ML080930291

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Exam 05000269, 270, & 287/2008301 Final SRO Written Exam & References
ML080930291
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/20/2008
From:
NRC/RGN-II
To:
Duke Energy Carolinas
References
50-269/08-301, 50-270/08-301, 50-287/08-301
Download: ML080930291 (32)
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Text

Final Submittal (Blue Paper) ocooee zoqg -~\ ~E11)tE

~rdk.f'\ "E-X MAt UtfTIW 3 JCD/ZC08 FINAL SRO WRITTEN EXAMINATION AND REFERENCES

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: March 20, 2008 Facility/Unit: Oconee Region: I 0 /I ~ 1/1 0 IV 0 Reactor Type: W D CE D BW ~ GE D Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results RO/SRO-Only/Total Examination Values / -- / -- Points Applicant's Scores / -- / -- Points Applicant's Grade / -- / -- Percent

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 76 Unit 1 initial conditions:

  • RCS pressure = 1800 psig decreasing
  • pzr level = 280 inches increasing
  • 1B HPI pump trip Current conditions:
  • LOSCM tab in progress
  • RCS pressure = 825 psig increasing
  • pzr level = 400 inches stable
  • ALL SCMs = 4 Q F increasing
  • RC makeup flow = 10 gpm Based on the current conditions, which ONE of the following states an acceptable SG pressure per the LOSCM tab and which EOP tab will be used to cool down the unit to decay heat removal conditions?

A. 1010psig / LOCACD B. 1010 psig / FCD C. 780 psig / LOCA CD D. 780 psig / FCD

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 77 Unit 1 initial conditions:

  • Reactor power = 100%
  • 1SA2/B2 HP RCP SEAL INLET HEADER FLOW HIGH/LOW actuated y 0 GPM stable
  • 1SA2/C2 HP INJECTION PUMP DISCH HEADER PRESSURE LOW actuated Y=:::O psig stable
  • 1SA2/C3 RC PRESSURIZER LEVEL HI/LO actuated y 199 inches decreasing slowly
  • Highest RCP seal return temperature = 175 QF stable
  • RC Makeup Flow = 0 gpm Based on the above conditions, which ONE of the following describes the current plant condition and what action will be required to mitigate this condition?

A. HPI Seal Injection header rupture I enter AP/2 (Excessive RCS Leakage) and close 1HP-31 to prevent RCP Seal damage B. Loss of running and Stby HPIPs I enter AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) and close 1HP-20/21 to prevent exceeding 1HP-21 temperature limit C. HPI injection header A rupture I enter AP/2 (Excessive RCS Leakage) and close 1HP-115 to split the injection headers D. Loss of running and Stby HPIPs I enter AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) close 1HP-5 to minimize RCS inventory loss

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 78 Unit 1 initial conditions:

  • 1B SG has a 50 gpm tube rupture
  • SGTR tab in progress
  • Reactor has been manually tripped at 4% FP Current conditions:
  • 1A SG pressure = 0 psig stable
  • 1B SG pressure = 900 psig and increasing slowly
  • RCS temperature = 532 QF increasing slowly
  • RCS pressure = 1280 psig increasing slowly Based on the current conditions, which ONE of the following describes how the EOP will be used to mitigate the event?

A. Remain in SGTR tab Unisolate and feed 1A SG B. Remain in SGTR tab Feed and steam the 1B SG

c. Transfer to Excessive Heat Transfer tab Unisolate and feed 1A SG D. Transfer to Excessive Heat Transfer tab Feed and steam the 1B SG

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 79 Which ONE of the following describes the basis for the mitigation strategy of the Blackout tab of the EOP and why?

