Text

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 951127-1201
	ML20129E641
Person / Time
Site:	San Onofre
Issue date:	01/05/1996
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9610280125
	Download: ML20129E641 (231)
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r ES-301 Administrative Topics Outline Form ES-301-1 Examination Level: SRO Facility: San )nofre Nuclear Generating Station hk of Examination: 27 November 1995 l Examiner's Name (print): I Administrative Describe Method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A1 Estimated Critical J106S - ECP Calculation Position 001-010-A4-03 3.9 I

Logs & security During declared emergencies, informatior, not directly entered into the CO or SS log is kept on numbered note sheets. After this information is transferred to the logs, what is the disposition of the numbered sheets? l 194-001-A 1-06 3.4 While touring the plant you observe an individual with a secunty photo-ID and an orange non-photo security ID.

What does the orange non-photo security ID mean?

194-001 -K 1-05 3.4 A2 Tagging & Who is required to initial the CO log pnor to giving a clearances significant verbal approval to a worker?

194-001-K1-02 4.1 I How is a SSAM (Shift Superintendent Accelerated Maintenance) item tracked?

194-001-K1-02 4.1 A.3 Radiation Control You are the Emergency Coordinator. An emergency exposure to protect valuable property is necessary. What is the maximum exposure authorized?

194-001-K 1-03 3.4 A special repair must be made to the plant. Only one individual is available who is qualified to perform the repair.

The expected job exposure is 1200 mrem. The worker has no exposure this year and a cumulative exposure over the last five (5) years of 9 rem. Whose approval for exposure extension is required?

194-001-Kl-04 3.5 A.4 Emergency J1265 - Determine Protective Action Recommendation Procedure 194-001-A 1-16 4.4

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Examiner: Chief Examiner: -

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ES-301 Individu:1 Wrlk-threugh Test Outline Form ES 301-2 Examination Level: SRO Facility: San Onofre Nuclear Generating Station Week of Examination: 27 November 1995 Examiner's Name (print):

! System / JPM Safety Planned Follow-up Questions:

! Function K/A/G // Importance // Description i 1. J036S - Align four finger 1 001-010-K4-08 // 2.5 // Why are the 4 finger CEAs

.! CEA misaligned from the rest of Shutdown Group A when j 001-000-G0-13 3.6 the CEAs are initially withdrawn?

1 000-003-K2-05 // 2.8 // Will a single rod drop cause a

] reactor trip?

2. 3033FS - Rad Monitor IX 073-000-KI-01// 3.9 // Using elementary 30817,

Surveillance determine how many continuous exhaust units must be

! 073-000-A4-01 3.9 deenergized to cause FV-7202 to close?

073-000-K3-01// 4.2 // Besides a high radiation

alarm, what other action / event on 2/3RE7808C will l cause FV-7202 to close?

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3. 3027S - Start RCP IV 003-000-K6-02 // 3.1// SCE expects that RCP seals i 002-000-G0-09 34 will remain intact with RCS in Hot Standby for 24

hours without CCW cooling. What condition (or

! conditions) must be met at the end of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

period? ;

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000-011-K3-14 // 4.2 // Why is it necessary to trip one

, RCP in each loop if RCS pressure falls to 1430 psia following a SIAS during SPTAs?

I 4. 3113S - RAS Actuation II 006-020-K4-03 // 3.6 // How could a low Containment Verification Emergency Sump level lead to a potential radiological 006-020-A3-04 4.3 release on a Recirculation Actuation Signal?

006-020-K4-01// 3.0 // What is the purpose of j maintaining nummum Si flow after RAS?

l S. JlISS - Transfer Charging Ill 004-000-Ki-06 // 3.1// Under what circumstances

] Pump Suction post-LOCA would the Boric Acid Makeup pump NOT stop during j 000-011-Al-05 3.9 this evolution?

006-020-Al-05 // 3.4 // Why is the charging pump suction shifted from the Boric Acid Makeup Tanks to l the Refueling Water Storage Tank post-LOCA?

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6. J017 - Secure CEDMCS MG I 001-000-G0-07 // 3.3 // if you had opened the Set generator output breaker on panel L-046 instead of L.

001000-G0-09 3.6 045 during the shutdown of MG set L-85, what would be the efTect on plant status?

001-010-K6-03 // 3 3 // Why do you verify that amps have increased on MG set L-86?

7. J019 - Perform actions as VIII 062-000 GO-07 // 3.2 // What is the purpose of the CRS outside Control Room Fire Isolation switches?

000-068-A 1-10 3.9 062-000-A2-01// 3.9 // What is the purpose of transferring the power supply for the source range neutron flux monitor from Train 'B' to Train 'A'?

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8. Jl17 - Restore Non-qualified VII C62-000-K4-04 // 2.9 // Since the equipment being i Loads from Outside Control restored is "Important-to-safety" why is it de-l Room energized initi ally?

062-000 A2-01 3.9 062-000-K4-03 // 3.1// If a degraded grid voltage condition occurs and the diesel generator is parallelled with the preferred source, what action is required and whyis it necessary?

9. J041S - Continue Startup of V 000-007-G0-10 // 4.1// SO23-12-1 requires Reac Main Feedwater Pump Trip Override (RTO) actuated when verifying RCS ,

K-005 Heat Removal. What conditions are required for !

l 059-000-A0-01 3.1 correct RTO actuation?

059-000-G0-07 // 3.2 // Using elementary 30901 or 30902, explain the interlocks necessary for the MFWP turning gear to start. .

l l 10, J013S - Transfer Shutdown IV 005-000-K4-11// 3.9 // How is shutdon cooling l Cooling from Parallel Pump & flowrate affected if a 16" ilowpath is not available?

Heat Exchanger Operation to 005-000-K3-07 // 3.6 // Shutdown Cooling is in Single Pump & Heat Exchanger senice with one (1) pump and one (1) heat exchanger 005-000-A1-01 3.6 in operation. Temperature is 165 F. 2HV-9339 is found closed. What is the required saturation pressure margin?

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Examiner: - Chief Examiner:

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p Simulation Facility: SONGS 2/3 Scenario No.: 1 Examiners : Applicants :

l Initial conditions : Recovered a Dropped CEA 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ano. Circulatine Water DP is between 8 and 9 PSID with l Screen wash numn in senice. Auxiliary Feedwater numn P-504 Out Of Senice for Boundary of the week exnected return in four hours.

Turnover:

Event . Malf. Event Event K/A's No. No. Type

Description PEM P-504 Rack out Scieen Wash Pump Auto Start 1 RO-R Increase Power to 100%

BOP-N 2 RC09A RO-I Reactor Coolant Pump Speed Sensor Failure 035010A203 1 3.6 3 RD03 RO-C Dropped CEA 000003A105 4.1 4 RC03 RO-R Reactor Coolant System Leak 000009A204 BOP-R 4.0 5 RC03 RO-M Loss Of Coolant Accident 000011G011 BOP-M 4.5 6 RP01G BOP-C Component Coolant Water Pump Auto Stan Failure 008030A304 3.9 7 EC08D RO-C HPSI pump Over current ground 006000A202 4.3

(N)onnal, (R)eactivity, (I)nstrunent, (C)omponent, (M)ajor (PEM) Preexisting Malfunctions Examiner-ChiefExaminer:

Simulation Facility: SONGS 2/3 Scenario No.: 2 Examiners : Applicants :

Initial conditions : Circulatine Water DP is between 8 and 9 PSID with Screen wash nump in service. Auxiliary Eeedwater nump P-504 Out Of Service for Boundary of the week expected return in four hours Tumover:

' Event Malf. Event Event K/A's No. No. Type

Description PEM P-504 Rack out Screen Wash Pump Auto Start 1 SG03E RO-I Steam Generator Pressure Transmitter Failure 035010A203 3.6 2 RX05A RO-! Pressurizer Level Setpoint Failure 000028A108 3.6 3 FW12 BOP-C Condensate Pump Sheared Shaft 056000A204 2.8 4 SG02A RO-R Steam Generator Tube Lea c i 000037G008 BOP-N Down power req 2 ired 3.9 5 CVl7A RO-C Boric Acid Makeup pump failure OC GRD 004000A401 3.9 6 SG02A RO-M Steam Generator Tube Rupture 000038A132 BOP-M 4.7

(N)ormal, (R)eactivity, (I)nstmment, (C)omponent, (M)ajor (PEM) Preexisting Malfunctions Examiner:

ChiefExaminer:

Simulation Facility: SONGS 2/3 Scenario No.: 3 Examiners : Applicants :

Initial conditions : Circulatine Water DP is between 8 and 9 PSID with Screen wash pumn in service. Auxiliary Feedwater numn P-504 is Out Service for Boundary of the week expected retum in four hours Turnover:

Even. Malf. Event Event K/A's No. No. Type

Description PEM P-504 Rack out Screen Wash Pump Auto Start .

1 1 CWO5C BOP-C Loss of Circulating Water Pump P-117 overcurrent ground 075000A202 BOP-N Downpower required 2.7 RO-R 2 RC10A RO-I RCS T cold Temperture Transmitter Failure 00200(. A103 3.3 3 ED03B RO-C Loss of 4160 Emergency Bus 062000A201 i 3.8 )

4 ED01 RO-M Loss of 0ffsite Power 0000562448 BOP-M 4.5 5 FW25 BOP-C Overspeed trip of P-140 061000A204 3.8

(N)ormal, (R)cactivity, (1)nstnunent, (C)omponent, (M)ajor (PEM) Preexisting Malfunctions l

Examiner.

ChiefExaminer:

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l Simulation Facility: SONGS 2/3 Scenario No.: 4 BACKUP Exammers : Applicants : l I

1 Initial conditions : Circulatine Water DP is between 8 and 9 PSID with Screen wash pumn in service.

Au. xiliary Feedwater numn P-504 Out Of Service for Boundary of the week expected retum in four hours 1

Turnover: ,

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Event Malf. Event Event K/A's No. No. Type

Description PEM P-504 Rack out l Screen Wash Pump Auto Start 1 WD02 BOP-C Ruptured Waste Gas Decay Tank 071000A203 3.3 2 FWO9A BOP-N Feedwater Pump Turbine High Vibration followed by 059000A204 i RO-R feedwater pump trip 3.3 l 1 3 RC10A RO-1 RCS T Cold Transmitter Failure nimognoll 3.4 4 RP0lM RO-C Containment Spray Pump Auto Start Failure 026000A301 l 4.5 5 MS03A RO-M Main Steam Line Break Inside Containment 000040A201 BOP-M 4.7

. * (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (PEM) Preexisting Malfunctions Extaniner:

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} Report -

ALL "TG" TAGGED ITEMS

Print Date: 11/13/95

' L.tsson Plan #: System: gen emp trng Test Item.#: 8180 Status: LCF Objective : Point Value: 1.00 j === -

I Question: You are the Shift Superintendent on duty. During your plant tour

you come across an area., posted with a red and white safety j warning sign. i i Which one of the following would require placement of a red and I white safety warning sign?

f A. Overhead work in progress B. Escaping gas or working on fuel lines C. Confined Space Atmospheric Monitoring Required D. Permit-Required confined Space Answer: D

Reference:

SO123-XVI-1 Quest Type: MC Time Est: 4 (

System: gen emp trng Level: SRO Graphic: ;

KA #:194-000-K1-14 KA Value: RO: SRO:3.6 J Task #s: l Written'/ Revised By: Miller, D. Date:10/24/95 Verified: W '

Verified By: Date:

W UJ (2 rr revd Page: 1 {q}((()

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f Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: System: Test Item #: 8207 l Status: LCF Objective : Point Value: 1.00 1

Question: Chemistry samples indicate specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Technical Specification 3.4.7 required you to be in at least HOT STANDBY with RCS average temperature less than 500 deg F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Which one of the following is the bases for this action?

