Text

Forwards NRC Operator Licensing Exam Rept (Included Completed & Graded Tests) for Tests Administered During Wk of 970825
	ML20199A307
Person / Time
Site:	Perry
Issue date:	11/13/1997
From:	Bies M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9711170134
	Download: ML20199A307 (381)
	v • d • e

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" " '64 UZlTED STATES g, e 's NUCLEAR REZULATORY COMMISSION O )

E REGION m i D f 801 WARRENVILLE ROAD 4,,e.... /

USLE, IWNOIS 80532-051 November 13, 1997 NOTE T0: NRC Document Control Desk' Mail Stop 0-5-D-24 FROM: M ry Ann Bies, Licensing Assistant m ,

Operating Licensing Branch, RIII

SUBJECT:

OPERATOR LICENSING EXAMINATION ADMINISTERED THE WEEK OF AUGUST 25, 1997, AT THE PERRY NUCLEAR POWER PLANT, DOCKET NO. 50-440 During the week of August 25,1997, Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the following informition for arocessing through NUDOCS and distribution to the NRC staff, including tie NRC PDR:

Item #1 - 'a) Facility submitted outline and initial exam subniittal, designated for distribution under RIDS Code A070, b)- As given operating exainination, designated for distribution under RIDS Code A070.

Item #2 - Examination Report with the as-given written examinatin attached, designated for distribution under RIDS Code IE42.

Attachments: As stated W

9711170134 971113 O DR ADOCK O l

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l INITIAL SUBMITTALS FOR PERRY AUGUST 1997 EXAM 9

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OUTLINE FOR PERRY AUGUST 1997 EXAM t

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RO WRITTEN EXAM 1

PERRY NUCLE AR POWER PLANT EXAM COMMENCING 08/22/97 f I

System - K/A - Statement Rating .RO Only?

Plant-wide Generics: 13%

294-001: K1.01 Valve lineups 3.7 Kl.02 Tagging procedures 3.9 Kl.03 10CFR20 and radiation control 3.3 Kl.04 A1. ARA 3.3 Kl.05 Controlling access to vital areas 3.2 Kl.07 Electrical safety 3.3 K1,16 Fire brigade requirements 3.5 Al.02 Execute procedural steps 4.2 A1.03 Locate and use procedures related to staffing reqmts 2.7 A 1.06 Maintain clear, accurate records 3.4 A 1.08 Obtain, interpret graphs, charts, tables 3.1 A1.13 Locate control room switches, determine correct plant lineup 4.5 A1.16 Take actions in E Plan 2.9 h$Y Y b? !$ !Y Y$ Y Group I Plant Systems: - 28%

201-001 K2.0 i CRDil pump power supply 2.9 201-005 K4.03 Rod block signals 3.5

-201 005 G004 System purpose 3.3 )X 202-002 G001 Operator responsibilities 3.6 Site-5pecific Priority 202-002 A4.02 Monitor / operate llPU's 2.8 XX 203-000 K4.10 Initiation logic 3.9 203-000 K6.10 Effect ofloss of cooling water 3.0 XX 209-001- G010 System P & L's 3.4 XX 209-002 K4.07 Knowledge ofinterlocks 3.5 XX 211-000 A4.03 Operate / monitor explosive valve A.I I

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1 PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 212-000 A 1.08 Solenoid valve position on scram 3.4

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RO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 -

System K/A Statement Rating RO Only?

Group I Plant Systemrt 28% (Continued) 212 4 00 K2,01 RPS MG Set power supplies 3.2 215-005- A1.04 Predict / monitor rod blocks / scrams 4.1 216-000 K5.07 ETect of Cntmt / DW temp. on level 3.6 217-000 A4.04 Operate / monitor manual isolation 3.6 XX 218-000 A4.03 ADS logic reset 4.2 239-002 A3.09 Lo-Lo Set logic 3.9 241-000 K3.02 AFect ofloss of Press. Regulating system on Rxi 4.2 259-001 A2.01 Impact of pump trip on FW System 3.7 259-002. K4.09 Single element control of FW System 3.1 259-002 K5.03 Effect on FW level control with a loss oflevel indication 3.1 XX 261-000 K4.01 Auto initiation of Standby Gas Treatment 3.7 264-000 A2.09 Operation of DG w/ loss of AC 3.7 223-001 K5.01 Operation of vacuum breakers 3.1 XX 223-002 A3.01 System indicating lights 3.4 XX 209-002 A2.01 Predict impact of system initiation (inadvertant) 3.8 215-304 K4.02 SRM scram signals 3.4 241-000 , K4.03 Backup overspeed control 3.0 XX Group Il Plant Systems: 19 %

202 001 A2.23 Effect of / actions taken on Recire FCV clostre 3.2 XX 204-000 K 1.08 Interrelationship btwn. RWCU & SLC 3.7 205-000 G0ll Knowledge of Tech Spec LCO's 3.1 XX 219-000 G010 System operating instruction P & L's for SP Cooling 34 226-001 A4.07 Valve logic reset / bypass / override 3.5 256-000 A1.05 Predict changes due to CST level 2.9 XX 262-001 A3.02 Automatic Bus Transfer operation 3.2 263-000 K2.0i Major DC loads 3.1 2

271-000 K4.08 Auto isolation of Offgas system 3.1 RO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 Sysu m K/4 Statement Rating - RO Only?

Group ll Plant Systeos: 19% (Continued) 272-000 A 1.01 Predict / monitor lights / alarms / indications 3.2 226-001 K4.09 Auto entmt. spray initiation interlock 3.2 XX 290403 A3.01 Auto reconfiguration 3.3 239-001 Kl.10 Interrelationship btwn Main and extraction steam 2.7 245-000 G012 Immediate action for Core Monitor alarm 3.3 XX 245-000 K5.02 Turbine operation and limitations 2.8 201 003 K1.03 Relationships btwn CRDM and RPIS 2.8 XX 286-000 K6.01 Effects ofloss of AC on Fire Protection Sys. 3.1 XX 201-003 K4.02 Interlock detecting uncoupled rod 3.8 XX 204-000 G010 Explain / apply system instruction P&L's 3.2 XX Group I!! Plant Systems: 4%

233-000 K4.08 LOCA Isolation of fuel Pool Cooling and Cleanup System 2.6 239-003 A2.l l Effect ofincreasing Rx press on MSIV Leakage Control 3.1 288-000 A2.04 EITect of high radiation on plant ventilation 3.7 XX 290-002 G011 Knowledge of Tech Spe entry conditions 3..' XX Group I F.mergency and Abnormal Plant Evolutions: 13 %

295-005 AK2.01 Effect of turbine trip on RPS 3.8 295-006 A A l.02 Ability to monitor level control following scram 3.9 295-007 A K3.04 Response of SRV's on high pressure 4.0 295-009 AK l .02 Relationship btwn low RPV level and recire pump NPSH 3.0 295-025 EA 1.03 Operate / monitor SRV's during high Rx pressure 4.4 XX 295-014 AK l.01 Implications of prompt critical on inadvertent reactivity addition 3.7 295-015 AA 1.04 Operate / monitor Rod Control & Info. System during incomplete 3.4 scram 3

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PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 295-024 EA2.09 Interpret entmt. pressure (PSP) during high DW pressure 4.0 295-025 EK2.03 Interrelationship of RRCS during high RPV pressure 4.0 4

l RO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 System - K&A Statement Rating RO Only?

Group I Emergency and Abnormal Plant Evolutions: 13% (Continued) 295-031 EA l.08 RPV low water level altemate injection systems 3.8 295-037 EK3.01 Reason for Recirc FCV runback during ATWS 4.1 XX 295-037 EK3.03 Reason for lowering RPV water level during ATWS 4.1 XX t 295-006 AK2.07 Pressure control during scram 4.0 XX

?

Group II Emergency and Abnormal Plant Evolutions: 19 %

295-002 AA2.01 Interpret effects ofloss of vacuum on plant 2.9 295-008 A A l.01 Abihty to monitor RPV level control during high RPV water level 3.7 295-011 AK l .01 Impact of cntmt. pressure on high entmt. temp. 4.0 295-013 A A 1.01 Operate / monitor suppression pool cooling during high SP temp. 3.9 295-016 G010 Perform immediate actions from memory during CR abandonment 3.8 295-018 AK3.02 Reason for power decrease on loss of cooling water 3.3 295-019 G010 Ability to perform immediate actions from memory on loss of air 3.7 295-022 A A2.01 Interpret accumulator pressure on loss of CRD pumps 3.5 295-001 A A2.01 Interpretation of the power to flow map during loss of forced 3.5 circulation 295-063 - AA2.03 Predict system lineup changes on loss of AC 3.5 XX 295-004 AA2.04 Predict system lineup changes on loss of DC 3.2 XX 295-016 AA1.07 Operation of remote shutdown panel switches during CR abandonment 4.2 XX 295 027. EK3.01 Reason for emergency depressurization w/high entmt temp. 3.7 XX 295-026 G012 Determine llCL using symptom-based procedures 3.8 295-029 G012 Use of symptom based procedures during high SP water level 3.6 295-030 EA 1.04 Operating SPMU with low SP level 4.0 XX 4

w PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 ~

295033 .G012 Use of symptom-based procedures during hi secondary entmt rad 3.8 levels 295038 EK2.05 Emergency plan during high offsite release rate 3.7 XX 29k028 EK2.03 Impact of high DW temp on RPV water level 3.6 XX RO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 System . ,. K/A Statement Rating - RO Ocly?

Group 111 Emergency and Abnormal Plant Evolutions: 4%

295-021 A A 1.04 Alternate decay heat removal methods during loss of shutdown cooling 3.7 295-023 AA 1.03 Operation of fuel handling equipment during a refuel accident 3.3 295-032 G012 Use of symptom-based procedures during high secondary entmt temp. 3.6 295-036 G012 Use of symptom based procedurc during high secondary entmt water 3.8 Ivl.

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PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/2237 fm 6

SRO WRITTEN EXAM

- PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 System -K/A Statement - Rating 'SRO Only?

Plast wide Generics: 17 %

294-001-. K l.01 Conduct / verify valve lineups 3.7 K1.02 Tag l ing / clearance procedures 4.5 Kl.02 Tagging / clearance pro::dures 4.5 RO only has i Kl.02 K1.03 10CFR20 and radiation control 3.8 K1.03 10CFR20 and radiation control 3,8 RO only has i Kl.03 K1.04 Knowledge of ALARA 3.6 Kl.05 Requirements for controlling access to vital / control areas 3.7 K 1.07 Safety procedures related to electrical equipment 3.6 K 1.14 Knowledge of safety procedures related to con 0ned spaces 3.4 XX K1.16 Facility protectic,.i requirements regarding fire briga le / Gre equipment 3.8 A1.02 Ability to execute procedural steps 4.2 A1.03 Locate and use procedures related to shift stalTmg and activities 3.7 A1.06 Ability to maintain eccurate, clear and concise, logs, records, etc. 3.6 Al.08 Obtain / interpret station reference material 3.6 Al.13 Locate control room controls to determine proper lineup 4.3 A 1.15 Use plant computer to obtain / evaluate information on system status 3.4 XX Al.16 Ability to take Emergency Plan actions 4.7

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SRO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97- _

Systens K/A Statement Rating SRO Only? -

Gosp I Plant Systems: 23 %

201-005 K4.03 Rod withdrawal blocks 3.5 G001 Knowledge of operator responsibilities 3.7 site-specific 202-002=

Priority 203-000 K4.10 Dedicated injectiori sys during auto initiation (injection viv. int rlocks) 4.1 209-001 K4.04 LPCS line break detection 3.2 XX 209-002 A2.01 Predict impact ofinadvertant system initiation 3.8 211000' G005 Knowledge of Tech Spec LCO / Safety Limits for SLC 4.4 XX 212 000 A1.08 Predict solenoid valve position on scram 3.4 218-000 A4.03 ADS logic reset 4.2 226-001 A4.07 Valve logic reset / bypass / override 3.5 223-001 K6.07 Effect of a loas of the flydrogen Igniters on the containment 3.1 XX 223-002 K6.07 Effect of a loss of AC power on NSSSS 3.3 XX 259-002 K4.09 Single element control of the FW system 3.1 217-000 G005 Knowledg: of Tech Spec LCO / Safety Limit for RCIC 4.3 XX 216-000. K5.07 Effect of containment / DW temperature on RPV water level 3.8 239-002- A3.09 Lo-Lo set logic 3.9 241-000 K3.02 Afrect ofloss of the pressure regulating system on Rx pressure 4.3 215-005 A1.04 Predict / monitor rod blocks / scrams 4.1 264-000 A2.09 Operation of the diesel generators with a loss of AC 4.1 261-000 K4.01 Auto initiations of Standby Gas Treatment 3.8 211-000 A4.03 Operate / monitor explosive valve 4.1 212-000 K2.01 RPS MG set power supplies 3.3 262-001 A3.02 Automatic Ilus Transfer operation 3.3 215-004- K4.02 Source Range Monitor scram signals 3.5

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SRO WRITTEN EXAM .

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PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 System K/A Statement Rating SRO Only?

Group II Plant Systems: 13 %

201-001 K2.01 CRDit pump power supply 3.1 202-001 G005 Knowledge of Tech Spec LCO / S ifety Limit for Recirc System 4.2 XX 204-000 k' R

, Interrelationship between RWCU and SLC 3.8 205-000 G005 Knowledge of Tech Spec LCO / Safety Limit for Shutdown Cooling 3.9 XX 215-003 K3.03 EfTect of a loss or malfunction of IRM's on RC&ls 3.7 XX 214-000 G010 System Operating Instruction P & L's for SP Cooling 3.5 239-003 A2.l l EfTect of increadne, Rx pressure on MSIV Leakage Control 3.3 245-000 K5.02 Main turbine operation and limitations 3.1 259-001 A2.01 Impact of a pu np trip on the FW system 3.7 263-000 K2.01 Major DC loads 3.4 271-000 K4,08 Auto isolation of Offgas system 3.3 272-000 A l.01 Mcaitor lights, alarms, indications of Radiation Monitoring system 3.2 290 303 A3.01 Auto re<.onfiguration of the Control Room Ventilation system 3.5 Group III P! ant Systems: 4%

233-000 K4.08 LOCA isolation of the Fuel Pool Cooling & Cleanup System 2.8 290-002. G005 Knowledge of Tech Spec LCO / Safety Limit for Rx Vessel & Intemals 4.1 XX 239-001 K l.10 Interrelationship btwn Main and extraction steam 2.8 256 000 A4.01 Manual operation of flW / Condensate pumps w/high IIST level 3.3 XX 9

SRO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 System K/A Statement Rating SRO Only?

Group i Emergency and Abnormal Pls~t Evolutionst 26% -

295003 AK l.06 Definitior of N vice LOOP / TLAC 4.0 XX 295006 G010 Immediate actions if station loads don't auto shift on a scram 4.2 XX 295007 AK3.04 Response of SRV's on high Rx pressure 4.1 295-009 AK 1.02 Relationship btwn low RPV level and Recite pump NPSil 3.1 295023 AKl.01 Knowledge of radiation exposure hazards during Refuel Accidents 4.1 XX 295013 A A 1.01 Operate / monitor SP Cooling during high SP Temp. 3.9 295-014 AKl.01 Implications of prompt critical on inadvertant reactivity additions 3.8 295-015 A A 1.04 Operate / monitor RC&lS during an incomplete scram 3.7 295-016 G010 Perfonn immediate actions from memory during CR abandonment 3.6 295017 G002 Knowledge of events requiring reports to outside agencies 4.7 XX 295-023 A A 1.03 Operation of Fuel Handling Equipment during Refuel Accidents 3.6 295-024 EA2.09 Interpret Cntmt pressure (PSP) during high DW pressure 4.1 295031 EK3.04 Knowledge of steam cooling during low RPV water level 4.3 XX 295-025 EF2.03 Interrelationship of RRCS during high Rx pressure 4.3 295-026 G012 Determine llCL using symptom-based procedures 4.5 295-027 EK3.03 Knowledge of reason for scram during high containment temperature 3.7 XX 295-030 G008 Recognize entry conditions for Tech Specs during low SP level 4.4 XX 295031 EK l .01 Knowledge ofimplications for adequate core cooling during low RPV 4.7 XX tvl.

295-037 G012 Use of symptom-based procedures (Use Special Plant instructions) 4.6 XX 295-037 EA2.01 Ability to determine power (Rx shutdown under nll conditions) 4.3 XX 295038 G012 Use symptom based procedures during high off site release rate 4.5 XX 295-031 EAl.08 RPV low water level alternate injection systems 3.9 295 006 A Al.02 Ability to monitor RPV water level fo!h. wing a scram 3.8

- = = -

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SRO WRITTEN EXAM PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97

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System . K/d Sistement Rating SRO Only?

Group ! Emergency and Abnormal Plant Evolutions: 26% (Continued) 295-024 EAl.17 Impact of high DW pressure on containment spray 3.9 XX 295-025 EK2.01 Reason for EOC / RPT during high Rx pressure 4.1 XX 295-015 AA2.01 Ability to interpret pwr follow ing incomplete scram (ONI vs PEI) 4.3 XX Group li Emergency and Abnormal Plant Evolutions: 17 %

295-001 AA2.01 Interpretation of power to flow map on loss of forced circulation 3.8 295-002 A A2.01 Interpret effects of a loss vacuum on the plant 3.1 295-004 AK2.03 Knowledge ofloads lost on a loss of DC 3.3 XX 295-005 AK2.0 Effect of a turbine trip on RPS 3.9 295-008 A Al .01 Ability to monitor RPV level control during a high RPV water level 3.7 295-011 AK l .01 Impact of containment pressure on high containment temp. 4.1 295-020- A K2.09 Interrelationship btwn inadvertant entmt isolation at.1 shutdown 0.3 XX cooling 295-019 G010 Ability to perform immediate actions from memory on loss of air 2.4 295-021 AA 1.04 Alternate decay heat removal methods during loss of shutdown cooling 3.7 295-022 A A2.01 Interpret accumulator pressure on loss of CRD pumps 3.6 295-028 G012 Use of symptom-based procedures during high DW temperature 4.3 XX 295-029 G012 Use of symptom-based procedures during high SP Level 4.4 295-032 G012 Use of symptom-based procedures during high secondary entmt temp. 4.4 295-033 G012 Use of symptom-based procedures during high secondary entmi rad 4.4 levels 295-018- AK3.02 Reason for power decrease on loss of cooling water 3.4 295-036 G012 Use of symptom-based procedures duringhigh secondary entmt water 3.9 Ivl 295-022 A A I.03 EITects of k> sing CRD on Recirc system 2.8 XX l1

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ES-301 Administrative Topics Outline Form ES-301 Examination Level (Circle One): RO / SRO Facility: PERRY STATION Week of Examination 08/25/97 Examiner's Name (print) :

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Temporary RO: Write a Non-Intent Procedure Change modifications of. procedures SRO: Approve a Non-Intent Procedure Change Rx S/L admin Using supplied SRM / IRM readings, verify roper requirements overlap and take appropriate actions (overlap data will not be adequate to continue startup and will require a Rx shutdown'to be commenced)

A.2 Tagging and Write an Information Tag on a conponent clearances A.3 Use of Checkout a radiac from HP and perform applicable portable checks to use this device radfation monitorring equipment A.4 SRO: Classify SRO: Classify simulator scenario and fill out an event appropriate paperwork RO: RO: Candidate will be told that Site Accountab'lity Demonstrate is required. Demonstrate the method for performing account- accountability by control room personnel and state ability the time required-for him to do so.

Chief Examiner:

ES-301 Individual Walk-through Test Outline Form-ES-301-2 Examination Level (Circle One): RO / SRO(I) / SRO(U)

Facility: PERRY STATION Week of Examinations _ 08/25/97 Examiner's Name (Drint):

System / JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description

1. CRDH / Perform I a. 201001G010 Fast Restart of a tripped CRDH pump. b. 201001A304 (f aulted) (U)

2. FW/ Shift TDRFP II u. 259002G010 to MDRFP on S/U Level b. 239002K101 Controller.

3. SRV/ Attempt to III a. 229002G005 close a stuck open SRV by b. 239002A309 pulling fuses. _

4. HPCS/ Override IV a. 209002A206 Level 8 trip for HPCS pump for RPV b. 209002A109 injection. (U) ,__

5. Cnmt. & V a. 223001K505 Auxiliaries:

Perform S/U of H2 Recombiner b. 223001A105 A. (U)

6. A.C. Elec/ VI a. 262001K403 TrancCer Sta electrical leads to the b. 262001A405 SU Xfmr.

7. NIS/ Bypass a VII a. 215005G010 failed LPRM (U) b. 215005K402

Examination-Level (Circle One) : RO / 5...O (I)- / SRO (U)

Facility: PERRY STATION Week of Examination: 08/25/97 __

Examiner's Name (print):

System / JPN Safety Planned Follow-up Questions:

Function. K/A/G // Importance // Description

8. Fire VIII a. 286000K402 Protection:

Initiate control room subfloor CO2 b. 286000G0001 from outside the control room.

9. Annulus IX a. 261000K401 Exhaust Gas Treat / Shift fans from A to b. 261000A303 B.

10. RHR/ Perform II a. 203000A103 RHR Loop B Flood Alt b. 203000K117 Iniect. (U)

Examiner: Chief Examiner:

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1 ES-301 Scenario Events' Form ES-301-3 i

Simulation Facility: PERRY STATION Scenario No.: 1-Examiners: Applicants: -

Initial Conditions: Rx at 75' CTP. oower ascension in oroaress. HPCS is OOS ;

Turnovers-Continue oower ascension

-Event Malf. Event Event No.- No. Type

Description 1 R Power increase of a5% using Reactor recirc flow 2 I APRM "A" fails upscale causing.AFDL ckt, to runback power 3 N Reset H scram 4 N Restore Recirc. FCV hydraulics 5 I CRDH Flow Controller fails upscale 6 M Earthquake causes an instrument air leak in containment, DW press, increases 7- M ATWS 8 C Ctmt. And DW Inst. Air valves fail to auto close 9 C Leak of Scram Discharge volume into the containment 10 I Sequential loss of RPV level indication 11 C Two ADS valves f ail to o[w:n w<

- - This scenario contains a loss of air which is #9 & 10 events on our IPE/PRA.

- (N) orma l , . .( R)eactivity, (I)nstrument, (C)omponent, (M)ajor Chief Examiner:

,n. . . , ,

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ES-301 Scenario Events- Form ES-301-3 Simulation Facility: PERRY STATION Scenario No'.: 2 Examiners: -Applicants:

Initial Conditions: Rx at 100% CTP. Division 1 outaae in oroaress Turnover: Plant at 100% CTP with a Div. 1 Outaae in broaress. Div 1 DG, RHR A. LPCS, and RCIC were olaced in secured status last shift and RTO.

This crew should clan on the Wo's beino brouaht to the control room this shift to commence work. SVI-R10-T5217 is due in one hour.

Event Malf. Event Event No. No. Type

Description 1 N Performance of S"I-R10-T5217 2 I FW Heater SA level controller fails upscale, isolating Htr SA 3 R Power decrease to s95%

4 N Htr. either restored to service or lined up per SOI ,

5 I RFPT "A" fails upscale w/a 1 min, ramp 6 C Trip of Isophase Bus Duct Cooling Fan "A" 7 M Lightning strike in transformer yard causes a LOOP 8 C/M Div 2 DG starts then trips on overspeed, causing a SBO 9 C HPCS Injection valve fails to auto open, can be manually opened

**This scenrrio is representative of a PNPP IPE/PRA dominant accident sequence.

. (N) ormal, . (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ,

Chief Examiner:

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ES-301- Scenario Events Form EC-301-3 Simulation Facility: PERRY STATION Scenario No.: 3 Examiners: Applicants: l Initial Conditions: Rx cower at 33% CTP cower-ascension in Drocress Turnover Rx at 33 % CTP with a oower ascension in crocress. ready to ghift Rx Recire oumos to fast speed.

-Event Malf. Event Event

'No. No. Type

Description 1 N/R Shift Rx Recirc pumps to fast speed 2 I Failure of DW pressure instruments causes an inadvertant HPCS initiation 3 C HPCS Injection valve blows fuses while stroking open 4 I Hot Surge Tank level controller fails downscale 5 M/C Fire in MCC (one of the loads is Recirc isol.

valves) e 6 C Recirc pump seals begin *.o fail on one loop (DW pressure increase) 7 C Rx mode switch fails in " operate" position 8- C Failure of RPS solenoids to de-energize (RRCS works) 9 M Rupture of Recirc pump seals 10 C MSIVs auto close when Rx pressure decreases to 807 psig 11 C Failure of breaker to close for Div. 2 essential bus

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Chief Examiner:

4

_ , _ . _ _ ~ _ _

ES-301 Scenario Events Form ES-301-3' Simulation Facility ' PERRY STATION Scenario No.: 4 l

-1 1

Examiners:- Applicants:

Initial-Conditions: Rx at 100% CTP, HPCS is OOS Turnover: HPCS is OOS due to excessive vibration durina last Dumo run.

last shift olaced-it in secured status and taaaed it out, decrease owr.

to ~90%. Derform SVI-C85-T1314 followina owr. decrease Event Malf. Event Event No. No. Type

Description i

, 1 R Reduce power using Recirc flow to s90%

2 N Perform SVI-C85-T1314 ' Bypass valve cycling) 3 C Bypass valve sticks open 4 I MSL Pressure Instrument fails (auto awap to stby inst.)

5 I RPV Level inst. Line break in DW 6 M/C Spurious MSIV closure w/ ATWS 7 I Startup Level Controller fails dowr. scale in Auto (OK in man.)

8 C SLC pumps fail tu start 9 I RCIC speed control failure f- 10 C Three SRVs fail to open

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Chief Examiner: _

r -- - w s-w, ,-r --

f

~ INITIAL WRITTEE EXAMINATION SUBMISTAL- ' PERRY - AUG 1997'

']

'b t

QNUM'

-HNUM-

' ANUM-

- 'QCHANGED = FALSE - ,

'ACHANGED FAI.SE

QDATE 1997/08/30- 4

FAC- -440' l

RTYP GE-BWR6

?EXLEVEL' R

EXMNR . FACILITY

QVAL' 1.00

-SEC

'SUBSORTo

KA 201005G004 )

-* QUESTION Which one of the below responses correctly describes the purpose behind the Rod

. _ Control & Information System enforcing notch limits above the Low Power Setpoint?

l

a. Prevent exceeding MCPR or LHGR during a postulated control rod drop accident.

b. Prevent exceeding MCPR or LHGR during a postulated contro! rod -

continuous withdrawal accident.

c. Restrict control rod pattems to those analyzed resulting in acceptable

. fuel enthalples during a Rx startup.

d. Restrict control rod pattems during a power increase to prevent exceeding the Reactivity Anomalies technical specification.

! *AN3WER b.

REFERENCE SDM: C11(RC&lS)

LP: OT-3036 C11(RC&lS), Obj. G

ONUM .l

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC ~440

RTYP GE-BWR6

EXLEVEL R

EXMNR FACILITY

OVAL 1.00

SEC

SUBSORT

KA 202002A402

OUESTION Given the following initial conditions on Reactor Recirc Hydraulic Power Unit "A" :

Subloop ': Operational, LEAD, READY selected Subloop 2: READY selected.

Select the condition that would cause Subloop 1 and Subloop 2 to shift to the MAINTENANCE mode.

a. Oil reservoir level decreases to 60 gallons.

b. Oil reservoir tempe,ature increases to 145degF.

c. Hydraulic pump discharge pressure increases to 2050 osig.

d. Fullers Earth Filter differential pressure increases to 10 psid.

ANSWER a.

REFERENCE SDM: B33 LP: OT-3036-B33, Obj. E 1

i

)

L*QNUML

'HNUld

ANUM -

QCHANGED FALSE

ACHANGED FALSE

- QDATE- 1997/08/30-

FAC ~440

RTYP _GE-BWR6

EXLEVEL 'R-

EXMNR FACILITY

QVAL -1.00

SECi

SUBSORT-

KA 203000K610

QUESTION Emergency Service Water pumn "B" has just been declared inop. due to

- a. shaft seizure. It has been determined that RHR Loop "B" needs to be lined up in its Containment Flooding mode. Which of _the following sources of water are still available to perform this operation?

a. . Diesel Fire Pump.

b. The suppression pool.

c. Emergency Service Water Loop "A".

d. Emergency Closed Cooling Loop "B".

ANSWER a.

REFERENCE PEl-T23 LP: OT-3402-16, Obj. D i

i w - > , . w - ~ -- ,wn- 4-n-, s u g--n--awm , .,p-, ,, .

. . - . - - . . . ,- = . .- . .

QNUM

HNUM-

ANUM '

QCHANGED= FALSE.

ACHANGED- FAI.SE -

- *QDATE -1997/08/30

FAC . 440

RTYP GE-BWR6

EXLEVEL- R

EXMNR: FACILITY

?QVAL- 1.00-

SEC-

'SUBSORT

KA 209001G010

'

QUESTION Th_e RHR "A" pump was running in Suppression Pool Cooling when the-Ursit Supervisor reque!,ted you t'> start tne Low Pressure Core Spray System and place it on Minimum Flow. The System Engineer will be coming up to the _ control roort shortly to assist you in a LPCS Work

- Order retest. This should not be done because it would result in:

a. a loss of flow to the LPCS pump.

b. - a loss of flow to the RHR "A" pump.

c. excessive load on the Div.1 Diese.4 Generator,

d. check valve cycling on the common SP return line.

ANSWER a.

REFERENCE SOI-E21 LP: OT-3036-E21, Obj. H t '

~

., v ,+__ -- e ~ - - - - - -

QNUM

' *HNUM

ANUM-

QCHANGED- ~ FALSE-

ACHANGED FALSE

QDATE 1997/08/30

FAC ._440

RTYP GE-BWR6

EXLEVEL-- R

EXMNR - FACILITY

QVAL 1'03

SEC

SUBSORT

"*KA 209002K407

? QUESTION The HPCS_ system has automatical;y initiated due to BOTH a high drywell and a low reactor water level. Which one of the following

statements is correct about resetting the initiation?

a. The initiation signal can be reset with both initiating signals still present.

b. - Both the high drywell and low reactor water level signals must clear irs order to reset.

c. Only the low reactor water ievel signal must clear as the high drywell pressure signal can be locked out by the reset.

d, Only the high drywell pressure signal must clear as the low reactor water level signal can be locked out by the reset.

ANSWER c.

REFERENCE SC,M: E22 LP: GT-3036-E22, Obj. E

a.-

x

=

QNUM

HNUM

ANUM -

'QCHANGEDi FALSE

ACHANGED: . FALSE:

'QDATE- L 1997/08/30

FAC 440-

RTYP' GE-BWR6

EXLEVEL R --

EXMNR FACILITY

QVAL 1.00

SEC ,

'SUBSORT KA- 217000A404

QUESTION-

During a full flow test of the RCIC system (CST to CST), a problem is encountered and the Control Room operator makes the decision to

^

. isolate the RCIC system. - He arms and depresses the RCIC Manual

' Isolation' pushbutton. How does the RCIC System respond?

a. The RCIC TurLine trips.

b. The RCIC System isolates, Divistor 1 anly,

c. The RCIC System isolates, Division 1 and 2.

d. Nothing happens, RCIC System doesn't isolate.

ANSWER d.

REFERENCE SDM: . E51 LP: OT-3036-E51, Obj. D

,1 1,

__i______._ - . . . . -

v ,, , ,,, , . - . ,.m..- , y y m--

i

ONUM l

'HNUM '

' ANUM i

QCHANGED FALSE

. 'ACHANGED FALSE i

'QDATE 1997/08/30 [

'FAC 440 '

RTYP GE BWR6

'EXLEVEL R

EXMNR FACILITY i

QVAL 1.00 '

SEC

'SUBSORT

KA 259002K503 5

' QUESTION The unit is operating at 100% power with both RFPTs in service.

Narrow Range level instrument N004A is FAILED HIGH. Feedwater level control is selected to "B" level instrument. Narrow range level instrument N004C has just FAILED HIGH. Which ONE of the following correctly describes the Feedpumps response?

a. Both feedpumps will trip,

b. The feedpumps will lock in the last called for speed position,

c. RFPT A ONLY will trip because Narrow Range level instrument "B" is still indicating properly,

d. The feedpumps would not be affected since level Instrument N004B is used for input into Feedwater Level Control.

' ANSWER a.

REFERENCE-SDM: C34 LP: OT-3036-C34, Obj. C i

t_ ._ ,

i

'ONUM f

HNUM

ANUM

'QCHANGED FALSE .

ACHANGED FALSE

QDATE 1997/08/30

'FAC 440

RTYP GE-BWR6

EXLEVEL R

'EXMNR FACILITY :

'QVAL 1.00

SEC

'SUBSORT

'KA 223001K501

' QUESTION Following a small sieam line break in containment, the differential

. pressure between the Containment and Drywell builds up to a positive .5 psid. The expected response of the Drywell Vacuum Relief System is which of the following? The Vacuum Relief MOV lsol. Valves (F010A/B) will open:

a, but can be closed and will remain closed by taking the control switch to CLOSE.

b. .but will automatically close and remain closed if a BOP LOCA cendition is present,

c. but can be closed and will remain closed only if the Drywell vacuum condition clears,

d. only if a BOP LOCA condition is present with the Drywell vacuum condition present.

ANSWER c.

REFERENCE SDM: mig LP: OT-3036 M10, Obj. C, E

- , - ,-,.--,,--.-p.- .-- y --m.- y . ,---. m 9,r, ,,-- . . . , ry,, ..A-.-

h k

'i

QNUM !

t.NUM !

_ ANUM ~ ;

'QCHANGED FALSE- !

ACHANGED - FALSE i

QDATE 1997/08/30 l

FAC 440 l

'RTYP GE-BWR6

EXLEVEL R l'

EXMNR FACILITY

QVAL 1.00- -

'SEC

'SUBSORT 3

KA 223002A301 ,

fQUESTION ,

While operating at 100% Rx power an l&C Technician asks you to place i the RWCU lsolation Bypass switch,1E31-S1A on H13 P632, to the .

I l BYPASS position for the performance of his surveillance test. If you L _ perform this action, what implications does it have on the RWCU i system? - l

a. The low RPV level 2 RWCU isolation is bypassed. !

1

b. The RWCU isolation due to SLC Initiation is bypassed.

c. The High RWCU differential flow isolation is bypassed.

d. The Non Regenerative Heat Exchanger high outlet i

> temperature isolation is bypassed.

ANSWER ,

c,

REFERENCE SDM: G33 LP:- OT-3036 G33 E31 OT-3036 E31 -

P f

i >

f a

, _ _ - - . , , _ , _ . . . _ _ . . , _ _ ,.r.,,., ,,m.- ,_ . , . .

QNUM

HNUM

ANUM >

QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440 :

'RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00 :

'SEC k

SUBSORT

'KA 241000K403

QUESTION With EHC control in the STANDBY mode, SELECT from below the i system response to a Main Turbine Overspeed condition,

a. The turbine will not trip.- Overspeed protection NOT is-provided in the STANDBY mode.

b. The BOST Unit will trip the main turbine at 105%, due to <

operating in STANDBY.

c. The main turbine will trip on high MSOP dischargo pressure as turbine speed increases.

d. At 100.5%, the turbine control valves will start to close and be fully closed at 105.5%, if speed continues to increase, ,

the intercept valves will start to close at 105.5% and be fully closed at 107.5%. If speed continues to increase, the MT will trip at 110%.

ANSWER b.

REFERENCE SDM: N32/C85 LP: OT-3036-N32/C85, Obj. G, D 9

l i

'ONUM

'HNUM

' ANUM

'OCHANGED FALSE

'ACHANGrD FALSE

'QDATE 1007/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

'QVAL 1.00

'SEC

'SUBSORT

'KA 256000A105

' QUESTION Which of the below statements is correct assuming that Hotwell Storage Tank level decreased to approximately 62" during normal full power operation?

a. The Normal Hotwell Makeup valve would begin to open at this level,

b. sol N21 directs securing all Hotwell and Condensate Booster pumps at this level.

c. The Emergency Hotwell Makeup valve would open and the Normal Hotwell Makeup valve would close,

d. Dissolved oxygen concentration of the condensate in the hotwell storage tank would most likely increase.

' ANSWER d.

' REFERENCE SDM: N21 LP: OT-3036 N21, Obj. B, D T

'QNUM

'HNUM

' ANUM

'QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R

'EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA 226001K409

' QUESTION XXX - 18 a. argueable correct? Will the pump trip on overload (automatic)?

SELECT the statement that correctly describes the operation of the Residual Heat Removal (RHR) System.

a. The RHR Pump C will automatically trip if no suction path is available.

b. Suppression Pool Test Return Valves (F024A/B) cannot be opened with a LPCI initiation signal present.

c. A Containment Spray initiation signal will cause the RHR Pump A to start if it had been manually overridden while in the LPCI mode.

d. RHR Pump A and B suction valves (F004A/B) will automatically realign for the LPCI mode when an initiation signal is received.

ANSWER c,

REFERENCE SDM: E12 LP: OT-3036 E12, Obj. F

'ONUM

'HNUM

' ANUM i I

'OCHANGED FALSE

ACHANGED FALSE c 'QDATE 1997/08/30

FAC 440

'RTYP GE BWR6

EXLEVEL R :'

'EXMNR FACILITY

QVAL 1.00

SEC

'SUBSORT

'KA 245000G012

' QUESTION While operating at 100% power, alarm window " GENERATOR CORE MONITOR P864" on panel H13 P680 energizes. The following indications exist on the Generator Validation Control Panel H13 P864:

MACHINE HEATING LED is ON, and the current reading is 80% What IMMEDIATE action is the operator required to perform?

a. Insufficient Information is available to determine operator actions,

b. Notify l&C of equipment malfunction.

c. Within 5 minutes, remove generator from service per 101-14, Fast Unload and Trip of Main Turbine,

d. Monitor generator hydrogen pressure. Maintain generator load within the limits of the Generator Capability Curvr.

ANSWER c.

' REFERENCE ARl H13 P680 9 LP: OT-3036 N35, Obj. H

= -- - - - , y , .r.=--r, -v-y-,---, ,- , , ~r,--,.#- ., -. - , .~ ... m ----- . - - - c.,.,--- - . -- + , -.m -, , - - - ,,. ..m--m--, - , ,..f,-. v. -

QNUM

'HNUM

ANUM

QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

'KA 201003K103

QUESTION While withdrawing control rod 30 31, a " channel disagree" light comes on and a rod withdrawal block is generated. It is determined that, at the current position, there is a faulty position reed switch in channel"A".

Can the operator continue to withdraw control rod 30-317

a. No, both reed switches must be operable per Tech. Specs, to continue rod withdrawal.

b. Yes, a data substitution must be made for the faulty reed switch using the channel "B" data,

c. Yes, the control rod is required to be bypassed at the Rod Gang Drive Cabinet, but can then be moved.

d. No, substitute data is not allowed to replace good data, and since the faulty reed switch is considered real data at that position, then substitute data is not allowed.

ANSWER b.

REFERENCE SDM: C11(RCIS)

LP: OT-3036-C11(RCIS), Obj. E

ONUM

HNUM

ANUM

OCHANGED FALSE

'ACHANGED FALSE

'ODATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

OVAL 1.00

SEC

SUBSORT

'KA 286000A301

QUESTION SELECT the statement that describes the response of the Fire Service Water system pumps to an inadvertant actuation of the deluge system for the main transformer.

a. The motor and diesel fire pumps both start when the deluge initiation signal is received,

b. The motor fire pump starts at 120 psig, the diesel fire pump starts when pressure is less than 105 psig in the fire header.

c. The diesel fire pump auto starts when pressure is less than 120 psig and the motor fire pump starts at 105 psig in the fire header,

d. The motor fire pump is started by the receipt of the deluge initiation signal, the diesel fire pump starts when pressure is less than 105 psig in the fire header.

ANSWER b.

REFERENCE SDM: P54 (WTR)

LP: OT-3036-P54(WTR), Obj. D

QNUM

HNUM

ANUM '

QCHANGED FALSE

'ACHANGED FALSE ,

QDATE 1997/08/30 l

FAC 440

RTYP GE BWR6 ,

EXLEVEL R

EXMNR FACILITY

QVAL 1.00 ,

'SEC

SUBSORT ,

KA 201003K402

' QUESTION Which one of the following statements is correct concerning an uncoupled control rod during coupling checks? >

a. Up to two attempts may be made to recouple the drive,

b. If attempts to recouple the rod are unsuccessful, the rod should be disarmed at that position,

c. Digital display of control rod position on the Rod Display >

Module will go blank if the rod is uncoupled. ;

- d. When the ROD UNCOUPLED Indicating light has illuminated, li will not clear until the rod is successfully recoupled.

ANSWER c.

REFERENCE ONI C11-2 LP: OT 3036-C11(RC&lS), Obj. H

ONUM

HNUM

ANUM

QCHANGED FALSE

'ACHANGED FALSE

'ODATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA 204000G010

' QUESTION A Rx start up and heat up is in progress. RPV water level is being controlled by use of the RWCU DUMP TO MAIN CNDR STOP VALVE, 1G33-F046. In order to lower RPV level at a faster rate, it is suggested to open RWCU DUMP TO RADWASTE STOP VALVE,1G33 F035, to provide an additional dump flowpath. Why is this not advisable?

a. This could cause possible runout conditions on a running RWCU pump.

b. This could cause formation of a void space and excessive water hammer to equipment.

c. The two flowpaths are fed by a common line and thus total dump flow would not be increased.

d. This could cause a loss of condenser vacuum and possible damage to the Waste Collector Tank.

ANSWER d.

REFERENCE SOI-G33 LP: OT-3036-G33, Obj. C

ONUM

'HNUM-

' ANUM ;

OCHANGED FALSE !

ACHANGED FALSE !

QDATE 1997/08/30

'FAC 440

RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

' OVAL 1.00 i

SEC

'SUBSORT

'KA 288000A204

QUESTION SELECT the statement that describes the expected response of the Containment Vessel and Drywell Purge Supply (M14) System following i a refueling accident where an exposed fuel bundle is drcpped and is damaged. The M14 system is currently operating in the Refuel mode.

a. M14 system isolation valves automatically isolate on a containment ventilation exhaust high radiation signal.

b. The M14 system isolation valves close which cause the M14 exhaust fans to trip The M14 supply fans continue to operate,

c. The M14 system isolation valves close which cause the M14 supply fans to trip. The M14 exhaust fans continue to operate,

d. M14 system isolation valves remain open. The M14 supply and exhaust fans trip on a containment ventilation exhaust high radiation signal.

' ' ANSWER

a. I

' REFERENCE-SDM: M14 LP: OT-3036-M14, Obj. D .

l l

l 1

s i

l 'QNUM

, 'HNUM i

' ANUM +

'QCHANGED. FALSE

ACHANGED FALSE !

'QDATE 1997/08/30 l;

'FAC 440

'RTYP GE BWR6 l

EXLEVEL R ;

I

EXMNR FACILITY

'QVAL 1.00 !

'SEC ,

'SUBSORT

KA 295037K301

' QUESTION

- A plant transient is in progress. The following indications are observed:

- A Reactor Scram signal has been received. :

4 - Pressure set at 940 psig.

No control rods have Inserted into the core.

2

- Reactor power is approximately 100%.

- The MSIVs are open; the main turbine is on line. .

- Recirculation pumps are in FAST.

Reactor water level is 196 inches.

Which ONE of the following describes the consequences of tripping the l reactor recirculation pumps? Assume the operators take no other actions,

a. A level transient may cause a turbine trip. Bypass valves t will open, and will control reactor pressure at pressure set.

I

b. A level transient may cause a turbine trip. Bypass valves will open, and reactor pressure will increase until an SRV opens.

l c. Tripping the recirculation pumps will result in an immediate power reduction, with a subsequent decrease in reactor '

pressure and level,

d. . Tripping the recirculation pumps will rapidly increase vessel water level, resulting in a large power transient and i

possible fuel damage..

ANSWER b.

' REFERENCE .

l l ,

i

)

i PEI Bases l LP: OT 3402-03, Obj. D 8

9 L

+- -

. --_r_

_, .. __,m.,, .,_,,r . - - - , , ,, , , ,-.y- --., r,rr,-,-,.-- , ...y-- _ r., m , , .w_y_-_,._,, .-

i

'ONUM ,

HNUM

' ANUM i

'QCHANGED FALSE

-*ACHANGED FALSE 6

'QDATE 1997/08/30

FAC 440 !

'RTYP- GE BWR6 l

EXLEVEL R .

EXMNR FACILITY

QVAL 1.00 -

'SEC- .

SUBSORT

KA 295037K303 _;

' QUESTION i An ATWS with a MSIV closure has occurred resulting in the following

- plant conditions:

- Reactor power is 15%.

- Reactor pressure is 890 psig. -

- Reactor level is stabilized at 100" with the MFP on the Startup Level Controller. .

- Rx mode switch is in SHUTDOWN

- Containment pressure is 0.5 psig.

- DW pressure is 2.1 psig.

- Suppression Pool temperature is 112*F.

- SP Level is 18.7 feet.

- RHR Status: NB/C have been terminated and prevented. ,

NB are lined up for outside-the shroud injection.

Why should all injection into the RPV be terminated and prevented with the exception of boron and CRD?

a. This terminates or reduces, as much as possible, any continued containment pressure increase.

b.- This ensures that if Emergency Depressurization is required later, the heat rejected to the containment will be minimized,

c. This ensures that an Emergency Depressurization will not result in_ exceeding the suppression chamber design temperature.

d. ECCS pumps which take suction on the Suppression Pool -

t P

'A I

could lose adequate NPSH and containment integisty could !

be lost. !

ANSWER ;

d. ,

REFERENCE f

- PEI Bases ;

LP: OT-3402-11, Obj. D !

r e

-sF i

i i

+

y-*-,----.my,w, v,-w,- c, y..we-7.w.r w- w i 3,-. r a--t-**'"e**+'r -tv ~ ~ w -1e~-w v"*-*--e+m'w-- *Te'~,Fe'+- -

t- v-'T **'-e- e-ev' -w*r'=-+-*' *-= = - ' '*-*-= ' " * ' - --w* - - - - * * - - -- - ' * * * *

=-. - .-

I l

ONUM '

'HNUM

' ANUM

'OCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

'SEC

'SUBSORT

KA 295006K207

' QUESTION The reactor was operating at 100% power with HPCS OOS. A trip of the feed system resulted in a level 3 scram. The RCIC system auto started but RPV water level decreased to 10" before the Motor Feed Pump was manually started and is being used to restore level. With RPV level under control the Unit Supervisor has directed you to reaintain reactor pressure 800# 900#. How are you going to maintain this pressure band?

a. Manually cycle Safety Rollef Valves in the order listed on H13-P601 to maintain this pressure band,

b. Lower the pressure set setpoint down to a maximum of 900# which will allow for automatic pressure control,

c. Manually throttle the output of the Bypass Valve Jack to use Bypass Valves to maintain this pressure band.

! d. Leave the Steam Bypass and Pressure Control system as-is and it will automatically control pressure in this band.

ANSWER a.

' REFERENCE i PElB13 LP: OT-3402-02, Obj. F

'ONUM

'HNUM

' ANUM

'QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30 !

'FAC 440 ;

'RTYP GE BWR6

EXLEVEL R ',

'EXMNR FACILITY

'QVAL 1.00

'SEC

'SUBSORT

'KA 295003A203

' QUESTION The plant is operating at 50% power with the electric plant in its normal operating lineup sad all divisional and non-divisional batteries being supplied by their normal chargers. Bus L11 suddenly experiences a bus lockout. What effect is there on both the divisional and non-divisional DC systems? :

a. No effects, the normal chargers will continue to supply their DC loads and batteries,

b. Both non-divisional DC systems will be supplied by their batteries, all divisional DC systems will be unaffected,

c. Tne non-divisional 18 DC system will switch to its alternate charger, the non-divisional l A DC system will be supplied by its battery, and the divisional DC systems will be unaffected,

d. The non divisional 1 A DC system will switch to its alternate charger, the non divisional 18 DC system will be supplied .

hy its battery, and the divisional DC systems w!!! be unaffected.