A. Maintain RCS temperature -- 532 Q F To stabilize RCS Temperature and pressure to prevent challenging the Pressurizer PORV B. Maintain RCS temperature -- 532 QF To prevent contracting RCS inventory and emptying the Pressurizer due to loss of makeup capacity C. Maintain RCS temperature at -- 550 QF To stabilize RCS Temperature and pressure to prevent challenging the Pressurizer PORV D. Maintain RCS temperature at -- 550 Q F To prevent contracting RCS inventory and emptying the Pressurizer due to loss of makeup capacity

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 80 Unit 1 plant conditions:

Time = 0400

  • Reactor power = 100%
  • AP/2 (Excessive RCS Leakage) in progress due to a 15 gpm RCS leak
  • CT-1, 1TA & 1TB Lockout Time = 0401
  • Power restored from CT-4 Time = 0410
  • FCD tab in progress
  • CETC = 555 QF Stable
  • Loop A level = 573 inches stable
  • Loop B level = 573 inches stable
  • Rx Vessel head level = 155 inches decreasing
  • Pressurizer level = 180 inches increasing
  • RC Make Up Flow = 30 gpm Which ONE of the following describes how the EOP will initially mitigate the event above and the highest priority AP that will be performed in parallel with the EOP?

A. Open Rx Vessel High Point Vents and maintain pressurizer level> 100 inches AP/2 (Excessive RCS Leakage)

B. Raise pressurizer level to 200 - 300 inches and increase RCS pressure ~ 200 psig AP/2 (Excessive RCS Leakage)

C. Open Rx Vessel High Point Vents and maintain pressurizer level> 100 inches AP/11 (Recovery from Loss of Power)

D. Raise pressurizer level to 200 - 300 inches and increase RCS pressure ~ 200 psig AP/11 (Recovery from Loss of Power)

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 81 Unit 1 initial conditions:

  • Reactor power = 100%

Current conditions:

  • 1HP-5 indicating lights (UB 1) are OFF
  • Pressurizer Level = 230 inches increasing
  • Letdown Flow = 0 gpm
  • 1HP-5 will NOT open from the control room
  • NEO dispatched to open 1HP-5 locally Based on the above conditions, which ONE of the following describes what has occurred and whether 1HP-5 is operable after it is manually opened?

A. 1HP-5 has failed closed due to a loss of DC power to the valve solenoid 1HP-5 is operable provided an operator in constant communication with the control room will close the valve on ES actuation.

B. 1HP-5 has failed closed due to a loss of DC power to the valve solenoid 1HP-5 is inoperable because it will not automatically close on a subsequent ES actuation.

C. 1HP-5 has closed due to an inadvertent ES Signal to the valve 1HP-5 is operable provided an operator in constant communication with the control room will close the valve on ES actuation.

D. 1HP-5 has closed due to an inadvertent ES Signal to the valve 1HP-5 is inoperable because it will not automatically close on a subsequent ES actuation.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 82 Unit 1 initial plant conditions:

  • Rx s~artup in progress
  • Source Range (SR) Nls 1 and 3 are out of service for repairs
  • Reactor is critical
  • WR NI-2 = 1.0 E-2 %
  • WR NI-4 = 1.0 E-2 %
  • SR NI-2 = 1.0 E5 cps
  • SR NI-4 = 1.0 E5 cps Subsequently, SR NI-2 fails LOW Which ONE of the following describes the technical specification required action and the surveillance requirement for returning NI-2 to service?

A. Initiate action to restore SR NI -2 to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

NI-2 must agree with NI-4 within 1 decade B. Initiate action to restore SR NI -2 to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

NI-2 must agree with NI-4 within 2 decades C. Immediately suspend positive reactivity changes and initiate control rod insertion.

Open control rod drive trip breakers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

NI-2 must agree with NI-4 within 1 decade D. Immediately suspend positive reactivity changes and initiate control rod insertion.

Open control rod drive trip breakers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

NI-2 must agree with NI-4 within 2 decades

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 83 Unit 1 initial conditions:

  • Fire occurred at the Unit 1 TO EFDW pump area
  • Deluge system activated Current conditions:
  • Fire extinguished
  • Deluge system isolated
  • ALL fire detection equipment in area is inoperable Based on the above conditions, which ONE of the following states SLC 16.9.2 "Sprinkler and Spray System" requirements regarding the establishment of a fire watch?

