ML093640783

Final (Reference) RO Written Exam

ML093640783
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/08/2009
From:	Division of Nuclear Materials Safety II
To:	Duke Energy Carolinas
References
50-369/09-302, 50-370/09-302
Download: ML093640783 (187)

Text

FACILITY NAME: McGuire Section 9 REPORT NUMBER: 05000369,370/2009302 FINAL REFERENCE RO WRITTEN EXAM CONTENTS:

o Final RO Written Exam (75 'as given' questions with KA and Development History, and Distracter Analysis)

Location of Electronic Files:

As submitted RO Written:

Attached Submitted By: __

--""~::...-.J::.

Verified By £(~

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"'---- 1---

FACILITY NAME: McGuire Section 9 REPORT NUMBER: 05000369,370/2009302 FINAL REFERENCE RO WRITTEN EXAM CONTENTS:

o Final RO Written Exam (75 'as given' questions with KA and Development History, and Distracter Analysis)

Location of Electronic Files:

As submitted RO Written:

Attached Submitted By: __

--""'~:....-..<:..

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 1

B IQueStio~Ba~k-#

lKA~;Y8tem--lKA~~;"m-ber-- --

I.<A.=-deac -------- --------------------

-~-----------+----------_t--------- ---

1--------- ------- --- -------- ------- ---- ---------------- -----~------ ----------- ---- - ------ --- --

I 1801 i

SYS003 L A 1_02 lAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RepS

---

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

~()l1tr() 1s.~~~u~iI1~~ (5:FY-.:_4JJ!_4'?J 2 Q~~~jJllmp ll11~ E1_()to!.~~arirJ.K~111p~ratuE.es ______________ _

CURRENT Given the following plant conditions:

- Unit 2 is at 20% RTP.

- NC Pump 2A Lower Bearing Temperature is currently 190°F and has been increasing for the last six hours (at a rate of approximately 5°F/hr).

Which ONE (1) of the following is the MINIMUM NCP Lower Bearing Temperature requiring NCP TRIP AND where this indication can be monitored?

A.

235°F OAC AND Main Control Board B.

225°F OAC AND Main Control Board C.

235°F OAC ONLY D.

225°F OAC ONLY 45 DAY VERSION Given the following plant conditions:

- Unij 2 is at 20% RTP.

- NC Pump 2A Lower Bearing Temperature is currently 190°F and has been increasing for the last six hours (at a rate of approximately 5°F/hr).

Which ONE (1) of the following is the minimum NCP Lower Bearing Temperature requiring NCP TRIP AND where this indication can be monijored?

A.

235°F OAC AND Main Control Board B.

225°F OAC AND Main Control Board C.

235°F OAC ONLY D.

225°F OAC ONLY 401-9 Comments:

'uesday, November 10,2009 003AI.02 Stem: Underline and/or cap the word "minimum" RF A 10/27/09 Page 1 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 1

B

---

--1-- -

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

-~--

I.<A -deac ---- -----

---

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

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

I--=~---- ------~ --- -------- ~------ ---- ----------------.-----:-----.----; -----:-~--- -.--- - --:--- --- --

lAbility to predict and/or monitor changes in parameters (to prevent exceedIng desIgn lImIts) assocIated wIth operatIng the RepS

~ue~~~n~!nk~+~~~1~!~~-~~=~~~P!~-

I 1801

~

i ___ S'i~0~3 ___ L _____ ~~.~~ __

~()l1tr()I~~~~u~iI1~~ <s:FY-~_4IJ!~4~J2Q~~~jJllmp ll11~E1~.t0~~~arirJ~~111p~ratu~es ____ :--.~:-::--~ ___ ~

... _____ ~ _____ _ ___~

CURRENT Given the following plant conditions:

~ Unit 2 is at 20% RTP.

- NC Pump 2A Lower Bearing Temperature is currently 190°F and has been increasing for the last six hours (at a rate of approximately 5°F/hr).

Which ONE (1) of the following is the MINIMUM NCP Lower Bearing Temperature requiring NCP TRIP AND where this indication can be monitored?

A.

235°F OAC AND Main Control Board B.

225°F OAC AND Main Control Board C.

235°F OAC ONLY D.

225°F OAC ONLY 45 DAY VERSION Given the following plant conditions:

- Unij 2 is at 20% RTP.

- NC Pump 2A Lower Bearing Temperature is currently 190°F and has been increasing for the last six hours (at a rate of approximately 5°F/hr).

Which ONE (1) of the following is the minimum NCP Lower Bearing Temperature requiring NCP TRIP AND where this indication can be monijored?

A.

235°F OAC AND Main Control Board B.

225°F OAC AND Main Control Board C.

235°F OAC ONLY D.

225°F OAC ONLY 401-9 Comments:

'uesday, November 10,2009 003AI.02 Stem: Underline and/or cap the word "minimum" RF A 10/27/09 Page 1 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 1

B iM~~~~

NCP-I~~rb~~~~g t~p~-;:-at~r;i~~ 225~ d~g:-NCP k>~~;~b~~ri~gte~p~;a~~; c~~b; ~~Itit~~i~g fr;~ both th~ OAC ~;d;i~ gag;s l~~t~d;; th;~~~r~lr~~~ -0~MC-5------~

I IKA is matched because in order to answer the question the candidate must know where the parameter (RCP pump bearing temp) can be monitored (ability to monitor), and recall the design Imaximum temperature and recognize at what point this limit will be exceeded and at which the pump controls would have to be operated to trip the pump_ito prevent exceeded the design

!11.1a)(iI11..ull1_t~fI1~ratu.l"e)~ _______ ~_~__ ___ _ ________ ~~ _____ ~

__ ~

_____ ~ __ ~~~ _________________ ~~ __________ ~

Answer A Discussion iI~~~rre~t-Fi;st part i~ i;-;;-;;e~t but pi~~sible be~~u~~e-i3~Fi;the Ii~it fu-;:-#TSe~IOtrtlet t~~p~r-;t~~e~ S;c~~dpcrti; c-o;;'~ct,NCPl~;;rb;a-;:-i~g-t~~p~;at~;~a; -b~ ~~~ito~i;g -fr~~ -b~th--'

Ithe OAC and via gages located in the control room on MC-5 L ___________________ ~_~ ________________________________________ ~~ _______

~ __ ~ ___ ~ ___

~ ______________

~ ______ ~_~ ___ ~

Answer B Discussion iCORRECT~225 deg -i;th~~-~i~~~-de;;~-NCPlo~~; be;ri~gt;~p~;at~~;;nd ~ho~lithi;t;~p~;atu~; be-r;~ch~~(; p-u~Ptripi;~q~i~ed:-Thi;-p~a~ete-;:-~~-b~~~~i~~i~g-;;~ both the 11()~~_al1d_()~~~~M~-5_ __

_~ _______ ~_~ __ ~~ ~ ______ ~ ___________ ~~ _____ ~ __________ ~_~ ________________ ~ ______ ~ ________ _

Answer C Discussion r- - -------

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

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

---

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

---

~~-- ---

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

---

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

IIncorrect. First part is incorrect but plausible because 235°F is the limit for #1 Seal Outlet temperature_ Second part is plausible if the applicant does not recall that temperatures can be I

Im~l1it0l"~d_~_g~~es 011~.c.-~-___ ______ _ __ ___ _ __

____ ~~~~~__

_~ _______ ~~ ___________________ ~ ____ ~ ___ ~ _____________ ~

Answer 0 Discussion Ilin-c~r~~ct -Fi;;tPart~fth~~dj;tr;ct~is-~-;:-r~ct_-S~;;-ndp~rtis-pl;u;ibl~ifthe-appli~a~tdo~~ ~~~e~all that-t;~peratu--;:e;~;n-b;;-~o;ito~;d-~g~ge~ ~~ MC~S:--~

---

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

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

---

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

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory

---

~--

---

~--

Question Source

~-

-~ ----

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

---

~ ---

--~ --- -

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

~ --~

~~'\\'~!()p.f'!-~n.t-~e!~~fl~!~--- __ ~__ ____ ___

1~!~tiElfl~~~!~"!'!c~~ f!.C>... I~!tJ._

ILesson Plan OP-MC-PS-NCP Reactor Coolant Pump I401-9 Comments?

I land Motor Rev_ 25, Pg 43 I

I I

ILearning Objective: OP-MC-PS-NCP Obj_ 15 I

1 __________ ~ __ ~~ ___________________ ~___

1 __ _

I

- - ___________ ~ ___ ~~ _______ 1 401-9 Comments RESPONSE 10/02/09: Requested change made_

Approved_ RF A 11l09109

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

-~- 1:"- ------ ---- ---

QuestlonBank # IKA_system IKA_number

---

-- ------ -----:r~-------- --~ + ------ - -- ----- -

~A..,~!~c: _________ ~ __ ~~~ ~_

_ ~ ____ ~

_____~~ _____________ ~ ______ ~~_-~~~~~~~~-~~~-

1801lSYS003 IAl.02

_ -.1 _____________ ~ ___________________ _

[Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the

~_C!,'§ ~()ntrolsJI1c1l1dil1&~{C!_R...= _41 Jl..4~-~ll~ItC:P_Ell...mLaE~ rn~tc>1" ~~ril1&Je~m2.e~a!U.I"~~ __________ ~~ _~ ______ _

Tuesday, November 10,2009 Page 2 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 1

B iM~~~~

NCP-I~~rb~~~~g t~p~_;:_at~r;i~~ 225~ d~g:-NCP k>~~;~b~~ri~gte~p~;a~~; c~~b; ~~Itit~~i~g fr;~ both th~ OAC ~;d;i~ gag;s l~~t~d;; th;~~~r~lr~~~ -0~MC-5------~

1 IKA is matched because in order to answer the question the candidate must know where the parameter (RCP pump bearing temp) can be monitored (ability to monitor), and recall the design Imaximum temperature and recognize at what point this limit will be exceeded and at which the pump controls would have to be operated to trip the pump.(to prevent exceeded the design

!11.1a)(iI11..ull1_t~fI1~ratu.l"e)~ _______ ~_~__ ___ _ ________ ~~ _____ ~

__ ~

_____ ~ __ ~~~ _________________ ~~ __________ ~

Answer A Discussion iI~~~rre~t-Fi;st part i~ i;-;;-;;e~t but pi~~sible be~~u~~e-i3~Fi;the Ii~it fu_;:_ #TSe~IOtrtlet t~~p~r-;t~~e~ S;c~~dpcrti; c-o;;'~ct,NCPl~;;rb;a_;:_i~g-t~~p~;at~;~a; -b~ ~~~ito~i;g -fr~~ -b~th--'

Ithe OAC and via gages located in the control room on MC-5 L __.. ________. ___. __ ~_~ ____. ____. _____,_.. __. ___________._. ____ ~~ ___. ___ ~ __ ~

._.~ __.~ _____________.~. _____ ~_~ ___ ~ _~ _____

~~ ___ ~ ____. ___

~ __ _

Answer B Discussion

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

---

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

---

.~---- --- _*-----1 ICORRECT: 225 deg is the maximum design NCP lower bearing temperature and should this temperature be reached, a pump trip is required. This parameter can be monitoring on both the I 11()~~_al1d_()~~~~M~-5_ __

_~ _______ ~_~ __ ~~ ~ ______ ~ ___________ ~~ _____ ~ __________ ~_~ ________________.~ ______ ~ __________ J Answer C Discussion rI~c~-;'~ct.-Fi;stp~i;-in~o-rr~~t-~tpl~~sible-~~~~~~23 5°F-i; th~li~it -f;r#lS~~IOutl~it~pe_;:_at~~;.S~~;ndp~rt-i~pl~-;;-sibl;ifth~~ppli~a~td~';~n~t ;e~all-th~ te~p~~t~;e~ ~~-b~ -.-- --I Imonitored on gages on MC-5.

l~_ __ __ ____ __

_ ____________. _____.. ____. _____.~ __. _______.~ ~~.~~._._... _~ _______

.~~ ________. ___________ ~ _______ ~ __. _~ ______________ ~

Answer 0 Discussion II~c~r~ec~ ~Fi~~ Part~r0~~~tr~C!~ls~0~r~0*y~~nd!~~~JI<0~i~l~l(t~e~~~~~a~t~~~ ~~ ~~~Il tl1~t~~~~~a~u~e~ ~;n~~~~o;ito~~~~y!~e~ ~~ ~~~ ~==~----=-_ = = -~---~~~~-

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory c--~ -'--

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

---

~----

IDevelopment References

~--~-.--.-

~-- -.-.' ---

ILesson Plan OP-MC-PS-NCP Reactor Coolant Pump land Motor Rev. 25, Pg 43 1

ILearning Objective: OP-MC-PS-NCP Obj. 15 II_~_- ________________ ~ ___________

~ ___________ _

Question Source l~!~~~~~~!~r!ic~~ f:r~~I~!~=

1401-9 Comments?

I 1

1 1 __

401-9 Comments RESPONSE 10/02/09: Requested change made.

Approved. RF A 11l09109

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

.~- 1:"- ------ ---- ---

QuestlonBank # /KA_system IKA_number

.. -.- -- -.. --- ---'-:r~-----.--.-~ + -. ---- -.. --.-. -

~~.<!!~c: _________ ~ __ ~~~ ~. ~ ____ ~

_____~~ _____________ ~ ______ ~ _____ ~~_ ~ __

~

1801lSYS003 IAl.02

_ -.1 _____________ ~ ___________________ _

[Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the

~_C!.§.c()ntrolsJ~c1l1diI1&~.lCF_R...: _41 Jl..4~*~ll~ItC:P_E~mLa.l1~ rn~tc>1" ~~ri~Je~m..p.e~aE-I.l"~~... ~...-:..............:....:.::..._~~ _~ ______ _

Tuesday, November 10,2009 Page 2 of 185

c FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 2

---~ -~-

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

-~--

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

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IQuestionBank #I IKA_system IKA_number IIKA_desc

---~-- -~----- - r-~~~- - -----!- -~~-~---- -~- ----! ~ --~-~~- -~~---~~------ ~--~~~ --~--~- --- ~-~~-~-~~--- ---------~---~----~~~-~-

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r 1802

',SYS003:

A3.0 1

! lAbility to monitor automatic operation of the RCPS, including: (CFR: 41.7/ 45.5)IJSeal injection flow L_~~ __ --- ----~ -.-

-~- ------- ~----~--- --- -- __ ~_J I I:"~'~'~'~:'~'~:~~'~:-::-::-:~'~'~-- ~~_~ _______

~ ____ ~~ __

~ __

~ ___ ~ _____ ~ ___ ~ ___ ~~_ - -

~ ___________ _

CURRENT Given the following INITIAL conditions on Unit 1:

Unit is operating at 100% RTP with all control systems in AUTO Charging Header Flow - 100 GPM Total Seal flow to NCPs - 30 GPM The following occurs:

1NV-241 (U1 Seal Water Inj Flow Control) fails CLOSED Operators have performed the immediate actions of AP-12 (Loss of Letdown, Charging Or Seal Injection).

Which ONE (1) of the following completes the statement below?

Assuming NO FURTHER OPERATOR ACTIONS, TOTAL seal injection flow 15 minutes after the failure will be A

OGPM a

30GPM C.

35GPM

~

50GPM 003A301 Swap B with C so values are increasing 45 DAY VERSION Given the following INITIAL conditions on Unit 1:

Unit is operating at 100% RTP with all control systems in AUTO Charging Header Flow - 100 GPM Total Seal flow to NCPs - 30 GPM The following occurs:

1NV-241 (U1 Seal Water Inj Flow Control) fails CLOSED Operators have performed the immediate actions of AP-12 (Loss of Letdown, Charging Or Seal Injection).

Assuming NO FURTHER OPERATOR ACTIONS, TOTAL seal injection flow 15 minutes after the failure will be A.

OGPM B.

WG~

C.

35GPM D.

WG~

401-9 Comments:

D: Why would flow go up given this failure and these conditions?

RF A 10/08109 fuesday, November 10, 2009 Page 3 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2

2009 RO NRC Retake Examination QUESTION

~~!tl~"_~E~-~l~~~~is}~~~I~~~~r!'~= ~~-==J~=Ci!s~~~-~~-~- ~~~~ ~~~~~~ __ ~~~~~~~~ _~_~~ __ ~~~~~~~~~~_ ~_ ~~~ _~ _~~ ~~~ ~~~~_~

r 1802 T SYS003 I

A3.0 1

! lAbility to monitor automatic operation of the RCPS, including: (CFR: 41.7/ 45.5)IJSeal injection flow L~,~~ ~ ~

__ ~~~~' ~,_ ~ ~,~ __ ~_~~_ L~~ __ ~ __ ~ -~~ -- ~~~~J I I:"~'~'~'~:'~'-"":~~'-"":-::-::-:~'~'~~~ ~_~~ ~~ ~~~_~,~~~_~~~ ~,~~,~_ ~ ___ ~~_~

~~~ ~~~~~~~

~ ~,_~ ______ ~~~~

CURRENT Given the following INITIAL conditions on Unit 1:

Unit is operating at 100% RTP with all control systems in AUTO Charging Header Flow - 100 GPM Total Seal flow to NCPs - 30 GPM The following occurs:

1NV-241 (U1 Seal Water Inj Flow Control) fails CLOSED Operators have performed the immediate actions of AP-12 (Loss of Letdown, Charging Or Seal Injection).

Which ONE (1) of the following completes the statement below?

Assuming NO FURTHER OPERATOR ACTIONS, TOTAL seal injection flow 15 minutes after the failure will be A

OGPM B.

30GPM C.

35GPM D.

50GPM 003A301 Swap B with C so values are increasing 45 DAY VERSION Given the following INITIAL conditions on Unit 1:

Unit is operating at 100% RTP with all control systems in AUTO Charging Header Flow - 100 GPM Total Seal flow to NCPs - 30 GPM The following occurs:

1NV-241 (U1 Seal Water Inj Flow Control) fails CLOSED Operators have performed the immediate actions of AP-12 (Loss of Letdown, Charging Or Seal Injection).

Assuming NO FURTHER OPERATOR ACTIONS, TOTAL seal injection flow 15 minutes after the failure will be A.

OGPM B.

30GPM C.

35GPM D.

50GPM 401-9 Comments:

D: Why would flow go up given this failure and these conditions?

RF A 10/08109 fuesday, November 10, 2009 Page 3 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 2

c

[The r;;,u:;.-e-oflNV=-241 ~~~id-i~oltrt;th;~~~~I-ch;rg~g fl~;P~th-r~;~itingin-all-of the ~h~gi~gfl~;bci;g di;ert~d-t~ th~ NCP-;~aTs~I;;~iate-a~tio~~;;fAP-12~~uld hav~ th~ - -- --I loperators isolate letdown. lfno further actions are taken by the crew, PZR level would then begin to increase due to the loss ofletdown and the PZR level master would reduce charging I

lattempting to bring PZR level back to program. The level master would continue to reduce total charging flow until a flow rate of 35 GPM is reached at which point the minimum setting of I

llevel master would be reached The PZR level master is set via a potentiometer, for a min charging flow of35 GPM. This is the minimum flow regardless of the level master demand. Due to Ithe closure of INV -241, all of the flow would be directed to the seals and the total charging flow is sensed upstream of INV -241so regardless of the seal injection individual flow control ivalve positions, charging flow would end up at 35 GPM.

I IKA is matched because the candidate is required to understand the expected charging flow (seal injection) automatic response to a given transient and indicate what he would be seeing on the (control board indications. (Monitor)

I IThis is a higher cog question because the candidate given an initiating transient must predict the plant response and the resulting effect on the PZR level control system.

---

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

---

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

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

Answer A Discussion

~I;~silil~ lith; ~~didate-~~~~tiY~~~i;e~ that~h-;~gi;g-fl~~-;iii-g;;t~~ini~~~ b~t-d;;~s-;ot ~~d-;;~Ul;d th~-ch;gi;g fl~; J; li~it;d-t~~ ~~imu;;;fl;;;~f35-GPM_:_-- ----- - --- --JI

---

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

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

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

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

Answer B Discussion l~~~~I~I~_~~i~~i~~~h~_~~d~~~~~~;;~s ~~t-~~~~I~~~t[ei~0v~_~~_~~~-~~_i~~I<l.t~~iAp~I_2~t5is~~ild _b~ :~fl"e:t. __.

-.-... - - -.-- --I I

_____.. _____._J Answer C Discussion

[--------

CORRECT: See explanation above L _._. __.... _______. ______... _______. __. ____._

Answer D Discussion I

. __.J i[Having flow go up is plausible if the applicant fails to realize that Letdown would be isolated per the immediate actions of AP-12.

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

~- -- --_.-.- -- -- -.-

-~.. _- - ---- --_._- _._-- ---- -'

~~gl!l!i~! ~~... el Cl.ue~!i~rl!)'Jl.e_

Question Source

--- ---*---**-1

! 401-9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension NEW

~- -- ---

---

--- --l

_.. ____.. _ - ____. ______. ____. __.. ____.. __. I loe;elopmentRefe,e';ces--- --------- --

'StudentReferencesProilded-----

l _______._._. ____. ______ ~_._._. __.__

p_. ____. ___________._. ________ _

ITechnical Reference(s): OP-MC-PS-ILE, Rev. 18 page I

117 I

ILeaming Objective: OP-MC-PS-ILE, Obj. 7 r

I I

I I

l. __. __. _________.. ____. __.. _. _____. __... ___. ____ i _________._. _______. ___. ___. ____ _

Having flow go up is plausible if the applicant fails to realize that Letdown would be isolated per the immediate actions of AP-12. This statement added to the distracter 'D' discussion. Per Chief Examiner's general comments added WOOTF question.

.. ---- ------ -'-----.. ---.-r.:--.. ------- ----

luestlonBank # IKA system IKA number

_ ---.--.----- -1_ -=-- --- __ 1_._,-.-.- ----- --.. -

[~~:~~i~~=~====== __ =~========~=========-=====~~_====~====_=_======_=~_===-_=~_==--_== __

18021SYS0031A3.0 I

__._~ ______._-----C ____________ L _________ _

[Ability to monitor automatic operation of the RCPS, including: (CFR: 41.7 / 45.5)~JSeal injection flow I

I....

• .-.*****~*.-*~.'*::*.-.*:-*_.. :-:::***.. ****::---_.- -

'uesday, November 10, 2009 Page 4 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 2

c

[The r;;,u:;.-e-oflNV=-241 ~~~id-i~oltrt;th;~~~~I-ch;rg~g fl~;P~th-r~;~itingin-all-of the ~h~gi~gfl;-;bci;g di;ert~d-t~ th~ NCP-;~aTs~I;;~iate-a~tio~~~fAP-12~~uld hav~ th~--- --I loperators isolate letdown. lfno further actions are taken by the crew, PZR level would then begin to increase due to the loss ofletdown and the PZR level master would reduce charging I

lattempting to bring PZR level back to program. The level master would continue to reduce total charging flow until a flow rate of 35 GPM is reached at which point the minimum setting of I

llevel master would be reached The PZR level master is set via a potentiometer, for a min charging flow of35 GPM. This is the minimum flow regardless of the level master demand. Due to Ithe closure of INV -241, all of the flow would be directed to the seals and the total charging flow is sensed upstream of INV -241so regardless of the seal injection individual flow control ivalve positions, charging flow would end up at 35 GPM.

I IKA is matched because the candidate is required to understand the expected charging flow (seal injection) automatic response to a given transient and indicate what he would be seeing on the (control board indications. (Monitor)

I I!ll.i~ is~ _hlg_h~rco~ 9..lI.e~tlo_nb~c:a.'ls.e_ t~e.. c:al1,:!i~~e.. ~i"e_n a.l11~~a~iI1~!1lI15;iel1t..~lIst. j)~~~tt~e..£lllI1!.I"e..sj)<J..~e..il..n~.!.h~.!~.ll.lti.l1.~ ~f'e~t..2l1.!.h~!_ZlZle..v~~ C.l1.11.tr()L~Xst.ern ________ _

Answer A Discussion

~l;~~~I~l!-~i_~~d~id~~~~~~~~~~~~;e~ tF~t:.~~~~i~;~E~~-~~-~~ti_~ni~i~_b_~~-~~~3-i~~~~~~-~~~d_~~-~~~g~~_fl~~~ ~~~~~~~~~~~~~~~~~~D".s~~~~~~~ ~-_~-_-_~~-_~ ~J Answer B Discussion l~~~~I~I~_~~i~~i~~~h~_~~d~~~~~~~~s ~~t-~~~~I~~~t[eict.0v~_~~_~~~-~~_j~~I<l.t~~iAp~I_2~t5is~~il~i~i~~~~~t.-=- ~ ~_~~_-~ ~~_--~ -~ _-~~_~-_- ~_-~~=_~-_-~~-_-~ _-_=-_-_~~-~]

Answer C Discussion

[CORRECT:- S;e-e-xpl-;;~i;;ab~v~-

- ---- - -- --------- ----- -------- ------------------ ---------- -- ------ ------ ---- ------ -- --------1 L _._. __.. ________. ______... _______. __. ____. ______________________________. _______.. __. ____... _____. ____. _____. _______________. _______. __.J Answer D Discussion

---.----.-.-------.. ------..... -.--.----- ---- ---*---***-1 Question Source

! 401-9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

--.------.---.---.---.----------.-------.----.---- --- --l

____. __. __.. ___ L __. __. _____________. _______.. _______. ______. ____. __.. ____.. ___ I

[Q!~e]~itit!~~~!i!~e.~c~~~ =-~=~===~ -_-_.. -._-. ____ -j ~~t~!~£Re~~~O£~~~~~~~-=

~ ~ ~ ~-

ITechnical Reference(s): OP-MC-PS-ILE, Rev. 18 page I

117 I

ILeaming Objective: OP-MC-PS-ILE, Obj. 7 I

I I

L ______________________________ ~ ____________________

1 _____________________ ~

__ ~ __

Having flow go up is plausible if the applicant fails to realize that Letdown would be isolated per the immediate actions of AP-12. This statement added to the distracter 'D' discussion. Per Chief Examiner's general comments added WOOTF question.

.. ---- ------ -'-----.. -----r.:--.. ------- ----

luestlonBank # IKA system IKA number

_ ---.--.----- -1_ -=-- --- __ 1_._,-.-.- ----- --.. -

[~~:~~i~========= __ =~_== ~=~===========~-======= _____ ~==== ___ ~==~==_=~_===-_=~_==--_ =~ __

18021SYS0031A3.0 I

____ ~ ________ -----'- ____________ L_

[Ability to monitor automatic operation of the RCPS, including: (CFR: 41.7 / 45.5)~JSeal injection flow I

I.... *--*****~*--*~.-*.. *.-.*:-*--*:-:.. ***.. ****::---_.- - _. _________. ____._. _____. ____. ___ -

'uesday, November 10, 2009 Page 4 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 2 DISTRIBUTE c Tuesday, November 10, 2009 Page 5 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION 2 DISTRIBUTE c Tuesday, November 10, 2009 Page 5 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 3

D 2009 RO NRC Retake Examination QUESTION 1:- -

-~~--

--.~.-~--~-.---~--,~--~ --

--.--~~-

~---

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--~

~~

~~.-

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-~~~

~~~.-~

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

rQuestionBank # !KA_system iKA_number iKA_desc I-~~-~---~

-1~~~-~~~ -~--t-~----~~ ~-~~- -~--

r~~'-~~~-~~'- - ~.- ~--.~.~~~~~.-- - ~-~ ~~

~----.~.~ ~-~~--~-.-~-- -~~~.~-~--~-- -~~~~ --_._-_._- ~--.~-~.

i 1803 SYS004 i

KS.49 iKnowledge of the operational implications ofthe following concepts as they apply to the evcs: (CFR: 41.S14S.7)ClPurpose and

,-~--~- ~

__ ~~._L ~~ ~- --~-~-"---- ~~~ ~-~--- -

Imethod of hydrogen removal from RCS before opening system: explosion hazard, nitrogen purge.....................

L ________. _____

~

~ ____

~

~

CURRENT Given the following conditions on Unit 1:

Unit is in Mode 5 Preparations for refueling are in progress The crew is preparing to perform a Nitrogen purge of the VCT Which ONE (1) of the following completes the statements below?

Nitrogen is aligned to the VCT from ---1J.L.

The purpose for performing this evolution is to ~.

A.

B.

C.

D.

(1) Bulk Nitrogen (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Bulk Nitrogen (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

(1) Shutdown Waste Gas Decay Tank B (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Shutdown Waste Gas Decay Tank B (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

004KS.49 No comment at this time RF A 10/27/09 fuesday, November 10, 2009 45 DAY VERSION Given the following conditions on Unit 1 :

Unit is in Mode 5 Preparations for refueling are in progress The crew is preparing to perform a Nitrogen purge of the VCT Nitrogen is aligned to the VCT from (1)

The purpose for performing this evolution is to --'2l A.

B.

C.

D.

(1) Bulk Nitrogen (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Bulk Nitrogen (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

(1) Shutdown Waste Gas Decay Tank B (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Shutdown Waste Gas Decay Tank B (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen I Oxygen mixture.

401-9 Comments:

Page 6 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 3

D 1:- -

-~~--

--.~.-~--~-.---~--,~--~ --

--.--~~-

~---

I.~~~~~-'~-'~~~~~~~--~'~-~'~~--~-

--~

~~

~~.-

~~.-~--~~--

~~----~

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

-~~~

~~~.-~

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

IQuestionBank # !KA system iKA number iKA_desc r-~~1-803--~-1~~sYS004~-r~-=--~K5.49~--~-- rK~~kdge-ofth~~pe~~i~~al;;;pliZati~~s-ofth~foUo~i~g~c~~~pt;~t~Y;PPiYt~th~C~V~CS~(CFR~41.5/45.7)[1P~rP~s-;;;;d

,-~ -- ~ - ~---~._L ~~ ~---- ~-"-- ~-~ ~-~--- -

lllle!ho~ ~£ Ilydro~~Il!~Ill{)v!I!roll1~CS ~~!o!eO"p~~Ili~~~.!.el11-=- ~)(pJ9~i().~ ~~..l"d-, I1itr().g~I1 plll"~e_ -.:...... :..:.... :-.:.:-.:..... ~_ _ _ ~~ ____ ~ _. _

CURRENT Given the following conditions on Unit 1:

Unit is in Mode 5 Preparations for refueling are in progress The crew is preparing to perform a Nitrogen purge of the VCT Which ONE (1) of the following completes the statements below?

Nitrogen is aligned to the VCT from ---1J.L.

The purpose for performing this evolution is to ~.

A.

B.

C.

D.

(1) Bulk Nitrogen (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Bulk Nitrogen (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

(1) Shutdown Waste Gas Decay Tank B (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Shutdown Waste Gas Decay Tank B (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

004K5.49 No comment at this time RF A 10/27/09 fuesday, November 10, 2009 45 DAY VERSION Given the following conditions on Unit 1 :

Unit is in Mode 5 Preparations for refueling are in progress The crew is preparing to perform a Nitrogen purge of the VCT Nitrogen is aligned to the VCT from (1)

The purpose for performing this evolution is to (2)

A.

B.

C.

D.

(1) Bulk Nitrogen (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Bulk Nitrogen (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

(1) Shutdown Waste Gas Decay Tank B (2) Remove air and non-condensable gases from the NC System in preparation for taking the plant solid.

(1) Shutdown Waste Gas Decay Tank B (2) Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen I Oxygen mixture.

401-9 Comments:

Page 6 of 185

FOR REVIEW ONLY - DO N T DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 3 D

General Dfscusslon iTt;:; vCTis~n~~aUy;;I~~;d-t~b;lk H2-i-~ ~;:ct;r-t~ ;~~~;~-a -~~i;~l-c~;;-~~;;-t;~ti~~ io;02;~;;;e;gi~g~ the-NC~y;t;;;'- I~ ~~d~~~t~pe~fo~;;;d~g~-~f ili; RCS:-Rad;~;

~~ii align the I'B' Shutdown Waste Gas Decay Tank to the VCT in order to provide a Nitrogen overpressure. The PZR Stm space sample is then aligned to the WG compressor which is also aligned to the I'B'SWGDT. The alignment is maintained until the Hydrogen concentration in the VCT is less than 4 % and the NCS hydrogen is less than 5cc/kg.

I IKA is matched because must understand the method ofH2 removal from the RCS during degas. The operational implication would be alternate alignment required to be performed associated Iwith the WG system, SWGDT B alignment to the VCT (CVCS). The candidate must also understand the operational implication of performing this alignment (To prevent an explosive

[mixture from being created in the NC system).

---

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

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

---

~---~--- -

---

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

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

Answer A Discussion IPlausible: (I )During degas, the NCDT and the PRT are aligned to bulk Nitrogen, it would be reasonable

~tp.<:~~~lll~()l1~b-':l~ i~~()t~a~coI112!i~~d by 1ii~r()~~n_ali~~~~nt.

to believe that the VCT would be aligned there as well. (2) ) This is also part of the Answer B Discussion r;~~-

--~----~-

~~---------

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

IPlausible: (I) As explained above, Answer (2) is correct.

---

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

Answer C Discussion iPI~~sibl~A~s;e~l) is-c~~;ct.-~~ --- - ---------~-------~-~--~

---

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

~-

l(~J~rlilllS~bl~ ai>!hl~i:5 ~I~o_r~'!o! ~h_e~~~~~~oJllti0!l but_I1()~ilc~~mpl~~e~jJ2'1'l'itl~o~~~illigE:I11~Ilt=-_~~~ _~_

Answer 0 Discussion

[~R~~T~-~~--~~~-~_~-~-

L= J~~~~el= J

=~= ~~~f1itl~~I~![~I=g~ejs~~il!~~J=~~= ~_= __ ~=~~= __===~U:~!ion)~~~;-

I RO I

Memory

[

NEW I

L_

_ ____ ~ _ ~_~ ___ ~ ____ ~ ____ ~ __ ~ ___ ~_~ _____ ~ ____ ~ ___ ~~ ____ ~~~ __ ~_ ~ __

~ _______ ~_~ __ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~~!I~p~~LR~!~!~~S-=========

li~tu~~~!~!f!i~~~!f!~~~~d ~ __ = __ -

ITechnical Reference(s): OP-MC-WE-WG Rev 11 Pg.

~7 I

I I

I I

ILeaming Objective: OP-MC-WE-WG Obj. 2 i

L _~_ _ _ ____ _ ____ ~ ~ ___ ~_~ __ ~_~_~~_~________ L ___ _

401-9 Comments RESPONSE Per Chief Examiner's general comments, added WOOTF question~ HCF 11/04109

~--

---

~-~---~-

-T-~--~~-

~--r----~---------~--

}uestlon~f1I<~ lKA_sJ~!ell!_i~_=lllll1l~r _____ _ ~~~e~~===-_===~=~-=-====== -===-=== =

____ ~ __ -_=-_== ___ ~ __ ~ ___==-_== _

====-===== =-_==_====== __ --

fKnOWledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)iJPurpose 1803[SYS004 IK5.49

~ __________

~ ___ J ___________

~ ______ _

[all'! l11~t~()~()fJ11~ro~~n_r~I11()\\,a~fr()111 RCJ)_b!!o!~()p~llill~ ~st~I11~~PIo~()1l ~~il:rcl,~nit~o~~~~~e_:-... :-............ ~. ____ ~ ~

ruesday, November 10, 2009 Page 7 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 3 D

General Dfscusslon iTt;:; vCTis~n~~aUy;;I~~;d-t~b;lk H2-i-~ ~;:ct;r-t~ ;~~~;~-a -~~i;~l-c~;;-~~;;-t;~ti~~ io;02;~;;;e;gi~g~ the-NC~y;t;;;'- I~ ~~d~~~t~pe~fo~;;;d~g~-~f ili; RCS:-Rad;~;

~~ii align the I'B' Shutdown Waste Gas Decay Tank to the VCT in order to provide a Nitrogen overpressure. The PZR Stm space sample is then aligned to the WG compressor which is also aligned to the I'B'SWGDT. The alignment is maintained until the Hydrogen concentration in the VCT is less than 4 % and the NCS hydrogen is less than 5cc/kg.

I IKA is matched because must understand the method ofH2 removal from the RCS during degas. The operational implication would be alternate alignment required to be performed associated Iwith the WG system, SWGDT B alignment to the VCT (CVCS). The candidate must also understand the operational implication of performing this alignment (To prevent an explosive rIIlixtllf~fr~~~eJllg~c~~~~~n~~~~<::~s~eEIL _~~_~~ ___ ~ __ ~_~ __ ~~_~_~~~~ __ ~ _,_~~ ____ ~_~~ __ ~~ __ ~_~_~~ ~_~ __ ~~~ ___ ~ ____ ~~ ______ ~ ___ _

Answer A Discussion

,~-.-~~~.-

-~

.. ~--~~

-~~

---

~-

-~~~~~~,--~-.. ~~-.. - '---

.----~-~~-

-~,~~~~~---~.~-~~~-~-~

~-.-'-~~-~~-~

~

'--~~~-

~~~

~.-~~-~

---,-~~~-

-~'-~----l IPlausible: (I )During degas, the NCDT and the PRT are aligned to bulk Nitrogen, it would be reasonable to believe that the VCT would be aligned there as well. (2) ) This is also part of the I

~tp.<t.~~~lllti.()ll~b-':l~)~.'l.()t~a~COIJ1.P!i~.:d by 1ii~r()~:.n_ali~~~e..nt.~_~~~~~ ___ ~_~ _~~_~~_~ ~~ ___ ~_ ~~ ~~~~_~_ ~~~~ ~~~~~ ~ __ ~~ ___ ~~~~ _~~ _ ~~~ _______ ~~ J Answer B Discussion

~~~~~b~~j-~)~i~~I~~~~d~~_b~-~~~~Il~~~-~2T~s _~~!=-~~~-~~~~-~_~~~~~ _~~~~_~_~~-_-~~~~~_-_~_-_~_-_~_-=-_~~_~~~-__ ~~~~~-_~-=-~~~~_-_~~~~~-~~~~~_ ~~-~-=-_~_~~-~~-~-_~~-=~~ ~~-~~_-~~-J Answer C Discussion iPI~~sibl~A~s;e~i) is~c~~;ct.-~~ --~ - ~---~~---~--~~--~~-~--~

---

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

-~-~~~~~ -

~-~-

l(~J~rlilllS~bl~ ai>!h.iS.i:5 ~Is.o_ra.'!.o! ~h_e~~~~.:~oJl)ti0!l but_I1()~ilc~o.mplis.~e~jJ2'1'l'itl*O~~n.illigE:I1l~Ilt=-~~~~ ~~ ___ ~~_~~_~~~ ~ ~ _____ ~~_ ~_ ~ ~~~ ~ ~_ ~ __ ~~ ~ _ ~~, __

Answer 0 Discussion

[~R~~T~-~~--~~~-~_~-=~-~_-_~~- --~_~_~~-~_

-_~_~~~_-_~~ ___ -_ ~_-_~-~_~~~~-_~-_

~-~-_~~~

~~_~_

~_~-_~~

___ ~_ ~

~~

__________ =~

___ ~ ___.~'~-~ ______ ~ ____________ ~~ ____________ ~ ____ ~=-~-~-____ -________ ~

L= J~~~~el= J

~= ~~~f1itl~~I~![~I=g~ejs~~il!~~J=~~= ~_==~=~~=====~U:~!ion)~~~~====~===

=====j 401-9 Comments RESPONSE I

RO I

Memory r

NEW I

i Per Chief Examiner's general comments, L..

--~--~ L._ --~- --- --~-~~- - ~~-- --~- -~- --- -~---~~~~--- -~---~-- - -~--- --~-~~~~-~- ~- -~~

. added WOOTF question. HCF 11/04109

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IDev;lopme~t Refe-;';nces~ -~ ----~ -~

r;:;~- --

-.~-~--, --~--.-~--.-- -~---.-

ITechnical Reference(s): OP-MC-WE-WG Rev 11 Pg.

127 I

ILeaming Objective: OP-MC-WE-WG Obj. 2 L. _._ _ _ ____ _ _, __ ~ ~_,_~ ____ ~ _'_,~_~ _____ ~ __

i~tu~~~!~!f!i!.~~!f!~~~!.d ~~~ =-

I I

I I

L _____ ~~_~~ __ ~~~~_~~~_

~~~~I~~~~I<~IKA~~~!e~=4~_:~~",~r===== =l fA~~e~~===--~~~~=~-==========-=== =---------=-~==--~--~- -~~=-~== -========= =--=--~=======--

1803[SYS004 IK5.49 I IKnowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45. 7)iJPurpose

-- ---------- ---- ~ ------- ___ ~ ___ J __ -- ---- -- -~-------- --

[~~'! IE~t~~~~~J1x~_~~~1!_r~~~~~~~r~IE R~~_?~!O!~_~P~~~~~ ~~t~IE~_~p!?~i~~~~~~~,_~it~o~~~J~~~e __ ~.~~.~~~.~~.~._.~~._~ ____ _

ruesday, November 10, 2009 Page 7 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 4

_C

,~-

--~

iQu-estio~B8nk # IKA-System-rKi-n-umber---

r--~-~-----~---~- f"--..,..----- --~--"""---- - ----

I 1804 SYSOOS:

2.4.S0 IKA desc

~ ---=--- ~--~--~- ~- -- --~--- -~-- -- -~--- -~-- -- ~- ~-- -~ ----.-- -.- - -- ----~-.- -.~-- - - --- -

-. -- -~ - -

1 _____ ~_~~ ______ l __________

~ ____________ _

iSYSOOS GENERICI:!Ability to verity system alarm setpoints and operate controls identified in the alarm response manual. (CFR:

141 __ 12~ ~~*~~.i~ll __ _________________________________________________________ _

CURRENT Given the following INITIAL conditions on Unit 1:

L TOP is in service Tave = 175°F Train B NO is in service The following occurs:

Annunciator 1A0-6 012 (PORV NC-32B Actuated) is in alarm 1NC-32B (PZR PORV) indicates OPEN Loop "C" NARROW Range Pressure is reading 370 PSIG Loop "0" WIOE Range Pressure is reading 390 PSIG Which ONE (1) of the following completes the statement below?

The controlling channel for 1 NC-32B is ~,

and based on the conditions above, what action (If any) would the operator be required to take? ~.

A B.

C.

O.

(1) Loop "C" Narrow Range Pressure (2) None, the system is responding as designed.

(1) Loop "0" Wide Range Pressure (2) None, the system is responding as designed.

(1) Loop "C" Narrow Range Pressure (2) Close or isolate 1 NC-32B (1) Loop "0" Wide Range Pressure (2) Close or isolate 1 NC-32B 00SG2.4.S0 45 DAY VERSION Given the following INITIAL conditions on Unit 1:

L TOP is in service Tave = 175°F Train B NO is in service The following occurs:

Annunciator 1AO-6 012 (PORY NC-32B Actuated) is in alann 1 NC-32B (PZR PORV) indicates OPEN Loop "CO NARROW Range Pressure is reading 370 PSIG Loop "0" WIOE Range Pressure is reading 380 PSIG The controlling channel for 1 NC-32B is~, and based on the conditions above, the operator would be required to ~.

A.

B.

C.

O.

(1) Loop "C" Narrow Range Pressure (2) Ensure 1NC-32B doses when NC pressure is reduced below setpoint (1) Loop "0" Wide Range Pressure (2) Ensure 1NC-32B doses when NC pressure is reduced below setpoint (1) Loop "C" Narrow Range Pressure (2) Close or isolate 1NC-32B (1) Loop "0" Wide Range Pressure (2) Close or isolate 1NC-32B 401-9 Comments:

The second part of distracters A and B do not state any manual or automatic actions. That action is not much different then the correct answer a stated in C. Potentially A and C are both correct answers. Modity the second parts of A and B.

This Q is U because of two potentially correct answers.

RFA 10/27/09 fuesday, November 10, 2009 Page 8 of 185 FOR REVIEW ONLY - DO c

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 4

~~~~====.=~=~======~~=========~====--===========-==--==================-========]

iQu-estio~B8nk # [KA-system-rKA~n-umber~--

r- -.-.~~~ - ~--~---

("~-..,..-~--- -- ~-~"""---- -

I 1804 SYSOOS:

2.4.S0 I~ ~ ___. __ ~ ___ ~_l ____ ~~ ____________ ~ ____ _

iSYSOOS GENERICI:!Ability to verity system alarm setpoints and operate controls identified in the alarm response manual. (CFR:

I 141,-12~~~*~~.i~ll~ ________ ~ ___ ~ ________ ~ ___ ~_~ ___ ~ ___ ~_~ ________ ~_~~_~ ___ ~ _______ ~ ___ J CURRENT Given the following INITIAL conditions on Unit 1:

L TOP is in service Tave = 175°F Train B NO is in service The following occurs:

Annunciator 1A0-6 012 (PORV NC-32B Actuated) is in alarm 1NC-32B (PZR PORV) indicates OPEN Loop "C" NARROW Range Pressure is reading 370 PSIG Loop "0" WIOE Range Pressure is reading 390 PSIG Which ONE (1) of the following completes the statement below?

The controlling channel for 1 NC-32B is ---.l1L...., and based on the conditions above, what action (If any) would the operator be required to take? ~_

A B.

C.

O.

(1) Loop "C" Narrow Range Pressure (2) None, the system is responding as designed.

(1) Loop "0" Wide Range Pressure (2) None, the system is responding as designed.

(1) Loop "C" Narrow Range Pressure (2) Close or isolate 1 NC-32B (1) Loop "0" Wide Range Pressure (2) Close or isolate 1 NC-32B 00SG2.4.S0 45 DAY VERSION Given the following INITIAL conditions on Unit 1:

L TOP is in service Tave = 175°F Train B NO is in service The following occurs:

Annunciator 1AO-6 012 (PORV NC-32B Actuated) is in alann 1 NC-32B (PZR PORV) indicates OPEN Loop "CO NARROW Range Pressure is reading 370 PSIG Loop "0" WIOE Range Pressure is reading 380 PSIG The controlling channel for 1 NC-32B is~, and based on the conditions above, the operator would be required to ~.

A B.

C.

O.

(1) Loop "C" Narrow Range Pressure (2) Ensure 1NC-32B doses when NC pressure is reduced below setpoint (1) Loop "0" Wide Range Pressure (2) Ensure 1NC-32B doses when NC pressure is reduced below setpoint (1) Loop "C" Narrow Range Pressure (2) Close or isolate 1NC-32B (1) Loop "0" Wide Range Pressure (2) Close or isolate 1NC-32B 401-9 Comments:

The second part of distracters A and B do not state any manual or automatic actions. That action is not much different then the correct answer a stated in C. Potentially A and C are both correct answers. Modity the second parts of A and B.

This Q is U because of two potentially correct answers.

RFA 10/27109 fuesday, November 10, 2009 Page 8 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 4 c

General Discussion I~---- -- ----- --~- --.- - ------.--- ----

~--

[Per procedure, RHR cannot be placed in service until RCS temperature is 250 Deg or less. Cold overpressure protection is required at this reduced temperature and is provided by PZR IpORV NC-32B and NC-34A which are placed in LTOP mode at less than 320 Deg RCS temperature. The pressure channels which provide input to actuate these PORV's are 0-600 psig NR Ipressure instruments which are placed in service with RCS pressure below 1000 psig. The lift setpoint for these valves in LTOP mode is 385 PSIG and the input to NC-32B is from Loop 'C' INR pressure transmitter (NCPT5142). The WR pressure transmitters are in service providing indication but provide no control actions.

I IKA is matched because of the low temperature requirement in order to place ND in service L TOP operation is an integral part of RHR operation in providing low temperature overpressure iprotection. In the given situation the candidate is presented with a situation where a relief valve has actuated (alarm generated) and then failed to reclose below setpoint. The candidate much

[then understand how to verifY alarm setpoint (correct channel) and operate controls to isolate the PORV which should now be closed.

I l!~~ ~~ ~i~~ ~o~~ll~~()fl~b~~~u!e e~llIlla~~~ ~

\\,e~~et~tylan!C~)Jl<ii~0!l~~~~l'ITIi~~

a_ll1i~s_ ~~~t~~n~!~ ~o~onent_aI1~ ttl~~ c!e~i~~ ()fl3 ~ct~ol1 ~()I~~~aie~~~c~~~equ~~c~s. __ ___ _

Answer A Discussion I--------~ -.-.- ---- ---- -----

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

---

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

IPlausible: Answer I is correct, answer 2 is plausible because the given WR pressure is within the range where a L TOP POR V actuation would be expected to occur but is not an input to the icontrolling circuit.

L _______________ _

~-- -----.-

Answer B Discussion iPht~;;hl~:lf th;;~~id,rt; beli~v~;th~WR-p-;~s~~; inputs L TOP. Setpoint is plausible as described above.

~-~-~--

~~~---l I

L _______. _________

~ _______

~~ _________. _____________________. ___ ~ _________________ _

_ _____ J Answer C DIscussion

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

~~ --

---

~-~ --~--~

---

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

Answer D Discussion rpl;u~ilil~ :-A~~;'~;-~~~ is -pla~;; bl~ ~-d~;~~ib~d~ ab;;e -a~d;n~~e~2is -~~~ct.~~-

~

~- -- --- -

~--

Question So~urce- ~- --- ~ -- ~~ -~~

~~- -I 401-9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

--~-~--

-"-~"~~--

"-~~ --~~~~~-- - -

~--- ---

-~l

__ ~~_~ __ ~ __ ~_~ _____ ~" _____ ~~~~ __ "_~~ __ ~_J IOevelopmen-t -Rete-;'ences - ----~~~-~ - -""-~---

lStude-ntReferences Provided

~~ -"~~~- ~ ---~"~-~---- ~--- -~-~~--- --- - --

~"---"-~~- --~~"----~~~----- -- --"-~~

ITechnical Reference(s):Lesson Plan OP-MC-PS-NC, I

IReactor Coolant System, Rev. 32, page 35 I

[Lesson Plan OP-MC-PS-IPE, Pressurizer Pressure I

!Control page 27 and 29 I

l _________ ~ __ ~ __ ~ _______ ~~ ___ ~ _____ ~"_ _ ____

L ___ ~ ________ ~_

Stem modified to ask what action (if any) would be required, distracters A,B changed to "None" system is responding properly. this addresses the concern with A,B being potentially correct. Per Chief Examiner's general comments added WOOTF question.

~~- - ---"r,--

~~--~--"-,------

~-

~~~--~

-"-~

~u_e~!I5>"!~I!~ ~ ~~_~~St!fll __ (!<!<..... ~lJrn~l'_ ~ __ ~

~.-:-jJ~~~===~-================== =-====== =-==============~============---~-~

18041SYS005

[2.4.50

__ -.1. _____________...1._

~ ___________ _

ISYS005 GENERlCOAbility to verifY system alarm setpoints and operate controls identified in the alarm response manual.

l(~~R:~4JJ2 L~~~~ ~5*~L ______ ~~~~ __ ~~ ______ ~ ___ ~~_~

fuesday, November 10, 2009 Page 9 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 4 General Discussion I~---- -- ----- --~- --.- - ------.--- ----

~--

[Per procedure, RHR cannot be placed in service until RCS temperature is 250 Deg or less. Cold overpressure protection is required at this reduced temperature and is provided by PZR IpORV NC-32B and NC-34A which are placed in LTOP mode at less than 320 Deg RCS temperature. The pressure channels which provide input to actuate these PORV's are 0-600 psig NR Ipressure instruments which are placed in service with RCS pressure below 1000 psig. The lift setpoint for these valves in LTOP mode is 385 PSIG and the input to NC-32B is from Loop 'C' INR pressure transmitter (NCPT5142). The WR pressure transmitters are in service providing indication but provide no control actions.

I IKA is matched because of the low temperature requirement in order to place ND in service L TOP operation is an integral part of RHR operation in providing low temperature overpressure iprotection. In the given situation the candidate is presented with a situation where a relief valve has actuated (alarm generated) and then failed to reclose below setpoint. The candidate much

[then understand how to verifY alarm setpoint (correct channel) and operate controls to isolate the PORV which should now be closed.

I l!~~ ~~ ~i~~ ~o~~ll~~()fl~b~~~u!e e~llIlla~~~ ~

\\,e~~et~tylan!C~)Jl<ii~0!l~~~~l'ITIi~~

a_ll1i~s_ ~~~t~~n~!~ ~o~onent_aI1~ ttl~~ c!e~i~~ ()fl3 ~ct~oll ~()I~~~aie~~~c~~~equ~~c~s. __ ___ _

Answer A Discussion I--------~ -.-.- ---- ---- -----

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

---

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

IPlausible: Answer I is correct, answer 2 is plausible because the given WR pressure is within the range where a L TOP POR V actuation would be expected to occur but is not an input to the

~~~ro~~~.c:iI:cui!. ___ ~~ __ ~ ______________ ~ ___________ ~ ______ ~ __________ ~_~~ _~ ~_~ ______ ~_~_~ __ ~ _____ ~ _______ ~_~_

Answer B Discussion

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

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

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~~a~~l>I::~~tlJe.~a.'1~idate_~e~i:\\'e~t~.:~IZ_P!:s.:~~ ~njJut~1'OI~._S.:tp~iI1~i~~Ill~ls~l~llS~.:sc~~e~!~ove. _______ ~ __________________ ~_~ _________ ~ _____ ~~ __ J Answer C DISCUSSion

~~-~~~--~~==-=_~=~-== ~~==_-~==_=~_~-= _-~~-== _-_-_-_-= _-~_-__ -= =

~=_-~-==~=_-==-===_-_-~_-_-~~_-~_-_-_-~_-_-___ -_-_ ~_~~-_-___ -_~_-~ __ ~~~ ___ -_=-~_=_==-_-=~ ______ J Answer D Discussion rpl;u-;ilil~:-A~-;;'~;-~~~ is-pla~;;bl~~-d~;~~ib~d-ab;;e-a~d;n-;~e~2is-~~~ct.~------------ -~ ---- -------~~- - ~~- ~- --------- -- -~--- -~-~~---

~---------

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---

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

---

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

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

---

~~--- ~---Qu;stk)n-So-urce------~-----------I 401-9 Comments RESPONSE

.---~--

-.-~.~~--

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

~--- -.-

-~l

______ ~ _____ ~_~ _____ ~. ___._ ~ _____._~~ __ ~ _J IOevelopmen-t -Rete--;'ences - -----~--~ - --~---

~~ -.~-~- -

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

ITechnical Reference(s):Lesson Plan OP-MC-PS-NC, IReactor Coolant System, Rev. 32, page 35 ILesson Plan OP-MC-PS-IPE, Pressurizer Pressure iControl page 27 and 29 I L.. _.. __.. ___ ~. __._. _____ ~ __.~... ___. _____.

lStude-ntRefernnce;IProvlded t-=.--.. -~ ~- - --~.~--'-~~'-'- - - -.-.---

I I L __. ~_. ____._~. _______. _________ _

Stem modified to ask what action (if any) would be required, distracters A,B changed to "None" system is responding properly. this addresses the concern with A,B being potentially correct. Per Chief Examiner's general comments added WOOTF question.

- -- - - --- - -'-'r,--

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---

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l.u_e~!I5>"!~I!~ ~ ~~-~¥.8t!fll--(!<!<..... -"'lJrn~l' ____ ~

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

iSYS005-GENERlC-O-AbJilty to-v~ritY -sy;te~ ~,;~-s~tpoim;-~d ~p~~~~~o;trcl;-id~ntifi;d-i; th~~~ ~sp~~;-e~~ual.

18041SYS005

[2.4.50

_____________ -..L___ _______

L(~~R:_4JJ2 ~~~~~ ~5*~L _______ ~~~ ___ ~ ______ ~ ___ ~~___ ____ ~ _______ ~ __ ~ __ _

fuesday, November 10, 2009 Page 9 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 4 c

ruesday, November 10, 2009 Page 10 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 4 c

ruesday, November 10, 2009 Page 10 of 185

A FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 5

9~;~~~~~~~!E<~jiS!!~~~l~:~~~~~~--

!~~~i~_~=-~===~~_~~===_====-====~======~=====~====~========~~-----

I:

1805 I

SYS006 K2.01 jKnowledge of bus power supplies to the following: (CFR: 41.7)CECCS pumps L ___________ ~ ___________ 1-__ _________

---

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

CURRENT 45 DAY VERSION Given the following on Unit 2:

Given the following on Unit 2:

j

-~

I J

A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA The 2A Safety Injection (NI) pump failed to automatically start Attempts to manually start the pump have been unsuccessful To which ONE (1) of the following locations should the NEO be dispatched to check the 2A NI pump feeder breaker?

A 2ETA B.

2EMXA C.

2ELXA D.

2TA 006K2.01 The 2A Safety Injection (NI) pump failed to automatically start Attempts to manually start the pump have been unsuccessful To which ONE (1) of the following locations should the NEO be dispatched to check the 2A NI pump breaker?

A.

2ETA B.

2EMXA C.

2ELXA D.

2TA 401-9 Comments:

Please justify why 2EMXA and 2ELXA are plausible. Neither the distracter analysis nor the reference material supports their plausibility.

This E is U until justified due to two NP distracters.

RFA 10/27/09

'uesday, November 10, 2009 Page 11 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 5 I~~-

~

~-~~~~~

~~-- -

~-~~~~,--~-~

~~-

-~~---

IQuestlonBank # iKA_system

[KA_number r--~ -1805 -~ --~j~~Sysoo6~~T-~-~~K2~01 ~ ---

~ ~ __ ~~~ ~ _ ~ ~

___ ~~~~ ~~ ~ ~L_~ __ ~ ~~ ~~~~

CURRENT Given the following on Unit 2:

A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA The 2A Safety Injection (NI) pump failed to automatically start Attempts to manually start the pump have been unsuccessful To which ONE (1) of the following locations should the NEO be dispatched to check the 2A NI pump feeder breaker?

A 2ETA B.

2EMXA C.

2ELXA D.

2TA 006K2.01 45 DAY VERSION Given the following on Unit 2:

A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA The 2A Safety Injection (NI) pump failed to automatically start Attempts to manually start the pump have been unsuccessful To which ONE (1) of the following locations should the NEO be dispatched to check the 2A NI pump breaker?

A.

2ETA B.

2EMXA

c.

2ELXA D.

2TA 401-9 Comments:

Please justify why 2EMXA and 2ELXA are plausible. Neither the distracter analysis nor the reference material supports their plausibility.

This E is U until justified due to two NP distracters.

RFA 10/27/09

'uesday, November 10, 2009 Page 11 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 5

r;;-'-----'--

~,-------,----- --------- - ------ --,----,----

-~,--- -,---

[The 2A NI Pump is powered from Emergency Bus 2ETA. It is not powered from a Safety Related Load Center (i.e. EMXA).

I

~~~~_i~ I!llltc:~~ ~~~u~~ tI1~ ~£Pli~llI1~~sl"e~t1il"e9t~~~~ ~~ Jl~~~ ~llEP~~~~th~,~llf~tx inj~~~I1SJll1mps~

Answer A Discussion rcORRECT~-------

Answer B Discussion A

---

1

, _______ J

~~~~~~j~~~-rr~ ~~~~~~~~v~~ ~~o-~ib~~~!'1~~ is p~a~~i~I~ ~e:~~~ i~~_at1,e~~~~nc)'bus _\\\\'I1~c~:~n:i~ ~~~I~a~~~6~~ ~~~~ ilIl~~~fed_~o_~ 2E! ~

!~a_~~)(.'\\~,

Answer C Discussion rI~c~;:;'e~tC~;:;'~~t ~~it~ H;~e~~r~;;~~g bus~iELXA-i~ pi~~sib'l~ -b~Z;~s~iti~ ~n-;~e~g~~cyb~s~ ;hi~h-Za;:;'k~ ~~~);~d~'(600 -YA-E) ~d-i; f~dfrom 2ET A.

L ____________________

~ ____________________ ~ ___________________ ~_. _______

~

Answer 0 Discussion r;--'---'---- -,-,- -- -- - -- -- ---,'--,---- - ---- - ---- - --,---,--- --,-,-- ------- ----

~nc~f1"~t. ~~rr~c~ ~n!~ H~\\\\'ev~r, ~ong ~~~!~~p~a~~~I~be~~~e_~ is_t~e_/1()~~~~\\\\'~rsup~!Y_t~ e!11t:r~en~~~~E,1!'. ______, ____ ~ _________ ~ __

Job Level I

Cognitive Level

---

+

---

,-~-----,----

~ 9~~s_t!oj.Il~- _~ ___ "

Question Source RO

[

Memory IY'l Developed IY'l OPT Approved

~ OPS Approved IY'l NRC Approved NEW I

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[Lesson Plan OP-MC-ECC-NI Objective 5 Section 2.2 I

i

[

I I

[

I I

I I

[

I I

I

"_, __,_,_, _______, __,_~____

L,_,, ________ ~ _____ _

401-9 Comments RESPONSE Included additional plausibility statements to justify distractors. HCF 1112/09 Added "feeder" to stem of question.

---

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---

~-, ---,'~-

QuestionBank # IKA system IKA number

--- -,-,- ---- - t'---,..------- j',-~---,- -,,-- --,--

18051SYS006 iK2.0 I f~A--'d~!~=~===~~=================-==~_~-_== -_====-_-_=_-==~= __==-==- =-_==~=~,-. -..

L~n~~t:~~e_ O!"~lls_p~~:r_s~J_lJ_l~~ tel ~he !~I~o_w~~~~C~IZ~ ~.~ 'Q~'J~~~~ ~~~P! ______. ___________ _

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

'uesday, November 10, 2009 Page 12 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 5

A fTh~ 2A Nlp-;;-~pi;~;e~;-d-~~E~~ge~~iB~s-2ETA~Iti; ~otp~;~;-d-from-'; Saf;ty Rclcrt~d-~~dC~rrt;-r (i~:-EMXA~--- ---- -- ~----------------------- -~----1 I

I

~~~~_i~ I!llltc:~~ ~~~U~~tI1~~£Pli~llI1~~sl'e~t1il'e9t~~~~~~ Jl~~~~t1EP~~~~th~~~~f~txinj~~~I1SJll1mps-,- ________ ~ ____________________________ ~. _______ J Answer A Discussion

~~~~T~:-~~~=~_~==~~===-===~==~~~=-~===-~~-=~~~:~~~~~===~====~=~~~=~~~~~=~====~~=~=========~:=~~~== ______ _

Answer B Discussion

~nc~rre~~~~rr~~ un~~~~\\\\,e.":r~ \\\\,ro~~ bus~~!'1~~ is p~a~~j~I:. ~e.:~~:. i~~_at1~el1l:r~:.nc)'bus _\\\\'I1~c~:~n:j~ ~~~I~a~~~6~~ ~~~~

ilIl~~_fed_~o_~ 2E! ~

!~a_~~)(i\\~.

Answer C Discussion

~~c~~~~~~~~~t~~it.-ii~i~~~~~~~j~~~~~~~~-~i~~~s~l~-~~~~~~i~ii~-i~i~~~~~~s-~h~~~.:~~~~~~J~~~~(t;()~-i~9_~~-~!~d!~~_2~fE~=-_-=-~~~_-=-======_~_!,

Answer 0 Discussion r;--.---.----

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---

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_ ~~~if1i!'\\'! !-~\\feJ ~..

Job Level RO Memory

~ 9~~St!~Il~-=~===~== -= ~=====~911is~~~~~~~~=~~=~~- =~-======_-] 401-9 Comments RESPONSE

__ ~~~_ ~_~ J ___ ~ ______ ~ __ _ _ _______ ~ ___ _

~ ____. ___ ~ ~ I !~~~Us~~~ ~~~~~~~:~:~~~bi~i:i!~~~~~~~s IY'l Developed IY'l OPT Approved

~ OPS Approved IY'l NRC Approved 1- --

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

--~-.-

--~.

IDevelopment References r--- -.---~-.- -.-- -.-----.- ----

~

ILesson Plan OP-MC-ECC-NI Objective 5 Section 2.2 i

I I

I

_~~. ___._ __ _ _ __ _ _ _. _______ ~

"feeder" to stem of question.

l~ttJE~f1t_F!!f!r:!f1~~_fl.rovided I l._.. _______________.. _~._~ __ _

9~! __ ti=~~~~~ ~~~~~1!teln-= t~~n~~b_e! ~=_= =~~1 f~A~d~!~=~===~ ==================-===-~~-_== -_ =-=== -_ -_=~-=======~== -=-~==~=~~ -_~ =...

l8051SYS006 IK2.O 1 I IKnowledge of bus power supplies to the followmg: (CFR: 41.7)[]ECCS pumps....................................................

____________ -L ________,_ -L ____________ ~ ___ ~ ___ I L __ ~ ___________________________________

~ ______

~ ____________ - ____ -- -

'uesday, November 10, 2009 Page 12 of 185 I

~ ~

J

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 B

r-

---

~- -- -- -- ;:-[------ -- - -T------ ----

-~-

~-

~----- -

---

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

~------ -

IQuestlonBank # IKA_system IKA_number IKA_desc

--~--- -~-

--~-I-~---~----t- -

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

f:--~-~- -~-~- --- -

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

-~-

I 1806 I

SYS006 I

K2.04 IKnowledge of bus power supplies to the following: (CFR: 41.7)LJESFAS-operated valves L _______

~ ____ ~_l_~ _____

~ ___ l_~ ____ ~ ___ ~_

I~ ___

~_~ __ ~_~~_~ __ ~~_~_~ ____ ~ __ ~

~ __ ~~

~ ___ _

CURRENT 45 DAY VERSION Which ONE (1) of the following ESF operated valves will lose power if 1EVDD is de-energized?

Which ONE (1) of the following ESF operated valves will lose power if 1 EVDD is de-energized?

A 1NI-10B, NC Cold Leg Inj from NV A

1 NI-1 OB, NC Cold Leg Inj from NV

8.

1 NV-24B, NC Loop to Excess LD Hx Isol B.

1 NV-24B, NC Loop to Excess LD Hx Isol C.

1 KC-228B, Trn B Rx Bldg Non Ess Sup Isol C.

1 KC-228B, Tm B Rx Bldg Non Ess Sup Isol D.

1 NV-142B, VCT Outlet Isolation D.

1NV-142B, VCT Outlet Isolation 401-9 Comments:

006K2.04 This Q has low DV. Increase DV by adding a second valve to each choice:

A. XZ incorrect B. XY correct C. ZY incorrect Tuesday, November 10, 2009 Page 13 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 B

r-

---

~- -- -- -- ;:-[------ ----T------ ----

-~-~-

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---

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---

~------ -

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

---

~

IQuestlonBank # IKA_system IKA_number IKA_desc

--~~-- -~-

~-~-I-~--~~----t- -

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

f:-~~-~- -~-~- --- -

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

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

I 1806 I

SYS006 I

K2.04 IKnowledge of bus power supplies to the following: (CFR: 41.7)LJESFAS-operated valves...........................................

L ___ ~ ___

~ ____ ~_l _______

~ ___ l_~_~ __ ~ ___ ~_

I~ __ ~~_~ __

~ ___

~ ___

~

__ ~_~ ______ ~~

_____ ~~~ __ ~~

___ ~_~ ___ ~~~~_~~~~~ __ ~_~ ____ ~ __

~_~ _____

~

CURRENT 45 DAY VERSION Which ONE (1) of the following ESF operated valves will lose power if 1EVDD is de-energized?

A 1NI-10B, NC Cold Leg Inj from NV

8.

1 NV-24B, NC Loop to Excess LD Hx Isol C.

1 KC-228B, Trn B Rx Bldg Non Ess Sup Isol D.

1 NV-142B, VCT Outlet Isolation 006K2.04 Which ONE (1) of the following ESF operated valves will lose power if 1 EVDD is de-energized?

A 1 NI-1 OB, NC Cold Leg Inj from NV B.

1 NV-24B, NC Loop to Excess LD Hx Isol C.

1 KC-228B, Tm B Rx Bldg Non Ess Sup Isol D.

1NV-142B, VCT Outlet Isolation 401-9 Comments:

This Q has low DV. Increase DV by adding a second valve to each choice:

A. XZ incorrect B. XY correct C. ZY incorrect Tuesday, November 10, 2009 Page 13 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 General Discussion D.. WZ incorrect This Q is U because of low DV RF A 10/27/09 B

rNV -248 ;~p~~e~edfr~~IEVDD:-All~the~ I~;d-sli;-t~d-i~fu~di'~~a~t~~ ~~

powe~~d -f~~-IEMXB~Ali~f-the-v;l~e~ii~~d-~ di;tr-;ct~~;-a~~i~ificant with respect to verification of Iproper ESF valve alignment. It is not an expectation that our operators memorize the power supplies to these valves. The information the application is required to know is that, 3 of these ivalves are motor operated 600 v AC valves and the comect answer is a solenoid operated air valve. The understanding of what types of valves requires system knowledge and operational Iknowledge.

[ttis _K_A_~s ~<lt~h~d~~'lu~e ~I. v<l~~sJ ~t~~ ()r>e~ateaut<.ll1l<tt~<llly ~1'l~~~~~~~n~g; ~~_t~~

apElic~flt~ustl(11o~_t~_ep()\\\\,~~tpply ~~

al~~<ll~~ li~~d_t()<!~eE!liI1~the correct answer.

Answer A Discussion r- -- - ---- --.----- - -. ----.. -- --.-- ------

lIn correct. Power supply is 1 EMXB I.

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

~---

Answer B Discussion

~~~~~:----- -~---'----'

Answer C Discussion IIn~~~~Zt~Po~~;~r-s~pplyis lEM:XB.

---

~---

---

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

Answer 0 Discussion 1.----- -.- ----.---.-- - -.- --- ---... - ----------

IIncorrect. Power supply is IEMXB2.

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

I Job ~~!I_ -I.

Memory

_Q~ej!I~'!TJP!~ C~.

NEW I

Question Source j--'R:o l

L. __.. _

_ __ L

__ ~ ______, __

~ ________

~ _____________ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~-

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

IDevelopment References f--- ---- --.----

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

IAP/IIA/5500115, Loss of Vital or Aux Control Power I Ipage 107 I

i i L. __ ______.. ___ ~ ___ ~ _______._. ___. _..

r::- ---- -

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

[Student References Provided I~-~-- -.- - ---- - ------.--.---- ----

I I

I I

I I..

---

.----.. ~-.--- **---*-----l--.-. ---~--.. -.. -

1.----------.-- -.-.. --

QuestlonBank # IKA_system IKA_number IKA_desc 401-9 Comments RESPONSE It is not an expectation that applicant have memorized all of the power supplies to all of the ESF valves. This question as asked, requires knowledge of what type each valve is, ie, solenoid vs. motor operated. Discuss when on site. No changes.

--.-. --.------l'--.-~ ---.- -'1--- - - --- --~. -'-

r----- ---- ----- - -.------ ---------- -.. -~--------.-------

1 ~0!~1'~~0~ __ __ 1~2

__ ~__ _ _ __~ _

~no\\\\'l_=dg_= ~~~~~()-'~e~ s_u£~I~e: ~~t~~~o~~\\\\'illg~ (~~~:_~'..-'2~~~~~:_O~erat~_valves Tuesday, November 10, 2009 Page 14 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 General Discussion D.. WZ incorrect This Q is U because of low DV RF A 10/27/09 B

rNV -248 ;~p~~e~edfr~~ IEVDD:-AI! ~the~ I~;d-sli;-t~d-i~fu~ di'~~a~t~~ ~~

powe~~d -f~~-IEMXB~Ali~f-the-v;l~e~ li~~d -~

di;tr-;ct~~;-a~~i~fi~~rrt~ith ;sp~ct to -~~~ifi~;tio~~f- --

Iproper ESF valve alignment. It is not an expectation that our operators memorize the power supplies to these valves. The information the application is required to know is that, 3 of these ivalves are motor operated 600 v AC valves and the comect answer is a solenoid operated air valve. The understanding of what types of valves requires system knowledge and operational Iknowledge.

I

[ttis _K_A_~s ~<lt~h~d~~<lu~e <111. vil~~sJ ~t~~ ()fle~ateaut<.ll1lilt~<l11y ~~~~~~~~~nills ~~_t~~ apE~c~~~ustl(11o~_t~_ep()\\\\,~~tpply ~~

al~~<ll~~ li~~d_t()<!~e~iI1~~h~~()1'f~~!.a_n_sw_.. e._r.. ____. ~

Answer A Discussion r- --- --... --.----- -.. ----.. --.-.. - ----.-.----.-.-.--.. ---~-.-

--~----

~-.--.-

---

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

lIn correct. Power supply is 1 EMXB I.

---

~-----

---

~---- --

~- ---------

Answer B Discussion

~~~~~: ----- -~--_._--_.-~~---.~-~.=~-.~ *. ~ --~-----.=~.-_. -.--~~ ~~ ~~---~~---~ ~

--~.. =----~.. ~.~~~~.~--~.. ~=~~= ~.-==~==---.----=-.--'-". -----

Answer C Discussion rln~~i~~~!~~~!-~~ppli!s.I~~xB __===-===-_ = =_ -_== =.~~. -_==_== =

-.~====.===-=======_.

Answer 0 Discussion 1.-'-'- -.. -.. -.---.-- - -.- --- --.. --. -.------

IIncorrect. Power supply is IEMXB2.

L l~pJ-~~!'_j. ---. -------

RO I

Memory L. __.. ___. _. 1.. ____... _. __.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

_Q~ej!I~,!TJP!~ C~. ---*_~~~=~~===§LI!s!lo~=S-ource-=_===_==.*~ ---

NEW I

___ L

__ ~ _________ ~ ______ _

~-

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

~D-e."~~p!!'~!l~~!f!,.ence..!.- ____________ _

IAP/IIA/5500115, Loss of Vital or Aux Control Power I Ipage 107 I

i i L. __. _____ __

r::- ---- -

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

IStudent References Provided I~---- -.-- ---- --.---... --.-----.. -

I I

I I

I I... ____. ________. ________ _

401-9 Comments RESPONSE It is not an expectation that applicant have memorized all of the power supplies to all of the ESF valves. This question as asked, requires knowledge of what type each valve is, ie, solenoid vs. motor operated. Discuss when on site. No changes.

Q~e$tlo~sank#IKA~$yst;rn--lKA~numbe~-**-... --

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r----- -.-- -.--- - -.------ --.--.---- -.. -~----.-... --.-----.-~-.---.------.-.-.-.---~--- -.---.-

1806[ISYS006 IK2.04 IKnowledge of bus power supplies to the following: (CFR: 4 1.7) 0 ESFAS-operated valves...........................................

___________________ ~

~ _ ____L~_________ _____ _

L ______________________________________________________________________________ ~

__________ ~

Tuesday, November 10, 2009 Page 14 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 B

fuesday, November 10, 2009 Page 15 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 6 B

fuesday, November 10, 2009 Page 15 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 7

,--~~---- - ~-- -l

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I 1807 I

SYS007 I

A 1.0 I

[lAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS L ----~- - ~ --

~- _. ___ ~~_l..~~ ~-- ---~- ----------ILcontrols including: (CFR: 4 I.5 / 45.5)~Maintaining quench tank water level within limits CURRENT Unit 1 was operating at 100% RTP when it was determined that 1 NV-6 (Letdown Line Inside RB Relief) is leaking 9.0 GPM to the PRT. The 1A NCDT pump has failed and was tagged last shift.

A B.

C.

D.

1) Assuming a starting level in the PRT of 70%, what would be the indicated PRT level after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

2) To which location is the PRT drained to prevent exceeding the design limit for PRT level per OP/1/N6150/004 (Pressurizer ReliefTank)?

REFERENCE PROYIPED

1) 86%

2) Containment Floor and Equipment Sump

1) 86%

2) NCDT

1) 90%

2) Containment Floor and Equipment Sump

1) 90%

2) NCDT 007Al.OI 45 DAY VERSION Unit 1 was operating at 100% RTP when it was determined that 1 NV-6 (Letdown Line Inside RB Relief) is leaking 9.0 GPM to the PRT.

A.

B.

C.

D.

1) Assuming a starting level in the PRT of 70%, what would be the indicated PRT level after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

2) To which location is the PRT drained to prevent exceeding the design limit for PRT level per OP/1/A/6150/004 (Pressurizer ReliefTank)?

REFERENCE PROVIDED

1) 86%

2) Containment Floor and Equipment Sump

1) 86%

2) NCDT

1) 90%

2) Containment Floor and Equipment Sump

1) 90%

2) NCDT 401-9 Comments:

The containment floor and equipment sump plausibility is not justified. The distracter analysis says the floor is used sometimes but doesn't say when. Consider changing A2 and C2 to the radwaste facility or something or justify plausibility.

This Q is E until A2 and C2 are either justified or replaced.

RFA 10/27/09 fuesday, November 10, 2009 Page 16 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 7 I---~-----

-l----~-- ---- - -

---,--~---~-- ---

-~- ---ll---------------- -------- -- ----- - ---- ----- ---- --- - --

---

~-

---

~-

---

~--

---~--- - ---

9~~s~~I1~~'!~ #Jt5~~ys~!"~~ l!<~,...'!~01~E!'"~-~~~~J 11S~-de~<:~ ___ ~_~ _ ~~ __ ~ _~ ~~~~ ~~ ___ ~ ~~ ~~~~~~ _ ~~_~~~ __ ~~~ ~~ _~ ~~~ ~ __ ~ ~_ ~_~~_

I 1807 I

SYS007 I

A 1.0 I

[lAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS L --~-~- - ~ ~ ~ ~~ ~ ~ ~-~ ~~1-~~ ~~ ~-~~---- -- --lC()lltl*ols~iIlClu~l~:(~£~:_ ~~5L4~22~~lv!~ntaiIlin~ 1~eIl0J:an~~ilt~EJev~1 ~wJtEinJiIl1l~...... ~......... ~........... ~........ ~.... ~:.~......_

CURRENT Unit 1 was operating at 100% RTP when it was determined that 1 NV-6 (Letdown Line Inside RB Relief) is leaking 9.0 GPM to the PRT. The 1A NCDT pump has failed and was tagged last shift.

A B.

C.

D.

1) Assuming a starting level in the PRT of 70%, what would be the indicated PRT level after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

2) To which location is the PRT drained to prevent exceeding the design limit for PRT level per OP/1/N6150/004 (Pressurizer ReliefTank)?

REFERENCE PROYIPED 1 ) 86%

2) Containment Floor and Equipment Sump

1) 86%

2) NCDT 1 ) 90%

2) Containment Floor and Equipment Sump

1) 90%

2) NCDT 007Al.OI 45 DAY VERSION Unit 1 was operating at 100% RTP when it was determined that 1 NV-6 (Letdown Line Inside RB Relief) is leaking 9.0 GPM to the PRT.

A.

B.

C.

D.

1) Assuming a starting level in the PRT of 70%, what would be the indicated PRT level after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

2) To which location is the PRT drained to prevent exceeding the design limit for PRT level per OP/1/A/6150/004 (Pressurizer ReliefTank)?

REFERENCE PROVIDED

1) 86%

2) Containment Floor and Equipment Sump

1) 86%

2) NCDT

1) 90%

2) Containment Floor and Equipment Sump

1) 90%

2) NCDT 401-9 Comments:

The containment floor and equipment sump plausibility is not justified. The distracter analysis says the floor is used sometimes but doesn't say when. Consider changing A2 and C2 to the radwaste facility or something or justify plausibility.

This Q is E until A2 and C2 are either justified or replaced.

RFA 10/27/09 fuesday, November 10, 2009 Page 16 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 7 B

General Discussion II;iti;!PRT k~clj;g~~n-at70O/~;hi~-;:~p~e~;nts ~~~I~;~~f9750g~.-With~-9GPM~~t f;; 4ho-;~s(240Min--;;t;;;),-at~;I~f2160-g~I~- Th~-;:e~~t~g ~~u-;ei~th;U;-~-;iii be 11910 igal. Using the reference provide this new volume would represent a new indicated level of 86%. The X axis on the tank curve is graduated in divisions of 250 gal, if the candidate was off rll2 of this value Standard allowable margin for error reading curves, on each tank level, the new derived level would be 90%.

lPer station procedure OPIIIN6150/004 (Pressurizer Relief Tank), Enc. 4.2 (Adjusting PRT level) the PRT level is lowered by draining to the NCDT via PRT Drain to the NCDT. The lalternate option, via the sample line to the CF&E sump is provided in section 3.6 of this enclosure. This flowpath is very limited and would not be sufficient to prevent exceeding the design Imaximum level in the tank. This fact makes the choice possible and thereby established plausibility for the distracter.

IKA is matched because given an input to the PRT the candidate must predict a resulting level after a stated period of time using a reference tank curve to determine this new level. "Operating Ithe controls" knowledge is required due the required knowledge as to where to the PRT would be drained in this situation and all of the above is required in order to maintain the water level Iwithin limits.

1 IThis is a higher cognitive level question because the candidate must take the information given, interpret a tank curve and predict an outcome.

Iknowledge. At the very least, the question requires a multi-part mental process to successfully answer.

He must also possess system operational L __________________________________

~ _____________ ~

~ ______________

~ __ _

Answer A Discussion ilncorrect: Level is correct, location to drain is wrong. Plausible because the level is correct, and the location is possible but would not used in the situation.

L _______________. _______.. ____________________________._. _____. ___. _________________. ___________. ______ _

Answer B Discussion r--- - -- -.-.-.----.- ---.---

~9~C:T

... ~,:_e:r~<l.n~tio~ _a~~~ ____ _

Answer C Discussion r: ---~.- - - --- -- --- ---.- --- -----.-- -.- -- -- -.- -- -- ----.---- ------.--. ---- - - - ---.. -- -.--.---.-.-----.----.-- - - - --- - ---- -- -- -

-- - - - --I

~~~0..rr.:~~_~o~_ ~s..w..:I"S ~r.:_~()n_g __ ~,lu.:i~~:_~s~:~<l.iI1e~~~0~~.:.~0I" ~e~~I1g_tl1~~_k.:~rve_\\\\'()u~dy..rCJ..v~d~ ~~s_I~.:.I~I1.~t~.:.I~c!tio~ ~sy~~~le bllt_W()lllc!.I1.~~~c!.iI1~.: !~atio~_g~v.:.fl. J Answer D Discussion

---~-

---

~-- - -

-~------- "------ - --------.---.-- -------

-~------

ilncorrect: First answer wrong, second is correct. Plausible: As explained above for tank level, an error reading the tank curve would provide this answer.

--- -.- ---- --- -*-*-1 L. ________. _______________. _____________

~_~ ___._. __________________

~ __ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestlonTypeT---------------Q"uestionSou-rce----

~--*----*--*-I--*----*--.-.- -.-.---

--.~-.-

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

NEW i

_______ ~

____ L

--=~

1

_. _____. ___ ~

-_. ___._1 c*-*-----------*-- -.---------------

1-*------*-------*-*----- -----

[Development References Student References Provided 1-_____ -.-- --.--.------.-------~-

l-. __._. ______. __. ______. ___ ---- -

ITechnical Reference(s) Lesson Plan OP-MC-PS-NC, IU-l Data Book Curve 7.2 (Q7) iReactor Coolant System, Rev. 31, page 35-37 1

1 I

!Learning Objective: OP-MC-PS-NC Obj. 19 1 L __. ________. ______. ____._. ___. ____. _______._

L ____._. __. ________ _

401-9 Comments RESPONSE Distracter analysis has been revised to strengthen the argument supporting the plausibility for the CF&E flowpath option.

This is a clearly stated option in the procedure and therefore is both possible and plausible. Will discuss further with Lead.

~~~~~~Tio1s$s-~f!e!""~f~~~Itl~~== ~ -== 1

~~li~~~p~;~;:n~/~~ ;~nit~~h~g~i~ p~~;~te~(t~ pr~;e;~~~e~di~g -d~sig~ li~it~-)as~~ciated ~ith ;p~r~tin-ith~- -

[

- _L -- -- --- -

. [PRTS controls including: (CFR: 41.5 I 45.5)'JMaintaining quench tank water level within limits l.. *.**:**:.-:~**.. ~**:.... ::**~**.. *.~*:.... *~.... *...._:.***.. ___. _____.___ __

_____________. __ ~ J Tuesday, November 10, 2009 Page 17 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 7 B

General Discussion II;iti;!PRT k~clj;g~~n-at70O/~;hi~-;:~p~e~;nts ~~~I~;~~f9750g~.-With~-9GPM~~t f;; 4ho-;~s(240Min--;;t;;;),-at~;I~f2160-g~I~- Th~-;:e~~t~g ~~u-;ei~th;U;-~-;iii be 11910 igal. Using the reference provide this new volume would represent a new indicated level of 86%. The X axis on the tank curve is graduated in divisions of 250 gal, if the candidate was off 1112 of this value Standard allowable margin for error reading curves, on each tank level, the new derived level would be 90%.

lPer station procedure OPIIIN6150/004 (Pressurizer Relief Tank), Enc. 4.2 (Adjusting PRT level) the PRT level is lowered by draining to the NCDT via PRT Drain to the NCDT. The lalternate option, via the sample line to the CF&E sump is provided in section 3.6 of this enclosure. This flowpath is very limited and would not be sufficient to prevent exceeding the design Imaximum level in the tank. This fact makes the choice possible and thereby established plausibility for the distracter.

IKA is matched because given an input to the PRT the candidate must predict a resulting level after a stated period of time using a reference tank curve to determine this new level. "Operating ithe controls" knowledge is required due the required knowledge as to where to the PRT would be drained in this situation and all of the above is required in order to maintain the water level Iwithin limits.

1 IThis is a higher cognitive level question because the candidate must take the information given, interpret a tank curve and predict an outcome. He must also possess system operational

~IlO~-,e~~e __ ~!.tI1~",-eJ"Y--'~a5it,-tI1~9u~S!.icJ~r~.<luJn~sa_.n1u!ti:r>..aI"tEI~fl!.1l!p~(;e-"0.c>.~u~~e~!u..!!~~3~~ ___________________________________________ _

Answer A Discussion 1------ --~-----~----- ------~-- -- ----- - --

---~------

---

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

---

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

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

--~------ -------1 IIncorrect: Level is correct, location to drain is wrong. Plausible because the level is correct, and the location is possible but would not used in the situation.

1 L ___________________________

~~ _____________________________

~ _______

~ ___ ~ ______________________________________________________

~ ___ ~

_____ J Answer B Discussion r---- -- -.-.-.----.- ---.--- -------- ---.-.-.-- --- ------- -

---

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

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

lCORRECT. See explanation above.

L ____________________

~ ___ ~

~ _________

~ ________

~ ______________

~ ____________________________ _

Answer C Discussion r: ----.- - - --- -- --- ---.- --- -----.-- -.- -- -- -.- -- -- ----.---- ------.--. ---- - - - ---.--- -.--.---.- ------.----.-- - - - --- - ---- -- -- ~

-- - - - --I iIncorrect: Both answers are wrong. Plausible: As explained above, error reading the tank curve would provide this level and the location is possible but would not used in the situation given.

1 L.-__________________________________________________________________________________________________________ ~

~ __________ ~ ________

Answer D Discussion

~n~~~e~t~~i;:~c0~~~~~~~~ i~~~dJ~~~~ct*!I~~~~~~~xP~0~d~a~~v~!~~~~~~eL!~~io~~~clir19~~~~E~~~~I~£"~0~e3§~c0~~~~~==~=~=~===_------

c:~$1_nlt!.;e~~e~!t~~=_~~9~-!~~~iiP~~ l======~=~=-~ ~.=. =~=qu~stlir!~i~£~=_~==___======~.::.=~ 401-9 Comments RESPONSE Comprehension 1

NEW i

1 Distracter analysis has been revised to

---

-.-------- ~ ___.L _______ ~

____ L ----.--- ----.-. ---.----------.-- --- ----~.. --.---- I strengthen the argument supporting the

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved ioeveiO-pmentReferences--------------

1*----- -.-- --------- -- -.---- ---~-

ITechnical Reference(s) Lesson Plan OP-MC-PS-NC, iReactor Coolant System, Rev. 31, page 35-37 1

!Learning Objective: OP-MC-PS-NC Obj. 19 i L __. ________. ______. ______. ___. ____________._

~..;dent Rei~;:-enc;s-Pro;ide(i -----

l-. __._. _______ ~_. __________ ---- -

IU-l Data Book Curve 7.2 (Q7)

I L ________________________________ _

plausibility for the CF&E flowpath option.

This is a clearly stated option in the procedure and therefore is both possible and plausible. Will discuss further with Lead.

--- -- - - --. - --1--- - -- -- - ----r- - --. ----- -.---- -I 1---* - - - ---- ----. --------- -----.--- -------- --.--.-.--- --- ---------------- ---- --------*1

~~~~~1l~5i~fF~~~~~_-j~)E'!'~'"--- ~*--l I~li0~\\~~~t and~~~ ;~nit~~h~g~i~ p~~;~te~(t~ pr~;e;~~~e~di~g -d~sig~ li~it~-).as~~ciated ~ith ;p~r~tin-ith~- --1 IPRTS controls mcludmg: (CFR: 41.5 I 45.5)'JMamtammg quench tank water level wIthm lImIts l.. *.**:**:.-:~**.. ~**:.... ::**~**.. *_~*:.. :**~.... *.. "..":.***.. _________.___ __

_ ___ _____ ________ J Tuesday, November 10, 2009 Page 17 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION 7 DISTRIBUTE B

fuesday, November 10, 2009 Page 18 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION 7 DISTRIBUTE B

fuesday, November 10, 2009 Page 18 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 8 B

r----- - - -----:-r-------- -- ---- - --- ---- --, 1.:--- -------- -.--.-. -- - -------- --- - ----.- - - - - ----- - -- -- --------- - -.---.- -.---.----------.-

IQu8stionBank # rKA_system rKA_number IrKA_desc 1*---*---- --- r-- ----.-.----.--------.-----1[--.--------.----- -----------------------.- ------.--.--- -- -.-.-- -------- - ----------

L ___ ~~O! ____ L_~~~~o~ __ L__ A2.~3 _____ J lAbility to (a) predict the impacts of.t~e following malfunctions or operations on the CCWS, and (b) based on those predictions, use rprocedures to correct, control, or mItigate the consequences of those malfunc-tIOns or operatIOns: (CFR: 41.5/43.5/45.3 /

tr45.13)LJHighilow CCW temperature.......................................

---

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

CURRENT 45 DAY VERSION The following conditions exist on UnH 2:

The following conditions exist on Unit 2:

• A normal plant shutdown is in progress

• All NC pumps are in seIVice

• Train A of NO cooling was placed in service 5 minutes ago

• 3 minutes ago the following alarms were received on the OAC:

o "2A KC HX Outlet Temp Hi Hi" o "NC Pump Thermal Barrier KC Outlet Temp Hi" for all NCPs o "NC Pump Mtr Upper BRG CLR KC Outlet Temp Hi" for all NCPs

• The following readings exist on all running NCPs:

o Motor bearing temperatures are 190°F o Lower radial bearings are 200°F o Seal outlet temperatures are 165°F Which ONE (1) of the following completes the statement below?

Operator action in response to these condHions will be to.J1L because ~.

A.

B.

C.

O.

(1) reduce the KC heat load by reducing NO flow (2) an NCP bearing temperature IimH has been exceeded due to a loss of cooling flow (1) reduce the KC heat load by reducing NO flow (2) KC HX temperatures are approaching design limHs (1) immediately stop all running NCPs (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) immediately stop all running NCPs (2) KC HX temperatures are approaching design limHs 008A2.03 A.

B.

C.

O.

• A normal plant shutdown is in progress

• All NC pumps are in seIVice

• Train A of NO cooling was placed in seIVice 5 minutes ago

• 3 minutes ago the following alarms were received on the OAC:

o "2A KC HX Outlet Temp Hi Hi" o "NC Pump Thermal Barrier KC Outlet Temp Hi" for all NCPs o "NC Pump Mtr Upper BRG CLR KC Outlet Temp HI' for all NCPs

• The following readings exist on all running NCPs:

o Motor bearing temperatures are 185°F o Lower radial bearings are 200°F o Seal outlet temperatures are 165°F Operator action in response to these condHions will be to -.-l1l.

because ill (1) reduce the KC heat load by reducing NO flow (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) reduce the KC heat load by reducing NO flow (2) KC HX temperatures are approaching design limits (1) immediately stop all running NCPs (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) immediately stop all running NCPs (2) KC HX temperatures are approaching design limits 401-9 Comments:

Change motor bearing temperatures to 190. This will give C I and D I more plausibility.

RFA 10/27/09 Tuesday, November 10, 2009 Page 19 ofl85 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 8 B

r----- - - -----:-r-------- -- ---- - --- ---- --, 1.:--- -------- -.--.-. -- - -------- --- - ----.- - - - - ----- - -- -- --------- - -.---.- -.---.----------.-

IQu8stionBank # rKA_system rKA_number IrKA_desc 1*---*---- --- r-- ----.-.----.--------.-----1[--.--------.----- -----------------------.- ------.--.--- -- -.-.-- -------- - ----------

L ___ ~~O! ____ L_~~~~o~ __ L__ A2.~3 _____ J lAbility to (a) predict the impacts of.t~e following malfunctions or operations on the CCWS, and (b) based on those predictions, use rprocedures to correct, control, or mItigate the consequences of those malfunc-tIOns or operatIOns: (CFR: 41.5/43.5/45.3 /

tr45.13)LJHighilow CCW temperature.......................................

---

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

CURRENT 45 DAY VERSION The following conditions exist on UnH 2:

The following conditions exist on Unit 2:

• A normal plant shutdown is in progress

• All NC pumps are in seIVice

• Train A of NO cooling was placed in service 5 minutes ago

• 3 minutes ago the following alarms were received on the OAC:

o "2A KC HX Outlet Temp Hi Hi" o "NC Pump Thermal Barrier KC Outlet Temp Hi" for all NCPs o "NC Pump Mtr Upper BRG CLR KC Outlet Temp Hi" for all NCPs

• The following readings exist on all running NCPs:

o Motor bearing temperatures are 190°F o Lower radial bearings are 200°F o Seal outlet temperatures are 165°F Which ONE (1) of the following completes the statement below?

Operator action in response to these condHions will be to.J1L because ~.

A.

B.

C.

O.

(1) reduce the KC heat load by reducing NO flow (2) an NCP bearing temperature IimH has been exceeded due to a loss of cooling flow (1) reduce the KC heat load by reducing NO flow (2) KC HX temperatures are approaching design limHs (1) immediately stop all running NCPs (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) immediately stop all running NCPs (2) KC HX temperatures are approaching design limHs 008A2.03 A.

B.

C.

O.

• A normal plant shutdown is in progress

• All NC pumps are in seIVice

• Train A of NO cooling was placed in seIVice 5 minutes ago

• 3 minutes ago the following alarms were received on the OAC:

o "2A KC HX Outlet Temp Hi Hi" o "NC Pump Thermal Barrier KC Outlet Temp Hi" for all NCPs o "NC Pump Mtr Upper BRG CLR KC Outlet Temp HI' for all NCPs

• The following readings exist on all running NCPs:

o Motor bearing temperatures are 185°F o Lower radial bearings are 200°F o Seal outlet temperatures are 165°F Operator action in response to these condHions will be to (1) because (2)

(1) reduce the KC heat load by reducing NO flow (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) reduce the KC heat load by reducing NO flow (2) KC HX temperatures are approaching design limits (1) immediately stop all running NCPs (2) an NCP bearing temperature limit has been exceeded due to a loss of cooling flow (1) immediately stop all running NCPs (2) KC HX temperatures are approaching design limits 401-9 Comments:

Change motor bearing temperatures to 190. This will give C I and D I more plausibility.

RFA 10/27/09 Tuesday, November 10, 2009 Page 19 ofl85

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 8 B

General Discussion r;:;-~ ---~---~~

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

~~~~-

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

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

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

--~-~

-~

--~------~~

I ExPlanation (Optional): In the scenario provided in this question, indications are provided in which an excessive heat load has been placed on the operating train ofKC. NCP pump temperatures are elevated but have not exceeded any operational limits. To address this condition the crew will need to reduce the NC cooldown rate which will decrease the heat load on the IKC system to provide additional cooling to the NCP's.

i iThe KIA is matched because the applicant must evaluate the impact of the malfunction (Hi CCW temperature) on the system's ability to perform its design function (in this case provide Icooling to the NC pumps). Based on the predicted impact to the system (design limits will be exceeded), the applicant must select the correct action to mitigate.

)

I I

IT_he~u~~tion_ is Ei~~~ co~~eeall~~~h~ ~<lfl~i~ilt~rnus!f>r~cIi~t ~o~ute~ll1~ and~e1ectaJ1~cti9~t<J~{)lve !~ey~o~~IIL_l'l!i~~guir~s_ ~il1~tl1e ~~~~ed¥~ IIJ~d Jt~Il1~aI1il1~ to ~()\\~e~aEroblell1~_ J Answer A Discussion rla~~~~!~~E~~i~~~~c~_L~~~~adlai ~~rl~~_teln£~~~~~~l ~~d~~~~~~ih~E0~!oi0~t~r}~~0i~~~ ~==~~==

Answer B Discussion IICORRECiS~e~~pl~~i;n above

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

Answer C Discussion

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

---

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

tlPlausible: Candidate may believe that NCP limits have been exceeded. The values given in the stem are close to design limits.

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

Answer 0 Discussion

!CPlausible Candidate may believe that NCP limits have been exceeded. The values given in the stem are close to design limits. Second part is correct.

---

~-

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

---

~----- ----

---~ -

~--- --

,I-----------T-----------~-- -

---

~-

~.J()~ '-!\\le!_~ ___ ~~ojJE'!~~!_~\\lel

~ 911!s~I~/'IType NEW

---~~-~- -

-~~ -~ -QuestionSo~rce--- - -~------l 401-9 Comments RESPONSE I

RO I

Comprehension L_~~~ __ ~~l_~ ___ ~_

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~-~~

---

~-~~- --1 1

r----

-~-~ --~~-

~--

~

---~-~- ---

~

~~

~------

~--~~ - --

~---

l[)!v~e!op~_!n_t ~!!!!~e~n~!~_ ~ _ ~~__ _. _~ _

i~tlJ~!'!~ ~e!~~,!c~! !=>>!<>v-'f!e_d _ ____.

[Technical Reference(s): Lesson Plan OP-MC-PSS-KC, I

iRev.25 I

[Lesson Plan OP-MC-PS-NCP, 1

[Learning Objective: OP-MC-PSS-KC, Obj. 8 I

I I

L __________________________________

~_ _

Per Chief Examiner's comment, changed motor bearing temperature to 190°F. Also, added WOOTF question per Chief Examiner's general comments. HCF 11102/09 r~----~---~--~-~---~----~~

r.~--~~--~ -~~------,

-~~~~----

---

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

IQuestionBank fl.IKA_system IKA_number I IKA_desc

~~~~ -

-~~~~~~~-

-~1-~~~ -~--~-- ~~ ~ -

-~~~-- ~-~-

-~-- - -- --I 1-- --- -~- -

-~ ~ --- -~~ -

-~~ - ~ - -

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

~ -

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

--~-

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

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

__ ~ ___ ~ __ 1~08IS~~~08 __ ~ _ JA2.0L_ _

~~. ~ J liAbility to (a) predict the impacts of the f~lIowing malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc-tlOns or operatIOns: (CFR: 41.5 143.5/45.3

(_~.!~~I!:li¥~o~c:c:\\\\'~e_my~r:a!tJ~e~ __ ~ ______ ~.. ~ _~ ____ ~_~ ___ ~ __ ~... ~ _____ ~ _____ ~ ___ ~~_~ ~ __

Tuesday, November 10, 2009 Page 20 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 8 B

General Discussion r;:;-~ ---~---~~

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

~~~~-

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

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

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

~-~-~

-~

--~------~~

---

~

I I

ExPlanation (Optional): In the scenario provided in this question, indications are provided in which an excessive heat load has been placed on the operating train ofKC. NCP pump I

temperatures are elevated but have not exceeded any operational limits. To address this condition the crew will need to reduce the NC cooldown rate which will decrease the heat load on the I IKC system to provide additional cooling to the NCP's.

1 I

1 1

iThe KIA is matched because the applicant must evaluate the impact of the malfunction (Hi CCW temperature) on the system's ability to perform its design function (in this case provide I

Icooling to the NC pumps). Based on the predicted impact to the system (design limits will be exceeded), the applicant must select the correct action to mitigate.

I

)

I I

IT_he~u~~tion_ is Ei~~~ co~~eeall~~~h~ ~<lfl~i~ilt~rnus!f>r~cIi~t ~o~ute~ll1~ and~e1ectaJ1~cti9~t<J~{)lve !~ey~o~~Ill:_l'l!i~~guir~s_ ~il1~tl1e ~~~~ed¥~ IIJ~d Jt~Il1~aI1il1~ to ~()\\~e~aEroblell1~_ J Answer A Discussion rla~~~~!~~E~~i~~~~c~_L~~~~adlai~~rl~~_teln£~~~~-;s~l~~d~~~~~~ih~E0~!oi0~t~r}~~0i~~~~==-~~======= -_-~~====~=============== __ _

Answer B Discussion

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

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--~~-----~--~-~---~l ICORRECT. See explanation above I

I~ ~ - ~ __ ~_ ~~ ____ ~ __

~ __ ~~ - ~ __ ~~_ ____

~____~~~ __ ~ __ ~ __ ~_~ _________ ~ _~_~~ ___ ~~ ____ ~ _____ ~ __ ~_~~ ___ ~_~ ~ __ ~~ ___ ~~ _______________________ ~

Answer C Discussion lP~~usi~I::~C_a~~i~~e ~!~~e~i:ve_t11a~~~~~~~sh~~e~b:eI1~:ce~d~cl. _ Th:~~~~ ~i~~n~~~h~~~~are c1{)s~~o_desi~ }iIn~t~~ ____ ~ __ ___ __ __ ________ ~ __ ~

Answer 0 Discussion

~~ -

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

!Plausible Candidate may believe that NCP limits have been exceeded. The values given in the stem are close to design limits. Second part is correct.

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RO I

Comprehension L ____ ~~~ __ ~~J_ ~ ___ ~~~_

~~ _____ ~~ __

__________ ~ _____ ~ _____ ~ _______ ~ __ ~~~ _________ ~~ __________ 1

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r----

-~-~ --~~-

~--

~ ---~-~- ---

l[)!v~e!op~_!n_t ~!!!!~e~n~!~_ ~ _ ~~__ _. _~_

[Technical Reference(s): Lesson Plan OP-MC-PSS-KC, iRev. 25

[Lesson Plan OP-MC-PS-NCP, ILearning Objective: OP-MC-PSS-KC, Obj. 8 L _____ ~ __ ~ ____ ~ _______ ~ ~ ~ ______ ~ __

IStudent References Provided I~-~~~--~-~---~~~---~~--

_~ ___ _

1 I

I 1

1 I

r-----~---~--~-~---~~---~~

r.--~--~

-~------

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Per Chief EXan1iner's comment, changed motor bearing temperature to 190°F. Also, added WOOTF question per Chief Examiner's general comments. HCF 11102/09 IQuestionBank fl.IKA_system IKA_number I IKA desc

~~~ - -~~~-i8-081SySO~08~- ~~ TA2JJ3 ~ - ~ -- -- -

-j lAbilitY to-(~) p~';-djct th; ~p;cts-of th~ foll;;i~i ;~iu~ctio~~~r-~p;r;tio~s~~ the CCWS, ;nd (b-) b;;';-i o~tho;e p~edi~tjons,

--- ---~- - -

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

.~ ~~~ ~- ~ -I luse procedures to correct, control, or mitigate the consequences of those malfunc-tions or operations: (CFR: 41.5/43.5/45.3

(_~.!3)~1!:li¥~0~ c:c:\\\\'!e_my~r:a!tJ~e~~:.......... :... '_.... :__... :.. :__... ~ ___ ~_~ ___ ~ __ ~~ _____ ~ _____ ~ ___ ~~_~ ~ __

Tuesday, November 10, 2009 Page 20 of 185

B FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 9 r------- ----- -

_r ____

~ _______

, __ ~*_.-----

---

l r-=-------------- -- ---- ------- - -----.- -- - ---- --

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IQuestionBank # IKA_system IKA_number

! IKA_desc i_-_~-_!-~o[-_~j- }y-soJ ~~-1~_-~ _-~~.04 ~-~ -j ~~~~dg~ ~ith~-eff';-ct~f~lo~;o-;:-~~f~cti~n-ofth~ folIowi~g -wi£l~~-o~th~ PZRPCS~cFR~4i~7i4~7)lJPRT --------

I...........................................................

l ___________________________________

~ ______________

~ _____ ~

~_~ ___

~ ______

~ _____ _

CURRENT Given the following conditions on Unit 1 :

NC system pressure is 1985 PSIG and slowly decreasing due to a leaking Pressurizer Code Safety Valve (1NC-1)

PRT pressure is currently 65 PSIG Discharge temperature downstream of 1NC-1 is 310°F Containment pressure is currently 0.1 PSIG Which ONE (1) of the following completes the statement below?

If the PRT rupture disc fails prematurely given the conditions above, the rate of NC system depressurization will (1)

AND the temperature downstream of 1NC-1 will m

A.

(1) increase (2) remain the same B.

(1) increase (2) decrease C.

(1) increase (2) increase D.

(1) remain the same (2) decrease 01OK6.04 45 DAY VERSION Given the following conditions on Unit 1 :

NC system pressure is 1985 PSIG and slowly decreasing due to a leaking Pressurizer Code Safety Valve (1NC-1)

PRT pressure is currently 65 PSIG Discharge temperature downstream of 1NC-1 is 310°F Containment pressure is currently 0.1 PSIG If the PRT rupture disc fails prematurely given the conditions above, the rate of NC system depressurization will (1)

AND the temperature downstream of 1 NC-1 will

.0 A.

(1) increase (2) remain the same B.

(1) increase (2) decrease C.

(1) remain the same (2) remain the same D.

(1) remain the same (2) decrease 401*9 Comments:

It's common knowledge that the Pzr relief valves discharge to the PRT. If the PRT ruptures, it will result in a lower pressure. This also is common knowledge. Therefore, distracter Cis NP. Change C to increase, increase.

RF A 10/27/09 fuesday, November 10, 2009 Page 21 of 185 B

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 9 r------- ----- -

_r ____

~ _______

, __ ~*_.-----

---

l r-=-------------- -- ---- ------- - -----.- -- - ---- --

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IQuestionBank # IKA_system IKA_number

! IKA_desc

! ---~~1809---t-SY~SOI 0--1---- - K6.04 ----1 iK~~~dg~ ~ith~~eff';-ct~f~lo~;o~~~f~cti~n-ofth~ folIowi~g -will~~-o~th~ PZRPCS~cFR~4i~7i4S:7)lJPRT - --~~ ---

1-- ~ --- -- ----~--~~- _____ L- ___ - ------- - ---~ I...........................................................

l ___________________________________

~ ______________

~ _____ ~

~_~ ___

~ ______

~ _____ _

CURRENT Given the following conditions on Unit 1 :

NC system pressure is 1985 PSIG and slowly decreasing due to a leaking Pressurizer Code Safety Valve (1NC~1)

PRT pressure is currently 65 PSIG Discharge temperature downstream of 1NC-1 is 310°F Containment pressure is currently 0.1 PSIG Which ONE (1) of the following completes the statement below?

If the PRT rupture disc fails prematurely given the conditions above, the rate of NC system depressurization will (1)

AND the temperature downstream of 1NC-1 will (2)

A.

(1) increase (2) remain the same

8.

(1) increase (2) decrease C.

(1) increase (2) increase D.

(1) remain the same (2) decrease 01OK6.04 45 DAY VERSION Given the following conditions on Unit 1 :

NC system pressure is 1985 PSIG and slowly decreasing due to a leaking Pressurizer Code Safety Valve (1NC-1)

PRT pressure is currently 65 PSIG Discharge temperature downstream of 1NC-1 is 310°F Containment pressure is currently 0.1 PSIG If the PRT rupture disc fails prematurely given the conditions above, the rate of NC system depressurization will (1)

AND the temperature downstream of 1 NC-1 will (2)

A.

(1) increase (2) remain the same

8.

(1) increase (2) decrease C.

(1) remain the same (2) remain the same D.

(1) remain the same (2) decrease 401*9 Comments:

It's common knowledge that the Pzr relief valves discharge to the PRT. If the PRT ruptures, it will result in a lower pressure. This also is common knowledge. Therefore, distracter Cis NP. Change C to increase, increase.

RF A 10/27/09 fuesday, November 10, 2009 Page 21 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 9 B

General Discussion

---

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

--~---

-,~-.---~------~--

IWhen the PRT rupture disc fails the differential pressure across the leaking Safety Valve will increase thereby increasing the rate of leakage and the rate of depressurization. With the Safety IValve now discharging to a lower pressure (Containment atmospheric pressure), the isenthalpic throttling process will now result in a lower discharge temperature on the Safety Valve idischarge line.

I IThe KA is matched because the applicant must determine what happens to the rate of the NC system pressure decrease when the PRT rupture disc fails.

I IThis is a comprehension level question because the applicant must evaluate a change in conditions (i.e. before and after PRT rupture disc failure) and determine the consequence to NC system i]ea~!ll~ ~~

~a~e!yy_a~~~i~cE<lf~e J~(; ~eJl1E~<ltIlf~'___ _ __. _. _ ______ _ _ ____ _____ _ __ __ ___ _

Answer A Discussion r -- -------- -- --.--- ---- ------

~----_:_-__:- ----

--~----- - --- ------- -- -------- --- - - --:------:-.-----~- -- -- ------ -------- -----.----.---;---;------- -------.

IIncorrect. Part 1 IS correct. Part 2 IS plauSible If the applicant does not comprehend that the Safety Valve IS now dischargmg to a lower pressure when the PRT rupture diSC fails.

I L __________________._. __. _____________________. ______________ ~ ________

~ ____________________ ~ _________

. ___________________ ~ _______

J Answer B Discussion

~~~c(- _-_-_-~_~ _-~---

____________ ~ ____________ ---.J Answer C Discussion ri;c~e~t p~

-I-i-;- ~o~r~ct.P~rt 2j;-pla~siw~-if th~ ~p-piic~;t d~~~-;;;t -u;de~sta-;:;d i;e~th;iPiZth~ottli;;-g-b~Za~;e itis-Pla~-;;ble-t~ bcli~~ -t~t~in~~~;dfl~;~att~ill r~;uli in-g;:~ter heater

~r_alls!e-," llIl.9 _t11U~ ~d inc)"e_as~ _in. ~I11f'e~a~~_ _ _.. _

Answer 0 Discussion r--- ---- ---- -- -.--- ---------- -- ------- --- -- -- ---.-- -- ----- ---- --------- - --- ---- --- -- -- ----- -- -.- --.- ----- - - -- -- -.-- ----- ------- --- ---

IIncorrect. Part 2 is correct. Part 1 is plausible if the applicant does not comprehend that the larger DP across the valve will result in a higher leak rate.

