ML13364A069
| ML13364A069 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/09/2013 |
| From: | Division of Reactor Safety III |
| To: | Detroit Edison, Co |
| Carl Moore | |
| Shared Package | |
| ML11354A438 | List: |
| References | |
| Download: ML13364A069 (5) | |
Text
NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 1 of 5 Operating Test JPM A1 Perform a CRS Short Term Relief
- 1. Need to see how applicant determines HPCI oil pump is inop. Is it just control switch miss positioned???
Yes control switch is not in the standby position it is in the OFF RESET position and an alarm will be lit above the main control panel.
JPM A2 Perform Torus Water Average Temperature Calculation
- 1. Shouldnt need to tell applicant torus water level is 0 inches. Let applicant determine this parameter.
- 2. Need to make sure applicants can get the temperature readings instead of just giving them the data.
- 1. Cue changed to add If asked, Torus water level indicates 0 inches.
- 2. Data will be provided because the data is obtained from the aux electric room and not in the main control room.
JPM A3 Evaluate Degraded Power Sources
- 1. Remove for potential Tech Spec impact, from initiating cue. No need to focus them on the TS.
- 2. Why isnt assigning SR 3.8.1 to be completed part of the critical step??? This needs to be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Applicants should determine it needs to be done and then make sure it gets done by assigning it to an RO. Step 3 should be enhance to add this requirement.
- 1. Left cue as initially suggested to minimize the length of the JPM. If cue were altered as suggested it could cause JPM completion time to increase drastically.
- 2. Step 3 to determine SR 3.8.1 needs to be completed was a critical step. The assignment of the task to an RO is implied in step 3 already. The critical step is to identify and ensure that it is completed.
JPM A4 Calculate Stay time and determine if dose extension is needed.
- 1. Add a follow-up question to this JPM as step
- 4. Who can authorize this dose extension???
I was determined that a follow up question was not necessary for this JPM. Calculation of the dose received and determination that it exceeded the allowable dose rate was sufficient for this JPM.
JPM A5 Activate ECOS in accordance with EP-290
- 1. Step 2. on the standard side of the JPM has the wrong phone number. The first number is correct the second doesnt match the procedure. It should be (615) 844-5611 NOT (615) 986-3719
NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 2 of 5 JPM Sim01 Conduct Control Rod Drive Coupling Integrity Test with Coupling Failure
- 1. No Comments JPM Sim02 Transfer Feedwater Control from Long Cycle Cleanup to Startup Level Control
- 1. At step 5 need to make sure that the level control switch is repositioned. If it is in 1 Element control not a critical step.
Control switch is in 1 Element position.
JPM Sim03 Control Reactor Pressure from the Remote Shutdown Panel
- 1. Why is the last bullet in the Initiating Cues there??? Does RO have to request permission to exceed 1093 psig???
- 2. At what point is applicant expected to open SRV B??? Will an automatic action occur if he doesnt open SRV B??? We should have limit on this JPM.
- 1. Cue is necessary to determine that low low set is not working correctly.
- 2. The applicant will open the B SRV when he determines that low low set is not working correctly. Pressure will increase until 1135 when an automatic SRV will begin to cycle.
JPM Sim04 Recovery of RCIC following a Manual Trip
Should we provide them the alarm that the SRO is concerned about??? Or should the applicant be in the sim when 64C trips???
- 2. Step 4 is NOT a critical step directing others to take manual control is not a critical step.
- 1. Licensee informed me that this is actually how this event would be cued. The SRO would direct an RO to perform an electrical walkdown.
- 2. Step 4 was changed to non-critical step.
JPM Sim07 Respond to Multiple Control Rod Drifts and RPS Failure
- 1. Are there two critical steps on this JPM???
- 1. Yes the applicant has to identify the drifting control rods before he can initiate the reactor scram.
NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 3 of 5 JPM Sim08 Perform Div 2 SGTS Filter and Secondary Containment Isolation Damper Operability Test
- 1. Why are steps 17 and 18 critical steps??? What do these actions accomplish???
- 1. Yes, both steps are critical because the power supply will not function correctly unless the Mode Switch is in AUTO and the RESET pushbutton is depressed.
JPM INP02 RBCCW/EECW to Drywell Isolations
- 1. Steps 2 and 3 are not adequate. It is not good enough to merely lift the lead, the end must then be insulated to ensure no shorting or actuations occur.
- 1. I was explained to me by the licensee that the expectation for lifting leads includes protection from unexpected grounds and shorts so no additional wording is necessary.
JPM INP03 Start up Fuel Pool Ventilation Exhaust Radiation Monitor D11-K609A
- 1. Step 1 is not a critical step. This is a verify step.
- 2. What does depressing the reset pushbutton do??? If all you have to do to start the rad monitor is place mode switch to operate that may be the only critical step for this jpm???
NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 4 of 5 Scenarios Scenario 1 a) More detail needs to be added so that operator actions are more clearly detailed.
a) Added the steps to be taken from procedure 23.109 and 23.110. Also added the steps for placing torus cooling and torus sprays in service.
Scenario 2 a) More detail needs to be added so that operator actions are more clearly detailed.
b) Change SRV that fails OPEN so you have more TS entries.
a) Added details such as which control rod accumulator lights are lit during event #1. Added that both RR pumps are tripped in FS/Q 1 thru 8. Added how DW pneumatics are restored during events 5 & 6. Also added steps required for Terminate and Prevent during event 5 & 6.
b) Changed SRV from C to H so applicant will have identify TS 3.4.3 and 3.5.1.
Scenario 3 a) More detail needs to be added so that operator actions are more clearly detailed.
b) a) Scenario 3 is planned to be utilized during this exam. Scenario three was validated and will be designated as the spare scenario for this exam.
More details similar to the above mentioned details were added to this scenario as well. They are not specified here because the licensee requested that scenario three not be placed in the public domain for two year.
NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 5 of 5