ML092390396

Initial Exam 2009-301 Post Exam Comments

ML092390396
Person / Time
Site:	Browns Ferry
Issue date:	07/29/2009
From:	West R Tennessee Valley Authority
To:	Widmann M Division of Reactor Safety II
References
50-259/09/301, 50-260/09/301, 50-296/09/301
Download: ML092390396 (22)

Text

CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 29, 2009 10 CFR 55.40 Mr. Malcolm T. Widmann, Branch Chief Operations Branch U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street S.W.

Suite 23T85 Atlanta, Georgia 30303-8931 Browns Ferry Nuclear Plant Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITIEN EXAMINATIONS - POST EXAMINATION RESPONSE Mr. Widmann TVA administered the final NRC Written Examination for the RO and SRO HLT Class 0801 on July 22,2009. Please find enclosed, the supporting documentation required by Section ES-501 of NUREG 1021, Post Examination Activities. The enclosure content listing is provided at the end of this letter.

The results were three Senior Reactor Operator (SRO) Candidates passed the examination with overall scores ranging from 89 percent to 92 percent and four of six Reactor Operator (RO) Candidates passed the RO portion of the exam with scores ranging from 89 percent to 90.6 percent. Two Candidates failed the RO portion of the written exam with scores of 78.6 percent and 76 percent. The SRO scores on the RO portion of the examination ranged from 90.6 percent to 93.3 percent.

Analysis of the RO portion of the examination indicated five questions, numbers 18, 37, 59, 62, and 68, with a greater than 50 percent failure rate. Analysis of the SRO portion of the examination indicates questions 78 and 96 have a greater than 50 percent failure rate. Additionally, there were specific comments posed by the candidates during the post-examination review.

CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390

Malcolm T. Widmann Page 2 July 29, 2009 Subsequent detailed analysis of high miss-rate questions and those identified during post-exam review indicates potential issues with four questions. There are two questions in the package that TVA believes have two correct answers. There are two questions in the package that may have job-link issues. TVA has submitted these two questions for deletion.

The results of this analysis, where applicable, will be forwarded to the HLT 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 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. Brian P. Stetson at (256) 729-7039.

r:u~

R. G. West Vice President

Enclosures:

Enclosure 1 - Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 - Graded Written Examinations (I.E., Each Applicant's Original Answer and Examination Cover Sheets) Plus A Clean Copy of Each Applicant's Answer Sheet Enclosure 3 - Master Examination(s) Excerpt Annotated to Indicate Any Changes Made While Administering the Examination - No Changes Made While Grading Enclosure 4 - Questions Asked By and Answers Given to the Applicants During the Written Examination Enclosure 5 - Substantive Comments Made By the Applicants Following the Written Examination

Malcolm T. Widmann Page 3 July 29, 2009 Enclosure 6 - Exam Seating Chart Enclosure 7 - Results of Any Written Examination Performance Analysis That Was Performed, With Recommended Substantive Changes

ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITTEN EXAMINATION - POST EXAMINATION RESPONSE FORM ES-403-1, WRITTEN EXAMINATION GRADING QUALITY CHECK (SEE ATTACHED)

ES-401 Sample Written Examination Form ES-401*5 ES-401-5 Question Worksheet

• Examination Outline Cross-reference:

295038 High Off-site Release Rate 19 EK1.03 (10CFR 55.41 ,10) .10)

I9 Knowledge of the operational implications of the following concepts as they apply to HIGH OFF*SITE OFF-SITE RELEASE RATERATE::

Level Tier #

Tier#

Group #

KIA #

KJA#

RO 1

1 SRO 1-295038EK1 .03

• Meteorological effects on off-site release I Proposed Question: # 18 Importance Rating 2.8 1-='

A General Emergency is declared due to a valid Wide Range Gaseous Rad Monitor (WRGERMS) reading. The current meteorological data is:

• 91 meter wind direction:

direction : 120 degrees

• 46 meter wind direction direction:: 115 degrees Which ONE of the following identifies the correct data point to use for this release AND the wind direction?

A. (1) 91 (2) wind is blowing Itom from the Southeast B. (1)46 (1) 46 (2) wind is blowing from the Southeast c.

C. (1) 91 (2) wind is blowing from the Northwest D. (1) 46 (2) wind is blowing from the Northwest Proposed Answer:

Answer:

A Post-Exam Post*Exam Delete the question.

