< 62E6 lbm/hr), the Unit Tave output feeds the Tave control circuit.
- IF either steam generator is on Low Level Limits, the highest Tave is selected.
1.5.3 WR Tcold feeds:
- Tcold digital meter (selected from A1, A2, B1, or B2 Loops) displays LO/HI IF off-scale low or high.
- Selected Tcold signal feeding the meter also feeds the recorder.
- Fourth Reactor Coolant Pump starting interlock. The lowest Tcold in the A loop feeds the starting circuit for the A1 and A2 RCPs, while the lowest Tcold in the B loop feeds the starting circuit for the B1 and B2 RCPs.
1.6 Pressurizer temperature is measured using three RTDs. Channels A and B feed ICCM.
These temperatures feed the temperature compensation circuits for pressurizer level.
Channel A is used to compensate Pzr Level 1 and Pzr Level 2. Channel B is used to compensate Pzr Level 3. Channel C feeds the OAC only. Additionally, Channel A feeds the pressurizer saturation indication.
- 2. RCS level is measured using three different methods: tygon tubing, Rosemount P cells, and ultrasonic level measurement.
2.1 Tygon tubing is used to provide level indication of the RCS cold legs. It is a manometer type measurement. By connecting the tubing to the bottom of the cold legs, the elevation pressure of the water in the cold leg will force a column of water into the tygon tubing which is equal in height to the cold leg level, provided both legs have equal overpressure.
2.2 A Rosemount P cell compares the pressure of a reference leg to the elevation pressure of a process fluid. This type of instrument feeds the respective unit's LT-5. LT-5 is referenced to the hot leg center line (water level at the centerline is 0").
2.3 Ultrasonic level detectors measure the time required for a sound pulse to travel from the sensor, through a medium, reflect from a surface due to density change, and return to the sensor. This time is correlated to a height of water AND output as inches of water.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 6 of 16
- 3. RCS flow is measured using a gentilli tube. The gentilli tube is used to measure the difference between the static head of the system and the velocity head of the system. The P between these two parameters is transmitted using a Rosemount P transmitter.
3.1 Five pairs of tubes, each pair has one tube pointing in the opposite direction of flow and the other tube pointed in the direction of flow. The tubes pointing in the direction opposite flow feed a common high pressure header. Those pointed in the direction of flow feed a common low pressure header.
3.2 With no flow, each pair of tubes pointing in either direction measure the same pressure; therefore P is 0 psid.
3.3 When RCS flow is present, a P is developed which causes a flow indication to be present.
3.4 Should the low pressure header fail, the pressure in the header will decrease, which increases the measured P, causing RCS flow indication to increase.
3.5 Conversely, should the high pressure header fail, the pressure in the header will decrease, creating a smaller measured P, causing a smaller indicated RCS flow.
3.6 Five P transmitters are attached to the high and low pressure headers, AND are referred to as Channels A - E, respectively. Channels A-D feed the RPS channels A-D. The ICS uses the median selected value between Channel A, B, and E.
3.7 The measured P is used to calculate a volumetric flow rate. This flow rate does NOT change as RCS temperature changes. The P signal is processed through a square root extractor. Flow is proportional to the square root of the P.
3.8 Mass flow rate is derived by temperature compensating the volumetric flow rate. Mass flow rate does change as RCS temperature changes. Loss of temperature compensation typically results in higher than actual flow. However, since mass flow is directly proportional to the density of the RCS, the following rules apply:
- IF Thot fails low, flow indicates HIGHER than actual, since it appears the RCS fluid is more dense.
- IF Thot fail high, flow indicates LOWER than actual, since it appears the RCS fluid is less dense.
3.9 RCS flow is temperature compensated from a WR Hot Leg RTD on the appropriate loop.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 7 of 16
- 4. Rosemount pressure measuring devices work on the principle of measuring a change in capacitance created by movement of a diaphragm between two capacitance plates and converting the output into a pressure signal.