' ANSWER a.

' REFERENCE SDM: R42 & R10: ,

LP: OT-3036-R42, Obj. B ,

h

ONUM !

'HNUM

' ANUM

'QCHANGED FALSE

'ACHANGED FALSE :

'QDATE 1997/08/30 *

'FAC 440 l

'RTYP GE BWR6 ,

'EXLEVEL R l

EXMNR FACILITY

'QVAL 1.00 i

'SEC i

'SUBSORT

'KA 203024A204 l

'OUESTION !

Given the following plant conditions:

Rx Power 100 % -

RFPT A & B on the Master Level Controller.

Narrow Range Channel "A" is selected for input into C34.

A loss of bus DiB occurs. if no operator action was taken, what would be the impact on RPV level control? ,

i

a. RPV level will rapidly increase due to partial luss ci RPV !

level and feedwater flow signals. i

b. RPV level will increase then stabilize near the level setpoint as RFPT "B" speed increases,

c. RFPT B speed initially increases then decreases as level error overcomes the flow error signal. -!

d. Signal to LOW FLOW RX LEVEL CONTROL,1C34 R614, fails caus!. ,1N27-F175 to ramp closed if in AUTO.

ANSWER a.

' REFERENCE ONI R42 5, Sect.1.3 LP: OT-3036 R42, Obj. E

)

I i 'ONUM

'HNUM

' ANUM

'QCHANGED FALSE i

ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R -

EXMNR FACILITY .

'QVAL 1.00 ;

'SEC

SUBSORT

'KA 295016A107

' QUESTION Regarding the Remote Shutdown System (C61), all Division 1 Remote

- Shutdown Transfer Switches are in their NORMAL position. MSIV pilot solenoid "B" control switch is in the NORMAL position. Which ONE of the following describes the response of the inboard MSIVs if the operator takes MSIV pilot solenoid "A" control switch to the close position and the reason for this response?

a. Inboard MSIVs close because the "A" pilot solenolds for the MSIVs de energize.

b. Inboard MSIVs remain open because only the "A" pilot solenoids for the MSIVs de-energized.

c. Inboard MSIVs close because this switch energizes one pilot solenold for each MSIV with 125 VDC.

d. Inboard MSIVs remain open because control has not been transferred to the MSIV pilot solenoid control switches on the Remote Shutdown Panel.

ANSWER b.

REFERENCE ,

SDM-C61 LP: OT 3036 C61 Obj. E -

s

,r-- , ,. , . r a- , , , - - , , - - - ~ . - - - -+ --r -

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

'KA 295027K301

QUESTION PEl T23, Containment Temperature Control, requires the operator to Emergency Depressurize the RPV prior to exceeding 18SdegF in the Containment. This is performed to:

a. Provent Primary Containment failure due to high temperature,

b. Keep level indication from flashing due to reference leg heating.

c. To further minimize heat input into the containment from the reactor vessel,

d. To prevent a negative pressure in containment prior to containment spray initiation.

ANSWER c.

REFERENCE PELT 23 LP: OT-3402-07, Obj. C PEI Bases a

'ONUM

'HNUM

' ANUM

QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

'KA 295030A104

' QUESTION Which one of the following statements correctly describes a method that would initiate the Suppression Pool Makeup System assuming that Suppression Pool level is currently at 17.0 feet and decreasing and no LOCA signal is present?

a. Arm & depress the LPCS / LPCI "A" Manual Initiation pushbutton to insert a LOCA signal,

b. Place the SPMU "A" Logic switch in OFF, then arm &

depress the SPMU "A" Manual Initiation pushbutton.

c. Place the SPMU "A" Full Flow Test Perm. switch in TEST, then arm & depress the SPMU "A" Manual Initiation pushbutton.

d. Place the SPMU "A" Logic switch in OFF, open SPMU First Shutoff 1G43-F030A, then open SPMU Second Shutoff 1G43-F040A.

ANSWER c.

'R2FERENCE SDM: G43 LP: OT-3036-G43, Obj. D

t

'QNUM !

'HNUM

' ANUM

'OCHANGED FALSE

'ACHANGED FALSE

'QDiTE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL R

EXMNR FACILITY

QVAL 1.00

SEC I

'SUBSORT

'KA 295038K205

'OUESTION XXX ROs have to know entry conditions, is this and entry condition?

L A LOCA has occurred and the Emergency Coordinator has just declared the site to be in an Alert based on an abnormal radiologico: effluent per EPI A1, Which of the following statements is true regarding this situation?

a. The Emergency Coordinator should start site evacuation of all unnecessary personnel,

b. The Unit Supervisor must enter PEl D17, Radloactivity Release, if not already In it.

c. The Emergency Coordinator should make Protective Action Recommendations per EPI B8, to the State and County Authorities,

d. The Unit Supervisor should place both trains of Control Room HVAC in Emergency Recirc per ONI D17, High Rad Levels Within Plant.

' ANSWER b.

REFERENCE

.PElD17 LP: _ OT 3402-15, Obj. B

QNUM

HNUM

ANUM

QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP- GE-BWR6

EXLEVEL- B

EXMNR FACILITY

'QVAL 1.00

SEC

SUBSORT

'KA 294001K101

QUESTION .

The plant is in a startup and the RCIC systom is being restored to Standby Readiness. Reactor pressure is 100 psig. You are performing the warmup of the RCIC system and reach a step in sol-E51 to throttle

__open the E51 F076, Steam Warmup Valve, and you find the valve already FULL OPEN. You should:

a. proceed with the procedure, since the valve is already open and the intent of the steam line warmup is accomplished,

b. proceed with the procedure after notifying your Supervisor who will change the valve position to open on the veilfication checklist and initiate a non intent temporary change,

c. stop the procedure and obtain your Supervisor's permission to annotate the step FIC and continue the instruction.

d. stop the procedure and obtain your Supervisor's permission to appropriately position the valve and document action taken in the Unit log.

ANSWER c.

REFERENCE PAP-0201, 6.8,6 ?

LP: OT 3039-01, Obj. A '

o

QNUM-

HNUM

ANUM

QCHANGED -FALSE

'ACHANGED- FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSCRT

KA 294001K102

- QUESTION The 'B' Turbine Building Closed Cooling (TBCC) Pump is RED TAGGED OUT of service for maintenance, A loss of the 'A' TBCC pump has occurred and a plant operator reports that the 'B' pump looks like it is fully reassembled and no one is working on it. _The Maintenance Supervisor, who is the person in < :iarge or the tagout, has left the site for lunch SELECT from below th a correct statement regarding this situation,

a. The Unit Supervisor can authorize the tag removal,

b. The responsible system engineer can authorize the tag removal,

c. The maintenance supervisor's immediate supervisor can authorize the tag removal.

d. The lead mechanic on the crew can authorize the tag removal in the supervisor's absence.

ANSWER-c.

REFERENCE PAP-1401 LP: OT-3039-01, Obj.A 2

.- -- - - .=

'QNUM

'HNUM

ANUM-

'QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

'SEC

'SUBSORT

KA 294001K103

' QUESTION XXX - Change to make practical application of RP Um!!s.

John Smith, age 33, is a radiation worker at Perry, John's current calender quarter radiation exposure is 250 millirem. What are John's whole body exposure lirrits according to the Perry Administration Limits of PAP-0514 (External Radiation Exposure Control)?

a. 6000 millirem per calender quarter,

b. 300 millirem per calender quarter.

c. 1250 millirem per calender quarter, up to 3,000 millirem per calender quarter provided that the dose to the whole body, when added to the accumulated lifetime occupational exposure, does not exceed 5(N-18).

d. 500 millirem per calender quarter; 2,000 millirem per calender year, and lifetime whole body occupational radiation exposure does not exceed "N" rem, where "N" is

', our age in years at your last birthday.

ANSWER di

REFERENCE PAP-0514 L P: OT-3039-00, Obj. B ,

i

QNUM

'HNUM i

' ANUM

QCHANGED FALSE

ACHANGED FALSE ,

QDATE 1997/08/30 t

FAC 440

RTYP GE BWR6

EXLEVEL B !

EXMNR = FACILITY

'QVAL 1.00 !

SEC

'SUBSORT ,

KA 294001K104

QUESTION A drywell entry is required, Rx power is 7% MWt with the main l

- generator off line. Which of the below statements is correct with respect to waiving the ALARA review for the drywell entry?

a. An ALARA review is not required for a drywell entry under these plant conditions per PAP-0118, ALARA Program.

b. An A! ARA review is required for work activities under these plant conditions and may not be waived per PAP-0118, ALARA Program,

c. The Unit Supervisor may waive the ALARA review by declaring this an urgent situation per PAP-0512, Radiation Work Permit Program.

d. The Shift Supervisor may walve the ALARA review by declaring this a Priority 1 Emergency per PAP-0902, Work Request System.

ANSWER d.

REFERENCE ,

PAP-0118, Sect. 6.5.1 l

I l

l l

l

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

I

QNUM~ l

'HNUM i

' ANUM l

QCHANGED FALSE

'ACHANGED FALSE !

QDATE 1997/08/30 i

FAC' _440 _

l

RTYP GE BWR6 -l

EXLEVEL B !

EXMNR FACILITY

QVAL 1.00

SEC .

'SUBSORT l

KA- 294001K105 i

QUESTION :

You have been assigned to escort several visitors for a plant tour that [

- will include the control room. You should::

a. .

process through the turnstiles ahead of your visitor wlian !

~

^

entering and exiting the Protected Area.

4

b. ensure that no more than 10 individuals are escorted in the

- Protected Areas, and no more than 5 individuals in the vital areas. :

+

c. use your key card first when traveling through key card ;

e controlled doors, then hold the docr open while your visitors use the'r issued key cards.

d. keep escorted individuals undar continuous observation and report any indications of aberrant behavior following your visitor's exit from the plant.

.

ANSWER b.

REFERENCE PAP 0219, Sect.- 6.8.2 LP: GEN-1001 i

5 i

f

,v'r,-,.-h--,-3y,h. ., h , ---r,- ,y..v . , .,,m.y. , ,,,mm m, , . ,w 3., _

m .m y_ ,,s., _.yry., y.., , w,,y .,.,n,,---- ,w.-_---,r

i

ONUM

HNUM

ANUM

OCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

'QVAl 1.00

SEC ,_. .. ,_ . ., , . . . , , , , ,,

KA 294001K107

QUESTION PAP-0504, Electrical Operating Rules and Practices, requires that an evaluation and pre-job inspection be done whenever working on energized equipment. Many of the PEl-SPI's involve use of lifted leads and jumpers in energized panels, however an evaluation and pre-job inspection is not done by operators performing PEl-SPI's. How is this in compliance with PAP-05047

a. The inspection / evaluation was done once and is applicable for all PEl-SPI's.

b. The inspection / evaluation is not required due to the low voltage in the associated panels,

c. PEl-SPI's are done in what is considered a " plant emergency" and therefore the requiremJnt for an inspection / evaluation is waived.

d. This requirement is only applicable when it is not prudent to use safety equipment, however, safety equipment is used during the performance of PEl-SPI's.

ANSWER a.

REFERENCE PAP-0504 LP: OT-3039-00, Obj. B

\

ONUM

HNUM- ,

QCHANGED ANUM- FALSE-

ACHANGED FALSE

'_*QDATE- 1997/08/30

FAC 440 '

'RTYP GE-BWR6

EXLEVEL 5

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA 294001K116

QUESTION PAP-0110, Shift Staffing and Overtime, states that the Fire Brigade must be on site per PAP 1910, Fire Protection Program. Which of the following statements correctly states the requirements for the site Fire Brigade?

a. The Fire Brigade is a five person team consisting a Fire Brigade Leader, the Fire Engineer, and three Fire Brigade members,

b. If less than the minimum number of Fire Brigade members is on-site, the minimum number will be restored within four hours.

c. The on shift Shift Supervisor shall not be assigned in the site Fire Brigade, and the SO at-the-controls should not be assigned as the Fire Brigade Leader.

d. With the exception of the Fire Brigade Leader, who is a licensed operator, Fire Brigade members will have no duties during a fire except those directly related to manual fire fighting.

ANSWER c.

REFERENCE PAP-1910, Sect. 6.4 LP: OT-3039-00, Obj. B p !

l-L L

L :

l

ONUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

ODATE 1997/08/30

FAC- 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

'KA 294001A102

' QUESTION Which ONE of the following statements conforms to the recommended good operating practices listed in PAP-02017

a. Disconnect switches or breakers opened as a result of SOI or ELI performance must be DANGER tagged,

b. The Unit Supervisor should have a nuisance alarm disabled if the work to correct the problem canr.ot be completed in a reasonable time, defined as one hour.

c. To prevent damage of remotely operated throttle valves when closing them, the control switch should be released as soon as the CLOSED indication is received,

d. Whenever possible, place systems having an automatic actuation feature in a lineup that prevents an automatic actuation, prior to performing system troubleshooting or repair.

ANSWER d.

REFERENCE PAP-0201 LP: OT-3039-01, Obj. A l

s

QNUM

HNUM

ANUM

QCHANGED- FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXI.EVEL B

EXMNR FACILITY

QVAL 1.00

SEC :

SUBSORT . -

KA 294001A103

QUESTION

. XXX - Required for RO?

With the reactor in Mode 1, the on-coming Shift Supervisor discovers that only one Supervising Operator for his shift has shown up for work.

The SS immediately starts taking action to find a replacement. In the meantime, shift turnover is completed and the entire off going shift leaves for home. A replacement SO is found and reports to the control room i hour and 45 minutes later. Per PAP-0110, Shift Staffing and Overtime, choose which one of the following statements is correct concerning licensed operator shift manning,

a. All requirements were followed since the replacement for the Supervising Operator showed up within the allowable time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

b. All requirements were not followed because a Supervising Operator from the previous shift should have been held over until the replacement arrived.

c. All requirements were not followed because even after finding a replacement, the shift did not have the minimum required number of three Supervising Operators for Mode 1.

d. All requirements were followed since only one Supervising Operator is required in Mode 1 as long as both the Shift Supervisor and Unit Supervisor remain in the control room.

ANSWER b.

REFERENCE L

l l

t . . __ _ __ _ - __ _

PAP-0110 LP: OT-3039-01, Obj. A 1

l D &

i

QNUM- ;

HNUM'

.* ' ANUM '- - '

-*QCHANGED FALSE-

.ACHANGED- FALSE

QDATE 1997/08/30

FAC _ 440 5

RTYP. GE-BWR6

EXLEVEL B- .

EXMNR FACILITY

-'QVAL 1.00

SEC

SUBSORT

KA 294001A106

-

QUESTION SELECT the correct action to be taken when taking logs if the _ .

Containment Humidity instrument is out of service for preventative maintenance which will continue for several days,

a. Place an "X" in the data block and explain in the remarks section.

b. Record the out-of service instrument reading and explain in remarks section.

e

c. Obtain the Unit Supervisor's permission to use alternate instrumentation, asterisk in data block, explain in remarks section.

d. Walt until the preventative maintenance has been completed on the instrument and then record the instrument reading in the rounds.

ANSWER c.

,

REFERENCE OAP-1702LP: OT-3039-00, Obj. B 1

, , - - - . , , , . r ---, n. ,,n. -

- ,, e e

h

QNUM

HNUM

ANUM

QCHANGED FALSE

'ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT . *

KA 294001A108

' QUESTION Given the following Rx cooldown data:

TIME TEMPERATURE TIME TEMP _ERATURE 0800 520 1000 325 0815 490 1015 310 0830 460 1030 275 0845 445 1045 250 0900 430 1100 225 0915 400 1115 205 0930 370 0945 340 Choose the correct response from below with regard to the results of the cooldown,

a. The cooldown was acceptable and no limits were exceeded.

b. The cooldown rate was exceeded durin0 one one-hour period.

c. The cooldown rate was exceeded during two one-hour periods,

d. The cooldown rate was exceeded during three one-hour periods, d.

ANSWER d.

REFERENCE 1 1

Tech Spec. 3.4.11 LP: OT 3037-08, Obj. D g ,

4 .

I l'

l-

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA 294001A113

QUESTION The following plant conditions exist:

ECC pump 'A' is running, ECC pump 'B' is in STANDBY READINESS, ECC Area Cooling Fan 'A' is RED TAGGED OUT, ECC Area Cooling Fan 'B' is in STANDBY READINESS, Control Complex 'B' Chiller & Chill Water Pump are operating.

As the operator at-the-controls, which one of the following actions should you take?

a. Start ECC pump 'B' from the control room,

b. Have the Nuclear Island rounds taker start ECC Area Cooling Fan 'B'.

c. ECC pump "A" must be secured due to no Area Cooling available,

d. Have Maintenance personnel install temporary ventilation directed at ECC pump 'A'.

ANSWER b.

REFERENCE SDM: M28 LP: OT-3036-M28, Obj. C

QNUM-

HNUM

-ANUM'-

QCHANGED FALSE

?ACHANGED FALSE

'QDATE 1997/08/30

FAC. 1440

RTYP GE-BWR6

EXLEVEL- B-

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT "

KA 294001A116

= QUESTION There are certain responsibilities that can only be performed by the Emergency Coordinator when the Site Emergency Plan is being implemented. Which one of the following actions is allowed to be performed by someone other than the Emergency Coordinator?

a. Direct the notification of offsite agencies and organizations.

b. Determine the emergency classification including reclassification or termination.

c. Recommend protective actions for the general public to State and local County Officials,

d. Coordinate and direct the actions necessary to terminate or mitigate the effects of the emergency,

ANSWER d.

REFERENCE Emergency Plan Instruction EPI-A2, section 4.1 LP: EPL-0823

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'ODATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

SEC n- i- - +, *S RS0RT 4 ,, ,

OUESTION The plant is operating at 100% power with all of the "A" pumps operating when bus EH11 is suddenly de-energized. The Div.1 DG auto starts, but does not tie into bus EH11. Which ONE of the following responses would you expect to see in this situation?

a. CRD Mechanism High Temperature alarm on P601,

b. Rx Recirc pump A will lose all seal cooling flow,

c. RHR Pump A will auto start on a LOOP signal, and run on min. flow.

d. Div.1 DG will run continuously unloaded due to auto bypass of the DG trips on a LOOP signal.

ANSWER a.

REFERENCE SDM: C11(CRDH)

LP: OT-3036-C11 (CRDH), Obj. C

QNUM

HNUM .

ANUM-

'OCHANGED FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP- GE-BWR6

EXLEVEL- B 1

EXMNR FACILITY -

'QVAL 1.00 .

'SEC

SUBSORT

KA 201005K403

QUESTION In which one of the following conditions will the RC&lS allow control iod movement? -

a. Rods in Group 5 may each be withdrawn from 00 to 12 prior to selecting the next rod,

b. Groups 3 and 4 are fully withdrawn, and a control rod in Group i is selected. An attempt is made to fully withdraw the rod.

p c. -Groups 1 through 4 are fully withdrawn with the exception of one rod left at position 44. An attempt to withdraw a rod in Group 5 is made,

d. Groups 1 through 4 are fully withdraw. Groups 7 and 8 are withdrawn to position 12. Groups 5 and 6 are still inserted.

An attempt is made to withdraw a rod in Group 9.

ANSWER a.

REFERENCE-SDM

C11(RC&lS)

- LP: OT-3036-C11(RC&lS), Obj. G i

,-- r 7,, - - - , - - -

,y---

'ONUM:

HNUM 1

ANUM -

QCHANGED: FALSE ACHANGED -FALSE

'QDATE '

-1997/08/30

FAC -440-RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

SEC

SUBSORT

.g ...+ ~ * " * ~ ' ' " '

..202601G001

QUESTION XXX - Is this an RO task?

Due to a xenon transient in the core, it becomes necessary to increaso Rx power using recirc flow to maintain 1250 MWe In accordance with Operations Policy 2-9, Operational Activity Evaluation, how should this evolution be classified by the Shift Supervisor?

a. As risk significant,

b. As a risk contributor,

c. As an unplanned change in reactivity per ONI-C51.

d. As an Infrequently Performed Test / Evolution (IPTE).

ANSWER a.

REFERENCE Ops. Policy 2-9 OT-3039-00, Obj. B PlF 96-3400 N =r twi -

_____,__,_____.2__

QNUM-

HNUM

ANUM-

-*QCHANGED FALSE

'*ACHANGED- FALSE

QDATE 1997/08/30

FAC 440

RTYP GE.BWR6

EXLEVEL ~ B

EXMNR FACILITY

' OVAL 1.00

SEC

. . . . '.S BSORT. _. . , , ,. ,, , , , , , , . , , , ..

QUESTION

- Select from below the conditions that would result in the "CNTMT Spray B Start Signal Received" annunciator,

a. LPCI "A" automatic LOCA start signal sealed-in for 10 minutes, drywell pressure is 3.0 psig, and containment pressure is 9.0 psig,

b. LPCI "A" & "C" automatic LOCA start signal sealed-in for 15 minutes, drywell pressure is 2.5 psig, and containment pressure is 7.0 psig.

c. Cntml Spray "B" Manual Initiation Pushbutton armed and depressed for 45 seconds, drywell pressure is 1.5 psig, and containment pressure is 10 psig,

d. LPCI "B" and "C" automatic LOCA start signal sealed-in for 12 minutes, drywell pressure is 2.5 psig, and the Cntmt Spray "B" Manual Initiation Pushbutton is armed and depressed for 40 seconds.

ANSWER d.

REFERENCE SDM: E12 -.

LP: OT-3036 212, Obj. F

~

?QNUM-l

HNUM-

ANUM; .

QCHANGED: ? FALSE:.

ACHANGED FALSE!

'*QDATE .- 1997/08/30:

FAC- 440. ;

RTYP- GE-BWR6 -

~'

EXLEVEL LB'

EXMNR - FACILITY a

QVAL 1.00- ;

SEC '

SUBSORT "

t> :

.g - :211000A403- *

QUESTION

, - An operator reports that the;"A" Standby Liquid Control (SLC) squib

-valve continuity meter indicates 5 ma of current.- SELECT the action

- that should be taken.

, . a. Do nothing, since 5 ma is a normal indication.

b. Declare the squib valve inoperable since 5 ma indicates '

4 the squib valve has fired.

c. Declare the squib valve inoperable since 5 ma indicates current is too low and the squib valve may not fire. j

d. - Declare the squib valve inoperable since 5 ma indicates current is too high and the ignitor element may have decomposed.

ANSWER '

a.

REFERENCE SO Rounds -

+

LP: OT-3036-C41, Obj. E 1.

m v-e r .- .=- e w .,,.mv- * * - *,-..u - t-^ ,,- *,a- -- -.r- r .s em m g r- -- --,- 1<,n- e-+- - + v' ~+ vey

S l

QNUM' l

'HNUM- 1

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE: '1997/08/30

FAC 440 ;

RTYP GE BWR6

EXLEVEL 'B ;

EXMNR FACILITY -

'QVAL 1.00

SEC

SUBSORT ' " "'

'KA- 212000A108

QUESTION During power operation with the Mode Switch in PUN, an event has resulted in the following conditions:

RPV level decreases to Level 3.

RPV pressure peaked at 1113 psig.

Drywell pressure has reached 1.2 psig.

.Which ONE of the following lists the expected status of the scram, backup scram and ARI valve solenoids. No operator actions have been taken.

SCRAM BACKUP SCRAM ARI

a. deenergized deenergized deenergized b, deenergized energized deenergized

c. deenergized energized energized -

. d. energized deenergized deenergized

ANSWER c.

REFERENCE SDM: C71 LP: OT-3036, C71, Obj. D C22 OT-3036-C22, Obj. D i A

o

'QNUM '

HNUM-

? ANUM E*QCHANGED ~ FALSE

ACHANGED; ' FALSE ~

QDATE- 1997/08/30

FAC 440-

RTYP . GE-BWR6

EXLEVEL B

- *EXMNR ' FACILITY

QVAL. 1.00

SEC

- * -'a*St{BSORT g . 4-f120"00K:201

QUESTION

- A transient occurs and it becomes apparent that the RPS "B" MG Set has been lost. Which bus normally powers th::s equipment?

a. F1808

b. -F1C08

c. -F1C12

d. F1D12

ANSWER

- c.

REFERENCE SDM: C71 LP: OT-3036-C71, Obj. D i

L . -

l 7

QNUMl

, ?HNUM:- o

ANUM- .

a

*QCHANGED: FALSEE -

4 ACHANGEDi: - FALSE :

QDATE- 1997/08/30- !

?FAC 440- 1

RTYP GE BWR6L .

- *EXLEVEL B' '

EXMNR FACILITY :

. ?QVAL '- 1,00. :

SEC: -t

SUBSORTL , _

~

KA- - .

215005A104

? QUESTION - i

-- A reactor startup is in progress with the Rx Mode Switch in "STARTUP/ STANDBY", The following is the present status of the

- APRM's versus LPRM inputs, and indicated power: ,

~ APRM A B C .D E F G H D Level Inputs: :4 5 4 3- 4 4- 6- 6

. 3

-C Level Inputs: -4 3 3 6 2 4 4-B Level lnputs: 3 4- 3 4 4 4 6 4 i A Level lnputs: 3- -3 3 4 6 4 4 2 a r

Indicated Power:- 11 % 16% -12 % 11 % 12 % 10% 12% 10%

-' SELECT the correct RPS response to the above data:

a, No trips -

b,- Rod block only.-

c, . Half teram only

= d. Full scram

-

ANSWER

. - d.

-

REFERENCE?

SDM: ~ C51(PRM) ..

LP:; OT-3036-C51(PRM), Obj. D, I-y d

i L

--7 r -W re- 4y--'w-29-g- yv -y'yrw,-' y-3y% t -w g7^

w + ru rar r *' ei n- r w - - efP -t r w wey -

-$-v-f+1 w =-mav w raattwr9-w r'M

V

I

QNUM-

'HNUM

' ANUM- .

QCHANGED FALSE-

ACHANGED FALSE-

QDATE: 1997/08/30

FAC 440

RTYP- - GE-BWR6

EXLEVEL- B

- *EXMNR FACILITY '

QVAL 1.00

'SEC

'SUBSORT .. . . .. , , ,

KA 216000K507

QUESTION

'A discrepancy is noted between RPV level instruments where Wide Range Level"B" is reading lower than the others. .Which ONE of the following conditions could cause this channel to read lower than actual vessel level?

a. Drywell temperature locally at WR "B" increases,

b. Drywell temperature locally at WR "B" decreases,

c. WR "B" level transmitter equalizing valve leaks.

d. A steam leak occurs at the condensing pot for WR "B" level instrument.

' ANSWER b.

REFERENCE SDM: 821(NBPI)

LP: OT-3036-B21(INST), Obj. B 4

4

,r u , -,-

- *QNUM

HNUM 2

' ANUM

QCHANGED FALSE

ACHANGED: FALSE

' 'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B-

EXMNR FACILITY

QVAL 1.00

-*SEC

SUBSORT- .

KA 218000A403

QUESTION

- A plant transient occurred such that the Automatic Depressurization

- System (ADS) automatically initiated. RPV level is steady at 10", all rods are inserted, and RPV pressure is 25 psig. Which ONE of the following actions would result in ADS logic being reset?

a. With RPV level steady at 10", ADS logic cannot be reset,

b. Increase RPV water level to 20", then place the ADS Logic Inhibit switches in INHIBIT.

c. Placing the ADS Logic Inhibit switches in INHIBIT, then depressing the ADS Logic Seal-In Reset pushbuttons.

d. Depress the ADS Logic Seal-In Reset pushbuttons, then take each ADS Valve Control Switch to the OFF position.

ANSWER .

c.

REFERENCE SDM: B21C LP: OT-3036-B21C, Obj. E f

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT . . _. . . ., o

KA 239002A309

QUESTION in order to reduce the number of SRVs that reopen following a reactor isolation event, the Low-Low Set function was added to several SRVs.

Which ONE of the following statements correctly describe this function?

a. At 1103 psig, F051D opens, arming LLS and 1821-F051C opens. IF pressure increases to 1113 psig, then four LLS valves open and close at 946 psig. F051C cycles between 1103 and 936 psig and F051D cycles between 1033 psig and 926 psig.

b. At 1103 psig, F051D opens, arming LLS at 1103 psig, F051C opens; and at 1123 psig, the other four LLS valves open, and then close at 946 psig. F051C cycles between 1103 psig and 936 psig, and F051D cycles between 1033 psig and 926 psig.

c. At 1103 psig, F051D opens, arming LLS and opening F051C. If pressure. Increases to 1113 psig, the other four LLS valves open and cycle between 1113 psig and 946 psig. F051C cycles beNveen 1073 psig and 936 psig, and F051D cycles between 1033 psig and 926 psig.

d. At 1103 psig, F051D opens, arming LLS. If pressure increases to 1113 psig, four LLS valves will open, arming F051C, which will then open and cycle between 1077 psig and 936 psig. The four LLS valves will cycle between 1113 and 946 psig. F051D wi;I cycle between 1033 and 926 psig.

ANSWER c.

REFERENCE

_ _ _ - - - - - _ - - - - - - - - - - . _ _ - - - J

SDM: B21/N11 LP: OT-3036 B21/N11, Obj. E

o. g 4 , , . , . , .,. .. .. _ ,_ . -

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

C.XMNR FACILITY tOVAL 1.00

SEC

SUBSORT '

KA 241000K302

QUESTION Reactor power is approximately 40%, Recirc pumps have been shifted to fast speed, and a plant startup is in progress. Which of the following statements correctly describes the plant response following a failure downscale of the in service Main Steamline pressure regulator?

a. Rx pressure will increase causing bypass valves to open and Rx pressure will return to the pre-transient value.

b. A slight pressure transient may occur, however pressure will remain relatively constant throughout this event,

c. Pressure will increase, bypass valves will open in an attempt to reduce pressure, however the reactor will scram,

d. Pressure will increase to the point where both the scram and RRCS setpoints for Rx pressure will be reached.

ANSWER b.

REFERENCE SDM: N32/C85 LP: OT-3036-N32/C85, Obj. E

i I

- *QNUM:

'HNUM'

' ANUM = -4

QCHANGED -FALSE-

ACHANGED FALSE-

_ *QDATE 1997/08/30

FAC. 440

- *RTYP- GE BWR6 -

EXLEVEL' B

EXMNR FACILITY

QVAL 1.00-

.*SEC

SUBSORT-

KA- 259001A201

QUESTION Both RFPTs are running,' being controlled by the Master Level Controller. The' MFP control switch is in OFF. The Startup Level

- Controller Select Switch is selected to RFPT "A" What would be the 4

resultant pump combination if RFPT "B" tripped, with no operator actions being taken?

a. RFPT "A" would be running alone on the MLC.

b. RFPT "A" would be running alone on the SULC.

c. The MFP would start and be controlled on the MLC with RFPT "A".

d. The MFP would start and be controlled on the SULC with RFPT "A".

ANSWER a.

REFERENCE SDM: C34 LP: OT-3036-C34, Obj. C

-,e- -_. -9 ,

1*CNUM:

' *HNUM :

ANUM:

QCHANGED . FALSE:

ACHANGED . FALSE

QDATE- -

-1997/08/30

FAC L440

RTYP: GE-BWR6

EXLEVEL B

EXMNR: FACILITY :

-QVAL- 1.00-

SEC

'SUBSORT - ^ '

KA- 259002K409

'

QUESTION

.;The plant is operating at 70% power with RFPT_"B" and the MFP on the master level controller, RFPT "A" is danger tagged OOS.1 Which of the -

following statements correctly describes _the response of the feedwater

' level control system to the trip of RFPT "B"?.

'I The level demand signal is that signal corresponcing to the

- a-tapeset of the master level controller and will remain so continuously.

b. The level demand signal is that signal corresponding to the tapeset of the startup level controller and will remain so continuously,

c. For 10 seconds the level demand signal is that signal corresponding to the tapeset_of the master level controller, it then drops to a level demand signal of approximately 178".

d. For 10 seconds the level demand. signal is that signal corresponding.to the tapeset of the startup level controller, it then drops to a level demand signal of approximately 178".

ANSWER

b. .

REFERENCE .

. SDM: C34 -

. LP: OT-3036-C34..Obj. C .

m

~

QNUM

HNUM

ANUM

OCHANGED' FALSE

ACHANGED FALSE-- ,

QDATE 1997/08/30 .

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR~ FACILITY

'QVAL 1.00

SEC-

SUBSORT

KA 261000K401

-

QUESTION

- Assuming that the plant is operating at 100% Rx power with AEGTS Fan "A"_ running, which ONE of the following conditions would provide an automatic start of the "B" Annulus Exhaust Gas Treatment System?

a. Annulus pressuie sensed as being -0.50" H2 0.

b. Low flow sensed on the discharge of the "A" AEGTS fan.

c. De-energizing the Division 2 RHR LOCA Relay 1E12-K110B.

d. Arm and depress the High Pressure Core Spray Manual Initiation pushbutton.

ANSWER b.

REFERENCE SDM: M15-LP: OT-3036-M15, Obj. E P

- ~ . .

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

p c

QNUM

'HNUMi ~

. - ? ANUM ' -

QCHANGED_ FALSE.

. '*ACHANGED

FALSE-

QDATEL 1997/08/30; -

^ *FAC . :440

RTYP- - GE-BWR6 -

EXLEVEL B c *EXMNR - FACILITY

.' ' *QVAL ' . 1.00

SEC. -

SUBSORT:

.g 4 - 264000A209~

? QUESTION

.The following plant conditions exist: q i .Rx power- :100% :

Busses L11 & L12 are being powered from the Unit 1 Aux.

Transformer Bus L10 is being supplied by the Unit 1 Sta tup Transformer

.Div 1 & Div 3 DGs are in standby readiness

' Div 2 DG is in " LOCAL" running fully loaded for a WO retest -

Preferred Source Breakers for EH11, EH12, and EH13 are all closed.

With th_ese plant conditions, a bus L10 lockout occurs, a scram signal is generated due to the trip of both Rx Recirc pumps and level 2 is -

reached._ After auto initiating,-the HPCS pump motor catches fire and

. -causes a lockout to occur on bus EH-13. The lowest RPV level .

-achieved during this transient is 100". Which of the following statements correctly _ describes the steady-state conditions you would expect to see following this transient?-

'a. Div.1 DG is the only DG running AND supplying its respective bus.

L -b. .Only_Div.1 & 3 DGs are running, supplying their respective

-busses.

tch s ta n o 1 o LdC L

d. All three DGs received an auto start on a LOOP signal and are supplying their respective busses.

1* ANSWER l q

! ~

- - _ ~ n.. - . . .~ _ . , . .

, _- , s a- __ . .-= - . _ . . - . . - - . , . .

l

8. '

REFERENCE SDM: E22B & R43 LP: OT-3036-E22B, Obj. E OT-3036-R43, Obj. D 9

>< b. .. . . . ) .

?

km - - - - _ _ . _ _ _ . _ _ _ _ _ -____._____.___--.__&_________m_ .._. - _____ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ __ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ d

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

I I

I

'QNUM f

HNUM - !

ANUM i

'QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30 )

FAC 440 !

'RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00 :

'SEC ;

SUBSORT i

KA 209002A201

QUESTION i The plant is operating at 90% power and stable. The following alarms are suddenly _ received at H13 P680: ,

RPV Level 7 alarm !

Stm Flow / Feed Flow Mismatch alarm ;

P601 alarm ;

The plant stabilizes at approximately 92% power, with level at 196".

Choose from below the correct response for this transient, i

a. Secure the HPCS pump. ,

b. Reset the ADS Initiation logic, j

c. Manually trip the RCIC turbine. >

d. Take the SRV control switch to OFF. !

ANSWER a.

REFERENCE

-ONIEib1 LP: OT-3036 E22, Obj. K - ;

i z.. , . . . - - . . - . . . - - - , ,. . - _ - - -_- -_--.--.___..-..A

'ONUM !

HNUM

' ANUM !

'OCHANGED FALSE

'ACHANGED FALSE

QDATE 1997/08/30 ,

'FAC 440

'RTYP GE BWR6 '

'EXLEVEL B

'EXMNR FACILITY ,

'QVAL 1.00

'SEC

'SUBSORT

'KA 215004K402 .

' QUESTION Assume that the plant is in Mode 5 with the Rx Mode Switch in REFUEL, fuel movement is occurring in the containment, ano the shorting links are removed. Which of the following would result in a Rx ;

- screm?

a. SRM Channel A falls downscale,

b. SRM Channel B falls upscale.

c. SRM Channel C porlod falls to a reading of zero.

d. SRM Detector D is partially withdrawn.

ANSWER b,

' REFERENCE SDM: C51(SRM)

LP: OT 3036-C51(SRM), Obj. D l

I

'ONUM i

'HNUM-

ANUM -

'QCHANGED FALSE i t

ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440 -i

RTYP GE BWR6 ;

4

EXLEVEL B

'EXMNR FACILITY

- 'QVAL 1.00

SEC .

'SUBSORT :

'KA 202001G005

' QUESTION The reactor is at 72% power and 65% core flow. The mismatch I

between recirculation loops must not exceed:

a. - 2% of rated recirculation flow. !

- b. 5% of rated recirculation flow.

c. 10% of rated recirculation flow,

d. 15% of rated recirculation flow.

ANSWER c.

- ' REFERENCE T.S. 3.4.1 LP: OT-3036 B33, Obj. J 4

,, , . , . . -, . . _ . _ . . _ . _ . . . . , . . _ . _ , , . . .,,..,,._..._.,_,_..,_._,,...__m.._...,.m.-. .. _ . . .. _ _ _ , , ... , _ _ . _ _ , _ _ . . . . ;_ _...- , _ , , . , .

l

ONUM

'HNUM '

ANUM l'

OCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

OVAL 1.00 <

SEC

SUBSORT

KA 204000K108

'OUESTION The plant is operating at 100% power and the only equipment that is OOS is SLC pump "A". An ATWS occurs and you are directed by the Unit Supervisor to initiato SLC "B". Upon initiating SLC "B", which of the following statements correctly describe what you would expect to occur?

a. RWCU valves will only isolate if both SLC pumps are started, RWCU will continue to run.

b. G33 F001, RWCU Suction Containment Inboard Isolation Valve will close, RWCU pumps will trip.

c. G33 F004, RWCU Suction Containment Outboard Isolatloc Valve will close, RWCU pumps will trip.

d. G33-F001 RWCU Suction Containment Inboard Isolation Valve and G33 F004, RWCU Suction Containment Outboard Isolation Valve will closo, RWCU pumps will trip.

ANSWER b.

REFERENCE SDM: C41 LP: OT-3036-C41, Obj. D

i h

QNUML

'HNUM

' ANUM

QCHANGED- FALSE l

'ACHANGED FALSE

QDATE 1997/08/30 i

FAC 440 ,

'RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

'SUBSORT >

KA 205000G005

QUESTION The following plant conditions exist:

- The plant is in MODE 4.

- Reactor Recirculation (RR) Pump "A" is secured for maintenance.

- Reactor Recirculation (RR) Pump "B" is in operation.

- Residual Heat Removal (RHR) "A" is in standby readiness. ,

- Residual Heat Removal (RHR) "B" is operating in shutdown ,

cooling, i

- Reactor coolant temperature is 120degF.

RHR "B" pump is required to be shutdown for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for a scheduled motor operated valve stroking surveillance. RHR "B" will be returned to shutdown cooling following the surveillance. From the following, choose the action required in accordance with Perry Technical Specifications.

a. Demonstrate the operability of at least one alternate method of decay heat removal within one hour,

b. Place the "A" loop of RHR in the Shutdown Cooling mode prior to removing the "B" loop of RHR from service.

c. None, one RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of a Surveillance.

t

. d. Verify reactor coolant circulating by an alternate method in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and monitor reactor coolant temperature and pressure.

ANSWER

.c.

t

-I__ _ - A**

REFERENCE T.S. 3.4.10 LP: OT-3037-08, Obj. C i

l l

i

QNUM l

'HNUM

ANUM

QCHANGED FALSE

'ACHANGED- FALSE i

'QDATE 1997/08/30

'FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR

- FACILITY

QVAL 1.00

SEC ,

'SUBSORT

KA 219000G010

'OUESTION !

Which'ONE of the following statements is true regarding operation of Residual Heat Removal (RHR)in the Suppression Pool Cooling Mode?

a. When 1E12 F024A(B)is open, system flow through 1E12-F024A(B) shall be maintained between 2000 and 7300 gpm.

b. The RHR system shall be declared inoperable whenever it is in a Secondary Mode of operation EXCEPT when in Suppression Pool Cooling, i

c. RHR Loop *B" shall not be operated in Suppression Pool Cooling when SPCU is in operation through Suppression Pool Return Line Bypassing RHR "A".

d. A lose of pumping power during any operation with RHR A(B) TES'i VALVE TO SUPR. POOL,1E12 F024A(B),

open will cause volds to be drawn in the higher elevations of ine affected loop.

ANSWER d.

REFERENCE SOIE12 LP: OT-3036 E12, J L

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

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

I

QNUM 4

HNUM l

ANUM-

QCHANGED. FALSE

'ACHANGED FALSE I

ODATE. 1997/08/30 l

FAC 440 !

'RTYP GE BWR6 ;

EXLEVEL B

EXMNR FACILITY ;

QVAL 1.00 .;

SEC

SUBSORT ;

KA- 226001A407

' QUESTION 4 Plant Conditions:

Containment sprays have been running (RHR A and RHR B) for 15 minutes.

Containment pressure is 1.5 psig.

. Drywell pressure is 2.0 psig.

Reactor pressure is 50 psig.

Which of the following plant responses describes what you would expect to occur if an operator depresses the CNTMT SPRAY A(B) SEAL IN RESET pushbuttons?

a. Nothing, containment sprays continue.

b. Containment sprays secure AND the RHR pumps secure,

c. Containment sprays secure AND the LPCI Mode of RHR A and RHR B initiate,

d. The RHR pumps continue to run, supplying flow to the containment spray header AND the LPCI injection flowpath.

ANSWER d..

' REFERENCE SDM: E12 LP: . OT-3036 E12, Obj. E, F

ONUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR0

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

'SUBSORT

KA 202001A302

QUESTION Given the following plant conditions:

A lockout has occurred on LH-1 B and tripped LH 1-B.

Breaker H1101, Bus H11 Normal Supply Breaker, is opening.

Which ONE of the following sets of conditions must be satisfied in order for breaker H1102, Bus H11 Alternato Supply Breaker, to automatically closo?

a. No lockout on bus H11 and no lockout on the Auxiliary transformer.

b. No lockout on bus H11 and no lockout on intorbus Transformer LH 1 C.

c. The ATS must be in OFF and normal voltage on the line side of breaker H1102.

d. The ATS must be in AUTO, no lockout on bus H11 and normal voltage on the line side of breaker H1102.

ANSWER b.

REFERENCE SDM: R10 LP: OT-3036 R10, Obj. D

ONUM

'HNUM

ANUM

'QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP 'GE BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC-

'SUBSORT

KA 263000K201

QUESTION The normal power supply to the plant vital inverter is bus:

a. D1A

b. D1B

c. ED1A

d. ED1B

ANSWER a.

REFERENCE-SDM: R14/15

- LP: OT 3036-R14/15, Obj. B R42 OT-3036 R42, Obj. B J

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

i

QNUM-

HNUM !

ANUM

OCHANGED. FALSE -+

ACHANGED FALSE

QDATE 1997/08/30 t

FAC 440 !

RTYP GE BWR6 :

EXLEVEL B i

EXMNR FACILITY

QVAL - 1.00 ;

SEC

'SUBSORT

KA 271000K408 i

' QUESTION LWhich of the following signals will cause the Off Gas Discharge Valve (N64-F632) to isolate? -

a. Post treat rad monitor A is reading 0, post treat rad monitor ~

B is alarming Hi Hl.

b. Post treat rad monitor A is alarming HI Hi, post treat rad monitor B is alarming Hi Hl.

c. Post treat rad monitor A is downscale, post treat rad monitor B is alarming Hi Hi-Hl.

d. Post-treat rad monitor A is alarming Hi HI Hi, post treat rad 3 monitor B is alarming Hi Hi.

ANSWER c.-

REFERENCE

.SDM: N64 LP: OT 3036 N64, Obj. E i

p i

1 W,-- .g-m-p-waqp9 .gpqywahws. .-p.e. m.

99.g.-wsw 9 s 1 -W t *M* eve *-y F Wr g%+ 4-',-rw+ "yv- w T *ft* p r'w w g y -

p*- -m-T= e-. 4ct-'-l-# FN4-- e W -e'*Wevvee="-=-MM-P"-r*0+P&r- *t'~r< w'-*'1P'*-:v 8'*-*N"w'8'

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

?

'QNUM

HNUM

' ANUM

'OCHANGED FALSE

'ACHANGED FALSE f

'QDATE 1997/08/30 l

'FAC 440 :

'RTYP GE-8WR6 l i

EXLEVEL B

EXMNR FACILITY r

'QVAL 1.00 i

SEC

'SUBSORT

'KA 272000A101 .

' QUESTION While operating at 100% power, is it possible to verify the HIGH alarm i setpoint on the Turbine Building West Area Radiation Monitor without actuating the local red warning light? +

a. No, depressing the Alarm Trip / Test button will peg the ratemeter and actuate the local light, Yes, placing the Function Selector Switch in ALARM, and b.

depressing the High Alarm button will do this.

c. No, depressing the Fall / Check Source button will bring in the High Alarm and actuate the local light. ,

d. Yes, depressing the Horn Silence button while depressing i the High Alarm button will do this.

ANSWER

- b. !

^

' REFERENCE SDM: D21 LP: OT-3036 D21 Obj. B

[

l

i f

QNUM i

HNUM

' ANUM l

QCHANGED FALSE >

ACHANGED FALSE

QDATE 1997/08/30 =

FAC 440 '

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY .

QVAL 1.00 ;

SEC !

SUBSORT .

KA 290003K101

i

QUESTION Perry was operating at 100% power when a Control Room HVAC high :

radiation condition was sensed in the supply duct. SELECT the correct response of the system components listed below to this condition. +

Supply Return Supply Exhaust Return !

Fan Fan Damper Damper Damper C001 C002 F010 F130 F110 i

a. Run Stopped Open Open Closed i

b. Run Stopped Closed Closed Closed !

c. Stopped Stopped Closed Open Closed

d. Run Run Open Closed Open

' ANSWER ;

b.

REFERENCE SDM: M25/26 LP: OT-3036 M25/26, Obj. E j s

k

e

QNUM

'HNUM

' ANUM

'OCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

QVAL- 1.00

SEC-

SUBSORT

'KA 239001K110

QUESTION While doing a building inspection, a steam leak is discovered by one of the PPOs on feedwater heater #6A. Which of the below statements describes a possible s9urce of this steam?

a. Heater 6A steam drains to the 2A MSR Drain Tank.

b. Heater 6A steam drains to the #4 direct contact feedwater 1 heater,

c. High pressure turbine 4th stage extraction steam supply to heater 6A.

d. High pressure turbine 7th stb 0e extraction steam supply to heater 6A.

ANSWER c.

' REFERENCE SDM: N36 -

LP: OT-3036-N36/25/20 Obj. B l

l i

t

'ONUM l

'HNUM '

' ANUM

QCHANGED FALSE

'ACHANGED FALSE [

'QDATE 1997/08/30

FAC 440 .

'RTYP GE BWR6 '

EXLEVEL B

'EXMNR- FACILITY ;

'QVAL 1.00 i

'SEC

'SUBSORT

'KA 245000K502

' QUESTION A main turbine shutdown is in progress. Generator load was approximately 300 MwE when the RO at the controls noticed that main condenser vacuum was 5.1" HgA. Which of the below statements is true regarding these plant conditions?

a. Operation may continue as long as vacuum does not increase to >5.5" HgA.

b. Operation under these conditions is not allowed, perform a fast reactor shutdown.

c. Operation under these conditions is not allowed, tdp tho ,

main turbine imi.iediately,

d. Vacuum should be lowered to <5" HgA but main turbine operation may continue as long as generator load does not fall below 275 MwE.

