ML22291A163
| ML22291A163 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/18/2022 |
| From: | Progress Energy Carolinas |
| To: | Division of Reactor Safety II |
| References | |
| Download: ML22291A163 (60) | |
Text
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 76. Given the following plant conditions:
- A large break LOCA has occurred
- The crew is implementing EOP-E-0, Reactor Trip or Safety Injection
- An Auxiliary Operator is dispatched to locally unlock and close the breakers for the CSIP suction and discharge cross-connect valves Which ONE of the following completes the statements below concerning this operation?
Closing these breakers is directed in (1).
These local actions in EOP-E-0 are performed earlier rather than later in order to (2).
(1) Attachment 1, SI Emergency Alignment (2) minimize operator dose (1) Attachment 1, SI Emergency Alignment (2) prevent ASI pump operation (1) Attachment 2, Local Actions To Prepare For Cold Leg Recirculation (2) minimize operator dose (1) Attachment 2, Local Actions To Prepare For Cold Leg Recirculation (2) prevent ASI pump operation A.
B.
C.
D.
76 ML22291A163
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 77. Given the following plant conditions:
- A large break LOCA occurs with a loss of offsite power
- EOP-E-1, Loss of Reactor Or Secondary Coolant, is in progress Subsequently the following occurs:
- A fire is reported from MCC 1B31-SB
- The crew is evaluating if cold leg recirculation capability exists Which ONE of the following completes the statement below?
Based on the conditions above AND the indications in the reference provided, the 1A-SA Safety Bus (1) energized AND the CRS will (2).
(Reference provided)
(1) has (2) remain in EOP-E-1 and brief the transfer to cold leg recirculation (1) has (2) transition to EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation (1) has NOT (2) remain in EOP-E-1 and brief the transfer to cold leg recirculation (1) has NOT (2) transition to EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation A.
B.
C.
D.
77
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 78. Given the following plant conditions:
- The unit was operating at 100% power when all RCP seal cooling was lost
- The Reactor was tripped and all RCPs stopped
- The crew entered EOP-E-0, Reactor Trip or Safety Injection Fifteen (15) minutes later:
- ERFIS is NOT available
- Core exit TCs are 624°F and stable
- RCS pressure is 1925 psig and stable
- RCS hot leg temperatures are 575°F and stable
- SG pressures are at 885 psig and lowering slowly
- RCS cold leg temperatures are 532°F and lowering slowly Which ONE of the following completes the statements below?
The natural circulation flow criteria for RCS (1) has NOT been met.
The crew will attempt to establish natural circulation by dumping additional steam from the intact SGs in (2).
(Reference provided)
(1) subcooling (2) EOP-ES-0.1, Reactor Trip Response (1) subcooling (2) EOP-ES-0.2, Natural Circulation Cooldown (1) cold leg temperature (2) EOP-ES-0.1, Reactor Trip Response (1) cold leg temperature (2) EOP-ES-0.2, Natural Circulation Cooldown A.
B.
C.
D.
78
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 79. Which ONE of the following completes the statements below regarding Reactor Makeup Control System (RMCS) operation during a complete loss of Instrument Air?
1CS-283, Boric Acid to Boric Acid Blender (FCV-113A), has failed (1).
Attachments in (2) will be used to perform manual makeups, borations, and dilutions of the RCS.
(1) shut (2) AOP-017, Loss of Instrument Air (1) shut (2) AOP-003, Malfunction of Reactor Makeup Control (1) open (2) AOP-017, Loss of Instrument Air (1) open (2) AOP-003, Malfunction of Reactor Makeup Control A.
B.
C.
D.
79
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 80. Given the following plant conditions:
- The crew has completed EOP-E-3, Steam Generator Tube Rupture, and a transition has just been made to the appropriate recovery procedure
- The crew is about to commence an RCS cooldown when the BOP reports that the Condenser Available light (C-9) is NOT lit Which ONE of the following completes the statements below regarding the PREFERRED methods for conducting the RCS cooldown and ruptured SG depressurization?
The RCS cooldown will be accomplished by dumping steam using the (1).
The ruptured SG will be depressurized using (2).
(1) intact SG PORVs (2) EOP-ES-3.1, Post-SGTR Cooldown Using Backfill (1) intact SG PORVs (2) EOP-ES-3.2, Post-SGTR Cooldown Using Blowdown (1) TDAFW Pump (2) EOP-ES-3.1, Post-SGTR Cooldown Using Backfill (1) TDAFW Pump (2) EOP-ES-3.2, Post-SGTR Cooldown Using Blowdown A.
B.
C.
D.
80
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 81. Given the following plant conditions:
- The unit experienced a LOCA several hours ago
- All Containment Spray pumps were secured in accordance with EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation, due to having four fan coolers running Subsequently:
- A transition is made to EOP-FR-Z.1, Response to High Containment Pressure
- Containment pressure is 10.4 psig and stable
- RWST level is 47% and slowly lowering Which ONE of the following completes the statements below?
Containment Spray pumps should be operated in accordance with (1).
Based on the subsequent conditions, (2).
(1) EOP-FR-Z.1 (2) operation with no Containment Spray pumps running should continue (1) EOP-FR-Z.1 (2) both Containment Spray pumps should be started (1) EOP-ECA-1.1 (2) operation with no Containment Spray pumps running should continue (1) EOP-ECA-1.1 (2) both Containment Spray pumps should be started A.
B.
C.
D.
81
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 82. Given the following plant conditions:
- The unit is operating at 80% power
- The crew is implementing AOP-012, Partial Loss of Condenser Vacuum
- Condenser vacuum is 4" Hg absolute and degrading
- All Circulating Water pumps are running Subsequently:
- A tube rupture develops in the 'A' Steam Generator
- The crew enters EOP-E-3, Steam Generator Tube Rupture
- The 'B' and 'C' MSIVs are shut when the 'A' MSIV fails to shut
- Condenser vacuum stabilizes at 6" Hg absolute Which ONE of the following completes the statements below concerning the RCS cooldown?
