ML042180316
| ML042180316 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/12/2004 |
| From: | Lanksbury R NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| 50-456/04-301, 50-457/04-301 | |
| Download: ML042180316 (3) | |
Text
BRAIDWOOD JULY 2004 INITIAL LICENSE EXAM OPERATING EXAM COMMENTS Source Comment Resolution 1.
Scenario No.
NRC 04-1 Scenario Overview Page 2 The scenario overview states that about 30 minutes into the scenario, the crew should commence the power decrease. To greatly reduce this time, the crew should have made preparations for the power reduction and reactor shutdown prior to entering the simulator.
The crew will be pre-briefed.
2.
Scenario No.
NRC 04-1 Outline Sheet Event No. 4 For Event No. 4, only the RO and SRO should be given credit for the component failure of a 30 gpm leak in 1A Letdown Heat Exchanger.
The BOP will be a surrogate operator. No credit will be given to the BOP.
3.
Scenario No.
NRC 04-1 Outline Sheet Event No. 7 For Event No. 7 (Failure of 1A AF pump to start which leads to a Loss of Heat Sink), this event should be considered part of the Major and NO credit should be given for a component failure.
No credit will be given to any member of the crew.
4.
Scenario No.
NRC 04-1 Outline Sheet Event No. 8 For Event No. 8 (Failure of Containment Isolation Valve 1RY8026 to auto close), only the RO and SRO should be given for the component failure.
The BOP will be a surrogate operator. No credit will be given to the BOP.
5.
Scenario No.
NRC 04-2 Scenario Overview Page 2 The scenario overview states that about 30 minutes into the scenario, the crew should commence the power decrease. To greatly reduce this time, the crew should have made preparations for the power reduction prior to entering the simulator.
The crew will be pre-briefed.
6.
Scenario No.
NRC 04-2 Outline Sheet Event No. 3 For Event No. 3, only the RO and SRO should be given credit for the instrument failure of the 1PT505 Turbine Impulse Pressure transmitter.
The BOP will be a surrogate operator. No credit will be given to the BOP.
7.
Scenario No.
NRC 04-2 Outline Sheet Event No. 6 For Event No. 6 (1D MSIV fails closed), this event should be considered the initiating event for the Major transient and NO credit should be given for a component failure.
No credit will be given to any member of the crew.
8.
Scenario No.
NRC 04-2 Event No. 7 Page 9 Add a NOTE for the Examiners that if a PZR PORV opens before the Reactor is tripped during the ATWS event, to then ask the SRO in a followup question what the applicable reporting requirements, if any, there are for the plant following the ATWS. Other than Emergency Plan reporting requirements, expect SRO to identify Tech Spec 5.6.4 (associated with reporting PZR PORV challenges in the Monthly Operating Report).
Noted.
BRAIDWOOD JULY 2004 INITIAL LICENSE EXAM OPERATING EXAM COMMENTS 9.
Scenario No.
NRC 04-2 Page 12 Typo: Near top of page, change AVAILABE TO AVAILABLE.
Changed.
10.
Admin JPM S-103 On page 1, change the K/A Importance from 3.3 to 3.4 to agree with NUREG-1122.
Changed.
11.
Admin JPM S-104 This JPM has a low level of difficulty. Change surveillances so that 1BwOSRSR 3.8.1.1 is the one that is NOT acceptable, because an OCB(s) is(are)
NOT available such that on page D-6, the surveillance performed is incorrectly taking credit for two sources of offsite power that are fed from lines on a common tower.
Changed.
12.
Admin JPM S-104 On page 2 under Task Standards, change 113 inverter to 112 inverter (if the surveillances are left as currently written).
Changed.
13.
Admin JPM S-408 This JPM has a low level of difficulty, since a potential loss of the RCS can be determined by more than one method (i.e., by noting that RCS pressure is only 450 psig OR by looking a the Graph of Containment Radiation versus Reactor Coolant System Lost). To ensure that the Graphs of Containment Radiation are reviewed, change the classification on the NARS form from FU1 to FS1, and have the applicant state that the classification should be FA1..
Changed.
14.
All Simulator and In-Plant JPMs To facilitate administration of the JPMs by the Examiners, on the Cover Sheet (page 1) of each JPM, state whether or not the JPM is an Alternate Path JPM.
Not required.
15.
Simulator JPM SIM-106 Step 3 should be a Critical Step, since determining the required flow rate of Primary Water is part of the Task Standard for the JPM Not required to be critical since step 5 is critical.
16.
Simulator JPM SIM-106 In step 3 change the lower part of the range of the desired PW flow rate from 38.3 to 38.2 gpm, since 2295 /60 = 38.2.
Change not made. Facility decided their numbers were acceptable as is.
17.
Simulator JPM SIM-106 Step 4 should be a Critical Step, since adjusting the PW controller to obtain the required flow rate of Primary Water is implied by the Task Standard for the JPM.
Not required to be critical since step 5 is critical.
18.
Simulator JPM SIM-106 In step 5 change the setting of the thumbwheels from 1836-1861 (1842) to 2295-2326 (2303) to agree with the amount of PW to be added.
Change made.
19.
Simulator JPM SIM-P403 In the Task Standard for the JPM, add: Coordinates adjustment of RCS seal injection flows to restore flow to within Tech Spec limits for the 1A CV pump (since this is a Critical Step in the JPM).
Change made.
BRAIDWOOD JULY 2004 INITIAL LICENSE EXAM OPERATING EXAM COMMENTS 20.
In-Plant JPM IP-202 On page 1 the first Initiating Cue should have the following words added at the end to make it agree with the Initiating Cue given to the Applicant (on page 6): that was started on the previous shift.
Change made.
21.
In-Plant JPM IP-202 On page 3, step 8 of the JPM, add to the CUE the following at the end to ensure the CUE agrees with step F.3.4 of the procedure: and the switch has been released and has spring returned to AUTO.
Change made.