ML14007A062

Initial Exam 2013-302 Final SRO Written Exam

ML14007A062
Person / Time
Site:	Sequoyah
Issue date:	01/07/2014
From:	Division of Nuclear Materials Safety II
To:
References
50-327/13-302, 50-328/13-302
Download: ML14007A062 (29)

Text

76. 008 AG2.1.7 576/BANK/SQN/HlGII E RI/SRO/SEQUOY AH/1311/NO Giv e n the following plant cond it ions: Unit 1 is at 1 00% RTP when a pressurize r safety valve failed open. -The operator manually tripped the reactor and initiated a safety injection.

When the crew transitions to E-1 , "Loss of Secondary or Reactor Coolant", the following plant cond it ions are observed:

PZR pressure 1580 psig and l owering Containment pressure reached 2.6 psig and is now stable. Just prior to performing step 14 , "Initiate evaluation of plant status:" as PZR pressure reached 1280 psig (its lowest recorded value) the PZR safety valve has c l osed. Cu rrent plant conditions are: Pressurizer level is 1 00% PZR pressure 1390 psig and rising RCS s ubcooling is 42°F -All four SG levels at 33% narrow range and stable Containment pressure i s 2.4 psig and slowly lowering Which ONE of the following identifies the required procedure implementation and operation of the RCPs for the above cond iti ons? A. Transition from E-1 to ES-1.1, S l Termination

The RCP s wil l have remained running throughout the event. B. Transition from E-1 to ES-1.1, S l Termination; The RCP(s) would hav e been shutdown , but will be restarted in ES-1.1 , S l Termination.

C. Continue E-1 until a transition is directed to ES-1.2, Post LOCA Cooldown; The RCPs will have remained running throughout the event. D. Continue E-1 until a transition is directed to ES-1.2, Post LOCA Cooldown; The RCP(s) would hav e been shutdown, but will be restart ed in ES-1.2, Post LOCA Cooldown.

Monday, N ovembe r 18 , 20131:10:27 PM 76 1311 IL T SRO EXAM 77. 011 EA2.05 677/NEW//HIGH ERJ/SRO/SEQUOYAH/1311/NO Given the follow ing plant conditions:

Unit 1 was operating 1 00% RTP. -The 1 A-A CCP tagged for maintenance due to an oil leak. -A LOCA occurred an hour ago. During the performance of ES-1.3, "Transfer to RHR Containment Sump," containment sump valves 1-FCV-63-72 and 1-FCV-63-73 could not be opened. -The crew entered ECA-1.1, "Loss of RHR Sump Recirculation." -While performing step 20 " Monitor if ECCS flow should be terminated," the crew observes the follow ing parameters:

-All RCPs are OFF -RVLIS Low Range is 70% and stable -Subcooling is 50°F and stable -RCS pressure is 150 ps ig and stable -RWST level is 20% and lowering -CTMT pressure is 3.0 psig and slowly lowering Which ONE of the following ident ifies: (1) in accordance with ECA-1.1, an action that you w i ll direct the crew to take AND (2) if the 1 B-B CCP tripped immediately after the start of the accident, the Design Basis for this accident being met? A. (1) Stop and Start ECCS pumps as necessary to establ i sh m i nimum ECCS f low. (2) is B. (1) Reset Phase A and Phase B, and stop RHR pumps, Sl pumps and all but one CCP. (2) is C. (1) Stop and Start ECCS pumps as necessary to establish minimum ECCS flow. (2) is NOT D. (1) Reset Phase A and Phase B, and stop RHR pumps, Sl pumps and all but one CCP. (2) is NOT Monday, No vember 18 , 2013 1:10:27 PM 77 1311 IL T SRO EXAM 78. 025 AA2.01 578/NEW//HIGHER//SRO/SEQUOYAH/131 1/N O Given the following plant conditions:

Unit 1 is in Mode 6 with the reactor vessel head being de-tensioned.

-The following plant parameters:

RHR pump 1 A-A is in service with flow at 3000 gpm. 1 A-A RHR pump amps = 20 amps RHR discharge pressure=

80 psig RCS pressure 0 psig. -An equipment malfunction occurs which results in the following plant parameters:

1A-A RHR pump flow= 0 gpm 1 A-A RHR pump amps = 3 amps RHR discharge pressure=

20 psig Which ONE of the following ident ifies both; (1) the equipment malfunction that occurred AND (2) in accordance with Tech Spec 3.9.8 , " Residual Heat Removal and Coolant Circulation", bases, the requirement for having two RHR loops OPERABLE?