ANSWER

. c,

' REFERENCE SOI N32 LP: OT-3036 N32/C85, Obj. K ONI N62 1

- . - - . , , . . - , , , - , ,. ,,,,--~.-.-...,-..,.,,.,_-n-,--~--. ,.,.a. , , - . - - , - -

'ONUM

'HNUM

ANUM

'OCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL B

'EXMNR FACILITY

'QVAL 1.00

SEC

SUBSORT

'KA 233000K408

' QUESTION SELECT the statement that describes the response of the Fuel Pool Cooling and Cleanup (G41) System as a DIRECT result of reactor water level decreasing to below Level 1.

a. The G41 containment isolation valves will isolate (G41 F100, F140, and F145).

b. The standby G41 pump wil! automatically start if the control switch is in AUTO.

c. The G41 filter domin isolation valve (G41 F360) will fall open and fully bypass the filter comin,

d. The G41 filter domins will isolate by closing G41 F280, F285, F290, and F295 (Filter domin isolation valves).

ANSWER d.

' REFERENCE SDM: G41 LP: OT-3036-G41, Obj. D i

l l

l

'ONUM

'HNUM

' ANUM

'QCHANGED FALSE

'ACHANGED FALSE

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR0

EXLEVEL B ,

'EXMNR FACILITY

'QVAL 1.00

'SEC

'SUBSORT

'KA 239003A211

' QUESTION SELECT the statement that describes the response of the inboard Main Steam Isolation Valve Leakage Control System (MSIV LCS) to reactor pressure increasing to 25 psig after the system has been operating for one hour. ,

a. The E32 F003 valve for each subsystem recolves an open signal returning the subsystems to the blood off mode,

b. The heaters for each subsystem trip, the Inboard blower trips, and the E32-F003 valve for each subsystem recolves an open signal.

c. The E32-F001, E32 F002, and E32 F003 valves for each subsystem receive close signals, the subsystem heaters trip, and the inboard blower trips.

d. The heaters for each subsystem trip and the E32 F001, E32-F002, and E32 F003 valves for each subsystem receive an open signal returning the subsystems to the bleed off mode.

' ANSWER c.

' REFERENCE SDM: E32 LP: OT-3036-E32, Obj. E

r i

QNUM i

'HNUM

' ANUM ;

t

'OCHANGED FAl.SE

'ACHANGED FALSE

'QDATE 1997/08/30 i

'FAC 440

'RTYP GE BWR6 .

EXLEVEL 8 l

EXMNR FACILITY

'QVAL 1.00

'SEC i

SUBSORT

'KA 290002G005

' QUESTION l IXXX Not required to be memorized. Ons hour tech spec.

A Safety Limit Violation has occurred. Which ONE of the following ;

describes a responsibility as defined in Tech. Specs regarding this:

a. Within oree hour, restore compilance with all SLs. ,

b. Within one hour, notify the NRC Operations Center.

c. Within one hour, insert all insertable control rods,

d. Within one hour, notify the plant manager and corporate executive responsible for plant safety.

' ANSWER b.

REFERENCE '

T.S. 2.2 LP: OT-3037 03, Obj. H

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

I i

'ONUM !

'HNUM i

' ANUM

'OCHANGED FALSE l

'ACHANGED FALSE l

'QDATE 1997/08/30 l

'FAC 440

'RTYP GE BWR6 i

EXLEVEL B

EXMNR FACILITY l

'QVAL 1.00 '

SEC

'SUBSORT :

KA 295005K201 :

' QUESTION Due to a level control problem on Molsture Separator Reheater 2A, a '

i fast unload of the main turbine was in progress using 10114, Fast Unload and Trip of Main Turbine. At 50% reactor power, a turbine trip. ;

signal was generated. Which of the following statements correctly describes the plant response to this transient.

a. A reactor scram will occur due to a pressure increase up to l' 1065 psig.

b. A reactor scram will occur due to the closure of turbine stop and control valves. -

~

c. A reactor scram will occur due to level 3 following the collapse of volds.

d. A reactor scram will occur due to high neutron flux following the collapse of volds, b.

' REFERENCE SDM: C71 LP: OT-3036 C71, Obj. F l l

i y ,,

...e - - - .

. _ - - - , ,..- , . , .,. _ . _ , ,.,v. ,,

QNUM

HNUM *

' ANUM ;

'QCHANGED FALSE

'ACHANGED FALSE

'QCATE 1997/08/30

FAC 440 ,

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY -

QVAL 1.00 ;

SEC i

SUBSORT

KA 295006A102

' QUESTION !

A Rx Scram has occurred with both Reactor Feed Pump Turbines (RFPTs) operating. RFPT A's flow controllor is in MANUAL and RFFT B's flow controller is in AUTOMATIC. The Startup Level Control Select ,

switch is selected to "MFP", RPV pressure is 825 psig and decreasing at approximately 2 psig per minute. Which ONE of the following describes the plant response to SLOWLY decreasing the speed on RFPT "A" down to 1100 rpm with the intent of removing it from service?

a. RPV level will be held fairly constant at approximately 178" by RFPT "B".

b. RPV level will decrease at, RFPT "A" is removed from service, unless the MFP is started,

c. RPV level will be held constant for approximately 10 minutes and then increase to Level 8, tripping both RFPTs.

d. RPV level will be held fairly constant at the tapeset level selected on the Master Level Controller by RFPT "B".

ANSWER c.

REFERENCE SDM: C34 LP: OT-3036-C34, Obj. D, G

'QNUM

'HNUM

' ANUM

'QCHANGED FALSE

ACHANGED FALSE !

ODATE 1997/08/30 i

'FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY -

'QVAL 1.00

SEC

'SUBSORT

'KA 295007A105

' QUESTION The reactor is operating at 85% power when the following Indications occur:

APRM A/E UPSCALE annunciator comes in ROD BLOCK APRM UPSCALE annunciator comes in RPV pressure increasing !

Mwe decreasing Which ONE of the following transients could result in the above?

a. Maximum combined flow limit fails high.

L. "A" pressure regulator fails open, then one minute later, the "B" pressure regulator slowly falls closed.

c. "A" pressure regulator falls closed, then one minute later, the "B" pressure regulator slowly fails open,

d. During the power increase from 65% to 85% Rx power, the turbine load Set setpoint was never increased.

' ANSWER b.

' REFERENCE ONI C85-1 LP: OT-3036-N32/C85, Obj. N

QNUM

'HNUM

ANUM

QCHANGED FALSE

'ACHANGED FALSE

'ODATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

'SUBSORT

'KA 295009K102

' QUESTION XXX - Remove the yes/no.

Following a Rx scram on RPV level 3, the P680 operator is directed by the Unit Supervisor to restore RPV water level between 185"-215" using the feed system. While restoring level, the P680 operator notes level at 140" and notices that Rx Recirc pump A is still running in fast speed.

Other than an important piece of equipment not operating correctly, is there any significance to this occurring?

a. No, tripping of at least one pump will add sufficient negative reactivity to overcome the positive reactivity that would have been added had the main turbine tripped at full power,

b. Yes, insuff;cient water level a.idlor subcooling of the water in the downcomer region may have caused cavitation to occur somewhere in the recirc "A" system,

c. No, even with level below the height required for natural circulation there is still enough mixing due to forced circulation such that significant thermal gradients would not form.

d. Yes, it can no longer be assumed that Rx Recirc pump "A" would have tripped while at power had the delta temperature between the steam dome and the bottom head drain exceeded 100degF.

ANSWER b.

REFERENCE o

SDM: 833 LP: OT-3036 833, Obj. E

QNUM- ,

HfJUM

' ANUM

(CHANGED FALSE i

/.0 HANGED FALSE

'QDATE 1997/08/30 [

FAC 440

'RTYP GE BWR6 .

t

EXLEVEL B .

EXMNR FACILITY :

QVAL 1.00 !

SEC l

SUBSORT &

KA 295025A107 !

QUESTION !

A main turbine trip occurred at 45% Rx power, but due to a malfunction of RPS, a Rx Scram failed to occur. Rx pressure increased to 1083 psig. SELECT from below tho ONE statement that correctly describes the Redundant Reactivity Control System response to this transient 25 deconds after reaching 1083 psig, assuming Rx power remaine constant .

M45%. !-

I

a. Alternate rod insertion will actuate.

b. The reactor recirculation pumps will trip off.

i

c. Standby Liquid Control will automatically initiate,

d. Feedwater flow is reduced to zero, unless the feedwater pump controllers are in manual, b.

REFERENCE SDM: C22 i LP: OT-3036-C22 Obj. D :

I l

L i

.-,-,,,,...vnr - - , . , . el ,,,nw--,v.nnr,.c-e, . ,-r- acv , - - , - - - . . . , , , , - .- nn . - ,.- . - ,,n-,~,

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

'ONUM t

'HNUM

ANUM !

'OCHANGED FALSE

'ACHANGED FALSE i

ODATE 1997/08/30 ,

'FAC 440 !

'RTYP GE BWR6 l

EXLEVEL B ,

'EXMNR FACILITY !

QVAL 1.00 l

SEC

SUBSORT- :

i

'KA 295r 14K101 '

' QUESTION A reactor startup was in progress. Power was approximately 2500 cps

- on all four source range monitors when a malfunction in RC&lS occurred, resulting in a continuous withdrawal of a four-rod gang, and causing a Rx period of 30 seconds. Which of the following statements correctly describes the implications of this event? :

a. This is an Indication of excess positive reactivity and the operator should insert a manual Rx scram.

b. Rx period will eventually return to between 60-150 seconds and therefore no operator action is necessary.

c. This is the design basis event behind the Rod Pattern Controller's banked position withdraw sequence (BPWS).

d. This event is more significant if power is initially at thn point of adding heat than if power is initially in tha source range.

ANSWER

a, '

' REFERENCE SDM: C11(RCIS)

- LP: OT-3039-01, Obj. A 101-1 & 2 PAP-0201

,m ~ .-y,-w ..v. w -ww,n.-, ,

.,.-.~.y.

~~-...c.y- . , _ . -.- r ,- . . . . - - , - _ . , , ,.,

QNUM

'HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE .

'QDATE 1997/08/30

'FAC 440

'RTYP GE BWR6

EXLEVEL B t

'EXMNR FACILITY

'QVAL 1.00

SEC i

SUBSORT

'KA- 295015A101

' QUESTION Given the following plant conditions:

- An ATWS has occurred.

- Rx power is steady at 23%. .

- The Main Turbine has tripped.

Several control rods are stuck out at various positions.

- The Unit Supervisor directs you to insert control rods using PEl-SPI, Section 1.

Why is it necessary to bypass the Low Power Setpoint?

a. To bypass the two notch limit, allowing continuous insertion of control rods,

b. To bypass the four notch limit, allowing continuous insertion of control rods,

c. To bypass the bank limits that are in effect because power is being sensed below the LPSP.

d, Thou0h not actually needed now, power will eventually decrease to LPSP during rod insertion, requiring the bypass.

ANSWER >

c.

REFERENCE

-SDM: C11(RCIS) .

LP: OT-3036-C11(RCIS), Obj. E, G

'ONUM

HNUM

' ANUM

QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL B

EXMNR FACILITY

OVAL 1.00

SEC

SUBSORT

'KA 295024A209

QUESTION XXX - Not an RO requirement. ROs don't drive the PEls.

Sometime after a small loss of coolant accident, the following stablo plant conditions are found to exist:

- Reactor Power 0%

- Reactor Level 180"

- Reactor Pressure 1000 psig

- Containment Pressure 4.5 psig

- Drywell Pressuro 4.3 psig

- Suppression Pool Lovel 21 ft.

- Suppression Pool Temport.ture 115'F.

Which one of the following is being exceeded?

a. Heat Capacity Limit

b. SRV Tailpipe Lovel Limit

c. Pressure Suppression Pressure

d. No PEl SPI curves are being exceeded.

ANSWER c.

REFERENCE PEl-T23 LP: OT-3402-09, Obj. C PElBases

a ., . . _,..m,_---_,mm_-_.m____ . . . . __ 4~.- =.-. - - . _ _ . ,2----m. - __ ._ - m m .i _w_.i. _ . _ , . a.a _c _ .

i t-

'ONUM

HNUM- ;

' ANUM. ;

'QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30 i

FAC 440

RTYP GE BWh6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

SEC i

SUBSORT t

KA 295025K203

QUESTION

- The Rx is operating at 100% power when a spurious Main Turbine trip

.results in a Px pressure excursion up to 1100 psig. What is the impact on the Feedwe6r Level Control System?

a. Operation of SULC in MANUAL is available after 30 seconds,

b. Operation of all controllers is automatically restored in 12.5 '

minutes.

c. Operation of RFP Controllers is available in MANUAL for the first 30 seconds,

d. The Master Level Controller will stay at its tapeset demand signal for 10 seconds.

ANSWER a.

REFERENCE i SDM: C34 LP: OT 3036-C34, Obj. D C22 OT-3036-C22, Obj. D

__ - - . , . . _ . _, , , . _ _ _ _ ._ ._ . _ , _ _ ~ _ _

QNUM-

HNUM

ANUM

QCHANGED: FALSE

ACHANGED FALSE-

'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL- B

EXMNP FACILITY

QVAL 1.00-

SEC

SUBSORT

- *KA 295031A108

QUESTION XXX - RO Task?-

PEl B13 RPV Control, has been entered on low reactor water level.

Current water level is +15 inches ai.a slowly decreasing, RPV pressure is 120 psig. Which of the following ALTERNATE INJECTION SYSTEM (S)/ SUBSYSTEM (S) can be used for RPV injection for the present plant conditions?

a. RHR Loop B Flood.

b. SPCU alternate injection.

c. Hotwell Dump Line alternate injection.

d. Condensate transfer alternate injection.

ANSWER d.

REFERENCE PEl-B13 LP: OT-3402-02, Obj. F s

, y ,

in SHUTDOWN, what additional actions . are to be taken in accordance with ONI-C61, Evacuation Of The Control Room, in the event a Control Room evacuation is required? a, trip the Main Turbine, initiate HPCS, and place Division 2 DG Control Transfer Switch in LOCAL.

b. verify all rods inserted, initiate RCIC, and place Division 1 DG Control Transfer Switch in LOCAL.

c. verify all rods inserted, initiate RCIC, and place Division 3 DG Control Transfer Switch in LOCAL.

d, verify all rods inserted, trip the Main Turbine, and place Division 3 DG Control Transfer Switch in LOCAL.

ANSWER d.

REFERENCE SDM: C61 LP:. OT-3036-C61 Obj. C ONI-C61

QNUM

HNUM

ANUM ~

QCHANGED FALSE

ACHANGED - FALSE

QDATE 1997/08/30

FAC 440

RTY' GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT-

KA- 295018K302

' QUESTION Which ONE of the following statements is correct concerning a complete - loss 'of Nuclear Closed Cooling water? The Reactor is shutdown in anticipatlon of...

a. the CRD pump tripping on a high lube oil temperature of 195degF.

b. the Drywell pressure increasing to 1.68 psig due to the loss of Drywell cooling.

c. RWCU Filter Demins. Isolating on - high NRHX Inlet temperature and the associated loss of Reactor chemistry.

d. tripping the Reactor Recirculation Pumps on high bearing temperature and the loss of instrument and Service Air compressors.

ANSWER -

d.

REFERENCE ONI-P43 LP: OT-3036-P43, Obj. H l

L e . h

QNUM

HNUM -

ANUM

QCHANGED FALSE

- *ACHANGED ~; FALSE

QDATE 1997/08/30

FAC 440:

RTYP GE-BWR6 -

EXLEVEL B

EXMNR F^CILITY ,

QVAL 1.00

SEC

-SUBSORT

KA 295019G010

QUESTION SELECT the statement that describes a condition requiring a fast reactor shutdown following a loss of instrument air while operating at 45% power, -

per ONI-FS2, Loss of Service and/or instrument Air.

a. The INST VOL NOT DRAINED annunciator is received,

b. The SCRAM VLV AIR HEADER PRESSURE LOW annunciator is received,

c. The outboard main steam line isolation valve (MSIV) B21-F028A drifts closed.

d. -The ROD DRIFT annunciator (for rod 22-11) and CRD MECHANISM TEMP HIGH annunciator (for rod 46-39) is received,

ANSWER 4

a.

REFERENCE ONI-PS2 LP: OT-3036-P51/52, Obj. G l'

i _ - -__ - .1_

ONUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

SEC

SUBSORT

KA 295022A201

QUESTION The plant is in Mode 2 performing a Rx Startup when the running CRDH pump trips. Which of the following describes the plant conditions that would require placing the Rx Mode Switch in SHUTDOWN immediately, per ONI-C11-1, Inability To Move Control Rods?

a. Rx Pressure is 500 psig.

Accumulator fault on rod 30-31 at 0" comes in. CRD Charging Water Pressure is 1570 psig.

b. Rx Pressure is 920 psig.

Accumulator faults on rod 30-31 at 0" and rod 20-27 at 24" has bee.: in for 20 minutes. CRD Charging Water Pressure is 1850 psig.

c. Rx Pressure is 900 psig.

Accumulator fault on rod 20-27 at 24". CRD Charging Water Pressure is 1500 psig,

d. Rx Pressure is 550 psig.

Accumulator fault on rod 20-27 at 24". CRD Charging Water Pressure is 1575 psig.

ANSWER d.

REFERENCE ONI-C11-1 LP: OT-3036-C11(CRDH), Obj. G

ONUM

HNUM-

ANUM

QCHANGED FALSE

ACHANGED FALSE ,

QDATE 1997/08/30

'FAC 440

RTYP GE-BWR6 -

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC -

SUBSORT

KA 295001A201

QUESTION Given the following initial plant conditions:

Current Reactor Power: 65% Current rod line: 105% Current total core flow: 60 Mlbm/hr Reactor Recirculation Flow Control in LOOP manual -The "A" Recirculation loop flow controller then_ falls, causing the "A" flow control valve to close, decreasing core flow to 41 Mlbm/hr. SELECT the appropriate IMMEDIATE action to be taken per ONI-C51, Unplanned . Change in Reactor Power or Reactivity, as a result of these plant conditions.

a. Insert Cram rods per FTI-802, Control Rod Movements, to exit the IMMEDIATE EXIT region.

- b. Immediately scram the reactor by arming and depressing the RPS MANUAL SCRAM CH A, B, C, and D pushbuttons,

c. Exit the MANUAL SCRAM REQUIRED Region of the Power-to-Flow map by increasing flow in the "B" Recirculation loop.

d. Establish a load line less than or equal to the 100% load line, then shutdown one Reactor Recirculation Pump per SOI-B33.

ANSWER b.

REFERENCE SDM: B33 LP: . .OT-3036-B33, Obj. I ONi-C51

-4

QNUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

'QVAL 1.00

SEC

SUBSORT

KA 295026G012

QUESTION The following plant conditions exist:

- A smal; break LOCA and ATWS have occurred - Reactor power is 8% and slowly decreasing - Both SLC pumps are running - 32 control rods failed to fully insert - RPV level / pressure is 90"/900 psig - Suppression pool temp. / level is 130degF /18.6 feet - Drywell temp. / pressure is 150degF / 0.3 psig Cntmt. temp. / pressure is 100degF / 0.2 psig What is the required operator action per the Plant Emergency Instructions? a, Restore and maintain Suppression Pool level between 17.8 and 18.5 feet.

b. Bypass the NCC lsolation using PEl-SPI 2.1 to restore NCC to the Drywell coolers.

c. Enter PEl-B13, RPV Controi (ATWS) at "X" to enter PEl-B13 Emergency Depressurization,

d. Manually control reactor pressure using SRVs as necessary to maintain RPV pressure below HCL.

ANSWER c.

REFERENCE PEl-T23 LP: OT-3402-06, Obj. C

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

QNUM .

HNUM.

' ANUM

QCHANGED FALSE

ACHANGED- ' FALSE '

QDATE -1997/08/30

'FAC' 440. a

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY -

QVAL: '1.00 +

SEC'

'SUBSORT -*KA 295029G012 ' QUESTION - Containment Flooding has been entered from RPV Flooding. Current plant conditions are as follows: Reactor level UNKNOWN Reactor pressure 0 psig - Suppression pool water level 62 feet - Containment pressure . 38 psig ' All Control Rods inserted- "00" The hotwell pumps are injecting 4 Mlbm/hr into the reactor. What actions are required based on these plant conditions?

a. Terminate injection to the RPV from the Condensate System.

. b. Exit Containment Flooding and go to RPV Level Control (START).

c. Decrease Condensate flow to lower Suppression Pool Water level to 61 feet,

d. Maintain Suppression. Pool level above 61 feet with Condensate System taking a suction external to the containment.

ANSWER a.

REFERENCE PEl-B13 LP: OT-3402-14, Obj. C PEl Bases .

q..

ONUM

- *HNUMt ' ANUM-

QCHANGED- FALSE

ACHANGED . FALSE--

- 'QDATE 1997/08/30.. 'FAC. 440

RTYP GE BWR6

EXLEVEL.- -B

EXMNR FACILITY ,

QVAL - 1.00

SEC-

SUBSORT-

KA 295033G012

' QUESTION XXX - RO knowledge??? The plant has experienced a LOCA with an ATWS. It has been determined that an unisolable steam leak has occurred in the RCIC pump-room. However, RCIC is the only system capable of injecting into the RPV. While fighting this casualty, the control room receives the AX 574' Area Radiation Monitor alarm on H13-P803. From this information, which of the following statements would be correct?

a. it can be assurned that a primary system is NOT discharging into the affected area,

b. RCIC pump room area must be verified at >4 rad /hr by survey to Emergency Depressurize.

c. RCIC area HVAC differential temperature must be >103degF to shutdown the RCIC pump,

d. It can be assumed that two area radiation levels are greater than their Max. Safe Operating Level.

ANSWER d.

REFERENCE PEI Bases page 344 -

LP: OT-3402-17, Obj. D

QNUM.

HNUM

ANUM-

?QCHANGED FALSE

ACHANGED FALSE-

'QDATE 1997/08/30

FAC- ._440 RTYP- GE-BWR6 :

EXLEVEL B

EXMNR FACILITY

QVAL 1,00

SEC

SUBSORT '

KA 295028K203

QUESTION Following a LOCA, the following parameters are noted:

RPV Pressure 100 psig Drywell Temperature 250degF, Containment Temperature 125degF. RPV LEVELS: L) 1 Narrow Range 180" 2)- Shutdown Range 190" '

3) Upset Range 195" Which of these level instruments may be used to determine level?

a. All of these instruments can be used,

b. None of these instruments can be used, c, Only the narrow range is providing valid level indication.

-d. Only the shutdown range is providing valid level indication.

ANSWER

- c.

REFERENCE PEl-B13 LP: . OT-3402-01, Obj.' D

.i i 4

QNUM

HNUM'

-

ANUM

QCHANGED- FALSE j

ACHANGED. FALSE

QDATE .-1997/08/30.-

?FAC 440

RTYP - GE-BWR6--

EXLEVEL B

EXMNR . FACILITY: .

QVAL. 1.00

SEC-

'SUBSORT.

KA 295021A104

QUESTION - ,

j XXX - Answer from within a procedure? The plant is shutdown in Mode 4 with RHR "B" in Shutdown Cooling and RHR "A" is OOS. RHR Pump "B" shaft seizes. Which ONE Of the - following is an approved alternate means of decay heat removal per ONI-E12-2, Loss of Decay Heat Removal?

a. Operate High Pressure Core Spray (HPCS) to circulate coolant between the suppression pool and the reactor vessel v!a the head vent,

b. If Rx coolant temperature is >190*F., align the RPV head

- vents by opening RX HEAD TO DW FIRST/SECOND VENT VALVES,1821-F002/F001. ,

c. Operate the condensate system to circulate water between the' main condenser and the reactor vessel to the hotwell pumps via the Main Steam isolation Valves (MSiVs).

.d. Operate Low Pressure Core Spray (LPCS) to circulate.the coolant between the suppression pool and the reactor vessel with the LPCS via two Gafety Relief Valves (SRVs). - c.

REFERENCE

~ ONI-E12 LP: .OT 3035-11, Obj. A-4

QNUM

HNUM

ANUM

QCHANGED PALSE

'ACHANGED FALSE 'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA 295023A103

QUESTION During refueling activities, a decrease in upper containment pool level requires suspension of core alterations after placing all irradiated fuel and core components in a safe condition. Which of the following is a SAFE CONDITION for a fuel bundle in the IFTS carriage?

a. Bundle properly seated in the IFTS carriage at the Bottom Out position with the upender vertical,

b. Bundle properly seated in the IFTS carriage at the Raise Lower Limit position with the upender inclined,

c. Bundle properly seated in the IFTS carriage at the Raise Lower Limit position with the upender vertical,

d. A bundle cannot be in a SAFE CONDITION in the IFTS carriage and must be placed in a pool storage location.

ANSWER b.

REFERENCE ONI-E12-2 LP: OT-3036-G41, Obj. E

t 'QNUM:

HNUM: .

ANUM i

-*QCHANGED FALSE-

ACHANGED FALSE *

'QDATE 1997/08/30

FAC- 440-

~*RTYP GE-BWR6

EXLEVEL B-

EXMNR FACILITY

- QVAL - 1.00 ,

SEC

SUBSORT-

KA 295032G012

' QUESTION The Maximum Safe Operating Condition Values for Area Temperatures , found in PEl-Nii, Containment Leakage Control, are based on: ,

a. Equipment necessary for safe shutdown of the plant will fail above this temperature.

b. Based on the high room temperature alarm setpoints for the surrounding containment areas.

c. The availability of alternate instrumentation use in the case of failed installed instrumentation,

d. Personnel access necessary for the safe operation of the plant will be precluded above this temperature.

ANSWER a.

REFERENCE PEI Bases page 341 LP: OT-3402-17, Obj. B PEl-N11

0NUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

'ODATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL B

EXMNR FACILIT"

QVAL 1,00

SEC

'SUBSORT

KA 295036G012

QlJESTION Due to a LOCA and a steam leak in the RCIC pump room, PEl-B13 RPV Control (Non-ATWS), and PEl Nii, Containment Leakage Control, have been entered. The RCIC pump room is inaccessible and steam makes observation of the room impossible. However, the following indications are available to the operators:

RCIC Pump Room Area Temperature is 295degF The RCIC Pump Room Sump hl level alarm ha:: been received RWCU Pump Room Area Temperature is 265degF, Which ONE of the following conditions would require the operators to enter PEl-813, RPV Control (Non-ATWS) at "Z" with the intentions of performing Emergency Depressurization?

a. RCIC Area HVAC Differential Temperature alarming and reading S5degF

b. Aux. Building Ventilation Exhaust Gas radiation monitor reading 34,050 cpm

c. Aux. Building 574' elevation Hallway Area Radiation monitor reading 4,200 mR/hr.

d. Aux. Building 574' elevation Hallway water level observed at 20" above the floor.

ANSWER d.

REFERENCE PEl-N11 LP:-3402-17, Obj. D

ONUM

HNUM

ANUM

QCHANGED FALSE .,

~

ACHANGED FALSE

ODATE. 1997/08/30

FAC- 440

RTYP- - GE-BWR6 '

EXLEVEL S '

EXMNR FACILITY

QVAL 1.00

SEC

-- SUBSORT

KA 294001K102

. OUESTION As the Unit Supervisor, you have been brought the following examples of tagouts that require your approval, Select the example below that violates the tagging rules defined in the PAP-1401, Safety Tagging. .

a. Tagout #1 has red danger tags and yellow grounding tags being hung on the same component.

b. Tagou.#2 o has a red danger tag attached to a solenold valve that is to be removed, bench-tested, then reinstalled !nto the system,

c. Tagout #3 has a single danger tag and a portable ground isolating a component from its 500 volt AC power supply because only one break is available, d, . Tagout #4 has a danger tag being used to provide separation between Unit 1 and Unit 2, and requires a 10CFR50.59 Applicability Check prior to your authorization.

ANSWER b,

REFERENCE

~ PAP-1401, Section 6.0.1 LP: OT-3039-01, Obj. A s

Q'NUM

-*HNUM

ANUM:

-QCHANGED FALSE- :

ACHANGED- FALSE

QDATE 1997/08/30

FAC 440 ,

RTYP GE.BWR6

EXLEVEL S:

-EXMNR FACILITY

QVAL 1.00

SEC ,

_SUBSORT ' KA 294001K103

QUESTION

' Assume that the plant is in a Site Area Emergency and you are the Shift , Supervisor acting as the Emergency Coordinator. It becomes necessary to send an individual into an area that will exceed his 10CFR20 dose limits -in order to save another individual's life. Per PAP-0514, Perry Plant Personnel Radiction Dose Control Program, the dose should be limited to the following when lower doses are not practical:

a. 5 rem TEDE

b. 10 rem TEDE c.- 15 rem TEDE _ .

d .- 25 rem TEDE

ANSWER-d.

REFERENCE PAP-0514, Section 6.4,1.c LP: OT-3039-00, Obj. A r

p .r.., _ .- , - ,- .. .,,. - -.

QNUM:

HNUM- '

' ' ANUM

QCHANGED FALSE

ACHANGED . FALSE

'ODATE: 1997/08/30

FAC : 440

RTYP- GE-BWR6

EXLEVEL. -S

EXMNR - FACILITY

QVAL 1.00

SEC

SUBSORT

'KA 294001K114

QUESTION XXX - MEMORY?

You are required to enter the Main Condenser to provide a final approval inspection for cleanliness. Before entering, you are g!ven the following atmospheric readings just taken on the condenser. Which of these is considered safe per PAP-0516, Confined Space Entry?

a. 20% oxygca content and 91dege temperatur6

b. 30% oxygen content and 8cdegF temperature

c. 25% oxygen content and 55degF temperature

d. 23% oxygen content and 31degF temperature

ANSWER a.

REFERENCE PAP-0516, section 5.6 LP: OT-3039 00, Obj. A m

QNUM

'HNUM-

? ANUM

QCHANGED: ' FALSE.

'*ACHANGED: ' FALSE ?QDATE - 1997/08/30- '

FAC - 440 '

RTYP GE-BWR6

EXLEVEL. S -~

~ *EXMNR - FACILITY

QVAL: 1.00

'SEC

SUBSORT. -

=*KA 294001A115 -'QUESTION

Upon ~ accessing an ERIS_ screen in the control room, you notice a white

asterisk in the value box for a parameter. Which ONE of the following.

statements correctly describes how this shou ld be interpreted? <

a. -The data that goes in that box has not been validated

b. The parameter that normally provides input to that box has been lost

c. The data is good but there is not enough room in the box to display the data

d. The data that goes in that box is normally compensated data but is not currently being compensated

ANSWER c.

REFERENCE

- SDM: C95 LP: OT-3036-C95, Obj. C C ( ': l L , . . + , . . - , . . - , . - . .,,.-~,, , - , , ,, .-,.,..,-_,,,,m.- . . , ..y 4

QNUM

HNUM

? ANUM

QCHANGED FALSE

ACHANGED FALSE

QDATE- 1997/08/30

FAC 440-

RTYP GE-BWR6

EXLEVEL S

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA- 209001K404

QUESTION The Reactor Rccirculation pumps have just been shifted to fast speed.

Immediately after the pump shift, the "LPCS OUT OF SERVICE" alarm annunciates, and upon investigation, you determine that this alarm is due to a LPCS line break. What caused this alarm to come in?

a. Excessive differential pressure between R! R "A" LPCI nozzle and the LPCS Spray Sparger.

b. Excessive differential pressure between RHR "B" LPCI nozzle and the LPCS Spray Sparger,

c. Excessive differential pressure between the vessel downcomer region and the LPCS Spray Sparger,

d. Excessive differential pressure between the LPCS Spray Sparger and the above core plate pressure tap.

ANSWER a.

REFERENCE

- SDM: E21 LP: OT-3036-E21, Obj. J } .QNUM

HNUM-

? ANUM - !*QCHANGED FALSE

ACHANGED. FALSE

'QDATE 1937/08/30

FAC- 440:

-*RTYP GE-BWR6

EXLEVEL S

EXMNR FACILITY ,

QVAL 1.00-

SEC

SUBSORT

KA 211000G005

QUESTION .

During a plant startup at 5% reactor power, the on-shift Chemistry Technican reports thef ollowi ng resu iht regard s to the Standby Liquid l ts w

Control Storage Tank per SVI-C41-T1026:

NET TANK VOLUME - 4475 gallons % WElGHT SOLUTION CONCENTRATION - 13% What ACTION (S) are you required to take with regards to the SLC System?

a. No action is required; the SLC system is OPERABLE.

b. Restore the SLC System to OPERABLE status within 7 days.

c. Have the plant shutdown to at least MODE 3 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

d. _ Restore at least one subsystem to OPERABLE status within

~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least MODE 3 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ANSWER

.d.

REFERENCE.

T.S.3.1,7-LP: OT-3037-02, Obj. E 7 ,v . - . , . ,e --- - - - --- - - - -

QNUM

PNUM

ANUM

OCHANGED FALSE

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL S

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT '

KA 223001K607

QUESTION The plant has experienced a LOCA. Per PEl-M51/56, Hydrogen Control, the H, Analyzers and the H algniters have been started. An electrical transient u:uses power to be lost to Div.1 and Div. 2 Ign!ters. Unaware that the ignite:s have de-energized, the operators restore ...swer to the bt ~.ses approx!mately two hours after it was lost. What effect, if any, could thit Nve on the Containment and/or Drywe!!?

a. Restoring the igniter power supply will have no impact on the containment because the igniters will not start unless restarted by the operators,

b. If hydrogen concentration has continued to increase while power was lost, restoring the Igniter power supply could result in excessive Cntmt. pressure threatening Cntmt, integrity.

c. If hydrogen concentration has continued to increase while power was lost, restoring the Igniter power supply will result in localized combustion resulting in little impact on Cntmt.

pressure,

d. Restoring the igniter powcr supply will have no impact on the containment because it is expected that during a LOCA the containment will be in a steam inert condition.

ANSWER a.

REFERENCE SDM:M56 LP OT-3036-M56, Obj. C OT-3402-10, Obj. C

QNUM

HNUM-

ANUM

QCHANGED FALSE

ACHANGED. FALSE

QDATE. 1997/08/30

- *FAC - '440

RTYP GE BWR6

EXLEVEL- S-

' *EXMNR - FACILITY '

QVAL- 1.00

SEC

SUBSORT

- *KA 223002K607

QUESTION

' Given the following initial plant conditions:

RHR loop "B" is in the Shutdown Cooling (SDC) Mode . Reactor coolant temperature is 300degF. RPV pressure is 65 psig. SELECT the statement that describes the effect on the Shutdown Cooling (SDC) Suction isolation inboard and Outboard Valves (1E12-F009 and 1E12-F008) if 4.16 KV Bus EH12 de-energizes due to a bus lockout

- condition,

b. 1E12 F008 and 1E12-F009 will both isolate when pressure reaches 135 psig.

a. 1E12-F008 and 1E12-F009 will not isolate at 135 psig due to a loss of power.

d. 1E12-F008 will isolate when pressure reaches 135 psig, 1E12-F009 will not isolate due to a loss of power.

c. 1E12-F009 will isolate when pressure reaches 135 psig, ,

1E12 F008 will not isolate due to a loss of power. d.

REFERENCE

SDM:' E12-

- LP: -OT-3036-B21(INST), Obj. F = B21(NS4)-- OT-3036-E12 , Obj. F 4 f -s, .- 4 , - ~

QNUM

HNUM

ANUM

QCHANGED- FALSE

ACHANGED-- FALSE-

QDATE 1997/08/30

FAC -440

kTYP GE-BWR6

EXLEVEL S-

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

KA -- 217000G005

QUESTION The plant is at 100% power. Due to a problem with the Reactor Core Isolation Cooling System, the Unit Supervisor declares the RCIC System Inoperable at 0930 on June 1. Because the High Pressure Core Spray System was also Inoperable, the Unit Supervisor also entered Action 3.0.3

- at 0930. A Main Condenser vacuum problem occurred, causing the operators to rapidly unload the turbine at 1000 and eventually place the Reactor mode switch in Startup at 1040. Based on these plant conditions, at the latest, (date and time), when must the plant be in Hot Shutdown (assume neither RCIC nor HPCS can be repaired)?

a. June 1,1640.

b. June 1,2130.

c. June 1, 2230.

d. June 2,2230.

ANSWER c.

REFERENCE T.S.3.0.3 LP: OT-3037-01, Obj. F -

_i.

ONUM

HNUM-:

ANUM

QCHANGED FALSE

ACHANGED FALSE

-QDATE 1997/08/30

FAC .440

RTYP1 GE-EV/R6 s

EXLEVEL- S

EXMNR FACILITY

QVAL' 1.00

SEC -

SUBSORT

KA- '215003K103 ,

'OUESTION RACS channel 1 is selected for display fRid B which is assigned to RACS -channel 2 fails upscale. No other IRMs are alarming. Which one of the following correctly describes the indications the operator will see? .,

a. No rod block present, Withdraw Block indicator lighted.

b. No rod block present, Withdraw Block indicator unlighted.

c. Rod block present, Withdraw Block indicator lighted.

d. Rod block present, Withdraw Block indicator unlighted.

ANSWER' d.

REFERENCE SDM: C11(RCIS)

~ LP: OT-3036-C11(RCIS), Obj. D , - - - e -ONUM 'HNUM ' ANUM 'OCHANGED FALSE 'ACHANGED FALSE 1 'ODATE 1997/08/30 'FAC 440 'RTYP GE BWR0

EXLEVEL S

'EXMN'1 FACILITY 'QVAL 1.00 'SEC 'SUBSORT ' 'KA 2SG000A401

QUESTION While operating at 100% power you receive the Hot Surge Tank Level Hi annunciator on 1H13 P000. Upon silencing the annunciator, you observe Hot Surge Tank Level go offscale high on recorder 1N21 R323. HOT SURGE LEVEL & CNDS TO HTR 4 FLOW.

Assuming that you are unchte to stop Condensate flow to the Hot Surgo Tank, which of the following statements correctly docribes the correct action to take per SOI N217

a. Manually isolate Foodwater Heater #4 prior to its auto-isolating on High HST Level.

b. Manually tr'p all Hotwell and Condensate Booster Pumps prior to 10 psig HST pressure.

c. Manually trip all Feedwater Booster Pumps and Rx Food Pumps prior to 120 psig HST pressure.

d. Decrease condonsate flow to th HST by securing one of the Condensate Booster Pumps and manually throttling 1N21 F230.

' ANSWER b. ' REFERENCE SOI-N21. Sect. 2.0.2 LP: OT 3030 N21, Obj. G . . - - . - .. . - = - _ - _ . . - . - .-. - . - .. _ . - , 'ONUM 'HNUM ' ANUM 'OCHANGED FALSE 'ACHANGED FALSE 'QDATE 1997/08/30 'FAC 440 l 'RTYP GE BWR6 !

EXLEVEL S l

'EXMNR FACILITY l 'QVAL 1.00 l 'SEC

SUBSORT

'KA 295003K106 ' QUESTION XXX Should distractor d. be 1 AND 27 The plant is in a condition of Loss of Offsite Power (LOOP). Which ONE of the following correctly describes a condition which would cause the plant to degrade into a Station Blackout (SBO)?

a. All remaining Divisional Diesel Generators fall, causing a de-energization of their respective buses, o

b. Division 3 Diesel Generator falls, resulting in a de-energization of Bus EH13.

I

c. Only Div.1 Diesel Generator remains running, resulting in only Bus EH11 energized,

d. The remaining Div.1 or 2 Diesel Generator falls, resulting in ,

only bus EH13 energized. ' ANSWER

d. l

REFERENCE ONI R10 LP: OT. 036 R10, Obj. J 1

' *ONUM- t 'HNUM [ ' ANUM 'QCHANGED FALSE- ! 'ACHANGEO FALSE l 'QDATE 1997/08/30 , 'FAC 440 'RTYP GE BWR6 , 'EXLEVEL S

EXMNR FACILITY

'QVAL 1.00 'SEC i

SUBSORT

'KA 295006G010 <

QUESTION A scram has occurred; however, during the transient, it is discovered that

, station loads nave failed to shift. Which ONE of the following statements correctly describes the actions you are required to take per ONI-C71-1, Rx ; - Scram?

a. Close START-UP SUPPLY BRKRS, L1006 and L1009, enter ,

ONI R22 2, Loss of Non Essential 13.8KV/4.16 KV bus.

b. Open NORMAL SUPPLY BRKRS, L1102 and L1202, enter ONI R22 2, Loss of Non Essential 13.8KV/4.16 KV bus,

c. Verify AUXILIARY TRANSFER SWITCH is in the AUTO position, then verify the START UP SUPPLY BRKRS close and NORMAL SUPPLY BRKRS open.

d. Restore power to at least one 13.8 KV bus by opening its associated NORMAL SUPPLY BRKR and closing its associated START UP SUPPLY BRKR.

' ANSWER

b. ,

' REFERENCE ONI C71 1 LP: OT 3036-C71, Obj. L m m- a 9w a- e y-- --wmumwr - p t M u- mp- g ,ywa w yeging'ww sv5 w ,t n- 3 m a-se--p. a y f- e r p-'M M---9 +-w3Mg- -e-=w=t ++-=9- [ 'QNUM ! 'HNUM ! ' ANUM 'OCHANGED FALSE 'ACHANGED FALSE

ODATE 1997/08/30

'FAC 440 'RTYP GE BWR6

EXLEVEL S

'EXMNR FACILITY 'QVAL 1.00 'SEC 'SUBSORT 'KA 295023G010 ' QUESTION During refueling operations, a fuel assembly was dropped while suspended in the Upper containment pool. The fuel handling crew reported that a large quantity of bubbles were observed coming to the water surface but no area high radiation alarms were present. What are the required immediate operator actions per ONI J112, Fue! Bundle Rupture During Fuel Handling?

a. Suspend ali Core Alterations and movement of fuel, and t evacuate the Containment upper pool area,

b. Suspend all Core Alterations and movement of fuel, and evacuate the containment if a high radiation alarm occurs.

c. Suspend all Core Alterations and movement of fael, sound the containment evacuation alarm, and start containment purge,

d. Suspend all Core Alterations and movement of fuel, evacuate the containment of all unnecessary personnel, and increase fuel pool cooling.

ANSWER a.

REFERENCE ONI-J112 LP: OT-3036-J11, Obj. J

- ,_ . - - - . _ _ - _ -. - . -_ -. - - . - ~ i i 't f 'ONUM 'HNUM i ' ANUM i 'QCHANGED FALSE ! 'ACHANGED FALSE :

QDATE 1997/08/30 i

'FAC 440 - *RTYP GE BWR8 ; 'EXLEVEL S i 'EXMNR FACILITY t 'QVAL 1,00 l 'SEC 'SUBSORT I

KA 295017G002

' QUESTION 1 - XXX . Check for 2 correct answers (b.) An unisolable steam line break has occurred in the Steam Tunnel and has resulted in a potential off site release. The Emorgency Coordinator has declared a Site Area Emergency. Which ONE of the below statements describes a correct action required to be taken for this situation? j

a. Within 15 minutes, notify the VP Nuclear.

b. Within 15 minutes, notify the State of Ohio and provide -

protective action recommendations,

c. Within one hour, notify the NRC d, Within one hour, notify the Ashtabula County off clals

ANSWER c.

REFERENCE EPI-A2 r LP: EPL-0823 L

i w- g----r ,- ,, y ,yw.-,- ,-- = - , , _ . . _ , ,, , m_c.,_., .,,,_ye,.,-_.,-.,,.e r.__m,m-m._ mm, . , , ,_ , , , . . , . - ,w_c_-. 'ONUM 'HNUM ' ANUM 'OCHANGED FALSE 'ACHANGED FALSE 'ODATE 1997/08/30 'FAC 440 'RTYP GE BWR6 'EXLEVEL S 'EXMNR FACILITY ' OVAL 1.00 'SEC 'SUBSORT 'KA 295031K304 'OUESTION With the reactor shutouwn, which of the following sets of plant conditions ensures the core is adequately cooled by STEAM COOLillG7

a. Reactor pressure is 125 psig, reactor level is 15 Inches, and the HPCS Pump is running and injecting,

b. Reactor pressure is 135 psig and reactor level is +10.5 inches and the Condensato System is injecting into the reactor,

c. Reactor pressure is 850 psig, reactor level is +10 inches, and no injection subsystems or attornato injection subsystems are running,

d. Reactor pressure is 450 pelg, reactor level is 25 inches, and no injection subsystems or altomato injection subsystems are running.

' ANSWER d. ' REFERENCE PElB13 LP: OT-3402-02, Obj. F QNUM 'HNUM

ANUM i

QCHANGED FALSE

'ACHANGED FALSE 'QDATE 1997/08/30

FAC- 440

RTYP GE BWR6

EXLEVEL S

EXMNR FACILITY

QVAL - 1.00

SEC l

SUBSORT

KA 295027K303

QUESTION

A LOCA has occurred and PEl T23 Containment Temperature Control, directs the operator to enter PEl B13, RPV Control (Non ATWS), if Containment Temperature cannot be maintained <185degF. Which of the below stataments correctly describes the reason for this action?

a. This will minimize containment heating and provide a margin to the containment design pressure.

b. This assures that, if possible, the reactor is scrammed before emergency depressurization is initiated,

c. Further release of energy from the RPV to the containment is minimized by rapidly depressurizing the RPV.

I

d. This will terminate containment temperature increase and thereby maintain equipment operability for as long as possible.

ANSWER b.

REFERENCE PEI Bases, pg. 256 LP: . OT-3402 07, Obj. C

. - _ ~ , . . - .. : - . . _. - .a.-.- . . . - : t f

QNUM !

HNUM l

' ANUM . 'QCHANGED FALSE l ACHANGED FALSE ; 'QDATE 1997/08/30 : 'FAC 440

RTYP GE BWR6 l

EXLEVEL S

EXMNR - FACILITY l

~

QVAL 1.00

SEC' l

SUBSORT.

KA 295030G008 ,

QUESTION XXX - Is a. also correct? ,

SELECT the ONE statement that describes the actions required to be taken'if the following plant conditions occur while testing safety relief valves. PLANT CONDITIONS: Reactor mode switch position: "STARTUP" Reactor coolant temperature: 540degF. , Reactor power: 2% , Suppression pool temperature: 97*F. (has exceeded 95*F for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Suppression pool level: 17 feet 8 inches. . Residual Heat Removal (RHR) system loop "A" is in suppression pool cooling mode,

a. Stop all testing which adds heat to the suppression pool, ,

b. Reduce suppression pool water temperature to less than 95degF within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in MODE 4 within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

c. Verify suppression pool water temperature is s110degFonce -

per hour and restore suppression pool water temperature to s95degFwithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 'd ,- Restore suppression pool level to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least MODE 3 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and .. - -- . _ _ _ - _ _ _ . _ _ _ _ _ . -_m.__. ~- l in MODE 4 within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ANSWER d.

REFERENCE T.S. 3.6.2.2 LP: OT-3037-05, Obj. B

l

QNUM

'HNUM . ' ANUM

QCHANGED FALSE- .

ACHANGED FALSE ;

-*QDATE 1997/08/30 'FAC 440

RTYP _

GE BWR6 l

EXLEVEL S i

EXMNR FACILITY :

QVAL -1.00

SEC

'SUBSORT

KA 295031K101

QUESTION . .

During a LOCA, indication of level has been lost, but SRV talipipe temperature indicates =340degF. on recorder 1B21 R614 located on H13- r P614. This may be indicative of: ,

a. Inadequate core cooling.

b. Feedwater should be cut back.

c. SRV has been open for too long, t

- d. Increased efficiency of heat transfer.