Evaluation Recomme ndation:

ndation :

,"I I A . c ," ,

(... IllIt l ( /U( i t 5

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Answer Key Incorrect I Stem Clarity - The stem requests the candidate Challenge demonstrate knowledge of meteorological implications during emergency Issue:

conditions. The stem asks for information that is not a part of a ROs normal job responsibility. Part (1) asks information on the correct data point to collect data from [46m or 91 m}. This information is normally collected by RP personnel per EPIP-13, ltDose Assessment," (See excerpt). If SPDS is unavailable, (see excerpt), operations could be asked specifically what parameters to monitorlreport. With SPDS out of service, there is NO information available inside the Control Room to support data collection for Wind Direction.

BROWNS FERRY DOSE ASSESSMENT EPIP-13 3.6.3 Stack Meteorological Data 3.6.3.1 For stack releases record measurements at the 91 meter reading.

3.6.3.2 The default value for stability cfass with no met data available IS "0" for stack releases.

3.6.3.3 The default value for wind speed with no met data available is 4.0 meters/second for the stack.

3.4 Oetennination of Noble Gas Release Rate In j.lCi/second (Step 3 of Appendix A and B) 3.4.1 Stack Noble Gas Release Rate 3.4.1.4 If SPDS IS unavaIlable, notify OperatIons personnel on the affected unit to gain the information utilizing control room instrumentation. or if unavailable, notify the Shift Manager/Site Emergency Director that TI-67, "Determination of Stack and Hardened Wetwell Vent Release Rates* (backup method), procedure must be performed by RP and Chemistry personnel.

The ROs do normally collect and record meteorological data per 1-SR-2, ltlnstrument Checks and Observations," based on TRM 3.3.7 requirements (See excerpt). This information is collected on all three levels (10m, 46m and 91 m), making it non-specific to the requirements of an emergency assessment.

Instrument Check** nd Observations Attachment 2 (PIIg8 49 of 96)

SUrveillance PrOC8dure Om Pickage. Modes 1, 2, & 3 TASLE 1.48

,48 METEOROLOGICAL INSTRUMENTATJON

!NSTRUMENTATJON VA Y SHFT DAY SHIfT <NEEI(

WEE" APPLtCABtliTY AT ALL TIMES (Note 2~

C1tarta C1tal1a &.ute So<ro! TSR:3371 TSR: 3.3 7 1 LOCATlON LOCATION rcs ICS~*_' .:Nc(e 1

'NINO DIRECTION WtNQSPEEO 91M 91104 46M 10M 9114 91M 46M 10M uo Uno! SI.1M FndoY The need for this information during emergency conditions is the responsibility/function of RP or an SRO if requested by RP, based on the following:

1) Per supplied "Guidance for SRO-only Questions," Rev 0, page 5 of 19, (see excerpt) part (1) would be considered SRO knowledge only.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

• Does the question involve one or more of the YES --+ SRO -only following for Tech Specs, Technical Requirements, question and/or Offsite Dose Calculation Manual?

• Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements (

Section 1) NO

• Applications of generic LCO requirements (LCO 3.0.1 thru 3.0.7 and LCO 4.0.1 thru 4.0.7) NO

• Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology YES Meteorological Monitoring Instrumentation B 3.3.7 TR 33 INSTRUMENTATION TR 3.3.7 Meteorological Monitoring Instrumentation BASES BACKGROUND A complete description of past meteorological conditions at BFN and the surrounding area is located in the FSAR The meteorology of the Browns Ferry site provides generally favorable atmospheric conditions for transport and dispersion of plant emissions An operational meteorological measurement program ensures that sufficient data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere A 91 meter tower with supporting meteorological instrumentation is located within the BFN site boundary to satisfy this objective However, none of this information is used during emergency conditions, making this NOT within the scope of a RO job function.

Thus, there are NO correct answers.

Candidate performance: 3 of 9 selected "C", 1 selected "B", and 5 selected "A" Explanation:

A. INCORRECT: Part 1= correct, Per EPIP-13, attachment A Met data is collected from the 91 meter point. This is a stack release. (WRGERMS = stack) This information is collected and documented by RP personnel, or if SPDS were non-operational, a request of Operations. However there is NO additional instrumentation within the Control Room that could be used to assess Wind Direction if SPDS were to be NON-OPERATIONAL. Part 2 = correct - Per EPIP-13, Attachment A, wind "from" is correct. Also the RO does collect Meteorological data per 1-SR-2, making this portion not specifically a function of the RO, but

• within the knowledge range of a RO.