The crew will (1) and conduct the cooldown by dumping steam to (2).
PROCEDURE TITLE:
EOP-ECA-3.1, SGTR With Loss of Reactor Coolant: Subcooled Recovery (1) remain in EOP-E-3 (2) atmosphere (1) remain in EOP-E-3 (2) the condenser (1) transition to EOP-ECA-3.1 (2) atmosphere (1) transition to EOP-ECA-3.1 (2) the condenser A.
B.
C.
D.
82
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 83. Given the following plant conditions:
- A release of WGDT 'E' is in progress
- REM-*1WV-3546, WPB Exhaust Stack 5 PIG, is MAGENTA Which ONE of the following completes the statements below?
REM-3546 PIG is inoperable due to a (1) failure.
Obtaining grab samples once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzing for radioactivity (2)
REQUIRED with the release in progress.
(Reference provided)
(1) RM-80 equipment (2) is (1) RM-80 equipment (2) is NOT (1) DICSP communication (2) is (1) DICSP communication (2) is NOT A.
B.
C.
D.
83
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 84. Given the following plant conditions:
- A fire in the Main Control Room (MCR) occurs
- The crew enters AOP-004, Remote Shutdown, trips the Reactor, and proceeds to the Auxiliary Control Panel (ACP)
Which ONE of the following completes the statements below?
NFP-805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, analyses assume the operator has (1) minutes to transfer control from the MCB to the ACP from the SM's decision to abandon the MCR.
Following completion of the transfer, Reactor trip conditions will be ensured at the ACP initially using (2).
(1) 10 (2) one Wide Range Neutron Flux Monitor (NI-60B2) until off-scale low then using one Source Range Flux Monitor (NI-60A2)
(1) 10 (2) two redundant Intermediate Range Detectors (NI-35 & NI-36) until off-scale low then using two redundant Source Range Detectors (NI-31 & NI-32)
(1) 20 (2) one Wide Range Neutron Flux Monitor (NI-60B2) until off-scale low then using one Source Range Flux Monitor (NI-60A2)
(1) 20 (2) two redundant Intermediate Range Detectors (NI-35 & NI-36) until off-scale low then using two redundant Source Range Detectors (NI-31 & NI-32)
A.
B.
C.
D.
84
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 85. The crew is implementing EOP-FR-Z.2, Response to Containment Flooding.
Which ONE the following completes the statements below in accordance with the WOG background document for EOP-FR-Z.2?
The basis for obtaining Containment sump activity samples is to determine if (1).
A transition from EOP-FR-Z.2 to the procedure and step in effect is allowed (2).
(1) ESW to the Containment Fan Coolers should be isolated (2) ONLY after the condition causing the orange path has been corrected (1) ESW to the Containment Fan Coolers should be isolated (2) after completion of the required actions in EOP-FR-Z.2 even if the associated orange path still exists (1) sump water can be transferred to tanks outside containment (2) ONLY after the condition causing the orange path has been corrected (1) sump water can be transferred to tanks outside containment (2) after completion of the required actions in EOP-FR-Z.2 even if the associated orange path still exists A.
B.
C.
D.
85
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 86. Given the following plant conditions:
- The unit is shutdown
- RCS temperature is 375°F
- OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1 - 4, has just been completed CSIP 'A' performance data is as follows:
- Discharge pressure is 2485 psig
- Operating suction pressure is 25 psig Which ONE of the following completes the statements below?
In accordance with Technical Specifications, a MINIMUM of (1) CSIP(s) is(are) required to OPERABLE for the plant conditions above.
Following the review of its performance data, the CRS (2) required to declare CSIP 'A' INOPERABLE.
(Reference provided)
(1) one (2) is (1) one (2) is NOT (1) two (2) is (1) two (2) is NOT A.
B.
C.
D.
86
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 87. Given the following plant conditions:
- The unit is operating at 100% power
- ALB-009-8-1, Pressurizer Relief Tank High-Low Level Press or Temp, is in alarm
- Pressurizer Relief Tank parameters are as follows:
- Level is 75%
- Temperature is 130°F
- Pressure is 10 psig Which ONE of the following completes the statements below?
One possible cause for the alarm could be excessive (1).
Based on the indications above, the crew will implement OP-100, Reactor Coolant System, (2).
(1) leakoff from RCP B #2 seal (2) Section 8.2, Venting the Pressurizer Relief Tank (1) leakoff from RCP B #2 seal (2) Section 8.5, Recirculating the Pressurizer Relief Tank (1) leakby of 1CS-10, Letdown Line Relief (2) Section 8.2, Venting the Pressurizer Relief Tank (1) leakby of 1CS-10, Letdown Line Relief (2) Section 8.5, Recirculating the Pressurizer Relief Tank A.
B.
C.
D.
87
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 88. Given the following plant conditions:
- The unit is in Mode 4
- GP-007, Normal Plant Cooldown Mode 3 to Mode 5 is being implemented
- All RCPs are running Subsequently:
- ALB-005-1-2A, RCP THERM BAR HDR HIGH FLOW, alarms
- The crew enters AOP-014, Loss of Component Cooling Water
- 1CC-252, RCP Thermal Barriers Flow Control, indicates OPEN
- FI-685, RCP Therm Barrier CCW Hdr Flow, reads 195 gpm locally Which ONE of the following completes the statements below?
1CC-252 will shut when CCW flow FIRST rises to (1) gpm.
The crew will use (2) to isolate the CCW System leakage.
(1) 198 (2) Section 3.1, Leakage into CCW System (1) 198 (2) Section 3.2, Leakage from CCW System (1) 245 (2) Section 3.1, Leakage into CCW System (1) 245 (2) Section 3.2, Leakage from CCW System A.
