ML110040749

RBS-2010-12-Post Examination Comments

ML110040749
Person / Time
Site:	River Bend
Issue date:	12/10/2010
From:	Fralick J Entergy Nuclear Operations
To:	Garchow S NRC Region 4
References
RBS-2010-12
Download: ML110040749 (4)

Text

-::::::-Entergy*River Bend Station -5485 US Highway 61 -St. Francisville, LA 70775 December 10,2010 Mr. Steve Garchow US Nuclear Regulatory Commission Region IV 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125

SUBJECT:

River Bend Station -Unit 1 Docket No. 50-458 License No. NPF-47 DECEMBER 2010 EXAM KEY CHALLENGE Mr. Garchow: This letter transmits the exam analysis required by ES-403-1 for questions missed by >50% of the candidates as well as justification for accepting an alternate answer for question numbers 55 and 88 on the River Bend Station NRC Initial License Examination administered on December 2, 2010. If you have any questions or require additional information, please feel free to contact me by phone at (225) 378-3530 or bye-mail at jfralic@entergy.com or Angie Orgeron at 225-378-3561 or aorgero@entergy.com.

John Fralick Superintendent Operations Initial Training River Bend Station

Enclosures:

As stated 9 9/14 = 64% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 12 12/14 = 85% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 54 7/14 = 50% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 58 7/14 = 50% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 61 7/14 = 50% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 81 6/8 = 75% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram 88 6/8 = 75% The station is proposing that this The individuals who had a knowledge gap question has two correct answer. associated with the question were remediated Justification is below. on 9/13/2010.

95 4/8 = 50% The station has reviewed the question The individuals who had a knowledge gap and believes it to be valid and have associated with the question were remediated only one correct answer. This on 9/13/2010.

knowledge item(s) was presented durin the trainin ro ram From this review the following challenge is presented for questions number 55 and 88 of the exam. The justification for the challenge is below: December 2010 RBS Initial NRC Written Exam Page 1 Question #55 -River Bend recommends both B & D be taken as acceptable answers. The question and the basis for accepting B & D follows: "The plant is operating at 100% power. A loss of RPS bus "B" has occurred.

Restoration of isolation has NOT been completed.

What is the expected response if a Recirculation Flow Control Runback occurs? A. Both FCVs runback to minimum position.

B. Both FCVs runback to the 60% drive flow position.

C. 'A' FCV runback to minimum position D. 'A' FCV runback to the 60% drive flow position.

Justification for B & D being

'A' and 'C' are clearly wrong because a FCV runback causes the FCVs runback to 60% drive flow -not minimum The question clearly tests the candidates knowledge of how a loss of RPS B affects FCV operation but in order to answer the question a assumption has to be made concering procedure implementation.

The question stem states "Restoration of isolation has NOT been completed." Upon a loss of RPS B there is an isolation of 10 systems / sub-systems.

The answer is dependent on the assumption the candidate makes concernil1g how much of the restoration has been completed per Abnormal Operating Procedure (AOP) 0010 "Loss of One RPS Bus". There is not enough information given in the stem to determine how many of the isolations caused by the loss of RPS B have been verified / restored -just that the isolation restoration is not complete.

B would be correct if the FCV isolation had been reset. D would be correct if the isolation had not been reset. Additionally the restoration of the FCV isolation would be restored relatively early in AOP implementation.

Recommendation is to accept both B & D answers as correct. December 2010 RBS Initial NRC Written Exam Page 2 Question #88 -River Bend recommends both C & D be taken as acceptable answers. The question and the basis for accepting C & D follows: A plant startup is in progress per GOP-OOl, PlANT STARTUP with the plant in Mode 2. All IRMs are on Range 8. IRM 'A ' is inoperable because it failed to cause an upscale trip during surveillance testing. Subsequently IRM 'C' experienced a power supply failure causing the instrument to be inoperable.

Which of the following describes the Technical Specification requirements and the effect on plant startup and entry into Mode I? The startup can not continue.

Conduct an orderly shutdown per GOP-0002, PlANT SHUTDOWN.

Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The channel or trip system must be placed in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Mode change is not allowed. Remain in GOP-OOOI, PlANT STARTUP but stabilize at the current power level until one of the IRMs ins restored to operable. The channel or trip system must be placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Continue the plant startup per GOP-OOOI, PLANT STARTUP. No further actions required.

Entry into Mode I is allowed since the actions taken may continue for an unlimited period of time. The channel or trip system must be placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Continue startup per GOP-0001, PlANT STARTUP after bypassing IRM C. Entry into Mode 1 is allowed since IRMs are not required in Mode 1. Justification for C & D being correct: Each choice (A-D) has individual statements that must be determined to be correct or incorrect. A & B contain clearly wrong statements.

A is wrong because a startup can continue.

B is wrong because the requirement to place the channel in trip is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not 6 and a Mode change is allowed. The individual statement intended to make C incorrect is "No further actions required".

This statement, based upon question construction, can be assumed to state that no further Tech Spec actions are required and this is correct. It could also be assumed that GOP-0001 PLANT STARTUP does not require any further action and this is correct. It is understood that IRM C will have to be bypassed to continue raising reactor power but this action is not directed by Tech Specs or GOP-0001 PLANT STARTUP. The construction of the question leads the candidate to answer based upon administrative requirements of Tech Specs and/or GOP-0001 PLANT STARTUP and not actual plant control manipulations.

Recommendation is to accept both C & D answers as correct. December 2010 RBS Initial NRC Written Exam Page 3