ANSWER a.

' REFERENCE MCD Text LP: OT-3401-06, Obj. F t . -- . .- 2 . . . _ . , , - . . - _ . _ . . - , . . . . . . _ _ . . - . - . . . . . . _ . . . . ~ . ,_

QNUM~

HNUM

ANUM

'OCHANGED FALSE-

ACHANGED FALSE

'QDATE 1997/08/30

FAC 440

RTYP GE BWR6

EXLEVEL S

EXMNR FAClllTY

QVAL- 1.00

SEC

'SUBSORT

KA 295037G012

' QUESTION Concerning the use of the HPCS System during an ATWS event, SELECT the correct statement.

a. HPCS injection is not allowed if reactor power is above 4%.

b. At no time is HPCS injection allowed during an ATWS condition.

c. HPCS injection into RPV is allowed if RPV level cannot be restored and maintained above -25 inches.

d. HPCS injection is allowed if Feedwater, RCIC, and CRD cannot maintain RPV level between and 0 and 100 inches.

ANSWER c.

-* REFERENCE PEl-B13 P: OT 3402-11, Obj. D I {

QNUM ,

'HNUM l ' ANUM '

QCHANGED FALSE

'ACHANGED FALSE , *QDATE 1997/08/30 ;

FAC 440

RTYP GE BWR6

EXLEVEL S

EXMNR FACILITY

QVAL. 1.00

SEC

SUBSORT

KA 295037A201

QUESTION Given the following plant conditions:

PEl B13 (ATWS) has been entered. The reactor failed to scram. SLC is injecting. SELECT the statement that describes when PEl B13 (ATWS) can be exited and PEl B13 (Non ATWS) can be entered.

a. Power is on IRM range 4 and decreasing, all SRVs are closed,

b. The SLC storage tank level is 100 gal, and the SLC pumps have tripped,

c. All control rods are fully inserted, power is on IRM range 2 and decreasing,

d. The reactor engineer confirms the reactor will remain shutdown with the present rod configuration, as long as the boron concentration remains 2:500 ppm in the RPV.

' ANSWER c.

REFERENCE PElB13 LP: OT-3402-11, Obj. C OT-3402-03, Obj, F

l i l l

QNUM !

'HNUM' ,

ANUM -:

QCHANGED= FALSE i

ACHANGED FALSE l

QDATE' 1997/08/30 l t

FAC 440

RTYP GE BWR6 :

EXLEVEL S '

EXMNR FACILITY

QVAL 1.00 ;

SEC

'SUBSORT l

KA 295038G012 :

QUESTION While venting.the Containment per PEl M51/56 to restore hydrogen

concentration to below HDOL, which of the following conditions requires venting to be secured? !

a. Containment pressure is 8 psig and Containment hydrogen is 8 %

b. Radiation levels at the site boundary increase to 1 mr/hr ;

above normal background,

c. Containment pressure is less than or equal to 1.75 psig and Containment hydrogen cannot be determined,

d. Adequate Core Cooling cannot be assured and the radiation

-level _ at the site - boundary is 0.5 mr/hr above normal background.

ANSWER a.

REFERENCE PEl M51/56' . l LP: OT-3402-10, Obj. C

' t 7 ,--,,,-r-ur- *, v- = ,- --- +-w +- - -w,m--.

QNUM

'HNUM i ' ANUM

QCHANGED FALSE

'ACHAtlGED FALSE 'ODATE 1997/08/30

FAC 440

RTYP GE-BWR6

EXLEVEL S :

EXMNR FACILITY l

QVAL 1.00 !

SEC

SUBSORT

KA- 295024A117 !

QUESTION During a LOCA condition, an automatic initiation of RHR A & B in the containment spray mode is received. SELECT the correct statement concerning operation of the RHR systems in this mode.

a. RHR Pump flow should be 6900 7100 gpm during containment spray operations.

b. With a High Drywell Pressure signal present, the containment spray logic cannot be reset irrespective of containment pressure,

c. Realignment from the containment spray mode to suppression pool cooling cannot be accomplished without a reset of the containment spray initiation logic.. :

d. When conta',n.nent pressure decreased to less than 1.5 psig, containment spray would be terminated per the PEl by ove riding closed the E1? F028 and the E12 F537 valves (CONTAINMENT SPRAY FIRST AND SECOND SHUTOFFS).

ANSWER ,

c.

REFERENCE SOIE12 LP:- OT-3036-E12, Obj. E

. _ _ - ,. _ . . , . . ~ . _ _ _ . . . _ . . , - . __ I

QNUM

'HNUM

ANUM i

'QCHANGED FALSE .ACHANGED FALSE ; 'QDATE 1997/08/30 'FAC 440 I 'RTYP GE BWR6

EXLEVEL S ;

EXMNR FACILITY :

'QVAL 1.00 ; 'SEC- [ 'SUBSORT

KA 295015A201

' QUESTION : An ATWS hra occurred and Rx power ls 37%. Several control rods are stuck at various positions in the core and neither Standby Liquid Control pump will start. . Which ONE of the below actions would serve to decrease :' Rx power?

a. Maintain Rx level using the Motor Feed Pump between 50-100".

b. Commence a controlled depressurization not to exceed 100degF per hour.

c. Start both Rx Recirc pumps in slow speed to increase circulation through the core,

d. If no Rx Recirc pumps are running, raise RPV level to 2:240" to provide natural circulation.

ANSWER a.

REFERENCE PEl B13 (ATWS)

LP. OT-340211, Obj. D i ) 'ONUM i 'HNUM : ' ANUM ! 'OCHANGED FALSE 'ACHANGED FALSE i 'QDATE 1997/08/30 'FAC 440 > 'RTYP GE BWR6 , 'EXLEVEL S , 'EXMNR FACILITY . ' OVAL 1.00 i

SEC

'SUBSORT

KA 295004K203

- *OUESTION SELECT the system that will NOT AUTOMATICALLY function if required following a loss of Bus ED1 A. ,

a. High Pressure Core Spray (HPCS) .

b. Turbine Bearing Emergency Oil Pump

c. Reactor Core Isolation CoolinD (RCIC)

d. Automatic Depressurization System (ADS)

ANSWER c.

REFERENCE SDM: R42 LP: OT-3036 R42, Obj. 8 ONI R42-1 i

1 b ; l

QNUM

'HNUM

ANUM

'OCHANGED FALSE 'ACHANGED FALSE 'QDATE 1997/08/30

FAC 440

RTYP GE BWR0

EXLEVEL S

EXMNR FACILITY

QVAL 1.00

SEC

SUBSORT

'A

. 295020K209

QUESTION The plant is shutdown to Mode 4 with RPV water temperature being maintained 100degF-140degF by RHR "A" in shutdown cooling. I&C is currently performing a Level 3 SVI on Narrow Range Level Channel "A".

The Unit Supervisor is rolleved by the Shift Gupervisor, who allows l&C Technicians to begin Surveillance Testing on RPV Narrow Range Level Channel "B" During performance of their SVis, l>oth insert a RPV Level 3 signalinto their channels. What could be the possible consequences of doing this?

a. RHR Pump "A" will trip.

b. RHR Pump "A" Min. Flow Valve,1E12 F064A will open.

c. RHR Pump "A" Shutdown Cooling Suction Valve,1E12-F006A will close,

d. RHR Pump "A" Test Valve to the SP,1E12-F024A can now be opened by the operator on P601.

ANSWER a.

' REFERENCE SDM: E12 LP: OT-3030 E12, Obj. F

0NUM

HNUM

' ANUM

OCHANGED FALSE

'ACHANGED FALSE 'ODATE 1997/08/30

FAC 440

RTYP GE BWR0

EXLEVEL S

EXMNR FACILITY

' OVAL 1.00

SEC

'SUBSORT

KA 295022A103

QUESTION The Rx is operating at 100% power when CRDH Pump "A" trips. What action, if any, is required to be taken with respect to the Rx Recirculation System?

a. Shift both Rx Recirc Pumps to slow speed and maintain seal temperatures <160degF.

b. Rx Rect c pumps are not allowed to be operated without seal purge ir operation trip both Rx Recirc Pumps to OFF.

c. Rx Recirc Pump operation may continue, however seal purgo should be shifted to its alternate supply via the Mixed Bed System,

d. Rx Recirc Pumps can be operated indefinitely without seal purge, operation may continue but seal purge should be restored as soon as possible.

ANSWER d.

REFERENCE SDM:B33 LP: OT 3036 833 Obj.

801-B33

END

. _ . _ . . - . .._-_-.---m-... _ _ _ _ . _ . _ _ _ . . _ . ... -. - . _ _ _ _ _ . . . _ _ _ _ . . _ _ _ _ h i i t t r i .i i ) t ? t INITIAL SUBMITTAL-OF ADMINISTRATIVE JPMs - PERRY - AUG ~ 1997 r I t P I k t i i t i i ? l t s 4 2 r 4 i i } 1 f s 1 1 l J 1 PERRY NUCLEAR POWER PLANT LICENSE EXAM OUTLINE ADMIN. .IPAG PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97 U CATI: GORY 10PIC Dr.SCRIPTION OF JPM A.I Uses of Operational procedures Write an Operations I:s olution Order Conduct of Operations Rs Plant startup administralise Using supplied SRM /lRM readings,serify requirements proper overlap and take appropriate actions (on crisp data will not be adequate to continue startup and will require a Rs shutdow n to l>e commenced) A.2 Tagging and Clearantes Write an Information Tag on a component I:quipment Control A.3 I:saluation of radiation uork permit. When directed to enter a Hgh radiation area. Radition evaluate the associated radiation work permit . Control A.4 SHO: Classification of esent SHO: Classify simulator scenario and fill out 1:mergency appropriate papernork Plan Ito: Demonstrale accountability 140: l' rom in the plant, candidate w ill be told that Site Accountability is required and he will demonstrate the method for performing accountability by control room oersonnel and state the time required for him to do so. 1 1 PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM No. A.1.a JOB PERFORMANCE MEASURES JPM No. A6.on A.1.a JPM

Title:

Writo an Operations Evolution Order Plant

Reference:

PAP-0201, Conduct of Operations NUREG Referenco: 294001 A1.02 Method of Testing: In Plant Time for Completion: NA

PERRY POWER PLANT INITIAL UCENSE EXAMINATION :

ADMIN. JPM NO A.1.a l

Task Standards: Obtain Form from PAP 0201 or Control Room Assistint and write an Operations Evolution Order.

Required Materials: Blank Operations Evolution Order stamped " Training Use Only", and example form READ TO Tile CANDIDATE I WILL DESCRillE Tile INITIAL CONDITIONS, Tile TASK TO IIE PERFORMED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIM 6

' CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED llY Pl ANT PROCEDURES OR SilllT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMl!NT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile

!!XAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU llAVE COMPLETED Tile TASK.

nitial Conditions: Plant is operating at 100% power.

Initiating Cue: In preparations for a Bus F 2 B outage the Unit Supervisor would like you to write an Operations Evolution Order to sequence through the correct S01 sections to:

1) Cross tie D2B to D1B with D1B supplying

2) Shif t MCC F2811 to its alternate power supply XF1 A, and

3) De energize Bus F 2 B.

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.1.s START TIME:

' STEP 01 Find correct form (can get from CRA or computer or PAP 0201). S. U (Cue: Examiner supply candidate w/ stamped form.)

STEP 02 Identify sol R42(Sys. B) section 7.2 as correct procedure for first step. S U

' STEP 03 Identify Sol 1R10(LV) Attachment 43 as correct procedure for second S U step.

STEP 04 Identify S012R10(LV) Attachment 17 as correct procedure for third S U step.

STEP 05 - Fill out OE0 form similar to supplied example fort... S --U STEP 06 Submit to Unit / supervisor for review / approval. S U Completed sample form will be reviewed with lead examiner during exam review l week.

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- STOP TIME:

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. . . . . . . . . . E N D O F J PM * * * * * * * * *

PERRY POWER PL. ANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.1.b JOB PERFORMANCE MEASURES JPM No. Admin A.1.b JPM

Title:

Evaluate SRM/lRM Overlap Readings During Rx Startup (Faulted)

Plant

Reference:

1011, Rev 7, Cold Startup, section 4.2, steps 25-29, pgs.13

& 14 NUREG

Reference:

215003G013, 294001 A1.02 Method of Testing: In-Plant Time for Completion: NA

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO A.1.b Task Standards: Using criteria found in Integrated Operating Instruction 1011, Cold Startup, determine that less than three IRM channels per trip system are operable and recommend a normal shutdown in accordance with 101-4 and note this fact in 101-1 section 4.10, Instruction Completion.

Required Materials: Attachment 1 with the SRM and IRM readings is to be handed to candidato Rl!AD TO Tile CANDIDATE I WILL ht". 'IU"E Tile INITIAL CONDITIONS, Tile TASK TO llE PERFORMED AND Tilli 'N!!1ATING CUES. I WILL INDICATE WilETilE't Tile TASK IS TIME CRITICAL YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED llY PLANT PROCEDURES OR SilliT SUPERVISION DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED llY Tile EXAMIN!!R. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU llAVE COMPLETED Til3 TASK.

Initial Conditions: The plant is conducting a Rx startup, criticality has been achieved and power is increasing towards the point of adding heat.

Initiating Cue: You are .irected to verify proper SRM/lRM overlap and have the following readings (hand Attachment 1 SRM/lRM readings to the candidate).

I PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.1.b START TIME:

STEP 01 Compare given readings to 1011 step 4.3.25 (page 13). S U STEP 02 Recognize that IRM channels A, C, and G do not meet the S U overlap criteria.

STEP 03 Por 1011 step 4.3.20 commence a normal shutdown in accordance S U with 101-4 and note this fact in section 4.10 of 1011.

STOP TIME:

. . . . . . . . . . E N D O F J PM * * " * " * *

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6 PERRY POWER PLANT INITIAL LICENSE EXAMINATION l ADMIN. JPM NO. A.1.b .j (Attachment 1) :

i SRM / IRM READINGS ?

1 for ADMIN JPM A.1.b -)

i SRM Channel A 1X10'eps IRM Channel A 5/125 on Range 1 SRM Channel B 9X10* cps IRM Channel 8 15/125 on Range 1 SRM Channel C _1 X10' cps IRM Channel C - 5/125 on Range 1 ,

10/125 on Range 1 SRM Channel D 9X10* cps IRM Channel D 2

IRM Channel E 15/125 on Range 1 !

IRM Channel F 15/125 on Range 1 IRM Channel G 5/125 on Range 1 IRM Channel H 10/125 on Range 1 9

h

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.2 JOB PERFORMANCE MEASURES JPM No. Admin A.2 JPM

Title:

Writo an Information Tag Plant

Reference:

PAP-1404, Rev 3, section 6.1, pgs. 3a 6 i4UREG

Reference:

204001 K1.02 Method of Testing: In-Plant Time for Completion: NA i

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.1 Task Standards: Utilizing PAP-1404 write an Information Sticker to be placed on controller M15 R060A, Annulus Differential Pressure Controller A, to temporarily replace a lamacold label that was accidently disfigured during an l&C surveillance.

Required Materials: Information Tag Sheet (PAP-1404) stamped " Training Use Only" and an Information Tag stamped " Training Use On.y' READ TO Ti1E CANDIDATE I WILL DESCRillE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORMED AND Tile INITIATINO CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS 1F DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTIIERWISE. INFORM Tile EXAMINER Wi!EN YOU llAVE COMPLETED Tile TASK.

Initial Conditions: During the last shift an l&C Tech accidently disfigured the MPL labelon controller M15-R060A, Annulus Differential Controller A, making it impossible to read.

Initiating Cue: You have been directed to temporarily replace this label by writing an Information Sticker and placing it on the controller.

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- PERRY POWER PLANT-INITIAL LICENSE EXAMINATION '

ADMIN. JPM NO. A.1 START TIME:'--

t e

Using the suppiled example, complete an Information Tag Sheet and S.- U STEP 01 Information Tag.

. STEP O Submit Tag and Tag Sheet to US for approval._ S U The Information Tag Sheet and Tag examples are prepared and will be reviewed Jwith the lead examiner during the exam review week.

STOP TIME:

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E N D O F J PM ' " ' * " "

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN JPM NO. A.3 JOB PERFORMANCE MEASURES JPM No. Admin A.3 JPM

Title:

Evaluation Of A Radiation Work Permit Plant

Reference:

PAP-0512, Rev 5, Radiation Work Permit Program NUREG

Reference:

294001 K1.03 Method of Testing: In-Plant Time for Completion: NA i

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.3 Task Standards: Using RWP 97 XX be able to correctly determine correct dress-out requirements, highest dose rate in the area, any hot spots.

Required Materials: None, use the actual RWP located at the RRA entrance.

READ TO TiiE CANDIDATE I WILL DESCRIBE TIIE INITIAL CONDITIONS, Tile TASK TO DE PERFORMED AND Tile INITIATING CUES I WILL INDICATE WlIETliER TliE TASK IS TIME CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION, DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNI.ESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU llAVE COMPLETED Tile TASK.

Initial Conditions: You .1 ave been directed by the Shift Supervisor to assist a Maintenance crew that is working on _.

Initiating Cue: When reviewing the RWP for that area ask the candidate the questions on the following page.

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- PERRY POWER PLANT INITIAL LICENSE EXAMINATION ,

iADMIN.-JPM NO.~ A-3 ,

- START TIME:

J STEP 01 Dress-out Requirements: S U ;

STEP 02- Highest Dose Rate in the area:- S U-STEP 03 When does the RWP expire? - S U .

8 This information will be input the week of the exam review to ensure that the Information is accurate using the up-to-date RWP.

STOP TIME:

. . . END OF JPM " " ' * * " "

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F PERRY POWER PLANT-INITIAL LICENSE EXAMINATION '

ADMIN. JPM NO. A.4 (RO Only)

I i

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JOB PERFORMANCE MEASURES JoM No. Admin A.4 (RO Only) i 1

JPM

Title:

- Perform an Emergency Plan Classification Plant

Reference:

EPIA1 NUREG

Reference:

294001 A1.16 Method of Testing: In-Plant '-

~ Time for Completion: Time critical JPM, must be completed within 3Q minutes, i.

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PERRY POWER PLANT INITIAL UCENSE EXAMINATION ADMIN. JPM NO. A.4 (R0 Only)

Task Standards: Candidate must come up to the control room (either Unit 1 or 2) and insert his keycard into the readers located just inside the control room doors. This action is required to be complete within 30 minutes of announcing site accountability.

Required Materials: None READ TO Tile CANDIDATE I WILL DESCRillE Tile INITIAL CONDITIONS, Tile TASK TO 13E PERFORMED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED IlY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUlPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED 13Y Tim EXAMINER. DO NOT ASSUME TIIE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM TiiE EXAMINER WilEN YOU liAVE COMPLETED TiiE TASK.

Initial Conditions: You are the Operations Foreman and are out in the plant observing one of the PPO's take the Nuclear Island Rounds-Inside, initiating Cue: Suddenly you hear the Shift Supervisor announce over the PA that he is declaring the site to be in a Site Area Emergency and that Site Accountability is required. Display the required actions you would take to demonstrate Site Accountability, and inform the examiner how long you have to do this.

PERR(POWER PLANT -

INITIAL LICENSE EXAMINATION

' ADMIN. JPM NOT A;4 (RO Only)-

START TIME:

STEP 01 Candidate must come up to either the Unit 1 or Unit 2 control room. S U (Cue: Alternate method is to have Shift Supervisor submit badge

- number of crew member for accountability, if candidate mentions this, inform him that SS wants him to come to the control room to assist in the transient and to perform accountability actions.)

.i ~

STEP 02 - Candidate must esimulate inserting and then withdrawing his keycard S U into one of the Emergency Plan Card Readers located just inside both the Unit 1 and Unit 2 control room doors.

STEP 03 Candidato must correctly state that the time required for him to S U complete Site Accountability actions is 3_Q minutes.

STO? TIME:

. . . . . . . . . . END OF JPM " " ' ' "

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- PERRY POWER PLANT INITIAL LICENSE EXAMINATION

~ ADMIN. JPM NO.- A.1 JOB PERFORMANCE MEASURES -

JPM No. Admin A.1 L

JPM

Title:

Emergency Plan Classification

- Plant

Reference:

EPl.A1, Emergency Action Levels NUREG

Reference:

- 294001 A1.16 4

Method of Testing: - Simulator.

Time for Completion: NA

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.1 Task Standards: SRO car.didate will accurately classify simulator scenario using EPI-A1.

I Required Materials: None )

READ TO TIIE CANDIDATE 1 WILL DESCRIBE TIIE INITIAL CONDITIONS, TIIE TASK TO BE PERFORMED AND TIIE INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU SI-lOULD SIMULATE TiiE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY TIIE EXAMINER. DO NOl' ASSUME T11E EXAMINER WIL.L ACCEPT AN ORAL DESCRIPTION OF TIIE REQUIRED ACTION UNLESS TliE EXAMINER INDICATES '

OTiiERWISE. INFORM TIIE EXAMINER WIIEN YOU IIAVE COMPLETED T!!E TASK.

Initial Conditions: Tiis Admin JPM will be implemented following each simulator scenario, initiating Cue: SRO License candidate will be required to classify the scenario for applicable Emergency Plan actions.

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s PERRY POWER PLANT INITIAL LICENSE EXAMINATION.

ADMIN.'JPM NO.' A.1 7

. START TIME: -

STEP 01- i For the following Simulator Scenarios annotate which is appliceble and -

whether the candidate correctly classified the event:

Scenario _ ' Classification Aeolicable? Sall

1- SAE CS1 S U AS2

2'- SAE -DS1 _

S U ,

3' - Alert CA1 S. U

4- SAE CS1 S U

=AS2 AS3 STOP TIME:

. . . . . . . . . . EN D 'O F J PM ' " ' ' ' ' -

INITIAL SUBMITTAL-0F WALKTHROUGH JPMs - PERRY - AUGUST 1997 l

I 1

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JOll PFJtFORM ANCE MEASURES PERRY NUCLEAR POWER P1] ANT EXAM COMMENCING 08/22/97r JPM location System /JPM Safety Notes Questions K/A/G No. Function i Simulator 201001/ CRDil: Perform Fast Restart of Abnorm. 201-001-G0010

- - a tripped CRDil pump. 1 Condition 201-001 A3.04 2 259-002 / Rx Level Control: Shift fc n Low 259-002-G0010 Simulator Rx Feed Pump Turbine to Motor FeuJ 2 Power Pump on the Startup Level Controller. JPM 259-002-K1.01 4 239-002 / Safety Relief Valves: Attempt Abnorm. 239-002-G0005 Simulator to close a stuck open SRV by pulling 3 Condition fuses. 239-002-A4.nl 5 217-0002 / RCIC: Startup RCIC from Normal 217-000-G0010 Simulator Siby. in CST to CST mode. 4 Condition /

- - Faulted 217-006-Al.07 8 in- 223-001/ Cntmt. & Auxiliaries: Perform Emerg. 223-001-K5.05 Plant a start of flydrogen Recombiner A. 5 Condition

- - 223-001 A1.05 6 262-001/ A.C. Distribution: Transfer Abnorm. 262-001 K4.03 Simulator station electrical loads to the Startup 6 Cond. / New Trfmr. JPM 262-001-A4.05 7 215-005 / LPRM's: Bypass a failed Abnorm. 215-005 G0010 Simulator LPRM instrument. 7 Cond. / New

- - JPM 215-005 K4.02 9 in. 286-000 / Fire Prucction: Initiate control Abnorm. 286-000-K4.02 Plant room subfloor CO, from outside the 8 Condition control room. 286-000-G0001 3 261-000 / Annulus Exhaust Gas Treat: 261-000-K4.01 Simulator Shutdown Train B from both trains 9 running. 261-000-A3.03 10 In- 203-000 / RilR (LPCI Mode): Perform Emerg Cond. / 295-003-A2.04 Plant RilR Loop B Flood Alternate injection. 2 inRRA

- - 203-000-K 1.17

** These JPM's are to be performed by the SRO Upgrade candidates.

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- PERRY POWER PLANT

- INITIAL LICENSE EXAMINATION -

- JOB PERFORMANCE MEASURES (WALKTHROUGH) .;

JPM NO,1 JOB PERFORMANCE MEASURES JPM No.1 JPM

Title:

CRD Pump Trip Recovery Plant

Reference:

SOI-C11(CRDH), section 7.2 NUREG

Reference:

201001 A2.01 -

3-Method of Testing: Simulator..

Time for Completion: 10 minutes

.s, , e om- r -e 3 -

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB Pf AFORMANCE MEASURES (WALKTHROUGH)

JPM NO.1 Task Standards: Start a tripped CRD pump as directed by the US per SOI-C11(CRDH), section 7.2, CRD Pump Trip Recovery.

Required Materials: None Simulator Setup: Reset to IC 25, take 1C11 C001 A control switch to STOP, reset all annunciators READ TO TIIE CANDIDATE 1 WiLL DESCRIBE TIIE INITIAL CONDITIONS, THE TASK TO DE PERFORMED AND Tile INITIATING CUES. I WILL INDICATE WHETilER TIIE TASK IS TIME CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SilIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTHERWISE. INFORM THE EXAMINER WilEN YOU IIAVE COMPLETED TIIE initial Conditions: The plant is operating at approximately 12% reactor power. CRD Pump "A" was in operation but inadvertently tripped. The cause of the trip was known and has been corrected.

Initiating Cue: The Unit Supervisor directs you as the SO to perform a Trip Recovery of CRD Pump "A", and return system parameters to Normal Operating Values.

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.1 START TIME:

STEP 01 . Takes CRD AUX OIL PUMP A, C11-C002 "A" switch to START, S U and observes CRD PUMP A TRIP OIL PRESS LOW alarm clears.

STEP 02 Places CRD HYDRAULICS FLOW CONTROL in Manual, holds S U CLOSED 1C11 R600 push-button until CRD FLOW CONTROL VALVE,1C11-F002A is fully closed.

STEP 03 Takes CRD PUMP A, C11-C001 A switch to START. S U STEP 04 Throttles open CRD FLOW CONTROL VALVE, C11-F002A S U slowly until desired flow is returned to pre-transient setting on flow controller R600.

STEP 05 Places CRD HYDRAULICS FLOW CONTROL,1C11 R600, in S U.

AUTO, verifies parameters are stable.

STEP 06 Informs the Unit Supervisoi that the CRD Pump has been restarted S U and parameters returned to normal.

STOP TIME:

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PERRY POWER PLANT '

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.1 l

USE

REFERENCE:

YES X NO OUESTION 1: ' Concerning the CRDH system:

a. What would be the significance of isolating a Recirc loop q without securing CRDH seal purge flow?

b. What are the two sources of temporary cooling water in the event the CRDH system must be shutdown and which one is the preferred source?

P ANSWER 1: a. Overpressurization of a Recirc loop could result if the loop is isolated and seal purge flow is still in operation,

b. Condensate Transfer System (P11) - preferred Mixed Bed System (P22)- alternate K/A: 201001G0010

REFERENCE:

a. SOI C11(CRDH), Section 2.0, P & L #2

b. sol-C11(CRDH), Section 7.3 Caution on page 13 CANDIDATE RESPONSE:

a.

b.

1 SAT = UNSAT

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.1 USE

REFERENCE:

YES NO X OUESTION 2: Describe what would you expect to see CRDH system flow do in the following two situations with no operator action:

a. Immediately following a Rx Scram

b. Following a scram reset?

ANSWER 2: a. CRDH flow will be maximum due to flow to the charging header, even though the Flow Control Valve is closed (flow is sensed upstream of the charging header which causes the FCV to close)

b. Flow win remain at maximum while all of the accumulators are being recharged and then will slowly decrease back down as the FCV throttles to maintain flow at the tapeset value of 60 g,:m.

K/A:- 201001 A3,04

REFERENCE:

System Description Manual SDM-C11(CRDH), pages 12 & 14 CANDIDATE RESPONSE:

a, b.

SAT UNSAT l'

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-i PERRY POWER Pl>2;T-INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)' .

JPM NO. 2 JOB PERFORMANCE MEASURES JPM No.2 I

- JPM

Title:

Feedpump Shift on Startup Level Controller Plant

Reference:

sol C34, section 7.4.2 NUREG

Reference:

259002G009

. Method of Testing: Simulator Time for Completion: 15 minutes

PERRY POWER PLANT IN TIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 2 Task Standards: Successfully shift from RFPT "A" on the Startup Level Controller to the MFP on the Startup Level Controller, Leave RFPT "A" running at whatever rpm results when it is removed from the SULC.

Required Materials: None Simulator Setup: Reset simulator to IC-25, take MFP control switch to start, reset all annunciators.

READ TO Tile CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, TiiE TASK TO BE PERFORhiED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS Tih1E CRITICAL.

YOU SilOULD Sih1ULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR S1IIIT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAhi!NER. DO NOT ASSUh11! Tile EXAh11NER WILL ACCEPT AN ORAL DESCRIPTION OF TIIE REQUIRED ACTION UNLESS Tile EXAhilNER INDICATES OTilERWISE. INFORh1 Tile EXAhilNER WilEN YOU llAVE COh1PLETED Tile TASK.

Initial Conditions: The reactor is operating at approximately 12% power. RPV level is being maintained by RFPT "A" on the Startup Level Controller in AUTO. The Motor Feed Pump has been manually started per SOI-N27.

Initiating Cue: The Unit Supervisor directs you to shift to the MFP on the Startup Level Controller and leave RFPT "A" idling until the System Engineer contacts the control room with further instructions.

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1 PERRY POWER PLANT INITIAL LICENSE EXAMINATION ' !

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 2 START TIME:

STEP 01' : Place the MFP in service per sol N27. (This step is fulfilled by the S U initial conditions)

STEP 02 Verify the in-service RFPT is being controlled by the STARTUP RX -S U LEVEL CONTROL,1C34-R602,in AUTO.

STEP 03 Slowly raise the MFP flow using the manual pushbutton of MFP FLOW-- S U CONTROL,1C34R601C, to maintain a constant reactor water level of 1 2 inches above the tapeset point of the STARTUP RX LEVEL CONTROL,1C34 R602.

STEP 04 Adjust RFP A FLOW CONTROL,1C34 R601 A, horizontal output S U meter to zero.

STEP 05 ~ Null the RFP DFV METER A,1N27-R426A, using the RFPT A S U MANUAL SPEEu CONTROL Dial,1N27-R425A.

STEP 06 Place the RFPT A GOV MODE CONT,1N27-S50, to MANUAL, S U putting RFPT A under control of the MANUAL SPEED CONTROL Dial,1N27 R425.

STEP 07 Place STARTUP RX LEVEL CONTROL,1C34-R602 in MANUAL. S U

. STEP 08 Use the manual pushbuttons of STARTUP RX LEVEL CONTROL, S U 1C34-R602, to match its horizontal output meter with the horizontal output meter of MFP FLOW CONTROL,1C34-R601C.

STEP 09 Select the MFP with the STARTUP FDW PUMP SELECT SWITCH, S U 1C34 S3.

PERRY POWER PLANT INITIAL LICENSE EXAMINATION

- JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 2 STEP 10 -- Use the STARTUP RX LEVEL CONTROL,1C34-R602, tapeset to S U null the controller devir. tion (red arrow in green band) and place it in AUTO.

STEP 11 Slowly adjust the STARTUP RX LEVEL CONTROL,1C34 R602, S U tapeset to restore level to the normal control band, (192-200")

s STEP 12 Shutdown RFPT A per Sol-N27 (step not required per initiating cue) S U 1

STOP TIME:

......**** EN D OF J PM **""**** -

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 2 USE

REFERENCE:

YES X NO QUESTION 1: While operating at 100% power with both RFPTs on the Master Level Controller RFPT "A" trips and the MFP auto starts. What power limitation are you procedurally under both when you are in the ONI and after you have exite the ONI?

ANSWER 1: ONI N27, Feedwater Pump Trip, Section 3.0.2 states that you have a power limitation of 90% with one RFPT and the MFP. Once you exit the ONI procedural guidance is given by SOI-C34, Feedwater Control System, Section 2.0, step 2 states that with the resultant pump combination power is limited to 89 /o as follows:

RFPT "A" 71 %

MFP 22 %

94 %

-5% for reserve capacity during level transients

=89%

K/A: 259002G0010 & 259002G0001

REFERENCE:

ONI N27 Feedwater Pump Trip, Section 3.0.2 sol-C34 Feedwater Control System, Section 2.0, P&L #2 CANDIDATE RESPONSE:

P SAT UNSAT

, , . - . _ m

- PERRY POWER PLANT INITIAL LICENSE EXAMINATION-JOB PERFORMANCE MEASURES (WALKTHROUGH) .

JPM No. 2 USE

REFERENCE:

sYES X -NO QUESTION 2: - If a failure of the Feedwater Level control System resu!'a in a level increase to Level 8, a reactor scram will occur What specific thermal limit does the RPV Level 8 scram protect us from?

ANSWER 2: Level 8 scram ensures that MCPR is maintained above the MCPR safety limit; K/A: 259002G0005

REFERENCE:

Tech. Spec. 3.3.1.1 basis, page - B3.313 in the Tech. Specs.

CANDIDATE RESPONSE:

SAT UNSAT l

i i

l . , . . . , , _ , _ - . , . - _ - _ . , _- , ,. , . _ , . .__ ,.__,_____,_, , _ _ , _ , . , , ,

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

J i

PERRY POWER PLANT?

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH) -

JPM NO. 3 JOB PERFORMANCE MEAStsRES JPM No. 3 JPM

Title:

Shutdown to Standby AEGTS Train "B" With Both Trains l Operating .

-Plant

Reference:

sol-M15, section 6.2 NUREG

Reference:

261000A4.03 Method of Testing: Simulator

__ Time for Completion: 12 minutes a

PERRY POWER PLANY INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO,3 Task Standards: AEGTS Train "B" shutdown from running to standby readiness with-associated heater off, and Train "A" running, maintcining Annulus Differential Pressure.

Required Materials: None Simulator Setup: Roset to IC 25, start M15-COO 1B, energize M15-D0018, clear all annunciators.

READ TO Tile CANDIDATE I WILL DESCRIBE THE INITIAL CONDITIONS, THE TASK TO DE PERFOlbdED AND Tile INITIATING CUES. I WILL INDICATE WHETIIER Tile TASK IS TIME CRITICAL.

YOU SIIOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF TIIE REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTHERWISE. INFORM THE EXAMINER WHEN YOU llAVE COMPLETED THE TASK.

Initial Conditions: The plant is operating at approximately 6% power. Both Annulus Exhaust Gc; Treatment System Fans are running to satisfy a Work Order retest.

Initiating Cue: The Unit Supervisor directs you to shutdown AEGTS Fan "B" to Standby Readiness.

j P

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

. . . - =.- -. -- - . . - . . -

i PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASUP5S (WALKTHROUGH)

L JPM NO, 3 :

l START TIME: ,

STEP 01 De-energize 'AEGT ELEC HT COIL Bf 1M15-D001B, by taking . S U .

control switch to STOP..

STEP 02 When the heaters have been cooled down for five minutes, confirm . S U-ANNULUS EXH FAN A FLOW LOW annunciatoriwindow 1H13-P800-1-A1, is reset, s STEP 03 Hold AEGT FAN B,1M15 C001B, control switch in STOP. -S U J STEP 04 After allowing 1 to 2 minutes for theTrain A dampers to reposition, . S-U .

1 check ANNULUS DIFF PRESSURE RECORDEk,-1M15-R016B to ensure annulus pressure is maintained between_0.75" and 1.0" H2 O Vacuum. .

. STEP 05 Confirm ANNULUS EXH FAN A FLOW LOW annunciator, window -S U ir11' P800-1 A1, is reset.

STEP 06 Take AEGT FAN B,1M15 C001B, control switch to STBY. S U v

STEP 07 Release AEGT FAN B,1M15-C001B, control switch. S U STEP 08 Perform independent verification of the required components. (Acting as US U inform candidate that you will get another operator to perform this step.)

- STOP TIME:

8

. . . . . . . . ' " END OF JPM " "" " '

w a. , ~ - , , . - - - - - , . - , , . , , . < . . . , . .,, , , . .,w-. . . , - - . - . , . , . . - , .,n.e

PERRY POWER PLANT :

= INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO 3 USE

REFERENCE:

YES X NO QUESTION 1: While operating at 100% power you receive the ANNULUS EXH FAN A '

- FLOW LOW annunciator. When you go back to panel P800.you see that-

~

the standby AEGTS fan did not auto start. What could be the cause for this?

ANSWER 1: The low flow annunciator comes in at 1600 scfm onthe running fan, however the standby fan does not auto start untilit senses 1500 scfm on the running fan.

K/Ai 261000K4.01

REFERENCE:

- Alarm Response Instruction H13-P800-01 fnr annunciator A1.

CANDIDATE RESPONSE:

JSAT UNSAT 4

_ , . ,.- . . , - - - . . ,w.--- ,-,u , ,

r-

i f

PERRY POWER PLANT ,

INITIAL LICENSE EXAMINATION - i JOB PERFORMANCE MEASURES (WALKTHROUGH) j

~

JPM NO. 3 USE

REFERENCE:

YES NO X {

c-i OUESTION 2: Assume that you are standing at 1H13 P8001. Current Annulus Diff [

~

Pressure Controller,1M15 R060A, tapeset is 0.80" H,0 and actual Annulus dif forential pressure is .0.80" H,0. Describe what you would ,

expect the Annulus Fan Exhaust Damper, M15 F080A, and Recirculation j Damper, M15 F070A, to do if you increased the tapeset value to 1,0" !

H,0. ,

ANSWER 2r The recire damper, F070A, would throttle closed while the Exhaust damper, F080A, would throttle open to increase the negative differential pressure in the annulus. They would then modulate as the annulus differential pressure approached the tapeset value, to maintain that setting.

K/A: 201000A3.03

REFERENCE:

SDM M15, section il.C.2 CANDIDATE RESPONSE:

l SAT. UNSAT I

i i

_._.m , , , . . . _ . , . . . . _ . . . - - , , . . . . , . . . . . . . _ . , _ . . _ -

i i

PERRY POWER PLANT !

. INITIAL LICENSE EXAMINATION i JOB PERFORMANCE MEAGURES (WALKTHROUGH) !

JPM NO. 4 :

Y F

t JOB PERFORMANCE MEASURES JPM No.4 i

h

?

.c JPM

Title:

Pull Fuses on Stuck Open Safety Relief Valve ,

Plant

Reference:

ONI 821 1, section 3.0, step 3.c and Attachments 1 & 2 -

NUREG

Reference:

239002A2.03 Method of Testing: Simulator Prne for Completion: 8 minutes s

1

l PERRY POWER PLANT -

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 4 Task Standards: Fuses pulled for Safety Relief Valve 1821 F0051A only.

Required Materials: None Simulator Setup: Reset to 1019, insert override lor ZD1B21F0051 A OPEN, place both the "A" and "B" SRV Control switches on P601 and P031 in OFF, reset all annunciators.

=

READ TO Tile CANDIDATE I Wil L DESCRillE Tile INillAL CONDITIONS, Tile TASK To llE PERFORhiED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TlhiB CRITICAL YOU Sil0ULD SlhiULATETilE REQUIRED ACTIONS AS IF DIRECTED llY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROL.S UNLESS SPECIFIC.,LLY DIRECTED llY Tile EXAhilNER. DO NOT ASSUh11! Till! EXAhilNER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLliSS Tile EXAhilNER INDICATES OTilERWIS!!. INFORhi Tile EXAh11NER WilEN YOU llAVE C0hiPLETED Tile Initial Conditions: Reactor is operating at 100% power. SRV 1821.F0051 A inadvertantly opened. The US entered ONI-821 1, SRV INADVERTANT OPENING / STUCK OPEN and has carried out allimmediate actions with the exception of pulling fuses.

Initiating Cue: The US directs you to de-energize the SRV solenoids by removing the applicable control power fuses for 1821 F0051A.

i PERRY POWER PLANT l lNITIAL LICENSE EXAMINATION ,

i JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM No. 4 :

i START TIME:

i STEP 01 Using Attachment i determine that the correct fuses to pull in S U _;

?H13 P628 are F19 (F83A) in the Left Panel and F6 (F84A) in the l Right Panel.

STEP 02 - Using Attachment 2 determine that the correct fuses to pull in S U :

1H13 P631 are F19 (F838) and F20 (F848), both in the Left Panel.

STEP 03 Remove metal that could come in contact with electrical circuits. S' U STEP 04 Using fuse pullers obtained from the horseshoe area of the control -SU ,

room, remove the associated fuses and their fuses covers. ;

i STOP TIME:

""***** END OF J PM *""""* t k

i

-y. . -, ,. . , - . . 4. c , . , . _ .

-_...__,...m.,. -. . - . , .,,_.-.._,,,.,.,__..._,.-,,,..;,,,_-,,,--.,-.--....m,.,- _ , . . - - ,

i PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH) 1 i

JPM NO. 4 USE

REFERENCE:

YES X NO ,

QUESTION 1: The plant is operating at 100% power with the HPCS System inop and in secured status. After a Surveillance test 1821 F0051D is declared -

inop. due to being mechanically bound in the closed position. What ;

Tech Specs have applicable actions and what is the most limiting action required to be taken? j t

ANSWER 1: Tech Spec 3.4.4, Safety / Relief Valves A Potential LCO must be written for this.

Tech Spec 3.5.1, ECCS Operating Action E Restore ADS valve to OPERABLE in 14 days ,

Action H Enter Tech Spec 3.0.3 Most Limiting K/A: 239002G0005 .

REFERENCE:

Technical Specifications CANDIDATE RESPONSE:

i SAT UNSAT Y

w,,, , , , , . , . ,g...,, _ , . . _ , .y,,,,,. .sp,,,.m. . , , , , , , y - . . g,_ ,

t j

PERRY POWER PLANT - !

INITIAL LICENSE EXAMINATION '

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 4 USE

REFERENCE:

YES NO X QUESTION 2: Describe three independent methodr. taat could be used to indicate that -L an open SRV has closed.

ANSWER 2: Candidate may discuss any three of the following:

- The "A" and *B" solenolds are doenergized as indicated by the red lights on panels P601 P628, and P631 extinguished ;

- The red light above the valve control switch on P601 is i extinguished indicating that the pressure switch located l downstream of the SRV senses less than 30 psig.

- The tailpipe temperature for that SRV as read on recorder 821 R614 on P614 is decreasing.

- An existing steam flow / feed flow mismatch as read on recorder C34 R607 on P680 will degrade to zero and steam flow will match feed flow

- MW output of the Main Generator will increase as steam flow that was diverted thru the SRV is once again restored to the Main Turbine.

K/A: 239001A4.01

REFERENCE:

SDM B21/N;1 ONI-821 1 r CANDIDATE RESPONSE:

s SAT UNSAT i

T

-...m_.,, , , . _ . _ . , , , . . . . . . . - , _ , _ , , , . , . . . . _ _ . ...~,,,_,g.., , . , , . . , , , _ , . _ , . . _. . . , , , , . . , , _ , , _ . . , , ,._., . . . _ ,., ,

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOS PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO, 5 l

b r

1 i

't b-s 5

JOB PERFORMANCE MEASURES 1 1

JPM No. 5 r

i I

JPM

Title:

Manual Startup of RCIC in CST to CST, Faulted l Plant

Reference:

S01 E51, section 4.5

NUREG

Reference:

217000A4.03 Method of Testing: Simulator - :

-Time for Completion: 20 minutes I

h s

. . . , .w.,-.-~, , ,--,l,,+-, ,, ..,gr.nm,--,, , ,-. ,,.,,,,,r,e, ,,l,-, ,-v-w,re-. ,,, ,,n-~.-,w,,w,,. a, . , , ,~~n, ,...a, ....n-'--, 4as

l i

PERRY POWER PLANT l INITIAL UCENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 5 Task Standards: Following a f ailure of the RCIC Flow Controller,1E51 R0600, to control RCIC flow the operator will obtain desired parameters using Manual control.

Required Materials: None Simulator Setup: Reset to IC 10, start ESW Pump "A" and ECC Pump "A", insert '

malfunction imf CNv2:1E51R0600 (none 0) 100 0 0, reset all annunciators. Overtido the CST Suction Valve F010 as Is and the SP Suction Valve F031 closed and override the annunciator RCIC SUPR POOL SUCT VLV OPEN SUPR PL LVL Hl, P601-G5 to 0FF.

READ TO Tile CANDIDATE I Wil.L DESCRIDE Tile INITIAL CONDITIONS, Tile TASK TO IlE PERFORh1ED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS Tih1E CRITICAL. YOU SilOULD Sih1ULATE Tile REQUIRED ACTIONS AS IF DIRECTED llY PI ANT PROCEDURES OR SilllT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPh1ENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAhilNER. DO NOT ASSUh1E Tile EXAhilNER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAh11NER INDICATES OTilERWISli. INFORM Tile EXAMINER WilEN YOU llAVE COMPLETED Tile initial Conaitions: Reactor is operating at 100% power. ESW pump "A" and ECC pump "A" are running. SVI D23-T1213, Suppression Pool Average Temperature is signed in and being performed by the STA. RCIC is in Standby Readiness aligned to the CST.

Initiating Cue: The Unit Supervisor directs you to parform a manual startup of the Rx Core Isolation Cooling system in the CST to CST mode to support a work order retest. The retest calls for RCIC flow to be 650 700 gpm with RCIC pump discharge pressure at approximately 100 psig greater than Rx pressure.

l PERRY POWER PLANT :

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH) i JPM NO. 5 l START TIME: i l

STEP 01 Initiate evacuation of any personnel from the Rx Building Annulus and S U Containment. (Cue candidate that no personnel are in these areas.)

STEP 02 Perform ECC Loop A Manual Startup (done per initial conditions). S U U '

STEP 03 Verify RCIC PUMP CST SUCTION VALVE,1E51 F010, is open. S-t STEP 04 Take the RCIC SECOND TEST VALVE TO CST,1E51 F059, to OPEN S U to provide a discharge path to the CST.

STEP 05 Take RCIC TURBINE GLAND SEAL COMP,1E51 C004, to START. S U STEP 06 Simultaneously perform the following:

a. Take RCIC STEAM SHUTOFF,1E51 F045, to OPEN to roll S U the RCIC Turbine,

b. Open the RCIC FIRST TEST VALVE TO CST,1E51 F022, by S U ,

holding the control switch in OPEN. ,

STEP 07 Ensure RCIC PUMP MIN FLOW VALVE,1E51 F019, opens if RCIC S U flow is less than 120 gpm and the RCIC Pump discharge pressure is greater than 125 psig.

STEP 08 Verify the following valves automatically close after RCIC STEAM S U ,

SHUTOFF,1E51 F045, is open: ,

a. RCIC TURB CNDS TO CHW FIRST SHUTOF?,1E51 F004 RCIC TURB CNDS TO CRW SECOND SHUTOFF,1E51 F005 i b.

c. RHR & RCIC ST SUPP FIRST DRN SHUTOFF,1E51-F025

d. RHR & RCIC ST SUPP SECOND DRN SHUTOFF,1E51 F026. ,

i i

PERRY POWER PLANT !

INITIAL LICENSE EXAMINATION '

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 5 -

f Using RCIC PUMP FLOW CONTROL,1E51 R600, adjust flow until the S U !

STEP 09 desired flow is reached (which for this JPM is 650 700 gpm).

STEP 10 Candidate should determine that the RCIC PUMP FLOW CONTROL, S U !

1E51 R0600, did not automatically throttle to maintain 700 gpm as l required by US direction. l STEP 11 Candidate chall notify US of f ailure of 1E51 R0600. S U t (As the US, after being informed of the system status direct the candidate to maintain RCIC parameters using manual control of the RCIC Flow Controller until the RSE is present in the control room, candidate may do this prior to contacting US.) i STEP 12 Candidate shall place 1E51 R0600 in MANUAL control. S U STEP 13 Candidate shall use the Flow Controller OPEN/CLOSE pushbuttons to S U molntain flow 650 700 gpm and RCIC pump discharge pressure approx.