A. 1A-A RHR pump shaft shear to ensure a single failure of an RHR loop does NOT result in a complete loss of res idual heat removal capability. B. 1A-A RHR pump shaft shear to ensure adequate time is provided to initiate emergency procedures to cool the core. C. FCV-63-93, RHR Cold leg to ensure adequate time is provided to init i ate injec tion to Loops 2 & 3 closed emergency procedures to cool the core. D. FCV-63-93, RHR Cold leg to ensure a single failure of an RHR loop does injection to Loops 2 & 3 closed NOT result in a complete loss of residua l heat removal capability.

Monday, Nov ember 18 , 20131:10:27 PM 78 1311 IL T SRO EXAM 79. 056 AG2.2.40 679/NEW/IHIGHER//SRO/SEQUOYAH/13 11!NO Given the following plant conditions:

Unit 2 is at 1 00% RTP. Unit 1 is at 547°F and 2250 psig, reactor trip breakers are OPEN. -The A-A EGTS fan is tagged out for maintenance.

-CSST "B" is tagged out for tap changer maintenance.

-At 0800,on 11/18 a malfunction in the switchyard causes off-site power to be lost to CSST "A." If the above conditions associated with CSST "A" remain unchanged, in accordance with Tech Spec, which ONE of the fo llow ing i dent i f ies the latest t i me Unit 2 would be required to be shutdown?

REFERENCE PROVIDED A. 2000 on 11/18 B. 2100on11/18 C. 2200on 11/18 D. 0800 on 11/25 Monday, November 18,20131:10:27 PM 79 1311 IL T SRO EXAM 80. 065 AA2.06 580/BANK/SQN

/HIGHER//S RO/SEQUOY AH/1311/NO Given the following plant conditions:

Unit 1 is at 12% RTP during a plant startup. -A loss of Essential and Non-Essential Control Air has occurred.

-The crew is attempting to restor e Control Air in accordance with AOP-M.02, "Loss of Control Air." -RCS temperature i s 555°F and rising. -PZR level i s 72% and rising. -SG NR levels are 15% and lowering.

Based on the current plant conditions, in accordance with AOP-M.02 , wh i ch ONE of the following indentifies:

(1) the reason a reactor trip is required , AND (2) if the action(s) required to control RCS temperature in AOP-M.02 can be performed concurrently with E-0? A. (1) loss of PZR lev e l contro l (2) yes B. (1) l oss of PZR level control (2) no C. (1) loss of SG level contro l (2) yes D. (1) loss of SG level control (2) no M o nd a y , Novemb e r 18 , 2013 1:10:27 PM 80 1311 IL T S RO EXAM 81. W/E04 EG2.4.18 58 1/BANK/SQN!HlGHER//SRO/SEQUOYAH/1201/NO Given the following plant conditions:

-The Unit 1 crew enters ECA-1.2 , " LO CA Outside Containment." -When ECA-1.2 is complete the following conditions ex ist: -CNM T pressure is 0.1 psig and stab l e. RWST level is 70% and lowering.

-CETs are indicating 51 ooF and stable. RCS pressure is 800 psig and lowering.

RVLIS i s 46% and slowly rising. Which ONE of the f o ll owi ng completes the statements below? The c r ew i s r eq uired to t ra nsition to (1) AND The Emergency Plan Classification for t hi s event is a(n) (2) REFERENCE PROVIDED A. (1) E-1 , " L oss of Reactor or Secondary Coo l ant" (2) Site Area Emergency B. (1) ECA-1.1 , "Loss of RHR Sump Recirculat io n" (2) Alert C. (1) E-1, "Loss of Reactor or Secondary Coolant" (2) Alert D. (1) ECA-1.1 , " Lo ss of RHR Sump Recirculat ion" (2) Si t e Area Emergency Monday , Nov ember 18,20131:10:27 PM 81 1311 ILT SRO EXAM 82. 069 AG2.1.23 682/BANK/S QN/HIGH E R//SRO/S E Q UO Y AH/1 3 1 J/NO Given th e following plant conditions:

Unit 1 is at 100% R T P. -At 0900 the l ocal leak rate test on the lower containment air lock test was performed following a containment entry and was NOT satisfactory. -System Engineering reports that U 1 overall containment leakage rate acceptance criteria is NOT met. -At 1800 Unit 1 remains at 1 00% RTP. Which ONE of the following identifies:

(1) if you are in compliance with Tech Spec A ND (2) the Tech Spec basis for the maximum a ll owed tota l containment l eakage (La)? REFERENCE PROV I DED A. (1) no (2) To prevent exceeding the design capability of the EGTS B. (1) ye s (2) To prevent exceeding the design capabil it y of the EGTS C. (1) no (2) To prevent exceeding 1 OCFR1 00 limits at the site boundary D. ( 1 ) yes (2) To prevent exceed ing 10CFR1 00 limits at the s it e boundary Monday, Nov e mb e r 18, 2 01 3 1: 10:27 PM 82 1311 ILT SRO EXAM 83. 076 AG2.4.46 583/NEW/SQN/HIGHER//SRO/SEQUOY AH/1311/NO Given the following plant conditions:

Unit 1 is at 100% RTP. -At 0800 a dropped rod occurred.