B. INCORRECT: See above.

C. INCORRECT: See above.

D. INCORRECT: See above.

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet QUestion Technical Reference(s): EPlp*13 Rev 38, EPIP-13 (Attach if not previously provided) 1-SR-2 Rev 19 (Including version I revision number)

Proposed references to be provided to applicants during examination: examination: NONE Learning Objective: (As available)

- 1.-.

Question Source: Bank.

(Note changes or attach parent)

New X

--~-~--~ ......

History:

Question History: RCExam (Optional- Ouestions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optional - Questions provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 ES-401-S Question Worksheet

• Examination Outline Cross-reference:

EA1.04 EA1 .04 (10CFR 55.41.7)

Wtr Lvi 295029 High Suppression Pool WIt LviIi 5 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

Level Tier #

Tier#

Group #

KIA #

RO 1

22 SRO 295029EA 1.

1.04 04

• RCIC: Plant-Specific Importance Rating 3.4 I Proposed Question: # 26 During a Unit 2 startup, with power ascension at 20% Reactor Power, a rapid loss of condenser vacuum forces the crew to insert a manual Scram. The following plant conditions exist:

• Reactor Water Level initially lowered to 0 inches and is currently being controlled (+) 2 to

(+) 51 inches with RCIC AND CRD

• The MSRVs are being used to control Reactor Pressure AND HPCI was started in pressure control mode

• Suppression Pool Water Level reaches (+) 7 inches Which ONE of the following predicts the current status of RCIC AND the required operator action in accordance with 2-EOI-1, "RPV Control?"

RCIC Suction _ _(1)_

(ll_AND AND the required operator action in accordance with 2-EOI-1, is to

_(2)_.

_(2)_.

A. (1) is aligned to the CST (2) continue RCIC operation in the current configuration.

C. (1) automatically swaps to the Suppression Pool (2) continue RCIC operation in the current configuration.

configuration.

D. (1) automatically swaps to the Suppression Pool (2) manually swap RCIC suction path. path .

I propo~ed propo:ed Answer: I Post-Exam Evaluation Accept both "A" and responses Recommendation:

ES-401 Sample Written Examination Form ES-401*5 Question Worksheet Answer Key Incorrect /t Stem Clarity - The stem requests the

• Challenge Issue:

candidate demonstrate knowledge of RC/C RCIC operation in accordance with 2*EOI*1. 2-EO/-1. 2-EO/-1 2*EOI*1 Flowchart step RCIL-4 RCIL*4 directs RCIC operation [with CST suction if possible}. However, 2*EOI RC/C 2-EOI APPENDIX*SC, INJECTION SYSTEM LINEUP RCIC, APPENDIX-5C, RCtC, the controlling document for placing RC/C RCIC in level control, gives the option in step 11 (see excerpt below) to shift suctions to the Suppression Pool if desired. desired.

l:' .

L... :r. ,.....

_. . ._:t.

t l.5 d~s:.red 1.5 d!!" s :.re:1 ~o -'0 all.q!l 1iI:'1.q7'. s*.1ct.ion t *:*

RC : : ,'Jct.!.on RC:C tt.e

.:, the Supp::essic,n S Po~l *

• ..lpp~e5.l11'i.o;.r.: Olc-:-l,

HE:: ... PERPCRN tr.* (e:lc.':'r.Q :

.. ~-;:"'.:-"1 - 17. It::

a . OPEN Z-FC'l-71-17,  :

R:::: C SOPP~ POeL SUPO:~ ~'O:::. :N3:::

N3D sucr STJCT VALVE.

VALVE..

b . OFEN O -i'CV-7 1-B. ac::

OPEN 2Z-::CV-71-B, RC: ::; SUPPR 5UP Pit PO POCLC::" OL '"7S:::

OUTS:>

socr SUCT 'rrLo,,"l.

VALVE..

c.

• . *1f":IEH WHEN ..  :-F>:v -n-17.

. ... :-:':V- 1 1-17, RC:C R.::: C SUPPR P".AiL PCO:' ll8:l

NED SUCT W V1.LVI

• .LVE,. and 2-P,;-....