I A. Prevents release of activity into the secondary systems

B. Prevents release of activity into containment j C. Prevents release of activity in the event of a steam generator tube rupture D. Prevents release of activity in the event of a loss of

coolant accident with a loss of offsite power 4

Answer: C

Reference:

T.S. 3/4.4.7 P. B 3/4 4-5 Quest Type: MC Time Est: 4 System: Level: RO/SRO Graphic:

KA #:000-076-G0-04 KA Value: RO:2.1 SRO:3.7 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #:

System: admin Test Item #: 8344 Status: LCF Objective : Point Value: 1.00 ,

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Question: Which one of the folowing individuals should be required to have an unscheduled shift alcohol screen or Station Manager's approval prior to access to the protected area at SONGS 2/3 per the l

" Fitness for Duty" policy"?

i A. An employee that consumed two cans of beer at a pincic at 10 AM prior to reporting to work at 4 PM.

B. An employee that shared a bottle of wine with his wife at I 1

a 7 PM dinner party prior to being called in for overtime i as an extra RO at 11 PM.

4 C. An employee called in for emergency maintenance at 11 PM that notified security that he had been to happy hour at his hotel until 5 PM and his blood alcohol content is 0.02%.

D. An employee who is called in on overtime at 4 PM reports !

, that he has taken a prescribed codeine based cough syrup '

at noon.

i Answer: B

Reference:

D-006 Quest Type: MC Time Est: 4

System: admin Level: RO/SRO Graphic:

KA #:194-001-K1-05 KA Value: RO:3.1 SRO:3.4 1

Task #s:

Written / Revised By: Miller, D Date:10/12/95 Verified: W Verified By: Date:

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1 Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 i

Lesson Plan #: System: ctmt entry Test Item #: 8345 Status: LCF Objective : Point Value: 1.00

Question: Given the following:

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Plant is at 100% power There is a suspected RCS leak inside containment The Shift Superintendent and Health Physics Supervisor have authorized entry into Containment to walkdown systems looking for ler.ks i Which one of the following is required prior to entry into l containment? ,

a l A. Health Physics Manager be present at the tailboard. I i )

B. Health Physics Manager approval for areas greater than 10 l rem /hr. !

! C. Alternate exit from containment provided and verifed by i health physics.

D. A person should be stationed inside the containment to assist.

Answer: C

Reference:

SO123-VII-20.10.8 Quest Type: MC Time Est: 4 System: ctmt entry Level: RO/SRO Graphic:

KA #:103-000-A2-05 KA Value: RO:2.9 SRO:3.9 Task #s:

Written / Revised By: Miller, D Date:10/12/95 Verified: W Verified By: Date: j

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0711 System: AOI Test Item #: 7359 Status: LCF Objective : 1.3 Point Value: 1.00 Question: How is a emergency boration flowpath assured on a loss of the Train "B" 1E-480 V bus B06? ;

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A. One Charging pump and both Boric Acid Makeup pumps are i powered off the Train "A" 1E-480 V bus B04.

B. One Charging pump, one Boric Acid Makeup pump, and one Gravity Feed valve are powered off the Train "A" 1E-480 V bus B04.

C. Two Charging pumps, one Boric Acid Makeup pump, and one Gravity Feed valve are powered off the Train "A" 1E-480 V bus B04.

D. One Charging pump and both Gravity Feed valves are powered off the Train "A" 1E-480 V bus B04.

Answer: A.

Reference:

SD-SO23-390 Quest Type: MC Time Est: 4 i System: AOI Level: RO/SRO Graphic:

KA #:004-000-K2-02 KA Value: RO:2.9 SRO:3.1 Task #s:

Written / Revised By:NRC Date:09/13/93 Verified: V

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Verified By: NRC Date:09/13/93 Page: 5

i Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 l

Lesson Plan #: 2A0702 System: ADMIN Test Item #: 8195 Status: LCF Objective : Point Value: 1.00

", Question: Units 2/3 has been placed in a condition that requires evacuation of the control room. Following the immediate operator actions

. the Shift Superindent goes to the remote shutdown panel.

Which one of the following should be used to inform the crew members of an evacation of the control room?

A. Phone B. Operator's Beeper C. Page System D. UHF Radio System Answer: D

Reference:

SO23-13-2 PAGE ATT 1 Quest Type: MC Time Est: 4 System: ADMIN Level: SRO Graphic: )

KA #:194-000-Al-10 KA Value: RO:3.9 SRO:3.9 ,

Task #s: I Written / Revised By: Miller, D. Date:10/24/95 Verified: W l Verified By: Date: '

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Page: 6

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i i Report - ALL " M " TAGGED ITEMS i

Print Date: 11/13/95

Lesson Plan #: 2AO702 System: admin Test Item #: 8196

. Status: LCF Objective : Point Value: 1.00 i

j Question: The_ control room has been evacuated due to a fire.

{ Which one of the following would the Shift Superindentent

coordinate with to assess potential damage locally due to the

fire?

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! A. Fire Captain 1

1 l B. Common CO I C. Emergency Services-Officer D. SRO Operations Supervisor

. Answer: B

Reference:

SO23-13-2 Quest Type: MC Time Est: 4 i System: admin- Level: RO/SRO Graphic:

KA #:194-000-K1-16 KA Value: RO:4.2 SRO:4.2 j Task #s:

j Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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1 Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0702 System: AOI Test Item #: 8182 Status: LCF Objective : 1.1 Point Value: 1.00 Question: According to SO23-13-2 Shutdown From Outside The Control Room securing the reactor. coolant pumps is the last required immediate )

actions to be performed from the control room. l Which one of the following is the preferred way to secure the reactor coolant pumps per SO23-13-2?

A. Open the 6.9 KV bus f6eder breakers.

l B. Stop the RCPs from the Second Point of Control. l I

C. Locally open the RCP 6.9KV breakers at switch gear l 2A01 and 2A02. )

I D. Stop the RCPs from the remote shutdown panel. l Answer: A

Reference:

SO23-13-2 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:000-068-G01-10 KA Value: RO:4.1 SRO:4.2 Task #s:

Written / Revised By: Miller, D Date:08/30/95 Verified: W Verified By: Date:

Page: 8

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0705 System: IA Test Item #: 7354 Status: LCF Objective : 1.1.1 Point Value: 1.00 Question: Which one of the following areas will the Instrument Air System AUTOMATICALLY isolate if a large air leak develops in that area?

A. Containment B. Fuel Handling Building C. Radwaste Building D. Penetration Area Answer: A.

Reference:

Quest Type: MC Time Est: 4 System: IA Level: RO/SRO Graphic:

KA #:078-000-K1-03 KA Value: RO:3.3 SRO:3.4 Task #s:

Written / Revised By:NRC Date:09/13/93 Verified: V Verified By: NRC Date:09/13/93 I

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l Report - _ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0705 System: AOI Test Item #: 8267 Status: LCF Objective : 1.1.4 Point Value: 1.00 1

I Question: Instrument air pressure is 58 psi and slowly lowering. In '

accordance with SO23-13-5, Loss of Instrument Air AOI, which one of the following is the first action to be performed?

A. Cross tie the instrument air system and Service Air Systems.

B. Manually trip the reactor-and carryout the SPTA's.

C. Continue to operate at a reduced power level of 50%

D. Commence a shutdown to Hot Standby Answer: B

Reference:

SO23-13-5;0-4, 3.1.3.1 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:000-065-A2-06 KA Value: RO:3.6 SRO:4.2 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W

. Verified By: Date:

Page: 10

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0707 System: AOI Test Item #: 7319 l Status: LCF Objective : 1.1 Point Value: 1.00 l I

l Question: According to SO23-13-7, " Loss Of Component Cooling Water (CCW)/ l Saltwater Cooling (SWC) " , which one of the following conditions would require an IMMEDIATE reactor and turbine trip?

A. Loss of CCW to the CEAs.

B. One (1) stage of a Reactor Coolant Pump (RCP) seal has failed on three (3) RCPs.

C. An RCP thrust bearing temperature greater than 225 degs F.

D. Two (2) stages of a RCP seal have failed on one (1) RCP.

Answer: C.

Reference:

S023-13-7 3.3 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:000-026-A2-04 KA Value: RO:2.5 SRO:2.9 l I

Task #s:

Written / Revised By:NRC Date:09/10/93 Verified: V !

Verified By: NRC Date:09/10/93 )

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Page: 11

Report - ALL "TU" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2AO707 System: AOI Test Item #: 5859 Status: LCF- Objective : 1.5 Point Value: 1.00 Question: The non-critical loop of CCW is being restored to service per l attachment 1 of SO23-13-7, " Loss of CCW/SWC." A note placed before a series of system alignment steps states: "The Letdown Heat Exchanger should be aligned to the Critical Loop that is supplying the Noncritical Loop."

i Which one of the following is the basis for this note? ;

A. While originally an arbitrary assignment, this arrangement is now standardized in various procedures and facilitates .

use of those procedures.

B. This arrangement ensures equalization of flows to various I system loads.

C. This arrangement ensures that the heat load-requirements !

are distributed appropriately between the loops. !

D. This arrangement ensures that radiation monitoring is available to help detect any radioactive leaks into CCW.

Answer: D

Reference:

SO23-13-7 Quest Type: MC Time Est: 4 l' System: AOI Level: RO/SRO. Graphic:

KA #:000-026-K3-03 KA Value: RO:4.0 SRO:4.2 Task #s:

Written / Revised By: Miller, D. Date:11/27/92 Verified: V :

Verified By: Exam Review Group Date:11/25/92 !

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Page: 12 i

i Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2AO708 System: EOI Test Item #: 8206 Status: LCF Objective : Point Value: 1.00 Question: A Loss Of Coolant Accident has occured concurrent with a Loss of l Offsite Power. Core Exit Saturation Margin is lowering rapidly. '

Which one of the following actions should be performed to control '

Core Exit Saturation Nhrgin?

A. Increase pressure Increase temperature B. Decrease pressure Decrease temperature C. Increase pressure Decrease temperature D. Decrease pressure Increase temperature Answer: C

Reference:

SO23-14-7 4.15 Quest Type: MC Time Est: 4 System: EOI Level: kO/SRO Graphic:

KA #:000-074-K1-03 KA Value: RO:4.5 SRO:4.9 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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Page: 13

1 Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0710 System: AOI Test Item #: 8347 Status: LCF Objective : 1.1 Point Value: 1.00 i

Question: SO23-13-10 " Loss of Condenser Vacuum" has a note which states

" Station Technical should be notified to evaluate potential turbine damage anytime condenser backpressure exceeds 4.0" Hg.

{ Which one of the following turbine areas could be damaged?

A. Last stages of the low pressure turbine B. First stages of the low pressure turbine

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C. Last stages of the high pressure turbine 5 D. First stages of the high pressure turbine

] Answer: A l

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Reference:

SO23-13-10 Quest Type: MC Time Est: 4

, System: AOI Level: RO/SRO Graphic:

i KA #:055-000-K3-01 KA Value: RO:2.5 SRO:2.7 l Task #s:

. Written / Revised By: Miller, D. Date:10/12/95 Verified: W

! Verified By: Date:

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4 Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 4

Lesson Plan #: 2A0710 System: AOI Test Item #: 8392 Status: LCF Objective : 1.1 Point Value: 1.00 Question: Given the following:

The plant is at 90% power. ,

" TURBINE VACUUM LO" alarm is lit. '

" EXHAUST HOOD TEMPERATURE HI" Alarm is lit ,

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Condenser vacuum is 7" Hg backpressure I i Which one of the following actions should be taken?

l A. Open the LP turbine seal regulator bypass valves to reduce exhaust hood temperature.

