ML13364A069

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Exam Operating Test Changes
ML13364A069
Person / Time
Site: Fermi DTE Energy icon.png
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 Operating Test JPM A1 1. Need to see how applicant determines HPCI Yes control switch is not in the standby position it is in Perform a CRS Short oil pump is inop. Is it just control switch miss the OFF RESET position and an alarm will be lit Term Relief positioned??? above the main control panel.

JPM A2 1. Shouldnt need to tell applicant torus water 1. Cue changed to add If asked, Torus water Perform Torus Water level is 0 inches. Let applicant determine this level indicates 0 inches.

Average parameter. 2. Data will be provided because the data is Temperature Calculation

2. Need to make sure applicants can get the obtained from the aux electric room and not in temperature readings instead of just giving them the main control room.

the data.

JPM A3 1. Remove for potential Tech Spec impact, 1. Left cue as initially suggested to minimize the Evaluate Degraded from initiating cue. No need to focus them on length of the JPM. If cue were altered as Power Sources the TS. suggested it could cause JPM completion time

2. Why isnt assigning SR 3.8.1 to be completed to increase drastically.

part of the critical step??? This needs to be 2. Step 3 to determine SR 3.8.1 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 completed was a critical step. The assignment determine it needs to be done and then make of the task to an RO is implied in step 3 sure it gets done by assigning it to an RO. Step already. The critical step is to identify and 3 should be enhance to add this requirement. ensure that it is completed.

JPM A4 1. Add a follow-up question to this JPM as step I was determined that a follow up question was not Calculate Stay time 4. Who can authorize this dose extension??? necessary for this JPM. Calculation of the dose and determine if received and determination that it exceeded the dose extension is needed.

allowable dose rate was sufficient for this JPM.

JPM A5 1. Step 2. on the standard side of the JPM has the Activate ECOS in wrong phone number. The first number is accordance with EP- correct the second doesnt match the 290 procedure. It should be (615) 844-5611 NOT (615) 986-3719 1 of 5

NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response JPM Sim01 1. No Comments Conduct Control Rod Drive Coupling Integrity Test with Coupling Failure JPM Sim02 1. At step 5 need to make sure that the level Control switch is in 1 Element position.

Transfer Feedwater control switch is repositioned. If it is in 1 Control from Long Element control not a critical step.

Cycle Cleanup to Startup Level Control JPM Sim03 1. Why is the last bullet in the Initiating Cues 1. Cue is necessary to determine that low low set Control Reactor there??? Does RO have to request permission is not working correctly.

Pressure from the to exceed 1093 psig??? 2. The applicant will open the B SRV when he Remote Shutdown Panel

2. At what point is applicant expected to open determines that low low set is not working SRV B??? Will an automatic action occur if he correctly. Pressure will increase until 1135 doesnt open SRV B??? We should have limit when an automatic SRV will begin to cycle.

on this JPM.

JPM Sim04 1. No Comments Recovery of RCIC following a Manual Trip JPM Sim05 1. No Comments Manually Isolate HPCI System JPM Sim06 1. Not sure I like how this JPM is cued. The SRO 1. Licensee informed me that this is actually how Loss 64C and EDG just asks to perform an electrical walkdown. this event would be cued. The SRO would 12 Fails to Start Should we provide them the alarm that the direct an RO to perform an electrical SRO is concerned about??? Or should the walkdown.

applicant be in the sim when 64C trips??? 2. Step 4 was changed to non-critical step.

2. Step 4 is NOT a critical step directing others to take manual control is not a critical step.

JPM Sim07 1. Are there two critical steps on this JPM??? 1. Yes the applicant has to identify the drifting Respond to Multiple control rods before he can initiate the reactor Control Rod Drifts scram.

and RPS Failure 2 of 5

NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response JPM Sim08 1. No Comments Perform Div 2 SGTS Filter and Secondary Containment Isolation Damper Operability Test JPM INP01 1. Why are steps 17 and 18 critical steps??? What 1. Yes, both steps are critical because the power Transfer UPS from do these actions accomplish??? supply will not function correctly unless the Normal to Alternate Mode Switch is in AUTO and the RESET Power using Static Transfer pushbutton is depressed.

Switch JPM INP02 1. Steps 2 and 3 are not adequate. It is not good 1. I was explained to me by the licensee that the RBCCW/EECW to enough to merely lift the lead, the end must expectation for lifting leads includes protection Drywell Isolations then be insulated to ensure no shorting or from unexpected grounds and shorts so no actuations occur. additional wording is necessary.

JPM INP03 1. Step 1 is not a critical step. This is a verify 1. This JPM was replaced because there was only Start up Fuel Pool step. one critical step. The new JPM is acceptable.

Ventilation Exhaust 2. What does depressing the reset pushbutton Radiation Monitor D11-K609A 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???

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NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response Scenarios Scenario 1 a) More detail needs to be added so that operator actions are more a) Added the steps to be taken from clearly detailed. 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 a) Added details such as which control clearly detailed. rod accumulator lights are lit during b) Change SRV that fails OPEN so you have more TS entries. 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 a) Scenario 3 is planned to be utilized clearly detailed. during this exam. Scenario three b) 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.

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NRC Exam Submittal Comments for Fermi 2013 Initial Exam Examiner Comment Facility Action/Response 5 of 5