B.
C.
D.
88
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 89. Given the following plant conditions:
- The unit is operating at 100% power
- A release from the CST pit to the Storm Drains is in progress Subsequently:
- REM-01MD-3530, Tank Area Drain Pumps Monitor, goes into HIGH ALARM
- Health Physics determines that the alarm is NOT valid Which ONE of the following completes the statements below?
When the HIGH ALARM was received on REM-1MD-3530, the Tank Area Drain Transfer Pump (1) automatically trip.
The effluent release via this pathway may continue using (2).
(1) did (2) AOP-005, Radiation Monitoring System (1) did (2) OWP-RM, Radiation, Effluent, and Explosive Gas Monitoring (1) did NOT (2) AOP-005, Radiation Monitoring System (1) did NOT (2) OWP-RM, Radiation, Effluent, and Explosive Gas Monitoring A.
B.
C.
D.
89
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 90. Given the following plant conditions:
- The unit is in Mode 6
- Containment Pre-Entry Purge is in service
- The Equipment Hatch cover has been removed
- Core offload is in progress in accordance with GP-009, Refueling Cavity Fill, Refueling and Drain of the Refueling Cavity Modes 5-6-5 Subsequently:
- ALB-028-3-3, Containment Pre-Entry Pur Exhaust Fans Low Flow - O/L, alarms
- The BOP verifies the following:
- The running pre-entry exhaust fan has tripped
- The associated pre-entry makeup fan continues to run
- The Shift Manager directs the suspension of fuel movement Which ONE of the following completes the statements below?
A slight (1) in Refueling Cavity level may be observed until the running pre-entry makeup fan is secured.
In accordance with GP-009, fuel movement may resume once evaluated and judged acceptable by the Shift Manager with concurrence of (2).
(1) rise (2) the SRO-Fuel Handling (1) rise (2) Fleet Reactor Services (1) reduction (2) the SRO-Fuel Handling (1) reduction (2) Feet Reactor Services A.
B.
C.
D.
90
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 91. Given the following plant conditions:
- A unit startup is in progress
- Reactor power is 32%
Subsequently:
- Instrument Bus IDP-1B-SIV de-energizes due to fault in PIC-CAB-4
- Instrument Bus IDP-1B-SIV is re-energized but PIC-CAB-4 remains de-energized while repairs are made Which ONE of the following completes the statements below?
The automatic Pressurizer Level Control System (1) impacted by the loss of Instrument Bus SIV.
Assuming repairs to PIC-CAB-4 were completed in fifteen (15) hours, a unit shutdown to Mode 3 (2) REQUIRED in accordance with Technical Specifications.
(Reference provided)
(1) was (2) was (1) was (2) was NOT (1) was NOT (2) was (1) was NOT (2) was NOT A.
B.
C.
D.
91
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 92. Given the following plant conditions:
- The unit is in Mode 6 with core reload in progress
- Refueling Cavity Level is at 23 6
- 'A' and 'B' RHR pumps are in operation in Shutdown Cooling mode Subsequently:
- The 'B' RHR Pump trips on overcurrent Which ONE of the following completes the statements below in accordance with Technical Specification 3.9.8 - Residual Heat Removal and Coolant Circulation?
Core reload (1) continue.
The bases for the LCO is to ensure that sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below (2) °F.
(1) may (2) 140 (1) may (2) 200 (1) may NOT (2) 140 (1) may NOT (2) 200 A.
B.
C.
D.
92
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 93. Given the following plant conditions:
- The unit is operating at 100% power
- Normal Containment Purge is in service
- Maintenance will be performed on the Containment Ventilation Isolation (Area)
Radiation Monitors during the shift Which ONE of the following completes the statements below?
In accordance with OWP-RM-02, Containment Ventilation Isolation (Area) Radiation Monitors, a MINIMUM of (1) radiation monitors must remain OPERABLE to allow Normal Containment Purge to remain in service.
In accordance with Technical Specification bases, the OPERABILITY of the primary containment to atmosphere vacuum relief valves ensures that the containment internal pressure does not become more negative than (2).
(1) 2 (2) -1.0 inwc (1) 2 (2) -1.93 psig (1) 3 (2) -1.0 inwc (1) 3 (2) -1.93 psig A.
B.
C.
D.
93
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 94. Given the following plant conditions:
- The crew is implementing EOP-ECA-0.0, Loss of All AC Power
- The operators are currently performing an RCS cooldown to protect the RCP seals Which ONE of the following completes the statements below?
The RCS cooldown is limited to a MAXIMUM rate of (1) °F/HR.
If offsite power becomes available during the cooldown, the CRS should direct the control board operators to perform Attachment 1, Restoration of Offsite Power to Emergency Buses, (2) the cooldown.
(1) 70 (2) in parallel with (1) 70 (2) following completion of (1) 100 (2) in parallel with (1) 100 (2) following completion of A.
B.
C.
D.
94
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 95. Given the following plant conditions:
- The unit is in Mode 3
- The 'A' Motor Driven Auxiliary Feedwater (MDAFW) Pump is feeding the SGs Which ONE of the following completes the statements below?
Shutting (1) would render BOTH MDAFW pumps inoperable.
In accordance with the bases for Technical Specification 3.7.1.2, Auxiliary Feedwater System, the Auxiliary Feedwater System is required to mitigate (2) accident(s).
(1) FK-2051-1A1 SA, AFW FW A Regulator 1AF-49 (2) ONLY a Loss of Normal Feedwater (1) FK-2051-1A1 SA, AFW FW A Regulator 1AF-49 (2) BOTH Loss of Normal Feedwater and Feed Line break (1) 1AF-55 SB, Aux FW A Isolation (2) ONLY a Loss of Normal Feedwater (1) 1AF-55 SB, Aux FW A Isolation (2) BOTH Loss of Normal Feedwater and Feed Line break A.