B. Increase turbine load to allow increased exhaust hood

. cooling.

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C. Reduce turbine load as required to stablize condenser vacuum.

l D. Trip the reactor, verify the turbine trip, and implement i SPTA's SO23-12-1 i

1 Answer: D ;

Reference:

SO23-13-10 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic-KA #:000-051-A2-02 KA Value: RO:3.9 SRO:4.1 1 i

Task #s: l Written / Revised By: Miller, D. Date:10/24/95 Verified: W I l Verified By: Date:

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l Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0711 System: AOI Test Item #: 8210 Status: LCF Objective : 1.2 Point Value: 1.00 Question: Which one of the following conditions would require emergency boration of the reactor coolant system?

A. One CEA fails to drop into the core following a reactor trip.

B. Group 6 inserted to 110" while at 100% power.

C. Uncontrolled cooldown of the RCS of 27 deg F caused by excessive steam demand.

D. Uncontrolled cooldown of the RCS of 15 deg F caused by excessive Loss of Coolant Accident.

Answer: C

Reference:

SO23-13-11 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:000-024-K3-01 KA Value: RO:4.1 SRO:4.4 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 16

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2AO713 System: CEDMCS Test Item #: 5485 Status: LCF Objective : 1.2 Poirat Value: 1.00 Question: Unit 2 is operating at 75% power with all CEAs fully withdrawn, when a group 6 CEA drops to the bottom of the core.

Assuming that rod recovery cannot begin for 60 minutes after the rod drops.

Which one of the following is the MAXIMUM REQUIRED Power Reduction?

A. 10% power B. 15% power C. 20% power D. 25% power Answer: B. 15% power

Reference:

SO23-13-13 Quest Type: MC Time Est: 4 System: CEDMCS Level: SRO Graphic:

KA #:000-003-K1-04 KA Value: RO:3.1 SRO:3.7 Task #s: 006537 Written / Revised By: Date: Verified: V Verified By: Date: l Page: 17

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TAGGED ITEMS Print Date: 11/13/95 a

l Lesson Plan #: 2A0714 System: AOI Test Item #: 8298

Status: LCF Objective : Point Value: 1.00

Question: Given the following:

i i

2RT-7870 Condenser Air Ejector radiation monitor setpoint is 1.05E-0 Current steam generator tube leakage is 12 GPD Air Ejector / containment radiation HI alarm actuates 5 minutes following 2RT-7870 HI alarm the reading has risen

to 2.20E-0 I

l Which one of the following action is required for the above conditions?

l A. Commence a controlled plant shutdown and trip the unit at 50% reactor power.

1 i B. Commence a controlled plant shutdown and trip the unit at

35% reactor power.

I

j. C. Commence a rapid plant shutdown and trip the unit at 50%

! reactor power.

2 D. Commence a rapid plant shutdown and trip the unit at 35%

j. reactor power.

Answer: D j~

Reference:

SO23-13-14 PAGE 13 Quest Type: MC Time Est: 4 l System: AOI Level: RO/SRO Graphic: !

KA #:000-037-K3-07 KA Value: RO:4.2 SRO:4.4 i Task.#s:

Written / Revised By: Miller, D Date:10/11/95 Verified: W Verified By: Date:

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Print Date: 11/13/95 -

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Lesson Plan #: 2A0717 System: Cnmt System Test Item #: 5752 Status: LCF Objective.: 1.1 Point Value: 1.00

)

Question: The unit is operating in Mode 1 when an inadvertant SIAS actuated.

The-plant conditions are: )

1

-s- Containment Pressure 0.5 psig

-s- Pressurizer Level 56%

-s- Pressurizer Pressure 2250 psia 1

-s- REPCET Margin to Saturation 32 DEG. F. I l

Which one of the following actions should be taken?

A. Reduce Turbine Load to match with Reactor Power B. Manually Trip the Reactor C. Place SIAS in BYPASS D. Secure all 4 RCPs Answer: A.

Reference:

SO23-13-17 Quest Type: MC Time Est: 4 System: Cnmt System Level: RO/SRO Graphic: ;

KA #:000-007-G0-11 KA Value: RO:4.1 SRO:4.3 Task #s:

Written / Revised By: Miller, D. Date:11/19/92 Verified: V Verified By: Exam Review Group Date:12/09/92 l

Page: 19

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! Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 l

Lesson Plan #: 2A0718 System: AOI Test Item #: 8203 Status: LCF Objective : Point Value: 1.00 i Question: 1E Pressurizer pressure instrument PI-0101-1 (NR) on CR-57 failed high.

i Which one of the following should be placed in bypass?

A. Pressurzier Pressure High

, Pressurizer Pressure Low B. Pressurizer Pressure Low DNBR

LPD

C. Pressurizer Pressure High DNBR LPD

) D. DNBR LPD Answer: C

Reference:

SO23-13-18 Quest Type: MC Time Est: 3 System: AOI Level: RO/SRO Graphic:

KA #: 016-000-K3-07 KA Value: kO:3.5 SRO:3.7 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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1 Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2A0718 System: inst bus Test Item #: 8208 Status: LCF Objective : Point Value: 1.00 Question: A Loss of Vital Bus Y-002 has occurred.

Which one of the following actions should be conducted to verify a reactor trip is NOT required?

A. Perform a channel check on remaining channels.

B. Perform a functional unit test on the remaining channels.

C. Perform a daily surveillance on the remaining channels.

D. Perform a shiftly surveillance on the remaining channels.

Answer: A

Reference:

SO23-13-18 ATT 2 Quest Type: MC Time Est: 4 System: inst bus Level: RO/SRO Graphic:

KA #:000-057-A2-03 KA Value: RO:3.7 SRO:3.9 Task #s:

Written / Revised Bf2 Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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j Report -- ALL "TG" TAGGED ITEMS Print Date: 11/13/95 A f Lesson Plan #: 2A0718 System: AOI Test Item #: 8296 :

Status: LCF Objective : Point Value: 1.00 !

i l -Question: Unit 2 is in MODE 1 when the lower detector of a excore safety il t

Channel 'A' fails.

j Which one of the following describes ALL of the Channel 'A' Plant i

Protection System functional units which must be placed in bypass? ,

i j A. Local Power Density - High 3

DNBR -

Low l B. Local Power Density - High

! Log Power Level - High t ,

a 1

1 C. Linear Power Level - High -

Local Power Density - High i j DNBR - Low I

! D. Linear Power Level - High l Local Power Density - High l Log Power Level - High

! Answer: C l

Reference:

SO23-13-18 ATT 1 Quest Type: MC Time Est: 4 i System: AOI Level: CR-SYS Graphic:

i KA #:000-033-K3-02 KA Value: RO:3.2 SRO:3.6 i Task #s:

I Written / Revised By: Miller, D Date:10/11/95 Verified: W i Verified By: Date: l maammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma I t

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 l Lesson Plan #: 2A0718 System: AOI Test Item #: 8277 Status: LCF Objective : 1.1 Point Value: 1.00 Question: Given the following:

Unit 2 is operating at 100%

DNBR is in bypass on channel A and in trip on channel C LPD is in bypass on channel A and in trip on channel C A loss of Y002 has just occurred Which one of the following actions should be taken assuming the unit is still at power?

A. Shutdown the reactor by reducing power at the maximum rate.

B. Return channel A to bypass condition C. Transfer the YOO2 to it alternate source D. Return channel C to trip condition Answer: A

Reference:

SO23-13-18 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:012-000-A2-06 KA Value: RO:4.4 SRO:4.7 Task #s:

Written / Revised By: Miller, D Date:10/11/95 Verified: W Verified By: Date:

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Print Date: 11/13/95 l i

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Lesson Plan #: 2A0720 System: ctmt integrity Test Item #: 8176

, Status: LCF Objective : Point Value: 1.00 ;

}

Question: Refueling operations are in progress. Maintenance is attempting

to move a large welder into containment thru the personnel hatch.

! Which one of the following will ensure containment integrity is

! maintained during this operation?

i I

A. Both ramps installed and one door closed i i

B. Both ramps installed and both doors closed C. One ramp installed and both doors closed i D. One ramp installed and one door closed i Answer: D l

l

Reference:

T.S. 3/4.9.4 Quest Type: MC Time Est: 4 j System: ctmt integrity Level: SRO Graphic:

4 KA #:000-069-K2-03 KA Value: RO:2.8 SRO:2.9 l Task #s:

Date:10/24/95 Verified: W Written / Revised By: Miller, D.

Verified By: Date:

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ALL "TG" TAGGED ITEMS Print Date: 11/11/95 Lesson Plan #: 2AO720 System: AOI Test Item #: 3186 Status: LCF Objective : 1.2 Point Value: 1.00 Question: Core Off load is in progress. A spent fuel assembly is being moved from the containment to the spent fuel pool. During this fuel movement the upender. operator informs the refueling SRO that Reactor Vessel Pool Seal pressures read 61 PSI and 0 PSI.

Which one of the following actions should be taken by the refueling SRO?

A. Leave the fuel assembly in the upender and secure core alterations.

B. Continue with fuel movement until fuel assembly is in the spent fuel pool racks and then secure core alterations.

C. Return the fuel assembly to the core and then secure core alterations.

D. Continue with fuel movement and log the seal pressure twice per shift in the CO log.

Answer: B

Reference:

SO23-13-20 Quest Type: MC Time Est: 4 System: AOI Level: RO/SRO Graphic:

KA #:000-036-Al-04 KA Value: RO:3.1 SRO:3.7 Task #s:

Written / Revised By: Miller, D. Date:08/30/95 Verified: W Verified By: Date:

Page: 25

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< Lesson Plan #: 2AP101 System: ADMIN Test Item #: 5149 l

{ Status: LCF Objective : 1.1.17 Point Value: 1.00 j Question: Use of a leverage device is allowed on:

e l A. Motor Operated Valve (MOV)

! B. Diaphragm Valve

.- C. Kerotest Valve 1

4 i D. Manual Glove Valve i

1 1

i Answer: D i

l

Reference:

SO123-0-23.1 Quest Type: MC Time Est: 4 System: ADMIN Level: ANPEO Graphic:

KA #: 194-001-K1-01 KA Value: RO:3.6 SRO:3.7

! Task #s:

Written / Revised By:Kuhner, P. Date:07/01/92 Verified: W Verified.By: Date:

4,

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 i Lesson Plan #: 2AP106 System: ADMIN Test Item #: 5323 '

Status: LCF Objective : 1.6 Point Value: 1.00 l Question: Which one of the following could be performed without a I Maintenance Order?

A. Resetting a tripped deluge valve.

B. I&C adjusting feedwater heater level controllers.

C, In-service Tests that do not remove equipment from

{ service.

l D. Meggering Non-Important-to-Safety motors.

, Answer: C.