L_____ ___ __ ______ ______ __

~_~_ _

__~_____ ___

Job Level Question Source 401-9 Comments RESPONSE

-~-

.. __ ~ogn!t!v~J_~~!I_

_ 9lJ!.s~i~I'I!.~! _ L ____. __

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

RO

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension NEW I

__ L _

roe;eloplTle~t -R-efen;~ces --. -------------

f---- --- - ----- ------- --- --- ---- - -------

ILesson Plan BNT-TH03R3 Steam Properties Objective 114 page 32 IBNT-CP02R8P, Sensors and Detectors - Process

Objective 16A page 46 and 47 I L __________________. _________. __ _

Per Chief Examiner's comment, changed distractor "c" answers to "increase/increase". Also, revised distractor "Student References Provided analysis to match new answers. Also, added 1------------- --- -------

WOOTF question per Chief Examiner's I

general comments. HCF 11/02/09 I

I

! l... _

- - -- --------- -T,--------,-- ---- --- --- -----, r----------

---

~-----

~~~tI~n_E!.a_n~ !lJ~~""_SJ!btf!l __ ~=I'I~Il\\~!r _____ i 1809[SYSOIO IK6.04 i

________

• _____ L ____________._.L __________. ______ J IKA desc r--=----- ------ - - -- ---- ------- - - ---------.------ ----.--- ---

IKnowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: (CFR: 41.7/ 45.7)L:WRT I:~*.-:*:.::.-::.-:.. *.. *:.-*.-:**~*:.:.***-:.-*:.-::.-:-.:*:.::-.::-.::~*** ___________ _

fuesday, November 10, 2009 Page 22 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 9 B

General Discussion rWhe;th~PRT~p~~-dis~faiis th;diffe~~ti;;l p~;s;r~ ;;c~o~;th;I~~i~g Safety-V~lv-;; ~iil-i~c~;aie t~;ebYi~c~~;gthe-r~; ofTe;k~ie~dt~~~e-;f dq;r~;;~ri;~t;;;~.~With the Safety

[Valve now discharging to a lower pressure (Containment atmospheric pressure), the isenthalpic throttling process will now result in a lower discharge temperature on the Safety Valve idischarge line.

I IThe KA is matched because the applicant must determine what happens to the rate of the NC system pressure decrease when the PRT rupture disc fails.

I IThis is a comprehension level question because the applicant must evaluate a change in conditions (i.e. before and after PRT rupture disc failure) and determine the consequence to NC system i]ea~!ll~ ~~

~a~e!yy_a~~~i~cl1<lf~e J~(; ~eJl1E~<ltIlf~'__~ _ __ _ _ ____ ~ _________ ~~__ _ ~_ __ ___ _

_ _____ ~ ___ ~ ~~ _~~ ~ __ ~ __ ~ ____ ~ ~_~~ ___ _

Answer A Discussion r --

--~----- -- --.-~- ---- ------ ~----_:_~-:~ -~--

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

-~:------:- ---~--:_- -- ~- ~~-~'--- ----~-~-

--~--------~--:----:------- --~-~-~.

]Incorrect. Part I IS correct. Part 2 IS plauSible If the applicant does not comprehend that the Safety Valve IS now dischargmg to a lower pressure when the PRT rupture diSC fails.

I L __________________._. __. _____________________. ______________ ~ ________

~ ____________________ ~ _________

. ___________________ ~ _______

J Answer B Discussion

~~~c(- _-_-_-~_~ _-~---

-- --- -- -~- -

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

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

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

- ----I I

_______________________________________________ ~ _________ ---.J Answer C Discussion I---~----- -- ---- -

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

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-~-~----~-

-~-

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

---

~---~

IIncorrect. Part I is correct. Part 2 is plausible if the applicant does not understand isenthalpic throttling because it is plausible to believe that an increased flowrate will result in greater heater

~r_alls!e-" llIlj _t11U~ ~d JIlc)'e_as~ _i~ ~I11f'e~a~~_ _ _"" _

Answer 0 Discussion r--- ----

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

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

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

-~--

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

~--~- -- - --

~~ --

~--~-

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

IIncorrect. Part 2 is correct. Part I is plausible if the applicant does not comprehend that the larger DP across the valve will result in a higher leak rate.

L_____ ___ __ ______ ______ __

_~ ________________ ~_~_ _

_ ___________________________________________________________________ ~

r "" Job Level t-- -

i RO

""~" _~ogn!t!.;~}.~~!i_ -.".1~9~~s~i~~!vj!~

l __ _ _ ____ _ _

_ C~m!~ehens~~ __ ~~J ___ 2'1~~_""

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~~~~~n"I!~=R!!e~~c~~ ~ -__ ~ -~~ =

=~=== --

ILesson Plan BNT-TH03R3 Steam Properties Objective 114 page 32 IBNT-CP02R8P, Sensors and Detectors - Process

Objective 16A page 46 and 47 I L ___________________________ ~" __ _

Question Source

St~ent-R&t;..en~es P~ovlded ~ - - ----

I---~ ~- - - - -"--

~- - --

~--- -- -

I I

l" ___ ~ ___ ~ ___ ~_

-~------- -T,--------,-- ---- -- - --- ---, r--- ----------- -

~--- - - -----

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

IKA desc 401-9 Comments RESPONSE Per Chief Examiner's comment, changed distractor "c" answers to "increase/increase". Also, revised distractor analysis to match new answers. Also, added WOOTF question per Chief Examiner's general comments. HCF 11102/09

~~~tI~n_~a_n~ !lJ~~""__SJ!btf!l __ ~=fl~Il\\~!r _____ i 1809[SYSOIO IK6.04 i

r---=-~~----------

---~~-

~---------

---

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

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

IKnowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: (CFR: 41.7/ 45.7)L:WRT

______ ~

_______ L _______ ~

__ L __ _______________ J I:~*~*~:-::-:.. *.. *~*~*~*~*-,-*-~*:-:~:-:*~~~:~,,* __ ~ ____________ ~~ ________ ~_~

___ ~ _____ ~ ___ ~~ __________ ~

____ ~_

fuesday, November 10, 2009 Page 22 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE C

2009 RO NRC Retake Examination QUESTION 10 r-:-'-~--~'-

-~---r-~-~~-'~~~,~-----~'-'-~~~-',

I-~~~~~--'-'~-

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l~_ ~~l!I ~~_~ __ ~~~~I~ ~ __ L __ ~ __ ~~~_~~_~_! iKnowledge ofthe effect of a loss or malfunction of the following will have on the RPS: (CFR: 41.7/ 4517) rJ Trip logic circuits l',~~'~:"'::~'~'~'~:=--'~=--'~',~:~:_':

CURRENT Given the following:

Reactor power is steady state at 50% RTP Power Range Channel N-42 has just failed LOW Which ONE (1) of the following combinations of remaining OPERABLE channels indicate the status of the trip logic coincidence required for the High Neutron Flux Trip:

1) After the failure has occurred, but BEFORE Power Range Channel N-42 is removed from service?

2) AFTER all required I&E actions have been completed for removing Power Range Channel N-42 from service?

012K6.03 45 DAY VERSION Given the following:

Reactor power is steady state at 50% RTP Power Range Channel N-42 has just failed LOW Power Range Channels N-41, N-43, & N-44 are OPERABLE Which ONE (1) of the following combinations of remaining OPERABLE channels indicate the status of the trip logic coincidence required for the High Neutron Flux Trip:

1) After the failure has occurred, but BEFORE Power Range Channel N-42 is removed from service?

2) AFTER all required I&E actions have been completed for removing Power Range Channel N-42 from service?

401-9 Comments:

The 3rd bullet is not required because they were never declared inoperable.

RFA 10/27/09 Tuesday, November 10, 2009 Page 23 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 10

__ c_. __

iclue;tlonBaOkiIKA~syste-m~~iKA=~umber--~~~-lfKA=desc~-- -~- -~- -~-~--~- ~~- -~~~=-~~==~=-~~

==--=-~ __ ~_~~~ __ ~ _____ ~ _~~~ ____ ~_

r -- ~]810-~--=-1--~YS03 ~_~r~==--=~~_~==_-=J i~-o~kdie~fili~~ffeZt ~f ;l~s-; ~r -~aTfu~cti~~fthe following will have on the RPS: (CFR: 41.7/ 4517) rJ Trip logic circuits I

~-- ~ - - ~

-~

l*_~~*~~,::~*~*-,-,*~:~*~~*-,-,*.~:~:_*:~_~~~~~ ___ ~.~~_~._~~ ______ ~~~~~~ __ ~_~~_~~~ ____ ~ __ ~_~~~~~.~~~_~J CURRENT 45 DAY VERSION Given the following:

Reactor power is steady state at 50% RTP Power Range Channel N-42 has just failed LOW Which ONE (1) of the following combinations of remaining OPERABLE channels indicate the status of the trip logic coincidence required for the High Neutron Flux Trip:

1) After the failure has occurred, but BEFORE Power Range Channel N-42 is removed from service?

2) AFTER all required I&E actions have been completed for removing Power Range Channel N-42 from service?

012K6.03 Given the following:

Reactor power is steady state at 50% RTP Power Range Channel N-42 has just failed LOW Power Range Channels N-41, N-43, & N-44 are OPERABLE Which ONE (1) of the following combinations of remaining OPERABLE channels indicate the status of the trip logic coincidence required for the High Neutron Flux Trip:

1) After the failure has occurred, but BEFORE Power Range Channel N-42 is removed from service?

2) AFTER all required I&E actions have been completed for removing Power Range Channel N-42 from service?

401-9 Comments:

The 3rd bullet is not required because they were never declared inoperable.

RFA 10/27/09 Tuesday, November 10, 2009 Page 23 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 10 c

I~-----------~-

---

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

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

---~--.--- -

---

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

---

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

---

~-----

ISince N-42 has failed low, the Hi Neutron Flux Trip Logic will never receive a trip signal from that channel. Since two high flux signals are required to initiate a trip signal and there are only Ithree channels remaining which could potential generate a high flux trip signal, the logic for a Power Range Hi Flux trip is 213 channels.

I IWhen the I&E actions for removing N-42 have been completed the High Flux Trip Bistable is placed in the tripped position. Since only one more (of the remaining 3) High Flux Trip Bistable

[signals is required to intiate a Hi Flux Trip, the logic now becomes 113 channels.

I I [The KA is matched because the question requires the applicant to know how the loss of a channel will effect the RPS trip logic before and after a channel is removed from service.

I IThis is a comprehension level question because the applicant must recall the normal trip logic from memory, must understand that with the channel failed low the trip logic is unaffected, must I~~!:~t:~~~:~ when the channel is removed from service the high flux trip bistable is placed in the trip condition, and must associate all of those pieces of information to determine the I~ __,~~~~,~ ~,

__ ~~~~_~~ _~~ ~ ~ ~~~~ ~__ ____

~~~~ ~~ ~~_~~~~~~ ~ ~~~_~ ______ ~~_ ~ __ ~ ~~ ___ ~~~~~~ __ ~~ _____ ~~ __ ~~~,_,~~~~.. _~ __ ~~_ --~~~------

Answer A Discussion ilncorrect. Plausible if the applicant confuses the channel failing low with the channel failing high in which case this answer would be correct.

L

~ ____________________ ~ __________. __________________________________________________ _

Answer B Dlscu8sion iI~;;~~~~tPla~~ibl~irth~~~;did~U: ~~f~;~ the~ha~~el faili~g I~~ th~ th~-ch~;clfaili~g highANDb~I;~~e~ th;-tth~I&E ~cti~n~fu~~~;;~vingii=-42-fr~~ -;~i~;-~iII de':-e~~gi~etheHi ~-i

!Flux Trip Bistable for that channel.

I L ____________. ________________________________________

~ __________________________________________ ~___ ___

~ _______

~

Answer C Discussion Ic:ORRECT~----~-~~~ -~~---- -,-

~ ~-

~~-

-~,--

l':~ __ ~_ ~_~ __ ~ ___, __ ~~_ ~~~~_~~_ ~

__ ~_ ~,~~~ ~ ____ ~~~~~ __ __

~,~_~_~ ~~_~~ __ ~~~ __,_ ~,~~_~'_

Answer 0 Discussion iIr:co~~~t~ PI~~~ibleif the ~~icl~t~does ~ot ~nd~r~t-;n-d that th~ f~iled ~h~;eIHi FI~; frip~Bist;bie i;-Pia~~ii~ ili; t~ippedpo~ition ;h-;;~ liE ~a~tio;;-~r;c-;;;;pi~t;fo-;:- ;e~~~ng the ~ha~nel lfr_om.s~r\\'~~

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---

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Job Level i

Cognitive Level 9lJ.!.s.!i()rl !yp~

~~ ~~~_~ _~~ ~~ ~a.!'!~ti.0_"-~~!C~_ _ _ _

~

--~-

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RO Comprehension

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved BANK Comanche Peak Bank EB878

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I I

I I

I l l___

-~--~--~-~~~-T -~-~--~~~T-~

~---

---~~--~--

~ue8t1onBank # iKA_system IKA_number 1----- --- ---- ----- - -- ------

--~--- --

IKA desc 401-9 Comments RESPONSE Per Chief Examiner's recommendation, removed third bullet. HCF I 1102/09

~~ =~ ___ ~~~~~~~YiO_I2=-~_-I~6~())~~~~~~_--~~

t,~""",-,~--~~--

---~~~------~---~~~~,-

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

~~~--~--,~

IKnowledge of the effect ofa loss or malfunction of the following will have on the RPS: (CFR: 41.71 4517)LJTrip logic lcir~uit.s~ __ ~ ~ ~~ ~~~ ~ __ ~_~_ ~ _~~ ~~_ ~ ___ ~~ __ ~~~ ____ _~ ~~~~ __ ~ ~~ _

fuesday, November 10, 2009 Page 24 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION General Discussion DISTRIBUTE 10 c

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

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---

~-----

ISince N-42 has failed low, the Hi Neutron Flux Trip Logic will never receive a trip signal from that channel. Since two high flux signals are required to initiate a trip signal and there are only Ithree channels remaining which could potential generate a high flux trip signal, the logic for a Power Range Hi Flux trip is 213 channels.

I IWhen the I&E actions for removing N-42 have been completed the High Flux Trip Bistable is placed in the tripped position. Since only one more (of the remaining 3) High Flux Trip Bistable

[signals is required to intiate a Hi Flux Trip, the logic now becomes 113 channels.

I I [The KA is matched because the question requires the applicant to know how the loss of a channel will effect the RPS trip logic before and after a channel is removed from service.

I IThis is a comprehension level question because the applicant must recall the normal trip logic from memory, must understand that with the channel failed low the trip logic is unaffected, must lunderstand that when the channel is removed from service the high flux trip bistable is placed in the trip condition, and must associate all of those pieces of information to determine the I~Orr~~tllIl~S~~._~~~~_~ ~~~

_ ~ _~_~ __ __

_~~ ___ ~~_~~~~~ ____ ~_~ ____ ~~ ___ ~ ~~ __ ~~~~ ___ ~ ___ ~~

__ ~~~_~~~~_~_~ ~_~_~

Answer A Discussion

~nc()lTec~ ~~a~s~b~e_if~he_~~E~c!n_t~()n~!~~~e~~ll1l~el ~aiIi~~ l~~\\\\'it~~h~~~a~~e~~a~i~~~i~~i~ \\V~i~~~a~et~~a~~w~~ \\\\,()uld ~~ ~o~-=c~~~_~~ __ ~~~ ~~~~~~_ ~ __ ~~~ __ ~ ~~_~

Answer B Discussion 1----------- -------------- -- -- -

.--- --- ------ --------- ---- ---- --- -- -------------- --- -- --- -----1 jlncorrect. Plausible if the candidate confuses the channel failing low the the channel failing high AND believes that the I&E actions for removing N-42 from service will de-energize the Hi I

~~u~JI'iEl3ist<t~~ !0I'~haJ~cllanIlel~_~~~ ___ ~_____ ___ _ __~_~~ _~ __ ~~~~~ ~~~ _~ ~~~ __ ~_~_ ~_

_~ ____ ~~ _~_ ~_~_~~~~~~~~~ ~~ __ ~~

____ ~J Answer C Discussion

~OlliCT

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

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

L _____ ~ ________ ~ __ ~~ __ ~~ __ ~~_ ~ __

~ ___ ~ ____ ~~

Answer 0 Discussion (Incorrect. Plausible if the candidate does not understand that the failed channel Hi Flux Trip Bistable is placed in the tripped position when I&E actions are complete for removing the channel lfr_om Y~r\\'~~ _ _____ __ __~~~_

I~Job Level I~-~

---

~-

l ___ ~~~~

~~!'!t!v~ _Leve_1 Comprehension Question Source Comanche Peak Bank EB878 401-9 Comments RESPONSE Per Chief Examiner's recommendation, removed third bullet. HCF I 1102/09

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved fuesday, November 10, 2009 I.~~ -~~ - -

~~--

~--~~ - - -

~~~~ -

~-~-- -

~~--

--~

l[)!~e!~~"!e_nt ~~f!.re~~!!_~_~_~~~~~~~_~

(Lesson Plan OP-MC-IC-IPE ISt~dentRefir;"ces Pro;id;d~ - - ~--

I I

I I~ ~-~~

-~ -

~

~~

--~ -

-~~~ ~~

~~-~--~~

I I

l _______ ~ ____ ~ ___ ~ __ ~ _______ ~~ ___ ~_

l_

1-------------------------

---

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

IKA desc t~-

-"""-~--- -~ --

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

-~-

-~~~- - -- -

-~-~~ -

~~--- -

--~~~~~ ~~

~ ~--~~~ -

~- ~ -~ ~- ~ -~~

IKnowledge of the effect ofa loss or malfunction of the following will have on the RPS: (CFR: 41.71 4517)LJTrip logic I*

Lclr~U1t.s:.',,_',,~._'._.:'.~:'.:'.:~,,:'... _:':~.:'... ~_~ ~ ________ ~~ _ ~ ___ ~~ _________ ~~~~

__ ~ __ ~~ _ ~_~~~_~ ___ ~_~~_~ __ ~~

Page 24 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 10 c

fuesday, November 10, 2009 Page 25 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 10 c

fuesday, November 10, 2009 Page 25 of 185

c FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 11 c- -------'----'1.- -----'--,,;-;- ------- -----, 1_'_ -,- - ----- --,-,---- ----- --- - -- -------- ---,-,-- ------------

t~~e~~~q~~nI<~t~~f:s~~i -f-~-~~!!'::.63-----1 ~lli~~:~~anuai,y -;;pe~ate -~d/~ ~~~i~~ ;;;th-;;~~trol ;:-~~~: (CFR:'-41.7 !45-:-5-t;;-4~8)CJESFASTnit~tTo~ - - - -

---

,-,- -- -~-- -----,---~-- --- ------,--- -I L:,-,:--... :.. ~,-,.... ~:.. :..... :--:..,,:~-:,-

CURRENT Given the following:

An inadvertent Reactor Trip/Safety Injection has occurred due to IAE testing Both reactor trip breakers opened as expected Which of the following describes the effect of pushing the SI reset pushbuttons after the safety injection actuation?

A.

B.

c.

D.

After the SI timer has timed out and the SI reset push buttons are depressed, automatic SI reinitiation can occur.

After the SI reset pushbuttons are depressed and the RTBs have been cycled, an automatic SI reinitiation can IMMEDIATELY occur.

After the SI timer has timed out and the SI reset push buttons are depressed, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

After the SI reset pushbuttons are depressed and the reactor trip breakers are cycled, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

013A4.03 45 DAY VERSION Given the following:

An inadvertent Reactor Trip/Safety Injection has occurred due to IAE testing Both reactor trip breakers opened as expected Which of the following describes the effect of pushing the SI reset pushbuttons after the safety injection actuation?

A.

B.

c.

D.

After the SI reset pushbuttons are depressed ONLY, automatic SI reinitiation can occur.

After the SI timer has timed out and the SI reset pushbuttons are depressed, automatic SI reinitiation can occur.

After the SI timer has timed out and the SI reset pushbuttons are depressed, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

After the SI reset pushbuttons are depressed and the reactor trip breakers are cycled, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

401-9 Comments:

I don't think you need the word ONLY in A because an auto S1 will NOT reoccur until the timer has timed out as in B. You can also rewrite A as follows: After the SI reset pushbuttons are depressed and the RTBs have been cycled, an auto SI reinitiation can immediately occur. (Note, this is wrong because the timer has not timed out yet)

Distracter A is NP as written.

Tuesday, November 10, 2009 Page 26 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 11 CURRENT Given the following:

An inadvertent Reactor Trip/Safety Injection has occurred due to IAE testing Both reactor trip breakers opened as expected Which of the following describes the effect of pushing the SI reset pushbuttons after the safety injection actuation?

A.

B.

c.

D.

After the SI timer has timed out and the SI reset push buttons are depressed, automatic SI reinitiation can occur.

After the SI reset pushbuttons are depressed and the RTBs have been cycled, an automatic SI reinitiation can IMMEDIATELY occur.

After the SI timer has timed out and the SI reset push buttons are depressed, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

After the SI reset pushbuttons are depressed and the reactor trip breakers are cycled, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

013A4.03 45 DAY VERSION Given the following:

An inadvertent Reactor Trip/Safety Injection has occurred due to IAE testing Both reactor trip breakers opened as expected Which of the following describes the effect of pushing the SI reset pushbuttons after the safety injection actuation?

A.

B.

c.

D.

After the SI reset pushbuttons are depressed ONLY, automatic SI reinitiation can occur.

After the SI timer has timed out and the SI reset pushbuttons are depressed, automatic SI reinitiation can occur.

After the SI timer has timed out and the SI reset pushbuttons are depressed, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

After the SI reset pushbuttons are depressed and the reactor trip breakers are cycled, only a manual SI can be initiated, automatic SI reinitiation remains blocked.

401-9 Comments:

I don't think you need the word ONLY in A because an auto SI will NOT reoccur until the timer has timed out as in B. You can also rewrite A as follows: After the SI reset pushbuttons are depressed and the RTBs have been cycled, an auto SI reinitiation can immediately occur. (Note, this is wrong because the timer has not timed out yet)

Distracter A is NP as written.

Tuesday, November 10, 2009 Page 26 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 11 c

RFA 10/27/09 General Discussion 1E~~htr~i~h~ ~ S-;;fetY i~j~~tk>~R~tp~~hb~tto;~~th;C~~t~1 Bo~d.-I~ ;rde~ to ~~~et safutY i~je~t~~, -~~e-min~t~ ~~t ~~

-p~;dsin~eth-e~ctu-;tio;(60;-e~~~dti~e~h-;;t~~d-~t) land the train related reactor trip breaker must be open (P-4). Following safety injection reset, only manual safety injection actuation is available. To reinstate the automatic actuation the Ireactor tri p breakers must be reclosed.

[

IThis KA is matched because the applicant must understand the consequences of manual action taken (Ability to manually operate and/or monitor) with regards to depressing the SI reset lPy~h/)~tt()ns~nd ~he ~npac~ ~~_~SI'~~illit!<l!i()Il_c~~billty~ ______________________________________________________________________ _

Answer A Discussion r

lncorrect. Plausible because the SI timer must time out and the SI reset pushbuttons depressed to reinstate auto SI. However, the Reactor Trip breakers must also be cycled to reinstate auto SI. I

,----~- - ---- ----- ----------------~- -

---

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

---

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

Answer B Discussion r; ------------------------------------ --- -- --------------- - ------- ----------- ----------- - --- -- - -- --------------------- ----- -------,

[Incorrect. Plausible because this actions described would result allow for auto SI but would require the 60 second timer to time out. The word "Immediately" makes this answer incorrect.

I

___________________ ~

__________________

• _________ I Answer C Discussion

~~R!Ecl~ ____ -_-_~~_-~_-_~-_-___ -_~_-____ -___ ~_-_~ _-_-_-___ -_-_~~_-_-____ -_-~~ -_ ~ __ -_____ -_-_-~_-_-_-~ ___ -_-_-_-_-_-~~-____ -___ ~_-_-_ -_ -___ ~-~_-_ -_-__

_________ J Answer D Discussion 1------------

~----- -.-

---

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

~nc~~e:t ___ J>l~usi/)j~~~alls:~his ~~I"ll=- IJf()v~d~~t~e_ ~

~meI" ~~~m~

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~~~~e.,![1 ___ ~~llltl"'!!_~~1

_ g~e~!'~nT}'~e BANK Question Source

~-- ---- ----l 401*9 Comments RESPONSE RO I

Memory

_L ~

MNS Ex~B~kQ~~~~AECCISEROI----- ---j As suggge.sted in the. 401-9 comments, Dist

---

----- --- --~-----------------~ A was revIsed and distracters A & B were

~ Developed 1.-- --------- ~--~---

reordered due to the increase in lengith of

~v-e~oPrn~Il~~!e-'"!nce~ _.____________

fS~~~iI~~e!!F'!~~~~__<>!i~!~__

the the new dist A.

~ OPT Approved

~ OPS Approved

~ NRC Approved

[Lesson Plan OP-MC-ECC-ISE Objective 12 page 25 I

I I

I I

I I

I i

I I

L _____

~ ______________ ~ ____ ---l r- -- ----------- - r;-- --- - - ------flJ--------- ----- --

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

,QuestionBank #'JKA_system l'KA_number i IKA_desc c-__ --- ---- ------ -- -- -

-~ -I f--- -~- ------ - ---------- - ---------- - ------------ - -------------- -~---

________ ~~II1S)'S~I_3 ___ Ji\\4.D! __________ J lAbility to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)CESFAS initiation t*-:*_-:* ____ -:*.. :.. *_***_**:--:-:*-:*..

• ____ :**-::-: ____________________________________________ _

Tuesday, November 10, 2009 Page 27 of 185

---

l

_--J I

_____ J FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 11 c

RFA 10/27/09 General Discussion lE~chtr~i~ h~ ~ S-;;fetY inje~tk>~ R~tpu~hb~tto;~~th; C~~t~1 Bo~d. -I~ ~rde~ to ~e~et safetY inje~t~~, -o~e-min~t~ ~~t ~~

-p~;dsin~e th-e actu-;tio;(6o ;-e~o~d ti~e~ h~; thn~d-~t) land the train related reactor trip breaker must be open (P-4). Following safety injection reset, only manual safety injection actuation is available. To reinstate the automatic actuation the Ireactor tri p breakers must be reclosed.

[

IThis KA is matched because the applicant must understand the consequences of manual action taken (Ability to manually operate and/or monitor) with regards to depressing the SI reset lPy~h/)~tt()ns~nd ~he ~npac~ ~~_~SI'~~illit!<l!i()Il_c~~billty~ ______________________________________________________________________ _

Answer A Discussion

~~~~~~~~j~~~~~~-~~~~~-~~~_~-~~~~~~~~~~~t~~~!~jI;:~_=ty~~~b~~~~~-~~~:~~~~~X~~~~-~~~;}Tg~~~~~~-i~~-~!i~~~~e~~~u~~~~~~j~~~~to~~~t~te~trto-SI.-I Answer B Discussion r; ------------------------------------ --- -- --------------- - ------- ----------- ----------- - --- -- - -- ---------------------- ----- -------,

[Incorrect. Plausible because this actions described would result allow for auto SI but would require the 60 second timer to time out. The word "Immediately" makes this answer incorrect.

I

~_ -

_~_ -

~ _____________ ~

_____

• ____________________

• _________ I Answer C Discussion

~~R!Ecl~ ____ -_-_~~_-~_-_~-_-___ -_~_-____ -___ ~_-_-_-_-_-_=_ -_-_~~_-_-____ -_-~~ -_ ~ ___ -______ -_-_-___ -_-_-~ ___ -_-_-_-_-_-~~-____ -____ ~_-_-_ -_ -____ ~-___ -_ -_-____ -____ ~_-_-_

_=_~~_-____ -_-_-J Answer D Discussion 1------------ --,--- -,-

---

~----,----.- -- - - ------- -

~----- ---- --,--

~nc()r~e~ ___ J>I~usi/)j~:~alls:~his ~~I"ll=- IJf()v~d:~t~e_~ ~meI' ~~~m~

~1It ~~

!=_a-=t()r~p bre~~~~~=_I1O~b~~~)'(:'=_~9~_= the ~1l(;t<Jr~~~b~e~er~£lf~~c~~'_ ~t<JlI1'lti~ ~

__ is reinstated.

Job Leve[1===~~Illtl",!!-~~I RO I

Memory

=

g~e~:!I~nTi~e- ---------- ----Qu;StIO~ SOU,:C;--~----------l 401*9 Comments RESPONSE

~--~---.-----------.---- ---I B~~K ____________ ~~!_"(llll_~~k_~u:~i~n_i\\_E~~~~~~ _________ J As sugggested in the 401-9 comments, Dist

_______ L

~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IDevelopment References F - - - --- - - ----------- ---------- -- - ------

[Lesson Plan OP-MC-ECC-ISE Objective 12 page 25 I

I I

A was revised and distracters A & B were reordered due to the increase in lengith of the the new dist A.

r- -- ------------ - r;-- --- - - -------flJ--------- ----- -- ---,

~--- -- ----- - - - - ---------- --- ---- --- ---------- ----- - -- --- - -------- --- ----- ---- - - - --------- --l

~4t~~Il~~'!.k#}~A-~~s~!fll_ lK.b......IllJ-.rJl~e! ______ J ~~_~(t~C __... ____________________________________________ ~

______________________ --l

__ ___ __ ~~II1S)TS~I_3 ___ Ji\\4.D! __________ J lAbility to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)CESFAS initiation I[

t*-:*_-:* ____ -:*.. :.. *_***_**:--:-:*-:*.. *..-::**-::-: __________________________________________________________ I Tuesday, November 10, 2009 Page 27 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 12 B

IQuestionBank # IKA system IKA number I KA desc I

1812 I

SYS013 I

Kl.Ol I Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8)illnitiation signals for ESF circuit logic...............................

CURRENT Given the following on Unit 1:

Unit is operating at 100% RTP Containment Pressure Channel III has been BYPASSED for testing Which ONE (1) of the following lists the logic for a Containment Spray actuation based on the conditions above?

A.

113 B.

213 C.

112 D.

212 Thursday, November 12,2009 013KI.OI No comment at this time RFA 10127/09 45 DAY VERSION Given the following on Unit 1:

Unit is operating at 100% RTP Containment Pressure Channel III has been BYPASSED for testing Which ONE (1) of the following lists the logic for a Safety Injection actuation based on the conditions above?

A.

1/3 B.

2/3 C.

1/2 D.

2/2 401*9 Comments:

Page 28 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 12 B

!QuestionBank # IKA system IKA number I KA desc r

1812 T SYS013 1 Kl.Ol I Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8)illnitiation signals for ESF circuit logic...............................

CURRENT Given the following on Unit 1:

Unit is operating at 100% RTP Containment Pressure Channel III has been BYPASSED for testing Which ONE (1) of the following lists the logic for a Containment Spray actuation based on the conditions above?

A.

113 B.

213 C.

112 D.

212 Thursday, November 12,2009 013KI.OI No comment at this time RFA 10127/09 45 DAY VERSION Given the following on Unit 1:

Unit is operating at 100% RTP Containment Pressure Channel III has been BYPASSED for testing Which ONE (1) of the following lists the logic for a Safety Injection actuation based on the conditions above?

A.

1/3 B.

2/3 C.

1/2 D.

2/2 401*9 Comments:

Page 28 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 12 B

General Discussion The normal logic for a Hi Containment pressure Containment Spray / Phase B is 2/4 channels. The applicant must undertand that bypassing the channel means that a Hi Pressure signal from that channel will not be seen by the logic. However, two channels are still required to initiate a Containment Spray signal and there are three channels remaining which could cause the initiation. Therefore, the logic is now 2/3.

The KA is matched because it requires the applicant to know the effect of bypassing a containment pressure channel on the initiation logic for a Containment Spray signal.

Answer A Discussion

[0correct. Plausible if the applicant confuses bypassing a charmel with placing the channel in trip.

Answer B Discussion

~9_RRE~T.

0 ___________

0 _____

0 __

0 ________

0 _______

0 _______

o ___ J Answer C Discussion Incorrect. Plausible if the applicant confuses the Containment Spray logic with the Safety Injection logic an confuses bypassing a channel with placing the charmel in trip.

Answer D Discussion

[Incorrect. Plausible if the applicant confuses the Containment Spray logic with the Safety 1I1iection logic.

Job Level Cognitive Level QuestlonType Question Source RO Memory NEW

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Development References Lesson Plan OP-MC-ECC-ISE, pages 59 and 77.

Student References Provided

~

401-9 Comments RESPONSE Question changed to use Containment Spray logic instead of the SI logic based on validation feedback results. Change approved RFA 11112/09.

QuestionBank-#lKA-syst;,n-KA~~mb;r-----] KAdes~---------------------- --- --- -- --- --0-- ---- -------- ----- ------- --

18121SYSOl3 K1.01 Knowledge of the physical cormections and/or cause effect relation I

41.2 to 41.9 / 45.7 to 45.8)CHnitiation signals for ESF circuit logic Thursday, November 12, 2009 Page 29 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 12 B

General Discussion The normal logic for a Hi Containment pressure Containment Spray / Phase B is 2/4 channels. The applicant must undertand that bypassing the channel means that a Hi Pressure signal from that channel will not be seen by the logic. However, two channels are still required to initiate a Containment Spray signal and there are three channels remaining which could cause the initiation. Therefore, the logic is now 2/3.

The KA is matched because it requires the applicant to know the effect of bypassing a containment pressure channel on the initiation logic for a Containment Spray signal.

Answer A Discussion

[0correct. Plausible if the applicant confuses bypassing a charmel with placing the channel in trip.

I Answer B Discussion Incorrect. Plausible if the applicant confuses the Containment Spray logic with the Safety Injection logic an confuses bypassing a channel with placing the charmel in trip.

Answer D Discussion IIncorrect. Plausible if the applicant confuses the Containment Spray logic with the Safety 1I1iection logic.

Job Level Cognitive Level QuestionType Question Source

-r----~-----------+--------~--+_----------------~--------------------------~

RO Memory NEW 401-9 Comments RESPONSE Question changed to use Containment Spray logic instead of the SI logic based on r-------------------~,----------------, validation feedback results. Change

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Thursday, November 12, 2009 f-D_e_v_e_'_o--'p_m_e_nt_R_e_fe_r_e_n_ce_s ________ --1 I-S_tu_d_e_n_t_R_e_t_e_re_n_c_e_s_P_ro_v_i_d_e_d ___ --I approved RF A 11 112/09.

Lesson Plan OP-MC-ECC-ISE, pages 59 and 77.

Page 29 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13 C

i9~!s}i~~~~rIi<! T~~..,~i~~~=l~=~~=t>!~====-~J ~~~~~~~=----=~=-~~-=~= ~-=~===============_==-==-~=-=-~===========-======-====--

l ___ ~~~ ___ J __ ~~~02~ _1____

A2.0~ __

lAbility to (a) predict the impacts of.the following malfunctions or operations ~n the CCS; and (b) based on those predictions, use

--- \\proced~lres to correct, control, or mltlg.ate the conseque~ces of those malfunctIOns or operatIOns: (CFR: 41.5/43.5/45.3/

l4~J.3]~~~~ mot0.i"0errmtl ov~I()~d~lllgh:SIJeed 0E~19~.. *.. ".:."*... *--.:.. *--.: ___________. ____________. __________ _

CURRENT Given the following conditions on Unit 2:

The unit is operating at 100% RTP A small NC System leak occurs inside Containment Annunciator 1AD-9 / A8, (CONT.5 PSIG ALERT) is received The BOP reports that 1A VL Fan is running in LOW speed Which ONE (1) of the following fan combinations is required in accordance with the above listed Annunciator Response Procedure?

A Place 1 Band 1 D VL Fans in LOW speed ONL Y.

B.

Place 1A and 1C VL Fans in HIGH speed ONLY.

C.

Place all four VL Fans in HIGH speed.

D.

Place the 1B, 1C, and 1 D VL Fans in LOW speed.

022A203 45 DAY VERSION Given the following conditions on Unit 2:

The unit is operating at 100% RTP A small NC System leak occurs inside Containment Containment pressure is currently 0.25 PSIG and increasing slowly When Containment pressure reaches 0.5 PSIG, the non-operating Lower Containment Ventilation (VL) fans will (1)

AND when Containment pressure reaches 1.0 PSIG, the VL fans will ------.0 Which ONE (1) of the following correctly completes the statement above?

A.

(1) start in slow speed on their normal power supply (2) swap to slow speed on their emergency power supply B.

(1) swap to emergency power and start in slow speed (2) swap to high speed on their emergency power supply C.

(1) start in high speed on their normal power supply (2) swap to slow speed on their emergency power supply D.

(1) start in high speed on their normal power supply (2) swap to high speed on their emergency power supply 401*9 Comments:

Under these conditions, I am not sure that swapping to high speed on their normal power is plausible. Suggest changing "A" and "C" part (2) to swap to slow speed on their emergency power.

U because Potentially 2 NP distracters.

Tuesday, November 10, 2009 Page 30 of 185 C

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13 i9~!s}i~~~~rIi<! T~~..,~i~~~=l~=~~=t>!~====-~J ~~~~~~~=----=~=-~~-=~= ~-=~===============_==-==-~=-=-~===========-=====~====---

I 1813 I

SYS022 I

A2.03 1 lAbility to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predICtIOns, use L._ ------ ---1------- - _-.-L _________ -----1 \\procedures to correct, control, or mitig.ate the conseque~ces of those malfunctions or operations: (CFR: 41.5/43.5/45.3/

l4~J.3]iJ~~ mot0.i"0errmtl ov~I()~d~lllgh:SIJeed 0E~I9~.. *.. ".:."*... *--.:.. *--.: ___________. ____________. __________ _

CURRENT Given the following conditions on Unit 2:

The unit is operating at 100% RTP A small NC System leak occurs inside Containment Annunciator 1AD-9 / A8, (CONT.5 PSIG ALERT) is received The BOP reports that 1A VL Fan is running in LOW speed Which ONE (1) of the following fan combinations is required in accordance with the above listed Annunciator Response Procedure?

A Place 1 Band 1 D VL Fans in LOW speed ONL Y.

B.

Place 1A and 1C VL Fans in HIGH speed ONLY.

C.

Place all four VL Fans in HIGH speed.

D.

Place the 1B, 1C, and 1 D VL Fans in LOW speed.

022A203 45 DAY VERSION Given the following conditions on Unit 2:

The unit is operating at 100% RTP A small NC System leak occurs inside Containment Containment pressure is currently 0.25 PSIG and increasing slowly When Containment pressure reaches 0.5 PSIG, the non-operating Lower Containment Ventilation (VL) fans will (1)

AND when Containment pressure reaches 1.0 PSIG, the VL fans will (2)

Which ONE (1) of the following correctly completes the statement above?

A.

(1) start in slow speed on their normal power supply (2) swap to slow speed on their emergency power supply B.

(1) swap to emergency power and start in slow speed (2) swap to high speed on their emergency power supply C.

(1) start in high speed on their normal power supply (2) swap to slow speed on their emergency power supply D.

(1) start in high speed on their normal power supply (2) swap to high speed on their emergency power supply 401*9 Comments:

Under these conditions, I am not sure that swapping to high speed on their normal power is plausible. Suggest changing "A" and "C" part (2) to swap to slow speed on their emergency power.

U because Potentially 2 NP distracters.

Tuesday, November 10, 2009 Page 30 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13 c

General Discussion Part 2 of the KA is not met (facility identified). Use procedures to correct, control or mitigate... If you cannot meet the entire KA, you have to meet at least the second part.

CE: Reissue a new KA if necessary.

RF A 10/08/09 Revisited A2 needs to read "will remain in slow speed.... "

Part 2 of the KA still not met. CAF RF A 10/27/09 Under these conditions, I am not sure that swapping to high speed on their normal power is plausible. Suggest changing "A" and "C" part (2) to swap to slow speed on their emergency power.

U because Potentially 2 NP distracters.

Part 2 of the KA is not met (facility identified). Use procedures to correct, control or mitigate... If you cannot meet the the entire KA, you have to meet at least the second part.

CE: Reissue a new KA if necessary.

RF A 10/08/09 I.-'~--- -

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

-.-.~-.~ -

---

~

--~

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

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

---

.-----~--

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

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

~

IWhen containment pressure reaches 0.5 PSIG, all VL fans should automatically start in high speed regardless of switch position. In this particular case 0.5 PSIG has been reached and the fans

[have failed to automatically start. When the Operators review the Annunciator Response Procedure, they should realize that the automatic actions have failed to occur and should place all Ifour VL fans in HIGH speed.

I IThis KIA is met since an automatic action associated with the Containment Cooling Fans (i.e. all four fans starting in HIGH speed) has failed to occur and the Operators must take actions in laccordance with the Annunciator Response Procedure to correct the problem. As a note, the Annunciator Response Procedure is the only place that the automatic start/swap of the lc:..Oll~'liIl~eIlt_C~~!i.~!'3IlSJ~~e~iQ~~a!>'<:>(;Cllring. __ ~_~_~~ __ ~~ ___ ~_~ _____ ~~ _____ ~ ___ ~_ ~_~ __ ~ _____ ~~_ ~_ ~ ________ ~~_ ~ ________________ ~~

Answer A Discussion c~ --.----

--~.~.--.-** --~------~-.-~--.~.-.------.--

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

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

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

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

-~.--~-----~.--::I

Incorrect. Since all four fans automatically start in HIGH speed (except on their emergency power supply) when Containment pressure reaches I PSIG, it is plausible to believe that running 3 i Ifans in LOW speed at 0.5 PSIG is appropriate.

I

~ _________

• _________________ ~

~ _____________

~_ -

~_ -

~ _____________ ~ ___

.~ _________________

• ___ -

__

• ________________

• _______ I Answer B Discussion 1.--- ----~.- -.---------

~ -

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

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

-.-.~---.-

-~

~---.-

~ ---.-

~.- -.-. ~--

--~.~

-~------.-

~--- -- -- - -

---

~ ~---~ - -

-~--

I Incorrect. Since the fans should have automatically swapped to HIGH speed at 0.5 PSIG, it is plausible to believe that placing the running fans in HIGH speed is appropriate. However, all 4 la.Il~~I1.0l!I.<l ~p~a(;e~ in. IfIG~H_s2.c:ej_aIl.cl.~1(.)tlust..tE~ rUIlIliIl.~~I1.s. ___ ~ _____ ~__ ___ ~ _____ ~ __ ~ _____ ~ ______ ~ ________________ ~ ____ ~ _____ ~_ ~~ __

Answer C Discussion

~9~~!~~_~~~_~~~~_-_-~_-~-_- _-~~-_-~_-_~- -----~ ---~- -~ --~~ -

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

Answer 0 Discussion

~n~~~~~!Ia~~~I~io}~e~~~h~~~I!~~~fi~~0~~I~~=-~~~i~ii~!~~~SE~~===~====~=========_=~~=~~~=~_-=~=~~=_-==~==~=~=~~~~~_-~_~~=~_~~-_-~

Tuesday, November 10, 2009 Page 31 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13 c

General Discussion Part 2 of the KA is not met (facility identified). Use procedures to correct, control or mitigate... If you cannot meet the entire KA, you have to meet at least the second part.

CE: Reissue a new KA if necessary.

RF A 10/08/09 Revisited A2 needs to read "will remain in slow speed.... "

Part 2 of the KA still not met. CAF RF A 10/27/09 Under these conditions, I am not sure that swapping to high speed on their normal power is plausible. Suggest changing "A" and "C" part (2) to swap to slow speed on their emergency power.

U because Potentially 2 NP distracters.

Part 2 of the KA is not met (facility identified). Use procedures to correct, control or mitigate... If you cannot meet the the entire KA, you have to meet at least the second part.

CE: Reissue a new KA if necessary.

RF A 10/08/09 I.-'~--- -

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

-.-.~-.~-

---

~--~

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

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

---

.-----~--

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

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

~ ~-----.

IWhen containment pressure reaches 0.5 PSIG, all VL fans should automatically start in high speed regardless of switch position. In this particular case 0.5 PSIG has been reached and the fans I

[have failed to automatically start. When the Operators review the Annunciator Response Procedure, they should realize that the automatic actions have failed to occur and should place all I

Ifour VL fans in HIGH speed.

I IThis KIA is met since an automatic action associated with the Containment Cooling Fans (i.e. all four fans starting in HIGH speed) has failed to occur and the Operators must take actions in laccordance with the Annunciator Response Procedure to correct the problem. As a note, the Annunciator Response Procedure is the only place that the automatic start/swap of the lC:o~!Il~eIlt_C~~li~!'3IlSJ~~e~iQ~~a!>'<:>(;Cllring. __ ~_~_~~ __ ~~ ___ ~_~ _____ ~~ _____ ~ ___ ~_ ~_~ __ ~ _____ ~~_ ~_ ~ ________ ~~_ ~ ________________ ~~

Answer A Discussion c~ --.----

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

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

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

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

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

-~.--~-----~.--::I

Incorrect. Since all four fans automatically start in HIGH speed (except on their emergency power supply) when Containment pressure reaches I PSIG, it is plausible to believe that running 3 i rf'an~ ~n..L~~\\\\'~e.e~<l.~ 2.2!'§!.~ ~~ppr()p!~t~~ ________ ~~ ____ ~~ _____ ~_~ __________ ~ __ ~ _____ ~_~ _~ ___ ~~ _~.~_ ~ ___________ ~ _____ ~~ __ ~ __ J Answer B Discussion 1.--- ----~.- -.---------

~ -

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

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

-.-.~---.-

-~

~---.-

~ ---.-

~.- -.-. ~--

--~.~

-~------.-

~--- -- -- - -

---

~ ~---~ - -

-~-- ~-,

IIncorrect. Since the fans should have automatically swapped to HIGH speed at 0.5 PSIG, it is plausible to believe that placing the running fans in HIGH speed is appropriate. However, all 4 I

la.Il~~I1.0l!I.<l ~p~a(;e~ in. IfIG~H_s2~ej_aIl.cl.~1(.)tlust..tE~ rUIlI1iIl.~~I1.s. ___ ~ _____ ~__ ___ ~ _____ ~ __ ~ _____ ~ ___.. __ ~ ________________ ~ ____ ~ _____ ~_ ~~ ___ J Answer C Discussion

~9~~!~~_~~~_~~~~_-_-~ -_-~-_-_-~~-_-~_-_~_-~-~~-=~_-_-~~~~_~_-_~~~-__ -~-~_-~-~~~_-_~~~-~-_-_-_-_-~~-~_-_-~~~_-~~~~~-~~~~-_-=~_-_-~~_-~~~-~~-_-_-_~-_~~--

Answer 0 Discussion

~n~~~~~!Ia~~~I~io}~e~~ih~~~I!~~~f~~~0~~I~i=-~~~i~ii~!~~~SE~~===~_===~======~==_=~==~~===_-=~====--~~-=~==========_-=_====_=~-_-~

Tuesday, November 10, 2009 Page 31 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~-

~,----~------

Ques~~-" ~S~t.t.~! _______________ 1

'De~;lopmentR~terences~ ------~ -----

IStudent References Provided 1*- --.- --.---.~.~ ~.--- - -- --.~.~ --.-.~-- - --- --~ ~--

!~

-~- --

iLesson Plan OP-MC-CNT-VUL Objectives 4 & 5 I

[pages 31 and 39 I

[

I

[

[

I I

l ______ ~ ___________ ~ __ ~ ___ ~~ _

L ________ _

r--

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

---

*-~-T--~-

--~--- ----I IKA desc I------~~- --.-~-- --- - - -------.----~~--~- ~ --- -.----

c 401-9 Comments RESPONSE Re-wrote question as it was impossible to meet Part B of the KIA with the previous question. HCF 11102/09 1~lJ.elJ!i~'!E!.a.l'l~~~~.tt~~~'ll._+~",,"-'!.lJ!"~~'"-__ -------1 I

1813ISYS022 iA2.03 II

______ ~~~~_L_~ __ ~~ __ ~~ ____ ~~ ______ ~ lAbility to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, fuse procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 /45.3 /

1'!5*I]lgF_~ ~t~l".tQ.erl11aI~\\'-eI'l(),\\d~i~Lh:.sE~~ <P~l"llti0.'1.......".:..... ~...... :.... ~.... _____ ~ ___ ~ __. __ ~ __ ~ __________ ~ __ ~_

Tuesday, November 10, 2009 Page 32 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 13 c

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Questloniype~T---

---

Question~Sou,:c;---- ----------l 401-9 Comments RESPONSE

---.-----1-----_.-

-~ --------------- ----- --*----------*---*--~I

__ I>I~~ ____ L ____ ~ __________________________________ j Re-wrote question as it was impossible to meet Part B of the KIA with the previous question. HCF 11102/09 rStudeOt-R~fer;n'C;s P~o~lded- - ---

I~ ----- -.-.-~--------- -~-.~ --.

I L ________. ______ _

'De~;lopment R~ter&nces- --.---------

I*- ~.----.--.. -.- -.-.- - --.-.-.- ----.--- - - -- -- - ---

i~:~~~~il:~d~~-MC-CNT-VUL Objectives 4 & 5 I

I L_. _____. _______. ___________ _

r~tJ.e~!J~~~aE~:!~~~i~~f!.~~~-=n.t.fn~~===~==J l~:~~.=~-=~-_~=~~-================*=~==========================*==========11 I

1813ISYS022 iA2.03 I lAbility to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions,

-~ -- --- - -- _L __ -- - ----" -

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

fuse procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 I i 1'!5*I]lgF_~ ~t~'"-tQ.erl11a1.9\\'eI'l(),\\d~i~Lh:.sE~~ <P~l"ilti0.'1.....".:..... ~...... :.... ~.... __ ~~ ________. ___._~._

~~ ____.~ _____ 1 Tuesday, November 10, 2009 Page 32 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 14

---

~-----------l~-------

IQuestionBank tllKA_system IKA_number IIKA_desc

~-------- ------f-"---- -----j---------- ------ r------------- ---- ------- ----------- ----- ------- ------------ --- ---------------

I 1814 I

SYS025 K502 IIKnowledge of operational implications of the following concepts as they apply to the ice condenser system: (CFR: 41.5/

--~---

I

,------- ___ l___ ---

- --- ----~

IJ1.Z)g!!e~!JnU1~fer

__ I CURRENT Which ONE (1) of the following completes the statements below regarding the effect of operating with elevated Ice Condenser temperatures on the process of SUblimation and the resulting operational implications should a high energy line break occur inside containment?

Sublimation rates would ~.

Peak containment pressure would be ~

A (1) increase (2) higher B.

(1) increase (2) unaffected C.

(1) decrease (2) higher D.

(1) decrease (2) unaffected 025K5.02 45 DAY VERSION Which ONE (1) of the following describes the effect of operating with elevated Ice Condenser temperatures on the process of sublimation and the resulting operational implications should a high energy line break occur inside containment?

Sublimation rates would -11L.

Peak containment pressure would be (2)

A.

(1) increase (2) higher B.

(1) increase (2) /ower C.

(1) decrease (2) higher D.

(1) decrease (2) lower 401-9 Comments:

Whether the ice sublimates or melts, the result is a higher containment temperature which yields higher pressures. Factor in melting instead of pressure. KA is not affected. B2 and D2 are NP.

This Q is U due to 2 NP distracters.

RFA 10/27/09 Tuesday, November 10, 2009 Page 33 of 185 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 14

~~~--'-------"-----'-~--'--'~~----~ -

~~~,-,- --l "---~-~~~-~---~'~~'--,-

---~--

~- -

--,~---

-~--,-~ --~-

~-"

--,~'-~--~~'--

~~--~

~q~!!i~!,~a~~!~~=8¥~~Il!~~=n~,!,~-,,_ ~~~~J f~~""'~IJ£--~ ___ ~ __ ~~~~ ~_~~ _______ ~~ _~ __ ~_ ~ __ ~_~~ __ ~~ ________ ~ __ ~, ___,~_

I 1814 I

SYS025 K502 IIKnowledge of operational implications of the following concepts as they apply to the ice condenser system: (CFR: 41.5/

,~--- ~~ ~ ~ __ l_ --~- ~~-

- ~-- ~---~ IJ1.Z)g!!e~!Jnul~f~E--,:-:.~:~:".. ~~.:-:.~:".:-::-:.~:-:~._

... _,~ _~~ _____,~_,_, __, __ ~ __ ~~ __ ~'~'~~~~~ ____ '~_~ ~_

j CURRENT Which ONE (1) of the following completes the statements below regarding the effect of operating with elevated Ice Condenser temperatures on the process of sUblimation and the resulting operational implications should a high energy line break occur inside containment?

Sublimation rates would ~.

Peak containment pressure would be ~

A (1) increase (2) higher

8.

(1) increase (2) unaffected C.

(1) decrease (2) higher D.

(1) decrease (2) unaffected 025K5.02 45 DAY VERSION Which ONE (1) of the following describes the effect of operating with elevated Ice Condenser temperatures on the process of sublimation and the resulting operational implications should a high energy line break occur inside containment?

Sublimation rates would -11L.

Peak containment pressure would be (2)

A.

(1) increase (2) higher

8.

(1) increase (2) lower C.

(1) decrease (2) higher D.

(1) decrease (2) lower 401-9 Comments:

Whether the ice sublimates or melts, the result is a higher containment temperature which yields higher pressures. Factor in melting instead of pressure. KA is not affected. 82 and D2 are NP.

This Q is U due to 2 NP distracters.

RFA 10/27/09 Tuesday, November 10, 2009 Page 33 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 14 A

General Discussion Whether the ice sublimates or melts, the result is a higher containment temperature which yields higher pressures. Factor in melting instead of pressure. KA is not affected. B2 and 02 are NP.

I

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

---

~-

---

~~~-~-~-

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

-~----~--~~

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

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

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

-~~-~-

As stated in the Ice condenser lesson plan, the process of sublimation is accelerated with prolonged operation with elevated Ice Condenser temperatures. This would result in a loss of ice jinventory would decrease the total heat transfer capability of the ice condenser system. This would result in an increase in the energy remaining in the containment atmosphere during a high lenergy line break and a corresponding increase in the peak containment pressure.

I

\\KA is matched because the candidate must first understand the process of sublimation (Heat transfer via changing state directly from a solid to a gas). He must then understand that this Iwould reduce the overall heat transfer capability of the ice condenser system resulting in the operational implication of a higher peak containment pressure in the event of a HELBIC.

I I

!:r'h~s_qtl~sEo_n.is..hJg_h..£(")~ni!~e~~au~~~e_ uE~er-s!an~ ~~eJ~

c..0l1c~IJt~ ~nti!.~11 predi~~e ~Illp.'l0.c>l1eJ(lni()p~r'lti.0.l1:",~ _~ __ ~~~ _ ~ ~_~

~~ ________________ ~ __

Answer A Discussion

[<59=~~f~~=====================~= =-===_===-_~=~~== _=_=~~ = = _= =~====~=====_==_-==-=======-~---~-

---

~ l

~ _____ J Answer B Discussion II~c;;;'ect:S~e-e~Pl~;-ti~~ ~bo~~.-Pla~sible~Fir;t p~rt ~f th~q~e~tio~ j;-c~;:e~~ ;e~~ndi~-i;~~;:;'~ct.-Sh~~dfu~ ~a:;;-di<i~t~-;~t~~tk~st~ll~dthe-p-;o-;;';;~f;ubli~~~~ th;;-;;~uld-b~ ~ ~reditable !

I'llls~~r~ ___ ~ ____ ~ __ ~ ____________ ~ __ ~ ____

~ ____ ~ _~_~_~_~ ___ ~~ __ ~ _____ ~ __ ~ ____ ~~ _____ ~~ ___ ~ _______ ~~ __ ~ _____ ~ _~~ _~

~ ______ ~~

I Answer C Discussion ir~~o~~~s-e~~x£~~i~~a~~~e=~~~i~~~~ ~;;-ul~~ ~~~~~b~e-~h!tt~~~a~~~~~~o~~ ~~i~kt~~~~ Ic~~~~~~n~i~~~t~~~gh~r~~~~~~h~~~~~a~=~e~~_~~~;rt~~~~~~."

Answer D Discussion III;;~~~ct:S~; e~pl;;-ati~n -<ili;;-;e.-i;lau;ibl~:-As -d;;-s~rib~d ;-b~~e- ~-

--~- -

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

_ _ _ _ ~()flnJt!\\le_,--e~ft'

_ ('.}~!ati_°!1!~ __

Question Source

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension NEW I

_______ ~ ___ --.1 __

---~- -

~--

-~-

~-~-

-~-

~--

-~- -~-

-~- - -

~-~ ---

1<,-

~--- - --- -

~ -

-~-~---~--

-~-

f!!!,,-e!cp~e_n!~ftf~\\"e_n~!s_ ~ __ ~ ~ _____ ~_ __

L~t~<!e_n! ~ef~.. e~~!s.p!c)\\lI<!e~ _____ _

ITechnical Reference(s): LP OP-MC-CNT -NF (Rev 31)

I iPg 13 & 59 I

!Learning Objective: OP-MC-CNT-NF Obj 16 i

I I

I_~_~ ~ _______

~ __ ~~_ ~ ___ ~ _____ ~ _ ~ __ ~ ___ ~~~_

L~ ___ ~ ~ ___ ~ _______ ~ _~~ __ ~~ _~_~ ___ _

---~~-=--=-_~_--=-_--=--=-~~_~_-_---=-~~-_~J 401-9 Comments RESPONSE Changed B2 and 02 from "lower" to "unaffected". Should add some degree of plausiblility of these distracters. Oificult KIA need to keep question is tact. Revised wording of stem to say "Which ONE (I) of the following completes the statements... "

~- -

-~- --

~

~- --1-- -- --

~---T~~-~~-~-

-~ --

QuestionBank # IKA system IKA number r--~---~ -~--~~~---~--

~--

-~~~--

---

~-~----

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

IKA_desc

- --- --~

~-- -~~~=-- -- - - f--~-=--- ---~- --- -

18141SYS025 IK502

__ ~_~~_~ ________ l ___

~ ______ ~_~ __

iK~wledg~-of ~p~~ti~n~li~plic~ti~~~;[t~foII;;i~i~o~c~Pt;~ th~y ~ply to theic~ -c;;-nden;; ~y-;t~~: (CFR:

l~5Jl[]l:!e<ltt["aIlge! ____ ~_~ _________ ~ ___ ~ __________ ~__

_~

41.51 Tuesday, November 10, 2009 Page 34 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 14 A

General Discussion Whether the ice sublimates or melts, the result is a higher containment temperature which yields higher pressures. Factor in melting instead of pressure. KA is not affected. B2 and 02 are NP.

IA~~;ed i~th~ ~-c~~d~~s~r-I~~o~ p~~,thep;o~~~ of~bli~~i;;-~i~~"Zele~~~d-;;-th prolo~ed~Pe~ti~;;;th ~k;a~dlc~C~nd~;e~~mpe~a~~e~:-This ~~~Id~;;ulti~; 1~;;~fiZe-jinventory would decrease the total heat transfer capability of the ice condenser system. This would result in an increase in the energy remaining in the containment atmosphere during a high lenergy line break and a corresponding increase in the peak containment pressure.

I

\\KA is matched because the candidate must first understand the process of sublimation (Heat transfer via changing state directly from a solid to a gas). He must then understand that this Iwould reduce the overall heat transfer capability of the ice condenser system resulting in the operational implication of a higher peak containment pressure in the event of a HELBIC.

I 1

!:I*h~s_qtl~s.!i0_n..i~hJg_h.£(")~ni!~e~~au~-.J:~e_ uE~eI's!an~ ~~eI~

~ol1c~IJt~ ~nti~~l1.predi~ti1.e ~rI1IJ(t0..c>l1.eI(ln!..()jJ~filti..0~~ ____________... __________________________ _

Answer A Discussion

[<59=~~f=~============~========_~_= =-===_===-_~=~~== _=_=~= = = _= =~==========_==_-==-========-===_-==-====_==_-=_-==~==-J Answer B Discussion II~c;;;'ect:S~e-e~Pl~;-ti~~ ~bo~~.-Pla~sible~Fir;t p~rt;;_f th~q~e~tio~ j;-c~;:e~~ ;e~;;_ndi~-i~~~;:;'~ct.-Sh~~dth~ ~a:;;-did~t~~~t~~tk~st~ll~d the-pto-;;';;;;_f;ubli~~~~ th;;-;;~uld-b~ ~ ~r~dit-;;hl;i I'llls~~r _________. ________________________________________________________________._______ ____ _ _ __ ______ ___ __ __ ___________________ I Answer C Discussion r-'- --------- ------------- -- ----- -------- - -------- - ----- -------- ---- ------------.-- ----------- --- -.- ------- ---- --

IIncorrect: See explanation above. Plausible: It would be reasonable that the candidate would think that the ice would tend to melt at higher temps rather that sublimate. Second part is correct.

~ ________

~_ ~ ___ -

~ ___

~_~

______.J Answer D Discussion l~~~~ct}~~ ~"j~~~~~-~~;e; ~-~~;~I~i"~~d~~~~~~ ~~~~=-_-_--=--=-~~-=-=_=-=-= _-~~-=---=~-~ -=_-=~=_-_=~_=__=~-_~~~-_=_-~~-=-=-_-_--= -==_-_-~ -=-=-=-=_-_--=_--=-==~_-_-_ ---==-~-_-J

~-- -------

-~- --- --

--I

____ ~()Q.nJt!ve-, __ e~ft'

_ ('.l~!sti_°!1!~ __

NEW Question Source 1 401-9 Comments RESPONSE

~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension I

1

_______ ~ ___ --.1 __ _. _______________ ~ ________________________________ J IOevelopnlentReferences------ --- ------

r---------~---------.-- --------- -- ---.----

ITechnical Reference(s): LP OP-MC-CNT -NF (Rev 31) iPg 13 & 59 ILearning Objective: OP-MC-CNT-NF Obj 16 I 1_._- __________________________. _________ _

1<,- ---- - -.-- ---.--.--'---'-

LStudent References Provided 1------ ---------- ---.--------

I I i 1 L _____ ~ ___________ _

Changed B2 and 02 from "lower" to "unaffected". Should add some degree of plausiblility of these distracters. Oificult KIA need to keep question is tact. Revised wording of stem to say "Which ONE (I) of the following completes the statements... "

-- - --- -- - -- - -r-- -- - -

~-- -_r----- - --

-- - ---l 9tJ!stlonf!~'!k.. ~~~=~!I~e~ _ ~I\\-n~f!l~r __ ----1 rKA~deSc ----------

18141SYS025 IK502 I

__________ ~ _____________ l _______________, iK~wledg~-of ~p~~ti;;-n~l-i~plic~ti~~;;[t~foIl~~;;i~i~o~c~Pt;~ th~y ~ply to theic~ -c~nden~; ~y~t~~:(CFR:-4 I ~5 I l45.71u}:!eilttl"aIlge!..............-:.-..... :.-..-:....... :.. :.. :.. :--:.-:....... - ----- -- _ ------

Tuesday, November 10, 2009 Page 34 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 14 A

fuesday, November 10,2009 Page 35 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 14 A

fuesday, November 10,2009 Page 35 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE C

2009 RO NRC Retake Examination QUESTION 15

~~!ti~~B~~~~~A-:"~~Ri= +~~~m!)!~ = ===J iKA=C!~~=======-======~==========~==---=======-====-===-====---=============== =.= J 1815 SYS026 I

A2.08

lAbility to (a) predict the impacts of.t~e following malfunctions or operations ~n the CSS; ~d (b) based on those predictions, use I

---

-- ------'-- - -----~------- - -.---- -Iprocedures to correct, control, or mitigate the consequences of those malfunctIOns or operatIOns: (CFR: 41.5 143.5/45.3 /

I l4?J ~)g~~~ ~~tlfing ~~

c~.'1.~il1~~I1t...sp.l"~-",J1<!llit...c~n_b~~()Il~L:-:..-:..-::.-::.-* ________________________. ________ :

CURRENT 45 DAY VERSION The following conditions exist on Unit 1:

LOCA inside containment 1 ETB has experienced a ground fault Auto swap to Cold Leg Recirc. has failed due to 1NI-185A (iA NO Pump Suction From Containment Sump Isol) not opening Attempts to manually open 1 NI-185A have failed Control Room has implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Containment pressure is 12 PSIG and slowly going up Which ONE (1) of the following describes Operator actions associated with NS system operation following the receipt of "FWST Lo Lo Level?"

A.

8.

C.

O.

Open iNS-18A (A NS Pump suctfrom Cont Sump) and close 1 NS-20A (A NS Pump Suct From FWST), 'iA' NS pump remains running.

Secure '1A' NS pump, close 1 NO-19A (1A NO pump suet. from FWST or NC),

swap NS suction to Containment Sump, restart NS pump.

Secure 'iA' NS pump, NS cannot be aligned to Containment Sump until1NI-185A is open.

Secure'1A' NS pump, close 1 NS-20A and open 1 NS-18A, restart' 1 A' NS pump.

026A208 The following conditions exist on Unit 1 :

LOCA inside containment 1 ETB has experienced a ground fault Auto swap to Cold Leg Recirc. has failed due to 1NI-185A (Containment Sump Isolation Valve) not opening Attempts to manually open 1NI-185A have failed Control Room has implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Containment pressure is 12 PSIG and slowly going up Which ONE (1) of the following describes Operator aetions associated with NS system operation following the receipt of "FWST Lo Lo Level?"

A.

B.

C.

O.

Open 1 NS-18A (A NS Pump suct from Cont Sump) and close 1 NS-20A (A NS Pump Suct From FWST), '1A' NS pump remains running.

Secure '1A' NS pump, close 1 NO-19A (iA NO pump suet. from FWST or NC),

swap NS suction to Containment Sump, restart NS pump.

Secure 'iA' NS pump, NS cannot be aligned to Containment Sump until1NI-185A is open.

Secure 'iA' NS pump, close 1 NS-20A and open 1NS-18A, restart 'iA' NS pump.

401-9 Comments:

CAF: Do you expect the applicants to know what 1 NI-185A is? If you state the valve nomenclature, would that give away the answer?

RF A 10108/09 Revisited fuesday, November 10, 2009 Page 36 of 185 2009 RO NR~~!a~eEE:!!:t~~L y ~!~T~~Tl~ISTRIBUTE_ _ _ C _ _ __ __ _

~~!ti~~B~~~~iKA_:..~~Ri= T~~~m!)!~ = ===J iKA=C!~~=======-======~======.====~=:--=====~====~ _________ ~ ____ ~ __ ~:_---- _= ~

I 1815 r SYS026 T A2.08 liAbility to (a) predict the impacts of the followmg malfunctIOns or operatIOns on the CSS; ~d (b) based on those predIctIOns, use I

1 ____ -- ------"--------~------- - ----- J Iprocedures to correct control or mitigate the consequences of those malfunctions or operatIOns: (CFR: 41.5/43.5/45.3/

I I

I 14?J ~L[j§~~ ~~tlnng ~~

c~~~II1~~~SPE~-",J1<!ll~~c~n_b~~{)fl~L:-:~:-:~:~* ______ ~ ____ ~ ____________. ________ I CURRENT 45 DAY VERSION The following conditions exist on Unit 1:

The following conditions exist on Unit 1 :

LOCA inside containment 1 ETB has experienced a ground fault Auto swap to Cold Leg Recirc. has failed due to 1NI-185A (iA NO Pump Suetion From Containment Sump Isol) not opening Attempts to manually open 1 NI~ 185A have failed Control Room has implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Containment pressure is 12 PSIG and slowly going up Which ONE (1) of the following describes Operator aetions associated with NS system operation following the receipt of "FWST Lo Lo Level?"

A.

8.

C.

O.

Open iNS-18A (A NS Pump suctfrom Cont Sump) and close 1 NS-20A (A NS Pump Suet From FWST), 'iA' NS pump remains running.

Secure '1A' NS pump, close 1 NO-19A (1A NO pump suet. from FWST or NC),

swap NS suction to Containment Sump, restart NS pump.

Secure 'iA' NS pump, NS cannot be aligned to Containment Sump until1NI-185A is open.

Secure'1A' NS pump, close 1 NS-20A and open 1 NS-18A, restart' 1 A' NS pump.

026A208 LOCA inside containment 1 ETB has experienced a ground fault Auto swap to Cold Leg Recirc. has failed due to 1NI-185A (Containment Sump Isolation Valve) not opening Attempts to manually open 1NI-185A have failed Control Room has implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Containment pressure is 12 PSIG and slowly going up Which ONE (1) of the following describes Operator aetions associated with NS system operation following the receipt of "FWST Lo Lo Level?"

A.

B.

C.

O.

Open 1 NS-18A (A NS Pump suct from Cont Sump) and close 1 NS-20A (A NS Pump Suct From FWST), 'iA' NS pump remains running.

Secure 'iA' NS pump, close 1 NO-19A (iA NO pump suet. from FWST or NC),

swap NS suction to Containment Sump, restart NS pump.

Secure 'iA' NS pump, NS cannot be aligned to Containment Sump until1NI-185A is open.

Secure 'iA' NS pump, close 1 NS-20A and open 1NS-18A, restart 'iA' NS pump.

401-9 Comments:

CAF: Do you expect the applicants to know what 1 NI-185A is? If you state the valve nomenclature, would that give away the answer?

RF A 10108/09 Revisited fuesday, November 10, 2009 Page 36 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 15 The valve nomenclature was added RFA 10/27/09 c

CAF: Do you expect the applicants to know what INI-IS5A is? If you state the valve nomenclature, would that give away the answer?

RF A 10/OS/09 General Discussion c-:-~-----~ ~---~-.---~ -

---

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

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

---~--~ ----------;----.-

-:--~--~--

---

~-~-~-----:-------------~--:~----------~~---l jDlstracter AnalysIs: Operator must know that at FWST 10 10 level the NS pump must be secured. ReqUired wlthm 45 sec. Operator must realIze that due to the physical arrangement on the I

!piping, the IA NS pump cannot take suction from the Containment Sump without INI-IS5A open. Also, in order to swap suction, the NS pump must be secured, suction realigned and then I

Irestarted. Additionally, INS-IA is interlocked with INI-IS5A such that INO-IS5 must be closed before INS-ISA can be opened.

I IKA is matched because the candidate is given a situation where a malfunction has occurred which will impact the operators ability to place NS in a CLR alignment. The candidate must then Ipredict the impact of this malfunction and understand how this condition will affect the ability the perform the appropriate procedure to mitigate this consequence. The NS pump will have to Ibe secured due to this malfunction and while in ECA 1.1 with containment pressure < 15 psig this would constitute a safe situation where the pump could be secured.

I

!This is a higher cognitive level question because evaluate a given set of conditions and predict an outcome. This will require using the system knowledge and applying its meaning to predict lthe impact.

c ________ ~

_~ ___ _

Answer A Discussion

~- - - ---- -

---

~---

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

IIncorrect: See explanation above. Plausible: Valve alignment is correct therefore plausible, pump remains running is plausible because the ND pumps remain running during swap to CLR.

1 ______ ----- ________ ~ ___ ~_~_~ ____ ~

__ ~

___ ~~_~

_______ ~

___ ~ ~~~~

___ ~

_____ ~

_____ ~ ______ ~~ ___

~

__ ~~~

__ ~

Answer B Discussion ifu~;--;;-ct~S~~~xpl~ation ;;-b-;~e~P~~sible~T~-a~ti~~~listed ~~~o~~Zt~iththe-~;c~Pt;;;~ ~fclo-s~giND-19A. This action is required to swap the ND pump suction to the sump,

~~l2.dl,!att: (;~u!d~ c()l1fll~.!.his_ \\\\,it_hJ'i~SII~ti0.l1~\\\\,ap~ ________________ ~ __ ~_~~_~ __ ~ ~ __________ ~~ _~ __ ~ ___ ~ ___ _

Answer C Discussion

~()~~T~-_-_-~-_-~-=-_~_-_-_-~_-_~- -_~ ~~~~_~~ ~~

~=~-~ -~=~=====------~-~ ----~

Answer D Discussion ilncorrect: See explanation above. Plausible: The actions listed would be correct if INI-IS5A were open.

L __________________________ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Question Source

--~-

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

MNS Bank Question ECCNSNOl2

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

loevelop~ent Refer:e,;ce;-* --~--~--- ---- Istudent-Re'erencesProvlded- -~--~ I r-- -~--~-~------~---- ~--- - -~-~------- -- - - -

f:----~~~--- ~~- --------- ___ ~ __.J ITechnical Reference(s): OP-MC-ICC-NS, rev. 30, page i15,35 and 39.

I I

I

!Learning Objective: OP-MC-ECC-NS, Obj. S 1

I L _____________________ ~ ___ ~~~ ________ ~ ___ ~_

1 ___ ~

_____ ~ ________ ~_ ~

401-9 Comments RESPONSE The nomenclature for INI-IS5A was added to the question during validation. The version of the question sent to the Lead Examiner did not have the nomenclature.

-~-~-

--~---

~ --

r-~-~~--

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

-~------

~LJf}~t~o..,f3!rt~i! 1'<!-.....II~S!e.n_J_ J~

.... rtU.l1l_~! ___.....

IKA desc-

~-- ---

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

-~ - -- -

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

1----= --- ---------

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

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

---

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

lAbility to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, 1 ______ -- __ ~~

____ ~~ ______ ~ ~_~ ___ ~ ______ ~

__ ~_~ ____ ~~

_______ ~ _________ ~ __ ~_~ _________ _

ISI5/SYS026 iA2.0S

_____ ~ ____ ~ _____ J __ _

Tuesday, November 10, 2009 Page 37 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 15 c

General Discussion The valve nomenclature was added RFA 10/27/09 CAF: Do you expect the applicants to know what INI-IS5A is? If you state the valve nomenclature, would that give away the answer?

RF A 10/OS/09 c-:-~-----~ ~---~-.---~ -

---

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

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

---~--~ ----------;----.-

-:--~--~--

---

~-~-~-----:-------------~--:~----------~~-

iDlstracter AnalysIs: Operator must know that at FWST 10 10 level the NS pump must be secured. ReqUired wlthm 45 sec. Operator must realIze that due to the physical arrangement on the

!piping, the lA NS pump cannot take suction from the Containment Sump without INI-IS5A open. Also, in order to swap suction, the NS pump must be secured, suction realigned and then Irestarted. Additionally, INS-IA is interlocked with INI-lS5A such that INO-IS5 must be closed before INS-ISA can be opened.

I IKA is matched because the candidate is given a situation where a malfunction has occurred which will impact the operators ability to place NS in a CLR alignment. The candidate must then Ipredict the impact of this malfunction and understand how this condition will affect the ability the perform the appropriate procedure to mitigate this consequence. The NS pump will have to

[be secured due to this malfunction and while in ECA 1.1 with containment pressure < 15 psig this would constitute a safe situation where the pump could be secured.

I

!This is a higher cognitive level question because evaluate a given set of conditions and predict an outcome. This will require using the system knowledge and applying its meaning to predict lthe impact.

L ________ ~

_~ ________________ ~ ______ ~~_~ ______ ~ ___ ~_~~_

~ __ ~~ ______ ~

___ ~~

__________ ~

_____ ~ ______ ~~_~ __________ ~ ____ ~~ ___ ~ ___ ~ _______ ~

Answer A Discussion iIn~~~ect~Se~~pl~~i~;;- ;bo~~.-Pla~sibi;-valv~ ~li~me;;-t is ~;;-~ect-th~~ef~~;;_pl~u~ilik:Pu~p~;~~in~~u;~;;gj;Pl~;bl~b~~u~e-theNDpu~p;~~~; ~;;_~~~d~ri;;-g~;;p-t~CLR.~1 1 ______ ----- ________ ~ ___ ~_~_~ ____ ~

__ ~

___ ~~_~

_______ ~

___ ~ ~~~~

___ ~

_____ ~

_____ ~ ______ ~~ ___

~

__ ~~~

__ ~

_____________ ~ __________ ~_~ ____ ~~ ___ ~~

Answer B Discussion ifu~;~ct~S~;;-~xpJ;;ation ~b~~e~P~~sible~T~-a~ti~~;listed ~~~o~~Zt~iththe-~;c~Pt;;;;;- ;;-fclo-s~gIND-19A.-This~Ztio;;- is~~q-;;:i-;:-edt~-s~;;;-p-th;NDpu~p ~~cti;;-n~t~th~~u~p: ~--

~~l2.dl,!att: (;~u!d~ c()l1fll~.!.his_ \\\\,it_hJ'i~SII~ti0.l1~\\\\,ap~ ________________ ~ __ ~_~~_~ __ ~ ~ __________ ~ __ ~ __ ~ ___ ~ _____ ~~~ __ ~~~~_~_~ ___ _

Answer C Discussion

~

---

~-~-------

---

~

-~-

--~~~-

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

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

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

---

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

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

CORRECT.

---

~- -

---

~-----~--

--~--

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

Answer D Discussion IIncorrect: See explanation above. Plausible: The actions listed would be correct if INI-lS5A were open.

L ~~ __ ~~ ___ ~ ___ ~ _____ ~ _____________________________ ~

___ ~ ______________ ~ __ ~ ___________ ~ _____ ~ ______ ~ ______ ~ ______ ~ ________ ~ __ ~ ______ _

Job level

---

~-~-~-~--r---------

-~-r-----

~-

--~---~--~-

---

~----~~ --

-~- ---- -

---

~~-----

Cognitive level I QuestionType I

Question Source

~--~---I-~--

RO

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

r-~-~- -----~~I--- ---- ------- -----~--------~-~~-----~--- ~~ ----~- - ----

Comprehension i

BANK

[

MNS Bank Question ECCNSN012

___________________ L ___________________ L ______

~ ______________

~_~_~ ________

~ ______________________ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 1--- ------ --- ---

---

~----- - --

---

~---- -- ----

IDevelopment References r-- -

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

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

[Technical Reference(s): OP-MC-ICC-NS, rev. 30, page 115,35 and 39.

I

!Learning Objective: OP-MC-ECC-NS, Obj. S 1 L ______________________ ~ ___ ~~~ ________ ~ ___ ~_

~!udent-R!t!r~~~~yI~~I~!.d~ -~ -- ~

[

[

I I ___ ~ __ -- _~ ________ ~_ ~ __

401-9 Comments RESPONSE The nomenclature for INI-lS5A was added to the question during validation. The version of the question sent to the Lead Examiner did not have the nomenclature.

-~-~-

--~---

~ --

r-~-~~--

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

-~------

~LJf}~t~o..,f3!rt~i! 1'<!-,....II~S!e.n_J_ J~

___ rtU.l1l_~! ___.....

IKA de;c-

~-- ---

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

-~ - -- -

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

lS151SYS026 iA2.0S

______ ~ ____ ~ _____ J __ _

1----= --- ---------

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

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

---

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

lAbility to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, 1 ______ -- __ ~~

____ ~~ ______ ~ ~_~ ___ ~ ______ ~

__ ~_~ ____ ~~

_______ ~ _________ ~ __ ~_~ _________ _

Tuesday, November 10, 2009 Page 37 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE C

QUESTION 15 2009 RO NRC Retake Examination iu; pr-;;-Zed;~;to-c~;;~~t~c-;~t~1, ;;-r~itig~;the -~~;-~qu~~~~ftho-;e-~alfun-;;ti;;s~~~p~;~~~~CFR: 41.5 /43.5 /45 J /

[L45.13)[]Safe securing of containment spray when it can be done)

---

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

---

~-

Tuesday, November 10, 2009 Page 38 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE c QUESTION 15 2009 RO NRC Retake Examination

-,~-,~-

~-,- -,-- -- ----- -,--

--~,-,--

~---,-,-

-,--~-,-,~-,~-,--,~-,-,---- ---- -~--~-~I luse procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 /43.5 /45 J / I i45.13)[]Safe securing of containment spray when it can be done)...............

I L __________

~ __________. __________________________________________________

~ __. ____

J Tuesday, November 10, 2009 Page 38 of 185

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 16 I

-- ---- ------- - -.--------1----

IQuestlonBank ## IKA system KA number 1-"'- - - --------- -f-=-=-------t:-: --=------ - ---

I 1816 I

SYS026 i

2.2.12 IKA dese r-------------------------------- ----

~I'S~~6_G~~~~I~~~~~lt:dg=_()[_~u_"'.:ilI<lIl=_e!!"()cedu~~ ~C!'~~!~~~~5___!2)

---..j I

1 ___________.J. _____ ~

__ 1 _____ _

CURRENT Unit 1 is at 100% RTP with the Ops Test Group (OTG) performing PT/1/A/4208/001 A (1A NS Pump Performance Test). The OTG Technidan has reached the step in this PT which directs the starting of the 1A NS pump.

Which ONE (1) of the following describes the required positions of 1 NS-29A (A NS Pump Disch Cont Outside Isol) and 1 NS-32A (A NS Pump Disch Cont Outside Isol)

AND the required system alignment for the performance of this PT?

A B.

C.

D.

Valves CLOSED "A" Train NS system flowpath is through the HX and directly back to the pump suction.

Valves CLOSED "A" Train NS system flowpath is through the HX to the FWST Valves OPEN "A" Train NS system flowpath is through the HX, through 1 NS-29A and 1 NS-32A, then directly back to the pump suction Valves OPEN uN Train NS system flowpath is through the HX, through 1 NS-29A and 1 NS-32A, then to the FWST 026G2.2.12 46 DAY VERSION Unit 1 is at 100% RTP with the Ops Test Group (OTG) performing PT/1/A/4208/001 A (1A NS Pump Performance Test). The OTG Technidan has reached the step in this PT which directs the starting of the 1A NS pump.

Which ONE (1) of the following describes the required positions of 1 NS-29A (A NS Pump Disch Cont Outside Isol) and 1 NS-32A (A NS Pump Disch Cont Outside Isol)

AND the required system alignment for the performance of this PT?

A.

B.

C.

D.

Valves CLOSED "A" Train NS system flowpath is through the HX and directly back to the pump suction.

Valves CLOSED "A" Train NS system flowpath is through the HX to the FWST Valves OPEN "A" Train NS system flowpath is through the HX and directly back to the pump suction Valves OPEN "A" Train NS system flowpath is through the HX to the FWST 401-9 Comments:

I am not sure C2 is plausible with the valves open. Please re-evaluate this. If the disch valvs are open, a basic understanding of fig 7. I of the reference renders this choice NP.

RFA 10/27/09 Tuesday, November 10, 2009 Page 39 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 16 IQLWstlonaank# IKA- ;Y;tem~lKA numbe~-

1", - - ~-,-,--,- -f-=-='~--~- ~

-=-~-~,- - ---

I 1816 I

SYS026 i

2.2.12 l ______ ' ____ ~ __,_~~ __ 1 _____ _

CURRENT Unit 1 is at 100% RTP with the Ops Test Group (OTG) performing PT/1/A/4208/001 A (1A NS Pump Performance Test). The OTG Technidan has reached the step in this PT which directs the starting of the 1A NS pump.

Which ONE (1) of the following describes the required positions of 1 NS-29A (A NS Pump Disch Cont Outside Isol) and 1 NS-32A (A NS Pump Disch Cont Outside Isol)

AND the required system alignment for the performance of this PT?

A B.

C.

D.

Valves CLOSED "A" Train NS system flowpath is through the HX and directly back to the pump suction.

Valves CLOSED "AN Train NS system flowpath is through the HX to the FWST Valves OPEN "AN Train NS system flowpath is through the HX, through 1 NS-29A and 1 NS-32A, then directly back to the pump suction Valves OPEN "A" Train NS system flowpath is through the HX, through 1 NS-29A and 1 NS-32A, then to the FWST 026G2.2.12 46 DAY VERSION Unit 1 is at 100% RTP with the Ops Test Group (OTG) performing PT/1/A/4208/001 A (1A NS Pump Performance Test). The OTG Technidan has reached the step in this PT which directs the starting of the 1A NS pump.

Which ONE (1) of the following describes the required positions of 1 NS-29A (A NS Pump Disch Cont Outside Isol) and 1 NS-32A (A NS Pump Disch Cont Outside Isol)

AND the required system alignment for the performance of this PT?

A.

B.

C.

D.

Valves CLOSED "AN Train NS system flowpath is through the HX and directly back to the pump suction.

Valves CLOSED "A" Train NS system flowpath is through the HX to the FWST Valves OPEN "AN Train NS system flowpath is through the HX and directly back to the pump suction Valves OPEN "A" Train NS system flowpath is through the HX to the FWST 401-9 Comments:

I am not sure C2 is plausible with the valves open. Please re-evaluate this. If the disch valvs are open, a basic understanding of fig 7. I of the reference renders this choice NP.

RFA 10/27/09 Tuesday, November 10, 2009 Page 39 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 16 B

General Discussion c----

~-~ ---- ---

~-~-----

---

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

~-------

---

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

!The IA NS pump perfonnance test is accomplished by aligning the discharge of the IA NS pump via the nonnally aligned suction to the FWST. The pump discharges to the associated HX land then downstream of the HX, a manual valve alignment is perfonned which directs the discharge to the FWST. Full flow capability is provided and the containment isolation valves remain lclosed with their associated interlocks bypassed to allow pump operation.

IKA is matched because the operator must be familiar with the operational alignment required to perfonn this surveillance procedure. The knowledge required is specific to its perfonnance land cannot be answered with system knowledge alone.

L

~

__ ~ ______________________________

~ ____________________________ _

~----- -----------~------ --- -------,'

Answer A Discussion c

---

~~ -~------

---

~ -

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

-~ ~--

~ -- -------

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

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

~ ~---- ----

~ ---

IPlausible: first part is correct, second part is plausible because when the ND performance test is perfonned the flowpath is directed back to the pump suction.

--~-------

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

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

---

~----

--~-----

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

Answer B Discussion lc~~:~-=-=-==== -==-_ ~_=-= =-= __ ~ __ _

Answer C Discussion IPI~~;bk:The Zorrtain~ent~~latio;~l~e;-are ;~t~rl-;;-c~ds;:;ch-atl~to;_e~;:;stb~p~;-t;-~Ilo~v -Pu;ps~rt~ ihi:0nterloZkisbyp~ssed by thi;-PT.S~~o;_ip~rt i~P1a~ibl~-~;-d~;:;b;;d----

laJ-lo.".e. ____ ~ __ ~ _________ ~_ ~ ___ ~_ ~ ___ ~ ___________ ~ _____ ~_~ _________________ ~ ___________ ~ ______ ~_~ ___ ~ ___ ~ __

Answer D Discussion iPl~~;ibl~Fir; Pctrti;-p~~~ible~~-de~~ibed abo~e~nd the~se~~;dp.;rt is Zo;:;:~~t.

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

l _______ ~ ___________________________________________________

~_~ ______ _

Question Source I 401-9 Comments RESPONSE

~= JO\\6~f f

=-=c~i~i:~!\\f~C-= 1

=~!sJ:~!¥~e=F= - -

---~-~- ------ --- i Added the isolation valves INS-29A and

__ ~ ___ ~ ___________ ~~ ______ ~.~~ _____ ~ ___

~...L_~ ____ _

~ --- - -------- _.J INS-32A to the second part of distracters C

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

,-~~

~ ~--

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

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

r-~-~--

~-~----~---

---

~ ---

l!'~!'~!!l!n!.~fftrEt~!.s~ ~ ___ ~ __ ~ __ ~_ __

I~u~!.n!.~efe~n.£es fr~vlde<!... ___ _

ITechnical Reference(s): OP-MC-ECC-NS, Rev. 30, Ipage 21 IPTIIIN4208/001 A (IA NS Perfonnance Test, Rev. 57, Ipage 7 IlLearning Objective: OP-MC-ECC-NS, Obj. 6 & 8 I

~~- ---~-- -

-~----- -------- --"------ ~--- ~

---

~--- _.-

-~-

and D to ehance plausibility.

~uestionBank#iKA~sy$teln-1KA=number-----i iKA-=.desc--- -~----- --~-~--- -

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

-~ l---~-----~ -- -~ --

~ --I 1-- --- ~-- ----

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

---

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

l_~ _~_. 1_8~61~Y~0~~ ~~.J~2~12 ________ ~_I 1~~0~6_G~1-IER~~[~~~no~~d~e~f_s~rv:il~a~ce!roG~~res*i~~R.:. 41.~ !4~1_3) _______ ~_

Tuesday, November 10,2009 Page 40 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 16 B

General Discussion

!The 1A~

NS pumpp~f~;;;an-;;~-te~t i;- ac~~plished byalig;ti;g th;cti;-~h~g~-;;fth~ lA ~NSp;~p ~i;t~ ~;;;;;;II~lign~d~~t~nt~th~FWST~Thepumpcli;~ha~es t~the;s;~ciat~d ~HX~I land then downstream of the HX, a manual valve alignment is performed which directs the discharge to the FWST. Full flow capability is provided and the containment isolation valves remain I Iclosed with their associated interlocks bypassed to allow pump operation.

I I

IKA is matched because the operator must be familiar with the operational alignment required to perform this surveillance procedure. The knowledge required is specific to its performance I

land cannot be answered with system knowledge alone.

I L

~

__ ~ ______________________________

~ ______________________________________. __

~ _________ ~ ________________ ~ ________________,

Answer A Discussion c

~-~~---

---

~--~

~-~-~~~~-

~ ~---~ - -

0-

_o~ ~O~O _____ o~ __ ~ _____ ~ooo ____ oo _____

~

_____ o _____ ~

~ __ O ____ ~~ ___ ~~~_

~o ___ ~o __ 1 IPla~si~l~firstpar~s ~orl"e~'~~~~aJ"t ~

p~a~itJl~-=-c~s: \\\\'ll~ ~e_

NE~e~~)"m~[1(;e~e~ ~~ ~r~fIl1~ ~=-n~~atlJ ~

c!ir~t-=-d~a~k ~

~h~~m~ ~c~on. ~_~_ ~~ __ ~ ~~ __ I Answer B Discussion rCo;;:-ect----~----~~ ----

_o_~ - -------

_O~ __ ----~ -

~

__ O_~ ____ ~O ____ - ---~--~~-----~~~-

~

~o~~

-~~~---~ ---

~-

~-- --

~~~-I IL __________

~ ________________________

~ ________________._. __________ " _________________________ ** _

____________________ I Answer C Discussion IPI;;~;bk:The Zorrtain~enti;~latio;~l~e;-are ;~t~r1~c~ds;:;ch-atl~to;e~;:;stb~p~;t;-;;lio~v ~Pu;ps~rt~ ihi;interloZkisbyp~ssed by thi;-PT.S~~o;d p~rt i~P1a~ibl~-~;-d~;:;b;;d~~--

laJ.lo~e* _____ o_~ ~ _______ ~ __ ~ __ o __ o_o~ __ ~ _________ o_o_~ _____ oo~ _____ ~ ~ ___ ~ _____ ~ _~ ____ ~~ __ ~ ___ ~ ____ ~~ _ ~~ __ ~

Answer D Discussion iPl~~;ibi~Fir; Pctrti;pJ;;~~ible-~-de~~ibed abo~e~nd the-se~~;dp.;rt is Zo;:;:~~t~ ~-- -

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

--- ~~-~~----~--O~Ol l_, ___,_ ~ ___________.

~_~ ____________________________. ______________

~ __

~_~ ___________________ _

I-~

--~ -- T ---- -

~_o_ --- -

O--l~-- -- -- -

~~_o_ -- -

--.~~- - - -

_~_o ___ oo ______ o~ ______ o ___ ~

~-- - -,

~I ~J-O~RLo~V~I-

+.1 --c-.e>-ItnM-'!e'm!eoo-ryL!\\f!'----+.1 -CltJ!SN!!Eo-Wn!¥e.e-- rl. - --~- ---~~- _qtJttSt!()E~o-",~~ ___ ~ ___ ~ ___ II 401-9 Comments RESPONSE Added the isolation valves INS-29A and

- -~- ~--

- -- - ---- ~---- -- ---~- ~_-.l~_~~~~_~_~ _____ ~~- --~~ __ ~~

__ ~_o~ _-.1 INS-32A to the second partofdistracters C

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~!r~~!nI~~~~!s= =

===~~=_=== __

ITechnical Reference(s): OP-MC-ECC-NS, Rev. 30, Ipage 21 IPTIIIN4208/001 A (IA NS Performance Test, Rev. 57, Ipage 7 IlLearning Objective: OP-MC-ECC-NS, Obj. 6 & 8 1

~- -

~~-.----- -

---

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

r---~ - --~-~ ~-~-- ~~- -~-~

and D to ehance plausibility.

I~u~~n~~efe~n~es fr~vlde,",--____ _

~uestionBank #iKA~systeln-1KA=number -- ~-~i iKA-=.deSc--- ------ - -~- --- ~~~~ --

---

~ -

0

[~== =-- ~ ~6~Y~0~~ ~= J~2~2~= =

_~= _- =.~ j :~EO~6~G~~ER~~ [~~~no~~~e~~s~~i1l~~ce!r~G~~e~. ~~R=41. 0!-4~1})-=_~ ~~ -==_- -

Tuesday, November 10,2009 Page 40 of 185

A FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 17

~~~~~~~~i4~A:~~~~=~':n~~tiG!=:::::::: :::: ~ ~-~~~=-:::: ::::_:::: :::::::::::::::::::: ::::::::=-::::=::::==-_::::::::::::==- _=:::::::::::::::::::: ::::::::-____ ~ ____ -_-___ -___ -_ -_ -_=--_==

I 1817 I

SYS039, K3.04

[iKnowledge ofthe effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.71 45.6)lJMFW pumps

____________. ______.1. ______________ [

1::'-: :.-.:....-..:.. ~. :'-:"'-':":'-- ':_::.-.:.' :'--'-':- '~"~':.-:'"

CURRENT 45 DAY VERSION Given the following:

Given the following:

• Unit 1 is at 100% RTP

• Unit 1 is at 100% RTP

• Due to a severe packing leak, the Plant SRO decides to dose 1SP-1 (MAIN STEAM TO 1A CF PUMP TURS ISOL)

• Due to a severe packing leak, the Plant SRO decides to dose 1SP-1 (MAIN STEAM TO 1A CF PUMP TURS ISOL)

Assuming no additional operator actions are taken, what would be the effect of this action on the 1 A FWPT operation?

The 1A FWPT would:

A B.

C.

D.

remain in operation supplied by MSR exhaust ONLY.

remain in operation but the steam supply would swap to Aux Steam ONLY.

remain in operation but the steam supply would now be a combination of Aux Steam AND MSR exhaust.

slow down and back out of the header due to the loss of its primary steam supply for full power operation.

039K3.04 Assuming no additional operator actions are taken, what would be the effect of this action on the 1A FWPT operation?

The 1A FWPTwould:

A S.

C.

D.

remain in operation supplied by MSR exhaust ONLY.

remain in operation but the steam supply would swap to Aux Steam ONLY.

remain in operation but the steam supply would now be a combination of Aux Steam AND MSR exhaust.

slow down and back out of the header due to the loss of its primary steam supply for full power operation.

401-9 Comments:

Since aux steam is normally isolated at 100% power, change the stem power level to 85%. This will give Band C more plausibility.

RFA 10/27/09 ruesday, November 10,2009 Page 41 of 185 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 17

~~~~~~~~i'-I~A:~~~~= ~':n~~tiG!=:::::::: :::: -I ~_~~~=-= =_====::::= ::::==-==::::==-_::::::::::::==-_=::::::::=:::::::: ::::::::-__ ::::~_=-_-_=--_-=--_ -_ -_=---_== -=::::::::::::=_

I 1817 1 SYS039 T K3.04

-lrlKnowledge ofthe effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.71 45.6)lJMFW pumps

_ -----------.- _ -- __.1. __ -.- _ -.--. ---'r l::-::.-.:....-..:**~*:-:*.-.:.*.... :.-.:*.-.:.*.... *.... *.".:*.".:*:-:*.... _________._. ___. ________________. ___________. ______. __._

CURRENT Given the following:

• Unit 1 is at 100% RTP

• Due to a severe packing leak, the Plant SRO decides to dose 1SP-1 (MAIN STEAM TO 1A CF PUMP TURS ISOL)

Assuming no additional operator actions are taken, what would be the effect of this action on the 1 A FWPT operation?

The 1A FWPT would:

A B.

C.

D.

remain in operation supplied by MSR exhaust ONLY.

remain in operation but the steam supply would swap to Aux Steam ONLY.

remain in operation but the steam supply would now be a combination of Aux Steam AND MSR exhaust.

slow down and back out of the header due to the loss of its primary steam supply for full power operation.

039K3.04 45 DAY VERSION Given the following:

• Unit 1 is at 100% RTP

• Due to a severe packing leak, the Plant SRO decides to dose 1SP-1 (MAIN STEAM TO 1A CF PUMP TURS ISOL)

Assuming no additional operator actions are taken, what would be the effect of this action on the 1A FWPT operation?

The 1A FWPTwould:

A S.

C.

D.

remain in operation supplied by MSR exhaust ONLY.

remain in operation but the steam supply would swap to Aux Steam ONLY.

remain in operation but the steam supply would now be a combination of Aux Steam AND MSR exhaust.

slow down and back out of the header due to the loss of its primary steam supply for full power operation.

401-9 Comments:

Since aux steam is normally isolated at 100% power, change the stem power level to 85%. This will give Band C more plausibility.

RFA 10/27/09 ruesday, November 10,2009 Page 41 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 17 A

General Discussion

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

IThe low pressure governor valve opens first and is supplied by the Auxiliary Steam System until the Moisture Separators Reheater (MSR) steam has sufficient capacity to supply which occurs labove 80% power. The high-pressure governor is supplied by the Main Steam System and is used when the low-pressure governor is not able to meet the demand. High-pressure steam will

[be supplied automatically if low-pressure stream cannot maintain turbine speed. At 100% RTP the FWPT steam supply is from MSR exhaust only with the HP governor valves completely Iclosed. With the given power level, closure of I SP-I would have no effect on FWPT operation. Aux Steam is normally isolated at 100% power but is the primary steam supply at low power Ilevels.

I IKA is matched because the candidate is being asked to evaluate the loss of the main steam supply to a operating main feed pump with the plant operating at 100%.

lI~s Js ~

E~h~r~gnitiv~ ~~~qlJ~t~~~~lJsetl1~ciln~~aie_mlls~

e~il!llilt~ ~~~nylaI"l!~~n(litiol1,~\\IilItI<lte_a~I1~~<~)~eIi}llt}i~~lJ~ ~d2~~i~ llI1 ~~colI1e-"--~ ~_~ __ ~ ___. __ _

Answer A Discussion I

ICorrect.

L ___________ ~_

J Answer B Discussion

[.-

~-.-. __

.~.-.- _._.. -

.-----.----~._--- ------ - _._-_._----_. __.- ---._-----.--_.- _.- - - - -. __... -----_.-._-

---

***----~I

)plausible because AS is the primary steam supply at lower power levels and AS pressure is high enough to provide this function but procedurally not aligned at high power.

I l ___________. __. __________. _____. ___________. __________________________________.. ________________________. _______________________________ _

Answer C Discussion 1.----------- -------- --------- - ---

-~---------

IPlausible because this would be true at lower power levels.

-.-----. ---- ---.--- - --.- ----------1 L _____________________________________ _

---

~--

._~. _____ ~ ____ ~ ____ J Answer 0 Discussion c*---**--*~-*-*-*-*- -

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

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

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

---

~-

- ---=-j

[plausible because at intermediate power levels 20% to 80% power this would be a true statement.

r-- -.- -.-.-,--.--.-.... ----.. -~-. -~- --.---.--.-

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

I Job Level i

Cognitive Level I QuestionType r

Question Source

--- ----- -.- --.. -.-- - ----*--*-f----*--- ~-- t--.~- - - ---.-.---.--.- ~~--.-.. --.. --.-

RO I

Comprehension I

NEW I

____. ______ L __... ___. _______ ~_. __________.L ___._.. __. ____ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

[Development Ref;re'lces---------

rStu(ient~ ReferencesProvlded----

F*- - - -.--- --.-.-- --.-- -.--.----.-

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

ITechnical Reference(s): OP-MC-MT-MSR Rev 17 I

[Pg 17 I

[Learning Objective: OP-MC-MT-MSR Obj. 2 i

I I

I

~__ __ __ ____ ____ _ __ __ ____ _ ___ _____ __ _ _ _ __ _ _

L _____________

~ _________ _

401-9 Comments RESPONSE Facility feels this distracters Band C have plenty of plausibility because both have been picked during validation. Validations scores are borderline ( 45%) miss rate as written, need to keep as is. ( In fact, all distracters have been picked)

~~~~*~nji~~k.~#J~AjY~.~~ -1~_~~nl~e~":-=-= = I r~J!s~ =.-~ -= ~-= -=..:-_=== =

~ _____ =~ ~-=-= =

-= --===== -=== = =-==-==-=== -= =.===== ~~---

18171SYS039 iK3.04

! [Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.7/ 45.6)iJMFW pumps

_____ 1._.. _ ~ ___. 1_..

. J !.:... :."":.""..:-.:.""........ :....:"":.-.:.. :."".~.:.. :-. ___ ~.

ruesday, November 10, 2009 Page 42 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 17 A

General Discussion IThe low pressure governor valve opens first and is supplied by the Auxiliary Steam System until the Moisture Separators Reheater (MSR) steam has sufficient capacity to supply which occurs labove 80% power. The high-pressure governor is supplied by the Main Steam System and is used when the low-pressure governor is not able to meet the demand. High-pressure steam will

[be supplied automatically if low-pressure stream cannot maintain turbine speed. At 100% RTP the FWPT steam supply is from MSR exhaust only with the HP governor valves completely Iclosed. With the given power level, closure of I SP-I would have no effect on FWPT operation. Aux Steam is normally isolated at 100% power but is the primary steam supply at low power Ilevels.

I IKA is matched because the candidate is being asked to evaluate the loss of the main steam supply to a operating main feed pump with the plant operating at 100%.

lI~s Js ~

E~h~r~gnitiv~ ~~~qlJ~t~~~~lJsetl1~ciln~~aie_mlls~

e~il!llilt~ ~~~nylaI"l!~~n(litiol1'~\\IilItI<lte_a~I1~~<~)~eIi}llt}i~~lJ~ ~d2~~i~ llI1 ~~colI1e-"--~ ~_~ __ ~ ___. __ _

Answer A Discussion ICorrect.

r L ________._. __________. ______________

• ____ ~

_______ ~

_____ ~

__

• _____ ~

_____ ~

_____

• ____________ ~ ___._. ____._. __ ~

__ ~_

• • ____________.J Answer B Discussion

~~sibl~_b:~~~~A§Ei~:E~~~i2'-~t~I11~~~p'iY!iIO~~~:P~-\\\\'~ -~~~~;-~~~ i~s;~~~~~g~ ~~u~~t~ir~v-i<i~_ ~~f~~~~tjio~~~~~~t!I~~~~~lliihy~~~-=~~~~~==~_=]

Answer C Discussion

1... - ----.-.- -.-.- --.------ - -- -- - -- - ----. - --.- -.-- --.-.--

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

---

~- -.- -- --. ---- ---- - -- - ---- --- ----- --1

~1~u.:i~I=_I:Je~a~=_t~~\\\\'ould~:t~.:.~~~er ~o_w:r~ev:ls_.~ ______. ___. _____ ~ __________.~_~ ______ ~ _____. ______ ~ _____ ~ ____ ~ ____ J Answer 0 Discussion c------~------~-------- - ------------.-----.---

---

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

---~---~- -

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

---

~--- -------- - --,

IPlausible because at intermediate power levels 20% to 80% power this would be a true statement.

1

~__ ______ _ __ _ ______

_ _________________ ~ ___

~ ____

~ _____, __

~ ____________________

~ ______

~ ______,_, ____ ----.1 r-- -.- ---

--,-----.---.--------~--

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

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

I Job Level I Cognitive Level

[QuestionType I Question Source

--- ----- --- -----.-- - ----*--*-f-------- ~-- t----~- - - -----.---.---- ~~--------

RO

[

Comprehension I

NEW I

____. ______ L _____ ~ __. _______ ~ _____________ L _____.. __. ____ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

[Development Refere,lces--- - -- ---

F*- - - ---- - - ---.-- --.-- -.--.- - --.-

ITechnical Reference(s): OP-MC-MT-MSR Rev 17

[Pg 17

[Learning Objective: OP-MC-MT-MSR Obj. 2 I

I

~-- -- -- ---- ---- - -- -- --,- -

~]~d~~~R"!f.(t~nCe~P.!~V!d~~=~.

I

[

I I

[

L_~ _________. ____ _

401-9 Comments RESPONSE Facility feels this distracters Band C have plenty of plausibility because both have been picked during validation. Validations scores are borderline ( 45%) miss rate as written, need to keep as is. ( In fact, all distracters have been picked)

--- -.. ----- -:1 ~

~-.- - - ------ -.---- - - -I,-- - - --.--- --- - --.- -.

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

}.... ~!'()_n.!'.llflk._#~~A-!y~.~!'l..-+~-.rl.... Ill~eE- _.. __ I f~=-d!S~ -... - --.. --- -----------.----.. --.~---- - -- - -;--- ---.-- --.------ -----

1817[SYS039

[K3.04

! [Knowledge of the effect that a loss or malfunctIOn of the MRSS will have on the followmg: (CFR: 41.7/ 45.6)iJMFW pumps

_. _____ 1._.. _~ ____

1 __._.. ~_.

. J !.:... :.--:.--..:-.:.--........ :....:--:.-.:.. :.--._... _

__ :-. ____. ____ ~ _____________. ~ _________ ~ _______. _____. __ _

ruesday, November 10, 2009 Page 42 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 18 B

I ~--

--~-

~-r---~~

~- ----I. -~~~--

--~~- -

--~-- I r ~~-~~~~--~-~-

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

~ -

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

~

~--~ -~--

~ -

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

---

~~-

~---~-

-~1 r~~~~~~n! ~~~~;~r -t~-~~~2~- ~ ~1 ~~~fe~;~~fth~~ff~tt~talo;s-~;I11;lfu~ctio~-~-fthe~MFw~will-h-;v~ o-;;th~-f-;II~;ing:(CFR:

I 41.71 45.6)CiAFW -;;t;I11-~--)

.-~~-~ ~ --- -

L __ ~_ ~~----'-- --- ~----~~-- ~~_J l~.:,:.:..~':":-:':":~"'~~:-:-:'~ ____ ~ __ ~ __________ ~~~~ __ ~ ~ ____ ~ ____ ~~ __

---

~

CURRENT 45 DAY VERSION Given the following conditions on Unit 1:

• Unit is in Mode 3

• NC pressure is 1940 PSIG

• CA auto start defeat "Defeated" lights are lit.

The following sequence of events occur on Unit 1 while in Mode 3:

1. A CF isolation occurs on S/G Hi-Hi level

2. The S/G Hi-Hi level clears

3. CF isolation is reset

4. T -ave increases and NC pressure increases to 1960 PSIG Which ONE (1) of the following describes when any CA pump(s) should have automatically started?

A.

B.

C.