A. Establish a Continuous Fire Watch within one hour Backup fire suppression is required B. Establish a Continuous Fire Watch within one hour Backup fire suppression is NOT required once fire watch is established C. Establish a Hourly Fire Watch within one hour Backup fire suppression is required D. Establish a Hourly Fire Watch within one hour Backup fire suppression is NOT required once fire watch is established

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 84 Unit 1 initial conditions:

  • Reactor power = 1000/0 Current conditions:
  • AIIICS Bailey Hand/Auto Stations lights are OFF Based on the above conditions, which ONE of the following describes which section of AP/23 (Loss of ICS Power) will be implemented and when that section will be performed?

A. Section 4A (Loss of ICS AUTO and HAND Power)

When EOP Subsequent Actions have been completed and transition to a normal operating procedure is directed B. Section 4A (Loss of ICS AUTO and HAND Power)

Immediately following performance of the EOP IMA's and Symptom Checks OR when directed by EOP Subsequent Actions C. Section 4B (Loss of ICS AUTO Power Only)

When EOP Subsequent Actions have been completed and transition to a normal operating procedure is directed D. Section 4B (Loss of ICS AUTO Power Only)

Immediately following performance of the EOP EOP IMA's and Symptom Checks OR when directed by EOP Subsequent Actions

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 85 Unit 1 initial conditions:

  • 1B SG is unaffected
  • Core SCM = OQF
  • LOSCM tab completed Current conditions:
  • SGTR tab in progress
  • Core SCM = OaF
  • LPI Flow Train A = 1750 gpm
  • LPI Flow Train B = 1725 gpm Which ONE of the following describes the procedure routing used to mitigate this event and the SG status?

A. Transition to HPI CD Tab and ONLY 1A SG is isolated B. Transition to LOCA CD Tab and ONLY 1A SG is isolated C. Transition to HPI CD Tab and BOTH SG's are isolated D. Transition to LOCA CD Tab and BOTH SG's are isolated

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 86 Unit 1 plant conditions:

  • RCS temperature = 240°F
  • RCS pressure = 260 psig
  • No RCS Vent Paths are open
  • HPI has been deactivated
  • 1A and 1B CFT pressure = 500 psig
  • Pressurizer level indicates 235 inches
  • Cooldown to Mode 5 in progress at 20°F/Hr Which ONE of the following describes the impact of this condition, and the action required?

SEE ATTACHMENT A. RCS pressure and temperature exceed the limits that ensure brittle fracture prevention in accordance with TS 3.4.3 RCS Pressure and Temperature (PT) Limits; Establish an RCS Vent Path or dedicated LTOP Operator.

B. RCS pressure and temperature exceed the limits that ensure brittle fracture prevention in accordance with TS 3.4.3 RCS Pressure and Temperature (PT) Limits; Restore RCS Pressure and Temperature to within limits in 30 minutes or less C. Administrative controls (Train 2) for an LTOP event are lost; Establish an RCS Vent Path or dedicated LTOP Operator in accordance with TS 3.4.12 Low Temperature Over Pressure Protection.

D. Administrative controls (Train 2) for an LTOP event are lost; Depressurize CFTs to less than RCS pressure within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in accordance with TS 3.4.12 Low Temperature Over Pressure Protection.

Enclosure 3.31 OP/O/A/II08/001 Unit 1 RCS Heatup/Cooldown Curves Page I of 5 NOTE: If changes are required to curves in this enclosure, the OAC curves must be updated at the same time or the OAC curves must be considered not valid. {I}

Enclosure 3.31 OP/O/A/IIOS/OOI Unit 1 RCS Heatup/Cooldown Curves Page 3 of 5 Unit 1 Wide Range Heatup Curve Tcold REACTOR COOLANT TEMPERATURE (OF) o 1900 - 1900 1800 - 1-t-+-iHH-+-+-t-t-+-+-t-+-+-t-t-t-f--t-I-t-t-H 20 of 1800 J If"Y\iI') FO 1700 - 1700 1600 - 1600 1500 - 1500 1400 - 1400 1300 - l+-+-+-+-+-+-I--+-+-+-+--+--+-*-+-++~~+++-~-r-t-+-+-+-Hr-+-t-+--+-+-I-+-+- 1300 1200 - HH-+-++-+-l-+-+-+-i--!-tI-+-+-H-+-+-+-H-+-+-+-+-Jf-H-++-+-+-+-+-+-H-+-t-+--+-+~ 12a0 1100 1100 1000 1000 900 -+-+-i-......j-l-T-+-+-+-I~-+-+-+-t--+-+-+~ft-+-H-++-+++-+-++-+-+-+-+-t-t-+-+-+-+-+-+-+-+-++-tr+t+1-++++-+-+-+-t-+-+-+-~IH-+-t- 900 800 I 800 700 700 600 NOT LIMIT SATURATION I-+-I-~~~-+- 600 500 500 f-!1-+-+--I--+--1~+--t--+-t-t--+--+-+-+-+--+-+--+-t-I'-f-+-+1 <4 RCPu mp t--+-+--t-+-h++.,rt--H'l-t-+-+-t--I-+-l-+-+--+-+-t--+-+-+--t-+-+--t-+--+-+--j-...,r-t-t-t 400 r--t-t-+--+-+-+++++-+-+-+-+--t-t--+--+--t-tH-t-I-HN PSH a 4 0 3a0