-At 1200 the rod was recovered and power was restored to 1 00% RTP. -At 1215 the following alarms were received pane l 1-M12-A: 1-RA-90-1A, "AUX BLDG AREA RAD MONITOR HIGH," (A-7) 1-RA-90-59A , "RX BLDG AREA RAD MON HIGH," (B-3) -At 1300 on 11/25 RCS Activ ity was determined to be 28 microcuries/gram DOSE EQU IV ALENT 1-131. Which ONE of the following comp l etes the statements below? In accordance with AOP-R.06 , "High RCS Activity," 1-RA-90-1A annunc i ator in a l arm (1) consistent with the given plan t cond it ions. AND In accordance with Tech Spec 3.4.8, "Specific Act iv ity," the unit i s required to be placed in Mode 3, w it h Tave < 500°F, NO later than (2) REFERENCE PROV ID ED A. (1) is (2) 1900 on 11/27 B. ( 1) is (2) 1900 on 11/25 C. (1) is NOT (2) 1900 on 11/27 D. (1) is NOT (2) 1900 on 11/25 Monday, N ovember 18,20131:10:27 PM 83 1311 ILT SRO EXAM 84. W/E 03 EA2.1 6R4/NEW//HIGH E R//SRO/SEQUOYAH/13 11/NO Given the following plant conditions:

Unit 1 was tripped from 100% RTP due to a Small Break LOCA. Containment pressure peaked at 2.9 psig. -The crew is performing ES-1.2 , "Post LOCA Cooldown and Depressurization." -The crew is evaluating step 37, "Determine if RHR should be placed in service:" -The following parameters exist: Both RHR pumps are stopped. Normal charging has been established.

PZR level is 28% and stable. RCP #2 is the only RCP running. RCS pressure-290 psig and slowly trending down. RCS temperature-340°F and slowly trending down. Containment pressure -1.1 psig and slowly trending down. RCS cooldown rate is 75°F/hr. Which ONE of the follow ing complete the statements below? The maximum cooldown rate allowed during the performance of ES-1.2 (1) being exceeded.

AND With the above conditions, the SRO will direct the crew to _

_with TSC concurrence.

A. (1) is (2) transfer to ES-1.4, "Transfer to Hot Leg Recirculation", B. (1) is (2) place RHR in service in accordance with EA-74-1, "Placing RHR Shutdown Cooling in Service," C. (1) is NOT (2) transfer to ES-1.4, "Transfer to Hot Leg Recirculation", D. (1) is NOT (2) place RHR in service in accordance with EA-74-1 , "Placing RHR Shutdown Cooling i n Service," Monday , November 18,20131:10:27 PM 84 1311 ILT SRO EXAM 85. W/E07 EA2.2 585/BANK/WB N/HT GHER//SRO/SEQUOY AH/l 3l l/NO Given the following plant conditions:

While operat in g at 100% RTP, a sma l l break L OCA occurred on Unit 1. -The operating crew has progressed through the emergency instructions and has placed RHR Train A in service in accordance with EA-74-1, "Plac i ng RHR Shutdown Cooling In Service," during performance of ES-1.2, "Post LO CA Cool down and D ep ressur izat ion." -Th e STA identifies a YELLOW path to FR-C.3 , "Saturated Core Coo li ng," and the SRO makes the transition.

Which ONE of the following completes the statements below? The basis of FR-C.3 is to (1) AND After entering FR-C.3, a transit ion to AOP-R.03, "RHR System Malfunctions," (2) be directed.

ill ill A. establi s h RCS cooling via SGs will B. establish RCS coo lin g via SGs w i ll NOT C. restore subcooling using ECCS wi ll D. restor e s u bcooling using ECCS will NOT M o nd a y, Novemb e r 1 8 , 2 013 1 : 10:27 PM 85 1311 ILT SRO EXAM 86. 005 A2.0 I 586/NEW//HIGHER//SRO/SEQUOY Ali/1311/NO Given the following plant conditions:

-Unit 1 is performing a plant shutdown in accordance with 0-G0-7, "Unit Shutdown From Hot Standby To Cold Shutdown." -When the 1 B-B RHR pump was started for boron sampling, it experienced excessive vibration and is tagged out of service. -Current plant conditions are: RCS temperature=

260°F RCS pressure = 290 psig -SG conditions:

1. 1 5% Wide Range RCP Tagged #2 #3 20% Narrow Range 8% Narrow Range RCP Running RCP available