B.
C.
D.
95
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 96. Given the following plant conditions:
- A Fire Protection System piping rupture occurs in the RAB
- 1FP-208 and 1FP-211, RAB 236 Riser Header Sectionalizing Valves, are shut to isolate the rupture
- FPP-013, Fire Protection - Minimum Requirements, Mitigating Actions and Surveillance Requirements, is entered to determine mitigating actions Which ONE of the following identifies the number of NONFUNCTIONAL fire hose stations that require mitigating actions to be completed within ONE (1) hour?
(Reference provided) 0 1
2 4
A.
B.
C.
D.
96
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 97. With unit operating at 100% power, the following sequence of events occur:
- 1200 Containment Spray Pump 1A-SA is declared inoperable due to a failed surveillance
- 1227 Containment Spray Pump 1B-SB is also declared inoperable due to the results of a common cause failure analysis
- 1421 Containment Spray Pump 1A-SA is returned to operable status
- 1540 Containment Spray Pump 1B-SB is returned to operable status Which ONE of the following completes the statements below?
The LATEST time that action must be initiated to shut down the unit is (1).
With a unit shutdown in progress, the EARLIEST time the shutdown may be terminated is (2).
(Reference provided)
(1) 1227 (2) 1421 (1) 1227 (2) 1540 (1) 1327 (2) 1421 (1) 1327 (2) 1540 A.
B.
C.
D.
97
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 98. Given the following plant conditions:
- Secondary Waste Sample Tank (SWST) is being aligned for a continuous release
- SWST samples indicate no man-made activity except tritium which is less than its allowable limit Which ONE of the following completes the statements below regarding the release in accordance with OP-120.01.02, Secondary Waste Sample Tank?
The SWST discharge will be sent to the (1).
(2) approval is required to start the release.
(1) Waste Neutralization Basin (2) Shift Manager (1) Waste Neutralization Basin (2) Control Room Supervisor (1) Cooling Tower Discharge (2) Shift Manager (1) Cooling Tower Discharge (2) Control Room Supervisor A.
B.
C.
D.
98
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL
- 99. Given the following plant conditions:
- A seismic event has occurred resulting in a small break LOCA inside Containment
- Damage to the intake structure has resulted in a loss of Emergency Service Water
- Containment pressure is 12 psig and rising
- No Containment Spray pumps are running
- Offsite power remains available The crew is currently implementing EOP-E-1, Loss of Reactor or Secondary Coolant.
Which ONE of the following describes restoration of containment cooling?
PROCEDURE TITLES:
AOP-022, Loss of Service Water EOP-FR-Z.1, Response to High Containment Pressure ISG-CC, Containment Cooling Continue in EOP-E-1 and perform AOP-022 in parallel to establish Service Water to the Containment Fan Cooler Units.
Transition to EOP-FR-Z.1 and perform AOP-022 in parallel to establish Service Water to the Containment Fan Cooler Units.
Continue in EOP-E-1 and perform ISG-CC in parallel to supply cooling water using fire water to the Containment Fan Cooler Units.
Transition to EOP-FR-Z.1 and perform EOP-E-1 in parallel to re-establish containment cooling using the Containment Spray System.
A.
B.
C.
D.
99
2022 NRC SRO WRITTEN EXAM - FINAL SUBMITTAL 100. Given the following:
- A General Emergency has been declared
- The Technical Support Center (TSC) has NOT been activated Which ONE of the completes the statements below in accordance with AD-EP-ALL-0111, Control Room Activation of the ERO?
Initial accountability must be completed within a MAXIMUM of (1) minutes from the time the General Emergency was declared.
The SM/EC task of approving Protective Action Recommendations (PARs) (2) be delegated until relieved by the TSC/EC.
(1) 30 (2) can (1) 30 (2) can NOT (1) 60 (2) can (1) 60 (2) can NOT A.
B.
C.
D.
You have completed the test!
100
2022 NRC SRO Question 77 (2) 1RH-1 SB 1RH-2 SA 1RH-40 SA 1RH-39 SB 1SI-322 SA 1SI-300 SA 1SI-323 SB 1SI-310 SA 1SI-301 SB 1SI-311 SB
2022 NRC SRO Question 77 (2)
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OST-1007 Rev. 54 Page 43 of 57
- Performance Data Sheet 1 of 3 1A-SA CSIP Pump (1C-SAB CSIP Pump)
INSTRUCTIONS
- 1.
IF pump hydraulic data does not meet Acceptance Criteria THEN PERFORM the following:
- a.
DECLARE the pump INOPERABLE.
- b.
INITIATE an NCR.
NOTE 1:
CALCULATE Total Flow as follows:
RCP 1A Seal Injection Flow + RCP 1B Seal Injection Flow +
RCP 1C Seal Injection Flow + Charging Flow = Total Flow
+ + + =
7.1.10.a 7.1.10.b 7.1.10.c 7.1.11 7.1.12 NOTE 2:
CALCULATE Differential Pressure as follows:
Discharge Pressure - Operating Suction Pressure = Differential Pressure
- =
7.1.18 7.1.19 7.1.20
- CIRCLE the source of the Reading Step Parameter Instrument Reading Acceptance Criteria Ref. Val.