~  :-r 30A - '1300 F 0 J..-+4'+-H......t-+-~~--J..--l-J--'---'-....L-L--Irt-+--!-JI'+++-iH-++-+-+-++-H-+++-+-+-+-+-+-+-+-HH-+--+-+-+-+-+-1-++-

~~W:-I-'1I~~"~YFj)')~!fL?3=!EE~1~:H4I-R,+C-f-P-+-u+-mHP,-\-N PS H 4-f-!.Jf H ~.A- -Y'q-+-H-+-++-t-+--+-+-+-11-+-+-1--"1-.1-~tj=t--tr-!--~l-i~t~J=1-+~+-I--t-~iJ--++-++-+-+-1-1-+-1-t_+++'+--+-i~

"+--17' 1 2 a0 ~_ ,: --I-k-t-t-+-+-+-t-I--t-+-I-I-+-t---r-+-+-+-+-t--+--Vt-VHf--+--t--+ H-+-t-t-t-+-+-+-t--.I-+-H-+--++--+-+--+--+-+-+-t--++-+-+-+--t--+---\---f--l 200 i

100 ~ 100

~'-+~I-i-+-+-+-+-+--f-+-+--+-I-f-+-+-+--+-+---1IA~V-¥+--f-f-+-+--+-+-+-t--+--l-+-+--f-l-t--+---+---'f-+-+-+-+--+-+-+-+-+-+-+-+--+-+--+-+-f--+-+-+--+--+--+-t-t--l--l a .....j1'.....L....L....l-....-l..-L..l.-L~-+-.L.....1---'--L-...L-J.-l....X-l-+/1'...I.....l-J'-.....l.-.L.-'--I.-L-..L.--+.....L..l-.L-L...L--.J...-I-...l-L.1i.--..L...L---'---L.-L...L-l---L-J-f----l-.-L~..I-..l-J......l.-I--+--J--~~..I.-.l.-J.-+- 0 a 100 200 300 400 500 600 700 Tcold REACTOR COOLANT TEMPERATURE (oF) UIWRHU 33 EFPY, Rev. 2 Res TEMPERATURE MAX HEATUP RATE

~ 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period

~ gOOF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period

Enclosure 3.31 OP/O/A/II08/001 Unit 1 RCS Heatup/Cooldown Curves Page 4 of 5 Unit 1 Low Range Cooldown Curve

'T co 11l Reactor Coolant Temperature... o'F a 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 600 +--,-.......,.....,~+-""!"~~-~1"""I*-~,-I--:........,......~-~'"f""""l"'"""I-,~+-:---r~+-r-,...,..~j~~--+---:--r-:-r+-----,-,----;-+-~-rl-..,,--,-~.,.....,..*~~,......,-+-----r~+/-- 600 575 575 f.

550 - 550 525 1. R.es cooldown limitations d2500F 525

2. Minirnum RC pressure for Rep operation

.::1 Subcooled f*ij-i****f***;**,,******!I***i****t**'"i<.:**~*+**!**+"*i***I*;**..;***",,******}******+*****+*+:#:;

3. Minirnurn RCS pressure for continuous ,;.-

500 operation of single Rep in a loop. Minimize

- 500 operating time below this line with single I

475 Rep in a loop operating to limit cumulative ~ 475 damage to operatjnq pump caused by H._.; ... ~_., ... +... j ... i .... I ... <. t.+ ...;, ...,.. "i.,..;..+.+....:'k..;,... l,.~. '"!-< .. i.+ .. i ...... ~#:..:.... .J v 1**..,.. ***** ..,**++..*.. *.;***,**11 cavitation.