1. 4 15% Wide Range RCP Tagged -During post work review, I&C technicians report to the WCC SRO that the flow transmitter for 1-FCV-7 4-12A, RHR Pump 1 A Mini-flow valve , has failed high. Which ONE of the following completes the statements below? Prior to taking any operator action the 1 A-A RHR pump is (1) AND in accordance with Tech Spec 3.4.1.3, "Reactor Coolant System-Shutdown ," bases , the LCO requirements for this specif i cation (2) being met. A. ( 1) OPERABLE (2) are B. (1) OPERABLE (2) are NOT C. (1) INOP ERABLE (2) are D. (1) INOP ERAB LE (2) are NOT Monday, Nov ember 18 , 201 3 1:10:2 7 PM 86 1311 ILT SRO EXAM 87. 008 G2.4.30 387/NE W//LOWERJ/S RO/SQN/1311/NO Given the fo ll owing plant cond i tions: -Both Units are at 100% RTP. Due to a potent i al breaker failure , the C-S CCS pump has been powered f r om it s alternate power supply (1 A2 480V SDBD) in accordance with 0-S0-70-1

," Component Cool i ng Water System "B" T rain." -The Train B power supp ly fo r th e C-S CCS pump will not b e ava i lab l e for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I n acco r dance with NPG-SP P-03.5 , "Regulatory Reporting Requirem ents," which ONE of the following identifies the Unit (s), if any , whose operating conditions, is/are requir ed to be reported to the NRC within 4 hrs? REFERENCE PROVIDED A. Neither Unit B. Unit 1 ON L Y C. Unit 2 ON LY D. Both Unit 1 & Unit 2 Monday, N ovember 18,20131: 10:27 PM 87 1311 ILT SRO EXAM 88. 026 G2.2.25 588/NEW/IHIGHER!/SRO/SQN/l311/NO Given the follow ing plant conditions:

Unit 1 is being shutdown for re fuel ing. RCS Tavg = 250°F PZR pressure = 290 psig -#2 RCP is running -The "1 B" train of RHR is being placed in service per 0-S0-74-1, "Residual Hea t Removal System." In accordance with Tech Spec 3.6.2.1, "Containment Spray Subsystems," (1) RHR spray operability

___ required for this plant condition AND (2) the action(s) that is/are required by 0-S0-74-1, to comply with Tech Spec 3.6.2.1, bases? A. (1) is (2) Close FCV-7 4-3, RHR Pump A suction isolat ion. B. (1) is (2) Ensure RHR pump A is aligned for auto start or an operator is standing by panel M6 to manually start the pump if required.

C. (1) is NOT (2) Close FCV-74-3, RHR Pump A suction isolation. D. (1) is NOT (2) Ensure RHR pump A is aligned fo r auto start or an operator is stand ing by panel M6 to manually start the pump if required. Monday, November 18, 2013 1 :10:27 PM 88 1311 ILT SRO EXAM 89. 062 A 2.07 589/NEW//HIGHER//SRO/SQN/131 !/NO Given the following plant conditions:

Units 1 and 2 are operat ing at 100% RTP. -The intertie transformer is OOS. -While removing the W i dow's Creek 500 kV l ine from service, a human performance error results in a complete loss of the 500kV switchyard.

Which ONE of the following completes the statements below? In accordance with Tech Spec 3.8.1, "AC Sources and Onsite Power Distribution Systems" bases , Offsite power is Operable for ( 1) AND The procedure that you will direct the crew to use to mitigate the event on Unit 1 is (2) A. (1) Unit 2 ONLY (2) AOP-P.01, " Loss of Offsite Power" B. (1) both Unit 1 and Un it 2 (2) ES-0.1, "Reactor Trip Response." C. (1) Unit 2 ONLY (2) ES-0.1, "Reactor Trip Response." D. (1) both Unit 1 and Unit 2 (2) AOP-P.01, "Loss of Offsite Power" Monday, November 18, 2013 1:10:27 PM 89 1311 IL T SRO EXAM 90. 06 3 G2.4.31 590/BANK/SQN/HIG H E R//SRO/SEQUOY AH/1311/NO Given the following plant conditions:

-Unit 1 is in Mode 3. -The following alarms are received in the control room panel1 M-C: -"125V DC V IT AL C HGR II FA I LURE OR VITAL BAT II D I SCHARGE" (B4) -"125V DC VITAL BAT BD II ABNORMAL" (B5) -Battery Board II Voltage indicates 119 VDC. Based on th e above conditions, in accordance with Tech Spec 3.8.2.3 , "D.C. Distribution-Operating ," Battery Board II is (1) AND in accordance with 0-S0-250-1 , "125 Volt de Vital Battery Boards" (2) A. (1) INOPERABLE (2) align the Spare Charger B. ( 1) I NOPERAB LE (2) Reduce Battery loading C. ( 1) OPERABLE (2) Align the Spare Charger D. (1) OPERABLE (2) Reduce Battery loading Monday , Nov e mber 18, 201 3 1: 10:27 PM 90 1311 I LT S R O EXAM 91 . 002 G2.2.37 59 1/BANK/S Q N/HJ GHER//S RO/SE Q UOY AHJ l/2009 RETAKE/NO Given the following plant con ditions: Unit 1 i s in Mode 3 following a pla nn ed shutdown for maintenance.