Reference:

SO123-0-21; 1-20 Quest Type: MC Time Est: 4 System: ADMIN Level: ANPEO Graphic: i i KA #:194-001-K1-02 KA Value: RO:3.7 SRO:4.1 l Task #s: i 4

Written / Revised By: Gates, P. Date:09/15/92 Verified: V Verified By: Exam Review Group Date:05/20/93 l mammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmamaammmmmmme d

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ALL *TG" TAGGED' ITEMS Print Date: 11/13/95 i

Lesson Plan #: 2BF710 System: Rad - Release Test Item #: 8276 :

Status: LCF Objective : 1.2.3 Point Value: 1.00 Question: Annunciator 57C40, " LIQUID RADIATION MONITOR FAILURE" is received !

on Unit 2. The Operator determines that the Neutralization Sump !

Effluent Radiation Monitor, 3RE-7817 is inoperable.

Which one of the following actions must be accomplished to continue discharging to the outfall? l l

A. Composite samples must be taken and analysed for-gross radioactivity.

B. Grab samples most be taken and analysed for gross radioactivity.

C. At least 2 independent samples are drawn and analysed by 2 independent technicians.

D. At least 2 technically qualified members of the facility staff independently verify release line valving.

Answer: B

Reference:

ODCM Quest Type: MC Time Est: 4 Systen: Rad - Release Level: RO/SRO Graphic:

KA #:000-059-K2-01 KA Value: RO:2.7 SRO:2.8 Task #s:

Written / Revised By: Miller, D Date:10/11/95 Verified: W Verified By: Date:

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Lesson Plan #: 2EO703 System: LOCA Test Item #: 5515 Status: LCF Objective : 1.1.2 Point Value: 1.00

=

Question: Why is it recommended to initiate simultaneous hot / cold leg injection BEFORE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months have elapsed following a LOCA7 A. Increased HPSI flow satisfies Core Cooling requirements.

B. Increased HPSI flow satisfies Shutdown Margin requirements.

C. Boric acid precipitation can occur and hinder cooling in the core.

D. Boric acid precipitation can occur and decrease Shutdown Margin.

Answer: C

Reference:

CEN 152 Quest Type: MC Time Est: 4 System: LOCA Level: RO/SRO Graphic:

KA #:000-011-K3-13 KA Value: RO:3.8 SRO:4.2 Task #s: 008627 Written / Revised By:Hollinger, S. . Date:06/12/92 Verified: V Verified By: Exam Review Group Date:11/19/93

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Lesson Plan #: 2EO705 System: EOI Test Item #: 8209 Status: LCF Objective : Point Value: 1.00 i ,

l Question: Which one of the following is the most restrictive conditions for a shutdown margin with a steam line break?

} A. BOL with Tcold at program temperature of 545 deg F

B. EOL with Tcold at program temperature of 545 deg F j

C. BOL with Tcold at program temperature of 553 deg F i l D. EOL with Tcold at program temperature of 553 deg F '

Answer: B

Reference:

T.S. 3/4.1.1 BASES Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic: l KA #:000-040-K1-05 KA Value: RO:4.1 SRO:4.4 '

Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date: l J

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Report - ALL " W TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2EO705 System: EOI Test Item #: 5759 Status: LCF Objective : 1.3.1 Point Value: 1.00 Question: Which one of the following is a reason for lowering pressure in the unaffected' Steam Generator prior to dryout of the affected Steam Generator during a ESDE?

A. To prevent over cooling of the RCS.

B. To prevent T-hot from lowering.

C. To prevent loss of pressurizer pressure.

D. To prevent rapid repressurization of RCS.

Answer: D.

Reference:

SO23-12-5 Quest Type: MC Time Est: 4 System: EOI Level:'RO/SRO Graphic:

KA #:000-040-K1-01 KA Value: RO:4.1 SRO:4.4 Task #s:

Written / Revised By:Ingram, O. Date:11/20/92 Verified: V i Verified By: Exam Review Group Date:11/25/92 1

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Print Date: 11/13/95 i

! Lesson Plan #: 2EO709 System: EOI Test Item #: 8204 Status: LCF Objective : 1.2 Point Value: 1.00 4

Question: Following a reactor trip with a loss of 2A04, Train 'A' 1E 4KV bus, an operator is performing " Diesel Generator Failure Follow-up Actions".

! Which one of the following describes the operation required for i the 2XR1 feeder breaker open pushbutton and bases for the

response regarding this action?

A. Depress the OPEN pushbutton to reset trip conditions and

automatically close the breaker. j i

j B. Depress the OPEN pushbutton to reset overcurrent trip j allowing a re-close attempt.

C. Do NOT operate the OPEN pushbutton because the control power required results in an unnecessary drain on the vital batteries.

1 D. Do NOT operator the OPEN pushbutton because the overcurrent trip will reset allowing the DG output breaker l

to close to a fault.

l Answer: D

Reference:

SO23-12-8 ATT 7 Quest Type: MC Time Est: 4 l

System: EOI Level: RO/SRO Graphic:

i KA #:000-055-A2-06 KA Value: RO:3.7 SRO:4.1 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W i Verified By: Date:

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 1

Lesson Plan #: 2EO712 System: EOI Test Item #: 8271 Status: LCF Objective : 1.2 Point Value: 1.00 l

Question: While verifying the Standard Post Trip Actions it is noticed that l the Megawatt output is NOT lowering.

Which one of the following actions should be performed by the operator? ,

I A. Manually trip the reactor and main turbine B. Close the main steam isolation valves l

C. Close the high pressure and low pressure stop valves :

I D. Close the high pressure and low pressure governor valves l

l Answer: B

Reference:

SO23-12-1; 3, 4F Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic:

KA #:000-029-A2-09 KA Value: RO:4.4 SRO:4.5 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 33

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ALL "TG" TAGGED ITEMS ,

Print Date: 11/13/95 a

! Lesson Plan #: 2EO712 System: EOI Test Item #: 8272 i Status: LCF Objective : 1.2 Point Value: 1.00 i

Question: Unit 2 has experienced a Station Blackout. Communication with the

! Energy Control Center is unavailable. I j l Which one of the following states the proper actions required to restore offsite power?

1 A. Open all circuit breakers and pickup on the first

available SCE 220 kv line.

! B. Open all circuit breakers and pickup on the first l l available SDG&E 220 kv line.

]

C. Close all circuit breakers and pickup on the first available SCE 220 kv line.

D. Close all circuit breakers and pickup on the first j available SDG&E 220 kv line. l i ,

j Answer: A l i

Reference:

SOB NO. 254 Quest Type: MC Time Est: 4

! System: EOI Level: RO/SRO Graphic: ,

KA #:000-055-A2-03 KA Value: RO:3.9 SRO:4.7 '

4 Task #s:

Written / Revised By: miller, d Date:10/10/95 Verified: W

, Verified By: Date:

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 4

, Lesson Plan #: 2EO712 System: EOI Test Item #: 8270 l Status: LCF Objective : 1.3 Point Value: 1.00 I

Question: A reactor trip just occurred on Unit 2.

l The operators have initiated the Standard Post Trip Actions.

Plant conditions are as follows:

l -s- Two CEAs are not fully inserted i -s- Pzr level is at 26%

-s- Pzr Press is at 1950 psia I

-m- S/G water levels are at 29% with MFW RTO actuated

! -u- Containment temperature is 105'F l -m- Containment pressure is 1.0 psig l Which one of the following is the correct operator action to be taken in the SPTAs?

, A. De-energize B15 and B2f 1

! B. Reenergize Pzr heaters to raise RCS pressure C. Override AFW system to feed both S/Gs at greater than 200 gpm D. Ensure containment normal cooling is functioning properly Answer: A

Reference:

SO23-12-1 Quest Type: MC Time Est: 3 System: EOI Level: RO/SRO Graphic:

KA #:000-029-K3-01 KA Value: RO:4.2 SRO:4.5 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 35

Report - ALL "TG" TAGGED ITEMS

Print Date: 11/13/95 Lesson Plan #: 2EO713 System: EOI Test Item #: 8334 Status: LCF Objective : Point Value: 1.00 l Question: A LOCA occured 90 minutes ago. You are monitoring Floating Step 4 "two-phase heat removal established."

Which one of the following temperature indications is required to be monitored during "Two-Phase Heat Removal?"

A. Cold leg temperature !

B. Hot leg temperature C. Core exit temperature D. Heated junction thermocouples Answer: C

Reference:

SO23-12-3 FS 4 Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic: l KA #:017-020-A4-02 KA Value: RO:3.8 SRO:4.1 ;

Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W !

Verified By: Date:

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Print Date: 11/13/95 Lesson Plan #: 2EO713 System: EOI Test Item #: 0161 ,

Status: LCF Objective.: 1.1.2 Point Value: 1.00 '

i Question: Given the following:

Unit 3 tripped from 100% power 60 minutes ago j Reactor Coolant Temp is 535 deg F 1 Reactor Coolant Pressure is 1000 PSIA l Containment Pressure is 3.1 PSIG 1 Pressurizer Level is 21% and slowly rising )

I Which one of the following is the correct number of Reactor !

Coolant pumps that should be secured? l A. One B. Two I C. Three !

D. Four i

e Answer: D

Reference:

SO23-12-3, ATT 13 Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic:

KA #:000-011-Al-03 KA Value: RO:4.0 SRO:4.0 Task #s:

Written / Revised By: Miller, D. Date:10/09/95 Verified: V Verified By: Date:

Page: 37

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Print Date: 11/13/95 I

1 Lesson Plan #: 2EO713 System: EOI Test Item #: 0436

Status: LCF Objective : 1.3 Point Value: 1.00 4 -

l Question: Unit 2 tripped 90 minutes ago. You are in EOI SO23-12-3 LOCA I

attachment for " VOID COMPENSATION".

i l Which one of the following is the purpose of that attachment?

l 4

l A. To compensate for RCP restart void collapse.

I B. To correct the RVLMS for accurate readout on QSPDS and CFMS )

! C. To ensure that there is sufficient inventory to cover the j pressurizer heaters.

l i

D. To verify that the core exit thermocouples have sufficient l j liquid contact to give an accurate response. l Answer: A- !

Reference:

SO23-12-3: 4-0, ATT-18 Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic:

KA #:000-009-K3-21 KA Value: RO:4.2 SRO:4.5 Task #s:

Written / Revised By:Macdonald, J. Date:03/15/90 Verified: V Verified By: Hollinger, S. Date:04/13/90 1

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2EO713 System: EOI Test Item #: 8280 Status: LCF Objective : 1.3 Point Value: 1.00 ;

Question: Given the following:

The unit was tripped 30 minutes ago and a LOCA was diagnosed RCS temperature is 525 degress F.

RCS pressure is 1600 psia Power has been lost to the switchyard 1E power is being supplied by the diesel generators Voids have formed in the head Which one of the following will cause greater cooling in the reactor vessel head? 1 A. Increase RCS pressure to force cooler water into the head.

B. Start a reactor coolant pump to force water into the head area.

C. Secure Charging pump to allow more HPSI flow into the head j D. Lowering RCS pressure to allow flashing in the head area. i Answer: D

Reference:

SO23-12-3: ATT 2 Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic:

KA #:000-009-A2-38 KA Value: RO:3.9 SRO:4.3 Task #s:

Written / Revised By: Miller,D Date:10/11/95 Verified: W ,

Verified By: Date: '

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Prine Date: 11/13/95 '

i i Lesson Plan #: 2EO713 System: EOI Test Item #: 8285 i j Status: LCF Objective : 1.3 Point Value: 1.00 l 1

4 1

l Question: Given the following:

j -

The plant tripped at 1430 hrs.

A LOCA was diagnosed SO23-12-3 attachment 3 cooldown & depresrurization is in use Excessive feedwater flow cooled the RCS to 530 degress F.

i at 1445 i

j At 1530 per procedure, which one of the following is the MINIMUM l RCS temperature allowed?