100 psig above Rx pressure using 1E51 F022.

I STOP TIME:

. . . . . . . . . . EN D O F J PM * * * ' * * * "

-I i

v.. . .-.r4.->4-.. e . --.--.r- y, , , - , , -- 4 w --. . , - - . . . - -++,-,y---, mor,..- - ~ , ,. ..,-- *~re,e .vv-+-.,-- --, - . n.<-.e . , . - - - - ,-%<'

= +

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO,5 USE

REFERENCE:

YES X NO QUESTION 1: In order to reduce galvanic corrosion of the governor valve stem moisture must be removed from the governor valve packing. How is this accomplished in the System Operating Instruction?

ANSWER 1: The Gland Seal Compressor should be operated for a minimum of one hour af ter the RCIC Turbine has been shutdown.

K/A: 217000G0010

REFERENCE:

sol E51, Section 2.0, Precaution and Limitation # 17 CANDIDATE RESPONSE:

SAT UNSAT

l PERRY POWER PLANT l lNITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 5 l

USE

REFERENCE:

YES X NO i OUESTION 2: State the response of the RCIC system if aligned in the CST to CST ,

mode to an increasing Suppression Pool Level., include in your answer any setpoints, i ANSWER 2: At > 18.4 feet in the Suppression Pool:

RCIC PUMP SUPR PL SUCTION ISOL, E51 F031 will open RCIC PUMP CST SUCTION VALVE, E51 F010 will close l RCIC FIRST TEST VALVE TO CST, E51 F022 will close RCIC SECOND TEST VALVE TO CST, E51 F059 will close, K/A: 217000A1.07 ,

r

REFERENCE:

Alarm Response Instruction H13 P60121 for annunciator GS CANDIDATE RESPONSE:

SAT UNSAT b

p

.-e y- ,e p ,,c--ru:,e. ----e.-- -

-,.y .,.,-.-,.4 , - .s-,, - ...w,- ., , . . , , . , . , , , , ~ , . 3- ,%.-,, . . . ,_ ..r,..yr,-...,,m,m,4w ,

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

i PERRY POWt:R PLANT INITIAL LICENSE EXAMINATION '

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 6 i

l i

JOB PERFORMANCE MEASURES

'JPM No.6 d

l i

. JPM

Title:

Transfer Station Electrical Loads To The Startup Transformer Plant

Reference:

101-8, step 4.2.9 NUREG

Reference:

262001A4.01 Method of Testing: Simulator Time for Completion: 6 minutes -

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

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 6 Task Standards: Electrical busses L11 and L12 are being powered from bus L10 via the Unit 1 Startup Transformer.

Required Materials: None Simulator Setup: Reset to 1019, reset all annunciators.

READ TO Tile CANDIDATE I WILL DESCRlllE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORhiED AND Tile INITIATING CUES. ] WILL INDICATE WilETIlER Tile TASK IS TlhiE CRITICAL. YOU SilOULD SIhfULATE Tile REQUIRED ACTIONS AS IF DIRECTED llY PLANT PROCEDURES OR SilllT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROLS UNLESS SPECIFICALLY DIREC1ED BY Tile EXAh11NER. DO NOT ASSUh1E Tile EXAhilNER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAhilNER INDICATES OTilERWISE. INFORh1 Tile EXAhi!NER WilEN YOU llAVE COhiPLETED Tile Initial Conditions: The plant is operating at 100% power when it experiences a significant problem forcing the Unit Supervisor to enter 101-8, Shutdown By Manual Reactor Scram.

Initiating Cue: The Unit Supervisor directs you to transfer station electrical loads from the Auxiliary Transformer to the Startup Transformer using 101-8.

, . v.-, , . . . - - . . . - . - , , -

. PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

- JPM NO. 6 START TIME:

STEP 01 Verify the AUXILIARY TRANSFER SWITCH is b the AUTO S U position.

STEP 02 - Verify Bus L10 is energized. S U STEP 03 Close Brkr L1106, START UP SUPPLY BRKR. S-U

' STEP 04 Verify Brkr L1102, NORMAL SUPPLY BRKR, opens S U automatically.

STEP 05 Take Brkr L1102, NORMAL SUPPLY BRKR, to TRIP to reset S U position indicating flags and clear annunciator.

STEP _06 Close Brkr L1009, START UP SUPPLY BRKR, S U STEP 07 Verity Brkr L1202, NORMAL SUPPLY BRKR, opens S U automatically.

STEP 08 Take Brkr L1202, NORMAL SUPPLY BRKR, to TRIP to reset S U position indicating flags and clear annunciator.

i STOP TIME:

i

..."""* END OF JPM """""

i.

l l____..____._______________ . _ _ . . . . . . . _ . , , . . _ _ . _ _ - . _

PERRY POWER PLANT r

INITIAL LICENSE EXAMINATION JOB PERFO3MANCE MEASURES (WALKTHROUGH)

JPM NO. 6 USE

REFERENCE:

YES NO -X QUESTION 1: When sychronizing the main generator with the grid you have selected i SS10 with the Sync. Selector switch, matched voltages and frequencies, and closed S610, you then reach towards S611 and !

attempt to close it but it does not close. What could be the reason for !

this? ;

ANSWER 1: The Sync. Selector switch must also be selected to S611 for it to be !

closed by the switch.

K/A: 262001K5.05

REFERENCE:

1013, Power Changes, step 4.3.15 CANDIDATE RESPONSE:

SAT UNSAT

, , - , - ,_ - _ . . - _ _ , . . . - , . . ._,..._,-,..;..._,..__,._L.. . . . , ,,.m._.. , , . . _ .. . . . , _ .,r.,_,,._., , , .

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 6 USE

REFERENCE:

YES NO X OUESTION 2: While performing synchronization with the grid with the main generator how is main generator frequency of the generator varied in order to match it with grid frequency?

ANSWER 2: Main turbine speed must be varied to change turbine generator frequency and this is performed by using the INCREASE or DECREASE Load Selector pushbuttons.

K/A: 262001A4.05

REFERENCE:

1013 SDM N32/C85 CANDIDATE RESPONSE:

SAT UNSAT

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

- PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 7 !

i I

JOB PERFORMANCE MEASURES JPM No.7 i

JPM

Title:

Bypass A Failed LPRM 0817A Plant

Reference:

Sol-C51(APRM), section 7.3 NUREG

Reference:

215005A4.04 ,

Method of Testing: Simulator Time for Completion: 15 minutes l

wyer--<r -g =y v e w-gy-gg--q,-g-- ,---gw 'g.yw-,-yw--+ -m -wvt- s w-. , wry g .e -w- ,~,s-,,,y=m. ,, -3,-my9-.g,y% _

--rw-+w.g- y .cuy.-,_. 9- g-w-s.

PERRY POWER PLANT .

i INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 7 l Task Standards: Bypass LPRM 0817A. l Required Materials: None Simulator Setup: Reset simulator to 1019, inseri malfunction NM03:LO817A (none 0) 0 0 0, reset all annunciators. ,

READ TO Tile CANDID ATE 1 Wil.L Dl!SCRlllE Till? INITIAL CONDITIONS, Tile TASK To llE PERFORhiED AND Tile INITIATINO CUES. I WILL INDICATE WilETilER Tile TASK IS Tlh1E CRITICAL. YOU S110VLD Sih1ULATE Tile REQUIRED ACTICNS AS IF DIRECTED llY PL ANT PROCEDURES OR SillIT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED 11Y Tile EXAhilNER. DO NOT ASSUh1E Tile EXAhilNER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAh11NER INDICATES OTilERWISE. INFORhi Tile EXAhilNER Will!N YOU llAVE Coh1PLETED Tile Initial Conditions: Reactor is operating at 100 % power, when LPRM 0817A fails downscale. The I&C Supervisor has determined this to be a faulty buffer '

card that will take approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to replace.

Initiating Cue: Unit Supervisor directs you to bypass LPRM 0817A.

i s

l' . - . . .- . .. - . --. - .-

f PERRY POWER PLANT INITIAL LICENSE EXAMINATION i JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 7 !

START TIME:

STEP 01 Determine the associated APRM Channel for the LPRM to be S U i bypassed per Attachment 1; LPRM to APRM Channel Assignment.

(The appropriate APRM Channelis channel"H")

STEP 02 Determine if the associated APRM Channel will be operable after S U the LPRM is bypassed. j NOTE: An APRM channelis Inoperable if there are less than 2 LPRM inputs per core level or less than 14 LPRM inputa to an APRM channel.

(Cue: If asked by the candidate there are no other LPRM's inop.) ;

' STEP 03 Notify Reactor Engineering of the intent to bypass a LPRM so a TIP S U ,

Trace may be performed, if necessary. i (Cue: Notify candidate as Rx Eng. that TIP Trace will not be necessary.)

STEP 04 If desired, bypass the associated APRM Channel. S U (Cue: As Unit Supervisor Inform candidate that you dg want the APRM bypassed for this evolution. This will necessitate that the candidate l enter section 7.1 of the instruction.)

STEP 05 Place NEUTRON MONITOR BYPASS,1C518-S6, in CH H". S U STEP 06 Ensure the BYPASS half of the APRM DNSC/ BYPASS status light S U backlights white on H13 P680 and the APRM Bypass status light on APRM Mon Panel,1H13-P672 comes on.

S *EP 07 Inside the associated APRM Power Range Neutron Mon Panel, S U 1H13-P669,1H13-P670,1H13-P671, or 1H13 P672, place the LPRM Card Mode Switch for the LPRM to be bypassed in BY.

NOTE: The bypassed LPRM's white bypass status light on the display section (top) of the panel will come on.

jJ

PERRY POWER Pl. ANT INITIAL LICENSE EXAMINATION i

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 7 STEP 08 When in Mode 1 and Reactor Power > 25%, compare the APRM S U Channel with tha bypassedLPRM with Rated Thermal Power: .

a. ERIS screen #73 may be used. S U

b. If not within *2% of Rated Thermal Power, perform S U l SVI-C51.T0024.

STEP 09 if the associated APRM Channel was bypassed, return to service per S U Removing an APRM Channel From Bypass.

I STOP TIME: :

I

.......*" E ND OF JPM """""

1 w e- -- .

n- e -

,,.-,e-y- .p:, w - ,, .,n-- n - , -w ,,-,,~..r - - , - , ,e, --,r-r, w,-a.,-cw- - , , , . - -

PERRY POWER PLANT '

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 7 USE

REFERENCE:

YES_ NO X QUESTION 1: The following plant conditions exist:

Rx power is 100 % when APRM "A" fails upscale. Describe the plant response if the P680 operator's first action is to take APRM "A" to BYPASS.

ANSWER 1: The Rx Recire Automatic Flow Demand Limiter (AFDL) would switch from an APRM input of Channel"A'to Channel"E"which senses actual Rx power. Because actual Rx power is lower than the upscale power sensed by APRM "A"it will remove the negative bias being fed into the Rx Recirc system and allow the pre-transient flow demand signal to be passed, causing Recirc flow control valves to open and a corresponding power increase.

K/A: 215005G0010

REFERENCE:

SOI C51, Precautions and Limitations SDM-C51(APRM)

CANDIDATE RESPONSE:

SAT UNSAT l

f l

1

i PERRY POWER PLANT INITIAL LICENSE EXAMINATION i JOB PERFORMANCE MEASURES (WALKTHROUGH) l JPM NO. 7 :

USE

REFERENCE:

YES NO X !

QUESTION 2: If Reactor power were 75% and Reactor Recirc flow were 70% _

l Mlbm/Hr, what would you expect your APRM Thermal Scram setpoint to ,

be?

ANSWER 2: Scram setpoint = (.66Wr + 64%) ;

= (.66 x 70) + 64

= 46.2 + 64 ,

=110.2% Rx Power-There is a 111% clamp on this but this isn't in effect at this power / flow. 3 K/A: M 5005K4.02 ,

REFERENCE:

SDM C51, Table 1 CANDIDATE RESPONSE:

l P

s b

SAT- UNSAT_

rr w1r w -=- wev y 2-= sw w+w --r = weer- w,a-r-i-3--*w~w-c=y,-,-w-g- ~ r ..w%-ve---, ,,--e-*,4 4 > - ~ ~ * + ---- e 's-w-.- ,1--+e---~ ---<r------r- - - - - - - -w'~ --*

r k

i PERI Y POWER PLANT !

lNITIAL LICENSE EXAMINATION t JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 8 .

A f

i i

I JOB PERFORMANCE MEASURES ;

JPM No.8 t

i I

h 6

r

,r JPM

Title:

Hydrogen Recombiner A Startup Post LOCA F

Plant

Reference:

sol-M51/56, Rev. 6, TCN 6 . :

PEl M51/56, Rev,3 1

NUREG

Reference:

223001A4,13 Method of Testing: In-Plant

- Time for Completion.= 15 minutes T

l

,-.,,-g

- .iv, . , -r e ,.-+y.6rm.%,. ,,,-c., .-- , , -.m,, , - . , gw.g-.-e .,+y -- e<%.,-rrer,- w

---w--e g -*+ *'

PERRY POWER PLANT !

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 8 i

Task Standards: Locally start the "A" Hydrogen Recombiner and warm up to operating j temperature.

Required Materials: S ol M 51/56 ,

i Simulator Setup: N/A (In plant)

READ TO Tile CANDIDATE I WILL DESCRIBE Till! INITIAL CONDITIONS, Tile TASK TO DE PERFORhiED AND Tile INITIATINO CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL.

YOU S110UI.D Slh1UIATl! Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROL,S UNI.ESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUMilTilE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile Rl! QUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER Will!N YOU llAVE COMPLETED Tile TASK.

Initial Conditions: Operating in accordance with PEl M51/56. Containment Hydrogen concentration is et 3% and increasing 0.5% per hour. Hydrogen Igniters and CGMS "A" are in operation. The initial Recombiner Power Setting for Recombiner "A" has been calculated to be 46.2 KW.

Initiating Cue: The US directs you as an in-plant operator to start up Hydroge i Recombiner "A" and adjust for proper operation.

e l'

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

f PERRY POWER Pt. ANT . i INITIAL LICENSE EXAMINATION !

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 8 r

START TIME: i STEP 01 - - Verified PWR ADJ potentiometer set at zero (000). S U STEP 02 Places PWR OUT SW in ON and verifies status light energizes. S U ;

STEP 03 Adjusts PWR ADJ potentiometer until 5 KW is obtained on .S U PWR OUT meter and holds for 10 minutes.

~ (Cue: Inform candidate 10 minutes have elapsed.)

STEP 04 Adjusts PWR ADJ potentiometer until 10 KW is obtained on SU PWR OUT meter arH holds for 10 minutes.

(Cue: Inform can. .ste 10 minutes have elapsed.)

STEP _05 Adjusts PWR ADJ potentiometer until 20 KW is obtained on PWR OUT S U meter and holds for 5 minutes.

(Cue: Inform candidate 5 minutes have elapsed.) i STEP 06 Adjusts PWR ADJ potentiometer until - 46.2 KW ls obtained on S U on PWR OUT meter.

STEP 07 Readjusts potentiometer as required to maintain initial power setting S U (46.2 KW) until recombination temperature (1225'F.)

is reached.

(Cue: Point to temperature meter at 1225'F. and state temperature is increasing faster than before.)

STEP 08 Monitors and confirms Recombiner operation by observing a ramp S U '

temperature change when Recombiner temperature re6ches 1225'F.

STEP 09 Adjusts the potentiometer as required to maintain heater temperature S U 1225'F. to 1400'F.

STOP TIME:

e

.uuu..* END OF JPM ""'*""

I i

l i

PERRY POWER PLANT INITIAL LICENSE EXAMINAllON JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 8 USE

REFERENCE:

YES NO X QUESTION 1: Describe the operation of the Hydrogen Recombiners including tneir location and how they effect the Hydrogen concentration.

ANSWER 1: Located in the Containmant (664' elev.) the Hyd Recombiners reduce hydrogen volume by oxidation of hydrogen to form water. Alrflow through the recombiners is caused by natural convection. As air is heated it rises through the recombiner causing hydrogen to combine with oxygen. The mass of hydrogen should be reduced, which should reduce the hydrogen concentration and preclude a flammable mixture.

K/A: 223001K5.05

REFERENCE:

SDM-M51, section I.B.3 CANDIDATE RESPONSE:

SAT UNSAT

t I

o PERRY POWER PLANT '

INITIAL LICENSE EXAMINATION -

JOB PERFORMANCE MEASURES (WALKTilROUGH) '

JPM NO. 8 USE

REFERENCE:

YEs X NO l i

QUESTION 2: Given the following plant conditions: l A LOCA has occurred Containment pressure is 2.0 psig ,

Drywell hydrogen concentration is 3.0%

Containment hydrogen concentration is 8.8%

Div 2 Hydrogen ignitors are operating.

What is the correct action to take per PEl-M51/567 ANSWER 2: Prepare vent paths using PEl SPl 7.1, Preparation for Containment Venting .

K/A: 223001A1.05

REFERENCE:

PEl M51/56 ,

CANDIDATE RESPONSE:

P SAT- UNSAT

+ 9: +- w w y mn --

--,_7%.. sgrw ,. .,-m-

,w4,- -

m .. -,r- -%2, , , , - -,-*w,- ,,.m---e.

1 PERRY POWER PLANT - i

,lNITIAL LICENSE EXAMINATION l

JOB PERFORMANCE MEASURES (WALKTHROUGH) )

JPM NO. 9.

1 L

JOB PERFORMANCE MEASURES JPM No. 9 JPM

Title:

Manually Initiate CO, for the Control Room Subfloor Areas Plant

Reference:

SOI P54(GAS), Rev. 0 ,

NUREG

Reference:

. - 286000 SG-9

i. -

4 Method of Testing: Plant c

Time for Completion: 15 minutes k

J

.m, .y ,r- -a,-,.w- + , . . - ,. . -- ,. ,, _ _ , . , _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ _ . _ _ _ , . _ . , _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

=. =. . _. - _ -

PERRY POWER PL ANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHRCUGH)

JPM NO. 9 Task Standards: Candidate willinitiate a CO, dump by local operation of the Master and Selector valves.

Required Materials: sol-P54 (GAS)

Simulator Setup: N/A (In Plant)

READ TO Tile CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORMED AND Tile INITIATING CUES. I Wil L INDICATE WilETilER Ti1E TASK IS TIME CRITICAL, YOU SilOULD SIMULATE T11E REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFI' StirERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY TIIE EXAMINER. DO NOT ASSUME TIIE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTIIERWISE. INFORM TIIE EXAMINER WilEN YOU llAVE COMPLETED TF Initial Conditions: Electrical equipment fire in Control Room Subfloor area requires Control Room evacuation. All ONI-C61 Immediate Actions are complete.

Initiating Cue: The Unit Supervisor directs you to manually initiate a CO2 dump for all the Control Room Subfloor areas.

PERRY POWER PLANT INITIAL UCENSE EXAMINATION

-JOB PERFORMANCE MEASURES (WALKTHROUGH)._

JPM NO. 9 '

P

. START TIME:-

STEP 01 Open the Selector valves by amashing breakglass and rotating pilot. S U valves clockwise. (Three valves, PS4-F3451, F3461, F3471)

- STEP 02 Hold the Se' r as open for 4 miteutes each then close the valve.S U (Cue: Inform candir finw nolce can be heard.)

STEP 03 : If no CO, dit t e o.emn .save Selector Valve pilot valves open.. S U

. STEP 04 Open the Master 2 4 , 4 ashing breakglass and rotating pilot S U valve clockwise. ,, .'

34-F3441)

STEP 05 Hold Master Valve Pilot Valve open for discherge time listed (4 minutea$ U then shut Master Valve Pilot Valve, STEP 06 - Shut the Selector Valve pilot valves.. (Three valves) S U i STOP TIME:

4-

. . . . . . . . . . END OF JPM " " ' " " '

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 9 USE

REFERENCE:

YES NO X OUESTION 1: Assume that you are in the Div.1 DG room assisting with the monthly Surveillance diesel run. Suddenly you hear the CO, predischarge horn sounding. How long do you have to exit the diesel room before the CO2 discharge occurs?

ANSWER 1: 60 seconds K/A: 286000K4.02

REFERENCE:

SOI-P54 (GAS)

CANDIDATE RESPONSE:

SAT UNSAT

i PERRY POWER PLANT +

INITIAL LICENSE EXAMINATION ,

JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 9 USE R'EFEREN'CE: . YES X NO OUESTION 2: Assume that the plant is in Mode 4 with RHR "B" in shutdown cooling. A fire occurs in the Intermediate Building 599' elevation in Fire Zone Designator 018 2. The Unit Supervisor enters ONi P54. What would be the correct actions to take if RHR ."B" suddenly tripped and it is due to the fire, per ONI P547 ANSWER 2: Method A: Estehlish communications between the Control Room -

and an opero w et the pump brcaker EH1208. Operate pump from breaker EH1200 Method B: Lift lee.: (1E12A0851E) from relay 1E12-K198.

K/A: 286000G0001

REFERENCE:

ONI-P54, Attachment 1 and Attachment 2 CANDIDATE RESPONSE:

(

1 i

SAT UNSAT

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

PERRY POWER PLANT -

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH) -

JPM NO.10 .

t c

i

-1 JOB PERFORMANCE MEASURES JPM No.10-J JPM

Title:

- RHR Loop B Flood Alternate Injection Plant

Reference:

PEl SPl 4.2, Rev. 0

- NUREG

Reference:

295031 EA1.08 Method of Testing: Plant

_ Time for Completion: 20 minutes A

[ ;.

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.10 Task Standards: Line up RHR "B"in the Containment Flooding Mode frorr outside th6 control room.

Required Materials: PEl SPI 4.2 RHR Loop B Flood Alternate injection Simulator Setup: N/A (In-plant)

READ TO Tile CANDIDATE I WILL DESCRIBE Tile INIDAL CONDITIONS, Tile TASK TO BE PERFORMED AND Tile INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL.

YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SilIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU liAVE COMPLETED TIIE TASK.

Initia; Conditions: Operating in accordance with PEl B13, a LOCA has occurred, no injection systems are available, alternate injection systems will be lined up. ESW Pump B is operating. The Div. 2 D/G is in secured status due to a governor failure and is not required.

Initiating Cue: The Unit Supervisor directs you as an in-plant operator to coordinate with the Control Room to perform PEl SPI 4.2, RHR Loop B Flood Altemate Injection.

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

- PERRY FOWER PLANT INITIAL LICENSE EXAMINATION

- JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.10 START TIME:

STEP 01 Contacts the Control Room. S U (Cue: Inform the candidate that steps 1.0 through 2.4 are complete.)

STEP 02 Verifies RHR B FPCC Supplement Cooling Viv 1E12-F0998 is closed, S U AX 599' C/03.

(Cue: Inform the candidate that steos 2.6 and 2.7 are complete.)

(RHR Pump B is secured and E12-F027B is open.)

STEP 03- Closes ESW Emg. Inject to Rx Vsl Loop Drain,1P45-F578, S U AX 599' B/03.

STEP 04 Unlocks and opens ESW Emg. Inject to Reactor Vessel isol 1P45-F072, S U AX 599' B/03.

STEP 05 Unlocks and opens - 260 turns ESW Emg. !nject to Reactor Vessel isol S U 1P45-F573 to open the valve 20%, AX 590' B/03.

STEP 06 Closes ECC HX B ESW Inlet 1P45-F5368, CC 574' C/05. S U N_QT.g- Div. 2 DG is in secured status per initial Conditions.

STEP 07 Unlocks and closes Civ. 2 Diesel HX ESW Outlet 1P45-F534B, E U DGB 620' A/02, Div. 2 DG Room.

(Cue: Inform the candidate that steps 2.11, ".12, and 3.2.1 are complete.)

(ECC to FPCC valves closed, ESW B is running, injecting inside

the shroud.) _

STEP 08 Places Remote Shutdown Switch for RHR B HX's ESW Outlet Valve ':i U 1P45-F068B in CLOSE to close the valve, CC620' B/03, MCC EF1D07 Comp. XL.

STOP TIME:

_ .......... EN D OF J PM ******

l l

I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION

~ JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.10 t

USE

REFERENCE:

YES NO X OUESTION 1: Assuming that RHR "B" was required for alternate injection, however the plant was also experiencing a Station Blackout, what water source, if any, .

would still be available for use in this injection flowpath?

ANSWER 1: Diesel Fire Pump

- K/A:- 295003AA2.04

REFERENCE:

PEl-SPI 4.2 CANDIDATE RESPONSE:

SAT UNSAT L

I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO.10 USE REFEREN E: YES NO QUESTION 2: Assuming that RHR "B" is lined up for alternate injection using the "B" Emergency Service Water Diesel Fire Pump as its source of water. Reactor pressure starts a slow increase due to an ATWS. At what RPV pressure would you expect to see injection from this alternate irijection lineup to stop?

ANSWER 2: Approximately 94 psig Rx pressure.

t K/A: 203000K1.17

REFERENCE:

PEl 813 RPV Control (Non-ATWS) or (ATWS)

CANDIDATE RESPONSE:

SAT UNSAT

+

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

i INITIAL SUBMITTAL OF SCENARIOS - PERRY - AUGUST 1997 EXAM.

e

~ - - m + e .-- ,. g

SIMULATOR SCENARIOS E PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97f Scenario No. 1 Page 1 of 5 Initial Conditions: Rx at 75% CTP. nower ascension in procress. IIPCS is OOS Es ent No. Malf. No. Event Type Eg ent Description i R Power increase of 25% using Reactor recirc flow 2 I CIU)ll Flow Controller fails downscale ic$n$o 3 NhiO4A I APRhi "A" fails upscale causing AFDL ekt. to runback power 4 N Reset % scram 5 N Restore Recire. FCV hydraulics 6 Trg E3 h1 Earthquake causes an instrument air leak in containment, DW press.

increases 7 RDIS hi ATWS 8 ,p Q C Ctmt. And DW Inst. Air valves fail to auto close IP521%86 9 RDl6 C Leak of Scram Discharge Volume into the containment 10 C^r P' I Sequential loss of RPV level indication lescl_ toss il g,' Ig. C Two ADS valves fail to open This scenario contains a loss of air which is #9 & 10 events on our IPF1PRA.

Crew Turnover: Plant at 75% pwr, with a power ascension in progress.101-3 is complete thru step 4.5.28.

Currently on step 86 of the BOC pullsheet. IIPCS system is OOS due to failure ofits monthly SVI last night. Was declared inop at 0000 today. A8er you take the shiR continue the power ascension to 100%

power by increasing Recirc Flow to 90% power with no ramp rate, then contact Rx Engineering for increase to 100% power.

Simulator Setun: Reset simulator to IC-17. Perform switch check, insert Batch 6te LNC-1, place danger tags on the llPCS pump ar.d ilPCS Injection valve i E22 F004, verify the following:

Active- RD15 @ 40% hlV05:lP52F0200 RV04:lB21F0041 A IIP 03 RDl6 @ 0% hlV05:!PS2F0646 RV04:lB21F0041F llP08 ROR infotags Triggers- El: CN02:lCl lR0600,0%

E2: Nh104 A,100%,10sec ramp E3: 09A19DS13 ON AN:P680 7A[56] ON imf IA02B 25 30 0 09A19DS19 ON AN:P680-8A[9] ON 09A19DSil ON AN:P680-8A[15] ON 09A19DS17 ON AN:P680-8A[16] ON 09A19DS03 ON 09A19DS09 ON 09A19DS15 ON E4: CAEP: levei_ loss

l ES-391 Operator Actions Form ES 301-4 Scenario No.: 1 Event No.: 1 Page .2., of _,L Event

Description:

Reactor nower ir}srease of at least 5% usine Reactor Recire flow. Aner power has been increased by at least 5%. CRDil Flow Controller 1Cl1-R600 fails downscale.

Sim. Operator: Aner nower increase of at least 5% and when cued by lead examiner initiate Triceer El to fail controller ICl l-R600 dowmcale.

Time Position Applicant's Actions or Behavior US lirief shift on power increase SO Increase reactor power with recirc flow control valves BOP Responds to annunciator lill3-P601-22-A3, "lligh CRD Mechanism Temperature" Recognizes CRD flow controller output at minimum value Informs US US Directs BOP to restore CRDil parameters to nonnal using manual control of controller 1Cl1-R600 Verifies l&C contacted for repairs

- I&C willinform llS that it appears to be a problem with the output of the Auto Card, controller is not operable in auto, manual operation will be required, repairs should be complete in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

l

._ . . _ . . .- ___ . =_ - .- .- . - = . . ..

ES-301 Operator Actions Form ES-301-.I Scenario No.: 1 Event No.: 2.3.4 & 5 Page.3. of _J 4

Event

Description:

APRM "A" will fail unselle. causine AFDL in control. a Reactor Recire FCV nmback. a half-scram. and onerators will be reauired to hydraulically lock-out the FCV's to ston the power transient Sirnulator Operator: When cued by lead examiner initiate Triceer E2 to fail APRM "A" Unscale with a 10 second ramn. Provide I&C suonort durine eauinment failures and for HPU restart actions.

Time Position Applicant's Actions or Behavior SO Recognizes APRM "A" failed upscale and power decrease

. Informs US BOP Consults ARI H13-P680-4-E9 for "AFDL In Control" US Enters ONI C51, Unplanned Change in Rx Power or Reactivity Verifies plant is not in areas ofinstability on Power To Flow Map If enterred increased Awareness area will call Rx Engineering Consults Tech. Spec. 3.4.1 and 3.3.1.1-1

- - If crew scrams the Rx,let them discover & follow ATWS actions then initiate ***

carthquake per lead examiner's eue and go to next page in this guide.

US directs and SO's performs following actions SO Arm & Depress llPU Shutdown pushbuttons, power decrease stops BOP I&C contacted for repairs SO Bypass APRM "A" using SOI-C51(APRM), sect"n 7.1 SO Reset % scram A/C using SOI-C71, section 7.3 BOP Restart ilPU A & B, and the FCV Motion Inhibit using Sol-B33, section 4.2

**To support Recire FCV restoration the operators will need the following***

In S011133 section 4.2:

step 1. a No fuse failure lights on associated modicons inside P614 step 1. c. No Channel I or Channel 2 red lights on in P634 step 1. f.1) a) & b) Subloop 1: Isolate coil 115 Vac,1.6 amps / Operate Coil 0 Vac,0 amps c) & d) Subloop 2: Isolate coil i15 Vac, 0.6 amps / Operate Coil 0 Vac,0 amps step I. f. 2) a) & b) Subloop 1: Isolate coil 115 Vac, 0.6 amps / Operate Coil 0 Vac,0 amps c) & d) Subloop 2: Isolate coil 115 Vac, 0.6 amps / Operate Coil 0 Vac,0 amps step 5 As PPO in field report 0 psig on local gauges Ill33-R708A & R709A step 10 a.1) & 2) Subloop I: Isolate coil 0 Vac, 0 amps / Operate Coil 115 Vac,0.6 amps

3) &4) Subloop 2: Isolate coil 0 Vac, 0 amps / Operate Coil i15 Vac,0.6 amps step 10 b.1) & 2) Subloop 1: Isolate coil 0 Vac, 0 amps / Operate Coil 115 Vac,0.6 amps

3) &4) Subloop 2: Isolate coil 0 Vac, 0 amps / Operate Coil 115 Vac,0.6 amps

L%301 Operator Actions Form FS301-4 Scenario No.: 1 Event No.: 6. 7. 8 & 9 Page.4_ of_L Event

Description:

Earthouake occurs (<OBE) causine vellow lichts on the Seismic Panel H13-P969 and startine an Instrument Air leak in the containment.

Sim. Operator: }Vhen cued by lead examiner initiate Triccer E3 for earthauake. instrument air leak in containment. and Scram D:scharce Volume break into the containment.

wu.

Time Position Applicant's Actiorn or Behavior SO Responds to annunciators Ill3-P680-8-B3, SEIShilC ALARM P969, and H13 P680-8-C3, SEISMIC MONITOR TRBL Recognizes increasing containment and drywell pressure Infomu US BOP Checks panc! lil3 P969, informs US of all yellow lights, no red lights Responds to annunciators lill3 P870-2-B4, Parallel IA lidr Press Lo, then lill3-P680-5-D6, Scram Viv Air Ildr Press to Informs US US Enters ON1-D51, Eanhquake, verifies earthquake is less than OBE Directs Supplemental Actions of ONI D51 Enters ONI PS2, makes plant announcement regarding loss of air Verifies all available air compressors running as necessary Orders Rx to be shutdown either by a manual scram or a Fast Rx Shutdown, enters ONI-C71-1, Reactor Scram SO Inserts a manual Rx scram or Fast Rx Shutdown (depends on US order), places Rx Mode Switch in SilUTDOWN Recognizes incomplete scram, APRM's not downscale, infonns US Inserts a manual ARI, recognizes all rods not fully inserted, APRM's not downscale, infomis US US Enters PEl-Bl3, RPV Control (ATWS)

Enters PEl-T23, Containment Control Directs operators to spray containment at 2.25 psig, and secure at 1.75 psig Ifdetennines can't maintain PSP, goes to PEl-B13 to ED SO Uses PEl-SPI section I to insert control rods

- If eued by lead examiner, simulator operator can increase containment pressure by varying malfunction RD16.

IC-301 Operator Actions Form E9-301-4 Scenario No.: 1 Event No.: 10 & 11 Page 5. of_$_.

Event

Description:

Seouential loss of all RPV level indication and durine the ensuine emercenev depressurizaticin two of the ADS valves will fail to open and two additional SRV's will have to be manually opened by the operator.

Sim. Operator: When coed by the lead examiner initiate CAEP/ level loss to seauentially lose level indication. . _.

Time Position _plicant's Actions or Behavior SO/ BOP Recognize RPV level instruments failed upscale or downscal Informs US US Enters PEl B13, Einergency Depressurization BOP Attempts to ED, recogaizes 2 ADS valves fail to open, informs US US Directs BOP operator open additional SRV's to achieve 8 open BOP Opens two SRV's,infonns US 8 SRV's open US Enters PEl Bl3, RPV Flooding Enters Pf" N151/56, flydrogen Control BOP Starts the hydrogen igniters US When RPV pressure is <120 psig:

Directs htSIV's, htSL Drains, RCIC Stm Isol valves closed Commences injection to establish / maintain h1ARFP SO Injects w/RFDP's and/or bypasses hiFP L8 trip, injects with h1FP BOP Injects with LPCI (outside the shroud), per US direction Terminatine Criteria: Crew is elTectively feeding the Reactor Vessel to maintain RPV pressure

>l20 psig but as low as possible.

Emercency Plan: Site Area Emergency: CSI AS2

- - END OF SCENARIO ***

v

,5ijMULATOR SCENARIOS g - : PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/2287m Scenario No. _2_ _ Page 1 of 6 Initial Conditions: Rx at 100% CTP. Division 1 outage in nrogress Event No. Malf. No. Event Type Event Description 1- N Performance of SVI R10 T5217

^ FW litrs 5 A&6A level control valve fails closed, isolating litrs 2 ,g L I 5A & 6A 3 R Power decrease to s95%

4 N litr. cither restored to service or lined up per SOI-N27 5 cso2 ic34 I RFPT"A" fails upscale w/a 1 mh. ramp R0601A 6 y',3; C Trip ofIsophase Bus Duct Cooling Fan "A" due to loss of head em iru. on TBCC pump "A", auto swap to "B" fan COOlA 7 TF, 1;S" M Lightning strike in transformer yard causes a LOOP 8 ZDIR4M6 C/M Div 2 DG starts then trips on overspeed, causing a SBO 9 C llPCS Injection valve fails to auto open, can be man opened QF22

--- - If crew pursues, can restore ofTsite power via Unit 2 Startup Transformer to either Bus L10 or to Bus Elll2---

"*This scenario is representative of a PNPP IPFJPRA dominant accident sequence.

Crew Turnover: Plant is operating at 100% power, all rods out, on last step of EOC pullsheet. A Division 1 outage is in progress with the following systems OOS and danger tagged: RilR A, LPCS, RCIC, Div I DG. This crew should plan on the WO's being brought to the control room this shift to commence work.

SVI-R10-T5217 is due in two hours and should be performed as soon as you take the shift.

Simulator Setun: Reset to IC-19, perform switch check. Initiate batchtile LNC-2, place RCIC in secured status per SOI-E51, close E12-F004 A, tag out RCIC, RHR "A", LPCS< Div. I DG, place OOS switches for each in INOP, verify correct malfunctions inserted ner attached batchfile summary:

Active MV04:1E22F0004 AV02:lN25F0280A AV02:lN25F0330A CB04:1R22LI004 Triggers El AV02:lN25F0340A E2 CN02:lC34R0601 A E3 ORIRI DOOI A, OFF CP03:lP44C0001 A E4 TF01:15 lS0002 ior ZDIR43S6 3:00TD i

ES301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 1 Page 1.of 6

.i Event

Description:

HOP Operator will nerform SVI-R10-T5217. Electrical Distribution System Enercization Check due to inon Div 1 DO.

Simulator Operator: Sunnly info. to DOP enerator to sunnort the SVI when asked for Unit 2 Control Room indiqgions.

Time Position Applicant's Actions or Behavior US Directs BOP operator to perform SVI-R10-T5217 sections 5.1.3.a,c,d, & c only due to being in T.S. 3.8.1, action b and to meet SR 3.8.1.1 HOP Performs SVI.R10-T5217 applicable steps

- - Simulator driver will have to supply the following information that would be found in Unit 2 Control Room when asked by BOP:

Il u s Tic H rk r L2 001...................................C LOS E D Mn Startup Supply Brkr L2003................ CLOSED H u s Tic H rk r L2 004...................................O P EN Control Sw Flag... . ... .... ....... GREEN Interbus Xfrmr Hrkr L2006........... .......... CLOSED 2 R2 2-R012 Volts.............. ........................ 13.5 Kv Hus Tie Hrkr El12101................................. CLOSED No annunciators on 21113-P870-1 A US Reviews / Approves SVI-R10-T5217, verifies in compliance w/f.S.

l l

ES-301 Operator Actions Form ES-301-4 l

Scenario No.: 2 Event No.: 2. 3. & 4 Pagelof 6 1 Event

Description:

liich Pressure Feedwater lleaters S A & 6A level coes hich causine an extraction steam isolation to those heaters.

Simulator Operator: When cued by the lead examiner insert Triceer El to override F0340A closed.

Time Position Applicant's Actions or Behavior HOP Respond to Ili litr Level annunciators, inform US ofIIcater 5A &

6A isolation US Enters ONI-N36, Loss of Feedwater Heating Directs SO to reduce power to s95% using Rx recire flow Directs supplemental actions of ONI N36 Contacts Rx Engineer to verify no thermal limits exceeded Consults Ffl BIO, Final Feedwater Temperature Reduction Operation (will probabely request STA to perfomi FTl actions)

Consults Tech Spec 3.2.1, 3.2.2, 3.2.3, 3.3.1.1, 3.3.4.1, 3.3.2.1 using input regarding status of Thermal Limits SO Reduces Rx recire flow to achieve and maintain s95% power

- As I&C inform US that you will send a crew to investigate, but that you suspect **

a possible common mode failure with both litr SA and 6A level controllers.

BOP Verifies 5A&6A Ileaters isolated per Attachment 3 of ONI-N36 As directed by US will either complete heater isolation or retum heaters to service per SOI-N27 l

E%301 Operator Actions Form ES301-4 Scenario No.: 2 Event No.: 5 Page 4_ of 6 Event

Description:

Failure unseale of the "A" Reactor Feedwater numn flow controller 1C34 R601 A on lil3-P680.

Simulator Operator: When cued by lead examiner initiate Triccer E2 to fail the "A" RFP Controller to 100% with a 1 minute ramn.

s Time Position Applicant's Actions or Behavior SO Respond to panel indications or annunciators 1H13 P680-3-A9

" REACTOR LEVEL HI L7" and/or lill3-P680-3 B7

" FEED FLOW / STEAM FLOW hilShiATCil" to recognize abnormally high output from RFPT "A" Inf? mis US US Enters ONI-C34, Feedwater Flow Control hialfunction Directs SO to place ilFPT "A" on manual speed control dial and place RFP "A" Flow Controller in hianual Directs ONI C34 supplemental actions Verifies I&C contacted for repairs SO Places "A" RFP to lowest form of control As directed by US, balances flow on RFPT's A&B

- As I&C report that fault is in FW flow signal to RFP "A" controller and**

that repairs will take approximately one shift, there is no problem with Manual Speed Control Potentiometer.

US hlay elect to stay with both RFPT's (ie base loading the "A" RFPT and keeping "B" RFPT on the hiaster Level Controller) or may decide to go down to the hiotor Feed Pump with RFPT "B" on the hiaster Level Controller.

1

1 ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 6 Page _$_ of 6 Event

Description:

Trin ofIsonhase ilus Duet Cooline Fan "A" Simulator Operator: When cued by lead examiner initiate Triceer E3 to override R13-C001 A fan control switch to OFF. and to input a head loss on Turbine lluildine Closed Cooline Pumn "A" 1 P44-C001A.

1 Time Position Applicant's Actions or Behavior SO Respond to annunciators 1lil3-P680 9-D1 "lSOPilASE BUS CLG TRBL" and lill3 P680-9-El "lSOPilASE STBY FAN AUTO START" Verify R13 "B" fan auto starts in approx. 45 seconds Refers to ARI's for alarms US Verifies electric plant stable Verifies Maintenance and/or I&C contacted for repairs BOP Dispatch PPO to the fan and fan breaker (FIC06-Xil)

- As a PPO report Notes that even though TBCC pumps A&B are running there is low discharge pressure indicated on TBCC pump "A" Informs US US Directs BOP to shift to TBCC pumps B&C running BOP Shifts TBCC pumps per SOI-P44, section 5.1.2

Simulator Operator- Delete override on annunciator illl3-P680-9-D1 whenTHCC* **

Pump "it" is started If TBCC pumps are not shifted within 10 minutes bring in annunciator till3 P680-9-CI.

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ES-3010perator Actionsform ES-3014 Scenario No.: 2 Event No.: 7. 8. & 9 Page.5_of 6 Event

Description:

Lichtenine strike in transmission vard results in a loss of Unit 1 Startun Transformer and a LOOP. Div 2 DG initially starts then 'rins causine a Station illackout. the HPCS Iniection valve fails to auto open but can be manually opened if attempted by the enerator. If crew oursues it tbav can restore offsite power to Unit I via Unit 2 Startun Transformer.

Simulator Operator: When cued by lead examiner initiate Trincer F4 to simulate lichtenine strike and kxkout relav for bus I,10 to initiate I OOP Afler Div 2 DG has auto staried. it will nm for 3 minutes and then trin niacine the niant in a station blackout.

Time Position Applicant's Actions or Behavior US Responds to scram by enterring ONI-C71-1, Rx Scram Responds to LOOP by enterring ONI-RIO, Loss of AC Power Enters PEl-B13, RPV Control (Non-ATWS) on level 3 Enters PEl-T23, Containment Control on high SP temperature Directs that Unit 2 Startup Transformer be cross-tied with bus L10 or is used to reenergize bus EH12, per ONI-RIO, Att.10 SO Recognizes scram, carries out actions for ONI-C71, Rx Scram Infonns US that no feedwater pumps available to feed the Rx Verifies Rx shutdown Monitors available plant instrumentation per ONI RIO, Att.12 llOP Responds to loss of offsite power annunciators i Determines status of Emergency Diesel Generators ifIIPCS receives an initiation signal, notes injection valve E22-F004 does not auto open, informs US, attempts to open valve manually, is successful, maintains RPV level per US direction Recognizes trip of Div. 2 DG, informs US Per US direction perfomis applicable actions in ONI-RIO to

, maintain Div. 3 DG running, and to restore offsite power via Unit 2 Startup Transformer Dispatches PP_O's to Div 2&3 DG's

- As PPO, after trip of Div 2 DG, report oil all over floor of DG Room **

- Override annunciator till3-P680-7-A3 to "on" following scram.**

Terminatine Criteria: Crew has power, pressure, and level stable and have developed an action plan to restore AC power to either bus L10 using Unit 2 Startup Transformer and/or to bus EH12 using Unit 2 Startup Transformer.

Emercency Plan: DSI due to power not being restored to either bus EH11 or Elll2 within 15

minutes.

l ****END OF SCENARIO ****

l=

I SIMULATOR SCENARIOS

~

PERRY NUCLEAR POWER PLANT EXAM COMMENCING 08/22/97D Scenario No. 3 Page 1 of 6 Initial Conditions: Rx nower at 33% CTP power ascension in procress Event No, Malf. No. Event Type Event Description 1 N/R Shift Rx Recirc pumps to fast speed 2 ' 1 Failure of DW pressure instruments causes an inadvertant n0b'TL ih21N0f>67R IIPCS initiation 3 nyQ C llPCS Injection valve blows fures while stroking open 4 ,yg2 ,3 I 110t Surge Tank level controller fails downscale 5 ED167. M/C Fire in MCC F1 DOS (one of the loads is Recire isol. valves) 6 T{Igj'g' C Recire pump "B" outer seal begins to fail (DW pressure increase) 7 33,3, C Rx mode switch fails in "RUN" position 8 RY 2 i C paj}ure of RPS solenoids to de-energize (RRCS works) 9 T1105B M Rupture of Recire pump seals 10 C MSIV's auto close when Rx pressure decreases to 807 psig i1 cti 3 iR22 C Failure of breaker to close for Div. 2 essential bus Crew Turnover: A Reactor startup is in progress. Rx power is 33%,1013 step 4.5.5 is complete and you are on the MOC pullsbeet step 53. Upon taking the shift you need to shif1 Rx Recirc pumps to fast speed and then continue on with the plant startup.

Simulator Setun: Reset to IC-14, perform switch check. Insert Batchfile LNC-3, verify the following:

Active: RYO2:lC71 K14 A, K l4B, K14C, Kl4D, K l4E, Kl4F, K 14G, K1411 ORZDIC71S1 MV06:1E22F0004 CB03:1R22Elli116 ROR infotags Triggers: El BS02:lB21N0667L

. BS02:1B21N0667R, 1:00 time delay E2 CN02:1N21 R0475, 0%, 30 sec. ramp E3 EDl6Z E4 T1106B, 100 %, 1:00 ramp Til02B, 100%, 2:00 ramp Til05B, 100%, 1:00 time delay, no ramp PC01A, 100%, no TD or ramp

ES 301 Operator /crions Form ES-301-4 l

Scenario No.: 3 Event No.: 1 Page 2_ of 6 Event

Description:

Shift Rx Recite numns to fast sneed.

Simulator Operator: Role olav ns PPO durine this evolution. If US calls Rx Encineer for a final flow to attain. tell him to increase Recire flow to 58 Mlbm/hr followine the numn shifl. This should caual sprox. 47% Rx nower.

Time Position Applicant's Actions or Behavior US Directs SO to shin Rx Recire pumps to Fast speed in accordance with 1013, section 4.5.6 Provides oversight ofevolution Verifies loop flows balanced per Tech Spec 3.4.1 SO Shins Rx Recire pumps to fast speed per SOI-B33, section 5.i Ensures loop flows balanced

- As a PPO perform S011133 step 5.1.4 a & b using remote functions to operate the Power Interlock and Total Feedwater Low Flow Interlock switches as follows:

1Il33-S126A: TIIO6 11133-S12611: T1107 1Il33 S127A: T1108 1Il33-S12711: T1109.

E%301 0jv :to? Actions Form ES 301-4 Scenario No.: 3 Event No.: 2&3 Page _)_.of 6 Event

Description:

Failure of two llPCS DW Pressure bistables causes an automatic initiation of IIPCS. The llPCS Iniection valve.1 E22-F004 blows fuses as it strokes onen.

Simulator Operator: When cued by lead examiner initiate Tricrer El to initiate llPCS.