450

4. rv1ax HCS pressure and temperature for 450 LPr pump initiation.

425 5. ReS is considered depressurized when ~ 425 ;~J) all of the following conditions exist: (I'J.

0<

400 400

a. RCS Temperature < 200°F J'
b. FZCS Pressure < 50 psig OJ) 375 c. 1\11 RCFJs are off 375 ~
6. BriefiyoperaUng above the LPI pressurecurve~.~~h~*~~_~~~~r~ __ +'~+.~~~~_~~_0~~~~~~~+~+++~-~~i~~I~H0-~r~~~ 0:::

(#4) or belovo' the RCP NPSH curve 350 350 ~

< 40 psig i while ;vv8pping ~r 0

.J 325 325 Q.)

~

t 300 i'./j i;)

~

w 275 ~

~

~

~

250 '0 LTOP Limit 0 Maintain ....*... 225 U PZR Level 5

< 220 inches t-"'..I<ri-+++"k+-~~~--r-+-i-r--rl-~----""-+- 200 ~

~

jElllE::£~~elA2nU1thtEBl$l+/-iliUnht[fl~~in~t~hi~sia=reiadt£EBWJJ1i1-11l+/-tE3JL6£:a

.*.. <l,.)

175 CG

'75 , ;, i .. f********t**+-*i**Ar**:**..;***..*i***;**+*"-;d* ..,*+**!"i<,**'*.+.++-"'k++-++"k***,*"i.. + '*'x--*.;***j-;"*-!*-',-i""'"""""1"'"--f+""'-:**il.. + . j",,;---o--1*'-***.. i* ..;..J i "'**-i,"*0+ *c* .. - ..... *v.. "!-**...**j .... + ..

1 150

  • . *r .:

125 100 75 o

U 1LRcn ]3 EFPY, Rev. 7 T COld Reactor C:ooJant 'l'enlperaturc, up'

"" PZR level restricted to s; 380 inches Res TEMPERATURE MAX COOLDOWN RI-\TE c

when ReS temperature is:: 160 F o

7 T 2. 280 F ~ 4SoF in any 1;2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period find NO HPIPs operating. 150°F.:: T < 280°F .:: 20°F in any 1/2 hour period T < 150°F 2: 90F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Res depressurized (note 5)  ::: 45°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period

Enclosure 3.31 OP/O/A/llOS/OOl Unit 1 RCS Heatup/Cooldown Curves Page 5 of 5 Unit 1 Low Range Heatup Curve

'l'cOid I{eactor C:oolanT 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 GOO 57'5 St)O 525

()OO 475 450 425 400 375

$ 350

~

325 t

~

Vi 300

~

~ 215

~

~

~

'0 250 c

U <)r)r"

._.:::',;:)

b 0

~

~ 200

~

N

~

"1"75 150 25

'100 75 50 25 0 **+***,*_",,,;,,,~"'"'rhy>-W n;..*,**t*****~ __,C.,,L__..P f-'i. ,-...;. *..

~+~~,."'.> M"""c~¥..J~..:,......:........~_.....:-.i-'-"+'~.:..._.~¥-_.L'"'-....;.::.y-:J.......i.......--@fW~-i..,...!*:¥* __ *"-'-4:::.---L..;........::;-4.......:.~..!..v..i,*.w****+***,***,'" ..,....l****l--J...._"'-_*t__ 0 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 UfLRHU.33 LFPY, Re\" 5

  • PZR level restricted to 5; 380 inches v/hen ReS ternperature is ~ 1GOOF T and NO HPiPs operating, T::: 280°F

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 87 Unit 1 initial conditions:

  • Unit startup and heatup in progress
  • OP/1102/001 Controlling procedure for Unit Startup in progress Based on the above conditions, choose the response below that answers the following questions:

a) Which ONE of the following describes the RCS pressure band at which the Core Flood tanks are placed in service per OP/11 04/001 (Core Flood Tank Operation)?

b) What is the Tech Spec Bases for not requiring CFT operability at RCS pressures below the TS limit?