-Th e unit is bein g cooled down in accordance with G0-7 , "Unit Cooldown from H ot Standby to Cold Shutdown." Current RCS temp erature is 465°F and pressurizer pressure 1 535 ps i g. -A pressurizer PORV sp urious l y ope ned. Which ONE of the foll owing identifies:

(1) the procedure required t o be entered to address the fa i lu r e , AND (2) in accorda nce with Tech Spec 3.4.3 " Safe ty and R elief Valves-Operating ," b ases , assum in g the PORV can be opened and closed usi n g its control switch , the PORV is ? ( 1) Pro ced ur e A. AOP-R.05 , "RCS L eak and L eak Sou r ce Identification" B. AOP-R.05, "RCS L eak a nd L eak Sou r ce I den t ifi cat i on" C. AOP-1.04 , "Pressu r ize r I nst rum ent a nd Contro l Malfunctions" D. AOP-1.04, "Pressurizer In s trument and Con trol Malfun ct i ons" M o nd a y, N ovember 18 ,2 013 1: 10:2 7 PM (2) PORV Status Operable Inope rable Operable I nop e r ab l e 91 13111LTSROEXAM

92. 02 8 G 2.1.32 592/I3A NK/SQ N/HI G I I ER//SRO/S E Q UO Y AI I/1311/N O Given the following plant conditions: -A vapor space LOCA occurred on Unit 1. Some fue l damage was experienced during the accident.

-The LOCA has been stopped and the Safety Injection has been terminated.

The operating crew has transitioned to FR-1.3, "Voids in Reactor Vessel," and is current l y addressing the steps to prepare for and execute venting the reactor vessel. The following conditions are reported to exist: PRT pressure is 5 psig Containment hydrogen concentration is 6.3% Containment Pressure is 0.29 psid Neither Air Return Fan is avai l ab l e Which ONE of the following identifies

... (1) the actions directed by the procedure relative to Hydrogen Recombiner operation AND (2) the action that would be directed associated with reactor vessel venting? Hydrogen Reactor Vessel Recombiner Venting A. Would be placed Vent the vessel before transitioning in service. from FR-1.3. B. Wou l d be placed Return to procedure and step in effect without i n service. venting the reactor vessel. C. Would NOT be Vent the vesse l before transition i ng placed in serv i ce. from FR-1.3. D. Wou l d NOT be Return to procedure and step in effect w i thout p l aced in service. venting the reactor vessel. Monday, November 18,2013 1:10:27 PM 92 1311 ILT SRO EXAM 93. 079 A2.0 1 593/BANK/SQN/LOWER//S RO/SEQUOY Al I/1 311/NO Given the following p l ant conditions:

Unit 1 in Mode 3 with the RCS at normal operating temperature and pressure preparing for reactor startup. -Alarm "PS-32-104 TRAIN A AUX CONTROL AIR PRESS LOW" (M15-B) is actuated.

-Control Air pressure indications are: -P l-32-200 Contro l Air Header pressure is 65 psig and lowering. P l-32-1 04 Aux Bldg Control air header A pressure is 65 psig a nd lowering.

P l-32-105 Aux Bldg Control air header B pressure lowered to 82 psig and is now rising. Which ONE of the following completes both statements?

AOP-M.02 , "Loss of I nstrument Air," directs the crew to ensure _ ......

_are closed. AND In accordance with Tech Spec, the Turbine Dr i ven AFW pump _ _.(=2.._)

_required to be declared I NOPERABLE. Note: 0-FCV-32-82 , Aux. Compsr. A-A Aux. Bldg /sol. 0-FCV-32-85 , Aux. Compsr. 8-B Aux. Bldg /sol. 1-FCV-32-80, Unit 1 Train A Rx Bldg /sol. 1-FCV-32-1 02 , Unit 1 Train B Rx Bldg /sol. A. ( 1) 0-FCV-32-82 and 0-FCV-32-85 (2) is NOT B. (1) 1-FCV-32-80 and 1-FCV-32-102 (2) is C. (1) 0-FCV-32-82 and 0-FCV-3 2-85 (2) i s D. ( 1) 1-FCV-32-80 and 1-FCV-32-1 02 (2) i s NOT M o nd a y , Novemb e r 1 8,20 1 3 1:10:27 PM 93 1311 IL T SRO EXAM 94. G 2.1.42 094/BANK/SQN/LOWERI/S RO/SEQUOY AH/13 1 1/NO In accordance w i th FHI-3 , "Movement of Fuel ," which ONE of the following i dentif i es the m axim um number of NEW and IRRADIATED fue l assemb l ies within th e areas listed below that can be l ocated out of approved storage locations?