7.1.2.c Idle Suction Pressure Test Instrument 13 psig 7.1.10.a RCP 1A Seal Flow FCS0130/
FI-130A
- N/A 7.1.10.b RCP 1B Seal Flow FCS0127/
FI-127A
- N/A 7.1.10.c RCP 1C Seal Flow FCS0124/
FI-124A
- N/A 7.1.11 Charging Flow FCS0122/
FI-122A.1/
ultrasonic flow rate meter installed in Step 7.1.4.b
- 30 gpm 7.1.12 Total Flow NOTE 1 105 to 110 gpm 106.9 gpm (107.5 gpm) 7.1.18 Discharge Pressure Test Instrument N/A 7.1.19 Operating Suction Pressure Test Instrument 13 psig 7.1.20 Differential Pressure NOTE 2 2471 to 2988.1 psid (2471 to 2959 psid) 2716.5 psid (2690 psid) 7.1.25.j Balance line flow Ultrasonic flowmeter N/A (Trending purposes only)
SRO QUESTION 86 (11)
OST-1007 Rev. 54 Page 44 of 57
- Performance Data Sheet 2 of 3 1A-SA Boric Acid Transfer Pump INSTRUCTIONS
- 1.
IF pump hydraulic data does not meet Acceptance Criteria THEN PERFORM the following:
- a.
DECLARE the pump INOPERABLE.
- b.
INITIATE an NCR.
NOTE 3:
CALCULATE Differential Pressure as follows:
Discharge Pressure - Operating Suction Pressure = Differential Pressure
- =
7.2.35 7.2.36 7.2.38
OST-1007 Rev. 54 Page 45 of 57
- Performance Data Sheet 3 of 3 1A-SA Boric Acid Transfer Pump (continued)
NOTE 4:
Quarterly test acceptance criteria.
NOTE 5:
IF PMID 22958-03 is due, USE 2-Year CPT acceptance criteria. This test satisfies the quarterly test.
NOTE 6:
In the event the quarterly pump pressure differential reading exceeds 2-Year CPT acceptance criteria but remains within quarterly acceptance criteria, the pump remains operable. Engineering/IST will evaluate as part of its trending program.
NOTE 7
- 1. IF pump hydraulic data is outside the Acceptable Range but within the Alert Range:
- a.
INITIATE an STR to direct the Surveillance Testing Scheduling Coordinator to double the testing frequency of the pump.
- b.
INITIATE an NCR.
- c.
RECORD the STR and NCR numbers in the Comments section.
- 2. IF pump hydraulic data meets the Required Action Criteria:
- a. DECLARE the pump INOPERABLE.
- b. INITIATE an NCR.
- CIRCLE the source of the Reading.
Step Parameter Instrument Reading Acceptance Criteria Ref. Values 7.2.14 Idle Suction Pressure Test Instrument
@ 1CS-534 5 psig 7.2.16 Boric Acid Pump 1B-SB Idle Disch Press PI-01CS-0110SW N/A (Trending Purposes Only) 7.2.26 FK-113 Demand Output FK-113 N/A (Trending Purposes Only) 7.2.29 FK-113 Demand Output FK-113 N/A (Trending Purposes Only) 7.2.33 Flow Rate FCS0113A/
FR-113
- 34 to 36 gpm 35.1 gpm 7.2.35 Operating Discharge Pressure Test Instrument
@ 1CS-535-V1 N/A 7.2.36 Operating Suction Pressure Test Instrument
@ 1CS-534 5 psig 7.2.37 Boric Acid Pump 1B-SB Idle Disch Press PI-01CS-0110SW N/A (Trending Purposes Only) 7.2.38 Differential Pressure Calculation NOTE 4 and NOTE 6 99.18 to 121.22 psid 110.2 psid PMI 22958-03 2-Year CPT NOTE 5 and NOTE 7 102.49 to 113.5 psid Acceptable Range 99.18 to <102.49 psid Alert Range
< 99.18 or > 113.5 psid Required Action Range 110.2 psid
SRO QUESTION 91 (16)
SHEARON HARRIS - UNIT 1 3/4 3-17 Amendment No. 154 INSTRUMENTATION ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within its limit specified in the Technical Specification Equipment List Program, plant procedure PLP-106, at the frequency specified in the Surveillance Frequency Control Program.
SHEARON HARRIS - UNIT 1 3/4 3-18 Amendment No.
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO. OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 1.
Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Isolation, Start Diesel Generators, Containment Ventilation Isolation, Phase A Containment Isolation, Start Auxiliary Feedwater System Motor-Driven Pumps, Start Containment Fan Coolers, Start Emergency Service Water Pumps, Start Emergency Service Water Booster Pumps)
- a. Manual Initiation 2
1 2
1, 2, 3, 4 18
- b. Automatic Actuation Logic and Actuation Relays 2
1 2
1, 2, 3, 4 14
- c. Containment Pressure--High-1 3
2 2
1, 2, 3, 4 26
- d. Pressurizer Pressure--Low 3
2 2
1, 2, 3#
19
- e. Steam Line Pressure--Low 3/steam line 2/steam line in any steam line 2/steam line 1, 2, 3#
19
SHEARON HARRIS - UNIT 1 3/4 3-21 Amendment No.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO. OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 3.
Containment Isolation (Continued)
(1) RCS Leak Detection (normal purge) 1 See Table 3.3-6, Item 1b1, for initiating functions and requirements.
(2) Preentry Purge Detector 1
See Table 3.3-6, Item 1b2, for initiating functions and requirements.
- c. Airborne Particulate Radioactivity (1) RCS Leak Detection (normal purge) 1 See Table 3.3-6, Item 1C1, for initiating functions and requirements.
(2) Preentry Purge Detector 1
See Table 3.3-6, Item 1C2, for initiating functions and requirements.
- 5) Manual Phase "A" Isolation See Item 3.a.1) above for Manual Phase "A" Isolation initiating functions and requirements.
4.
Main Steam Line Isolation
- a. Manual Initiation
- 1) Individual MSIV Closure 1/steam line 1/steam line 1/operating steam line 1, 2, 3, 4 23
- 2) System 2
1 2
1, 2, 3 27
SHEARON HARRIS - UNIT 1 3/4 3-22 Amendment No.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO. OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 4.