A. 730 - 750 psig At a reduced pressure, safety injection pumps can provide sufficient flow to prevent exceeding cladding temperature limits during a Large Break LOCA.

B. 780 - 800 psig At a reduced pressure, safety injection pumps can provide sufficient flow to prevent exceeding cladding temperature limits during a Large Break LOCA.

C. 730 - 750 psig At a reduced pressure safety injection pumps can provide sufficient flow to ensure the core remains completely covered during a Large Break LOCA.

D. 780 - 800 psig At a reduced pressure safety injection pumps can provide sufficient flow to ensure the core remains completely covered during a Large Break LOCA.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 88 Unit 1 plant conditions:

  • Reactor power = 100%
  • IAI RPS Variable Low RCS Pressure Trip Bistable trips
  • The crew determines that the bistable has failed
  • The bistable output state cannot be reset by the crew
  • SPOC has been contacted to investigate
  • While performing action for the failed channel, the RO inadvertently places the IBI RPS Channel to MANUAL BYPASS Based on the above conditions, which ONE of the following correctly describes the effect on the unit when the "B" RPS channel is placed in MANUAL BYPASS and the operability of the RPS Variable Low RCS Pressure Trip function(s) at this time?

ASSUME NO OPERATOR ACTION A. The reactor trips IAI RPS Variable Low RCS Pressure Trip function is no longer required to be operable B. The reactor trips IAI RPS Variable Low RCS Pressure Trip function is operable C. The reactor remains at power RPS Variable Low RCS Pressure Trip function is operable D. The reactor remains at power RPS Variable Low RCS Pressure Trip function is NOT operable

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 89 Unit 1 initial conditions:

  • Reactor power = 1000/0
  • 1A and 1C RBCUs operating in low speed
  • 1C and 1B RBCUs will be switched for run time Current conditions:
  • 1B RBS pump in recirc for testing
  • 1C RBCU secured
  • 1B RBCU started in low speed
  • OAC alarm 1B RBCU Vibration HIGH and can not be cleared Based on the current conditions, which ONE of the following describes actions to be taken per OP/11 04/015 (Reactor Building Cooling), and whether RB pressure will be maintained below the design pressure during a subsequent LOCA?

A. Start 1C RBCU, then stop 1B RBCU RB pressure will be maintained below design pressure B. Start 1C RBCU, then stop 1B RBCU RB pressure will NOT be maintained below design pressure C. Stop 1B RBCU, wait 30 minute,s to start 1C RBCU if desired RB pressure will be maintained below design pressure D. Stop 1B RBCU, wait 30 minutes to start 1C RBCU if desired RB pressure will NOT be maintained below design pressure

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 90 Unit 1 plant conditions:

Time = 0400:00

  • Reactor power = 75% power
  • AMSAC/DSS Bypassed
  • TDEFDW Pump out of service
  • 1A FDW Pump trips Time = 0402:00
  • 1B FDW Pump trips Time = 0402:05

ASSUME NO ADDITIONAL FAILURES OCCUR A. Minimize challenges to the pzr PORV I Subsequent Actions B. Minimize challenges to the pzr PORV I Loss of Heat Transfer C. Prevent exceeding DNBR limits I Subsequent Actions D. Prevent exceeding DNBR limits I Loss of Heat Transfer

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 91 Unit 3 plant conditions:

  • Shutdown for refueling in progress
  • Mode 4
  • Component Handling in progress in the Spent Fuel Pool
  • A fuel assembly is currently in the mast and being moved
  • 3RIA-6 (SFP Area Monitor) shows an observable increase, approximately 1/2 decade above background
  • Spent Fuel Pool level = (-) 2.7 feet decreasing Based on the above conditions, which ONE of the following describes the Abnormal Procedure that will provide direction for system operations to mitigate the event and a required Technical Specification entry and its bases?

