ML113570483

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Initial Exam 2011-302 Draft Administrative Documents
ML113570483
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/21/2011
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
50-335/11-302, 50-389/11-302
Download: ML113570483 (5)


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Date of Examination: 11/17/11 Examination Level (circle one): RO/SRO Operating Test Number: NRC HLC-20A Administrative Topic Type Describe activity to be performed (see Note) Code*

M, R A1 Conduct of Operations Determine time to boil upon loss of Shutdown Cooling, Unit 1.

N, S A2 Conduct of Operations Perform manual RCS inventory balance.

N, S or R A3 Equipment Control Develop ECO for 2B Component Cooling water pump.

M, S or R A4 Radiation Control Determine radiation exposure limits under non emergency conditions.

Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams ( 1; randomly selected)

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 ADMINISTRATIVE JPM

SUMMARY

A1: Determine time to boil upon loss of Shutdown Cooling. Given plant conditions of reduced inventory and time after shutdown, determine time to boil the RCS and the required RCS makeup.

A2: Perform manual RCS inventory balance. Applicant will perform a manual RCS inventory balance on the simulator. The simulator will be turned over at 100% power steady state.

After the Applicant takes the initial data, the simulator will initialize to a new 100% power steady state set of conditions, simulated to 120 minutes after the initial set of data. The Applicant will use this new set of data to complete the final RCS leak rate.

A3: Develop ECO for 2B Component Cooling water pump. Directions to generate an equipment clearance to remove the 2B Component cooling water pump for pump overhaul.

A4: Determine radiation exposure limits under non emergency conditions. Four individuals, two contract personnel and two FPL personnel are assigned to repair the spreader on the refueling machine. Given previous radiation exposure, determine the individuals that can perform the repair without Site VP approval.

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: St. Lucie Date of Examination: 11/17/11 Exam Level (circle one): RO, SRO(I), SRO(U) Operating Test No.: NRC HLC-20A Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1 Respond to loss of RCP Controlled Bleedoff and failed RCP D, E, A, S 4p Seals.

S-2 Restore offsite power with both Diesel Generators in D, E, S, L 6 operation.

S-3 Respond to alarms on SFP monitors D, A, S 7 S-4 Transfer Letdown Level control to the alternate Level Control P, S 2 valve S-5 Start 2C AFW to feed the 2A and 2B SG M, E, L, S, A 4s S-6 Initiate Once Through Cooling M, E, S, A 3 S-7 Emergency Borate using V2504, Refuel to Charging pumps M, E, S, A 1 C-1 Pump ECCS area sumps to RDT post LOCA - Unit 1 D, E, C 5 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 Align U-2 CST to supply 1C AFW pump D, E 4s P-2 Initiate Containment hydrogen purge D, E, R 5 P-3 Perform actions outside Control Room for dropped / D, E, A 1 misaligned CEA - Unit 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

@ All control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / > 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator JPM

SUMMARY

DESCRIPTION S-1 Respond to loss of RCP Controlled Bleedoff and failed RCP Seals.

The Applicant will be directed to respond to loss of RCP controlled bleedoff at 100% power. Applicant will be required to recognize V2505, RCP bleedoff valve is closed and will not open. As a result V2507, bleedoff to Quench Tank will be aligned. Upon opening V2507, three seals on the 2B1 RCP will fail requiring a manual Reactor trip and stopping the 2B1RCP.

S-2 Restore offsite power with both Diesel Generators in operation.

A LOOP has occurred and both Diesel Generators are loaded on their respective busses. Offsite power is now available and direction will be given to restore offsite power to the A side first. The Applicant will be expected to bring offsite power back and stop the 2A Diesel generator.

S-3 Respond to alarms on SFP monitors.

During refueling operations a fuel handling accident occurs. The spent fuel radiation monitors went to high alarm and the ventilation system aligned and started on the Spent Fuel pool. The applicant is directed to use the AOP and verify proper alignment. Various equipment failures are to be noted and corrected by the Applicant.

S-4 Transfer Letdown Level control to the alternate Level Control valve.

The in-service letdown level control valve is operating erratically. Direction will be given to place the alternate level control valve in service.

S-5 Start 2C AFW and feed the 2A and 2B SG Direction will be given to start the 2C AFW pump and feed the 2A and 2B Steam Generator. When the pump is started, it will trip on mechanical overspeed. The applicant will be required to communicate and work with the field operator to reset the overspeed trip and align the pump to feed the 2A and 2B Steam Generators.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S-6 Initiate Once Through Cooling.

A total loss of feedwater has occurred. Direction will be given to initiate Once Through Cooling. Upon attempt to open the block valve on the normally isolated PORV the breaker will trip just as the valve starts to open. Procedure guidance will continue with the lineup using the other PORV by pulling two RPS High Pressure Bistables. When Bistable pulled the PORV with the block valve open will not open. Procedure guidance states continue efforts to open at least one PORV and associated block valve. The Applicant will contact the field operator to reset the breaker on the tripped PORV block valve. Once the breaker is reset the block valve can be opened and Once Through Cooling can be initiated. Although not directly procedurally driven to reset the breaker, OP-1250020, Valve, Breaker, Motor and Instrument Instructions states If breaker trips on a piece of equipment AND is needed to protect the health and safety of the public, Then the breaker may be reset and / or one reclosure attempted. (step 8.3.4)

S-7 Emergency Borate using V2504, Refuel to Charging pumps.

Direction will be given to respond to a reactor trip. The applicant must recognize that two CEAs are not inserted and should emergency borate. When aligning for emergency boration, the emergency borate valve and the gravity feeds will not open. Procedural guidance will be to use V2504, RWT valve to the suction of the Charging Pumps, C-1 Pump ECCS area sumps to RDT post LOCA - Unit 1.

Unit 1 has experienced a LOCA. RAS has occurred and direction is given to align the ECCS area sumps to the RDT IAW 1-EOP-03, LOCA.

P-1 Align U-2 CST to supply 1C AFW pump.

Unit 1 CST is not available due to tornado damage. Direction will be given to align the Unit 2 CST to the suction of the Unit 1, 1C Auxiliary feedwater pump.

P-2 Initiate Containment hydrogen purge.

Uni1 has experienced a large break LOCA. The TSC has requested to align the Hydrogen Purge system in accordance with 1-EOP-99, Appendix N.

P-3 Perform actions outside Control Room for dropped / misaligned CEA - Unit 1.

A CEA has dropped on Unit 1. Attachment 6, CEA Functional test and Operability Determination is being performed. The Applicant will be directed to perform section 3 of Attachment 6. This is performed in the electrical switchgear room. Various malfunctions should be noted and corrected by the Applicant.

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