4.1 NR Pressure Range 1700 psig - 2500 psig.
4.2 Loop A has (2) NR pressure transmitters, while Loop B has (3) NR Pressure transmitters.
4.3 Loop A NR pressures feed the RCS Channels A and B, while Loop B NR pressures feed RPS Channels C and D, AND Channel E.
4.4 Median select from RPS Channels A, B, and E feed:
- RC-66 PORV "HIGH" open circuit
- RC-1, PZR SPRAY AUTO circuit
- Pressurizer Heater AUTO circuit
- Auxiliary Shutdown Panel indication
- NR Recorder
4.6 (Old ES System) Five WR Pressure Range sensors are located on the two hot legs.
- Two feed the SSF (one from each loop).
- The remaining (3) feed ES AND Subcooled Margin Monitors. Loop A WR transmitters feed ES Analog Channels A and B. Loop B WR transmitter feeds ES Analog Channel C.
- The OAC core SCM uses the lower of the two pressures feeding ES Channel Analog B and ES Channel Analog C.
4.7 (New ES system) Five WR Pressure Range sensors are located on the two hot legs.
- Two feed the SSF (one from each loop).
- The remaining (3) feed ES AND Subcooled Margin Monitors. Loop A WR transmitters feed ES Channels A and B. Loop B WR transmitter feeds ES Channel C.
- The OAC core SCM uses an input from a Loop A transmitter and a Loop B transmitter, fed from hard-wired OAC points.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 8 of 16 4.8 (Old ES System) WR RCS Pressure recorder displays the signal selected using the amphenol connector in the ES Analog A cabinet. This connector can be plugged into ES Analog Channel A or ES Analog Channel B.
- The amphenol selected signal also feeds the LP-1 open interlock, as well as the ES HP AND LP INJECTION BYPASS PERMIT statalarms.
4.9 (New ES system) WR RCS Pressure recorder displays the signal fed from ES Train 2 which is normally fed from ES WR Channel A. ES Train 2 automatically transfers input to ES Channel B WR pressure upon loss of Channel A signal. Signal may be manually selected to Channel A or B using the GSM. The Open-Permissive interlock to LP-1 is supplied from all three ES channels RCS pressure through three 2MIN blocks. If the output of each 2MIN block is less than the setpoint of 375 psig, then the Open-Permissive is then sent to 2/3 Logic Block located in the ODD Voter Cabinets. The output of the 2/3 Logic Block (1/Subsystem) provides the permissive signal to LP-1 from either Subsystem. The permissive signal is lost when the 2.MIN RCS WR Pressure increases to 400 psig on at least 2/3 of the Input Instrument Channels 2.MIN values in Both Subsystems.
4.10 ICCM Pressure range is 0 psig - 3000 psig.
4.11 Each ICCM train pressure feeds the ICCM SCM and meters. The meters will display HI at 2750 psig.
4.12 RCS Low Range Pressures range is 0 psig - 600 psig.
- The sensor is located on the ICCM RVLIS impulse line.
- Although the instrument is always valved in, the meter is NOT turned on unless RCS pressure is 600 psig or less.
- This signal inputs into the RC-66 LOW AUTO open circuit.
- For the PORV to open on the LOW AUTO circuit, the Low Range Pressure switch must be ON AND the PORV selector switch placed in LOW.
- The digital Dixon meter blinks AND the bar graph is pegged high when the Low Range Pressure Switch is ON AND RCS pressure is greater than 600 psig.
- 5. RCS Level 5.1 Pressurizer Level and Temperature Instrumentation 5.1.1 Three P transmitters are used for measurement and control of Pressurizer Level.
Each of these feed the HI/LO statalarm.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 9 of 16 5.1.2 Levels #1 and #2 are fed through ICCM Train "A". #2 tap also feeds SSF uncompensated Pzr level and Pzr pressure.
A. Level tap #2 has a separate pressure/level transmitter to feed Pzr uncompensated level and Pzr pressure indication to the SSF Control Room.