Main Steam Line Isolation (Continued)
- b. Automatic Actuation Logic and Actuation Relays 2
1 2
1, 2, 3, 4 14
- c. Containment Pressure--High-2 3
2 2
1, 2, 3 26
- d. Steam Line Pressure--Low See Item 1.e. above for Steam Line Pressure--Low initiating functions and requirements.
- e. Negative Steam Line Pressure Rate--High 3/steam line 2 in any steam line 2/steam line 3***, 4***
19 5.
Turbine Trip and Feedwater Isolation
- a. Automatic Actuation Logic and Actuation Relays 2
1 2
1, 2 24
- b. Steam Generator Water Level--High-High (P-14) 4/stm. gen.
2/stm. gen. in any stm. gen.
3/stm. gen. in each stm. gen.
1, 2 19
- c. Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.
SHEARON HARRIS - UNIT 1 3/4 3-24 Amendment No.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO. OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 6.
Auxiliary Feedwater (Continued)
- g. Steam Line Differential Pressure--High 3/steam line 2/steam line twice with any steamline low 2/steam line 1, 2, 3 26 Coincident With Main Steam Line Isolation (Causes AFW Isolation) See Item 4. above for all Steam Line Isolation initiating functions and requirements 7.
Safety Injection Switchover to Containment Sump
- a. Automatic Actuation Logic and Actuation Relays 2
1 2
1, 2, 3, 4 14
- b. RWST Level--Low-Low 4
2 3
1, 2, 3, 4 16 Coincident With Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.
8.
Containment Spray Switchover to Containment Sump
- a. Automatic Actuation Logic and Actuation Relays 2
1 2
1, 2, 3, 4 14
SHEARON HARRIS - UNIT 1 3/4 3-25 Amendment No. 179 TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO. OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION
- 8.
Containment Spray Switch-over to Containment Sump (Continued)
- b. RWST--Low Low See Item 7.b. above for all RWST--Low Low initiating functions and requirements.
Coincident With Containment Spray See Item 2 above for all Containment Spray initiating functions and requirements.
- 9.
Loss-of-Offsite Power
- a. 6.9 kV Emergency Bus--Undervoltage Primary 3/bus 2/bus 2/bus 1, 2, 3, 4 15a
- b. 6.9 kV Emergency Bus--Undervoltage Secondary 3/bus 2/bus 2/bus 1, 2, 3, 4 15a
- 10.
Engineered Safety Features Actuation System Interlocks
- a. Pressurizer Pressure, P-11 3
2 2
1, 2, 3 20 Not P-11 3
2 2
1, 2, 3 20
- b. Low-Low Tavg, P-12 3
2 2
1, 2, 3 20
- c. Reactor Trip, P-4 2
2 2
1, 2, 3 22
- d. Steam Generator Water Level, P-14 See Item 5.b. above for all P-14 initiating functions and requirements.
SHEARON HARRIS - UNIT 1 3/4 3-26 Amendment No.
TABLE 3.3-3 (Continued)
TABLE NOTATIONS
- Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock)
Setpoint.
- During CORE ALTERATIONS or movement of irradiated fuel in containment, refer to Specification 3.9.9.
- Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.
ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.
ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 15a - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. With less than the minimum channels OPERABLE, operation may proceed provided the minimum number of channels is restored within one hour, otherwise declare the affected diesel generator inoperable. When performing surveillance testing of either primary or secondary undervoltage relays, the redundant emergency bus and associated primary and secondary relays shall be OPERABLE.
ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the Containment Purge Makeup and Exhaust Isolation valves are maintained closed while in MODES 1, 2, 3 and 4 (refer to Specification 3.6.1.7). For MODE 6, refer to Specification 3.9.4.
ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SHEARON HARRIS - UNIT 1 3/4 3-27 Amendment No.
TABLE 3.3-3 (Continued)
ACTION STATEMENTS (Continued)
ACTION 19 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk-Informed Completion Time Program, and b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.
ACTION 20 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 21 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 23 - With the number of OPERABLE channels less than the Total Number of Channels, declare the associated equipment inoperable and take the appropriate ACTION required in accordance with the specific equipment specification.
ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 25 - During CORE ALTERATIONS or movement of irradiated fuel within containment, comply with the ACTION statement of Specification 3.9.9.
ACTION 26 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.
SHEARON HARRIS - UNIT 1 3/4 3-27a Amendment No.
TABLE 3.3-3 (Continued)
ACTION STATEMENTS (Continued)
ACTION 27 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 37 of 160 6.4 Fire Hose Stations 6.4.1 Functionality NOTE x
Hose stations that are the primary means of fire suppression are annotated on, Fire Hose Stations.
The fire hose stations listed in Attachment 2, Fire Hose Stations shall be FUNCTIONAL when equipment in the areas protected by the fire hose stations is required to be FUNCTIONAL.
6.4.2 Mitigating Action
- 1.
With one or more of the required fire hose stations NONFUNCTIONAL, restore the NONFUNCTIONAL fire hose station to FUNCTIONAL status, a restoration time limit of 14 days is applicable when the hose station is the primary means of fire suppression.
AND within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, perform one of the following where the NONFUNCTIONAL hose station is the primary means of fire suppression OR within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> where the hose station is NOT the primary means of fire suppression: {8.1.8}............................................. ________
- a.
Provide gated wye(s) on the nearest FUNCTIONAL hose station(s) as follows:.................................................................... ________
x One outlet of the wye shall be connected to the standard length of hose provided for the hose station...... ________
x The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the NONFUNCTIONAL hose station............................................................................... ________
x If the physical routing of the fire hose results in a recognizable hazard to plant personnel, plant equipment, or the hose itself, the fire hose connected in Step 1.a shall be stored in a roll at the outlet of the FUNCTIONAL hose station.............................................. ________
x Place signs above the gated wye(s) to identify the proper hose to be used..................................................... ________
- b.