2-FC"O/-i- ,!.-:c, l -1E. ReI":Ro:rC SUPPR wer.

suP"~ SU*::;: 1lAl.'!E Ol:TS!; Si:C:

YOC::" Ol'":B: VAL'.'E,. are Ar e ffully

,.Jj.ly cpe open, r.,

T~N ...

THEN .. . VERI VERIF'l FY CLOSED :-::C'1-71-19,

> : C":-'71 - 19, RC:: RC:C CS-: Sl'CTION ',,

CS: Sr:CTIOti '1U,..or .

VALVE.

The stem did not clarify what portion of 2-EO/-1 2*EOI*1 to reference

[flowchart step RCIL-4 RCIL*4 gr Q! Appendix SC}; 5C); only that 2-EOI*1 2-EO/-1 is the controlling document document. Also, NO CST level is provided in the stem, forcing the candidate to make an assumption. With Suppression Pool level requiring a vel}' vety narrow band of control, the candidate(s)thought it was a prudent decision to lower level in the Suppression Pool; thus applying the portion of Appendix SC step 11 (if desired to align RCIC 5C RC/C suction to the Suppression Pool).

Therefore, with the option to shift suctions in Appendix Appendix SC 5C (also within a 2*EOI-12-EO/-1 document) taken in conjunction with the fact that we are now in 2-EOI-2 2*EOI-2 on High Suppression Pool level, it would be considered a valid operational action that protects containment integrity. integrity. Additionally having 01-71 01*71 Precaution & &

Limitation knowledge supports the fact that at +7 "uSuppression Suppression Pool Level, a suction swap should be performed. Thus, there are TWO correct answers: "A" uA" and "US". S II.

Candidate performance:

performance: 3 of 9 selected "8 "8", ". 6 selected "A" Explanation:

A. CORRECT" Part 1 _correct - NarmalIIUCIIon A Normal suction ....., rln8Up for lor RCIC RelC is 10 lhe caT to the CST and . . . no automatic there*

IIUCIIon _ . PIr12 suction swap. Part 2 correct

_ RCle ~

- RCIC injection In lhe EOIa in the EOis is dhdiId directed 10 -with caT to be "WillI CST SUctionSUctian if JIG POSllble-II""

e-(see pllCldln procedure .-rpI) excerpt)..

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet C. INCORRECT:

INCORRECT: Part 1 incorrect - Plausibility based on on the overwhelming similarities between the HPCI and Rele Systems: and the frequently confused differences. HPCI automatically swaps suction to the RCIC Systems; Suppression Pool Pool at +5.25 inches. Part 2 correct - Rele RCIC injection injection in the EOls is directed to be "with CST Suction if poss ible~ (see procedure excerpt) .

possible" O. INCORRECT: Parts 1is D. INCORRECT: 1is incorrect and 2 correct as explained in ~"B". B~ _

Technical Reference(s):

Reference(s): 2-01-71 Rev 57 57,, 2-EOI-1 2-EOI- 1 Rev 12, 12, 2-EOI-1 2- EOI-1 (Attach Ifif not previously provided)

Appendix-5C Rev 4 OPL 171.040 Rev 22 /1042 Rev 19 (Including version I/ revision (Including version revision number)

Proposed references Proposed references to be provided to applicants during examination:examination: NONE Learning Objective: V. B.6, V.B.9.

V.B.B, V.B.9, V.B.11.

V. B.ll , V.B.12 (As available)

Question Source:

Modified Bank # 0610 Audit # 64 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional- Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optiona/-

provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:Level: Memory or Fundamental Knowledge

• 10 CFR Part 55 Content:

Comments:

55.41 55.43 Comprehension or Analysis X

x X

OPL OPL171 171.040

.040 Revision 22 RCIC has no automatic transfer from CST to torus. 01-71 directs transfer of RCIC when HPCI auto transfers on low CST level or high torus level and if RCIC trips on low suction pressure 10" Hg vacuum. vacuum .

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

• 6.1 BFN Unlt2 Reactor Cor. Isolation Cooling Normal Operation (continued) 2..()1-71 Rev. 0057 Page 22 0176

[5) BEFORE SuppressIOn Pool temperature reaches 95"'F, PLACe RHR in Suppression Pool Cooling Mode.

(REFER TO 2-01-74) [J (5.1) IF Suppression Pool temperature reaches 95°F. THEN ENTER 2-EOI-2 Flowchart [J

[5.21 IF Suppression Pool temperature reaches 105"F, THEN SHUT DOWN RCIC System operatIOn and return to Standby ReadIness REFER TO Step 61[12] or 6 1[13J. [J

[6) MAINTAIN Suppression Pool level between *5.5 and -2 in.