D.

When the SG Hi-Hi level cleared ONLY When pressure increased above 1955 PSIG ONLY Following the CF isolation reset OR when the SG Hi-Hi level cleared Following the CF isolation reset OR when pressure increased above 1955 PSIG.

059K302 Given the following conditions on Unit 1 :

Unit is in Mode 3

• NC pressure is 1940 PSIG CA auto start defeat "Defeated" lights are lit.

The following sequence of events occur on Unit 1 while in Mode 3:

1. A CF isolation occurs on S/G Hi-Hi level

2. The S/G Hi-Hi level clears

3. CF isolation is reset

4. T-ave increases and NC pressure increases to 1960 PSIG Which ONE (1) of the following describes when (if at alO any CA pump(s) should have automatically started?

A B.

C.

D.

Following the CF isolation reset When the S/G Hi-Hi level cleared When pressure increased above 1955 PSIG Should have remained off for these events 401-9 Comments:

Choice "C": Change P-II to 1960 psig. This way they have to know what pressure P-ll is. This will increase plausibility and make the answer less obvious RF A 10/08/09 Revisited tuesday, November 10,2009 Page 43 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 18 B

r~~~~~~ni~~\\~~t~t~=~~~~====1 ~~i~;~~;;;t~~~I~s=~~m;I~~~ti:-~-fthe~MFw~will~h~V~ o~th~-f~II~;ing:(CFR:~41.7;45.6)[jAFW ~;t;~ -~-

C_c ___ ~ -~- ~ L ___ ~ _c __ ~_L_ ~-- __ ~ __ c ____ c_J l~.:,:.:..~':":-:':":~"'~'~"~:-:-:'~" c _______ ~ _____ ~ _____ c~~ ______ ~ _c~ ___ c _____ c~c_c ___________ c __ c_

CURRENT 45 DAY VERSION Given the following conditions on Unit 1:

• Unit is in Mode 3

• NC pressure is 1940 PSIG

• CA auto start defeat "Defeated" lights are lit The following sequence of events occur on Unit 1 while in Mode 3:

1 c A CF isolation occurs on S/G Hi-Hi level

2. The S/G Hi-Hi level clears

3. CF isolation is reset

4. T -ave increases and NC pressure increases to 1960 PSIG Which ONE (1) of the following describes when any CA pump(s) should have automatically started?

A B.

C.

D.

When the SG Hi-Hi level cleared ONLY When pressure increased above 1955 PSIG ONLY Following the CF isolation reset OR when the SG Hi-Hi level cleared Following the CF isolation reset OR when pressure increased above 1955 PSIG.

059K302 Given the following conditions on Unit 1 :

Unit is in Mode 3

• NC pressure is 1940 PSIG CA auto start defeat "Defeated" lights are lit.

The following sequence of events occur on Unit 1 while in Mode 3:

1. A CF isolation occurs on S/G Hi-Hi level

2. The S/G Hi-Hi level clears

3. CF isolation is reset

4. T-ave increases and NC pressure increases to 1960 PSIG Which ONE (1) of the following describes when (if at alO any CA pump(s) should have automatically started?

A B.

C.

D.

Following the CF isolation reset When the S/G Hi-Hi level cleared When pressure increased above 1955 PSIG Should have remained off for these events 401-9 Comments:

Choice "C": Change P-II to 1960 psig. This way they have to know what pressure P-ll is. This will increase plausibility and make the answer less obvious RF A 10/08/09 Revisited tuesday, November 10,2009 Page 43 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 18 B

Additional comment:

D is NP for set of events given. For this level of exam and knowledge, failure to recall that P-II resets is not likely. Therefore D is not plausible.

I suggest the following:

A.

Following the CF isolation reset or when the SG Hi-Hi level cleared.

B When the SG Hi-Hi level cleared ONLY C.

Following the CF isolation reset or when pressure increased above 1955 psig.

D.

when pressure increased above 1955 psig ONLY RF A 10/27/09 Choice "C": Change P-II to 1960 psig. This way they have to know what pressure P-II is. This will increase plausibility and make the answer less obvious RF A 10108/09 General Discussion I~ith both~CF p~p; tripped,.th~ CAp~~p;;;-uld~~0~ly~t~~Ho-;~v~~th~-CA-iu~p;-uto -;t~rt h;;b~~n d~f~at;;d~~;vid;n~ed-byt~ ~';Defe;rt~'~light;-b;~glit.-Wh~~ ~p~~s~;;; - ~-

Ilncrease above P-Il (1955 pSlg), the auto start defeat will be automatically unblocked and the CA Pumps Will auto start.

I liThe KIA is matched since the applicant must know how the Feedwater Isolation (loss or malfunction of the MFW) will affect the operation of the AFW system (i.e. AFW auto start).

--,~----------- -------.- - ----

~--

---

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

---

~-

Answer A Discussion I ~-- -

--~~

--~- ~-

~~- -

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

~.~ -

-.~ -

- --.-- -~-

~-----

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

~----l

[Incorrect: P-14 is defeated by CA auto start defeat

[Pl~slb.!e~I!te~cle1li:.irI~l)f.thE> ~~al\\\\'OllI.cI~IIcJ~ !o~ gFp_uIl"le.S!aI"t,-Clll1di9llt~.911IcI~0~tllS~ !his.~vitI1.a~~A.P~rmissive.

I

_~_I Answer B Discussion rcORREcr-~s~~r-~~~t-;;;t;;-rt-d~feat ;ilTA.~t-;; RESET ~he~~~;e-P~

l-;;-~ ~-;;-n-b~ m~~aJjyRESET at;nyti~e-:- -~-- -- -~---

L_._. ___._. ______ ~_.. ~ ___ ~~ ____.~_. __________________ ~ ___._~_~ ________ ~ ______._._~~ ___._._

Answer C Discussion

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

-~- ----

IIncorrect: Neither action will afftect CA pump operation IIPlausible: Either one of these action would allow for CF pump operation, applicant may confuse CF pump permissives with CA.

---

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

---~---- ---

---

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

1

____ ~ ___ ~ __ J Answer D Discussion iI-;;~~;~t~Fi~st-p~rt~ ~xpl~i~~~bo~; --- ---- - -- - -- -- -~- - ---

~- --

.~.. _- --

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

---~~

--~----,

[I'~alls~~e:...CF JS.9~ati().I1~~u!d_aB<>-~f()r..s::! J>ll..ll1p ~):Je~~ti~n~, ~~o_n~ ):J~J!.()f".tlle_a!1s~~ ls~<>-n:e~t_

I

~ ______ I

____ C_ojl,!l!Jve_ Le'ltll Comprehension

~~!~I<?fl.T2'~

BANK

_________ ~_ ~ _ ~ _ 9.lI.~!J~I!_~O_U~.! ____ ~~ ________ ~--I 401-9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved ruesday, November 10, 2009 2003 CNS NRC Q29 (Bank 229)

I

______________ J

-.~- --.-

~ ---

-.-~-

--~-.- --.- -

r< -

---

~-.- --

-.---.--~-... ~ - ----,

~e."!I~'Jl.e..!'!..~efe_,"!~,!",, ____ ~_~ ~_ _ __

@!,u.5l!.n.!~!f~'!fl.~~~~!i<l!~_ ~. _~ __

ILesson Plan OP-MC-CF-CA, Objectives 4 & 6 Pages 113 and 15 I

I I

I I

~-

~-

--~~-

-~-- ---- ---

Page 44 of 185 Question revised per Ron's suggestion dated 10/27, (2nd 401-9 comments),

barring additional concerns not identified in the 401-9 comments, should be OK now.

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 18 General Discussion Additional comment:

D is NP for set of events given. For this level of exam and knowledge, failure to recall that P-II resets is not likely. Therefore D is not plausible.

I suggest the following:

A.

Following the CF isolation reset or when the SG Hi-Hi level cleared.

B When the SG Hi-Hi level cleared ONLY C.

Following the CF isolation reset or when pressure increased above 1955 psig.

D.

when pressure increased above 1955 psig ONLY RF A 10/27/09 Choice "C": Change P-II to 1960 psig. This way they have to know what pressure P-II is. This will increase plausibility and make the answer less obvious RF A 10/08/09 I~ith both~CF p~p; tripped,.th~ CAp~~p;;;-uld~~0~ly~t~~Ho-;~v~~th~-CA-iu~p;-uto -;t~rt h;;b~~n d~f~at;;d~~;vid;n~ed-byt~ ~';Defe;rt~'~light;-b;~glit.-Wh~~ ~p~~s~;;; - ~-

Ilncrease above P-Il (1955 pSlg), the auto start defeat will be automatically unblocked and the CA Pumps Will auto start.

I 11'l1~ ~~Js_

~a~~e_d ~~c~

t!J_~ a2pli(;<lI1~ I1!u~t_~o~_ho\\\\, t!J~F"e~d~'lt~ ~s(jl~tio~Q~~~~alfullc~i()n~o!'t!J~ tvl~\\\\I)~!U ~~~~~~ op~~ti9~~ £h~!~Fyv_~s£e~~iL~*_A.!~_allt~ ~aIi l* ~_

Answer A Discussion I~------~--~-~-~~---*---*-~*-"~*~-

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

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

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

~ --.--.--

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--I

[Incorrect: P-14 is defeated by CA auto start defeat I

[Pl<ll1s1b.!e~I!te~cle1li:.irI~l)f.thE> ~~al\\\\'OllI.cI~IIcJ~ !o~ gFp_uIl"lps!aI"t,-clJ11.di9llt~.911IcI~o~ills~ ~his.~vitI1.a~~A.P~f111issiv~ __________ ~~~ ____ ~_~_~_

~ __________ ~J Answer B Discussion E9~i:!~~s~~r~~~~t~~t~rt=d~~a~~i~~~t~~~~'l' ~he~~~~-!~I~~~~ }~

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Answer C Discussion

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[Incorrect: First part as explained above.

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Job Level

____ C_ojl,!l!Jve_ Le'ltll Comprehension

~~!~I<?fl.T2'~

BANK Question Source I 401-9 Comments RESPONSE

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~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved ruesday, November 10, 2009 2003 CNS NRC Q29 (Bank 229)

I

____________________ ~ _________

~ __________________________ J IDevelopment References I-~ -.. --.----.-.- ~.-.-.---- -~--~-- --

ILesson Plan OP-MC-CF-CA, Objectives 4 & 6 Pages 113 and 15 I

I I

I Page 44 of 185 Question revised per Ron's suggestion dated 10/27, (2nd 401-9 comments),

barring additional concerns not identified in the 401-9 comments, should be OK now.

B FOR REVIEW ONLY - DO N T DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 18 lQue.tionB-ank'KA~;yatem--IKA=-n;m-ber -----l cKA~des~------ -------- ---- --------- ---------- ------------- -----------l r======= ~~~~~~ c===J~y~ ______ ~~~_-_-~--=--j ~~~kdge of th~ ;ffectthata lo-;~-o-; ~;lfu~cti~;-ofth; MFW ~illh~~~ ~n-t~f~~;i;;-g~(CFR:-41.7 / 4-5 ~):JAFW~ystt~-l i.. :: ___ :-::-:.:-:: ___ : ___

• ___

• ___ *:-.* ___ ~* ___ *-:::-: ___ *.. *_. _______. _______________. _________._c ___________________ J ruesday, November 10, 2009 Page 45 of 185 FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 18 I~~-------~--- ~-~

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~ __ ~_~ ____ ~ __________

~~~ _______

~ ______________ ~ ______ J ruesday, November 10, 2009 Page 45 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 19 A

---

~~-----

r-'---- -

---~-------"~--~-'- -,--- - - -- c'----'-- ----

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QuestionBank # IKA_system IKA_number IKA_desc I----~-----+----~----j-,-----,-,- ----

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I 1819 I

SYS059 I

K3.03 iKnowledge of the effect that a loss or malfunction of the MFW will have on the following: (CFR: 41.7 145.6)C]S/GS L ---,--- -~-~~-,-,------,-------,--

I...........................................................

CURRENT Given the following conditions on Unit 1 :

Unit 1 is operating at 60% RTP Channel 41 of Nuclear Instrumentation fails to 120%

"PR TO S/G PROGRAM LEVEL CHANNEL DEFEAT' switch is in the "Normal" position Which ONE (1) of the following describes the effect this failure will have on the S/G level control system?

A The feedwater regulating valves on A and 0 SGs ONLY will open to increase the NR levels to 65%.

S.

The feedwater regulating valves will remain in the same position for all SGs.

C.

O.

All feedwater regulating valves will open to feed all SG NR levels to 65%.

The feedwater regulating valves on Sand C SGs ONLY will open to increase the NR levels to 65%.

059K3.03 45 DAY VERSION Given the following conditions on Unit 1 :

Unit 1 is operating at 60% RTP Channel 41 of Nuclear Instrumentation fails to 120%

"PR TO S/G PROGRAM LEVEL CHANNEL DEFEAT' switch is in the "Normal" position Which ONE (1) of the following describes the effect this failure will have on the S/G level control system?

A.

S.

C.

The feedwater regulating valves on "A" and "0" S/G will open to increase the levels to 65% since NI Channel 41 is now the controlling channel for these S/G's.

The feedwater regulating valves will remain in the same position for all S/G's.

Trip program for "A and "0" S/G's will increase.

All feedwater regulating valves will open to feed all S/G levels to 65%. Since the programmed level is a "High Select" circuit, Channel 41 will be controlling.

D.

The feedwater regulating valves on "S" and "C" S/G will open to increase the levels to 65% since NI Channel 41 is now the controlling channel for these S/G's.

401*9 Comments:

Too much teaching in all distracters/choices. Furthennore, the second parts may give away the correct answer.

Reduce to the following:

A. The feed water regulating valves on A and 0 SGs only will open.

ruesday, November 10,2009 Page 46 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 19 r---~~~

~

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

--~~ -

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I 1819 I

SYS059 I

K3.03 L ~~ ___ ~_ ~ __ ~~~

____ ~_~ ____ ~_~

~~ __ ~~

r~~i~g;-Ofth~e-ff;ctth~;I;s~~~~lfu~tio-;-;it~MFW-willh-;v~o-;thefuIlo~i~g:(CFR:-41~7!45~)[!s/6s~~-~--~~1 I_.~:-:... :.. :~:-::.. :-:~:.. :.. ::o<:.. ",-"'~:O<'~~ __ ~~~_~ __ ~ ~~_~~~~~_~~~_~ ~_~ ___ ~ _~~ ____ ~ __ ~ _~ I CURRENT Given the following conditions on Unit 1 :

Unit 1 is operating at 60% RTP Channel 41 of Nuclear Instrumentation fails to 120%

"PR TO S/G PROGRAM LEVEL CHANNEL DEFEAT' switch is in the "Normal" position Which ONE (1) of the following describes the effect this failure will have on the S/G level control system?

A The feedwater regulating valves on A and 0 SGs ONLY will open to increase the NR levels to 65%.

S.

The feedwater regulating valves will remain in the same position for all SGs.

C.

O.

All feedwater regulating valves will open to feed all SG NR levels to 65%.

The feedwater regulating valves on Sand C SGs ONLY will open to increase the NR levels to 65%.

059K3.03 45 DAY VERSION Given the following conditions on Unit 1 :

Unit 1 is operating at 60% RTP Channel 41 of Nuclear Instrumentation fails to 120%

"PR TO S/G PROGRAM LEVEL CHANNEL DEFEAT' switch is in the "Normal" poSition Which ONE (1) of the following describes the effect this failure will have on the S/G level control system?

A.

S.

C.

The feedwater regulating valves on "A" and "0" S/G will open to increase the levels to 65% since NI Channel 41 is now the controlling channel for these S/G's.

The feedwater regulating valves will remain in the same position for all S/G's.

Trip program for "A and "0" S/G's will increase.

All feedwater regulating valves will open to feed all S/G levels to 65%. Since the programmed level is a "High Select" circuit, Channel 41 will be controlling.

D.

The feedwater regulating valves on "S" and "C" S/G will open to increase the levels to 65% since NI Channel 41 is now the controlling channel for these S/G's.

401*9 Comments:

Too much teaching in all distracters/choices. Furthermore, the second parts may give away the correct answer.

Reduce to the following:

A. The feed water regulating valves on A and 0 SGs only will open.

ruesday, November 10,2009 Page 46 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION DISTRIBUTE 19 B. The feedwater regulating valves will remain in the same position for all SGs C. All feedwater regulating valves will open to feed all SG (WR or NR) levels to 65%.

A D. The feedwater regulating valves on Band C SGs will open to increase the (WR or NR) levels to 65%.

RFA 10/27109 General Discussion IWithth~U~iti~iti~IIY~at60%Po-;-~~th;S/Gp;.~-g~a~-~ill~-;i~t;J;S/Gl~v~l~; ;ppr;xi~at;;ly55%~Whe~ N4-1 fails high: it be~~~th~ ~Tgh Sele~~~tr~ling cl;~~el io~--l A ~d lD IS/G level programs. The program level for A and D S/Gs will now be the 100% RTP program level or 65% NR S/G level. Therefore the feed reg valves on A and D will open to increase level Ito the new program level.

I IThis question matches the KA in that a malfunction of the Main Feedwater System has occurred (Feedwater Regulating Valves opening) as a result of the failure ofN41 (a malfunction of the IS/G Level Control portion of the Main Feedwater System). This malfunction results in an increase in S/G levels (the affected component).

I

\\ThiS question is Comprehension level because the applicant must associate two pieces of information (one given and one recalled from memory) to correctly answer the question. The given linformation is that N41 has failed high. From memory, the applicant must recall that S/G A and D program levels are controlled by the High Select ofN41 and N43.

Answer A Discussion E<:>~~T

__ -_~ _~~_~~~_-~~-_ -____ _

Answer B Discussion IIncorrect. Plausible if the S/G Level Program Select switch were in the "Defeat 41143" Position.

1'---_____ --------------------- ___________________________

• __________________________ _

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

~- ~--- -- -

--,.-~-

Answer C Discussion

~~~i~eZ~~~_~~~ Tft~j~GJ,~-v_~l~~-;~~:I-~Z~~;i~~~~~i~~ ~~~-;-'§~f~~~~4~~~P~~-~11.._~

Answer D Discussion 1----*_---------------------'- ------ -- ----,---------

~---,- --,- ----- ------,-,- ---,-- --------

[Incorrect. Plausible if the applicant does not understand which S/G level programs are controlled by which NIs.

~,

Job Level Cognitive Level --- T -Questi~onType Question Source

- - -~~~p~~hensio~-* ~ L~~~~A~NK_~~-

--~,--- ------------

RO MNS Exam Bank Question #ACFIFER07

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r----------- ---- ---- ---

---

~-~--- - -- - ---,--

ID~*!*f~I~!'l~'!t_R~!.e_"~~~ ___ ~ ___ ~~ _ ~_~--'

[Lesson Plan OP-MC-CF-IFE Objective 6 & 10, pages 119 and 21.

I I

L __________

~ ______ _

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IStudent References Provided r-'-~'~'~ ~-~.-.-~.--~ ~ - ~~.--.-

[

I I

I

[ L __. ______________, _________. __

401-9 Comments RESPONSE Question revised as suggested by Ron.

(Small change to what he suggested to distracter A) 1112/09 ltJ!s.!'~I'l.-~.!l~ !)!<A=SJ!.t!.'!l_l~-=!l~~~e-,,~ ____ ~

1819iSYS059 IK3.03

[

~~.=-----.~-~- ~.~~.--~.-~~~~-.~~~.--.~.-.-.-~ -~~.-

-~~~

~ -.-~-

IKnowledge of the effect that a loss or malfunction of the MFW will have on the following: (CFR: 41.7 1 45.6)llS/GS

_~~~._ ~~_~._ ~~

___ L ___.~ _____. _

I l*... :--*... *..... :-**.. *:-****:...... **:-*.. *.... *....... ::**... *:.-*... ~ __.~._. ___._ __.. ~~_. ____.. ~.

ruesday, November 10, 2009 Page 47 of 185 I

FOR REVIEW ONLY - DO DISTRIBUTE 19 A

2009 RO NRC Retake Examination QUESTION General Discussion B. The feedwater regulating valves will remain in the same position for all SGs C. All feedwater regulating valves will open to feed all SG (WR or NR) levels to 65%.

D. The feedwater regulating valves on Band C SGs will open to increase the (WR or NR) levels to 65%.

RFA 10/27/09 IWithth~U~iti~iti~IIY~at60%Po-;-~~th;S/Gp;.~-g~a~-~ill~-;i~t;J;S/Gl~v~l~; ;ppr;xi~at;;ly55%~Whe~ N4-1 fails high: it be~~~th~ ~igh Sele~~~tr~ling cl;~~el io~--l A ~d lD IS/G level programs. The program level for A and D S/Gs will now be the 100% RTP program level or 65% NR S/G level. Therefore the feed reg valves on A and D will open to increase level Ito the new program level.

I IThis question matches the KA in that a malfunction of the Main Feedwater System has occurred (Feedwater Regulating Valves opening) as a result of the failure ofN41 (a malfunction of the IS/G Level Control portion of the Main Feedwater System). This malfunction results in an increase in S/G levels (the affected component).

I

\\ThiS question is Comprehension level because the applicant must associate two pieces of information (one given and one recalled from memory) to correctly answer the question. The given liflf~fl!l~ti~nJS!llatJ~4l11a~!lt~e~!i.[h ___ F'l:()I~~e~~'2',~h~~Elic~n~Illu~t!:e~llll~ha~{~~at1c!Q pr~~~~~~~~~tI"0Jl~

~Ltl1~H~g~~e~ct ()[J'f~ l_a~~

~4~. ~_~ ____ ~ ~_~ ~

Answer A Discussion E<:>~~T

__ -_~ _~~_~~~_-~~-_ -__ ~_~--~--=--_-~~-~ ~~~~~_~~~~~~-_-~~~~:.~ ~~_-~ ~_~ ________ ~_-~~~~~ ___ ~_-~-_-~~-=~ ~=~-~~_=~-~ -=-_=--~~~ __ ~_~~~~~_-=-~_-=-~-~~ -_-=-~=_-_J Answer B Discussion

~~c~~~t:!~a~sib~eif~.:~19 ~~v~I_PI'O~r~~e~e~t_~\\\\,it(;h_~~e ~n.!~~~e.!'e~t~~~3~~o-=~i())1~ ~_~ __ ~ ~ __ ~ __ ~ ~~ _____ ~ ~ ___ ~ __ ~_ ~ ____ ~~_~_ ~ __

Answer C Discussion

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Answer D Discussion I--'--~---~- --,--,-,---- ------ ------ -- ------- ------ -

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~---~---I 1!~(;()I'I"~c~~I~u~i~le i£t~~a~p~i<;a~!.d()es I10~ ~~eJ"sta~d_\\V?LC~~~ ~:"e~JCf~~a~~~e_c~~~I~e~ ~y_~~~ ~I~ ____ ~ ~ __ ~_~ ____ ~~ __ ~ __ ~ __ ~ ~~ ___ ~ ______ J

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____, __ ~_, ___ ~9~!s.!~'!~ou!C~ __ ~ __ ~ _______ ~~ 401-9 Comments RESPONSE RO Comprehension I

BANK

_ ___,, __ ~ _____,_~ ___ L~ __ ~ _____ ~~

MNS Exam Bank Question #ACFIFER07 I Question revised as suggested by Ron.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

---

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

_~ ____ ~_~ ___ ~.J (Small change to what he suggested to r-----~-- ---- -~,~ --- ~-,-,~,--- -

~- -

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distracter A) 1112/09

~~~~~~~g!-=~h~~V.~F~Obj~~ti;e6 &~10, pages r!t~ct.e~!. F!e.!~!.~!s~.!~v'!d!ct._ ~---

119 and 21.

I I

I I

i L __. ______________. _________. __

'---~ -,---- ---1.:'---"- -- - To ~~ --,-,---- -~-'-~ ;---'-~~'~ -,-,~--,~--------,,--- ~- -----~,~

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luestlonBank # If<A_system lKA_number I IKA_desc

-- -~=-~J8!~S:Y_S~5?~ -=-~_-J~~~-~-~_-_~_-_ ---1 ~-;o~kdge~fth;~ff~ctfu~; k>;~;;alfu~ct;;~ ~ith~MFW~ill h;v~~n

-th~ folio~wing:(CFR~4i~7-/ 45.6) DS/GS-~ -

l*~:"*~*~:_**-'*:_****:~****:_*.. *~*.. **~::**~*.. *:. ___,_, _____,_ __ _ _________ "~ ________________ ~_~_ ~ ______ ~ __

ruesday, November 10, 2009 Page 47 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 19 A

ruesday, November 10,2009 Page 48 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 19 A

ruesday, November 10,2009 Page 48 of 185

B FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 20 rr;---~-~- -- -1.---- -

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1820 J

SYS061 KI.OI IKnowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to

---

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

141.9/45_7 to 45.8)l;S/G system.....................................................

L_~ __

~ ____

~ ________

~ _________________

~ __

~ _________________________________________ ~ ____

~ ________

~_

CURRENT 45 DAY VERSION Given the following on Unit 2:

A reactor trip from 100% RTP has occurred The TO CA pump tripped on overspeed upon starting Bus 2ETA locked out Which ONE (1) of the following describes which S/Gs are currently being fed and the associated flow rates?

A B.

C.

O.

A and B S/Gs at 450 GPM total flow C and 0 S/Gs at 450 GPM total flow A and B S/Gs at 450 GPM to each S/G C and 0 S/Gs at 450 GPM to each S/G 061KI.OI No comment at this time RFA 10127/09 ruesday, November 10, 2009 Given the following on Unit 2:

A reactor trip from 100% RTP has occurred The TO CA pump tripped on overspeed upon starting Bus 2ET A locked out Which ONE (1) of the following describes which S/Gs are currently being fed and the associated flow rates?

A A and B S/Gs at 450 GPM total flow B.

C and 0 S/Gs at 450 GPM total flow C.

A and B S/Gs at 450 GPM to each S/G O.

C and 0 S/Gs at 450 GPM to each S/G 401-9 Comments:

Page 49 of 185 2009 RO NR~~!a~~E~!~:t~~L y ~~~T10N_ 2;~~~~I~UT~_ _ __ B __ _ _

r~~de~~~=-=-~ =~====~ ~_~ ____ ~~~_______ ~~ __ _ _ __ ~_~ ____________ ~ __ _

IKnowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to

~L~!~7~to_,!?3~~/9~~~~~.*~~::,:*-::~*~*:~~**~*~*:,:.:-::~*:,:*:,:~ __ _ ~_~_~ ___ ~_~~ _______ ~~ ____ _

CURRENT Given the following on Unit 2:

A reactor trip from 100% RTP has occurred The TO CA pump tripped on overspeed upon starting Bus 2ETA locked out Which ONE (1) of the following describes which S/Gs are currently being fed and the associated flow rates?

A B.

C.

A and B S/Gs at 450 GPM total flow C and 0 S/Gs at 450 GPM total flow A and B S/Gs at 450 GPM to each S/G C and 0 S/Gs at 450 GPM to each S/G 061KI.Ol No comment at this time RFA 10/27/09 ruesday, November 10, 2009 45 DAY VERSION Given the following on Unit 2:

A reactor trip from 100% RTP has occurred The TO CA pump tripped on overspeed upon starting Bus 2ET A locked out Which ONE (1) of the following describes which S/Gs are currently being fed and the associated flow rates?

A A and B S/Gs at 450 GPM total flow B.

C and 0 S/Gs at 450 GPM total flow C.

A and B S/Gs at 450 GPM to each S/G O.

C and 0 S/Gs at 450 GPM to each S/G 401-9 Comments:

Page 49 of 185

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 20 General Discussion

[Th~ Tu7bi~~Dr~~n -CAp;mp i; tripp~d. IfTt-~~r~~~~git;o~ldfued ~I4 S/G-;.I ACA-~;;p-n-;;-~~lyfu~~-S/G-;lA-~d-1 B~IBCXP~;-p~~~alIy-f;;dsS/G;-IC~d-w~Withthe--

Iloss of power to Emergency Bus lETA, the IA CA Pump will not be running. Therefore, only IB CA Pump will be running feeding IC and 1D S/Gs.

'I lEach motor driven CA Pump is capable of supplying two S/Gs at a design total flow rate of 450 GPM.

I iThe KIA is matched because the applicant must know both the physical connections (i.e. which S/Gs are fed by which CA pumps) and the cause-effect relationship (i.e. the effect of the TD iCA pump and 2ETA lockout) as a result of the malfunctions related to the CA system.

I

[This is a comprehension level question because the applicant must associate mUlitple pieces of information, some given and some recalled from memory. First, the candidate must recall that Iwith Emergency Bus lETA locked out, the IA MDAFW pump will be unavailable. The candidate must then recall which S/Gs are fed from each MDAFW pump. The applicant must also

~ec~II~hat_t~ !"a~dJl()\\~'f()r_th~!v1p~~~EUl"I1£s_ ~__ ___ __ __ ___ _ _ ______ ___ __ _ ___ ______________ __ _____ ______ ~____ ___ ____ _ ____ _

Answer A Discussion iI;~rr~clPI;;;ihle-ifthe -;pplic~ntdo~s~~ ~e~a-ITwhi~SKi;- ;e-f~by ~cl;-MDAFW pu;;p.-Thefl~w~~te is-c~~-;ct. -----

i _______

~ ____________

~ ___ ~ ___________________________

~~ _____ ~ ____

~ _________ ~ _________________________ ~ ________ _

Answer B Discussion rCORRECT~- - --- - - --

--- - -----l L

I Answer C Discussion

[1,- -- -------- - -

,Incorrect. Plausible if the applicant does not recall which S/Gs are fed by each MDAFW pump. Also, the flowrate number is correct but it is total flow and not flowrate to each S/G.

L ________________________________ ~ ___________________________________________________________

~ ______. ___

~ _________________

~ _________

~ ____________

Answer 0 Discussion iln~o~e~t Th~S;G;-suppli~d ;~-~~~ect-~~ ili-; fl ~\\V~at~~~~ri;.;J~;;j u~is~~rr~~t b~t itis-t-;';-t;;j fl~w-;:-ate;nd;;tflo~r_;;_t~-t~;;_~~h-S!G.- --- -- - -

______. ____..J r-~~~ t...e... e,1 I

RO L __________ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Question Source 2006 NRC Q21 (CNS NRC Bank 98)

~!v:!~e~~nl~~~~~=-===-===_~= =-==-

1~~~eE! ~]e!e~~~ ~~'{I~e..cJ ____ _

ILesson Plan OP-MC-CF-CA Objectives 4, 7, & 8 page I

113 I

I 1

I, 1

I I

1 I

L ____________________.__

401*9 Comments RESPONSE Question considered SAT for submittal, no changes

- ---- --- - --~ - --- - -- -- - --- ---- '---,,--- -.- - -.'-'- -.-- ------.---.- --.. - ------ ------ - --.--- ------- ---------- --.- ---------- ---

!uestionBank,IKA_system IKA_number 1 ~KA_desc

--._------ -:+--- --~- -.~ -------- -- - -

- _._-- -----_._- ------.- ---~ ---- --.- _._---_._--- -_._----- -- ~------ -- ~---------

_______ I ~2~!~v..S~6~ ___ J~I... 0~________.' _J 1~~~~~e:r9 ~f;~e7~~y:~~;~~~~~e~~~:~and/or cause-effect relationships between the AFW and the following systems: (CFR:

I' _______. _____. ________. ________. _________. ____. ____.. _____________. _____________. __ _

Tuesday, November 10, 2009 Page 50 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 20 General Discussion

[Th~ Tu7bi~~Dr~~n -CAp;mp i; tripp~d. IfTt-~~r~~~~git;o~ldfued ~I4 S/G-;.I ACA-~;;p-n-;;-~~lyfu~~-S/G-;lA-~d-1 B~IBCXP~;-p~~~alIy-f;;dsS/G;-IC~d-w~Withthe--

Iloss of power to Emergency Bus lETA, the IA CA Pump will not be running. Therefore, only IB CA Pump will be running feeding IC and 1D S/Gs.

'I lEach motor driven CA Pump is capable of supplying two S/Gs at a design total flow rate of 450 GPM.

I iThe KIA is matched because the applicant must know both the physical connections (i.e. which S/Gs are fed by which CA pumps) and the cause-effect relationship (i.e. the effect of the TD iCA pump and 2ETA lockout) as a result of the malfunctions related to the CA system.

I

[This is a comprehension level question because the applicant must associate mUlitple pieces of information, some given and some recalled from memory. First, the candidate must recall that Iwith Emergency Bus lETA locked out, the IA MDAFW pump will be unavailable. The candidate must then recall which S/Gs are fed from each MDAFW pump. The applicant must also

~ec~II~hat_t~ !"a~dJl()~ f()r_th~!v1p~~~EUl"I1£s_ ~__ ___ __ __ ___ _ _______ ___ __ _ ___ ______________ __ _____ ______ ~ __________ _

Answer A Discussion iI;~rr~clPI;;;ihle-ifthe -;pplic~ntdo~s~~ ~e~a-ITwhi~SKi;- ;e-f~by ~cl;-MDAFW pu;;p.-Thefl~w~~te is-c~~_;ct. ---------- - ---- ----- - - - ------- -

i _______

~ ____________

~ ___ ~ _____________________________

~~ _____ ~ ____

~ _________ ~ _________________________ ~ __________________________________ ~_

Answer B Discussion rCORRECT~- - --- - - -

- -------- --- -- - -- - - --- - - --- -- -- ----- ----------------- -- - -- ---------- ---------- - -- ---l L

Answer C Discussion

[1,- -- -------- - -

r~c~rr~~.!~~i~le_ i!' t~~PJ~i~~t~~s_~~r:clll~\\Vhic~ S/Ci.s !r:!~d by !£IC~ ~l.)~F~Y~l1"lp.. ~1~00~eE.Cl.w~a~e~u_1l1~~ ~~orr~~b~t ~t ~s ~~~f1()\\~,_'~Ild_~t~.Cl.\\\\'fil:e~o_e~c~ ~Ci* ______ I Answer 0 Discussion iln~o~e~t Th~S;G;-suppli~d;~-~~~ect-~~th-; fl~\\V~at~~~~ri;.;J~;;ju~is~~rr~~t b~titis-t_;;_t;;j fl~w_;:_ate;nd;;tflo~r_;;_t~-t~;;_~~h-S!G.- --- -- - - --- ------ -- - - - ------(

c ________________________________________________________________________________________________________________ ~ ____ __.J

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Comprehension L ___________ ----.l ___________________ _

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QuestlonType

• Question Source

-- - BANK-- - --------2006NRCQ2I (CNS NREB~;k 98) - ------- --

____ ~ ________..1 _______________________________________________ _

~ Developed

~!v:!~e~~nl~~~~~=-===-===-~= =-==- IStude-;;t Refe~-ncespf('-;ided-- - -

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~ OPT Approved

~ OPS Approved

~ NRC Approved ILesson Plan OP-MC-CF-CA Objectives 4, 7, & 8 page 113 I

1 i l _____ _

I I

I 1

401*9 Comments RESPONSE Question considered SAT for submittal, no changes

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Tuesday, November 10, 2009 Page 50 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 20 B

'uesday, November 10, 2009 Page 51 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 20 B

'uesday, November 10, 2009 Page 51 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 2]

C

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~ ___ ~~~~ _J __ ~Y~~~~J ______ ~4}~ ____ J IKno~Iedg~ of ac distribution system design feature(s) and/or interJock(s) which provide for the following: (CFR:

j~*22':::1~n!.ll!el1:lIJ:lta~~1l(;J)()v,'e~.CJtJI:(;es __ -.:............ :......-.:............... :-.._~ __ ~ ~ __________ ~ ________ ~. ___ _

CURRENT 45 DAY VERSION Given the following conditions:

The loads supplied by Static Inverter 1KU are being supplied by their alternate power source due to an automatic transfer on low inverter output voltage.

Which ONE (1) of the following describes the response of the Auxiliary Control Power system when inverter voltage is restored to normal?

A.

B.

C.

D.

No response, loads must be manually restored to the inverter.

No response, the altemate power source must be deenergized and the loads will then auto swap back to the inverter.

Loads will auto swap back to the inverter if the inverter voltage remains stable for 30 seconds.

Loads will auto swap back to the inverter as soon as inverter overcurrent is detected to be less than 120%.

062K4.1O Given the following conditions:

The loads supplied by Static Inverter 1 KU are being supplied by their alternate power source due to an automatic transfer on low inverter output voltage.

Which ONE (1) of the following describes the response of the Auxiliary Control Power system when inverter voltage is restored to normal?

A.

B.

C.

D.

No response, loads must be manually restored to the inverter.

No response, the alternate power source must be deenergized and the loads will then auto swap back to the inverter.

Loads will auto swap back to the inverter if the inverter voltage remains stable for 30 seconds.

Loads will auto swap back to the inverter as soon as inverter voltage returns to normal.

401-9 Comments:

Need boundary for D. As written, D could be potentially correct since if it takes 30 s or so to return to normal. Suggestion for D:

"uesday, November 10, 2009 Loads will auto swap back to the inverter as soon as inverter over current is detected to be less than 120%

RFA 10/27/09 Page 52 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE C

2009 RO NRC Retake Examination QUESTION 21

~~~j~f!~IT~~ji~~'!!=-~t<!':nu~~~====J ~:~~~==~==========~_=======-==;-=====;==.=====_======== __ ~ ______ _

[ ___ ~~~_~J_~~Y~~~_J ____ ~_K4}~ ____ JI~I~~~~~!~n~::~p~~~~!b::i;~;~:t:~r~:~ig~.:~:.~.~~.:~~.~~::.~::o~~~s~~~c~~:~~f:r~~_~~~~~:_(~_~ ______ ~ __

L ________ ~ __________________________ _

CURRENT Given the following conditions:

The loads supplied by Static Inverter 1KU are being supplied by their alternate power source due to an automatic transfer on low inverter output voltage.

Which ONE (1) of the following describes the response of the Auxiliary Control Power system when inverter voltage is restored to normal?

A.

B.

C.

D.

No response, loads must be manually restored to the inverter.

No response, the altemate power source must be deenergized and the loads will then auto swap back to the inverter.

Loads will auto swap back to the inverter if the inverter voltage remains stable for 30 seconds.

Loads will auto swap back to the inverter as soon as inverter overcurrent is detected to be less than 120%.

062K4.1O 45 DAY VERSION Given the following conditions:

The loads supplied by Static Inverter 1 KU are being supplied by their alternate power source due to an automatic transfer on low inverter output voltage.

Which ONE (1) of the following describes the response of the Auxiliary Control Power system when inverter voltage is restored to normal?

A.

B.

C.

D.

No response, loads must be manually restored to the inverter.

No response, the altemate power source must be deenergized and the loads will then auto swap back to the inverter.

Loads will auto swap back to the inverter if the inverter voltage remains stable for 30 seconds.

Loads will auto swap back to the inverter as soon as inverter voltage returns to normal.

401-9 Comments:

Need boundary for D. As written, D could be potentially correct since if it takes 30 s or so to return to normal. Suggestion for D:

"uesday, November 10, 2009 Loads will auto swap back to the inverter as soon as inverter over current is detected to be less than 120%

RFA 10/27/09 Page 52 of 185

FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 21 General Discussion

,-~ -~------~~-

---

~~-~--

-~ -

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---

~-~-----~-------~----------------- ---I IThe static automatic transfer switch will automatically swap auxiliary control power from its alternate source back to the inverter is the condition that caused the auto-swap has cleared (in this I

!case low voltage) and conditions are stable for 30 seconds.

I I

!ThiS KA is met because the applicant must understand the system design features which provide for automatic transfer of auxiliary control power from its normal source (static inverter) to its!

1~~k-':lp_s~lIrce~~d~~e_v~~a. ______ ~~_~ __ ~ ____ ~_~~ __ ~ ___ ~~ ______ ~ __ ~ ~ _______ ~ _____ ~~ _______________________ ~~:

Answer A Discussion lI~c~~ct.-Pht~ibl~bt;~~s~ ~~o;~ ~~e~l-;;ads-~u;t be-~~u-;;:liy tran;f;rr~d-b;clc to the;; ~o~al p-o;e-;:~upply.

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___. ____ ~ ______________________________________

~ ____

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~ __

~ _____ _

Answer B Discussion I* --~~.~-~--.----- ---- - -

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LIn_ correct. Plausible because loads will automatically transfer back to normal power supply. However, the alternate source does not have to be de-energized to cause this to happen.

I

~ __

~ _____. ____________

~ __________

~ __

~ ____________________

~ ____. ________________

~

_________________________________________________________ -l Answer C Discussion

~§~!:~f*~ ~_ ~~_-~_-~~~~~~~~_-~-_-__ -_-=-~~-~ _-~_-_-_-_-_~~ __

Answer 0 Discussion

_ C_ogll,!I~e.. ':e'i!'_

Memory 9~!S~I()F!.l)t~e~= ~ =

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~==_-= =~=_=I 401-9 Comments RESP~SE

_ __ ~~N_K ____ L __________ ~~

~llIl~<!.u~~i~n_E~~!~3~ _______ ~ _~J ~~;~~:~r~I::~~=~~~;~~;.h;;~F 11103/09

~ Developed

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~ OPS Approved

~ NRC Approved r---- - ---

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--.J 14 1.7)0 Uninterruptable ac power sources L ___ ~ ________. _____ ~~ ___ ~ ___ ~ __ _

ruesday, November 10, 2009 Page 53 of 185 FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 21 General Discussion

,-~ -~------~~-

---

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~-~-----~-------~----------------- ---I IThe static automatic transfer switch will automatically swap auxiliary control power from its alternate source back to the inverter is the condition that caused the auto-swap has cleared (in this I

!case low voltage) and conditions are stable for 30 seconds.

I I

!ThiS KA is met because the applicant must understand the system design features which provide for automatic transfer of auxiliary control power from its normal source (static inverter) to its!

1~~k-':lp_s~lIrce~~d~~e_v~~a. ______ ~~_~ __ ~ ____ ~_~~ __ ~ ___ ~~ ______ ~ __ ~ ~ _______ ~ _____ ~~ _______________________ ~~:

Answer A Discussion lI~c~~ct.-Pht~ibl~bt;~~s~ ~~o;~~~e~l-;;ads-~u;t be-~~u-;;:liy tran;f;rr~d-b;clc tothe;;~o~al p-o;e-;:~upPlY------------- -----~- ---~----- ---~- ~--~~--~-:

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________ ~___ ___ _ __ _ _________

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~ ________ 1 Answer B Discussion 1

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-~ ----- -I IIncorrect. Plausible because the loads will automatically transfer back to the inverter. However it is based on voltage and not on overcurrent.

I 1_-

- ~~og~I!I~~~!I~==-~9~!sjl()rt.l)t~~~~ = ===--=====-====g-~!t~~~~~rc;=======-=-=====1 401-9 Comments RESPONSE

~ ____ Mem~f.)' __ ~ __ 1 ___ ~~N_K ____ L __________ ~~

~llIl~<?u~~i~n_E~~!~3~ _______ ~ _~J Changed Distractor 'D' per Chief

~ Developed

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~ OPS Approved

~ NRC Approved Examiner's recommendation. HCF 11103/09

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IDevelopment References

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L41 :DJJ'yllIlltt~n*u£tll~e~~J~o~er~~.'"(;t:S _............................. =..... ___ ~~~ ____. ____ ~ ______ ~ ______ ~

ruesday, November 10, 2009 Page 53 of 185

c FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 22

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SYS063 I

K2.01

• IIKnowledge of bus power supplies to the following: (CFR: 41.7)CIMajor DC loads

-.l ___ ~ ________ L __________________ L

~_~ ________

~ _______

~ ____________________

~ _______

~ _________ ---------- ---

_.-----.- --I I

- ---- --- -----1

- - -- -.~.-~ -- ~I CURRENT 45 DAY VERSION Which ONE (1) of the following receives power from 250VDC Auxiliary Power System?

Which ONE (1) of the following receives power from 250VDC Auxiliary Power System?

A.

DIG Fuel Oil Booster Pump A.

DIG Fuel Oil Booster Pump AND FWPT "A" Emergency Oil Pump B.

C.

D, B.

Reactor Trip Switchgear Control FWPT "A" Emergency Oil Pump(s) AND Reactor Trip Switchgear Control C.

Turbine Emergency Bearing Oil Pump Turbine Emergency Bearing Oil Pump AND Turbine Backup Vapor Extractor Turbine Emergency Bearing Oil Pump AND DIG Fuel Oil Booster Pump D,

Power Operated Relief Valves Solenoids (both NC and SV systems) 401-9 Comments:

063K2.01 This Q has low DV, Suggested fix:

A. DIG Fuel Oil Booster Pump and FWPT A Emergency Oil Pump(s)

B. FWPT A Emergency Oil Pump(s) and Reactor Trip Switchgear Control C. Turbine Emergency Bearing Oil Pump and Turbine Backup Vapor Extractor(s)

D, Turbine Emergency Bearing Oil Pump and DIG Fuel Oil Booster Pump

'uesday, November 10, 2009 Page 54 of 185 c

FOR REVIEW ONLY - DO NO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 22

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.. ~.: __ :~~:-' ___ ' _____ ~_~_~~I CURRENT 45 DAY VERSION Which ONE (1) of the following receives power from 250VDC Auxiliary Power System?

Which ONE (1) of the following receives power from 250VDC Auxiliary Power System?

A.

DIG Fuel Oil Booster Pump A.

DIG Fuel Oil Booster Pump AND FWPT "A" Emergency Oil Pump B.

Reactor Trip Switchgear Control B.

FWPT "A" Emergency Oil Pump(s) AND Reactor Trip Switchgear Control C.

Turbine Emergency Bearing Oil Pump C.

Turbine Emergency Bearing Oil Pump AND Turbine Backup Vapor Extractor D.

Turbine Emergency Bearing Oil Pump AND DIG Fuel Oil Booster Pump D.

Power Operated Relief Valves Solenoids (both NC and SV systems) 401-9 Comments:

063K2.01 This Q has low DV. Suggested fix:

A. DIG Fuel Oil Booster Pump and FWPT A Emergency Oil Pump(s)

B. FWPT A Emergency Oil Pump(s) and Reactor Trip Switchgear Control C. Turbine Emergency Bearing Oil Pump and Turbine Backup Vapor Extractor(s)

D. Turbine Emergency Bearing Oil Pump and DIG Fuel Oil Booster Pump

'uesday, November 10, 2009 Page 54 of 185

FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 22 This Q is U because General Discussion 1.-'--'---"- -~-- -,--,----,---- ---,,---- -"--'-'-'-'--- ---- ---,----- --------,-,----,----------- -------

IAII loads are DC loads, DIG booster pump comes from IDGDA. And rx trip switchgear and PORVs come from 125VDC vital LiThe KIA is matched because the applicant is required to know and differentiate from memory the power supplies to major DC component~ _________________ _

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

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

Answer A Discussion rI~~~e;t~Pi~~bl~-be~~s~it"i~ ~upPl~d by -riC-p~~e~.--- - ---

i ______. _________

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~llc~~e~t~~I;:IU~~I~b_e~alls_=~!S supplied by DC power.

Answer C Discussion

~~~c'f~ =~=====~=== ____________ _

Answ.r 0 Discussion c---'--- -,-----,------------- -,--,---- ---,-,-- -------

IIncorrect. Plausible because it is supplied by DC power.

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Memory L. __ ________ ---.l _______ ____ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved MODIFIED I

2008 CNS NRC Q48 (Bank 554)

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~!ei~~~n! ~!fere~~es=~=====_ _____

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______ J 401-9 Comments RESPONSE Question revised to add mUltiple choices for each answer per Ron's suggestion.

Should be good to go.

---

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1822[SYS063 IK2.01

[ [Knowledge of bus power supplies to the following: (CFR: 41.7)CM~ior DC loads

~ ___ _ L ________ ____ ----.l ____________

~ _____

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~ _________________ -_ -_" ________________________________

~ ________ ~~

____ J fuesday, November 10, 2009 Page 55 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 22 This Q is U because General Discussion 1.-'- -,-- -,,- -~-- -,--,-- --,---- ---,,---- -"--'-'-'-'--- ---- -

IAII loads are DC loads, DIG booster pump comes from IDGDA. And rx trip switchgear and PORVs come from 125VDC vital I

bE~ ~

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Answer C Discussion

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Answ.r 0 Discussion

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i Job-Leve,-1 ---CognitIVe ievel--

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QuestlonType-T--- -------- ----Que;tion-So~ree------------ --

401-9 Comments RESPONSE MODIFIED--l-- - --------2008CNSNRCQ48(B;~k554)---

Question revised to add mUltiple choices I

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Memory L~ _______, __ ---.l ___ ~ _____________ _

- -- -- -- _-L _______ ------- - -- -- --,---- ---

for each answer per Ron's suggestion.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IOevelopm;rli Reterences--------

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40%. A (1) 225 - 235 PSIG (2) 10 seconds B. (1) 210-225PSIG (2) 10 seconds C. (1) 225 - 235 PSIG (2) 20 seconds D. (1) 210-225 PSIG (2) 20 seconds 064A3.01 Move the WOOTF statement to the top. 45 DAY VERSION The Diesel Generator Starting Air compressors are designed to automatically maintain the Starting Air Header pressure between (1) . During an automatic start of the Diesel Generator, the Starting Air solenoid will open to supply the diesel for ~ or until Diesel Generator speed is >40%. Which ONE (1) of the following correctly completes the statement above? A (1) 225 - 235 PSIG (2) 10 seconds B. (1) 220-250PSIG (2) 10 seconds C. (1) 225 - 235 PSIG (2) 20 seconds D. (1) 220 - 250 PSIG (2) 20 seconds 401-9 Comments: CAF: Look at A I and C I and make sure that they are not subsets of B I and D I because 235 psig is between both choices. You might consider using an actual value where the limits have to be applied instead. RFA 10/27/09 ruesday, November 10, 2009 Page 56 of 185 FOR REVIEW ONLY - DO C DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 23 r~~=c!!8~========~=======================-=====-_=-=-=-_==-============~===_========_~_ [Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7 1 45.5)i~Automatic start of compressor and ED/G 1- ---- -----'~---------'-r.-----~--------- f9~esti~n~E!~n!<~j!<!-=~}'!f.!~- ~~",",~~f!!~er ____ _ I I 1823 I SYS064 I A3.01 l,_ ~ _________ ~ _~ ________ ~L~ __, __, __ ' __ _ L:.. *.-:,.. *.. *.-:.. ~ ~ __ ~ ~ __________ ~ ____, _______________, _____ ~_~ ________ _ CURRENT Which ONE (1) of the following correctly completes the statement below? The Diesel Generator Starting Air compressors are designed to automatically maintain the Starting Air Header pressure between (1) . During an automatic start of the Diesel Generator, the Starting Air solenoid will open to supply the diesel for ~ or until Diesel Generator speed is >40%. A (1 ) 225 - 235 PSIG (2) 10 seconds B. (1) 210-225PSIG (2) 10 seconds C. (1) 225 - 235 PSIG (2) 20 seconds D. (1) 210-225 PSIG (2) 20 seconds 064A3.01 Move the WOOTF statement to the top. 45 DAY VERSION The Diesel Generator Starting Air compressors are designed to automatically maintain the Starting Air Header pressure between (1) . During an automatic start of the Diesel Generator, the Starting Air solenoid will open to supply the diesel for (2) or until Diesel Generator speed is >40%. Which ONE (1) of the following correctly completes the statement above? A (1) 225 - 235 PSIG (2) 10 seconds B. (1) 220-250PSIG (2) 10 seconds C. (1) 225 - 235 PSIG (2) 20 seconds D. (1) 220 - 250 PSIG (2) 20 seconds 401-9 Comments: CAF: Look at A I and C I and make sure that they are not subsets of B I and D I because 235 psig is between both choices. You might consider using an actual value where the limits have to be applied instead. RFA 10/27/09 ruesday, November 10, 2009 Page 56 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 23 c General Discussion iih~ Di~clG~n~r~~~St;rtingAj;:-Zo~pr;'~r~~ill ~ut~;tkilly c;cle-t~ ;ainta;the start~g-aTrh~ct;;~s-pr~s;uri~;d~b~t;~;i25-235-p-;ig:Whe-;; th~ Di~sel G;~~~-;;~;n ~~to-start Isignal, four starting air solenoids open to supply the diesel for 20 seconds or until Diesel Generator speed is greater than 40%. I iThe KIA is matched because in order to monitor the automatic operation of the EDG starting air comperssors and the automatic operation of the EDG, the applicant must know the setpoints at ['which the EDG starting air compressor will automatically start and stop and must know the amount of time the EDG starting air solenoids will remain open on an auto start. ~~---,----.---~------.---~---------------------~--------.------------------~-~---------------------~------~------------- Answer A Discussion I~- --~- ~~-- ~-~

---

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~nco_rr~c~ !3~t~p~rts ~n~o~~c: ~1~lIsi~le_i~t~e~!)jJ~c!n~ ~o~_~~ I"e:.a~ ~i~~I1lp.l"e.:'()r ~~~s~~o~t~.: ~h~t~~=_I~ellel_a~rt>~r=_s.tl~~e~s~aJii~~~:

Answer C Discussion

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Answer 0 Discussion 10~~~t!2r~~~ I~~~~~c~ ~e~~_~~~~~tI~~ ls~~~~E~~~I~~~~

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RO I

Memory L_~ _________ ~_J ____._~~ ____

~ __

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

~*1 Per Chief Examiner's suggestion, changed

_~ __ ~ ______ ~ __ ~J Bl andDl to 235-250PSIG so that Al and

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved roev-e/opme,rt References - - ~ -

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ILesson Plan OP-MC-DG-DGA Objective 5 page 25 and

[Objective 8 page 31 I

I I L_

I __ ~~_ -----~~-~~-~- ----~~--- Cl would not be a subset ofBl and Dl.

IStudent References Provided HCF 11103/09 r----~~ -

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--~-- ----j ~-- ~---- ----------~- ~----~- -----------~-~-~-~--~---~---~~~~--~-~-~-~--- -~~~~--- ---~----j

~ _______ 1~2~~~S_0~4 ~ ~_t~*~I _________ ~ J ~~~~ty~~:.=::~:~~~~.=~t~~~e~a~on_of~~e_~~G::t~: ~~I~~~~:~~~:_~1 ~~45~~~:~u:~~~:~~~mpressor and Tuesday, November 10, 2009 Page 57 of 185 FOR REVIEW ONLY - DO T DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 23 General Discussion iih~ Di~clG~n~r~~~St;rtingAj;:-Zo~pr;'~r~~ill ~ut~;tkilly c;cle-t~ ;ainta;the start~g-aTrh~ct;;~s-pr~s;uri~;d~b~t;~;i25-235-p-;ig:Whe-;; th~ Di~sel G;~~~-;;~;n

~~to-start Isignal, four starting air solenoids open to supply the diesel for 20 seconds or until Diesel Generator speed is greater than 40%.

I iThe KIA is matched because in order to monitor the automatic operation of the EDG starting air comperssors and the automatic operation of the EDG, the applicant must know the setpoints at

~~i~~h~~e_EI2Q~~~n~ ilir~~~lI~p-,"e~()I"~ill ~lIt()J11~t~~I~ ~tal"t1ll1i.s!<P~~ 11111S~ ~()w~t~e ~~~t

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Answer A Discussion 1--- -~--- ----

---~------------------ "-- -

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

---

~--- --l IIncorrect. Pressure is correct. Second part is plausible if applicant does not recall the amount of time air is supplied to the diesel.

I

~ ___._

• ___

________ ~ ___________

.~ _____

~ __________________

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~ ______ -----_.-.------ ______

1 Answer B Discussion I--~--~~~-

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Answer 0 Discussion 10~~~t!2r~~~ I~~~~~c~ ~e~~_~~~~~tI~~ ls~~~~E~~~I~~~~ ri~i~<00~e~ ~~~~c~~~ ~~IllP~e~~ ~U; ?~~.~=== =~~ =~=_==-=-~==~== =_-=~=~_~=-

r-Job-Level -r -~ Cognitive Le-;ei-QuestlonType -r -- -~ ---------~

Questlon-S-~urC; - - ---- - ~ ~- -- ~ l 401-9 Comments RESPONSE 1- -- ~--~~- - -t-- - - - ~--~-~---~---~-~-+-~---~~--~-~- -I-~-~-~~-~-- - ~~--------~-~~-~~~~~--~--~-- --~ ~~

-~--- --1 I

RO 1

Memory 1

NEW I

. Per Chief Examiner's suggestion, changed L ___ ~~ ______ L _____ -

- ----- ~~-~--~--- --- -~~ - ---- -- -------- ---------~~- -~- -~--- _______ J Bl and Dl to 235-250 PSIG so that Al and

~ Developed

~ OPT Approved

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~ NRC Approved Tuesday, November 10, 2009 ro;v~Topm;nt References -- ~ -

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ILesson Plan OP-MC-DG-DGA Objective 5 page 25 and

[Objective 8 page 31 I

I I L ___ ~~_~ ___ ~~ ___ ~ ________

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L_~ _________ ~_ ~_~ __

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Page 57 of 185 C 1 would not be a subset of B I and D I.

HCF 11103/09

FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 24

~~stio~~~~!_~=si~i~=~~~w~_~===~ ~~~!c====~=========-===========================-============~=

[.. 1824

. J SYS064 I

. K6.08

.. I [Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 1 45.7)~]Fuel oil L_ ------ -

---

______ c :sto~a~e_t1lI1k~o..::_._:._:.:...:_.._:..._::.-:~.-.:...._::.-:~:.-.:_._~_o ________

0 _________________

0 _______________

CURRENT The following on Unit 1:

A unisolable leak develops on the 1A Fuel Oil Storage Tank (FOST)

At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 1A FOST level is 41,250 gal At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> 1A FOST level is 40,000 gal Assuming the leak rate from the FOST remains constant, when is the EARLIEST time that 1A DIG will fail to meet the LCO requirements for TS 3.8.3 (Diesel Fuel Oil and Starting Air)?

REFERENCE PROVIDED A.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> B.

1136 hours0.0131 days <br />0.316 hours <br />0.00188 weeks <br />4.32248e-4 months <br /> C.

1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br /> D.

2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> 064K608 45 DAY VERSION The following on Unit 1:

A unisolable leak develops on the 1A Fuel Oil Storage Tank (FOST)

At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 1A FOST level is 41,250 gal At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> 1A FOST level is 40,000 gal Assuming the leak rate from the FOST remains constant, when will the 1A DIG fail to meet the LCO requirements for TS 3.8.3 and what action is required?

REFERENCE PROVIDED A.

0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> Immediately declare the associated DG inoperable B.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> Immediately declare the associated DG inoperable C.

0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> Restore fuel oil level to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> Restore fuel oil level to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 401-9 Comments:

Since refis provided, and there is no mention of problems with DG starting air, the second part of A and Bare NP. Why not change to 7 days and put a particulate bullet in the stem that is within the limits.

ruesday, November 10, 2009 Unless I am missing something, this Q is U because of2 NP distracters.

RFA 10/27/09 Page 58 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 24 A

I ~-~~~-

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~~-~--r_--~~--~-~--~I.: ----~--~-~----~-

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[

1824 I

SYS064 I

K6.08 IIKnowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 1 45.7)~]Fuel oil L_~~ ___ ~_~~_~~_~ __ ~~ ___ ~ ___ ~ _~_~_~c :sto~a~e~t1lI1k~.~~~.~~.~:-:~~.~:-:~~.~~_. ____ ~ ___.~ __ ~ ___ ~ ____ ~ __.~._~ ___ ~ ___ ~~~ ___ ~

CURRENT 45 DAY VERSION The following on Unit 1:

A unisolable leak develops on the 1A Fuel Oil Storage Tank (FOST)

At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 1A FOST level is 41,250 gal At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> 1A FOST level is 40,000 gal Assuming the leak rate from the FOST remains constant, when is the EARLIEST time that 1A DIG will fail to meet the LCO requirements for TS 3.8.3 (Diesel Fuel Oil and Starting Air)?

REFERENCE PROVIDED A.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> B.

1136 hours0.0131 days <br />0.316 hours <br />0.00188 weeks <br />4.32248e-4 months <br /> C.

1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br /> D.

2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> 064K608 The following on Unit 1:

A unisolable leak develops on the 1A Fuel Oil Storage Tank (FOST)

At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 1A FOST level is 41,250 gal At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> 1A FOST level is 40,000 gal Assuming the leak rate from the FOST remains constant, when will the 1A DIG fail to meet the LCO requirements for TS 3.8.3 and what action is required?

REFERENCE PROVIDED A.

0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> Immediately declare the associated DG inoperable B.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> Immediately declare the associated DG inoperable C.

0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> Restore fuel oil level to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D.

1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> Restore fuel oil level to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 401-9 Comments:

Since refis provided, and there is no mention of problems with DG starting air, the second part of A and Bare NP. Why not change to 7 days and put a particulate bullet in the stem that is within the limits.

ruesday, November 10, 2009 Unless I am missing something, this Q is U because of2 NP distracters.

RFA 10/27/09 Page 58 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 24 A

General DIscussion r::

~~~,,~,~,~ ~~,~,~~-~----~-,-~~~-,~,~- -,-

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lIn accordance with Tech Spec 3.8.3 Diesel FOST level must be >/= 39500 gal. IfFOST is <39500 gal but >31600 gal a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> LCO is entered to refill the FOST.

i I IThe leak rate from the tank = (41250 - 40000) / 90 = 13.89 GPM iLCO 3.8.3 Condition A will be entered when FOST decreases to less than 39,500 gal. With a 13.89 gpm leak rate it will take approximately 36 minutes for FOST level to reach 39500 gal.

I

\\(40000 - 39500 gal) /13.89 gpm = 36 min.

I 136 min from 0930 would be 1006.

I iThe FOST leak will eventually lead to a condition where FOST level will place the unit in an LCO condition. Therefore, the KJ A is matched.

I

[This is an analysis level question because the applicant must evaluate Tech Specs to determine the level at which the Diesel Generator operability will be effected, then calculate a leak rate,

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Answer A Discussion

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Answer B Discussion IIncorrect. Plausible if the applicant uses the change in level from 41250 to 39500 gal and the correct leak rate but starts at correct time of 0930. This would yield the time given.

l __

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Answer C Dlscusalon

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Incorrect. Plausible if the applicant believes that LCO requirements are not met until the low level of 31600 gal is reached. The time given is correct using the correct leak rate.

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

Answer D Discussion r--

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[Incorrect. Plausible if applicant believes LCO requirements not met until 3 1600 gal level is reached. Using the difference between 412500 and 3 1600 gal with the correct leak rate from 0930 I 1!1~lIr~\\ViIIl'(~i~d!l1is,tl~e~ ~~ ~ __ ~_~,~~_ ~ __ ~ ___ ~~~, __ ~~_~~~_ ~_~ ~ __ ~~~~ __ ~_~ __ ~_~ ~~~ ___ ~_~~_~~, ~_~_,~~~_,,~, __ ~~~_ ~_~_,_~_,_ ~ J COgnltl~e~Levet~

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iTechnical Specification 3.8.3, Diesel Fuel Oil and

[Starting Air iLesson Plan OP-MC-DG-DGA page 65 I

I L _________________

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401-9 Comments RESPONSE Changed question such that "Immediately declare the DG inoperable" is plausible.

HCF 11103/09

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]Knowledge of the effect ofa loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/ 45.7)CJFuel oil

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fuesday, November 10, 2009 Page 59 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 24 A

General DIscussion r::

~~~,,~,~,~ ~~,~,~~-~----~-,-~~~-,~,~- -,-

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lIn accordance with Tech Spec 3.8.3 Diesel FOST level must be >/= 39500 gal. IfFOST is <39500 gal but >31600 gal a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> LCO is entered to refill the FOST.

i I IThe leak rate from the tank = (41250 - 40000) / 90 = 13.89 GPM iLCO 3.8.3 Condition A will be entered when FOST decreases to less than 39,500 gal. With a 13.89 gpm leak rate it will take approximately 36 minutes for FOST level to reach 39500 gal.

I

\\(40000 - 39500 gal) /13.89 gpm = 36 min.

I 136 min from 0930 would be 1006.

I iThe FOST leak will eventually lead to a condition where FOST level will place the unit in an LCO condition. Therefore, the KJ A is matched.

I

[This is an analysis level question because the applicant must evaluate Tech Specs to determine the level at which the Diesel Generator operability will be effected, then calculate a leak rate,

~d~ \\)a~~d_o~ ~h~ ~~~rllt~~~~fI11iI1~ tl1~t~llle~ <t! ~hi~~Dj~~ 9~lle~<t!()f~~e~(l\\)~i!Y_ \\\\'iD,\\)~~ff~0:~~a~~t!l~<lC0~~~~

must~~~alceE~~~_~~ ~_~ ~ ~ ~~,_ ~~ _~~ ~ _~~~ ~~ ~

Answer A Discussion

~~o~~§f~~~-_~~_~~~~~~~~~~~_-~-~~~~~~_~~~~_~_~~~ ___ ~~~,=-_~~~ __ -_~~=-~~~~~_~~~~~~~~-~_-_~ ___ ~ __ -_-~~-~~~~~_~~ ____ -________ -_~ _____ -~ __________________________ ~ ____ ~~~~

~n~s~~E! Pl~~~!I~f!~_,_~~ ~~_ ~~_~~~~ _ ~_~_~~~ ~~ __ ~~_~ ~~~_~ __ ~~ __ ~~~_~ __ ~_~~~~ ~ _~ ____ ~~~~ ~~~_~~ __ ~~~ _~~~ _~ ~~~

~~~01T~c~.!~all~~I~~tl1=-ap£I~~aI1t~u~e~~~~h~~~~~ le~~fI-~~ ~1~~0 ~~~~~~~a-'~n~~~~,orr~~ l~a~~~t~~u~~aI*t~llt ~~~~~il11~ ~_?~3~ ~~~~w~~I~~i~~~~~il11=- ~i~e~~_,~

Answer C Olscusalon

~~~~~~~t.~I~~~i~;Fth~j~~i~~~~~~~i~~~~-llt~L§<:)!~~~;~!~~~~~~-~~~~~~~I~~~~~~~~~~~~~g~l~isX~~~~~T~~~~ji~~~-~~i~~~~i§~~~~~~~~~t:~~~~~~ __ -~-

Answer D Discussion r--

~~~~,-

~,~-~---,~~

-~,--~-

-~---~-~~~~-,-,-~,--~~~,~,-,~--~,- -'-'-

--,--~

~

-,-~

-,~,- -

~-~

--,~~-~-~-

-,~--~~~

-~~,--,~~-,~- -,-

-~~--~-:-l

[Incorrect. Plausible if applicant believes LCO requirements not met until 3 1600 gal level is reached. Using the difference between 412500 and 3 1600 gal with the correct leak rate from 0930 I 1!1()lIr~\\Vi-'Il'(~i~d!l1is,tl~e~ __ ~ _____,~~_ ~ ____ " ~~~, __ ~~_~~~_ ~ _____ ~~~~ ____ ~ __ ~_~ __ ~ ___ ~_~~_~_, ~_~_,~_~_,,_, __ ~~~_ ~ ___,_~_,_ ~ J

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestlonType-T- -~~~--~- -~ ~--~-Questio~Sou-rCe~ --~---~

~ - --~-~+- -,-,~-,- ~~,- ~~,-,---,~---,- ~~

-,--~~ -

-,-,--~,~,~- ~ -'-,-

NEW i

-' ~~~ ~,~-~-- ~~~-~--~~~,~~ -,~,--,~~-~----,~~,~ ~ ---~,--~ -~~,~,-"-~

Io;velo~pme-nt Reien;nc;s-'~--

I,-~ -

-~-~,-,-~~~,,--~-~--~- -'- - -~~-~~---

iTechnical Specification 3.8.3, Diesel Fuel Oil and

[Starting Air iLesson Plan OP-MC-DG-DGA page 65 I

I L _________________

~ ___________________. __

'-~'~"-~~~'-

~~,-,~--,--

~~

-,-,~- "-

IStudent References Provided r;;~~~~-

--~ --~,~-~--~-~-

--~-

ITech Spec 3.8.3 (Q24)

I I

I I L __,~ __,_~ ~,,_~_~_,,_~ ___ ~~,,~

401-9 Comments RESPONSE Changed question such that "Immediately declare the DG inoperable" is plausible.

HCF 11l03/09

'--~~-'--~~-r-~~'~-

'--l~'~'-~'" - --

-~,--

luestlonBank # IKA system KA number 1'- ~,-,-~---~~--

-~~--- -

~-~-~,~

-,---,-~,-,~~,,--~,-~---,-,~~~-,---~~----

~

---

'~--~-~-,

~=-~!S~- -~_~ ___, '_, _,~~ __ ~~ ___, ____, ~~ ______ -----__ ~ - ~ _____ ~_ -_~ --~~-~~~-~,i

~~,-~-~,~,t-,~~-,-,---j~- =~ -, ~-,~~~,,~~

I 824!SYS064 IK6.08

__ ~_~_~,_,_ ~L _,_,_, _, __ J,, ___ ~_~ __,_, _~_,

]Knowledge of the effect ofa loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/ 45.7)CJFuel oil

!~t()r(l~e ~l<~~.. ~.~~.:-.~.~.. ~.:-.... ~:--:~.. ~.,.~.:-: ___ ~ ___ ~_

~, __ ~_ ~~ ___ ~ ___ ~ __ ~~_~ _~~ _________ ~

fuesday, November 10, 2009 Page 59 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 24 A

ruesday, November 10,2009 Page 60 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 24 A

ruesday, November 10,2009 Page 60 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 25 l'~~'~~~'~-~'-;-)-'~-~~-~~~-~---~ ~ ~ ~-

--~l

~~-~~-----~---~'--~'- - ------

--,-------,-----------~---~'--'-----

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

!QuestionBank # IKA_system IKA_number

,IKA_desc 1--- ~------ -J'-----~-~,~---r:__=-"-~------ -

~,-~~-! I"--'--'-~ - - -~-,---~--,--- -~--------- -- -,-, ~ --- -~~---- --:-'-----~ -,- -~--~--,--,~--

L~~ __ ~~~~ __ L _~~'S~~3 __ ~ ____ ~~~3 ____ J i~e~~~s!~a~~u~~~~.~:.~~~~~.~.~.~or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)CJCheck source for operability i ________

~_~ _____. ________

~

________ ~ __

~ ___

~ ________________ ~

~ ________ _

CURRENT While perform ing daily surveillance checks on 1 EMF -33 (Condenser Air Ejector Exhaust), you determine that the OPERATE light is OFF. The Control Room Supervisor asks you to perform an operability check of 1EMF-33.

Which ONE (1) of the following is required to be performed for this check per PT/1/A14600/0038 (Daily Surveillance Items)?

A.

8.

C.

D.

Have RP perform a setpoint check ONLY.

Have RP perform a source check ONLY.

Start the associated sample pump for this EMF AND have RP perform a setpoint check.

Start the associated sample pump for this EMF AND have RP perform a source check.

073A403 45 DAY VERSION While performing daily surveillance checks on 1 EMF-33 (Condenser Air Ejector Exhaust), you determine that the OPERATE light is OFF. The Control Room Supervisor asks you to perform an operability check of 1EMF-33.

Which ONE (1) of the following is required to be performed for this check per PT/1/A1460010038 (Daily Surveillance Items)?

A.

Have RP perform a setpoint check.

8.

Have RP perform a source check.

C.

Verify the sample pump is in operation.

D.

Verify the correct sample point is selected.

401-9 Comments:

In accordance with the reference, it appears that a source check is required not a setpoint check. Please re-verifY correct answer..

ruesday, November 10, 2009 The stem ask for a requirement. The word "Ensure" (distracters "C" and "D") are NOT "requirements". These two distracters will be immediately eliminated.

U because "C" and' D" are NP Page 61 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 25 CURRENT While perform ing daily surveillance checks on 1 EMF -33 (Condenser Air Ejector Exhaust), you determine that the OPERATE light is OFF. The Control Room Supervisor asks you to perform an operability check of 1EMF-33.

Which ONE (1) of the following is required to be performed for this check per PT/1/A14600/0038 (Daily Surveillance Items)?

A.

8.

C.

D.

Have RP perform a setpoint check ONLY.

Have RP perform a source check ONLY.

Start the associated sample pump for this EMF AND have RP perform a setpoint check.

Start the associated sample pump for this EMF AND have RP perform a source check.

073A403 45 DAY VERSION While performing daily surveillance checks on 1 EMF-33 (Condenser Air Ejector Exhaust), you determine that the OPERATE light is OFF. The Control Room Supervisor asks you to perform an operability check of 1EMF-33.

Which ONE (1) of the following is required to be performed for this check per PT/1/A1460010038 (Daily Surveillance Items)?

A.

Have RP perform a setpoint check.

8.

Have RP perform a source check.

C.

Verify the sample pump is in operation.

D.

Verify the correct sample point is selected.

401-9 Comments:

In accordance with the reference, it appears that a source check is required not a setpoint check. Please re-verifY correct answer..

ruesday, November 10, 2009 The stem ask for a requirement. The word "Ensure" (distracters "C" and "D") are NOT "requirements". These two distracters will be immediately eliminated.

U because "e" and' D" are NP Page 61 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 25 General Discussion RF A 10108/09 Revisited The stem asks for a requirement. C and D are "verity" steps. A and B are performance steps. If the stem asked for a requirement, then the applicant will rule out C and D because they are NOT performance steps.

RFA 10/27109 In accordance with the reference, it appears that a source check is required not a setpoint check. Please reverity correct answer..

The stem ask for a requirement. The word "Ensure" (distractors "c" and "D") are NOT "requirements". These two distracters will be immediately eliminated.

U because "C" and 'D" are NP RF A 10108/09 c---*~--~*-**-*-*~'-~'~*~-~*--*--~'-*~----~--*~~'-~-~*-----'~,-.---~.~~--,---,--,-.-,----.-.-----,-~-.~-.---.------~-~.----~-.--.

i IEMF-33 is a process radiation that monitors the gaseous activity levels released to the unit vent by the condenser air ejector exhaust. As part of the daily surveillance checks performed by

!the reactor operators, the OPERATE light associated with the EMF control module is verified to be illuminated. If it is dark the PT being performed requires a source check to be performed.

IA successful source check ensures operability and usually results in the recovery of the operate light.

1 iKA is matched because know that due to indications on the EMF control module located in the CIR (Operate light dark) the question examines ability to monitor and understand that because

!~!~isJ.n~d~~i(m.'a_~~r~.<:~e~kJ~_rt.:Cjuir~d~ ~ ~.~.~_~ ___ ~_~ __ ~ __ ~ _________ ~ ___ ~ _____ ~ _ ~~ __________ ~ ________ ~_~~. ___ ~

Answer A Discussion 1J~~~~~e-;;t~ Se;~P1~~~~~b~~e~Pi~~~bi;;-:In~ord~;f~r thi;EMF to-p~rt~~its-d~;g~ fu~Zt;;;~ ~f-dct;ctio~ ~-;pri;;~ryto

~s;;-c~nd;ryl;;-ak, th~;etP~~irrt; ~~ld need to be correct therefore

~~s~~i()I~_i~Ehlu~i[)!~~t..I1{)~r~guirej bYtl1~~I __ ~ ~ ___ ~ _,~. ________ ~~ __ ~ ____ ~ ________ ~_. ____,,~.~. ___. __________, __

Answer B Discussion 1------------ --------- --------.---- ---- ------ ------

-~-

ICORRECT: See explanation above

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

Answer C Discussion 1-

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~--

---

.~ -

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[Incorrect: See explanation above. Plausible: This would be a correct action if this EMF had an sample pump which it does not. Plausible because we have other EMFs that do which are i

~11.e~~ecl.tJy..tl!eX!~ ___________________ ~ _~ ________ ~ ______ ~_~ _______________,. ___ ~ ____________ ~ ____________ ~_j Answer 0 Discussion rI~c;~e~t~S~~~~;pI;~~ti~n-abO~~Pht~;ble~This ~~uld b~~a~~;;:~ct~ti~iithis-EMF h~-~~Pi;;-p~~ts~l~cti~-Z<w~bility~pi;u~bi~beZa~s~;;h-;;~~th~EMFs th~td~ ~hi~h-are Lc.h~c~e<i ~xthePJ.. ~~, ~._,_,,'_, ___, ~ ___ ~___ _ _~ ____ ___ ~ ____ ~ __ ~ ______ ~ ~ ____ ~ _____ ~ ___ ~~ __ ~ ____ ~ ___ _

ruesday, November 10, 2009 Page 62 of 185 FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 25 General Discussion RF A 10108/09 Revisited The stem asks for a requirement. C and D are "verity" steps. A and B are performance steps. If the stem asked for a requirement, then the applicant will rule out C and D because they are NOT performance steps.

RFA 10/27109 In accordance with the reference, it appears that a source check is required not a setpoint check. Please reverity correct answer..

The stem ask for a requirement. The word "Ensure" (distractors "c" and "D") are NOT "requirements". These two distracters will be immediately eliminated.

U because "C" and 'D" are NP RF A 10108/09 c---*~--~*-**-*-*~'-~'~*~-~*--*--~'-*~----~--*~~'-~-~*-----'~,-.---~.~~--,---,--,-.-,----.-.-----,-~-.~-.---.------~-~.----~-.--.

i IEMF-33 is a process radiation that monitors the gaseous activity levels released to the unit vent by the condenser air ejector exhaust. As part of the daily surveillance checks performed by

!the reactor operators, the OPERATE light associated with the EMF control module is verified to be illuminated. If it is dark the PT being performed requires a source check to be performed.

IA successful source check ensures operability and usually results in the recovery of the operate light.

1 iKA is matched because know that due to indications on the EMF control module located in the CIR (Operate light dark) the question examines ability to monitor and understand that because

!~!~isJ.n~d~~i(m.'a_~~r~.<:~e~kJ~_rt.:Cjuir~d~ ~ ~.~.~_~ ___ ~_~ __ ~ __ ~ _________ ~ ___ ~ _____ ~ _ ~~ __________ ~ ________ ~_~~. ___ ~

Answer A Discussion 1J~~~~~e-;;t~ Se;~P1~~~~ ~b~~e~Pi~~~bi~:In~ord~;f~r thi;EMF to-p~rt~~its-d~;g~ fu~Zt;;;~ ~f-dct;ctio~ ~-;pri;;~ryto ~s~c~nd;ryl~ak, th~;etP~~irrt; ~~ld needt~be~;;_~ct th~;~f~r~ -i

~~s~~i()I~_i~Ehlu~i[)!~~t..I1{)~r~guirej bYtl1~~I __ ~ ~ ___ ~ _,~. ________ ~~ __ ~ ____ ~ ________ ~_. ____,,~.~. ___. __________, ______. _____ _

Answer B Discussion 1------------ --------- --------.---- ---- ------ ------

-~-

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

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

---

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

ICORRECT: See explanation above

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

-,-~-- ----- ------ ------ ---

Answer C Discussion 1-

-~

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

~--

---

.~ ~ ~ ~- ---'-

.~~.~,- -,.- ---.-

~

~,~ ~--'-'-'-~-

~ - -

--~

~.---

---.-~,--~-

~.,--~ ~,--~.--

~ ----

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

'~~---I

[Incorrect: See explanation above. Plausible: This would be a correct action if this EMF had an sample pump which it does not. Plausible because we have other EMFs that do which are i

~11.e~~ecl.tJy~l!e.!'!~_~ __ ~ ~ ~ ~ ______ ~~_ ~_~ ~~ __ ~ ____ ~ ~~_~ __ ~~_~_ ~ _____ ~ ______ ~,. ___ ~ _______ ~ ____ ~ ____________ ~_j Answer 0 Discussion rI~c;~e~t~S~~~~;pI;~~ti;;-n-abO~~Pht~;ble~This ~~uld b~~a~~;;:~ct~ti~iithis-EMF h~~~~Pi~p~~ts~l~cti~-Z<W~bility~pi;u~bi~beZa~s~;;h-;;~-;th~EMFs th~td~ ~hi~h-are Lc.h~c~ee _ T _______________ ~ ~~S!i~'!~~~~e_ ~ ~ ____ ~ __ ~ __ -1 401-9 Comments RESPONSE

_~~~~__ L _____ ~~~~ ______ L __ ~~~I~I~l)~_l __ ~ _______ ~ ~~~O~ ~~~~5~(Ban~~O~L _________ ~ ___ I ~~~~o~ ~~~:~t,~~ ~~da::;s~gp:~~;a%.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r;:;----~ ~~~--~~~~~~-~---

---

~----

t!'~,!,~()p_~~n!,!~!,"~nce~ _ ~ ______ ~ _ ~ __

[Technical Reference(s): PT/I/N4600/003 B (Daily iSurveillance Items) Rev 128 I

1 L _~

_~~~

~ __ ~ ~ ____ _

1- -~-

~~~~-

-~----~--

--~- ----~

IStudent References Provided r---~--------~------

I 1

I 1 L __

~ _________ ~ ___ ~ ______ ~_~ _

~

Removed "ensure" from dist C & D and replaced with "Verity". Not sure what his problem is with this question, need to discuss during review. Also changed dist C

& D 1I/3

~~~!i~~~E!~A=system=J~2~~~== _

i~:~~~_==========================-======-======================== __ _

[Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)[JCheck source for operability I

18251SYS073 IA4.03 l __ ~ __ ~~ __ ~ __ ~--L __ ~~_ ~ _

~-1_~ __

~ _____ ~_

idemonstration..........................

L

_~_~ __ ~ __

~~ ___

~~ _______ ~ _________

~ _____

~~ ____

~ __

~ ____________

~ ___

~ ____

~ _______

~ __

~

ruesday, November 10, 2009 Page 63 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 26 B

~ -- -

-~------ T----------,------------------- r:-----

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

IQuestionBank # IKA_system IKA_number IrKA_desc j--1826 ---T --SYS076--r---- K4:D6 ------1 [K~~I~dg;;~fSWSd-esig~f~atu~e(s);nd;~ri;-t~i~ck(;)~h~h p-r~vTd~ fu;the-follo;i~~(CFR:41!7)CS~~~e-'~ate~-t~j;-- --

L _________ ~

______ ~

____________..J 1~E'l['ati()_n _______________________________________ ~ _________ ~

CURRENT Given the following conditions:

Unit 1 @ 100% RTP 18 RN Pump is in service with suction aligned to the Low Level Intake A spurious Safety Injection Signal occurs (on both trains)

Which ONE (1) of the following describes the alignment of the RN Pumps after the spurious Safety Injection?

A

8.

C.

D.

RN Pump 1A is running with suction from SNSWP and RN Pump 18 is running with suction from the Low Level Intake.

RN Pump 1A running with suction from the Low Level Intake and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A is running with suction from the RC Crossover and RN Pump 18 is running with suction from the SNSWP.

RN Pump 18 is running with suction from the RC Crossover and RN Pump 1A is running with suction from the SNSWP.

076K4.06 45 DAY VERSION Given the following conditions:

Unit 1 @ 100% RTP 18 RN Pump is in service with suction aligned to the Low Level Intake A spurious Safety Injection Signal occurs (on both trains)

Which ONE (1) of the following describes the alignment of the RN Pumps after the spurious Safety Injection?

A

8.

C.

D.

RN Pump 1A is running with suction from SNSWP and RN Pump 18 is running with suction from the Low Level Intake.

RN Pump 1A running with suction from the Low Level Intake and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A is running with suction from the RC Crossover and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A and RN Pump 18 are running with suction from the SNSWP.

401-9 Comments:

With train separation being common knowledge, I do not believe that D is plausible since the suction is common from SNSWP.

Replace D.

RF A 10/27/09 ruesday, November 10, 2009 Page 64 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 26 B

~est~~~~~

T~~~s!~~=r~:~~ni~~=-_=_=_=J ~:c!!~~=~_=_ =

~-_~.~~~~ = =

___ _=_ ___==-~.=-=== ___ _=_~ ~-____ =

~ _______________ ~__=_.=_---= ___ =-= ______ ~ __ ~ ____ ~:- ~~ ~ ~

I 1826 T SYS076 r K4.06 I [Knowledge of SWS deSIgn feature(s) and/or mterlock(s) whIch provIde for the followmg: (CFR: 41!7)USefVIce water tram L ___ ~_~ ___ ~_~ ~~~~-~ -~---~~~------~ ISt:Eli['ati~n-,:.. _:...,-,.-".......,-,.... -".,-,....... __ ~ __ ~ _____ ~~ __ ~ ___ ~ _~ ____ ~ __ ~ ____ ~~_~~ __ ~ _~ __ ~ __ _

CURRENT Given the following conditions:

Unit 1 @ 100% RTP 18 RN Pump is in service with suction aligned to the Low Level Intake A spurious Safety Injection Signal occurs (on both trains)

Which ONE (1) of the following describes the alignment of the RN Pumps after the spurious Safety Injection?

A

8.

C.

D.

RN Pump 1A is running with suction from SNSWP and RN Pump 18 is running with suction from the Low Level Intake.

RN Pump 1A running with suction from the Low Level Intake and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A is running with suction from the RC Crossover and RN Pump 18 is running with suction from the SNSWP.

RN Pump 18 is running with suction from the RC Crossover and RN Pump 1A is running with suction from the SNSWP.

076K4.06 45 DAY VERSION Given the following conditions:

Unit 1 @ 100% RTP 18 RN Pump is in service with suction aligned to the Low Level Intake A spurious Safety Injection Signal occurs (on both trains)

Which ONE (1) of the following describes the alignment of the RN Pumps after the spurious Safety Injection?

A.

8.

C.

D.

RN Pump 1A is running with suction from SNSWP and RN Pump 18 is running with suction from the Low Level Intake.

RN Pump 1A running with suction from the Low Level Intake and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A is running with suction from the RC Crossover and RN Pump 18 is running with suction from the SNSWP.

RN Pump 1A and RN Pump 18 are running with suction from the SNSWP.

401-9 Comments:

With train separation being common knowledge, I do not believe that D is plausible since the suction is common from SNSWP.

Replace D.

RF A 10/27/09 ruesday, November 10, 2009 Page 64 of 185

FOR REVIEW ONLY - DO NO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 26 General Discussion I-~---

-~--~-

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

-~---- -

---~- ---

---

~~-- -- -

-~- --

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

--~

---

~---~- ---

---

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

--~-I IWhan an SI signal occurs the RN trains are automatically aligned to split the trains and IA RN pump is started taking a suction from the LLI while 1B RN pump takes suction from the ISNSWP.

I IThe KA is match because the applicant must be familiar with the RN system automatic alignment during an SI which provides for train separation which assures an RN supply to the units l!r~m ~le~i~~_tr<li~ ________________________

~ _______ ~~ _________ ~_

Answer A Discussion

[-

--~-

---

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

-~--- -- ----

--~-

---~--~- -- -

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

--~- - ---

--~---

---~---

-~- ---

---

~-- --- ---

--~- ---

IIncorrect. Plausible as both RN pumps do get an auto-start signal and the Low Level Intake and SNSWP are the correct suction sources for the RN system. However, the alignment is iincorrect.

l_ ~ __ ~ ____________ ~_~ ________

~ ______ ~ _____

~ _______ ~ _______

~ ______ _

---

I Answer B Discussion 1 ~-

~-

-~ - - -

--~-~---~--

iCORRECT.

L ____________________

~ _____ _

Answer C Discussion r;-:~-

~-

~---- -- ---

-~-~ - -

-~~-

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

--~-- - - -

---~--~-

---~-

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

~-~-

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

-~---- -- - --

--~- -~----

-~- --- --

-~-

IIncorrect. Plausible since both RN pumps get an auto start signal on an SI and the RC Crossover is one of the suction sources for the RN system. However, it is not a suction source during an lSI.

I c __

~~ ___ ~_~ __

~ __ ~ _________ ~_~ __ ~ ___ ~ _____ ~ ___

~ __________

~ ___

~ __

~ _____________ ~ _________

~ ______

~ __

~ ___________

~ _____

~ ______

~ _____ J Answer D Discussion rll~~r~ct.-Pla-u;hle-si~_;;~ b~th-RN-pu~p; g~t-~~~~t~ ~;rt-sig~~ ;;a~ SI;dth~RCCr~;s~;e~ i~;-~~fth; s~~ti~~ s~~r~~fo~ th~RN ;y~-~H~;e~e~,iti;n~t a-s~cti;;s~~r~~ d~ring--i Ian SI.

I

_~ ____

~ __________

~_~ ___________ ~ ______ ~_~ _____

~ ___________ ~ ________________

~ _______

~_~ _____

~ __

~ ________

~ ___________

~ _______ J

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory

- --- ---~-------~---~-~----- --- - ----l Question Source I 401-9 Comments RESPONSE

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

~

---I CNS NRC Bank Question 1046 (Never Used)

I Per Lead examiner suggestion, distracter D

- -- ~-- -----~ - -~-~--------------- -- ----------~ was replaced with a reveresed version of I------~-~------ ---

-~-

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

r;------~--

---

~- ---

LD_e... !'~pm~flt_R!!e~~n~!~__ _ _ ____ _ _____

i!>~~~!!~Fle!!'!~~fl Pro-,,!c1~~ _ _ __ _

distracter C. 11103 iLesson Plan OP-MC-PSS-RN, Objective 8 Section 3.2 I

I I

I I

I I

I I

I i

I L _____________ ~~ _____ ~_~________ _ __

1 ___ ~ __ ~ __ ~ _____________ ~ ____ 1

-- ---1---- ------- --- -- T---

~-

---

~- ---- ---

QuestlonBank ## IKA_system IKA_number

~A:.~~s~~~===~~======~~====~==_-_~~-~====_~_=========_====~=_=_===~=~==~_~====J

-~- -

-~~- r;: ~-~ ~---- ~- -~-~- +- - -

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

1

~26t~~0?6 _____ iK4!~ ______ _

Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 4117)llService water train

~tp~riltiOl1 __ **_: ___ *~..

• ___

• ___ *.. *~~*~*~* ___ *_:*~_~ ________ ~ ________________ ~ ___________ ~ ______________ J Tuesday, November 10, 2009 Page 65 of 185 FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 26 General Discussion I-~---

-~--~-

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

-~---- -

---~- ---

---

~~-- -- -

-~- --

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

--~

---

~---~- ---

---

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

--~-I IWhan an Sf signal occurs the RN trains are automatically aligned to split the trains and IA RN pump is started taking a suction from the LLI while 1B RN pump takes suction from the ISNSWP.

I IThe KA is match because the applicant must be familiar with the RN system automatic alignment during an Sf which provides for train separation which assures an RN supply to the units l!r~m ~le~i~~_tr<li~ ________________________

~ _______ ~~ _________ ~ _______ ~_~ ______________

~ _____ ~ _____ ~_~ __________

~ __ ~_~ ____ _

Answer A Discussion

[r~c;;-;;:-e~t:-PI~;W;~both-RNpu~p;-ct;;-g~t-~~t~=st-trt~gn;I~~the -L~;Le~cllntak~~d-SNSWP ;r;th~Z~;:;'~~t~~t;;~ ~~r~e';-fo;:-th~-RN-sy~e~~Ho~~v~~the-~lig~~~~tis- - ---l l~n~oITect._ __ ___ __ ____ __ _____________ ___ _______ ___ ____ ___ ________ ___ _ __ __

~ __________ ~ ____

~ ________

~ _____ ~ __ ~ ___ J Answer B Discussion I~-~-

-~---

--~-~---~--

~------- -

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

~-

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

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

---

~----~---

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

~---------~~-~--,

ICORRECT.

j L- _______

~ _____

~ ___________

~ ________ ~ _____ ~ _____________

~ ______________________ ~

_____________________ ~ ____________________________________________

~ __

Answer C Discussion r;-:~-

~-

~---- --

---

~-~- -

-~~-

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

--~-- - - -

---.--~-

---~-

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

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

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

IIncorrect. Plausible since both RN pumps get an auto start signal on an Sf and the RC Crossover is one of the suction sources for the RN system. However, it is not a suction source during an lSI.

I c __

~~ ___ ~_. __. __ ~ _________ ~_~ __ ~ ___ ~ _____ ~ ___

~ __

• _____________

• _________

~ ______

~ __

~ _____

~ ______

~ _____ J Answer D Discussion rll~~r~ct.-Pla-u;hle-si~-;;~ b~th-RN-pu~p; g~t-~~~~t~ ~;rt-sig~~ ;;a~ SI;dth~RCCr~;s~;e~ i~;-~~fth; s~~ti~~ s~~r~~fo~ th~RN ;-y~-~H~;e~e~,iti;n~t a-s~cti;;s~~r~~ d~ring--i Ian Sf.

I

~_. ___________ ~ ______._. _____ ~ ___________ ~ ________________. _______._. _____

~ __. ________. ___________

~ _______ J I Job Level 1-- -- ---

~

I RO L, ________ _

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

__~~f!ltI~e_~~!'_ _

Memory

-~---

-.----~-

-r--~----*---- - --- ---.-------.---~-.----- --- - ----l QuestlonType I

Question Source I 401-9 Comments RESPONSE

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

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

-.--.-~------ -I

__ ~~~~ ___ L ________ ~~~~~~~llI1~ Que~~o~~~~~~e~eI'~:e~) ________ ~ Per Lead examiner suggestion, distracter D was replaced with a reveresed version of distracter C. 11103 r;------~--

---

~----

i!>~~~.'!~ Fle!!'!~~fl Pro-,,!c1~~ _ _ __ _

~ Developed

~~~!I~pm~~ ~!ei~n~!~~~~=~~~ ~ ___ _

I I

I I

I i

I I ___ ~ __. __ ~ _____________. ____ 1

~ OPT Approved

~ OPS Approved

~ NRC Approved iLesson Plan OP-MC-PSS-RN, Objective 8 Section 3.2 I

I I

q~~i~a~~-~f.-A:~jj!e~IKA~~~r!t~~~_~~ -~~l ~A:.~~s~ ~ ~~~ ~~~ ~ ~ =~== =.=~~ =~== _-.~ ~- ~====-.~_==== =

== =~_====~~ _=-==~~=~=~=.~= =-==J 1826iSYS076 iK4.06 i IKnowledge of SWS design feature(s) and/or interiock(s) which provide for the following: (CFR: 4117)llService water train

-.- ~

~ -- ------~- - -"-- --- ----- --~ -

~ ---~ ~tp~rilti.OI1-,.. '.:",.~... ",.",.'.:.-'.:~.-'.:.-,.",.'.:~.-,--~_. _______._ ~ _______________ ~_ ~~ _______. ____ ~_. ________ ~_. _. ___ J Tuesday, November 10, 2009 Page 65 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 27

~!8tion!J~"--~~~:S-y8~~ =-T~jt~1>!r~~=-=-=~ [KA_ de8~~ =-=-~=-=-==-~ ____===-=_-_==-=-=-=-=-= ~===~==-_~==-= =-=-_==-=-=-=-=-==-=-=-~~ ~==== =-====-= = -= J L ___ ~~~ ___ L ~~~078 __ 1 ____ ~~.~~ ____ J ~~i~~to_l11O~i~o~~ut~m_atic_o£~'lti~~~~-=~~S~iI1C~U~~~~C~R~~~~~~*~~!-~£r:ss_~=-:--:--*~*~ ~:--'~~'~-'~'~~'~':--:--~' '- __ I CURRENT 45 DAY VERSION Due to a leak on the VI system the Unit 1 OATC observes the following indications:

1AD-12 C1 (VINS Lo Pressure) is LIT OVIP-5090 (VINS Press) dropped to a lowest reading of 86 PSIG and is now 89 PSIG and increasing.

Which ONE (1) of the following describes automatic actions which have occurred as a result of the indicated pressure transient?

A.

B.

C.

D.

G and H VI Compressors Auto Started ONLY 1 VI-820 (VI to VS Supply) Auto Closed ONLY 1 VI-820 Auto Closed AND 1 VI-1812 (VI Dryer Bypass Vlv) has Auto Opened G and H VI Compressors Auto Started AND 1V1-820 (VI to VS Supply) Auto Closed 078A3.01 No comment at this time RFA 10/27/09

'uesday, November 10, 2009 Due to a leak on the VI system the Unit 1 OATC observes the following indications:

1AD-12 C1 (VINS Lo Pressure) is LIT OVIP-5090 (VINS Press) dropped to a lowest reading of 86 PSIG and is now 89 PSIG and increasing.

Which ONE (1) of the following describes automatic actions which have occurred as a result of the indicated pressure transient?

A.

B.

C.

D.

G and H VI Compressors Auto Started ONLY 1 VI-820 (VI to VS Supply) Auto Closed ONLY 1 VI-820 Auto Closed AND 1 VI-1812 (VI Dryer Bypass Vlv) has Auto Opened G and H VI Compressors Auto Started AND 1VI-820 (VI to VS Supply) Auto Closed 401-9 Comments:

Page 66 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 27 Ql..!8tion!J~"--~~~:S-y8~~ =-T~jt~1>!r~~=-=-=~ [KA_ de8~~ =-=-~=-=-==-~ ____===-=_-_==-=-=-=-=-= ~===~==-_~==-= =-=-_==-=-=-=-=-==-=-=-~~ ~==== =-====-= = -= ~

f 1827 I

SYS078 I

A3.01 liAbility to monitor automatic operation of the lAS, inclu~~~ (CFR: ~~~~~.~~!-~£r:ss_~=-:--:--'~'':--'~~'~-~'~~'~':--:--~- __ I L _______ ' __ ~ ___,_~ __ ~ _______, ______ ~ L ___ '_,_, ___,_, ________,_,_, _________, __

CURRENT 45 DAY VERSION Due to a leak on the VI system the Unit 1 OATC observes the following indications:

1AD-12 C1 (VINS Lo Pressure) is LIT OVIP-5090 (VINS Press) dropped to a lowest reading of 86 PSIG and is now 89 PSIG and increasing.

Which ONE (1) of the following describes automatic actions which have occurred as a result of the indicated pressure transient?

A.

B.

C.

D.

G and H VI Compressors Auto Started ONLY 1 VI-820 (VI to VS Supply) Auto Closed ONLY 1 VI-820 Auto Closed AND 1 VI-1812 (VI Dryer Bypass Vlv) has Auto Opened G and H VI Compressors Auto Started AND 1V1-820 (VI to VS Supply) Auto Closed 078A3.01 No comment at this time RFA 10/27/09

'uesday, November 10, 2009 Due to a leak on the VI system the Unit 1 OATC observes the following indications:

1AD-12 C1 (VINS Lo Pressure) is LIT OVIP-5090 (VINS Press) dropped to a lowest reading of 86 PSIG and is now 89 PSIG and increasing.

Which ONE (1) of the following describes automatic actions which have occurred as a result of the indicated pressure transient?

A.

B.

C.

D.

G and H VI Compressors Auto Started ONLY 1 VI-820 (VI to VS Supply) Auto Closed ONLY 1 VI-820 Auto Closed AND 1 VI-1812 (VI Dryer Bypass Vlv) has Auto Opened G and H VI Compressors Auto Started AND 1VI-820 (VI to VS Supply) Auto Closed 401-9 Comments:

Page 66 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 27 D

General Discussion IAt~d;-c;:-e~j;;gVIP~~~s~-~f 90 PSiGt~f~I-~~~g~a-;;ti<;~s ~Z~~~-: ~.~

II VI-820 (VI to. VS Supply) Auto. clDseS

!G and H (Diesel VI compressDrs) Auto. Start

!IfVI pressure cDntinues to. decrease to. 85 PSIG, IVI-1812 (VI Dryer Bypass) will OPEN.

---

~---

--~-

iKA is matched because the candidate, given infDrmatiDn Dbtained from mDnitDring a trend DfVI pressure indicatiDns IDcated in the cDntrol room, what automatic actions have occurred lassDciated with the Instrument Air system.

I lTh~ ~s~~~mlI~is ~\\,e~ 'l':l~s~()~ b~~au~~ !'1e_~£llc~n.t ~ ~\\,eE ~e~~E~11t.(X)~cI.iti.0E~~ci.f!llJS~r~~,!a_ ~tp~n~ !fCJ..~

~el11()l2'!9 ~~t~~I1.eJf_a~~ ()~ll.l1t()Ill_ati.c...~tlo~s...s~oll'9 Eave occurred.

Answer A Discussion iI~~~~;;t~~s~~rTs -~~t~~~plete-a~di;Zo~e~td~e-t~th~ ONL~Y-d~~ig~~ti~~~Pla~;ible ~b~~~~~th~ acti~~-;o~ldha~ ~~c~~~d b~~;~Zo~pi~t~~ - ~ -~- -- - -

I L ___ ~.

__. _______

• ____ ~_._. ___.. __. _.~~ __._~_

. __.~. ___

~. ___.~_~. ____ ~_~ __

.* ____ ~~ __ ~ ___. ______._. ____

. ___ ~ __

. _______. ___ J Answer B Discussion l~n~IT~c:._Answ:l"..i~no.:.~Ill~I:t~ ~n~ ~s~~~rr~~ ~~etD_t~~~N~!~esig~a~iCl.~ !~a~sib.':!~c~~s:.tI1i~ll.~~~~~Idha~~ D~Zu~~but is not cDmplete.

Answer C Discussion r- -

---

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

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

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

IIncorrect: I VI-1812 will nDt open until pressue decreased to 85 PSIG. The lowest pressure given in the stem is 86 PSIG. Plausible: First part of the answer is cDrrect, candidate may believe lIV.!--'8)~£tctuCltes_\\\\'it11..!h~()tller~oI11j)()~n.ts_a~ 90J'§I<:Jo __ ~ _________ ~ __ ~ ___ ~ _ __ ____ _ ___.. ~ _____ ~ __ ~ ________ ~ ______________ ~ _____ _

Answer 0 Dl$cussion r:.---~--.. --.------.- -

-~.

ICorrect as described above.

Job Level

---Cognitive Level

- Q-~estio-nType -r -- - --- ----------Q~estiOnSource---~----------

401-9 Comments RESPONSE

- ----_. ---- -~-.

.~ --- -.-.- -.-.-.-.). ~--- -.-.-~- -- --- -- - _._--.--.-._.- ---- -

RO Comprehension NEW I

Considered SAT for submittal with no.

-.---~

__ ~ __....L~~ _________________ ---~~----~-------~--

comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 1;:---- -.. - -.... --.- --.... - ---- -._- --- - --.

@!\\l.e!op.rn~rl~~e1e-,,!.n~!s ________ _

iLesSDn Plan OP-MC-SS-VI Objective 7 Section 1.2.10 ipage 67 and Objective 2 SectiDn 1.3.1 page 89 iARP fDr IAD-12 CI (VIIVS Low pressure)

I I L __

[student Refere~ces Provided I -.- -- -~- - --- -- ------ -----

I I

I I

I L ___ _

~---

-~~---~- -

l 1.-------

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

luestlonBank." IKA_system IKA_number I IKA_desc 18zlSYS078 - - - - fAioI- - - - -- ~---1 iAbiiitY-t~-ll1o~it~r ~uto-~ati~-op~r;ti~~ ~Tth~IAS~i~cludi~g:(CFR~-4I~7/ 45~5)l.iAi;p-;:e~s~r~

. -----~ --.1. ____._._ - _1 __ - - -~----- -.-

l:-.':":-":-:'.":"":~".".".. "':'-:'-oo:-:~,:-:,.".,~_. _____ ~ ____. ___.. _~ _._._. ____._.~_. _____._

ruesday, November 10, 2009 Page 67 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 27 D

General Discussion IAt~d;-c;:-e~j;;gVIP~~~s~-~f90 PSiGt~f~I-~~~g~a-;;ti<;~s~Z~~~-: ~.~ -~~~~~~~~~~

~~ -~-~~--~

~

---~~-~.~ -

~~~

~~

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

II VI-820 (VI to. VS Supply) Auto. clDseS

!G and H (Diesel VI compressDrs) Auto. Start

!IfVI pressure cDntinues to. decrease to. 85 PSIG, IVI-1812 (VI Dryer Bypass) will OPEN.

iKA is matched because the candidate, given infDrmatiDn Dbtained from mDnitDring a trend DfVI pressure indicatiDns IDcated in the cDntrol room, what automatic actions have occurred lassDciated with the Instrument Air system.

I lTh~ ~s~~~mlI~is ~\\,e~ 'l':l~s~()~ b~~au~~ !'1e_~£llc~n.t ~ ~\\,eE ~e~~E~11t.(X)~cI.iti.0E~~ci.f!llJS~r~~,!a_ ~tp~n~ !fCJ..~

~el11()l2'!9 ~~t~~I1.eJf_a~~ ()~ll.l1t()Ill_ati.c...~tlo~s...s~oll'9 Eave occurred.

Answer A Discussion iI~~~~;;t~~s~~rTs -~~t~~~plete-a~di;Zo~e~td~e-t~th~ ONL~Y-d~~ig~~ti~~~Pla~;ible ~b~~~~~th~ acti~~-;o~ldha~ ~~c~~~d b~~;~Zo~pi~t~~ - ~ ~~~ ~~ ~ - - ~~--- ~- -~~--1 L

~_~.

__._~~ _ ~_ ~. ___ ~~~._.~~_

.. __. _.~~~~.~~~._~._ ~.~. __

~~.~~_.~_~._~_~~_~ ~~

.* ___ ~~~ _~~~

~~.~~ ___ ~._.~~~~.

___ ~

~. ______ ~.

__ ~J Answer B Discussion

--~~

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

~---

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

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

--*--~~~~~*---~~*--~~-~-~--~--*~-l l~n~IT~c~_An~w:~i~no~~Ill~I(~t~ ~n~ ~s~~~rr~~ ~~etD_t~~~N~!~esig~a~iCl.~ !~a~sib~!~c~~s:.tI1i~~~~n~w~uI~h~\\'e~:C~f1"e~~~~~o~~D~£,~~te.. ~ __ ~_~ ___ ~~ _____ ~ _~ ~I Answer C Discussion r- -

---

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

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

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

IIncorrect: I VI-1812 will nDt open until pressue decreased to 85 PSIG. The lowest pressure given in the stem is 86 PSIG. Plausible: First part of the answer is cDrrect, candidate may believe lIV.!-.!8)~£tctuCltes_\\\\'it11..!h~()tller~oI11j)()~n.ts_a~ 90J'§I<:Jo_ ~~ __ ~~ _____ ~ __ ~ __ ~~ ___ ~ __ ~_~ ___.. ~_~ ___ ~_ ~~_~ ______ ~ ____ ~~~~_ ~~~ ~_~ _____ _

Answer 0 Dl$cussion r:.---~~-.. --.---~-~.~ -

-~.

ICorrect as described above.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Ir~~- -.. - -.... ~-.~ --.... -

--~- -._- ~-- - --.

@!\\l.e!op.rn~rl~~e1e.!'!.n~!s _____ ~ ~~_

iLessDn Plan OP-MC-SS-VI Objective 7 Section 1.2.10 ipage 67 and Objective 2 SectiDn 1.3.1 page 89 iARP fDr IAD-12 CI (VIIVS Low pressure)

I I L __

--~-~.~-.---.,~-

~----~~-~-~- --**--*---*l r;-~-~~--

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

r;;.~.~-

~~.-.~~ -

~

~~ -

~.-.-.~~.-~.~~-,

~S_tl!<!erl!. ~e!!,"!,~!!, ~r()~i~~d _____ ~ _~ I I

I I

I I

I I L ___ _

401-9 Comments RESPONSE Considered SAT for submittal with no.

comments. No changes.

luestlonBank." IKA_system IKA_number I IKA_desc

.. ~--.-.. --~--.- f*~~*--**-*-~-r~*---*- -.---.- ~~-*-l r- - --.. ~.- --

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

. __ ~ __ ~ I_8_271S!S~7~ ____ l~~O~ ~ _ ~_~ ~~ __ J C~~~~~~::~:~:.:~:~;~.t.i~:~~~~i:~D~th: ~~~ I~C~U~ing~~C~~:_~I: ~~5:~l~~r::~~r~ ~~~~~ _~ __ ~

ruesday, November 10, 2009 Page 67 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 28 1,-

~ ------~-I---~~~~

-I----~~~

--~

re~t~~~~!~~~~s~;~~--r=~~Ill::~3--~~- l~~~~~~==== ================ =======================-===-=-=-=---========= ----

___ ~~ __ ~ ~ ____ J_~ ~ __ ~ __ ~_~~ __ ~~_~ _ ~

lAbility to manually operate andlor monitor in the control room: (CFR: 41.7/45.5 to 45.8)CESF slave relays l* ___ : ___...

• ____ ~*~** ____... :-* ___ *:-: ___

• ____

• ____

• ___

• ____ ~ ____ ~ ________ ~ ______ ~ _____ ~ ___ ~ ___ ~ ____ ~~ ___ ~~_~ __ ~ __ ~ ___ ~~ __ ~ ___ ~

CURRENT Given the following conditions on Unit 1:

A Steam Break has occurred inside Containment Containment pressure is 3.5 PSIG and decreasing Which ONE (1) of the following describes the MINIMUM action(s) required to allow restoration of Component Cooling Water to the NC pumps?