Place a fire hose cart with a gated wye, a turbojet nozzle (or equivalent) and 150 feet of hose in the proximity of the FUNCTIONAL hose station......................................................... ________
SRO QUESTION 96 (21)
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 38 of 160 6.4.3 Surveillance Requirement Each of the required Fire hose Stations listed in Attachment 2 shall be demonstrated FUNCTIONAL: {8.1.4}
- 1.
At least once per quarter by visual inspection of each accessible hose station to assure all required equipment is at the station.
- 2.
At least once per 18 months by:
- a.
Visually inspecting each hose station not accessible during plant operation to assure all required equipment is at the station.
- b.
Removing, inspecting, and re-racking each hose.
- c.
Visually inspecting all gaskets in couplings and replacing any degraded gaskets.
- 3.
At least once per 3 years by:
- a.
Partially opening each hose station valve to verify valve FUNCTIONALITY and NO flow blockage.
- b.
Conducting a hose hydrostatic test in accordance with NFPA 1962-1979 except that the test pressure shall be at a minimum pressure of 300 psig.
- 4.
Hose stations in containment are only required to be FUNCTIONAL in MODES 5 and 6. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after going to Cold Shutdown, these stations shall be inspected per Step 2 and then once per quarter while in MODES 5 and 6 per Step 1.
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 80 of 160 ATTACHMENT 2 Page 1 of 7
<< Fire Hose Stations >>
NOTE
- 1. These hose stations are the primary means of suppression and are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stations.............................................................................................................................
- 2. Required only during refueling and maintenance outages...............................................
Location Elevation Hose Station ID Hose Rack No.
Note CNMT 221 C-9-11 221-C-4 2
CNMT 221 C-9-10 221-C-12 2
CNMT 221 C-9-12 221-C-19 2
CNMT 236 C-9-7 236-C-4 2
CNMT 236 C-9-9 236-C-12 2
CNMT 236 C-9-8 236-C-19 2
CNMT 261 C-9-5 261-C-4 2
CNMT 261 C-9-4 261-C-12 2
CNMT 261 C-9-6 261-C-19 2
CNMT 286 C-9-1 286-C-4 2
CNMT 286 C-9-3 286-C-12 2
CNMT 286 C-9-2 286-C-19 2
RAB 190 AX-9-32 190-G-16 RAB 190 AX-9-31 190-G-38 RAB 216 AX-9-20 216-G-16 RAB 216 AX-9-18 216-Fz-27 RAB 216 AX-9-19 216-G-38 RAB 216 AX-9-21 216-Gy-13 RAB 236 AX-9-14 236-Fw-43 RAB 236 AX-9-15 236-Gy-13 RAB 236 AX-9-11 236-G-16 RAB 236 AX-9-13 236-Fz-27 RAB 236 AX-9-9 236-D-27 RAB 236 AX-9-12 236-G-38 RAB 236 AX-9-16 236-Kz-31
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 81 of 160 ATTACHMENT 2 Page 2 of 7
<< Fire Hose Stations >>
NOTE
- 1. These hose stations are the primary means of suppression and are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stations.............................................................................................................................
- 2. Required only during refueling and maintenance outages...............................................
Location Elevation Hose Station ID Hose Rack No.
Note RAB 236 AX-9-8 236-C-39 RAB 236 AX-9-42 236-Fw-43 RAB 236 AX-9-17 236-Jz-43 RAB 236 AX-9-10 236-E-15 RAB 236 AX-9-41 236-Jz-43 RAB 236 AX-9-43 236-B-44 RAB 236 AX-9-44 236-C-43 RAB 261 AX-9-33 261-GY-13 RAB 261 AX-9-1 261-E-15 RAB 261 AX-9-6 261-G-16 RAB 261 AX-9-2 261-D-27 RAB 261 AX-9-35 261-Kz-31 RAB 261 AX-9-7 261-G-38 RAB 261 AX-9-3 261-C-39 RAB 261 AX-9-4 261-Fw-42 RAB 261 AX-9-5 261-Jz-43 RAB 261 AX-9-34 261-Fw-43 RAB 286 AX-9-22 286-C-15 1
RAB 286 AX-9-23 286-E-15 1
RAB 286 AX-9-25 286-E-38 1
RAB 286 AX-9-24 286-C-39 1
RAB 286 AX-9-37 286-G-16 RAB 286 AX-9-36 286-Jv-41 RAB 286 AX-9-26 286-Fw-42 RAB 286 AX-9-38 286-Jv-45 RAB 286 AX-9-27 286-Fw-44
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 82 of 160 ATTACHMENT 2 Page 3 of 7
<< Fire Hose Stations >>
NOTE
- 1. These hose stations are the primary means of suppression and are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stations.............................................................................................................................
- 2. Required only during refueling and maintenance outages...............................................
Location Elevation Hose Station ID Hose Rack No.
Note RAB 286 AX-9-46 286-D-45 RAB 305 AX-9-28 305-C-39 1
RAB 305 AX-9-30 305-I-41 1
RAB 305 AX-9-29 305-Fw-43 1
RAB 305 AX-9-45 305-I-45 RAB 324 AX-9-39 324-I-41 RAB 324 AX-9-40 324-I-45 FHB 216 FH-9-62 216-L-41 FHB 216 FH-9-45 216-L-45 FHB 216 FH-9-46 216-L-71 FHB 236 FH-9-61 236-L-41 FHB 236 FH-9-60 236-L-45 FHB 236 FH-9-47 236-L-71 FHB 261 FH-9-58 261-L-41 FHB 261 FH-9-59 261-L-45 FHB 261 FH-9-48 261-N-73 FHB 261 FH-9-49 261-M-75y FHB 286 FH-9-53 286-L-27 FHB 286 FH-9-54 286-N-36 FHB 286 FH-9-52 286-L-43 FHB 286 FH-9-55 286-N-51 FHB 286 FH-9-51 286-L-65 FHB 286 FH-9-56 286-N-71 FHB 286 FH-9-50 286-L-75Y DGB 261 DG-9-3 261-C-2 DGB 261 DG-9-1 261-B-1
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 83 of 160 ATTACHMENT 2 Page 4 of 7
<< Fire Hose Stations >>
NOTE
- 1. These hose stations are the primary means of suppression and are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stations.............................................................................................................................