(REFER TO 2-01-74.) [J

[7] MONITOR CST 2 LEVEL, 2-Ll-2-161A, on Panel 2-9-6. [J

[S} IF ANY of the following conditions occur while RCIC IS injecting into the RPV:

• Suppression Poolieve! reaches +7 in., OR o

• HPCl suctIOn auto transfers to suppressiOn pool, OR [J

• RCIC Turbine trips on pump low suction pressure, THEN PERFORM the following steps to transfer RCIC Suction to the Suppression Pool:

(8.1] OPEN RCIC SUPPR POOL INBD SUCT VALVE, 2-FCV-71-17. o

[8.2] OPEN RCIC SUPPR POOL OUTeD SUCT VALVE, 2-FCV-71-18.

[83] WHEN RetC SUPPR POOL INBD SUCT VAlVE, 2-FCV-71-17, and the RCIC SUPPR POOL OUTSD SUCT VALVE, 2..fCV-71-18. are fully open, THEN VERIFY CLOSED RCIC CST SUCTION VALVE, 2*FCV.71-19 o

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

/

"'\

~ ..

CAUT'tON CAUTION I I .2#2 PUMP PO .... P NPSH AND VORTEX LIMiTS t.PSH"'!>(l l!MrtS I

I .3 #3 ElEVA ELeVATED TEO SUPPR SUPPA CHM8R CHMSR PRESS MAY TRIP RelC RCIC I

I#. #6 HPCI OR 0f'I RelC RCIC SUCTION lEW ASO\IE 140 TEMP ABO\l£ l.o 'F

'F I L L

~

_n oa. Nro

!tESTOIIiE .... INT .. IN RPV WA AND MAINTAIN WATER TER LVL BETWEEN 8E't'MOtN

.2 IN

+2 .o.NO.M IN. AND +51 IN IN. WITH ONE OR MORE OF T11E FOLLO~NG Of 111£ FDllOIMNO INJ SOURCES:

IN.J SOURCES :

~t. IIiJ SOURCE INJSOURCE APPX

"'~ '" ,...,,"

INJ PRESS CNDSANDFW CNOS"NOFW '~PSIG 1250 PS4G SA CRO eRD 58 1640 160W PS4G PSIG RCIC.

RelC. 1240PS/G 5C 1240 PS4G

... WITH CST SUCTION IF POSSIBLE HPCI.

50 ,Z*OPSIG 1240 PS4G

~TH WITH CS CSTT SUCTION IF POSSIBLE POSSl8 l E

~t. eNOS CNO' SA M

480 PSIG CS C' &l.

60, 6EBE 330 PSiG LPGI 68.6C 320 PSIG RCJL-4

""" '". oc L RESTORED AND RESIOREO CAN RPV WATER L VL BE RPVW"TEl!L\lL8E

... NO MAINTAINED A80\I£ ASO'"

+2IN .

wo.INTNNE.D NO L L ~

.. ..... '\

RCIL*~

RCIL*S

,~

" L YESL t-.. ....... ........ I RPV WATER lLVi..

MAINT AI" RP\!wATE,R.

MAINTAIN VL ABO\I£ A80VE *162 IN.

-182"'.

'CA' RC/l~

ES-401 Sample Written Examination ES-401*5 Form ES-401-S Question Worksheet APPENDIX-5C 2-ECI APPENDIX- 5G Rev. 4 Pae 3 of 3 PaGe 11 .

11. IF .....

.**** It de~ired to aliqn I1: is desired align ReIC ReIe ~c~ on

. 1:.lon to 1:he 1:0 the Suppression Suppre s~ion Pool, P 1, THEN .. ***. PERFORM p ~he fol1o

'the rtlinq:

fol l ow1nq:

a. aP'£5 2-I!II. 2- ~ 17, ReTe FCV-71-17, RCIC stiP PR POOL L INBD suer VAL SUC! VALV! ~.

b. OPEN 2-fCV-71-1B, Rele OPEN" 2-FCV-71-18, Rcre S PPR ?R POOL OUTED  ;,;m suer VALVE.

sueT

c. WHEN *** 2- l'CV- 1l - 1i, ReIC SUPPR POOL INBD IN3D suer VAL\rE, and 2- FCV-71-18, Re!C :C SUPPR POOL OUlBD $OCT VALVE, are

!ul1.,y ~,

!"'!iEN VEIUPY Cl.OSED Z- fCV 19, RCte CST SUc:nOli VA!. .c .