Time Position Applicant's Actions or Behavior BOP Responds to annunciators Recognizes initiation ofIIPCS, informs US Notes that ilPCS Injection Valve,1E22-F004 lost indication When directed by US, secures liPCS pump, and if directed places llPCS in secured status SO Verifies that feedwater system, power, pressure, and level are stable US Enters ONI-E12-1. Inadvertant Initiation of ECCS/RCIC Verifies by two independent indications that llPCS initiation is incorrect Directs BOP to override IIPCS pump control switch to STOP Consults 'l ech Spec 3.5.1 for llPCS inoperability Action B.1 - Verify RCIC operable w/i one hour Action B.2 - Restore IIPCS to operable w/i 14 days Verifies Maintenance and I&C contacted for repairs May direct BOP to place llPCS in secured status

ES 30) ()perator Actions Form ES-301-4 Scenario No.: 3 EventNET 4 Pagelof 6 Event

Description:

Hot Surce Tank level contraller outnut fails downscale causine level to decrease.

Simulator Operator: When cued by lead examiner initiate Triccer E2 to cause llST level decrease.

Time Position Applicant's Actions or Behavior SO Respond to annunciators:

11113-P680-7-E12, CNDS DEMIN TRBL llil3-p680 7-D12, CNDS FLTR TRBL 1lil3 P680 2-E3, list LEVEL LOW Recognizes condensate flow at 0 gpm and outnut of11ST Level Controller at 0%

Informs US US Directs SO to attempt to restore and maintain IIST level using manual control Verifies I&C contacted for repairs SO Using IIST Level Controller in MANUAL or manual theostat for 1N21-F220 restores and maintains approximately 120" in llST BOP Contacts I&C for repairs Calls PPO to investigate Condensate local panel to clear trouble alamis

ES 301 Operator Actions Form ES-3014 Scenario No.: 3 Event No.: 5-11 Page l.of_f Event

Description:

A fire occurs in MCC Fl DOS which denereires the Recire numn "B" discharce valves. both seals fail on the "B" Recire numn.durine the ensuine scram RPS fails to work properly gad the onarator utilites the Redundant Reactivity Control System.ttshutdown the Rx. ',fSIV's auto close at 807 osic due to the Rx Mode Switch contacts beine stuck in the OPERATE nosition. and Div. 2 Fssential 4.16 Ky bus (Xill2) fails to onen darine the transient.

Simulator Operator: When cued by the lead examiner initiate Triceer E3 to cause a loss of FI D05.

When a PPO is dispatched to F1 D call the control room as S AS to renort smoke alarms on TPC 64I elevation and that you have niaced the fire bricade on Al ERT and are sendine a first resnonder. When cued by the lead examingr. initiate Triceer E4 to cause Recire numn "B" seal failures and a leak in the DW.

Time Position Applicant's Actions or Behavior SO/ BOP Respond to annunciators upon loss of power BOP Dispatch PPO to F1D

- - Simulator Operator: make fire report as stated in directions above.***

US Enters ON1-R23-2, LOSS OF A NON ESSENTIAL 480V BUS Enters ONI P54, FIRE SO Recognizes loss of power to Rx Recire pump "B" isolation valves Informs US BOP Upon being informed of Recire pump IIPU annunciators by SO, investigates, tells US that both FCV llPU subloops swapped to #2 in LEAD and #1 in MAINT mode

- - Simulator Operatm acting as the PPO sent to F1D,infoa m control room that***

there is smoke in TPC 647' caused probabely by FID05.The panelis now deenergized but is charred on the outside of the panel, it appears that the fire is no longer burning but the fire brigade is manning to assess the situation and have ordered him out of the area.

SO Responds to annunciator ilil3-P680-4-B10, RCIRC B OUTER SEAL LKG HI Notes No. 2 Seal Cavity pressure decreasing Receives annunciator lill3 P680-4-A10, RCIRC B INNER SEAL FLOW Ill/LO Notes No.1 Seal Cavity pressure decreasing Notes increasing DW pressure Informs US US Upon realizing that he has an unisolable leak orders a Rx Scram When DW pressure reaches 1.68 psig enters PEl-B13, RPV Control (Non-ATWS) and PEl-T23, Containment Control

Scenario No

3 Event No.: 5-11 Page_s_.of_n_-

l~ Time Position Applicart's Actlam or Behavior SO When directed by US inserts a manual scram Recognizes a failure of RPS to shutdown the Rx -

Manually arms and depresses the ARI pushbuttons Recognizes Rx shutdown, informs US US Directs stabilization of power, pressure, and level per PEl's

- At 807 psig in the RPV, MSIV's will auto close due to failure ofIhe Rx Mode ***

Switch, this should occur due to either the DW leak or as crew depressurizes the RPV.

BOP Recognizes closure of MSIV's, inferms US US Redirects pressure control from Bypass valves to SRV's and orders RilR to be placed in Suppression Pool Cooling Directs restoration of DW and/or Cntmt cooling per PEI's Directs BOP to initiate Containment Spray at 2.25 psig in Cntmt.

Evaluates elevated Containment pressure to maintain below PSP BOP Places RilR "A" and/or "B" in SP Cooling Restores DW and Cutmt cooling Initiates Containment Sprays, secures if Cntmt pressure <l,75 psig Terminatine Criteria: RPV being cooled down at 100 F/ hour to mitigate efTects ofleak in the drywell. Containment pressure is stable by use of containment sprays. Drywell cooling restored and as Containment temperature and resources warrant restoration of containment cooling.

Emergency Plan: Alert cal

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

SIMUL,ATOR SCENARIOS

. PERRY NUCLEAR POWER PI;, ANT EXAM COMMENCING 98/12/97 : ;

Seemtrio No. 4 Page .,_L of 5 initial Conditions:lb at 100% CTP. HPCS is DOS Event No, Malf. No. 1: vent T3 pc b ent Description [

l N/R Reduce power using Recire flow to s90%

2 N Perform SVI C85 T1314 (llypass valve cycling) 3 TC0413 C Ilypass valve sticks open ,

4 ,cf'y 1 MSL Pressute Instrument falls (auto swap to stby inst.)

RpV "II" Level Inst. Reference Leg Line break in DW !

5 Til1911 1 6 M/C Spurious MSIV closure w/ ATWS 3

7 ,j"j7g C Motor Feed Pump fails to start 8 ((Cy .C SLC pumps fall to start 9 RC04 i RCIC speed control failure 10 Q',!$3, C Three SRV's fall to open "This scenario is similar to the ll3 IPlVPRA dominant accident.

Crew Turnover: Plant is operating at 100% power, all rods out on 110C pullsheet. IIPCS is DOS due to excessive vibration during last pump run SVI,last shin placed it hi secured status and danger tagged. As soon as you take the shin you need to reduce power to 90% and perform SVI-C85 T1314. SOC has been infbnned of the power decrease and has grid loads established for the power decrease. Following completion of the SV1 we plan on maintaining power at 90% until further notice from S9C.

Simulator Setup: lleset to IC 19, perform switch check. 'nitiate 11atch0le LNC-4, ve*ify the following:

Active 11V04:lll21F004111, lil21F0047D, ill21F000510 CP01:lC41C0001 A CP02:lC41C000ll!

ItD15, 40%

llP03 open, llP08 open C1107:lN27C004, Motor Feed Pump fails to start 11011 infotags Triggers . - til TC0411 (insert uhen 11PV #5 is full open)

!!2 PT01:lC85N0001 A, 100%

113 Tilt 911, 100 %, 5:00 ramp

!!4 MS05A,II.0,Il Spurious MSIV Closure RC04, 0%, 1:00 Time Delay

t E%301 (1perator Actions Form E%3014 Scenario No.: 4 livent No.: 1. 2. & 3 page 2 of 5 Event

Description:

Pow er decrease usine f(ceire flow to 90% nower. Performance of SVI C85 TI).1,L.

.Juibine livnassValve Onerabliny Test. however durine the test Ilvoan Valve #5 will not close.

Simulator Operator: When power has been decreased to s00% and wben the crew!iperformine SVI.

C85 T1314. initiate Tricter El when #5 livoass Valve reaches 100% onen.

Time Position Aryrlicant's Actions or Behavior ,

SO Decrease Rx power using Rx Recire flow Stop periodically to allow power / pressure / level to stabilize Stops power decrease at approximately 90% power Infonns US of completion of power decrease US Monitors power decrease At completion of power decrease, directs SO or llOP to perform SVI C85 T1314 SO /llOP Performs SVI CHS Tl314 Upon testing #5 llPV, recognizes that #5 IIPV does not close Ensures plant is r. table,infonus US Contacts 1&C for repairs US Instructs SO to stupend control rod movement (TS 3.3.2.1)

Instruct 3 IlOP to back out of SVI, may keep flypass Valves in TEST until problem can be diagnosed by I&C or the System Engineer Consults Tech Specs:

3.7.6 Restore w/i 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or <25% pwr w/l 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 3.3.2.1 Immediately suspend control md withdrawal Verifies l&C contac?cd for repairs

. - - . - . - . . - _ , ~ ~ _ . ,. _..__.__.-- _ ..- .. . - _ . _..___ - - . - .. .

KV 301 (hwator Actions Form EV.3(II 4 l I

4 Scenario No.: _4_ IIvent No.: 4 Page )__of 5 livent L'escription: failure unseale of the hiain Steamline Prr.ssure Tr nsmitter IC85h0001 A v.hich is

_ eurtently beine used as innut into the Steam Ilvoass Syriem. This failure will cause an auto-swanja ;

ibe "l1" transmitter but will cause no system neny.i ations.

Simulator Operator: When cued by the lead nnminer insert Triecer l'2 to insert failure of the"A" hiain Steamline ntnnusjtansmitter. !

Time l'oAltion Applicant's Actions or Beharlor SO Notes the red llGLTil Elll10lt light lit on 11113.p680 7 Verifies C85 has shilled to the "11" llegulator Verifies pressure stable and no transient in progreos Notifies US US Verifies plant stable Verifies I&C contacted for repairs

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

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

i l3-301 Operator Actiorn Form E%3014 Scenario No.: 4 th ent No.: 5.6.7.8.9.10 Page L of 5 Ih'ent

Description:

1he "11" les el instnnnent reference lec breaks in the DW causinn an increase in DW

. pressttre. As crew discusses their ootions for a shutdown a sourious closure of the MSIV's occurs.

Durine the ensuinn tran31r,t the followinc comoonent failures occur: the MFP fails to start. both SLC oumps fail to A,n. +. RCIC Governor control fails at masimum outout. and durine the limercency Deoressurization three of the ADS valves fail to ooen.

Simulator Operator: When cued by the lead examiner initiate Triccer I!3 to cause an instrument line break in the DW. As crew is discussine this event and when cued by lead examiner initiate Trincer I!4 le_Esnutios MSIV clesure and remainine malfunctions.

_ m Time Posillors Afy>licarti's Actiorn or Beharmr SO llespond to scram by taking actions per ONI C71 1 llecognize ATWS,infonn US Itecognize that Feedwater is unavailante, inform US Attempts to initiate manual Alti hianually inserts control rods per PEl SPI's llOP ltecognize hiSIV closure,infonn US llecognize 1(CIC governor failure,infonn US Starts St.C pumps, recognize failure, infonns US hiaintain pressure using SitV's pcr US direction Perfonus Emergency Depressurization per US direction itecognize failure of three ADS valves, opens additional valves per US direction to attain eight valves open Will have to initiate llCIC because it will not auto initiate with the "11" level instrument failed upscale Place 11.1111 in SP Cooling if directed by US Peribnn Tenninate and Prevent of ECCS systems per PEl's Lineup Rillt for outside the shroud injection per PEl's Starts hydrogen analyzers and hydrogen igniters per US direction US Due to increasing DW pressure directs plant shutdown belbre i

1,68 psig i linters Piil lil3,itPV Control (Non ATWS) then transitions to PEl lll3. IIPV Control (ATWS)

Enters PEl T23, Containment Control Enters PEl h151/56, Ilydrogen Control at level 1, directs liydrogen Igniters started Directs pressure control using SRV's. level control using itCIC, and directs SO to manually insert control rods Ibliowing ATt 3 Ensures SP temperature & RPV pressure maintained below IICL

. When level can't be maintained above -25" directs Emergency Depressuiization

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

Scenario No.: L IIvent No.: 4 P ge L of 5 1 i

Time IUsition Applicant's Actions or lichavior US Directs panel operators to terminate and prevent injection using )

Piil SPI's 5.2 and 5.3 due to ATWS, this must be complete l prior to directing Il0P to !!D When told by llOP that three ADS valves didn't open, directs llOP to open additional SRV's to attain eight valves open Directs operators to restore and maintain level > 25" using Feedwater and/or I.PCI injection outside the shroud once RPV pressure is less than MARPF pressure (120 psig)

Tenninatine Criterla: Phnt is stable following an timergency Depressurization with level being maintained using either the Rx 17eed flooster Pumps and/or IlllR lined up for outside the shroud injection. Control rods are being manually inserted to shutdown the Reactor.

Emergency Phtu: Site Area limergency CSI, AS2, AS3 1

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FINAL AS-ADMINISTERED OptRAllNG TEST FOR PERRY AUGUST 1997 gx y

/ 0 70

FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR PERRY riUGUST 1997 EXAM l

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PERRY POWER PIANT I

INITIAL LICENSE EXAMINATION i ADMIN.JPM NO A.1.a t

i t

JOB PERFORMANCE MEASURES JPM No. Admin A.I.a Questions

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PERRY l'OWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.I.a QUES'IION #1 USE

REFERENCE:

YES X 'NO_

QUESTION 1:

With the reactor in Mode 1, the on-coming Shin Supervisor discovers that only one Licensed Supervising Operator for his shin has shown up for work. The SS immediately starts taking action to find a replacement. In the meantime, shin tumover is completed and the entire off going crew leaves for home. A replacement Licensed Supervising Operator is found and reports to the control room I hour and 45 minutes later. Were any plant procedures or Technical Specifications violated during this time period?

CUE: If asked by candidate, state that the Fire Brigade Leaderis being stafTed by a non-licenseJ individual who is certilled Fire Brigade Leader. This reduces the requirement for licensed supervising operators t'o two vice three per PAP-0110, page 1, step ta.

ANSWER 1:

Tech Spec Admin 7.2 and Table 7.2.1-1 requires 1 RO

.. Tech Spec Admin 5.2.2.c allows one less than minimum, not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months -

provided immediate action taken to restore min shia complement PAP-0110, Shift Stafling and Overtime, states that one of the off going supersising operators should have been held over until a replacement arrived so this procedure was violated.

K/A: 294-001-A1.03

REFERENCE:

PAP-0110, Shin Stafling and Overtime Tech Spec 5.2.2 & 7.2 ,

CANDIDATE RESPONSE:

SAT UNSAT 2

l 1

1 1

PERRY POWER PLANT l INITIAL LICENSE 13 AMINATION -

ADMIN. JPM NO. A.l.a f

1 QUESTION #2 USE

REFERENCE:

YES NO X QUESTION 2: l PAP-0110, Shift Staffing and Overtime, defines cenain areas in the control room. One of ;

these areas is the " Operations Area". Where is the location of the " Operations Area" in the control room?

ANSWER 2:

See accompanying picture to assist in evaluating area defined as the " Operation Area",

t K/A: 294-001.Al.03 1

REFERENCE:

PAP-0110, Shift Stafling and Ovenime, Attachment 1, page 9 CANDIDATE RESPONSE: >

f SAT UNSAT b .

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OM1A: PAP-0110 Page 9 Rev. 4 Attachment 1 C0!TTR01, ROOM ARF.AS P869 P865 P840 P612 P864 PB68 w

P872 P866 5h:l: a-;- E00I POI' b$$ ,

%*II"1 1 c P821 P637

$/$E(( P630

!0kkQ!

PS23 P842 P800 P883 etG'-

P808 P807 P810 P809 P811 NW % W Jh% '

N x s s P870 2

\

P601 x_ h D , P00 B '

\ kN \h,,N wa P634 P619 P844 es*4 ses wx P600 xx P604 P804 PB03 P614 P672 P694 P653 P651 P613 P873 P625 P693 P671 P669 P691 P623 P632 P652 P642 P622 P692 P670 PS29 P621 PS:8 P655 P640 P610 P6 P631 Pb18 1

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PERRY POWER PLANT INITIAL LICENSE EXAh!! NATION ADMIN. JPhi NO. A.I.b .

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Jolt PERFORA1ANCE AIEASURES t

.IPhi No. Admin A.1.b n

t JPM

Title:

Evaluate SRM/IRM Overlap Readings During Rx Startup (Faulted)

Plant

Reference:

101-1, Rev 7, Cold Startup, section 4.2, steps 25-29, pgs.13 & 14 NUREG

Reference:

215003G013,294001 A1.02 Method ofTesting: Simulator Time for Completion: 15 minutes h .

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o PERRY POWER FIANT 1

INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.I.h Task Standards: Using criteria found in Integrated Operating Instruction 101 1, Cold Startup, determine that less than three IRM channels per trip system are operable and recommend a normal shutdown in accordance with 101-4.

Required Materials: None, this is to be conducted in the simulator during low-power JPM's Simulator Set up: Using the low power JPM setup in IC.25 insert the following' malfunctions:

NM01A 10.1 NM02A '4.4 NM01B 10.2 NM02B 11.9 NM01C 10.1 NM02C 4.ll NM01D- 10.13 NM02D 11.0 NM02E 13.4 NM02F 13.3 NM020 4.2 NM021I 11.6 READ TO THE CANDIDATE I WILL DESCRIDE THE INITIAL CONDITIONS, THE TASK TO BE PERFORMED -

N' AND TIIE INITIATING CUES. I WILL INDICATE WHETHER TiiE TASK IS TIME CRITICAL. YOU SIIOULD SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SHIFT SUPERVISION DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY TIIE EXAMINER. DO NOT ASSUME TIIE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICA'iES OTHERWISE. INFORM THE EXAMINER WilEN YOU IIAVE COMPLETED THE TASK.

1 Initial Conditions: The plant is conducting a Cold Rx startup, criticality has been achieved and power is increasing towards the point of adding heat.

Initiating Cue: The SO pulling control rods has asked for your assistance in determining proper SRM/IRM overlap.

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PERRY POWER PLANT l INITIAL LICENSE EXAMINATION ADMIN.JPM NO. A.2 l (RO Only) i l

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I J0ll PERFORMANCE MEASURES ,

JPM No. Admin A.2 (RO Only) l l

JPM

Title:

Write an Safety Tagout Plant

Reference:

Safety Tagging PAP-1401, Rev 8, section 6.4 NUREO

Reference:

294001Kl.02 Method of Testing: _in Plant Time for Completion: 20 minutes PERRY POWER PLANT l

INITIAL LICENSE EXAMINATION ADMIN.JPM NO, A.2 (RO Only)

Task Standards: Utilizing PAP 1401 prepare a Safety Tagout for Acid Pump OP21C0004r' to perfonn Repet. Task RS4 000242, Gearbox Oil change. (An example copy of a conectly witten tagout is available as a reference.)

Required hiaterials: Candidate will be expected to assemble all tagout papmvork.

READ TO TIIE CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORMED AND Tile INITIATINO CUES.1 WILL INDICATE WiiETliER Tile TASK IS Tlh1E CRITICAL. YOU S1100LD SlhiULATE TliE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR StilFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY TiiE EXAhilNER. DO NOT ASSUhiE TIIE EXAhilNER Wii.L ACCEPT AN ORAL DESCRIPTIO OF Tile REQUIRED ACTION UNLESS Tile EXAh11NER INDICATES OTilERWISE. INFORhi Tile EXAh11NER WHEN YOU llAVE C0hiPLETED TiiE TASK.

Initial Conditions: The plant is operating at 100% power. Repetitive Task R84 000242 is due to be performed on this shift.

Initiating Cue: The Unit Supervisor directs you to prepare a tagout to perform this repet, task and submit for review.

CUE: Iland copy of Repet. Task R84-000242 to candidate.

2

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN.JPM No. A.2

. (RO Only)

START TIME:

Denotes critical step

' STEP 01 Using the rupplied repetitive task the candidate should detemiine the S U need to tagout OP21C0004C for an oil change.

NOTE: Using the TENERA tagging system the candidate can search for prior tagouts for this Repet. Task.

STEP 02 The candidate shall use either the TENERA tagging system or manually S U write a tagout covering the following components:

Component Position

'02A OP21C0004C disconnect FIE04 D3 OFF S U

'02D OP21C0004C control sw. on lilSIP0017 'B' selected S U

'02C OP21F0592C(Suction valve) CLOSED S U

'02D OP21F0593C(Discharge valve) CLOSED S U Acting as the U.S. the examiner will accept the completed materials from the candidate.

STOP TIME:

* * ' * * * * *

EN D O F J PM * * * * * * * * *

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.2 (SRO Only)

JOH PERFORMANCE MEASURES JPM No. Adtnin A.2 (SRO Only)

D JPM

Title:

Review a Safety Tagout Clearance (Faulted)

Plant

Reference:

Safety Tagging PAP 1401, Rev 8, section 6.9 NUREG

Reference:

294001Kl.02 Method ofTesting: In-Plant Time for Completion: 10 minutes

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i PERRY POWER PLANT !

INITIAL LICENSE EXAMINATION ADMIN.JPM NO A.2

. (SRO Only) i Task Standards: The candidate shall review the supplied tagout for proper clearance and +

determme that all tags have not been returned and that independent verification of component restoration during clearance wasn't signed off.

Required Materials: Cleared tagout and tags are included with this JPM and are to handed to candidate during Initiating Cue.

READ TO TiiE CANDIDATE I WILL DESCRIDE TIIE INITIAL CONDITIONS, TIIE TASK TO DE PERFORMED AND TIIE INITIATING CUES. I WILL INDICATE WHETIIER THE TASK IS TIME CRITICAL. YOU SHOULO SIMULATE TIIE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SilIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICATES OTHERWISE, INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK.

Initial Conditions: The plant is operating at 100% power. Safety Tagout #00028909 has just come back from the field afler being cleared. ,

Initiating Cue: Acting as the Unit Supervisor complete the clearance review for this tagout and forward to the Control Room Assistant.

" CUE: Hand copy of tagout and tags to candidate, however do not give the candidate tag #9 unless candidate identifies this tag as missing.

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PERRY POWER PLANT {'

INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.2

. (SRO Only) ,

START TIME:

-

Denotes critical step

' STEP 01 Review tagout and determine that tag #9 is raissing. S U

- CUE: If candidate identifies tag #9 as missing hand this tag to him as Ifit was mistakenly not given to hir2.

' STEP 02 Determine that the independent verification ofcomponerf restoration is S U not initialed.

' STEP 03 Candidate shall determine that all tags that were removed were S U verified and initialed by an independent verifier, and then initial n'or this on the tagout coversheet.

' STEP 04 The candidate shall sign and date on the bottom line of the tagout S U coversheet under gy>g "ALL CLEARANCE REQUIREMENTS COMPLETE /rAO-OUT CANCELLED (US)".

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STOP TIME:

a a a a a a a a a

END O F J PM * * * * * * * * * *

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Y.

PERRY POWER PIANT INITIAL LICENSE EXAh!INATION

, ADh!19. JPA1 NO. A.3 JOli PERFORA1ANCE h!EASURES JPAI No. Adniin A.3 9

4 JPM

Title:

iivaluation Of A Radiation Work Pcimit Plant

Reference:

PAP-0512, Rev 5, Radiatioin Work Permit Program NUREG

Reference:

29400lKl.03 Method of Testing: In-Plant Time for Completion: 15 minutes

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADh11N. JPh! NO. A.3 Task Standards: Using RWP 97-00 or 97-02 be able to correctly determine correct dress-out requirements, highest dose rate in the area, expiration date, any hot spots.

Required Materials: None, use the actual RWP and survey map located at the RRA entrance, however copies of the RWP's and survey map are included for reference.

READ TO TIIE CANDIDATE ,

i WILL DESCRIBE THE INITIAL CONDITIONS, THE TASK TO LE PERFORMED l AND TIIE INITIATINO CUES. I WILL INDICATE WHETHER TIIE TASK 3 TIME CRITICAL. YOU SilOULD SIhfULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PL/ NT PROCEDURES OR SHIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAhflNER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICe .TES OTIIERWISE. INFORM THE EXAMINER WHEN YOU HAVE COMPLETED TIT 3 TASK.

Initial Conditions: The plant is operating at 100% power with the High Pressure Core Spray System out of service.

Initiating Cue: The Shift Supervisor directs you to locally observe the HPCS SP Suction Valve, IE22-F015, as it is stroked from the control room to verify that the vawe strokes smoothly with no binding or leakage. (If asked to see a Work Order you can prompt the candidate that the work package is at the valve.) As candidate reviews RW)' Survey map for the HPCS Pump Room, ask the questions on the following page.

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PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.3 START TIME:

Denotes critical step The candidate may ask IIP if there is a special RWP for this work, however we'are assuming entry under either the General RWP (97 000) or Ops. 97 002. These RWP's can be used to enter this room and perform this work activity and are hanging up outside the RRA for reference. The llPCS Pump room survey map is located on the hallway leading to the RRA entrance, this is the survey map that the candidate should use to answer the following questions. RWP 97 000 wili ng.L allow entry into the designated contaminated areas, but 97 002 would.

' STEP 01 Dress out Requirements: S U None (llP has the ability to require a dress-out above the requirements stated on the RWP since this is a general RWP and they may have up to-date data, therefore the candidate may want to query IIP about this before stating his answer.

D ' STEP 02 Highest Dose Rate in the area: S U 30 mrem /hr next to E22 F015 70 mrem /hr next to opposite wall

' STEP 03 When does the RWP expire? S U Either RWP expires 01 Jan 98

' STEP 04 Any hot spots located in the area? S U No STOP TIME:

} *aaaaaaa" END OF JPM aa"aaaaaa 3

Parry Nucles Irnt RADIATION WORh, (RWP)

Locatlon VAtl0US atlas RWP Nwe;er 970000 Rev.: 0 Descriptions ACCESS CONTROL C[N(RAL RWP

)

* *

This CRWP DOES woi peralt access into Containment * * *

This GRWP provides for RRA access control and governs activltles that have little or no radiological la$ect or persorrel dose as determined by Health Physics personnel.

Work cri tais RWP includes plant tours, mirer inspections, etnor work within clean Radletimt Areas, and hardling/ transport of radioactive materist within RRAs.

This CRWP AUTHORl!ES entry into the following areas:

A $

llVHRAs l l L2 LHRAs llL1LHRAs llHRAs

ll l1H l 6..l. ARAs. higher t han.1.0 e.e.. 4 6 HPCAs....

..... 6.le CAs........

... .... ........... ... ..D. AC....*

gWO NWart N/A Contacts C. REllER Contact Phone N d er: 5535 Work Codet RM

~ [Ccepletion Date: 01 JAN 1998 Person seen Estimate: 3100 Persor, wrs Estimate 88000 WORK AREA SURVEY See Posted Surveys DOSIMETRY REQUIREMENTS M G DRD .. ILD PROTECTIVE CLOTHING WORKER INSTRUCT 10N #2 LABCOAT WORKER INSTRUCil0N #3 , MODESTY CARMENi$

._ RESPIRATORY PROTECTION EQUIPMENT expirator Type None Work Steps 1 Notify HP prior to each entry into the RRA.

2 lewdlately notify HP of all unexpected M G alarins.

3 Notify HP prior to working on the DG Bldg. roof.

WORKER INSTRUCTIONS 1

2 Participate in a radiological briefing to discuss the nature of the work and the current radiological conditions.

A LABCOA1, C0110W tlNERS, and RUBBER or SURGEON *S CLOVES may Le used to transport radioactive materlat within RRAs, as directedli/* health Physics.

3 All personnel are encouraged to wear modesty garmerns, either long or short sleeved, while in the RRA. Modesty garments may also Le sttistituted for the labcoat for hardllng Red Materlat.

l

D'PitCIAL INDTRUCTIONS 1 No work in wry area wicro the generet crc 3 (ossNts esceeds 100 swem/hr.

2 tech irdivithat task asproved tsder this RWP will not eActed 0.025 p ree for the job. The task will not Irwolve entries into High Radletican, L,xked Nigh Rad, Not Particle Control. Nighly Centaminated: nr arent at,0 har:

3 Mlnleite crew stro armi star times when workirig '.n Radiation Areas.

, . Workers shall esplay good radiological work practices and ALARA technicpes while performing this work.

$ he transport or harriting of any Radioactive Material with contact dose rates eAcceding 5 anrem/hr.

6 20 (NTRY into a6y areas posted *RWP Required for Entry".

7 Nestth Physics should docunent the status of work perforced Iri accordarce with this GRWP on the RWP Narrative theet.

8 Health Physics should atterpt to unconditionally release areas on the Diesel Gen. Bldg. roof to f acilitate work.

Att persorret will perform a whole t<dy frisk prior to entering the released area (s).

91he dose t;udget for this GRWP is for the 1997 caterder year. The ALARA Coordinator will review this GRWP periodically to ensure that the dose remains within the dose budget.

GENERAL RP NOTES

%:alth Physics Survey f requency: As directed try MP $upervissuVT.I.C.

Worlth Physics Survelttarice Requirements: PERl(CIC ALARA Task Ntsders 6C VA*Mi Ne:lth Pnysics pertorvwl should consult the enclosed Health Physics Job Standard for all work on the Diesel Generator Battding.

RWP e?T 0000 0 PetPARIO Bf _ /k 'h / Dates /2.t - 6'[ MP PLANN!hGt h Date / 6 NP $UPERVl& ort _

I Date s M*/b"kb- PHP APPROVAll Al !/% Dates a V!A itRMINAltD BY Datet eJ f

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Par Nucir r Pow 3r Plant RAPIA ION WORK PERMIT (RWP)

Ltc pions VARIOUS AREt,$

WW N der: 970002 Rev.: 0 Description OPIRAilDNS CCNtsAL RWP Opetations Section Fersonnet (incltding fire Protection personnel) to perform systers tagging, fitt & vents, Repetitive issks kFEPETS), Work Order tasks, Survelttance testing (Svls), PHis, Pils, Sols, librications,oll changes, oil senpling, plant runds, inspections, walkdowns, alors response, system flushes, training, fire watches, maintenance / minor maintenance tasks ard transport of

' radioactive material within RRAs as approved try Health Physics ord all other necessary support activities.

N 5

t k LU co This CRWP AUTHORI2E$ entry into the following areas l

,' 3 llVHRAs llL2LHRAs lXlL1*LHRAs lXlHRAs Q/

ll lyl llA *

. .. 4 4.HP.CAs

. ....... 4 4..MCAs........

... 4 4.. ras.highe.r

... ..... .than..1

. .. 0.D.AC MWO Nupd.ers N/A Contact Sniff SUPERVISOR Contact %one Ntsters $647 Work Codes.0P Completion Date: 01.JAN 1998 Person-mree Estimates 8200 Person k s Estimate: 32000 WORK AREA SURVEY <

See Posted surveys DOSIMETRY REQUIREMENTS

> G DRO TLD PROTECTIVE CLOTHING WORKER INSTRUCil0N #2 IVLL PROTECilVE CL0fMING WORKER INSTRUCTION #3 DOUBLE PROTECTIVE CLO1NING WORKER INSTRUCTION #4 PLASTIC Sulf WORKER INSTRUCTION #5 LABCOAT M tIR INSTRUCil0N #6 LABCoAT WORKER INSTRUCTION #7 MODESTY GARMENTS WORKER INSTRUCTION #3 MODESTY GARMENTS WORKER INSTRUCTION #9 FACE SHIELD AND/OR DUST MASK RESPIRATORY PROTECTION EQUIPMENT Respirator T n e: None

e JtCp3 ry MP pelor to each entry into the RRA.

sdietely notify MP of all unespected M G alarms.

MER INSTRUCTIONS Participate in a redlological briefing to discuss the nature of the work and the current radi: logical corditions.

TULL PR0f tCilVE CLOTHING respired for work in Contaminated Areas. FULL PR0f tCilVE CLQ1NikG consists of covers (ts, hood, cotton litiers ard rtAtser gloves, cloth shoe ccvers and rutters.

DCUBit PCs thwld be considered den GENERAL contam levels exceed 100 kopm or areas have a seccad Step-Of f

Pad.

DOUBLE PCs is dwbte c9veretts & ruther gloves, ord double cloth shce covers .

A PLASTIC $Ulf may te required when water present. HP will prescribe the use of PLASTICS but t:llt limit use to situations when it is absolutely necessary. Reusable rain suits should to used whenever possible.

. A LABCoAT may to substituted for IULL PCs provided:

a) HP $@ervision/Ilc give concurrence ,

b) no physical work (i.e. cliebing, crawling, kneeling etc.)

c) cmtaminatIon Leveie ere < 50,000 dpn/100 sq. cm. %y>*

i A LABCOAT, COTTON LINERS, and kUBBER or $UR0tDN8$ GLOVis may te used to trs esport radioactive reterlet within RRAs, as directed by Health Physics.

$NC)? $lt(VE modesty garmente may be considered PCs lf t o.) contam. levels are <10,000 dpn/100 sq cm, b.) they are used for valve manipulations /walkdowns (N0 uutK) ard c.) Health Physics concurs

%(

) LowG $LttVE modesty garments may be considered PCs Ifs s.) contam, tevets ere <50,000 durv100 sq cm, ty, b.) used for L.cf work orly ord c.) Realth Physics concurs 7 A FAtt$NILLD ard/or DU$f MA$K may be required by Health Physics to control f acial contaminetlen.

10 Covera ll cuf f a witt te tsped when:

e.) contamination levels are > 100,000 dyn/100 s : cm; b.) strerasous activities will be performed; or c.) as directed by Health Physics 11 HP persorciel may alter the PC recpirements by making an entry in the RWP Warrative Sheet detalling the altered dr:ss requirement ord the reason for the change.

12 entrants into Locked Hlgh Radletion Areas are responsible to control access to those areas t to close, tatch, 4,rd tock the barricade @on exiting the eres. Return HR$ keys tr to exiting the RRA.

13 DOSE RATE miter le reqeired for entry into Nigh Radiation Areas. An ALARMlWG DO$1MEf tR ney Le used in lieu of a doss rate seter if redlological conditions are known ard workers are made aware of them.

14 Th3 work crew ord/or work crew supervisor are responsible for the disposition of ett Redioactive Materiet generated by the work crew.

SPECIAL INSTRUCTIONS 1 toch Irdivickial task arproved under this RWP will not eAceed 0.100 p rerm f or the job.

2 Minleite crew site ord stay times when trorking in Radiation /Nigh Radletion Areas.

3 Ensure that att required engineering controls are avaltable and operable before correnencing work on this RWP.

4 Pro stage att tools and equipnent to minimise work delays in Radiation /Migh Radiation Areas.

5 Utiltre Low Dose Waiting Areas whenever work stonages/ slowdowns occur, 6 DO NOT RtHOVE or ALTER Ternporary $hlending without express Health Physles Supervisjon/T.I.C. or Health Physics Planning permission.

7 23 anticipated personnel contaminations s're expected or approved on this RWP to reckJce dose.

8 Workers shall ecoloy good redlological work practises ord Al, ARA techniques while performing this work.

9 Inrediately exit the area ord contact He when dose rates exceed 1000 mrem /hr OR when work area dose rates exceed those discussed dt. ring the redlological briefing.

10 Whste bcdy dosleetry should te positioned on the portion of the Aote body exposert to the highest dose rate.

11 DO NOT (Kli FRCol THE NUf 0L0lWG PLATFORMS INIO THE OVERHEAD at!AS W11HOUT THE kWOWLEDGE AWD APPROVAL OF NEALTH PHY$lC$ $UP[RVI$10N/I(CHNICIAN IN CHARGE.

12 WO Fersonnet shall reach more than sin (6) feet above the floor in the Contairvnent Building without the knowledge ard antovat of Health Physics.

13 ALL PER$0NWEL who enter the Contairvnent Building ord who trust leave the nornut walkway access crt:s (i.e. go across/under hardralls etc.) $RALL obtain the approval of Health Physics PtlNt 10 gerforming the task.

14 LEMets should te used senever possible to reckre the time spent in Radiation /High Radiation Areas by eliminating th3 scaffolding erection /removat time.

15 Th3 Collective Dose estisute for this CRWP is for the 1997 celerstar year. The ALARA Coordinator will gerledically review this GRWP to ensure that the Colle:the Oose rmains within

tablished tsabets, ad the At Ae4 seview e9/ 002.

CENERAL RP HOTE] l Mealth ehysics $urvey f re<chency As directed ty MP Stgervision/ilC.

'Me'alth Physics surveltlance te<Nitecentti Pitt00lt ALARA f ask kuders f.C VA UP kWP #97 0002 0 PetFAtt0 Bis /A. . Iff p.g., //. ,

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i RADIOLOGICAL SURVEY REPORT '""V'*"-

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R .:

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN.JPM NO A.4 (RO Only) 3 JOll PERI'ORMANCE MEASURES JPM No. Admin A.4 (RO Only)

)

- JPM

Title:

Perform Sit. Accountability Actions from Outside Control Roorp Plant

Reference:

EPI 85, Personnel Accountability NUREG

Reference:

294001 Al.16 Method ofTesting: In-Plant Time for Completion: Time critical JPM, must be completed within 30 minutes, 1

~

PERRY POWER PLANT

, INITIAL LICENSE EXMllNATION ADMIN. JPM NO. A.4 (F0 Only)

Task Standards: Candidate murt go to either the OSC accountability card reader located in the TSC hallway, or the control room accountability card readers (either Unit 1 or 2) located just inside the control room doors, and simulate inserting his keycard into the reader. This action is required to be complete within 30 minutes of announcing site accountability.

Required Materials: None READ TO THE CANDIDATE I WILL DESCRIBE THE INITIAL CONDITIONS, THE TASK TO B'd PERFORMED AND Ti!E INITIATING CUES. I WILL INDICATE WHETHER THE TASK IS TIME CRITICAL YOU SIIOULO SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SHIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL q DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICATES q OTHERWISE. INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK.

Initial Conditions: You are the Operations Foreman and are out in the plant observing one of the PPO's take the Nuclear Island Rounds-Inside.

Initiating Cue: Suddenly you hear the Shin Supervisor announce over the PA that he is declaring the site to be in a Site Area Emergency and that Site Accountability is required. Display the required actions you would take to demonstrate Site Accountability, and inform the examiner how long you have to do this.

9 2

i i

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN.JPM NO. A.4

, (RO Only)

START TIME:

Denotes critical step

STEP 01 Candidate must go to either the Unit 1 or Unit 2 control room, or go S U to the OSC accountability card reader located in the TSC hallway.

(Cue: Alternate method is to have Shift Supervisor submit badge number of crew member for accountability. If candidate mentions this, ask him if there are any other methods available to perform accountability actions.)

STEP 02 Candidate must simulate inserting and then withdrawing his keycard S U into one of the Emergency Plan Accountability Card Readers listed above.

' STEP 03 Candidate must correctly state that the time required for him to S U complete Site Accountability actions is 1Q minutes.

STOP TIME:

* * * * * * * *

EN D O F JPM * * * * * * * * *

3 ;

PERRY POWER PLANT I INITIAL LICENSE EXAMINATION ADMIN.JPM NO. A.4 (SRO Only)

JOB PERFORMANCE MEASURES JPM L. Admin A.4 (SRO Only)

JPM

Title:

Emergency Plan Chssification, Associated Paperwork, and PAR's Plant

Reference:

EPI-Al, Emergency Action Levels NUREG

Reference:

294001 A1.16 4 Method of Testing: Simulator Time for Completion: 15 minutes

) I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.4 (SRO Only)

Task Standards: SRO candidate will ac;arately classify event as a General Emergency using EPI-Al, fill out the Ge6.cral Eaiergency documentation including the Initial Notification Forms, and make Protective Action Recommendations.

Required Materials: Emergency Plan Papenvork packets are pre-staged in the simulator Unit Supervisor's desk.

READ TO THE CANDIDATE 1 WILL DESCRIBE THE INITIAL CONDITIONS, TIE TASK TO DE PERFORMED AND TIIE INITIATING CUES. I WILL INDICATE WHETHER THE TASK IS TIME CRITICAL. YOU SHOULD SIMULATE TIE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SHIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE h EXAMINER. DO NOT ASSUME THE EXftMINER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICATES OTHERWISE. INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK.

Initial Conditions: See the following page for the Initial Conditions.

t Initiating Cue: The Unit Supervisor informs the Shift Supervisor that plant conditions have stabilized. As the Shift Supervisor classify this event and take all appropriate actions.

) .

2

PERRY POWER PLANT INITIAL LICENSE EXAMINATION

)- ADMIN.JPM NO. A.4

, (SRO Only)

)

INITIAL CONDITIONS: -

The plant is operating at 100% power. The Division 1 Diesel Generator is Out of Service and danger tagged due to a broken oil line that was occurred last shift Maintenance estimates 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to repair this problem.

The following sequence of events occurs:

0000 A plane crash in the transmission yard results in the following annunciators being received 1H13-P877-01-Cl Bus EH11 Stripped Undervoltage IH13-P877-02 Cl Bus EH12 Stripped Undervoltage lH13-P877-02 E2 DG Trip Protect Relay Lockout lH13-P877-02-A5 Diesel Generator Out OfService 0030 While fighting this casualty a loss of high pressure injection into the core requires you to line up Alternate Injection Systems. (

0045 RPV level decreases to <0" requiring you to enter Steam Cooling in PEI-B13, RPV Control Non-ATWS, 3

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ADMIN. JPM NO. A.4

, (SRO Only)

START TIME:

Denotes critical step CUE:' If asked by candidate, Maintenance Section estimates ihat the Div 2 Diesel Generator will be restored to service at 0600. If asked for Meteorlogical conditions ir. form candidate that the wind speed is 5.5 mph, and wind direction is coming from 3000

' STEP 01 Classify event as a General Emergency using DGl in the Emergency Plan Instruction EPI-Al, Emergency Action Levels.

' STEP 02 Correctly fill out documentation for the General Emergency including Initial ' 4 Notification Form (PNPP Form No. 7794) aad forward to communicator within 15 minutes ofclassification. (Our procedure requires completion of this form within 10 minutes in order for the comunicator to notify the State and Counties within 15 minutes) '

STEP 03 Correctly make Protective Action Reconunendations to Evacuate Subareas 1,2, and 3 using EPI A2 section 5.1.1 and/or EPI B-8 Attachment 2.

STOP TIME:

t

) a a a a a a a a a a END OF JPM * * * * * * * *

a 4

FINAL AS-ADMINISTERED WALKTHROUGH JPMS FOR PERRY AUGUST 1997 EXAM o

E

_ ___ _-__ __-_=_____-__ _ __ _ _

PERRY POWER PLANT c INITIAL LICENSE EXAMINATION JOli PERFORMANCE MEASURES (WALKTilROUGfi)

. JPM NO.1 JOll PERFORMANCE MEASURES JPM No.1 JPM

Title:

CRD Pump Trip Recovery ,

Plant

Reference:

SOI-C11(CRDil), section 7.2 NUREG

Reference:

201031A2.01 Method of Testing: Simulator Time tbr Completion: 10 minutes I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORM ANCE MEASURES (WALKTilROUGil)

. JPM NO.1 Task Standards: Start a tripped CRD p" np as directed by the US per sol-Cl 1(CRDil), section 7.2, CRD Pump Trip Recovery.

Required Materials: None Simulator Setup: Reset to IC-19, insert component malfunction CB01:lCl 1 C001 A then remove this malfunction, verify CRD PUMP A TRIP OIL PRESS LOW annunciator is lit, reset all annunciators.

READ TO TiiE CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORMED AND T11E INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU Si!OULD SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SHIFT SUPERVISION. DO NOT Ol'ERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF TIIE REQUIRED ACTION UNLESS THE LMMINER INDICATES OTiiERWISE. INFORM Tile EXAMINER WIIEN YOU HAVE COMPLETED THE TASK.

initial Conditions: The plant is operating at approximately 90% reactor power. CRD Pump "A" was in operation but inadvertantly tripped. The cause of the trip is known and has been corrected.

Initiating Cue: The Unit Supervisor directs you as the SO to perform a Trip Recovery of CRD Pump "A" and retum system parameters to Normal Operathg Values. 1 9

9 2

l 1

l PERRY POWER PLANT INITIAL, LICENSE EXAMINATION-JOH PERFORMANCE MEASURES (WALKTilROUGil)

JPM NO.1

- START TIME: -

Denotes critical step.

' STEP 01 Takes CRD AUX OIL PUMP A, Cll C002 'A" switch to START, S U and observes CRD PUMP A TRIP OIL PRESS LOW alarm clears.

STEP 02- Places CRD llYDRAULICS FLOW CONTROL in Manual, holds S U CLOSED 1Cl 1-R600 pushbutton until CRD FLOW CONTROL VALVE,1Cl1 F002A is fully closed.

STEP 03 Takes CRD PUMP A, Cl1 C001 A switch to START. S U

, ' STEP 04 Throttles open CRD FLOW CONTROL VALVE, Cl 1-F002A S U slowly until desired flow is retumed to pre transient setting on flow controller R600.

' STEP 05 Places CRD liYDRAULICS FLOW CONTROL, ICl l-R600, in S U AUTO, verifies parameters are stable.

STEP 06 Perfomi independent verification of required components. S U

. As US inform candidate that he will assign this to another RO.

STEP 07 Informs the Unit Supervisor that the CRD Pump has been restarted S U

and parameters retumed to normal.

STOP TIME:

* * * * * * * *

EN D O F .I PM * * * * * * * * *

v PERRY POWER PLANT INITIAL LICENSE EXAMINATION -

JOB PERFORMANCE MEASURES (WALKTilROUGil) -

.- JPM NO.1 -

USE

REFERENCE:

YES NO X QUESTION 1: . What would be the significance ofisolating a Recirc loop without securing CRDil seal purge flow?

. ANSWER 1: Overpressurization of a Recire loop could result if the loop is isolated and seal purge flow is still in operation.

K/A: 201001G0010

' REl-dRENCE: SOI-Cl1(CRDil), Section 2.0, P & L #2 CANDIDATE RESPONSE:

a.

4

-SAT UNSAT a

4

PERRY POWER PLANT -

INITIAL LICENSE EXAMINAT'ON <

JOB PERFORMANCE MEASURES (WALKTHROUGH)

. JPM NO,1 USE

REFERENCE:

- YESl NO- X _..

QUESTION 2: Describe what would you expect to see CRDH system flow do in the following two ;

situations with no operator action:

a. Immediately following a Rx Scram -

b. Following a scram reset?

ANSWER 2: a. CRDH flow will be maximum due to flow to the charging header, even though the Flow Control Valve is closed (flow is sensed upstream of the charging header which causes the FCV to close)

b. - Flow will remain at maximum while all of the accumulators are being recharged and then will slowly decrease back down as the FCV throttles to maintain flow at the tapeset value of 60 gpm.

K/A: 201001A3.04

REFERENCE:

System Description Manual SDM-Cl1(CRDH), pages 12 & 14 CANDIDATE RESPONSE:

a.

p - b.

SAT UNSAT i

+

5

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORM ANCE MEASURES (WALKTIIROUGil)

. 'JPM NO. 2 JOB PERFORMANCE MEASURES JPM No. 2 i

i JPM

Title:

Feedpump Shift on Startup Level Controller

- Plant

Reference:

SOi-C34, section 7.4.2 NUREG

Reference:

259002G009 Method ofTesting: Simulator Time for Completion: 15 minutes I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTilROUGil)

. JPM NO. 2 Task Siandards: Successfully shift from RFPT "A" on the Startup Level Controller to the MFP on the Startup Level Controller.

Required Materials: None Simulator Setup: Reset simulator to IC-25, take MFP control switch to start, open the MFP and RFPT "A" recire flow control valves to 100%, reset all annunciators.

