ML12188A684

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Initial Exam 2012-301 Post Exam Comments
ML12188A684
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/24/2012
From: Polson K
Tennessee Valley Authority
To: Mccree V
NRC/RGN-II
References
Download: ML12188A684 (17)
v • d • e


Text

10 CrR 2.390 (hf) \/

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 24, 2012 10 CFR 55.5 Mr. Victor M. McCree Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention: Mark A. Franke Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Reactor Operator and Senior Reactor Operator Initial License Written Examinations Post Examination Response The Tennessee Valley Authority (TVA) administered the final NRC Written Examination for the Browns Ferry Nuclear Plant Reactor Operator and Senior Reactor Operator Initial License Training (ILT) Class 1205 on May 18, 2012. The supporting documentation specified by Section ES-SQl of NUREG 1021, Revision 9, Supplement 1, Operator Licensing Examination Standards for Power Reactors, for Post Examination Activities is enclosed. The enclosures content listing is provided at the end of this letter.

Printed on recycled paper

Victor M. McCree Page 2 May 24, 2012 Analysis of the preliminary facility graded examination results indicated eight questions; numbers 29, 79, 83, 84, 86, 92, 93, and 100 had a 50 percent or greater failure rate.

The results of this analysis, where applicable, will be forwarded to the ILT Supervisor for potential inclusion in the appropriate training material.

The enclosures to this letter are considered by TVA to be of a personal nature and, as such, are requested to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).

If you have any questions or comments, please telephone Mr. Michael D. Gibson at (256) 729-2783.

Respectfully, K. J. Pon Vice President

Enclosures:

Enclosure 1 - Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 Graded Written Examinations (Each Applicants Original Answer and Examination Cover Sheets) and a Clean Copy of Each Applicants Answer Sheet Enclosure 3 Questions Asked By and Answers Given to the Applicants During the Written Examination Enclosure 4 Examination Seating Chart Enclosure 5 Results of Written Examination Performance Analysis that was Performed

Pcr3onwIy iucniiriuoic-m-rormauon-- vv-imnoia unaer 1U i.,i K Enclosure 5 Browns Ferry Nuclear Plant Units 1, 2, and 3 Reactor Operator and Senior Reactor Operator Initial License Written Examination Post Examination Response Results of Any Written Examination Performance Analysis That Was Performed (See Attached)

QUESTION 92 Unit 2 is operating at rated power.

. A sustained loss of Panel 2-9-9 Cabinet 6, Unit Preferred, occurs Which ONE of the following completes the statements below?

Entry into a Required Action statement in TRM 3.3.5, Surveillance Instrumentation,

_(1)_ required.

Given the power loss, in accordance with Tech Spec SR 3.1.3.1, Control Rod positions can still be determined by the use of (2).

Reference Provided A. (1)is (2) OPERABLE position indicators B. (1) is (2) other methods C. (1) is NOT (2) OPERABLE position indicators D. (1) is NOT (2) other methods

Level:

Tier#

Group Examination Outline Cross-Reference KIA#

214000 G2.2.42 Importance Rating f 4.6 214000 RPIS: G 2.2.42 Ability to recognize system parameters that are entry level conditions for technical specifications.

Explanation: CORRECT D, Loss of Pnl 2-9-9, Cab 6 will cause Loss of RPIS for TRM 3.3.5 control rod motion requires either rod position or neutron monitoring entry to a condition is not required. Rod Position must be verified every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, this can accomplished by an alternate method A. hicorrect first part incorrect TRM 3.3.5 entry is not required because neutron monitoring is available. Second part incorrect position indication is NOT operable.

B. incorrect first part incorrect see above and second part correct C. Incorrect - first part correct and second part incorrect see above Technical Reference(s): TS 3.1.3 and Bases, TRM 3.3.5 Proposed references to be provided to applicants during examination: TRM 3.3.5 Learning Objective (As available): OPL171.029 V.B.7 Question Source: Bank:

Modified Bank:

New X Question History: Previous NRC Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 X b(2)

1 Level of Knowledge Justification: This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to decide on a tech spec ico condition entry for a loss of RPIS.