NOIE.:

NOtE: Step S~ep 12.b 12 . b oust 5t be p=r per !f orceded p:c=ptly p !' t ly foll owing

. ing Step 5 1:

12.~ to avoid loss of l2.a ct i o n pa of ~ uuction th..

path

12. 1=

11. _*...

T';<' * * * *' It I t is ~5 des ir ed t.o desired to align RCIC RCI e gsuct:.on uct~o n to t o i:he t he Condensate 51;.or Gcr.densa'te S~orage age Tank, T a~k ,

'lHElJ THEN ..* *.. PERFORM ::h t.hee ffollowing:

o ll owing:

a.

a. CLOSE 2-:CV-71-:7, 2- : C'i-il-:' 7 , RCICRCrC SIJPPR SCPPR POOL :N3D  :~J 3 D Sr;CI SIJCT VAL VAL'IE.'IE.

b. i\~HEU 2-FCV-7 1- 1-17, 17 , RCIC RCre SUPPR ?OOL rNSD SUFPR ?OO;. INBD SCC! VJ....LVE SlJeT V]..L'lE st arts ~raveling starts -:rave linq clcsed, closed,

rEN OPEN 22-FC/-71-19,

- fC~-7~-19 , ReIC CSTT SUCTION RCI C CS 5UC I !ON VALVE.

Vl lVE.

c.

c. CLOSE  :-:CV-7 1 - ':' 3, RClC CWSE ::-fCV-71-::'B, RCC SUPPRSr.;PPR POOL OUTSDOU'IBD scer SeCT VA!.VE .'

V1>.l.

LAST PAGE lASI' ?AG!!:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

• Exami nation Outline Cross-reference:

Examination 241000 Reactorrrurbine A1 .01 (10CFR A1.01 (10C FR 55.41.5)

Cross-reference:

ReactorfTurb!ne Pressure Regulator 55.41 .5)

Ability to predict and/or monitor changes in parameters associated with with operating the REACTORrrURBINE REACTORITURBINE PRESSURE REGULATING Level Tier #

Group #

KIA ##

KIA RO 2

2 SRO 241 OOOA 1.01 SYSTEM controls including:

• Reactor pressure Reactor Importance Rating 3.9 I Proposed Question:

Question: # 59 Unit 3 is at 93% Reactor Power.

Which ONE of the following completes the statements?

For this power level, level, EHC Pressure Set is nominally set to _(1)_

_ (1)_ psig.

psig .

IF ONE Turbine Control Valve were to fail OPEN OPEN,, then Reactor Pressure, Pressure, upon stabilizing, stabilizing, would be_(2)_.

A.

A. (1) 955 (2) lower B. (1) 1036

• (2) lower D. (1) 1036 D.

(2) the same Proposed Answer: A Post-Exam Evaluation Accept both "A" and and. responses Recommendation:

Recommendation:

ES-4Dl ES-401 Sample Written Examination ES-4DI-5 Form ES-401-5 Question Worksheet

• Issue:

Challenge Issue: The correct answer originally submitted to the NRC by the BFN Exam Team was "C" IIC" based on theoretical documented system response. Operations personnel performing exam validation indicated that there was actual plant OE which indicated pressure would lower a small amount for the conditions identified in the question. The scenario was run on Unit 3 simulator and pressure lowered a small amount (approximately

.5%). If this were an analog display, versus digital, there is a high probability that it wouldn't be noticeable. But, based on validation input, the correct answer was changed to A.

There are several references which would lead a candidate to conclude that pressure would return to setpoint after the perturbation; including FSAR sections 7.11 and 11.2, EHC Controls Lesson Plan OPL 171.228, and Unit 3 Simulator Malfunction Cause & Effects Manual.

OPL 171.228 171 .228 ELECTRO-HYDRAULIC CONTROL LOGIC Steam Pressure Control maintains either the Header Pressure or the setpoiOl Steam pressure Reactor Pressure at a pressure reference setpoint control , as a reactor pressure controlling parameter is utilized at all control, times, either by the Bypass Valve Control or the Turbine Control.