{4}
5.1.3 Level #3 is fed through ICCM Train "B".
5.1.4 Pressurizer Level control is protected from failure by SASS.
5.1.5 Each transmitter has individual upper and lower instrument taps.
5.1.6 Pzr temperature for compensation is supplied from a single well with three RTD elements located in the well.
A. Pzr Temperature Channel 'A' is fed to ICCM Channel 'A'.
Pzr Temperature Channel 'B' is fed to ICCM Channel 'B'.
Pzr Temperature Channel 'C' is fed to the non-safety OAC only.
B. ICCM develops the temperature compensated signal. This selected signal is supplied to :
- Pzr Chart Recorder
- HP-120 control
- Aux Shutdown Panel
- Low Pzr Level Heater Cutoff
- Emergency HI/LO Statalarm C. RCS Pressure compensated Pzr level is fed to the OAC only.
D. Uncompensated Pzr Level will always read lower than the actual level.
E. Pzr Heaters will return to the mode they were in prior to reaching the cutoff setpoint.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 10 of 16 5.1.7 RCS Level Measurement using LT-5A and LT-5B A. Reference leg is a water filled leg open to the Reactor Building atmosphere.
B. Variable leg is connected to the RCS Cold Leg piping between a RCP and the reactor vessel. At 0 inches, the water level is at the centerline of the hot leg and cold leg.
C. LT-5 Fluctuations with Reactor Building/RCS pressures:
- IF PRCS < PRx Bldg Vessel Level indicates LOWER than actual.
- IF PRCS > PRx Bldg Vessel Level indicates HIGHER than actual.
- IF Rx Building temperature increases, the water in the reference leg swells and may spill out. Should this occur, Vessel Level will indicate HIGHER than actual.
5.1.8 RCS Level Measurement using Ultrasonics A. A sound pulse is transmitted from the bottom of the piping. The wave travels to the surface and is reflected back to a receiver. The time for the wave to travel is measured. Based on this time, a vessel level is inferred.
B. One instrument is placed on one hot leg, and one instrument is placed on one cold leg.
C. Measurement is from -18" to +18" (Hot Leg) and -14" to + 14" (Cold Leg).
0" is the piping centerline.
D. OAC alarms at +10". String checks are performed on levels greater than 0" only.
- 6. Pressurizer Relief Valve Monitor 6.1 The monitor detects flow through the RCS relief valves using a self generating piezoelectric transducer. This means it requires no outside power supply. One detector per valve exists for unit three, while units one and two employ two detectors per valve.
6.2 Alarms on:
- Switch in Test
- 5th lamp (25 % flow) is lit
- Power switch is OFF
- Supplied from: Unit 1 and Unit 2- KVIA; Unit 3- KVIB
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 11 of 16
- 7. SASS Operation 7.1 SASS protects against instrument failures by comparing one signal against another. Should the selected signal suddenly change from the compared signal, SASS automatically selects the alternate signal.
7.2 The OAC provides a MISMATCH alarm upon SASS actuation.
7.3 The following signals are monitored by SASS:
- OTSG "A" Operating Range Level Channel 1 AND Channel 2
- OTSG "B" Operating Range Level Channel 1 AND Channel 2
- Pressurizer Level (Channel 1 OR 2) AND Channel 3 NOTE: If Pzr Level Channel 1 or 2 is selected, SASS input is from the selected level channel and Channel 3. If Pzr Level Channel 3 is selected, SASS input is Channel 3 and Channel 1.
7.4 When SASS is in AUTOMATIC, SASS selects the alternate signal IF the selected signal deviates rapidly from the alternate signal. The action is independent of the selector switch position.
7.4.1 Upon SASS actuation the following will be observed:
- MISMATCH OAC Alarm.
- SASS Panel red TRIP light will be ON.
- SASS Panel green AUTOMATIC light will be OFF.
- SASS Panel amber MISMATCH light will be ON.
- The channel will stay in MANUAL until the signal is good and the channel is manually reset.
- Once channel is manually reset, the AUTO light will be ON, the MISMATCH AND TRIP lights should be OFF.