A B.

C.

D.

Reset Phase A ONLY Reset Phase B ONLY Reset Phase A AND Phase B ONLY Reduce Containment pressure below 3.0 PSIG AND reset Phase AAND Phase B I03A4.03 If C was correct, D would be also.

Modify C or D or add an ONLY to C.

RFA 10/27/09 Muesday, November 10, 2009 45 DAY VERSION Given the following conditions on Unit 1:

A Steam Break has occurred inside Containment Containment pressure is 3.5 PSIG and decreasing Which ONE (1) of the following describes the MINIMUM action(s) required to allow restoration of Component Cooling Water to the NC pumps?

A B.

c.

D.

Reset Phase A ONLY Reset Phase B ONLY Reset Phase A AND Phase B Reduce Containment pressure below 3.0 PSIG AND reset Phase A AND Phase B 401-9 Comments:

Page 68 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 28 B

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

l~~..,.<i~~~_~_ _ _ _ __ ~ __ ~ _________ ~~ ___ ~_ ~ ____ ~ __ ~ ___ ~~ ~_~~~ __________ ~ _

~_ ~ __ ~

lAbility to manually operate andlor monitor in the control room: (CFR: 41.7/45.5 to 45.8)CESF slave relays I

l*~:~... *~~*~**~... :-*~*~:~*~*--=-*~*~~_. ____._._.. ______ ~. ____________. ____. ___. __________. ______ ~ _____ _

CURRENT Given the following conditions on Unit 1:

A Steam Break has occurred inside Containment Containment pressure is 3.5 PSIG and decreasing Which ONE (1) of the following describes the MINIMUM action(s) required to allow restoration of Component Cooling Water to the NC pumps?

A B.

C.

D.

Reset Phase A ONLY Reset Phase B ONLY Reset Phase A AND Phase B ONLY Reduce Containment pressure below 3.0 PSIG AND reset Phase AAND Phase B I03A4.03 If C was correct, D would be also.

Modify C or D or add an ONLY to C.

RFA 10/27/09 Muesday, November 10, 2009 45 DAY VERSION Given the following conditions on Unit 1:

A Steam Break has occurred inside Containment Containment pressure is 3.5 PSIG and decreasing Which ONE (1) of the following describes the MINIMUM action(s) required to allow restoration of Component Cooling Water to the NC pumps?

A B.

c.

D.

Reset Phase A ONLY Reset Phase B ONLY Reset Phase A AND Phase B Reduce Containment pressure below 3.0 PSIG AND reset Phase A AND Phase B 401-9 Comments:

Page 68 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 28 B

General Discussion r~-~~----.------.-------------.--------- ---~- ---- -- ------ - --- -- --~--.------.----- -

---

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

IKC to the NC pump motor coolers isolates on a Phase B signal. The Phase B can be reset with the signal still present. When the Phase B reset pushbuttons are depressed, control of valves Iithat close on a Phase B signal is regained.

'I IThis KA is matched because the applicant must understand the operation of Containment Isolation Phase B valves (operated by ESF slave relays) and how control is regained for those valves lafter a Phase B actuation to correctly answer the question.

c_. ____. __. __. _____. _______. ____. __. _____________________

~ __

~ ____

~ _________________. _____

~ __________ -------~-------

Answer A Discussion

~~~~~~;;-~-~I~~-ilJle~fi~ ~pP~~,~~lt-~~~~~~~d~~?~d}~~ ~~i~t~~~h!s~ E]~~~~~~~~~~~~c~~t~I~~~~~~~_;~~~~~~jJl~~~d~~~~ Ph~e B ~i~nal.

Answer B Discussion tcORRECT.----------- _._._-- -----

---

~---

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

-~-

-~----

Answer C Discussion

~--- ------

---

.1 I~--~-~-- ----- --- ---------------------- -------

---

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

IIncorrect. Plausible because frequently SI, Phase A and Phase B signals are reset simultaneously during the performance of Emergency Procedures.

l ________________________________________________________________________________ ~

~ ___________

~ ______________ _

Answer 0 Discussion r;-----.---

---

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

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

---

~- -----

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

---~~---.-

--~-.--~.--- -- ---1 IIncorrect. It is plausible to assume that since a Phase B signal occurs at 3.0 PSIG that Containment pressure must be reduced to less than 3.0 PSIG to be able to reset Phase B. However, it imay be reset at any time.

j L

_______ ~ _______________________________________________________________ ~ ___________

~ __________________________

~ _________________________________________ _

_C~fl'!'.!I... e_~~~I_

q~!!~rl!ype Question Source Memory BANK MNS Exam Bank: Question ECCISEN04 1---

-~-

-.-~--~.-

---

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

I~!"'!~J>!,,~,!~ ~ei!~~c~~ __

[OP-MC-ECC-ISE Objective I3 page 3 I r*-

.-~- --- - -

~-.-

-~~-

f~tll<!ent References Provided

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved I

I I

I

! L ______ _

I I II I

I I,-- -~--

401-9 Comments RESPONSE Added "ONLY" to distracter C as requested by lead examinier. 11103

~u!~!~~~~~ ~~~=~~l!rn=-lK~~~~~r= ~~

--=-~ [tSA~~!!~-~=--~~-=---~~-=----~ -=-----=--=~-~---=-~---~-=--~ ---=~ ---=-~-~--=---==~-----~ -=---~=-~-= --~----~~---~-------l 18281SYSlO3 IA4.03 I lAbility to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)[JESF slave relays

- ------ - ___ L -.--~ - -- - - L._ - --.-- -- --- --

l~:._.. _""............ :._.:._::._..... :._....... ~.::._..... ________.~ _~. __ ~ ___ ~ ___ ~ __ ~_~~ _~_ ~~~ __________ ~ _________. __ ~ _______ ~_.

ruesday, November 10, 2009 Page 69 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 28 B

General Discussion r~-~~----.------.-------------.--------- ---~- ---- -- ------ - --- -- --~--.------.----- -

---

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

IKC to the NC pump motor coolers isolates on a Phase B signal. The Phase B can be reset with the signal still present. When the Phase B reset pushbuttons are depressed, control of valves Iithat close on a Phase B signal is regained.

'I IThis KA is matched because the applicant must understand the operation of Containment Isolation Phase B valves (operated by ESF slave relays) and how control is regained for those valves latter a Phase B actuation to correctly answer the question.

c_. ____. __. __. _____. _______. ____. __. _____________________

~ __

~ ____

~ _________________. _____

~ __________ -------~-------

Answer A Discussion c------------------------

---

~------------------------------------------------------~---------------------------------1 lI~~orrec~ ~I~tlSilJle ~f ~~ ~I=T~~t~oe~llO~ ~n~~s?~d_t~~~~!i~t~~f>h!"~ E~S!~s~~t~e2'~~ 1lO~ ~a_"~c~~t~~ ~~~~~~.:s_w~~~~~e_oJl~~~d ~~ tile Ph~e B ~i~11a~ __________ J Answer B Discussion l~~~2'*~==========-_ =

-_==-==~== =~==== =~=== =_-==================-_===-=====-= =-==~====-======-= -====-=-==-=-==---= =i Answer C Discussion 1--------.--.- --- ----- -----.--------.-- ------ -

l~n(;~rr.:(;t._~~atJ~llI~ be~a~s.:!:~u~ntI~~I'_ ~~~~_~~P_h~_= ~ ~i~~~':_~_=_.1"e~e~~~~I~~e~tlsl~~~ring ~.:~eI"form,lll(;e_o!"~l11~~e~~ ~r~~e~tlf~ _________________________ J Answer 0 Discussion r;-----.---

---

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

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

---

~- -----

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

---~~---.-

--~-.--~.--- -- ---1 IIncorrect. It is plausible to assume that since a Phase B signal occurs at 3.0 PSIG that Containment pressure must be reduced to less than 3.0 PSIG to be able to reset Phase B. However, it ilnay~e~~s~tat_aE~t~me~__ ____

~ ___________________________________________________________________________ 1

---

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--1 QuestlonType I Question Source

! 401-9 Comments RESPONSE

~

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-~---- -.--~ --t-~ -- -~--~ ---~~-~--------.-----.--------.- ~--~--*--*-I BANK MNS Exam Bank: Question ECCISEN04 i Added "ONLY" to distracter C as

--- ~-- --

.-~ -

-~-.---.----- ---- -.- -- --.- -.- -- ------------~ requested by lead examinier. 11103

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved ruesday, November 10, 2009 1---

-~-

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IOP-MC-ECC-ISE Objective I3 page 31 I I I

I I I

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I I L _________. ____._~_~ ___________. ____ 1 ! ___. _____

~ ___

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Page 69 of 185

A FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 29

,'--'----'-'---------'----,---- - ----------1 r------ ----,--- -- ---- -,--- --- - --------- ----,-- ----,---,-----,----,-,-- ---,----

~U~Sti~~i'!l~!t~As~}'~~i-l~=~~~~3 -----I fi~~~~ie ~fthe ;rrect th~t-al~s~~;_~alfu~ction of the RCS will have on the following: (CFR: 41.7)~Containment l ___, ______,_~ __

, ______ L ___________, ___ 1 L*~*~~:.:~:..:*:...:....:*~:.:********************************

CURRENT The following conditions exist on Unit 1:

Unit 1 is at 100% RTP with a small NC system leak in Containment Containment pressure is 0.28 PSIG and slowly increasing The BOP places all VL fans in High Speed Which ONE (1) of the following correctly describes the impact of this action on the following Containment parameters?

A.

B.

C.

D.

Containment Pressure AND Temperature will DECREASE.

Containment Pressure will INCREASE. Containment Temperature will DECREASE.

Containment Pressure will DECREASE ONLY.

Containment Temperature will DECREASE ONLY.

002K3.03 45 DAY VERSION The following conditions exist on Unit 1 :

Unit 1 is at 100% RTP with a small NC system leak in Containment Containment pressure is 0.28 PSIG and slowly increasing The BOP places all VL fans in High Speed VVhich ONE (1) of the following correctly describes the impact of this action on the following Containment parameters?

A.

B.

C.

D.

Containment Pressure AND Temperature will DECREASE.

NO IMPACT on either Containment Temperature OR Pressure.

NO IMPACT on Containment Temperature. Containment pressure will DECREASE.

NO IMPACT on Containment Pressure. Containment Temperature and will DECREASE.

401-9 Comments:

"No impact" (distracter B) is not plausible especially with fans in high speed.

Replace B RFA 10/27/09 fuesday, November 10, 2009 Page 70 of 185 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 29

~~sti~~i'!l~!It{A::'~i~!~= I~~~~~! = =-===] ~~0~~~~-_~== ~= =~ ~ ____ =

=-:=~=-=-~~~= ____==~

____======~_=-===-================-==-~~= =~~===_~

I 1829 I

SYS002 1 K3.03 i IKnowledge of the effect that a loss or malfunction of the RCS will have on the following: (CFR: 41.7)~Containment I

l_~_.~~ ___ ~._~_~._~~~_~L~~~

__ ~~~_~~*_~_1 L'~'~~:':~:':'~'--=-::':'~'~'~~'~_'~'_'~'_~-=--=-:-=-=-_______

~ _____________________

~ __

~_~ ________________

~ ____________ _

CURRENT The following conditions exist on Unit 1:

Unit 1 is at 100% RTP with a small NC system leak in Containment Containment pressure is 0.28 PSIG and slowly increasing The BOP places all VL fans in High Speed Which ONE (1) of the following correctly describes the impact of this action on the following Containment parameters?

A.

B.

C.

D.

Containment Pressure AND Temperature will DECREASE.

Containment Pressure will INCREASE. Containment Temperature will DECREASE.

Containment Pressure will DECREASE ONLY.

Containment Temperature will DECREASE ONLY.

002K3.03 45 DAY VERSION The following conditions exist on Unit 1 :

Unit 1 is at 100% RTP with a small NC system leak in Containment Containment pressure is 0.28 PSIG and slowly increasing The BOP places all VL fans in High Speed VVhich ONE (1) of the following correctly describes the impact of this action on the following Containment parameters?

A.

B.

C.

D.

Containment Pressure AND Temperature will DECREASE.

NO IMPACT on either Containment Temperature OR Pressure.

NO IMPACT on Containment Temperature. Containment pressure will DECREASE.

NO IMPACT on Containment Pressure. Containment Temperature and will DECREASE.

401-9 Comments:

"No impact" (distracter B) is not plausible especially with fans in high speed.

Replace B RFA 10/27/09 fuesday, November 10, 2009 Page 70 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 29 General Discussion

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

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

IThe student must recognize that high speed effects more than just the air flow for the AHU. The student must determine what the higher air flow will impact.

[

I [The KA is matched because under the conditions where a small NC system leak has occurred in containment, the applicant must determine the effect on containment conditions when ladditional ventilation flow is provided to containment.

l': _____ ~

_____ ~

__ ~

_______________________________________ ~

___________ ~

_______________________ ~

______________ ~

Answer A Discussion

[CORRECT

---

.---~------

L Answer B Discussion

~~~~~~~t}~~~~!Ucl~~~~~ ~o~~n~~~~~~h~~~ati~~hip~~~.JJ~~tu~~~~i~~;~- t;;i~c~~~d Zo-;;Iingfr~~the-VC~nits.

Answer C Discussion

---l

_______ J

((Incorrect. If the student does not understand the relationship of temperature and pressure or the methodology of dehumidific-;tio~ h~ ;ilI ~~~e

~~iyth~pr~~u~;;-go;;-s-d~~ -- - - - - - ~- i

_________________ ~ ____________________________ ~

_______________________ ~

_______ ~

______________________ ~

_____________________ -----.J Answer D Discussion IIncorrect. If the student does not understand the relationship of temperature and pressure or the methodology of dehumidification he will assume only the temperature goes down.

L ______________________________________________________ ~

-~-.-- ---- T--- --- -- -------- -------, ----

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_______.l _______________

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_____ L

~ _________ _

~ Devetoped

~ OPT Approved

~ CPS Approved

~ NRC Approved iD;velOpment-References-- -- -----

I--------------~-- ------------ -----

IOP-MC-CNT-VUL pages I I, 15, and 17 I

I '------- - -

- ---- - ~-

lS.!~<<!!.~B!i~r~~~8 P!~vlded I

I I

I 1 __ -

401*9 Comments RESPONSE Distracter B was replaced as requested by Lead Examinier. I 1103 r--- ----- - - - ---- r-------------- --I --- -- ----- -- - - --- - -, r - ------- -- ---- ------- -- - - --- -----------~- - ------ -- -- ---

t~lI!.S!i()fl..8---~~~t§$S;J28~!fl1-i~o~~'!'E!'"------1 rin;~~~ie-;;f th~ ~ffect th..tt al~;;- ~r_;_aTfu~cti~~ ofth~ Rcs-;ill h~v~ ;;-~he-f~lo_;irIg;-( CFR:------

_~

_________ '___ __________.L _________________ J I I~*".':.:**........ *.':*.'::-'-"*-*-*"*".'::-"...... *~*."*------ ____________ ~

__ ~_ ~ __ _

Tuesday, November 10, 2009 Page 71 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 29 General Discussion

,~--~~-

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---

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IThe student must recognize that high speed effects more than just the air flow for the AHU. The student must determine what the higher air flow will impact.

[

I

[The KA is matched because under the conditions where a small NC system leak has occurred in containment, the applicant must determine the effect on containment conditions when ladditional ventilation flow is provided to containment.

l':, _____

~ ____

~ ____ ~ __,_~ ___ ~ ____, __ ~ __ ~ ____,_~ _______,~ ___ ~_,_~~_~ ______, _________

~ _____, __

,~ ____ ~ ____, __ ~_,~_~ _____ _

Answer A Discussion

~~~c);-==-=-=--=-~~-~ ~~~~=~~===============~~--==_-~=-=--_=--_____ -_~=_-_-= _____ ~_-_~_~~_-_-_-~-_=--_=--_-_________==-===-===== =~============J Answer B Discussion r ~~-

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Answer C Discussion

((Incorrect. If the student does not understand the relationship of temperature and pressure or the methodology of dehumidification he will assume only the pressure goes down.

i

-'----~~--'-~-~-------~--~---~~---~~-~~--,~~---~~-~~---,----,-,-----------~-,---~~---,~--~--~---~--,---~--,----,---~,-,---~

Answer D Discussion

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IIncorrect. If the student does not understand the relationship of temperature and pressure or the methodology of dehumidification he will assume only the temperature goes down.

I L ___ ~_,~ _____

~ _,_, _________ ~ __ ~

~ ___ ~ _____,_ ~ _, __, ______ ~,~ _____

~ ___,~ _,_~ ___,~ ___, __ ~ __

,~ _____, ____,_, __

~ ____ ~ ___

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~ Developed

~ OPT Approved

~ CPS Approved

~ NRC Approved iD;velOpment-References-- -- -----

I--'-'~~~~--~'--~- ~-,-,-,----~ -~--

IOP-MC-CNT-VUL pages II, 15, and 17 I

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• ___, _______, __, __,~ __________, ______________ ~ ____,_, ___ ~ __ ~_J Tuesday, November 10, 2009 Page 71 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 30 B

~~sii~~~a~~~~~!Y!t!~=~~-=-n~~~~~====J~~~~~~-~-==-====.==========_==========~~~==~==~=.====~==_.~_~~.~_

I 18~0_~ J __ ~YS~ ~ 4~_ t~.. _~_~ 1.02 ____ J lAbIlity to. predl~t and/or mom tor changes m parameters (to. pre.ve~t e~ceedmg design limits) associated with operatmg the RPIS i~()11tJ:.ols,-lllcl~_Ill~lgB-:..'!.l}'!~s.:~CJ.c:.~t1'o! ~cl..£9~t19E~cl..I~.!.Wll"<>~ contf(jj~~I11.2.at1~~...:.~...... ::.-: __ ~

CURRENT 45 DAY VERSION Given the following plant conditions:

Reactor Startup in progress Control Board Annunciator 1AD-2 / 09 (RPI at Bottom Rod Drop) is LIT.

Which ONE (1) One of the following describes the EARLIEST rod configuration at which 1AD-2/ 09 will dear during the startup?

A.

All Shutdown Bank rods >6 steps.

B.

All Shutdown Bank rods withdrawn AND Control Bank 'A' rods >6 steps.

C.

All Shutdown Bank rods AND Control Bank 'A' rods fully withdrawn.

D.

All Shutdown Bank rods withdrawn AND all Control Bank rods >6 steps.

~---

-.~.

ruesday, November 10,2009 014Al.02 A is a subset ofB.

Ife was correct so would D.

Psychometrics need to be addressed.

RFA 10/27109 Given the following plant conditions:

Reactor Startup in progress IMMEDIATELY after the Control Board Annunciator 1AD-2 09 (RPI at Bottom Rod Drop) extinguishes, the Digital Rod Position Indication (DRPI) displays will indicate which ONE (1) of the following?

A.

All Shutdown Bank rods >6 steps.

B.

All Shutdown Bank rods withdrawn and Control Bank 'A' rods >6 steps.

C.

All Shutdown Bank rods and Control Bank 'A' rods fully withdrawn.

D.

All Shutdown Bank rods withdrawn and ALL Control Bank rods >6 steps.

401*9 Comments:

Page 72 of 185 DISTRIBUTE B

~u~~~:'n:!~A~.~~m5:~n~~x~~~~~.. :c~=~lTES=T!~~_~O== __ -~==_===_==....._-=_... -=- _-=

i 1830 SYS014 I

A 1.02 liAbility to predict and/or monitor changes m parameters (to prevent exceedmg desIgn limIts) assocIated wIth operatmg the RPIS I

FOR REVIEW ONLY - DO I-~---- --~~ J___ ---- -L__ __ ~-----j Icontrols, including: (CFR: 41.5/ 45.5)[iControl ro(lJ~()sitioll~(ii(;1ItioE~llcontf()]~~111J)at1~~~.~...... :~ _____________ i I ______ -.------------------.----~---

CURRENT Given the following plant conditions:

Reactor Startup in progress Control Board Annunciator 1AD-2 / 09 (RPI at Bottom Rod Drop) is LIT.

Which ONE (1) One of the following describes the EARLIEST rod configuration at which 1AD-2/ 09 will dear during the startup?

A All Shutdown Bank rods >6 steps.

B.

All Shutdown Bank rods withdrawn AND Control Bank 'A' rods >6 steps.

C.

All Shutdown Bank rods AND Control Bank 'A' rods fully withdrawn.

D.

All Shutdown Bank rods withdrawn AND all Control Bank rods >6 steps.

-~~-

---

~-.-~- ----_._----------

ruesday, November 10,2009 014Al.02 A is a subset ofB.

IfC was correct so would D.

Psychometrics need to be addressed.

RFA 10/27/09 45 DAY VERSION Given the following plant conditions:

Reactor Startup in progress IMMEDIATELY after the Control Board Annunciator 1AD-2 09 (RPI at Bottom Rod Drop) extinguishes, the Digital Rod Position Indication (DRPI) displays will indicate which ONE (1) of the following?

A.

All Shutdown Bank rods >6 steps.

B.

All Shutdown Bank rods withdrawn and Control Bank 'A' rods >6 steps.

C.

All Shutdown Bank rods and Control Bank 'A' rods fully withdrawn.

D.

All Shutdown Bank rods withdrawn and ALL Control Bank rods >6 steps.

401*9 Comments:

Page 72 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 30 General Discussion ITh~--;iPIatB;tt~-R~d-D~op"cl~~s~;h;;~;;JI-Shutd-;;;~B~nk~~d-;~~-;ithct;.~wn a;dControl Bank 'A' rods are >6 steps.

I I

B IDifficult KIA match as there are no controls associated with the DRPI system to operate which could cause a change in parameters or prevent exceeding design limits. The closest KIA match IPossible is related to the DRPI indications in the Control Room as the system is operated. The "RPI at Bottom Rod Drop" annunciator was chosen since when it clears the indication for a rod Ibeing dropped is now enabled. Additionally, once the rod drop alarm is enabled, if a rod remains on the bottom as the other rods in that bank are withdrawn (>6 steps) the annunciator would

~1llf11l ~()aI~r£tE~o~~~t()f~~d po~eE:t~aBx jJI"~v~nt ~)(c~~din~~~esi~I~'!l~_on the ~filel Q:~ ~p~~k~~ ia~t~rs ). ~ _ ~ ~ ~ __ ~~~ ~ _~ ___ ~ ~ _~ ~ _~ __ ~ ~ ~ ~~ __ ~_~ ___ ~ ~ __ _

Answer A Discussion

-~--

I[Incorrect. Plausible because >6 steps is the correct setpoint for the alarm to clear.

--~---- -- - -

Answer B Discussion I-~----- ---- ----- --------------

I~(")~~~*-- __ __ ~ __

Answer C Discussion

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

-l I

--- - -- - -----)

!Incorrect. Plausible because the Shutdown Banks being withdrawn is correct and clearing the alarm is associated with withdrawal of Control Bank 'A'. However, it is >6 steps withdrawn and

[I1()tfu}Ir_wJt!tdnl~~ __ ~ ___ ~ ____ ~__ ____ _ _~~_~~ _____ ~ ____ ~~ _____ ~ _______ ~ ___ ~~~ _______ ~~ _~ ______________ ~~ ______ ~~ ___ ~

Answer D Discussion r~c;r~~ct~ Pl~u~ibk-b~c-;~s~th~Sh~do-~~-B~~ksb~i;g ~ithd~a~~ i;-c~;~ct ~ndthe~ctp~~t(>6-step;)is~;;~~tH~~~~er, it i~ th~fi~stba;;k(C~~r-;;IBa~k ~~);~d-n~tall C-~~t;ol B~ks~-

r l~~~\\Vit~d!-~w_n>Ji_SteEst~~ ~1~~~tE~ alarIl1~ _______ ~ ________ ~_ ~ _____ ~~ ___ ~_ ~~_~ ____ ~ _ ~ ~~ ___ ~~~~~ __ ~_~~_~ ~_ ~_~~~~ ___ ~_~ ___ ~_~~ ~

Job Level RO

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

--~'~~-'-~-r-*-'-~-

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--~~,~-

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---

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

401-9 Comments RESPONSE Revised stem to more clearly defme a time line to address psychometric issues raised by the Lead Examinier.

--~~-~-

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lAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS

!controls, including: (CFR: 41.5 / 45.5)~Control rod position indication on control room panels................

L-___________

~ ______________________

~

[uesday, November 10, 2009 Page 73 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 30 B

General Discussion IThe--;1ZPI atB;tt~

-R~d-D~op " cl~~s~;h;;~;;JI-Shutd-;;;~ B~nk

~~d-;~~ -;ithct;.~wn a;d Contr;IB-a~k-'A'-r~d-;~r~;6step;. - - -~- ~~- - - ~~- - - - ~

--~ - -- -

- - -~ -- -~-

I I

IDifficult KIA match as there are no controls associated with the DRPI system to operate which could cause a change in parameters or prevent exceeding design limits. The closest KIA match IPossible is related to the DRPI indications in the Control Room as the system is operated. The "RPI at Bottom Rod Drop" annunciator was chosen since when it clears the indication for a rod Ibeing dropped is now enabled. Additionally, once the rod drop alarm is enabled, if a rod remains on the bottom as the other rods in that bank are withdrawn (>6 steps) the annunciator would

~1llf11l ~()aI~r£tE~o~~~t()f~~d po~eE:t~aBx jJI"~v~nt ~)(c~~din~_~e.si~I~'!l~_on the ~filel Q:~ ~p~~k~~ ia~t~rs ). __ ~ _ ~ ____ ~ __________ ~ __ __ ~ ___ ~ ____________ _

Answer A Discussion IIncorrect. Plausible because >6 steps is the correct setpoint for the alarm to clear.

[~--- --

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

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

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

Answer B Discussion I-~--- -- --~- ----- ---- -~------ ---- --- -

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

---

~

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

--~-----------l I~~~~~*-----~----~-----~---------~------------~-----~- __ ~ _____________ ~ ______ ~

___ ~_~_~ ______ ~ _______ ~ _____ !

Answer C Discussion

---

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

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

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

---

~----l ilncorrect. Plausible because the Shutdown Banks being withdrawn is correct and clearing the alarm is associated with withdrawal of Control Bank 'A'. However, it is >6 steps withdrawn and I

lI1()tfu}Ir_wJt!tdnl~n..._____ ___ ___ ___ ____ _ __ ___ ~ _______________________________ ~ _______ ~~ _____________ ~ _______________ ~ I Answer D Discussion r~c~r~~ct~ Pl~u~ibk-b~c~~s~th~Sh~do-~~-B~~ksb~i;g ;ithd~a~~ i;-c~;~ct ~ndthe~ctp~~t(>6-step;)is~;;~~tH~~~~er, it i~ th~fi~stba~k(C;~r-;;IBa~k ~-;-);~d-n~tall C-~~t;ol B~ks--

r l~~~\\Vit~dr~w_n>....§SteEstt.~ ~1~~stE~alarIl1""_ __

_ __ ~ _________________________ ~ ____ ~ ______ ~ __ ~ ___________ ~ ________ ~_~ ______ ~.J

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Question Source

-- ~~~ - -.--~---t--- -- ------- -------- --- -.~- ------ ~---- -~

---~ - -- -

~-- -

401-9 Comments RESPONSE Revised stem to more clearly defme a time line to address psychometric issues raised by the Lead Examinier.

RO

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved BANK I

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lAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS

~l1t~oI~ ~~~(liE_L<:g~~:_ ~lJJ~~*~S~C..<>l1!l"oI~0~2()sJtion ~ncli<:~ti<l~.c>.I1.~~tl"oI~~!l1jJ~1s.... :-:... ~.~..... _ ~_

[uesday, November 10, 2009 Page 73 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE c __

2009 RO NRC Retake Examination QUESTION 31

'~-~~'~'~--'-~'--,-~~~ ~----"T-~-

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IQueatlonBank # IKA_syatem IKA_number KA_deBe f~~-~~-~-~-I~~-~~'~~~T~~--~'~'-

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1831 I

SYSO 17 I

K6.0 I IKnowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7 145.7)[1 Sensors and L_~~~,~~_,_ -,~~,~,~,~,~~-- ~,--~~~-,-- ---~

lc!~e<.:t<JE~_~,_~ ___ ' _____ ' _______ '_~_, ______,~ __, __ ~, ______, _____ ~ ___ '_' ______, ___ _

CURRENT Given the following conditions on Unit 1 :

• Unit is operating at 100% RTP

• It is discovered that ONLY three (3) Gore Exit Thermocouples (GETs) are OPERABLE in core Quadrant 2 Which ONE (1) of the following describes the status of GETs in Quadrant 2 and the requirements ofTech Spec 3.3.3 (PAM Instrumentation) at the time of discovery based on these conditions?

A B.

G.

D.

REFERENCE PROVIDED Both channels of GETs are INOPERABLE. Immediately restore one channel to OPERABLE.

Both channels of GETs are INOPERABLE. Restore one channel to OPERABLE within 7 days.

One channel of GETs is INOPERABLE ONLY. Restore required channel to OPERABLE within 30 days.

One channel of GETs is INOPERABLE ONLY. Initiate the actions of T.S. 5.6.7 immediately.

017K601 45 DAY VERSION Given the following conditions on Unit 1 :

• Unit is operating at 100% RTP

• It is discovered that ONLY three (3) Gore Exit Thermocouples (GETs) are OPERABLE in core Quadrant 2 Which ONE (1) of the following describes the status of GETs in Quadrant 2 and the requirements ofTech Spec 3.3.3 (PAM Instrumentation) if any, based on these conditions?

A.

B.

G.

D.

REFERENCE PROVIDED Both channels of GETs are OPERABLE. No further actions required.

Both channels of GETs are INOPERABLE. Restore one channel to OPERABLE within 7 days.

One channel of GETs is INOPERABLE. Restore required channel to OPERABLE within 30 days.

One channel of GETs in INOPERABLE. Initiate the actions ofT.S. 5.6.7 immediately.

401-9 Comments:

I do not see where "A" is plausible given the circumstances.

Replace "A" or prove plausibility.

RF A 10/08/09 CAF: Must demonstrate plausibility fuesday, November 10, 2009 Page 74 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 31 c

[t§\\~~~c~=-~=-~=-== =-=-= =

=-==~_=-==-=-==-====-=-===-==~~~=-=-=== =-==-=-==~=--==-=-=-===-===-=-=-=== ]

iKnowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7/45. 7)uSensors and I

lc!~e<.:t<J~~:...:.. :..:..~*.. *:..:..~*~*~*.~*.:..~,,~ ____ ~~ ________ ~_~ ___ ~ _____ ~ ____ ~_~ __ ~~_. ________ --.!

CURRENT Given the following conditions on Unit 1 :

• Unit is operating at 100% RTP

• It is discovered that ONLY three (3) Gore Exit Thermocouples (GETs) are OPERABLE in core Quadrant 2 Which ONE (1) of the following describes the status of GETs in Quadrant 2 and the requirements ofTech Spec 3.3.3 (PAM Instrumentation) at the time of discovery based on these conditions?

A B.

G.

D.

REFERENCE PROVIDED Both channels of GETs are INOPERABLE. Immediately restore one channel to OPERABLE.

Both channels of GETs are INOPERABLE. Restore one channel to OPERABLE within 7 days.

One channel of GETs is INOPERABLE ONLY. Restore required channel to OPERABLE within 30 days.

One channel of GETs is INOPERABLE ONLY. Initiate the actions of T.S. 5.6.7 immediately.

017K601 45 DAY VERSION Given the following conditions on Unit 1 :

• Unit is operating at 100% RTP

• It is discovered that ONLY three (3) Gore Exit Thermocouples (GETs) are OPERABLE in core Quadrant 2 Which ONE (1) of the following describes the status of GETs in Quadrant 2 and the requirements ofTech Spec 3.3.3 (PAM Instrumentation) if any, based on these conditions?

A.

B.

G.

D.

REFERENCE PROVIDED Both channels of GETs are OPERABLE. No further actions required.

Both channels of GETs are INOPERABLE. Restore one channel to OPERABLE within 7 days.

One channel of GETs is INOPERABLE. Restore required channel to OPERABLE within 30 days.

One channel of GETs in INOPERABLE. Initiate the actions ofT.S. 5.6.7 immediately.

401-9 Comments:

I do not see where "A" is plausible given the circumstances.

Replace "A" or prove plausibility.

RF A 10108/09 CAF: Must demonstrate plausibility fuesday, November 10, 2009 Page 74 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 31 General Discussion RFA 10/27/09 I do not see where "A" is plausible given the circumstances.

Replace "A" or prove plausibility.

RF A 10/08/09 iT~~sp~-ii3~PAMI~-;:-u~m;tic;~ ~equire~ha~~eTsp~-;;~;qu;d~~tb~~e~abki~-MODES-C2,-~d3;itht~-~p~;;ble-dett;ct~;-~;-ch;~el.

I c

IThe KA is matched because the applicant must take a given set of conditions and apply technical specifications to determine the operability of the system and the required actions. In doing so,

~h~ <leP!i~~~~u~t ~~mol1~~t~ Ql~~ ~ex ~o~t11ejJff"eI"e~~~etw~I1~~ op~r~~~d~~~())"_~d_al1~~er~1:l1t: ~h~n~L Answer A Discussion

[n~~~~t!l~~i~:~ ~~,:PJ~~~t=d~~ot~~~ers~ct:ha~ ~ith} _ d-=~ct()r~ opef<l~I=~-=~ ~':'~~ be one operable channel..

I

__ I Answer B Discussion

---

~--- - -- ----

l~n~()f~ct*!~a_u~~I~ i~tI1~ ajJ~l~cant ~~~ ~~ llrl<i~rst~~!~t wi~

_3_d~t~ct0!~~~':!JIe, ~h~-= ~a:~o_b~~~_oE~~~ec~~~~~e ~ct~~ i~l:O_rre,= ___ _

Answer C Discussion iCOIUtECT.-'------- ---,---------------,-- ----- ---- -------- - --,---- -----,---- ---- - -'-' -- --------

1 _______,_

Answer D Discussion iIn~~~Zt:-P1~~;;;ble be-;;;u;~~e Zh~n~Ti;i~~per~W;:H~;e~~r ~ the-i~ ~o-i~f~rmatio~ to-i~ply th;tthe-LCOti~e h~ be~~~x~e~ded.- --- -

1 ____

~ ____________________________________. _______________________________

~ _______________ ~

--'---------------1---'----'----,-----'-'----'---------,-----,-----,-

cog!1i!~!!:~"'_e_'_ ___ r-q~e~!'-~"-TX~~------ ____________ ~u~~t~oE_Source

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~I11~~h~11s~0~

_ J ____ ~!~ ____ 1 _________ _

~!~e}~~e=ni ~~f!r!~~!:s=====-----------

iLesson Plan OP-MC-IC-ICM Objective 19 rTech Spec 3.3.3, PAM Instrumentation i

I I L ______

iStudent-ReferencesProvlded -- ---

I::------~------------

rCopy ofTS 3.3.3 (Q3l) i I

r I L ____ ~

~ _________

~ __________________ _

401*9 Comments RESPONSE The distracter analysis is fine as written, should be able to convince Ron iliat this one is plausible. No Changes, will discuss during review. (See comments for better explination)

~ue8tlonB;nk-iti<A -system- -fKA number

- ---- ---~-,---I'-- =-----~-_t ---=--- ------- -'--j l831lSYSOl7 rK6.01 I

~-=~!~-_-_=~~-_~-~~=-=-=--_~ ~-_-_-~-_-_ -_-= ~-_~-~_ =~_-_~ __ -~==-=-=-=--= =-=-== -_ =-_ =

=-.~.=-===-=~=-=-=-=-1 IKnowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7 /45.7) [J Sensors and I

_______ J____ _ __ _ _ --1 __, ______, ___, ___ J I(It:~ct~~ ___ *~........ *~-::.. *~~*~:~.. *.. ** __ *~: _____________________________________________________ J ruesday, November 10, 2009 Page 75 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 31 General Discussion RFA 10/27/09 I do not see where "A" is plausible given the circumstances.

Replace "A" or prove plausibility.

RF A 10/08/09 c

I-~-~-~*~------ ------

---

~~ -

-.-~- -

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

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

---

~

-.-.~----- --- -~---,

ITech Spec 3.3.3, PAM Instrumentation requires channels per core quadrant be operable in MODES 1,2, and 3 with two operable detectors per channel.

1 I

IThe KA is matched because the applicant must take a given set of conditions and apply technical specifications to determine the operability of the system and the required actions. In doing so, I Ithe applicant must demonstrate that they know the difference between an operable detector and an operable channel.

I L ______, __________________________________

~ ________________________

~ ___________

~ _____________________

~ _____________

Answer A Discussion I-~-~---*~----*~----- -----

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

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

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

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

~~~------,

IIncorrect. Plausible if the applicant does not understand that with 3 detectors operable, there has to be one operable channel..

I L ____________________________ ~

~ _______________ J Answer B Discussion l~n~()f~ct*!~a_u~~I~ i~tI1~ a)J~I~cant ~<>e~ ~~ llrl<i~~t~~!~t wi~

_3_d~t~ct0!~':l'~il!JIe, ~h~~ ~a:~o~b~~~~oE~~~ec~~~~~e ~ct~~ i~l:O~rre,= ________ ~ __

Answer C Discussion iCollicT.-*----~----------------~--------

---

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

---

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

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

~--.----

1 _______. ______ ~

_____ ~ ______. _______ ~ _______ ~ _______ ~ ___ ~~ ____. __ ~~ _____ ~ ____________ ~ ___________ ~ _________ ~

________ ~__

_ _ ~ ___. __

Answer D Discussion iIn~~~Zt:-P1~~;;;ble be~~u;~~eZh~n~Ti;i~~per~W;:f.I~;e~~r~the-i~ ~o~i~f~rmatio~ to-j;!lply th;tthe-LCOti~e h~ be~~~x~e~ded.- -~- - --------~ ~----

- -~-- -- -

1 ____

~ _________, _____________, _________, __. ______________________, ________

~ _____, _________ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~!~e}~~e=ni ~~f!r!~~!:s=====_========--

iLesson Plan OP-MC-IC-ICM Objective 19 ITech Spec 3.3.3, PAM Instrumentation i

I I L __ ~

. ________________ ~_~_

iStudent-ReferencesProvlded -- - --- -

ICopy-;fTS3.33(Q31)- -~~-~

i I

I L __________________.~ __ ~ ____ _

one is plausible. No Changes, will discuss during review. (See comments for better explination)

~U_!!tI~~;~:fil~sy;!!nLT~~~,.n~_~~ __ -_-=~ ~-=~!~-_-~= ____ ~~ __ -== ______ -_____ ~_-_-~-_-_ -_-= __ -_____ -~_ =~_-_

_=__ ~-== ________ -= ________ -________.~.= _________ ~ __________ 1 183 ~SYSOI7..

IK6.0 1..

I IKnowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7/ 45.7)[JSensors and I

-- ------~-~-- -- _-1 _____ --~~- -~ _~J 1(.It:~ct~~-".................... :.............. :.......... _".:.. ______ ~ ____ ~_~ _____________________________________ J ruesday, November 10, 2009 Page 75 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 31 c

Tuesday, November 10, 2009 Page 76 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 31 c

Tuesday, November 10, 2009 Page 76 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 32

~~~~n~~n~ ~~Aj~!e~l~:;;"'~~~ ~--~~J f'=~!~~=-=- ~~ =-==-~~---==~~-~=-----=----~=-=-== -==-== ~==-=-=-=--=~~=----==---=-===-=-=~==- ~====-= ~=~-

i 1832 L SYS029 I

A2.03 i lAbility to ~a). predict the impacts of the following malfuncti.ons or operations on the Containment Pu.rge System; ~d (b) based on

-~-~-- -- -- --- -- -~-------- ----- Ithose predictIOns, use procedures to correct, control, or mitigate the consequences of those malfunctIOns or operatIOns: (CFR: 41.51 l4~.5l~l*~~5 __ I:3Jr::'~t~llE~~r~t0~s~I1CI ~~~s~~~~e~(Jl~ir"~ va~~}iIle~p~ ~~.. ~._. ~ __

~~ _____________ _

CURRENT 45 DAY VERSION Given the following conditions on Unit 2:

Unit is in Mode 5 Containment personnel airlocks are currently in service VP Train B is being placed in service Containment pressure begins to increase at 0.1 PSIG per minute An Operator in the plant reports that supply and exhaust flow rates indicate flow is balanced Which ONE (1) of the following is the probable cause of the Containment pressure increase and how can it be stabilized per OP/1/A/6450/015 (Containment Purge System)?

A B.

C.

VP SUPPLY AIR FLOW indication is reading LOWER than actual flow.

Supply flow to Containment must be DECREASED.

VP EXHAUST AIR FLOW indication is reading HIGHER than actual flow.

Exhaust flow from Containment must be DECREASED.

VP SUPPLY AIR FLOW indication is reading HIGHER than actual flow.

Supply flow to Containment must be INCREASED.

D.

VP EXHAUST AIR FLOW indication is reading LOWER than actual flow.

Exhaust flow from Containment must be INCREASED.

029A2.03 Unit 2 has entered Mode 5 for a refueling outage. Containment personnel airlocks are currently in service. VP Train B is being placed in service.

Containment pressure begins to increase at 0.1 PSIG per minute An Operator in the plant reports that supply and exhaust flow rates indicate flow is balanced Which ONE (1) of the following is the probable cause of the Containment pressure increase and how can it be stabilized?

A.

B.

C.

D.

VP SUPPLY AIR FLOW indication is reading LOWER than actual flow.

Supply flow to Containment must be DECREASED.

VP EXHAUST AIR FLOW indication is reading HIGHER than actual flow.

Exhaust flow from Containment must be DECREASED.

VP SUPPLY AIR FLOW indication is reading HIGHER than actual flow.

Supply flow to Containment must be INCREASED.

VP EXHAUST AIR FLOW indication is reading LOWER than actual flow.

Exhaust flow from Containment must be INCREASED.

401-9 Comments:

Identify the procedure that must be used to support the second part of the KA.

..... and how can it be stabilized as stated in procedure ___ _

RF A 10/28/09 Tuesday, November 10, 2009 Page 77 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 32 CURRENT Given the following conditions on Unit 2:

Unit is in Mode 5 Containment personnel airlocks are currently in service VP Train B is being placed in service Containment pressure begins to increase at 0.1 PSIG per minute An Operator in the plant reports that supply and exhaust flow rates indicate flow is balanced Which ONE (1) of the following is the probable cause of the Containment pressure increase and how can it be stabilized per OP/1/A/6450/015 (Containment Purge System)?

A B.

C.

VP SUPPLY AIR FLOW indication is reading LOWER than actual flow.

Supply flow to Containment must be DECREASED.

VP EXHAUST AIR FLOW indication is reading HIGHER than actual flow.

Exhaust flow from Containment must be DECREASED.

VP SUPPLY AIR FLOW indication is reading HIGHER than actual flow.

Supply flow to Containment must be INCREASED.

D.

VP EXHAUST AIR FLOW indication is reading LOWER than actual flow.

Exhaust flow from Containment must be INCREASED.

029A2.03 45 DAY VERSION Unit 2 has entered Mode 5 for a refueling outage. Containment personnel airlocks are currently in service. VP Train B is being placed in service.

Containment pressure begins to increase at 0.1 PSIG per minute An Operator in the plant reports that supply and exhaust flow rates indicate flow is balanced Which ONE (1) of the following is the probable cause of the Containment pressure increase and how can it be stabilized?

A.

B.

C.

D.

VP SUPPLY AIR FLOW indication is reading LOWER than actual flow.

Supply flow to Containment must be DECREASED.

VP EXHAUST AIR FLOW indication is reading HIGHER than actual flow.

Exhaust flow from Containment must be DECREASED.

VP SUPPLY AIR FLOW indication is reading HIGHER than actual flow.

Supply flow to Containment must be INCREASED.

VP EXHAUST AIR FLOW indication is reading LOWER than actual flow.

Exhaust flow from Containment must be INCREASED.

401-9 Comments:

Identify the procedure that must be used to support the second part of the KA.

..... and how can it be stabilized as stated in procedure ___ _

RF A 10/28/09 Tuesday, November 10, 2009 Page 77 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 32 A

General Discussion r;:~~- -~~

~--~

-~

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

~ -~-- -

---

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

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

---~

---

~-

-~---

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

~

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

iThe system is placed in service per OP/I! A/6450/0 15 (Containment Purge System) Enclosure 4.2 (VP System Startup) Step 3.24.2 states directs the operator the check the Total Supply and I,Exhaust Air flow equal to prevent placing containment vessel under a positive or negative pressure. It then provides guidance to adjust the airflow as needed~

I IMore air is being supplied to containment than is being exhausted which has resulting in an increase in containment pressure. This has been caused by the fact that I VPPG9140 Supply Air IFlow is indicating low or I VPPG9250 Exhaust Air Flow is indicating high and the subsequent flow balance based on the erroneous indication is admitting more air to containment than is

[being exhausted. To correct the imbalance, supply air flow must be decreased or exhaust air must be increased.

i I

IThis KA is matched because the applicant must evaluate and adverse condition (containment pressure increasing) that has resulted from operation of the Containment Purge system during

!startup of the system and determine what actions must be taken to correct the problem.

[

IThis is a comprehension level question because the applicant must analyze the given indications, determine what is causing the containment pressure increase, and determine what erroneous

~ndicaQ~n! ~llI~~~ !~~t~d J~1lI1~llian~~}~t~e_s_upjJIx1ll1~~~llU!t flo~~ _______________ ~ ____________ ~ ____________________ ~ _______ ~

Answer A Discussion

~~~~!.~~=-=====------------------

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

Answer B Discussion r-

~~~~-- - -

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

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

~-

~---~ --

--~~-~

---~~- -

---

~-~--

-~-~-

---~-~-

-~--~~-~- -

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

iIncorrect. First part could be correct. However, if Exhaust flow was indicating higher than actual the correct action would be to increase exhaust flow to balance the Supply and Exhaust Iflows~

L __

~ ____

~ ________________

~ ___________________________________________________________________ _

Answer C Dfscusslon

~~~~ct.F~~ parti;Zo~~ct.c~~tain~ntPr;s~~ -~~~d-b~d~r~~~ii-i a~h;~ -;-upPly~flo; ~~s-< indi;;;ed.-S~c~ndp~rt isi~~~~t.I~c~~~g ~~pply -fl~;_~d~;~i~g-e)~i;~~t-fu;;--I 1v.'()lj!9 ~~t~e~orI'e~~cEonJor ~o_n~i11IEent PEe~sll~~e~r~~ing. __ ~~_~ ____________ ~ _~ _~ _________ ~ __ ~ ___ ~ __ ~ ______ ~_~ ~ _____________ ~J Answer 0 Discussion rI~~;'e~t~Th~ fir-;-tp~rtis~i~c~~;e~t~If~xh~~~flo~-;~ r~~di~g-l~;e~th;n ~ct~aTflo;,-c~rrt~n~~rrtpr~s;u~e-w~~db~ de~r~~i~g-:-I~~~e~ing ;~;u;fl~w-~~ld'Zo~~tthis-p~obl~m.

l, ___

~ _______

~ ____________

~ ___

~ ______

~ ________________. ____________________________________________________

r-~-~-- --- -

~

~~ -"'~~ ~e-,,~I_

__ ~~fl~~v~L.!~el Questlo-oType ~ r -----

~~~~ ----

Question Source

~-L~_~~_ ~~~_~_~

__ + __ ~~~

_~~~ __

~ ___ ~~~ ____

~~ _~~ ______ ~

401-9 Comments RESPONSE Procedue added to the stem ofthe question. The procedure and the reference l ___ ~~ __

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension BANK I

2006 NRC Q61 (Bank 667)

~ __

~ _____

~ ____ L_~~~_ ~ _____ ~

1.----- - -

-~~-~~- ~ -

--~-~ -

-~

~-

~-~~-~~-

-~-

~

l~~!'~~~e~~~~~"!'!c~~ ________ ~_~_ 1~~~~'!tB~ft)~!l~! ~1'O... i~~d _

iLesson Plan OP-MC-CNT-VP Objective 2 & 4 Section I

13.1.2 1

I

'I L~ __ ~ _____ ~ ________ ~~ _____ ~~__ _

_ __ ~~ _____ _

_ section which provides this guidance was added to the distracter analysis the question reference folder.

---~~~--

--~ -~-1-- --- -

r~----

9ue!~on~!I'!~i#j~~ls~_"! _ ~..,,!umber

_ =1 ~=-~e~~ -=--_ ~_ -=-=~-=-=~=~-=--=-= _=_-=_ -_= -=--=- -=--=- ___ = _ -=--_ -=-_=_ _=_ =_-=-=-_-= ___ =~ ___ ~_-=-==_ -=-_=_=_ ___== =_=__=_ =--

I lAbility to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based

--~

__ J ion those predictions, use procedu~es to correct, c~ntrol, or mitigate ~he conse~uences of ~hose malfunctions or operations:

I(CFR: 41.5 /43.5/45.3 / 45.13)~IStartup operatIOns and the assocIated requIred valve lmeups.............

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

---

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

---

~---- -"-

18321SYS029 IA2.03

__ ~_ ~ L ______ ~

_~ ~ __ ~ __

Tuesday, November 10, 2009 Page 78 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 32 A

General Discussion r;:~-- --- ---- ~- --- ~-~--~---- -

-~-- -

---

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

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

---

~~ -~---

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

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

iThe system is placed in service per OP/I! A/6450/0 15 (Containment Purge System) Enclosure 4.2 (VP System Startup) Step 3.24.2 states directs the operator the check the Total Supply and I,Exhaust Air flow equal to prevent placing containment vessel under a positive or negative pressure. It then provides guidance to adjust the airflow as needed.

I IMore air is being supplied to containment than is being exhausted which has resulting in an increase in containment pressure. This has been caused by the fact that 1 VPPG9140 Supply Air IFlow is indicating low or 1 VPPG9250 Exhaust Air Flow is indicating high and the subsequent flow balance based on the erroneous indication is admitting more air to containment than is

[being exhausted. To correct the imbalance, supply air flow must be decreased or exhaust air must be increased.

i I

IThis KA is matched because the applicant must evaluate and adverse condition (containment pressure increasing) that has resulted from operation of the Containment Purge system during Istartup of the system and determine what actions must be taken to correct the problem.

[

IThis is a comprehension level question because the applicant must analyze the given indications, determine what is causing the containment pressure increase, and determine what erroneous

~ndicaQ~n! ~III~~~ !~~t~d J~~~llian~~}~t~e_s_upjJIxill1~~~llU!t flo~~_~ ____ ~ __________________________ ~ _______ ~ _____ ~ _____ ~ ___ ~

Answer A Discussion

~~~~!.~~=_-==== =-==~-=~~ =~=-_-~~= =-=~~ ~==-=~==-==~ -========~========-= =

====-==-===-=-=====_====-=-===-=====-=====J Answer B Discussion r-

-~-~-- - -

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

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

~-

~--~- --

--~---

-~-~-~ -

---

~----

-~~--

~--~--~

-~~--~-~- -

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

---~-~--

iIncorrect. First part could be correct. However, if Exhaust flow was indicating higher than actual the correct action would be to increase exhaust flow to balance the Supply and Exhaust I

Iflows.

I L __

~ ____

~ ________________

~ _______________________________________________________________________________________________ -.1 Answer C Dfscusslon

~~~~ct.F~~ parti;Zo~~ct.c~~tain~ntPr;s~~ -~~~d-b~d~r~~~ii-i a~h;~ -;-upPly-flo; ~~s-< indi;;;ed.-S~c~ndp~rt isi~~~~t.I~c~~~g ~~pply -fl~;_~d~;~i~g-e)~i;~~t-fu;;~-I lv.'()lj!9 ~~t~e~orI'e~~cEonJor ~o_n~i11IEent PEe~sll~~e~r~~ing. ________________ ~ _________________ ~ _____________________ ~ _________ J Answer 0 Discussion I--~-'-

-,~- -

---

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

---

~------ -

-~-- ----

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

-~-~--I

[Incorrect. The first part is incorrect. If exhaust flow was reading lower than actual flow, containment pressure would be decreasing. Increasing exhaust flow would correct this problem.

I l ____

~ _______ ~ ____________

~ ___

~ ______

~ ________________. _______. _____ ~ __________

~ ___

~ _________________________________________________________ J

- - Cognitive Leve,---r-Questlo-oType -T--~------ ----Q--stl~-SourCe------~- ----~~1 401-9 Comments RESPONSE

---

---- _~_l~ ___ ~ _____ -+~ __________ ~ ___ ~e_y-"'-_ ---- --~~---------l Comprehension I

BANK I

2006 NRC Q61 (Bank 667)

I Procedue added to the stem ofthe

___ ~_L_~

__ - --~----~-- -- -------- ------ ------~-

question. The procedure and the reference

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

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

-~~-

l~~!,~~~e~~~~Et-"!'!C~~ _____ ~~ __ ~ __

iLesson Plan OP-MC-CNT-VP Objective 2 & 4 Section 13.1.2 I

1

'I L~_ ~~ __ ~ ___________ ~ __________ _

---~-~--

--~ -~-1-- ----- - r-----

-~-~---~~~--"

~~jt!~¥~~~~~!f~~i~~

~~~~ -- ~~-

~~~~nt:~~~fs~;:~!~s a~!~y~~;~~~~eu:s~~on I

reference folder.

IKA desc r~=--~----~~---

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

~- ---- ---

---

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

lAbility to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based 9ue!!!on~!I'!~i#J~~ls~_"!_ ~..,,!u~b~E __ ~ __ j 1832 1SYS029 IA2.03 I

Ion those predictions, use procedu~es to correct, c~ntrol, or mitigate ~he conse~uences of~hose malfunctions or operations:

1~£~~J*~_~~~

_L~5.3} ~5.!3l~~StaJ1:'P_op~a!J()~~c!tl1~

asso~ll!ed ~<Lull'~d_valve Jl~e~IJs~.~.~~. _____ ~ ________ _

__ ~ __ L___ _ ___

_~ ~ __ ~__

_~ _____ J Tuesday, November 10, 2009 Page 78 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 32 DISTRIBUTE A

fuesday, November 10, 2009 Page 79 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 32 A

fuesday, November 10, 2009 Page 79 of 185

C FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 33 I~~

-~~--

-~- -

~~--

~~~-~~~,------

-~~-~---~-l

~~~~ -

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

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

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~~~

l~~~I~~~~~=t~)~~;~ i~~~!!j~

~~~~_-j ~li~e~£~O~i~~ ~to-;~tic-op~~t~~~fthe F~clH~dlingSyste~,~i;;-cludi~g: (CFR~I~7!4S:-5)UHighflu~~tshutdown 1:-: :-::-:~::'-':-: ~.~:-:~..,.. ".,.. ".,....

CURRENT Given the following conditions:

Reactor is in MODE 6 Core reload is in progress Source range instrument N31 has read approximately 80 CPS for the past hour Electronic noise from a welder inadvertently caused N31 to reach 3000 CPS for 30 seconds Which ONE (1) of the following describes the correct plant response?

A

8.

C.

D.

If a VQ release is in progress, it should be secured.

The Containment Purge Supply and Exhaust dampers close ONLY.

The Containment Evacuation alarm sounds.

A Containment Ventilation Isolation actuates.

034A303 Revisited No comment at this time RF A 10/28/09 fuesday, November 10, 2009 45 DAY VERSION Given the following conditions:

Reactor is in MODE 6 Core reload is in progress Source range instrument N31 has read approximately 80 CPS for the past hour Electronic noise from a welder inadvertently caused N31 to reach 3000 CPS for 30 seconds Which ONE (1) of the following describes the correct plant response?

A.

If a VQ release is in progress, it should be secured.

8.

The Containment Purge Supply and Exhaust dampers close ONLY.

C.

The Containment Evacuation alarm sounds.

D.

A Containment Ventilation Isolation actuates.

401-9 Comments:

Page 80 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 33 Given the following conditions:

Reactor is in MODE 6 Core reload is in progress Source range instrument N31 has read approximately 80 CPS for the past hour Electronic noise from a welder inadvertently caused N31 to reach 3000 CPS for 30 seconds Which ONE (1) of the following describes the correct plant response?

A

8.

C.

D.

If a VQ release is in progress, it should be secured.

The Containment Purge Supply and Exhaust dampers close ONLY.

The Containment Evacuation alarm sounds.

A Containment Ventilation Isolation actuates.

034A303 Revisited No comment at this time RF A 10/28/09 fuesday, November 10, 2009 Given the following conditions:

Reactor is in MODE 6 Core reload is in progress Source range instrument N31 has read approximately 80 CPS for the past hour Electronic noise from a welder inadvertently caused N31 to reach 3000 CPS for 30 seconds Which ONE (1) of the following describes the correct plant response?

A If a VQ release is in progress, it should be secured.

8.

The Containment Purge Supply and Exhaust dampers close ONLY.

C.

The Containment Evacuation alarm sounds.

D.

A Containment Ventilation Isolation actuates.

401-9 Comments:

Page 80 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination Genera' Discussion No comment at this time RF A 10/08/09 QUESTION 33 c

Wthe Thgh-FI~~tSh~tdo~~;i;~~bl~~k~d-o-n th~~ff~~U:d~~rce r~n-g~in~t~u~~~~hi~hit ;~uldb~ ~~ci~d t;-b;i~ M~&-6

-d~ring~~~;Jt~r~tio;~~~-i~c-;:e~;-e i;~~nt ;;k i~-e-;;~;s ~f-I.S decades above background would result in the actuation of the containment evacuation alarm. A related alarm which would result in a containment evacuation alarm would be a Trip 2 Ifrom on the containment radiation monitors, lEMF 38,39 & 40. This would also result in a containment ventilation signal which in tum isolate a VQ release, VP release and secure the I

fl icontamment oor eqUIpment sump pumps.

i lIt is not possible to completely match this KA at MNS because there is no automatic action associated with the fuel handling equipment affected by a high flux shutdown alarm. A high flux lat shutdown alarm would actuate a containment evacuation alarm which would require fuel handling activities to be suspended, equipment to be placed in a safe configuration and the fuel

!handling crew to leave containment. With this in mind, the question is testing the candidates ability to monitor what should have occurred in the event of a high flux at shutdown alarm.

I I

iThis is an analysis level question since the applicant is given a set of plant conditions and is required to recall from memory the setpoint for high flux at shutdown to determine what automatic lacti()"'~~~lIl~ 1111"e...oc(;uE'ed.________________________________ _____ ___ __ _________ _______ _________________ __ _____ _

_ _____ 1 Answer A Discussion r-- ----.- -.-.- ----.- ------- --.---- -- ----- -.-----.------ - ------ -.-- -----.. -------.- --- -------.-------.----.--.- - ------.----- --.-

IIncorrect: A VQ release be unaffected. Plausible: If the candidate believes the high flux condition described should have resulted in a containment ventilation isolation signal then this Lw_ould./J~~ cOlTec~atls..w~.£. ___________ _

Answer B Discussion r~~;;-;e~t:AV-P rel~se ;o~idb~ ~n~ffec~d~Pht~sible~ :-Ifthe-Za~did~te b~I-~~~ -th~highfl~x-c~~iti~~ de-;-c-;:ibed~h~~dh-a~~-r~s~itedin-'; c~nt~i~~e~t ~~ntil~tio~-i~httio_;;sig~al then this Iwould be a correct answer

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

~-

--~---- -- --

Answer C Discussion iL~O~~l:_~;~-~~~~~tio~ above Answer 0 Discussion

---~---- -- --,----- ---- -

---

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

--~--- --

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

---

--- --- -- --.- - ---- -- ----- -----.-- ------.---.-- ----- -----1 IIncorrect: Containment sump pumps would be unaffected. Plausible If the candidate believes the high flux condition described should have resulted in a containment ventilation isolation I~i~_alt~e_n!hi~ ""olJl9jJ~ l.l_c.0lT~c.!..~n~_~.r-.___ ___ _ ____ __ _____ _____ __ ________ __ ____ ___ ___________ _____ _ ____ ___ _ _ _ _

_ __ __. _J Job Level RO

-=_-~~i~I~~e=~ttV~ =-=-I=-~~~~i~=_ 1=====-=-== =-=-_~ =-==-_=~u~~t~!' _S_o~l'C~

Comprehension 1

BANK I

MNS Exam Bank Question AICENBROS

___. ____. __________ L

---I 401-9 Comments RESPONSE

---

1 I Considered SAT for submittal with no

'-.- _...J comments. No changes.

~ Developed r------- - -- -.-.. -.--- -- -- -----

r---' -. -.- ---

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

~~~v.e~PIll~Il~ ~e!!r~ll~e~_ ___ _~_

f~t.u~!,!!_~~er!..nc~~r()~id!<! ___ _

ILesson Plan IC-ENB Rev 27 Pg 19 I

I

'rLeaming Objective: OP-MC-IC-ENB Obj # 4 j

I I

i

~ OPT Approved

~ OPS Approved

~ NRC Approved I

L_._~ _______________. ____________.

)~~stionBank -#IKi ___ sys-iem -IKA-=nulllbe~-

.----- --- -.-1---------.-1-----.-----

l8331SYS034 IA3.03

___. _. __._1.. _._. __. ____.L ___.'

r~-=d~!i_=-=-=_==-_ =_-=-=_-=_===_==== = _=_===== _-==_====-====- ----=~=======~=== -- --

lAbility to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7/ 4S.S)fJHigh flux at shutdown 1 __.. _

Tuesday, November 10, 2009 Page 81 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination Genera' Discussion No comment at this time RF A 10/08/09 QUESTION 33 c

Wthe Thgh-FI~~tSh~tdo~~;i;~~bl~~k~d-o-n th~~ff~~U:d~~rce r~n-g~in~t~u~~~~hi~hit ;~uldb~ ~~ci~d t;-b;i~ M~&-6

-d~ring~~~;Jt~r~tio;~~~-i~c-;:e~;-e i;~~nt ;;k i~-e-;;~;s ~f-I-S decades above background would result in the actuation of the containment evacuation alarm_ A related alarm which would result in a containment evacuation alarm would be a Trip 2 Ifrom on the containment radiation monitors, lEMF 38,39 & 40_ This would also result in a containment ventilation signal which in tum isolate a VQ release, VP release and secure the I

fl icontamment oor eqUIpment sump pumps_

i lIt is not possible to completely match this KA at MNS because there is no automatic action associated with the fuel handling equipment affected by a high flux shutdown alarm_ A high flux rat shutdown alarm would actuate a containment evacuation alarm which would require fuel handling activities to be suspended, equipment to be placed in a safe configuration and the fuel

!handling crew to leave containment. With this in mind, the question is testing the candidates ability to monitor what should have occurred in the event of a high flux at shutdown alarm_

I I

iThis is an analysis level question since the applicant is given a set of plant conditions and is required to recall from memory the setpoint for high flux at shutdown to determine what automatic lacti()"'~~~lIl~ 1l11"e...oc(;uE'ed-_______________________________ _ _____ ___ __ _________ _______ ___________ ______

_ ______________ 1 Answer A Discussion r-- ------ ----- ------ ------- -- ----- -- ----- - ------------- - ------ ---- ---------------- --- ------------------------- - ------------ ----

IIncorrect: A VQ release be unaffected_ Plausible: If the candidate believes the high flux condition described should have resulted in a containment ventilation isolation signal then this Lw_ould./J~~ cOlTec~at1s..w~.£. ___________ _

Answer B Discussion r~~;;-;e~t:AV-P rel~se ;o~idb~ ~n~ffec~d~Pht~sible~ :-Ifthe-Za~did~te b~I-~~~ -th~highfl~x-c~~iti~~ de-;-c-;:ibed~h~~dh-a~~-r~s~itedin-'; c~nt~i~~e~t ~~ntil~tio~-i~httio_;;sig~al then this Iwould be a correct answer

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

---

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

---

~---- -- --

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

Answer C Discussion iL~O_~~~:_~e~ ~~~~~ti~~ ilb~~e ____________________ _

Answer 0 Discussion

---~---- -- --,-

--~-----

--~--- --

-~---

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

---

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

]Incorrect: Containment sump pumps would be unaffected_ Plausible If the candidate believes the high flux condition described should have resulted in a containment ventilation isolation i

r~i~_altlle_n!hi~ ""olJl9jJ~ l.l_c.0lT~c.!..~n~_~.r-____ ___ _ ____ __ _____ _____ __ ________ __ ____ ___ ___________ _____ _ ____ ___ __ _ _

_J Job Level

---

~--- ------

RO

-=_-~~i~I~~e=~ttV~ =-=-I=-~~~~i~=_ I====-=-=-=-=-=_ =-_~ =-==__=~~~~t~!' _s_o~.:c.!-=-=-=--===--=-=_=-== =~ 401-9 Comments RESPONSE Comprehension 1

BANK r

MNS Exam Bank Question AICENBROS I Considered SAT for submittal with no

---

______ L

___ ------ ---------------- -------- _________..J comments_ No changes_

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r------- --- ---------- -- -- -----

Development References f---- --------- ---------- ---~----

iLesson Plan IC-ENB Rev 27 Pg 19 I

I 1Learning Objective: OP-MC-IC-ENB Obj # 4 L ___ ~

r----

---

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

IStudent References Provided t--- - - ------ - -- -- -- ---- - - ----

I i

I l __________________________ _

)~~stionBank -#IKA ___ sys-i~m -IKA-=nulllbe~-

---

--- ---1-----------1---------------------

r~-=d~!i _= =_===_ =_-==_-=_===_==== = _=-_ ===== _-==-_====-====-==- -_=-=~==-=====~== =--- --

l8331SYS034 rA3_03

__________ 1.. ____________ L ____ _

lAbility to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7/ 4S_S)fJHigh flux at shutdown 1 ______________________________________________________________________________________________ _

Tuesday, November 10, 2009 Page 81 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 33

_ C ___ ~ ___ _

ruesday, November 10, 2009 Page 82 of 185 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 33 ruesday, November 10, 2009 Page 82 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 34 C

~~!~~~!~~~~~S~~~~~~-=rl!J~iHtr _~~_

---.-- --.- r.: -.-.---

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

-.--~--- -

-~.--.~.~--

~ --.- ~-

.--.~-

.---~

~ --

rKA_desc I

1834 i

SYS045 r

K4.13 L _____________ ~

___. _______ L ____

~ _____ _

r~owledg~~fMT/G~yst;~~:;d;sign feature(s) and/or interlock(s) which provide for the following: (CFR: 4I.7)iJOverspeed

!EI"~t.t:~i~~

CURRENT Which ONE (1) of the following best describes the overspeed protection for the Main Turbine?

A B.

c.

D.

Electrical trip at 103% and mechanical trip at 113%.

Electrical trip at 111% and mechanical trip at 113%.

Mechanical trip at 110% and electrical trip at 111 %.

Mechanical trip at 110% and electrical trip at 115%.

045K4.13 No comment at this time RF A 10/28/09 Tuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following best describes the overspeed protection for the Main Turbine?

A Electrical trip at 103% and mechanical trip at 113%.

B.

Electrical trip at 111% and mechanical trip at 113%.

c.

Mechanical trip at 110% and electrical trip at 111 %.

D.

Mechanical trip at 110% and electrical trip at 115%.

401-9 Comments:

Page 83 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE C

2009 RO NRC Retake Examination QUESTION 34

~~:!~~~!~~~~~S~~~=-~~-=rl!J~iHtr*-~~ ~

I 1834 i

SYS045 I

K4.13

~=de:!~==-====-=====~=======.=-===-============-========.==-=-=======-=======~

[Knowledge ofMT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)iJOverspeed I

L _____________ ~

___. _______ L ____

~ _____ _

!EI".{)t~(;ti~l!...'.-::'-:'''''''=''''''''''''''""-_.~_~ ___ ~~~~~_~~_~ __ ~

~._. __ ~~ ___.~~~ __ ~ ~ _._~_.~_~ ~._.~j CURRENT Which ONE (1) of the following best describes the overspeed protection for the Main Turbine?

A B.

C.

D.

Electrical trip at 103% and mechanical trip at 113%.

Electrical trip at 111% and mechanical trip at 113%.

Mechanical trip at 110% and electrical trip at 111 %.

Mechanical trip at 110% and electrical trip at 115%.

045K4.13 No comment at this time RF A 10/28/09 Tuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following best describes the overspeed protection for the Main Turbine?

A Electrical trip at 103% and mechanical trip at 113%.

B.

Electrical trip at 111% and mechanical trip at 113%.

C.

Mechanical trip at 110% and electrical trip at 111 %.

D.

Mechanical trip at 110% and electrical trip at 115%.

401-9 Comments:

Page 83 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 34 General Discussion r-~----- ---.---

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

---

~~--

--~------ -

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

~--~-~-

~-.~----

IThe mechanical overspeed trip mechanism trips the Main Turbine at 110%. The electrical overspeed device trips the Main Turbine at 111%.

I.

c

-~- ---

iThe KIA is matched because the applicant must know the setpoints for the Main Turbine overspeed protection trips.

~---"----- --- -.-.-.---------- ---.- - ---- --- - -------------- ~-- ----- -

---

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

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

Answer A Discussion

[----.~~--~~----.~-.----~~---~.-.-~.-~--~---~-.--.~------~~-.----~-~-~--.-

IIncorrect. The mechanical overspeed trip is correct. An electrical trip at 103% is plausible since the OPC overspeed protection actuates at 103%.

L __________________________

~ _____________

~ ___________________

~ ___________ _

Answer B Discussion fi;;:c~~t~h;;-ek:~tri~~~_;:sp;dtr;p~ ~o-;:r_;;_ct.A-~Zh~ic_:;l-o~;;;;-edtrip-:;t-113O/:-i~Pi~~ibi;;-ifthe applicant confuses the Main Turbine trip with the EDG Overspeed trip.

i ____ ~~. __._~ __._. _____ ~_. ____

.~ __ ~ ______ ~_~

.. __.. __. ___ ~. ___ ~~

_.~_.~ _____.~_~_. __

~ ___. ______. ___

.~ __ _

--~~~~I

_~~~J Answer C Discussion r---

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

ICORRECT.

---

~--------

Answer 0 Dfscusslon IIncorrect. The mechanical overspeed trip ~~;-rr~ct.-A~~I~tr;;;~;;~;~r~p~ed trip crt 115% is plausible if the candidate confuses the Main Turbine trip with the SSF Diesel Overspeed trip.

I_.~ ___ -

. _____ ~~. _______ ~ ___. __ ~~_~~

___ ~. __ ~. ___ ~. ______._. ______ ~ __ ~.~ __ ~~~~~~_

~

__ ~_~ __ ~. ___. ___ ~~~

__. __ ~ __ ~_

I-Job Level-

-CognHI;eLeve'- ~T ~Qu-eatIOnType-T ---- ~

Question Source 1----- ~-.--

--~.---.- ---~---.--+- -.~-~ ~--.--.+- -~-----~~--------.-.--~--~--

I RO Memory I

BANK I

CNS NRC Exam Bank 1048 (Never Used)

I __ ~__ _____

_ _______________ --.1 ___

~ __________ -1 ___

~ ______________. __________________________________

---1

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved I~e!elopmen! Refe'!.!'c..e~

IOP-MC-MT-MT Objective 22 I

i I L ___________ ~._

-1

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

-~.-~.-,

IStudent References Provided i

--~~-~-1 F--~~~~~-- ----~---~----l i I I

I I I i I I

I I i!

_. _____ ~.J I _______. __ ~ _____ ~ __.' __ ~ _____ '

401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

~qu~~tlo~~~~k.~~~~ist;"i=l~-n~"!ber I

1834 1SYS045 IK4.13 r~-=~!~-======-===-=======-===-==-~=--==-==-===-=-===-===-==-===== --~---------

L ____

~ _______ ~

~ __________ ---L- ____________ _

IKnowledge ofMT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 4 I.7)L'Overspeed

~<>t:c!io_n _

Tuesday, November 10, 2009 Page 84 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 34 General Discussion r-~----- ---.---

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

---

~~--

--~------ -

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

~--~-~-

~-.~--- -

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

--~

IThe mechanical overspeed trip mechanism trips the Main Turbine at 110%. The electrical overspeed device trips the Main Turbine at 111%.

I.

!The KIA is matched because the applicant must know the setpoints for the Main Turbine overspeed protection trips.

L. ___

.~ _______._._. __

~ ____

~ __._ ~ ____. ___

. __._.~ ___._. _______ ~ ___. ____ ~_.

__ ~ ____ ~. __._~ ___ ~ ___,_._.~~_~ __ ~._~_~

_.~ ___.~._

Answer A Discussion

['---.~~--~~----.~-.----~~---~.-.-~.-~-'~---~-.--.~------~~-.----~-~-~--.--.~--~~~-~-.-~-~.-~-.--~~~~.-.-~---~-~~.-.---

IIncorrect. The mechanical overspeed trip is correct. An electrical trip at 103% is plausible since the OPC overspeed protection actuates at 103%.

L __________________________

~ _____________

~ ___________________

~ ___________________________________________

• __________ _

Answer B Discussion

.-~~~~-.-.~.----~~----.-~--~-------~---~-~-.-----.--.~---.-~~--~~--~~~~~-.--~---.---~~-~-----~.~-~~~-~--~~~.~I lII1~~ec;~!~~I~tri~~~v:r~~:d~rip_i~~rr_e<:~~ ~e_c~aIlic;~~~r~p~~~rip_a~ ~I~~ ~s!~allS_i!J~ ~f ~llt:~~~c~~~~filses t~~!~'flll"~~ ~rp _w~~ tl1e_~~~~v.:r~~~ecl ~r~~ ___ ~ ~~J Answer C Discussion r---~-----------------~-------~---------------~-------------------~------------------------------.-------------~-----------------~---

~<:)~~'f~ ____ ~ ______ ~ __ ~ __ ~ ___ ~~~~ ____ ~_~_~~ ___ ~_~ _____ ~ __ ~ _____ ~_~~~_~ __ ~_~_~

__ ~~ ______ ~ _____. __

Answer 0 Dfscusslon

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

-~-~~~---.~-----~-.-.-.--.-.--~--~---~-----~-~---~.~.---*--*-*~~~-~---*-~------**-*~-l iIncorrect. The mechanical overspeed trip is correct. An electrical overspeed trip at 115% is plausible if the candidate confuses the Main Turbine trip with the SSF Diesel Overspeed trip.

i I_.~ ___ -

. _____ ~~. _______ ~ ___. __ ~~_~~

___ ~. __ ~. ___ ~. ______._. ______ ~ __ ~.~ __ ~~~~~~_

~

__ ~_~ __ ~ ____._._~~~ __. __ ~ __ ~ - ____ ~_

I-Job Leve'-

1---- ~---

I RO

~ Developed

- CognHI;eLevel-~T~Qu-eatIOnType-T----~~~------QuestlonSo;-rce-~~-~----~~---i 401-9 Comments RESPONSE

--~.---.----~---.--+- -.~-~~--.--.+- -~-----~~--------.-.--~~-~----~----~~--I Memory 1

BANK I

CNS NRC Exam Bank 1048 (Never Used)

I Considered SAT for submittal with no

---

~- ------~ --'- --.- ----._~..l_ --.----.-----~.--.--.~~- -

~~---~--~~--~~~~~-~ comments. No changes.

~ OPT Approved

~ OPS Approved Tuesday, November 10, 2009 Page 84 of 185

FOR REVIEW ONLY - DO N A

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 35 r--'-- - -,- -~-'T--- ---,- -'l----- -

-,-~-

fCl~~8!i?~~~"-k_#+~~_SY~~!l'_l~_n~"!~L __

I 1835 I

SYS055 I

K1.06 1~j1~!~===~==~============-=-======-==-====-== ----------- ---~-------------

IKnOWledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: 41.2 c __________ ~

__ __ ~

__ L _______ _

I!~ ~Jl~~~~t~ ~~*~iJ l'~~rs~I!l CURRENT The following conditions exist on Unit 2:

2A S/G has developed a 200 GPO tube leak 2EMF-33 (CSAE Discharge) Trip 2 light is illuminated Which ONE (1) of the following describes th e discharge f10wpath for th e Condenser Steam Jet Air Ejectors (CSAE) AND what occurs as a result 2EMF-33 counts reaching Trip 2?

A.

B.

C.

D.

The CSAEs discharge to the Unit Vent.

Annunciator ONLY.

The CSAEs discharge to the Unit Vent.

Annunciator AND CSAE discharge flowpath isolates.

The CSAEs discharge to the Turbine Building roof.

Annunciator ONLY.

The CSAEs discharge to the Turbine Building roof.

Annunciator AND CSAE discharge flowpath isolates.

055K1.06 No comment at this time RF A 10/28/09 fuesday, November 10,2009 45 DAY VERSION The following conditions exist on Unit 2:

2A S/G has developed a 200 GPO tube leak 2EMF-33 (CSAE Discharge) Trip 2 light is illuminated Which ONE (1) of the following describes the discharge flowpath for the Condenser Steam Jet Air Ejectors (CSAE) AND what occurs as a result 2EMF-33 counts reaching Trip 2?

A.

The CSAEs discharge to the Unit Vent.

Annunciator ON L Y.

B.

The CSAEs discharge to the Unit Vent.

Annunciator AND CSAE discharge f10wpath isolates.

C.

The CSAEs discharge to the Turbine Building roof.

Annunciator ON L Y.

D.

The CSAEs discharge to the Turbine Building roof.

Annunciator AND CSAE discharge flowpath isolates.

401-9 Comments:

Page 85 of 185 A

DISTRIBUTE FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 35

'KAde;~- ~--~ -~~ -~ ~-~~~-~--~~~~

---~~-------~~-~-- ~~------~-- ~-------~~~~--~:~~~-I iKn;;I~dg~ ~fthe-Phy~~;J~~n~~cti~n~~ci7o-;~~;-~ffe~t rel~t;;~shiPsbt:tw~e~th~CARS~d the f~l~i~g~y;t;-m~~(CFR:~ 412~ 1 CURRENT

!!~4]Jl_~~2t~~~.~~,1'~~~'s~~

~. ___.~-:.~:-::--:-:,"":~:--.~-":... :--~:--___ ~ ~~~ _____ ~ __ ~ __ ~ ~ __ ~_~~ ___ ~ __ ~~ ~~.!

45 DAY VERSION The following conditions exist on Unit 2:

2A S/G has developed a 200 GPO tube leak 2EMF-33 (CSAE Discharge) Trip 2 light is illuminated Which ONE (1) of the following describes th e discharge f10wpath for th e Condenser Steam Jet Air Ejectors (CSAE) AND what occurs as a result 2EMF-33 counts reaching Trip 2?

A.

B.

C.

D.

The CSAEs discharge to the Unit Vent.

Annunciator ONLY.

The CSAEs discharge to the Unit Vent.

Annunciator AND CSAE discharge flowpath isolates.

The CSAEs discharge to the Turbine Building roof.

Annunciator ONLY.

The CSAEs discharge to the Turbine Building roof.

Annunciator AND CSAE discharge flowpath isolates.

055Kl.06 No comment at this time RF A 10/28/09 fuesday, November 10,2009 The following conditions exist on Unit 2:

2A S/G has developed a 200 GPO tube leak 2EMF-33 (CSAE Discharge) Trip 2 light is illuminated Which ONE (1) of the following describes the discharge flowpath for the Condenser Steam Jet Air Ejectors (CSAE) AND what occurs as a result 2EMF-33 counts reaching Trip 2?

A.

The CSAEs discharge to the Unit Vent.

Annunciator ON L Y.

B.

The CSAEs discharge to the Unit Vent.

Annunciator AND CSAE discharge f10wpath isolates.

C.

The CSAEs discharge to the Turbine Building roof.

Annunciator ON L Y.

D.

The CSAEs discharge to the Turbine Building roof.

Annunciator AND CSAE discharge flowpath isolates.

401-9 Comments:

Page 85 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 35 General Discussion ITh~CSAE;di~h~g~t;the-U;;jt Ve~t.lnthe~p~t,-the-CSAE;di~ch;;;,gdt~-th; T~b-i~-B~iicii~g--;'~of~~d-the~disch~g;;w~pp~d-U;th~U~itVe;to~ ~ I EMF-n-TriP 2 ~;~~i~;H~;~~r~1

)that automatic action has been defeated and the CSAEs now continuously discharge to the Unit Vent. IEMF-33 now only performs a monitoring function with no automatic actions.

I I

[

iThe K/ A is met because the candiate must be understand the discharge flowpath of the CARS (Physical connection) and the effect of an alarm associated with the PRM which monitors this I

I system

[

1 __ ~~~_~ ___ ~

___ ~_

-~-~~ - -~~~~--~~~-~--~-~-~~~--~---- ------~-'

Answer A Discussion iCORRECT--~~~- -

t_~ ________ ~~ _________ ~_~~_~ ________ ~~

___ ~

___ ~ _____ ~ __

Answer B Discussion IJ~c~~e~t~C~rr~~tdi;ciJ-;;-rg; path~ The -PRM-~~~t~olfilI;-cti;n-i; Pi~~ilik b~caus~it~;ed to-;o~kth;; ;--;; ~dthi;Tst~;cl ~U;ithe~th~~PRR~ th~t;o~Tt;--;fl~;p~th -~ich di~~h--;rge~~-

lc!i~~t'rto_tI1e_e.Il~iroI1~e.Il.t-_~ ________ ~~ ______ ~ ___ ~ _____ ~~ _____ ~ __ ~ __ ~~ __ ~_~ __ ~~~_ ~ _____ ~ ____ ~~ _____________ ~_

Answer C Discussion I~---------------------

--~-~----- -

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

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

--~---~-~--

IIncorrect. Discharge flow path is plausible since the discharge at one time did go to the turbine building roof. The second part of the question is correct.

L ___________________________________

~ ____

~_. _________________ ~_~ __________________________

~ ______________

~_

Answer 0 Discussion r::-------------------~------~--~-----

---

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

[Incorrect. Discharge flow path is plausible as explained above. The PRM control function is plausible because it used to work this way and this is true of all of the other PRR's that monitor a ltlo_w..Path~~i(;11.. <ii~c11..arges.. <ii~(;t'x_t~tl1~ ~viJ"()nE1.e.I1t.. __ ~ __

~- --- - -

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Cognitive level

[QuestionType i

Question Source 401-9 Comments RESPONSE

---

~_t--~~-------~--I-~----------~------~--~--~~-----~-~---~--------

Memory L

NEW

[

Considered SAT for submittal with no

---

~--~----I--~-----------~~-------------~-------~~----

comments. No changes.

~ Developed IDe;&i-opment-References r-~~-------- --~~------~- ----~-

---

~------,

iStudent References Provided

~ OPT Approved

~ OPS Approved

~ NRC Approved

[Lesson Plan OP-MC-MT-ZM Objective 4 Section 2_2 I

r----~~------ ~-~~---~~---

I i

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---

~--------- ---- --- -- --I QuestionBank #I tKA system IKA number i

---

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______________ _..l~ ____ _

~ _____ L Tuesday, November 10, 2009*

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-~-----~~---I IKA_desc I

I::-:-~--------~- ------------- -- -- -~-----~- --~--------~--~- ------------------------ ----- ---1 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: i

~I.~..!.O'!.IJ./ j~2..t(). 45... !l [J !'IU.1 ~,)'s~.l11-_........ :.. :.. =.",.. -.:... -:-... _.::--:.... :......___ _ ___ _ __ _~ __________. ___ ~_ _ J Page 86 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 35 General Discussion ITh~CSAE;di~h~g~t;the-U;;jt Ve~t.lnthe~p~t,-the-CSAE;di~ch;;;,gdt~-th; T~b-i~-B~iicii~g--;'~of~~d-the~disch~g;;w~pp~d-U;th~U~itVe;to~ ~ I EMF-n-TriP 2 ~;~~i~;H~;~~r~1

)that automatic action has been defeated and the CSAEs now continuously discharge to the Unit Vent. IEMF-33 now only performs a monitoring function with no automatic actions.

I I

I iThe K/ A is met because the candiate must be understand the discharge flowpath of the CARS (Physical connection) and the effect of an alarm associated with the PRM which monitors this I

I system.

i 1 __ ~~~_~ ___ ~

___ ~_~ _______ ~_

~~~~ _____ ~ ___ ~ ___ ~~ _______ ~

______ ~ __ ~ ______ ~_~ ___ ~_~~ __ ~~~~_

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

Answer A Discussion I~~~~~f~====_====~=~_=====-=== =_-===_-~~~-_~~-_-_= ___ ~~_

-_-~====-=~ = -_== __ =

__===~~_~_-_~~~ ___ ~==~-_____ =

___ -_=~_-_______ =

____== __ _= ______ =

__==J Answer B Discussion IJ~c~~e~t~C~rr~~tdi;;;ll;;-rg; path~ The -PRM-~~~t~olfilI;-cti;n-i; Pi~~ilik b~caus~it~;ed to-;o~kth;; ;-;;-; ~dthi;Tst~;cl ~U;ithe~th~~PRR~ th~t;o~Tt;~fl~;p~th -~ich di~~h-;;-rge~~-I lc!i~~t'rto_tI1e_e.I1~iroI1~e.I1.t-_~ ________ ~~ ______ ~ ___ ~ _____ ~~ _____ ~ __ ~ __ ~~ __ ~_~ __ ~~~_ ~ _____ ~ ____ ~~ _____________ ~ ___ ~~~ ____ ~i Answer C Discussion I~-*----- -----.------ --

--~-~----- -

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

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

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

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

IIncorrect. Discharge flow path is plausible since the discharge at one time did go to the turbine building roof. The second part of the question is correct.

L ___________________________________

~ ____

~_. _________________ ~_~ __________________________

~ ______________

~

~ _______

~ __ _

Answer 0 Discussion r::---.--.-----.------~--.---~--~-----

---.-.------------------.-.~-------~-----~---~---.---.-.--~~--~--~~--~--.---~~~~~----- --*----1 IIncorrect. Discharge flow path is plausible as explained above. The PRM control function is plausible because it used to work this way and this is true of all of the other PRR's that monitor a,

ltlo_w...Path~~i(;11.. <ii~c11..arges.. <ii~(;t'x_t~tl1~ ~viJ"()nE1.ellJ.. __ ~ __________ ~ ________ ~~ _____ ~ __ ~ ______ ~ _____ ~ ___ ~~_~_~~_~_~_~_~_~_~_ ~ _~_~~_J 1-- --------

I Job Level

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---

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~ Developed

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~ OPS Approved

~ NRC Approved r -- -----.- -

--.--~-- -.--, I*-~--

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l ___ ~ ________ ~ _______________ ~~ ___ J I ___ ~ _____. _________ ~ ______ ~_~ J 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

---

~--------- ---- --- -- --I QuestionBank #I IKA system IKA number i

--~-.-~

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

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---

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~--~~~--1835tsYS055----fKio6----------1

______________ _..l~. ___.~ _____ L I::-:-~------.~~- --------.-.-- -- -- -~-~---~- --~--.--~--~~-~- -----.. ----------------- ----- -*-1 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: i

~I.~..!.O'!.IJ./ j~2..t(). 45... !l [J !'IU.1 ~,)'s~.l1l-_........ :.. :.. =.",.... :.... :...... ::--:.... :......___ _ ___.._ _~ _________.. ___ ~_ _ J Tuesday, November 10, 2009*

Page 86 of 185

FOR REVIEW ONLY - DO N T DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 36

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

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1836 i

SYS068 J

2.4.50 IISYS068 GENERlCDAbility to verifY system alann setpoints and operate controls identified in the alann response manual. (CFR:

~~~ _~~~~~~~.J.

__ ~~~~_~~~...l~~~~~~~~~~~~~~ 141.10 1 43.5 145.3)

[-~~~~~~-~~~-~~~-~~~~~~.~~~~---~~~--~-~~~~~-~~~-~~~~~~-~~~~~~~~~~~~~~~~~~~~~~

CURRENT Units 1 and 2 were operating at 100% RTP with a WMT release in progress. Given the following:

Annunciator 1RAD1 C5 (EMF 49 Liquid Waste Disch Hi Rad) is in alarm.

1WP-37 (Liquid Waste to RC Cntrl) indicates OPEN.

1WP-35 (WMT & VUCDT to RC Cntrl) indicates OPEN.

1WM-46 (OEMF-49 Outlet Hi Rad Shutoff Isol) indicates CLOSED.

Concerning the OEMF-49 RP86A Digital Module, which ONE (1) of the following statements correctly describes the status of the associated indicator lights and the required operator actions?

A.

Yellow Light ONLY - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

B.

Yellow Light AND Red Light - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

C.

Yellow Light ONLY - LIT Ensure 1WP-37 and 1WP-35 are closed on 1MC-11.

D.

Yellow Light AND Red Light - LIT Ensure 1WP-37 and 1WP-35 are closed on 1MC-11.

068G2.4.50 Stem: Delete the word "is."

45 DAY VERSION Units 1 and 2 were operating at 100% RTP with a WMT release is in progress. Given the following:

Annunciator 1 RAD1 C5 (EMF 49 Liquid Waste Disch Hi Rad) is in alarm.

1 WP-37 (Liquid Waste to RC Cntrl) indicates OPEN.

1WP-35 (WMT & VUCDT to RC Cntr~ indicates OPEN.

1WM-46 (OEMF-49 Outlet Hi Rad Shutoff Isol) indicates CLOSED.

Conceming the OEMF-49 RP86A Digital Module, which ONE (1) of the following statements correctly describes the status of the associated indicator lights and the required operator actions?

A.

Amber Light ONLY - LIT Ensure 1 WP-35 and 1WM-46 are closed on 1 MC-11.

B.

Amber Light AND Red Light - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

C.

Amber Light ONLY - LIT Ensure 1WP-37 and 1WP-35 are closed on 1MC-11 D.

Amber Light AND Red Light - LIT Ensure 1WP-37 and 1WP-35 are closed on 1MC-11 401-9 Comments:

The reference provided does not support answer and choices.

Facility demonstrate and provide proper reference during review.

RF A 10/28/09 fuesday, November 10, 2009 Page 87 of 185 FOR REVIEW ONLY - DO NO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 36

~~~lfA~~~~!~~~~f~r=~~1~~===~~i f~s~SfE~~~~~~;~~~~e~i~~~s~;~~=s;~;;~~;;p~r~t;~ntro~~~;~~di~~:;:~~~~~~~u~:~~;:-~

I-~- ~_~ __ ~ __ -L~~_~~~ __ ~~~ ______ ~~_~ __ ~~ 141.10 1 43.5 145.3)

[-~~~---~----~~~~~-----~~~~~-~---~~---~-~-~-~-~------~----------~~~---~~--~--

CURRENT 45 DAY VERSION Units 1 and 2 were operating at 100% RTP with a WMT release in progress. Given the following:

Annunciator 1RAD1 C5 (EMF 49 Liquid Waste Disch Hi Rad) is in alarm.

1WP-37 (Liquid Waste to RC Cntrl) indicates OPEN.

1WP-35 (WMT & VUCDT to RC Cntrl) indicates OPEN.

1WM-46 (OEMF-49 Outlet Hi Rad Shutoff Isol) indicates CLOSED.

Concerning the OEMF-49 RP86A Digital Module, which ONE (1) of the following statements correctly describes the status of the associated indicator lights and the required operator actions?

A.

Yel/ow Light ONLY - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

B.

Yel/ow Light AND Red Light - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

C.

Yellow Light ONLY - LIT Ensure 1WP-37 and 1WP-35 are cfosed on 1MC-11.

D.

Yellow Light AND Red Light - LIT Ensure 1WP-37 and 1WP-35 are closed on 1MC-11.

068G2.4.50 Stem: Delete the word "is."

Units 1 and 2 were operating at 100% RTP with a WMT release is in progress. Given the following:

Annunciator 1 RAD1 C5 (EMF 49 Liquid Waste Disch Hi Rad) is in alarm.

1 WP-37 (Liquid Waste to RC Cntrl) indicates OPEN.

1WP-35 (WMT & VUCDT to RC Cntr~ indicates OPEN.

1WM-46 (OEMF-49 Outlet Hi Rad Shutoff Isol) indicates CLOSED.

Conceming the OEMF-49 RP86A Digital Module, which ONE (1) of the following statements correctly describes the status of the associated indicator fights and the required operator actions?

A.

Amber Light ONLY - LIT Ensure 1 WP-35 and 1WM-46 are closed on 1 MC-11.

B.

Amber Light AND Red Light - LIT Ensure 1WP-35 and 1WM-46 are closed on 1MC-11.

C.

Amber Light ONLY - LIT Ensure 1WP-37 and 1WP-35 are cfosed on 1MC-11 D.

Amber Light AND Red Light - LIT Ensure 1WP-37 and 1WP-35 are cfosed on 1MC-11 401-9 Comments:

The reference provided does not support answer and choices.

Facility demonstrate and provide proper reference during review.

RF A 10/28/09 fuesday, November 10, 2009 Page 87 of 185

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 36 General Discussion

,~--~-----.---~.--~~.-- --~------- -

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

~

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

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

-~---*--~~--~---I iAlarm given in the stem of this question is caused by a Trip 2 associated OEMF-49. The EMF digital module has a red led with would be illuminated if the Trip 2 setpoint were to be I

[reached. The yellow LED is for a Trip 1. ARP for this annunciator directs the operator to ensure 1 WP-35 and 1 WM-46 are closed.

I

[

I IKA is matched because candidate must know how to verifY from the a liquid rad waste alarm is valid and then determine the required controls which need to be operated in order to respond

[

It<>.tl!e~~fIl1~e!. thea~()Ciltt~~~aI"Ill_~s.EClI1~.!'r.<>.~d~~ ___ ~ ________ ~ _ ~ _________________ ~ _ ~ _________ ~ _______ ~ _____ ~ ________ I Answer A Discussion ri - - -- - --.- ---.- --.--

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

~ - -- -

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

[Plausible if the candidate believes that the amber light indicates Trip 2, second part of the question is correct.

---~- --._------ -

---

~- -

--~-~-

-~- -

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

Answer B Discussion r; ---.. --.- - -

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

---

~-

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CORRECT I ~. __._. _____.~_~ ___ _

Answer C Discussion r:--~-- -

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

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

~

---

~~-~---.-.-

l}>IilU~b~e~ firs~ part_ ~~e~c~b~~ ~()\\I~~coll(l.. b_=.c~~s~.. o~e~~tlle~<lI~~i~.c0fI"e~,~h_=.~t~~ is closed by a different EMF for a similar liquid waste release.

Answer 0 Discussion r--- --------------- -------~-.-.----- -.-.--------- -

[Plausible: First part is correct, second is plausible as described above.

---

**-*-~T-*----~----~-~-----*~--~-------,-~-----~-----~-

~o~_L!~'- -+ __ ~ ~oSLn!tI!!~e~!'__ _~ _9u~~~ TYJ>!J _____ ~ __

RO I

Memory

[

NEW I

___. _____....L_~ _____ ~._~ ___._....L_. _____ ~~._~...1 ______ _

Question Source 401-9 Comments RESPONSE Per Chief Examiner comment removed "is" from stem of question and included

~ Developed

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

~ -~ - ~ ~------------~----~----l references to support the answer and

~D~!e~oj>~Il_t B!f..!,,!~c..!~ ____________ ~ ~!'J~~~ Refe~nce~!~~~~d_~ ___ ~ choices. HCF 11/03/09

~ OPT Approved

~ OPS Approved

~ NRC Approved ITechnical Reference(s): OP-MC-WE-EMF, Rev 19 I i I

[pages 35, 57, 59, Ill, & 113 I [

I

[OP/lIAl6100101O Q Pg 28 i

I

. I I

I[Learning Objective: OP-MC-MC-EMF, Obj. 3 I

~ _______

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~ ___ ~_

I 1836SYS068 112.4.50 1_. __________ L_~ _____________ ~_~~

fSYS068 GENERlClrAbility to verifY system alarm setpoints and operate controls identified in the alarm response manual.

~~FB.~4]*l~L4~5J~~._~ ____ ___ ~ _________ ~ _____________ ~ ______________ ~ ____ J Tuesday, November 10,2009 Page 88 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 36 General Discussion

,~--~-----.---~.--~~.-- --~------- -

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

~

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

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

-~---*--~~--~---I iAlarm given in the stem of this question is caused by a Trip 2 associated OEMF-49. The EMF digital module has a red led with would be illuminated if the Trip 2 setpoint were to be I

ireached. The yellow LED is for a Trip 1. ARP for this annunciator directs the operator to ensure 1 WP-35 and 1 WM-46 are closed.

I i

I IKA is matched because candidate must know how to verifY from the a liquid rad waste alarm is valid and then determine the required controls which need to be operated in order to respond

[

It<>.tl!e~~fIl1~e!. thea~()Ciltt~~~aI"Ill_~s.EClI1~.!'r.<>.~d~~ ___ ~ ________ ~ _ ~ _________________ ~ _ ~ _________ ~ _______ ~ _____ ~ ________ I Answer A Discussion ri ---- ---.----.---.--

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

---.--~---

-~--- -.----

---

~-------------------------------~-~-----~----,

1~lllI1~i~le~fth~~alld~~e~~Ii~":s~~att~~~b:ry~hti~dj(;a~e~~~~,~e~o~~~~~~e_~~t~~i~c~~~t. ______ ~ _____ ~ ___ ~ _____________ ~ ______ !

Answer B Discussion to~~i ~ ~====~ =-===~~==-==_~~=_~_=~~~-_-=-=~~_-~_-~~=~-=~~_~~-____ -~~=-=-_~~-=_-=-~~-~-_-_-~_-=-_--=-~-=-~ ___ -_~-_~_~_~_~~-_-=--~]

Answer C Discussion r:--~---~--------'---------'--------'-'-----------~'~~---'--.~---~~~--~---~--------~~-~---.-.---.-----------------*~--------I l~lllU~b~e~ firs~ ~~

~~e~c~b~~ iltJ()\\I~~co~~b~c~~s~o~e~~tl~e ~ilI\\'t:~i~ c0l1"e~,_th~~t~~~ ~o~~tJy~a ~i!!~e~~~~f<Jr_a ~i~~a!'I~~~d_w~~e !:e~~=- __ ~ _____________ I Answer 0 Discussion

[P§~~~~~i~~~p~~i~c_~~i0~_~-=-C~~~iS iT~~i~~!i~~~~b~d_;~~~~~_-_-_-~~_~~~~-~-=-_~-_-~ ___ --=-~-_~_-_~~~_--=-~~~=~--=--=-_~_-==~-=-_~_~-=-==-=~-~-~~-==--=--=~J

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Per Chief Examiner comment removed "is" from stem of question and included

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

~ -~ - ~ ~------------~----~----l references to support the answer and

~D~!e-,-oj>~Il_t B!f..tt"!~c..tt~ ____________ ~ ~!'J~~~ Refe~nce~!~~~~d_~ ___ ~ choices. HCF 11/03/09 ITechnical Reference(s): OP-MC-WE-EMF, Rev 19 I i I

[pages 35, 57, 59, Ill, & 113 I [

I iOP/lIAl6100101O Q Pg 28 II I i

I

, I I

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1836SYS068 12.4.50 1_. __________ L_~ _______ L _____ ~_~~

fSYS068 GENERlClJAbility to verifY system alarm setpoints and operate controls identified in the alarm response manual.

I

~~FB.~4]*l~L4~5J~~._~ ____ ___ ~ _________ ~ _____________ ~ ______________ ~ ____ J Tuesday, November 10,2009 Page 88 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 37 A

---

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r-.:---

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IQuestionSank #KA_system I KA_number IKA_desc r---1837---~--SYS071-t-~--A4J4----i rAbilitY-t~~~uaIlyoperate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)[JWDGS status alarms

,--------~---- L---------L--------------~-l*:~~:~=~~:_:****************....

CURRENT Given the following:

Unit 1 is operating at 100% RTP Unit 2 is refueling Unit 1 is releasing a minimally decayed Waste Gas Decay Tank A si91ificant packing leak starts on isolation valve 1WG-160, ryvG Decay Tank Outlet to Unit Vent Control)

Which ONE (1) of the following correctly describes the automatic actions which will ensure that the leak is contained and filtered?

A B.

C.

D.

1 EMF-35 (Unit Vent Part Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160.

1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160 AND 1EMF-35 (Unit Vent Part Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

OEMF-50 (Waste Gas Disch Hi Rad) automatically closes 1WG-160 AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans.

071A4.14 45 DAY VERSION Given the following:

Unit 1 is operating at 100% RTP Unit 2 is refueling Unit 1 is releasing a minimally decayed Waste Gas Decay Tank A significant packing leak starts on isolation valve 1WG-160, ryvG Decay Tank Outlet to Unit Vent Control)

Which ONE (1) of the following correctly describes the automatic actions which will ensure that the leak is contained and filtered?

A B.

C.

D.

1 EMF-35 (Unit Vent Part Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaustfans AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1 WG-160.

1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160 AND 1EMF-35 (Unit Vent Part Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

OEMF-50 (Waste Gas Disch Hi Rad) automatically closes 1WG-160 AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans.

401*9 Comments:

The KA says to operate and/or monitor in the CR. Rad alarms are a form of monitoring. KA is met.

No additional comments at this time RF A 10/28109 Tuesday, November 10, 2009 Page 89 of 185 2009 RO NR~~!a~~E~!!:t~~L y ~~~TION 3~IS~~IB~T_~ _____ A _ _ _

~~!i!~it~~k!J~'::81!t!~~J~A'::n~~~!r~=~==] rtSA~~~=====_===== =-======= ____________________. ___. __________._. _____ _

r 1837 I

SYS071!

A4.l4 i lAbility to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)[JWDGS status alarms

---

_1. ________ L ________ ~---~ l...-.::.-.:..-.:=........ :.-:....-.::=:.-:..-.:._' _______________________________________________ _

CURRENT 45 DAY VERSION Given the following:

Unit 1 is operating at 100% RTP Unit 2 is refueling Unit 1 is releasing a minimally decayed Waste Gas Decay Tank A si91ificant packing leak starts on isolation valve 1WG-160, ryvG Decay Tank Outlet to Unit Vent Control)

Which ONE (1) of the following correctly describes the automatic actions which will ensure that the leak is contained and filtered?

A B.

C.

D.

1 EMF-35 (Unit Vent Part Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160.

1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160 AND 1EMF-35 (Unit Vent Part Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

OEMF-50 (Waste Gas Disch Hi Rad) automatically closes 1WG-160 AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans.

071A4.14 Given the following:

Unit 1 is operating at 100% RTP Unit 2 is refueling Unit 1 is releasing a minimally decayed Waste Gas Decay Tank A significant packing leak starts on isolation valve 1WG-160, ryvG Decay Tank Outlet to Unit Vent Control)

Which ONE (1) of the following correctly describes the automatic actions which will ensure that the leak is contained and filtered?

A B.

C.

D.

1 EMF-35 (Unit Vent Part Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaustfans AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1 WG-160.

1 EMF-36 (Unit Vent Gas Hi Rad) automatically closes 1WG-160 AND 1EMF-35 (Unit Vent Part Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.

OEMF-50 (Waste Gas Disch Hi Rad) automatically closes 1WG-160 AND 1 EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans.

401*9 Comments:

The KA says to operate and/or monitor in the CR. Rad alarms are a form of monitoring. KA is met.

No additional comments at this time RF A 10/28109 Tuesday, November 10, 2009 Page 89 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 37 General Discussion iTh~;I~;-~f radi~~ti~e-g;-s-iItl~the Au~ili;Y Buiicli~g~ilib~ Pkk~~pbYth~ A~riI~ry B~Idi;g Ve~i~tio~ Sy~t~; ;hichdi~ha~g~t~-the-PI~t~m.-Th~Unitl Low Range IParticulate Vent Monitor (EMF 35) should alarm which will automatically stop the Auxiliary Building Unfiltered Exhaust Fans. The Auxiliary Building Ventilation Monitor (EMF 41) should (also alarm which will place the Auxiliary Building Ventilation Filter system in service.

I

'1lThere are no specific WGDS status alarms in the Main Control Room. Therefore, an exact match for this KA is difficult. The closest match possible is to test applicant's ability to evaluate conditions related to the WGDS and determine how the status of the WGDS will change based on radiation monitor alarms (in the Main Control Room) and automatic actions associated with

[those alarms.

i IThis is a higher cognitive level because the candidate must comprehend the physical location of the leak and based on that location analyze the given answers to determine which automatic

!~c~~~\\\\,il!~itL~~~~c~~s~q~~~e~~~h~~~~ __________________ ~

Answer A Discussion iCORREC-r.----- - ----

L ___________ _

Answer B Discussion I-------------~--- ------------- ------- ------ --------------- ---------- -------~------------ ------------------ ---

t~~rr~ct:_ ~rvt.~_4~~o~~n~!...a~t~lll.a~i~~~~oj) ~h='~~~. Plal.ls~b~e ~f

~h:.:a.'1cli~a~~{j().l1~~e~~~i~~h!~this i~~~al1.<lll~I1lil.ti<; ~c~~n!o! ~~~'~L_tJ_llt!O~~F'3~~ ~ ________ _

Answer C Discueslon

---

~---

-- - --1-- --------- - ----- T--------------------

Job Le~e! ---l ____ ~~g.E!!i_"! Le~! __.1_ ~~~!o.!'.!~_l----

Question Source RO I

Comprehension I

BANK i

___________ 1 ___________________ ~

________________ ~ ______ _

MNS NRC Bank 771/2009 NRC Question 49

~ Developed

~ OPT Approved

~ CPS Approved

~ NRC Approved r;;;----~--------------------l IDevelopment References IStudent References ProvIded F-------------------

r-------------------------~

IOP-MC-WE-EMF, rev. 29, page 29 Objective 3 I

I I

I I

I I

I 1

I I

1 I

I L_ __ _ __ __ _______________ _ ______ ______ _

l ___________________________ J 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

-- ---------- -- -c::--------- - - -,-- -- --- - ----- -

QuestionBank # !KA_8Ystem IKA_number c- ------- ----

IKA_Mac

---

1------- - -,-------- ------1 l8371SYS071 jA4.l4

__________ L ___________ L _______ _

Tuesday, November 10, 2009 lAbilitY to ~a;;ually operate and/or monitor in the control room: (CFR:

I....................................*.*......

l ___

~ ___ _

Page 90 of 185 41.7/45.5 to 45.8)[]WDGS status alarms

---1 I

__________,,_J FOR REVIEW ONLY - DO DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 37 General Discussion

~-'-.~--.-~-~.---

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

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

-~-

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

---~-----~-

.---~-.-.-~-~-----~-------~.--.--~--.----~-,

iThe release of radioactive gas into the Auxiliary Building will be picked up by the Auxiliary Building Ventilation System which discharges to the plant vent. The Unit I Low Range I

IParticulate Vent Monitor (EMF 35) should alarm which will automatically stop the Auxiliary Building Unfiltered Exhaust Fans~ The Auxiliary Building Ventilation Monitor (EMF 41) should 1 (also alarm which will place the Auxiliary Building Ventilation Filter system in service.

I I

I

'1iThere are no specific WGDS status alarms in the Main Control Room. Therefore, an exact match for this KA is difficult. The closest match possible is to test applicant's ability to evaluate I

conditions related to the WGDS and determine how the status of the WGDS will change based on radiation monitor alarms (in the Main Control Room) and automatic actions associated with (

~~

i I

!This is a higher cognitive level because the candidate must comprehend the physical location of the leak and based on that location analyze the given answers to determine which automatic I

!~c~~~\\\\,il!~itL~~~e.c~~s~q~~~e~~!.h~~~~ __ ~ _______________ ~

__ ~._. _______ ~._~~ ________ ~_~_~_~ ___

~ ____._~ _______________ J Answer A Discussion iE<:)~E~~-_-=-~ ____ -_-_-_-_-____ -~~

___ -~~_-~_-_-_~_~~-___ ~_= ______ -~=-_-~~~~=_== _________====. ___________=== ________== ________==-=============.=====J Answer B Discussion I--~~---~~---*~~-~ -.-- -~--~--~-

--~----

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

--~--.--

-~-.-~---~

---

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

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

-~- - - -- -

--~- - -

-~~--

t~~rr~ct:_ ~~~_4~~0~~n~~a~t~~a~i~~~~0j) ~h=,~~~. Plal.ls~b~e ~f

~h~-=a~cli~a~~{j().l1~~e~~~i~~h!~this i~~~a~<lll~I1l~ti<; ~c~~n!o! ~~F'.'~L~~t!0~~F'3~~ ~ _________ _

Answer C Discueslon iI~c~~~~t~EMF-3 5do~~-n;t-r;alig~-~~~til;t~~ filtt;~:-Pla~silile ii~ppli~a~t d~~;;otr~_;~i~~ this. AI;;;-,EMF 36-;;;n~I~; lwa:{-(;o :B-ut,;j~~iC ;sctp~inti; hlgh~~~gh to-allow the Irelease to occur, EMF 36 will not alarm.