New Fuel Ass emblies I rradiated Fuel Assemblies within th e fuel-handling area within the refu eling cana l A. 1 2 B. 1 3 C. 2 2 D. 2 3 M o n day, Novemb er 18,20 1 3 1: 10: 27 PM 94 1311 ILT SRO EXAM 95. G 2.2.15 295/NEW//LOWER//SRO/SQN/1 311/NO Which ONE of the following completes the statements below (consider each statement separately)?

In accordance with NPG-SPP-1 0.1, "System Status Control," the _ _.(-'-1 ._) _ is responsib l e for au thorizing the re l axation of s t a t us cont rol. Maintenance requests that an additional drain valve be opened, which is located inside a clearance isolation boundary.

Th e NPG-SPP-1 0.1, Attachment 3, " Deviation Tracking Sheet," (2) an allowable method to track the drain valv e posit i on. A. (1) Plant Manager (2) is B. (1) Plant Manager (2) is NOT C. (1) Operations Superintendent (2) i s D. (1) Operations Superintendent (2) is NOT Monday , Nov embe r 18 ,2013 1:10:27 PM 95 13111 LT SROEXAM 96. G 2.2.20 196/B AN K MOD/SQN/III G H ER//SRO/SEQUO Y AH/131 1/NO Given the f o ll ow ing conditions:

Unit 2 i s co min g out o f a refueling outage. 0-SI-SXV-074

-203.2 , "Full Stroking of RHR Va l ves 2-FCV-74-1 and 2-FCV-74-2" is being perfo r med. Personnel are in posi t ion and monitoring valve operation local l y. FCV-74-1 to ok 1 1 8.8 sec ond s to ope n on fir st cyc l e. F C V-74-1 took 87.5 seco nds to c l ose on first c y cle. -Valve ope rat ed smoothly and all i nd i cation worked proper ly. Which ONE of the following identifies the curren t status of the valve? REFERENCE PROVIDED A. Valve open ing tim e is in the ALERT range. Va l ve is INOPERABLE . B. Valve opening time is in the ALERT range. Valve is OPERABLE . C. Valve closing time is in the ALERT range. Va l ve is OPERABLE . D. Valve c l osing time is in the ALERT range. Valve is INOPERABLE . M o nd a y , November 18 , 20131:10:27 PM 96 1311 ILT SRO EXAM 97. G 2.3.4 097/BANK/SQN/L OW ERI/S R O/S QN/13 11/NO Given the following plant conditions:

A LOCA occurred on Unit 1 . A Site Area E mergency has been declared.

The Containment Barrier is intact (i.e. no loss or potential loss of containment).

The Containment Critical Safety Function Status Tree (FR-Z) is Yellow due to high radiation in containment.

Containme nt pressure i s 2.1 psig and decreasing.

There is no release to the environment in progress.

The "A" train of containment spray is operating normally for plant conditions.

The "B" containment spray pump tripped, 25 minutes ago , after pump amps were observed to be oscillating.

Authorization has been given for an eme rgen cy responder to receive an emergency exposure of 11 Rem TEDE in order to restore "B" train containment spray. Which ONE of the following completes the statement below? The emergency exposure author izati on (1) the requirements of EP IP-15 , "Em ergency Exposure Guide l ines," because _ _.(=2...._)

_ ill ill A. met emergency exposure limits can always be authorized during any Si te Area Emergency REP class ifi cation B. violated emergency exposure limits can on l y be authorized during a General Emergency REP classification C. met the emergency exposure was necessary to maintain critica l safety functions D. violated the emergency exposure was NOT necessary to maintain critical safety functions Monday , November 18 , 20131:10:27 PM 97 1311 ILT SRO EXAM 98. G 2.3.7 398/BANK//LOWERJ/S RO/SE QUOYAH/1 3 11/N O Given the following plant conditions:

-A diving operat io n in the Spent Fuel Pit is p l anned to commence later in the shift. Which ONE of the following completes th e statements below? The dive (1) the requirements of NPG-SPP-07.3, "Work Activity Risk Managem e nt Process ," to be classified as a HIGH risk activity.