The system controls reactor pressure such that a change of 1 psig in reactor pressure causes a change of 1 .1%

1.1% in steam flow fiow demanded which the system converts to valve opening demanded and sends to the Turbine Control and/or Bypass Control valves (3 .3% per psig (3.3%

when selected to control on header pressure).

pressure). As reactor power is increased, reactor pressure increases and as pressure increases the increased, EHC system opens the Turbine Control valves or Bypass Control valves to use the extra steam produced by the increased power. power.

FSAR 11.2 TURBINE-GENERATOR I

During normal operations, the steam admitted to the turbine is controlled by the pressure regulator which maintains essentially constant pressure at the turbine inlet, thus controlling reactor vessel pressure. The EHC system pressure regulator can control reactor pressure.

pressure directly.

directly. The ability of the station to follow system load depends on adjustment of reactor power level. This is accomplished by changing Reactor Coolant Recirculation System flow or repOSitioning of control rods .

repositioning FSAR 7.11 PRESSURE REGULATOR AND TURBINE-GENERATOR

• CONTROL The pressure regulation function of the turbine control system is designed to manipulate turbine control valves and turbine bypass valves, individually or in parallel, parallel, to maintain reactor pressure within a narrow range of the pressure setpolnt setpoint as reactor power varies from 0

ES-401 Sample Written Examination Form ES-401*5 ES-401-5 Question Worksheet percent to 100 percent nuclear boiler rated flow.

flow.

According to the Simulator Cause & Effects Manual:

BROWNS FERRY UNIT 3 MALFUNCTION CAUSE AND EFFECTS 06/14/06 .- REV 3 TC08 CONTROL VALVE POSITION UNIT FAILURE:

TCOS FAILURE:

A) FCV 1-75 EFFECTS:

THIS MALFUNCTION WILL CAUSE THE SELECTED CONTROL VALVE TO BE POSITIONED AS DEMANDED BY THE INSTRUCTOR. THE POSITION INDICATOR FOR THE CONTROL VALVE WOULD REFLECT THE POSITION CHANGE. ALSO, ALSO, THE RECORDED TOTAL CONTROL VALVE POSITION COULD RESPOND TO THE VALVE POSITION CHANGE IF THE GENERATOR BREAKER IS CLOSED AND THE OTHER CONTROL

• VALVES ARE NOT ABLE TO COMPENSATE. THE EHC SYSTEM PRESSURE CONTROL UNIT WILL RESPOND BY POSITIONING THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES IN RESPONSE TO ANY PRESSURE CHANGE.

IF THE SELECTED VALVE IS POSITIONED TO A LOWER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES WILL OPEN TO COMPENSAT COMPENSATE E AS PRESSURE INCREASES.

IF THE CONTROL VALVE VAlVE IS POSITIONED TO A HIGHER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES AND/OR ANDIOR BYPASS VALVES WILL CLOSE TO COMPENSATE AS PRESSURE DECREASES.

IF SYSTEM VALVE POSITIONING IS LIMITED BY ANY OTHER (Le. MAX COMBINED FLOW LIMITER, CONTROL MECHANISM (i.e.

VALVES FULLY OPEN, ETC.), THE SYSTEM RESPONSE WOULD BE ALTERED AND A REACTOR PRESSURE CHANGE AND ITS ACCOMPANYING EFFECTS ON POWER COULD RESULT.

Based on these references the candidate would reasonably

• expect the EHC System to maintain essentially constant pressure at the turbine inlet, inlet, thus controlling reactor vessel pressure. Therefore, following failure of ONE Turbine Control Valve open, the candidate would conclude that the remaining valves would close to compensate for the pressure decrease

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet and Reactor Pressure would stabilize at the same pressure.

This makes both tA' and te' a correct response.

8 of 9 candidates selected 'C' as the correct answer. 1 candidate Candidate Performance:

selected 'A' and this candidate was the SRO Upgrade.

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet Technical Reference(s)

Reference(s):: 2*GOI*100*1A 2-GOl-100-1A Rev 139 (Attach if not previously provided)

OPL 171.228 Rev 3 (Including version I revision number)

Proposed references to be provided to applicants during examination: NONE Objective:

Learning Objective: V.B.9 (As available)

Question Source:

Source: Bank.