I l A. 465 Degress F.

! l j B. 455 degress F. .

1

] C. 445 degress F.

4

! D. 435 degress F.

l l Answer: B i

Reference:

SO23-12-3: ATT 3 Quest Type: MC Time Est: 4 l System: EOI Level: RO/SRO Graphic:

! KA #:000-025-Al-01 KA Value: RO:3.6 SRO:3.7 i Task #s:

l Written / Revised By: Miller, D. Date:10/24/95 Verified: W j Verified By: Date:

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2EO716 System: EOI Test Item #: 4042 Status: LCF Objective : 1.1 Point Value: 1.00 Question: A loss of Forced Circulation has occurred as a result of a Loss of Offsite Power. You are attempting to establish natural circulation in accordance with Emergency Operating Instruction SO23-12-7, Loss of Forced Circulation / Loss of Offsite Power.

Which one of the following conditions will require a " Response Not Obtained" action when performing verification of Natural Circulation?

A. Loop delta-T at 30 degrees-F and stable.

B. T-hot / Representative Core Exit Thermocouples delta-T at 5 degrees-F and stable.

C. Reactor Vessel plenum level at 82% and constant.

D. Core Exit Saturation Margin at 21 degrees-F and slowly rising.

Answer: C.

Reference:

EOI SO23-12-7 P.9 Quest Type: MC Time Est: 4 System: EOI Level: RO/SRO Graphic:

KA #:000-056-K1-01 KA Value: RO:3.7 SRO:4.2 Task #s:

Written / Revised By: Miller, D. Date:05/15/91 Verified: V Verified By: Exam Review Group Date:11/13/92 Page: 41

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Print Date: 11/13/95 l

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Lesson Plan #: 2EO720 System: EOI Test Item #: 8259 Status: LCF Objective : Point Value: 1.00 I

Question: Unit 2 entered the Station Blackout procedure SO23-12-8 following a plane crash near the switchyard.

Which one of the following is the reason for ensuring TS-2 DC 127F1 through 127F4 knife switches at diesel generator bus PT cubicle are open? ,

A. Reset the LOVS signal B. Reset the SIAS signal l C. Reset the undervoltage flags D. Reset the overcurrent flags Answer: A

Reference:

SO23-14-8 STEP 4.13 Quest Type: MC Time Est: 4 System: EOI level: RO/SRO Graphic:

KA #:000-058-K3-02 KA Value: RO:4.0 SRO:4.2 l Task #s: l Written / Revised By:/ miller, D Date:10/11/95 Verified: W Verified By: Date:

i Page: 42

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} Print Date: 11/13/95 ..

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i Lesson Plan #: 2LC705 System: ADMIN Test Item #: 5750 Status: LCF . Objective : Point Value: 1.00 l

1 d

Question: Which one of the following statements correctly states radiation

posting or access control requirements at San Onofre?

I A. All areas in which the radiation levels exceed 0.25 i mrem /hr shall be within Restricted Areas and all .

individuals must log into and out of the Restricted Area j for each entry or exit. ;

! B. All areas in which the radiation levels exceed 0.5 mrem /hr-i shall be within Restricted Areas and all individuals must log into and out of the Restricted Area for each entry i or exit.

] i l C. Each accessible area having radiation levels greater than l or equal to 0.25 mrem /hr measured at 30 cm from the 1 source (s) shall be posted as a Radiation Area.

D. Each accessible area having radiation levels greater than or equal to 2.5 mrem /hr measured at 30 cm from the source (s) shall be posted as a Radiation Area.

Answer: D.

Reference:

SO123-VII-7.4 TCN 16-3 Quest Type: MC Time Est: 4 System: ADMIN Level: RO/SRO Graphic:

KA #:194-001-K1-03 KA Value: RO:2.8 SRO:3.4 Task #s:

Written / Revised By: Miller, D. Date:11/19/92 Verified: V Verified By: Exam Review Group Date:12/09/92 l

Page: 43

, i

Report - ALL "TG" TAGGED ITEMS j Print Date: 11/13/95 Lesson Plan #: 2LC705 System: Admin Test Item #: 5746 i Status: LCF Objective : 3.6, 3.7 Point Value: 1.00 i Question: Which one of the following situations can be accomplished without 1

an independent verification for a valve lineup?

2 A. When preparing to enter a Mode where the valve is required to be operable.

a B. When venting a system, opening the valve and removing the

cap.

C. During the installation and removal of a temporary modification involving a valve in the waste water system.

! D. Work Authorization installation and removal of Red Man-at-Work tags on valves on Auxiliary Feedwater System.

Answer: B.

i

Reference:

SO123-0-23 Quest Type: MC Time Est: 4 System: Admin Level: RO/SRO Graphic:

KA #:194-001-K1-01 KA Value: RO:3.6 SRO:3.7 i

Task #s:

!' Written / Revised By: Miller, D. Date:11/19/92 Verified: W Verified By: Date:

j .......................................................................

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Print Date: 11/13/95 l 4

i- Lesson Plan #: 2LC705 System: ADMIN Test Item #: 8348 1 i Status: LCF Objective : E Point Value: 1.00 l l

1 l 1 Question: Which one of the following would require a complete system lineup l l- verification? i I

i i j A. A system misalignment was caused by operator error.

i B. A system misalignment was caused by sabotage. l 1

C. A system misalignment was discovered during a WAR-return )

to service. i D. A system misalignment was discovered during a refueling ,

outage. !

Answer: B

Reference:

SO123-0-23 Quest Type: MC Time Est: 4 I' System: ADMIN Level: PEO-RQL Graphic-KA #:194-001-Al-12 KA Value: RO:3.1 SRO:4.1 I Task #s:

Written / Revised By: Miller, D Date:10/12/95 Verified: W )

Verified By: Date: I s

Page: 45 1

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' Report - ALL "TG" TAGGED ITEMS l Print Date: 11/13/95 4

4 Lesson Plan #: 2LC706 System: IPO Test Item #:'3709 j Status:.LCF Objective : ? Point Value: 1.00 l

j Question: A reactor trip has occurred 10 seconds ago on Unit 2. The cause i of the trip was an overfeeding of steam generator E-089. The

~

trip also resulted in a high level override (HLO) . Present steam generator levels are: E-089 e 85% NR, and E-088 e 30% NR.

Which one of the following will be the flow demand signal sent to

! the main feedwater regulating valve for E-089 (2 FV-1111) ?

1 l

A. 50%

B. 25%

}

i C. 5%

j D. 0%

j Answer: D. l 1

Reference:

SD-SO23-250 Quest Type: MC Time Est: 4 1 j System: IPO -Level: RO/SRO Graphic: l 4 KA #:059-000-A2-03 KA Value: RO:2.7 SRO:3.1 l Task #s:

} Written / Revised By: Miller, D. Date:03/19/91 Verified: W i Verified By: Date:

j ........................................................................ l i l j

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Page: 46

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2LC706 System: ESEAS Test Item #: 4019 Status: LCF Objective : ? Point Value: 1.00 l l

1 Question: Which one of the following Engineered Safety Features Actuation !

Systems (ESFAS) signals are generated by an AUTOMATIC Safety Injection Actuation Signal (SIAS) but NOT by a MANUAL SIAS?

A. Main Steam Isolation Signal (MSIS).

B. Containment Cooling Actuation Signal (CCAS).

C. Main Feedwater Isolation Signal (MFWIS).

D. Non Critical Loop CCW Isolation Signal (CCIS). l Answer: B.

Reference:

SD-SO23-720 P. 8 Quest Type: MC Time Est: 4 System: ESFAS Level: RO/SRO Graphic:

, KA #:013-000-K1-03 KA Value: RO:3.8 SRO:4.1 Task #s:

Written / Revised By: Miller, D. Date:05/15/91 Verified: W Verified By: Date:

t Page: 47

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j Print Date: 11/13/95 i 5 .

, i Lesson Plan #: 2LC811 System: ADMIN Test Item #: 3991 ;

Status: LCF Objective : 1.1 Point Value: 1.00 !

! n n i i l l

Question: SO123-0-11 " NARRATIVE LOGS " explains ways in which log j entries are made.

4 i

i If during a log entry an error is made which one of the following l l is the correct way to make this correction? 1 4

i l A. Draw one line through the entry, date, and initial. l

, 1 j B. Draw one line through the entry, time, and initial.

} C. Draw one line through the entry, date, time, and initial.

)

D. Draw one line through the entry and initial.

Answer: D

]

Reference:

SO123-0-11 Quest Type: MC Time Est: 4 System: ADMIN Level: RO/SRO Graphic:

l KA #:194-001-Al-06 KA Value: RO:3.4 SRO:3.4 l Task #s:

! Written / Revised By: Miller,.D. Date:05/01/91 Verified: V i i Verified By: Exam Review Group Date:12/09/92 4

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1 Report - ALL "'IG" TAGGED ITEMS Print Date: 11/13/95 i.

I Lesson Plan #: 2LC820 System: admin Test Item #: 8198 i Status: LCF Objective : Point Value: 1.00 Question: An editorial procedure change is required on an emergency operating instruction.

Which one of the following is the correct way to complete this change?

A. Temporary Change Notice (TCN)

B. Revision C. Procedure Modification Permit (PMP)

D. Abnormal Alignment / Evolution Document Answer: B

Reference:

SO123-0-20 PAGE 4 Quest Type: MC Time Est: 4 System: admin Level: RO/SRO Graphic:

KA #:194-001-Al-01 KA Value: RO:3.4 SRO:3.4 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W l Verified By: Date:

l l

Page: 49

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I Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2LC820 System: admin Test Item #: 8199 J Status: LCF Objective : Point Value: 1.00 j

i Question: Which one of the following groups is required to review and l approve test procedures? 1 A. Onsite Review Committee u ,

a I B. Plant Management Staff 1

i C. QA Affecting Committee D. Shift Superintendent & Plant Superintendent 1

g Answer: A i

{

Reference:

SO123-0-20 Quest Type: MC Time Est: 4

System: admin Level: RO/SRO Graphic:

l KA #:194-001-Al-01 KA Value: RO:3.4 SRO:3.4

) Task #s:

1 Written / Revised By: Miller, D. Date:10/24/95 Verified: W ,

j Verified By: Date: l k

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, Page: 50 i

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i I Report - ALL '"IG" TAGGED ITEMS Print Date: 11/13/95 I II I ll lI I I Lesson Plan #: 2LC820 System: admin Test Item #: 8200 l Status:'LCF Objective : Point Value: 1.00 II I I I I I II s

j Question: Which one of the following types of procedures can have steps i left blank if not applicable, however should be frequently

, re-checked to ensure action is taken when applicable?

i 1

A. Emergency Operating Instruction

! B. Abnormal Operating Instruction i

C. Normal Operating Instruction i

D. Normal Surveillance Procedures Answer: B

Reference:

SO123-0-20 & ANY AOI Quest Type: MC Time Est: 4 System: admin Level: RO/SRO Graphic:

KA #:194-000-Al-02 KA Value: RO:3.9 SRO:3.9 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W i Verified By: Date: l I

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Page: 51 !