[-- -~-.---~-~- -~-~- -~- --- -~--~--~- -

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

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

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

Answer 0 Discussion r --~~.--~---~--.---~--

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-~-~-~-

IIncorrect. EMF 50 will not get to Trip 2 because it is set for the activity being released, and EMF 41 does not automatically stop these fans. Plausible as these are automatic actions for the l~1!F_~Ei!.ors:.. ______________ ~ __________________________. _______________________. __ ~_~

___ ~~ ____________ I

~- - --1--

-~-----~- - ----- T*-~---~-~--~-~---- -- ----~-~.~

---

.-~-~~--- -~--- -~-~-----,

Job Le~e! -l_. __ ~~g.E!!i."!Le~!. __.1_ ~~~!O~_"!~_l---- __________ 9.ue8ti~"-!0.!lrce __________ ~ ___ ~ 401-9 Comments ReS~ONS.e RO I

Comprehension I

BANK i

MNS NRC Bank 771/2009 NRC Question 49 1 ConSIdered SAT for submIttal WIth no

____ ~ __ ~.~.J ---~---~---~- ~.---. ~-.--~---~-~--~--~- -- ~.--~- ~---------- -----~--.-------~-- -

comments. No changes.

~ Developed lOev;,opment Re,.-";';ce;---

i=.-----~-~-.~--.--- ~-~- --.-.-~--.~-.. -----

~ OPT Approved

~ OPS Approved

~ NRC Approved IOP-MC-WE-EMF, rev. 29, page 29 Objective 3 I

I 1

1 L _________ ~_~_. ____ ~ ______

._~ __._. _~ __

-~---.--~-

-~ -c::-~-~--~~- - - -,- --

-~- -

-~-- - -

QuestionBank # !KA_8Ystem

]KA_number

---

.--~---~-_1-~--~-- - -,-.-------

18371SYS071 jA4.14

______ ~

___ 1. ___._. ___ ~.L _______ _

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IKA_desc I----------~~------*----~--~-~---~-*----~--~~---------~-~-~-~--*--~------~~-*--~-1 lAbility to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)[]WDGS status alarms I

I.............................................

j l __

,~ _____

~ ___, ____________________

~ _______

._~

~ ________________________________

,,_J Tuesday, November 10, 2009 Page 90 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 37 DISTRIBUTE A

ruesday, November 10, 2009 Page 91 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 37 DISTRIBUTE A

ruesday, November 10, 2009 Page 91 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 38

~~---

~~~~

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~~~~~

~~~~l r.-~~~~~ --~~ -

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IQuestionBank ## IKA_system IKA_number IKA_desc I~ -~~ -~~~~ I-~~

-~ -~I~~~ --~~---~ ~~~--j I~~~-~-~~ ~~ -~~~~-~---

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

I 1838 I

SYS075 I

K2.03 IIKnowledge of bus power supplies to the following: (CPR: 4 I. 7) o Emergency/essential SWS pumps I_~ __ ~~ ~ _ ~._ ~_~~~~~_~~._..L~~~~

__ ~.~ ___ ~~

~I ~~~. ____ - - __ ~~ ~.~~~~~_

~ ~_. __ ~~ ~.~_~ ~~~~~.~.~~~~.-~~._~.~~~~_

CURRENT 45 DAY VERSION I&E has requested that the 1B Nudear Service Water Pump breaker be racked out for lubrication.

To which ONE (1) of the following locations should an Operator be dispatched to rack out the breaker?

A.

1ETB B.

1ELXB

c.

1TB D.

1EMXB 075K2.03 VVhich ONE (1) of the following is the power supply to 1B Nudear Service Water Pump?

A.

1ETB B.

1ELXB

c.

1TB D.

1EMXB 401-9 Comments:

If I TB supplies power to I ETB, then C is also a potentially correct answer. The stem is not specific enough.

This Q is U because of potentially two correct answers.

RF A 10/28/09 fuesday, November 10, 2009 Page 92 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 38 A

9~~~~t!B~~~:t.~:.Y8ie~~=~:~~b~~====-=-J ~~:c!e~£==~=-=====-~ =-=-=====-=~~==~====_-=-=-=-======= =-=========== ________ _

I 1838 I

SYS075 I

K2.03 I [Knowledge of bus power supplIes to the followmg. (CPR. 4 I. 7) o Emergency/essentJal SWS pumps...................................

1 _________

. __.~ _______

. _______ I ~ __. _______ ~

___. _________. _____. ________._. ____. ___.~_. ____ -

CURRENT 45 DAY VERSION I&E has requested that the 1B Nudear Service Water Pump breaker be racked out for lubrication.

To which ONE (1) of the following locations should an Operator be dispatched to rack out the breaker?

A.

1ETB B.

1ELXB

c.

1TB D.

1EMXB 075K2.03 VVhich ONE (1) of the following is the power supply to 1B Nudear Service Water Pump?

A.

1ETB B.

1ELXB

c.

1TB D.

1EMXB 401-9 Comments:

If I TB supplies power to I ETB, then C is also a potentially correct answer. The stem is not specific enough.

This Q is U because of potentially two correct answers.

RF A 10/28/09 fuesday, November 10, 2009 Page 92 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination General Discussion c -~

~-'~'-'~----~~'~

-~-----~-~-~,~ -- ~-~,-,~

--~

~

~

IThe IB Nuclear Service Water Pump is powered from emergency bus IETB.

I QUESTION 38 l!~e~ KI A ~ mat~~~~~a~s~~~~E~c~ ffill:S£ ~~\\\\'_~~E9~w~r~upp!!,!~~~ l'ft1~~r~Serv~~\\y ~~E~Il1P~' ____ ~ __ ~ _______ ~_~ _~ __ ~

Answer A Discussion Ic=ORRECT~ --- ~

L_~ ____ " ___ _

Answer B Discussion r;~--'-'-~---~~'~~~~-~---~-~~~~~---~~-~~,~

~~-, ~-

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,~, --

~

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IIn~oIT:c~~~~~J: be~<llI~e~~i~t~~_c~~~~u~~ ~nd ~~rr~~~r~i~lI11~~~~B~i~sllr>P~~!r~Il1~~f) whic~~s supplied by IATB.

Answer C Discussion A

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--~~ --~'-~I I

~,~~ __ ~J

~-,-~~~--~~-~-

-'~~I~~~'~'~~

9oJl~~v~~level~ ~+ ~~8t~I'l!Y~~

Question Source 401-9 Comments RESPONSE Memory BANK

,_ ~~ ~_,~,~ ~_~~

~~, J~ ~~~ _, ___ ~ ~

MNS Bank Question PSSRN006 Per Chief Examiner's comment, question

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~ ~ ~-~ -

was revised to be more specific to eliminate

____ ~_~~ __ ~_~ __ ~ __ ~~_~~ ~~ _

the possibility of two correct answers. HCF

~~e~!'~"!!nt ~!f~I'e~~~~,~ __ ~_~,~,~ ~_~_ ~~~dfl~~~!e!~~~s~~rg~i~ed 11103109 IOP-MC-PSS-RN Objective 3 i

Ipage 21 I

I I

I I I I

" I I_~ __ ~~~~ __ ~,~,~~ __ ~_'~'_ ~~_~_'~_,~~ __ ~J I ~,~ __,~~~~_,_~~~~ ___ ~_~ __,~~~

1§~~~~B=aE~~~:~~~!!'=J-~:~~l>!~-=~ ~

18381SYS075 IK2.03

~A~~~=-=-==_==-=_==~~====-===-==-==-===== ~-====-= __ ~

iKnowledge of bus power supplies to the following: (CFR: 41.7)[JEmergency/essential SWS pumps

~~~~~

~-l

-- ~-~~-1

__ ~,~L~~_~~~ __,~~~~

L _________________________________________________ "_" ____________. __

fuesday, November 10, 2009 Page 93 of 185 FOR REVIEW ONLY - DO DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 38 General Discussion c-~

~-'~'-'~----~~'~-~-----~-~-~'~--~-~'-'~--~

~~~--~-~,~-- ~--~--~

~

---~

-~~~~,--~ --- ~-----~

---~~~-~

-~

~~

,-~~ --~'-~I IThe IB Nuclear Service Water Pump is powered from emergency bus IETB.

I I

I l!~e~KlA~mat~~~~~alls~~~~E~C~ffilI:S£~~\\\\'_~~E9~w~r~upp!l'!~~Ilt:l'f11~~r~Serv~~\\Y~~E~Il1P~' ____ ~ __ ~ _______ ~_~_~ __ ~~_~~ ____ ~,_~~~~~ __ ~J Answer A Discussion t~~~~~~~-=-~-~-=-=~--=~~~~-~~~~~~,~ ~_~_-=~~ ~~~~ ~~~~=~=~==~ ~========= _______ ~_-_~~~ ___ ~_-~~~ ___ -~-~~~~~~-_-~~_= ______ -= _____== ___===== _____ =1 Answer B Discussion GII;corr;;t:PI~usiWeb~c-;~;iti;th~;;-o;';c~nTt-;~d~c~rrectt~a~~d~IETBis-;~pplTt;dfr~~ITD~h;;;hi;-;-~pli~b; iATB~~-~-~~-~ ----~ ~~--~-~-~ ~--, ~~-

---

~-

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

---

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

Answer C Discussion

---

~------

---

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

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

---

~- ---------------------l IIncorrect. Plausible because it is the correct unit and IETB can be supplied from ITB.

I 1 __________

~ _________

~ ________

~ ___

~ __________________. ___________________________________________________________________

~ ___ -.J Answer 0 Discussion

In~~r;e~t.~Pla~;;bkb~c~~se it isth~~~~ct ~~t~a~X~~~e~tt;_ai; ~~d~IEMX~B~~a

-s~f~tY-~~;d k>~d~~te; ~hi~his~;ppl~d fr~~IETB.-~ ----~ ~-~ -~ -~ --~ ~--~-

L ________________. ________

~_. ___

~ ___________________

~ ______________________

~ __._. ___. _____

~ ________. ____________

~ __________

~ _____ _

~,,-~~~,,~~-~-

-'~~I~~~'~'~~

9oJl~~v~~level~ ~+ ~~8t~l'l!y~~

Question Source Memory BANK

,_ ~~ ~_,~,_ ~_~~

~ _, J~ ~~~ _, ___ ~ ~

MNS Bank Question PSSRN006

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~e~tlI~"!!nt ~!f~I'e~~~~. ~ __ ~_~.~.~ ~_~_

IOP-MC-PSS-RN Objective 3

[Page 21 I

I I

i_~_~ ~~~~,_ ~~~~_ ~_~_ ~~_~_~~~_ ~J IStudentReferencesp,:o;ided ~ ~

r'---~~'~~ ~---~~- ~ ~

i I

[

i I~,~ __,~~~~-,-~~~~ '_ ~_~,_,~~~

401-9 Comments RESPONSE Per Chief Examiner's comment, question was revised to be more specific to eliminate the possibility of two correct answers. HCF 11103/09 1§~~~~B=aE~~~:~~~!!'=J-~:~~l>!~~=~ ~

18381SYS075 IK2.03

~A~~~=~==_===_==~~~=====:-~.~==~==;== ~=====~:-~=~~=-=='==============~

,Knowledge of bus power supplIes to the followmg. (CFR. 41.7)cJEmergency/essentlal SWS pumps...................................

i

~ ~_~~_,_ ~,~L~~_~~~ __,~~~~

L _____________________._. _________. _______________. ___

~ __________. ___. __. _________

~ ____ _

fuesday, November 10, 2009 Page 93 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 39 D

,------ -'----T-'-------- --r-------- - ----------Il---------------------- ---~------ ---

---

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

---

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

---

~- ---------

~qu~!~~1i~"!-!#i~~l::~f --r~=~~'!'i:~2-- ~~ -11~E~~s~ENERIc 6K~;kd;-of sy~~;;etpoi~ts:i~t~lo~ks ~~d~~;~ati~;;ti~n~ ;;o~i_;;:t~d;ith-EOP-e~try-c-;;~iti~~s~(cFR:

L __ ~---~-~ _~ ____ ~

__ ~L

_~ _______ ~_J j!:2~ 45 ___ 7'L4~~L~~ ____ ~ __ ~~~ __ ~~~ _____ ~ ____ ~_~~ ______ ~~ __ ~ ___________ ~~_

CURRENT Given the following:

Unit 1 was operating at 100% RTP A Reactor Trip occurs due to the loss of Bus 1 TA NC system temperabJre is 569°F The 1A S/G NR level peaked at 82% and is decreasing Which ONE (1) of the following describes the CURRENT plant status based on the conditions above?

A Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are modulated open B.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are tripped open C.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are tripped open D.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are modulated open EPE007G2.4.2 45 DAY VERSION Given the following:

Unit 1 was operating at 100% RTP A Reactor Trip occurs due to the loss of Bus 1T A NC system temperature is 569°F Which ONE (1) ofthe following describes the CURRENT plant status based on the conditions above?

A Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are modulated open B.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are tripped open C.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are tripped open D.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are modulated open 401-9 Comments:

The KA match is OK for actions that should have occurred on EOP entry.

ruesday, November 10, 2009 "Main feed pump turbines are tripped" is not plausible without something in the stem that might drive the applicant to thinking so. Add something in the stem like a failed annunciator that might elude the applicant to thinking so.

This Q is U because of two NP distracters.

Page 94 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 39 D

Given the following:

Unit 1 was operating at 100% RTP A Reactor Trip occurs due to the loss of Bus 1 TA NC system temperabJre is 569°F The 1A S/G NR level peaked at 82% and is decreasing Which ONE (1) of the following describes the CURRENT plant stabJs based on the conditions above?

A.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are modulated open B.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are tripped open C.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are tripped open D.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are modulated open EPE007G2.4.2 Given the following:

Unit 1 was operating at 100% RTP A Reactor Trip occurs due to the loss of Bus 1T A NC system temperature is 569°F Which ONE (1) ofthe following describes the CURRENT plant status based on the conditions above?

A.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are modulated open B.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are tripped open C.

Main Feed Pump turbines are tripped Bank 1 Condenser Dump valves are tripped open D.

Main Feed Pump turbines are in MANUAL at 2800 RPM Bank 1 Condenser Dump valves are modulated open 401-9 Comments:

The KA match is OK for actions that should have occurred on EOP entry.

ruesday, November 10, 2009 "Main feed pump turbines are tripped" is not plausible without something in the stem that might drive the applicant to thinking so. Add something in the stem like a failed annunciator that might elude the applicant to thinking so.

This Q is U because of two NP distracters.

Page 94 of 185

FOR REVIEW ONLY - DO N T DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 39 RF A 10/28/09 General Discussion

,-~----~------~~-~~---~---~-

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

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

Ian a reactor trip, the Main Feed Pump turbines will go to Manual Speed control with a setting of2800 rpm (rollback hold). With NC system temperature at 569°F, this is 12°F above no-load ITave. The turbine trip controller portion of the Steam Dump control system will modulate the Bank I Condenser Dump valves open until NC system T-ave is 14.4°F above no-load T-ave 1(557°F) at which point the Bank 2 dump valves will receive a trip open signal.

I iThere is no direct correlation for automatic actions, interlocks, or setpoints associated with EOP entry conditions. Closest match to this KIA is to ask automatic actions that should have loccurred on EOP entry (in this case a Reactor Trip) given a specific set of plant conditions.

I iThis is an analysis level question as it required the applicant to associate multiple pieces of information both calculated and recalled from memory to correctly answer the question. The lapplicant must first determine that the CF pumps should be in rollback hold and not tripped based on the difference between their response on a reactor trip and SI (or other CF pump trip Iscenarios). The applicant must then determine that there is a 12:0F delta-T between T-ave and no-load T-ave and recall from memory that on the Plant Trip Controller, with less than a 14.4°F Idelta-T the Bank I Steam Dump valves will be modulated open and not tripped open. The applicant must recall the difference in setpoints betweent the Load Rejection Controller and Plant l!rip_C()fltro!!e~~tl1eyet~irlt!o-,"-~~IcJ~ip e>p~n()_lI tlle_L()a~~j~~~nS=on!!oJI~~~I"I'.: ____ ~ _______ ~ __ ~ __ ~ __ ~~ ~ __ ~ ____ ~_~_~~~ _______ ~~

Answer A Discussion

---

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

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

IIncorrect. Main Feed Pump turbine trip is plausible as the turbines will trip on an S/G Hi-Hi with a setpoint of 83%. (IA peaked at 82%). Second part of answer is correct.

I __ ~_~_------------.-------------------------.----~---._"

Answer B Discussion I

IIncorrect. Plausible because first part is correct and with the current delta-T, the Bank I Condenser Dump valves would be tripped open if control was on the Load Rejection Controller.

L ______ ~ ______. ________________________. _________. _____________________._. ______________________. ___________. _________ _

Answer C Discussion rI~c;;-rr~tM~inF_;;edPu~p~rbine trip is plausible as the turbines will trip on an S/G Hi-Hi with a setpoint of 83%. (IA peaked at 82%).. Bank I Condenser Dumps would be tripped open if Icontrol was on the Load Rejection Controller.

L_, __________. _________. _____________. ______. ____, __._. ____. ____. ___________

~ ___________

~ _______________

~ ___________________________.J Answer 0 Discussion fCORRECT.

L~~

__. _____ ~

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I RO i

Comprehension L. ____ ~_

~_

~ __. _______.. __. __ _

Question Source 1-*-

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~ Developed f~e~!'cp~~~t~!f!"!n~!S _______ ~ ___ ~~

l~tud~'!!_R!fe~n~e~~r()!j~~ ~_

~ OPT Approved ILesson Plan OP-MC-STM-IDE pages 25, 29, and 31 I

ILesson Plan OP-MC-CF -CF pages

!19 Lesson Plan OP-MC-CF-IWE I

~ OPS Approved I

ipage 29 I

~ NRC Approved I

i

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

- --.- -.- ~~

-~~-

I. __.. _~~--.~--~~--~.~~--~-~

401-9 Comments RESPONSE Stem revised to add a possible challenge to S/G Hi Hi Level (P-14) in order to provide plausibility to the main feed pump tripped distracters. Revised distracter analysis.

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~:EO~S~ENiRiCQ K~~;Ied~;~Ys~~ ;;tpcints,in~rlo~k_;~d~~t~~atk;ctio~s~s_;o~i;ed ;ithEOP-entry Zo~diti~~ II

-~ - ~- _~ ____. __ L_._ ~- -- ---

I(CFR: 41.7 /45.7/45.8) l ___ ~ ____._. ______ ~_._.~ _____ ~~ __ ~.~~. ________________ ~ __._~_ ~_~_~~

____ ~~.~ ___.~ __.~

Tuesday, November 10,2009 Page 95 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 39 RF A 10/28/09 General Discussion

,------~------~~-~~-------~-

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

---~---~----~----~~------~-------~~--~----~--------------~~~~----I Ian a reactor trip, the Main Feed Pump turbines will go to Manual Speed control with a setting of2800 rpm (rollback hold). With NC system temperature at 569°F, this is 12°F above no-load I ITave. The turbine trip controller portion of the Steam Dump control system will modulate the Bank I Condenser Dump valves open until NC system T-ave is 14.4°F above no-load T-ave 1

1(557°F) at which point the Bank 2 dump valves will receive a trip open signal.

I I

iThere is no direct correlation for automatic actions, interlocks, or setpoints associated with EOP entry conditions. Closest match to this KIA is to ask automatic actions that should have loccurred on EOP entry (in this case a Reactor Trip) given a specific set of plant conditions.

iThiS is an analysis level question as it required the applicant to associate multiple pieces of information both calculated and recalled from memory to correctly answer the question. The lapplicant must first determine that the CF pumps should be in rollback hold and not tripped based on the difference between their response on a reactor trip and SI (or other CF pump trip Iscenarios). The applicant must then determine that there is a 12:0F delta-T between T-ave and no-load T-ave and recall from memory that on the Plant Trip Controller, with less than a 14.4°F Idelta-T the Bank I Steam Dump valves will be modulated open and not tripped open. The applicant must recall the difference in setpoints betweent the Load Rejection Controller and Plant IITrip Controller as the setpoint for Bank I trip open on the Load Rejection Controller is 8.1 OF.

---

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

---

.-~----

~-

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

Answer A Discussion IIncorrect. Main Feed Pump turbine trip is plausible as the turbines will trip on an S/G Hi-Hi with a setpoint of 83%. (IA peaked at 82%). Second part of answer is correct.

I __

~ ___ ------------.-------------------------.----~---._"

Answer B Discussion

-.~----~-~-.------ -- ---_._-._-_._-- -.--

IIncorrect. Plausible because first part is correct and with the current delta-T, the Bank I Condenser Dump valves would be tripped open if control was on the Load Rejection Controller.

1 L ______ ~_. ____

~ _________. _____________________._. ____._~ ____________. __

.~ __. __. ___. ______ ____.J Answer C Discussion rI~c;;-rr~tM~inF~edPu;;p ~rb;~e tripispI;u;ible~;-thetu~bin~;ill trip~~n-s/G-Hi-Hi~ith-a__;~tP;;i~t of83%~IA-p~~ed ;82% ~Ba:;;-k -I c~ctt:~~-;: D~~ps -;~ld betripPedo~; if-I Icontrol was on the Load Rejection Controller.

1 L_. ___. ______. _________. _____________. ______. ____. __._. ____. ____. _________________. ___

._~ _____._. _____________

.~ __________________ ~ __ J Answer 0 Discussion rCORRECT.---~-------- --- -- ----~~~---------~---~----~-- ---~--- -~- -- ------

--~~--------~---- ~------ ------1 L _

~

_______________ ~

_____________________________________________________ ~

______________________ ~

_____________ ~_~ _____ ~

___ --.l

-L'J-bl..--,-T **-CO -itl---L-~I- -'Q --ti-T--r------- --~~-Q~StI~-So~-~-- -~~~-----I 401-9 Comments RESPONSE 1-<>:. R~~-e -i ~--C:~Pr"~:;sT:~-~-I-~\\l8tf~ ype-l------~~--~-~-u~~~.'!.-~rc!-~----~___:----l Stem revised to add a possible challenge to L __ ----- ~- ---- --- --- ___ L ____ - --- -

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

S/G Hi Hi Level (P-14) in order to provide

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r[e~!I~~~r!t~!f~!~~~~-=~=_ _~-===-==~~.

ILesson Plan OP-MC-STM-IDE pages 25, 29, and 31 ILesson Plan OP-MC-CF -CF pages

!19 Lesson Plan OP-MC-CF-IWE ipage 29 1_- ______________________________ ~

r-- --

-~-

--~-- -

--~---

--~~~

l~tud~'!!_R.ftfe~n..c:.e~~r()!j~~ __

I I

i 1 ______ - - - - - - - - - - - - - - - - - - - - -

plausibility to the main feed pump tripped distracters. Revised distracter analysis.

~

-~-

--~~- ~ -- - - -

-r----~--

---

~ --- ---

a~~tI~'!El..a.'!~ ~K.~=I!)'IJ!!"'- _ l~-.'!!J"!...b!,"-___ _

~Aj!S~=--= =-===_~_==_====~_==_==~_=_======_~=_==-= =~=-~===_==-~=-~===-=-=-1 IEPE007 GENERICC.lKnowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.l I

I 8391EPE007 12.4.2

________________ ---------.1-------

ILC£R: i.'.7 L~2L~*~L ____ _______ ~____ __ __________ ~_~ ____ ~ ____ ~ __.J Tuesday, November 10,2009 Page 95 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 39 DISTRIBUTE D

Tuesday, November 10,2009 Page 96 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE D

QUESTION 39 Tuesday, November 10,2009 Page 96 of 185

A FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 40

~9ie~~~~Bar!k=I[l~~~~~!~~=J~!t~~~i======1 r~~*:d:!~~=======================================-_========================

l 1840 j

APE008 I

AK 1.0 1

IKnowledge of the operational impli~ations of the following ~oncepts as they apply to a Pressurizer Vapor Space Accident: (CFR

- ---------- ------.-- _____ L _______ - --- ------- Li41.8 1 41.10 1 45.3)ClThennodynamlcs and flow charactenstlcs of open or Jeakmg valves.......................................................

---

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

CURRENT 45 DAY VERSION Unit 1 is in Mode 3 at full temperature and pressure. The crew has entered AP/1/A/55001011 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly.

• Pressurizer pressure is 2150 PSIG

• PRT pressure is 2 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PORV Discharge Temperature State of the Effluent A.

200-240°F Wet Vapor B.

200-240°F Saturated Vapor

c.

24D-280°F Wet Vapor D.

24D-280°F Saturated Vapor APE008AKI.OI Unit 1 is in Mode 3 at full temperature and pressure. The crew has entered AP/1/A/55001011 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly.

• Pressurizer pressure is 2150 PSIG

• PRT pressure is 2 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PO RV Discharge Temperature State of the Effluent A.

200-240°F Wet Vapor B.

200-240°F Saturated Vapor

c.

240-280°F Wet Vapor D.

240-280°F Saturated Vapor 401-9 Comments:

Double jeopardy with Q 9: This Q is not double jeopardy with Q 9 because 9 dealt with a ruptured PRT. This Q deals with the usage of the mollier diagram. I am researching the SRO ONLY aspect of this.

RF A 10/28/09 ruesday, November 10, 2009 Page 97 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 40

~9ie~~~~Bar!k=I[l~~~~~!~~=J~!t~~~i======1 r~~*:d:!~~=======================================-_========================

I 1840 I

APE008 I

AK 1.0 1

IKnowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: (CFR L - -----

-- ------ -- _._L ______ - ------- ~l.~~'!I_=19l ~~D.[lI~~ID1()cl!'I2~~s~~ci.J'lo~_cE1!r~c~.:i~t~~()f.<"JPen.<"Jr}t~a.'c~n~.".alv~~.:.:.... ~

........ :.:.... :__~.... _::__:_.:.... ~:.::__. _____ _

CURRENT Unit 1 is in Mode 3 at full temperature and pressure. The crew has entered AP/1/A/55001011 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly.

• Pressurizer pressure is 2150 PSIG

• PRT pressure is 2 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PORV Discharge Temperature State of the Effluent A.

200-240°F Wet Vapor B.

200-240°F Saturated Vapor

c.

Wet Vapor D.

240-280°F Saturated Vapor APE008AKI.OI 45 DAY VERSION Unit 1 is in Mode 3 at full temperature and pressure. The crew has entered AP/1/A/55001011 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly.

• Pressurizer pressure is 2150 PSIG

• PRT pressure is 2 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PO RV Discharge Temperature State of the Effluent A.

200-240°F Wet Vapor B.

200-240°F Saturated Vapor

c.

240-280°F Wet Vapor D.

240-280°F Saturated Vapor 401-9 Comments:

Double jeopardy with Q 9: This Q is not double jeopardy with Q 9 because 9 dealt with a ruptured PRT. This Q deals with the usage of the mollier diagram. I am researching the SRO ONLY aspect of this.

RF A 10/28/09 ruesday, November 10, 2009 Page 97 of 185

FOR REVIEW ONLY - DO A

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 40 General Discussion r;:;--~--~~---~~--

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

!Required Reference is steam table.

[This question is associated with TMI. Per the TMI lesson plan:

lIt was clear from the operator's understanding of the PZR PORV discharge temperature and the indications of saturation/superheated fluid in the hot leg, that operator knowledge of Ithermodynamics needed to be drastically improved.

[At 0520 the operators obtain a printout of PZR Safety and PORV discharge temperatures showing 232°F and 283°F respectively, but the operators still believe the PORV to be closed. For Isome time the PORV had been leaking prior to this day. The PORV leakage had been accepted as a normal part of operation (i.e. workaround). The temperature on the discharge of the PZR PORV had indicated what would be seen for PORV open or leaking since the PORV had started leaking. The operators believed the discharge temperature would increase to PZR Itemperature if the PORV actually opened.

i

[A Pressurizer pressure of2150 psig (2165 psia) corresponds to a Saturated Vapor Enthalpy of 1125 BTU/Ibm. This Enthalpy undergoing a throttling process discharging to a PRT at a

[pressure of 2 psig (17 psia)

IIThiS KA is matched since the applicant must know how to use the Mollier diagram to detemline the thermodynamic characteristics of the fluid entering the PRT.

~~is_ is...a£l3~IY~~\\lt:1 becau~ the apEli<:lin.t... m~s~v~l~te-.£h~g~eE... ~nditions...u~n~ __ the ~oIlier._diagram to~termine t~~rrect~empeI"ilture.....ani.state~f the fluid: _______ _

Answer A Discussion E~-;:;:e~:2i~p~s:.u~_~r~~I~~~Il ~tha~~~:l~~~e_~nt~r~ction ofth~PR~)ressure resu~ in ~atur~on temperature of200-240 Answer B Discussion rr:~---~-------~- ---

---

~-~--- -----

---

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

---~-~-~~--

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

Lln~orrect. ~ J>latISilJle_a: thi~ t~ll1~ature \\\\l()~d ~e ~b~i~d~

~e-=~ent~ll<lwed ~h~en~oE~~~~m the PRT pressure~o th:....saturation curve.

Answer C Discussion 1---- -- -

IIncorrect. Plausible if the applicant follows the entropy line from the PRT press to the saturation curve.

L_~ __________________________._. __. ____________________._._. ____._. ___ _

Answer 0 D'scusslon fn~~~~tP~~b~ as thi~~I"at~;~~\\(j~~b~~~d?th~~~f~l~thei;;-tr~~~ f~om thePRT-pre;; t;the ~turation curve.

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

---

~-r~-~-~-~-----

-~--

-~~-

Cognitive Level I QuestlonType Quest/on Source

-- --~-~--- ------~-~r-----~ -- -~---f- ------- -

---

~----

Comprehension BANK L-2006 NRC Q2 (Bank 608)

--- ---------~--.-.-- - -_.- -

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

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

[OevelopmentReferences --------- -

[Stt;ientRete~nces Provided r;;~-

---~-~~--

~-~---

-~--- ~-~-

-~- -- ~-

r-=--~- --~----~--

ITHFFL007 ISteam Tables (Q40)

IoP-CN-II-TMI

[

[

I

[

i L ___ __ __ ___ __ _ __ __

__J ~ ______ _

I I

_J

---1

---~- ---._---

______ ~ _______ ~J 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

~- - -- -

-r--~-

-~-

-I-~~-~--- --

-~~~- --

~ - ---

-~ ---~-

---

~-~~~-~-

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

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

--~-~-

---

~-~-~~-I Lue~~~~,*-~~~;~:~:~~m-l~~z~l'!l_~~ ~-_-_ -:j 1~::I::~e~f the~~~ati~~imp~atio;~ ofth~-follo~ing ~~~~e~ts ~ th~y-applyt?a P~~~urizerVapor sP;c~Accident:-l

[(CFR 4 1.8 /41.10/45.3 )UThermodynatmcs and flow characterIstics of open or leakmg valves

---~-

---

~- --- ----

__ ______ J ruesday, November 10, 2009 Page 98 of 185 FOR REVIEW ONLY - DO A

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 40 General Discussion lR~q~~dRefe-;~ceiss~amtilik:-------~--*-~----~*~~--**~--~-- --~ -------~

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

[This question is associated with TMI. Per the TMI lesson plan:

lIt was clear from the operator's understanding of the PZR PORV discharge temperature and the indications of saturation/superheated fluid in the hot leg, that operator knowledge of Ithermodynamics needed to be drastically improved.

[At 0520 the operators obtain a printout of PZR Safety and PORV discharge temperatures showing 232°F and 283°F respectively, but the operators still believe the PORV to be closed. For

'[some time the PORV had been leaking prior to this day. The PORV leakage had been accepted as a normal part of operation (i.e. workaround). The temperature on the discharge of the PZR PORV had indicated what would be seen for PORV open or leaking since the PORV had started leaking. The operators believed the discharge temperature would increase to PZR Itemperature if the PORV actually opened.

i

[A Pressurizer pressure of2150 psig (2165 psia) corresponds to a Saturated Vapor Enthalpy of 1125 BTU/Ibm. This Enthalpy undergoing a throttling process discharging to a PRT at a

[pressure of 2 psig (17 psia)

IIThiS KA is matched since the applicant must know how to use the Mollier diagram to detemline the thermodynamic characteristics of the fluid entering the PRT.

~~is_ is...a£l3~IY~~\\lt:1 becau~ the apEli<:lint_ m~s~v~l~te...!h~gi~eE... ~ndition~u~n~_!he ~oIlier...diagram to~termine t~~rrect-.!.empeI'iltur~ani.state~f the fluid:~ ______ _

Answer A Discussion E~~e~:2h~p~~u~_~r~~I~~ ~Il ~tha~~~:I~~'I'I1~n~;~~~n ofth~PR~pres~~r~~esu§in a satur~~n temperature of 200-24() __===-=-========-== -= =-J Answer B Discussion rr:----~----.---~.-~~--.-~---~-~--.~.-.--.-.~--.---.--------~~~----.---.. ------~---.. ---.------------

Lln~orrect.. J>latISi~e_~ thi~ t~ll1~ature ~~d

~e ~b~i~d~

~e---=~entfCll\\()wed ~h~en~oE~~~~m the PRT pressure~o th:!aturation ~~. ____ ~ _________ _

Answer C Discussion

-~.-- ----

~.---~ ----

---

~ -.--

-~.-------~---------------.-~--------~-----.. -.-----.----*---~-l

~n~~ct.. Plausible if t~:~Eplic1ll1t fo~ws the~ntroEY lin..=. fro~t~PR'!'.tJ~~~t~~_~turatio~u.rv.:-. _______ ~~. _____________ ~

____ ~ ____ J Answer 0 D'scusslon fn~~~~tP~~b~ as thi~~~t~;~~l<I~~b~~~d?th~~f~l~thei;;-tr~~~ f~m theP~~~~ ~he ~turation~~~.~-=_-=-___ =--=--=--=--=--=--=--_======--=-J

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

---~*~r-~*-*----*-- --~~

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

Cognitive Level I QuestlonType Quest/on Source

~. ~-~--.-- ----*----r*~---* -. -*-*~f- --.---- -

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

Comprehension BANK L-2006 NRC Q2 (Bank 608)

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

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

~ Developed r;;:--

-~---- --- -

-~-- -.--

IDevelopment References fTHFFLo07~ ----- -~~-~ -- -~-

IOP-CN-II-TMI I

I I I

~ OPT Approved

~ OPS Approved

~ NRC Approved

__ J,.~ ___.. _

~_

~ ______________._" _____ J 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

Luestj~f!B~nj< #JKA:SYste....,;_1KA:~~'!l~ber ~~-___ -_J ~=de~ -_-~==-=-=--== =-=-=-==-~~= ~~=-~=== = =_===--====-=-__ =-====-=_=-~

I 840lAPE008.

JAKl.OI.

.. l !Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident:

I

-- ~. -- -

,-~--

---

-- -- -- -I [(CFR 41.8 / 41.10 / 45.3 )CJThermodynamics and flow characteristics of open or leaking valves l.. **.. **~.. ::.---: ____ *~*.-::*.. *=.... :.*_:***_... *=.~~.~ ____ ~ ______ ~. ________. ___ ~ ____

_ ______.J ruesday, November 10, 2009 Page 98 of 185

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 40 A

'uesday, November 10, 2009 Page 99 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 40 DISTRIBUTE A

'uesday, November 10, 2009 Page 99 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 41 c~~ ~--

-~ ~-

~tiI--~- -~

~~-~--~~~~

~1J~t!<>~B~nk!I~~sys~e,!,~ rl~-!!U~be-," __ _

iKA~des-c~ ---~-~--~-~~~ ~~- -

-~-

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

---~-~-

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

-~~-

I 1841 i APE015/017.

AK2.08 L-_~ __

~ _____ ~ ____ L _________

~ __ ---1 _____________ _

fK~~-wl~dg~oftJ; i~t;;:;'eTat~~b~t;eenth~Rea~t~;-Co~I;;-~tP~mp M~alfu~t~n~C;s-; oric FI~;)~ndthe follo;i~g:(cFi4 i~7!

i+/-?*n[~c~~s __ ::--:: ___ ::~.:--:. ____.:~.~.... :.~:---::--.. ~= __ ~~~ __ ~~~ __ ~ ___ ~~_~~ ___ ~~_~~_

CURRENT Given the following conditions on Unit 1 :

Seal Injection AND Thermal Barrier Cooling have been lost to all NCPs Which ONE (1) of the following describes the OPERATIONAL IMPLICATIONS associated with this condition?

A.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless seal injection is restored within 30 minutes.

B.

C.

D.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless EITHER seal injection OR thermal barrier cooling is restored.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless BOTH seal injection AND thermal barrier cooling are restored.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless thermal barrier cooling is restored within 30 minutes.

APE015/017 AK2.08 45 DAY VERSION Which ONE (1) of the following describes the OPERATIONAL CONCERN associated with a Loss of Seal Injection Flow coincident with a Loss ofThermal Barrier Heat Exchanger KC Flow?

A.

B.

C.

D.

An increase in pump lower bearing temperature, seal temperatures, and No.1 sealleakoffflow is expected. However, prompt closure (within five minutes) of a Seal Retum Containment Isolation Valve should allow continued NCP operation.

NCP operation in this condition is limited to 30 minutes, due to the affect of borated NCS fluid on the pump seals. Seal Injection flow must be recovered or a pump trip will be required.

No temperature increase of the pump or motor bearings is expected but No.1 seal operation can not continue without fluid between the non-rubbing seal faces. Therefore, the No.2 seal must be placed in operation immediately or No.1 seal failure will occur.

An increase in pump lower bearing temperature, seal temperatures, and No.1 sealleakoff flow is expected. Exceeding one of the pump operational limitations is expected unless seal injection or thermal barrier cooling is recovered.

401-9 Comments:

All choices involve teaching. Additionally, the stem does not solicit much of the info included.

Since the Q is comprehensive, redesign it to a two part Q.

RF A 10/28/09 ruesday, November 10, 2009 Page 100 of 185 B

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 41 DISTRIBUTE

~~~t~~B~nk!f~A.:sisIe~=-I~_~u~be-,"-=-=-=-~~_de~C- -=-===::::::::==~=-::::==-====-_=::::::::====-===-===~::::_::::===::::~::::=-=-=::::=-

I 1841 i APE015/017 r AK2.08 IlKnowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss ofRC Flow) and the following: (CFR 41.7 1

~~- ~

___. __ L._._. __._..J __.~~~

--~~, i+/-?n[::r..c~~S __ ::-.-::... ::..... :-.-:..... :............. :..... :...-.::......-:-..... __ ~~~ ______________ ~ _____ ~_~~_

CURRENT Given the following conditions on Unit 1 :

Seal Injection AND Thermal Barrier Cooling have been lost to a/l NCPs Which ONE (1) of the following describes the OPERATIONAL IMPLICATIONS associated with this condition?

A.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless seal injection is restored within 30 minutes.

B.

C.

D.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless EITHER seal injection OR thermal barrier cooling is restored.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless BOTH seal injection AND thermal barrier cooling are restored.

NCP operational limits will be exceeded and NCPs will have to be seaJred unless thermal barrier cooling is restored within 30 minutes.

-.~----

APE015/017 AK2.08 45 DAY VERSION Which ONE (1) of the following describes the OPERATIONAL CONCERN associated with a Loss of Seal Injection Flow coincident with a Loss ofThermal Barrier Heat Exchanger KC Flow?

A.

B.

C.

D.

An increase in pump lower bearing temperature, seal temperatures, and No.1 sealleakoffflow is expected. However, prompt closure (within five minutes) of a Seal Retum Containment Isolation Valve should allow continued NCP operation.

NCP operation in this condition is limited to 30 minutes, due to the affect of borated NCS fluid on the pump seals. Seal Injection flow must be recovered or a pump trip will be required.

No temperature increase of the pump or motor bearings is expected but No.1 seal operation can not continue without fluid between the non-rubbing seal faces. Therefore, the No.2 seal must be placed in operation immediately or No.1 seal failure will occur.

An increase in pump lower bearing temperature, seal temperatures, and No.1 sealleakoff flow is expected. Exceeding one of the pump operational limitations is expected unless seal injection or thermal barrier cooling is recovered.

401-9 Comments:

All choices involve teaching. Additionally, the stem does not solicit much of the info included.

Since the Q is comprehensive, redesign it to a two part Q.

RF A 10/28/09 ruesday, November 10, 2009 Page 100 of 185

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 41 General Discussion r::;:'-"~-'----"---'------ ---,-,-'--' -' -- ----,-, -------,-,- -,-,----,,- ---,---,--'-,--,-----,-- -

--'--'------'--'-'------':1 IThe conditions presented in this question represent complete loss of seal cooling to the NCP seals and the NCP lower pump bearing. This would result in the water at NC system temperature I Ireaching the pump seal package within approximately 10 minutes and would result in the pump parameter reaching trip criteria for both sealleakofftemperature and lower bearing i

Itemperature.

I IKA is matched because the candidate must demonstrate and understand interrelations between a loss of KC cooling to the thermal barrier coincident with a loss of seal injection. Additionally Ithe conditions presented will result in a loss of the pump.

I IThis is a higher cognitive level question because the candidate must interpret mUltiple symptoms of a failure, evaluate the impact to continued pump operation and evaluate alternate actions to lnliti~~tlle~Il5ieqtI~l1c~s ~f~eJ~s_of~ooli~g ____________________________________________________________,

Answer A Discussion r - --- ---- -,---- --- ---,-,--- --"--- -- -,-'-'---,-,-'-,------,-,---- ----,-,----

-,-,--,--~-, --,-,----- - ----I

[Incorrect. Plausible because seal injection or thermal barriier cooling must be restored to continue operation ofNCPs. The time that is must be restored is significantly less than 30 minutes.

I

~~li!Ple~~e~n~e~~o_~~

m~llte~in Li_mits ~<!f>r-e~atltiolls___ ______ __ _ ___ __ __ _ ______ _________________, _________________,~

Answer B Discussion E~~~CT=-=~-=-===== =-========-=====-

Answer C Discussion

~--,'- -- -,- -,-,- -- ----,,-------,-,'------,---- --- -,-,-,-- -,- -,--,---- --- -- - ---- -'--'- - -'---------l i~n(;o~e~_Sil1Ce_both ~e~ inj~ti~~_~fl~ ~he~m~ bar~ieI" c~olin!pl*o~~: ~olin~~~e~~=P

~~riflg~and ~e~s,~t is ~allSit)le~o~elieve~~ ~t~ar~ ~~uir:ct f~~ollti~ued _CllJeI"at~o~ _____ J Answer 0 Discussion 1---- ----

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

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

---

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

---

~-

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

[Incorrect. Plausible because seal injection or thermal barriier cooling must be restored to continue operation ofNCPs. The time that is must be restored is significantly less than 30 minutes.

I,

[!v!tIlitp~~terellce~ ~o3~mi~~_~n~illli~all(!l'~c~utioIl5i. ________________________________________________________ ~

'~

Job Level I

Cognitive Level I QuestlonType

~

--- ~ --'- ----,-,---

- -'-'/-' ------,-,---

RO I

Comprehension I

BANK

_____ ' __ L ____________,_-1, ____, ___,_, __,

Question Source Bank #PSNCP043

_J 401-9 Comments RESPONSE

! Per Chief Examiner's comment revised

---, -- -- J question to remove 'teaching' statements

~ Developed 1--' - ---,- - -- -

I. - --,-- ---- -,--,- --,-

from the answers.

1~~e~~~f!tB~1ftre~c~s_ __ __ ___

~tude~tBf!!erenc~~~v~!cL----

~ OPT Approved

~ OPS Approved

~ NRC Approved ITechnical Reference(s): Lesson Plan OP-MC-PS-NCP I

IRev. 25, page 25 I

\\Leaming Objective: OP-MC-PS-NCP, Obj. 4 I

I

---

~---

---

~-

[-------~--------------------

-' ';]----' -

-, ~--

~, -

~lU~s~o~Ba~k_~+~".~yste"! _1~-f!'Jr1'l~~ ___ _

~~~e~~ ___________________________________________ _

184lAPE0151017t *AK2.08

___,_J __, ___ ' ___,, ___, __,, ___ _

IKnowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss ofRC Flow) and the following: (CFR I i41*~/4?~LC:~C:_\\V~~*.... *... *~**~***~*...... **... *:~*:~*:*~*.. **~~* ___ ~ _________________________ J ruesday, November 10, 2009 Page 101 ofl85 FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 41 General Discussion r::;:'-"~-'----"---'------ ---,-,-'--' -' -- ----,-, -------,-,- -,-,----,,- ---,---,--'-,--,-----,-- -

--'--'------'--'-'------':1 IThe conditions presented in this question represent complete loss of seal cooling to the NCP seals and the NCP lower pump bearing. This would result in the water at NC system temperature 1

Ireaching the pump seal package within approximately 10 minutes and would result in the pump parameter reaching trip criteria for both sealleakofftemperature and lower bearing i

Itemperature.

I IKA is matched because the candidate must demonstrate and understand interrelations between a loss of KC cooling to the thermal barrier coincident with a loss of seal injection. Additionally Ithe conditions presented will result in a loss of the pump.

I IThis is a higher cognitive level question because the candidate must interpret mUltiple symptoms of a failure, evaluate the impact to continued pump operation and evaluate alternate actions to lnliti~~tlle~Il5ieqtI~l1c~s ~f~eJ~s_of~ooli~g ____________________________________________________________,

Answer A Discussion r - --- ---- -,---- --- ---,-,--- --"--- -- -,-'-'---,-,-'-,------,-,---- ----,-,----

-,-,--,--~-, --,-,----- - ----I

[Incorrect. Plausible because seal injection or thermal barriier cooling must be restored to continue operation ofNCPs. The time that is must be restored is significantly less than 30 minutes.

1

~~li!Ple~~e~n~e~~o_~~

m~llte~in Li_mits ~<!f>r-e~atltiolls___ ______ __ _ ___ __ __ _ ______ _________________, _________________,~

Answer B Discussion E~~~CT=-=~-=-===== =-========-======_=====-== __===-==_========================-----

Answer C Discussion

~--,'- -- -,- -,-,- -- ----,,-------,-,'------,---- --- -,-,-,-- -,- -,--,---- --- -- - ---- -'--'- - -'---------l i~n(;o~e~_Sil1Ce_both ~e~ inj~ti~~_~fl~ ~he~m~ bar~ieI" c~olin!pl*o~~: ~olin~~~e~~=P

~~riflg~and ~e~s,~t is ~allSit)le~o~elieve~~ ~t~ar~ ~~uir:ct f~~ollti~ued _CllJeI"at~o~ _____ J Answer 0 Discussion 1---- ----

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

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

---

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

---

~-

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

[Incorrect. Plausible because seal injection or thermal barriier cooling must be restored to continue operation ofNCPs. The time that is must be restored is significantly less than 30 minutes.

I,

[!v!tIlitp~~terellce~ ~o3~mi~~_~n~illli~all(!l'~c~utioIl5i. ________________________________________________________ ~

"~b L~!' J_~=- ~~grlii'!e=L!v!'

9~~I~rlTypeT -- ------ -----QueStlon-Souree------ --- -

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RO Comprehension BANK*

Bank #PSNCP043

___ ' __ L ____________, __ L ____, ___,_, __,,~, __

~ Developed 1--' --.-.-,- -

1~~e~~~~t~~1ftre~c~s _______ _

ITechnical Reference(s): Lesson Plan OP-MC-PS-NCP IRev. 25, page 25 ILeaming Objective: OP-MC-PS-NCP, Obj. 4 I i 1.---'-'- -,,---,--,- -,-,-

~tude~tBf!!erenc~~~v~!cL ___ _

I 1

1,

~ OPT Approved

~ OPS Approved

~ NRC Approved L, __,_,, __ '

1_, __,_,- _, ___, ____, _____,

401-9 Comments RESPONSE Per Chief Examiner's comment revised question to remove 'teaching' statements from the answers.

-' ';]----' -

-, ~--

~lU~s~o~Ba~k_~+~".~yste"! _1~-'!'Jr1'l~~ ___ _

~~~e~~ ______________________________________________,, ___,1 IKnowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss ofRC Flow) and the following: (CFR 184llPE0151017 lAK2.08

---

~--- --- -

~- ---- -

i41*~/4?~LC:~c:_\\V~~*.... *... *~**~***~*...... **... *:~*:~*:*~*.. **~~* _____________________________ ~

ruesday, November 10, 2009 Page 101 ofl85

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 41

[uesday, November 10,2009 Page 102 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 41

[uesday, November 10,2009 Page 102 of 185

C FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 42 rU*J.,t~ 'r~~~;rlKA~nu:~ro:~ --i i~;-i:~ Of,th,~p'r":'nal ;m~;~t':~~O~h~f01l0:mgroo;p~ Mih;y ~pply[o CO"O~R~"'O;O~I;;' Mak,:;.~;r{41.8 !

14 I.I 01 45.3)LRelatlOnshtp of chargmg flow to pressure dIfferentIal between chargmg and ReS.............................

l~=----~~ __

~_~_~_~_~_~~_~_~_~ ___ ~ __

~~_~ ______

~ __

~_~~~_~~ ____ ~_~~ ___

~_~_~ ______

~_~ __

CURRENT Which ONE (1) of the following describes why NC system pressure is checked less than 2335 PSIG immediately after initiating emergency boration in FR-S.1 (Response to Nuclear Generation / A lWS)?

A

8.

C.

D.

To reduce NC pressure to allow dosing of NV pump recirc valves to maximize emergency boration flow.

To maintain positive control of NC pressure to prevent lifting a code safety relief valve.

To ensure that the boration flow rate is sufficient for emergency boration.

To maintain pressure below the PORV setpoint to prevent cyding the PORVs.

APE022AKl02 Revisited No comment at this time RF A 10/28/09 fuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following describes why NC system pressure is checked less than 2335 PSIG immediately after initiating emergency boration in FR-S.1, Response to Nuclear Generation / A TWS?

A.

8.

C.

D.

To reduce NC pressure to allow dosing of NV pump recirc valves to maximize emergency boration flow.

To maintain positive control of NC pressure to prevent lifting a code safety relief valve.

To ensure that the boration flow rate is sufficient for emergency boration.

To maintain pressure below the PORV setpoint to prevent cyding the PORVs.

401-9 Comments:

Page 103 of 185 C

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 42 IQ~;~~~ank#lKA:~yste~JKA:n~m-~r== ~=-I i~-=d~s~= ~====-= ~~===-=== =-=====~== =_~==~=~--= ~-_====-~=== ~

r. __ 1842 __ L~P~0~2_J ___

AI(J~2 __ ~ J IKnowledge of the o~erati?nal implic.ations of the followin~ conc~pts as they apply ~o Loss of Reactor Coolant Makeup: (CFR 41.8 1

~~ -

141.1 0/45.3 )iJRelatlOnshlp of chargmg flow to pressure dIfferentIal between chargmg and RCS.............................

l.=---.~ __

.~._._. ____.~_~ ______.~~_. __________ ~ ___ ~

_____ ~ __._. _____ ~._. ____ ~~_~ __ ~

CURRENT Which ONE (1) of the follOwing describes why NC system pressure is checked less than 2335 PSIG immediately after initiating emergency boration in FR-S.1 (Response to Nuclear Generation / A lWS)?

A

8.

C.

D.

To reduce NC pressure to allow dosing of NV pump recirc valves to maximize emergency boration flow.

To maintain positive control of NC pressure to prevent lifting a code safety relief valve.

To ensure that the boration flow rate is sufficient for emergency boration.

To maintain pressure below the PORV setpoint to prevent cyding the PORVs.

APE022AKI02 Revisited No comment at this time RF A 10/28/09 fuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following describes why NC system pressure is checked less than 2335 PSIG immediately after initiating emergency boration in FR-S.1, Response to Nuclear Generation / A TWS?

A.

8.

C.

D.

To reduce NC pressure to allow dosing of NV pump recirc valves to maximize emergency boration flow.

To maintain positive control of NC pressure to prevent lifting a code safety relief valve.

To ensure that the boration flow rate is sufficient for emergency boration.

To maintain pressure below the PORV setpoint to prevent cyding the PORVs.

401-9 Comments:

Page 103 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination General Discussion No comment at this time RF A 10/09/09 QUESTION 42 c

~-~----~---------------------~--------------------------------------------------------------------------------I INC system pressure is checked after initiation of emergency boration in FR-S.I to ensure that pressure is low enough to provide adequate boration flow to the NC system. IfNC system Ipressure is elevated, it would impede charging flow (and hence boration flow) to the NC system.

IThe higher level portion ofthis KA related to Loss of Rector Coolant Makeup could not be directly matched. The MNS Abnormal Procedure for associated with Loss of Reactor Coolant IMakeup (AP-12, Loss of Letdown, Charging, or Seal Injection) does not address checking NC system pressure to determine if an elevated NC system pressure is impeding charging flow to

[the system. The closest possible match was to relate the question to a potential for insufficient boration flow as a result of the differential pressure between the NY and NC systems when

~m~r~~e~cyJ)()l"a~o~}s_require~ _____________________________________________________________ J Answer A Discussion

,,- --- ------- ----------------- ------ -----------------------------------------------------------------l

~ncorrect. Plausible as there is Foldout criteria which has the operator check NC system pressure to determine if the NY pump recirc valves should be open.

---~-,~-.-- -

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

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

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

Answer B Discussion

---I

---~

~c~~c~P~allSi~le~s~h~ i~_ b_=_Io~ ~h~ift ~~int for~h-= ~essu~z~~_~ty_valv__=_s________ ___ _______ _

Answer C Discussion r~O~£T~=--====- _~=-=-_~===-==-=-=-=========_=-====-

~ ___. ____________ J Answer 0 Discussion r------------- -- ------------ -- ------------ -------- --- --- ------- ---

~n~l"I"e~.~laus~I_=__~~tl1is~~e~~t~e ~~e~~n~!()~h_=_P~~~~Y: ________ ~ __ _

Job Level T -

Cognitive Level

-- ---- ----i-~ --

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

---

QuestlonSource - --- -- -- --I 401-9 Comments RESPONSE RO*

Memory

- ______ 1 __ -

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

- --MNSBank EPFRSN07 - -- - - -----1 Considered SAT for submittal with no

-- ------------ --------- ---I comments. No changes.

c----- ----------- ---- - -----

pe,,!loerne,!!Refere~e8 _____ _

\\OP-MC-EP-FRS page iStudentR-;iere~ce; Provlded---

1-----------------

1 I L ____ ~ _______________________ _

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

l~e!t~~~njt!lE_A-;y8!e~=IKAjl.:.~==-=--=-1 rt<A-=-d!SC=-~=====_=__-_===_=_========_==_=_==~=_======_===_=_==_==_--

______ ~8~2~P~~~ ___ J~~O~ _

_. J [Knowledge of the o~erational i~plications.ofthe following conc~pts as.they apply to Los~ of Reactor Coolant Makeup: (CFR 141.8 141.1 0/45.3 )CRelatlOnshlp of chargmg flow to pressure differential between chargmg and RCS...................

1.... :---*---. ___. ___._.. ________________________________________________________ _

ruesday, November 10, 2009 Page 104 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination General Discussion No comment at this time RF A 10/09/09 QUESTION 42 c

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

INC system pressure is checked after initiation of emergency boration in FR-S.I to ensure that pressure is low enough to provide adequate boration flow to the NC system. IfNC system Ipressure is elevated, it would impede charging flow (and hence boration flow) to the NC system.

IThe higher level portion ofthis KA related to Loss of Rector Coolant Makeup could not be directly matched. The MNS Abnormal Procedure for associated with Loss of Reactor Coolant IMakeup (AP-12, Loss of Letdown, Charging, or Seal Injection) does not address checking NC system pressure to determine if an elevated NC system pressure is impeding charging flow to

[the system. The closest possible match was to relate the question to a potential for insufficient boration flow as a result of the differential pressure between the NY and NC systems when

[emergency boration is required.

L

~ _______

~ _____

Answer A Discussion

,,- --- ------- ----------------- ------ -----------------------------------------------------------------l

,[Incorrect. Plausible as there is Foldout criteria which has the operator check NC system pressure to determine if the NY pump recirc valves should be open.

________________________. _________________. ____________. ________________._. ___. _________________. ____. ______________________ -----1 Answer B Discussion

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

~------------- --------------------- -------------------------- ------ ----I

~correct. Plausible as this is below the lift setpoint for the Pressurizer safety valves.

I

~.

. ____________.-----1 Answer C Discussion r~O~£T~=__====_ _~=_=__~===_==_=_=_=========_=_=========-=-=========-====-==---===-=--=-=====~-_=__j Answer 0 Discussion r------*------ -- --.--------- --

---

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---

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---

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

---~---*--------l

~n~l'I'e~.~laus~I=_~~tl1is~~e~~t~e ~~e~~n~~~h~P~~~~\\T: ________ ~ ______________________________________ ~

- ----- T----------------

Job Level Cognitive Level

-- ---- ----i-~ --

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

RO I*

Memory

---

~- -.----

QuestionType T-- ------ ----QuestlonSource - --- -- -- --I 401-9 Comments RESPONSE

-SANK---1----------MNSBank EPFRSN07 - -- - - -----1 Considered SAT for submittal with no

.~ -

-- ---- ----------- ------------ --------- ---I comments. No changes.

c----- ----------- ----- -----

peV!loerne,!!Refere~e8 _____ _

IStudent References Provided

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

\\OP-MC-EP-FRS page 1-----------------

1 I L ____ ~ _____________________ _

L _________________________________ _

-- ---- -- -I.:---------T.-- -------- -- - -1 1------ ---- ---

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

---

~ -

---

~---- -

luestionBank # iKA_system IKA_number I IKA_desc

~=_-~~~}8~22~~~-_-_~J~~0~ _------ -J [Kn~kdg~~th~o~e~~nali~pLi;;ati~~s~fth~ f;;Iiowi;g~~c~t~s.they~pplyt;L~S~ofR~~cto~ C--;;~lantMake~p:(CFR 141.8 141.1 0/45.3 )CRelatlOnshlp of chargmg flow to pressure differential between chargmg and RCS...................

1----:---*---. ___. ___._._. ________________________________________________________ _

ruesday, November 10, 2009 Page 104 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 42 c

fuesday, November 10,2009 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 42 c

rucsday, NO\\'ember 10, 2009

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 43 B

(QuestionBank # (KA system (KA number (KA desc I

1843 I

APE026 I

AA2.04 I Ability to detennine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.51 45.13)DThe nomlal values and upper limits for the temperatures of the components cooled by CCW.................................

CURRENT Given the following current conditions on Unit 1:

Unit is operating at 100% RTP A malfunction of the Letdown Hx Outlet temperature controller has caused 1KC-132 (Letdown Hx Cooling Water Control) valve to slowly drift closed Letdown Heat Exchanger Outlet temperature has increased from 106°F to 115°F Which ONE (1) of the following correctly completes the statement below?

Based on current conditions, NC system temperature will....l1.l-due to reactivity effects AND if Letdown Hx Outlet temperature continues to increase, 1NV-127A, LD Hx Outlet 3-Way Cntrl will divert to the VCT at ~.

A.

(1) decrease (2) 120°F B.

( 1) decrease (2) 138°F C.

(1) increase (2) 120°F D.

(1) increase (2) 138°F APE026AA2.04 45 DAY VERSION Given the following current conditions on Unit 1:

Unit is operating at 100% RTP A malfunction of the Letd own Hx 0 utlet temperatu re controller h as caused 1 KC-132 (Letdown Hx Cooling Water Control) valve to slowly drift closed Letdown Heat Exchanger Outlet temperature has increased from 106°F to 115°F Based on current conditions, NC system temperature will -.dL AND if Letdown Hx Outlet temperature continues to increase, 1NV-127A, LD Hx Outlet 3-Way Cntrl will divert to the VCT at~.

Which ONE (1) of the following correctly completes the statement above?

A.

(1) decrease (2) 120°F B.

(1) decrease (2) 138°F C.

(1) increase (2) 120°F D.

(1) increase (2) 138°F 401*9 Comments; I think 1200F is NOT plausible because it is too low. Consider using a higher temperature. At what temp does the resin bum? Something higher than 138 would also be acceptable.

RF A 10/28/09 Thursday, November 12,2009 Page 106 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 43 B

!QuestionBank #!KA system

!KA number I KA desc I

1843 I

APE026 I

AA2.04 I Ability to detennine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.51 45.13)DThe nomlal values and upper limits for the temperatures of the components cooled by CCW.................................

CURRENT Given the following current conditions on Unit 1:

Unit is operating at 100% RTP A malfunction of the Letdown Hx Outlet temperature controller has caused 1KC-132 (Letdown Hx Cooling Water Control) valve to slowly drift closed Letdown Heat Exchanger Outlet temperature has increased from 106°F to 115°F Which ONE (1) of the following correctly completes the statement below?

Based on current conditions, NC system temperature will....l1.l-due to reactivity effects AND if Letdown Hx Outlet temperature continues to increase, 1NV-127A, LD Hx Outlet 3-Way Cntrl will divert to the VCT at ~.

A.

(1) decrease (2) 120°F B.

( 1) decrease (2) 138°F C.

(1) increase (2) 120°F D.

(1) increase (2) 138°F APE026AA2.04 45 DAY VERSION Given the following current conditions on Unit 1:

Unit is operating at 100% RTP A malfunction of the Letd own Hx 0 utlet temperatu re controller h as caused 1 KC-132 (Letdown Hx Cooling Water Control) valve to slowly drift closed Letdown Heat Exchanger Outlet temperature has increased from 106°F to 115°F Based on current conditions, NC system temperature will -.dL AND if Letdown Hx Outlet temperature continues to increase, 1NV-127A, LD Hx Outlet 3-Way Cntrl will divert to the VCT at~.

Which ONE (1) of the following correctly completes the statement above?

A.

(1) decrease (2) 120°F B.

(1) decrease (2) 138°F C.

(1) increase (2) 120°F D.

(1) increase (2) 138°F 401*9 Comments; I think 1200F is NOT plausible because it is too low. Consider using a higher temperature. At what temp does the resin bum? Something higher than 138 would also be acceptable.

RF A 10/28/09 Thursday, November 12,2009 Page 106 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 43 General Discussion The increase in Letdown Heat Exchanger Outlet temperature causes an increase in mixed bed demineralizer resin temperature. This temperature increase results in thennal regeneration of the resin and the release of boron from the demineralizer resin to the letdown. This results in an increase in the boron concentration of the charging water going back to the NC system which causes NC system temperature to decrease. If Letdown temperature increases to I38°F, letdown will divert to the VCT to protect the demineralizer resin from damage.

This KA is matched because the applicant must determine the effect that increase in letdown line temperature will have on NC system temperature and the upper limit for letdown temperature before NV-I27A diverts.

This is a comprehension level question because the applicant must process and evaluate multiple pieces of information to determine the correct answer. First, the applicant must detennine the increase in letdown temperature will result in a release of boron from the demineralizers and then determine that the increase in boron concentration in the NV charging will result in a temperature decrease. The applicant must then recall from memory the temperature setpoint for the diversion ofletdown flow.

Answer A Discussion IIncorrect. NC system temperature decreasing is correct. The temperature of 120°F is plausible because that is the setpoint for the Letdown Hx Oulet Hi Temperature Annunciator.

Answer B Discussion ICORRECT.

__________________________________ J Answer C Discussion Incorrect. Plausible if the applicant does not recall the effect ofletdown line temperature on the atlinity of de mineralizer resin for boron. 120°F is plausible because it is the setpoint for the Letdown Hx Outlet Temperature Hi Annunciator.

Answer D Discussion Incorrect. Plausible if the applicant does not recall the effect of letdown line temperature on the atlinity of demineralizer resin for boron. The temperature setpoint is correct.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestionBank # IKA_system Development References J IStudent References Provided Annunciator Response Procedure for Panel I AD-7 / H2 I BNT-CH05R3, Ion Exchange Objective 23 page 23 I

l____!~

___________ ~

KA number KA desc 401-9 Comments RESPONSE Disagree with Lead on this one, facility feels that 120 deg has ample plausibility, plan to discuss further when during on site review.

I 843iAPE026 AA2.04 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 /

L-__________ ____

~

45.13)1 ; The normal values and upper limits for the temperatures of the components cooled by CCW................................

Thursday, November 12,2009 Page 107 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 43 General Discussion The increase in Letdown Heat Exchanger Outlet temperature causes an increase in mixed bed demineralizer resin temperature. This temperature increase results in thennal regeneration of the resin and the release of boron from the demineralizer resin to the letdown. This results in an increase in the boron concentration of the charging water going back to the NC system which causes NC system temperature to decrease. If Letdown temperature increases to I38°F, letdown will divert to the VCT to protect the demineralizer resin from damage.

This KA is matched because the applicant must determine the effect that increase in letdown line temperature will have on NC system temperature and the upper limit for letdown temperature before NV-I27A diverts.

This is a comprehension level question because the applicant must process and evaluate multiple pieces of information to determine the correct answer. First, the applicant must detennine the increase in letdown temperature will result in a release of boron from the demineralizers and then determine that the increase in boron concentration in the NV charging will result in a temperature decrease. The applicant must then recall from memory the temperature setpoint for the diversion ofletdown flow.

Answer A Discussion IIncorrect. NC system temperature decreasing is correct. The temperature of 120°F is plausible because that is the setpoint for the Letdown Hx Oulet Hi Temperature Annunciator.

Answer B Discussion ICORRECT.

Answer C Discussion Incorrect. Plausible if the applicant does not recall the effect ofletdown line temperature on the atlinity of de mineralizer resin for boron. 120°F is plausible because it is the setpoint for the Letdown Hx Outlet Temperature Hi Annunciator.

Answer D Discussion Incorrect. Plausible if the applicant does not recall the effect of letdown line temperature on the atlinity of demineralizer resin for boron. The temperature setpoint is correct.

Job Level Cognitive Level Question Source RO Comprehension QuestionType I 401-9 Comments RESPONSE Disagree with Lead on this one, facility feels that 120 deg has ample plausibility,

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestionBank # KA system r-------------------, plan to discuss further when during on site Development References J Student References Provided review.

Annunciator Response Procedure for Panel I AD-7 / H2 I BNT-CH05R3, Ion Exchange Objective 23 page 23 I

l____

KA number KA desc AA2.04 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 /

I 843 1APE026

~_____

L-________

~

45.13)1 ; The normal values and upper limits for the temperatures of the components cooled by CCW.................................

Thursday, November 12,2009 Page 107 of 186

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 43 DISTRIBUTE B

fuesday, November 10, 2009 Page 108 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 43 DISTRIBUTE B

fuesday, November 10, 2009 Page 108 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 44 A

!QuestionBank # IKA system IKA number I KA desc I

1844 i APE027 I AK3.04 I Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.5,41.12 05~ 05J3lD~]'. ij'P~R~v~ i~ost and then restored, that pressure recovers much more slowly................................

CURRENT 45 DAY VERSION Given the following events and conditions on Unit 1:

Given the following events and conditions on Unit 1:

• A Reactor Trip and SI have occurred due to a faulted S/G

• The affected S/G has now been isolated per E-2 (Faulted S/G Isolation)

• The transient resulted in PZR level indicating off scale low for a period of time but is now 70% and stable

• Safety injection has been terminated and normal letdown and charging have been restored.

• The Pressurizer Pressure Master has been placed in MANUAL with a 50%

output and all backup heaters have just been energized.

• NC system pressure is 2000 PSIG and increasing.

Which ONE (1) of the following describes the resulting behavior of PZR pressure AND the automatic action that will occur to protect the NC system if an overpressure condition develops?

A B.

C.

D.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORV 1NC-34 will open at 2335 PSIG.

• A Reactor Trip and SI has occurred due to a stuck open PZR Safety valve

• The affected Safety valve has now reseated and is no longer leaking

• The transient resulted in PZR level indicating off scale low for a period of time but is now 70% and stable

• Safety injection has been terminated and normal letdown and charging have been restored.

• The Pressurizer Pressure Master has been placed in MANUAL with a 50%

output and all backup heaters have just been energized.

• NC system pressure is 2000 PSIG and increasing.

Which ONE (1) of the following describes the resulting behavior of PZR pressure AND the automatic action that will occur to protect the NC system if an overpressure condition develops?

A B.

C.

D.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

401-9 Comments:

Thursday, November 12,2009 APE027AK3.04 Stem: 1st bullet: Change "has" to "have".

Psychometrics: As written, B is also a correct answer.

Additionally, IfC was correct, so would D.

This Q is U because of multiple correct answers.

Page 109 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 44 A

\\QuestionBank # \\KA system \\KA number J KA desc I

1844 I

APE027 I AK3.04 J Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.5,41.10 / 45.6 / 45.l3)DWhy, ifPZR level is lost and then restored, that pressure recovers much more slowly................................

CURRENT 45 DAY VERSION Given the following events and conditions on Unit 1:

Given the following events and conditions on Unit 1:

• A Reactor Trip and SI have occurred due to a faulted S/G

• The affected S/G has now been isolated per E-2 (Faulted S/G Isolation)

• The transient resulted in PZR level indicating off scale low for a period of time but is now 70% and stable

• Safety injection has been terminated and normal letdown and charging have been restored.

• The Pressurizer Pressure Master has been placed in MANUAL with a 50%

output and all backup heaters have just been energized.

• NC system pressure is 2000 PSIG and increasing.

Which ONE (1) of the following describes the resulting behavior of PZR pressure AND the automatic action that will occur to protect the NC system if an overpressure condition develops?

A B.

C.

D.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORV 1NC-34 will open at 2335 PSIG.

• A Reactor Trip and SI has occurred due to a stuck open PZR Safety valve

• The affected Safety valve has now reseated and is no longer leaking

• The transient resulted in PZR level indicating off scale low for a period of time but is now 70% and stable

• Safety injection has been terminated and normal letdown and charging have been restored.

• The Pressurizer Pressure Master has been placed in MANUAL with a 50%

output and all backup heaters have just been energized.

• NC system pressure is 2000 PSIG and increasing.

Which ONE (1) of the following describes the resulting behavior of PZR pressure AND the automatic action that will occur to protect the NC system if an overpressure condition develops?

A B.

C.

D.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover slowly because the water in the PZR is subcooled:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORVs 1 NC-32 & 36 will open at 2335 PSIG.

PZR pressure will recover rapidly because of the elevated level and smaller steam space volume:

Pressurizer PORV 1 NC-34 will open at 2335 PSIG.

401-9 Comments:

Thursday, November 12,2009 APE027AK3.04 Stem: 1st bullet: Change "has" to "have".

Psychometrics: As written, B is also a correct answer.

Additionally, IfC was correct, so would D.

This Q is U because of multiple correct answers.

Page 109 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 44 RFA 10/28/09 General Discussion The first part of the question applies anytime the PZR is emptied and subsequently refills. This results in subcooled liquid in the majority ofthe PZR liquid space which has to be heated to saturated temperature before normal pressure response is recovered. There is no specific objective that covers this phenomena but in all the EP steps which the plant is recovering from a loss of inventory such as step 17 ofES 1.1 (SI Termination), the basis references restoring the PZR to saturated conditions. In the scenario given in the question, pressure response from backup heater operation would be extremely slow. Second part of the question concerns the effect of placing he pressure master in manual at a 50% output. As long as it remains in manual, the output would be unaffected by actual NC system pressure therefore the components controlled by this instrument would be unaffected as well. One of the PZR PORVs, INC-34A is controlled strictly by the output of the pressure master (Opens at 81.2%), the other two (NC 32 &36) are controlled by the second selected pressure channel and would function independent ofthe pressure master output.

KIA is matched because the candidate must understand how a scenario involving a loss and subsequent recovery ofPZR level would affect pressure control. Additionally he must evaluate the effect of an off normal alignment of the pressure control system.

Analysis level because the candidate must evaluate a given scenario and predict an outcome based on selected switch positions and evaluation ofa transient associated with PZR level.

Answer A Discussion r.~~-

~~--

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

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

-~--~-----~-~-~-~--~----~-----------------l ICorrect: See explanation above Answer B Discussion Plausible: First answer is correct, Second answer is plausible because if the PZR pressure master is selected to auto, INC-34 would open before the other two due to the build in of the integral function of the controller.

Answer C Discussion Plausible: if the candidate believes that the elevated PZR level would have a significant impact to pressure control, this condition would have a very limited effect but in the scenario given it would be insignificant. 2nd part is correct.

Answer D Discussion Plausible: Fist part is plausible as explained above, second.

Second answer is plausible because if the PZR pressure master is selected to auto, INC-34 would open before the other two due

,to the build in of the integral function of the controller

~--=----+-

Cognitive Level QuestionType Question Source

=J Comprehension NEW I

~ Developed IDevelopment References

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestionBank # IKA_system Technical Reference(s): OP-MC-PS-IPE Rev 28 Page 21 Learning Objective: OP-MC-PS-IPE, Obj 4 & 9 KA_number KA desc

~udent References Provided 401-9 Comments RESPONSE Per Chief Examiner's comment change 'has' to 'have' in stem of question. Answers B and D cannot be correct because with the Pressurizer Pressure Master in MANUAL at 50%, 1 NC-34 will never open regardless ofNC system pressure. HCF 11I03/09 1 844iAPE027

~_ L_

AK3.04 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR Thursday, November 12,2009 Page 110 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 44 RFA 10/28/09 General Discussion The first part of the question applies anytime the PZR is emptied and subsequently refills. This results in subcooled liquid in the majority ofthe PZR liquid space which has to be heated to saturated temperature before normal pressure response is recovered. There is no specific objective that covers this phenomena but in all the EP steps which the plant is recovering from a loss of inventory such as step 17 ofES 1.1 (SI Termination), the basis references restoring the PZR to saturated conditions. In the scenario given in the question, pressure response from backup heater operation would be extremely slow. Second part of the question concerns the effect of placing he pressure master in manual at a 50% output. As long as it remains in manual, the output would be unaffected by actual NC system pressure therefore the components controlled by this instrument would be unaffected as well. One of the PZR PORVs, INC-34A is controlled strictly by the output of the pressure master (Opens at 81.2%), the other two (NC 32 &36) are controlled by the second selected pressure channel and would function independent ofthe pressure master output.

KIA is matched because the candidate must understand how a scenario involving a loss and subsequent recovery ofPZR level would affect pressure control. Additionally he must evaluate the effect of an off normal alignment of the pressure control system.

Analysis level because the candidate must evaluate a given scenario and predict an outcome based on selected switch positions and evaluation ofa transient associated with PZR level.

Answer A Discussion (C;rr~~t~S~~xPl~~;t;;';~b~-v~- ~~~~----- -~

-~-~~

-~~ -~~-~--

-~~~~~-~----~~~~-~~--~~~~-~~---~J Answer B Discussion Plausible: First answer is correct, Second answer is plausible because if the PZR pressure master is selected to auto, INC-34 would open before the other two due to the build in of the integral function of the controller.

Answer C Discussion Plausible: if the candidate believes that the elevated PZR level would have a significant impact to pressure control, this condition would have a very limited effect but in the scenario given it would be insignificant. 2nd part is correct.

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

Answer D Discussion Plausible: Fist part is plausible as explained above, second.

Second answer is plausible because if the PZR pressure master is selected to auto, INC-34 would open before the other two due to the build in of the integral function of the controller Cognitive Level QuestionType Question Source

--l

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

Comprehension NEW 401-9 Comments RESPONSE Per Chief Examiner's comment change 'has' to 'have' in stem of question. Answers B and D cannot be correct because with the f-[S1_t_u_d_e_n_t_R_e_f_e_r_e_n_c_e_s_P~ro_v_i_d_e_d ______ ---J Pressurizer Pressure Master in MANUAL

~ Developed Development References

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestionBank # IKA_system 1 844iAPE027

. ____ L ____ _

Thursday, November 12,2009 Technical Reference(s): OP-MC-PS-IPE Rev 28 Page 21 Learning Objective: OP-MC-PS-IPE, Obj 4 & 9 KA desc at 50%, 1 NC-34 will never open regardless ofNC system pressure. HCF 11I03/09 AK3.04 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR Page 110 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 44 A

41.5,41.10/45.6/ 45.13)C]Why, ifPZR level is lost and then restored, that pressure recovers much more slowly

~-

--~-~ -

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

Thursday, November 12,2009 Page 111 of186 2009 RO NRC Retake Examination QUESTION 44 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 41.5,41.10/45.6/ 45.13)C]Why, ifPZR level is lost and then restored, that pressure recovers much more slowly Thursday, November 12,2009 Page 111 ofl86

FOR REVIEW ONLY - DO NO'T DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 45 C

~--- ------ --------- -----,--~----.~--~

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

~~~:~an~!r~.&.i!:~~--r-"--uf!1ir2-~~ ll~:E~8~ENERicDKn~Wkdge -;;-i syste~set Po"i~ts:T~krl-;;-~ks and---;;:utomatic act~ns associated with-EOP~ntry~onditions. (CFR:

--~---~~-- ------"---~---- -~------" ~!Ji~:Zii5~L~ ___ ~~ __ ~ ___ ~~_~_ ~_~~ __ ~ __ ~~ _______ ~_~~~

CURRENT 45 DAY VERSION Which ONE (1) of the following lists the indications which are checked in E-G, (Reactor Trip or Safety Injection) prior to implementing monitoring of Critical Safety Function Status Trees to determine if entry into FR-S.1, Response to Nudear Generation I ATWS is required?

A B.

C.

D.

1. I/R Amps - GOING DOWN

2. All Rod Bottom Lights - LIT

3. Reactor Trip and Bypass Breakers - OPEN

4. IIR SUR - ZERO OR NEGATIVE

5. All Power Channels - LESS THAN 5%

2,3, and 5 ONLY 3,4, and 5 ONLY 1,2, and 3 ONLY 2,3,and40NLY EPE029G2.4.2 No comment at this time RF A 10/28/09 fuesday, November 10, 2009 Which ONE (1) of the following lists the indications which are checked in E-G, (Reactor Trip or Safety Injection) prior to implementing monitoring of Critical Safety Function Status Trees to determine if entry into FR-S.1, Response to Nudear Generation I ATWS is required?

1. IIR Amps - GOING DOWN

2. All Rod Bottom Lights - LIT

3. Reactor Trip and Bypass Breakers - OPEN

4. IIR SUR - ZERO OR NEGATIVE

5. All Power Channels - LESS THAN 5%

A 2, 3, and 5 ONLY B.

3,4, and 5 ONLY C.

1,2, and 3 ONLY D.

2, 3, and 4 ONLY 401-9 Comments:

Page 112 of185 c

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 45

~--- -

---

I-----------,---------~--------~-I----------

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

---

~-------------~-------l IQuestionBank # jKA_system J'5A_number J IKA_desc r ~~ 1845 ~~--I ~-EPE029-~1 ~~-~ iA2-~- IIIEPE029-GENERicDKn~wkdge ~f syste;-set P;i~ts:T~;rl~~ks and-;utomatic act~ns associated with~EOP--;;ntry~onditions_:(CFR:1 l~._~._~~~~~~ -~~--'-~--~--- __.. ~.-.J 41.7/45.7/45.8) i

[.-~-.-.-.~.----.. ~---.~ ---.-.~.-.~-.-~ --~~~ -.--.- --~.--- -

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CURRENT 45 DAY VERSION Which ONE (1) of the following lists the indications which are checked in E-G, (Reactor Trip or Safety Injection) prior to implementing monitoring of Critical Safety Function Status Trees to determine if entry into FR-S.1, Response to Nudear Generation I ATWS is required?

1.

2.

3.

4.

5.

A B.

C.

D.

I/R Amps - GOING DOWN All Rod Bottom Lights - LIT Reactor Trip and Bypass Breakers - OPEN IIR SUR - ZERO OR NEGATIVE All Power Channels - LESS THAN 5%

2,3, and 5 ONLY 3,4, and 5 ONLY 1,2, and 3 ONLY 2,3,and40NLY EPE029G2.4.2 No comment at this time RF A 10/28/09 fuesday, November 10, 2009 Which ONE (1) of the following lists the indications which are checked in E-G, (Reactor Trip or Safety Injection) prior to implementing monitoring of Critical Safety Function Status Trees to determine if entry into FR-S.1, Response to Nudear Generation I ATWS is required?

1. IIR Amps - GOING DOWN

2. All Rod Bottom Lights - LIT

3. Reactor Trip and Bypass Breakers - OPEN

4. IIR SUR - ZERO OR NEGATIVE

5. All Power Channels - LESS THAN 5%

A.

2, 3, and 5 ONLY B.

3,4, and 5 ONLY C.

1,2, and 3 ONLY D.

2, 3, and 4 ONLY 401-9 Comments:

Page 112 of185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination General Discussion IIm~~diat~~ctions from E.:o.--- - - - -.--- ---

I

[When checking the Reactor Tripped:

[I) All Rod Bottom lights - LIT

12) Reactor Trip and Bypass Breakers - Open QUESTION 45

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

c

13) IR AMPs - Going Down I

I I!'hi" JSAJs~~che~b~a~t:...t~'luesti<.ln~.<J.uire~t~_ap£!ican.!.to know wha,t, i~~ations (i.e~ntry c()l1ciitioEs f()l" E-e>,Lare ch~k~d as.£ilI!0f the ~cii.ate action~ for E-o.:, _______ J Answer A Discussion

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

-~-- ------

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

lI~c~rr~t~P~u~b~~:cau~e~ ~~re co~ct ~d!'.o~~~nge~~nnel~less~h~n~~i:!~ent~ ~n~tion for FR-S.l.

Answer B Discussion

---

~---

IInco-;:;.~ct.Plausibkbecaus~3is~~rrect~4is ;s~~c~t~ -;ith IRTndicatio~ ;hi;;his~h~ck;;d( ~c~Pt~~o -;;r~~gativ~ an~ntry conditi~ fu~-FR~S~)~~ndPowe;:Rang;;Chan~-;;i~~s ili;-

l5~i~ a_~~h}'_~nditi(Jn!()I"~-:§*L _______ _

Answer C Discussion ICORRECT. ----- -----

1 _____

~ ________._~ ____ _

Answer 0 Discussion C~Jln'!!v!,=-eve-,-_-+_qu~tIO.!1TJ'P~

Question Source

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory I

NEW fQ.eve~ime~Refere~es -===-=-= -===-

~t~den!Reference~~o~~!i __ _

IE-O, Reactor Trip or Safety Injection page 3 1

I I

1 1

1 f

1 ___. ____. ___

,L _____. __.. __. ____

401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

- ------fj---------

-.- -l ~.-

-.----------.-.----.----~- -----.-------------.. ----.. -----.-.---,

luestlonBank # KA_system IKA_number IKA_desc J

~ - -184~E029 - - -£.4.2- ----- -- -1 fPE029 GENERICDino-;l~d~ -;;-f syste~ ~t point~ i~erlo~k-;-~d-aut~matic ;;tion-;-asso-Zi;ed~ith-EOP~~try

~;-nditi~n;:- I

~g;~ i,1.7/ 4~.7_~~.8) __________________________________________ _

ruesday, November 10,2009 Page 113 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 45 General Discussion IIm~~diat~~ctions fromE.:o.--- ----.--- ----~--- ----.--- --------------.~------ -------------l I

II

[When checking the Reactor Tripped:

[I) All Rod Bottom lights - LIT I

12) Reactor Trip and Bypass Breakers - Open

13) IR AMPs - Going Down I

I!'hi" }~AJs~~che<!.b~a~t:..t~'luesti<.ln~.<J.uire~_t~_ap£!ican.!.to know wha,t, i~~ations (i.e~ntry c()l1ciitioEs f()l' E-C>.Lare ch~k~d as.£ilrt..0f the ~cii.ate action,s" for E-o.:, _______ ~

Answer A Discussion

-.----.-.----.-.----.- -.--.----. ---.-. --- ---.-.. -------.-- --- ----.-.--.---.-- --.- -.--- ---'-- --'-'---'--'--l lI~c~rr~t~P~u~b~~:cau~e~~..!rec0n-:ct~d!'.o~~~nge~~nne1~less.!h~n~~i:!l1...ent~~n~t~~~FR-S._~ ________________.. __________

1 Answer B Discussion IInco-;:;'~ct.Plausibkbecaus~3is~~rrect~4is ;s~~c~t~ -;ith IRTndicatio~ ;hi;;his~h~ck;;d(~c~pt~~o -;;r~~gativ~ an~ntry conditi~fu~-Fi{~S~)~-~ndPowe;:Rang;;Chan~-;;i~~s ili;-I l5~i.s..a.r~..e.'1ch}'_~nditi<Jn!()I'~-:§*L ___________. _________________________________________________ J Answer C Discussion 1-----*--.. -*-*- -._--.- -------.--.. - ----.- -.----.-.- --.--.. --.-.-.... -------.-.-.. -.. ---.---.. -.--.---'--'---'- -'-"-'--'-'--'l

,CORRECT.

1. ___. ______._. ___. __._. ____._. ___.. ___. _____

. __ ~

. ___. __._._1 Answer 0 Discussion r---- --

---

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

---

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

IInco~ct._P~~i~e since~ <IIl~3_ar:.~rrec~a~d4~s~~c~t~~i~ ~~~c~~n~hic~~cll:c~e~(ex'=~zerl1...0r negativ.:.!.s...~e~try c()i1~tion for FR-~.lL _ _____ _

Job Level

- -cognltiveLe-e'-'-QestlonT pe-I ----- - -----ci -tl-S--- - - --------1 401-9 Comments RESPONSE

_________..... __ -+_...u ___ '1_ ~ ____________ _ ues ~'!.._o~rce ~ __________ I' RO Memory 1

NEW 1

Considered SAT for submittal with no

- ------.-- -- --'-.-.---.-------'-- - ----.--.-- -.-----.-.--.- --. '---'-- _J comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 1'- -

.~- - --- -.--

Q.eve~.e.meF!! Refere~es ________ _

iE-O, Reactor Trip or Safety Injection page 3 1

1 1

1_._. __ --. ___._ '_." ___. __ "_. __._.,, __,,

I~t~den! Reference~ ~ovi.<!!.<! __ _

I I

I I L ___________________

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

______ ~8~E:P_~02.9 ___ £:.~.~ __.__. ___ 1 I~~i~~: IG7E~~~I; ~5~~Owledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

1Ic ___. __. __.. __. __. __. ____. ____._. ___. __.. _._._. __.. __.. __. ____. ____._,, ___. __ _

ruesday, November 10,2009 Page 113 of 185

D FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 46 1- -

-~- ----r-----To:- ----- -----1,.::------- -

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

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

i9U~8t1~:~ank! :KAE7iJ~~t~-E~~~~r 10--l ~Cli~e:~-p~~~te;nd~~~it~7 the foll-;;;tng;; th-ey~pply to-aSGTR: (CFR 4I~- 1 4~5/45.6) D C~trol ro~7adi~tion monitoring

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

~dic~o~1lI1~I~s __________________________________________________________ ~

CURRENT Unit 1 is operating at 100% RTP. Given the following conditions:

1 EMF-33 (Condenser Air Ejector Exhaust) alarms in Trip 2 Given the conditions above, which ONE (1) of the following should be used to confirm that a primary~to-secondary leak exists per NSD-513 (Primary-to-Secondary Leak MonitOring Program)?

A S/G feed flow to steam flow mismatch B.

1EMF-24, 25, 26 and 27 (STEAMLINE HI RAD-Doghouse)

C.

1EMF-34 (S/G SAMPLE)

D.

1EMF-71, 72, 73, and 74 (STEAMLINE N-16 LEAKAGE)

EPE038EALIO 45 DAY VERSION Unit 1 is operating at 100% RTP. Given the following conditions:

1 EMF-33 (Condenser Air Ejector Exhaust) alarms in Trip 2 Which ONE (1) of the following provides the best indication per NSD-513 (Primary-to-Secondary Leak Monitoring Program) that a S/G tube leak has occurred?

A S/G feed flow to steam flow mismatch B.

1 EMF-24, 25, 26 and 27 (STEAMLINE HI RAD-Doghouse)

C.

1 EMF-34 (S/G SAMPLE)

D.

1 EMF-71, 72, 73, and 74 (STEAMLINE N-16 LEAKAGE) 401-9 Comments:

This Q is confusing. NSD-513 states that the best method is EMF-33 and the secondary method is the N-I6 monitor. The Q stem asks what the best indication is to determine that a SG tube leak has occurred. The stem seems to contradict the ref material slightly by the way it is worded.

Facility please re-evaluate.

RFA 10/28/09 ruesday, November 10, 2009 Page 114 ofl85 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 46 Unit 1 is operating at 100% RTP. Given the following conditions:

1 EMF-33 (Condenser Air Ejector Exhaust) alarms in Trip 2 Given the conditions above, which ONE (1) of the following should be used to confirm that a primary-to-secondary leak exists per NSD-513 (Primary-to-Secondary Leak MonitOring Program)?

A.

S/G feed flow to steam flow mismatch B.

1EMF-24, 25, 26 and 27 (STEAMLINE HI RAD-Doghouse)

C.

1EMF-34 (S/G SAMPLE)

D.

1EMF-71, 72, 73, and 74 (STEAMLINE N-16 LEAKAGE)

EPE038EAl.l0 Unit 1 is operating at 100% RTP. Given the following conditions:

1 EMF-33 (Condenser Air Ejector Exhaust) alarms in Trip 2 Which ONE (1) of the following provides the best indication per NSD-513 (Primary-to-Secondary Leak Monitoring Program) that a S/G tube leak has occurred?

A.

S/G feed flow to steam flow mismatch B.

1 EMF-24, 25, 26 and 27 (STEAMLINE HI RAD-Doghouse)

C.

1 EMF-34 (S/G SAMPLE)

D.

1 EMF-71, 72, 73, and 74 (STEAMLINE N-16 LEAKAGE) 401-9 Comments:

This Q is confusing. NSD-513 states that the best method is EMF-33 and the secondary method is the N-16 monitor. The Q stem asks what the best indication is to determine that a SG tube leak has occurred. The stem seems to contradict the ref material slightly by the way it is worded.

Facility please re-evaluate.

RFA 10/28/09 ruesday, November 10, 2009 Page 114 ofl85

FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 46 General Discussion IIIn accordance with NSD-513, the primary method for detecting primary-to-secondary leakage while on line is the condenser off-gas (EMF -33) radiation monitor. The secondary method for detecting tube leakage on line is the N-16 (EMF-71, 72, 73, & 74) radiation monitors.

I iThiS KA is matched because the applicant must know which methods (radiation monitors) are valid or accurate indications of S/G tube leakage under various plant conditions. The "operate" Ipart of'~i~KA ~~o~aEPlic~blt:~~S a~ther~J~_ll()thing t()_()pe~a~~ate(lt~t~ radiati0~~~tor~~o~a~~with_c1ete~ti()!l of SG~~~Jeak~~ __ ~ ___ ~ _ ~~~_~ ______ _

Answer A Discussion

[Incorrect. Not sensitiv~;nough ~~dct~ct k~,;ge~ithTs;;;~nTtude:P~~ibleb~~~s~~~~ be ~s;d todetect;SGTR~- -~~

~ -~~~~~

l ____. __. ________. __. ________. _________________________. _____________ _

Answer B Discussion c--

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

-~---~~~-~

~--~~--

---~-

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

---

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

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

IIncorrect. Can be used. However, it is not the best indication for detecting tube leakage as they are not as sensitive as the N-16 monitors. Plausible because they would be the most accurate

~e.ri.f~aE()~ !J..ftlI~ It:llka~jfQ1eu~it.....WllS..s...~.cI.Cl...~_~ __ ~ __ ~~ _~ __ ~~~_ ~ __ ~_~~ ~_~~~~~~~ __ ~ __ ~~_~_~~ __ ~ ___ _

Answer C Discussion

[in~o;~t:-SG ~~ph: iin~i;-oJ;t;s -;n~;EMF-33 t~;P2. Pla~silil~ bec-;-u~~it ;~~ld b-;;;-g~d~s~;;.ifthe_;;rt~~~tic-;ctions did not occur.

~~~

~-~-~I L ____________. ____. ______________________________

~ ___________________________. ____________ _

Answer 0 Discussion rcORRECT.-~ ~~--

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________ ~

___ ~

______ ~~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IDev8toPment References ~- ~~~~-- ~

[Student Referenc"~Provlded r:;:--- ~~----~----~--~~~~~-----~-~----

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

~---

INSD-5 13, Primary-to-Secondary Leakage Monitoring f

t rogram I

I I

I I I L ________ ~~_~~ ___ ~_ ~~~~_~J L~~~

~~~~- -- -

r----~---

--~-I~---~-----

~

~~I I

~-~- --~~~ __ ~~I 401*9 Comments RESPONSE Per Chief Examiner's comment, revised question to remove confusion from the stem. HCF 11104/09 QlJe~t!5>nB~"-k..#l<A_s~te'!l_ ~,....I",!mber ~~ __

18461EPE038 IEAUO

___ 1. ____ _

r.<~ji!8i=-_~~-_=--=---=-=-~~~~=-==--=-~~ ~-=---====-_--=~ ~~ ~~

rbility to operate and monitor the following as they apply to a SGTR: (CFR 41.7 145.51 45.6)[JControl room radiation

~0!lit~~I1~i~~~0I'tl~nc!ala~ _____ ~ __ ~_ _ ~ ____ ~_ ~~ __ ~~ __ ~ ___ ~~ ~~~_~~~

Tuesday, November 10, 2009 Page 115 of 185 FOR REVIEW ONLY - DO DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 46 General Discussion lifu acc~da~c~~ithNSD~5i3,-th~ pri~ary ;eth;-d fo~dctecti~g-I)fim~;;t~;c-;;-ndary~ak~~~hil~on line*~ the-;;-ond~n;r~ff-~(EMF-33)~diatio~;0~itor ~he-;-e;;;;J;Y ~ct~d-f~ ~1 detecting tube leakage on line is the N-16 (EMF-71, 72, 73, & 74) radiation monitors.

I I

iThiS KA is matched because the applicant must know which methods (radiation monitors) are valid or accurate indications of S/G tube leakage under various plant conditions. The "operate" I Ipart of't11.i~KA ~~o~aEP!.ic~blt:.t<>~S a~ther~)~!l()thing t()_~e~a!t:.~ate(lt()_t~ radiati0~~~tor~~0..0a~~with_(lete~ti()!l of SG.-!~~-'eak~~ ________ ~_~

________ ~~.J Answer A Discussion

[Incorrect. Not sensitive enough to detect leakage of this magnitude. Plausible because it can be used to detect a SGTR.