7.4.2 While SASS is in AUTO, the normal selector switch can be used to select the input signal.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 12 of 16 NOTE: An instantaneous mismatch (rapid mismatch >6 %) can occur and clear immediately. This will cause only a red "trip' light to illuminate without an Amber "Mismatch" light or OAC mismatch alarm. The green "Auto" light will be extinguished also.
7.4.3 Upon receipt of a MISMATCH (triggered by a deviation between signals of 3-6%), SASS swaps to MANUAL, but does NOT select the alternate signal. The following will be observed at the SASS panel:
- SASS Panel green AUTOMATIC light will be OFF.
- SASS Panel amber MISMATCH light will be ON.
- MISMATCH OAC alarm.
- When condition clears, the channel will reset to AUTOMATIC with no operator action.
7.4.4 When SASS is in MANUAL, no protection is provided.
7.4.5 Upon a loss of power to SASS, whichever signal is selected is fed though.
7.4.6 The TEST switch simulates rapid failure. The direction the switch is moved to is the signal being simulated to fail. The alternate signal shall be verified as being accurate prior to testing the trip function.
- 8. Recognizing Problems With Dixon Meters 8.1 Loss of power to an instrument causes the indicator to go blank. Should the input signal fail, the meter may fail either mid-scale or low.
8.2 OVERRANGED
Off scale HIGH with the upper LEDs blinking. (Blinking Digital 8's)
8.3 UNDERRANGED
Analog bottom LED flashing. (Solid Digital 0's OR Low Scale Value)
9.2 Tave feeds Reactor Demand and OTSG Low Level Limit Circuitry.
9.3 WR Thot feeds the temperature compensation for RC Flow.
9.4 WR Tc feeds the RCP starting interlocks.
9.5 Total RC Flow feeds the RC Flow Runback Circuitry.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 13 of 16 9.6 Loop RC Flow feeds:
- FDW Reratio Circuit
- Total Flow Control
- Core Thermal Power Best
- CTP Demand Load Limit
- Tave selection circuit 9.7 RCS and Core Subcooling Margin Programs.
- 10. OAC Program 10.1 Operability requirements are found in TS.
10.2 Each units Surveillance PT checks operability of the inputs.
10.3 Inputs:
- NI NI-8 Power
- Reactor Building Pressure
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 14 of 16 NOTE:
- Core SCM uses the lower of the two Loop WR pressure inputs.
- When NI power > 2%, the program takes the average of operable CETCs NOT used by the SSF. (Total of 47). Operable is typically defined as the indicated value is within 50 degrees of the average. Should the CETC be in "scan lockout" or "inserted value", the calculation will exclude this point.
- When NI power < 2% for > 45 seconds, the program takes the average of the five highest qualified CETCs. The OAC looks at all 24 qualified CETCs.
10.4 The OAC SCM provides the input into the statalarms ("RC APPROACHING SATURATED CONDITIONS"). Listed below are the alarm setpoints:
- IF NI power > 2% , Loop SCM < 15°F OR Core SCM < 10°F.
- IF NI power < 2%, Loop SCM < 15°F OR Core SCM < 15°F.
- The alarm reflashes IF any SCM reaches 5°F.
- The OAC alerts the operator to actual saturated conditions at 0°F SCM.
10.4.1 IF the RCS is subcooled, the indications display solid red numbers indicating the SCM.
10.4.2 IF the RCS is saturated, the indications display flashing red 000's.
10.4.3 IF the RCS is superheated, the indications display flashing red negative numbers indicating the amount of superheat.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 15 of 16 NOTE: Normal alignment is for ICCM to be selected to feed the SCM Meters.
10.4.4 IF the OAC is in Automatic and Reactor Building pressure is < 3 psig, the OAC feeds the Loop 'A', Core, and Loop 'B' indications. The remaining window (third from the left) is the ICCM Train 'B' Core SCM. IF the Reactor Building pressure is > 3 psig, ICCM Loop 'A', ICCM Train 'A' Core, ICCM Train 'B' Core and ICCM Loop 'B' is displayed.