SRO Only Justification: This question is SRO Only because it meets the requirements of Clarification Guidance for SRO, Section II. B Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)] See Attached.

KA Justification: The KA is met because the question tests knowledge of LCO entry criteria on a loss of RPIS.

Figure 1: Screening for SRO-only linked to 10 CFR 55.43(b)(2)

(Tech Specs)

I Can question be answered sole/y by knowing S 1 jYL,fiaquestiofl hour TSITRM Action?

No nrn.......o//

I Can question be answered solely by knowing the Yes LCOITRM information listed above-the-lineT RO question III!!! No Can question be answered so/ely by knowing the Yes TS Safety Lim its? RO question No Does the question involve one or more of the following for TS, TRM, or ODCM?

  • Application of Required Actions (Section 3) and Surveillance Requirements (Section 4) in accordance with rules of application requirements (Section 1)
  • Application of generic LCO requirements (LCO 30.1 thru 3.0.7 and SR 4.0.1 thru 4114)
  • Knowledge of TS bases That is required to analyze TS Yes LI SRO-only question required actions and terminology

FN Loss of RP1S 2-AOl4-4 Unit 2 Rev. 0020 Page 4 of 17 1.0 PURPOSE This abnormal operating instruction provides synptoms, automatic actions and operator actions tar a total or partial loss of Rod Position lnfomation System (RPIS) or an mdiv dual rod position indication.

Control Rod Position may be determined by the use of operaDle position indicators, by moving a Control Rod to a position with an operable indicator or by the use of other approved methocs. Control Rods need 3I be immeciately declared

/ INOPERABLE upon discovery of inoperable position indication. The Tech Spec Bases should be referred to for Control Rod Position veriricaUon methods to satisfy the requirements of TS SR 3.1.3.1.

Operable Position indicators include, but are NOT limited to te tollowinq:

  • Full Core Digital Display
  • Four Rod display
  • Full Core Display green background lightinç (Full In)
  • Full Core Display red background lighting (Full Out)
  • Full Core Display double green dashes (Full In Overtravel)
  • Full Core Display double red dashes (Full Gut Overtravel)
  • lCSdsplay
  • RWM SR3.1.3.1 REQUIREMENTS The position of each control rod must be determined to ensure adequate information on control rod position is available to the operator for determining control rod OPERABILITY and controlling rod patterns. Control rod position may be determined by the use of OPERABLE position indicators, by moving control rods to a position with an OPERABLE indicator, or by the use of other appropriate methods. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is based on operating experience related to expected changes in control rod position and the availability of control rod position indications in the control room.

31 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control ----

---NOTE---------------

rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, ControI Rod Block Instrurnentation if required, to allow continued operation.

A.1 Verity stuck control rod Immediately separation criteria are met.

AND A.2 Disarm the associated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> control rod drive (CRD).

AND I (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.1.3.3 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from each withdrawn discovery of OPERABLE control rod. Condition A concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM AND A.4 PerformSR3.1.1.1. 72hours B. Two or more withdrawn B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> control rods stuck.

C. One or more control rods C.1 ----NOTE----

inoperable for reasons RWM may be bypassed other than Condition A or as allowed by B. LCO3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> control rod.

AND C.2 Disarm the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CRD.

(continued)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. ----.-----NOTE---------- Di Restore compliance with 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Not applicable when BPWS THERMAL POWER

>1O%RTP. PR D2 Restore control rod to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Two or more inoperable OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods E. Required Action and El Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable.