(Note (Nole changes or attach parent)

New X

~---------------~

Question History:

History:

10195 will generally undergo less rigorous review by the NRC; failure to (Optional- Questions validated at the facility since 10/95 provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Conlen!:

Content: 55.41 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Fonn Form ES-401*5 Question Worksheet WorkSheet Examination Outline Cross-reference:

Cross-reference: Level Level RO SRO 2.2.13*

2.2 .13 - Knowledge of tagging and clearance procedures.

Tier# 3 Group # - I KIA # G2.2.13 Importance Rating 4.1 I Proposed Question:

Question: # 68 Which ONE of the following completes the following statements regarding the thawing process for a freeze plug in accordance with SPP*10.2 SPP-10.2,, Appendix E, "Special Requirements For Mechanical Clearances?"

During the time that the freeze plug is being thawed , the clearance is required to be _(1)_ AND the vents/drains are required to be verified _(2)_.

A.

A. (1) Released but tags still on boundary valves (2) OPEN B. (1) Released but tags still on boundary valves B.

(2) CLOSED C. (1) Actively Issued (held) all tags in place

• C. (2) OPEN D. (1) Actively Issued (held) all tags in place (2) CLOSED Proposed Answer:

Answer: B Post-Exam Evaluation Evaluation Delete the Question Recommendation::

Recommendation

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Challenge Issue: This question was drafted after we returned from the Atlanta In-office review with the NRC. The question was unintentionally written at the wrong license level (RO versus SRO) and not linked to job requirements of a Reactor Operator. The requirements for releasing a clearance associated with a freeze seal would be determined, briefed, and directed by a SRO. There are no objectives in OPL 171.086, "TVAN CLEARANCE PROGRAM" Lesson Plan specific to the requirements of Freeze Seals.

OPDP-1, "Conduct of Operations," provides the following guidance:

6.3C Preparation for Clearance Removal When preparing to remove a clearance the SRO will:

o Review restoration of clearance sequencing to ensure the restoration specified is accurate for plant conditions, specific tags to remove, and precautions o Ensure verification of components configuration inside the clearance boundary based on work performed and controls imposed by work documents before the tags are removed o Ensures the operator removing the clearance reviews the lift and then ensures a pre-job brief is conducted This question evaluates knowledge and abilities at a level that is unique to the SRO job position. Therefore, in accordance with NUREG 1021 ES-401, this is an SRO-Only question.

Additional information provided during Exam Analysis with the candidates (from the SRO Upgrade) was that in fact, due to conservative decision-making practices, in his only experience in dealing with a freeze seal to replace a CRD Valve, the clearance was revised to keep the tags that were still hanging active, versus the Clearance being released with the tags still hanging; as the shift felt like there would no longer be any "administrative controls" over the tags that were still hanging.

Candidate Performance: All RO candidates selected an incorrect answer. 4 selected 'D' and 2 selected 'C'. All SRO candidates selected the correct answer.

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet Technical Reference(s):

Reference(s) : SPP-10.2 SPP*10.2 Rev 12 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: examination : _ NONE N"O"N.:.E

=-_ _ _ _ _ _ _ _ __

Learning Objective:

Objective: (As available)

Question Source: Bank' (Note changes or attach parent)

New rX X"-_ _ _ _ _- ,

~--------------~

Question History: Last NRC Elcam I..aBt Exam 1005 will generally undergo less rigorous review by the NRC; failure to (Optiona/-- Questions validated at the facility since 10/95 (Optional wi/I necessitate a detailed review provide the information will re view of every question.)

Question Cognitive Level:Level : Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Comments:

• F.

F_ The following instructions govern govem the use of freeze plugs

1. The clearance should be in place place,, but not issued.

issued, before establishing the freeze plug .

plug.

2.

2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be in In accordance with approved procedures or work documents. documents.

3 The freeze plug must be attended by qualified personnel to 10 ensure that itil is maintained intact until all work is complete and the proper Post Maintenance Tests (PMT s) are performed.

performed .

4.

4. If the clearance must be released to allow performance of a PMT, the equIpment equipment must be retagged relagged before aHowingallowing the freeze plug to thaw.

thaw . This will prevent miQration of a portion of the pluQ miQralion pluQ..

5.

5. The clearance must be released before allowing the freeze plug to thaw. thaw .

However, However, to prevent migration of the freeze plug.

plug, tags on boundary valves shall not be removed until the freeze plug has completely thawed. thawed .

6.

6. All vents and drains must be verified CLOSED before allowing the freeze plug to thaw..

thaw