A. Enter AP/35 (Loss of SFP Cooling and/or Level)

TS 3.10.1 (SSF) - Ensures the RC Makeup pump can maintain all three Oconee Units in MODE 3 for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

B. Enter AP/35 (Loss of SFP Cooling and/or Level)

TS 3.7.11 (Spent Fuel Pool Water Level) - Ensures adequate iodine removal during a fuel handling accident.

C. Enter AP/18 (Abnormal Release of Radioactivity)

TS 3.10.1 (SSF) - Ensures the RC Makeup pump can maintain all three Oconee Units in MODE 3 for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

D. Enter AP/18 (Abnormal Release of Radioactivity)

TS 3.7.11 (Spent Fuel Pool Water Level) - Ensures adequate iodine removal during a fuel handling accident.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 92 Unit 1 initial conditions:

  • Reactor power = 50%
  • 1A SG Startup Control Valve fails open Current conditions:
  • 1A SG level = 97% Operating Range (OR) increasing Based on the above conditions, which ONE of the following describes the actions required by the Subsequent Actions tab of the EOP and the basis?

A. Trip BOTH Main FDW pumps and steam the 1A SG to prevent flooding the aspirating ports B. Trip BOTH Main FDW pumps and close the 1A TBVs to prevent water hammer in the main steam line C. Manually throttle Main FDW to control SG level < 96% and steam the 1A SG to prevent flooding the aspirating ports D. Manually throttle Main FDW to control SG level< 96% and close the 1A TBVs to prevent water hammer in the main steam line

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 93 Plant conditions:

  • All 3 units are in Mode 1
  • 1SA-3/B-6 (Fire Alarm) actuated
  • The alarm was generated from address point 0202041
  • Subsequently, a Challenging Active Fire is reported in the affected area
  • The fire continues for approximately 15 minutes
  • The affected control room(s) have been evacuated
  • All subsequent required actions were taken within 10 minutes Which ONE of the following describes ALL of the units affected by the fire in accordance with the alarm response, and which ONE of the following describes the minimum emergency classification for this event?

SEE ATTACHMENT A. Units 1 and 2 ONLY; Unusual Event B. Units 1 and 2 ONLY; Alert C. All 3 Units; Unusual Event D. All 3 Units; Alert

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 94 Unit 1 initial conditions:

  • Reactor power = 100%
  • Loss of all Main and Emergency feedwater occurs
  • All CBPs are tripped
  • Rule 3 (Loss of Main or Emergency FDW) initiated
  • Loss of Heat Transfer tab initiated Current conditions:
  • RCS pressure = 2305 psig increasing
  • Rule 4 (Initiation of HPI Forced Cooling) has just been initiated
  • 1B HPIP tripped Based on the above conditions, which ONE of the following describes the correct action and the requirements for plant announcement?

A. Ensure adequate HPI flow in both headers / IIEmergency dose limits in effecf' will be announced to plant staff per the parallel action page.

ll B. Open reactor vessel head and loop vents / IIEmergency dose limits in effect will be announced to plant staff per the parallel action page.

ll C. Ensure adequate HPI flow in both headers / IIEmergency dose limits in effect will NOT be announced to plant staff since Emergency Dose limits have previously been in effect.

D. Open reactor vessel head and loop vents / IIEmergency dose limits in effect will ll NOT be announced to plant staff since Emergency Dose limits have previously been in effect.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 95 Unit 1 initial conditions:

  • Mode 6
  • Fuel Transfer Canal level = 21.5 feet
  • 1C LPI pump operating Current conditions:
  • Main Fuel Bridge operator has requested temporarily securing 1C LPI pump to facilitate fuel assembly insertion Based on the above conditions, which ONE of the following describes who approves securing the 1C LPI pump in accordance with OP/1502/007 (Operations Defueling/Refueling Responsibilities) and any additional requirements?

A. Refueling SRO I 1C LPI pump may be stopped provided movement of irradiated fuel assemblies is suspended immediately B. Operations Outage Manager I 1C LPI pump may be stopped provided movement of irradiated fuel assemblies is suspended immediately C. Refueling SRO I 1C LPI pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period D. Operations Outage Manager I 1C LPI pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 96 Unit 1 plant conditions:

  • MODE 2
  • RCS pressure = 2755 psig Which ONE of the following states the Technical Specification required action and its basis?