READ TO TIIE CANDIDATE I WILL DESCRIBE TIIE INITIAL CONDITIONS, T11E TASK TO BE PERFORMED AND THE INIMATING CUES. I WILL INDICATE WHETliER THE TASK IS TIME CRITICAL. YOU SHOL'LD SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OP SHIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER INDICATES OTHERWISE. INFORM THE EXAMINER WHEN YOU HAVE COMPLETED Tile TASK.

Initial Conditions: The reactor is operating at approximately 12% power. RPV level is being maintained by RFPT "A" on the Startup Level Controller in AUTO. The Motor Feed Pump has been manually started per SOI-N27.

Initiating Cue: The Unit Supervisor directs you to shift to the MFP on the Startup Level Coptroller and leave RFPT "A" idling at 3300 rpm until the System Engineer contacts the control room with fmther instructions.

W 2

s = a - n n

..k, a - -

aA 4 - A..n- --u>. - e - n~, s .w = .

-m PERRY POWER PLANT

- INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (M ALKTilROUGil)

. JPM NO. 2 START TIME:

Denotes critical step STEP 01 Place the MFP in service per SOI-N27. (This step is fulfilled by the S U initial conditions)

STEP 02 Verify the in service RFPT is being controlled by the STARTUP RX S U LEVEL CONTROL,1C34 R602,in AUTO.

STEP 03 Slowly raise the MFP Dow using the manual pushbutton of MFP FLOW S U CONTROL,1C34R601C, to maintain a constant reactor water level of 1 ? inches above the tapeset point of the STARTUP RX LEVEL CONTROL,IC34 R602.

' STEP 04 S U Adjust RFP A FLOW CONTROL, IC34 R601 A, horizontal output f meter to zero.

STEP 05 :Jull the RFP DEV METER A, IN27-R426A, using the RFPT A S U MANUAL SPEED CONTROL Dial, IN27-R425A.

STEP 06 Place the RFPT A GOV MODE CONT, IN27-S50, to MANUAL, S U putting RFPT A under control of the MANUAL SPEED CONTROL Dial,1N27-R425A.

'STEPOT Place STARTUP RX LEVEL CONTROL,1C34-R602 in MANUAL. S U

' STEP 08 Use the manual pushbuttons of STARTUP RX LEVEL CONTROL, S U 1C34-R602, to match its horizontal output meter with the horizontal output meter of MFP FLOW CONTROL, IC34-R601C.

STEP 09 Select the MFP with the STARTUP FDW PUMP SELECT SWITCH, S U IC34-S3.

3

PERRY POWER PLANT INITIAL LICENSE EXAh11 NATION JOB PERFORhf ANCE 51EASURES (WALKTilROUGil)

JPh1 NO. 2

STEP 10 Use the STARTUP RX LEVEL CONTROL, IC34-R602, tapeset to S U null the controller deviation (red arrow in green band) and place it in AUTO.

3

STEP 11 Slowly adjust the STARTUP RX LEVEL CONTROL,1C34 R602, S U tapeset to restore level to the normal control band. (192-200")

NOTE: The last step in the SOI is to shutdown RFPT "A" per SOI N27, however the initiating cue directed the candidate to maintain the RFPT at 3300 rpm until the Responsible System Engineer can contact the control room. This will be accomplished as fo' lows:

STEP 12 Using the h1ANUAL SPEED CONTROL Dial, IN27 R425A, decrease S U RFPT "A" speed to achieve 3300 rpm.

This willleave the candidate in the last ster. of this SOI until the System Engineer comes to the control room.

STOP TINTE:

* * * * * * * *

EN D O F J Phi * * * * * * * * *

9 4

I PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOll PERFORM ANCE M EASURES (WALKTilROUGil)

JPM NO. 2 USE IEFERENCE: YES NO X QUESTION 1: While operating at 100% power with both RFPTs on the Master Level Controller RFPT "A" trips and the MFP auto starts. Assuming that RFPT "A" cannot be restored, what will be your long-term power limitation?

ANSWER 1: (ONI N27, Feedwater Pump Trip, Section 3.0.2 states that you have a power limitation of 90% with one RFPT and the MFP. Once you exit the ONI procedural guidance is given by SOI C34, Feedwater Control System) Section 2.0, step 2 states that with the resultant pump combination power is limited to 89% as follows:

RFPT "A" 71 %

MFP 23_%

94 %

-5% for reserve capacity during level transients

=89%

K/A: 259002G0010 & 25900200001

REFERENCE:

SOI-C34 Feedwater Control System, Section 2.0, P&L #2 CANDIDATE RESPONSE:

SAT UNSAT

PERRY POWER PLANT INITIAL LICENSE EXAMINATION .

' JOB PERFORMANCE MEASURES (WALKTilROUGil)

. JPM NO. 2 -

USE

REFERENCE:

YES -X NO 4

QUESTION 2: The plant is operating steady state at 100% power with both RFPT's on the Master Level Controller utilizing input from Narrow Range "B" Level Instrument. A failure of the "B" differential pressure cell results in a slow increase in the differential pressure sensed by Narrow Range "B" Level Detector. Assuming no operator action, explain the plant response to this transient including any limits that might be exceeded if this automatic plant response did not occur.

ANSWER 2: -As D/P increa=s, indicated level decreases

--The Master Level Controller responds to this decreasing level by increasing feed flow into the Rx Vessel (indicated level 4, actual level t)

-Actual level will continue to increase until a level 8 scram and trip of the Rx Feed Pumps occurs

-Level 8 scram ensures that MCPR is maintained above the MCPR safety limit.

K/A: 25900200005

REFERENCE:

Tech. Spec. 3.3.1.1 basis, page B3.3 13 in the Tech. Specs.

CANDIDATE RESPONSE:

SAT UNSAT ___

6 9

w n ._-,.-- - _ - ,__.;- - - - - - c . - . - - -- _ - _ . _ _ - _ _ _

.1 ..

PERRY POWER PLANT INITIAL LICENSE EXAh11 NATION JOB PERFORh!ANCE A1EASURES (WALKTIIROUGil)

. JPA1NO.3 JOB PERFORh!ANCE SIEASURES JPA1 No.3 JPM

Title:

Shutdown to Standby AEGTS Train "B" With Both Trains Operating Plant

Reference:

SOI-hi15, section 6.2 NUREG

Reference:

261000A4.03 hiethod ofTesting: Simulator Time for Completion: 12 minutes 9

1

PERRY POWER PLANT INITIAL LICENSE EXAMINATION

.iOB PERFORMANCE MEASURES (WALKTilROUGil)

JPM NO.3 Task Standards: AEGTS Train "B" shutdown from running to standby readiness with associated heater off, and Train "A" running, maintaining Annulus Differential Pressure.

Required Materials: None Simulator Setup: Reset to IC-19, start MI 5-C001 B, energize M15-D001 B, clear all annunciators.

READ TO THE CANDIDATE I WILL DESCRIBE THE INITIAL CONDITIONS,THE TASK TO BE PERFORMED AND THE INITIATING CUES. I WILL INDICATE WHETHER THE TASK IS TIME CRITICAL. YOU SHOULD SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SHIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE >

EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF TIIE REQUIRED ACTION UNLESS THE EXAMINER INDICATES OTHERWISE. INFORM TIIE EXAMINER WHEN YOU HAVE COMPLETED THE TASK.

Initial Conditions: The plant is operating at approximately 90% power. Both Annulus Exhaust Gas Treatment System Fans are running to satisfy a Work Order retest.

Initiating Cue: The Unit Supervisor directs you to shutdown AEGTS Fan "B" to Standby Readiness.

2

l.. ..

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTilROUGil)

. JPM NO.3 START TIME:

Denotes critical step

STEP 01 De-energize AEGT ELEC llT COIL B, IM15-D001B, by taking S U control switch to STOP.

CUE: Five (5) minutes has passed.*

STEP 02 When the heaters have been cooled down for five minutes, confirm S U ANNUL US EXII FAN A FLOW LOW annunciator, window 1H13-P800-1 Al,is reset.

STFP 03 Hold AEGT FAN P 415 C001B, control switch in STOP. S U

NOTE: Candidate must b 4 switch in STOP for 1-2 minutes.*

' STEP 04 After allowing 1 to 2 minutes for the Train A dampers to reposition, S U check ANNULUS DIFF PRESSURE RECORDER, IM15-R016B to ensure annulus pressure is maintained between 0.75" and 1.0" H,0 vacuum.

STEP 05 Confirm ANNULUS EXH F 'I A FLOW LOW annunciator, window S U 1 H 13-P800-1-A1, is reset.

STEP 06 Take AEGT FAN B, IM15-C001B, control switch to STBY. S U STEP 07 Release AEGT FAN B,1MI5-C001B, control switch. S U STEP 08 Perform independent verification of the required components.

CUE: Acting as US inform candidate that you will get another operator to perform this step.

STOP TIME:

* * * * * * * *

EN D O F J PM * * * * * * * * *

3 1

-_ _ -__-_-__- ._ -. I

a

. PERRY POWER PLANT

INITIAL LICENSE EXAMINATION _

JOB PERFORMANCE MEASURES (WALKTIIROUGil)

JPM NO. 3 USE

REFERENCE:

YES NO X QUESTION 1: While operating at 100% power you receive the ANNULUS EXH FAN A FLOW LOW annunciator. When you go back to panel P800 you see that the standby AEGTS fan did not auto start. Assuming the system is operating properly, what could be the cause for this?

ANSWER 1: The low flow annunciator comes in at a low air flow rate (1600 scfm) on the -

running fan, however, the standby fan does not auto start unless flow 6egrades and senses a lower flow (1500 scfm) on the running fan,

-K/A: 261000K401

REFERENCE:

- Alarm response Instruction H13-P800-01 for annunciator Al.

CANDIDATE RESPONSE:

, SAT' UNSAT 9

4

+1 s - .. . . _ _ _ _ _ _ . _ _ . - - _ _ J

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFOR.\ LANCE MEASURES (WALKTHROUGH)

, JPM NO. 3

., USE

REFERENCE:

YES NO X QUESTION 2: Assume that you are standing at lH13 P800-1. Current Annulus Differential Pressure Controller, IM15 R060A, tapeset is -0.80" H2 O and actual Annulus differential pressure is -0.80 " H 0.~

2 Describe the expected response of the Annulus Fan Exhaust Damper, M15-F080A, and Recirculation Damper, M15-F070A, to do if you increased the tapeset value to -1.0" H2 0.

ANSWER 2: The recire damper, F070A, would throttle closed while the exhaust damper, F080A, would throttle open to increase the negative differential pressure in the annulus.

(They would then modulate as the annulus differential pressure approached the tapeset bvlue, to maintain that setting.)

K/A: 261000A3.03

REFERENCE:

SDM M15, section II.C.2 CANDIDATE RESPONSE:

SAT UNSAT 5

g -----_--_N

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTIIROUGil)

, JPM NO. 4 JOll PERFORMANCE MEASURES JPM No.4 JPM

Title:

Pull Fuses on Stuck-Open Safety Relief Valve Plant

Reference:

ONI B21-1, section 3.0, step 3.c and Attachments 1 & 2 NUREG

Reference:

239002A2.03 Method of Testing: Simulator Time for Completion: 8 minutes 1

~

l PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTIIROUGil)

.- JPM NO.4 Task Standards: Fuses pulled for Safety Relief Valve 1B21 F0051 A only.

Required Materials: None Simulator Setup: Reset to IC-19, decrease recire flow to achieve 90% power, insert override ior ZDIB21F0051 A OPEN, place both the "A" and "B" SRV Control switches on P601 and P631 in OFF, reset all annunciators.

READ TO THE CANDIDATE I WILL DESCRIBE TIIE INITIAL CONDITIONS, THE TASK TO BE PERFORMED AND THE INITIATINO CUES. I WILL INDICATE WilETHER THE TASK IS TIME CRITICAL. YOU SliOULD SIMULATE T11E REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY THE EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF TiiE REQUIRED ACTION UNLESS THE EXAMINER INDICATES OTHERWISE. INFORM THE EXAMINER WHEN YOU HAVE COMPLETED TIIE TASK.

Initial Conditions: Reactor is operating at approximately 90% power. SRV 1B21-F0051 A inadvertantly opened. The US entered ONI B21-1, SRV INADVERTANT OPENING / STUCK OPEN and has carried out all immediate actions with the exception of pulling fuses.

Initiating Cue: The US directs you to de-energize the SRV solenoids by removing the applicable control power fuses for 1 B21-F0051 A.

.e e

e 2

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKT11ROUGil)

. JPM NO. 4 START TIME:

Denotes critical step

' STEP 01 Using ON1 B21-1, SRV INADVERTANT OPENING / STUCK OPEN, S U Attachment 1, determine that the correct fuses to pull in lH13 P628 are F19 (F83 A) in the Left Panel and F6 (F84A)in the Right Panel,

' STEP 02 Using ONI-B21-1, SRV INADVERTANT OPENING / STUCK OPEN, S U Attachment 2, determine that the conect fuses to pull in iH13-P631 are F19 (F83B) and F20 (F848), both in the Lefl Panel.

STEP 03 Remove metal that could come in contact with electrical circuits. S U

' STEP 04 Using fuse pullers obtained from the horseshoe area of the control room, S U remove the associated fuses and their fuses covers.

STOP TIME:

s

* * * * * * * *

FM O F J PM * * * * * * * * *

3

l PERRY POWER PLANT I INITIAL LICENSE EXAMINATION -

JOB PERFORMANCE MEASURES (WALKTIIROUGil)

, JPM NO. 4

- (SRO ONLY)

USE

REFERENCE:

YES X- NO QUESTION 1: The plant is operating at 100% power with the HPCS System inop and in secured (SRO ONLY) status. After a Surveillance test 1B21-F0041F is declared inop, due to being mechanically bound in the closed position. What Tech Specs have applicable actions and what is the most limiting action required to be taken?

ANSWER 1: Tech Spec 3.4.4, Safety / Relief Valves A Potential LCO must be written for this.

Tech Spec 3.5.1, ECCS-Operating Action E Restore ADS valve ta OPERABLE in 14 days Action H Enter Tech Spec 3.0.3 Immediately - Most Limiting K/A: 239002G0005

REFERENCE:

Technical Specifications CANDIDATE RESPONSE:

SAT UNSAT 4

}

4 PERRY POWER PLANT '

INITIAL LICENSE EXAMINATION !

JOH PERFORMANCE MEASURES (WALKTilROUGil) )

. JPM NO,4 l (RO ONLY) l i

USE

REFERENCE:

YES X NO I QUESTION 1: While performing this task you inadvertantly pull fuses Fi l3 A & F1138 instead of [

(RO ONLY) F083 A & F0838. What Tech Specs would this put you into? !

I ANSWER 1: Candidate will use either the electrical prints or ONI D21 1, Attachment I to i detennine that pulling these fuses would inop. valve D21.F0510 w hich is an ADS l valve. i

. Candidate may mention being in a PLCO for Tech Spec 3.4.4, Safety / Relief, although we are meetirig the LCO and in no action statem:nts. <

With an ADS valve inop. we are also in Tech Spec 3.5.1, ECCS Operating

. .With a Low Low Set vrdre inep. we are in Tech Spec 3.6.1.6 Low. Low Set (LLS) ,

Valves.

\

K/A: 239002G0005 l t

REFERENCE:

Technical Specifications CANDIDATE RESPONSE: ;

SAT. UNSAT 5

W PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORM ANCE MEASURES (WALKTilROUGil)

, JPM NO. 4 USE

REFERENCE:

- YES NO_-- X QUESTION 2: Describe three independent methods that could be used to indicate that an open :

SRV hes closed.

ANSWER 2: Candidate may discuss any three of the followingi The "A" and "B" solenoids are deenergized as indicated by the red lights on panels P601, P628, and P631 extinguished

-The red light above the valve control switch on P601 is extinguished indicatirg that the pressure switch located downstream of the SRV senses less than 30 psig.-

-The tailpipe temperature for that SRV as read on recorder B21 R614 on P614 is decreasing.

An existing steam flow / feed flow mismatch as read on recorder C34 R607 on P680 will degrade to zero and steam flow will match feed flow

-MW output of the Main Generator will increase as steam flow that was diverted thru the SRV is once again restored to the Main Turbine K/A: 239002A4.01

REFERENCE:

SDM D21/ Nil ONI D21 1 CANDIDATE RESPONSE:

l i

L SAT UNSAT .

-6 L

i

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

l l

PERRY POWER PLANT I INITIAL LICENSE IWAMINATION l Jolt PERFORM ANCE MEASURES (WALKTilROUGil)

, JPM NO,5 l

I JOll PERFORMANCE MEASURES JPM No. 5 JPM

Title:

Manual Startup of RCIC in CST to CST, Faulted Plant

Reference:

S01851, section 4.5 NUREG

Reference:

217000A4.03 Method of Testing: Simulator Time for Completion: 20 minutes I

e_. . - . .. ..

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORMANCE MEASURES (WALKTilROUGH)

, JPM NO 5

'Iask Standards: Following a failure of the RCIC Flow Controller,1E51 R0600, to coritrol RCIC flow the operator will obtain desired parameters using Manual control. :

Required Materials: None Simulator Setup: Reset to IC 25, start ESW Pump "A" and ECC Pump "A", insert rnalfunction l imf CN02:1 E51R0600 (none 0) 100 0 0, reset all annunciators. Fall l READ TO Tile CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, Tile TASK TO DE PERFORMED AND Tile INITIATINO CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU S110ULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES ~

OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS I TNLESS SPECIFICALLY DIRECTED llY Tile EXAMINER. DO NOT ASSUMll Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU llAVE i COMPLETED Tile TASK.

Initial Conditions: Reactor is operating at approximately 12% power. ESW pump "A" and ECC pump "A" are running. SVI-D23 T1213, Suppression Pool Average Temperature is signed in and being perfomied by the STA RCIC is in Standby Readiness aligned to the CST.

Initiating Cue: The Unit Supervisor directs you to perfonn a manual s'artup of the Rx Core Isolation Cooling system in the CST to CST mode to support a work order retest.

The retest calls for RCIC flow to be 650 -700 gpm with RCIC pump discharge pressure at approximately 100 psig greater than Rx pressure.

2

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORMANCE MEASURES (WAIKrilRCUGil)

. JPM NO.5 START TIME:

Denotes critical ste; STEP 01 Initiate evacuation of any personnel from the Rx Building Annulus and S U Containmem. (Cue candidate that no personnel are in these areas.)

STEP 02 Perform ECC Loop. . Manual Startup (done per inillal coaditions). 3 U STEP 03 Verify RCIC FUMP CST SUCTION VALVE, IE51 F010,is open. S U

STEP 04 Take the RCIC SECOND 1 EST VALVE TO CST, I E51 F059, to OPEN S U to provide a discharge path to the CST.

STEP 05 Take RCIC TURBINE OLAND SEAL COMP, IE51-C004, to START. S U

STEP 06 Simultaneously perform the following:

a. Take RCIC STEAM SilUTOFF, IE51 F045, to OPEN to roll S U the RCIC Turbine.

b. Open the RCIC FIRST TEST VALVE TO CST, l E51 F022, by S U holding the control switch in OPEN.

STEP 07 Ensure RCIC PUMP MIN FLOW VALVE, IE51 F019, opens if RCIC S U flow is less than 120 gpm and the RCIC Pump discharge pressure is greater than 125 psig.

STEP 08 Verify the following valves automatically close aller RCIC STEAM S U SilUTOFF, IE51.F045,is open:

a. RCIC TURD CNDS TO CRW FIRST SilUTOFF, IE51 F004

b. RCIC TURB CNDS TO CRW SECOND SilUTOFF, IE51 F005

c. RilR & RCIC ST SUPP FIRST DRN SilUTOFF, I E51.F025

d. RilR & RCIC ST SUPP SECOND DRN SilUTOFF, IE51 F026.

3

i i

PERRY POWER PLANT i INITIAL LICENSE EXAMINATION :

JOli PERFORM ANCE M EASURES (WALKTilROUGil) 3

. JPM NO.5 i

STEP 09 Using RCIC PUMP FLOW CONTROL, IE51 R600, adjust flow until the S U desired flow is reached (which for this JPM is 650 700 gpm),

STEP 10 Candidate should detennine that the RCIC PUMP FLOW CONTROL, S U 1E51 R0600, did not automatically throttle to maintain 700 gpm as required by US direction.

STEl .1 Candidate shall notify US of failure of 1E51 R0600. S U (As the US, after being Informed of the system status direct the candidate to maintain RCIC parameters using manual control of the RCIC Flow Controller until the RSE is present in the control room, candidate may do this prior to contacting US.)

STEP 12 Candidate shall place IE51 R0600 in MANUAL control S U

STEP 13 Candidate shall use the Flow Controller OPEN/CLOSE pushbuttons to maintain S U flow 650-700gpm, and throttle RCIC FIRS T TEST VALVE TO CST, E51-F022, to maintain RCIC pump discharge pressure approx.100 psig above Rx pressure.

STOP TIME:

* * * * * * * *

EN D O F J PM * * * * * * * * *

4

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTliROUGil)

, JPM NO,5 USE

REFERENCE:

YES No X QUESTION 1: What components are supplied by the RCIC Gland Seal Compressor?

ANSWER 1: -The Gland Seal Compressor supplies sealing air to :

IES t FS10, RCIC Trip 1hrottle Valve 1ESl FS11, RCIC Governor Valve RCh Turbine Glands.

K/A: 21700000008 --

REFERENCE:

Piping & Instrumentation Diagram sheet 302-332 SDM ESI CANDIDATE RESPONSE:

SAT- UNSAT 4

5

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

PERRY POWER PLANT l INITIAL LICENSE EXAMINATION JOH PERFORMANCE MEASURES (WALKTilROUGil)

, JPM NO 5 i i

USE

REFERENCE:

YES N0_ X '.

i QUESTION 2: State the response of the RCIC sy stem if aligned in the CST to CST mode to - l an increasing Suppression Pool Level.. !

-ANSWER 2: RCIC PUMP SUPR PL SUCTION ISOL, E51 F031 will open RCIC PUMP CST SUCTION VALVE. E51.F010 will close !

RCIC FIRST TEST VALVE TO CST, E51 F022 will close !

RCIC SECOND TEST VALVE TO CST E51 F059 will close Pump will mn on min. flaw.

1

}UA: 217000A1,07-

REFERENCE:

Alann Response Instruction 1113 P60121 for annunciator OS CANDIDATE RESPONSE: ,

i i

9 SAT UNSAT k

r 6

w WMat ?'5-MyeM + WW - 4 P'wr'Y'-t* T449'r'Mw-4-"Y w--Mer q. wq , , -yg..wq g ,- g.._ 5-g.g y,. vyy, w p- -

g g qp. r.-i--- +wgs- y r-w'% %1yt- --F't

e3 .

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOli PERFORMANCE A1EASURES (WALKTilROUGil)

, JPM NO.6 JOli PERFORMANCE MEASURES JPM No. 6 JPM

Title:

Transfer Station Electrical Loads To The Startup Transformer Plant

Reference:

1018, step 4.2.9 NUREO

Reference:

262001A4.01 Method of Testing: Simulator Time for Completion: 6 minutes I

..( .

PERRY POWER PLANT i INITIAL I,1 CENSE EXAMINATION

JOli PERFORM ANCE MEASURES (WALKTilROUGil) i

, JPM NO,6 Task Standards: Electrical busses Ll1 and L12 are being powered from bus L10 via the Unit i Stanup Transfonner.

Required Materials: None Simulator Setup: Reset to IC 19, reset all annunciators.

k READ TO Tile CANDIDATE I WILL DESCRIBE Tile INITIAL CONDITIONS, Tile TASK TO BE PERFORMED AND T11E INITIATING CUES. I WILL INDICATE WilETilER Tile TASK IS TIME CRITICAL. YOU S1100LD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCFDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN Y OU 11 AVE COMPLETED Tile TASK.

Initial Cc,ditions: The plant is operating at 90% power when it experiences a significant problem forcing the Unit Supervisor to enter 1018, Shutdown By Manual Reactor Scram.

Initiating Cue: The Unit Supervisor directs you to transfer station electrical loads from the Auxiliary Transfomier to the Startup Transfonner using 1018.

2

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

.. g ..

PERRY POWER PLANT i INITIAL LICENSE EXAMINATION IOH PERFORal ANCE h!EASURES (WALKTilROUGII) !

.. JPhlNO.6 START Tih1E:

Denotes critical step STEP 01 Verify the AUXILIARY TRANSFER SWITCll is in the AUTO S U position.

STEP P2 Verify Bus LIO is energized. S U

STEP 03 Close Urkr L1006, START UP SUPPLY BRKR. S U

-STEP 04 Verify Brkr L1102, Nod 1AL SUPPLY BRKR, opens S U automatically.

STEP 05 Take Brkr L1102, NORh1AL SUPPLY BRKR, to TRIP to reset S U position indicating flags and clear annunciator.

STEP 06 Close litkr L1009, START UP SUPPLY BRKR. S U STEP 07 Verify Brkr L1202, NORh!AL SUPPLY BRKR, opens S U automatically.

/

STEP 08 Take Brkr L1202, NORh1AL SUPPLY BRKR, to TRIP to reset S U position indicating flags and clear annunciator.

STOP TIME:

* * * * * * * *

EN D O F J Ph1 * * * * * * * * *

PERRY POWER PLANT -

3

--,.-n.,-- - - , , - , - ,-

.c ..r.,ye -. , , , ,, -c--r , ., , .-- , , .

.e .

l INITIAL LICENSE EXAMINATION l JOH PERFORMANCE MEASURES (WAli(TilROUGil)

JPM NO. 6 USE

REFERENCE:

YES X NO 1

QUESTION 1: A plant stanup is in progress. You have been tasked with detennining if Main Turbine Shell Wanning is required, and if sa for how long. What points are you going to use to determine this?

ANSWER 1: 1. Using Sol N32/39/41/51, section 4.4, step 10 the candidate will note that it '

requires use ofeither:

a. Process Computer MAIN TURBINE Screen,1s' STAGE SilELL TEMP (process computer point, N31 BA025, TURBINE lst STAGE SilELL IN TEMP).

b. TEMPERATURE AND EXPANSION Recorder, IN31 R001, point 4, 1st Sill LOWER INNER, on lill3 P823.

CUE: Once the candidate has identified these points, ask candidate how long shell warmup u ould he required for if shcIl temperature were 170'F.

2. Using SOI N32/39/41/51, ' ttachment 1. Turbine Shell Prewarming by Pressurization, candidate should determine that 3.0 hours0 days 0 hours 0 weeks 0 months ;f shell warming is required, i

i K/A: 245000KS.02

REFERENCE:

sot N32/39/41/51 l

CANDIDATE RESPONSE:

1.

2.

SAT UNSAT 4

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORMANCE MEASURES (WALKTilROUGil)

, JPM NO. 6 USE

REFERENCE:

YES NO X QUESTION 2: .With the plant operating at 20% power, the Main Turbine trips. While trying to match breaker flags on breakers L1009, L1006, L1102, and L1202 you mistakenly open the breakers which are closed. Describe the automatic response of the Div.1

' 4.16 KV system including all major breakers and the diesel generator.

ANSWER 2: Since Transfomier Lill A is aci de-energized during this transient there is no loss of power to the Div.1_4.16 KV bus, therefore the DO doesn't start and all breakers will remain in their current positions.

K/A: 262001A4.01 PEFERENCE: SDM RIO, AC Distribution CANDIDATE RESPONSE:

SAT UNSAT-5

PERRY POWER PLANT INITIAL LICENSE EXAMINATION Jolt PERFORMANCE MEASURES (WALKTilROUGil)

, JPM NO. 7 4

Jolt PERFORMANCE MEASURES JPM No. 7 JPM

Title:

13ypass A Failed LPRM 0817A Plant

Reference:

SOI C51(APRM), section 7.3 NUREG

Reference:

215005A4,04 Method of Testing: Simulator Time for Completion: 15 minutes

-I

PERRY POWER PLANT INITIAL LICENSE EXAMINATION ;

~

JOB PERFORSI ANCE MEASURES (WALKTilROUGil)

. JPM NO. 7 Task Standards: Bypass LPRhl 0817A. !

Required hiaterials: None i Simulator Se'up: Reset simulator to IC-19, insert malfunction Nhf 03:L0817A (none 0) 0 0 0, reset all annunciators.

READ TO TiiE CANDIDATE I WILL DESCRIBE Tile INITIAL COND1110NS, Tile TASK TO BE PERFORhiED AND Tile INITIATINO CUES. I WILL INDICATE WilETilER Ti1E TASK IS Tlh!E CRITICAL. YOU -

S110ULD SihiULATE Tile REQUIRED ACTIONS AS IF DIRECTED DY PLANT PROCEDURES i

OR S11117 SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPhiENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAhilNER. DO NOT ASSUh!E TiiE EXAhllNER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAhilNER WHEN YOU llAVE COMPLETED Tile TASK.

Initial Conditions: Reactor is operating at 90 % power, when LPRM 08-17A fails downscale. The l&C Supervisor has determined this to be a faulty butter card that will take approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to replace.

Initiating Cue: Unit Supervisor directs you to bypass LPRM 08 17A.

2

- - , . _- ....-,,,g -..--w----, .,.w , --- , , . . - ,. m..

PERRY POWER PLANT INITIAI. LICENSE EXAMINATION JOll PERFORM ANCE M EASURES (WALKTilROUGil)

. JPM NO. 7 START TIME:

' Denotes critical step

'STEF 01 Determine the associated APRM Channel for the LPRM to be S U bypassed per Attachment 1: LPRM to APRM Channel Assignment.

(The appropriate APRM Channelis channel"II")

' STEP 02 Determine if the associated APlo! thannel will be operable aller S U the LPRM is bypassed.

NOTE: An APIS 1 channel is inoperable if there are less than 2 LPRM inputs per core level or less than 14 LPIGi inputs to an APIG1 channel.

(CUEt if asked by the candidate there are no other LPRM's inop.)

STEP 03 Notify Reactor Engineering of the intent to bypass a LPRM so a TIP S U (

Trace may be performed, ifnecessary. (

(CUE: Notify candidate as Rx Eng. that TIP Trace will not he necessary.)

STEP 04 Ifdesired, bypass the associated APRM Channel. S U (CUE: As Unit Supervisorinform candidate that you da want the APRM bypassed for chis evolution. This will necessitate that the candidate enter section 7.1 of the lustruction.)

STEP 05 Place NEUTRON MONITOR BYPASS,1CSIB S6,in Cil "11". S U I

STEP 06 Ensure the BYPASS halfof the APRM DNSC/ BYPASS status light S U backlights white on lil3 P680 und the APRM Bypass status light on APRM Mon. Panel,11113 P672 comes on.

STEP 07 Inside the nssociated APIGi Power Range Neutron Mon Panel, S U lill3-P672, place the LPRM Card Mode Switch for LPRM 0817 05A in BY.

NOTE: LPRM 08-17-05A white bypv.s status light on the display section (top) of the panel will come on.

PERRY POWER PLANT INITIAL LICENSE EXAMINATION

- JOH PERFORMANCE MEASURES (WALKTilROUGil)

. JPM NO. 7 -

STEP 08 -When in Mode I and Reactor Power > 25%, compare the APRM SU Channel with the bypassed LPRM with Rated 1hermal Power:

a. ERIS screen #73 may be used. S U

b. If not within *2% of Rated Thennal Power, perform S U SVI C31 T0024.

STEP 09 Return APRM Channel 'll' to service per Removing an APRM Channel S U From Bypass, by placing the NEUTRON MONITOR BYPASS, APRM joystick in the neutral position.

STOP TIME:

B k

a

* * * * * * * *

EN D O F J PM * * * * * * * * *

i .

l. -4

PERRY POWER PLANT INITIAL LICENSE EXAMINATION !

JOH PERFORMANCE MEASURES (WAIETilROlJGil) !

, JPM NO. 7 l USE

REFERENCE:

YES NO X QUESTION 1: 1he following plant conditions exist:

Rx power is 100 % when APRM "A" fails upscale, Describe the plant response if the P680 operator's first action is to take APRM "A" to BYPASS.

ANSWER 1: The Rx Recire Automatic Flow Demand Limiter (AFDL) would switch from an

_ APRM input of Channel "A" to Channel "E" which senses actual Rx power.

Because actual Rx power is lower than the upscale power sensed by APRM "A"_it will remove the negative bias being fed into the Rx Recirc system and allow the pre- transient flow demand sign 11 to be passed, causing Recire flow control valves to open and a corresponding power increase.

K/A: 215005G0010

REFERENCE:

Sol CSI, Precaution and Limitations SDM C51(APRM)

CANDIDATE RESPONSE:

SAT UNSAT 4

5 4

y.. ._ s . _ ...u- ------ w-eem

PERRY POWER PLANT INITIAL LICENSE EXAMINATION !

JOH PERFORMANCE MEASURES (WALKTilROUGil) ;

, JPM NO. 7 i USE

REFERENCE:

YES X No i

QUESTION 2: If Reactor power were 75% and Reactor Recire flow were 70 Mlbnvilr, calculate !

the APRM Thermal Scram setpoint. <

ANSWER 2: Scram setpoint = [.66Wr + 64%), where W, is percent Recire Loop flow Must conven 70 Mlbnvilt which is total core flow to n % Recirc Loop Flow by using Plant Data Book Curve A012:

70 Mlbnvilt en the horiz. axis corresponds to approx.124 % on the vertical axis

, Divide 124% by 2 to achic.>e a Recirc leop flow of 62%

= [.66 x [62%) ) + 64%

= [.40.9%] + 64%

= 104,9% Rx Power (There is a 111% clamp on this but this isn't in efTect ut this power / flow.)

K/A: 21500$K4.02

REFERENCE:

Tech Spec Table 3.3.1.1 1, page 3 3 7 CANDIDATE RESPONSE:

SAT UNSAT 6

. . ..--b.

o PERRY POWEP. PLANT INITIAL LICENSE EXAh11 NATION '

Jolt PERFORA1ANCE MEASURES (WALKTilROUGil)

, JPM NO. 8 f

JOli l'ERFORMANCE MEASURES I JPM No.8 JPM

Title:

Ilydrogen Recombiner A Startup - Post LOCA Plant

Reference:

SOI M51/56, Rev. 6, TCN 6 PEl M51/56, Rev. 3 NUREO

Reference:

223001 A4.13 Method of Testing: In Plant Time for Completion: 15 minutcs 4

PERRY POWER PLANT INITIAL LICENSE EXAhtINATION JOll PERFORM ANCE S1EASURES (WALKTilROUGil)

, JPM NO.8 Tasi Standards: Locally start the "A" liydrogen Recombiner and warm up to operating temperature.

Requiied Materials: SOI h151/56 Simulator Setup: N/A (In plant)

READ TO THE CANDIDATE 1 '1LL DESCRIBE Tile INITIAL CONDITIONS. Tile TASK TO BE PERFORMED AND Ti1E INITIATINO CUES. I WILL INDICATE WilETiiER Tile TASK IS TIME CRITICAL. YOU Sil0ULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SilllT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME THE EXAMINER WILL ACCEPT AN ORAL DESCRIPT10N OF Tile REQU; RED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WiiEN YOU liAVE COMPLETED Tile TASK.

Initial Conditions: Operating in accordance with PEl M51/56. Containment Hydrogen concentration is at 3% and increasing 0.5% per hour, liydrogen Igniters and CGMS "A" are in operation. The initial Recombiner Power Setting for Recombiner "A" has been calculated to be 46.2 KW.

Initiating Cue: The US directs you as an in plant operator to start up ifydrogen ,

Recombiner "A" and adjust for proper operation. !

2

Y t

PERRY POWER PLANT INITIAL LICENSE EXAh11 NATION JOH PERFORSIANCE hlEASURES (WALKTilROUGII)

. JPh1NO.8 START TIME:

4 STEP 01 Verified PWR ADJ potentiometer set at zero (000). S U

' STEP 02 Piaces PWR OUT SW in ON and verifies status light energizes. S U STEP 03 Adjusts PWR ADJ potentiometer until 5 KW is obtained on S U PWR OUT meter and holds for 10 minutes.

(CUE: Inform candidate 10 minutes have elapsed.)

STEP 04 Adjusts PWR ADJ potentiometer until 10 KW is obtained on S U PWR OUT meter and holds for 10 minutes.

(CUE: Inform candidate 10 minutes have clapsed.) ,

STEP 05 Adjusts PWR ADJ potentiometer until 20 KW is obtained on PWR OUT S U meter and holds for 5 minutes.

(CUE: Inform candidate 5 minutes have clapsed.)

STEP 06 Adjusts PWR ADJ potentiometer until - 46.2 KW is obtained an S U on PWR OUT meter.

STEP 07 Readjusts potentiometer as required to maintain initial power setting S U (46.2 KW) until recombination temperature (1225'F.)

is reached.

(CUE: Point to temperature meter at 1225'F. and state temperature is increasing faster than before.)

STEP 08 Monitors and confinns Recombiner operation by observing a ramp S U

temperature change when Recombiner temperature reaches 1225'F.

(CUE: Temperature is increasing.)

STEP 09 Decreases the potentiometer as required to maintain heater temperature S U 1225*F. to 1400*F.

(CUE: Temperature stabilizes atl350*F)

STOP TIME:

* * * * * * * *

EN D O F J Phl * * * * * * * * *

3

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORMANCE MEASURES (WAI.KTilROUGH)

, JPM NO,8 USE

REFERENCE:

YES NO._ X-QUESTION 1: ~ If a LOCA occurs the Unit Supervisor enters the Plant Emergency Instmetions which direct him to start the flydrogen Analyzers. What options does the Unit Supervisor have as far as where he can monitor hydrogen concentration with the Ilydrogen Analyzers and at what concentration is h- required to enter PEl M51/56, Ilydrogen Control?

ANSWER 1t The 11ydrogen Analyzers can monitor from the:

a.Drywellllead Area

b. Dry.vell Dome Area

c. Containment Dome Area

d. Suppression Pool Area.

The Unit Supervisor must enter PEl M51/56 when hydrogen concentration in the Containment or the Drywell reaches 0.5%.

K/A: 22300lRS.12

REFERENCE:

SDM M51, Combustible Gas Control PEl M51/56,liydrogen Control CANDIDATE RES'r DNSE:

1 SAT __.UNSAT 4

_ _ . - , - - - - . . _ . . . _ . - .-a. _ __ _ . _ _ _ , . _ _ . _ - . _ . . _ - - - _ . _ _ . . _ . -

t PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORMANLE MEASURES (WALKTIIROUGil)

. JPM NO. S USE

REFERENCE:

YES X No QUESTION 2: Given the following plant conditioi s:

(SHO Only)- A LOCA has occurred Containment pressure is 2.0 psig Dr>well hydrogen concentration is 3.0%

Containment hydrogen concentration is 8.8%

Div. 2 Ilydrogen igniters are the only hydrogen control equipment operating.

What is the correct action to take per PEl M51/567 ANSWER 2: Prepare vent paths using PEl-SPI 7.1, Preparation for Containment Venting (SRO Only)

IUA: 223001 A1.05

REFERENCE:

PEl M51/56 CANDIDATE RESPONSE:

S

1

\ ** .

PERRY POWER PLANT INITIAL LICENSE EXAMINATION Joll PERFORM ANCE M EASURES (WALKTilROUGil)

. JPM NO. 8 USE

REFERENCE:

YES X NO QUESTION 2: Using the P & ID's show and explain the flowpath used by the Combustible Gas (RO Only) Mixing Compressors to effect hydrogen concentration.

ANSWER 2: Using the prints describe the following flowpath:

(RO Only) -Combustible Gas Mixing Compressors are located inside the containment Take suction from Cntmt volume (at approx. the 689' elev.) and from the entmt. dome

-Compressor discharges through an after-cooler into the Drywell via the Drywell Vacuum Relieflines(M16)

This pressurizes the DW sufliciently to cause the first row of Suppression Pool Vents to become uncovered This will allow the hydrogen air mixture to flow from the DW to the Cntmt which, because ofits larger volume, results in a reduced hydrogen concentration (by dilution).

K/A: 223001 A1.05

REFERENCE:

302 831 Combustible Gas Control System 912 606 Drywell Vacuum kelief System CANDIDATE RESPONSE:

SAT. UNSAT

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOH PERFORM ANCE MEASURES (WALKTilROUGil)

. JPM NO.9

.1011 PERFORMANCE MEASURES

.IPM No. 9 i

JPM

Title:

Manually Initiate CO2 for the Control Room Subfloor Areas Plant

Reference:

SOI P54(OAS), Rev. O NUREO

Reference:

286000 SG 9-Method ofTesting: Plant Time for Completion: 15 minutes l

I l

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOll PERFORMANCE M EASURES (WAL KTilROUGil)

. JPM NO. 9 Task Standards: Candidate will initiate a CO2 dump of the Control Room only by local operation of the Master and Selector valves.

Required Materials: sol P54 (GAS)

Simulator Setup: N/A tin Plant)

READ TO Tile CANDIDATE I WILL DESCRIBE Tile INarlAL CONDITIONS, Tile TASK TO BE PERFORMED AND TliE IN111ATING CUES. I WILL INDICATE WilETilER TIIE TASK IS TIME CRITICAL. YOU SilOULD SIMULATE Tile REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SilIFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CONTROLS UNLESS SPECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF Tile REQUIRED ACTION UNLESS Tile EXAMINER INDICATES OTilERWISE. INFORM Tile EXAMINER WilEN YOU IIAVE COMPLETED Tile TASK.

Initial Conditions: Electrical equipment fire in Control Room Subiloor area requires Contiol Room evacuation. Allimmediate Actions from ON1 C61 Evacuation of the Control Room, are complete.

Initiating Cue: 1he Unit Supervisor directs you to manually initiate a CO2 dump for all the Control Room Subfioor areas.

2

PERRY POWER PLANT INITIAL LICENSE EXAMINATION Jolt PERFORMANCE MEASURES (WALKTIIROUGil)

. JPM NO. 9 START TIME:

Denotes critical step

STEP 01 Open the Selector valves by smashing breakglass and rotating pilot S U valves clockwise. (Three valves, P54 F3451, F3461, F3471)

STEP 02 llold the Selector valves open for 4 minutes each then close the valve. S U .

(CUE: Inform candidate that no flow noise can be heard.)

STEP 03 If no CO, discharge occurs, leave Selector Valve pilot valves open. S U

-

STEP 04 Open the Master Valve by smashing breakglass and rotating pilot S U valve clockwise. (1 valve, P54 F3441)

(CUE: If step 03 was not performed tell candidate that flow nelse was heard for a few seconds and then stopped.)

STEP 05 lloid Master Valve Pilot Valve open for discharge time listed (4 minutes), S U then shut Master Valve Pilot Valve.

f STEP 06 Shut the Selector Valve pilot valves. (Three valves) S U t

)

STOP TIME:

3

* * * * * * * *

EN D O F J PM * * * * * * * * *

3 l

. -_ -_- -- --_-- - - _ - - - - - _ - _ _ --- - A

. . i PERRY POWER PLANT

. INITIAL LICENSE EXAMINATION l JOH PERFORMANCE MEASURES (WALKTIIROUGII) {

. JPM NO. 9 USE

REFERENCE:

YES X _. 'NO _.

QUESTION 1: An Emergency Diesel SVI is in progress and the "A" train of the Control Room Ventilation system is operating in the Emergency Recirc Mode.You receive a repon from a PPO that there is a fire in the "A' Control Room Ventilation Exhaust Plenum. Explain how you would perform the deluge on this exhaust plenum fire.

ANSWER 1: Per S01 P54(WTR), section 5.6 and using Attachment 6 the following steps must be perfomied:

1. Shutdown the "A" train of Control Room Ventilation per the Sol.

2. (Direct a PPO to) open P54-F1160.

3. (Direct a PPO to) open P54-Fl164.

4. IDirect a PPO to) verify P54-F3699 opens.

K/A: 290003A2.04 S

REFERENCE:

SOI P5 4 (WTR), secti s :hment 6 CANDIDATE RESPONSE:

SAT UNSAT PERRY POWER PLANT -

4

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTHROUGH)

JPM NO. 9

- USE REFEREhCE: = YES NO -X __,

QUESTION 2: Upon being sent to the Metrology Lab for a fire alarm you determine that an (RO Only) automatic Halon initiation countdown is in progress with 15 seconds showing on 4 the digital display. You determine that there is no fire and get the Control Room's permission to abort the Halon initiation. Afler depressing the Halon Abort pushbutton you see the timer count down from 05 seconds to 00 seconds. What is the status of the Halon Dump Initiation Circuitry at this point?

ANSWER 2: It is overridden as long as the Abort pushbutton is depressed. Since the timer has -

(RO Only) . counted down all the way,if the Abort pushbutton is released a Haloa dump will immediately occur. The only way to release the pushbutton without getting a Halon dump is to reset the initiation logic prior to releasir.g the Abort pushbutton. !

~K/A: 286000G0001

REFERENCE:

SOI-P54(GAS), section ~ ,7.4 e

CANDIDATE RESPONSE: ,

SAT UNSAT 9

l 5

). . . . .. .

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTilROUGil)

. JPM NO. 9

- USE

REFERENCE:

YES X NO QUESTION 2: Assume that the plant is in Mode 4 with RliR "B" in shutdown cooling. A fire (SRO Only) occurs in the Control Complex 620' elevation in Fire Zone Designator 1CC-3A, ,,

making it inaccessible. Acting as the Unit Supervisor you enter ONI P54. What would be the correct actions to take if RHR "B" suddenly tripped, it is due to the fire, and it is desired to resore RHR "B" to shutdown eculing? Explain.

ANSWER 2: ONI P54, Attachment 1, page 5 directs actions that can be taken if a fire occurs -'

(SRO Only) somewhere in the fire zones listed in Attachment 2 (which candidate will have to determine from the initial conditions), and a Shutdown Cooling Pump trips Method A, (Establish communications between the Centrol Room and un operator at the pump breaker EH1208. Operate pump from breaxer EH1208) would be inappropriate due to this breaker being located in the area where the fire is located.

Method B, Lift lead (1E12A0851E) from relay 1E12-Kl9B is appropriate because this relay is located in control room panel H13-P618 (this can be determined by using drawings listed below) and is therefore accessible.

K/A: 286000G0001

REFERENCE:

ON1-P54, Attachment I and Attachment 2 Drawings bio 8-055, sheet 4 and sheet 8 CANDIDATE RESPONSE:

0

-SAT .UNSAT

, 6 i

L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ --

.o ,

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOll PERFORM ANCE MEASURES (WALKTIIROUGII)

JPM NO.10 i

JOll PERFORMANCE MEASURES h

JPM No 10 JPM

Title:

RHR Loop B Flood Altemate Injection Plant

Reference:

PEI-SPI 4.2, Rev. O NUREG

Reference:

295031 EA1.08 Method ofTesting: Plant Time for Completion: 20 minutes I

h l - - - - - - - - - - - - - - - - - - - - - - -

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORM ANCE MEASURES (WALKTilROUGil)

JPM NO.10 Task Standards: Line up RHR "fr' in the Containment Flooding Mode frora outside the control room.

Required Materials- PEl SPI 4.2 RHR Loop B Flood Alternate Injection Simulator Setup: N/A (In-plant)

D READ TO Tile CANDIDATE I WILL DESCRIDE Tile INITIAL CONDITIONS,THE TASK TO BE PERFORMED AND THE INITIATING CUES. I WILL INDICATE WIIETilER THE ~JASK IS TIME CRITICAL. YOU

. SliOULD SIMULATE THE REQUIRED ACTIONS AS IF DIRECTED BY PLANT PROCEDURES OR SillFT SUPERVISION. DO NOT OPERATE ANY PLANT EQUIPMENT OR CON TROLS UNLESS "PECIFICALLY DIRECTED BY Tile EXAMINER. DO NOT ASSUME Tile EXAMINER WILL ACCEPT AN ORAL DESCRIPTION OF THE REQUIRED ACTION UNLESS THE EXAMINER !NDICATES OTHERWISE. INFORM Tile EXAMINER WHEN YOU HAVE COMPLETED THE TASK.