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SU RIEILLANCE FREQUENCY SR 31 31 Determine the position of each control rod 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Surveillance lnstnjmentation TR 3.35 TABLE 3.3.5-1 (page 1 of 2)

Surveillance Instrumentation PARAMETER AND APPLICA8LE REQUIRED CONDITIONS TECHNICAL TYPE INSTRUMENTS MODES OR CHANNELS REFERENCED SURVEILLANCE INDICATION OTHER FROM REQUIREMENTS AND RANGE SPECIFIED REUlRED CONDITIONS ACTION A.1 I. Deleted

2. Control Rod Motion
a. Control Rod 1.2 1(b) C TSR 3.3.5.2 lndicatoi-sOO-48 Position (a
b. Neutron 1.2 1(c) C TSR 3.3.5.3 SRM Indicators Monitorin(a) TSR 3.3.5.4 c 6 ps IRM 0.1-lO TSR 3.3.5.7 Indicators 0-125 TSR 3.3.5.8 LPRM Indicators TSR 3.3.5.9 0-125 (a) The channel of Control Rod Position instruments and the channel of Neutron Monitoring instruments are consicerect redundant to each other for the parameter of Control Rod Motion.

(b) The Control Rod Position channel consists of full core display position indicators or four-rod display position indicators capable of determining position of all OPERABLE control rods. Position indicators are considered to be capable of determining rod position vihen they display the rod position or the rod can be moved to a position where rod position is displayed.

(C) The Neutron Monitoring channel contains the following:

1. In MODE 2 with IRMs on Range 2 or below a minimum of 3 OPERABLE channels of SRMs.
2. In MODE 2 a minimum of 6 OPERABLE channels of IRMs.
3. In MODES 1 and 2, 43 LPRM detector assemblies, each containing four ssion chambers.

Individual failed chambers can be bypassed to the extent that APRM5 remain OPERABLE.

(d) The channel of Drywell Pressure and the channel of Drywell Temperature and Pressure and Timer instruments are considered redundant to each other for the parameter of Drywell PressurelTemperature Alarm.

TR 3.35 TR 33 INSTRUMENTATION

( TR 3.35 Surveillance Instrumentation LCD 3.3.5 I he surveillance instrumeitation for each parameter in Table 3.3.5-1 slaIl be OPERABLE.

APPLICABILITY: Accordinç to Table 3.35-1

NO I h--

TRM LCD 3.0.4 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETiON TIME A. One or more required A1 Erter the Condition Immediately chaniels inoperable, referenced in Table 3.3.5-1 for the channel.

B. Deleted.

C. As required ty C. 1 Restore one of the 7 days from Requred Action A. 1 required control roDn- discovery of both unci leleleilced in icidiuiliuri Jiaiiriels 101 ieduiidiriL c[iunnels Tuble 33.5-1. eucli ussociuted [ci uiie ui FTIUIC p1an1eieI LU OPERABLE ussociited status. pammeters not indicating in the control room C2 Restom reqiiireil control 30 days morn inilication chnnIs to OPERABLE status.

ccntinuedi

Surveillance Instrumentation TR 335 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 Monitor torus Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action Al temperature to observe and referenced in any unexplained Table 3.3.5-1. temperature increase which might be indicative of an open relief valve.

AND D.2 Restore control room 30 days indication by either the Tailpipe Themiocouple Temperature or Acoustic Monitor to OPERABLE status for each relief valve.

AND D.3 When inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> more than 30 days, initiate a Problem Evaluation Report (PER).

ACTIONS CONDFICN REQUIRED ACTION COMPLET ON TIME E. Psiequiiedby -----------------NOTE-------------

Required Action A. 1 Required Actions E. ii and sid ieleienced in E. 1.2 une nut uppliuiLile wheni in Tuble 3.3.5-1. MODES 4 and 5.

E.1.1 Restore required control 72 [10 Jrs room indication channel to OPLRAOL[ status.

OR E.1.2 Initiate the preDlanned 72 hojrs nItniti- mcthnd of mrrnitcnng thc parameter.

AND E.2 When inoperable fo- 24 hoUrs more than seven days, initiate a Problem Evaluation Report (PER).

(cohIInhJcNVI

ACIIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F1 Be in MDDE 4 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> associated Completion Time of Condition C not met.