AND I f the rad level in the area of the dive is estimated at 20 Rad/hr, in accordance with RC I-14 , "Radiat i on Work Perm i t (RWP) Prog r am," the RWP would be required to be approved by (2) ill A. m eets B. meets C. does NOT meet D. does NOT meet M onday, Novemb e r 1 8,20 131: 10:27 PM Radiation Protection Manager on l y Radiation Protec t ion Manager and Pl a nt Manager Radiat i on Protection Manager o nl y Radiat i on Protection Manager an d Plant Manager 98 1311 I LT SRO E XAM 99. G 2.4.35 599/BANKJDC COOK/IIIG H ER//SR O/S E QUO Y AH/131 1/ Given the fo llowing plant condi tions: 0200 -Unit 2 is operating at 1 00% RTP when im plementation of AOP-C.04, "Shu t down from Auxiliary Control Room ," was required.

0204 -All ma in contro l room actions have been completed and the main contro l room is evacuated.

0212 -All transfer swi t ches are placed in the requ i r ed position in accordance with AOP-C.04, Check list 2, Unit 2 Auxil i ary Control Room. 0218 -AUO report s 6.9Kv Shu tdown Board eq uipm ent is configured in accordance with Checklist

4. Which ONE of the following comp let es the stateme n ts below? The cond iti o n s requir e the declaration of a/a n _in accordance with the Radiological Emergency Pl an. AND (2) con trol is/ar e ava il a ble for Pr essu ri ze r Ba ckup H eate rs 2A-A. REFERENCE PRO VI DED A. (1) Alert (2) ONLY manual B. (1) Alert (2) BOTH manual and automa t ic C. (1) Site Area Emergency (2) ONLY manual D. ( 1) S it e Ar ea Emergency (2) BOTH manual and automa ti c M o nd a y, N ovember 18 ,2 0131:10:27 PM 99 1311 ILT SRO EXAM 100. G 2.4.38 200/BANK MOD/SQN/lii G HER//SRO/SQN/1 3 1 1/N O Given the following plant conditions:

-A Genera l Emergency has been declared due to a plant event that resu l ted in a radiation release. -Th e duration of the release is estimated to be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. -Wind Direction is from 181 degrees@ 10 mph. Dose projections and surveys have not yet been performed Which ONE of the following identifies the Protective Action Recommendations required in acco r dance with EPIP-5, "General Emergency?" REFERENCE PROVIDED A. She lt er the entire 10 mile EPZ, consider issuance of Kl in accordance with the State Plan. B. Evacuate A1-B1-C1-01 , A2, A3 and 82. Shelter the remainder of the 10 mile EPZ. C. Evacuate A 1-B 1-C1-01, A2 and 82. She lter the remainder of the 10 mile EPZ. D. Evacuate A1-B1-C1-D1, A2, -5 , -6 , 82, -3, -4. Shelter the remainder of the 10 mile EPZ. You have completed the test! Monday, Novemb er 18, 2013 1 :10:27 PM 100 ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers # ID Points Type 0 007 EK2.02 501 1.00 MCS A 2 009 EA2.11 602 1.00 MCS c 3 015 AK1.01 503 1.00 MCS A 4 025 AK3.02 504 1.00 MCS A 5 026 AA1.01 205 1.00 MCS D 6 027 AK1.02 106 1.00 MCS D 7 038 EG2.4.31 507 1.00 MCS D 8 055 EA2.03 8 1.00 MCS A 9 056 AG2.1.20 609 1.00 MCS A 10 057 AA1.04 410 1.00 MCS B 11 058 AK3.01 211 1.00 MCS B 12 062 AA2.06 512 1.00 MCS B 13 065 AK3.04 13 1.00 MCS c 14 077 AG2.2.42 214 1.00 MCS A 15 W/E04 EK2.2 15 1.00 MCS D 16 W/E05 EK1.3 516 1.00 MCS D 17 W/E11 EA1.3 517 1.00 MCS A 18 W/E12 EK2.1 118 1.00 MCS A 19 001 AA1.04 119 1.00 MCS D 20 036 AK3.02 520 1.00 MCS c 21 037 AKI.02 621 1.00 MCS A 22 051 AA2.02 522 1.00 MCS D 23 068 AA2.05 623 1*.oo MCS B 24 076 AK2.0 1 524 1.00 MCS c 25 W/E02 EG2.2.44 625 1.00 MCS A 26 W/E03 EK2.2 26 1.00 MCS D 27 W/E08 EK3.3 527 1.00 MCS A 28 003 K6.14 628 1.00 MCS B 29 004 K2.02 29 1.00 MCS A 30 004 K3.06 30 1.00 MCS D 31 005 K5.03 531 1.00 MCS B 32 006 A4.01 32 1.00 MCS B 33 007 K5.02 633 1.00 MCS A 34 008 K3.03 534 1.00 MCS B 35 010 Kl.08 35 1.00 MCS A 36 012 A2.05 636 1.00 MCS D 37 013 K2.01 537 1.00 MCS D 38 022 A3.01 38 1.00 MCS D 39 022 K3.01 39 1.00 MCS B 40 025 A3.02 40 1.00 MCS c 41 026 G2.2.36 541 1.00 MCS c 42 039 A4.04 42 1.00 MCS D 43 059 A2.11 43 1.00 MCS B 44 059 K4.16 44 1.00 MCS B 45 061 Kl.07 45 1.00 MCS A 46 061 K6.01 146 1.00 MCS D Friday, December 20, 2013 2:28: 11 PM 1 ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers # ID Points Type 0 47 062 Al.Ol 547 1.00 MCS c 48 063 Al.Ol 348 1.00 MCS c 49 063 A2.0149 1.00 MCS B 50 064 G2.4.4 550 1.00 MCS B 51 073 K4.01 551 1.00 MCS c 52 076 A3.02 552 1.00 MCS A 53 076 K2.04 53 1.00 MCS B 54 078 Kl.04 54 1.00 MCS D 55 103 K4.04 655 1.00 MCS B 56 001 K4.23 556 1.00 MCS c 57 011 K6.04 557 1.00 MCS B 58 015 Al.Ol 558 1.00 MCS D 59 028 K5.04 59 1.00 MCS A 60 041 K2.02 560 1.00 MCS B 61 045 K3.01 661 1.00 MCS A 62 055 A3.03 562 1.00 MCS A 63 056 A2.04 63 1.00 MCS A 64 072 A4.01 564 1.00 MCS A 65 075 G2.4.1 665 1.00 MCS D 66 G 2.1.32 566 1.00 MCS D 67 G 2.1.45 467 1.00 MCS A 68 G 2.2.14 568 1.00 MCS A 69 G 2.2.22 569 1.00 MCS c 70 G 2.2.38 70 1.00 MCS B 71 G 2.3.13 571 1.00 MCS D 72 G 2.3.14 672 1.00 MCS ..-IV' c i 2../-:l-o fo A k:., t2/SI jfj 73 G 2.3.4 573 1.00 MCS B 74 G 2.4.20 574 1.00 MCS D 75 G 2.4.25 575 1.00 MCS c SECTION 1 ( 75 items) 75.00 Friday, December 20, 2013 2:28:11 PM 2 ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers # ID Points Type 0 008 AG2.1.7 576 1.00 MCS A 2 011 EA2.05 677 1.00 MCS c 3 025 AA2.01 578 1.00 MCS A 4 056 AG2.2.40 779 1.00 MCS c 5 065 AA2.06 680 1.00 MCS A 6 W/E04 EG2.4.18 581 1.00 MCS D 7 069 AG2.1.23 682 1.00 MCS c 8 076 AG2.4.46 583 1.00 MCS B 9 W/E03 EA2.1 684 1.00 MCS D 10 W /E07 EA2.2 585 1.00 MCS c 11 005 A2.01 586 1.00 MCS c 12 008 G2.4.30 487 1.00 MCS c 13 026 G2.2.25 588 1.00 MCS c 14 062 A2.07 589 1.00 MCS B 15 063 G2.4.31 590 1.00 MCS A 16 002 G2.2.37 591 1.00 MCS c 17 028 G2.1.32 592 1.00 MCS D 18 079 A2.01 593 1.00 MCS A 19 G 2.1.42 94 1.00 MCS B 20 G 2.2.15 295 1.00 MCS c 21 G 2.2.20 196 1.00 MCS B 22 G 2.3.4 97 1.00 MCS D 23 G 2.3.7 498 1.00 MCS A 24 G 2.4.35 599 1.00 MCS B 25 G 2.4.38 200 1.00 MCS c SECTION 1 ( 25 items) 25.00 Friday, December 20, 2013 2:28:43 PM 1 References for 1311 NRC SRO Exam 1. Steam Tables 2. Mollier Diagram 3. Unit 1 Tech Spec LCO 3.6.1.8 Emergency Gas Treatment System EGTS Cleanup Subsystem, Amendment 263 (2 pages 3/4 6-13 and 3/4 6-14) 4. Sequoyah EPIP-1 Emergency Plan Classification Matrix, rev 50 (2 pages 11 and 12 of 49) 5. Unit 1 Tech Spec 3/4.4.8 Specific Activity, Amend 301 (page 3/4 4-19) 6. ASME Code Valve Testing 0-SI-SXV-074-266.0, Rev 0021 (pages 1 19) 7. SQN Unit 0 EPIP-5 General Emergency, Rev 0044 Appendix A (page 1 of 1) and Appendix H (2 pages 1 & 2 of 2) 8. NPG-SPP- Appendix A (pages 19-33) 9. Sequoyah EPIP-1 Emergency Plan Classification Matrix, rev 50 Sect 4 (pages 25-32)