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Print Date: 11/13/95 '

Lesson Plan #: 2LC823 System: admin Test Item #: 8189 Status: LCF Objective : Point Value: 1.00 Question: Which one of the following may sign authorizations as " Plant Management Staff-Operations" on QA program affecting or safety-related procedures? ]

A. Individuals designated by a Single X B. Individuals designated by a Double X C. On Shift Shift Superintendent with Double X D. On Shift Shift Superintendent With Single X i

l Answer: B ;

I

Reference:

S0123-0-23 PAGE 35 Quest Type: MC Time Est: 4 System: admin Level: SRO Graphic:

KA #:194-001-Al-02 KA Value: RO:3.9 SRO:3.9 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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Page: 52

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2LC823 System: Admin Test Item #: 8410 Status: LCF Objective : Point Value: 1.00

==

Question: An incorrect MOV torque switch setting could cause which one of the following?

A. Incorrect valve positica of a jog valve B. Motor overload ara possible motor burn up C. Inability to manually operate the valve D. Torque switch setting has no impact on valve operation i

Answer: B I

Reference:

SO123-0-23.1 Quest Type: MC Time Est: 4 System: Admin Level: RO/SRO Graphic:

KA #:194-001-K1-01 KA Value: RO:3.7 SRO:3.7 Task #s:

Written / Revised By: miller, donald Date:10/10/95 Verified: l Verified By: Date:

..............................--......... --===----.......= ...--- ..--

Page: 53

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95

Lesson Plan #: 2LC830 System: admin Test Item #: 8201

! Status: LCF Objective : Point Value: 1.00 !

4 Question: The units are in the following configuration; Unit 2 is in Mode l 1 and Unit 3 is in Mode 5.

Which one of the following describes the minimum shift crew

' composition?

i i

j A. SS 1, CRS 1, RO 3, AO 2, STA 0 B. SS 0, CRS 2, RO 2, AO 1, STA 0 C. SS 1, CRS 1, RO 1, AO 2, STA 1 i

j D. SS 1, CRS 2, RO 2, AO 2, STA 1 i

! Answer: D i

l

Reference:

SO123-0-30 ATT 1 Quest Type: MC Time Est: 4 i

System: admin Level: SRO Graphic:

KA #:194-001-Al-03 KA Value: RO:3.4 SRO:3.4 Task #s:

/ Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 54

4 1

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2LC840 System: ADMIN Test Item #: 8192 Status: LCF Objective : 1.2 Point Value: 1.00 Question: Hoses used for chemicals, such as caustic and acid, will be

, tagged with labels that read "FOR CHEMICAL USE ONLY".

i Which one of the following is the correct tag for chemical use?

j A. Red with white lettering

] B. White with red lettering C. Orange with white lettering ;

j D. White with orange lettering s.

Answer: C l

Reference:

SO123-0-40 PG 7 OF 14 Quest Type: MC Time Est: 4 System: ADMIN Level: RO/SRO Graphic:

KA #:194-001-K1-10 KA Value: RO:3.3 SRO:3.3 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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Lesson Plan #: 2NI701 System: RCS Test Item #: 0006 '

Status: LCF Objective : 1.1 Point Value: 1.00

\

Question: During Reactor Startup, MODE 2, which one of the following administrative CHEMISTRY limits is out of spec. ,

A. Chlorides equal to .10 ppm j B. Fluorides equal to .10 ppm l

C. Dissolved Oxygen equal to .15 ppm D. Boron equal 800 ppm l

Answer: C

Reference:

T/S 3.4.6 Quest Type: MC Time Est: 4 System: RCS Level: RO/SRO Graphic:

KA #:004-000-K5-01 KA Value: RO:2.6 SRO:3.3 Task #s:

Written / Revised By:Dufresne, L. Date:03/02/90 Verified: V Verified By: Rauch, K. Date:03/06/90 l

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ALL "TG" TAGGED ITEMS j Print Date: 11/13/95 i 1

i Lesson Plan #: 2NI701 System: ESF Test Item #: 5248 Status: LCF Objective : 1.1 Point Value: 1.00 Question: Unit 3 is at 100% full power. The D.C. control power fuses for HPSI pump P018 have blown and P018 is in the process of being tagged out. P018 is still aligned to Train "A" and racked in when a SIAS "A" train actuation signal is received.

Which one of the following statements below indicates the proper response of the HPSI pumps in the described configuration.

A. HPSI pump P017 will only start in manual.

B. HPSI pump P017 will only start in automatic.

C. HPSI pump P019 will only start in manual.

D. HPSI pump P019 will only start in automatic.

Answer: A

Reference:

SO23-5-1.3; 13-10 PG 34 Quest Type: MC Time Est: 4 System: ESF Level: RO/SRO Graphic:

KA #:013-000-A3-02 KA Value: RO:4.1 SRO:4.2 Task #s:

Written / Revised By: Miller, D Date:10/11/95 Verified: W Verified By: Date:

Page: 57

1 1

I Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 )

l Lesson. Plan #: 2NI701 System: RCS Test Item #: 0042 Status: LCF Objective : 1.1.a Point Value: 1.00 Il Question: Unit 3'is in Mode 3 with RCPs P001 and P004 cleared for l maintenance. Can P-002 be cleared per maintenance request?

A. Yes, all pumps can be cleared.

B. Yes as long as there is one pump available.

C. No,there must be one pump in each loop'available in Mode 3.

D. No, P-002 can only be stopped for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in Mode 3.

Answer: C

Reference:

T/S 3.4.1.2 . Quest Type: MC Time Est: 4 System: RCS Level: RO/SRO Graphic:

KA #:002-000-GO-06 KA Value: RO:2.7 SRO:3.8 Task #s:

Written / Revised By:Westman, W. Date:02/15/90 Verified: V Verified By: Exam Review Group Date:09/03/92 Page: 58

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i i 1 i Report - ALL "TG" TAGGED ITEMS l l Print Date: 11/13/95 ,

4 _, )

i j Lesson Plan #: 2NI701 System: RCS Test Item #: 5231 .

Status: LCF Objective : ???? Point Value: 1.00 ,

e i l

! I Question: When initially performing a pressurizer heatup (drawing a j pressurizer steam bubble), the.RCS is in a solid condition and 1 RCS pressure is being controlled by the letdown backpressure l regulating valves. What are the expected operator actions should I the letdown backpressure regulating valves become full open in j automatic and RCS pressure continues to increase?

A. Initiate auxiliary spray flow to decrease RCS pressure. l

}

B. Stop charging pumps and/or turn off pressurizer heaters. !

l C. Take manual control and throttle closed the letdown flow I control valves to prevent lifting letdown reliefs.

D. Take manual control and throttle closed the letdown backpressure regulating valves.

Answer: B.

Reference:

SO23-5-1.3,13-10, 6.4.4.4 Quest Type: MC Time Est: 4 System: RCS Level: RO/SRO Graphic:

KA #:003-000-K1-04 KA Value: RO:2.6 SRO:2.9 Task #s:

Written / Revised By: Carter, K. Date:08/31/92 Verified: W Verified By: Date:

1 Page: 59 ,

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i Report - ALL "TG" TAGGED ITEMS i Print Date: 11/13/95 1

Lesson Plan #: 2NI702 System: IPO Test Item #: 8191 i; Status: LCF Objective : 1.5 Point Value: 1.00

?

4 4

Question: All full length CEA's are required to have a maximum individual

! CEA drop time. The drop time shall be from the time power is i interrupted to the CEA drive mechanism until the CEA reaches its j 90 percent-insertion position.

This requirement is in effect whenever the reactor is in Mode 1 i or 2 with:

i i a 1 l

A. Average temperture greater than 545 deg F and

Three reactor coolant pumps in service

, B. Average temperature greater than 545 deg F and j Four reactor coolant pumps in service i

l C. Average temperature greater than 520 deg F and 3

Three reactor coolant pumps in service i

j D. Average temperature greater than 520 deg F and l Four reactor coolant pump in service ,

i !

l Answer: D l

Reference:

T/S 3.1.3.4 Quest Type: MC Time Est: 4 i System: IPO Level: RO/SRO Graphic:

l KA #:000-015-K3-04 KA Value: RO:3.4 SRO:4.1 l Task #s:

j Written / Revised By: Miller, D. Date:10/24/95 Verified: W

Verified By: Date: J 4

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i Print Date: 11/13/95 i

l' Lesson Plan #: 2NI703 System: IPO Test Item #: 8279 r Status: LCF Objective : Point Value: 1.00 i

Question: Unit 2 is operating at 100% power when alarm 50A31 " PRESSURIZER SAFETY VALVE OUTLET TEMP HI " comes in. The ARP allows

! continuing operation provided RCS pressure has not dropped below

! 2200 psia, i

i Which one of the following is the bases for this limit? -

! l

. A. Minimizes operation of heaters and spray valves.

1 i B. The LPD safety analysis does not allow operation below ,

j 2200 psia. ;

j C. A reactor trip with pressure below 2200 psia will result in RCS pressure lowering to SIAS setpoint.

D. A normal power maneuver will reduce RCS pressure below the SIAS trip setpoint ,

Answer: C

Reference:

SO23-15-50.A Quest Type: MC Time Est: 4 )

-System: IPO Level: RO/SRO Graphic:

KA #:000-008-GO-07 KA Value: RO:3.2 SRO:3.4 Task #s:

Written / Revised By: Miller, d Date:10/11/95 Verified: W Verified By: Date:

Page: 61 -

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Report -

ALL "TG" TAGGED ITEbis Print Date: 11/13/95

=

l Lesson Plan #: 2NI704 System: IPO Test Item #: 0247

Status: LCF Objective : 1.2.1 Point Value: 1.00 Question: Select the statement that best describes the reason for

maintaining 15" minimum overlap between Group 5 and Group 6 CEA's l with Group 5 being the most withdrawn during power operations.

A. Maintaining the overlap prevents the Plant Monitoring System (PMS) from " locking up".

B. Maintaining the overlap permits the CPC's to continue l calculating azimuthal tilt. j

. C. Maintaining the overlap permits the operator to bypass the logging requirements of CEA insertions into the core.

D. Maintaining the overlap prevents a CPC trip on "out of i sequence".

l l

Answer: D .

l 1

i 4

Reference:

SO23-5-1.4 Quest Type: MC Time Est: 4 System: IPO Level: RO/SRO Graphic:

KA #:012-000-K6-07 KA Value: RO:2.9 SRO:3.2 Task #s:

Written / Revised By:Rauch, K. Date:03/01/90 Verified: V Verified By: Exam Review Group Date:09/17/92 4

Page: 62

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f Report - ALL "TG" TAGGED ITEMS l Print Date: 11/13/95

, Lesson Plan #: 2NI706 System: IPO Test Item #: 0277 l Status: LCF Objective : 1.1.4 Point Value: 1.00 Question: Containment closure time is reduced from two hours to 45 minutes when only the cold leg is vented.

Which one of the following is the bases for this reduction in time?

A. The cold leg vents are closer to the access door.

B. Inventory loss is faster through the cold legs.

C. Shutdown cooling returns to the cold leg.

D. There are twice as many cold leg nozzle dams which could fail.

Answer: B l

Reference:

SO23-3-1.8,7-2 Quest Type: MC Time Est: 4 '

System: IPO Level: RO/SRO Graphic:

KA #:000-025-K1-01 KA Value: RO:3.9 SRO:4.3 Task #s:

Written / Revised By:Macdonald, J. Date:03/06/90 Verified: V Verified By: Exam Review Group Date:09/17/92 I

Page: 63

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

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} Report - ALL "TG" TAGGED ITEMS 1 Print Date: 11/13/95 1

! Lesson Plan #: 2RP181 System: IPO Test Item #: 4083 j Status: LCF Objective : 1.1.1 Point Value: 1.00 1

3 Question: The plant is operating in Mode 1 at 100% power. Annunciators l 56A04 - DNBR LO RPS channel trip and 56A03 - LOCAL POWER DENSITY 3 channel trip are received. Further investigation reveals that j the DNBR and LPD trip lights are illuminated for Channel "A" CPC and the pretrip lights are extinguished.

l Which one of the following choices below could have caused this?

j A. Hot Pin Axial Shape Index, Point ID 187 +0.53

! B. Loop 1 cold leg temperature, Point ID 160 = 553 deg F.