OR Required Action and associated CompIeon Time of Condition C not met for Instruments 3.a or 3.b.

G. Required Action and G.1 Be in MDDE 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition C not met for Instruments 2.a, 2b, 4.a, or 4.b.

H. Required Action and Hi Reduce THERMA 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion POWER to 15% RTP.

Time of Condition C not met for Instrument 5 channels.

Facility response to Applicants comments on question 92 A combination of TRM 3.3.5 Bases and TRM Table 3.3.5-1 notes show that entry into TRM LCO 3.3.5.C.2 is required.

-TRM Table 3.3.5-1, requires one channel of control rod position and one channel of neutron monitoring to be operable for the function of Control Rod Motion.

-Note (b) to the table defines the requirements for operability of control rod position:

(b) The Control Rod Position channel consists of full core display position indicators or four-rod display position indicators capable of determining position of all OPERABLE control rods. Position indicators are considered to be capable of determining rod position when they display the rod position or the rod can be moved to a position where rod position is displayed.

With a total loss of Unit Preferred, no full core display or four-rod display position indications are available. Therefore, control rod position indication is INOPERABLE.

-Note (a) to the table describes that neutron monitoring and Control rod position are redundant to each other:

(a) The channel of Control Rod Position instruments and the channel of Neutron Monitoring instruments are considered redundant to each other for the parameter of Control Rod Motion.

With all control rod position indication inoperable, the redundant method for the function of Control Rod Motion is unavailable.

-Therefore, entry into TRM 3.3.5.C.2 is required due to TRM 3.3.5 bases:

When required control room indication channels are inoperable but the redundant channels for the parameters are still OPERABLE, the required control room indication channels must be returned to OPERABLE status in 30 days (Required Action C.2).

CONCLUSION Operations, Licensing (James Emens, see attached e-mail), and Training have confirmed that question 92 is keyed wrong, and that B is the correct answer.

Gibson, Michael David From: Emens, James E Jr Sent: Tuesday, May22, 2012 1:44 PM To: Zielinski, Daniel Kenneth; Rasmussen, Matthew; Hakenewerth, Douglas G Cc: Gibson, Michael David; Green, Daniel

Subject:

RE: NRC ILT Exam Mr. Zielinski, of 2-AOI-57-4 indicates that RPIS is powered from Panel 2-9-9 Cabinet 6, Unit Preferred (Note: Neutron Monitoring Instrumentation is not listed as being powered from this panel). As a result of a sustained loss of this panel, RPIS is inoperable. Therefore, TRM Table 3.3.5-1, Instrument 2.a, Control Rod Position, requirements are not met and the specified Condition (Condition C) is required to be entered. Based on Note (a) to TRM Table 3.3.5-1, the channel of Instrument 2.a is considered to be redundant to the channel of Instrument 2.b, Neutron Monitoring, for the function of Control Rod Motion. Therefore, the appropriate Required Action to take is Required Action C.2, since Required Action C.1 only applies when both redundant channels for Control Rod Motion are inoperable.

I concur with the applicants, answer B is correct. The submitted answer of D for Question 92 is not correct.

James Emens From: Zielinski, Daniel Kenneth Sent: Tuesday, May 22, 2012 8:14 AM To: Emens, James E Jr; Rasmussen, Matthew; Hakenewerth, Douglas G Cc: Gibson, Michael David

Subject:

NRC ILT Exam MR. Emens Matt Rasmussen asked me to contact you regarding the just completed ILT Exam.

The applicants are challenging question 92, and we need to know if the plant supports their argument or if the original answer is correct for this question.

The answer as submitted was D.

Attached is Question 92, the reference provided was TRM 3.3.5 without the bases document.

Also attached is the applicants discussion why they believe that answer B should be the correct answer.

The submittal is due to be sent to the NRC on Thursday, so that they have it Friday.

Please contact Mike Gibson or myself with any questions extension is 2783.

In addition can contact Matt or Doug Hakenewerth.

Thank You for your assistance Dan Zielinski 1

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