ML19290E426
| ML19290E426 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/01/2019 |
| From: | NRC Region 1 |
| To: | Exelon Generation Co |
| Shared Package | |
| ML18347A730 | List: |
| References | |
| EPID L-2019-OLL-0039 | |
| Download: ML19290E426 (29) | |
Text
TQ-AA-151-F11 Revision 01 Page 1 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Date: 07/31/2019 Submitted By:
Buckingham, Story, Whitman RO SRO Exam Section(s):
Written /
Walk-Through /
Simulator Scenario Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks Question #2 Caroline Buckingham (55-73009)
B is incorrect. A containment isolation from the control board gives a T-signal to close 427, which then reopens on the loss of air to containment caused by the same signal.
Initiating a CI from the control board would have an end result of 426 being open.
CI does not prevent 427 from being re-opened, as its failure position on a loss of air is open.
There is no correct answer, remove question from Exam ATT-11.0 33013-1887 The stem clearly states that the question is asking what signal prevents OPEN operation, NOT valve operation on loss of Instrument Air.
Enhance wording in 2nd part of question statement by changing re-open to operate Recommend NO change to Exam.
Question to be revised prior to entering into Ginna Exam question bank.
Question #8 John Whitman (55-63285)
Multiple correct answers since S/G pressure less than RCS pressure results in S/G temperature less than RCS temperature Accept both answers (B and D) as correct ECA-1.1 Recommend changing Exam to both answers B and D as correct.
Question to be revised prior to entering into Ginna Exam question bank.
Question #37 Tim Story (55-73018)
Selected backup heaters are energized because the question stem discusses change in Accept both answers (A and D) as correct P-10, 5.3.3.3.c.5 NO changes, question stem provides all the requisite data, including rate of change for PRZR
TQ-AA-151-F11 Revision 01 Page 2 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks PRZR level, but controller 428 is failing high and in accordance with P-10, 5.3.3.3.c.5 Backup Heaters ON if level fails greater than 5% above programmed.
level and pressure, required to correctly answer Recommend NO change to Exam.
Question to be revised prior to entering into Ginna Exam question bank.
Question #61 Caroline Buckingham (55-73009)
C is incorrect. The siphon break is NOT at approximately normal SFP level. In accordance with UFSAR, 9.1.3.4.2, the siphon break hole is located approximately 18 in.
below the normal SFP water level. The answer for C and UFSAR definition do not match.
There is no correct answer, remove question from Exam UFSAR, 9.1.3.4.2 33013-2835 33013-0638 S-9M, Att 1, NOTE page 13 AR-K-29 Question wording is not specific enough; therefore, there is no correct answer. UFSAR, Section 9.1.3.4.2 states a 1/4-in diameter drilled hole in the discharge piping, located approximately 18 in.
below the normal spent fuel pool (SFP) water level, anti-siphoning protection UFSAR, Section 9.1.3.2.2 states The SFP cooling water return line, which terminates at the bottom of the SFP, contains a passive siphon breaker device near the normal SFP water level so that the pool water cannot be
TQ-AA-151-F11 Revision 01 Page 3 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks siphoned.
Recommend NO change to Exam.
Question to be revised prior to entering into Ginna Exam question bank.
Question #67 John Whitman (55-63285)
The NOTE on page 10 of O-1.2 gives examples of alternate power level indications, but is not intended to be an all inclusive list. Step 6.8.1 shows that RCS temperature is an acceptable indication of power.
All answers are correct, remove question from Exam O-1.2 Steam Dumps are placed in service in pressure control mode at 1005 psig in step 6.7.9 of O-1.2, the difference between Tavg and 547F gives an alternate indication of Reactor power. Furthermore, step 6.8.1 of O-1.2 states WHILE monitoring diverse indications of Reactor power level (pressure, flows AND temperature),
CONTINUE power ascension using control rods AND steam dumps.
specifically calling out temperature as a diverse indication of Reactor power. This means that all four indications presented in the question stem are indications that can be used to confirm
TQ-AA-151-F11 Revision 01 Page 4 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks Reactor power.
Recommend NO change to Exam.
Question to be revised prior to entering into Ginna Exam question bank.
Question #81 Caroline Buckingham (55-73009)
D is also correct. ECA-1.1, Step 7 directs the operator to establish and maintain cooldown rate in cold legs less than 100°F/HR to cold shutdown conditions, per the header of the step.
Therefore, it is maintained and monitored continuously, including during the depressurization.
Accept both answers (B and D) as correct ECA-1.1, Step 7 ECA-1.1, Step 7.a states Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100°F/HR. A-503.1, Section 3.3 states Maintain implies a continuing action.
Therefore, Tcold would also be monitored during S/G depressurization.
Recommend changing Exam to both answers B and D as correct.
Question to be revised prior to entering into Ginna Exam question bank.
Question #100 Caroline Buckingham (55-73009)
B is a responsibility delegated to the Communicator. Also, verbiage in stem of question asks about designating authority, versus the procedure Accept both answers (B and D) as correct EP-AA-1000 Per EP-AA-1000 Section B.4, Non-delegable responsibilities include the following functions:
Event classification.
Protective Action
TQ-AA-151-F11 Revision 01 Page 5 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks EP-AA-1000, where it asks if the responsibility itself can be designated.
Communicator does perform notifications.
Recommendations (PARS) for the general public.
Notification of offsite authorities (approval of state/local and NRC notifications).
Authorization of emergency exposure controls in excess of 5 Rem TEDE and the issuance of potassium iodide (KI),
for Exelon Nuclear emergency workers per EPA-400.
Because the parenthetical approval of state/local and NRC notifications is left off Answer B, it changes the meaning of the statement, changing it from a non-delegable approval function to a delegable notification function. The actual state/local and NRC notifications are performed by the
TQ-AA-151-F11 Revision 01 Page 6 of 6 Exam Comment Sheet SRRS: 3D.100; Retain this document until all regulatory actions associated with the exam are complete, at which time it may be discarded.
Test Item (Question/JPM/Scenario, etc.)
Concern or Problem Recommended Resolution Reference Remarks Communicator.
Recommend changing Exam to both answers B and D as correct.
Question to be revised prior to entering into Ginna Exam question bank.
Additional comments: Facility will be submitting additional comments Exam Analyzer comments: Applicant comments reviewed and resolution determined by QRC Final Resolution: Submit recommended changes to NRC Chief Examiner and make revisions to questions, as necessary, prior to entry into Ginna VISION Reviewed by: David Eckert 08/06/2019 Approved by: Don Dettman 08/06/2019 Facility Author Date Facility Representative
/ Date