I l __________ ~. _______ ~~

_______________. ____________ ~ _________ ~

_____ ~

____ ~_~ ____________

~~~

~. ______ ~

___ ~

_______. ___ ~_.J Answer B Discussion c*-

---

~---

---

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

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

---

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

---

~---- -----,

IIncorrect. Can be used. However, it is not the best indication for detecting tube leakage as they are not as sensitive as the N-16 monitors. Plausible because they would be the most accurate

'I

~e.ri.f~aE()~!J..ftlI~lt:llka~jfQ1eu~it.....WllS..s...~i~~_~ _________________________ ~~~ _____________ ~~ _________ ~ ___ J Answer C Discussion r;-~~---------~--------------~-------~----------------~~---~-

--~----~--

-~-------

~ ---

.~~.

~~0~e~t.~<:T~!11p~~n0~1~~ ~

!~EM~3!t~i~~ P~ausil)I:.b~~s: ~~~l~b~~g~~ ~s~~ i.0~ ~uto~atic<lc~ions..<ii~not~ccur ___ =_ ___ ~~ __ =--=-_ -= _ =_~= ~ -=.=1 Answer 0 Discussion iCORRECT.---~~------------~---------

---

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

-~----~~------------~~----~-----"I l _____ ~

_________________________________________._._~ ______

. _________________________ ~ ___________________________

1 I-JObL;v;l-l~--6ognltive-LeveJ--1--Qu;stlonType-T-----~-----~Q-;ti--s---~~~~~----~-~1401.9CommentsRESPONSE

~ - -RO--i~~---Me;ory----i~--BANK~ -t ~~---~-----MN~B~~{~~04 --~-~-- --I Per Chief Examiner's comment, revised

-~------~--- ------ L __ ~_ ------ ~----- -~- --~----------~~~ ___________ ~_~..J question to remove confusion from the

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

I-Studen-t*R-e1e--re* nc~es-P-ro-vlde---~d -~~.---.[ stem. HCF 11104/09

~ Developed IDe--"f!!0p,!,!.n~ ~f!'!fl~!fl_~~_____ _____

rSD-5l3, Primary-to-Secondary Leakage Monitoring r--- ----~---- --------I

~ OPT Approved trogram

[

~ OPS Approved I

r I

I I I I

~ NRC Approved L ________ ~ _________ ~ __ ~ ___ J L~_~ __ ~ ____________ J

--~-- -- -,--.. ---- -*--1---------- ~

9lJe~t!5>nB~"_k...#l<A-s~te'!l- ~,...-",,!mber ___ _

l8461EPE038 IEAI.IO

___________ L ___________, ____________ _

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

--~-

~--~-~-----~----~-----~---l IKA_desc I

rbilitY-t~~pe~~t;; ~d m~cit-;;-rth~fui~wing aSth0 ;pplyt~__;SGTR~CFR 41.7i455!45.6)[JContr~r-;0-;7adia~~---1

~0!lit~~ll~i~~~0l'tl~nc!ala~...:****:-"*:,,,*~____

_ ________ ~ __ ~ ___________ ~ ___ ~_I Tuesday, November 10, 2009 Page 115 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 47 C

I,~--- --- --

-~~-~--

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

~----II------

-~--------

-~---- ----

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

-~-- -----

---

~-------

fue~~~:~~!, I~AA-:~1o'"-1KA-n~:~~o 1---1 ~~::~:e ~th~~~r~ion:ti imPiicatio;~fth;rollowi~~o~~~~ as they ~ply to St~m Lin~Ruphlfe: (CFR41.8/41.1O / ---

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

- -~---- -~-----1145.3)LJConsequences ofPTS.................. ~.......................,.

-~--,~-,-.-----.---------

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

CURRENT 45 DAY VERSION Unit 1 is responding to a Steam Break inside Containment from 100% RTP.

Given the following events and conditions:

Narrow Range S/G level is 15% for each intact S/G The NCPs were TRIPPED FR-P.1 (Response to Imminent Pressurized Thennal Shock Condition) has been implemented NCS temperature is now STABLE NCS pressure is STABLE Letdown has been RESTORED The crew has determined that a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is required. Which ONE (1) of the following evolutions could be perfonned by the crew in the next hour while continuing on through the EP procedures?

A.

Start 1D NCP B.

Energize Pressurizer Heaters C.

Place Auxiliary Spray in service D.

Increase CA flow to one intact S/G to raise NR level to 50%

APE040AKl.OI Unit 1 is responding to a Steam Break inside Containment from 100% RTP.

Given the following events and conditions:

Narrow Range S/G level is 15% for each intact S/G The NCPs were tripped FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) has been implemented NCS temperature is now stable NCS pressure is stable Letdown has been restored The crew has detennined that a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is required. Which ONE (1) of the following evolutions could be perfonned by the crew in the next hour while continuing on through the EP procedures?

A.

Start 10 NCP B.

Place Auxiliary Spray in service C.

Increase CA flow to one intact S/G to raise NR level to 50%

D.

Commence a 25-degreelhour cooldown to Mode 5 401-9 Comments:

Distracter D is NP. Replace D with a statement that would cause a CD without stating so. For example opening a valve or series in the primary or secondary that would cause a CD would be acceptable.

RF A 10/28/09 ruesday, November 10, 2009 Page 116 ofl85 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 47 CURRENT Unit 1 is responding to a Steam Break inside Containment from 100% RTP.

Given the following events and conditions:

Narrow Range S/G level is 15% for each intact S/G The NCPs were TRIPPED FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) has been implemented NCS temperature is now STABLE NCS pressure is STABLE Letdown has been RESTORED The crew has determined that a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is required. Which ONE (1) of the following evolutions could be performed by the crew in the next hour while continuing on through the EP procedures?

A.

Start 1D NCP B.

Energize Pressurizer Heaters C.

Place Auxiliary Spray in service D.

Increase CA flow to one intact S/G to raise NR level to 50%

APE040AKl.OI 45 DAY VERSION Unit 1 is responding to a Steam Break inside Containment from 100% RTP.

Given the following events and conditions:

Narrow Range S/G level is 15% for each intact S/G The NCPs were tripped FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) has been implemented NCS temperature is now stable NCS pressure is stable Letdown has been restored The crew has determined that a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is required. Which ONE (1) of the following evolutions could be performed by the crew in the next hour while continuing on through the EP procedures?

A.

Start 10 NCP B.

Place Auxiliary Spray in service C.

Increase CA flow to one intact S/G to raise NR level to 50%

D.

Commence a 25-degreelhour cooldown to Mode 5 401-9 Comments:

Distracter D is NP. Replace D with a statement that would cause a CD without stating so. For example opening a valve or series in the primary or secondary that would cause a CD would be acceptable.

RF A 10/28/09 ruesday, November 10, 2009 Page 116 ofl85

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 47 General Discussion r-------- ------------ -----.-.-- -.-.------ ------ ----------.. --.--- ----.----- --.------ - - -------------.-------.------'-,

IDuring the NC system soak, evolutions may be performed from other procedures which do not increase NC system pressure or decrease NC system temperature iKiA is matched because the candidate is presented with a steam line rupture scenario and must understand what components can be manipulated during the soak (operational Implications)

[which will not violate the requirement to not increase pressure or decrease temperature. These limitations are part of the consequences of the PTS conditions which exist as a result of the lrupture.

I I,

~na~~sJe~elJ>t~caus~tl1_e ~(l11d~~e!'lust..'ln~I~~~h !lnswer ~nd ~eteElli~~e~ff(:~<:>fll1anip-'.ll~t~~... !h_~t~omponen~~N~3~e~ ~mperattJr~ll~d-.pl!ssur!- _ _ _ ________ J Answer A Discussion IPla~ihl~-b~c~~~ ea;lie;:-i;PR-P. ~ifSIt~r~~~ti~n

~riteria is~ot

~t,-a~ NC p~pi; sta:rt~dt~~ixin~~i;gSI-w~~with NC-;Ystem ;-at;;r to~i;eth;;-temPerat~e~f t~;-at;;r entering Ithe reactor vessel down comer L

~

~ ____

~ ____. _________ _

Answer B Discussion

[-.------.-.----'-- - ----- -------.--- ----.--.---.--------.-----.-.. ---.-----.-------------------~-.--------- ----------l IIncorrect. Plausible because FR-P.I directs controlling pressure using heaters and spray in a step prior to initiating a soak. With NCS pressure stable, energizing heaters alone would increase lP~~u!.<:~i()laEn~ the.<iir~CY()l1 t~_n_o~il1..c~ase £f~s11r~ ___ _ ______ ____ ___ ____ __ ____ ___ _ ___ __ _ ___ ____ __ ___ _____ J Answer C Discussion ICORRECT~s;;-e~~lanati~ ~~v~- -- ------

-.-~-

---

~------------ -------- --------1 L ___________________ _

1 Answer 0 Discussion

~~OIT:ct~P~~i~e if the candidate bel~~es..!h_~t ~ai~i~g ~CJ..I~v:I to il..~o~aI_I:~~~ ap{)l'o~r~t~llI1d~~s....n()t~~ider..!h~c~eq~~~~f~d~ing ~~d~at; t~~ ~Gs. ___ _

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

_ JOE!-e~!,-+ __ ~<>-gl'li!!v~!_!Yel S1~e~ittypfll======~==-===~::~;~F~N~~

RO 1

Comprehension

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

_______..J _______________ _

1

- ---- - --- -- -- -- ------------------, r-----*--------

g~elo!>'!!e_"t....R~f!'"!O~e~ _____________ I ~~!'1!....~'!r~nces Provided ITechnical Reference(s): FR-P.I, Response to Imminent 1

IPressurized Thermal Shock Condition, rev. 10, page 28 I

ILearning Objective: OP-MC-EP-FRP, Objective 6 I

I 1

I 1

l__

L _______ _

1 401-9 Comments RESPONSE

- I Changed Distractor IDI to "Energize

---

J Pressurizer Heaters". Then, rearranged answers for psychometric balance (D to B, B to C, C to D) making Ie' the correct answer. HCF 11104/09

- - -- - -- -r-- --- -------- -----,------ -

---

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

~u~tJ!I~~~~~4~j~~~:~i!I1l- -t~l~~-'!'~ --- - -1 ~;~~;;fth;;--~;atio~ali;pli~t~~~fth~fOll;;i~g~OncePt-;; th~y ;pplyt~ S~~Li~e R~t~r~(CFR4T8 141.10/1

-- ~---- -

....L ------ ----

l4~.31l:J....C().,n~e(lu~n~~ot'Pl§...._'.. ~.. :'..':..'::.--..':..'.~:.':..':.':..'::..:..,,".'.::..:.. ___________________________..J fuesday, November 10, 2009 Page 117 of185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 47 General Discussion r-------- ------------ -----.-.-- -.-.------ ------ ----------.. --.--- ----.----- --.------ - - -------------.-------.---

IDuring the NC system soak, evolutions may be performed from other procedures which do not increase NC system pressure or decrease NC system temperature iKiA is matched because the candidate is presented with a steam line rupture scenario and must understand what components can be manipulated during the soak (operational Implications)

[which will not violate the requirement to not increase pressure or decrease temperature. These limitations are part of the consequences of the PTS conditions which exist as a result of the lrupture.

I

~na~~sJe~elJ>t~caus~tl1_e ~(l11d~~e!'lust..'ln~I~~~h !lnswer ~nd ~eteElli~~e~ff(:~<:>fll1anip-'.ll~t~~... !h_~t~omponen~~N~3~e~ ~mperattJr~ll~d-.pl!ssur!- _ _ _ _______ _

Answer A Discussion

--.----.-.---------.----------.--------.-.--------------------------------------------------------------------------1 IPlausible because earlier in FR-P.!, if SI termination criteria is not met, an NC pump is started to mix incoming SI water with NC system water to raise the temperature of the water entering I

Ithe reactor vessel down comer L

~

______________ ~ ____

~ ____. _____________________________. ____, ______________________

~ __________

~ __________________________

~

Answer B Discussion

[-.------.--------- - ----- ----------- -------.-------------------------.---------------------------.--------- ----------l IIncorrect. Plausible because FR-P.! directs controlling pressure using heaters and spray in a step prior to initiating a soak. With NCS pressure stable, energizing heaters alone would increase lP~~u!.<:~i()laEn~ the.<iir~CY()l1 t~_n_o~i~c~ase £f~s11r~ ___ _ ______ ____ ___ ____ __ ____ ___ _ ___ __ _ ___ ____ __ ___ _____ J Answer C Discussion ICORRECT~

&e~~lanati~ ~~v~- -- ------ -- - -- -- ------ -- -- --- ---- - - ----- -- -- --- --- - ----- - ---- - ---,

L ______________________________________________. _____________ ~

__________________________ ~

_________________ I Answer 0 Discussion

,------- ---------- --------- ------------ ---------------- ---- --- --- ------------------.-- ----- ------------ -----1

~~OIT:ct~P~~i~=_if~ht: c_an~i~~t~beI~~es~h_~t ~ai~i~g ~~I~v:I to ~~o~aI_I:~~~ ap{)l'o~r~t=_llI1d~~~n()t~~ider~h_=_co~equ~~~~f~d~ing ~~d~ater to tilt: ~Gs. ________ ~

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

_ JOE!-e~!,-+ __ ~<>-gl'li!!v~!_!Yel

~~e~ittYpfl]=======-=====~::~;¢F~N~~=-==== =-===== I ~~~~e~oD7s~:c~:I~I~:;.:!~e RO 1

Comprehension

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

- --- ----- --- ------- ----- J Pressunzer Heaters". Then, rearranged 1---- - --- ----- -------------, r----------------------- answers for psychometric balance (D to B, g~elo!>'!!e-"~R~f!'"!O~e~ _____________

1 ~~!'1~~'!r~nce~~r~~d~----~ B to C, C to D) making Ie' the correct ITechnical Reference(s): FR-P.I, Response to Imminent I

I answer. HCF 11104/09 IPressurized Thermal Shock Condition, rev. 10, page 28 I

1 ILearning Objective: OP-MC-EP-FRP, Objective 6 i

I I

1 L ____________________________ J

- - -- - -- -r-- --- -------- -----,------ -

~uestionBank # jKA_system IKA_number 1 IKA_desc I

---

-- -18471APE040 - -- -IAizI.OI--- --- - -1 iKno;J~g~~ith;-~;atio~ali;pli~t~~~fth~foll~;i;g~oncept~;' th~y ;pplyt~ St;;~Li;e R~t~r;-(CFR4T8 141.10/1

- -- -- ~---- -

.. -.l ______ ----

l4~.31~C~n~e-'lu(~n~~ot'Pl~_'.. ~.. :'..':..'::.__..':..'.~:.':..':.':..'::..:..,,".'.:~ ___________________________ ~

fuesday, November 10, 2009 Page 117 of185

FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 48 r---~~--~-

--T.~-

---~-~--,---

-~-~---

~-~st'~~a!!k~fA1!~~~~r--!!U~i08 IKA=desc I

I--~~--~-~-~---~~---~--~------~~-~--~-------------~-~~~--~-~--~~------~--~--I L~ ___

~ ___

~ ___ ~

_______ ~ __

lAbility to detennine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 145.13)[JSteam I

Lf1~\\\\':feedJren<!!~c()l"~r~.. ~~.~.. -""".-""".~.~.:Oo:~': ___ ~

__ ~

___ ~ ___________ ~_~_~_~ ___ ~_~ _______ ~_~

CURRENT Given the following conditions on Unit 1:

The unit is operating at 100% RTP The steam pressure input for S/G '8' controlling channel fails LOW The S/G '8' trend recorder will indicate which ONE (1) of the following?

A.

- Steam Flow increased

- Feed Flow decreased

- S/G Narrow Range level decreasing

8.

- Steam Flow increased

- Feed Flow increased

- S/G Narrow Range level increasing

c.

- Steam Flow decreased

- Feed Flow increased

- S/G Narrow Range level increasing D.

- Steam Flow decreased

- Feed Flow decreased

- S/G Narrow Range level decreasing ruesday, November 10, 2009 Ape054AA2.08 No comment at this time RF A 10/28/09 45 DAY VERSION Given the following conditions on Unit 1 :

The unit is operating at 100% RTP The steam pressure input for S/G '8' controlling channel fails LOW The S/G '8' trend recorder will indicate which ONE (1) of the following?

A.

- Steam Flow increased

- Feed Flow decreased

- S/G Narrow Range level decreasing

8.

- Steam Flow increased

- Feed Flow increased

- S/G Narrow Range level increasing

c.

- Steam Flow decreased

- Feed Flow increased

- S/G Narrow Range level increasing D.

- Steam Flow decreased

- Feed Flow decreased

- S/G Narrow Range level decreasing 401-9 Comments:

Page 118 ofl85 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 48 D

CURRENT Given the following conditions on Unit 1:

The unit is operating at 100% RTP The steam pressure input for S/G '8' controlling channel fails LOW The S/G '8' trend recorder will indicate which ONE (1) of the following?

A.

- Steam Flow increased

- Feed Flow decreased

- S/G Narrow Range level decreasing B.

- Steam Flow increased

- Feed Flow increased

- S/G Narrow Range level increasing

c.

- Steam Flow decreased

- Feed Flow increased

- S/G Narrow Range level increasing D.

- Steam Flow decreased

- Feed Flow decreased

- S/G Narrow Range level decreasing ruesday, November 10, 2009 Ape054AA2.08 No comment at this time RF A 10/28/09 Given the following conditions on Unit 1 :

The unit is operating at 100% RTP The steam pressure input for S/G '8' controlling channel fails LOW The S/G '8' trend recorder will indicate which ONE (1) of the following?

A.

- Steam Flow increased

- Feed Flow decreased

- S/G Narrow Range level decreasing

8.

- Steam Flow increased

- Feed Flow increased

- S/G Narrow Range level increasing

c.

- Steam Flow decreased

- Feed Flow increased

- S/G Narrow Range level increasing D.

- Steam Flow decreased

- Feed Flow decreased

- S/G Narrow Range level decreasing 401-9 Comments:

Page 118 of185

FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 48 General Discussion I~---~ -~--~- --.--- -~-~--- ~- -

--~~-

-~ -

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

---~--~-~-

-~--.-~-.

-~-

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

IThe steam pressure channel failing low causes a loss of density compensation to the controlling S/G B steam flow channel which causes the steam flow channel to decrease. In response the IS/G water level control system with see a steam-flow feed flow mismatch and will close the Feed Control valve in an attempt to match feed flow to steam flow. The decrease in feedwater flow Iwill cause S/G narrow range level to decrease.

1 iThe K/ A is match because the applicant must diagnose a instrument failure which results in a loss of feed water flow and determine what the indications on the steam flow - feed flow trend Irecorder would be.

I

'IThis is an analysis level question because the applicant must analyze the effect of the failed intrument on the steam flow input to the S/G water level control program and how the change in Ithe input affects the response of the system and the associated recorder trends which indicate that response.

I L __________________

~ _____________. _____

~ ___. ________________ ~

~ ______________ ~

~ _____________. _______._-------!

Answer A Discussion IIncorrect. Plausible if the applicant does not understand the effect ofthe loss of density compensation on the indicated steam flow. The feed flow and S/G level response are correct.

L._~ _~ __

~_. ____

~ __

~ ___

~ __. __. _____

~.~_~ __

~~ __. ___

~ __

~~_~ ___

~ ___

~ ________

._~ _____________

~ ___________

~_~ ___

~ __

~_

Answer B Discussion r:~- ---.-

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

-~--

.-.--~---

--~-~-

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

---

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

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

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

iIncorrect. Plausible if the applicant does not understand the effect of the loss of density compensation on steam flow. And if steam flow increases it follows that feed flow would increase to Ill1lltcEste~Qow ~~"!~W()u.!<!}llc~~e _____________ _

Answer C Discussion Ii

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

.-~~-

-~--~---

--~------

---~-

-~~--~~----

--~-

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

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

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

IIncorrect. Steam flow decreasing is correct. Feed flow increasing is plausible if the applicant does not understand the effect of the steam flow decrease on Feed Control valve response. If the 1

1Y~~Qo~in~r~~~t~e~/SJJe~~~~i~cre<lS~ __________________________________

~ ___ ~ ____________________________ J Answer D Discussion

,,--~----

CORRECT.

[--~---

-JobLe~;' ~ I-~ Cognitive Level

---~-- -~-t-

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

___ ~? ____ l ___ ~o~!Jr~h~n~ion

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r;~~--~-.- ~-~-~ -~~-~--- ~- - -- ~--

e~velop~~!l~~f!"!flc~~ ___ _

ITechnical Reference(s): OP-MC-CF-IFE, rev. 21, page

133, 1

I 1 L __________________

• ____________________ _

iUestlonBank ir~system-TKA=number - --- -1 IKA_desc Question Source

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

MNS CFIFENO 1 iStuderlt-ReterencesProvlcted--

r~------*---~~--~-~--~-

I 1

I 1- ____

~ ____

~ ___

~ _____

~ __._

---~--~-l

---

.--~-~~-- -- --~-- --~~-- j 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

---

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

---~---~- -

f~-~-.-- --~-f:--~-~~- - - - -

--~- -*1 I-~-~-~-*----. -- - -

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

-~---- _. ---

18481APE054 IAA2.08 I lAbility to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 /

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

l~:l D~S!.e~flo~.:f~e.cJ.t~~

J~()J"~~'~""

ruesday, November 10,2009 Page 119 of 185 FOR REVIEW ONLY - DO DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 48 General Discussion I~---~ -~--~- --.--- -~-~--- ~- -

--~~-

-~ -

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

---~--~-~-

-~--.-~-.

-~-

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

--~.

-~--~~-~--~-~--------l IThe steam pressure channel failing low causes a loss of density compensation to the controlling S/G B steam flow channel which causes the steam flow channel to decrease. In response the 1

IS/G water level control system with see a steam-flow feed flow mismatch and will close the Feed Control valve in an attempt to match feed flow to steam flow. The decrease in feedwater flow I Iwill cause S/G narrow range level to decrease.

1 I

I iThe K/ A is match because the applicant must diagnose a instrument failure which results in a loss of feed water flow and determine what the indications on the steam flow - feed flow trend 1

Irecorder would be.

I

'IThis is an analysis level question because the applicant must analyze the effect of the failed intrument on the steam flow input to the S/G water level control program and how the change in Ithe input affects the response of the system and the associated recorder trends which indicate that response.

t _____

~ _______

~ ____

._~ ___

~ _____

~_. __

.~ __._~_~_. _____

~ ___ ~

~_~~ __

~ ____. ___ ~_~ ___

~ ______

~_. ____

~_~ __. ____

~_~_

Answer A Discussion IIn~~~t~ Pl;-~~hl~iith~ ;pPIi~~t does-n-~t ~~~;sta~dth~clfuct of ili;l;;-s;;-ofde;-s1tY ~~~p~n~~ti~;-~th~;;;dic;ted~a~flo~:The fe;dfl~w-a;-d-S!G le~cl ;,po~;~;~;-c~;;ct. ----I L._~ _~ __

~_. ____

~ __

~ ___

~ __. __. _____

~.~_~ __

~~ __. ___

~ __

~~_~ ___

~ ___

~ ________

._~ _____________

~ ___________

~_~ ___

~ __

~_~ ____ --"

Answer B Discussion

~~~o~~tPI~~bkif th; ~pPli~rrtdo~s~~ ;nde~st;~dth;clr~ctofthel;~s-of de~sitY-;;~mPe~;;tio;--~~~;m fl~;' :-And if st;;~;fl~;in--;;;~a-;,;jtf;lIo~ ili;tl fi:;d fl;;-w-wouldi~c;:;;~e to Ill1lltcEste~Qow ~~"!~W()u.!<!}llc~~e __________________________________ ~

~ ________________________ _

Answer C Discussion Ii

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

.-~~-

-~--~---

--~-----~

---~-

-~~--~~----

--~-

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

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

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

IIncorrect. Steam flow decreasing is correct. Feed flow increasing is plausible if the applicant does not understand the effect of the steam flow decrease on Feed Control valve response. If the 1

1Y~~Qo~in~r~~~t~e~/SJJe~~~~i~cre<lS~ __________________________________

~ ___ ~ ____________________________ J Answer D Discussion

~~~E~f*~===========~=========== =~===~==================================~=========]

c~~- ------

~

I-~ -~~~.-

--~-~---~--,- -

-~-- ---

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

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

~---~----

---~--~--~,

~._J~~'=_~!'_~- _ Cogl'lltlY!!.!"!'-_--L9~e..!!'o_nT~

Question Source I 401-9 Comments RESPONSE RO I

Comprehension BANK

_---_-._-. -_-_-_-._-MN.*-_S._CFI_FENO._I_-. _-_-_-_~

__ -_-_- -_- - -Jl Considered SAT for submittal with no

~ ______ ~~_~ ___

~_~~_~_~ __ ~ __ ~_..l ___ ~-

---~---~,~.--~-.-

~

~~

~

comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r;~~--~-.-

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

e~velop~~!l~~f!"!flc~~ ___________ _

ITechnical Reference(s): OP-MC-CF-IFE, rev. 21, page

133, 1

I l __ ~ __ ~ __ ~ __ ~ ____ ~ ___ ~ _____ ~~ ______ ~_

iStudent-ReterencesProvlcted --

r~------*---~~--~-~--~-

I 1

I 1- ____

~ ____

~ ___

~ _____

~ __._

~-~- -

-~-

~- - -

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}uestlonBank 'KA_system IKA_number I IKA_desc J'

---~---~- -

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--~- -*1 I-~-~-~-*----. -- - -

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

-~---- _. --- - ----- -~-~- --~---~--.-~--~-~-

18481APE054 IAA2.08 1 lAbility to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 /

1

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

l~:lD~S!.e~flo~.:f~e.cJ.t~~J~()J"~~.~"".... ~"":~:~:,--: __.. ",,. _______

~ _______________

~ _______ J ruesday, November 10,2009 Page 119 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 48 ruesday, November 10,2009 Page 120 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 48 ruesday, November 10,2009 Page 120 of 185

D FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 49 I---~--~-~ -~

'-r&;-~

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

~'~I,- ---

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

--~.-.- ~~~'-~-"-'~-"- - --- -. --.~-~-~- -

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--~~~--

QuestionBank # KA system IKA number IKA dese f-~---~-~l"-'--=~--'-I---=~-*-*-*--~**--Ir:-~---'--'----~--~------ ~-~

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

I 1849 I

EPE055 i

EK3.02 IIKnowledge of the reasons for the following responses as the apply to the Station Blackout: (CFR 41.5 ! 41.10 ! 45.6 !

~--~---~- ~------ J..-----~-~---145.13)[JActions contained in EOP for loss of off site and onsite power..........

l ________________________________________________________________________

~ ___ _

CURRENT Given the following conditions:

A loss of All AC power has occurred on Unit 1 Crew has implemented ECA-O.O (Loss of All AC Power)

The Unit 1 Standby Make Up pump has failed Incore Cooling Monitor indicates subcooling is - 5°F Which ONE (1) of the fol/owing describes the reason for depressurizing the S/G's to 290 PSIG?

A B.

C.

D.

Initiate Cold Leg Accumulator injection to restore subcooling.

Initiate Cold Leg Accumulator injection to maintain the core subcritical.

Reduce NC system temperature and pressure to establish Natural Circulation conditions.

Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss.

EPE055EK3.02 45 DAY VERSION Given the following conditions:

A loss of All AC power has occurred on Unit 1 Crew has implemented ECA-O.O (Loss of All AC Power)

Attempts to place the Unit 1 Standby Make Up pump in seNice have failed The crew is performing actions to depressurize the S/G's to 290 PSIG Which ONE (1) of the following describes the reason for this action?

A B.

C.

D.

Initiate Cold Leg Accumulator injection to re-establish NC system subcooling.

Initiate Cold Leg Accumulator injection and establish Natural Circulation conditions.

Reduce NC system temperature and pressure to establish Natural Circulation conditions.

Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss.

401-9 Comments:

A is NP because there is nothing in the stem to indicate that NC system subcooling has been lost or challenged.

There is nothing in the reference to support the use or potential use ofCLAs in this case..

Distracters A and B do not appear to be plausible.

This Q is U until it is proved otherwise.

fuesday, November 10, 2009 Page 121 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 49 D

---

~-li---------------,---------------I'------------------------------ -- - -------- ----------- - ----------- --

~ue~o~ani(~~A-sy~em-I~-nu~E!'"--~--IIKA-~~S~------ _______ ;--___ ~ ___________.-----------------------

I 1849 I

EPE055 I EK3.02 I !Knowledge of the reasons for the followmg responses as the apply to the StatIOn Blackout: (CFR 41.5 ! 41.1O! 45.6!

~------~- ~------ L-----~-~---145.13)[JActions contained in EOP for loss of off site and onsite power..........

l ________________________________________________________________________

~ ___ _

CURRENT 45 DAY VERSION Given the following conditions:

Given the following conditions:

A loss of All AC power has occurred on Unit 1 Crew has implemented ECA-O.O (Loss of All AC Power)

The Unit 1 Standby Make Up pump has failed Incore Cooling Monitor indicates subcooling is - 5°F Which ONE (1) of the following describes the reason for depressurizing the S/G's to 290 PSIG?

A B.

C.

D.

Initiate Cold Leg Accumulator injection to restore subcooling.

Initiate Cold Leg Accumulator injection to maintain the core subcritical.

Reduce NC system temperature and pressure to establish Natural Circulation conditions.

Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss.

EPE055EK3.02 A loss of All AC power has occurred on Unit 1 Crew has implemented ECA-O.O (Loss of All AC Power)

Attempts to place the Unit 1 Standby Make Up pump in seNice have failed The crew is performing actions to depressurize the S/G's to 290 PSIG Which ONE (1) of the following describes the reason for this action?

A B.

C.

D.

Initiate Cold Leg Accumulator injection to re-establish NC system subcooling.

Initiate Cold Leg Accumulator injection and establish Natural Circulation conditions.

Reduce NC system temperature and pressure to establish Natural Circulation conditions.

Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss.

401-9 Comments:

A is NP because there is nothing in the stem to indicate that NC system subcooling has been lost or challenged.

There is nothing in the reference to support the use or potential use ofCLAs in this case..

Distracters A and B do not appear to be plausible.

This Q is U until it is proved otherwise.

fuesday, November 10, 2009 Page 121 of 185

FOR REVIEW ONLY - DO DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 49 RF A 10/28/09 General Discussion

---.~---

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

[The S/Gs are depressuized to 290 psig to reduce NC system temperature and pressure. This will reduce the amount of leakage from the NC pump seals which will minimize the NC system

!inventOry loss until AC power can be restored.

]If SGs are de?r.essu~ized to less than 190 psig, the CLA accumulat?rs wi~l inje.ct into the ~C. System: While this is desirable i.n.some EOP ~itigating s.chemes to depressuize the SGs t~ cause Ithe CLAs to Inject (I.e. ECA-I.I, Loss of Emergency Coolant ReCirculatIOn), In ECA-O.O It IS undesirable to have the CLAs Inject as any mtrogen which enters the NC system could disrupt INatural Circulation flow.

I IKiA is matched since the applicant must know the basis for actions taken in the EPs L-___

a Station Blackout.

Answer A Discussion fI~c;rr~~t.PI~u;ibk-b~;;-u; th;;-~ept~ depr~s_;;ri~;theS;G;;_t;_ n~tp~f~~~ unl~;;ub~~ing i;-lost~dditio~auy~~ect~gtht;CLA;;~o~;idpro~d~~el~tivcly c~CJ1 ;at~;-t;;-the-NC

[system which would act to improve subcooling.

L __ o ______________ 0 __ 0 ____ 0 _______ 0 _____ 0 ____ o ___ ~

___ o _____ 0 ______ 0 __ 0 ________________________ 0 Answer B Discussion

~

o o

o o

o o

o o

o

-_____________ 0_0 ____________ 0 ________ 0 ____________ 0 ____ 0_00_0, IIncorrect. Plausible because there is extensive discussion in the WOG background document regarding the potential to return to a critical condition during SG depressurization prior to i

~~~iI1~

the_C~~i!1jecti0!lpr~s..t'.rt: Q.~ ~O~_\\vithJ()w..!em~.':.a!.u~"_ _________________________________________________________ I Answer C Discussion ii~c~~~ct.WhiJ;; -;:-educi~gNCp~~p;;al k~ag;i;-c~;~ct;nd~t~blishi;-g-N-;turaIC;;-;;-i~ti~n-c~nditio~s i~;;-s;;~bl~~ r-;;-d~i;;gSG-p-;:-~~~;~;-t~290 p-;ig i~~t;.equired to establish Natural lCir~~ti<J!l..~ll.di!i~n~

Answer D mscusslon ICORRECY-------- ---------

l_o ___________

0 ____ 0 ___

-- -- --- --r--- -- -- -----0-,---0-0--0------0---0--0-0--0------

-~o----------I Cognitive Level I QuestlonType I

Question Source

. 401-9 Comments RESPONSE

__ 0 __ 0_0 __ -

___ 0_0 _____ 0 ________ 0,_ 0_0 ____ 0 ______________ 0 __ 0 _______ 0_0 __ 0 __ 0 ____ j Memory

[BANK I

CNS NRC Exam Bank Question 126

[

______..1_0 __ 0 ___ 0 ___ 1. ___ 0 __ 0 ____________ 0 _____ 00 _____ 0 ________ 0_0 ____ ' Per Chief Examiner's comments, revised distractors 'A' and 'B' to add plausibility.

~ Developed

~ OPT Approved

~ CPS Approved

~ NRC Approved 1.------ - -- -------------

RCF 11104/09 l~~e-'-oJ>r\\1!~B~er!~!s____ ______

~!ud!.~~ef!!'~~e! ~r~~<!e~ ___ --J IECA-O.O page 22 I

1

[Lesson Plan OP-MC-EP-ECA-O pages 19 and 49 I

[

I

[

i I

I

[

l______ ____________________

l ______________________ J -----0--- - 1

--- -o--o--r-o---o- __ ---0---,,00--- ___ 0 _____

~

____ o __ o_o ___ 0 ____________ 0_0 _______ 0 ____ 0 __ 0 ________ _

luestionBank # KA_system KA_number

[ IKA_desc i

~-~-_-_---184~EPE055--- - ~K3~02 ---- --- -l ~n~ledg~ ?fth-;;~e;;;'.~;-~~rth~ f~U~in~~sp~~';s ~th~ apPlyt~ theSt;~~m~d~~:(CFR4W 41~ O/45.6T ---l o

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

1~.?J31[~_~f'.0!ls~~~111e~'--n E0I>.f()r--'~s.9!'.0!fslt~a!ld..9~~.2.~~r_.......... -" ______________________.J fuesday, November 10, 2009 Page 122 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 49 RF A 10/28/09 General Discussion

---

.--------.-.--------.-.-------------.---.------.-----.----.-------------.--------.--------------.--.-----------*--*----1 IThe S/Gs are depressuized to 290 psig to reduce NC system temperature and pressure. This will reduce the amount of leakage from the NC pump seals which will minimize the NC system I

!inventOry loss until AC power can be restored.

]If SGs are de?r.essu~ized to less than 190 psig, the CLA accumulat?rs wi~l inje.ct into the ~C. System: While this is desirable i.n.some EOP ~itigating s.chemes to depressuize the SGs t~ cause Ithe CLAs to Inject (I.e. ECA-I.I, Loss of Emergency Coolant ReCirculatIOn), In ECA-O.O It IS undesirable to have the CLAs Inject as any mtrogen which enters the NC system could disrupt INatural Circulation flow.

I

~A_i~

~t<:~!sin~ th~ appli~~ ~~~kl10W~h~~~lo~~(;t~~!<t~~i~the~X~dllr~~~~~o~ Bl~~0.ttt~ _____________________________ _

Answer A Discussion

~-------.------.---------.------.----.-.--------~--------.--.------.-------.---.----.. ---------.------------------1 IIncorrect. Plausible because the step to depressurize the S/G's is not performed unless subcooling is lost. Additionally, il1iecting the CLAs would provide relatively cool water to the NC I

~~~~~~~\\~'OIII_! act~oJ~~()\\'e~ub~()

.. li~~ ______________ ~

__________________________________________. _____. ______ J Answer B Discussion

~--------------.-.-----------------.----.-------.-----------------_._------------_._-------.------------.----.-.-_.,

IIncorrect. Plausible because there is extensive discussion in the WOG background document regarding the potential to return to a critical condition during SG depressurization prior to i

~~.(;lliI1~ the_C~f~i!1jecti0!lpr~s~rt: Q.~ l~O~_\\vithJ()w-.!em~~a~u~"_ _ _ ______ __ _____ ___ ___ _____ ____ _____ ____ __ ___ _ ___ _________ I Answer C Discussion

-.------.-- --- ------.-.---- ------ -.- -- ---.---.--.----.-- ------ --.---.- ----.------.------.-----.. -- ---- ------*-*----*---------*-1 IIncorrect. While reducing NC pump seal leakage is correct and establishing Natural Circulation conditions is desirable, reducing SG pressures to 290 psig is not required to establish Natural I lCir~~ti<l~~~di!i~n~ ___________________________________________________________________ ~

______ J Answer D mscusslon

---

.---------.-.. ---------.----------------------------------.------------.---------.------.---.-----.-.-'-'---'l ICORRECT I

l_. ________________. __________. ___._. _________. _____________. __________________________________._.. ________. _______.

~ Developed 1.---.--.- -- --- --------.-.------

l~~e!oJ>r\\1!~B~er!~!s _________._

~ OPT Approved IECA-O.O page 22

[Lesson Plan OP-MC-EP-ECA-O pages 19 and 49 I

I

~ OPS Approved i

L._. ____. ____. _____._. ___________._

~ NRC Approved

iUestlonBank,lKA-syatem-fi<:A-number -----i IKA--iesc- - -- ------.--.-.-- ----- ---------.-.---- ------- -*--*---------*-*-*---1

~-~-_-_---184~EPE055--- - ~K3.-02 ---- --- -l ~n~ledg~~ith~~e;;;,.~~~~rth~f~U~in~~sp~~.;s~th~ apPlyt~ theSt;~~m~d~~:(CFR4W 41~O/45.6/----l

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

1~.?J3JL~~~0!lS~~~llle~'_n EO~f?rJ~s.9!'0!fslt~a!ld_.9~~JJ.~\\\\'(:r_............. ______________________ ~

fuesday, November 10, 2009 Page 122 of 185

FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 49 DISTRIBUTE D

Tuesday, November 10,2009 Page 123 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 49 DISTRIBUTE D

Tuesday, November 10,2009 Page 123 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 50 A

~u~s!i~nB!~#1RA_~t!rJi=rKA_n~m~==-==] iKA~di~~=-=~=-=====-==--_=-=-~~==--=-=-===-=-==-===-====--=-=-=--=-= =-= =-==-===-=-==

L_~~850~~_1_ ~~~~~ 1 ___ ~~:~7 ___ J lAbility to ?etermine and interpret the following as they apply to the Los~ of Off site Power: (CFR: 43.5 1 45. 13) LJ ED/G indicators for lthe followmg: voltage, frequency, load, load-status, and closure of bus tie breakers......................

---

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

CURRENT 45 DAY VERSION A Loss of Off-Site Power (LOOP) has occurred.

DIG '1 B' is supplying bus 1 ETB. loaded as follows:

Voltage - 4120 volts.

Frequency - 59.4 Hz.

Load - 1800 KW.

Which one of the following describes the response of DIG '1 B' when the Governor Control RAISE pushbutton is depressed?

A.

8.

C.

D.

Frequency increases; load and voltage remain the same.

Frequency and voltage remain the same; load increases.

Frequency increases; load remains the same; voltage increases.

Frequency remains the same; load and voltage increase.

APE056AA2.37 No comment at this time RF A 10/28109 fuesday, November 10,2009 A Loss of Off-Site Power (LOOP) has occurred.

DIG '1 B' is supplying bus 1 ETB, loaded as follows:

Voltage - 4120 volts.

Frequency - 59.4 Hz.

Load - 1800 KW.

Which one of the following describes the response of DIG '1 B' when the Governor Control RAISE pushbutton is depressed?

A.

Frequency increases; load and voltage remain the same.

B.

Frequency and voltage remain the same; load increases.

C.

Frequency increases; load remains the same; voltage increases.

D.

Frequency remains the same; load and voltage increase.

401-9 Comments:

Page 124 of 185 A

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 50 19u~St~nB!~#lKA-~t!rJi=rKA-n~m~==_==J iKA~di~~=_=~=_====_=_==_-_=_=_~~=_=__=_=_===_=~~ __ ~ _~~ __ ~_~ __ ~ _ ~_~_.~:_~-~

I

~-1850 r APE056 j

AA2.37 liAbility to determine and interpret the following as they apply to the Los~ of Off site Power: (CFR: 43.5 145. 13) LJ ED/G mdlcators for L_~ --~~-~ ~ -~--- L_~_~_~ ~--~, l~eloll~wing: :"9l!a~"__fr~qtl~cy,.lolldcJoad-status'_a~~(}~ure.c>f~~tle ~r~ke~~~~:~.~= ____ ~~ ______ _

CURRENT 45 DAY VERSION A Loss of Off-Site Power (LOOP) has occurred.

DIG '1 B' is supplying bus 1 ETB, loaded as follows:

Voltage - 4120 volts.

Frequency - 59.4 Hz.

Load - 1800 KW.

Which one of the following describes the response of DIG '1 B' when the Governor Control RAISE pushbutton is depressed?

A.

8.

C.

D.

Frequency increases; load and voltage remain the same.

Frequency and voltage remain the same; load increases.

Frequency increases; load remains the same; voltage increases.

Frequency remains the same; load and voltage increase.

APE056AA2.37 No comment at this time RF A 10/28/09 fuesday, November 10,2009 A Loss of Off-Site Power (LOOP) has occurred.

DIG '1 B' is supplying bus 1 ETB, loaded as follows:

Voltage - 4120 volts.

Frequency - 59.4 Hz.

Load - 1800 KW.

Which one of the following describes the response of DIG '1 B' when the Governor Control RAISE pushbutton is depressed?

A.

Frequency increases; load and voltage remain the same.

B.

Frequency and voltage remain the same; load increases.

C.

Frequency increases; load remains the same; voltage increases.

D.

Frequency remains the same; load and voltage increase.

401-9 Comments:

Page 124 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 50 General Discussion r;::;-~---- -.-.----------------

[Generator running disconnected from grid - No V AR loading or load sharing. Generator in isochronous mode means governor is speed = frequency. Voltage is excitation=volts. When

\\frequency is raised, other parameters may change slightly depending on the value of those parameters.

I IKiA is matched as the applicant must understand how EDG indications are affected when the diesel generator is operated in isochronous mode (i.e. during a Loss of Offsite Power).

I

[This is an analysis type question as the applicant must relate several pieces of information both given and recalled from memory. The given information is the initial condition where the EDG lis operating supplying the bus in isochronous mode. The applicant must then recall from memory the effect of depressing the Geneerator Control RAISE pushbutton with the generator loperating in isochronous mode.

L ____

~_.~ _____________________. ______.. _. __._. ______________________. ___. ______

~. __._. ______. ___________. ____._

Answer A Discussion IcORRECT.- -

-~~-

-~-

---~---

Answer B Discussion

~~~l'f~~t~!!~~~~0~~~f'I)~\\V<lS Earalle~d Answer C Discussion 1--------

IIIlc~rr~c~~n~s~c~~~~f(ti~n~ fre<luen~y_\\\\I~~~~t~~e~s~v~lt<lg~ __

Answer 0 Discussion I----*--~--------- ----

IIncorrect. Voltage remains the same.

L ________________________________

~ _______________________________ _

--~---~--- -

1

___ I

~----l

_J

--*-1 9uestlo~!~u~~~ __________ 1 401-9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 2006 CNS NRC Q50 (Bank 127)

I Considered SAT for submittal with no

-~-------------~----------.-I comments. No changes.

r:- -- ---

---~----

-*-------*--*-*----~-I '---------------------------~

l!>!v.!'op_m~nt~!!f)~~e! ___________._j IStu~'!t~.!ference~~rO"'de~ ____ ~

\\Lesson Plan OP-MC-DG-DG Objectives 14 and 15 I I I

[page 3 I I 1 I

[

II I

I II I

I I I i

1 _____ ~ __. ___

~ __________. _______ I L _______________. __. __

.~ __ i

~.--- -----_._--.---.-,--._--

~- --- -

}uestlonBa....,~~~A-.!Yste"!-~A-l'~Frl.-~'"--

r~/01e;~ -=--==-_ -=-==_-=-=-_-_--====~~_= ~-= __ -_-__ ~= __ _== -= ___ ~

_=-=-~-=--======-== ~==-===_

1850APE056 IAA2.37

'J _____

~ __ i ____

~ __

lAbility to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5 I 45. I 3 )DED/G

[itl.cliCl1t()l:si()l: Q1~foll<l.\\\\Ii~~()ltag~ E:~l!(:nc~.1()ad, lo!id-st~~ ~~ cIosuI'\\:.c>.f ~~

~

E.r~ake~..-.:=...-.::... ::........ _____ _

ruesday, November 10, 2009 Page 125 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 50 General Discussion r;::;-~-----.-.------------------------------.-------.------~-------~--~------~-------------.--.-------

[Generator running disconnected from grid - No V AR loading or load sharing. Generator in isochronous mode means governor is speed = frequency. Voltage is excitation=volts. When

\\frequency is raised, other parameters may change slightly depending on the value of those parameters.

1 IKiA is matched as the applicant must understand how EDG indications are affected when the diesel generator is operated in isochronous mode (i.e. during a Loss of Offsite Power).

I

[This is an analysis type question as the applicant must relate several pieces of information both given and recalled from memory. The given information is the initial condition where the EDG lis operating supplying the bus in isochronous mode. The applicant must then recall from memory the effect of depressing the Geneerator Control RAISE pushbutton with the generator loperating in isochronous mode.

L_~~

___. _______________. _______. ______.. _. __._. ______________________. ___. _____ ~_. __._. ______. ___________. ____._

Answer A Discussion IcORRECT.- ---------- ------- -

---

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

~------.---

---

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

Answer B Discussion

,------------------.---.----------------.--.---------------.-.--~-----.------.-~------------.~.------- ------1

~n~0l'fe~t~_~I'tia~~()IT~c~f'I)~\\V<lS Earalle~d _______________ ~

____________________________________ ~

_________ I Answer C Discussion

,-------.---.--.-----.-------------.-----------~-----.-------.-.-----~--.--.---------.-.---------.------.. ------l lIn correct. In isochronous, raising frequency would not increase voltage

. __. ____. __.. _. _____________. _____.. ___. ____. _____. ___________. _____. __ ~

__________._. _________ ~

___. ________ ~

___ _.J Answer 0 Discussion 1----*------------ -------- ---.---------.----------------- -- ----.---- --------

-.-------~----.---.--- ---------*--1

~~o~ec~~o~~~r~ai~~e_s1lITl~ _____________________________________________________________ ~

__ J

'-Job Le~' +~-=-~1!!fu_~L~~_~}~~;StlOErYpe=r~====-==-=-~ ~=QuestIO~!~U~~========_=_=_] 401-9 Comments RESPONSE

___ ~~ __ L ___ C~~~lJ:~~~ __ l ___ B!~~ __ ~ __________ 2~~~~S_N~~ ~~(B~n~~~ ____ ~ ___ -' ~:~~~:~~ ~~ :::;~:.mittal with no r:- -- --- -------- -*-------*--*-*------1 c---------------------------

~ Developed l!>!v.!'op_m~nt~!!f)~~e! ___________._j IStu~'!t~.!ference~~rO"'de~ ____ ~

\\Lesson Plan OP-MC-DG-DG Objectives 14 and 15 1 I 1

~ OPT Approved

[page 3 I I

1 I

[

II I

~ OPS Approved I

I I 1

~ NRC Approved I

I I i

1 ________. ______________. _______ 1 L _______________. __. __. ___ i

~~!s![~n~ajlf~~-~ste~--~A~~~'"------

r~/01e;~ -=--==-_ -=-==_-=-=-_-_--==-=--=-_~_= -=-= __ -_-__ ~= __ _== = ___ -=-_=-=-~-=-= -=====~= _===== _

__ ~ _____ I~~~~O~6

____ J~~2~__ _

~~~~;1~e;~~:I~~t:e;~~!;~e ;~;;~~~~~~ro~~!~~~~~o:I~~~~~:~::;~:~~:r~:~~... 5L~*.~.~?~~~ __ _

ruesday, November 10, 2009 Page 125 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 51 c

~--.-.----.-.------- -,.---------------1*- --------------.-.------- -- -----

c~~ilr~~1~~~:f-j~-n~~~~6~~~l :~li~e~co~~~~and /~~niU;~th_;; follo;~ng as they~pIYt~heLo-;s~fVital A-C ~_;_trume;Bus: (CFR 41.7/45.5 1 145.6)uManual control of components for which automatic control IS lost.......

l ____________

~~ ____________

~~

~ __

~ _______________

~

CURRENT Reactor power is at 45% RTP with all systems in automatic when you notice the following:

120 VAC ESS PVVR CHANNEL A TROUBLE alarm CH 1 Impulse pressure indicates 0 PSIG All 4 S/G CH 1 Feed Flow, Stm Flow and Levels indicate 0 %

CH 1 PZR pressure indicates 1700 PSIG Which ONE (1) of the following lists the IMMEDIATE ACTIONS which must be taken based on these indications?

A B.

C.

D.

Manually trip the reactor.

Place Control Rods and Feedwater Reg valves in Manual and restore Tave to Tref.

Place Control Rods and Feedwater Reg valves in Manual, and manually restore S/Gs to program med level.

Place Pressurizer Pressure Master in Manual, adjust to 50%, and then place "PZR PRESS CNTRL SELECT" switch to backup channel.

APE057AAl.06 45 DAY VERSION Reactor power is at 45% RTP with all systems in automatic when you notice the following:

120 VAC ESS PVVR CHANNEL A TROUBLE alarm CH 1 Impulse pressure indicates 0 PSIG All 4 S/G CH 1 Feed Flow, Stm Flow and Levels indicate 0 %

CH 1 PZR pressure indicates 1700 PSIG Which ONE (1) of the following lists the IMMEDIATE ACTIONS which must be taken based on these indications?

A B.

C.

D.

Manually trip the reactor and go to E-O (Reactor Trip or Safety Injection).

Place Control Rods and Feedwater Reg valves in Manual and restore Tave to Tref.

Place Control Rods and Feedwater Reg valves in Manual, and manually restore S/Gs to programmed level.

Place Pressurizer Pressure Master in Manual, adjust to 50%, and then place "PZR PRESS CNTRL SELECT" switch to backup channel.

401-9 Comments:

To be consistent, state in B, C, and D the procedure you will go to after completing the lAs.

RF A 10/28/09

[uesday, November 10,2009 Page 126 of 185 2009 RO NR~~~a~~::!!:t~~L y ~~~T~N 5~ISTRI~UTE ____ C _ _ __ _

~st[~~~~)IKA:sYstejn~ I~_n-U~~~=~~ Il~=~e~c===~~-=-=-=_===--=~==-=- =~ ______ ~_~ __ ~ _~ __ ~~ ___________ ~~ I I

1851 1

APE057 1 AAI.06 liAbility to operate and 1 or monitor the follow~ng as they ~pply to th.e Loss of Vital AC Instrument Bus: (CFR 41.7 1 45.51 l

L __ ~---- - L. __ ~~ __ ~ _L --~-~- ---- ~ !42.~g~al1u~~0.E:tr.c>~£(;~IllP~~~for w.h.2c11~utom(ltJc ~llt~~i..'.sJ?~ ~~ ______________ ~_~

_____ J CURRENT 45 DAY VERSION Reactor power is at 45% RTP with all systems in automatic when you notice the following:

120 VAC ESS PVVR CHANNEL A TROUBLE alarm CH 1 Impulse pressure indicates 0 PSIG All 4 S/G CH 1 Feed Flow, Stm Flow and Levels indicate 0 %

CH 1 PZR pressure indicates 1700 PSIG Which ONE (1) of the follOwing lists the IMMEDIATE ACTIONS which must be taken based on these indications?

A B.

C.

D.

Manually trip the reactor.

Place Control Rods and Feedwater Reg valves in Manual and restore Tave to Tref.

Place Control Rods and Feedwater Reg valves in Manual, and manually restore S/Gs to program med level.

Place Pressurizer Pressure Master in Manual, adjust to 50%, and then place "PZR PRESS CNTRL SELECT" switch to backup channel.

APE057AAl.06 Reactor power is at 45% RTP with all systems in automatic when you notice the following:

120 VAC ESS PVVR CHANNEL A TROUBLE alarm CH 1 Impulse pressure indicates 0 PSIG All 4 S/G CH 1 Feed Flow, Stm Flow and Levels indicate 0 %

CH 1 PZR pressure indicates 1700 PSIG Which ONE (1) of the following lists the IMMEDIATE ACTIONS which must be taken based on these indications?

A B.

C.

D.

Manually trip the reactor and go to E-O (Reactor Trip or Safety Injection).

Place Control Rods and Feedwater Reg valves in Manual and restore Tave to Tref.

Place Control Rods and Feedwater Reg valves in Manual, and manually restore S/Gs to programmed level.

Place Pressurizer Pressure Master in Manual, adjust to 50%, and then place "PZR PRESS CNTRL SELECT" switch to backup channel.

401-9 Comments:

To be consistent, state in B, C, and D the procedure you will go to after completing the lAs.

RF A 10/28/09

[uesday, November 10,2009 Page 126 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 51 General Discussion IT~ I~--;;di;e-~tio~;_~AP-IS:-Lo~~f Vit;I~;Au~ C~troI p-;;~~~~ir;t~~pe~atot ~-;;hedth~;tatus ~fTnst;~;I~em-chan-;~I~T~d 2:Jfth;;;-~h~~cls~ l~~t th;~p~r;~ ~~st- -

[place the control rods in manual and place the CF control valves in manual and restore S/G levels to program level.

I

~~~~~ ~~~cl:e<i~~atJ~ ~h~ llPl'li<:~n0~~qtli!-e~_t<l ~~~anllil~~i9~~hic~

ll1ll~~eJ:~~ ~~C()-'~tr~I~~_jJhll1~~llJ()S~ ~~\\li.tlll~S!r~~~tJ'us,-_________________ _

Answer A Discussion r:------------------------------------------------------------------------------------------ ------------

[Incorrect. Plausible if the applicant believes that MSIVs have closed or control of the plant has been lost and that tripping the reactor is necessary to place the plant in a safe condition.

j

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

---

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

---

~ ----

Answer B Discussion c- ------ -- -

---

-- - ----I

[Incorrect. Plausible because these are actions that will be taken to restore plant conditions to normal. However, these are done later in AP-15 and are NOT immediate actions.

_ 1 L __________ ~

___________________________________________________________________________________________________________________ -.J Answer C Discussion E~~c:.~~ ____ --=--=-____ ~-_~~ ___ -_-_

Answer 0 Discussion rfuco-;:;'~t Pl~~ble-~th~te-ar~~ti;;_~;lat;rTn -AP..--15;~~;di~gth~P~;;~~i~;;p;.-;;-s;-ute -;;h~nclf~l~r~:H~;-e~~ they;'; n~ti~~edi;e---;cti~n-;.--- - - - -

---

- - - --I L __________________________________________________________ ~__ __________ _ __________ _ _ _ __ _______ _ _______ __

_ _______.J

- --------T- ---- ------- --r---------- --- - ----- - ------- - ---- -

Cognitive Level

! QuestionType I Question Source 401-9 Comments RESPONSE Job Level RO

~

---

~-----I---------------~-----------------------~------------------------

Memory i

BANK I

MNS Bank Question APl5002 Per Chief Examiner's comment, removed

---.--.-~-- -- - ____..1 ______ - - -- - --- ------ - - - - - ----- ---- -

reference to procedure (E-O) in distractor

________________ -~___

'A'. HCF ll/04/09

~.!-'e!oJ>~~'!t-R!f!l'!flCCt!.---------_ _ _

l~~dent.. ~ferefl.c.!s.P~... i~~ _____ _

IAP-I 5, Loss of Vital or Aux Control Power page 3, 6,

[

IS and 22

[

I'

~ Developed

~ OPT Approved

[

[

~ OPS Approved

~ NRCApproved L________________________

- ------ ------T.:------------- --,,----------------- ------------------- - ----- ----- -- ------ ------ ------ ------------1 c.llJ!.!tI~!S~i{~ t~E~:?!'!' -FI.~~.IllE!r-----l ~~e~~p~~~;~~I/~ ~~t-;;rthe foll~ng~th~-~pp-lytotheL~;; of vitaiXEI~str~~_;;_nt B~s~cFR4~7145.5 ;---1

---

- --- -- - - -- - -- -- -~ l~.6)LJM.~ull!~()l1!()l()fc()IIIP.9~lltsJ{)r.w.!Iic;~a~t()mati.ccontl'O'!~lo~_".:-_,,_ _______ _ ___________ __ _

_ ____ J ruesday, November 10, 2009 Page 127 of 185 FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 51 General Discussion IT~ I~--;;di;e-~tio~;-~AP-IS:-Lo~~f Vit;I~;Au~ C~troI p-;;~~~~ir;t~~pe~atot ~-;;hedth~;tatus ~fTnst;~;I~em-chan-;~I~T~d 2:Jfth;;;-~h~~cls~ l~~t th;~p~r;~ ~~st- -

Iplace the control rods in manual and place the CF control valves in manual and restore S/G levels to program level.

1

~~~~~ ~~~cl:e<i~~atJ~ ~h~ llPl'li<:~n0~~qtli!-e~_t<l ~~~anllil~~i9~~hic~

ll1ll~~eJ:~~ ~~C()-'~tr~I~~_jJhll1~~llJ()S~ ~~\\li.tlll~S!r~~~tJ'us,-_________________ _

Answer A Discussion r:------------------------------------------------------------------------------------------ ------------

IIncorrect. Plausible if the applicant believes that MSIVs have closed or control of the plant has been lost and that tripping the reactor is necessary to place the plant in a safe condition.

j

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

---

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

---

~ ----

Answer B Discussion c- ------ -- -

---

-- - ----I IIncorrect. Plausible because these are actions that will be taken to restore plant conditions to normal. However, these are done later in AP-15 and are NOT immediate actions.

_ 1 L __________ ~

___________________________________________________________________________________________________________________ -.J Answer C Discussion E~~c:.~~ ____ --=--=-____ ~-_~~ ___ -_-_~-~~-_-_-_-_= __ -_-_-_-___ -_-_-_~ ____ _=_-_-_ _=_-_-__ _=__~ ____ -~~

-_~_-_-_=-~_=_ ___ ~_~-~== ______ -____ --____ ~~

~-_-_-_-_-_-_____ =~

-~-_-_~-

Answer 0 Discussion 1-----------------------------

---

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

---

~--- --- -

~---- -

IIncorrect. Plausible as there are actions later in AP-15 regarding the Pressurizer Pressure channel failure. However, they are not inunediate actions.

L ____

~ _______________________ ~

_____________ ~ _____________________ ~

~ _________

~ ____ ~ __

~ ________________________ _

---

- -- ---I

________.J

-~!;~i~~v~1!vel~ -~~

~~!tI~~~e.~I=~~~.:::~=_== = -=-== =

9-ties.!ion !~~! -=--= =-=-= =~.::: -=-.::: --=J 401-9 Comments RESPONSE Memory

_ 1__

BA_N_K __ ~__

_ _MN

__ S B_an_k Q_u_estio_n_AP1_50_02__

I Per Chief Examiner's comment, removed

~

reference to procedure (E-O) in distractor

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

. _________________ ~___

'A'. HCF 11104/09 l~~dent.. ~ferell.c.!s.P~... i~~ _____ _

~.!'... e!oJ>~~'!t-R!f!l'!IlCCt!.---- _______ _

IAP-15, Loss of Vital or Aux Control Power page 3, 6, i8, and 22 I

I I L _______________________________ _

I

--T.:--- --- -- ---,,----------------- ------------------- - ----- ----- -- ------ ------ ------ ---- -------1

~.!tI~!S~n.!< !#+~~sy~!Il'l_ L~,...'!.ufll~_ _ _

[ ~=<<!e~~-_-------------------------------------- ___________________ j 1851tPE057 IAA 1.06

---l iAbility to operate and 1 or monitor the following as they apply to the Loss of Vital AC Instrument Bus: (CFR 4 1.7 1 45.5 1 I,

--- ------ - ----- ___..L __ - - ------- -~ l~.6)LJM.~ull!~()l1!()l.<>fc()Il1p.<>~llt.s..fcJr.wEic;~a~t()mati.ccontl'O'!~lo~_"':'_" _______________________. _______ J ruesday, November 10, 2009 Page 127 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 52 lcJuestlonBa-nk# iKA_syste';~~number----llKA_desc ---- --- ~-- ~ - --------- - ------ --- --~-- -~---~-~ - ----------~--I r-- 1852 - APE058-r-_-AK3~o2 -~-1 [K~owl~g~~fth~ ~~~ns. f~th;f~k;wi~ ~spon;~-th;;yapPtytoth~ Lo-;;'~fDCPo~;-r:(EFR 4i-:S,4I~IOi4S:6!---~----l

- ---~----~------ ----~-----~------~1145.l)~ActlOns contamed m EOP for loss ofdc power.......................

~

,--~--~----.---- ---.- ----.-

---

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

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

CURRENT Given the following:

A loss of ALL AC power has occurred on Unit 1 Crew has implemented ECA 0.0 (Loss of All AC Power)

The crew is performing Enc 7 (DC Bus Alignment) of AP-07 (Loss of Electrical Power)

Which ONE (1) of the following completes the statements below?

Power must be restored to the battery chargers within ~.

The MAXIMUM DESIGN loads that the 125v DC Vital Batteries are designed to carry under emergency conditions with NO Essential AC available to the Vital Chargers is~.

A B.

C.

D.

(1) ONE hour (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters (1) ONE hour (2) Two(2) 125v DC Distribution Centers, Four (4) 125v DC Panel Boards, Four (4) 120v AC Static Inverters (1) 30 minutes (2) Two(2) 125v DC Distribution Centers, Four(4) 125v DC Panel Boards, Four(4) 120v AC Static Inverters (1) 30 minutes (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters APE058AK3.02 No comment at this time RF A 10/28/09 ruesday, November 10, 2009 45 DAY VERSION Given the following:

A loss of ALL AC power has occurred on Unit 1 Crew has implemented ECA 0.0 (Loss of All AC Power)

The crew is performing Enc 7 (DC Bus Alignment) of AP-07 (Loss of Electrical Power)

Power must be restored to the battery chargers within ---11L-.

The MAXIMUM DESIGN loads that the 125v DC Vital Batteries are designed to carry under emergency conditions with no Essential AC available to the Vital Chargers is~.

A B.

C.

D.

(1) ONE hour (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters (1) ONE hour (2) Two(2) 125v DC Distribution Centers, Four (4) 125v DC Panel Boards, Four (4) 120v AC Static Inverters (1) 30 minutes (2) Two(2) 125v DC Distribution Centers, Four(4) 125v DC Panel Boards, Four(4) 120vAC Static Inverters (1) 30 minutes (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters 0401*9 Comments:

Page 128 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 52 lcJuestlonBa-nk# iKA_syste';~~number----llKA_desc ---- --- ~-- ~ - --------- - ------ --- --~-- -~---~-~ - ----------~--I r-- 1852 - APE058-r-_-AK3~o2 -~-1 [K~owl~g~~fth~ ~~~ns. f~th;f~k;wi~ ~spon;~-th;;yapPtytoth~ Lo-;;'~fDCPo~;-r:(EFR 4i-:S,4I~IOi4S:6!---~----l

---

~--~--------~-----~----~142:!)~~~oE:s~()n~1I1ecl~iQPJ'or19~~f~SIJ~wer~

______ :--:~:--.:-::-:. _____ ~

_____ ~ ___ ~ ______________ ~~~~~

CURRENT 45 DAY VERSION Given the following:

A loss of ALL AC power has occurred on Unit 1 Crew has implemented ECA 0.0 (Loss of All AC Power)

The crew is performing Enc 7 (DC Bus Alignment) of AP-07 (Loss of Electrical Power)

Which ONE (1) of the following completes the statements below?

Power must be restored to the battery chargers within ~.

The MAXIMUM DESIGN loads that the 125v DC Vital Batteries are designed to carry under emergency conditions with NO Essential AC available to the Vital Chargers is~.

A B.

C.

D.

(1) ONE hour (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters (1) ONE hour (2) Two(2) 125v DC Distribution Centers, Four (4) 125v DC Panel Boards, Four (4) 120v AC Static Inverters (1) 30 minutes (2) Two(2) 125v DC Distribution Centers, Four(4) 125v DC Panel Boards, Four(4) 120v AC Static Inverters (1) 30 minutes (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters APE058AK3.02 No comment at this time RF A 10/28/09 ruesday, November 10, 2009 Given the following:

A loss of ALL AC power has occurred on Unit 1 Crew has implemented ECA 0.0 (Loss of All AC Power)

The crew is performing Enc 7 (DC Bus Alignment) of AP-07 (Loss of Electrical Power)

Power must be restored to the battery chargers within ---11L-.

The MAXIMUM DESIGN loads that the 125v DC Vital Batteries are designed to carry under emergency conditions with no Essential AC available to the Vital Chargers is~.

A B.

C.

D.

(1) ONE hour (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters (1) ONE hour (2) Two(2) 125v DC Distribution Centers, Four (4) 125v DC Panel Boards, Four (4) 120v AC Static Inverters (1) 30 minutes (2) Two(2) 125v DC Distribution Centers, Four(4) 125v DC Panel Boards, Four(4) 120vAC Static Inverters (1) 30 minutes (2) One (1) 125v DC Distribution Center, Two(2) 125v DC Panel Boards, Two (2) 120v AC Static Inverters 0401*9 Comments:

Page 128 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 52 General Discussion r;::-~-

~~-~--

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

~

~~ --

--~~ -

~-~---~-~

~~-~~~

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

~~~

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

-~-~----~--.~~~.,

IStep 24 ofECA 0.0 directs the crew to :align DC buses per AP-07. Enc 7 (DC bus Alignment). This step is preceded with a caution stating that it is time critical action. In a loss of all AC I

Iscenario, the station batteries are the only source of electrical power. The vital batteries are sized to supply (two DC buses which includes the two inverters and their panel boards), plus I

Isupply the loads of its sister distribution center (two DC buses which includes the two inverters and their panel boards), if required, for a period of one hour.

r I

I iKA is matched because the candidate must understand why the action directed in ECA 0.0 (Loss of all AC) Step 24 is time critical and what components are potentially affected should this I

lactions not be taken. This action is taken in order to preserve the DC power sources, our EOPs contain no actions that deal directly with a loss of DC power. Loss of DC power sources are I

l~d~~~~~\\\\fitl!~C.)~~s~tl!~b~s~~a.!(;~~-.!'0 E~~t~t~0lle ~~~~t~pre-,,~n~a -'-oss~!' ~C-.£{)\\\\'er~~ul"c~ ~~~lI>>(JJ}s}()f ~~~a~t~~:_ ~.~ ~_~ ~ ~~~ _~. ~_

~~ ~ __ ~ __ ~~J Answer A Discussion IPlausible: Answer 1 is correct,

~nswer 2 is plausible because the loads listed are the normal loads for a vital battery.

Answer B Discussion ICORREC-i ~~~~-~~~

-~~-

,_~ ~~~-~.~ -~-~~'~.'~~-. ~ -~~---~~ ---~

~ ~~-- ~~.-

Answer C Discussion

~~-~-I

_~~_J I~~--

~~

~

~~~~

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

~

---

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

~~~-

~-~-

~.~~-~-~~~~

~

LP~a~ib~:~3~~~~~~u~~)'CI~\\\\'~uld be~~~~f()I*s~Jl1e ~~o~

~t~e~~at~e~~~u~~~t~ose s~PRI~~~ll<:~D~~: A~wer 2 is plausible as explained above.

~- -

--~

~ --

~-

~. -.-~

~l I

Answer 0 Discussion r;--~~~~----~.----.~--~----~---~~.---~.-~~ -----~~~.----~-~-

lP!1llls~b!e~A~~\\\\'er~~s~~u~~I~ ~

=-x~I~J1e~_~o~~a~d ~~~\\V~ 2 is correct.

QuestiO;Type-'f-~-~~-~-

Question Source

-=_~~~~-~-=~1-=-~~~-~~_~~~~~~~~~-_____ -_-=-~=--____ =

____ =-=-=-____ -==- ~

_ ~~~.'!I!I"'e

~I:!'t'e_'_ __

Memory

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

[Development References I::~--~~-~~~~~~~'~--- -~ --~ --~~-~--~

ITechnical Reference(s): Lesson Plan OP-MC-EL-EPL, IRev. 23 Pg 25

[Learning Objective: OP-MC-EL-EPL, Obj 12 I

I I~-~----~-~

~'-'~~---'~~ ~~~--~- I IStu~.'!~

Re~renc~~~~"!<i!~~ _ ~~

~I I

I I

I I

I I

I I

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___ ~_~~ __ ~ __.~ _____ ~~~_i r: ---.~.~

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

~-~-

-~-

--'~~--',

~~ ___ ~~~J 401-9 Comments RESPONSE Per Chief Examiner's general comments, added WOOTP question. HCP 11104/09

~ -

--~-- - -

~K.~---~~~~~~

~~~~~~~~i5~~iE6r~~-1l1-1~3~~,,!f)!,. ~----

1t(A desc

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

IKnowledge of the reasons for the following responses as they apply to the Loss of DC Power: (CPR 41.5,41.10/45.61

_ ~._. ______ ~_~ I_.~.~~ _____ ~.~~ __ ~ ~ __ ~_.

l4~ D~~~i~~~()llt~i~e!iI1 EQ~f()r-'~~i~c-.p~~~~~ ~~~ ________ _

fuesday, November 10,2009 Page 129 of 185 FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 52 General Discussion r;::-~-

~~-~--

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

~

~~ --

--~~ -

~-~---~-~

~~-~~~

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

~~~

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

-~-~----~--.~~~.,

IStep 24 ofECA 0.0 directs the crew to :align DC buses per AP-07. Enc 7 (DC bus Alignment). This step is preceded with a caution stating that it is time critical action. In a loss of all AC I

Iscenario, the station batteries are the only source of electrical power. The vital batteries are sized to supply (two DC buses which includes the two inverters and their panel boards), plus I

Isupply the loads of its sister distribution center (two DC buses which includes the two inverters and their panel boards), if required, for a period of one hour.

r I

I iKA is matched because the candidate must understand why the action directed in ECA 0.0 (Loss of all AC) Step 24 is time critical and what components are potentially affected should this I lactions not be taken. This action is taken in order to preserve the DC power sources, our EOPs contain no actions that deal directly with a loss of DC power. Loss of DC power sources are I

l~d~~~~~\\\\fitl!~C.)~~s~tl!~b~s~~a.!(;~~-.!'0 E~~t~t~0lle ~~~~t~pre-,,~n~a -'-oss~!' ~C-.£{)\\\\'er~~ul"c~ ~~~lI>>(JJ}s}()f ~~~a~t~~:_ ~.~ ~_~ ~ ~~~ _~. ~_

~~ ~ __ ~ __ ~~J Answer A Discussion iPl;;~bl;~A~sw;;;:I~~;:;:e-;;t~-~ ~-~~- ~ -~---~~-~~-~-~~~- -~~--~~

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

~~~~-~---l

~~\\\\fe~~ i~e!atl~~~~alls~ !l!~I()a~Jistecl!!'~ tl!e~n(.)r~~ l~acls!~~ \\,itiil~a!f~1)'. ~. _

.. _~.~~~_~~~~.~.~ ~ ~.~~.~ __ ~ __ ~_ ~ ~ ~ ~~ _ ~.~ __ ~_~~ ___ ~ _ ~ ~ ~~

Answer B Discussion r~~~~T

~~=-~-====~~==~~~~~-=_-~~~~=~~-=~~_~~~=~-_________ ~=~ ______ ~ _____ -~ _____________________________________________ ~~~~~ ________ ~ ______________ ~_~-=-~_~ _____ ~~~ __________ J Answer C Discussion I~~--~~~~~~~-~-~~*~~~*~-~--~-~--~-~~----*-~-~~*~~~----~~~~.~~-~~~~~--~-~--~.~~-~-~~~~~~--~-~~-~~~.-.-~-~--~~

--~~~-*-~~l LP~a~ib~:~3~~~~~~u~~)'CI~\\\\,~uld be~~~~f()~s~Jl1e ~~o~ ~t~e~~at~e~~~u~~~t~ose s~PRI~~~ll<:~D~~: A~\\\\,e~ ~i~-,-ausible~ exp~~~ ~~:-~_~ ~~~~ ____ ~ ___ J Answer 0 Discussion 1,--

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

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

~.- -

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

-~-

~-------

~-

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

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

-~-

--.~~ --.,

[Plausible: Answer 1 is plausible as explained above and answer 2 is correct.

I

~ ______

~ ______

~ ________

~ __

~ ______

~ _____________________________ ~

________________________________________ ~

___________________________ ---.J

-~cognitlve-Cevel-~T~ QuestiO;Type-T-~-~~-~-~~-~QuestlO;}S~;:ce~~~~~~-~--~~l 401-9 Comments RESPONSE

--~.~ ~~.- --~- -~-- ~-t ~.~~-~.- -

~.-.--t-~~-~-.~.~.~~ -~~- -.~~---~-~.~ ~~ -

~

~.~ -~~-- ~

-.-~.~

Memory I

NEW I

I Per Chief Examiner's general comments,

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

~_.~-l added WOOTF question. HCF 11104/09

~ Developed fuesday, November 10,2009 Page 129 of 185

B FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 53 l~~~~~~~~~lKA-=Si~~~~':;'~~~=-=~=-J I~~e~~~_-==-===-=-=~=-=-~_-=~~ =-_==~_==========~=====-======~_====-=-------

I 1853 I

APE062 I

AAI.05 I [Ability to operate and lor monitor the following as they apply to the Loss of Nuclear Service Water (SWS): (CFR 41.7 1 45.51 L_. __ -

__ ~~_L_. _____ ~------- - -- -1~..0.lJ..!he CC~.§..s..uI"g~tank, in(;ludil1lL~v~~E.trol~J:~~al~fl!1~<lI1ci.rll:..diitti()Il...alal"l11.":.... ~..... :~"":".":.... ~:.... "".:.."".,,,.~ ___ ~ __ ~

CURRENT 45 DAY VERSION Given the following:

Due to air entrainment, both Unit 1 RN pumps were tripped The Unit 1 Reactor was tripped along with all NC pumps As a result of this transient, a leak developed associated with the 1A NC pump thermal barrier 1EMF-45A (Unit 1 Component Cooling A) is in Trip 2 KC Surge tank levels are increasing Which ONE (1) of the following best completes the statements below?

1KC-354B (A NC PUMP THERM BAR OTl T) will Auto Close at~.

1KC-122 (U-1 KC Surge Tank Vent Valve)~.

A (1) 50 GPM (2) must be re-opened from the local Control Station B.

(1) 50 GPM (2) will re-open when the EMF signal clears C.

(1) 70 GPM (2) must be re-opened from the local Control Station D.

(1) 70 GPM (2) will re-open when the EMF signal clears APE062AAI.05 Given the following:

Due to air entrainment, both Unit 1 RN pumps were tripped The Unit 1 Reactor was tripped along with all NC pumps As a result of this transient, a leak developed associated with the 1 A NC pump thermal barrier 1EMF45A (Unit 1 Component Cooling A) is in Trip 2 KC Surge tank levels are increasing 1 KC-364B (A NC PUMP THERM BAR OnT) will Auto Close at---.i1L.

1KC-122 (U-1 KC Surge Tank Vent Valve)-.0 Which ONE (1) of the following best completes the statements above?

A.

(1) 50 GPM (2) must be re-opened at the local Control Station B.

(1) 60 GPM (2) will re-open when the EMF signal clears C.

(1) 70 GPM (2) must be re-opened at the local Control Station D.

(1) 70 GPM (2) will re-open when the EMF signal clears 401-9 Comments; Reverse the WOOTF statement and put it up front.

Tuesday, November 10,2009 The discussion (distracter analysis) does not line up with the Q. Please re-evaluate. However, the reference does support the correct answer.

RF A 10/28/09 Page 130 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 53 CURRENT Given the following:

Due to air entrainment, both Unit 1 RN pumps were tripped The Unit 1 Reactor was tripped along with all NC pumps As a result of this transient, a leak developed associated with the 1A NC pump thermal barrier 1EMF-45A (Unit 1 Component Cooling A) is in Trip 2 KC Surge tank levels are increasing Which ONE (1) of the following best completes the statements below?

1KC-354B (A NC PUMP THERM BAR OTl T) will Auto Close at~.

1KC-122 (U-1 KC Surge Tank Vent Valve)~.

A (1) 50 GPM (2) must be re-opened from the local Control Station B.

(1) 50 GPM (2) will re-open when the EMF signal clears C.

(1) 70 GPM (2) must be re-opened from the local Control Station D.

(1) 70 GPM (2) will re-open when the EMF signal clears APE062AAI.05 45 DAY VERSION Given the following:

Due to air entrainment, both Unit 1 RN pumps were tripped The Unit 1 Reactor was tripped along with all NC pumps As a result of this transient, a leak developed associated with the 1 A NC pump thermal barrier 1EMF45A (Unit 1 Component Cooling A) is in Trip 2 KC Surge tank levels are increasing 1 KC-364B (A NC PUMP THERM BAR OnT) will Auto Close at---.i1L.

1KC-122 (U-1 KC Surge Tank Vent Valve)

(2)

Which ONE (1) of the following best completes the statements above?

A.

(1) 50 GPM (2) must be re-opened at the local Control Station B.

(1) 60 GPM (2) will re-open when the EMF signal clears C.

(1) 70 GPM (2) must be re-opened at the local Control Station D.

(1) 70 GPM (2) will re-open when the EMF signal clears 401-9 Comments; Reverse the WOOTF statement and put it up front.

Tuesday, November 10,2009 The discussion (distracter analysis) does not line up with the Q. Please re-evaluate. However, the reference does support the correct answer.

RF A 10/28/09 Page 130 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 53 B

General Discussion INCP Th~~;)Barrk=rjsol;rt~; valves (KC-345, 364, 394, & 413) will automatically close to isolate the thermal barrier on high flow (60 GPM) which is indicative of a ruptured thermal Ibarrier.

I IThe KC Surge Tank Vent valve, which is normally open, will receive a close signal on an EMF-46A and B alarm. However, the 'OPEN' position is latched in such that the valve will (automaticallY reopen when the signal clears.

iKA is matched because the situation described in the stem represents a loss of Nuclear Service Water concerning the CCWS (KC) system. The candidate must demonstrate knowledge of lassociated KC system level alarms and then demonstrate the ability to monitor a level change by the use of the associated tank curve.

I IThis is a comprehension level question because the candidate must demonstrate the ability to use a tank curve in solving a problem whose parameters are set up in the stem of the question.

i!:I~ ~ust also ~Ild~st~<!!Il<l~Ilt:_as~o~i1l!e~ ~ll~cllf~e ~n2~<J>r_e~Il!~0~~ £t~e J\\\\'O~~lllP~rt~n~l~v~~aIl<!!ller~t()r~

f!ll!~ ~olltJIeJIlt:~~lts~o_o~.iti~ tlle~()/"f~c~<lI1s-""'t:I". _______ _

Answer A Discussion r~~~~t~ Pl~~ble b~a~~~P~rtlis~~;ct~P~rt2i;plau;hl~-b~~~etht:;;;;r~~h~rin-;t;~~e-;;h~r~~ is-;l~i~n th~ ~ccurs on a high EMF alarm must be manually restarted after the

[a'--arm ~1~aJ"s J.i..~:_W~t:~ftS _R:~I~a~L ______________ _

-,------ ~--- -

Answer B Discussion r;:-----.--.- ---.-.---

CORRECT.

l ______. ____. __

Answer C Discussion J -.--.--

IIncorrect. Part I is plausible because 70 GPM is close to the actual setpoint of 60 GPM. Part 2 is plausible because other isolations that occurs on a high EMF alarm must be manually

~~tit.rted afte! Q1~al~_c~ilfs Ji.e... ~<l.S~ Q.a.s..~tieClS~L __ _

Answer 0 Discussion Iin~orr~ct.Part I is plausible because 70 GPM is close to the actual setpoint of 60 GPM. Part 2 is correct.

1_- __________________________. ___

,-L.... ()b_l-.evei RO---

---

~--I 401-9 Comments RESPONSE

---

l ~oved WOOTF statement to before the fill III the blank statements. Also, corrected

,--------*-------*_--*-*----*---------l '-.----.--~----------

~"!!'!,()p.!!'.!rl.t...R!l'!'!lfl.C::.!!._ _ _ _______

lS.!~!f1.t B~~.!nc!.! Provided distractor analysis to match question.

Original discussion was for previous version of question. HCF 11104109

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved ITechnical Reference(s): OP-MC-PSS-KC Rev 25 Pg 21 I

land 23 123 I

iLeaming Objective: OP-MC-PSS-KC Obj. 5

! I I

1 I

_. __________________________. _____.1 L. __

- ------ - - -- -------- ------*l r*- ------- - ----

~~s.!i<>>..nBa~~5~i~E~~f!~t~I~~~!... ----~ r~li~~~pe~te-;;i! ~r~~rtit-;rthe folIo-;i~g ;;;tlJ~~ppiY t;;"th~L~~fNuclear Service Water (SWS): (CFR 4 I.7 / 45.5/

.L. ____ -

--- J II'!?jlilTlleS~~~~urge!.llll..Is.i~clllc!i~-'e."'~~o.lltl"O'_a.ll.<iJ~~llllll1llS_'_<lI1ti..rad~ti0.ll~~ ________________ _

Tuesday, November 10,2009 Page 131 of 185 FOR REVIEW ONLY - DO B

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 53 General Discussion INCP Thennal Barrier isolation valves (KC-345, 364, 394, & 413) will automatically close to isolate the thennal barrier on high flow (60 GPM) which is indicative of a ruptured thennal Ibarrier.

I IThe KC Surge Tank Vent valve, which is nonnally open, will receive a close signal on an EMF-46A and B alann. However, the 'OPEN' position is latched in such that the valve will (automaticallY reopen when the signal clears.

iKA is matched because the situation described in the stem represents a loss of Nuclear Service Water concerning the CCWS (KC) system. The candidate must demonstrate knowledge of lassociated KC system level alanns and then demonstrate the ability to monitor a level change by the use of the associated tank curve.

I IThis is a comprehension level question because the candidate must demonstrate the ability to use a tank curve in solving a problem whose parameters are set up in the stem of the question.

i!:I~ ~ust also ~Ild~st~<!!Il<l~Ilt:_as~o~i1l!e~ ~ll~cllf~e ~n2~<J>r_e~Il!~0~~ £t~e J\\\\'O~~lllP~rt~n~l~v~~aIl<!!ller~t:t()r~

f!ll!~ ~olltJIeJIlt:~~lts~o_o~~iti~ tlle~()/"f~c~aIls\\\\'t:I". _______ _

Answer A Discussion r;:~---~- - - --- -

~-

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

---

~---~

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

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

---

~-

jlncorrect. Plausible because Part 1 is correct. Part 2 is plausible because there are other instances where an isolation that occurs on a high EMF alann must be manually restarted after the I

[a~arm ~1~aJ"s Q.~:_W~~.QftS_R:~It:a~L_~_~ _______________________________________________________________ ~~ _____ ~ __ J Answer B Discussion E~~~~-_-_-=~~-_-_-_-~-_-_-_=__-_-_=_=__= ~-~--==-_=__=_-_-_=_=__=_~-_=_-~~=-_=-_= ___ ~-_=__-_=_ -==-_______ --= __

-_=_-=--=-=~=__-_~=__-_-_=__-____ -_=-_~_=__=__=__== ___ --=--=_=__=_ _=__=-=-J Answer C Discussion rI:;;c-;~ect.-P~rt-li~pL;~ibl~-i;~~~70GPM i;~I~~t;th~~t~alsctpointof60-GPM~P~2i;-Pi~~sibk b~~~-; other~~I~~ ili~;-cZ;;s ~~highEMF

~;_nn ;~tb~ ~an~iiY ----I Irestarted after the alarm clears (i.e. Waste Gas Release).

I L-, ______.. ________

~_. __ " ___

.~_

~ __________

~ ____

~

~

~ ____

~ __________________

~

Answer 0 Discussion fIn~orr~ct.Partlj;pl~-~;Jbl~-b~c;_~-70GPMi_;cl~-t~the-~_;;_t~!;ct~~t of60GPM:-p~2is--;;;~ct.----- - --~----- ---- ------------ -- -~-----,

I ___

~ __________________________________

~

~~

~ ____________ J

[JobLeV&l-l---CognltlveLevel---rQ"l.estlonTYp~-!-------------QueStlOnSourc;--- ----------1 401-9 Comments RESPONSE

-~ ----~----"- -

-~-~-~~~~ - -- ~~- -t- --~--~-----

I--~-~-~--~- -

-~~ -- -~-~- -~-~~---~-~~-~ - - ----- --~-1

! ____ IZ? __ L~ __ C~lllP~e~~_~()I1 ____ L ____ N~~ ___ J ____________________________________ I Moved WOOTF statement to before the fill in the blank statements. Also, corrected

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Tuesday, November 10,2009

,-----------------------------------------l IDevelopment References

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

---

~-~-

ITechnical Reference(s): OP-MC-PSS-KC Rev 25 Pg 21 land 23 123 iLeaming Objective: OP-MC-PSS-KC Obj. 5 I

I

~~----~-----~------ ~---- ----~-----.I Page 131 of 185 distractor analysis to match question.

Original discussion was for previous version of question. HCF 11/04109

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE B

QUESTION 53 ruesday, November 10, 2009 Page 132 of 185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 53 DISTRIBUTE B

ruesday, November 10, 2009 Page 132 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 54 r

-~-~-~ -

---~--~-~-----~~~----~------- ---1 c~---~ --------

-~-

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

QuestionBank IIIKA system

[KA number IKA desc

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

F--1854---r-WE04~ -i-=--~E~K22----j rK;~edg~~iili~~te--;:;:cla~~~tween the (LOCA Outside L_ -

-- -- ------- - ---------- ~_--1 IContainment) and the following:

CURRENT I(CFR: 41.7 ! 45.7)UFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, land relations between the proper operation of these systems to the operation of the facility.

L __

,_~,_, ___________

~ ______________________

~ ________

~ _____________ _

45 DAY VERSION Unit 1 was operating at 100%. Given the following events and conditions:

Unit 1 was operating at 100%. Given the following events and conditions:

0210 - reactor tripped due to a LOCA 0300 - crew enters ECA-1.2, (LOCA Outside Containment) 0340 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc) 0350 - The crew is at step 21.b of ECA-1.1 Current conditions:

o 1B NC pump running, all other NC pumps secured o 1A NI pump is running, indicating 310 GPM o Both NV pumps are running, indicating 300 GPM o Both NO pumps off o Subcooling is 35°F Which ONE (1) of the following describes the MINIMUM SI flow required and the required actions (if any)?

REFERENCE PROVIDED A

Minimum flow required is 305 GPM, stop both NV pumps.

B.

Minimum flow required is 315 GPM, stop one NV pump.

C.

Minimum flow required is 305 GPM, stop the running NI pump.

O.

Minimum flow required is 315 GPM, no pumps can be stopped at this time.

WE04EK2.2 0210 - reactor tripped due to a LOCA outside containment 0220 - crew enters ECA-1.2, (LOCA Outside Containment) 0230 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc) 0250 - The crew is at step 21.b of ECA-1.1 Current conditions:

o 1B NC pump running, all other NC pumps secured o 1 NI pump running, indicating 220 GPM o 1 NV pump running, indicating 385 GPM o Both NO pumps off o Subcooling is 35°F Which ONE (1) of the following describes the MINIMUM SI flow required and the required actions (if any)?

A.

B.

C.

REFERENCE PRQVIDED Minimum flow required is 408 GPM, stop the running NI pump.

Minimum flow required is 380 GPM, stop the running NI pump.

Minimum flow required is 408 GPM, neither pump may be secured at this time.

O.

Minimum flow required is 380 GPM, neither pump may be secured at this time.

401-9 Comments:

If the graph wasn't marked then I would agree with the distracter analysis for distracters Band D. However, since the graph is incrementally marked, it is not possible to misread it on the horizontal axis. Therefore, 380 GPM is not plausible.

ruesday, November 10, 2009 Page 133 of185 A

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 54 rQueStlonB;nk-ilKA~syStem~1KA=-number~~~--~lIKA~deSc~~~~~-~ ~-~~-~~~~~~~=~-=~=~~======::::=::::::::=-=--=-=====-===::::~~~~~~~

F~~1854~~~r~WE04- - i-~--E-K22~ ~~~j rK;~edg~-;;-iili-;;~te~cla~~~t;~~~the(LOCA o;tsid~~ -

L~ ~

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

~ ~-~~--~-~- _~-1 IContainment) and the following:

CURRENT I(CFR: 41.7 ! 45.7)UFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, land relations between the proper operation of these systems to the operation of the facility.

L _~_~~_~_~~~

__ ~_ ~

__ ~.~ ~~~~

~~~~.~_.~_~_~~~~~

__ ~~._~

~~ ___ ~.~~~_~

__ ~

. __ ~ __ ~~ ___ _

45 DAY VERSION Unit 1 was operating at 100%. Given the following events and conditions:

Unit 1 was operating at 100%. Given the following events and conditions:

0210 - reactor tripped due to a LOCA 0300 - crew enters ECA-1.2, (LOCA Outside Containment) 0340 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc) 0350 - The crew is at step 21.b of ECA-1.1 Current conditions:

o 1B NC pump running, all other NC pumps secured o 1A NI pump is running, indicating 310 GPM o Both NV pumps are running, indicating 300 GPM o Both NO pumps off o Subcooling is 35°F Which ONE (1) of the following describes the MINIMUM SI flow required and the required actions (if any)?

REFERENCE PROVIDED A

Minimum flow required is 305 GPM, stop both NV pumps.

B.

Minimum flow required is 315 GPM, stop one NV pump.

C.

Minimum flow required is 305 GPM, stop the running NI pump.

O.

Minimum flow required is 315 GPM, no pumps can be stopped at this time.

WE04EK2.2 0210 - reactor tripped due to a LOCA outside containment 0220 - crew enters ECA-1.2, (LOCA Outside Containment) 0230 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc) 0250 - The crew is at step 21.b of ECA-1.1 Current conditions:

o 1B NC pump running, all other NC pumps secured o 1 NI pump running, indicating 220 GPM o 1 NV pump running, indicating 385 GPM o Both NO pumps off o Subcooling is 35°F Which ONE (1) of the following describes the MINIMUM SI flow required and the required actions (if any)?

A.

B.

C.

REFERENCE PRQVIDED Minimum flow required is 408 GPM, stop the running NI pump.

Minimum flow required is 380 GPM, stop the running NI pump.

Minimum flow required is 408 GPM, neither pump may be secured at this time.

O.

Minimum flow required is 380 GPM, neither pump may be secured at this time.

401-9 Comments:

If the graph wasn't marked then I would agree with the distracter analysis for distracters Band D. However, since the graph is incrementally marked, it is not possible to misread it on the horizontal axis. Therefore, 380 GPM is not plausible.

ruesday, November 10, 2009 Page 133 of185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 54 A

General Discussion I do not have a suggested fix for this problem unless you can provide a curve that doesn't have the 2-9 incremental markings.

This Q is U because 2 distracters are not plausible.

RF A 10/28/09

~im~~-;;;trip~1 OO~~tes, which makes the required flow 305 GPM.

I ISince the minimum flow required is 305 gpm and the flow from the running NI pump is 310 GPM, both running NY pumps should be secured.

I lIt is a difficult KIA match to relate ECA-I.2 (LOCA Outside Containment) to the facility's heat removal systems. To match this KIA initial conditions were given which placed the plant in IECA-l.2 and then a transition to ECA-I.I (Loss of Emergency Coolant Recirc) was made. A transition to ECA-I.I from ECA-I.2 is a possible flow path based on plant conditions.

I

!IhJsJs~a~iln~ISi~ ~u.~stio~as ~~ app~~~~~till~erp~etJ1~~fll~hlr()~ ~~I()S~r~~ilIl~tllen d~~~~ Jf ~~a~ty !J1j~~~np~np~ilIl ~e~tI:>lP~~'_~ ~_ ~ __ ~ ___ _

Answer A Discussion ICORREci--

---

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

L __. _______ _

An8wer B Discussion

,~~.----.. ---.--.--

---

.-~.--

--.~---

-~

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

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

---

~-~.~--

---

.--~.---~.-

-~~--~-~--.--~.-,

IIncorrect: Plausible if the applicant uses the time from the trip to the time of ECA-I.I entry or makes a math error calculating the time after the trip. If so, a required flow of 315 GPM would I l~...c>bt~necl.. aI1c1..s.!.0E.Pi..~J~~.Eu~~()Illd _~c.9fJ'e~-,--- _~ ____ ~

I Answer C Discussion r;:-'--~'---'--------'---~---'---~~'-~'-~---~--'----'--~----~-~.-------~-.-.-------------~.---~---~-

IIncorrect. Plausible if the applicant reads the part of the procedure step which directs stopping a Safety Injection pump but misses the part regarding "while maintaining flow above minimum

~<:9.tI.ired" ___ 1'Il.~ ~il~iI111:,m~ flo~~"<:0.E"~ct._. _____ ~_

Answer 0 Discussion ii;;-~-;;:;:-ect:-PI~~~ibkiffu~ appiic~t~;-c;-I~/;;s-the~~~ired flow as previously described the applicant could determine 315 GPM. Since neither of the individual flows is greater than 315

!Q.r..M--,tll~a2E.Iic:ant~_()uJd~b~I~~.!.hlltl1~IJ..Ump.s..<:~.Qe..st<JIJP~<!-.~ _. __. ____ ~~. ___.~. _____ ~ __ ~. __. ____ ~ ___ ~ _.~. __ ~ ___ ~ _~ _____ ~ _______ ~_~_~~,

-.-.~---,-.------ ---- ---- -----T-*- ---- ----- -- ----,---

Cognitive Level

[Quest/onType [

Question Source

[ 401-9 Comments RESPONSE

-~----.

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

1-----~*-~ -.-~ - --- -~----.--~.-

__ C~~jJf~h~n~i()n~~_ J ____ B~~~ ____ L_~ _______ CNS NRC Exam Bank Question 521 Per Chief Examiner's comment, completely revised question such that all distractors are

~------~---~~-- ---~-- -~--~- __ ~I I~~-- --~--- -----~~ -~-~ now plausible. HCF 11104109

--~--i

~j

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~~e~e~cp~~t_ R~!e~~~ __ ~ __ ~_~~ _____ ~ ~tU<f.!."!'!tt!!..renc~.!=l!o~l<<:I~cI.. __ _

[Lesson Plan Objective: EP-EP2 SEQ 29

! !EP/Il Al50001ECA-I.l (Step 21)

[

References:

I iEP/l/Al5000IECA-1.l (Enclosure 9)

11. ECA-l.I step 21 and Encl 9 - PROVIDED

\\ I(Q54)

\\

I [

I

[ I L~ __ ~

_____ ~ ________ ~ ~~_~ ___ J L_

i~~~~~a~)]KA~!y~~e.tlt~-lt§\\_il~';ber-----

r--

-.~ --.-- -'- -~

~-- -

-~

-~.~

---

.-~-- ----

-~~----

---

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

~.--

IKA_desc rv------------~~--

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

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

---

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

1854[WE04 IEK2.2

___________ -----1 _____ ~ ______ 1 ____________ _

ruesday, November 10, 2009 IKnowledge of the interrelations between the (LOCA Outside

[Containment) and the following:

I(CFR: 41.7 1 45.7):'lFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal L ______ ~~~

__ ~ _____. _______. ___

._~_._~. ________ ~_._. ______ ~

.~ __ ~~_~

Page 134 of 185 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 54 A

General Discussion I do not have a suggested fix for this problem unless you can provide a curve that doesn't have the 2-9 incremental markings.

This Q is U because 2 distracters are not plausible.

RF A 10/28/09

~im~~~;:trip~100~~~~~k:hm~~th~~~ir~n;;-w305-GPM~~~~-~~---~-~----~-~-----~-~--~---------------~~~~---~

I ISince the minimum flow required is 305 gpm and the flow from the running NI pump is 310 GPM, both running NY pumps should be secured.

I lIt is a difficult KIA match to relate ECA-I.2 (LOCA Outside Containment) to the facility's heat removal systems. To match this KIA initial conditions were given which placed the plant in IECA-l.2 and then a transition to ECA-I.I (Loss of Emergency Coolant Recirc) was made. A transition to ECA-I.I from ECA-I.2 is a possible flow path based on plant conditions.

I

!IhJsJs~a~iln~ISi~ ~u.~stio~as ~~ app~~~~~till~erp~etJ1~~fll~hlr()~ ~~I()S~r~~ilIl~tllen d~~~~ Jf ~~a~ty !J1j~~~np~np~ilIl ~e~tI:>lP~~' __ ~ ____ ~~ ______ ~

Answer A Discussion

~~~~I========~==================-=================~========~====~======~.======-======J An8wer B Discussion

,--.---~

.. ---.--.-~

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

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

---

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

~-~------~.---.-,

IIncorrect: Plausible if the applicant uses the time from the trip to the time of ECA-I.I entry or makes a math error calculating the time after the trip. If so, a required flow of 315 GPM would I l~...c>bt~necl.. aI1c1..s.!.0E.Pl~J~~.Eu~~()Illd ~~c.9fJ'e~-,--- _~_~ __ ~ ~ __ ~ ~_~_~~ ~_ ~ __ ~~ ___ ~ ______ ~ __ ~ ~ __ ~ ~. ~~_~ _~ _____ ~_~ __ ~_~ _____ 1 Answer C Discussion r;:-'--~'~-~---

-~-~- -.~

~-~ -~

~'--- -

~.~ -.-~

~ ---

~

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

~ -

---

~- ~---~-~

--~-~.-.-

IIncorrect. Plausible if the applicant reads the part of the procedure step which directs stopping a Safety Injection pump but misses the part regarding "while maintaining flow above minimum !

~<:9.tI.ired" ___ 1'Il.~~il~iI111:'m_flo~~.<:0.E"~ct._._~ ___ ~_~ ____ ~~~_~ __ ~._~. ___ ~ ___ ~ ___.~.~ _______ ~~ __ ~ __ ~ __ ~. ______ ~_~.. _~_~_~ _____ j Answer 0 Discussion

,.--~--~.--~-~-~--~----~--~~~---~-.-~.~----.~-~~.-.~.-~~-~--~-~~---~--~-~-------~-~-~-~---~-------~----~~-~------~-----l IIncorrect. Plausible if the applicant miscalculates the required flow as previously described the applicant could determine 315 GPM. Since neither of the individual flows is greater than 315 I

!Q.P..M--'tll~a.PE.Iic:ant~_()uJd_b~I~~.!.hlltl1~£.ump.s.<:~.Qe..st<JIJP~<!-. ___ ~ ~_~~ __ ~_. __ ~ ___ ~~ ~_~~ __ ~ _____ ~ ___ ~~ ___. ______ ~ _________________ ~_~ __ I

---

---- ---- -----T--- ---- ----- -- ----,------------------------------------------------

---

~

Cognitive Level

[Quest/onType [

Question Source

[ 401-9 Comments RESPONSE

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

~-~-- ~-~ 1-----~--~ ~-~- ~ --~

-~-------------~---~ --~ -- ~ ~-~.~ i Comprehension BANK I

CNS NRC Exam Bank Question 521 i Per Chief Examiner's comment, completely

- ~ - --~~ ~_~_~_~~J~ ~ ~- ~ ~---~-~-~- -~-~-~~-~.~-------~---~--~--~-~--~-~--~ revised question such that all distractors are

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved now plausible. HCF 11104109

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

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~~e~e~cp~~t-R~!e~~~ ___ ~ _ ~ __ ~ ___ ~.~ ~tu<!!."!'!tt!!..renc~~!o~l<<1.!cI.. __ _

[Lesson Plan Objective: EP-EP2 SEQ 29 I !EP/Il Al50001ECA-I.l (Step 21)

[

References:

I iEP/l/Al5000IECA-1.l (Enclosure 9)

11. ECA-l.I step 21 and Encl 9 - PROVIDED I I(Q54)

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It' nhte~elllati~ns between the (LOCA Outside

[ on ammen an e 10 owmg:

I(CFR: 41.7 1 45.7):'lFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal L ___ ~ ___

~~ _____ ~_~ __ ~ ____ ~ _____ ~~_._~ __ ~_~ _______ ~ ___________.~~~_~_~

ruesday, November 10, 2009 Page 134 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 54

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2009 RO NRC Retake Examination QUESTION 54

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th~ ~cili!y ____ ~ ___ ~ ____ ~_ j ruesday, November 10, 2009 Page 135 ofl85

B FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 55

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i(CFR: 41.71 45.7)lJComponents, and functions of control and safety systems, including instrumentation, signals, interlocks, failure Iillodes, and automatic and manual features.

c _____________ ~ _______ _

CURRENT Unit 2 was operating at 100% power. Given the following:

A S/G has faulted inside Containment Containment pressure peaked at 3.1 PSIG and is now 2.7 PS IG and slowly decreasing The crew has implemented FR-H.1 (Response to Loss of Secondary Heat Sink)

All CA flow has been lost Which ONE (1) of the following completes the statements below?

A.

B.

C.

D.

1) The NEXT source of feed water that FR-H.1 will prioritize for restoration of flow to the S/Gs is through the CM/CF system using ~?

2) Based on S/G conditions, the crew would be required to establish bleed and feed when WIR level in at least 3 S/Gs is less than ~?

1) a Main Feed Water pump

2) 24%

1) a Main Feed Water pump

2) 36%

1) Hotwell and Booster pumps

2) 24%

1) Hotwell and Booster pumps

2) 36%

WE05EK2.!

45 DAY VERSION Given the following conditions on Unit 1 :

A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA Both MD CA pumps and the TO CA pump failed to start and attempts to restore them have been unsuccessful FR-H.1 (Response to Loss of Secondary Heat Sink) has been implemented I&E has been dispatched to block the Feedwater Isolation in accordance with FR-H.1, Enclosure 6 (Feedwater Isolation Override)

Which ONE (1) of the following describes the required actions to regain control of CF pumps in accordance with FR H.1?

A.

Block the Feedwater Isolation ONLY B.

Block the Feedwater Isolation AND Reset Phase A C.

Block the Feedwater Isolation AND Reset the Sequencers D.

Block the Feedwater Isolation AND Reset SI 401-9 Comments:

It is common knowledge that an SI signal isolates FW and that FW cannot be regained until SI has been reset.

This Q is U because it has no DV.

RF A 10128/09 Tuesday, November 10, 2009 Page 136 of 185 B

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 55 iQ~stiOIlBank#TKA-sy;tem-IKA-;umber-rl~~~~£=--=============-======-================================--

r--~--- ----+--= -------r--=------

I ___ ~ 8~~ ___

W_E~~ __ I__

EK2.1 IKnowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

_________ -1 i(CFR: 41.71 45.7)lJComponents, and functions of control and safety systems, including instrumentation, signals, interlocks, failure IInJ)d~~~~lll1~I11ii!i~ aIl~man~If~tllr~~ ____________________________________________________ _

CURRENT Unit 2 was operating at 100% power. Given the following:

A S/G has faulted inside Containment Containment pressure peaked at 3.1 PSIG and is now 2.7 PS IG and slowly decreasing The crew has implemented FR-H.1 (Response to Loss of Secondary Heat Sink)

All CA flow has been lost Which ONE (1) of the foHowing completes the statements below?

A B.

C.

D.

1) The NEXT source of feed water that FR-H.1 will prioritize for restoration of flow to the S/Gs is through the CM/CF system using ~?

2) Based on S/G conditions, the crew would be required to establish bleed and feed when WIR level in at least 3 S/Gs is less than ~?

1) a Main Feed Water pump

2) 24%

1) a Main Feed Water pump

2) 36%

1) Hotwell and Booster pumps

2) 24%

1) Hotwell and Booster pumps

2) 36%

WE05EK2.1 45 DAY VERSION Given the following conditions on Unit 1 :

A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA Both MD CA pumps and the TO CA pump failed to start and attempts to restore them have been unsuccessful FR-H.1 (Response to Loss of Secondary Heat Sink) has been implemented I&E has been dispatched to block the Feedwater Isolation in accordance with FR-H.1, Enclosure 6 (Feedwater Isolation Override)

Which ONE (1) of the foHowing describes the required actions to regain control of CF pumps in accordance with FR H.1?

A.

Block the Feedwater Isolation ONLY B.

Block the Feedwater Isolation AND Reset Phase A C.

Block the Feedwater Isolation AND Reset the Sequencers D.

Block the Feedwater Isolation AND Reset SI 401-9 Comments:

It is common knowledge that an SI signal isolates FW and that FW cannot be regained until SI has been reset.

This Q is U because it has no DV.

RF A 10128/09 Tuesday, November 10, 2009 Page 136 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 55 General Discussion

T~~gain ~ontrcl~CF ~~~p;n_;;rrts~fte-;: ;n~SI,th~ Si~;-st b_;;~e;t ~d~

NORMAllY t~-;~~cto-;: trip break~~s~~uldbe~Io;d.The~eq~~~~r~ ~e~~etbyp~du~ b;n;ot~~~d to--:

[restore control to the CF components. During performance of FR-H.I, the reactor trip breakers are NOT closed. Instead the Feedwater Isolation signal is overridden.

[

1 I

IThis KA is match because the applicant must have knowledge of the interlocks which must be met to restore CF flow during a Loss of Secondary Heat Sink scenario.

I I

I

[Question is comprehensive because the candidate must evaluate a given plant scenario and apply that assessment to determine what must be done (How) to reset a safety signal. These actions I Icould be different depending on plant conditions so this is above just straight recall for system knowledge.

1 I_.~ ___ ~.~.~ _. __._.~. _____._~ ____ ~ ______ ~._.~._~~_. ___ ~ ____ ~_~~

___. ___________ ~ __

._~ __ ~_~~ ____________.. __ ~._._._~._ ~~.~._~.J Answer A Discussion r;'-'-'-~--- -.-

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[Incorrect. Plausible because using a CF pump is correct and 24% would be correct if Adverse Containment condition numbers were not in effect.

---I

____ J

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Answer B Discussion l~~0=

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Answer C Discussion ifuZ~~tPl;u';;bkb~~~;the~H~hvclla-;;-d-B~-;;-stt;~~~p;-;;-o~idbe-u~;difS/G~~~fir;td~~~-;;;zed.H~w_;;~~they-;~~t~~~~-;~de;-~pri~ritY.Al-;'-:-i4O/~~otiliib~Zo;;~tif-

~dverse Containment condition numbers were not in effect.

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

Answer 0 Discussion

!fuco;;:~;;t~Pi~~~e~b~;;;u_;;the-Hotw~ll;nd Bo~ie-;:-Pu~p-;~ldb;u-;edifS/G~-;;~fir;td~;~~~~H;;~~Zthey -;-re ~ot ~_;;~ in-;rde-;: ;;fprlority. Also, 36% is correct.

L ________

~ _______ ~

~ ____________________ _

\\--.. -.~--,-.-.--

--~--~*~~-*-,*---*--*----T~------~-*--*-**-*---------~------*--~*---~-*l I_..J~_I:!.!~_II- _~ ~ogn'!l.!~ L.~v!'----4-~.lI.!!!i~n.IlP...!--+- _____ ~ ____ ~ ___.9.lJ~8tl~'!...~~I".C.!.-~-~ _______ -~i ~1-9 Co~ments RES~ONSE 1

RO

...1 __ ~~p.:ehen~l~n ___ J __ ~_~~~~~~_ L _____ ~_~5_N~~~~I:.~~Ban~~l!e.:tI~I~~8_~ ____ ~_ J ~~:;;~:g :~hD~I~~;C:a~~n;~~;~::ent

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

---

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---

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'-'~'------'--'---~~'---'-'-'---,

lQ!v.!~e'l'l.~'!! ~!!~'!.c!.!.. _;_ -:- ~ ____ ~_~_~ ~~tll...~'!.t...~~.I"&.'l~-".!;)~!Ic:t!.d- __ --J ILesson Plan OP-MC-CF-CF Objective 12 pages 35 and 1 i i

137 I 1 I

IFR-H.I pages 9 & 10 II

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I 1

I 1

1 1

I I I I

L __

.~. __ '_.' ___ ~_~

__._~.~_~.

_______ ~

__ I L_

Isolation is being blocked instead of being reset (normal method), regaining control of the CF pumps is not as straight forward as it may seem. Will discuss with Chief Examiner.

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

I(CFR: 41.7 I 45.7) 0 Components, and functIOns of control and safety systems, mcludmg mstrumentatlOn, signals, mterlocks, I

Ifailure modes, and automatic and manual features.

I L ___

~ ___________

~ _______________________. _________________________________________ _

ruesday, November 10, 2009 Page 137 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 55 General Discussion

T~~gain ~ontrcl~CF ~~~p;n_;;rrts~fte_;: ;n~SI,th~ Si~;-st b_;;~e;t ~d~ NORMAllY t~-;~~cto-;: trip break~~s~~uldbe~Io;d.The~eq~~~~r~ ~e~~etbyp~du~ b;n;ot~~~d to--:

Irestore control to the CF components. During performance of FR-H.I, the reactor trip breakers are NOT closed. Instead the Feedwater Isolation signal is overridden.

I 1

I IThis KA is match because the applicant must have knowledge of the interlocks which must be met to restore CF flow during a Loss of Secondary Heat Sink scenario.

I I

I IQuestion is comprehensive because the candidate must evaluate a given plant scenario and apply that assessment to determine what must be done (How) to reset a safety signal. These actions I Icould be different depending on plant conditions so this is above just straight recall for system knowledge.

1 I_.~ ___ ~.~.~ _. __._.~. _____._~ ____ ~ ______ ~._.~._~~_. ___ ~ ____ ~_~~

___. ___________ ~ __

._~ __ ~_~~ ____________.. __ ~._._._~._ ~~.~._~..J Answer A Discussion r;'-'-'-~----'-~-"'-'-'~-~-'-'--'-----~'-'-'---'-----'---~~---~~-.----.--~-.~-~-.--~.--~.----.--.---~-~--.~----~--*~~*-----~---I

[II1~rre~!~a.'1s~b~e ~~aus:.'1~il1.g! ~~~u~£~~o~:c~

al~~2~'Y0\\\\l(~u~~:..c:~~ec:~f!:~\\,:~~C~l1.~~.:n~ ~~~t~l1...~!11.~~~~=-n~t~-=ft'e.:t~ ___ ~ ___ ~ __ ~ ~ _ ~ ________ J Answer B Discussion l~~0= =-===-=~======-===============-= -======~======-=-==-= =-= =-=--=-==-~_~-=-=_-_=-=-==-=-=-=-=-==--=-= =-=--=-=====-===-_-_]

Answer C Discussion ifuZ~~tPl;u.;;bkb~~~;the~H~hvclla_;;_d-B~_;;_stt;~~~p;-;;-o~idbe-u~;difS/G~~~fir;td~~~-;;;zed.H~w_;;~~they-;~~t~~~~-;~de;-~pri~ritY.AI-;,-:-i4O/~~otiliib~Zo;;~tif-

~~~~~<>.n!alnfl1~.t.c..<>.l1..di!i.c>11.. nllfl1!J.e~~~t:.!1()t..i~t:.~~.~ ___ ~~ ____ ~_ ~ ____ ~ ____ ~ _________ ~_~_~ ___ ~ _____ ~___ _ ___ ~ __ ~ __ _

Answer 0 Discussion l0.:~-;~!~~~T?~~;u-;~~h~~~~~~~~()~~te-;:-pll.~J1~~0~b.:~u-;ed~j!'.s2~~~...fI~;-:.d~~:.~~~~ie~~he~~ei()t~-;;;~in~~~-;:j5i~£~~~6%~~~i:ct.- ___ -_-____ -_~J

\\JobLevel-'--CognltiVeLev8t~--IQue'-tlonType-T~------~-----Q-u-8ti--Souc-~--------~---~-l 401-9 Comments RESPONSE I---R:o---i- -~ -comp~h~n;io;----r~-'~ioDiFffiD----t - ----~ ---CNSNRCE~m ~~kQ~~i~n~I:028------- -~I Disagree with Chief Examiner's comment

.~._. _____.J __ ~~~_

.. _._.~. ___...J ______ ~_~.~_L._._. __._~_~ __._._~. ____. ______ ~--.~-.---~.--I regarding no DV. Since the Feedwater

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved i~v"!~e~~~ ~!!~ric!.~ -== = =

=-=-=-=-=--=-=-=~ ~~t~d!~~~~!&-;)~"!E~!@!(1=-==-==-]

[Lesson Plan OP-MC-CF-CF Objective 12 pages 35 and 1 i i

137 I 1 I

IFR-H.I pages 9 & 10 II I

I 1

I i i I

L __ ~

______ ~_~

___ ~~_~

______ ~

__ I L __ ~ _____ ~_~ ____

~~ ___ ~_

Isolation is being blocked instead of being reset (normal method), regaining control of the CF pumps is not as straight forward as it may seem. Will discuss with Chief Examiner.

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I(CFR: 41.7 I 45.7) 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, I

lfitilu~~(fe~~~..<lll.to..~!ic_arl(!_~a.l1tIal.!t:.a.!ll~~_~ _______ ~ ____ ~ ______ ~ ___ ~_~ ~_~_~~J ruesday, November 10, 2009 Page 137 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 56 A

r- ----- -

---~---~------I--~- ------- -

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~~--~I 19-~~t~on~~nI<~ ~=81'!t~~_~=~~~b~-,"-~ _ ~~~i ~_des~ _~ __

L ~_~1~~6~ __ 1_~~~~~~~_~~~_2!~ ____ ~J I~El~\\ GENERlC[;Knowledge of how abnonnal operating procedures are used in conjunction with EOPs. (CFR: 41.IO! 43.5!

l:'"._~_.~ ___._~ ____. __ ~ ___ ~~ ___._~~~

__ ~~_~.~. __._.~_~ ___ ~ __ ~. ___ ~_.~~~~_~~

CURRENT 45 DAY VERSION Given the following conditions on Unit 1 :

Given the following conditions on Unit 1 :

Unit 1 FWST level is 175 inches follo'll1ng indications of a Large-Break LOCA The crew is performing actions in ES-1.3 (Transfer to Cold Leg Recirc) 1 NI-184B (1 B ND Pump Suction From Cont Sump Isol) has failed in the CLOSED position Containment sump level is 3.0 feet A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA The crew was performing E-1 (Loss of Reactor or Secondary Coolant) and have implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Annunciator 1AD-12 C1 0IINS LO PRESS) is in alarm Which ONE (1) of the following symptoms and/or indications would require the crew to transition to E CA-1.1 (Loss of Emergency Coolant)?

Which ONE (1) of the following describes the requirements for implementing AP-22 (Loss of VI) in conjunction with ECA-1.1?

A B.

C.

D.

A.

1A ND Pump is lost 1A and 1B NI pumps are lost.

B.

AP-22 may be implemented concurrently with ECA-1.1. However, it must be suspended if transition is made to a Functional Restoration Procedure (FRP).

AP-22 may not be implemented since no other procedures may be implemented while an ECA procedure is in effect.

CIR receives report that the Unit 1 FWST is ruptured.

C.

AP-22 may be implemented concurrently with ECA-1.1. However, the operators must use caution since an sn has occurred.

FWST Lo Lo Level is reached with Containment sump indicating a level of 3.5 ft.

WEIIG2.4.8 D.

AP-22 may not be implemented since an SI has occurred. The APs are written assuming the S/I had not occurred and shall not be used if S/I has actuated.

401-9 Comments:

B and D are not plausible because you asked them in the stem WOOTF describes the requirements or implementing...

Therefore Band D are automatically ruled out.

Change stem: WOOTF describes whether or not AP-22 can be implemented in conjunction with ECA-I.I. (something to that affect)

I agree that this Q may be SRO ONLY ruesday, November 10, 2009 Page 138 of 185 A

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 56 rq~~ili>-n~~rlI<!I T~~81'!~~=T~:~~b~r~ =-=--_=: ~-=des~-_=-=-=-=--_~=--_=--_~~_=-===-=-=-==-~-==-===-=-==-.==~===--.=-==-=-=-=-=_=~=-=-=-=-=-=-=-:

r 1856 r WEll T 2.4.8 IIWEII GENERlC[;Knowledge of how abnonnal operatmg procedures are used m conjunctIOn With EOPs. (CFR: 41.1O! 43.5 !

I

---

----------------------, ~~l~L __________________ ~ ___ ~ ____ ~~~ ______________________________________ J CURRENT 45 DAY VERSION Given the following conditions on Unit 1 :

Given the following conditions on Unit 1 :

Unit 1 FWST level is 175 inches follo'll1ng indications of a Large-Break LOCA The crew is performing actions in ES-1.3 (Transfer to Cold Leg Recirc) 1 NI-184B (1 B ND Pump Suction From Cont Sump Isol) has failed in the CLOSED position Containment sump level is 3.0 feet A Reactor Trip and Safety Injection have occurred due to a Small Break LOCA The crew was performing E-1 (Loss of Reactor or Secondary Coolant) and have implemented ECA-1.1 (Loss of Emergency Coolant Recirc)

Annunciator 1AD-12 C1 0IINS LO PRESS) is in alarm Which ONE (1) of the following symptoms and/or indications would require the crew to transition to E CA-1.1 (Loss of Emergency Coolant)?

Which ONE (1) of the following describes the requirements for implementing AP-22 (Loss of VI) in conjunction with ECA-1.1?

A B.

C.

D.

A.

1A ND Pump is lost 1A and 1B NI pumps are lost.

B.

AP-22 may be implemented concurrently with ECA-1.1. However, it must be suspended if transition is made to a Functional Restoration Procedure (FRP).

AP-22 may not be implemented since no other procedures may be implemented while an ECA procedure is in effect.

CIR receives report that the Unit 1 FWST is ruptured.

C.

AP-22 may be implemented concurrently with ECA-1.1. However, the operators must use caution since an sn has occurred.

FWST Lo Lo Level is reached with Containment sump indicating a level of 3.5 ft.

WEIIG2.4.8 D.

AP-22 may not be implemented since an SI has occurred. The APs are written assuming the SI/ had not occurred and shall not be used if S/I has actuated.

401-9 Comments:

B and D are not plausible because you asked them in the stem WOOTF describes the requirements or implementing...

Therefore Band D are automatically ruled out.

Change stem: WOOTF describes whether or not AP-22 can be implemented in conjunction with ECA-l.l. (something to that affect)

I agree that this Q may be SRO ONLY ruesday, November 10, 2009 Page 138 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 56 General Discussion Replace the Q or request a new KA.

RP A 10/28/09 A

r;:----------------- -

---

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

IFor this scenario, the applicant is presented with a set of conditions where the FWST has reached the LO Level setpoint of 180 inches. This requires the crew to transition to ES 1.3 (Transfer

[to CLR). There are a number of conditions which would require a transition to ECA 1.1 (Loss of ECR) namely, the loss of either both ND pumps or the inability to establish a flowpath from Ithe containment sump to a least one of the ND pumps. The "B" Train containment sump isolation valve is given as not available therefore if either the "A" Train containment sump isolation

[valve cannot be opened or the "B" Train ND pump is lost, this would represent a loss of ECR capability and require a transition to ECA 1.1.

IThe containment sump level is provided at a level which is sufficient for CLR (>2.5 feet) therefore as long as a flowpath can be established and a ND pump is available, a transition to ECA 11.1 would not be required, i.e., a rupture of the FWST I IKA is matched because the candidate must understand the plant challenges that ECA 1.1 is written to address. The evaluation of transition criteria represents a applicants understanding of Iboth the purpose and function of this procedure.

I IThis question is analysis level because the candidate must analyze the conditions given and evaluate the applicability of a given procedure. This requires both a multi part mental process and

~<iet(:l"I1li~ !ht: £f~~I"apE!i.c:~ti~l1...<>!'~~~el1jJf~~ci.uI"e _____________________ ~

Answer A Discussion rc~~-;ct:-Th~k;~~fili___;;~ A'-;-t-;:-ain-ND-p~~p\\~~~id -;:-eq~ir~-;;' tra~;itio~ to ECAIJ~-de;;ri~d above L __, __, ______

~ ______

~ __

~_~ ________

~ ___

~ _______. ____________________ _

Answer B Discussion

[-----

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

[Incorrect: Plausible because without one NI pump recirc would not be possible ifNC system was greater than the shutoff head of the ND pumps. However, since it is given that a large-break ILOCA has occurred this is not the case.

L ____

.~

Answer C Discussion 1.-------- - ---- ---------------------------~-

[Incorrect: There is adequate level in the containment sump to support ECR. Plausible; l~0.':lld n()f.!e9,lIi~ir~~i~~l1...!~ ~~~!.-I A loss ofFWST inventory would~ep;.~s~~_;~alleng;t;-ECR;p;bilitYbut;i!hth;~~nditi~;gi;~~1

[

__.. ___ J Answer 0 Discussion

Incorrect: 3.5 feet inth;-co~t~in~~~__;~mpis -;~ffici~~tt~;~p;;rt ECR.;t.P~~ible_:Tht;-;;~-~~r ~epr~~~t~-sig~ific~t ~~~fi~v~Jtl~ry-;~~PI~vcl-~tthi;point sh;uld be approx. 7 feet.

[i:>ut there is sufficient sump level to support ECR.

---

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

--~

Cognitive Level QuestionType [

Question Source Comprehension NEW ___ L ___ _

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

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

'uesday, November 10, 2009 InFDevelOpmentRef;;';rlCeS---- ------

iStud;ntRer;rencesProvfded--

I---------------~-----~----

[Lesson Plan OP-MC-EP-EI rev. 22, pages 23

[

I

[

I IES 1.3 (Transfer to CLR) Rev 25 Pgs 2,12 & 27 I

[

[

[Learning Objective::--JOP-MC-EP-EI Obj. 6 I

L _ _ ____________ ______ _

L ________________________ _

Page 139 of 185 401-9 Comments RESPONSE 11104109 New question for replacement KIA.

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 56 General Discussion Replace the Q or request a new KA.

RP A 10/28/09 A

r;:.-----.-.---.---- -

---

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

IFor this scenario, the applicant is presented with a set of conditions where the FWST has reached the LO Level setpoint of 180 inches. This requires the crew to transition to ES 1.3 (Transfer ito CLR). There are a number of conditions which would require a transition to ECA 1.1 (Loss of ECR) namely, the loss of either both ND pumps or the inability to establish a flowpath from ithe containment sump to a least one of the ND pumps. The "B" Train containment sump isolation valve is given as not available therefore if either the "A" Train containment sump isolation

[valve cannot be opened or the "B" Train ND pump is lost, this would represent a loss of ECR capability and require a transition to ECA 1.1.

IThe containment sump level is provided at a level which is sufficient for CLR (>2.5 feet) therefore as long as a flowpath can be established and a ND pump is available, a transition to ECA 11.1 would not be required, i.e., a rupture of the FWST I IKA is matched because the candidate must understand the plant challenges that ECA 1.1 is written to address. The evaluation of transition criteria represents a applicants understanding of Iboth the purpose and function of this procedure.

