ML042180316

NRC Operating Test Comments for Briadwood Initial Examination - July 2004

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

1. Source Comment Resolution

1. Scenario No. The scenario overview states that about 30 minutes The crew will be pre-briefed.

NRC 04-1 into the scenario, the crew should commence the power decrease. To greatly reduce this time, the Scenario Overview crew should have made preparations for the power Page 2 reduction and reactor shutdown prior to entering the simulator.

2. Scenario No. For Event No. 4, only the RO and SRO should be The BOP will be a surrogate NRC 04-1 given credit for the component failure of a 30 gpm operator. No credit will be leak in 1A Letdown Heat Exchanger. given to the BOP.

Outline Sheet Event No. 4

3. Scenario No. For Event No. 7 (Failure of 1A AF pump to start No credit will be given to NRC 04-1 which leads to a Loss of Heat Sink), this event any member of the crew.

should be considered part of the Major and NO credit Outline Sheet should be given for a component failure.

Event No. 7

4. Scenario No. For Event No. 8 (Failure of Containment Isolation The BOP will be a surrogate NRC 04-1 Valve 1RY8026 to auto close), only the RO and SRO operator. No credit will be should be given for the component failure. given to the BOP.

Outline Sheet Event No. 8

5. Scenario No. The scenario overview states that about 30 minutes The crew will be pre-briefed.

NRC 04-2 into the scenario, the crew should commence the power decrease. To greatly reduce this time, the Scenario Overview crew should have made preparations for the power Page 2 reduction prior to entering the simulator.

6. Scenario No. For Event No. 3, only the RO and SRO should be The BOP will be a surrogate NRC 04-2 given credit for the instrument failure of the 1PT505 operator. No credit will be Turbine Impulse Pressure transmitter. given to the BOP.

Outline Sheet Event No. 3

7. Scenario No. For Event No. 6 (1D MSIV fails closed), this event No credit will be given to NRC 04-2 should be considered the initiating event for the any member of the crew.

Major transient and NO credit should be given for a Outline Sheet component failure.

Event No. 6

8. Scenario No. Add a NOTE for the Examiners that if a PZR PORV Noted.

NRC 04-2 opens before the Reactor is tripped during the ATWS event, to then ask the SRO in a followup question Event No. 7 what the applicable reporting requirements, if any, Page 9 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).

BRAIDWOOD JULY 2004 INITIAL LICENSE EXAM OPERATING EXAM COMMENTS

9. Scenario No. Typo: Near top of page, change AVAILABE TO Changed.

NRC 04-2 AVAILABLE.

Page 12

10. Admin JPM S-103 On page 1, change the K/A Importance from 3.3 to Changed.

3.4 to agree with NUREG-1122.

11. Admin JPM S-104 This JPM has a low level of difficulty. Change Changed.

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.

12. Admin JPM S-104 On page 2 under Task Standards, change 113 Changed.

inverter to 112 inverter (if the surveillances are left as currently written).

13. Admin JPM S-408 This JPM has a low level of difficulty, since a Changed.

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..

14. All Simulator and To facilitate administration of the JPMs by the Not required.

In-Plant JPMs Examiners, on the Cover Sheet (page 1) of each JPM, state whether or not the JPM is an Alternate Path JPM.

15. Simulator JPM Step 3 should be a Critical Step, since determining Not required to be critical SIM-106 the required flow rate of Primary Water is part of the since step 5 is critical.

Task Standard for the JPM

16. Simulator JPM In step 3 change the lower part of the range of the Change not made. Facility SIM-106 desired PW flow rate from 38.3 to 38.2 gpm, since decided their numbers were 2295 /60 = 38.2. acceptable as is.

17. Simulator JPM Step 4 should be a Critical Step, since adjusting the Not required to be critical SIM-106 PW controller to obtain the required flow rate of since step 5 is critical.

Primary Water is implied by the Task Standard for the JPM.

18. Simulator JPM In step 5 change the setting of the thumbwheels from Change made.

SIM-106 1836-1861 (1842) to 2295-2326 (2303) to agree with the amount of PW to be added.

19. Simulator JPM In the Task Standard for the JPM, add: Coordinates Change made.

SIM-P403 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).

BRAIDWOOD JULY 2004 INITIAL LICENSE EXAM OPERATING EXAM COMMENTS

20. In-Plant JPM On page 1 the first Initiating Cue should have the Change made.

IP-202 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.

21. In-Plant JPM On page 3, step 8 of the JPM, add to the CUE the Change made.

IP-202 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.