OAC (RB pressure < 3 psig)
OAC OAC OAC Core ICCM B Core Loop A Loop B OAC (RB pressure > 3 psig)
ICCM ICCM ICCM A Core ICCM B Core Loop A Loop B
- 11. ICCM SCM 11.1 Core SCM is calculated from the average of the five highest qualified CETCs for that train and the 0 - 3000 psi RCS pressure transmitter feeding that train.
11.2 Loop SCM is calculated from the ICCM WR Thot and the 0 -3000 psig RCS pressure transmitter.
11.3 ICCM Indications:
11.3.1 A spare CRDM tap is used for one impulse line that splits and feeds one side of two P cells, one for each train.
11.3.2 The other impulse line taps into the decay heat drop line. A separate impulse line exists for each train.
11.3.3 The ICCM channel "A" RCS pressure indication taps are located on the impulse line which feeds the hot leg level P cell.
11.3.4 The ICCM channel "B" RCS pressure indication taps are located on the impulse line which feed the reactor vessel level P cell.
11.3.5 Reactor Vessel and hot leg level indications are NOT valid IF one or more RCPs or LPI pumps are operating since the calculation can NOT compensate for pressure fluctuations caused by forced flow.
Enclosure 4.45 OP/0/A/1108/001 RCS Instrumentation Page 16 of 16 11.3.6 Hot leg level is NOT valid IF Hot Leg vents are open, since the vents tap into the same impulse line.
11.3.7 IF RCPs are running, INVALID is displayed on the ICCM meter, pointer and whole numbers go blank.
11.3.8 MALFUNCTION is displayed IF the RCPs are off and an input sensor fails. The pointer and whole number does NOT go blank.
11.3.9 MALFUNCTION is displayed IF the RCPs are on and an input sensor fails. The pointer and whole number is blank.
11.3.10 FORCED FLOW CONDITION is displayed IF an LPI pump is operating. This is NOT affected, nor does it affect the INVALID indications received when RCPs are running.
11.3.11 CETC indicates in reverse video when > 700°F.
11.3.12 SCMs are displayed in reverse video when saturated or superheated conditions are present.
11.3.13 OFF HIGH indicates a temperature is off scale high or transmitter volts are off scale high.
11.3.14 OFF LOW indicates a temperature is off scale low or transmitter volts are off scale low.
11.3.15 ALARM indicates a hydraulic isolator limit switch is activated.
11.3.16 DISABLED indicates a sensor is disabled.
11.3.17 ICCM can be monitored on the Plasma display, the OAC, the trend recorder on VB2 (train "A" only), and ICCM control cabinets.
11.3.18 IF ICCM is off-line for test, maintenance, or calibration, it displays DATA LINK FAILURE. All other indications freeze as is.
11.3.19 Loss of ICCM main cabinet incoming power results in LOW indication and blank plasma screen. Loss of internal cabinet power results in LOW indication and DATA LINK FAILURE indication on plasma screen.