I IThis question is analysis level because the candidate must analyze the conditions given and evaluate the applicability of a given procedure. This requires both a multi part mental process and

~<iet(:l"I1li~ !ht: £f~~I"apE!i.c:~ti~l1...<>!'~~~el1jJf~~ci.uI"e _____________________ ~

Answer A Discussion r----------------- ----- ---- ------ - ---- -- - ----- -------------'-- ---------------~---~ --------- ------ -- --- ---------~-----------,

Correct: The loss of the "A" train ND pump would require a transition to ECA 1.1 as described above

[

L: ___________________ ~

_______________________. ______________________ ~

_________________________________________________ J Answer B Discussion

[---.-

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

~------- -~ ---------- ---------------------- ------- ---.-------------- -------l

[Incorrect: Plausible because without one NI pump recirc would not be possible ifNC system was greater than the shutoff head of the ND pumps. However, since it is given that a large-break [

ILOCA has occurred this is not the case.

[

L ____

.~

~

.~

_____ J Answer C Discussion r;-------------~---------------.-----------~----------------------.------------.--------~-------------------------------1

[Incorrect: There is adequate level in the containment sump to support ECR. Plausible; A loss ofFWST inventory would represent a challenge to ECR capability but with the conditions given [

l~0.':lld n()f---"e9,lIi~ir~~i~~l1...!~ ~~~!.-~ _________ ~. _____________________________. ______________ ~

__________ ~

~

________________________ oj Answer 0 Discussion 1-----------------------*---------------------------------------------.---------------.----------------------~----------------l

[Incorrect: 3.5 feet in the containment sump is sufficient to support ECR.net. Plausible: This answer represents a significant loss of inventory sump level at this point should be approx. 7 feet. i i'J.u~ tl!~~~i~ ~ufr~~I1t~u...m.P~~eItcJ~tpE.o..rt~B::... _______________ ~

_______ ~_~ __________________ ~. ______________________________________ J

--~-- ~

Job Level I Cognitive Level QuestionType [

Question Source

---

~-[------ - - ------ -- --------- --------- ------- ------------~----

RO

[

Comprehension NEW

[

L _______________ 1 __________ ~ __________________________________ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

'uesday, November 10, 2009 rn- ------ ------ --- ---------------

,Development References F---------- ---- ---- - ----.--- ----

[Lesson Plan OP-MC-EP-EI rev. 22, pages 23 I

I IES 1.3 (Transfer to CLR) Rev 25 Pgs 2,12 & 27

[

~earning Objective::-JOP-MC-EP-EI Obj. 6 r---'-

---

~------

[Student References Provided I---------------~--~--~----

[

I I

[

I L ________________________ _

Page 139 of 185 401-9 Comments RESPONSE 11104109 New question for replacement KIA.

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 56 A

I: ----,- -

- --:-r---'----- --~---~--.----- - ----l I-----------~--- -------- --.---.-----.- ---------------- --- ------- ----- --------.-

~~~!().r!~~"_k!#+/-~A-$y8tefl!-1KA_n~fl!!>eL_ - ----11 ~A=~~£ __________________ _

I 18561WEII 12.4.8 lWEI I GENERICuKnowiedge of how abnonnal operating procedures are used in conjunction with EOPs. (CFR: 41.10/43.5

__________ ~ ________ l __. ______. _____

1 i~~L _____ _

ruesday, November 10, 2009 Page 140 of 185 FOR REVIEW ONLY - DO DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 56 ruesday, November 10, 2009 Page 140 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 57 c

IQuestionBank # IKA system IKA number I KA desc I

1857 I

APE003 I

AKI.07 I Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: (CFR 41.81 4I.I0 1 45.3)[JEffect of dropped rod on insertion limits and SDM....................

CURRENT 45 DAY VERSION Given the following:

Given the following:

Unit 1 is operating at 100% RTP with Rod Control in AUTO A rod in Control Bank C drops into the core Tave dropped to 584°F and was restored to 585°F by the OATC with the Rod Control system in MANUAL NC system pressure has stabilized at 2235 PSIG NC system boron concentration has not changed Which ONE (1) of the following completes the statement below?

Based on the steady-state conditions above, shutdown margin --.Ul insertion limits _ ill A.

1) increases

2) decrease B.

1) remains the same

2) decrease C.

1) remains the same

2) remain the same D.

1) increases

2) remain the same APE003AKI.07 and rod Unit 1 is operating at 100% RTP with Rod Control in AUTO A rod in Control Bank C drops into the core Tave dropped to 584 of and was restored to 585°F by the Rod Control system before Rod Control was placed in MANUAL NC system pressure has stabilized at 2235 PSIG Based on the conditions above, shutdown margin -ID limits m

and rod insertion (ASSUME XENON CONCENTRATION HAS NOT CHANGED)

A.

1) decreases

2) decrease B.

1) remains the same

2) decreases C.

1) remains the same

2) remain the same D.

1) decreases

2) remain the same 401-9 Comments; Please re-evaluate the assumption in the question. If they know Xenon did not change, then power did not change and reactivity did not change.

This may key them to the answer.

Thursday, November 12, 2009 Can the assumption be removed without affecting the question?

RFA 10128/09 Page 141 of186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 57 c

IQuestionBank # IKA system IKA number I KA desc I

1857 I

APE003 I

AKI.07 I Kno,,;ledge of the operational im.plica~ions.o~the following concepts as they apply to Dropped Control Rod: (CFR 41.8 1 4I.I0 1 45.3)clEffect of dropped rod on msertIOn lImIts and SDM....................

CURRENT 45 DAY VERSION Given the following:

Given the following:

Unit 1 is operating at 100% RTP with Rod Control in AUTO A rod in Control Bank C drops into the core Tave dropped to 584°F and was restored to 585°F by the OATC with the Rod Control system in MANUAL NC system pressure has stabilized at 2235 PSIG NC system boron concentration has not changed Which ONE (1) of the following completes the statement below?

Based on the steady-state conditions above, shutdown margin (1) and rod insertion limits (2)

A.

1) increases

2) decrease B.

1) remains the same

2) decrease C.

1) remains the same

2) remain the same D.

1) increases

2) remain the same APE003AKI.07 Unit 1 is operating at 100% RTP with Rod Control in AUTO A rod in Control Bank C drops into the core Tave dropped to 584 OF and was restored to 585°F by the Rod Control system before Rod Control was placed in MANUAL NC system pressure has stabilized at 2235 PSIG Based on the conditions above, shutdown margin (1) and rod insertion limits (2)

(ASSUME XENON CONCENTRATION HAS NOT CHANGED)

A.

1) decreases

2) decrease B.

1) remains the same

2) decreases C.

1) remains the same

2) remain the same D.

1) decreases

2) remain the same 401-9 Comments; Please re-evaluate the assumption in the question. If they know Xenon did not change, then power did not change and reactivity did not change.

This may key them to the answer.

Thursday, November 12, 2009 Can the assumption be removed without affecting the question?

RFA 10128/09 Page 141 of186

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 57 c

General Discussion Shutdown margin is defined as the amount of reactivity by which the reactor is shutdown OR could be made instantaneously shutdown. With the dropped control rod, the control rods withdraw slightly to compensate for the decrease in Tave caused by the dropped rod. Since Reactor Power, Boron Concentration, and Tave are at the same value as they were prior to the dropped rod SDM does not change. Since power is the same Rod Insertion Limits remain the same.

This KA is matched because the applicant must know the effect of a dropped rod on SDM and RILs to correctly answer the question.

Question is comprehensive because the candidate must evaluate the effects of a rod drop scenario on SDM and rod insertion limits. This represents a multi part mental process and a prediction of an outcome.

Answer A Discussion Incorrect. Part 1 is incorrect but plausible if the applicant believes that the dropped rod adds negative reactivity to the core which would increase SDM. Part 2 is plausible if the applicant does not understand the RILs are determined by reactor power.

Answer B Discussion Incorrect. Part 1 is correct. Part 2 is plausible if the applicant does not understand the RILs are determined by reactor power.

~

Answer C Discussion FORRECT~ -- -------------------

-]

Answer D Discussion

~ncorrect. Part 1 is incorrect but plausible if the applicant believes that the dropped rod adds negative reactivity to the core which would increase SDM. Part 2 is correct.

Job Level RO

~ Developed Cognitive Level Question Type Question Source Comprehension NEW Lesson Plan OP-MC-RT-RB Objective 9 page 45 I

Lesson Plan OP-BNT-RT03 Objective 8 pages 19 and I

20 i

'Student References Provided

~ OPT Approved

~ OPS Approved

~ NRC Approved

~

_______________________ ~L' QuestionBank # !KA_system KA number KA desc 401-9 Comments RESPONSE Chief Examiner's asked if statement regarding Xenon concentration not changing could be removed. Xe statement gives time reference. IfXe had started building in it would change SDM. Will discuss further with CEo Added WOOTF question. HCF 11104/09 1857iAPE003 AKl.07 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: (CFR 41.8 141.10 145.3 )liEffect of dropped rod on insertion limits and SDM....................

Thursday, November 12, 2009 Page 142 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 57 c

General Discussion Shutdown margin is defined as the amount of reactivity by which the reactor is shutdown OR could be made instantaneously shutdown. With the dropped control rod, the control rods withdraw slightly to compensate for the decrease in Tave caused by the dropped rod. Since Reactor Power, Boron Concentration, and Tave are at the same value as they were prior to the dropped rod SDM does not change. Since power is the same Rod Insertion Limits remain the same.

This KA is matched because the applicant must know the effect of a dropped rod on SDM and RILs to correctly answer the question.

Question is comprehensive because the candidate must evaluate the effects of a rod drop scenario on SDM and rod insertion limits. This represents a multi part mental process and a prediction of an outcome.

Answer A Discussion Incorrect. Part 1 is incorrect but plausible if the applicant believes that the dropped rod adds negative reactivity to the core which would increase SDM. Part 2 is plausible if the applicant does not understand the RILs are determined by reactor power.

Answer B Discussion Incorrect. Part 1 is correct. Part 2 is plausible if the applicant does not understand the RILs are determined by reactor power.

Answer C Discussion

[CORRECT.

Answer D Discussion

~ncorrect. Part 1 is incorrect but plausible if the applicant believes that the dropped rod adds negative reactivity to the core which would increase SDM. Part 2 is correct.

Job Level Cognitive Level Question Type Question Source 401-9 Comments RESPONSE RO Comprehension NEW Chief Examiner's asked if statement regarding Xenon concentration not changing could be removed. Xe statement

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved QuestionBank # !KA system 1857rAPE003 Thursday, November 12, 2009 Development References Lesson Plan OP-MC-RT-RB Objective 9 page 45 Lesson Plan OP-BNT-RT03 Objective 8 pages 19 and 20 KA number KA desc f--S_t_u_d_e_n_t_R_e_f_e_re_n_c_e_s_P_r_o_v_i_d_e_d ____ -I gives time reference. IfXe had started building in it would change SDM. Will discuss further with CEo Added WOOTF question. HCF 11104/09 AKl.07 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: (CFR 41.8 141.10 145.3 )liEffect of dropped rod on insertion limits and SDM....................

Page 142 of 186

C FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 58

~~!8jt~:!~~~~;ys~m:=]~=~~b~~-=====i ~=<!e:!~====~========-=~====-==_~==================-==-====_=====]

[

1858 T APE005

. i AK2.02.

i IKnowledge of the interrelations between the Inoperable 1 Stuck Control Rod and the following: (CFR 41.7 145. 7);]Breakers, relays, I

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

~i~(;9E.~cE,--~~(;()ntrol--'".()()~~\\"'it~~s~..-.:..-.:.~.~-:=:..-:.:--:..-::..-:..... :..-:..-.::... :.-: ___________________________ J CURRENT Given the following conditions on Unit 1 :

Control Rod M-4 (Control Bank D, Group 2) indicates 186 steps on DRPI Bank D Group Step Counters indicate 195 steps on both banks I&E has determined that Control Rod M-4 is immovable due to a failure of its Lift Coil Disconnect switch There has been no indication that the rod is mechanically bound.

It will take approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to replace the failed disconnect switch Which ONE (1) of the following describes the OPERABILITY of Control Rod M-4 as described by Technical Specification 3.1.4 (Rod Group Alignment Limits)?

A B.

C.

D.

The control rod does not meet alignment limits but remains OPERABLE because it can be tripped.

The control rod can be tripped but is INOPERABLE because it is not within alignment limits.

The control rod is OPERABLE because it can be tripped and it is within alignment limits.

The control rod is within alignment limits but is INOPERABLE because it can not be moved.

APE005AK2.02 45 DAY VERSION Given the following conditions on Unit 1 :

Control Rod M-4 (Control Bank D, Group 2) indicates 186 steps on DRPI Bank D Group Step Counters indicate 195 steps on both banks I&E has determined that Control Rod M-4 is immovable due to a failure of its Lift Coil Disconnect switch There has been no indication that the rod is mechanically bound.

It will take approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to replace the failed disconnect switch Which ONE (1) of the following describes the OPERABILITY of Control Rod M-4 as described by Technical Specification 3.1.4 (Rod Group Alignment Limits)?

A.

B.

C.

D.

The control rod does not meet alignment limits but remains OPERABLE because it can be tripped.

The control rod can be tripped but is INOPERABLE because it is not within alignment limits.

The control rod is OPERABLE because it is can be tripped and it is within alignment limits.

The control rod is within alignment limits but is INOPERABLE because it can not be moved.

401-9 Comments:

D is not plausible because the stem stated that there was no indication that the rod is mechanically bound in the 4th bullet. To state in D that it cannot be moved is a contradiction to the stem. The distracter analysis for D is not acceptable.

ModifY or replace distracter D.

RF A 10/29/09 ruesday, November 10, 2009 Page 143 of 185 C

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 58

~~!8jt~:!~~~~;ys~m:=]~=~~b~~-=====i ~=<!e:!~====~========-=~====-==_~==================-==-====_=====]

[

1858 __ I __ AI)EO~~_l ____ AIC~~~ ___ J i~nowledge of the interrelations b~tween the Inoperable 1 Stuck Control Rod and the following: (CFR 41.7 145. 7);]Breakers, relays, I tcil~~E~cE,--~~(;()ntrol~()()~~\\\\,lt~~s~~~.~.~-:=:-::--:~~.~:~~:~:.-: _________ ~ ___________________ I CURRENT 45 DAY VERSION Given the following conditions on Unit 1 :

Control Rod M-4 (Control Bank D, Group 2) indicates 186 steps on DRPI Bank D Group Step Counters indicate 195 steps on both banks I&E has determined that Control Rod M-4 is immovable due to a failure of its Lift Coil Disconnect switch There has been no indication that the rod is mechanically bound.

It will take approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to replace the failed disconnect switch Which ONE (1) of the following describes the OPERABILITY of Control Rod M-4 as described by Technical Specification 3.1.4 (Rod Group Alignment Limits)?

A B.

C.

D.

The control rod does not meet alignment limits but remains OPERABLE because it can be tripped.

The control rod can be tripped but is INOPERABLE because it is not within alignment limits.

The control rod is OPERABLE because it can be tripped and it is within alignment limits.

The control rod is within alignment limits but is INOPERABLE because it can not be moved.

APE005AK2.02 Given the following conditions on Unit 1 :

Control Rod M-4 (Control Bank D, Group 2) indicates 186 steps on DRPI Bank D Group Step Counters indicate 195 steps on both banks I&E has determined that Control Rod M-4 is immovable due to a failure of its Lift Coil Disconnect switch There has been no indication that the rod is mechanically bound.

It will take approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to replace the failed disconnect switch Which ONE (1) of the following describes the OPERABILITY of Control Rod M-4 as described by Technical Specification 3.1.4 (Rod Group Alignment Limits)?

A.

B.

C.

D.

The control rod does not meet alignment limits but remains OPERABLE because it can be tripped.

The control rod can be tripped but is INOPERABLE because it is not within alignment limits.

The control rod is OPERABLE because it is can be tripped and it is within alignment limits.

The control rod is within alignment limits but is INOPERABLE because it can not be moved.

401-9 Comments:

D is not plausible because the stem stated that there was no indication that the rod is mechanically bound in the 4th bullet. To state in D that it cannot be moved is a contradiction to the stem. The distracter analysis for D is not acceptable.

ModifY or replace distracter D.

RF A 10/29/09 ruesday, November 10, 2009 Page 143 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 58 c

General Discussion IITh~-Z~ntr~I rod;; oper~bI;;-b~a~se iti;-stilltrippabi~(n;indh::;ti;~~~the~~~)~Si~~ the c~~;:-ol~dis-;ithin 12 steps of the group step counter position, the rod is not out of alignment as required by TS 3.1.4 I

IThe KJA is matched because the applicant must understand the relationship between the lift coil disconnect switches for the control rod and the Tech Spec operability of the rod.

I IThis is an analysis level question because the applicant must apply multiple given indications to information recalled from memory (control rod alignment TS limits) and must comprehend

!tll<l~t~e_~oEtr()\\~~c!J~ ~t~l tri lP~1JI~ia[1~£h~~~~~~II()p~~alJl~L\\\\'i0J~eJlft~~1'~ ~(li~C()~~e<;£ s~l~~fitiled. _____________ _

Answer A Discussion r;---~--~-

---

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

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

IIncorrect. Plausible if the applicant does not understand the control rod alignment limits and the control rod can be tripped.

L ___, ____, _______. _____. _____

• __________. __. __

~~

Answer B Discussion I--~-------~----

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

LI~~~rr~:t~~us~t:~~'T~I~c~rlt~~:s~~~~n~:r~t~~~~e_ contl"O~ro~!~gnment limits.

Answer C Discussion I~------~- - --

ICORRECT.

L ___________________ _

Answer 0 DISCUSSion

---

------~

IIncorrect. Plausible because control rod is within its alignment limits. The control is immovable for electrical reasons. Since it is not mechanically bound, there is no indication that the rod is Iinot trippable. Therefore, the rod remains OPERABLE.

___ ~og~~tIy~=~~~C=_=I=~~~il~~yp~=I=_== ____________ ~sU()~~~~~

_ _____ ~ _J 401*9 Comments RESPONSE

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved I

NEW I

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

rDe;;J~pm;nt Reference.-----------------r ISt~dent-R;,e,:en~e-s -proYlded---

L-~------:_--:__--~--------- -----:_ ~------, f-- ----- - ---~- -----~--~ -~- -

iTechnIcal SpeCIficatIOn 3.1.4 Rod Group AlIgnment I:

iLimits I I I

I I I

i I I I I

I I I

I l 1 ______________________

~~ ____________ _' _____ ~_~ _~_~ ___________

~ ______ _

---~-- -.~- -- ------iu---- -

-~-----

i Chief Examiner commented that'D' is not plausible since it contradicts the the stem

("not mechanically bound"). Not a contradication only a clarification that it can still be tripped even though it is immovalbe (electrically). Fixed distractor analysis.

Mdesc---------

f"-:--=--~--- --~ - --- - --~--~----

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

~e.tlo'!~!'!!<_ ~1~~I!l~tt'!' __ IKA=nu"'~CJ~---

18~8:AJl~~~ ____ J~~~~ _______ _

IKnowledge of the interrelations between the Inoperable I Stuck Control Rod and the following: (CFR 4 1.7 I 45. 7) [JBreakers, I~-'ars, ~~~~~e~~,- [\\l1~ ~~nt~-'-I"0~~_s~i!~h~~ ___________ _

fuesday, November 10, 2009 Page 144 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 58 General Discussion IITh~-Z~ntr~I rod;; oper~bI;;-b~a~se iti;-stilltrippabi~(n;indk;ti;~~~the~~~)~Si~~ the c~~;:-ol~dis-;ithj;I~~Ps~fth~g;;~~tep counter position, the rod is not out of alignment as required by TS 3.1.4 I

IThe KJA is matched because the applicant must understand the relationship between the lift coil disconnect switches for the control rod and the Tech Spec operability of the rod.

I IThis is an analysis level question because the applicant must apply multiple given indications to information recalled from memory (control rod alignment TS limits) and must comprehend

!tll<l~t~e_~oEtr()\\~~c!J~~t~1 trilP~1JI~ia[1~£h~~~~~~11()p~~alJl~L\\\\'i0J~eJlft~~1'~~(li~C()~~e<;£s~l~~fitiled. _______________ ~

~ ____ _

Answer A Discussion r;---~--~-

---

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

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

--~---~------------------ -------------- - ----- ----- - --- --1 IIncorrect. Plausible if the applicant does not understand the control rod alignment limits and the control rod can be tripped.

I L ___, ____, _______ " ________________________________________. ____________________

~

~

~

Answer B Discussion I--~-------~-------~--~--------------~---------~---~---------~------------------------~-----~---~---------------------------1 IIncorrect. Plausible if applicant does not understand the control rod alignment limits.

I L ________________________

~ _____

~ _____________________

~ _____________

Answer C Discussion I-------------------~--------------~-~------------*------~---.~-------------------------------------------~--------------~

ICORRECT.

L _______________________. ___

~ __

~ __. _________

. ___. ____________ ~ ________. ____________________________________________________

~ ________

Answer 0 DISCUSSion 1I~;;:~t~Pht;ill,I;;_b;cau_;;;_~~~tr~;di~~ithi~its alig~~tii~its~ Th~con~l~i~ovable fo;-electr;;;;}~~~~;_sin~-it~~-~e_;;_h~i_;;_~Iyb~~d:there i~;~ind;;;~t;;;;th~tthe rod is-I i~O! E"ppabl~:!Jl~~fore,J~~f9~I"~~ins 2PE~I!l:~ _____________________________________________________

~ ____________

~ ___ ~ ___ ~_~ ____ J I-J-I)-C ~I-T ---c---itI--C--,----r(i-tl-T---1---- ---------- aUe-u--s ------------------I 401.9 Comments RESPONSE f-- ~

__ ~!4t -i--__ ~~_~~ __ e!~ ___ -1 __ ~~~_()~~!'_ L ------___________ ~.<>~_~~~ _____ -- --------~

L __ ~_O ___ J ___ ~~~~re~~n~~~ ____ L ____ ~~~ ____ 1 _________________________________________ J ~l~:~~l:a:~~:ritc~r::~:~~ t~~ ;~~ ~~:t

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

---~-- -.~- -- ------iu---- -

-~-----

~estlo'!~!'!!<_ ~1~~I!l~tt'!' __ IKA=nu"'~~~---

. _______ 18~8:AJl~~~ ____ J~~~~ _______ _

fuesday, November 10, 2009

("not mechanically bound"). Not a contradication only a clarification that it can still be tripped even though it is immovalbe (electrically). Fixed distractor analysis.

IKA-desc---------

---

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

f"-:--=--~--- --~ - --- - --~--~---- -~-~- ------~--~-- - -----~--- -~ ~ -----

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

IKnowledge of the interrelations between the Inoperable I Stuck Control Rod and the following: (CFR 41.7 I 45. 7) [JBreakers, I~-'ars, ~~~~~e~~,- [\\Il~ ~~nt~!1"0~~_s~i!~h~~.:-:~:~.~.~.~::-:~:--:.~.::-~.................

Page 144 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 59 A

r--~-~ -

~-~-

-~-~'~~-~-~~--~~~l---

--~~ ---

-~-~

r:~-----

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

---

~--

IQuestionBank t# IKA_system KA_number IrKA_desc r ---1859 --T-APE02T~f--AK T04-~-1 ~~~~~~~fth~-op~~ati;;-n-;li~Piicati;;-~~ ~fth~follo~~g co~cepts~

th~~ppiYtoE~;~~yBo-;,ili~~icFR4i8/41J 0/

L_ ------

-~ ~-~ --- ___ L -

---

~ ___ ~J 145.3)lJLow temperature limits for born concentration....................

L _________________________

~ _______________

~ _________

~~ __ _

CURRENT 45 DAY VERSION Given the following conditions on Unit 1:

Given the following conditions on Unit 1 :

An Operator in the plant reports that the FWST Heater Overtemperature light on the FWST Heater Control panel is LIT Which ONE (1) of the following describes the operational implications of the FWST Heater overtemperature condition?

A B.

C.

D.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 80°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 80°F.

APE024AK 1 04 An Operator in the plant reports that the FWST Heater Overtemperature light on the FWST Heater Control panel is LIT Which ONE (1) of the fol/owing describes the operational implications of the FWST Heater overtemperature condition?

A B.

C.

D.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 65°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 65T 401-9 Comments:

CAF: The KA is for low temperature limits for Boron Concentration. This Q references an over-temperature annunciator. Is this for a high temperature or a low temperature condition? The ref does not explain well.

Stem: Is this a high Temperature or a low temperature condition?

Remove the double period from "C" and "D" fuesday, November 10,2009 Page 145 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 59

~

r(juj,!tI~nBa~~ItS!--=;ys!e~=~~~n-U~~====~~I~-:'~e~i~==============-=====================-==-~~--~-.~~-~~-~-~~-~-

r 1859 T

APE024 f AK1.04 IlKnowledge of the operational implications of the following concepts as they apply to Emergency BoratiOn: (CFR 41.8 /41.10 /

L

- --~~- ___ L_ - -~- --- L --- -~~-- ~-.-.-.I ~2.-~_Qloo~Jemp~£ltul"~J.~sf()r J:)(~_ftl..~.I1.c~111.f1tti9~..........-...:.... :...-..-...: ___ :......... ___ ~ ____ ~~ _____ ~ __. __ ~ ____ ~ __

CURRENT Given the following conditions on Unit 1:

An Operator in the plant reports that the FWST Heater Overtemperature light on the FWST Heater Control panel is LIT Which ONE (1) of the following describes the operational implications of the FWST Heater overtemperature condition?

A B.

C.

D.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 80°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 80°F.

APE024AK 1 04 45 DAY VERSION Given the following conditions on Unit 1 :

An Operator in the plant reports that the FWST Heater Overtemperature light on the FWST Heater Control panel is LIT Which ONE (1) of the fol/owing describes the operational implications of the FWST Heater overtemperature condition?

A B.

C.

D.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 70°F.

All FWST heater groups are tripped. The FWST will remain OPERABLE until FWST temperature decreases to less than 65°F.

Only the FWST heater group with the overtemperature condition has tripped.

The FWST will remain OPERABLE until FWST temperature decreases to less than 65T 401-9 Comments:

CAF: The KA is for low temperature limits for Boron Concentration. This Q references an over-temperature annunciator. Is this for a high temperature or a low temperature condition? The ref does not explain well.

Stem: Is this a high Temperature or a low temperature condition?

Remove the double period from "C" and "D" fuesday, November 10,2009 Page 145 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 59 General Discussion RF A 10109/09 Revisited After revisiting this Q, I think 800F would be more plausible then 65 of. 80 is the excessive water temperature in the RWST where 65 is the min RCS cold leg temp. Consider changing and we will discuss during the onsite review.

RF A 10/29/09 CAF: The KA is for low temperature limits for Boron Concentration. This Q references an over-temperature annunciator. Is this for a high temperature or a low temperature condition? The ref does not explain well.

Stem: Is this a high Temperature or a low temperature condition?

Remove the double period from "c" and "D" RF A 10109/09 1-- --.-.- - - ----.---- ----- -----.------ -- --------

---

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

---

~-

--~-- ------

-~----.-- ----- ------- -- ----I iThe first part of the questions deals with FWST heater operations. The stem is questioning "heater" overtemperature not Tank overtemperature. This sometimes comes in during heater

[

loperation which would be energized to PREVENT the temperature from going low. Because the condition prevents ALL of the heaters from operating, the result would be a LOW

[temperature in the FWST.

lIn accordance with the Limits and Precaution for the FW system, the minumum temperature for the FWST is 70°F. This is also the low limit for OPERABILITY in accordance with TS 3.5.4, IRWST, SLC 16.9.11, Borated Water Sources - Operating, and SLC 16.9.14, Borated Water Sources - Shutdown.

I

[

[While there are no low temperature limits for boron concentration which are specific to Emergency Boration, the low temperature limit for the FWST are an operational implication tied to the loperability of that water sources and its associated flowpaths under all operating conditions including times when Emergency Boration is required. Since this is a potential source of water 1911ring~mer~~~~~01*a!i()11 __ tll~~~!J13:tc:~e~: ________ ~ ____________________________________________ ~ _________________________________ _

Answer A Discussion E~~c}

__ -__ -_--~-_~--_-~_=~~_=--___ ~ __ --__ -_-_=--_-_=~~_--_===~ _______ _

Answer B Discussion

,.----.~------

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

---

*-------------------------------~--l IIncorrect. Plausible because there are temperature indications for each individual heater group. However, a high temperature on one group of heaters trips all groups. The temperature limit for i

~e.~al>ili!Lis.. COIT~c.t.__ __ ___________________ _______ _ ____________ ~ _______________________________ ~ ___________________________________ J Answer C Discussion

[

---

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

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

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

II1~olT.:~2~i~~0~:c~ ~~t ~1~~e~t:~~()u£~t~iIJ.:_Th: ~1l1~~atu_"e_l~mi~i~~~u~i~\\(:~~c~ust:~ ~s~~ _~~111~~ ~~~

~~2e~~e~Ee!<itllTt:_ ____________________________ _

Answer 0 Discussion ii~~;rr~ct.-PI;_u~bl~b~~~~;ethe~e--;et~~~;ahI;e i~di~~ti;~; fu; ~Zh i~di~du~l--h--e~t~rg;:~~p.H~~~v~r~ ;high--t~~~rature on one gro~p of he~k;r~trip;- all--g;o~p~.--Thete~pe--;:atu--;:.;-li~it-is--

leI~u~ible !:~~llS~~~.th.e.rnJnil11l1rl1.~c:~~o~dJ~g

__ t~I11P.e~atu/'e_'______ __ ___ __ ________ _____ _____ _ __________

fuesday, November 10,2009 Page 146 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 59 General Discussion RF A 10109/09 Revisited After revisiting this Q, I think 800F would be more plausible then 65 of. 80 is the excessive water temperature in the RWST where 65 is the min RCS cold leg temp. Consider changing and we will discuss during the onsite review.

RF A 10/29/09 CAF: The KA is for low temperature limits for Boron Concentration. This Q references an over-temperature annunciator. Is this for a high temperature or a low temperature condition? The ref does not explain well.

Stem: Is this a high Temperature or a low temperature condition?

Remove the double period from "c" and "D" RF A 10109/09 1--

---~-~

-~

---

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

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

---

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

~~~~

---

.~~

--~-~

~~----~

iThe first part of the questions deals with FWST heater operations. The stem is questioning "heater" overtemperature not Tank overtemperature. This sometimes comes in during heater loperation which would be energized to PREVENT the temperature from going low. Because the condition prevents ALL of the heaters from operating, the result would be a LOW

[temperature in the FWST.

lIn accordance with the Limits and Precaution for the FW system, the minumum temperature for the FWST is 70°F. This is also the low limit for OPERABILITY in accordance with TS 3.5.4, IRWST, SLC 16.9.11, Borated Water Sources - Operating, and SLC 16.9.14, Borated Water Sources - Shutdown.

I

[

[While there are no low temperature limits for boron concentration which are specific to Emergency Boration, the low temperature limit for the FWST are an operational implication tied to the loperability of that water sources and its associated flowpaths under all operating conditions including times when Emergency Boration is required. Since this is a potential source of water 1911ring ~mer~~~L.~ol*a.ti()I~_tlleJ~~~!Jl'ltc:~e.cI:_ ~ __ ~~ _____ ~ _~~~~ ___ ~~~_~ ___ ~~ ___ ~~~ ____ ~ _____ ~ _____ ~ __ ~ ___ ~ ______ ~_~ __ ~_~~ ~

Answer A Discussion E~~C}

__ ~_ -_- ___ ~ ____ -_~~~=~ ______ -~_~_-_-~~~ ___ -_~~=~~_-~ ___ =

___ ~ ____ ~~ ___ -~-~~-_~=_-_-_______ ~ ____ =_-~_-_~~~-_

_==_~_-_-_==~~_-~~~_~~-~~_~~=-~=~=~-~-~~_-~ _____ =_-~~- ~

Answer B Discussion

,.--~.--~--~~ --------- -------------

~--

---

~.-

---

~-.~---

-~.-~~-~--

---

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

~----~*----------~---------------~---l IIncorrect. Plausible because there are temperature indications for each individual heater group. However, a high temperature on one group of heaters trips all groups. The temperature limit for i

~e.~al>ili!Lis.. COIT~c.t. __ ~_ ~_~ ________ ~~~_~_ ~~ __ ~_~ ~ ______ ~ ____ ~_~ ~_~_ ~~ __ ~ __ ~ ______ ~ ____ ~ ____ ~ ___ ~~ ________ ~ ___ ~~ __ ~_J Answer C Discussion

[~~~~~E;~~~i:~~~-~t~~-i1.~!~~~~~£~~t~i~~_Th~~~~~~~~~~1l~~~~~~~i~~~F~~~~~-~~~~~_~~~~~~~~ ~~~~~~~~ie!~~r~~_-=-~~~-~ __ ~~_~-~ ~~~=~ -__ ~~=~~-~-___ ---

Answer 0 Discussion ii~~;rr~ct.~PI;-u~bl~b~~~~;ethe~e-;et~~~;ahI;e i~di~~ti;~; fu; ~Zh i~di~du~l-h-e~t~rg;:~~p.H~~~v~r~ ;high-t~~~rature on one gro~p of he~k;r~trip;- all-g;o~p~'-Thete~pe--;:atu--;:';-li~it-is-leI~u~ible !:~~l1S~~~ihe.rnJniI11111l1.~C:~~o~dJ~g_t~l1lp~~atu/,e _____ ~ ___________ ~_~ ___ ~_ ~ ~ __ ~_____ ~ ______ ~ ___ ~ ______ ~ _____ ~ ____ ~ ___ ~ ___ ~_

fuesday, November 10,2009 Page 146 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 59

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

~qu~~!i~f!Ii~~~~ ____ ~ ___ ~~ ______ 9~e~!I()~~()~~~~ ___ ~ _______ ~~~ 401-9 Comments RESPONSE NEW I

I 10/14/09

--"-- - - -- -~-~ ~--~-- - -----~-----------~ ---~-- -- --, Revised distracter discussion to better W~!!lop~~n(~e~r!~c~!=-===-==~========1 ~~5s!~=R~~~n<:~!-~~O-;Id~~- ~~-

~~~:~!::~e:~,~;~~id ~!I~~~C~~e:\\~

iSLC 16.9.11, Borated Water Sources (Operating)

I I no double period. 11104/09 Changed 65°F

[Lesson Plan OP-MC-FH-FW Objective 6 page 23, II I to 80°F in distractors 'C' and 'D' per Chief IObjective 4 page 43 and Objective 7 page 31.

I Examiner's recommendation.

I I I I

I I I I c~

~ _________ ~ ________________________ : L ________________________ _

1.-------- ~-----,~-~---------I-~--~--- --~-----

l~~~!!()'!I!'!!l~ !'l-K.6.-=~t!!!I'l'l_J~ ___ n~u'!l.~~ - -~ --I

---

~------- ---

IKA deac I 8591APE024 iAKI.04 I

_____ ~ ____ ~ ____.l. ~ ________________ ~~_~ _~ _ ~ ___...J I~ --=--- ---- - ~-----~~------ - --- - -------~-- ~

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

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

IKnowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8 1 41.10 1 i45.3)rJLow temperature limits for born concentration....................

L __________________

~_. ___________________ ~

fuesday, November 10, 2009 Page 147 of 185 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 59 A

~~

• • ~~,--~~~~~~--~~~-~~l~~~

-~-~.~~ ~-~!.-~.-~-~~.~~~-~--~~~~~~~~~~~---~~~~~~~~

~~*~-~~-l Job Level I Cognitive Level I QuestionType I

Question Source I 401-9 Comments RESPONSE

~~*-~~~~~l--~~~~*~~~~~~*~--~~t-~~~~~-~~*----i-~~~--~~~-~*~*~~-~~*~~*~~*~*~-~~~-~-*~-~-~*-~---~-I RO Memory I

NEW I

I 10114/09

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

--~--I.~-~~ ~~ ____ ~~..l~~ ~ - ~~ -~-~ ~~-~~~ ~~--~-~~--~---~---~-~-~-~ -~ ~-. Revised distracter discussion to better

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r ~.~.~~~~

~~-.-

~ ~~

.. ~ ~.-~~ ~

~.~ ~-~.-

~'~'~~'~~'~'~I ~~~

~.~.~.'~-~~'~'~~~

~

~~ ~~

~~-

IDevelopment References IStudent References Provided r::~'~~ ~-~.~ ~ ~~~~

~.'- ~'~-~~'~-'~----~~~--~~I I~-~~~~**~-~*-*-~*~~~~ ~~-

ISLC 16.9.11, Borated Water Sources (Operating)

I I

[Lesson Plan OP-MC-FH-FW Objective 6 page 23.

II I IObjective 4 page 43 and Objective 7 page 31.

I I

I I I

I I I I c~

~ _________ ~ _________________________ : L ________________________ _

r:~~--~~-.

~*~~-,~*~~*~*--~**~~~I~~-~~~-* ~-~~~-~,

explain low temp angle. Will discuss with Ron when on site, should be OK. There is no double period. 11104/09 Changed 65°F to 80°F in distractors 'C' and 'D' per Chief Examiner's recommendation.

l~~~!!<>.'!I!'!!l~ !'l--K.6.-=~t!!!I'l'l_J~ ___ n~u'!l.~~ ~ ~~

~-l I 8591APE024 iAK1.04 I

IKA deac I~ -=-.- ~.~~ - ~.~-.--~~~--~- ~ ~-- ~ -~---~~~~- ~

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

_ ~._.~ ~._~~ __ ~ _.1. ~_~ ~ ~

__.~~.~~~ ~~~ ~~.~ _~

~ ~.~~...J IKnowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8 1 41.10 1 i45.3)rJLow temperature limits for born concentration....................

L __________________

~_. ___________________ ~

fuesday, November 10, 2009 Page 147 of 185

FOR REVIEW ONLY - DO N A

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 60 1tQ."""~~s~====-=-=-=-===========::::::::_=::::::::=::::=_=::::::::=::::::::::::==::::==-=-::::=--=::::=::::::::====-=::::=::::==::::::::::::-=::::::::t

[Ability to detennine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alanns: (CFR: 43.5 11 lc;}~estionBanki1KA system -IKAn-Umber I~~ ~----- ----+~-=- ~---~-~+--=- --~-----------

I 1860 I

APE061 I

AA2.04 l~ _________ ~_~l ___ ~~ ______ I ____ ~~

___ ~

____ ~ __

~~~3)C\\y~e!l1e~<lll~Ifl~~~n~li~~~!i~~£Ef~~I"ly~",-*",-:",-*",-*",-* ____ *",-* ____ ~~~_~~ __ ~ ________ ~ ____ ~ ______ ~J CURRENT Given the following conditions on Unit 1 :

Unit is in Mode 6 The reactor is being defueled The following alarm has JUST been received in the Main Control Room:

o "1EMF-16 (CONTAINMENT REFUELING BRIDGE)" annunciator Which ONE (1) of the following alarms could be used to confirm that the 1EMF-16 alarm is valid?

A B.

C.

1 EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator OR SPENT FUEL POOL LEVEL LOW computer alarm.

INCORE INST ROOM SUMP HI LEVEL alarm OR HIGH FLUX AT SHUTDOWN alarm.

1EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator OR 1EMF-51 (REACTOR BUILDING ACTIVITY) alarm.

D.

1 EMF-51A (REACTOR BUILDING ACTIVITY) alarm OR SPENT FUEL POOL LEVEL LOW computer alarm.

APE061AA2.04 45 DAY VERSION Given the following conditions on Unit 1 :

Unit is in Mode 6 The reactor is being defueled The following alarm has JUST been received in the Main Control Room:

o "1EMF-16 CONTAINMENT REFUELING BRIDGE" annunciator Which ONE (1) of the following alarms could NOT be used to confirm that the 1EMF-16 alarm is valid?

(CONSIDER EACH OF THE FOLLOWING ALARMS SEPARATELY)

A 1 EMF-51A (REACTOR BUILDING ACTIVITy) alarm B.

1 EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator C.

(SPENT FUEL POOL LEVEL LOW) computer alarm D.

(lNCORE INST ROOM SUMP HI LEVEL) annunciator 401-9 Comments:

If you wanted to write this W/O it being a NOT Q, consider the following:

WOOTF alarm(s) can be used to confinn that the lEMF-16 alarm is valid?

A.

lEMF-17 annunciator or SFP level Low computer alann fuesday, November 10, 2009 Page 148 of 185 A

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 60 f~e~Io~~~r!k)J~ji~~=~~~~~~===-==~ItQ."""~~s~==================::::=_==::::===_=::::::::==::::::::::::::::::::==-=-::::-:-:::::===========-===::::::::==::::::::~

1 1860 I

APE061

_I AA2.04 _

I [Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: 43.5 I I 1 _____________ l ____ --- -

1----------- ----. 145.13)CWhether an alarm channel is functioning properly.....................

I

'----- ---~- -- _._--------.-.--------- --~- ---------- - --- ------.--------------- - ---- -~--------- -

~-~

CURRENT Given the following conditions on Unit 1 :

Unit is in Mode 6 The reactor is being defueled The following alarm has JUST been received in the Main Control Room:

o "1EMF-16 (CONTAINMENT REFUELING BRIDGE)" annunciator Which ONE (1) of the following alarms could be used to confirm that the 1EMF-16 alarm is valid?

A B.

C.

1 EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator OR SPENT FUEL POOL LEVEL LOW computer alarm.

INCORE INST ROOM SUMP HI LEVEL alarm OR HIGH FLUX AT SHUTDOWN alarm.

1EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator OR 1EMF-51 (REACTOR BUILDING ACTIVITY) alarm.

D.

1 EMF-51A (REACTOR BUILDING ACTIVITY) alarm OR SPENT FUEL POOL LEVEL LOW computer alarm.

APE061AA2.04 45 DAY VERSION Given the following conditions on Unit 1 :

Unit is in Mode 6 The reactor is being defueled The following alarm has JUST been received in the Main Control Room:

o "1EMF-16 CONTAINMENT REFUELING BRIDGE" annunciator Which ONE (1) of the following alarms could NOT be used to confirm that the 1EMF-16 alarm is valid?

(CONSIDER EACH OF THE FOLLOWING ALARMS SEPARATELY)

A 1 EMF-51A (REACTOR BUILDING ACTIVITy) alarm B.

1 EMF-17 (SPENT FUEL BLDG REFUEL BRIDGE) annunciator C.

(SPENT FUEL POOL LEVEL LOW) computer alarm D.

(lNCORE INST ROOM SUMP HI LEVEL) annunciator 401-9 Comments:

If you wanted to write this W/O it being a NOT Q, consider the following:

WOOTF alarm(s) can be used to confirm that the lEMF-16 alarm is valid?

A.

lEMF-17 annunciator or SFP level Low computer alarm fuesday, November 10, 2009 Page 148 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 60 B.

Incore Inst Room Sump Hi Level or IEMF-5IA alann C. IEMF-17 annunciator ONLY D. IEMF-5IA alarm ONLY RF A 10/29/09 General Discussion

[For IEMF-16, oth~~id ~l;~;-;hicl; couldb;;-~s~dt~~o~finn that the alann is valid are:

I IIEMF-17 (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

ISpent Fuel Pool Level Low (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

IIncore Inst Room Sump Hi Level (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

[Any Unit Vent or Spent Fuel Building Ventilation monitor alann (indicating fuel damage)

I A

i IEMF-5IA would not be a valid alann to confinn that I EMF-16 is valid since it is a high range alann and should not be in alarm if IEMF-16 has just been received.

I I IK/A is matched because the applicant must know which redundant indications can be used to evaluate whether the alarming Area Radiation Monitor is functioning properly.

I

!ouestion is comprehensive because the candidate must evaluate the validity of a given alarm against a set of alternate indications.

1&~~iil~2~~~is-'l~est~~~~~e_<lll~I)'fl~le~~ ______________ ~ _____________. _______. __ _

This process of understanding the relationships between the Answer A Discussion

[C~~~~f*=======*=-_=~ __. __.. _____ _

Answer B Discussion

~~~~~-;;':!~;ll-;~~~~~~:!~~~:~R~~~s~i~-E~~~-;;l-~-~~~~t~d~~e_a£1~~iln~~lll~~~~,,-et~~t~~~i!~u~~~S~llt~~\\V~~()Il~d~~u:=-il.!~~~. __ I~iil~ITl1~\\V.e~:

Answer C Discussion IIncorrect. Plausible because IEMF-17 is correct. IEMF-51 is plausible since it detects a high radiation level in containment. However, it is not reasonalbe to believe that lEMF-51 would be

[ill ~~Jl1.tl1is.c:o..~i!i~n.. ____________.. _______________._~_

Answer 0 Discussion

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

Tuesday, November 10, 2009 Page 149 of 185 FOR REVIEW ONLY - DO DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 60 B.

Incore Inst Room Sump Hi Level or IEMF-5IA alarm C. IEMF-17 annunciator ONLY D. IEMF-5IA alarm ONLY RF A 10/29/09 General Discussion r;;-r~IEMF-16~~th~~id ~I~r~-;-;hicl; could~~s~dt;;-~o~fi~ thatth;~i;~i~ ~lid ~--=------ ~-------------------------- -----~ ------------1 I IIEMF-17 (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

ISpent Fuel Pool Level Low (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

IIncore Inst Room Sump Hi Level (indicating a loss of Refueling Cavity and Spent Fuel Pool Level)

[Any Unit Vent or Spent Fuel Building Ventilation monitor alarm (indicating fuel damage)

I i IEMF-5IA would not be a valid alarm to confirm that I EMF-16 is valid since it is a high range alarm and should not be in alarm if IEMF-16 has just been received.

I I IKiA is matched because the applicant must know which redundant indications can be used to evaluate whether the alarming Area Radiation Monitor is functioning properly.

I

!ouestion is comprehensive because the candidate must evaluate the validity of a given alarm against a set of alternate indications. This process of understanding the relationships between the 1&~11..ii1~.P~~~is3.~est~.fl.<l.I1..!/1.e_<lll~I)'fl~.!e~~ _________________________ ~ ____ ~ ____ ~ ____________. _______________ _

Answer A Discussion c------*--~ -----.. -

~-

-.-~--

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

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

---

.-------.---------------.~----------,

lC_O_~~~,!,._~ ~ ___ ~ ______________ ~ _________________________________________ ~ ___________________________ J Answer B Discussion

---

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

---

~--.--.-

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

~.--.- ------------ - --------1 II~~o~ec.: !~alls~bIe_ b~c_a~s: !~~r: IZ~o_~S~~~2.f~~e~el !:~~f!"e~t ~d~~e_a£1~~iln~~lll~~:I~"_et~~t~~~i!~u~.t\\~S~~t~~\\V~ ~()Il~d~~u:=_(l}~~~ ___ l~ <tI~fIl1~~e~~ ____________ J Answer C Discussion II~~;~ct."Pla~;;bI;b~c~~~~ 1 EMF-Ii i~~~~ct.-IEMF:51 i-;pI~~ibk~i~~itd;;ct;a high~adi~ti;;-n I~~I-i;~;rt;i;m~;;t~ ifu~~;e~Ttis -;~t~e-;;~~al~ tobeli~~h~EMF=5T;0~id 1;;-:

lil1~~Jl1..tI1is.c:o...~i!i?.~ ________________________ ~ _____________._. _________________. _____________._._. ___________ ~ _____ J Answer 0 Discussion II~~orr;ctPJ;;~ibk:_;ince-Sp~ntF~~iPo~ILe~eIL;;;I;~ is c~~e;;i~iEMF-5Ii;pia~;;bi~;j~c;it dete~~-;;high-r_;diati;;_nl~;eIi~;;ontain~~~tH~~~iti;~~t r~ason~b~~bcli;v~ th;t-:

I IEMF-51 would be in alarm in this condition.

I 1 ___.. __.. _____ ~ ____ ~ _______ ~ ____ ~ __ ~ _____. __

~ _____. _________._.___

_.~ ____. _____. ___________

. ___ ~ ___________________

Tuesday, November 10, 2009 Page 149 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 60 Cognltlve-Level-~-T-QuestlonTYpe-1---~ -- -- -

Question Source

~~~~~~~~~====t=~~=~~===I=========~~---~ -~-----~~- ----~-

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IDevelopment References 1-,------,- --,--- '-'---~'----

lAP-40, Loss of Refueling Cavity Level page 2 IIAP-25, Spent Fuel Damage page 2 I

I L-_, __

fsiu(ientReferences Provided r ----~-------~

--'-~--

I 1

I I l __

A 401-9 Comments RESPONSE Wrote this as a 'NOT' question due to the diffuculty in coming up with sufficient plausible distractors. In the suggestion offered by Chief Examiner answers 'A' and

'C' are both correct. Discuss further with Chief Examiner during on-site review.

~U'e!~~aE~!~~!~te~_~~~n~rll1i!~=-~===~ ~~~:d!~==~ _______ _

I I 860lAPE061

[AA2.04 1 lAbility to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR:

~ -

-,,'--- -~---.,- _____ ~

_L ___________, __,~_" 143.5/ 45. I 3)DWhether an alarm channel is functioning properly l __ ~ _____, ____ ~ __, ____,_' ____ ~_, __, __, ______, _____ _

'uesday, November 10, 2009 Page 150 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 60

[}~~L-e~!L~I _________ C~~IE~!1!~!C::::::I ___ g~~s~~~Tip~ ___ +-_________ ~ _______ ~. ___ =-______ :::= ___ ~i~~n:::~~iC_;= ___ =_ ___ =__~= ______ ::::::-

I RO 1

Comprehension NEW I

'-_____ ~_~ __ l_ ~ __

~ ____________ L_~ ___ ~_~ __

~ ___ ~_~ ________

~ __ ~ ___

~ _____

~_~ __

~~ ___________ _

A 401-9 Comments RESPONSE Wrote this as a 'NOT' question due to the diffuculty in coming up with sufficient

__ - _____ ~_~ _____ ~_~_ --- --~_~_~ ___ -

-~---~-, ~ _________ _ ____ -

plausible distractors. In the suggestion 1Il!\\If!-'<>p-,!!~n~~!~_re_n~e_s _____ ~______ _

f~~<!~"!~~~!~nces Provided offered by Chief Examiner answers 'A' and

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved IAP.40, Loss of Refueling Cavity Level page 2

'C' are both correct. Discuss further with IAP-2S, Spoof Fud Dmn""" P"I<' 2 I

i Ch;d'E"m;n" dud", on-,;" "';'w II I

I I

1 L- _~ ______._~_~~ ____ ~ __________ ~ ___ ~_

l_~~ _____.~ ________________ -1

~U_e!~~aE~ !~~!~te~_~

~~n~rll1i!~ ______ :::=::: ~ ~~~:d!~:::=:::=:::---------:::---::::::=== ___ :::====-::::::::::::::: =::::::=-= ______ ::: ___ ~

______ ::: ___ :::== ___ ~::::::::: ___ :::==-___ ::: =::::::---J I

I 860lAPE061 lAA2.04 1 lAbility to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: I

~ - -~~--- -~---~.~- --------'------------.--.---" l143.5 / 45. I 3)DWhether an alarm channel is functioning properly.....................

I

- --- --~--~--------- -- -------- -------------- ------------- ----.-- ~------- ----~-----------,

'uesday, November 10, 2009 Page 150 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 61 A

IQuestionBank # IKA system IKA number I KA desc I

1861 I

APE067 J AK3.02 J Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.1 0/45.6/ 45.13)OSteps called out in the site fire protection plan, FPS manual, and fire zone manual.......................,....... '".....

CURRENT 45 DAY VERSION Unit 2 was operating at 100% power when an electrical fire started inside the auxiliary building cable spreading room. AP/OIAJ5500/45 (Plant Fire) has been implemented.

If a fire was reported in the McGuire Office Complex (MOC), which one of the following responses is correct by station procedures?

Which ONE (1) of the following describes how the fire suppression system is actuated AND the hazards to personnel if they enter this room?

A.

Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade may provide limited support if resources allow.

A.

B.

C.

D.

An NLO is dispatched to open a manual deluge valve. An electrical shock hazard exists.

Automatic sprinkler system actuation. An electrical shock hazard exists.

Automatic Halon system actuation. An asphyxiation hazard exists.

An NLO is dispatched to actuate a manual Cardox system. An asphyxiation hazard exists.

APE067AK3.02 B.

C.

Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade cannot respond to any events outside the protected area.

Fire Brigade members are responsible for fire suppression activities at the scene. An offsite fire department may be called to provide support if additional resources are required.

D.

Fire Brigade members are responsible for fire suppression activities at the scene. They are required to turn over control of the scene as soon as an offsite fire department arrives and immediately retum to the protected area.

401*9 Comments:

According to the reference (OMP 2*2, Page 13,) A and B are both correct.

If that is not so then:

Change the 2nd part of A to "The fire brigade will respond."

Change the 2nd part ofB to "The fire brigade will NOT respond."

Thursday, November 12,2009 Page 151 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 61 A

IQuestionBank # IKA system IKA number I KA desc I

1861 I

APE067 J AK3.02 J Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.1 0/45.6/ 45.13)OSteps called out in the site fire protection plan, FPS manual, and fire zone manual.......................,....... '".....

CURRENT 45 DAY VERSION Unit 2 was operating at 100% power when an electrical fire started inside the auxiliary building cable spreading room. AP/OIAJ5500/45 (Plant Fire) has been implemented.

If a fire was reported in the McGuire Office Complex (MOC), which one of the following responses is correct by station procedures?

Which ONE (1) of the following describes how the fire suppression system is actuated AND the hazards to personnel if they enter this room?

A.

Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade may provide limited support if resources allow.

A.

B.

C.

D.

An NLO is dispatched to open a manual deluge valve. An electrical shock hazard exists.

Automatic sprinkler system actuation. An electrical shock hazard exists.

Automatic Halon system actuation. An asphyxiation hazard exists.

An NLO is dispatched to actuate a manual Cardox system. An asphyxiation hazard exists.

APE067AK3.02 B.

C.

Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade cannot respond to any events outside the protected area.

Fire Brigade members are responsible for fire suppression activities at the scene. An offsite fire department may be called to provide support if additional resources are required.

D.

Fire Brigade members are responsible for fire suppression activities at the scene. They are required to turn over control of the scene as soon as an offsite fire department arrives and immediately retum to the protected area.

401*9 Comments:

According to the reference (OMP 2*2, Page 13,) A and B are both correct.

If that is not so then:

Change the 2nd part of A to "The fire brigade will respond."

Change the 2nd part ofB to "The fire brigade will NOT respond."

Thursday, November 12,2009 Page 151 of 186

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 61 General Discussion As written, the question is leading the applicant to the correct answer.

Currently, the Q is U because of two correct answers.

RFA 10129/09 A

OP-MC-SS-RFY (p37) states that manually operated MulsifYre systems are provided for the Unit 1 and Unit 2 cable rooms and ETA HV AC equipment rooms. These systems are further described as "Consisting of a number of open spray nozzles with locked closed manual isolation valves."

The KIA is matched because it requires the applicant to know the procedure requirements related to initiating the fue suppression system for the auxiliary building cable spreading room.

Answer A Discussion ICORRECT J

Answer B Discussion Incorrect. Plausible: Extensive use of Automatic deluge systems is employed at McGuire, typically protecting systems containing oil, or other class B fuels, as well as ventilation systems.

This system is not automatically operated OP-MC-SS-RFY (p37)

Answer C Discussion Incorrect. Plausible: Halon I301 Total Flooding systems are used in the DG Rooms, the CA Pump rooms and the Computer Room in the Admin Building. Plausible because Halon does provide protection against electrical fires by removing oxygen OP-MC-SS-RFY.

Answer D Discussion Incorrect. CARDOX gas is a personnel hazard - although all the CARDOX systems have been replaced with HALON, the pull switches still say CARDOX in some areas (like the diesel generators). Also storage areas on site with CARDOX systems.

Job Level Cognitive Level QuestionType Question Source 401-9 Comments RESPONSE Question replaced after final site review due to original question being SRO level knowledge. Approved RFA 11112/09 RO

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory QuestionBank # iKA system 186 I IIAPE067 Thursday, November 12,2009 BANK MNS Exam Bank Development References

IStudent References Provided Lesson Plan OP-MC-SS-RFY pages 37, 47, 49, 51, and i 53 i

i KA number KA desc AK3.02 Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 4/.5,41.10 1 45.61 45.13)CISteps called out in the site fire protection plan, FPS manual, and fire zone manual.......................................

Page 152 of 186 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 61 General Discussion As written, the question is leading the applicant to the correct answer.

Currently, the Q is U because of two correct answers.

RFA 10129/09 A

OP-MC-SS-RFY (p37) states that manually operated MulsifYre systems are provided for the Unit 1 and Unit 2 cable rooms and ETA HV AC equipment rooms. These systems are further described as "Consisting of a number of open spray nozzles with locked closed manual isolation valves."

The KIA is matched because it requires the applicant to know the procedure requirements related to initiating the fue suppression system for the auxiliary building cable spreading room.

Answer A Discussion ICORRECT Answer B Discussion Incorrect. Plausible: Extensive use of Automatic deluge systems is employed at McGuire, typically protecting systems containing oil, or other class B fuels, as well as ventilation systems.

This system is not automatically operated OP-MC-SS-RFY (p37)

Answer C Discussion Incorrect. Plausible: Halon I301 Total Flooding systems are used in the DG Rooms, the CA Pump rooms and the Computer Room in the Admin Building. Plausible because Halon does provide protection against electrical fires by removing oxygen OP-MC-SS-RFY.

Answer D Discussion Incorrect. CARDOX gas is a personnel hazard - although all the CARDOX systems have been replaced with HALON, the pull switches still say CARDOX in some areas (like the diesel generators). Also storage areas on site with CARDOX systems.

Job Level Cognitive Level QuestionType Question Source 401-9 Comments RESPONSE Question replaced after final site review due to original question being SRO level knowledge. Approved RFA 11112/09 RO

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Memory QuestionBank # KA system 186 I IIAPE067 Thursday, November 12,2009 BANK MNS Exam Bank Development References i Student References Provided Lesson Plan OP-MC-SS-RFY pages 37, 47, 49, 51, and i 53 i

i KA number KA desc AK3.02 Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 4/.5,41.10 1 45.61 45.13)CISteps called out in the site fire protection plan, FPS manual, and fire zone manual.......................................

Page 152 of 186

C FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 62 DISTRIBUTE I~ ~.~-

-.~ _... -

~~~~~

~~.~~~[-~~.~~~~-.. -

~~~~ll**--**~~-~~~~-

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~

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~~~~~~~~~~~~~-~~~~~~-l CURRENT 45 DAY VERSION Which ONE (1) of the following describes the expected method of Pressurizer level control, in accordance with AP-24 (Loss of Plant Control Due to Fire or Sabotage)?

A B.

C.

D.

Maintain level at 25% by cycling the Standby Makeup pump and by letdown flow through the Reactor Vessel Head vents (NV-272 and NV-273).

Maintain level between 60-80% with either Normal or Excess Letdown flow and manual adjustment of Charging Line Flow Control valve (NV-238) and NCP Seal Injection flow (NV-241).

Maintain level between 60-80% through adjustment of the Reactor Vessel Head vents (NV-272 and NV-273) with charging supplied by the Standby Makeup pump through the NCP seals.

Maintain level at 25% utilizing letdown flow through Normal or Excess Letdown and manual adjustment of Charging Line Flow Control valve (NV-238).

APE068G2.1.28 No comment at this time RF A 10/29109 Tuesday, November 10, 2009 Which ONE (1) of the following describes the expected method of Pressurizer level control, in accordance with AP-24 (Loss of Plant Control Due to Fire or Sabotage)?

A B.

C.

D.

Maintain level approximately 25% by cycling charging (Standby Makeup pump Start/Stop) and letdown flow (Reactor Vessel Head vents, NV-272 and NV-273).

Maintain level between 60-80% with either Normal or Excess Letdown flow and manual adjustment of Charging Line Flow Control valve, NV-238 and NCP Seal Injection flow, NV-241.

Maintain level approximately 60-80% through adjustment of the Reactor Vessel Head vents. NV-272 and NV-273, with charging supplied by the Standby Makeup pump through the NCP seals.

Maintain level approximately 25%. utilizing letdown flow (Normal or Excess Letdown) and manual adjustment of Charging Line Flow Control valve, NV-238.

401-9 Comments:

Page 153 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 62 Which ONE (1) of the following describes the expected method of Pressurizer level control, in accordance with AP-24 (Loss of Plant Control Due to Fire or Sabotage)?

A B.

C.

D.

Maintain level at 25% by cycling the Standby Makeup pump and by letdown flow through the Reactor Vessel Head vents (NV-272 and NV-273).

Maintain level between 60-80% with either Normal or Excess Letdown flow and manual adjustment of Charging Line Flow Control valve (NV-238) and NCP Seal Injection flow (NV-241).

Maintain level between 60-80% through adjustment of the Reactor Vessel Head vents (NV-272 and NV-273) with charging supplied by the Standby Makeup pump through the NCP seals.

Maintain level at 25% utilizing letdown flow through Normal or Excess Letdown and manual adjustment of Charging Line Flow Control valve (NV-238).

APE068G2.1.28 No comment at this time RF A 10/29109 Tuesday, November 10, 2009 Which ONE (1) of the following describes the expected method of Pressurizer level control, in accordance with AP-24 (Loss of Plant Control Due to Fire or Sabotage)?

A B.

C.

D.

Maintain level approximately 25% by cycling charging (Standby Makeup pump Start/Stop) and letdown flow (Reactor Vessel Head vents, NV-272 and NV-273).

Maintain level between 60-80% with either Normal or Excess Letdown flow and manual adjustment of Charging Line Flow Control valve, NV-238 and NCP Seal Injection flow, NV-241.

Maintain level approximately 60-80% through adjustment of the Reactor Vessel Head vents. NV-272 and NV-273, with charging supplied by the Standby Makeup pump through the NCP seals.

Maintain level approximately 25%. utilizing letdown flow (Normal or Excess Letdown) and manual adjustment of Charging Line Flow Control valve, NV-238.

401-9 Comments:

Page 153 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 62 General Discussion

~n-~~~d~~-;;-~ithAPli4~th~~~;-a~~*;rtth~-SSF~ill~~ntr~lp;-e~uri~~Te~clby q~l~g th-;;-R;;-a-Zt~r-Ve;s~I-H~;d~~~ts~Ch~~i;;gTs~~pi~dbithe-St~dbYM~ke~pP~~pth~~ughthe NC IPump Seals.

!rhiS KIA is matched because the applicant must know the function of various components during a scenario when the Control Room must be evacuated and controlled from a remote facility.

IlIn this case the applicant must know the difference in how components function when operated from the SSF as opposed to the ASP.

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

-~------

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

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

Answer A Discussion IIncorrect. The level is plausible as it is the correct level that would be maintained if the plant was being controlled from the ASP in accordance with AP1l7. Charging is via the standby I

Imakeup pump but it remains in operation and is not cycled.

Ii L __._. ___._.. __. ____________._. ________________. _____.. ____________. ____________________. ________. __. ______._ ----. ___ ------ ________ ---- ---

Answer B Discussion 1-*-*------ ---.- ------- - - ---.----- -- ----- --------.------ ------ --.----- ---- ----------.. ----- ---------.---.--.-------

IIncorrect. Correct level wrong flowpath for letdown flow and wrong flowpath for charging. Flowpaths are plausible because they are the normal flowpaths for letdown or charging.

L _____________

• _____________________________

~

Answer C Discussion r::.--- ------- --------

ICORRECT.

---

-.--- --- ---l Answer 0 Discussion rI~c~~ct~ W rongk~~1 ~d ~~~ngfl~;path;.i~~~l-i~pl~u~ilik~thi;isth~-l~v~lif th~pI~t ~;s-b~i~g~~t~II~d

-fr~m th~ASP:F~~p;rths-a;e-pI~~hle as they are normal charging and l~etd~\\\\,~ f!o..WjJilt!IS.___ _ _ ---*----------

Cognitive Level QuestlonType i Question Source

---

+ - -----

---

.--r------.-.---------------------- --.---.---~---

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved B~~K

____ 1_ __ _________ ~NS Bank Question CPSS006 r------~--------**-----------------, c------- -

I

~~!I.<>PIll!fl!. ~e!!.f!fl~!8 __________ ~ ___ ~ i~t!'!i.!.n!~.!!.el'e_nE!S_~~'!'I~!'! __ ~ ___ I IAP124, Loss of Plant Control Due to Fire or Sabotage, I I Ipage 7 and 9 i II I

I I

I I I

I I I

I I l _______________. ______. _______________ J L 401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

~~~~t!()n~~i~fA!i~!~--JtS~-.~i"~~ei~~~--=1 ~:~!~C~~ ~~~ ~~~~~~~~_~~ ~=~== ~~~~=~=~~_-~~~-_-= ~

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_ _____ ___ _ 18_6~~~~~6! ___l~~~s.. _________ J :~I~O~~ 9~~~~~_[J_Kn~\\\\1I=dge~E~ey~~.<>~e_~~ fu~cti()n_oEll1i~J~rs2's~ell1!~I11~o~ents~~~co~t~o~~ (~Flt:~* ~) ___ _

Tuesday, November 10,2009 Page 154 of 185 FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 62 General Discussion

~n-~~~d~~-;;-~ithAPli4~th~~~;-a~~-;rtth~-SSF~ill~~ntr~lp;-e~uri~~Te~clby q~l~g th-;;-R;;-a-Zt~r-Ve;s~I-H~;d~~~ts~Ch~~i;;gTs~~pi~dbithe-St~dbYM~ke~pP~~pth~~ughthe NC IPump Seals.

!rhiS KIA is matched because the applicant must know the function of various components during a scenario when the Control Room must be evacuated and controlled from a remote facility.

lII1~hi~c~seJ.~~IJP!i~aIlt_l11l1~t _kJ1c~w_tlle_dit!e!eE~j~~~ c0I11E.0E(:llt_SJljll~!io~~h~~<pera~<L f.l'~~~e_~S£.!l~£~~ei.!<0~e_~S!'~ _______ ~

Answer A Discussion r--------------~-------------------------~-----~~-----------------------------~-----------------------------------

IIncorrect. The level is plausible as it is the correct level that would be maintained if the plant was being controlled from the ASP in accordance with API I 7. Charging is via the standby I

kn.a~e_uE.£u..mjJb~tJt.!_(:r~ai.n~~n.<p~llti9E~Il(U~ I19tcJ~It:.ct.-. ________________________________________________________________________ J Answer B Discussion 1---------- ----- ------- - -

~-------- -- ----- --------------- ------ -------~ ---- ----------------- ---------------------- --------1 IIncorrect. Correct level wrong flowpath for letdown flow and wrong flowpath for charging. Flowpaths are plausible because they are the normal flowpaths for letdown or charging.

I L ___________________________________________

~ ________ ~

____________________________

• ___________________________________ ~

_______________ J Answer C Discussion r::----------------- -----------------------

-~---------- -- ------------ ----------------- - -------------- -- -------------- ----- --- ---l ICORRECT.

______________________________. __________. ___

• __

• _____________

• ________. _____________________________________________ ~

__________________________......J Answer 0 Discussion 1- ------~-------------------- -------------- ------------ ---------- ------- --------------------------- ----------- ---

-~---

IIncorrect. Wrong level and wrong flowpaths. Level is plausible as this is the level if the plant was being controlled from the ASP. Flowpaths are plausible as they are ~rmal clta~i~g and -

I l~etd.<-J\\\\'l1..fl.O"'WjJil.t~s. ____. _____________________ ~

________ ~

____________________ ~ _____ ~

____________________________________ J

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r-----------------------------------, c--------

---

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

100veiopment References 1 IStudent References Provided 1--------------- -- ---- --.----- --- - -------~----j 1----------------- ---------- ---

IAP124, Loss of Plant Control Due to Fire or Sabotage, 1 I (page 7 and 9 1 I 1

1 1

I 1 1

I 1 l ______________________________________ J L ________________________ _

\\, ------- --------1---

---

~------ ----------1 r;:; -------- --- -------- ----------------- ------- -------------- ------------- --- ---- ----------

LCl.u~tlt!<>.n_~!'J( I#.IK_~!~~!rn_ Jt5~..,..'!'_'.!"~e_". __ _I IKA_desc

r; I -

_________ 18_6~~~~~6! ___J~~~s.. ___ ~ _____ J I~I~O~~ 9~~~~~_[J_Kn~\\\\1I=dge~E~ey~~*po~e_llI1.~ fu~cti()n_oEIl1<Y_~rs2's~ell1!~I11~o~ents~~~c0l1.t~o~~ (~Flt:~* ~) ___ _

Tuesday, November 10,2009 Page 154 of 185

C FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 63

---

'-------'--~-'-------1I--------'--'-----1-----'----,--,-,---,------------------------------------------------------------

IQuestionBank # IKA_system KA_oumber IIKA_desc i

I"--'---'----I---------~'---'------'----If"--------------,---------,-----,-------,-----------,--,-,------,-----,---,----,--j i

1863 I

WE03 1

EK3.2 IlKnowledge of the reasons for the following responses as they apply to the (LOCA Cooldown an~ Depre~surization)

I L_, __ --,---~----- -------- ------ ----~ I(CFR: 41.5/41.10, 45.61 45. 13)DNormal, abnormal and emergency operatmg procedures associated With (LOCA Cooldown and 1P~~e~sllI"i~tio~L __________________________________________________________ J CURRENT Which ONE (1) of the following describes the basis for establishing conditions so that only one NC pump is running during the performance of ES-1.2 (Post LOCA Cooldown and Depressurization)?

1. Minimize house electrical loads

2. Provide normal Pressurizer Spray

3. Eliminate stratification in the S/Gs

4. Provide mixing of NC system water

5. Minimize NC system heat input A

2,3,5 B.

1,2,4 C.

2,4,5 D.

1,2,3 ruesday, November 10, 2009 WE03EK3.2 No comment at this time RF A 10/29109 45 DAY VERSION Which ONE (1) of the following describes the basis for establishing conditions so that only one NC pump is running during the performance of ES-1.2 (Post LOCA Cooldown and Depressurization)?

1. Minimize house electrical loads

2. Provide normal Pressurizer Spray

3. Eliminate stratification in the S/Gs

4. Provide mixing of NC system water

5. Minimize NC system heat input A

2,3,5 B.

1,2,4 C.

2,4,5 D.

1,2,3 401-9 Comments:

Page 155 of 185 C

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 63

---

'-------'--~-'-------1I--------'--'-----1-----'----,--,-,---,------------------------------------------------------------

IQuestionBank # IKA_system KA_oumber IIKA_desc i

I"--'---'----I---------~'---'------'----If"--------------,---------,-----,-------,-----------,--,-,------,-----,---,----,--j i

1863 I

WE03 1

EK3.2 IlKnowledge of the reasons for the following responses as they apply to the (LOCA Cooldown an~ Depre~surization)

I L_, __ --,---~----- -------- ------ ----~ I(CFR: 41.5/41.10, 45.61 45. 13)DNormal, abnormal and emergency operatmg procedures associated With (LOCA Cooldown and 1P~~e~sllI"i~tio~L __________________________________________________________ J CURRENT Which ONE (1) of the following describes the basis for establishing conditions so that only one NC pump is running during the performance of ES-1.2 (Post LOCA Cooldown and Depressurization)?

1. Minimize house electrical loads

2. Provide normal Pressurizer Spray

3. Eliminate stratification in the S/Gs

4. Provide mixing of NC system water

5. Minimize NC system heat input A

2,3,5 B.

1,2,4 C.

2,4,5 D.

1,2,3 ruesday, November 10, 2009 WE03EK3.2 No comment at this time RF A 10/29109 45 DAY VERSION Which ONE (1) of the following describes the basis for establishing conditions so that only one NC pump is running during the performance of ES-1.2 (Post LOCA Cooldown and Depressurization)?

1. Minimize house electrical loads

2. Provide normal Pressurizer Spray

3. Eliminate stratification in the S/Gs

4. Provide mixing of NC system water

5. Minimize NC system heat input A

2,3,5 B.

1,2,4 C.

2,4,5 D.

1,2,3 401-9 Comments:

Page 155 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 63 General Discussion

,-.---------- --.--.-------- --~--------~- --.-----.-----------.-------"-- ~- -.--- ----.- --.---- ---- ---.---- --- -- - ----------"------- ----.- ----------1 IOnce NC subcooling, Pzr level, and other NC support conditions are established, a NC pump can be started if no NC pumps are running. If more than one NC pump is running, all but one I

lare stopped to minimize NC heat input. The NC pump restarted (or left running) is used to provide normal Pzr spray and mix the NC.

I IlThe KJA is since the applicant must have knowledge of the basis for the major action category in ES-I.2, Post LOCA Cooldown and Depressurization.

i

---

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

Answer A Discussion I[T.n~o~-;;ct:-Pl~~~ible ~~~ ~isthe~

p~~~ry~~~o~-f~r -e~t~bli~hi~~;iY -;;;;-e~Nci~;;-~~-:-~-;;- &--;'3';-a~e~pl~;;hl~~n~~th~y-~-;:e~b~;-e;-fu;:-~aJo-;:~cti;;~~ in -ofu~r-E~~e~g~;~y P;;;~ed;;-;~s-:-

---

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,--~---------~------

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Answer B Discussion 1i~~~~t.PI~~~hle

~in~~ 2 ;nd4~ar~ ~;~e~t_:_ A.l;o-I-i~ ~b~;; fo~ ;~j-;;~~ti~n-;i; othe-;:E~~;g;n~y Pr~~d~;-;~~* ---- - ~~- ~ -- --- ~~ -~~-

L ____ ~ ___ ~. __ ~ ~.~~~ ___ _

Answer C Discussion

[CORREcT. --- -~~ -- -- ~ -~--

L_~ ~ _____. __ ~~ ~

Answer D Discussion 1-----

IIncorrect. Plausible since 2 is correct. Also I and 3 are bases for major actions in other Emergency Procedures.

t __ ~ ~_~ ~~ __. ___ ~~ ~ ____ ~ ____ ~ __ ~~ ___ ~

___ ~~~ __

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Q~estlonTypeT~~ --~-~~-~--~~-Questlon Source

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~!V~~PI1l~Il! ~!f~!6~n~!!_~ ~~ __ ~ __ ~ ___ ~J LS~,!~~~ ~'!!!\\"e~n£!s Provided ILesson Plan OP-MC-EP-EI Objective 3 II I

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~-

-~~.~ -

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

~~~---~~*--~---~--t t~*- -.. -~.~.-

401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

QuestionSank # IKA_system IKA_number I IKA_desc

- ~-~.- ---~-+---.~~ -.-~~-f"_~.~-~-~~~--~--- - -j ~-~-~ -~-

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

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

I 8631WE03

.. IEK3.2 I IKnowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)

- ~~~~-

~ - -- -

- ---- -~-- - -.J~_ ~ ~--- - - -- ~~--

~.J i(CFR: 41.5/41.10,45.6/ 45.13)LJNormal, abnormal and emergency operating procedures associated with (LOCA Cooldown i<tnd Depressurization).

---

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

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

fuesday, November 10,2009 Page 156 of 185 FOR REVIEW ONLY - DO DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 63 General Discussion

,-.---------- --.--.-------- --~--------~- --.-----.-----------.-------"-- ~- -.--- ----.- --.---- ---- ---.---- --- -- - ----------"------- ----.- ----------1 IOnce NC subcooling, Pzr level, and other NC support conditions are established, a NC pump can be started if no NC pumps are running. If more than one NC pump is running, all but one I

lare stopped to minimize NC heat input. The NC pump restarted (or left running) is used to provide normal Pzr spray and mix the NC.

I l"I'~~~~i~~iI1(:C~th_e _aEEiican~I11~~~~~~!l~Ie~[e~£tI1~ai>~£o~Q1~~,0~llC!i()~~a~[o~~i~~~:L~,---~~~L~OCA S~()I~~\\\\'I1 ~a~~ Depl"e~~I"iZilti~~~ ~ ~ ~~~~ ~ __ ~_~ ~ _ ~~~~~ J Answer A Discussion

~~~~~~~~-~-~~ii!J~e i§~~~,is~~~~§~~~~o~~~~ -~~~~~~~~irl~~~~ ~I;-e~Nci~~~~~'~~~~i'~a~e~~~~~ii~~§~i~~~ieT~~~~~~!~!i~~ ~~~~}~~~~~~~~e~~~~

An8wer B Discussion 1i~~~~t.PI~~~hle

~in~~ 2 ;nd4~ar~ -;;;~e~t~ A.l~o-l-i~ ~b~;; fo~ ;~j~~~ti~n~i; othe-;:E~~;g;n~y Pr~~d~;-;~ ~----- - ~-~ - -- -~ - -~ -~~ - --~ - ~-~-~ ------ ~-

L ____ ~ _______ ~ __ ~~~

_____ ~~~ ___ ~

___ ~~_~_~~ ____ ~~~~_~

___ ~ __ ~~~~_~_~

__ ~_~

_____ ~~ __ ~

__ ~~~ ___ ~~ __ ~_~_

~ ___ ~ ____ ~ ___ ~ ___ ~~~~_~_~

Answer C Discussion

[COmCT. --- -- ---.----- -- ----.- ----.--.--------- --- --------------------------- -----

---

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

L~ __ ~

________ ~~

__ ~_~~ ______ ~~

____ ~_~~~~_~~_~~_~~ _____ ~~ __ ~ ____ ~_~ __ ~ ____ ~ __ ~~ ____ ~ ____ ~ __ ~ __ ~

__ ~_~ __ ~~~ ___ ~~~ __ ~ ___ ~_~_

Answer D Discussion 1- ---- ---------.-------------- --- ----------- -- ---------- - ------------- ------------------.--------- ---~----------.-- -------1 IIncorrect. Plausible since 2 is correct. Also I and 3 are bases for major actions in other Emergency Procedures.

t ___ ~~

__ ~ _____ ~_~

~~

____ ~~

____ ~~ ____ ~_~_~~_~ ~_~~_

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___ ~~

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~~.J

_=~ogn:!tIv~~L!t~!c= _l=~~!t[o!t!yp~=r=============- _~ues!!on~~urCe===~=========~ 401-9 Comments RESPONSE Memory I

NEW I

Considered SAT for submittal with no

_~_~_~ _______ ~ __ ~.L~_ ~ ___________..l _____ ~~ ____ ~ _______ ~~~ ________ ~ ~ __ ~_~ ___ ~_~ ____ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved comments. No changes.

~-

-~--~ -

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

~--~-~~-------~~--t t---

---~~-~--

---

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

---~~--~-

-~-~~

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QuestionSank # IKA_system IKA_number I IKA_desc

- --~-- ----~+--~--~ ---~~~f"_--~~~-~~---~--- - -j ~-~-~ -~-

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

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

I 8631WE03

__ IEK3.2 I IKnowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)

- - -- - - -~~- ---- -.J~_ - -

-~- - ------

~.J i(CFR: 41.5/41.10,45.6/ 45. 13)LJNormal, abnormal and emergency operating procedures associated with (LOCA Cooldown i't~dJ)epl"e~~u~i~<l!i~IJ) ___ ~_~~ ____ ~~~~~~_~ ___ ~~~_ _

~ _~ __ ~ ___ ~~ ~~_____~~ _____ _

fuesday, November 10,2009 Page 156 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 64 19~est~!t~!~~~f&~i!t~~=~~~n~~~~=~=~=J'~~-~~~~ __ ~_~~ ___ ~~~~ __

~~~ __ ~ ___ ~ __ ~~ __ ~~ ___ ~~ __ ~~~ __ ~

1864 WE09 I

EAl.l liAbility to operate and lor monitor the following as they apply to the (Natural Circulation Operations)

______ C_..... _

I _______ ~--- ---'------~--- ~_--1_~_~~_~~~ ___ ~_~_J !(CFR: 41.7 / 45.5/ 45.6) [l Components, and functions of control and safety systems, including instrumentation, signals, interlocks, Ilfailure modes, and automatic and manual features.

---

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

CURRENT Unit 1 has entered AP-09 (Natural Circulation). The following conditions are obselVed:

1. NC system subcooling > QOF

2. NC system hot leg temperatures at saturation temperature for S/G pressure

3. NC system cold leg temperatures going up slowly

4. NC system hot leg temperatures going down

5. S/G pressure stable

6. NC system cold leg temperatures at saturation temperature for S/G pressure

7. NC system pressure stable

8. Core Exit TIC's stable Which ONE (1) of the following sets of conditions confirm that Natural Circulation exists and is effective in cooling the core?

A 1,3,4,5,7 B.

2,4,6,7,8 C.

1,4,5,6,8 D.

1,2,3,5,7 WE09EAI.l 45 DAY VERSION Unit 1 has entered AP-09 (Natural Circulation). The following conditions are observed:

1. NC system subcooling > QOF

2. NC system hot leg temperatures at saturation temperature for S/G pressure

3. NC system cold leg temperatures going up slowly

4. NC system hot leg temperatures going down

5. S/G pressure stable

6. NC system cold leg temperatures at saturation temperature for S/G pressure

7. NC system pressure stable

8. Core Exit TIC's stable Which ONE (1) of the following sets of conditions confirm that Natural Circulation exists and is effective in cooling the core?

A 1,3,4,5,7 B.

2,4,6,7,8 C.

1,4,5,6,8 D.

1,2,3,4,5 401-9 Comments:

I think this is a comprehensive Q since a fair amount of evaluation is required.

RFA 10129/09 fuesday, November 10, 2009 Page 157 of 185 2009 RO N:C~~a~~E~!!:t~~L y ~~~T~N ~~I~~R~B_~~E ______ C_..... _

19~est~!t~!~~~f&~i!t~~=~~~n~~~~=~=~=JI~~-~~~~~===========_=~~ _______ ~~~ _____ ~~ ____ ~ __ ~~ ____ ~_~_~ ________ ~~_~~~_~ __

1864 WE09 I

EAl.l liAbility to operate and lor monitor the following as they apply to the (Natural Circulation Operations)

I-~--_~~-~-- ---'-----~--~~ _~..J __ ~ ________ ~ ____ J !(CFR: 41.7 / 45.51 45.6) C.l Components, and functions of control and safety systems, including instrumentation, signals, interlocks, 1!~ll1~_IIlO.cl~2..'ln~~atlt~l1"l'lt~_and l1"l~l2..u~,!(;atl.ll'~=-_~_.~~~~~ ~ ___ ~ ________ ~ _~~~_~~ __ ~ ~~~ ________ _

CURRENT 45 DAY VERSION Unit 1 has entered AP-09 (Natural Circulation). The following conditions are obselVed:

1. NC system subcooling > QOF

2. NC system hot leg temperatures at saturation temperature for S/G pressure

3. NC system cold leg temperatures going up slowly

4. NC system hot leg temperatures going down

5. S/G pressure stable

6. NC system cold leg temperatures at saturation temperature for S/G pressure

7. NC system pressure stable

8. Core Exit TIC's stable Which ONE (1) of the following sets of conditions confirm that Natural Circulation exists and is effective in cooling the core?

A 1,3,4,5,7 B.

2,4,6,7,8 C.

1,4,5,6,8 D.

1,2,3,5,7 WE09EAI.l Unit 1 has entered AP-09 (Natural Circulation). The following conditions are observed:

1. NC system subcooling > QOF

2. NC system hot leg temperatures at saturation temperature for S/G pressure

3. NC system cold leg temperatures going up slowly

4. NC system hot leg temperatures going down

5. S/G pressure stable

6. NC system cold leg temperatures at saturation temperature for S/G pressure

7. NC system pressure stable

8. Core Exit TIC's stable Which ONE (1) of the following sets of conditions confirm that Natural Circulation exists and is effective in cooling the core?

A 1,3,4,5,7 B.

2,4,6,7,8 C.

1,4,5,6,8 D.

1,2,3,4,5 401-9 Comments:

I think this is a comprehensive Q since a fair amount of evaluation is required.

RFA 10129/09 fuesday, November 10, 2009 Page 157 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 64 General Discussion

[Incorrect. 1,4, and 5 are correct. If the candidate confuses Nat Circ (loss ofal! NC pumps) with the loss of I NC pump where T-Cold would increase, 3 is plausible. 7 is plausble since most lE1lfarn3te~_a~e-"~t~ble_o~~oJ~g_clo-,",,~'~\\\\'~~E1~~i~orin~ fo/"~g:~ ________ ~ __________ ~__ ___ ~ _____________________ _

Answer B Discussion rn~~rrect.PI~~ibk~;;;Ze-4~6:~~d8 ;;Zo~;ct~2-;;;uld-b-;;~~r~e~tifit~~-~C~ld;~7is-P1~shl~~~ce most p~r~ete~s are-;'~t;';-bk~ goi~g-do~;;-;hen monitoring for NC.

~-

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

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

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

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

Answer C Discussion ICORRECT ~ -----

l _________ _

---

~-

-,--~-----~---- -

Answer D Discussion

~-'-- - - - -- - - -,--,-,- -, -- -,-, -,--~-,-- -,- ----,---,- ------,-,-------,----,----- ---- -~-------,--,- -

---~-- --- --,-,----

-~~---- - - --------- --- ------1

[Incorrect. Plausible since I, and 5 are correct. If the candidate confuses Nat Circ (loss of all NC pumps) with the loss of I NC pump where T-Cold would increase, 3 is plausible. 2 would be I

!correct if it was T-Colds. 7 plausible as described above.

I

~

~ __

~ _________________. ________________________________. ____________________________________________________________________________________ J

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Question Source 9~!~~o~!ype_

BANK

---~-,-,----- --- -------- -----

MNS Bank Question AP09003

~e~!J~£.lt~I1! ~!t~!8~~!!==~=~~===_~ __ _

!AP/I&2IAJ5500/09, Natural Circulation Background

[Document, pages 3 and 4 IAP/l&2/A/5500/003, Natural Circulation Enclosure I INatural Circulation Parameters I L ____________________, ______

~ _____ _

1.-

IStudent References Provided I----------'-~----~ ------ -

---

~-

I I

t i

L ___, ___________

~~ __________, __

---

,-- -~'-'-~-r--- ---'--1.--- --,-,--- ------

}uestlonBank., IKA_system tKA_number I.~----'-

~-------------------------~-------~" --------

IKA_desc 401-9 Comments RESPONSE Per Chief Examiner's suggestion, changed this to a comprehension level question.

---

'----~---t-~---'-'----t;:-'--------- -

18641WE09 IEA1.I 1.'--------- ----------------~-------- - -

,--------------~---~- ----

lAbility to operate and I or monitor the following as they apply to the (Natural Circulation Operations)

__ J _________ --.l __

~ _______________ _

i(CFR: 41.7 I 45.5 145.6)DComponents, and functions of control and safety systems, including instrumentation, signals, liI1!eI1~~~,!aJll1re_~o_d~s-'-~~~l1t()ITIa!ic:~~_~anll~ fe~hlr~s ____ ~ ~~ ___________ ~ ___. __ ~ ____ ~ __ _

fuesday, November 10,2009 Page 158 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 64 General Discussion ITh;j~ic-;;ti~~; ~N~W~ICirculatio~-a~~~- - --- ------------ --- -

! 1. NC Subcooling - Greater than O°F I 2. S/G Pressures - Stable or going down I 3. NC T-Hots - Stable or going down

! 4. Core Exit TICs - Stable or going down I 5. NC T-Colds - At saturation temperature for S/G pressure I IThis KA is matched because in order for the applicant to monitor components associated with Natural Circiation, they must know which instruments are monitored to determine that Natural iCirculation exist and must also know how those indications should be trending.

I 1!l1!~ ~~~0!l1pl"e~eE~i~n--'~v!~~u~sti()n be~<tu~e_t~~'P21ic~_~u~t _aI1<liy!~ <t~ ~EcIi~~~~ det~fl11i~(l~(;~ncliti()~ ~h<t~~_~~e _~tll~-'-~i~c~l(ltioE"--_____________________ _

Answer A Discussion

.-- ------ - ----------- --- - ---------------------------------- - ----- - --------- - -------- -- ------------------ -----------------1

[Incorrect. 1,4, and 5 are correct. If the candidate confuses Nat Circ (loss ofal! NC pumps) with the loss of I NC pump where T-Cold would increase, 3 is plausible. 7 is plausble since most I lE1lfarn3te~_a~e_"~~ble_o~~oJ~g_clo_""~'~\\\\'~~E1~~i~orin~ fo/"~g:___ _ ___________ _ ___ ____ __________________________________________________ J Answer B Discussion

---

------------ ----- ------ ----- ---- ------ ------------ ------------- -------- ------- -- ---------- ---- -----------------------l II~~~~:t.!~~~~~ s~~~~6_'_~n~ ~aJ"e~~fJ"t:c~~~~I~ ~~~_'"r~~t~f~~~~ -Co~ds. 7 ~s~~all~~e_s~n(;~ mos~~a_'"aJl1~~~~~_" st!ill~~_'"_~o~~~~\\\\'I1"_~~n_ mon~or~!!o_'"_~~ __________ J Answer C Discussion c _____________________________________________________ ------------------------------------------------------ __________ 1 l~~~~T ___________________________________________________________________________________________________________ I Answer D Discussion

---

- - - -- - - -------- ---- ------------- --- ---------- --------------------------- ---- -------------- - ------ --- --------- ------- - - --------- --- ------1

[Incorrect. Plausible since I, and 5 are correct. If the candidate confuses Nat Circ (loss of all NC pumps) with the loss of I NC pump where T-Cold would increase, 3 is plausible. 2 would be I

!correct if it was T-Colds. 7 plausible as described above.

I

~

~ __

~ _________________. ________________________________. ____________________________________________________________________________________ J

~-=iOb~~ey:!C ~~=~ EE~~itl~! Level 9~!~~o~!i~=_ ~=

~~_-___ ~ ___ ~~ ____ =-______ ~~ ~u~~~~~iu!~ ______ ~~-_= _________ ~~ ~---=~1 401-9 Comments RESPONSE I

RO I

Comprehension BANK 1

MNS Bank Question AP09003 I Per Chief Examiner's suggestion, changed L __ _______ L_________ ----- --

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

. _______________ 1 this to a comprehension level question.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 1.----- -

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

1.-- ---------~-------------------

IDevelopment References IStudent References Provided I

r.- ----------- ---

I--~--------------------- -------

IAP/1 &2/A/5500/09, Natural Circulation Background I

[Document, pages 3 and 4 I

IAPIl&2/AI5500/003, Natural Circulation Enclosure I I

!Natural Circulation Parameters I

L ___________________________

~ __ ~___

L __

~ _________________________

~ __

---

--------[--- ------1.--- -------- ------

}uestlonBank., IKA_system IKA_number 1.------- --------------------------------- -- -- ------- - --- - --- ---------------------

IKA_desc

---

t------------t;:----------- -

18641WE09 IEA1.I

__________ J _________ ----.l __

~_____

r,---------- ------------------------- - -

---

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

lAbility to operate and I or monitor the following as they apply to the (Natural Circulation Operations) i(CFR: 41.7 I 45.5 145.6)DComponents, and functions of control and safety systems, including instrumentation, signals, liI1!eI1~~~,!aJll1re_~o_d~s_'_~~~l1t()ITIa!ic:~~_~anll~ fe~hlr~s. _____________________. _ ___ __ _ _ _ __

fuesday, November 10,2009 Page 158 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 64 fuesday, November 10, 2009 Page 159 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE c 2009 RO NRC Retake Examination QUESTION 64 fuesday, November 10, 2009 Page 159 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 65 B

c~~~~'~"'~-~~~~-

--~~

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~--

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~---'~~'-~'--'-~-'~-~ -~--~-~~-

~~-~

-~~,~-,-

~-~--,-,---, ---~

,-,~~,~~~~~~~~~~~~~-~-~-

~-,-~-~

IQuestlonBank # IKA_system IKA_number rlKA_desc I~~- ~~ ---1~

~-~~--t-~~'~~~-~- -

-~,~-,- t--'~~~~-~'

1865 i

WEl3 I

2.2.37 jirWE 13 GENERlCCiAbility to determine operability and/or availability of safety related equipment. (CFR: 4 1.7 143.5 145.12) l _________ ~ ____ ~

________ ------.l _________________ L _________________ "_" __ " __

~ ______

CURRENT 45 DAY VERSION Given the fol/owing conditions on Unit 1 :

A B.

C.

D.

An inadvertent Main Steam Isolation resulted in a Reactor Trip.

FR-H.4 (Response to Loss of Normal Steam Release Capability) has been implemented due to a Yellow Path on Heat Sink The Main Steam Safety valves (MSSVs) have reduced S/G pressures to 1200 PSlG

1) What indications on MC-2 are required to be present to allow for S/G PORV operation?

2) Based on current conditions, how many MSSVs per S/G should be open?

1) S/G PORV RESET lights - LIT ONLY

2) 2

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 2

1) S/G PORV RESET lights - LIT ON L Y

2) 3

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 3 WEl3G2.2.37 No comment at this time RF A 10/29/09 fuesday, November 10, 2009 Given the following conditions on Unit 1 :

A.

B.

C.

D.

An inadvertent Main Steam Isolation resulted in a Reactor Trip.

FR-H.4 (Response to Loss of Normal Steam Release Capability) has been implemented due a Yellow Path on Heat Sink The Main Steam Safety valves (MSSVs) have reduced S/G pressures to 1200 PSIG

1) What indications on MC-2 are required to be present to allow for S/G PORV operation?

2) Based on current conditions, how many MSSVs should be open?

1) S/G PORV RESET lights - LIT ONLY

2) 2 MSSVs on each S/G should be open

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 2 MSSVs on each S/G should be open

1) S/G PORV RESET lights - LIT ONLY

2) 3 MSSVs on each S/G should be open

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 3 MSSVs on each S/G should be open 401*9 Comments:

Page 160 of 185 2009 RO NR~~!a~~~!!:t~~L y ~U~~T~N 6~ISTRIBU~E ___ _B_ _ _ __

IQ~estlonBa;tk~#lKA_sYSt8mT~numb.;----~-rIKA~d"C=~==-=~-=---=-_=-=---==--=---=-=--=--=-=-=-=-=-=~~-------~-~----~---------~~~~~-~--J r~~-1865--1~ -W-EI-3 --t--~-22~37 ----I iWEI3-GENERlCClAbility to determine operability and/or availability of safety related equipment. (C~R:~I.7 I ~3.~0~~~ ____ J

_____________ L_~ ___ ~_ -L_~~ __________ ~

__ I L_~ ____________________________ ~ __ ~

___________ ~

______ ~~

CURRENT 45 DAY VERSION Given the fol/owing conditions on Unit 1 :

A B.

C.

D, An inadvertent Main Steam Isolation resulted in a Reactor Trip_

FR-HA (Response to Loss of Normal Steam Release Capability) has been implemented due to a Yel/ow Path on Heat Sink The Main Steam Safety valves (MSSVs) have reduced S/G pressures to 1200 PSlG

1) What indications on MC-2 are required to be present to allow for S/G PORV operation?

2) Based on current conditions, how many MSSVs per S/G should be open?

1) S/G PORV RESET lights - LIT ONLY

2) 2

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 2

1) S/G PORV RESET lights - LIT ON L Y

2) 3

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 3 WE13G2.2.37 No comment at this time RF A 10/29/09 fuesday, November 10, 2009 Given the following conditions on Unit 1 :

A.

B.

C.

D.

An inadvertent Main Steam Isolation resulted in a Reactor Trip.

FR-HA (Response to Loss of Normal Steam Release Capability) has been implemented due a Yellow Path on Heat Sink The Main Steam Safety valves (MSSVs) have reduced S/G pressures to 1200 PSIG

1) What indications on MC-2 are required to be present to allow for S/G PORV operation?

2) Based on current conditions, how many MSSVs should be open?

1) S/G PORV RESET lights - LIT ONLY

2) 2 MSSVs on each S/G should be open

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 2 MSSVs on each S/G should be open

1) S/G PORV RESET lights - LIT ONLY

2) 3 MSSVs on each S/G should be open

1) Main Steam Isolation RESET light - LIT, S/G PORV RESET lights - LIT

2) 3 MSSVs on each S/G should be open 401*9 Comments:

Page 160 of 185

FOR REVIEW ONLY - DO DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 65 General Discussion

[-~---- -------------- -- -- -----------~------- ~--------------- -

---

~-~- -

---

~-

--~-------

---

~-- ----

IFor the S/G PORVs to operate automatically or manually using the Manual Loaders on the Main Control Board, the Main Steam Isolation must be reset and the S/G PORVs must be reset.

I I

IMSSV Setpoints - 1170, 1190, 1205, 1220, 1225 (PSIG). Therefore 2 MSSVs should be open based on plant conditions.

i (The KIA is met because the applicant must determine what conditions must be met for the S/G PORVs to be available and must also determine how many MSSVs should be operating based Ion plant conditions.

I iThis KIA is comprehension level because the applicant must evaluate a given set of conditions, recall from memory the MSSV setpoints and the interlocks for S/G PORV operation, and I

~~~ciate~l1o~e'p~e~e~_()fJllfo!l11ilti()E. to_olJ~il1.!.~~~rr~~t:!~~~r.__ _ __ ___ ___ ____________ _ ________ _ _______________________________ J Answer A Discussion 1-

-~-------

---

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

--~-~

---

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

IIncorrect. SG PORVs must be reset but MSI must be reset also. Number ofMSSVs open is correct.

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

Answer B Discussion 1---

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

ICORRECT.

Answer C Discussion rfu~~~~ct.SG -PORV;~~st-be ~~;;t-b~tMSI~~~tb~ ~~;t~;~~ 2-MSSVs-;h;uld-b~ ~p~; instead of 3.

L~ _____ ~ ____ ~_ ~

___ ~ ____ ~ ___________________________________________ ~ _________ ~ __________ ~ ______ _

---

~-~----

Answer D Discussion IIncorrect. Reset lights are correct. 2 MSSVs should be open instead of3.

L ____________________ ~ __ ~ _____

~ ____ ~ ___________________________ _

---

----1-------

~-~-

---

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

~-------

QuestionType 1 Question Source I 401-9 Comments RESPONSE

- -- --~- -----l------ -~----- -----~~ ----~------~- ------------ ~- ~~-1 NEW 1

Considered SAT for submittal with no

--~------

___ ~ ___________ L~~ _____ ---------- ----~--------~-------~ ------1 comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

---

~- ------

---

~- - --- ---~-------l 1.--------- --

jDevelopment References I IStudent References Provided r---------------

---~--------------- - ----I ----~---

---

~-

-~-

IOP-MC-STM-SM Objectives 9 and 7 pages 15, 17, 19 1 I land 23 i 1 I

II I i i I

1 I II l ___ ~ ____ ~ ____ ~ ___ ~ __ ~ ________ ~ __________ ~ ___

1 ~ ______ ~ _______ ~~~

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

--I-~-

-~-------- r:------

--~- -

--~ ---

91J~S!~.Ilf3~n~~f~~=8J'Sl!~ __ ~=fllJ.'!'.~eL __

8-£~~~=~====-=--=-==========-=======~---------

1865 WE 13 12.2.37

~ __________ l'_~ ______ ~_, __ ~ ___________ _

IWEl3 GENERICUAbility to determine operability and/or availability of safety related equipment. (CFR: 41.7 I 43.5 145.12) l_~ _____________ ~ ____________ ~

___________ ~~ ________ ~ _________________

~ ________ _

Tuesday, November 10,2009 Page 161 of 185 FOR REVIEW ONLY - DO B

DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 65 General Discussion IF~~-th; SIC; P(iRVst;;-;;p~~~t~ ~a~t;;~atiZ';liy~;~~~aliy usingth~M~~aILo-;de~~~th~M~i~ C~~;;;IB~~~,the~M~n-Ste~Is~i~t~~ ~~~t b~~;t~a;;-dth;S;GPORV;-~u~tb~-~;t~ ~ I I

!MSSV Setpoints - 1170, 1190, 1205, 1220, 1225 (PSIG). Therefore 2 MSSVs should be open based on plant conditions.

i (The KIA is met because the applicant must determine what conditions must be met for the S/G PORVs to be available and must also determine how many MSSVs should be operating based Ion plant conditions.

I iThis KIA is comprehension level because the applicant must evaluate a given set of conditions, recall from memory the MSSV setpoints and the interlocks for S/G PORV operation, and

~~~ciilte ~11o~e2~e~e~~fJllfo!~t~~to _OlJ~ill~~ ~~rr~~~~~u~s~~r~~ _ ~ ~~~ ~~_~ ~_ ~~~ _ ~ ~~~~~~~ __ ~~~~~ _~_~ _~ ~ _ ~ ~~~_~ __ ~_~~_~~ ___ ~~~ __ ~~ ~~

Answer A Discussion I~ --~~-~~--

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

-~~~-~~

~-~--

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

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

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

IIncorrect. SG PORVs must be reset but MSI must be reset also. Number ofMSSVs open is correct.

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

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

Answer B Discussion I-~~ ~-~~-- -

-~

~~-~~~-~~

~--

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

--~--~~~-

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

-~-

~--~~-

---

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

~--

--~

~---~ -~

-~----- - --

ICORRECT.

Answer C Discussion

~~j~~~~ __ ~~-~OR~;_0~S!-£~-~i;i~~tH~~ ~~~b~ r~~~;().~~-~s§~~~iu~~~b~_~~;~~;~~~

~~~~~-~-~~

-_-~ -~

~_~--=-~_-=-~~_ -~_-~~

~_ -~-_-~~ __ -~-_-~ _____ ~

~~~_ --__ =~

~

Answer D Discussion IIncorrect. Reset lights are correct. 2 MSSVs should be open instead of3.

L ~~ __ ~~_

~ __ ~_~ __ ~~ _______ ~~~_~ ______ ~ _~~ ____ ~_ ~_~~ __ ~_~~~_~~~ _______ ~~

__ ~~_~ __ ~~ _~_~~~

__ ~~_~ __ ~~~~~~~~~~~

_______ ~~~_~~ __ _

,~-~~-

-~

-~

-~~----~-

--~~~--~--~

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_~~C~J1E'!j\\.t!!-!vel

--~~--~

~~-~

I~--~--~ ----

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

~~-~-

~--

---~~

-~~--~ -

--~~--~-

QuestlonType I Question Source I 401-9 Comments RESPONSE

( ___ ~~__L_~~~~re~ension

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Tuesday, November 10,2009

-~ ---- -~-~-l--~-----~~~-~ -~~~--- --~~--~~~~~-- ~~-~~----~~--- --~1 NEW I

Considered SAT for submittal with no

-- ----- ---~ -- __ L __ -----

~~~~~-- - --

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

---~~-I comments. No changes.

-~-~~-----

-~-~~-

~

-~~-~-- - ---

-~---~~~~~-l r;:~~~--~--

~~ - -

~-~~-~~~-

---

~--

IDevelopment References I IStudent References Provlded-I

~~~-~-~~----~~-~ -~--~~---~-~-~~--~~ - ~-~-I ~~~~--~~ -~~~-- ~--~-~-~------~~~I IOP-MC-STM-SM Objectives 9 and 7 pages 15, 17, 19 I I land 23 i I I

I i I I

I i

• I I

I I I

__ ~_~ __ ~ ___ ~~

~ ~~_~_~~ _____ ~_~ __ ~J I ___ ~~ ____ ~~~~~ __ ~ ~~__J 8-£~~~=~====~=~-=~==========-=======~===-==~======~~-====:=-~~==~~==--

IWE13 GENERICUAbility to determine operability and/or availability of safety related equipment. (CFR: 4 1.7 I 43.5 145.12) l~ __ ~_~~

___ ~

__ ~~ ___ ~ __ ~

___ ~~ _____ ~~~~~~~

___ ~ __ ~~~~~ __ ~_~_~~~~

__ ~_~ __ ~ __ ~~~~~~~_

Page 161 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 66 r----------

I

'QW;-stionBarlk#IKA_~ystem-TKA-=-n~mber- --

I-,-~-,-,--- -- + -,-,~----,-'-t- -------'- ~--,--

I 1866 I

GEN2.1 I

2.1.28 IKA desc i'---""'"-'~--'- ----- -,-----,--------,-' -~- --- -,--,-~-------,--- -----,-,------

[Conduct of Operations rJKnowledge of the purpose and function of major system components and controls. (CFR: 41.7)

---1

~ ___, ____, _-_,-1---_-_---,--"

--~-

---

~-------

--~-

CURRENT Which ONE (1) of the following correctly describes the function of the Pressurizer Pressure Control Selector Switch?

A.

B.

C.

D.

In the "1-3" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 34A.

In the "3-2" Position, CHANNEL 2 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 368.

In the "1-2" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 2 actuates PORV 328 & 34A.

In the "1-4" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 4 actuates PORV 328 & 368.

G2.1.28 No comment at this time RF A 10/29/09 fuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following correctly describes the function of the Pressurizer Pressure Control Selector Switch?

A.

8.

C.

D.

In the "1-3" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 34A.

In the "3-2" Position, CHANNEL 2 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 368.

In the "1-2" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 2 actuates PORV 328 & 34A.

In the "1-4" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 4 actuates PORV 328 & 368.

401-9 Comments:

Page 162 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 66 i9~~~~~~~~1~~.,.~~iem=-~~'::n~~~r- --

r----------

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

---

~------~

IKA desc I

1866 I

GEN2.1 I

2.1.28

~ ___. ___ -. ___._1 _________.-" ___. _______. ____ _

r~~~~~9~~~~~rJ~~~I~i;cl~~~~~~oie~c!}~n~~~~~~~a~~~~e~~~~~~~~~~~~~~~~~-~~~_-_-_-_-~~J CURRENT Which ONE (1) of the following correctly describes the function of the Pressurizer Pressure Control Selector Switch?

A.

B.

C.

D.

In the "1-3" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 34A.

In the "3-2" Position, CHANNEL 2 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 368.

In the "1-2" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 2 actuates PORV 328 & 34A.

In the "1-4" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 4 actuates PORV 328 & 368.

G2.1.28 No comment at this time RF A 10/29/09 fuesday, November 10, 2009 45 DAY VERSION Which ONE (1) of the following correctly describes the function of the Pressurizer Pressure Control Selector Switch?

A.

8.

C.

D.

In the "1-3" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 34A.

In the "3-2" Position, CHANNEL 2 inputs the master pressure controller and CHANNEL 3 actuates PORV 328 & 368.

In the "1-2" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 2 actuates PORV 328 & 34A.

In the "1-4" Position, CHANNEL 1 inputs the master pressure controller and CHANNEL 4 actuates PORV 328 & 368.

401-9 Comments:

Page 162 of 185

FOR REVIEW ONLY - DO DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 66 General Discussion

---

~------ -

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

lIn the "1-4" position, Channell inputs the Master Pressure Controller and Channel 4 actuates PORV 32B and 36B.

I 1

lT~e_ ISJ ~Js_ ~a~~~d~~l1(;e_t~~'P21ic!l1t _n1u~tl1<l"_e!:~~\\\\'!~~~ of Q1~ fu~cti?n 0f'~~f>r~ssur~er P~e~~r:S~Iltf9l ~~~t<Jr S~t~h.

Answer A Discussion iI~c~;:;:e-;;t. The;ei;-NO;I~Y;-p;;tio~f;th~-Pre~~~i;e;-P~~~r~C;~r~IS~kct~S~it~~H~;;v~r~ tht;-~~;;risstilTPI~u~ibl~~~;;the;e is-a-;'1~3;;-Pc>;iti~n f~r the-P;-;s~ri~~L-e~~I-IControl Selector Switch. The applicant could confuse the two.

1 __,_~_,_, ___,_, _,_~

___,_~ ___, __, ____________, _______ ~

Answer B Discussion 1- -,--.--- -.-----.--.~--~---------- ----~--- ------------ -------- --~---- -

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

jIncorrect. Plausible because this is one of the positions on the selector switch. However, Channel 3 inputs the Master Pressure Controller and Channel 2 actuates PORV 32B and 36B.

L __________________________ _

Answer C Discussion 1- ----- --- -- ---.---

---

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

--.~---

~.---

---

.--~---

---

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

---

~--

---~-

IIncorrect. Plausible because this is the normal position of the selector switch and Channell inputs the Master Pressure Controller. Channel 2 does actuate the PORVs. However, it actuates 132B and 36B and not 34A.

1, _________ ' _________, ___,_~ ___, ______, ________________________, ________________, __

Answer D Discussion

~ORRECT~

L_, _________ '" _____ _

,----------r--' -,-- ------- -----

1 Job Level I Cognitive Level r---- ----r---------'- -,-----

~

______________ q~e~!i0n_ So,!r~~ ____ __ __ ___ --I 401-9 Comments RESPONSE From MNS Exam Bank Question PSIPE004 1 Considered SAT for submittal with no 1

RO J

Memory I

~ _________,

________ ", __, _____ "' __ -l_, ___ _

---

~-

---~-- ---- - ~ comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r= -,,-- - - --- -,-,---- ---

[Development References r------- ---,---,------ ----

iLesson Plan OP-MC-PS-IPE Figure 7.1 j

I 1

1 1 L ____, ____ _

I. - --,---,- --,---------,- ---" - -- -,

LS~~<!e_~~!f!~nce8 Provided I

[

i

[

19~e~~~~~~-#~R~=sl~~~~~=Il~tli~!r======~ ~_d!~~====-========= _______________________ ~ _____ ~ ______ _

18661GEN2.1 12.1.28 i :Conduct ofOperations:JKnowledge of the purpose and function of major system components and controls. (CFR: 41.7)

_______________ 1- _________ -'-_____. _________ ___ I ------------.---.-------------------------------------.- -------.---------------- ------ -

fuesday, November 10, 2009 Page 163 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 66 General Discussion lIn the "1-4" position, Channell inputs the Master Pressure Controller and Channel 4 actuates PORV 32B and 36B.

I I

lT~e_ ISJ ~Js_ ~a~~~d~~l1(;e_t~~'P21ic!l1t _n1u~tl1<l,,-e!:~~\\\\,!~~~ of Q1~ fu~cti?n 0f'~~f>r~ssur~er P~e~~r:S~Iltf9l ~~~t<Jr S~t~~~_~_~ __ ~ _ ~~~_~_~_~~ __ ~~ ~ ___ _

Answer A Discussion c:-

-~ -- -- -

-~-~---,-~~-~-~----------~-

-~----

--,-~~-----~--~-,~----~-,-~-,~~,--,-~---- -

-~~---,--,-~~ -~-~-,~--,-~-~-- ---'---,

IIncorrect. There is NO "1-3" position for the Pressurizer Pressure Control Selector Switch. However, this answer is still plausible since there is a "1-3" position for the Pressurizer Level i

IControl Selector Switch. The applicant could confuse the two.

I 1 __, ___,_, ___,_, _,~ ____,_~ ___

,~_, __________ ~_, _____ ~_~

___, ________ ~ __ ~ __ ~_,_ ~_~, ________________,_ ~-

-~~---~--~----,---~,----

Answer B Discussion I--'--*--~-*---*-*--*~~-~--------------~--------------------------------~---------- --- - ------- --- ---

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

jIncorrect. Plausible because this is one of the positions on the selector switch. However, Channel 3 inputs the Master Pressure Controller and Channel 2 actuates PORV 32B and 36B.

L ____________________ ~ ________________

• ___

~ _______________________

~ ______

~

___________

• _______ ~

Answer C Discussion 1- ----- --- -- -------

---

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

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

---

~---------------,----~-- -

~-----~--

---~-----------,--

IIncorrect. Plausible because this is the normal position of the selector switch and Channell inputs the Master Pressure Controller. Channel 2 does actuate the PORVs. However, it actuates 132B and 36B and not 34A.

1, _____ ~ ___, ______ ~~_,~ __,_~ __ ~, ______, ___ ~~~~ ___ ~~ _________ ~ __,~ ______ ~~~ ______,_~~_~~ _____, __,_~ _, ___ ~,_,,~_,_~~, ________ ~ __ ~_ ~ _____,

Answer D Discussion rc-O:RRECT~-'--'---'-'--

,--,~-----,---------~--------~--, --,-------,--,----,--~,-----'---~--------~---'-, -~----- ---

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

L_, __________ ' _ ~ ______, ____,_______ _ _

__, ~~, ______ ~_, ___,~~ _~_~

~_~ ____, ___, __, __ ~_' _______ ~

___ '_, __, __ ~ ________ '~~ ___________, _____,

i~job~Level-T--

~C~gnltive-ievel--

-QuestlonType-I---~~--~- ---------QuestionSource ------~-~~~----I 401-9 Comments RESPONSE r-~~- - ---T--~~-----'- -,~--- -

-,-,---~-- - + ~- ---~-- --,-,--,-- ----,---~-,---,~---,--,- ~~--,---I I

RO J

Memory 1

BANK I

From MNS Exam Bank Question PSIPE004 I Considered SAT for submittal with no

~------ -

-~, --- -----",- -,- -~-- ---, _-l~, ______ ~_,_~, ___ L ------ -- ------- ----,--- -~------------ ---~-- ---- - ~ comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved fuesday, November 10, 2009 r=-----------'-'----- --

IDevelopment References r---~---

--~,---,----- -

-~--

ILesson Plan OP-MC-PS-IPE Figure 7.1 j

I I

I I L_~ __, _________ ~ __ ~

__ ~ _________ ~,

I. - --,---,-

--,~------~-,- ----- - -- -,

LS~~<!e_~~!f!~nce8 Provided I

1 i

1 Page 163 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 67 lq~~ji~~~~nk #l~~~S~ys!8~]~~~~t!l~er-~=_====: ~:~!~============ ~============ =~========-===-_-=-=========--~==_===

l_~~ _l~~ 7~ _ ~_ L

~~~2. ~ ~ l~ __ ~~~L!~ ~ _ ~~J l~~dll~~O! ?£~~~~ol1~[~~~I~ty to ~o~<tt~~~_o~eJ"<ltec~~J)()~:n~s,il1~tld~n~~o~1!I-=~11~r~

CURRENT The SSF Diesel Generator is operating in the EMERGENCY Mode AND the Break Glass Station Overspeed Shutdown Bypass Switch is in the "Bypass" position.