- 2. Required only during refueling and maintenance outages...............................................
Location Elevation Hose Station ID Hose Rack No.
Note DGB 261 DG-9-2 261-B-2
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 84 of 160 ATTACHMENT 2 Page 5 of 7
<< Fire Hose Stations >>
Location Elevation Hose Station ID Hose Rack No.
Note DGB 261 DG-9-4 261-C-4 DGB 261 DG-9-5 261-A-4 DGB 261 DG-9-6 261-B-4 DGB 261 DG-9-7 261-A-5 DGB 261 DG-9-8 261-B-5 WPB 211 WP-9-97 211-S-9 WPB 211 WP-9-101 211-Pw-3 WPB 211 WP-9-104 211-H-3 WPB 211 WP-9-107 211-Jy-9 WPB 211 WP-9-109 211-My-9 WPB 216 WP-9-91 216-Iy-13z WPB 216 WP-9-94 216-My-13z WPB 216 WP-9-96 216-Qz-13z WPB 236 WP-9-64 236-Qz-13z WPB 236 WP-9-67 236-Iw-13z WPB 236 WP-9-72 236-Ix-9 WPB 236 WP-9-77 236-Ix-3 WPB 236 WP-9-82 236-Qy-3 WPB 236 WP-9-86 236-Qy-6 WPB 261 WP-9-39 261-Ly-9 WPB 261 WP-9-40 261-My-3 WPB 261 WP-9-46 261-Qy-2 WPB 261 WP-9-48 261-Qy-9 WPB 261 WP-9-50 261-Q-13z WPB 261 WP-9-54 261-Iw-13z WPB 261 WP-9-57 261-Ix-9 WPB 261 WP-9-60 261-H-5 WPB 276 WP-9-25 276-P-9 WPB 276 WP-9-30 276-P-3
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 85 of 160 ATTACHMENT 2 Page 6 of 7
<< Fire Hose Stations >>
Location Elevation Hose Station ID Hose Rack No.
Note WPB 276 WP-9-31 276-Ly-2 WPB 291 WP-9-1 291-Qy-12 WPB 291 WP-9-3 291-P-6 WPB 291 WP-9-5 291-P-3 WPB 291 WP-9-14 291-Ix-12 WPB 291 WP-9-16 291-Jy-6 WPB 291 WP-9-18 291-K-3 TB 240 TB-9-1 240-Av-11 TB 240 TB-9-2 240-Av-30 TB 240 TB-9-25 240-Av-35 TB 261 TB-9-3 261-Av-11 TB 261 TB-9-4 261-Ak-11 TB 261 TB-9-5 261-Av-35 TB 261 TB-9-23 261-Av-42 TB 261 TB-9-24 261-Ay-43 TB 261 TB-9-6 261-Ak-42 TB 261 TB-9-7 261-Aa-35 TB 261 TB-9-8 261-Aa-11 TB 286 TB-9-9 286-Aa-11 TB 286 TB-9-10 286-Aa-35 TB 286 TB-9-11 286-Ak-42 TB 286 TB-9-12 286-Av-11 TB 286 TB-9-13 286-Ak-11 TB 286 TB-9-14 286-Av-35 TB 314 TB-9-21 314-Ay-43 TB 314 TB-9-22 314-Av-42 TB 314 TB-9-15 314-Ay-40 TB 314 TB-9-16 314-Ay-27 TB 314 TB-9-17 314-Ay-11
FIRE PROTECTION - MINIMUM REQUIREMENTS, MITIGATING ACTIONS AND SURVEILLANCE REQUIREMENTS FPP-013 Rev. 111 Page 86 of 160 ATTACHMENT 2 Page 7 of 7
<< Fire Hose Stations >>
Location Elevation Hose Station ID Hose Rack No.
Note TB 314 TB-9-18 314-Aa-27 TB 314 TB-9-19 314-Aa-43 TB 314 TB-9-20 314-Aa-11
Not required to be met for system vent flow paths opened under administrative control.
SHEARON HARRIS - UNIT 1 3/4 6-11 Amendment No.
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s** or in accordance with the Risk-Informed Completion Time Program or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Refer also to Specification 3.6.2.3 Action.
NOTE -----------------------------------------------------------
- One Containment Spray System train is allowed to be inoperable for a total of 7 days to allow for maintenance on the Essential Services Chilled Water System and air handlers supported by the Essential Services Chilled Water System. Prior to exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the compensatory measures described in HNP LAR correspondence letter RA-19-0007 shall be implemented.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:
a.
At the frequency specified in the Surveillance Frequency Control Program by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position*;
b.
By verifying that, on an indicated recirculation flow of at least 1832 gpm, each pump develops a differential pressure of greater than or equal to 186 psi when tested pursuant to the INSERVICE TESTING PROGRAM; c.
At the frequency specified in the Surveillance Frequency Control Program by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation test signal and 2.
Verifying that each spray pump starts automatically on a containment spray actuation test signal.
3.
Verifying that, coincident with an indication of containment spray pump running, each automatic valve from the sump and RWST actuates to its appropriate position following an RWST Lo-Lo test signal.
d.
At the frequency specified in the Surveillance Frequency Control Program by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
e.
At the frequency specified in the Surveillance Frequency Control Program by verifying that containment spray locations susceptible to gas accumulation are sufficiently filled with water.
SRO QUESTION 97 (22)
Answers 0
ID Points Type 1
Answers 0
ID Points Type 49 2022 NRC RO 57 1.00 MCS B
Answers 0