11.3.20 IF HPI flow < 60 gpm, ICCM indicates 0 gpm.
11.3.21 IF LPI flow < 300 gpm, ICCM indicates 0 gpm.
11.3.22 IF RBS flow < 150 gpm, ICCM indicates 0 gpm.
Enclosure 4.46 OP/0/A/1108/001 Total Loss Of DHR Time To Boil Page 1 of 1 (DELETED- moved to OP/0/A/1108/001 A (Reactor Core And SFP Loss Of Cooling Heatup Tables))
Enclosure 4.47 OP/0/A/1108/001 Maximum SFP Temperature Vs. Total SFC System Flow Page 1 of 2 Unit 1&2 Maximum SFP Temperature vs. Total SFC System Flow 200 190 180 +0.5 Pool Level 170 +0.0 Pool Level 160 Temperature, oF Acceptable 150 Region is Below Applicable Curve 140 130 -0.5 Pool Level 120
-1.0 Pool Level 110 100 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 3000 Total System Flow, gpm OSC-6800 Rev. 1
Enclosure 4.47 OP/0/A/1108/001 Maximum SFP Temperature Vs. Total SFC System Flow Page 2 of 2 Unit 3 Maximum SFP Temperature vs. Total SFC System Flow 200 190 180 +0.5 Pool Leve 170 160 +0.0 Pool Level 150 140 Acceptable Temperature, oF Region is Below 130 Applicable Curve 120 110 100 -0.5 Pool Level 90 80 -1.0 Pool Level 70 60 50 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 3000 Total System Flow, gpm OSC-6800 Rev. 1
Enclosure 4.48 OP/0/A/1108/001 Appendix Page 1 of 2
- 1. PIP O-98-1375 CA #1- added Note to affected enclosures to verify that OAC P/T curves are updated when the P/T curves in these enclosures are updated.
NOTE: Item #2 superseded in Rev. 109 of this procedure; see Item #31.
- 2. PIP O-98-3399 CA #1- updated Enc. 3.1 "BHUT Volume Vs. Level Curve" with curve provided by ONS Engineering.
- 3. PIP O-01-097-3072- additional guidance for LDST level and pressure added.
- 4. PIP O-99-3297 CA #1- Revised steps to match information contained in OTC lesson plan.
- 5. PIP O-00-01273 CA #2- added reference to BAMT level vs. volume calculation.
- 6. PIP O-01-01955 CA #3- included additional notes on CBAST concentration vs. level curves.
- 7. PIP O-99-04378 CA #5- added new note to all Units' Low Range Heatup and Cooldown curves that allows brief periods of operation above LPI curve and below RCP NPSH curve while swapping RCPs.
- 8. PIP O-02-02537 CA# 14- added information for various plant equipment liquid volumes.
- 9. PIP O-02-05298 CA# 2- added information for various plant equipment liquid volumes.
NOTE: Item #10 superseded in Rev. 109 of this procedure; see Item #31.
- 10. PIP O-03-07998 CA #4- limit and Precaution for BHUT level indication and Notes on BHUT curves added.
- 11. PIP O-04-04423 CA #2- Pzr/Surge Line volume information added.
- 12. Not Used
- 13. Changes made to Enclosure 3.23 "Unit 1 Mechanical RB Penetrations (East And West)" and Enclosure 3.24 "Unit 2&3 Mechanical RB Penetrations (East And West)" must also be made to similar drawings in AP/1,2,3/A/1700/026 (Loss Of Decay Hear Removal).
- 14. PIP O-06-05769 CA #2- change made to add Keowee Forebay level/Lake Keowee level conversion.
- 15. PIP O-05-00965 CA #96- added reference in Enc. 3.39 to ONTC-0-101A-0005-01.
- 16. PIP O-07-02505 CA #16- deleted Enclosure (System Boron Concentration Vs. Time For The Purification Demineralizers).
- 17. Not Used
- 18. Not Used
Enclosure 4.48 OP/0/A/1108/001 Appendix Page 2 of 2
- 19. PIP O-03-05920 CA #1- added "Date Performed" block to top of Enc. "Condenser Flow And Temperature Data".
- 20. PIP O-08-01940 CA #77- inserted revised LR Heatup and Cooldown curves in Enc.4.32 and 4.33.
Change was to add new plot #3 for "Minimum RCS pressure for continuous operation of single RCP in a loop" for each Unit.
- 21. Not Used
- 22. PIP O-11-00459 CA #8- made changes to Heatup and Cooldown curves to add limits for both heatup and cooldown to both curves. All limits apply all the time per TS applicability statement.
- 23. Not Used
- 24. PIP O-11-06885 CA #3- changed the Low Range Heatup and Low Range Cooldown curves to make the 375 psig LTOP admin limit more visible.
- 26. PIP O-13-11188 CA #1 - revised information in Enc. 4.27 to help with setting alarm setpoints on U2 NI Recorder.