Which ONE (1) of the following lists ALL SSF Diesel Generator trips in addition to the Overspeed trip that are bypassed?

A Generator Differential ONLY.

B.

Low Lube Oil Pressure ONLY.

C.

Generator Differential and Low Lube Oil Pressure Trips ONLY.

D.

Generator Differential, Low Lube Oil Pressure, and High Jacket Water Temperature Trips.

G2.1.30 45 DAY VERSION Given the following conditions on Unit 1 :

The unit was operating at 100% RTP A spurious Safety Injection signal occurs on both trains Which ONE (1) of the following describes the MINIMUM requirements to regain control of ESF equipment and stop one of the RN pumps during the recovery from the spurious SI?

A.

Reset Sequencer ONLY.

B.

Depress the Safety Injection RESET pushbuttons ONLY.

C.

Depress the Safety Injection RESET pushbuttons AND depress the Diesel Generator Sequencer RESET pushbuttons.

D.

Depress the Safety Injection RESET pushbuttons AND momentarily place the Reactor Trip Breaker control switches to CLOSE.

401*9 Comments:

This Q does not have anything to do with locating/operating local controls. I suggest writing a Q where the CR had to be evacuated and the operator has to report to a local station to operated equipment.

This Q is U because the KA is not met RF A 10/29/09 Tuesday, November 10,2009 Page 164 of 185 FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 67 D

lq~~ji~~~~nk #l~~~S~ys!8~]~~~~t!l~er-~=_====: ~:~!~============ ~============ =~========-===-_-=-=========--~==_=== =-=====~= --~~

LI 1867 I,

GEN2.1:

2.1.30 IIConduct ofOperations:::1Ability to locate and operate components, including local controls. (CFR: 41.7/45.7)

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

~----- -~ ~--~~~~----~~~---~~ __ ~_~~I, ____ ~~_ -~~

___ ~~_ ~~

_____ ~~

-~~~

__ ~~ ___.~~~~~~~_ ~--~-.~~~~~--~~-~- ~-~~~~

~-~ -

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

CURRENT 45 DAY VERSION The SSF Diesel Generator is operating in the EMERGENCY Mode AND the Break Glass Station Overspeed Shutdown Bypass Switch is in the "Bypass" position.

Which ONE (1) of the following lists ALL SSF Diesel Generator trips in addition to the Overspeed trip that are bypassed?

A Generator Differential ONLY.

B.

Low Lube Oil Pressure ONLY.

C.

Generator Differential and Low Lube Oil Pressure Trips ONLY.

D.

Generator Differential, Low Lube Oil Pressure, and High Jacket Water Temperature Trips.

G2.1.30 Given the following conditions on Unit 1 :

The unit was operating at 100% RTP A spurious Safety Injection signal occurs on both trains Which ONE (1) of the following describes the MINIMUM requirements to regain control of ESF equipment and stop one of the RN pumps during the recovery from the spurious SI?

A.

Reset Sequencer ONLY.

B.

Depress the Safety Injection RESET pushbuttons ONLY.

C.

Depress the Safety Injection RESET pushbuttons AND depress the Diesel Generator Sequencer RESET pushbuttons.

D.

Depress the Safety Injection RESET pushbuttons AND momentarily place the Reactor Trip Breaker control switches to CLOSE.

401*9 Comments:

This Q does not have anything to do with locating/operating local controls. I suggest writing a Q where the CR had to be evacuated and the operator has to report to a local station to operated equipment.

This Q is U because the KA is not met RF A 10/29/09 Tuesday, November 10,2009 Page 164 of 185

FOR REVIEW ONLY - DO N T DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 67 General Discussion iWhe~ the~~gin~is~Utrt~d-a Fu~I-OilS~I~~id v~i~~~~~~~~st~pen ;~~d;it fucl ~lto-the-~g;;e~Ift~D/Gd~~ot~~-~~ trip~~ith;;trt~pp;r~nt~;;; the probk~ mayb~-an lelectrical failure ofthe Fuel Oil Solenoid valve. This solenoid valve can be bypassed by turning a manual knob located on the valve. Opening this bypass valve bypasses all engine trips l(including manual stop).

I IT. his KJ A is matched because the Operator has been directed to operate a local control at the SSF and must know the implications of operating that control.

--~- ------~------ -"------- -._- -

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

Answer A Discussion

!Incorrect. Plausible because this trip is bypassed. However, there are others that are bypassed also.

L. _____________________. ________________ _

Answer B Discussion IIn~~~ct. Pl~~~ibkb~~;;s~th;;-trip~byp~~d~fi;;-;e~;~there are others that are bypassed also.

L_ _____ __ ___ _ __ _________

Answer C DIscussion IIncorrect. Plausible because these trips are bypassed. However, there are others that are bypassed also.

L ________________________________________________. __________________ ~

Answer D Discussion ICORRECT.

Cognitive I..&V8,-

-T-OUeStlonType Question Source 401-9 Comments RESPONSE I

'--~_-~_-=-~~n0iY.--_-_-~-~ I-_-~~-~~~ ___ ---

MNS Exam Bank Question CPADOI5.

~ Developed 1---- ------------- -------------- -

---

~ r------*--------------- ----- -- --

~~~~e'!l!~t~~!~!!l-c..e~--- ____________ ~ 1~tt.l5i!l'l.t_~.e!!'!I'l.~fro,,_iC!.e~ ____ _

Per Chief Examiner's comment, changed question to ask about the operation of a

'local' control at the SSF as opposed to a control in the Control Room. HCF 11/04/09

~ OPT Approved

~ OPS Approved

~ NRC Approved ILesson Plan OP-MC-CP-AD Objective 3 page 31 I I I

I I I

i i [

I I I I

I.

i l l L ___. ___. _____________________. ______.~~_J L ___. __________ ~_

- ---------- --------.----,---------- ------ --I I~-*---*----- - ---------- ----.- ---.-----.--------------- ---------.---------------------

9~!s.!iC)I'l.~a..i{c0i~N~~t~!"--lii3~~f!'~'"----- -ll~~n~:~~Op-;;~~ti~n~uAbiii;y t~c~~~nd ope~~-~-mp~~e;t~:_;~cl~dingTo~~~~~t~~i~.(CFi~41.7/45.7)---

____________ ~ __ ~ ___________ L _________________ ~ ______ -1

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

ruesday, November 10, 2009 Page 165 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 67 General Discussion iWhe~ the~~gin~is~Utrt~d-a Fu~I-OilS~I~~id v~i~~~~~~~~st~pen ;~~d;it fucl ~lto-the-~g;;e~Ift~D/Gd~~ot~~-~~ trip~~ith;;trt~pp;r~nt~;;; the probk~ mayb~-an lelectrical failure ofthe Fuel Oil Solenoid valve. This solenoid valve can be bypassed by turning a manual knob located on the valve. Opening this bypass valve bypasses all engine trips l(including manual stop).

I lIh~s _~~i~_m_~~~d J:>~~1IS(:!h~~2erat()r_ has~een ~ir'e~t~~ t~ ~~~a~e_~I~Cil~c~~tJ'()l :l!!Il~S§f<' and _mustJ<Eow ~0~£~c~ti0E~~()re~atil1g~~at_~Ett:0I. ______________ _

Answer A Discussion

!Incorrect. Plausible because this trip is bypassed. However, there are others that are bypassed also.

I L ______________________________________________________________________________________________________________________ _

Answer B Discussion fIn~~~ct. PI~~~ibkb~~;;_s~th;;-trip~byp~~d~H~;e~;.~the~;;;othe~~fuat;r~byp;;,;~-aIs;;_.------ ------ -------------- -----------------------1 L _________________________________________________________ ~ ________________________________________________________________

~ _________________ ~

Answer C DIscussion IIncorrect. Plausible because these trips are bypassed. However, there are others that are bypassed also.

L ___________________________________________________________________ ~

Answer D Discussion ICORRECT.

---

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

---

~------

-~----~---- -- ----------- - ---- - ---I

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Question Source MNS Exam Bank Question CPADOI5.

1---- ------------- -------------- -

---

~ r---------------------- ----- -- --

~~~~e'!l!~t~~!~!.rl-c..e~--- ____________ ~ 1~tt.l5i!l'l.t_~.e!~'!I'l.~fro"_iC!.e~ ______ _

ILesson Plan OP-MC-CP-AD Objective 3 page 31 I I I

I I I

i I [

I I I I

I.

i l l L ______________________________________ ~_J L ______________ ~ ___ _

401-9 Comments RESPONSE Per Chief Examiner's comment, changed question to ask about the operation of a

'local' control at the SSF as opposed to a control in the Control Room. HCF 11/04/09

- ---------- -------------,---------- ------ --I 1------------ - ---------- ------ ------------------------- -------------------------------

9~!s.!iC)I'l.~~i{c0i~N~~t~!"--lii3~~f!'~'"----- -ll~~n~:~~Op-;;~~ti~n~uAbiii;y t~c~~~nd ope~~-~-mp~~e;t~:_;~cl~dingTo~~~~~t~;;-I~.(CFi~41-.7/45.7)---

____________ ~ __ ~ ___________ L _________________ ~ ______ -1

--- --- ----~---------------~-~-------~ ________ ~ _________ ~

____ -------------------~-- --~-------

ruesday, November 10, 2009 Page 165 of 185

A FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 68

'L[§~~~is~~~~~lf~A~tt¥=F~~~~2~~f>===*=*~I: ~~~¥~~~;~~~~~~;~;~~;a~:~~t~~~~~s;t;~~~~~tr~I;'~;d~~~;~:n~~~~t;~;~~~~~~~~ey~o~ectly reflect

---

--.-.... --- - ----~--.------- ---- Ithe desired plant lineup. (CFR: 41.10 1 45.12) l"._. __. ___. ________. ___________. ____. _______. __._._._. __._... ____. ____.... ____. _____.. _

CURRENT Given the following conditions on Unit 2:

An NC system cooldown and depressurization is in progress in preparation for refueling.

Annunciator 2AD-6/ A 12 (PORV LO PRESS MODE NOT SELECTED) alarms Which ONE (1) of the following sets of conditions could have caused this alarm?

A

8.

C.

D.

NC system temperature less than 320°F 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system temperature less than 320°F

- 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system pressure less than 380 PSIG

- 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM" G2.1.31 No comment at this time RF A 10/29/09 Tuesday, November 10, 2009 45 DAY VERSION Given the following conditions on Unit 2:

An NC system cooldown and depressurization is in progress in preparation for refueling.

Annunciator 2AD-6 A12 (PORV LO PRESS MODE NOT SELECTED) alarms Which ONE (1) of the following could have caused this alarm?

A.

B.

C.

D.

NC system temperature less than 320°F 2NC34A OR 2NC328 PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC328 PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system temperature less than 320°F

- 2NC34A OR 2NC368 PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC368 PORV OVERPRESS PROTECTION SELECT switches in "NORM" 401-9 Comments:

Page 166 of185 FOR REVIEW ONLY - DO N 2009 RO NRC Retake Examination QUESTION 68 DISTRIBUTE A

---

~-- ------

!§~~~is~~~~1~A~tt¥=F~~~~2~~f>===*=l ~~~¥~~~;~~~~~~;~;~~;a~:~~t~~~~~ s;t;~~~~~tr~I;,~~di~di~tio~n~~~dt~ dct~~i;;~ ili;t they~o~ectly reflect L_._._._ - -.-.-.--- - ----~--.----~-- ~---

~h~.~~lf~djJ.!.a.nt}ln~lIE._lC/<*~_=_'! 1-"-1()!.i~!32 ___________________. ________.

CURRENT 45 DAY VERSION Given the following conditions on Unit 2:

An NC system cooldown and depressurization is in progress in preparation for refueling.

Annunciator 2AD-6/ A 12 (PORV LO PRESS MODE NOT SELECTED) alarms Which ONE (1) of the following sets of conditions could have caused this alarm?

A B.

C.

D.

NC system temperature less than 320°F 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system temperature less than 320°F

- 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system pressure less than 380 PSIG

- 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM" G2.1.31 No comment at this time RF A 10/29/09 Tuesday, November 10, 2009 Given the following conditions on Unit 2:

An NC system cooldown and depressurization is in progress in preparation for refueling.

Annunciator 2AD-6 A12 (PORV LO PRESS MODE NOT SELECTED) alarms Which ONE (1) of the following could have caused this alarm?

A.

B.

C.

D.

NC system temperature less than 320°F 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC32B PORV OVERPRESS PROTECTION SELECT switches in "NORM"

- NC system temperature less than 320°F

- 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM" NC system pressure less than 380 PSIG 2NC34A OR 2NC36B PORV OVERPRESS PROTECTION SELECT switches in "NORM" 401-9 Comments:

Page 166 of185

FOR REVIEW ONLY - DO DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 68 General Discussion

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

---

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

---

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

IAnnunciator lAD-6IAI2, PORV LO PRESS MODE NOT SELECTED will alarm ifNC system WR temperature is less than 320°F with EITHER PORV Overpressure Protection Select Iswitch (NC34A or NC32B) not selected to "Low Press" (i.e. in "NORM").

I IThis KA is matched because the applicant must evaluate an alarm that is received and evaluate what could have caused this alarm. Evaluating what could have caused this alarm constitues a Idetermination of whether plant components (i.e. the PORV Overpressure Protection Select switches) are correctly aligned for current plant conditions.

I IThis question is analysis level as the applicant must analyze the alann and associate two separate pieces of information with that alarm (i.e. NC System Temperature and which PORV s are loperated by LTOP).

L _______________________________________________________ " ________________

Answer A Discussion

~o~~f~===~= =~=~~===-=== =~~==~

Answer B Discussion 1------------------

---

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

---

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

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Answer C Discussion

~~c~~~~~~~I=_~e~~~e~~e=~~§~~~~~~~~o~~~~E~~~~~~~~~~~3~1~~e~~~2i~~'=~I;;-a~~~h~~~~~~;~~~~~~~J~~~~ ~~~~t~~~~~V!~~e~Io~ ~f~~===

__ J Answer 0 Discussion ii~;~~t Pla~~hl; b~~;us~ -380pSiGisthe-~~;POiv ~etp~int;he;th~ PORVO~~rPr~~~~r~ p;;;t;;~t;;;;Sel~ts~itch~s~ s;l~cted ~-;;Lo~-p;.~s~'. Either ~ft~;~ PORY ~~le~t~;itch~s-to i~~~~"_\\\\,ill ~au~e_ala~:B~w~~1", ~~<::3j!3Js_ n()~on~ ~0~el11 ______________ _

,--~-~.--.-~-

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'- __________ 1_

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Que8tlonType-l-~~----------

Question Source

--.---- ~J -

~ -

- -- - -- -.-- - i-.- -~-- --.- -

Comprehension NEW I

____ ~ ______ L_. __________ ~ _________._._ ~ ___._

iO;v;topm-~':'i References----------------1 [student References Provided L"""_ --- -.-.-- -

~~.---- -.- - -- - -.----.------1 I-~--- ----.- -

---

.~-~- --.--

iLesson Plan OP-MC-PS-NC Objective 14 page 35 II

!OP/I/A/6100/1O G, Annunciator Response for Panel I I IIAD-6page15 I I I

i I I I I

I I L __________________ ~ ________ ~._~ ________ ~I L_~

401-9 Comments RESPONSE Considered SAT for submittal with no comments. No changes.

QuestlonB~q~!~1~?t!8it~~~~~~~~~~*~=~~l ~;~f~~~~;~~~DA~~~t>t~~~~~~~~*~~~~~~~~;~n~~~,~~d=i~~;~:n~,~nd~~~e~i~;~~~~:~~ectly

~-.-- ______ L __. __ ~ -~----~ [t:el'~ctth~~es~~F!aIl~lill~1IP~.LC!It_=_'!IJ~iis..:~2L____ _ ___ ~ _____________________. ____ ~ __ _

fuesday, November 10, 2009 Page 167 of 185 FOR REVIEW ONLY - DO N T DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 68 General Discussion

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

IAnnunciator lAD-6IAI2, PORV LO PRESS MODE NOT SELECTED will alarm ifNC system WR temperature is less than 320°F with EITHER PORV Overpressure Protection Select Iswitch (NC34A or NC32B) not selected to "Low Press" (i.e. in "NORM").

I IThis KA is matched because the applicant must evaluate an alarm that is received and evaluate what could have caused this alarm. Evaluating what could have caused this alarm constitues a Idetermination of whether plant components (i.e. the PORV Overpressure Protection Select switches) are correctly aligned for current plant conditions.

I IThis question is analysis level as the applicant must analyze the alann and associate two separate pieces of information with that alarm (i.e. NC System Temperature and which PORV s are 19P!0~9 !,y-,=,T~!L _______________________ ~ ____________________ " __ ~ __ " _______ " ___ ~ " _____ " __________ ~ __________ " ____ "_~~ ___,

Answer A Discussion

~o~~f~===~==~=~~========~~==~~==============~=======~====-=~=-=_===~~===============_==========----

Answer B Discussion 1---------"--------

---

~-----------"-"-------------"--~-------~-----"-------"---

---

"-----"-~------"- -- - --"----l II~~0I"f:c~.!~a~~\\)\\e_b~~a~~~~~~~CJ ~s t~_n~\\\\, !~~ \\f ~~~tp~iI1~\\\\'h~~tll~~~~ "'-~~e~~SStll"eJ>J_~t~c~~~ Sele~~~tche~~~~e~e~~d _t~~~\\\\' !~e_="'_!~~(~R_V~~~t~d~e_ C()~~~ __ J Answer C Discussion

~~c~~~~~~~I=_~e~~~e~~e=~~§~~~~~~~~o~~~~E~~~~~~~~~~~3~1~~e~~~2i~~'=~I;;-a~~~h~~~~~~;~~~~~~~J~~~~ ~~~~t~~~~~V!~~e~Io~ ~f~~===_=J Answer 0 Discussion ii~;~~t Pla~~hl; b~~;us~ -380pSiGisthe-~~;POiv ~etp~int;he;th~ PORVO~~rPr~~~~r~ p;;;t;;~t;;;;Sel~ts~itch~s~s~l~cted ~-;;Lo~-p;.~~~,. Eith~r ;ft;; POR\\! ~~le~t~;itch~s-to i~~~~"_\\\\,ill ~au~e_ala~:B~w~~I",~~<::3j!3Js_n()~on~~0~el11 ____________________________ ~ ___ " __________ ~_" ____ " ______________ ~ __

=-~9~iir!l~~!:~~~[==_l =~!!t~~Ii~=~====-=-====

-=.=

-Q~e~!~~~~£~====_====~ ___ =-===J 401-9 Comments RESPONSE Comprehension I

NEW I

I Considered SAT for submittal with no

---

-- - _L_ - - - -~ - ----- L ___ - --- - --- ~ ----- - --- ~---- -

- --~ -~ -- -- __. ____ J comments. No changes.

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved iO;v;topm-~':'i References----------------I [student References -Pro~ded---~---

L"""_ --- -"-"-- -

~~"---- -"- - -- - -"----"------1 1---------"- - ----"~--- --"--

iLesson Plan OP-MC-PS-NC Objective 14 page 35 II

!OP/I/A/6100/1O G, Annunciator Response for Panel 1 I llAD-6pagel5 I I I

i I I I I

I I L___ _________

~"_~ _________, L _________________

~ ____ ~ __ ~ __ _

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______== ___ =_=====_============-= ____ =_==-====-==-= ___ _

1 868iGEN2. 1 12.1.31 I

___________ ~ __________ 1" _____ " __ ~ _~ ____ ~ IConduct of Operations DAbility to locate control room switches, controls, and indications, and to determine that they correctly

[t:ell~ct th~~es~~F!aIl~lill~lIp*_tC!It_=_'!lJ~ii~~2L____ _ ___ ~ _____________________ " ____ ~ __ _

fuesday, November 10, 2009 Page 167 of 185

FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 69 I---~-'--'-

--~~--'---'-~-I.-~------'--~- -'I -'--' '---- ---~~---

---

~--- --- - ---

---

~-

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I _______

~ _________________. ___ ~ __

~ _______________ -' L ___. __

~ __. ___________________________________________________________

~ ___. __

CURRENT 45 DAY VERSION Given the following plant conditions:

Unit 1 is in MODE 3 The OATC has just denied a request from maintenance to close 1 ND-15B (Train B ND TO HOT LEG ISOL) for valve stroke time testing.

Which ONE (1) of the following describes the reason for the OATC's decision?

A Both trains of ND will become INOPERABLE.

B.

1 ND-15B would cause one ND train to become INOPERABLE.

C.

1 ND-15B is interlocked with 1ND-58A (TRAIN A ND TO NV & Nil.

D.

1ND-15B is interlocked with 1NI-136B (B NI PUMP SUCTION FROM ND).

Remove double period from "A" and "C" Given the following plant conditions:

Unit 1 is in MODE 3 The OATC has just denied a request from maintenance to dose 1ND-15B (Train B ND TO HOT LEG ISOL) for valve stroke time testing.

Which ONE (1) of the following describes the reason for the OATC's decision?

A B.

C.

1ND-15B is interlocked with 1ND-58A (TRAIN A ND TO NV & NI) and this will defeat the interlock and prevent 1ND-58A from opening.

Although this would be permitted in MODE 3, closing 1 ND-15B would cause one ND train to become INOPERABLE and is prohibited in MODE 4.

1 ND-15B is interlocked with 1 NI-136B (B N I PUMP SUCTION FROM ND) and will defeat the interlock and prevent 1ND-58A (TRAIN A ND TO NV & NI) from opening.

D.

This action would isolate the cross tie between the ND trains which ensures one ND pump can inject into all four NC loops. Closing it in MODE 3 would make both trains of ND INOPERABLE.

401-9 Comments:

Distracter analysis: "D" what does "the exposure will be greater if you wear the respirator" have to do with this Q')

"B" and "D": remove "to provide... " as this is teaching. Plus it is additional infonnation that is not needed.

RF A 10/09109 ruesday, November 10, 2009 Page 168 of 185 FOR REVIEW ONLY - DO N DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 69

---~-,--,-

--~~--'---'-~-I.-~------'--~- -'I -'--' '---- ---~~---

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---

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---

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c __, ____ ~~

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1869 11 GEN2.2 I

2.2.21 1

!Equipment ControlC'!Knowledge of pre-and post-maintenance operability requirements. (CFR: 41.10/43.2) 1 _____________,

, __ 0 L __. __. __. ______________________________________ ~ ___, _________________________ ~ ______ _

CURRENT 45 DAY VERSION Given the following plant conditions:

Unit 1 is in MODE 3 The OATC has just denied a request from maintenance to close 1 ND-15B (Train B ND TO HOT LEG ISOL) for valve stroke time testing.

Which ONE (1) of the following describes the reason for the OATC's decision?

A Both trains of ND will become INOPERABLE.

B.

1 ND-15B would cause one ND train to become INOPERABLE.

C.

1 ND-15B is interlocked with 1ND-58A (TRAIN A ND TO NV & Nil.

D.

1ND-15B is interlocked with 1NI-136B (B NI PUMP SUCTION FROM ND).

Remove double period from "A" and "C" Given the following plant conditions:

Unit 1 is in MODE 3 The OATC has just denied a request from maintenance to dose 1ND-15B (Train B ND TO HOT LEG ISOL) for valve stroke time testing.

Which ONE (1) of the following describes the reason for the OATC's decision?

A B.

C.

1ND-15B is interlocked with 1ND-58A (TRAIN A ND TO NV & NI) and this will defeat the interlock and prevent 1ND-58A from opening.

Although this would be permitted in MODE 3, closing 1 ND-15B would cause one ND train to become INOPERABLE and is prohibited in MODE 4.

1 ND-15B is interlocked with 1 NI-136B (B N I PUMP SUCTION FROM ND) and will defeat the interlock and prevent 1ND-58A (TRAIN A ND TO NV & NI) from opening.

D.

This action would isolate the cross tie between the ND trains which ensures one ND pump can inject into all four NC loops. Closing it in MODE 3 would make both trains of ND INOPERABLE.

401-9 Comments:

Distracter analysis: "D" what does "the exposure will be greater if you wear the respirator" have to do with this Q')

"B" and "D": remove "to provide... " as this is teaching. Plus it is additional information that is not needed.

RF A 10/09/09 ruesday, November 10, 2009 Page 168 of 185

FOR REVIEW ONLY - DO N T DISTRIBUTE A

2009 RO NRC Retake Examination QUESTION 69 General Discussion

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

---

~---

---

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

iThese motor operated valves are controlled from the ND section ofMC II in the Control Room by open/close pushbuttons. These 'fail as is' valves provide cross tie isolations for the ND ITrains. These valves have no auto open/close control features. These valves are opened in standby readiness, but closed in cold leg recirc.

iOn an ECCS actuation, the ND System must be capable of providing flow to all four NCS loops ( even with single failure). By having ND-15B and ND-30A open, either ND pump is icapable of supplying all four NCS loops. Therefore, closing either ND-15B or ND-30A in Mode I, 2, or 3 will make both ND trains inoperable. An alarm is actuated on the BOP panel iwhenever either of these valves reaches the 'closed' position.

IKA is matched because know the operability requirements for a proposed maintenance activity on a given component. Specifically, why the component cannot even be repositioned.

1

!question is comprehensive because the candidate must evaluate a given plant condition and mode and then evaluate the effect of a give component manipulation on system operability. This Irequires not only the recall of system knowledge but application of that knowledge to a given set of conditions.

L~~ __ ~~_. _____

~~. ___________._. __. ___.~. _____. ___. ____

~~ ___. __. ___. __________. __

~ _________

~ __. __. _______ ~ ____._. __

~~_. _____.

Answer A Discussion I-~------- -~--

ICORRECT

l. ____. __._.. ~ ____..

Answer B Discussion I. ------.-.-.-.-.-.-.-.- --- -

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

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

--'~-- -- - -

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

~~-.- - ---

IIncorrect. Plausible: Because it is a 'B' train valve it would be reasonable for a candidate to believe that it would only affect the 'B' train ofND L~ _______ ~

Answer C Discussion

--I

[----_..

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

IIncorrect. Plausible IND-58A is interlocked with other 'B' train valves..

~()t_~~ty~~~~a~I~!(J5(,)~fi1.s~ ~his.Y~~~iJ1!ll.at. ~ll.e!ll~ ___________ _

There are many interlocks associated with the train related electric valves associated with the ND system and would I

_~ __. ___ ~

... __. ___ J Answer D Discussion IIncorrect. Plausible. There are many interlocks associated with the train related electric valves associated with the ND system and would not be unreasonable to confuse this valve in that 1

l~cEeII~e_ _

_ _____ ~_

~ ~~ __.~ ~ ____. _____. __.. ~~_.. __. ____.~ ______.~ ___ ~ ____.~ _._._,~ _.~.~~ __ ~__ _ ~

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Question Source I 401-9 Comments RESPONSE r =~~I~I!v~!]~===~~~~1Y~1!~~I- --+-==-~-~~.=

I, RO 1

Comprehension l ________ -.l._. ___. __. _______.~_~

---~-MNS PSNDOi9---------~~ --- -1 Revised per Chief Examiner's suggestion.

-~- -~ - ~~---- ~ - -.~-~~~- -~ Rearranged answers for psychometric

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved r:--- - -------.---

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

!Development References t~--*~~*----*-- ---------- ~~-------~

ITechnical Reference(s): OP-MC-PS-ND Rev 40 iPg 39 lLearning Objective: OP-MC-PS-ND, Obj. 9 1

I _____ ~~.-~~-----.. ~-~-~--.--.----- ~. ____ _

~ ______ ~ _____ ~_.

balance. Answer 'A' is same correct answer ls.ttJ<<!~n.!~~~I'e_n~~8_~!>..,i~!<!____

as 'D' was before revision. HCF 11105/09 I

I i

1 1

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General Discussion ITh;;-;;;-~~t~;-~~r;rt~d~alv~~~;~~~t~ll;;-d~fr~~ th~ ND~ectio~~fMcllj~ th~C~t~IR~o~

-by~pe~~lo;e~p~shbutt~n-;~The;-;fail ~

T;'-v~I~sp;o~i~-cros;t~~i;-olati~~ for the ND ITrains. These valves have no auto open/close control features. These valves are opened in standby readiness, but closed in cold leg recirc.

iOn an ECCS actuation, the ND System must be capable of providing flow to all four NCS loops ( even with single failure). By having ND-15B and ND-30A open, either ND pump is icapable of supplying all four NCS loops. Therefore, closing either ND-15B or ND-30A in Mode I, 2, or 3 will make both ND trains inoperable. An alarm is actuated on the BOP panel iwhenever either of these valves reaches the 'closed' position.

IKA is matched because know the operability requirements for a proposed maintenance activity on a given component. Specifically, why the component cannot even be repositioned.

1

!question is comprehensive because the candidate must evaluate a given plant condition and mode and then evaluate the effect of a give component manipulation on system operability. This Irequires not only the recall of system knowledge but application of that knowledge to a given set of conditions.

L.. ~~.... ~~~ __.. _~ __ ~ ______._.~_.~_~. _____

~.~ __. __ ~ _.. ~ __. __. __ ~. ______ ~ ___. __.~ ____ ~~

__._~.~_.~ __ ~ ~ ~_. ___

~.~. __.. _.~ ___

~. _._._.~. __ -'

Answer A Discussion IcORRECT-~--~--~-----~-------~--------~~--~---~-~----~'~--~~---------.-------~~------.. -----~.~~---~-------~~I l _____, __

~ ____________________ ~~

____________________________________. ______________________________________________________________________ J Answer B Discussion I. ------

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.~~--.--~--

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

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IIncorrect. Plausible: Because it is a 'B' train valve it would be reasonable for a candidate to believe that it would only affect the 'B' train ofND L ________ ~

_____________________. __. ______. ______. __. __. __._. _____________. ___. _______________ ~

Answer C Discussion

[-

~~--... ~

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IIncorrect. Plausible IND-58A is interlocked with other 'B' train valves.. There are many interlocks associated with the train related electric valves associated with the ND system and would I

~()t_~~ty~~':J..n.a~l~!(J..c()n.111.s~ ~his.Y~~~iJ1!h.at.~ll.e!ll~.. ___ ~ _~ _________ ~ ___ ~ ________________ ~ _____ ~ _________ ~_~~~_. __ ~ __ ~

.. ~ ___ J Answer 0 Discussion

--~-------

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IIncorrect. Plausible. There are many interlocks associated with the train related electric valves associated with the ND system and would not be unreasonable to confuse this valve in that 1

l~cEe~e ____. _~ ______. ___... _. __... '~ ___ '~ ___ ~'_~.'_._.. _~. ____. ____ ~ __. __ ~_. __ ~~.. ' _._,_. __._.. __ ~.__ _ ~

______. _.. _. __._.. ~ ___._._

r=~~I~I!v~!]~===~~~~1Y~1!~!I~ _~ +. __.. _.~.. _~

I, RO 1

Comprehension l_~~ ____ ~.J._.~_~. __. ______ ~.. _.

.----9MNlIesStl5>.p'!SN~D~01l1~9 !---.~--~~~~ -'--'-"11 401-9 Comments RESPONSE Revised per Chief Examiner's suggestion.

-.. -~ - -. - --- ~- - -.- ~- - -.-~ --. - -'--'-.'- _....J Rearranged answers for psychometric

,--~

---

~--.--~

~ ---~~

!Development References I-Stud;nt-Refere-~ce8-P~ovided- ---

balance. Answer 'A' is same correct answer as 'D' was before revision. HCF 11105/09

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved t---*~

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

ITechnical Reference(s): OP-MC-PS-ND Rev 40 iPg 39 lLearning Objective: OP-MC-PS-ND, Obj. 9 1

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FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 69 A

fuesday, November 10,2009 Page 170 of 185 FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 69 A

fuesday, November 10,2009 Page 170 of 185

FOR REVIEW ONLY - DO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 70 B

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GEN2.2 I

2.2.35 IIEquipment Control [lAbility to detennine Technical Specification Mode of Operation. (CFR: 41.7 /41.10/43.2 /45.13)

I~ ____ ~ ____ ~

__..l~ ____ ~ ___.~ _____ ~ ___ ~~ __.I -~--___ ~~_~~_~

__ ~ ________ ~~_

---

~----~

---

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

~-- ~

CURRENT 45 DAY VERSION Given the following conditions on Unit 1 :

NC system temperature is 85°F Reactor Vessel head assembly is complete in preparation for Startup One Reactor Vessel head bolt was discovered not fully tensioned and has subsequently been re-tensioned Which ONE (1) of the following describes the current plant MODE and the Reactivity Condition requirements which apply per Technical Specification Definitions?

A MODE 5, Keff must be less than 0.95 B.

MODE 5, Keft must be less than 0.99 C.

MODE 6, Ketf must be less than 0.95 D.

MODE 6, Keff must be less than 0.99 G2.2.35 Given the following conditions on Unit 1 :

NC system temperature is 85°F All Reactor Vessel head bolts are fully tensioned Reactor Vessel head disassembly is in progress in preparation for Refueling Which ONE (1) of the following describes the current plant MODE and the Reactivity Condition requirements which apply (if any) per Technical Specifications?

A.

MODE 5, Keft must be less than 0.95 B.

MODE 5, Keft must be less than 0.99 C.

MODE 6, Keft must be less than 0.95 D.

MODE 6, no Reactivity Condition requirements 401-9 Comments:

I think C and D will immediately be eliminated but it meets NUREG requirements. The Q is OK as is.

RFA 10/29/09 Tuesday, November 10, 2009 Page 171 of185 B

FOR REVIEW ONLY - DO NO DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 70

~q~~~~~B~~k~~A=-s}t!~~=lKA_~~~~!~=====] [~~~!i~-=-===-=-=-==-~ ___====-~=====.==-===~=~======-=~=-=-==-=-=-==== =--==--====~=====- =-=~l i ~ ~~~~

.~1~_~N~*!~_t~~~_~~*~5~~~~~rl~qt1l{)me~~~~ntr~I~I~~I~~_to~d:t:.fll1~~l'echn~':'.~~CIf~~I()~l\\1()d.:.()~OY~~I()~:i~5~~..?L~L~~~~2!~5.. ~~~ __ ~_J CURRENT 45 DAY VERSION Given the following conditions on Unit 1 :

NC system temperature is 85°F Reactor Vessel head assembly is complete in preparation for Startup One Reactor Vessel head bolt was discovered not fully tensioned and has subsequently been re-tensioned Which ONE (1) of the following describes the current plant MODE and the Reactivity Condition requirements which apply per Technical Specification Definitions?

A MODE 5, Kett must be less than 0.95 B.

MODE 5, Keft must be less than 0.99 C.

MODE 6, Kett must be less than 0.95 D.

MODE 6, Keft must be less than 0.99 G2.2.35 Given the following conditions on Unit 1 :

NC system temperature is 85°F All Reactor Vessel head bolts are fully tensioned Reactor Vessel head disassembly is in progress in preparation for Refueling Which ONE (1) of the following describes the current plant MODE and the Reactivity Condition requirements which apply (if any) per Technical Specifications?

A.

MODE 5, Keff must be less than 0.95 B.

MODE 5, Keff must be less than 0.99 C.

MODE 6, Keft must be less than 0.95 D.

MODE 6, no Reactivity Condition requirements 401-9 Comments:

I think C and D will immediately be eliminated but it meets NUREG requirements. The Q is OK as is.

RFA 10/29/09 Tuesday, November 10, 2009 Page 171 of185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 70 B

General Discussion iMODE 5i;d~fi~ed a;-;200~F-~ith~Keff <. 99~ ~d <ill ~e~ct~~ ~e~-s~ihe~d ~l~;-b~u;,fi~iiyte~;~~~d~ MODE~6i;-d~tfu;d-~~20ifF ;jth';t k;~~e~~ct~~~;l~h~~cl~s;';-r~bolt ;~- ~

ifully tensioned. There are no reactivity condition requirements defined for MODE 6 in the MODE table in Tech Specs. However, the COLR requires that the reactivity condition requirement Ifor MODE 6 is <0.95.

I IThis KA is met because the applicant must evaluate a given set of conditions and determine the plant MODE and additional conditions which apply to that MODE.

I IThis is an analysis level question because the applicant must associate three pieces of information to determine the correct answer. The candidate must recall from memory the general irequirements for MODE 5 & 6 from the table in Tech Specs. The applicant must then determine from the given information that all reactor vessel head bolts are fully tensioned applying a l~~Jn~~eI~ Ia~I~(()~ifr~~n!iilte~b~~ee~~gQ~ _~ ~n~~gQ~~I~e

-.ilepli~~t E1lls.£tI1~l1!~c~l~tI1e -,,~a~tj~ity ~oE<iitl9~~!Jich-.ilePlie~t().£h~~PE*~ ___ ~_~

~ _~_ ~~ ~ ~_

Answer A Discussion

[-------~~-~---~----

---~--~~

~--~--

~-~-- --

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

~---~--~

~

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

---

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

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

lIn correct. This is the correct MODE. However, the required Keff is <0.99. Less than 0.95 is plausible as this is the required reactivity condition for MODE 6 described in the COLR.

L _____________________________________

~ ________

~ __

~ _______

~ ________.~

____ ~~

~ _______________________________

~ _________

J Answer B Discussion

~§~C!~~~_~--~-- -

--~~I

_~ ___ J

--~-

---

~~~-~

Answer C Discussion

'---~-~~~--

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

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

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--~~--

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~-~~--~--

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--~-~~

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~-~--

iIncorrect. Mode 6 is plausible since one head bolt was discovered to be not fully tensioned. However, after retensioning the unit returned to Mode 5. Also, the COLR requires Keff <0.95 for

~ODE6.

Answer 0 Discussion r;:-~~~--~-~~--~~--~~ -----~--~~~~--~-~-~--~-~-~~-~-~~----~~~-~~-~--~---~~-~~-~----~~~-----~---~~~~--~--~--~---~-~-~--~-~--~-,

Incorrect. Mode 6 is plausible since one head bolt was discovered to be not fully tensioned. However, after retensioning the unit returned to Mode 5. Keffless than.99 is plausible as that is

\\

Ithe required reactivity condition for Mode 5.

I

__ ~_~_~ ____ ~ __ ~~ __ ~ _______ ~ ___ ~ ____ ~

___ ~~ _ ~ _____ ~~~

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~ OPS Approved

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---

-~I comments. No changes.

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iTS 1.1 Definitions, Table 1.1-1 MODES I

iCOLR 2.1, Operational Requirements for MODE 6 I

I I

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IEquipment Control [!Ability to determine Technical Specification Mode of Operation. (CFR: 41.7 /41.10/43.2/45.13)

L_ ~~~~~ ____ ~~~~ _______ ~~_~ _~~_~~_~

__ ~ ~~~~

___ ~

__ ~ __ ~_~

__ ~ __

~~_~~ _

Tuesday, November 10, 2009 Page 172 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 70 General Discussion iMODE 5i;d~fi~ed a;-;200~F-~ith~Keff <. 99~ ~d <ill ~e~ct~~ ~e~-s~ihe~d ~l~;-b~u;,fi~iiyte~;~~~d~ MODE~6i;-d~tfu;d-~~20ifF ;jth';t k;~~e~~ct~~~;l~h~~cl~s;';-r~bolt ;~- ~

ifully tensioned. There are no reactivity condition requirements defined for MODE 6 in the MODE table in Tech Specs. However, the COLR requires that the reactivity condition requirement Ifor MODE 6 is <0.95.

I IThis KA is met because the applicant must evaluate a given set of conditions and determine the plant MODE and additional conditions which apply to that MODE.

I IThis is an analysis level question because the applicant must associate three pieces of information to determine the correct answer. The candidate must recall from memory the general irequirements for MODE 5 & 6 from the table in Tech Specs. The applicant must then determine from the given information that all reactor vessel head bolts are fully tensioned applying a l~~Jn~~eI~ Ia~I~(()~ifr~~n!iilte~b~~ee~~gQ~.~ ~n~~gQ~~I~e

-.ilepli~~t E1lls.£tI1~l1!~c~l~tI1e -,,~a~tj~ity ~oE<iitl9~~!Jich-.ilePlie~t().£h~~PE*~ ___ ~_~

~ _~_ ~~ ~ ~_

Answer A Discussion

[-------~~-~--.~----

---~-.~~

~-.~.-

~.~-- --

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

~---~--~

~

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

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

~-~--~--

--*-------~---~-~~-I

~~~0.l'r::t.~T~is.~s ~~~~ect_~~~~~W(:"_eI',~:.re~.u~~~~f~i~~0.9~.~~~~~.9~~. pla~i!'le as.!1li~is..t~e!'~~uired~r~a~t~~..:~nditi~n.!()I'~9~.~~(je~cI"i~e~ ~ ~~~~~~_~~_~I Answer B Discussion

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

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

~~-

~-~ ~~.~--

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

~~

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

~~--~~~--~-~---~~--~-----~~-----~~~-~-~----~~I I CORRECT.

I L~ ____ ~~ ______ ~ __ ~~~~~ __ ~.

__ ~~_~_ ~~~ ~ __ ~ __ ~ __ ~ __ ~~_

~_~ ~ ___ ~ ___ ~~~_~~

_____ ~ __ ~_~_~_~ ___ ~_~~

___ ~ ~_~ ___ ~~~_~~_~ __ ~~_~~

__ ~ __ ~ ___ ~

Answer C Discussion

'---~-~~~--

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

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

~--~~ ~~~--

--~~--

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

~-~~--~--

~~--~-~

--~-~~

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

--~-----

~-~--

~----.-:

IIncorrect. Mode 6 is plausible since one head bolt was discovered to be not fully tensioned. However, after retensioning the unit returned to Mode 5. Also, the COLR requires Keff <0.95 for

~.!2§~~_~_~_~_~ ~ ___ ~ __ ~_~ _~~~~ __ ~ __ ~~~ __. ___ ~~_~~_~ ___ ~_~ __ ~_~ _____ ~ ___ ~ __ ~ __ ~~.~ ___ ~_~~~_._~_~ ____ ~~~ __ ~ __ ~

Answer 0 Discussion r;:-~~~--~-~~--~~--~~ -----~--~~~~--~-~-~.-~-~-~~-~-~~----~~~-~~-~--~---~~-~~-~-.--~~~-~---~---~~~~--~--~~-~--.~-~-~--~-~--~-,

Incorrect. Mode 6 is plausible since one head bolt was discovered to be not fully tensioned. However, after retensioning the unit returned to Mode 5. Keffless than.99 is plausible as that is

\\

Ithe required reactivity condition for Mode 5.

I

__ ~_~_~ ____ ~ __ ~~ __ ~ _______ ~ ___ ~ ____ ~. __ ~~ _ ~ _____ ~~~

~ ___ ~~~~_~~_~~~~~~_~~~_~~~

____ ~~_~ ___ ~~~_~~_~ ___ ~.~~.~~_~_~~~_~ ____ ~~~_~--.J II =-Io~I~~i C()~"-'tiv~..l.-.!~e-,- _

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~

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~-~l Questi()f~_1}'ee~.l __ ~ ~_~_~~_~ ___ ~.9tJ~..!I'<>.fl.~~Ll.r~e~~~~~~_~_~~ ~ _~~ 401-9 Comments RESPONSE

\\

RO I_~ ~ ~ ____ ~~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension Tuesday, November 10, 2009 NEW I

I Considered SAT for submittal with no

__ L~ ~~~~--~~--~-~-~~--~~~-~~~ --~~---- ------~I comments. No changes.

rQ~elOe~!.n} ~~f!~~~ei~-==-~==~=-~--- ~ ~

ITS I.I Definitions, Table 1.1-1 MODES ICOLR 2.1, Operational Requirements for MODE 6 I

i L~_~~ __ ~~ ___ ~ ____ ~_~~~ ___ ~ __

8~.!!:~=--===--~====-~=====~~=~ -~ =-~====-===~~-~-~==~~~===== =~~-==========J IEquipment Control [!Ability to determine Technical Specification Mode of Operation. (CFR: 41.7 / 41.10 / 43.2/45.13)

I L __ ~~ ______ ~_~~ ________ ~_~ _~~ ____

~ ____ ~ _____ ~

__ ~ __ ~ ____ ~ ______ ~ _______ ~ ____ ~_~ __ ___._J Page 172 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE D

2009 RO NRC Retake Examination QUESTION 71

,---- ----- -----,---- -------- ------ - ---- ---1 r;:-------------- ---------------- ---------- ----- -

iQuestlonBank # IKA system IKA number IKA dese

]-------------t--=------ -f'-'-=--- --- -- ___ J 1- -=---- ------ - - -------- ------ -- ----- -

l_ ___

I_~~ ~__1 __

G_E_N_LL_l_~ __ ~~.~~ ____ J Radi.ation Control L;Kno~ledge of r~d!ol?gical safety principle~ pertai?i~g to licensed operator duties, such as containment entry ir<:'lu~r~fI1e...n!S,Jll~J1ll....ncI~~~espon~bIlltles,~~cess.t<:>}oc~~~h-r!lCl~tJ0_il!.r_.eas, ilI.~~~fiI~~~~~<<=~~:j!*!2.L4~_:2~'!5 __ J()L CURRENT Given the following:

A rapid load reduction from 1 00% power to 60% power was performed on Unit 1 approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

1RAD-2 / C3 (1 EMF 48 REACTOR COOLANT HI RAD) annunciator is LIT Chemistry confirms that reactor coolant 1-131 activity indicates that fuel damage has occurred.

In accordance with AP-18 (High Activity in Reactor Coolant), which ONE (1) of the following methods would be used to reduce the activity levels in the NC system?

A Ensure an NC filter is in service.

B.

Raise letdown flow to 120 GPM.

C.

Divert letdown flow to the Recycle Holdup Tank.

D.

Place the Cation demineralizer in service.

G2.3.12 45 DAY VERSION Given the following:

A rapid load reduction from 100% power to 60% power was performed on Unit 1 approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

1RAD-2 C3 (1EMF 48 REACTOR COOLANT HI RAD) annunciator is LIT Chemistry confirms that reactor coolant 1-131 activity indicates that fuel damage has occurred.

Which ONE (1) of the following actions would reduce the radiation levels in the Auxiliary Building caused by this event?

A Ensure an NC filter is in service.

B.

Raise letdown flow to 120 GPM.

C.

Place the Cation demineralizer in service.

D.

Ensure 1NV-127 A (LID Hx Outlet 3-way Temp Cntrl) in "VCT" position 401-9 Comments:

D is not plausible for this failed fuel event. It is common knowledge to redirect letdown.

Replace D.

RF A 10/29/09 Tuesday, November 10, 2009 Page 173 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 71 D

i9~~St~~~~~~t4gA---81~t8~~ _~:~u;~e-r~ ~ ~.~=] ~~~~

____ =~ =

___ ~==_=_==~=~=__==.=.~===-~===~_====.~~= _

.. ~ ______ ~ _________.

__________ ~._

i 1871 GEN2.3 i

2.3.12 IIRadi.ation ControH.:; Kno~ledge of r~d!ol?gical safety principle~ pertai?i~g to licensed operator duties, such as containment entry L -

___.l_~ __ --------- ir<:'lu~r~fI1e..n!S'-fiI~.I1ll...ncll1.~..':espon~bIlltles,..<t~cess.t<:>}oc~~~h-r!lCl~tJ0_il!.r_eas, ilI.~1l.[.fiIt~I"~.e~:...<<=J!..~:j.!..!2.L42:2~'!5_'J()L CURRENT 45 DAY VERSION Given the following:

A rapid load reduction from 100% power to 60% power was performed on Unit 1 approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

1RAD-2 / C3 (1 EMF 48 REACTOR COOLANT HI RAD) annunciator is LIT Chemistry confirms that reactor coolant 1-131 activity indicates that fuel damage has occurred.

In accordance with AP-18 (High Activity in Reactor Coolant), which ONE (1) of the following methods would be used to reduce the activity levels in the NC system?

A Ensure an NC filter is in service.

B.

Raise letdown flow to 120 GPM.

C.

Divert letdown flow to the Recycle Holdup Tank.

D.

Place the Cation demineralizer in service.

G2.3.12 Given the following:

A rapid load reduction from 100% power to 60% power was performed on Unit 1 approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

1RAD-2 C3 (1EMF 48 REACTOR COOLANT HI RAD) annunciator is LIT Chemistry confirms that reactor coolant 1-131 activity indicates that fuel damage has occurred.

Which ONE (1) of the following actions would reduce the radiation levels in the Auxiliary Building caused by this event?

A Ensure an NC filter is in service.

B.

Raise letdown flow to 120 GPM.

C.

Place the Cation demineralizer in service.

D.

Ensure 1NV-127 A (LID Hx Outlet 3-way Temp Cntrl) in "VCT" position 401-9 Comments:

D is not plausible for this failed fuel event. It is common knowledge to redirect letdown.

Replace D.

RF A 10/29/09 Tuesday, November 10, 2009 Page 173 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 71 D

General Discussion

'ISince the high activity is due to failed fuel, the appropriate action would be to ensure that a mixed bed demineralizer is in service (per AP-IS).

I iKJA is matched bacause the candidate is asked to evlauate a given set of plant conditions which represent a concern with elevated radiation levels in the auxiIIiary building. He is then asked Ito evaluate actions which would result is lowering the rad levels. This is consistant with the radiological safety principle of ALARA and the actions described are operational in nature and Itherefore not part of general rad working training.

I IThis is a comprehensive level question because the candidate must evaluate multiple pieces of information given and then analyize a proposed set of actions to take and arrive at an apropriate iconclusion for the correct couse of action.

L"_~_~~ __ ~~ _~~~

___ ~~ ___ ~~~~ ____ ~~ ___ ~~_~~~ ___ ~~_ ~~_~~~ __ ~~~~~~_~~~_~~ ___ ~ __ ~~~ _~ __ ~~~

__ ~~~~~ ~~~ __ ~~~ __ ~~_ ~ ~~~

Answer A Discussion r;---~ ~-~~-~~---~-~~ --

~~--

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

l~n~~rr~~~Plaus~b~e!,~~ ~~~~t~~~~.~ll~~o~a~~~~u~:

Answer B Discussion IIncorrect. Plausible if the high activity is due to a crud burst.

L ~.~~_~~._~~.~ ______ ~ ~~~~ __ ~

__ ~.~~_~~_~ ~ _ ~_~~~~~

Answer C Discussion

~~~-I

_~~~~~J r~~~~~-~~~

~-

~~~~

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~--~

~~-

---

~~-

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

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

IIncorrect. Plausible because diverting letdown flow to the RHT would reduce NC system activity levels due to dilution. However, it is not the method prescribed by AP-IS.

L ________. __________________ " _____ _

Answer 0 Discussion

!CORRECT~ ~-~

~~-

~ - ~~ - -~~

~

L_._~

_.~ ___

~ _~ ~ ~~~_.~._ ~~~_ ~

~J~obR~vel ~r ~~~~Sl'!i!'v~_~~el

~_.1 __. ___ ~. ~... __ ~

Que!tI_onTYp'e BANK

~ Developed

~ OPT Approved

~ OPS Approyed

~ NRC Approved

~~~Iop~~~ f!!!~,!11C~!

lAP-IS, High Activity in Reactor Coolant page 3 I

I I

i Question Source

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

CNS 2006 NRC Q71 (Bank 14S)

I~~-~~~~-~~~~-~~*~~~-~~~

IStudent References Provided r~~*~~~~~~-*-~~~~--~~-

~~

I I

I 1

L_~.~~ __ ~~~~~_~

_.~~ ~~_~~~.~ __ ~

---I 1

~. ~~ ~.~ ~~~J 401-9 Comments RESPONSE Per Chief Examiner's recommendation, replaced distractor 'D'. Then, swapped answers 'C' and '0' for psychometric balance making answer 'D' the correct answer instead of'C'. HCF 11105/09

-~.-~~ -

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~I IS7IiGEN2.3 12.3.12 J r~A~~~~~====-_========~====~=======___===~*======~=~=======~~=~=~=====-=~~~~~

IRadiation Control 0 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment I,

~.~ ~~~ ___ ~ __ ~~.~ __ ~.~.~ _~ _L ~~

.~~ ~ ____ ~~. __ ~

lentry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 145.9 1

~~5~ IQL~. _~ __ ~~~~~~~~ _~~ __ ~~~~ __ ~ __ ~~~~~ ~~_~~ __ ~ ~_~ ~~~~ __ ~~~~~~_~ ~~~~ j ruesday, November 10, 2009 Page 174 ofl85 FOR REVIEW ONLY - DO N T DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 71 D

General Discussion isin~the-high~cti~tyis-d~~t~fail~d f~el,th~ ~ppr~p;:i;t;a-;;tio~ ~~uldb~io---;;~~~~th;ta-~~~d~dde~iner~i~e;i~ ~

~;-vic~(p~ AP-I8).--- ~-- --- - - --- ---- ~-

I iKJA is matched bacause the candidate is asked to evlauate a given set of plant conditions which represent a concern with elevated radiation levels in the auxilliary building. He is then asked Ito evaluate actions which would result is lowering the rad levels. This is consistant with the radiological safety principle of ALARA and the actions described are operational in nature and Itherefore not part of general rad working training.

I IThis is a comprehensive level question because the candidate must evaluate multiple pieces of information given and then analyize a proposed set of actions to take and arrive at an apropriate iconclusion for the correct couse of action.

L"._. __.. ______._. ___. _____. ______________... _____. ____. ________ ~ ______. ____ ~_._._~ __.. ________ ~.

Answer A Discussion r;.--- ----.--.-.------ ---. ----.~-----.- --.----- --------.-

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

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

-~--

jlncorrect. Plausible if the high activity is due to a crud burst.

I

'_. __. ___.. _________ ~ ____.. ___. ______. __.~ _________. ______._. ____. __. _____. _________ ~ ___. _________. __. _______._~ _____ ~_~ ___._. __. ____ J Answer B Discussion l0~<0~!~0ib~i!t§E~~~~tT~t)'-~iu~i~~~0~~u~~_=_~=_~~~~~~-~~=~-~-_____ ~_-_-_~=-~~_-_-~-_-~~_-=__-~_-_~_-_-_-=-_=__-_-_-~=_~ __ =_-_-_-_-_-~ _______ -_=~-_~ ___ i Answer C Discussion r---~----- -- ---- --.------------.- -.-.- -----.- -.-- --- -------

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

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

IIncorrect. Plausible because diverting letdown flow to the RHT would reduce NC system activity levels due to dilution. However, it is not the method prescribed by AP-I8.

L._. ____. ________. ______. ______________. ___

. ___. ______. __._._._. _____. _____ ~

. ____. _______ ~

___. _____ ~

.~ _ ~._. __.. __._. _______ J Answer 0 Discussion ICORRECT- --- --- ---- -

---

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

---

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

L____

_. ____________._. _________ ~~ ____._._. _________. _______. __. ________

._~ ___________ ~_. ___. ______ ~. __. __ ~ ____ ~ ___. _____. ____ I

---

- -r -~-*----*----*---I------*-*-*--

Job Level I'

Cognitive Level I Quest/onType Question Source i 401-9 Comments RESPONSE

- -- -- -----~----- - --- - --------1----- ---~---

RO 1

Comprehension I

BANK

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

.-.~ --- -

- ----)

______________ C_NS 3~~6_N_R~_07 ~~~n~!..~L __________ J Per Chief Examiner's recommendation, replaced distractor 'D'. Then, swapped answers 'C' and '0' for psychometric balance making answer 'D' the correct answer instead of'C'. HCF 11105/09

--~

---~-----~ -

--~----------------'-------------~---

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved roevelopmeniRefe~n-ce8 --- -------~----

I""'--------.-----.--.--.------.--.--~-

JAP-18, High Activity in Reactor Coolant page 3 I

I I

i 1--*---_*_--_* __ *_------

IStudent References Provided r--*------------------ --

I I

I I L._. _________ ~

__. _____ ~ ___._~

Q~;stionBank-#~KA~System-1KA~nUmb~~--- - --1 IKA~d;;c- ----- --- ---------- - ---~-------------- ---------------~- -~-~--~i

-~=-~ ___ -_-_ -

18!~~~~z_.3~-~ _-_Ji3~2=_-_- -_ -_~--1 :Radi;tio~~~~tr~iOK-n~;I~dg.~ ~f ~ad;;I;;.~~~;futypr~~iPl~sp~~i;i~gt? ~~~s-;ct-~p~~~t~d~tk~~-u~h; -~~~~~~~nt--l lentry reqUirements, fuel handlmg responSibilities, access to locked high-radiatIOn areas, alignmg filters, etc. (CFR: 41.12 145.9 I II 45.10)

I

~- ___. ___. _____. ____. ____._~ ______. ___._._. ___________. ____ ~ _____. __ ~ ___. _____. __ J ruesday, November 10, 2009 Page 174 ofl85

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 72 C

9~sT~~~~~tIT~~ji!~,y; ___ ~~~rtU~b;r _______________ ] ~~=de~C

___ ---=~=---=

_________________________ =

________________________ =

~-__________ ~ ___________________________________________________________ ~ ___==~ _______________ -

---

I I

1872 I

GEN2.3 I

2.3.14

[IRadiation Control [JKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency l~_ ~- -- ~~-- -- ~ - --~~~- ~-'---~---~~----~ J Iconditions or activities. (CFR: 41.12 1 43.4 145.10)

L ______

~ _________________________________ _

CURRENT After realigning the NV system for startup, a valve located in a high radiation area requires independent verification.

Given the following conditions:

General area radiation levels are 130 MREM / hr Estimated time to independently verify the position is 10 minutes There are no known hot spots in the area There is no airbome activity in this room The room has no surface contamination areas What are the ALARA requirements related to waiving the independent verification of this valve per NSD 700 (Verification Techniques)?

A B.

c.

D.

Independent verification may be waived for all valves in high radiation areas until after shutdown.

Independent verification may NOT be waived until General Area radiation levels are reduced to less than 100 MREM / hr.

Independent verification may be waived because the exposure to the operator exceeds ALARA guidelines.

Independent verification may NOT be waived because exposure to the operator will be within ALARA guidelines.

G2.3.14 45 DAY VERSION After realigning the NV system for startup, a valve located in a high radiation area requires independent verification.

Given the following conditions:

General area radiation levels are 130 MREM / hr Estimated time to independently verify the position is 10 minutes There are no known hot spots in the area There is no airbome activity in this room The room has no surface contamination areas What are the ALARA requirements (if any) for waiving the independent verification of this valve?

A.

B.

c.

D.

Independent verification may be waived after an evaluation by the NLO.

Independent verification is waived for all valves in high radiation areas until after shutdown.

Independent verification may not be waived for ALARA considerations under these conditions.

Independent verification may be waived because the exposure to the operator exceeds ALARA guidelines.

401-9 Comments:

Distracter A is weak. This is too important of an evolution to be evaluated and approved by an NLO.

Replace A.

Tuesday, November 10, 2009 Distracter C: State a reason instead of "under these conditions" RF A 10/29/09 Page 175 ofl85 C

FOR REVIEW ONLY - DO 2009 RO NRC Retake Examination DISTRIBUTE QUESTION 72

9l1!sT~~~~~t1~~ji!~.n ___ ~~~rtU~b;r _______________ ] ~t{.(~de~C=~~~ ____________ = _____________________________________________ =

~ ___ ~~ ___________________ ---------=------------=-------------------------------~~--~----J I

1872 I

GEN2.3 I

2.3.14 IIRadiation Control [JKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency I

1 __ -- -- ---- ~~ ~ - ~-~--- --'-------~------ J Iconditions or activities. (CFR: 41.12 1 43.4 145.10)

I L ______

~ ______ ~

_______________________________ ~

~ _______________ _

CURRENT After realigning the NV system for startup, a valve located in a high radiation area requires independent verification.

Given the following conditions:

General area radiation levels are 130 MREM / hr Estimated time to independently verify the position is 10 minutes There are no known hot spots in the area There is no airbome activity in this room The room has no surface contamination areas What are the ALARA requirements related to waiving the independent verification of this valve per NSD 700 (Verification Techniques)?

A B.

c.

D.

Independent verification may be waived for all valves in high radiation areas until after shutdown.

Independent verification may NOT be waived until General Area radiation levels are reduced to less than 100 MREM / hr.

Independent verification may be waived because the exposure to the operator exceeds ALARA guidelines.

Independent verification may NOT be waived because exposure to the operator will be within ALARA guidelines.

G2.3.14 45 DAY VERSION After realigning the NV system for startup, a valve located in a high radiation area requires independent verification.

Given the following conditions:

General area radiation levels are 130 MREM / hr Estimated time to independently verify the position is 10 minutes There are no known hot spots in the area There is no airbome activity in this room The room has no surface contamination areas What are the ALARA requirements (if any) for waiving the independent verification of this valve?

A.

B.

c.

D.

Independent verification may be waived after an evaluation by the NLO.

Independent verification is waived for all valves in high radiation areas until after shutdown.

Independent verification may not be waived for ALARA considerations under these conditions.

Independent verification may be waived because the exposure to the operator exceeds AlARA guidelines.

401-9 Comments:

Distracter A is weak. This is too important of an evolution to be evaluated and approved by an NLO.

Replace A.

Tuesday, November 10, 2009 Distracter C: State a reason instead of "under these conditions" RF A 10/29/09 Page 175 ofl85

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 72 c

General Discussion

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

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~~_ -

_~~ ____ I Answer 0 Discussion

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BANK

___. __________ ~~ ____ L

___ ~ ~ __ ~~ __ _

MNS Bank Question ADMOMPN036

-'~- ---- - --

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~'---l c: --~-~

-~

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IDevelopment References I IStudent References Provided I

~~~~.~-~--.-- -------- ~--~ - -.-~- ~~-~--~ -~~---, I ~----~--~~.~~~--~~---~.-~-j iNSD 700 Verification Techniques page 9 (previously I I I

IOMP 8-2 Verification Techniques) and Lesson Plan OP-III I

iMC-ADM-OMP objective 22 related to OMP 8-2.

I.

I iOMP 8-2 was deleted in April 2009 and the ADM-II I

IOMP Lesson Plan has not yet been revised to make the III I

Ichange to NSD 700. However, the applicants would L_~~ ----~~- ~ ~ --- -~---~ ~ - --~~~

Ihave been responsible for the requirements ofOMP 8-2 I

~~<I. tl1()~_r~CjlJirenleI1~_did_l1O~~i1.al1£e~~i~h ~~_70J

___ ~!

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 401-9 Comments RESPONSE Per Chief Examiner's recommendation, replaced distractor 'A'. Changed distractor

'C' to state a reason instead of "under these conditions". Rearranged answers for psychometric balance (B to A, A to B, D to C, C to D) making 'C' the correct answer.

~~!!tI~~~~~~~KA":-S1~~~~~l~:lt~~tl!!=~==~=1 i~_~d~~~=====-=======~=====~==============_==~=-=-====-=========-================1 1872iGEN2.3

!2.3. I 4 1 !Radiation ControlCKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency I

-~~~----~- ~J __ ~_~ ___ L

---~~~-~--~~ --' ~l1cliti.0_n~()racE\\'iE~s. ~C!.!Z.:.~I __ t.2J~4~~!~~..!.()L __________ ~_~~ __ ~

___ ~ __ ~_~ ___ ~~_~ ____________ 1 ruesday, November 10, 2009 Page 176 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 72 c

General Discussion

,~ --,,~--

---,~~--

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IAccording to NSD-700, Independent and/or Concurrent Verification may be waived if the exposure to an individual of greater than 10 mrem for a single verification would occur. This waiver

!requires supervisory approval and documentation.

I IThis KA is met because the applicant must evaluate a potential exposure hazard and determine which requirement applies to that potential exposure.

i iTJ1i~~~~ lUlilly~s _ '!ll~s!i()n_~~au~_t~e ~EE!i<;~n~ ~ reg~iI"ed t~ ~a!c~lll~tlle ~_o~eE~ill ~~.?~lll"~aIl~ ~he~apEly ~limiiI"e~al~~t1-~~ll1e_~09_ <<)~~rr~~I!Y~lt~~w~~ tl1~ q~~t~Il'_~~

Answer A Discussion r;---'~ -----------------------,----- ~---------- -- -- -

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--~---,------- -,--

-~-'-- 1 IIncorrect. Plausible because IV in a high radiation could potentially exceed the 10 mrem guidance for a single exposure. However, IV cannot be waived simply because the component is in a

'I l!I~~~~clillti91l~I"elt* ____________ ~_~_~~___ ___ ______ ~~~ ___ ~ ___________________ ~ ______ ~ _______ ~~

__. ___, ___, ____,_._~~ ~ ___ J Answer B Discussion

,~ -,----'- -'--,----- -- - - ---- -----,------ -----~---~-----,-- --------------- ~-~--.-------------~----,-,---------,---

-~------ -'-l lIn correct. Plausible if the applicant believes that independent verification can not be waived in areas with radiation levels above 100 MREM / h r. 1

,_,~. _______. __,_~ _________ ~ ~ __

~ _____ ~ ___

~ ___.~_~~ ________ ~_~ _______ ~ _____ ~_,._.~ ___, _____, _____

~ _________. _____ ~ _____. _____________ J Answer C Discussion

~ORRECT~-~

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~ ___________

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~ __________________________________________________________ 1 Answer 0 Discussion c*~'----*-'--.-- -

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~~_Q!lJti'_'_~L.~v~! ___ 1 __ que~!i~'!"l)p~ _, i __ ~ __ ~ _________ ~u!!tion~~ur~! _______ ~~ _____ _

1 ___ ~() __ J~_~~ ~~lll~re~en~~~ __ ~ J~ ___ ~;\\~~ __ ~ _ L ________ ~ __ ~~!~~k_

~~~t~0~!_?!':f~rv1~~036 __

--~- - --

---

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--~~----~--~ ----.----,

l~!V~!OP_'"'!~fl~ ~e!!':!I1~ell ___ ~ _______ ~ ____ ~~ f~ud~nt~_e!~'!'!ces~!~\\IIcJ!~ ----J iNSD 700 Verification Techniques page 9 (previously I I I

IOMP 8-2 Verification Techniques) and Lesson Plan OP-II' I

jMC-ADM-OMP objective 22 related to OMP 8-2.

I.

I rOMP 8-2 was deleted in April 2009 and the ADM-II I

IOMP Lesson Plan has not yet been revised to make the I I I

ichange to NSD 700. However, the applicants would I L ___ ---~--~ - - --- ~----- - - -~---

Ihave been responsible for the requirements ofOMP 8-2 I

~Il~ tl1()~_r~CjlJirer~eIl~_did_~~~i1al1~e_~i~h ~~. 70J~_!

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved 401-9 Comments RESPONSE Per Chief Examiner's recommendation, replaced distractor 'A'. Changed distractor

'C' to state a reason instead of "under these conditions". Rearranged answers for psychometric balance (B to A, A to B, D to C, C to D) making 'C' the correct answer.

iuestlonB-ank #I IKA"

-system--TKA-=-number- ~~-~ -1 :KA_desc-----~--------------~ --------------.'.-

---

~--- -----------~------~-l

~ -~- -----I8721GEN2~3 --- ~ lf2-:iT~ --.-~ -~~ ----1 [Radi~ti~n-Co;tr-;ICi(n~~ledg~ ~f~~diati~;~r-c~~t~~i~ati~;h~;rd;th;t~ay~i~~d~rhIg~~~~C ab~~~~C ~;-e-;;;;;g~n~y--l

~---~----- _J_~ ____ ~ __ ------~--~-- --' ~~cli~o~n~()racE\\'iE~s. ~CX!Z~~I __ !2J_4~~!~~.1Ql ______ ~ _____ ~ _____ ~, __ ~ ___________ ~ ____ ~ ______ I ruesday, November 10, 2009 Page 176 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 72 c

fuesday, November 10, 2009 Page 177 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 72 c

fuesday, November 10, 2009 Page 177 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 73

---

~--- -~- r.--

---

~-c--~-----~-

IQuestlonBank # KA system IKA number f -

-~--- -~-f --=~- ---- T- ~"'"---~- - --------

IKA desc I-~--=-~-- ------~-~~~-~----~---- - --~~--- ---~~----~~---- --~~-~--~-~-~--

---

~-~-~----

IRadiation ControlCJAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 1 145.10) 1873 I

GEN2.3 1

2.3.7 L_~ ___

~ _____ ~ ______________,_

[~-~---~- ~----~-~--~-~----~---- -~-

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

CURRENT A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

The worker's present exposure is 1938 MREM for the year The RWP states:

o General area dose rate = 30 MREM/hr o Airbome contamination concentration = 10.0 DAC The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the oorker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the worker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which ONE (1) of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A B.

C.

D.

The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

The worker must wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one.

The worker must wear the respirator.

He will exceed DAC limits.

G2.3.7 D is not plausible as written.

45 DAY VERSION A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

The worker's present exposure is 1938 MREM for the year The RWP states:

o General area dose rate = 30 MREM/hr o Airborne contamination concentration = 10.0 DAC The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the oorker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which ONE (1) of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A B.

C.

D.

The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

The worker should wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one.

The worker should wear the respirator.

He could exceed DAC limits.

401-9 Comments:

D: Change to: "should" to "must" and "could" to "'will" RF A 10/29/09 Tuesday, November 10, 2009 Page 178 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 73

-~--~--- --- r.--

---~~~c--~~--~---

~-=~~!C------~-~~-~--------

_~~ ____ ~~_~~ _________ ~~ ____ ~_~ _____ ~ _____ ~ __ ~ ___ ~~_

lQue!~~n!i_a~~t#LK~-=~S!~,!,_ +~,=-"-lI!"_~,"-_____ _

1873 i

GEN2.3 I

2.3.7 L ___ ~ ______ ~ _________ ~ _____.~ ___ ~ _________ _

IRadiation ControleJAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 1

~~!~~-~- -----~~--~--~~-

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

CURRENT A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

The worker's present exposure is 1938 MREM for the year The RWP states:

o General area dose rate = 30 MREM/hr o Airbome contamination concentration = 10.0 DAC The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the oorker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the worker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which ONE (1) of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A B.

C.

D.

The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

The worker must wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one.

The worker must wear the respirator.

He will exceed DAC limits.

G2.3.7 D is not plausible as written.

45 DAY VERSION A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

The worker's present exposure is 1938 MREM for the year The RWP states:

o General area dose rate = 30 MREM/hr o Airborne contamination concentration = 10.0 DAC The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the oorker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which ONE (1) of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A B.

C.

D.

The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

The worker should wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one.

The worker should wear the respirator.

He could exceed DAC limits.

401-9 Comments:

D: Change to: "should" to "must" and "could" to "'will" RF A 10/29/09 Tuesday, November 10, 2009 Page 178 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE B

2009 RO NRC Retake Examination QUESTION 73 General Discussion r;:~-~-~-

~-~----~~-

IRadiation exposure comparison:

!Without respirator DDE = 30 mrem/hr x 1 hr = 30 mrem IFrom airborne contamination:

CEDE = 10 DAC 1 hr x 2.5 mremlDAC-hr = 25 mrem TEDE = 30 + 25 = 55 mrem from job

!With respirator Total exposure for year = 1938 + 55 = 1993 mrem IDDE = 30 mrem/hr x 2 hr = 60 mrem CEDE = 0 ITo tal exposure for year = 1938 + 60 = 1998 mrem TEDE = 60 mrem I (With respirator)

(Without respirator)

!TEDE = 60 mrem > 55 mrem = do not use a respirator I

IKJ A is matched because the information given in the stem of the question would be provided on a room survey map. This information would then be used to comply with the associated R WP

!for the work being performed. This question represents the kind of evaluaton which could be encountered in order to comply with the requirements on an R WP I

I iThis is a comprehension level question because the applicant must recall multiple pieces of information such as DAC hour conversion and Exposure limits. He must them perform a

~~lcllhlti_oI1_aIl<!!JI"~cli<;t!I1()llt~o~e. ~~~_ ~ __ ~~_~~ _~ ________ ~_~~~~~_~~_~ __ ~~ __ ~_~ __ ~_~~ ___ ~ ____ ~ _______ ~ ____ ~ __ ~~~ __ ~_~ ___ ~~_~_

Answer A Discussion II~c~;-;;ct~th~ do~~;il~~t~x~;dthe-2000 ~~e~~limit based on calculation.

IPlausible: If the candidate miscalculates the dose L ___,_, __, _________ _

Answer B Discussion I-~ ~--~~

~ -

-~-~~~-

ICorrect answer I

---~--

Answer C Discussion

[0~~;~=-:r~~~~~~~-~~~i~~~~~~II bijr~~ti/".-if~~~~~~;th~~~iPI~~!!I~~~~b~~~!~~~n~-~~~J~~~~~-~~i~~~~~~~~~~~~~~!"e.-=-t~iii~t~~~~~~~~answ~! ()Il_i!J!evious exam Answer 0 Discussion IIncorrect: DAC limits are not direct ALARA controls.

~~-~~~l lI'lilll"i\\)le: If't~e 5!~cli<!a~ed()~sI10! IIIld~I"5>~~ th_e ~0l.1C~t ~~

~e-,"~ed air\\)()f11~~()Il(;entrations.

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Job Level I Cognitive Level

! Quest/onType

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RO I

Comprehension I

BANK

~ ~_~~~~ ____ -.l_~ ~ ____ ~_~ ___ ~ ___ ~~~_ ~-.L_ ~_~ ____ ~_~~

~ ~ ____ _

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

'D;velopment-Refer-e~ces-~- -~--~ --- -

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ILesson Plan Objective: HP Obj: 22 & 29

11. OP-MC-RAD-RP I

I I

i_~~~_~ ~~ __ ~~_

Question Souree ---~- ---~-- -~~~-~l 401-9 Comments RESPONSE 2008NRC-Qn-(B~k -211)- ~~-- -~~~ ~ --~-I Per Chief Examiner's suggestion, in

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

~-~~--

distractor 'D' changed 'should' to 'must' and

'could' to 'will'. HCF 11/05/09 1--- ---- - -------------- ----- *--------1 IStudent References Provided f-=~~~~----~~~-~----~~~-- - ~~-~-l I

I I

I

--~

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~uestlonBank # IKA_system IKA_number I

--~---~~--~~:1 ~ --~---~~-~~1~--~-~~-~-~ ~-~~----l

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~

~

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18731GEN2.3 2.3.7 I

____________ ~ ____________________

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IRadiation ControlCAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR:

141J2L4~~Q) __ ~~ __ ~_~ ____ ~_ ~~___ _ _____ ~ __ ~ _____ ~~_~ __ ~~_ ~~~ ___ _____ ~

ruesday, November 10,2009 Page 179 of 185 I

I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 73 B

General Discussion r-:;~------------------------------------- -------- - -------- ---- - ---- -------------------------- ------ ---- - -- --------- ----------- -------

IRadiation exposure comparison:

!Without respirator DDE = 30 mrem/hr x 1 hr = 30 mrem IFrom airborne contamination:

CEDE = 10 DAC 1 hr x 2.5 mremlDAC-hr = 25 mrem TEDE = 30 + 25 = 55 mrem from job Total exposure for year = 1938 + 55 = 1993 mrem

!With respirator IDDE = 30 mrem/hr x 2 hr = 60 mrem CEDE = 0 TEDE = 60 mrem ITo tal exposure for year = 1938 + 60 = 1998 mrem I (With respirator)

(Without respirator)

!TEDE = 60 mrem > 55 mrem = do not use a respirator I

IKJ A is matched because the information given in the stem of the question would be provided on a room survey map. This information would then be used to comply with the associated R WP

!for the work being performed. This question represents the kind of evaluaton which could be encountered in order to comply with the requirements on an R WP I

1 iThis is a comprehension level question because the applicant must recall multiple pieces of information such as DAC hour conversion and Exposure limits. He must them perform a

~~lcllhlti_oI1_aIl<!!JI"~cli<;t!I1()llt~o~e. _________________________________ ~

_________________________________________ ~

Answer A Discussion II~c~;-;;ct~th~ do~~;il~~t~x~;dthe-2000 ~~e~-li~itba:;ed-o_; ~;l~cl;io~~ -- - ---~----------- ---------

-- - -------- - --~------- - ----- - ----- - ---- --~-l lJ)l[lus~ble~ !ftlle_C(lI1~cla_te_ll1i1i~a!clllate~the ~()S~ ____ _ __ ___ __ __________ _ ___ ____ ______ ____ __________ _ __________ _~

__________________ ~

Answer B Discussion 1-- ----- - - ------------ ----- -------------------- ----------- --- --------- ------------ ------------------------------ -------------

ICorrect answer L _____________

~

~

~

~

~

~

Answer C Discussion

[0~~;~=-:r~~~~~~~-~~~i~~~~~~II bijr~~ti'"--if~~~~~~;th~~~iPI~~!!I~~~~b~~~!~~~n~-~~~J~~~~_=-~~i~~_~~~-~~-~~~~!"~_=_t~iii~t~~~~~_=~~~~ ~~~!~~~~;-~~~ __

Answer 0 Discussion

lncorrect: DAC limits are not direct ALARA controls.

l~11l1"itJ!.e: lj'tl1..e 5.ilI1..cii.<!a~ed..Cl~s~0t.llIld~I"5>~ci. th_e ~ol1CeJJ.t..Cl~ ci.e-,"~ed airlJ()f11~~()nc;entr~tlon_s:.. _________________ _

Job Level I Cognitive Level j QuestionType

---

~-----j---------~-------I--------------

-====-_=~====-_9~~!t!~~~~~!=======~==~=_===J 401-9 Comments RESPONSE RO 1

Comprehension I

BANK

___________ -.1 ______________________...L ___________ _

2008 NRC Q72 (Bank 211)

I Per Chief Examiner's suggestion, in

---

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

distractor 'D' changed 'should' to 'must' and

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved

'D;velopment-Refer-e~ces----------- -

l ____________________________________ _

iLesson Plan Objective: HP Obj: 22 & 29

11. OP-MC-RAD-RP I

1 I i _______________________________ ~

'could' to 'will'. HCF 11/05/09 1--- ---- - -------------- -----

• --~-----I IStudent References Provided f-=------------------~--- - -----1 I

1 I

I

--- - ------ -:-1---------- - --,-- ------ ------- --I r------ ------------------------- --------------- ------ ------------ ----------- ------------,

~uestlonBank # IKA_system IKA_number 1 jKA_desc

-- -- - ----1873lGEN2.3----12~~7--- --- ---- -1 iRadiati~-C~nt;~j[]AbiljtYt~-c;~piY -;ith -;:;diatio~ w~kp~rt-req~i~~I11_;;~t~d~~g ~~r~~I-o~~-n~~-ai-~o;;diti~n~.-(CFR:

- --"-- ----- ---- -- -- --------~ 141J2L4~~Q)_____________ _______ ____ ____ _____ ____________ __________________ _

ruesday, November 10,2009 Page 179 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 73 B

ruesday, November 10, 2009 Page 180 ofl85 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 73 B

ruesday, November 10, 2009 Page 180 ofl85

D FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74

~~!tJ:~n-B~~~~~~ji~~~~~~~_:~~rll~r -~=-=-~ [<~~~!8~=~====~==_== ~ _-_-_=-= ~-=====~=~===~=======~=~~~============_- _==-=-===-=-==~

l 1874 I

GEN2.4 I

_ 2.4.16 I iEmergency Procedures 1 Plan LJ Knowledge of EOP implementation hierarchy and coordination with other support procedures or I

-- ---- L_

- ----- -- -- ---" Iguidelines such as, operating procedures, abnonnal operating procedures, and severe accident management guidelines. (CFR: 41.1O 1 I l~JJ!2:~~_~ _____ ~ ________. ______. __ ~

__________. ______________________. _______________ J CURRENT With the following conditions on Unit 1:

A Loss of Offsite Power (LOOP) has resulted in a Reactor Trip and Safety Injection All Rod Bottom Lights are LIT Train 'A' Reactor Trip breaker is CLOSED Both Unit 1 DIG's FAILED to start Pressurizer level 25%

Subcooling is 5°F NC system pressure is 1865 PSIG and stable Total CA flow is 500 GPM Which ONE (1) of the following correctly states which procedure will have the highest PRIORITY for the above conditions?

A AP-OO? (Loss of Electrical Power)

B.

FR-S.1 (Response to Nuclear Power GenerationlATWS)

C.

ES-1.1 (SI Termination)

D.

ECA-O.O (Loss of All AC Power) fuesday, November 10, 2009 G2.4.16 No comment at this time RF A 10/29/09 45 DAY VERSION With the following conditions on Unit 1 :

A Loss of Offsite Power (LOOP) has resulted in a Reactor Trip and Safety Injection All Rod Bottom Lights are LIT Train 'A' Reactor Trip breaker is CLOSED Both Unit 1 DIG's FAILED to start Which ONE (1) of the following correctly states which procedure will have the highest PRIORITY for the above conditions?

A.

AP-007 (Loss of Electrical Power)

B.

FR-S.1 (Response to Nuclear Power Generation/ATWS)

C.

ES-O.O (Rediagnosis)

D.

ECA-D.D (Loss of All AC Power) 401-9 Comments:

Page 181 of185 D

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74 I-~--- --- T.----- ------1---- -- --

- --- -l------------- -- -- -

-- --- ---- ---- - ---- -------- ---------------------- ---- -------i r~!~f~~~~ L-tl~~~~ __ l~-='!~~2~~ 6 __ -~ __ j ~~:;~~y P~~ed~r~~i~ht-;;lJK~o~l;dg~ ~f Eor -i-;;ple~~~t;;_t~_;hi~~~hy~~d Zo~~inatio~~ith~th~_;~~~rt.P~~~d~~;~r---1 IgUidelmes such as, operatmg procedures, abnormal operatmg procedures, and severe accIdent management gUidelInes. (CFR. 41.10 1 1 l~JJ!2:~~ _____________________________________________________________________________ J CURRENT With the following conditions on Unit 1:

A Loss of Offsite Power (LOOP) has resulted in a Reactor Trip and Safety Injection All Rod Bottom Lights are LIT Train 'A' Reactor Trip breaker is CLOSED Both Unit 1 DIG's FAILED to start Pressurizer level 25%

Subcooling is 5°F NC system pressure is 1865 PSIG and stable Total CA flow is 500 GPM Which ONE (1) of the following correctly states which procedure will have the highest PRIORITY for the above conditions?

A AP-DD? (Loss of Electrical Power)

B.

FR-S.1 (Response to Nuclear Power GenerationJATWS)

C.

ES-1.1 (SI Termination)

D.

ECA-O.O (Loss of All AC Power) fuesday, November 10, 2009 G2.4.16 No comment at this time RF A 10/29/09 45 DAY VERSION With the following conditions on Unit 1 :

A Loss of Offsite Power (LOOP) has resulted in a Reactor Trip and Safety Injection All Rod Bottom Lights are LIT Train 'A' Reactor Trip breaker is CLOSED Both Unit 1 DIG's FAILED to start Which ONE (1) of the following correctly states which procedure will have the highest PRIORITY for the above conditions?

A.

AP-OD7 (Loss of Electrical Power)

B.

FR-S.1 (Response to Nuclear Power Generation/ATWS)

C.

ES-O.D (Rediagnosis)

D.

ECA-D.D (Loss of All AC Power) 401-9 Comments:

Page 181 of185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74 D

General Discussion rwTththe~c~~itTo~;g;~en ~the ste~~fthi; q~~~tTo~~ ~~l~s~~f ~1-AEh';';~-;;-c~;'~d. I~ ;dditi;~~ ~trY~;ndTti~;-s-i~t;; FRP S-l-;;e-p~~~~U:d b~tth~i~;t~~g~~~;;uIX ~qui~~ th~~~~t~[

lenter ECA 0.0 instead of the FRP. All EP;s with the exception of the ECA 0.0 series are written assuming at least one train of AC power is available therefore ECA would take priority of the !

iCSF Red path for sub criticality as well as the other EP's listed in the distracters.

[

iKA is matched because the candidate must demonstrate an understanding of the implementation hierarchy of emergency, specifically the understanding that ECA 0.0 takes priority over all I

[other procedures.

I I

I IThis question is analysis level because the candidate must first determine from given information that a loss of all AC has occurred. In addition, the determination of a red path for FRP S-1 is i l\\V~n-ante~. ~"I}1_e _c~~~~~E1~u~~t~eE ~llk~ ~~s_ iEf?J'Il1a!i~n a~~e~~tIate t~~c~r-:~~tPI'9~ed~~-P~c:ritL~i~ ~~Il1()~S!rll~~ all_aIlll'rsis_llnd su.\\J~'ltle~tappli<;~j()E~i tI1~~~u1~<:>fthllt analysisj Answer A Discussion I----~ ~ ---- --------

-~- ----

---

~ ----

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

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

---

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

~~~~rr:~~~~e::IJI.1ll1.iltio~!.1J~V'e._!".ill1S~b~~~~/~2~s~~pleIl1~nt~~~~:-f>!~~()S~()~e~=_c~ic~ly()~~~:~n~~()S!ut i!.~~.I1~t~il.kt:Erior~tJ'.~v~r_~C~_~O.

Answer B Discussion Ifu~orre~t-:-S;~~Pl~~tTo-; ab;;e-:-Pl~usible--:A-v~lid~d p;rthi;g~~~;;_ndttti;i~~;;rmatlyth~highe~tp~~~ity procedure. If a loss of all AC was not in progress this would be the correct ill.ns~~_ ~ __________ ~~ _____________ ~ ____________________ _

Answer C Discussion iI~c~;:;'~ct:-s~~ ~xp~~,rt~~ ;;-bo~~-.phJ:~sibTe~i~~ sT t~~in-ati~n-c~rte~i~ is-~et as specified in the stem of the question.

L. ___. _______________________________________________________________________________________________ _

---

~-~ --- ---

Answer 0 DIscussion 1---------- ~---- -------~- -- - - ---

['Correct: See explanation above

-~----

---~--- -- -

---

~~--

~ ------

~ -

r~-------~ -

~ - ------

~---T ---- ------------

r~

~--- -------

Job Level 1 Cognitive Level 1 QuestlonType I

---

~---- --I~ ------~-- - -

---

~--- -i- -

~ -- -

--~- --- -

I~-~ -

-~

RO I

Comprehension I

BANK L

_______ ~_L~_~ _____ ~~ _____ ~_~ ____ ~~_~ __________ _

~ Developed

~eji'-ojiient~Fefe;enc;; ~ -----

QuestionSo~ree--------~ ----I 401-9 Comments RESPONSE 2006 NRC-Q74-(B~~-680)~---~-~- -- ----1 Considered SAT for submittal with no

_I comments. No changes.

r:-- -------- ---- --------- -- --~----

[Student References Provided I~------- ---~------~--

~ OPT Approved

~ OPS Approved

~ NRC Approved j

References:

I 1 Lesson Plan OP-MC-EP-ECA-O, rev. 15 page 11,13 IOMP 4-3 Pg 6 I

I I

1 I

1 1 __________________ _

L ______ _

---

~---- -

-~-----~ ----- - -r::-- ---- -----

---

~- --1 QuestionBank 1# lKA_system IKA_number I

---

~--~ - ~--~---~ ---~ -,---------- -~- -- --

1874!GEN2.4 12.4.16

~ ____

L

___________..L _____________ ~ __ ~_~ ~-~~~=======~~===-==~==-==-======-====-====-==========-==========~===========~

IEmergency Procedures / PlanL1Knowledge ofEOP implementation hierarchy and coordination with other support procedures 1

lor guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

i I~Y~~_'!.1.10J_i~J L4~*lIL ____________ ~ ____ ~ __________ ~ __ ~ ____________________ ~ __ J ruesday, November 10, 2009 Page 182 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74 D

General Discussion rwTththe~c~~itTo~;g;~en ~the ste~~fthi; q~~~tTo~~ ~~l~s~~f ~1-AEh';';~-;;-c~;'~d. I~ ;dditi;~~ ~trY~;ndTti~;-s-i~t;; FRP S-l-;;e-p~~~~U:d b~tth~i~;t~~g~~~;;uIX ~qui~~ th~~~~t~[

lenter ECA 0.0 instead of the FRP. All EP;s with the exception of the ECA 0.0 series are written assuming at least one train of AC power is available therefore ECA would take priority of the !

iCSF Red path for sub criticality as well as the other EP's listed in the distracters.

[

iKA is matched because the candidate must demonstrate an understanding of the implementation hierarchy of emergency, specifically the understanding that ECA 0.0 takes priority over all I

lother procedures.

I I

I IThis question is analysis level because the candidate must first determine from given information that a loss of all AC has occurred. In addition, the determination of a red path for FRP S-1 is i l\\V~n-ante~. ~"I}1_e _c~~~~~E1~u~~t~eE ~llk~ ~~s_ iEf?J'Il1a!i~n a~~e~~tIate t~~c~r-:~~tPI'9~ed~~-P~c:ritL~i~ ~~Il1()~S!rll~~ all_aIlll'rsis_llnd su.\\J~'ltle~tappli<;~j()E~i tI1~~~u1~<:>fthllt analysisj Answer A Discussion I-~---- - ---- -------- --- ---- -------- -----

---

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

---

~-

---~------------- ------------------------l IIncorrect: See explanation above. Plausible: AP/07 is implemented in E-O for loss of electrical power scenarios but it will not take priority over ECA 0.0.

I L_~ ____ ~~,~

~_,

_______ ~ __

,~~ _

~_, ___

~, ___ ~ ___

, _____ ~ _~ ____ ~~ ___ ~ __ ~ _________________ ~ ___,_, ____ ~ _____

~ ___

~, __,_~'_~, ____ J Answer B Discussion Ifu~orre~t~S;_;~Pl~-;tTo-; ab;;e~Pl~usible-:A -v_;Ud ~d p;rthi;g~~~ ;nd ttti;i~~;;rmatlyth~highe~tp~~~itYP~o~d-;;;e~ Ifa-I;;s-;-;;[ ~l-AE ;~n;;ti;p;;;-gr~~thi;;o~lcI~b~ t~~~~~ct - ---i lanswer I

I_~, __ -

~ __,~ _____ ~ __

,~~, _____, __ ~ ___, __ ~ __,_,_ - ___________, ___ '_

~_~ _____ ~,~~_, ___, ______,,~ ____ ~' ______ ~, _____ ~ ___,_,_,~ __

,_,~ ___ ~ __ ~_, __

Answer C Discussion

~~c~~~~=S~~ ~~~~~.~~~~o~~.~~~sIbI~l~~~~~in~a~~n~ c~~e~~ Is=~e~[iS~sp~~T~e~}~~~~§~~!th~~~~~~~=~_=_~=-_~*~_=_~=~=~====_~~-=====_~=====-

Answer 0 DIscussion 1---"--'-- ~----------,~- -- -

---~ -,-~,~-,,----,~--,--~.~,----~ ~-

-~,~---

-~---,-~--~,--~~----

---

,------~--~~--- -

---

,~----------

Eo~~c~:S~: ~X})~llIl~tion !~~v: ________ ~~ __ ~ ___ ~~~ _~ __ ~ _____ ~ __ ~~ ~ ____ ~ ~ ___ ~ _ __ __,_, _____ ~ ____,_~ ______,_ ~ ~ ______ ~ ~

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Ioe;;'opment~ Refe;enc;; ~ - -- -- --~ -~--,

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

j

References:

I 1 Lesson Plan OP-MC-EP-ECA-O, rev. 15 page 11,13 IOMP 4-3 Pg 6 j

I l __, _______ ~ _~~ __ ~ __ ~,~_, ______,~ __ ~_~_

r:'- -,- ---,- --~-

,~-,-----

-~

--~,-,-

IStudent References Provided I~-------

I I

I L _____ ~ _________ ~_~

~~!~~nii:a~~~JgA=;iS~rll ~t-~~~~~~~==-=.~] ~-~~~======~=~===-==~==~==-======-====-===-===========-======================~

1874!GEN2.4 12.4.16

! IEmergency Procedures I PlanL1Knowledge ofEOP implementation hierarchy and coordination with other support procedures 1

- --~-~ -- _.L ~--- ______ -L __ -~-- -~- -~~ ~ ~.~ for guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

i I~Y~~_~1.10J_i~J L4~*lIL ___ ~ ________ ~ ____ ~ ~ ___ ~_~ ___ ~. _~ _____ ~ _____ ~_ ~ __ ~~ __ ~ __ J ruesday, November 10, 2009 Page 182 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74 D

Tuesday, November 10, 2009 Page 183 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 74 D

Tuesday, November 10, 2009 Page 183 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 75 C

§~!S!~~~~~k#f[A_si~~=~~~~~~~j= = =

=~ [~~<Ie~~=-===-_==

=~= ___== _________==~ ___ ~. ___=== _____________ ~~

___ =====_ ___ ~=__====~=-=_ -_===_==-==== =-

l 1875 I

GEN2.4 I

2.4.46 I!Emergency Procedures 1 PlantJAbiIity to verifY that the alarms are consistent with the plant conditions. (CFR: 4 1.10 1 43.5 1 45.3 1

-- __________ -.l ___ --

___ L. _______ ---.-----~ !42.

.!.~ __. ________________. ______________________. __.~ ______. ______. __________________ _

CURRENT A Reactor Trip and Safety Injection have occurred on Unit 1 due to a Loss of Coolant Accident (LOCA). The following conditions exist:

Containment pressure is 10 PSIG All NC pumps have been secured NC system subcooling is -50°F CETs indicate 750°F Reactor Vessel Lower Range Level is currently 32%

Which ONE (1) of the following correctly completes the statement below?

The Critical Safety Function status for Containment is (1) and the status of Core Cooling is ~

A.

(1) ORANGE (2) ORANGE B.

(1) RED (2) ORANGE C.

(1) ORANGE (2) RED D.

(1) RED (2) RED G2.4.46 45 DAY VERSION A Reactor Trip and Safety Injection have occurred on Unit 1 due to a Loss of Coolant Accident (LOCA). The following conditions exist:

Containment pressure is 10 PSIG All NC pumps have been secured NC system subcooling is -50°F CETs indicate 750°F Reactor Vessel Lower Range Level is currently 32%

The Critical Safety Function status for Containment is (1) and the status of Core Cooling is ~

Which ONE (1) of the following correctly completes the statement above?

A.

(1) ORANGE (2) ORANGE B.

(1) RED (2) ORANGE C.

(1) ORANGE (2) RED D.

(1) RED (2) RED 401-9 Comments:

Is it fair to ask this question without a reference? If you allow a reference, will it become a direct look up (DLU).

Please re-evaluate RF A 10/29/09 fuesday, November 10, 2009 Page 184 of 185 A Reactor Trip and Safety Injection have occurred on Unit 1 due to a Loss of Coolant Accident (LOCA). The following conditions exist:

Containment pressure is 10 PSIG All NC pumps have been secured NC system subcooling is -50°F CETs indicate 750°F Reactor Vessel Lower Range Level is currently 32%

Which ONE (1) of the following correctly completes the statement below?

The Critical Safety Function status for Containment is _-,(,-,1-,-) _

and the status of Core Cooling is (2)

A.

(1) ORANGE (2) ORANGE B.

(1) RED (2) ORANGE C.

(1) ORANGE (2) RED D.

(1) RED (2) RED G2.4.46 A Reactor Trip and Safety Injection have occurred on Unit 1 due to a Loss of Coolant Accident (LOCA). The following conditions exist:

Containment pressure is 10 PSIG All NC pumps have been secured NC system subcooling is -50°F CETs indicate 750°F Reactor Vessel Lower Range Level is currently 32%

The Critical Safety Function status for Containment is _-1(-,-1L) _

and the status of Core Cooling is (2)

Which ONE (1) of the following correctly completes the statement above?

A.

(1) ORANGE (2) ORANGE B.

(1) RED (2) ORANGE C.

(1) ORANGE (2) RED D.

(1) RED (2) RED 401-9 Comments:

Is it fair to ask this question without a reference? If you allow a reference, will it become a direct look up (DLU).

Please re-evaluate RF A 10/29/09 fuesday, November 10, 2009 Page 184 of 185

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 75 c

General Discussion iWith cont~i;mentPre~s~e-g~;t~~th~3PSIGbutl;ss-tha;15PSIG CoJtlai~;ent CSF will be Orange.

IWith no NC pumps running, subcooling less than O°F, CETs greater than 700°F, and Rx Vessel lower range level less than 39%, the Core Cooling CSF will be RED.

I IThis KA is met because the applicant must analyze a given set of conditions and determine the status ofCSFST indications (alarms). This requires a knowledge of emergency procedures (F-lO) and the ability to determine applicability.

IThis question is comprehension level because the applicant must associate mUltiple pieces of information (some given and some recalled from memory) to determine the correct answer. The ia.pplicant must recall all setpoint for the Core Cooling and Subcriticality Safety Functions and apply the given conditions to determine the status of those two Safety Functions.

L _________

~~ ________________________________________. ___________

~ ________________________________

~ _________________ ~ _____ ~_. __ _

Answer A Discussion

---

~--- -------

~- --

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

[Incorrect. Part 1 correct. Part 2 is plausible if the applicant does not recall the setpoint for CETs or Reactor Vessel Lower Range Level.

--~~~--,

L ____________. ___.__

~~J Answer B Discussion ir~corr~~tPart ii;-pl~~ibl~~th~r~;ep~~du~ -;~ti~;-rcl~ti~ t~th~Co~t;;;~~~tSp~ysyste; ;hiZh~~stb~ ~rfo~~d~h~~~t;i;m~~ p~;~r~ ~a-;;-h~s-lOp~ig.P~2pl;u;b1eif" lapplicant does not recall CET or R V level setpoints.

L _______________ ~ __. _____

~ __________. _____________________________

~~ _________

~ ____________ _

Answer C Discussion iE6RRECi-

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

---

-~-

-~---

L __. _______. __

Answer 0 Discussion I

I

_ _____ J lI~~~~!~rt! ~o~~~

p;~~i;pl~~ible-;~the-;:-e~r~ Pr~~~r;a~t~~; _;:_el~t-iv;t-;;- the-Eo;;-t~~~~nt Sp;;y-syste~ ;hl~h~~~b; p~rfu~~d ~he~ZOntai~~entp-;-e~;~~~~lO-p~ig~ ~ ~ 1

.~ ___

~ ___

~ __________

• __

.~_~ _________

~ ________________________________________

• ___

---

.J

---

Qu;stioflType - --- ~-~----- Q~estion So;rce - ~ -- - --~--~ --j 401-9 Comments RESPONSE

~oJl~i!!v_e !~y_e~

--*-~------r---------*----*~---~*--~-*--~*-*--~---------- - I

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension NEW I This question is asking entry conditions for

______ ~ __.J..~ __ -- --- ------- -- --~-- ---------~~- ~--- -~--- the FR procedures and is considered RO r-----*-----*- - ------.-.. ----- ---

~--~-- -I r~*--***- -

~--.----.. -

fl?e~!'~.rtt~~t~!~!r:!'~!S ________ ~ ____ --j 1~~.!'!t_R.!tf!'!'!.c!s_~~v_'_d~<! __ _

rO Critical Safety Function Status Trees I i I

I I

i I

I L___________

_ _________ ~___

L. _____. ____.. _~

I I

_ J level knowledge. Will discuss further with Chief Examiner during on-site review.

HCF 11105109

@-- --- -- - -i--- - ---T-- -

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

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

iQ~e~ti~n~a~fs~N~~st!."!. - ~.~!!1.~ -- - ~l r~:r~~~ Pr;;-ced~r~s/Pla~DAbilitY to-v~rif'yth-;tth~ aia~silf~ c~~i~t;-nt~iih-th~ pI~~t c~nditi~ns-. (C-FR.:41.10/ 4is /

---...1 _____ ~- - L __ ~ _____ ----

~~3j~~I?L___ ________ ~~ ____________ ~_~ ____ ~~ _____________ _

Tuesday, November 10, 2009 Page 185 of 185 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2009 RO NRC Retake Examination QUESTION 75 c

General Discussion 1- -,~--~-,-~,-

---

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

--~-

--~ --- -

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

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

--~-------

IWith containment pressue greater than 3 PSIG but less than 15 PSIG Containment CSF will be Orange.

IWith no NC pumps running, subcooling less than O°F, CETs greater than 700°F, and Rx Vessel lower range level less than 39%, the Core Cooling CSF will be RED.

I IThis KA is met because the applicant must analyze a given set of conditions and determine the status ofCSFST indications (alarms). This requires a knowledge of emergency procedures (F-lO) and the ability to determine applicability.

IThis question is comprehension level because the applicant must associate mUltiple pieces of information (some given and some recalled from memory) to determine the correct answer. The LaE~~~ ~~tl'eca~I~~e!p<.Jillt io~ tl1e~C~r~ ~()()Ii_n~ llI1~ ~~cI'iti(;ilIi~ S_afety £unc~~~

aJ1d_aEP~!h~~~~c~nditi?Ils~oj~teI111in~Q1~st<ltl!s ~f!~~ ~w~ Sa~t)' £u~ctioE~_~.

Answer A Discussion

~

~-..

~-

.-.~~.~-

~~~~.--

.-~-.~.-

~-.~.~ -.-..

- -. ~

... -~-.~~

~~

~~~~-

~

~~~

~-

~

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

~---~~

~~~--.~~~

~-~~~.-~~

'-~~~~-,

[Incorrect. Part 1 correct. Part 2 is plausible if the applicant does not recall the setpoint for CETs or Reactor Vessel Lower Range Level.

I L ____________. ___. _______. __. ___. ______

---.J Answer B Discussion ir~corr~~tPart ii;-pl~~ibl~~th~r~;ep~~du~ -;~ti~;-rcl~ti~ t~th~Co~t;;~~~~tSp~ysyste~ ;hiZh~~stb~ ~rfo~~d~h~~~t;i;m~~ p~;~r~ ~a~h~s-lOp~ig.P~2pl;u;b1eifl

~eP!ic.<lnt. cio~s _no.!!~c-.<ll~ CET()rB-_\\T ~~e~~p~0t~. ~ ~ ~ ~_~~ _ ~_~_ ~_~_~ ~._ ~_~~~ ~~~ ~ ~~~~_._~ ~ ~ ~~~_~~~~.. ~~_~ ~ ~~ ~ ~ ~.~_~_ ~ ~_~J Answer C Discussion rC~6RRECT.~"* ~~.- -

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

~.-'-

~ - -' ~.~-~~.---... ~~.~ -~.- -

~.~~~----

~~.

~.-.~~ ~~

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

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

-~.~--~~~ -~~\\

L __, ________________________________________________________________________________ ~

__________________________________________________________________ J Answer 0 Discussion lI~~~~J'~rt! ~o~~~ p;~L~~I~~ibIe~~t~e~~r~ ~~~~~a~~~~e~ti:v~t~_0==~~t~~~~SP~~is~~ ~hl~h~~}~p~rfu~~d~Ee~~I1t~~~~~p~e~~~~~]o~~i~_=_J

~oJl'!.i!!v_e !~y.. e~

Qu;stioflType ~f--.~ ~ ~-~--- ~~ Q~estion So;rce - ~ _. -.~~-.~ ~-i 401-9 Comments RESPONSE

_~-~.~~~-~-_]_=___=_~~~~-_~_-~~~~~-~~~~~_~~ _____ --____ ~~~~ ___ ~

____ ~_=_~~_-~-~~~~~J This question is asking entry conditions for

~ Developed

~ OPT Approved

~ OPS Approved

~ NRC Approved Comprehension Tuesday, November 10, 2009 r- -..... ~-~~~.- -

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

~ -~-

~~~~'--I Il?.e~!'~,rtl~'!.t~!~!r:!'~!S___ __

~.. _

iF-O Critical Safety Function Status'T~es ~ ~ - ~.,

I I

L ~

~ ___ ~ _. __.

Page 185 of 185 the FR procedures and is considered RO level knowledge. Will discuss further with Chief Examiner during on-site review.

HCF 11105/09