C. Loop 2 hot leg temperature, Point ID 163 = 605 deg F.

l D. Pressurizer Pressure, Point ID 164 = 2236 psia Answer: A l

Reference:

SD-SO23-710 Quest Type: MC Time Est: 4 i Syster.:: IPO Level: RO/SRO Graphic:

i KA #:012-000-K6-07 KA Value: RO:2.9 SRO:3.2 Task #s: . ,

Written / Revised By: Miller, D. Date:10/24/95 Verified: W !

l Verified By: Date: ;

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ALL TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2RP209 System: SGTR Test Item #: 5516 Status: LCF Objective : 1.1.1 Point Value: 1.00 Question: Steam Generator Tube Rupture (STGR) requires the cooldown of the RCS to a T-Hot less than 530 degrees-F using both Steam Generator (s).

Which one of the following is the purpose of this action?

A. To minimize breakflow and increase subcooled margin.

B. To minimize breakflow and decrease subcooled margin.

C. To prevent subsequent lifting of any of the S/G safeties after the affected S/G is isolated.

D. To prevent subsequent lifting of the pressurizer safeties after the affected S/G is isolated.

Answer: C

Reference:

SO23-12-4 Quest Type: MC Time Est: 4 System: SGTR Level: RO/SRO Graphic:

KA #:000-038-K3-06 KA Value: RO:4.2 SRO:4.5 Task #s:

Written / Revised By:Hollinger, S. Date:06/18/92 Verified: V Verified By: Exam Review Group Date:11/19/93 Page: 65

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2RP210 System: LOFW Test Item #: 5524 Status: LCF Objective : 1.1.2 Point Value: 1.00 Question: After a loss of feedwater event, the operator maintains AFW flow at 130-150 gpm for 5 minutes.

Which one of the following is the bases for filling the steam generators at this rate?

A. This is a gradual fill method to allow for equalizing temperature across the S/G.

B. 5 minutos is the required time for minimizing the possibility of a water hammer event to the Steam Generator can deck.

C. 5 minute duration allows for thorough heat soak of the feedring.

D. 5 minute duration follows the "twice full" criteria of the feedring.

Answer: D

Reference:

SO23-12-6 Quest Type: MC Time Est: 4 System: LOFW Level: RO/SRO Graphic:

KA #:000-054-K3-03 KA Value: RO:3.8 SRO:4.1 Task #s:

Written / Revised By:Grabo, R. Date:06/01/92 Verified: V Verified By: Exam Review Group Date:11/19/93 l

Page: 66

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2RP227 System: CEDMCS Test Item #: 7103 Status: LCF Objective : Point Value: 1.00 Question: Which ONE of the following describes a condition which would require manually tripping the Reactor, due to a high voltage being applied to CEDM Coils?

Assume: A CEDMCS Logic Power Voltage Low Alarm Annunciate light is lit.

A. The Local Operator discovers all ACTM Cards have the UG Engaged light ILLUMINATED B. The Local Operator discovers all CEA Disconnect Switches I CLOSED C. The Local Operator discovers all CEDM Timer Failure Alarm lamps ILLUMINATED D. The Local Operator discovers all Reactor Trip Breakers CLOSED Answer: C.

Reference:

SO23-5-2.15 Quest Type: MC Time Est: 4 l System: CEDMCS Level: RO/SRO Graphic:

KA #:001-000-K1-05 KA Value: RO:4.5 SRO:4.4 Task #s:

Written / Revised By:Westman, W. Date:03/31/93 Verified: W Verified By: Date:

Page: 67

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! Lesson Plan #: 2TA702 System: EOI Test Item #: 8278 l Status: LCF Objective : 1.1 Point Value: 1.00

} Question: Emergency Operating Instruction SO23-12-1, " Standard Post Trip '

Actions," requires verifying that RCS Tc, is less than 555 i degrees F.

1 i

i Which one of the following describes the basis for this j .

requirement?

j A.. To ensure that Main Steam Isolation Signal (MSIS) does i j not occur.

B. To ensure that the steam generators are removing RCS heat.

! C. To prevent uncontrolled filling of the steam generators.

l D. .To prevent an imblance in steam generators cooldown.

l Answer: B J

l

Reference:

SO23-14-1 Quest Type: MC Time Est: 4 j System: EOI Level: RO/SRO Graphic:

KA #:000-007-K1-06 KA Value: RO:3.7 SRO:4.1 i Task #s:

i Written / Revised By:NRC Date:04/25/94 Verified: W i Verified By: Miller, D Date:10/11/95 i

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i Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2TS701 System: Tech Spec Test Item #: 8349 l Status: LCF Objective : Point Value: 1.00 i

Question: Technical Specification for containment spray systems ensures containment depressurization and cooling are available.

Which one of the following accidents requires that this depressurization and cooling be available?

Assume all events take place inside containment A. Loss of Coolant Accident B. Loss of Offsite Power C. Loss of Feedwater l

D. Steam Generator Tube Rupture Answer: A I

Reference:

T.S. 3/4.6.2.1 Quest Type: MC Time Est: 4 i System: Tech Spec Level: RO/SRO Graphic: l KA #:026-000-G0-06 KA Value: RO:2.5 SRO:3.8 Task #s:

Written / Revised By: Miller, D. Date:10/12/95 Verified: W ,

Verified By: Date: )

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Lesson Plan #: 2XA202 System: RCP Test Item #: 8178

Status: LCF Objective : 5.9 Point Value: 1.00 J

1 i Question: Given the following Reactor Coolant Pump (RCP) seal data, i determine what action should be directed-by the Shift Superindentent.

- Pressurizer pressure 2250 psia l - Middle Seal Cavity pressure 2250 psia

- Upper Seal Cavity pressure 75 psia

- Vapor Seal Cavity pressure 75 psia A. Continue normal plant operation B. Monitor affected RCP seal data on PMS and continue normal plant operation-C. Commence a normal plant shutdown and 5 seconds after tripping the reactor trip the affect RCP D. Immediately trip the reactor and 5 seconds after tripping the ~ '

reactor trip the affect RCP Answer: C.

Reference:

SO23-13-6 Quest Type: MC Time Est: 4 System: RCP Level: RO/SRO Graphic:

KA #:000-015-Al-22 KA Value: RO:4.0 SRO:4.2 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W !

Verified By: Date: !

Page: 70

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XA203 System: SDC Test Item #: 0062 Status: LCF Objective : 5.2 Point Value: '1.00 Question: Which one of the following statements describes the conditions that must be met to establish SDC in Mode 4 when one train of Containment Emergency Coolers is inoperable?

A. There are no special conditions that must be met.

B. Technical Specification 3.0.3 entry must be approved.

C. The other train of Emergency Coolers must be placed in service.

D. Both Trains of CCW must be Operable.

Answer: B

Reference:

SO23-3-2.6;6-22, 3.6.2.3 Quest Type: MC Time Est: 4 System: SDC Level: RO/SRO Graphic:

KA #:005-000-K1-06 KA Value: RO:3.5 SRO:3.6 Task #s:

Written / Revised By:Dufresne, L. Date:02/15/90 Verified: V Verified By: Hollinger, S. Date:03/20/90

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i Lesson Plan #: 2XA206 System: CVCS Test Item #: 0023 Status: LCF Objective : 2.8 Point Value: 1.00 I

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Question: What effect will high level in the pressurizer have on the letdown throttle valves, backpressure control valves and charging flow?

NOTE: ASSUME ALL CONTROLS IN AUTOMATIC A. Letdown throttle valve will open fully, backpressure l valves will open fully and charging will decrease to minimum. i B. Letdown throttle valve will open fully, backpressure i valves will open fully and charging will remain the same.

C. Letdown throttle valves will throttle close, backpressure valves will Throttle close and charging will remain the same.

]

l D. Letdown throttle valves will open further, backpressure 3 valves will open slightly and charging will decrease to

minimmm flow.

Answer: D I

Reference:

SD-SO23-390 Quest Type: MC Time Est: 4 i System: CVCS Level: RO/SRO Graphic:

KA #:000-028-K3-02 KA Value: RO:2.9 SRO:3.2 Task #s:

Written / Revised By:Dufresne, L. Date:02/14/90 Verified: V

Verified By: Exam Review Group Date:10/02/92 l =======================================================================

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Lesson Plan #: 2XA209 System: ctmt cooling Test Item #: 8202 Status: LCF Objective : 2.7 Point Value: 1.00 l Question: Which one of the following describes the design basis for the Containment Dome Air Circulator Subsystem?

1 A. Remove accident heat energy from containment atmosphere in

order to maintain pressure below the containment design

! pressure.

i B. Provide mixing of the containment atmosphere to prevent localized accumulation of hydrogen.

j C. Maintain the containment dome surface temperature less a than the design temperature of 150 deg F.

! D. Prevent steam voids from forming near the top of containment and causing overpressure conditions.

Answer: B

)

Reference:

SD-SO23-770 Quest Type: MC Time Est: 4 Systeia: ctmt cooling Level: RO/SRO Graphic:

KA #:022-000-G0-04 KA Value: RO:3.1 SRO:3.3 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W

- Verified By: Date:

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XALO7 System: ESF Test Item #: 6244 Status: LCF Objective : 1.9 Point Value: 1.00 Question: Given the following:

P-018 is aligned to train A SIAS and CCAS are actuated All HPSI pumps are operating All HPSI flow paths are aligned SO23-12-3 LOCA procedure is in use Throttle stop is in progress (all conditions have been met)

Which one of the following explains why HSPI pump P-017 override pushbutton is not required to be pushed to secure P-017?

A. P-017 did not receive an auto start signal and was manually started B. P-017 was manually started prior to it's auto start signal C. P-017 had an auto start failure and was manually started l

D. P-017 auto started on vaild SIAS & CCAS signal.

Answer: A

Reference:

TECHNICAL SPECIFICATIONS Quest Type: MC Time Est: 4 System: ESF Level: PRI-PS Graphic:

KA #:006-000-K4-05 KA Value: RO:4.3 SRO:4.4 Task #s:

Written / Revised By: Exam Review Group Date:01/04/93 Verified: W Verified By: Date:

Page: 74

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Report - ALL "'IU" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XAR06 System: CVCS Test Item #: 4229 Status: LCF Objective : 1.1.2 Point Value: 1.00 Question: The plant is at 100% steady state.

All systems aligned for " Automatic" Operation. l A 200 gpm LOCA occurs. ;

Which ONE of the following describes the automatic response of the CVCS system to the LOCA. (Assume NO operator action)

A. Letdown flow increases, all Charging Pumps start as PZR level decreases below setpoint. A Reactor trip /SIAS l actuates. Charging pump suction swaps to the RWST and letdown goes to " Minimum".

B. Letdown flow goes to " Minimum". Charging Pump suction shifts to the BAMU Tanks due to low VCT level. i A RX trip /SIAS actuates, letdown isolates and all '

Charging Pumps start. j C. Letdown flow goes to " Minimum". All Charging Pumps " Auto" start. A RX trip /SIAS actuates. Letdown isolates and Charging Pump suction is supplied by the Boric Acid Makeup Pumps.