- 27. PIP O-93-0324, CA# 1- PIP reference carried forward to this procedure from OMP 1-02 (Rules Of Practice) Rev. 085.
- 28. PIP O-14-0110 CA # 4- new enclosure added to provide guidance for removal/restoration of Control Room Statalarms/indications.
- 30. PIP O-14-08430 CA #2- updated CBAST level vs. volume curve using data from the OAC "Online Databook Calculator (DBK)" program and ONS calculation OSC 7129 Rev. 4.
- 31. PIP O-12-03564 CA #3- updated Enc. 4.1 (BHUT Volume Vs. Level Curve) with curve provided by ONS Engineering in OSC 7129 Rev. 4.
Room 208 Seal Supply Filter Survey # M-123106-1 Date/Time 03/18/2012 03:30 RM 208 UNIT 1 SEAL SUPPLY FILTER ROOM Significant Dose Contributor 8
- 50
+30 20 13 4
1 A B 2
22 N
7 3
2 LEWA Summary of Highest Readings Smears Air Samples & Wipes
- 1) 18775 DPM/100 cm2 b/g
- 4) 5k DPM/100 cm2 b/g
- 2) 3k DPM/100 cm2 b/g Symbol Legend (for example only) Type: Job Coverage
- 3) 1k DPM/100 cm2 b/g Dose Rate
- 150 Contact Reading HS-50 Hot Spot RWP: 5007
+75 30 cm Reading RCA Posting Reactor Power = 100%
20 General Area Drip Bag 15 Smear 15 Air Sample 15 Wipe Unless otherwise noted, dose rates in mrem/hr.
Surveyor: W. Walters Approved by: N. Wriston, 03/19/2012
INFORMATION Oconee Nuclear Station INFORMATION USE ONLY Radiation Work Permit USE ONLY Entry For Routine Plant And Systems Operation (Operations) RWP # 23 Rev: 15 Task # 1 Entry For Routine Plant And Systems Operation (Operations)
ED Alarm Set Points:
Dose Alarm: 10 Dose Rate Alarm: 30 RWP Requirements Dress Category/Work Description
- Dress Category "A" Work in a non-contaminated area
- Dress Category "B" Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand and durability of surgical gloves is sufficient (e.g., taking smears, etc.).
- Dress Category "C" Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand AND durability of surgical gloves is NOT sufficient.
- Dress Category "D" Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected skin or clothing
- Dress Category "E" Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires consideration; (3) Radioactive material is handled and/or transported AND the potential for loose surface contamination exist.
- Dress Category "F" Work in a contaminated area where complete protection of skin and clothing is NOT necessary.
- Dress Category "G" Work in a dry contaminated area.
- Dress Category "H" Work in a contaminated area.
- Dress Category "N" Performing work in contaminated wet conditions.
- Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn Contamination Control
- Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP
- Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP
- Install catch containments OR drain rigs to prevent spills if draining components
- If installing a drain rig, use hose clamps or similar device to secure hose OR tubing connections
- If installing a drain rig, secure hose OR tubing to floor drain
- Wear disposable (plastic) booties inside of orex booties for work in wet conditions
- Change outer rubber gloves often when handling highly contaminated material as directed by RP
- Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP RP Job Coverage
- Start of Job, Intermittent or No Coverage In Radiation Areas or Less
- RP Coverage Required To Transport All Radioactive Material Outside RCA, And Radioactive Material > 100 Mrem/Hr Contact Inside RCA
- If Hot Particle contamination is identified or expected, Notify RP Supervision and refer to RPSM 4.6 Hot Particle Program and SH/0/B/2000/005 Posting Radiation Control Zones, for guidance
- Continuous RP Coverage required for aggressive work in Alpha Level III or Alpha Level II areas with beta-gamma to Alpha ratios less than 3000 or where conditions could change Approved on 04/16/2012 by OCHOA, RONALD L Printed on 04/22/2012 Activated on 04/16/2012
Dosimetry Requirements
- Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example every 10 to 15 minutes.