Initial Conditions: Operating in accordance with PEl B13, a LOCA has occurred, no injection systems are available, alternate injection systems will be lined up. ESW Pump B is operating. The Div. 2 D/G is in secured status due to a governor failure and is not required.

Initiating Cue: The Unit Supervisor directs you as an in-plant operator to coordinate with the Control Room to perform PEI SPI 4.2, RHR Loop B Flood Alternate injection.

Steps 1.0 through 2.4 are complete.

t e

2

PERRY POWER Pl ANT -

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTIIROUGil)-

, JPM NO.10 START TIME:

Denotes critical step STEP 01 Candidate should identify the OSC Tool Locker located in the Control S U Complex 599' elevation as the storage location for all tools needed for this task.

STEP 02 Verifies RHR B FPCC Supplement Cooling Viv 1 E12-F099B is closed, S U AX 599' C/03.

(CUE: Inform the candidate that steps 2.6 and 2.7 are complete,le RIIR Pump B is secured and E12 F027B is open.)

STEP 03 Closes ESW Emg. Inject to Rx Vsl Loop Drain,1P45 F578, S U AX 599' B/03.

STEP 04 Unlocks and opens ESW Emg. Inject to Reactor Vessel isol 1P45 F572, S U AX 599' B/03.

STEP 05 Unlocks and opens - 260 tums ESW Emg. Inject to Reactor Vessel Isol S U 1P45-F573 to open the valve 20%, AX 599' B/03.

STEP 06 Closes ECC HX B ESW Inlet 1P45 F53 :3, CC 574' C/05. S U NOTE: Div. 2 DG in secured status per Init. Conditions allows next step to be done.

' STEP 07 Unlocks and closes Div. 2 Diesel HX ESW Outlet IP45-F534B, S U DGB 620' A/02, Div. 2 DO Room.

(CUE: Inform the candidate that steps 2.11,2.12, and 3.2.1 are complete ic ECC to FPCC valves closed, ESW B is running, injecting inside the chroud.)

STEP 08 Places Remote Shutdown Switch for RHR B HX's ESW Outlet Valve S U 1P45-F068B in CLOSE to close the valve, CC620' B/03, MCC EFID07 Comp. XL.

(NOTE: This switch is a maintain contact in " Cont Rm" position, spring-return-to- l

" normal". Valve will close as you go from " Cont Rm" to " Normal" because of passing ;

through the "Close" position)

STOP TIME-l

* * * * * * * *

END O F J PM " * * * * * * *

9 3

l l

PERRY POWER PLANT INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURES (WALKTIIROUGII)

JPM NO.10 USE

REFERENCE:

YES X _. NO QUESTION 1: Using the plant drawings sliow and explain the flowpath from Lake Erie to the Reactor Vessel used in this altemate injection flowpath.

ANSWER 1: 302 791: Lake Erie water enters through the intake structure into the Emergency Service Water forebay (located in the Emergency Service Water Pumphouse) and into the suction of ESW "B" Pump 302-792: (picks up at drawing coordinate E4) ESW enters the Auxiliary s Building using its normal flowpath however right before it enters the RiiR 11X Inlet MOV, P45-F014B, it is redirected thru valves P45 F572, F573, & F575 302-643: (picks up at coordinate E5) ESW enters the RliR "B" system piping just downstream af the RHR "B" HX's and is directed towards the Rx Vessel using the normal RIIR injection piping 302 642: (coordinate D3) ESW flow is directed into the Rx Vessel via either the normal LPCI injection line (Non-ATWS) using E12-F027B &

F042B, or it enters via the nonna! Shutdown Cooling injection flowpath (ATWS) using E12-F053 Band enterring vir. the Feedwater f

System All other non-essential ESW loads are isolated in order to provide maximum flow to the Rx Vessel.

IUA: 295003AA2.04

REFERENCE:

Drawings 302-642,643,791,792 CANDIDATE RESPONSE:

SAT UNSAT PERRY POWER PLANT .

4

r- .

,=. . . . _

INITIAL LICENSE EXAMINATION

- JOB PERFORMANCE MEASURES (WALKTIIROUGil)

- JPM NO.10 USE

REFERENCE:

YES :X' NO QUESTION 2:~' Assuming that RHR "B" is lined up for alternate injection using the Diesel Fire Pump as its source of water. Reactor pressure starts a slow increase due to an ATWS. At what RPV pressure would you expect to see injection from this alternate injection lineup to stop?

ANSWER 2: Approximately 95 psig Rx pressure.

. K/A: 203000Kl.17

REFERENCE:

PEl-Bl 3 RPV Control (Non-ATWS) or (ATWS) l CANDIDATE RESI'ONSE:

e d

SAT UNSAT 5

r' FINAL AS-ADMINISTERED SCENARIOS FOR PERRY AUGUST 1997 EXAM 3

ES-301 Scenario Events Form ES-301-3 Simulation Facility: _ Perry Station Scenario No.: 1 Examiners: D. McNeil Applicants:

.J. Lennartz

_H. Peterson 2nitial Conditions: _Rx at 90% CTP, nower ascension in oroaress, HPCS is OOS Turnover: Plant at 90% nwr with a power ascensira in oroaress. 10I-3 is '

comnlete thru sten 4.5.28. Currently on sten P6 of the BOC nullsheet.

HPCS system in OOS due to fai' _e of its monthly SVI last nicht. Was declared inon. at 0000 today. After you take the shift,Rx Enaineerina 111,3? coatact you for the nower increase method and ramo rate to 300%

pc.e t .

Event Malf. Event Event No. No. Type

Description 1 CN02 I CRDH flow controller fails downscale 2 NM04A I APRM "A" fails upscale causing AFDL circuit to runback power N Reset the half-scram N Restore recirc FCV hydraulics 3 R Raise reactor power using recirc flow control 4 Trg ES C Trip of RFPT "A" w/ failure of MFP to auto start 5 Trg M Earthquake causes an instrument air leak in E3 containment, DW pressure increases RD15 M ATWS MV05 C Containment and drywell instrument air valves fail to auto close 6 CAEP M Sequential loss of RPV water level indication RV04 C Two ADS valves fail to open .

(N)ormal, (R)eactivity, ( I) ns t rument , (C)omponent, (M)ajor Chief Examiner: / /f[ / .

O

=

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 1 Page 2 of 9 Event

Description:

CBDH Flow Controller 1C11-R600 fails downscale, Time l Position Applicant's Actions or Behavior BOP Responds to annunciator 1H13 - P6 01. - 2 2 - A3 , "High CRD Mechanicm Temperature" Recognizes CRD flow controller outpu't at minimum value Informs US As directed by US will use manual control of the CRDH Flow Controller to re-establish normal syatem parameters US Entern ONI-C11-1, " Inability To Move Control Rods" May attempt to swap CRDH FCVs or swap CRD pumps if they mis-diagnose the problam Directs BOP to restore CRDH parameters to normal using manual control of controller 1Cll-R600 Verifies I&C contacted for repairs SO Will ensure steady state conditions for power, pressure, level Back-up BOP Operator with ARI and SOI usage Contacts I&C for repairs I&C will inform US that it appears to be a problem with the output of the Auto Card, controller is not operable in auto, manual operation will be required, repairs should be complete in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . **

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

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 2 Page 3 of 9 Event

Description:

APRM "A" will fail unscale, causinct AFDL in control, a Reactor Recire FCV runback, a half-scram, and onerators will be .

reauired to hydraulically lock-out the FC7s to ston the nower transient.

Time Poeition Applicant's Actions or Behavior SO Recognizes APRM "A" failed upscale, AFDL In Control, and power decrease Informs US As directed by US, will arm & depress the HPU Shutdown PBs, verify recirc flow / power decrease stops, verify position on power-to-flow map is stable '

BOP Consults ARI-H13-P680-4-E9 for "AFDL In Control" Contacts I&C for repairs US Enters ONI-C51, " Unplanned Change in Rx Power or Reactivity" Verifies plant is rat in areas of instability on Power To Flow Map If entered Increased Awareness area will cal] Rx Engineering Consu]ts Tech. Spec. 3.4.1 and 3.3.1.1-1 During the recovery from this transient these actions will be performed by the ROs using the designated SOIs SO Bypass APRM "A" using SOI-C51(APRU), section 7.1 SO Reset M scram A/C using SOI-C71, dection '7.3 BOP Restart HPU A & B, and the FCV Motion Inhibit using SOI-B33, section 4.2

- - To support FCV restoration the operators need: II-

I-833 section 4.2:

step 1 a No fuse failure lights on associated iaodicons inside Pol 4 step 1. c. No Channel I or Channel 2 red lights on in P634 step 1. f.1) a) & b) Subh,op 1: Isolate coil 115 Vac. 0.6 amps / Operate C 61 0 Vac, O amps c) & d) Subloop 2: Isolate coil 115 Vac, 0.6 amps / Operate Coil 0 Vac, O amps step 1. f. 2) a) & b) Subh>op 1: Isolate coil 115 Vac, 0.6 amps / Operate Coil 0 Vac,0 amps c) & d) Subloop 2: Isolate coil 115 Vae, 0.6 amps / Operate Coil 0 Vac,0 amps step 5 As PPO in field report 0 psig ou local gauges 1B33-R70SA & k709A step 10 a.1) & 2) Suhloop 1: Isolate coil 0 Vac, O amps : Operate Coil i 15 Vac, 0.6 amps

3) &4) Subloop 2: Isolate coil 0 Vac, O amps / Operate Coil i 15 Vac,0.6 amps step 10 b.1) & 2) Subloop 1: Isolate coil 0 Vac, O amps / Operate Coil 115 Vac. 0.6 amps

3) &4) Subloop 2: Isolate coil 0 Vac. O amps / Operate Coi! ' 15 Vac, 0.6 amps

m.

ES 301L - Ol ierator Actions ---- Form ES 3014 Scenario No.i 1

~

Event No.: .}_ Page 4 of 9 Event Descriptioni Power increase to 100% rated thermal oower.

Time Position Applicant's Actions or Behavict -

US Brief crew on power increase, directs SO to increase to 90% using Rx recirc flow ,

Will call Rx Engineer to verify that a recire flow increase'is the desired method to increase power, determine any ramp rates During the power increase, will oversee the SO actions and plant response SO Using Rx Recisc Flow Control will increase recire flow to achieve 90% power, .

taking time to allow plant to stabilize between flow increases and to observe -

currect response by level and pressure control systems, and nuclear instrumentation i . -. . . . . , . . , . . . . . . ..,

. a __

_________i_______,__'__ _ _ _ _ _ , _ , . _ _ _ _ _ _ - , _ , _ _ _ _ _ _ _ _ . . _

l

ES-301 Operater Actions Foim ES-301-4 Scenario No.: 1 Event No.: 4 Page 5 of 9 Event

Description:

Trip of Rx Feed Pumn Turbine "A" with a failure of the Motor Feed Pump to putomatica,lly start (will start if operator manually starts it) l---

Time Position Applicant's Actions or Behavior SO Responds to annunciator lil3-P680-3-D6, RFPT A TRIP i

informs US that RFPI A tripped and that MFP did not auto start Manually starts the MFP Receives annunciators lil3-P680-4-84/B13 due to receiving a Recire FCV runback when RFPT "A" tripped concurrent with a RPV Level 4 Informs US, verifies that the FCVs ran back properiy to approx. the 17% valve position Verifies power, pressure, and level stabilize after MFP is started Depending upon US direction may align the Feedwater level cortrol system to ensure rcsultant pump combination as being controlled in automatic on the Master Level Controller BOP Backs up SO by getting out the appropriate ARIs for the annunciators received Calls PPO to investigate tripped RFPT "A" and to verify proper startup of -

MFP US Enters ONI-N27, "Rx Feedwcter Pump Trip"-

Orders SO to manually start the MFP and maintain RPV level 192-200" Directs BOP to contact Maintenance, & have PPO investigate pump trip Directs MFP Casing Wamiup Valves closed Directs RFPT "A" to be shutdown using SOI-N27 Directs an RO to reset the Recirc FCV runback per sol-B33 I

_ -- --- -- ---- - - - - - - - - - - ---- -- - - - - - - - - - - - - - ~

i. . .

L ES-301 I -

Operator Actions Fomi ES-301-4 Scenario No : 1 Event No.: 1 Page 6 of 9 Event

Description:

Barthauake occurs (<OBE) causine vellow liclits on the Seismic Panel lil3-P969 and startine an Instrument Air leak in the containment. with a failure of the entmt isol valves to auto close.

and an ATWS in the ensuine scram.

Time Position . Applicant's Actions or Behavior SO Responds to aimunciators H13-P680-8-B3, SEISMIC ALARM P969, and 1113-P680-8-C3, SEISMIC MONITOR TRBL Recognizes increasing containment and drywell pressure, informs US US Enters ONI-D51, " Earthquake":

Verifies earthquake is less than OBE by veri.ying only amber lights on panel P969 Directs all Emergency Service Water Pumps started Directs all Plant Underdiain Pumps stopped Directs plant personnel to begin walkdown of plant areas Enters ONI PS2, " Loss of Instrument Air"-

Makes plant announcement regarding loss of air Verifies all available air compressors running as necessary, (if he correctly diagnoses this leak he will recogr.ize that this action would worsen conditions)

Due to continuing loss of air into the Containment and the increasing Cntmt

- pressure, orders Rx to be shutdown either by a manual scram or a Fast Rx -

Shutdown, enters ON1-C71-1, Reactor Scram BOP Checks panel lil3-P969, informs US of all amber lights, no red lights Responds to annunciators lili3-P870-2-B4, Parallel IA Ildr Press Lo, then lill3 P680-5-D6, Scram Viv Air lidr Press Lo, informs US Recognizes decreasing air pressure in the Parallel Ait Header, informs US Starts all ESW pumps, as directed by the US Contacts PPOs to secure Plant Underdrain pumps

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 5 (cont) Page 7 of 9 Event

Description:

Earthquake occurs (<0HB) causine yellow lichts on the Seismic Panel lil3-P969 and startine an Instmment Air leak in the co_ntginment, with a failure of the entmt isol valves to auto close.

and an ATWt; in the ensuine scram.

Time Position Applicant's Actions or Behavior SO Inserts a manual Rx scram or Fast Rx Shutdown (depends on US order) .

Places Rx Mode Switch in SilUTDOWN Recognizes incomplete scram, APRMs not downscale, infomis US Inserts a manual ARl, recognizes rods not insened, APRMs not downscale, infomis US As directed by US will insert control rods using PEl-SPI 1.3, Manual insertion US Enters PEl-B13, RPV Control (ATWS):

Directs initiation of Standby Liquid Control and ADS inhibited Directs Ilydrogen Analyzers started Directs SO to runback Recirc FCVs to minimum position, trip Recirc pumps Directs SO to use PEl-SPI section I to insert control rods Directs to terminate / prevent injection ofinside the shroud systems using PEl-SPI 5.1 & 5.2 Di.ects to line up at least two outside the shroud injection systems using PEl-SPI 6.1 & 6.2 Directs level initially stabilized then a band of 50-100", and a pressure band of 800-1000 psig Enters PEl-T23, " Containment Control"-

Directs operators to initiate Containment Sprays at 2.25 psig, and sec"rc at 1.75 psig if detemiines can't maintain < Pressure Suppression Pressure, goes to PEl-B13 to Emergency Depressurize Directs using PEl-SPI 2.1 to restore Drywell Cooling, and staning of all Dry.vell Cooling Fans Directs using PEl-SPI 2.2 to restore Containment Cooling, and starting of all Containment Cooling Fans l

l

______________)

l l

ES.301 Operator Actions Form ES-301-4 Scenario No.: _L. Event No.: 5 (cont) Page 8 of 9 !

Event

Description:

Eanhauake occurs (<OllE) causingyellow lichts on the Seismic Panel fil3-P969 and startine an Instrument Air leak in the containment. with a failure of the cntmt isol valves to auto closem and an ATWS in the ensuing sgam

-. m .,

Time Position Applicant's Act ms or Behavior

~

BOP Stans Ilydrogen Analyzers Initiates SLC, inhibits ADS, aligns for outside the shroud injection using PEl-SPI 6.1 & 6.2 Performs Terminate / prevent actions per PEl-SPI 5.1 & 5.2 Initiates Containment Sprays per PEl-SPI 3.1 as directed by US Restores DW/Cntmt Cooling per PEl-SPI 2.1/2.2 l

l

ES-301 Operator Actions Form ES-3014 Scenario No.: 1 Event No.: 6 Page 9 of 9 Event

Description:

.Xe_quential loss of all RPV level indication and durine the ensuine emercency depressurization two of the ADS valves will fail to onen and two additional SRVs will have to be manually opened by the operator. (The emercency depressurization may have already occurred durine last event Time Position Applicant's Actions or Behavior SO/ BOP Recognize all RPV level instruments failed upscale or downscale (simulation is that some reference legs and some variable legs break in earthquake),

Inform US US Enters PEl-B13, Emergency Depressurization (if ED wasn't already entered during last ' transient):

Directs FW Inj. Prevention using PEl-SPI 5.3 Directs RCIC Turbine trip When inj. Prevention is complete directs ADS valves opened When told <8 open directs additional SRVs opened to achieve 8 Enters PEl-Bl3, RPV Flooding:

When RPV pressure is - 120 psig:

Directs htSIVs, h1SL Drains, RCIC Stm Isol valves closed Commences injection to establish / maintain hiARFP (120 psig)

Enters PEl-h151/56, liydrogen Control:

Directs BOP start the Hydrogen Igniters BOP Attempts to ED, recognizes 2 ADS valves fail to open, informs US Opens two SRVs, infonns 11S 8 SRVs open Starts the hydrogen igniters injects with LPCI (outside the shroud), per US direction SO Terrtinates FW Injection using PEl-SPl 5.3 Infonns US when h1ARFP pressure of 120 psig is reached injects w/RFBPs and/or bypasses N1FP 1.8 trip, injects with h1FP Terminatine Criteria. Crew is effectively feeding the Reactor Vessel to maintain RPV pressure >120 psig but as low as possible.

Emercency Plan: Site Area Emergency: CSI AS2

l ES-301 Scenario Events Form ES-301-3 Simulation Facility: fPerry Station Scenario No.: 2 Examiners: _ _ _D . McNeil Applicants:

J. Lennartz

--H. Peterson Initial Conditions: Rx at 100% CTP, Division 1 outage in propress Turnover r4 ant is operatinq at 100% nower, ,l_ rods out, on last steo of EOC pullcheet. A Division 1 outage is in nrogress with the followinq Gvstems DOS and danner taqqed: RHR A. LPCS, RCIC. Div 1 DG. This crew __

phould plan on the WO's beinq brought to the control room this shift to commence work. SVI-R10-TS217 was nerformed one hour aqo.

Event Malf. Event Event No. No. Type

Description 1 AV02 I FW Htro SA&6A level controller fails high, causing level 6A control valves to close, isolating Htrs SA &

R Power decrease to <95%

N Htr. restored to service or 1.ined up per SOI-N27 2 CN02 I RFPT "A" fails upscale w/a 1 min. ramp 3 Trg C SRV 1B21F0051B fails open (LLS valve)

E3 4 ES C Spurious Trip of Condensate Booster Pump "A" 5 TF01 M Lightning strike in transformer yard causes a LOOP ZD1R4 C/M Div 2 DG starts then trips on overspeed, causing a 3S6 SBO MV04 C HPCS Injection valve fails to auto open, can be man. opened li

~

(N)ormal, (R)eactivity, (I) nt,ul ument , (C)omponent, (M)ajor Chief Examiner Yd k

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)

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 1 Page 2 of 6 Event

Description:

_JIiqh Pressure Feedwater Heaters SA & 6A level coes high causinq an extraction steam isolation to those heateis. _

l I

Time Position l Applicant's Actions or Behavior BOP Respond to the following Hi Htr 5A & 6A Level annunciators, H13-P870-5-C1, C2, El, & G1 Inform US of Heater SA & 6A isolation US Enters ONI-N36, " Loss of Feedwater Heating:

Directs SO to reduce pser to s95% using Rx recirc flow Contacts Rx Engineer to verify no thermal limita exceeded Consults FTI-B10, Final Feedwater Temperature Reduction Operation (will probably request STA to perform FTI actions)

Consults Tech spec 3.2.1, 3.2.2, 3.2.3, 3.3.1.1, 3.3.4.1, 3.3.2.1 using input regarding status of Thermal Limits Dirccts BOP to verify proper heater isolation per ONI Att. 3 Directs BOP to lineup heaters per the Sys. Operating Inst.

SO Reduces Rx recirc flow to achieve and maintain s95%

power BOP Verifies SA&6A Heaters isolated per Attachment 3 of ONI-N36 As directed by US will either complete heater isolation or return heaters to service per SOI-N27

- As I&C inform US that you will send a crew to investigate, but that you suspect a possible common mode failure with both Htr SA and 6A level controllers. **

0 l

l

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: ___ 2 Page 3 of 6 Event

Description:

Failure upscale of the "A" Reactor Feedwater numn flow controller 1C34-R601A on-H13-P680.

Time Position Applicant's Actions or Behavior SO Respond to panel indications or annunciators 1H13-P680 A9 " REACTOR LEVEL HI L7" and/or 1H13-P680-3-B7

" FEED FLOW / STEAM FLOW MISMATCH" to recognize abnormally high output from RFPT "A" Informs US Transfers Rx Feed Pump Control to the Man Speed Control Dials Maintains RPV level 192-200", Places RFP Controllers in Manual US Enters ONI-C34, "Feedwater Flow Control Malfunction":

Directs SO to place RFPT "A" on manual speed control dial and place RFP "A" Flow Controller in Manual Verifies I&C contacted for repairs May elect to stay wi?.h both RFPTs (ie base loading the "A" RFPT and keep "B" RFPT on the Master Level Controller) or may decide to shift to the Motor Feed Pump with RFPT "B" on the Master Level Controller.

BOP Backs up SO with ARI usage and P'I usage Contacts I&C for repairs

- As I&C report that fault is in FW flow signal to 'RFP "A" controller and that repairs will take approximately one shift, there is no problem with Manual Speed Control Potentiometer.**

l

_ _ _ _ _ _ J

7

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,S-301 E

Operator ActionBorm ES-301-4 h Scenario No.:- 2 Event No.: 3 Page 4 of 6 Event

Description:

- Failure OPEN of Safety Relief Valve IB21-F0051B (Low-Low Set valve)

Time Position Applicant's Actions or Behavior BOP Responds to SRV Open annunciators Informs 11S that SRV 1B21-F0051B is open As directed by US and ONI B21-1 Immediate Actions: A When power is < 90%, takes control switches to OFF Pulls fuses for SRV, verifies SRV closes, informs US US Enters ONI-B21-1, "SRV Inadvertant Open / Stuck Open:

Directs SO to reduce to <90% power using Recirc flow When <90%, directs BOP to take SRV control switches to OFF When SRV doesn't close, directs BOP to pull SRV fuses Refers to Tech Specs 3.4.4 SRV's (In no action statements, only PLCO) and 3.6.1.6 Lo-Lo Set Valves (Action A.1, 14 day LCO)

SO Reduces recirc flow co achieve power c90%, informs US Has to remember that the Feedwater Level Control System is still in Manual control and therefore must be manually adjusted to maintain 192-200" 4

0 5

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O s' ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: ~4 Page 5 of 6 Event

Description:

Trip of Condensate Booster Pumn "A".

Time Position Applicant's Actions or Behavior SO Responds to following annunciators to determine CBP "A" tripped leaving only the "B" CBP running, informs the US:

H13-P680-2-A6CBP A TRIP H13-P680-2-D6CBP DISCH HDR PRESS LO H13-P870-1-ElBUS H11 BKR TRIP Upon US direction starts CBP "C", verifies condensate flow returns to normal U'. Directs SO to start CBP "C" Responds to other annunciators that were received during transient associated with condensate flow by directing that PPO's be dispatched to the Condensate Filter /Demin Panel Verifies that a PPO and Maintenance are dispatched to the tripped pump and to walk down the running pump BOP Backs up SO with ARI and SOI usage Dispatches PPO to CBPs and to Condensate Filter /Demin Panel Dispatches Maintenance to CBP "A" L-

ES-301 Operator Actions Form ES-301-4 Scenario Nc.: 2 Event No.: S Page 6 of 6 Event

Description:

Lightnin7 strike in transmission vard results in a losf_of Unit 1 Startun Transformer find a LOOP, Div 2 DG initially starts then trins causinq a Station Illackout, the HPCS Iniection valve fails to auto open but can be manually opened if attempted hv the gpf2ralor . If crew purcues it they can restore offsite power to Unit 1 via Unit 2 Startun Transformer.

Time Position Applicant's Actionc or Behavior US Responds to LOOP by enterring ONI-R10, " Loss of AC Power" Has containment building evacuated Determines status of Emergency DGs to determine extent of power loss Upon loss of Div. 2 DG determines plant to be in Station Blackout Hands out ONI Attachments to ROs to:

Restore Off-site power using either Unit 2 Startup Transformer powering Bus L10 or powering Div. 2 thru its alt source bkr. (Att. 10)

Maintain System operability (Att. 6)

Reduce DC load usage (Att. 4)

Instrumentation Availability (Att. 12)

Enters PEI-B13, RPV Control (Non-ATWS) on RPV Level 3 Directs pressure control using the SRVs Directs level control using HPCS Enters PEI-T23, Containment Control on high SP temperature SO Recognizes scram, carries out actions for ONI-C71, Rx Scram Informs US that no feedwater pumps available to feed

' the Rx Verifies Rx shutdown Monitors available plant instrumentation per ONI-R10, Att. 12 Controls Rx pressure / level per US direction using SRVs and HPCS BOP Responds to loss of offsite power annunciators Determines status of Emergency Diesel Generators, recognizes and informs US when Div 2 DG trips, dispatches PPOs to Diesel rooms If HPCS receives an initiation signal, notes injection valve, E22-F0 04, does not auto open, informs US, opens valve manually Per US direction performs applicable actions in ONI-R10 to maintain Div. 3 DG running, and to restore offsite power via Unit 2 Startup Transformer

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Terminatinc Criter_ia Crew has power, pressure; and level stable and have developed an action plan to restore AC power to either bus L10 using Unit 2 Startup Transfornier and/or to bus EH12 using Unit 2 Startup Transformer.

Emeroency Plan: DS1 due to power not being restored to either bus EH11 or EH12 within 15 minutes.-

h -

ES-301 Scenario Events Form ES-301-3 imulation Facility: Perry Station Scenario No.: 3 Examiners: D. McNeil Applicants:

J. Lennartz H. Peterson Initial Conditions: Rx power at 33% CTP nower ascension in nrepress Turnover: A Reactor startun is in Droareas. Rx power is 33%. IOI-3 steo 4.5.5 is complete and you are on the MOC_pullcheet sten 53. Upon takina the shift you need to shift Rx Recirc numns to fast speed and then continue on_with the olant startuo. I&C is nerformino SVI-B21-T0189-R.

ECCS/HPCS Drywell Pressure Hiph Channel Functional for 1B21-N667R. 1he 14FP is RTO due to a broken seal iniection line.

Event Malf. Event Event No. No. Type

Description 1 N/R Shift Rx Recirc pumps to fast speed 2 CUO9 C RWCU F/D "A" FCV fails closed 3 BS02 I Failure of DW pressure instrument causes an inadvertent HPCS initiation MV01 C HPCS Injection valve blows fuses while stroking open 4 CN02 I Hot Surge Tank level controller fails downscale 5 ED16Z

~

I Fire in MCC F1D05 (one of the loads is Recirc isolation valves) 6 TH06B C Recirc pump "B" outer seal begins to fail TH05B M/C Rupture of Recirc pump seals, DW pressure increase TH02B CB03 C Failure of stub bus breaker to auto open for Div. 2 essential bus 0 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M) aj or Chief Examiner: [t 'd e l i

ES-301 Operator Actions Form ES-301-4 l 1

Scenario No.: 3 Event No :

. 1- Page 2 of 9 Event

Description:

. Shift Rx Recire pumps to fast speed.

Time- Position Applicant's Actions or Behavior NI US Directs SO to shift Rx Recirc pumps to Fast speed in accordance with.IOI-3, section 4.5.6 i Provides oversight of evolution Verifies loop flows balanced per Tech Spec 3.4.1 l SO Shifts Rx Recirc pumps to fast speed per SOI-B33, section 5.1:

Take switch 1B33-S113 to "A" and "B" Take switch 1B33-S111 to "A" and "B" Directs PPO to bypass Power interlock and Total Feed Flow interlock.

Closes FCV to <10% open, goes to START on Bkr SA(B)

Takes Bkr IA(B) switchec to TRIP then back to NORM to reset breaker trip annunciators Directs PPO to restore bypass switches to normal Ensures loop flows balanced

*As a PPO perform SOI-B33 step 5.1.4 a & b using remote functions to operate the Power Interlock and Total Feedwater Low Flow Interlock switches as follows:

1B33-S126A: TH06 1B33-S1268: TH07 1B33-S127A: TH08 1B33-S127B: TH09

l. _.

I

1 ES-301- Operator Actions i Form CS-301-4 Scenario No.: 3- Event No.: 2 Page 3 of 9 Event Descriptions. Failure of FCV for RWCU Filter Demin "A" full-glpled.

Time Position- Applicant's Actions or Behavior SO Responds to the followina annunciators to determine that RWCU F/D "A" is losing flow, informs the US:

H13-P680-1-D1 RWCU F/D TRBL H13-P680-1-A7 RWCU F/D OUT COND HI/ FAILED When directed by the - US, throttles open on RWCU Filter /Demin Bypass Valve, 1G33-F044, to achieve 280-450 gpm.

US Directs SO to verify the status of the filter demin, ie is it in hold and properly isolated.

Directs SO to use SOI-G33, RWCU, section 5.4,

" Removing F/D A(B) from Service" to correctly align RWCU following the loss of F/D "A".

Verifies repairs.

that I&C or Maintenance are contacted for Verifies that Chemistry is contacted to inform them of reduced filter use in RWCU.

4

r ES-301 , Operator Actions Form ES-301-4 l

Scenario No.: 3 Event No.: 3 Page 4 of-9 Event Descriptions- ~ Failure of HPCS_DW Pressure bistable causes an automatic-initiation of HPCS. The HPCS Injection valvd, IE22-F004 blows fuses as it strokes open.

Time Position Applicant's Actions or Behavior BOP Responds to following annunciators:

H13-P601-16-A5 HPCS PUMP START SIGNAL RECEIVED H13-P601-16-D5 ESW TO DIESEL HX FLOW LOW.

Recognize initiation of HPCS with injection to the RPV, and start of Div. 3 Emergency DG, informs US Notes that HPCS Injection Valve, 1E22-F004 le indication When directed by US , secures HPCS pump, and if directed places HPCS in secured status US Enters ONI-E12-1, " Inadvertent Initiation of ECCS/RCIC":

Verifies by two independent indications that HPCS initiation is incorrect Directs BOP to override HPCS pump control switch to STOP Consults Tech Spec 3.5.1 for HPCS inoperability Action B.1 - Verify RCIC operable w/i one hour Action B.2 - Restore HPCS to operable w/i 14 days Verifies I&C contacted, as to whether SVI was responsible May direct BOP to place HPCS in secured status Recognizes that Div. 3 DG must be loaded for 60 minutes if it wasn' t secured within 2 min. of start per SOI-E22B P&L #5.

Directs operators to determine exact position of HPCS Injection valve and status of fuses, and to send' Maintenance for repairs SO Verifies that feedwater system, power, pressure, and level are stable

,. , - - ,-x-

? . . . .

Operator Actions Form ES-301-4 ES-301 Page 5 of 9 Scenario No.: 3 Event No.: 4 Event

Description:

_ Hot Surae Tank level controller outnut fails downscale causina level to decrease.

l Time Position Applicant's Actions or Behavior SO Respond to annunciators:

1H13-P680-7-E12, CNDS DEM.TN TRBL 1H13-P680-7-D12, CNDS FLTR TRBL 1H13-P680-2-E3, HST LEVEL LOW Recognizes condensate flow at 0 gpm and output of HST Level Controller at 0%, informs US Using HST Level Controller in MANUAL or manual rheostat for 1N21-F220 restores and maintains approximately 120" in HST US Directs SO to attempt to restore and maintain HST level using manual control of the HST Level Controller, 1N21-R475, or the IN21-F220 rheostat, 1N21-R708.

Directs SO to restore and maintain approximately 120" in the HST Verifies I&C contacted for repairs BOP Backs up SO with ARI usage and anhunciators Contacts I&C for repairs Calls PPO to investigate Condensate local panel to clear trouble alarms Y

s

m x

ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 5 Page 6 of 9 Event

Description:

- A fire occurs in MCC FID05 which amona various non-essential' loads also deenercizes the Recirc numn "B" discharge valves, Time Position Applicant's Actions or Behavior l

US Enters ONI-R23-2, LOSS OF A NON-ESSENTIAL 480V BUS:

Directs a PPO to bus F1D to investigate Directs ROs to investigate panels to determine extent of loss When told that F1D05 is deenergized, looks in .the Plant Data Book for the load list for this bus Verifies Maintenance is contacted for repairs

*

simulator Operator : r-be fire report as stated in directions above.***

SO Recognizes loss of power to Rx Recirc pump "B" isolation valves Responds to annunciators from loss of power to the Recirc FCV HPUs, informs US BOP Dispatch PPO to F1D Upon being informed of Recirc pump HPU annunciators by SO, investigates, tells US that both FCV HPU subloops swapped to #2 in LEAD and #1 in MAINT mode

- - Simulator Operators acting as the PPO sent to F1D, inform control room that there is smoke in TPC 647' caused probably by F1D05. The panel is now deenergized but is charred on the outside of the panel. It appears that the fire is no longer burning but the fire brigade is manning to assess the situation and have ordered ld.m out of the area.

US Enters ONI-P54, FIRE e

I r

ES-301 Operator Actions Form ES-301-4 1

Scenario No.: 3 Event No.: 6 Page 7 of 9 Event

Description:

_Both seals fail on the "B" Recirc numn,durina the ensuinq scram RPS fails to-work properly and the operator utilizes the.

Redundant Reactivity Control System to shutdown the Rx, MSIVs auto close at 807 noia due to the Rx Mode Switch contacts beina stuck in the OPERATE nosition. and Div. 2 Essential 4.16 KV bus (.H12)

X fails to open

[ imido the trancient, l

i Time Position Applicant's Actions or Behavior Loss of "B" Recirc Pump Outer Seal SO Responds to the following annunciators to determine that the outer (#2) seal on the "B" Recirc pump is degrading:

1H13-Pr10-4-B10, RCIRC B OUTER SEAL LKG HI 1H13-P680-4-A10, RCIRC B INNER SEAL FLOW HI/LO Notes No. 2 Seal Cavity pressure decreasing, informs US US Direct BOP to monitor Recirc Pump Seal temperatures Directs the "B" Recire pump tripped if seal temps.

>180"F May decide to call Operations Manager and/or the System Engineer BOP As directed by US, monitors Recirc pump seal temps. on panel H13-P614 Loss of "B" Recirc Pump Inner Seal / Drywell Leak SO Notes decreasing No. 1 Seal Cavity pressure May prompt / remind US that he cannot isolate the "B" recirc loop due to fire Notes increasing DW pressure As directed by US, inserts a manual Rx scram US Upon realizing either that he has an unisolable leak and/or increasing DW pressure, orders a Rx Scram l

a- .

! ES-301 Operator Actions Form ES-301-4 Scenario _No.: 3 Event No.: 6 (cont) Page 8.of 9 Event

Description:

Both seals fail on the "B" Recire cumo,durinq the ensuinq scram RPS fails to work nronerly and the operator utilizes the Redundant Reactivity Control System to shutdown the Rx, MSIVs auto close at 807 nsin due to the Rx Mode Switch contacts beinq stuck in the OPERATE nosition, and Div. 2 Essential 4.16 KV bus (XH12) fails to onen durinq the transient.

Time Position Applicant's Actions or Behavior Scram / Drywell Leak into Containment / MSIV Closure US At 1.68 psig DW enters PEI-B13, RPV Control (Non-ATWSi t Directs initial pressure control using Bypass valves then when MSIVs close will change to SRVs, maintaining 800-1000 psig, this pressure band will change when US determines that a cooldown will be required to depressurize the leak into the DW When told by SO that the feed system is unavai:able, will direct level control using RCIC, to maintain 185-215" When RCIC can't maintain 185-215", directs CRD Alternate Injectior Directs Hydrogen Analyzers started

- At 807 psig in the RPV, MSIVs will auto close due to failure of the Rx Mode Switch, this will occur either during the DW leak or as crew depressurizes the RPV.

US At 1.68 psig DW also enters PEI-T23, Containment Controls Directs BOP to initiate Cntmt Sprays at 2.25 psig Cntmt pressure and to secure sprays if Cntmt pressure drops below 1.75 psig Evaluates Cntmt pressure for Pressure Suppression Pressure Directs DW Cooling restored per PEI-SPI 2.1 Directs Cntmt , Cooling restored per PEI-SPI 2.2

l i

l ES-301 Operator Actions Form ES-301-4 !

s --

Scenario No.:- 3 Event No.: 6 (cont) _, Page 9 of 9 Event

Description:

_Both seals fail on the "B" Recire numn.during the ensuina scram RPS fails to work properly and the operator utilizes the Redundant Reactivity Control System to shutdown the Rx, MSIVs auto close at 807 nsia due to the Rx Mode Switch contacts beina stuck in the PPERATE nosition, and Div. 2 Essential 4.16 Ky bus (XH12) fails to onen ,,

during the transient.

J Time Position Applicant's Actions or Behavior SO Recognizes a failure of RPS to shutdown the Rx, informs US Manually arms and depresses the Alternate Rod Insertion pushbuttons Recognizes Rx shutdown, informs US Recognizes loss of RFPTs when MSIVs close, informs US As directed by US, initiates a controlled cooldown not to exceed 100 F/Hr using RCIC and SRVs BOP As directed by US:

Starts Hydrogen Analyzers Starts RCIC for level control fcllowing MSIV closure Restores DW Cooling per PEI-SPI 2.1 Restores Cntmt Cooling per PEI-SPI 2.2 Initiates Containment Sprays, secures sprays at

<1.75psig Cntmt press.

May assist in maintaining pressure band using SRVs Line up for CRD Alternate Injection per PEI-SPI 4.1 Recognizes closure of MSIVs, informs US Recognizes that the Division 1 Stub Bus breaker, EH1116, did not auto open on the LOCA signal, informs US Terminatina Criteria _: RPV 'eing b cooled down at 100'F/ hour to mitigate effects of leak in the drywell.

Containment -pressure is stable by use of containment sprays. Drywell cooling restored.

As Containment temperature and resources warrant, containment cooling is being restored.

EEerpency Plant Alert CA1

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ES-301 Scenario Events Form ES-301-3 simulation Facility: Perry Station Scenario No.: 4 Examiners: D. McNeil Applicants:

J. Lennartz H. Peterson Initial Conditions: Rx at 100% CTP. HPCS is OOS Turnovers __ Plant is onarating at 100% nower. all rods out on EOC nullsheet, HPCS is OOS due to excessive vibration durinq last numn run SVI, last shift nlaqqd it in secured status and danner taqqed. As soon as you take the shift you need to reduce power to 00% and nerform SVI-C85-T1314. SOC has been informed of the power decrease and has prid loads established for the nower decrease. Following complction of the SVI we olan on maintaininq nower a_t 90% until further notice from SOC.

(Direct US to have ATC do the SVI)

Event Malf, Event Event No. No. Type

Description 1 R Reduce power using Recirc flow to s90%

2 N Perform SVI-C85-T1314 (Bypass valve cycling)

TC04E C Bypass valve sticks open 3 TH20B I Narrow Range "A" Variable Leg Line break in Cntmt.

4 C/M Spurious MSIV closure w/ ATWS C307 C Motor Feed Pump fails to start CB05 C SLC pumps fail to start (CB06 for "B" pump)

RC04 I RCIC pump trip

, RV04 C Three SRVs fail La open

(N) ormal, (R)eactivity, (I)nstrument, (C)omponent, (M) aj or Chief Examiner: '

/

J

ES-301 Operator Actions Form ES-301-4 Scenario No.- 4 Event No.: 1 page 2 of 7 Event

Description:

Power decrease usino Recire flow to 90% nower.

Time Position Applicant's Actions or Behavior US Directs SO to pertcu power decrease to ' 90% power using Rx Recirc flow Directs that SOC, Chemistry, Health Physics ir. formed Oversees power decrease At completion of power decrease, directs SO or BOP to perform SVI-C85-T1314 SO Decreases Rx power by decreasing Rx Recirc flow Stops periodically to allow power / pressure / level /NIs to stabilize between FCV movements Stops power decrease at approximately 90% power Informs US of completion of power decrease Informs System Dispatch (SOC) of power decrease !

~

BOP As directed by US, notifies Chemistry and HP of power decrease 4

l L

ES-301 Operator Actions Form ES-301-4 Scenario No.: 4 Event No.: 2 Page 3 of 7 Event

Description:

_ Performance of SVI-C85-T1314. Turbine Bvnass Valve Operability Test, however durino the test Bvoass valve #5 will not close.

' Time Position Applicant's Actions or Behavior SO Performs SVI-C85-T1314:

Aligns system for test by depressing the Bypass Valve Testing PB As each individual TEST pushbutton is held depressed, observes BPV opens As TEST pushbutton is released, observes BPV close Upon testing #5 BPV, recognizes that #5 BPV does not close, informs US Ensures plant is stable, informs US US Verifies I&C and system engineer are contacted for repairs and assistance Instructs SO to back out of SVI, may keep Bypass Valves in TEST until problem can be diagnosed by I&C or the System Engineer Consults Tech Specs:

3.7.6 Restore w/i 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or <25% pwr w/i 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 3.3.2.1 Immediately suspend control rod withdrawal Instructs SO to suspend control rod withdrawal (all rods are fully withdrawn already)

BOP As directed by US, contact I&C and/or System-Engineer for assistance

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ES-301 Operator Actions Form ES-301-4 Scenario No.: 4 Event No.: '3 , Page 4 of 7 Event Descriptioni_The "A" narrow range level instrument variable leo breaks in the Cntmt, causino an increase in Cntmt. pressure. This will cause the Feedwater Level Control System to see a false low level-and

_ increase feed flow. Crew should rennond by takino Manual control of FN but ae instrument drifts low it will cause a Recirc FCV runback and a scram on level 3.

Time Posit on Applicant's Actions or Behavior SO Responds to either observed level fluctuations or to the following annunciators:

H13-P680-3-A9 Rx Level'Hi/Lo L7/L4 H13-P680-3-B6 Rx Level Channel Error High Informs US of Narrow Range channels "B&C" reading higher than "A" As directed by US places RFPTs A & B on their manual speed control dials Reduces feed flow to restore level to its normal band (192-200")

Notes that a Recirc pump downshift occurs when level "A" instrument passes through level 3 (178")

Notes that a level 8 scram occurs US Enters ONI-C34, "Feedwater Flow Control Malfunction":

Directs SO to put FW Control on Manual Speed Control Dials Directs SO to restore 192-200" RPV level Verifies I&C contacted for assistance - I May order a Reactor Scram if he feels that he has no level control and a scram is pending BOP As directed by US, contacts I&C for assistance

/

c ES-301 Operator Actions Form ES-301-4 Scenario No.: 4 Event No.: 4 Page 5 of 7 Event'Descriptioni_ As crew resocnds to the scram, a sourious closure of the MSIVs occurs. Durino-the ensuing transient the followinq component failures occurf the MFP fails to start. both SLC numns fail to start, the RCIC Turbine trios, and durina the-Emergency Deoressurization three of the AQE valves fail to open.

Time Position Applicant's Actions or Behavior US Enters PEI-B13, RPV Control (ATWS):

Directs initiation of Staadby Liquid Control Directs ADS inhibited Directs Hydrogen Analyzers started Directs SO to trip Recirc pumps Directs SO to use PEI-SPI section 1 to insert control rods Directs BOP terminate / prevent injection of inside the shroud systems using PEI-SPI 5.1 & 5.2 Directs BOP to line up at least two outside the shroud injection cystems using PEI-SPI 6.1 & 6.2 Directs level initially stabilized then a band of 50-100" using the RCIC system Directs CRD Alternate Injection lined up using PEI-SPI 4.1 Directs a pressure band of 800-1000 psig using SRVs When informed of incomplete MSIV isolation by BOP will direct that all MSIVs be closed to complete the isolation, however when he gets far enough along in PEI-B13 will realize that MSIVs must be reopened and give this order When informed of the RCIC trip will realize that he has a loss of all high pressure injection and be looking for a determination of whether or not he can maintain RPV level >-25" When determines that level cannot be maintained >-25",

directs entry into PEI-B13, Emergency Deprercurization Directs FW Inj. Prevention using PEI-SPI 5.3 When all injection is prevented, directs 8 ADS valves opened When told <8 ADS valves open, dire' cts total of 8 SRVs opened After ED, directs injection using outside the shroud systems as soon as pressure is <120 psig, then inject to achieve >-25"

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ES-301 Operator Actions Form ES-301-4 Scenario No.: __4 Event No.: 4 (cont) Page 6 of 7 r

~ Event

Description:

As crew responds to the etram, a sourious closure of the MSIVs occurs. During the ensuing transient the followinq component failures occur; tbn MFP fails to start, both SLC pumps fail to start, the RCIC Turbian ins, and during the Emergency Depressurization three of the ADS valves fail to open.

Time Position Applicant's Actions or Behavior U S Enters PEI-T23, " Containment Control", if determines (cont) cant maintain < HCL, goes to PEI-B13 to Emergency Depressurize At Level 1 enters PEI M51/56, Hydrogen Control, directs H 19 niters started 2

50 Places Rx Mode Switch in SHUTDOWN Recognizes incomplete scram, APRMs not downscale, informs US Inserts a manual ARI, re_ognizes rods not inserted, APRMs not downscale, informs US As directed by US will insert control rods using PEI-SPI 1.3, Manual insertion With MSIVs closed, will determine that the MFP did not auto start, will attempt to manually start the MFP (unsuccessful), will inform US of no available feedwater for injection As directed by US, 7erforms FW Injection Prevention per PEI SPI 5.3 If directed by US, injects into RPV uaing FW Booster pumps following ED BOP Ftarts Hydrogen Analyzers As directed by US, initiates SLC, recognizes failure, informs US As directed by US, inhibits ADS As directed by US, aligns for outside the shroud injection using PEI-SPI 6.1 & 6.2 As directed by US, performs Terminate / prevent actions per PEI-SPI 5.1 & 5.2 Recognize MSIV closure, inform US, if directed by US, closes all MSIVs e

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i ES-301 Operator Actions Form ES-301-4 Scenario No.: 4 Event No.: 4 (cont) Page7of7l Event.

Description:

__,_As' crew responds to the scram, a sourious closure of l

, the MSIVs occuro. Durina the ensuing transient the followinq component :

failures occur; the MFP fails to start, both SLC pumps fail to start, the RCIC Turbine trins. and during the Emergency Depressurination three of the ADS valves fail to open.

Time Position Applicant's Actions or Behavior B O P Recognize RCIC trip, inform US (cont)

Maintain pressure using SR7s per US direction Performs Emergency Depressurization per US direction Recognize failure of three ADS valves, opens additional valves per US direction to obtain eight ,

valves open If directed by US, uses RHR Outside the Shroud injection to maintain RPV level following the ED Starts Hydrogen igniters per US direction Terminatino Criteria: Plant is stable following an Emergency Depressurizati on with level being maintained using either the Rx Feed Booster Pumps and/or RHR lined up for outside the shroud injection. Control rods are being manually inserted to shutdown the Reactor.

Emeroency Plans Site Area Emergency CS1, AS2, AS3

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ML20199A307

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