A. Restore RCS pressure within 5 minutes 5 minute time limit is based on the increased probability of brittle fracture B. Restore RCS pressure within 5 minutes 5 minute time limit is based on the capacity of the PORV to return system pressure to within the safety limit C. Restore RCS pressure and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour time limit is based on changing to a mode where the potential for additional safety system challenges is minimized D. Restore RCS pressure and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour time limit is based on the capacity of the PORV to return system pressure to within the safety limit

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 97 Unit 1 plant conditions:

  • Startup in progress
  • TD EFDW pump OOS Based on the above conditions, which ONE of the following describes the current technical specification operational MODE, and whether a change to the next higher Mode is allowed and why?

A. Mode 2 No, T.S. 3.0.4 does NOT allow a Mode change unless the applicable action statements for the next higher Mode allow continued operation without time limits.

B. Mode 2 Yes. T.S. 3.0.4 allows a Mode change as long as the applicable condition statements are entered upon entry to the next higher Mode.

C. Mode 3 No. T.S. 3.0.4 does NOT allow a Mode change unless the applicable action statements for the next higher Mode allow continued operation without time limits.

D. Mode 3 Yes. T.S. 3.0.4 allows a Mode change as long as the applicable condition statements are entered upon entry to the next higher Mode.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 98 Which ONE of the following describes the MINIMUM level of authority for approval of ONE (1) GWR release at the 1/3 Station Limit, and the SLC bases for limiting the Curie content of the GWD Tanks?

A. OSM approval/limits Whole Body exposure of individual at the nearest exclusion boundary to ~ 0.5 Rem in the event of an GWD tank rupture.

B. OSM approval/limits Whole Body exposure of individual at the nearest exclusion boundary to ~ 100 mrem during a planned GWD tank release.

C. SRO approval/limits Whole Body exposure of individual at the nearest exclusion boundary to ~ 0.5 Rem in the event of an GWD tank rupture.

D. SRO approval/limits Whole Body exposure of individual at the nearest exclusion boundary to ~ 100 mrem during a planned GWD tank release.

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 99 Unit 1 initial conditions:

  • Reactor power = 100%
  • RCS pressure = 1900 psig decreasing Current conditions:
  • Reactor power indicates 4°;{, and stable
  • ReS pressure is decreasing rapidly
  • SCM = OaF
  • IMAs in progress Which ONE of the following describes how the SRO will transition through the EOP for this event?

A. Transfer to Subsequent Actions Transfer to Loss of Subcooling Margin Tab using Parallel Actions page Transfer to the LOCA Cooldown Tab from LOSCM tab B. Transfer to Subsequent Actions Transfer to Unanticipated Nuclear Power Production tab using Parallel Actions page Transfer to Loss of Subcooling Margin Tab using Parallel Actions page when UNPP tab is complete C. Transfer to Unanticipated Nuclear Power Production Tab Transfer to Subsequent Actions at the end of the UNPP tab Transfer to Loss of Subcooling Margin Tab using Parallel Actions D. Transfer to Unanticipated Nuclear Power Production Tab Transfer to Loss of Subcooling Margin Tab using Parallel Actions page Transfer to the LOCA Cooldown Tab from LOSCM tab

OCONEE NRC SRO EXAM 03-20-2008 1 POINT Question 100 Unit 1 initial conditions:

  • Reactor power = 100%
  • LOHT occurs
  • Rule 3 initiated Current conditions:
  • EOP LOHT tab in progress
  • 1A SG pressure = 980 psig stable
  • 1B SG pressure = 200 psig decreasing Based on the above conditions, which ONE of the following describes the proper progression in the EOP and why?

A. Remain in the LOHT tab and reduce heat sources in the RCS by securing all RCPs.

B. Remain in the LOHT tab and attempt to re-establish a heat sink with the intact SG.

C. Transfer to the EHT tab to address the steam line break while attempting to establish feedwater flow with the TO EFOWP.

O. Transfer to the EHT tab to provide guidance on stabilizing RCS press / temp to prevent a Pressurized Thermal Shock condition.

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