D. Letdown isolates. All Charging Pumps " Auto" start. A RX trip /SIAS occurs. Charging Pump Suction swaps to the Boric Acid Gravity Feeds when VCT level lowers to 6%.

Answer: C

Reference:

SYS DES SO23-390 Quest Type: MC Time Est: 4 System: CVCS Level: RO/SRO Graphic:

KA #:000-009-Al-04 KA Value: RO:3.7 SRO:3.5 Task #s:

Written / Revised By: Roger Jones Date:05/20/93 Verified: V Verified By: Exam Review Group Date:05/26/93

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Lesson Plan #: 2XAR07 System: ctmt spray Test Item #: 7712 Status: LCF Objective : 5.1 Point Value: 1.00 Question: Following a Large Break LOCA, which one of the following will ensure a PH of between 7.0 and 8.0? j A. Chemical transformation within trisodium phosphate B. Chemical transformation within trisodium sulfate C. Chemical transformation within trisodium acetate D. Chemical transformation within trisodium borate i

Answer: A l

Reference:

SD-SO23-720 Quest Type: MC Time Est: 4 !

System: ctmt spray Level: RO/SRO Graphic:

KA #:027-000-G0-04 KA Value: RO:3.2 SRO:3.4 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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g Lesson Plan #: 2XB204 System: SFP COOLING Test Item #: 8412 j Status: LCF Objective : 3.5 Point Value: 1.00 i

l Question: Given the following:

1 RCS pressure is 1486 PSIA Containment pressure is 5.7 PSIG Pressurizer level is 24%

Which one of the following actions must be taken to restore Spent Fueling Pool cooling?

f A. Use the CIAS override pushbuttons and open the critical j loop CCW valves.

j B. Use the SIAS override pushbuttons and open the critical j loop CCW valves.

i j C. Use the SIAS override pushbuttons to open the non-critical l CCW loop valves.

{ D. Use the CIAS override pushbuttons to open the non-critical j CCW loop valves.

l l Answer: D.

i

Reference:

SD-SO23-720 Quest Type: MC Time Est: 4

System: SFP COOLING Level: RO/SRO Graphic:

KA #:033-000-K4-01 KA Value: RO:2.9 SRO:3.3 Task #s:

i Written / Revised By: miller, donald Date:10/10/95 Verified:

i Verified By: Date:

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Lesson Plan #: 2XCR03 System: COLSS Test Item #: 8183 '

Status: LCF Objective : 1.2 Point Value: 1.00 l

Question: The unit is operating at 100% with COLSS backup computer OOS for maintenance. During normal plant operation a COLSS limit is ,

exceeded and COLSS alarm come in.

Which one of the following condition would be considered an existence of an Adverse Trend?

i A. DNBR new value is greater than DNBR initial value LPD new value is greater than LPD initial value B. DNBR new value is greater than DNBR initial value LPD new value is less than LPD initial value C. DNBR new value is less than DNBR initial value LPD new value is greater than LPD initial value !

D. DNBR new value is less than DNBR initial value LPD new value is less than LPD initial value Answer: C

Reference:

S023-3-3.6 Quest Type: MC Time Est:

System: COLSS Level: RO/SRO Graphic:

KA #:015-000-Al-06 KA Value: RO:3.7 SRO:3.9 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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j Lesson Plan #: 2XCR08 System: Excores Test Item #: 0110 Status: LCF Objective : 1.3.11 Point Value: 1.00 i

Question: Which one of the following statements best describes the result of placing any switch on the NI Safety Channel Drawer in an abnormal position ?

A. Placing any test or calibrate switch in a position other i than normal may defeat a required trip in the current

mode.

I i- B. Placing any test or calibrate switch in a position other I than normal will cause a Low DNBR and High LPD trip in the affected channel.

! C. Placing any test or calibrate switch in a position other j than normal will cause all channels to be returned to

! normal.

! D. Placing any test or calibrate switch in a position other i than normal may cause a channel trip if a calibration potentiometer is improperly adjusted.

i i Answer: B I

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Reference:

SO23-3-2.12; 3-11, 4.2 Quest Type: MC Time Est: 4 i System: Excores Level: CR-SYS Graphic:

l KA #:015-000-A4-02 KA Value: RO:3.9 SRO:3.9 j Task #s:

j Written / Revised By:Shumate, E. Date:04/24/92 Verified: V l

Verified By: Exam Review Group Date:05/26/93 i

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Print Date: 11/13/95 -

Lesson Plan #: 2XCR08 System: Excores Test Item #: 8295

Status: LCF Objective : 1.8.3 Point Value: 1.00 i Question: Given the following:

Unit 2 is in MODE 2 during a reactor startup i -

Reactor power is 4.9 E-4% !

both startup channels have just failed I l Which one of the following describes the corrective action (s) to l be taken?

.' I 1

3 A. Immediately insert all regulating group CEA's and take

] actions to restore at least one channel to operability.

B. Maintain current power level until at least one channel is l restored to operability.

C.

Commence a reactor shutdown per SO23-3-1.2, procedure for l reactor shutdown.

i D. Continue approach to criticality using safety channel power indication.

Answer: D

Reference:

SO23-3-2.15 STEP 6.5 Quest Type: MC Time Est: 4 System: Excores Level: CR-SYS Graphic:

KA #:000-032-K3-01 KA Value: RO:3.2 SRO:3.6 Task #s:

Written / Revised By: Miller,D Date:10/11/95 Verified: W Verified By: Date: l Page: 80

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Report - ALL "TG" TMGED ITEMS Print Date: 11/13/95 l Lesson Plan #: 2XCF09 System: RCP Test Item #: 8211 Status: LCF Objective : 1.4 Point Value: 1.00 Question: Reactor Coolant System flow sensed from the steam generator delta P is used to trip the reactor.

Which one of the following events is this trip protecting the ,

the reactor from? l A. Reactor Coolant pump vibrations B. Reactor Coolant pump sheared shaft C. Reactor Coolant pump seized shaft D. Reactor Coolant Pump loss CCW flow j Answer: B.

Reference:

SD-SO23-360 Quest Type: MC Time Est: 4 System: RCP Level: RO/SRO Graphic: .

KA #:000-015-K1-02 KA Value: RO:3.7 SRO:4.1 l Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date: l 4

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I Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XCR09 System: ESFAS Test Item #:.8266 Status: LCF Objective : 1.4.1 Point Value: 1.00 Question: Given the following:

Steam Generator Pressure 723 PSIA Reactor Coolant Pressure 1725 PSIA i Containment Temperature 125 deg F. '

Containment Pressure 13.0 PSIG Assume ALL ESFAS signals are actuated.

Which one of the following Engineered Safety Features Actuation Systems (ESFAS) signals was generated by Manual Actuation?

A. Main Steam Isolation Signal (MSIS).

B. Containment' Cooling Actuation Signal (CCAS).

C. Safety Injection Actuation Signal (SIAS).

D. Containment Spray Actuation Signal (CSAS).

Answer: D

Reference:

SD-SO23-720 P. 8 Quest Type: MC Time Est: 4 System: ESFAS Level: RO/SRO Graphic:

KA #:000-011-Al-04 KA Value: RO:4.4 SRO:4.4 Task #s: l Written / Revised By: Miller, D. Date:10/24/95 Verified: W l Verified By: Date:

Page: 82

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Print Date: 11/13/95 l i

i Lesson Plan #: 2XE110 System: EDG Test Item #: 2689 f Status: LCF Objective : 1.5.8 Point Value: 1.00 i 4

r l Question: The purpose of the maintenance lockout feature of the Emergency ,

j Diesel Generator (EDG) is to protect personnel by blocking all: .

1 l Which one of the following completes the above statement?

i i j A. auto start features of the EDG. j

,i ,

B. ESFAS starts of the EDG. !

i . 1 i C. starts of the EDG. l 1

l D. Governor Control System critical starts.

{

i j Answer: C i -i

Reference:

SD-SO23-750 Quest Type: MC Time Est: 4 ,

System: EDG Level: RO/SRO Graphic:

j KA #:064-000-A4-06 KA Value: RO:3.9 SRO:3/9 '

1 Task #s:

Written /~ Revised By: Curry, P. Date:11/12/90 Verified: V '

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Lesson Plan #: 2XELO4 System: E120 Test Item #: 7666 l

Status: LCF Objective : 1.12 Point Value: 1.00 .

2 !

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! Question: Which one of the following describes the reason to avoid l l 1E 120 VAC Inverter operation with the Cooling Fan Failure and/or l High Temperature alarms in? l A. The vital bus and associated equipment may become degraded.

B. The life expectancy of the inverter is greatly reduced.

C. The inverter DC input breaker will trip.

D. The inverter AC output breaker will trip.

Answer: B

Reference:

SO23-6-17 Quest Type: MC Time Est: 4 System: E120 Level: RO/SRO Graphic:

KA #:062-000-K4-10 KA Value: RO:3.1 SRO:3.5 Task #s:

Written / Revised By:Germann, L. Date:01/10/94 Verified: W Verified By: Date:

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Lesson Plan #:' 2XER06 System: EDG Test Item #: 8346 l

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Status: LCF Objective : 1.1.2 Point Value: 1.00 l Question: SO23-3-3.23 Diesel Generator Monthly Test precaution 4.5 '

states, i " If the D/G is operated at less than 30% generator load ;

for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (cumulative), then the D/G should be run ;

i for 30 minutes at greater than 50% load. '

i -

I Which one of'the following is the basis for this precaution?

l j A. To prevent overheating of the generator stator and winding i .

B. To prevent oil buildup in the turbocharger t

l C. To prevent excessive vibration of the generator .

D. To prevent oil buildup in the cylinders and exhaust stacks !

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I i Answer: D !

Reference:

SO23-3-3.23 Quest Type: MC Time Est: 4 System: EDG Level: CR-SYS Graphic: ;

KA #:064-000-A2-06 KA Value: RO:2.9 SRO:3.3 Task #s:

Written / Revised By: Miller, D Date:10/12/95 Verified: W Verified By: Date:

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Lesson Plan #: 2XER10 System: 125 VDC Test Item #: 8190 '

Status: LCF Objective : Point Value: 1.00 i

i Question: To ensure an inverter has sufficient DC voltage to close the DC

! input breaker, the DC input breaker should not be closed until 1 which one of the following conditions is met?

A. Precharge lamp is illuminated B. Precharge lamp is extinquisted C. Battery charger is in service ,

D. Battery is fully charged Answer: A l

Reference:

S023-6-17.3 PAGE 3 Quest Type: MC Time Est: 4 System: 125 VDC Level: RO/SRO Graphic:

KA #:063-000-K1-03 KA Value: RO:2.9 SRO:3.5 '

Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W ;

Verified By: Date:

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XF101 System: FPS Test Item #: 8409 Status: LCF Objective : 1.1.2 Point Value: 1.00 Question: Which one of the following room (s) are protected from fire with a Halon system?

A. Control Room i

B. Cable Spreading Room '

C. Diesel Generator Rooms D. Computer Room Answer: D

Reference:

SD-SO23-590 Quest Type: MC Time Est: 4 System: FPS Level: RO/SRO Graphic:

KA #:000-067-K1-02 KA Value: RO:3.1 SRO:3.9 Task #s:

Written / Revised By: Date: Verified:

Verified By: Date:

Page: 87

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XFR01 System: FPS Test Item #: 4735 Status: LCF Objective : 2.1.1 Point Value: 1.00 Question: Firewater to containment will isolate on which of the following ESFAS signal (s):

A. SIAS and CPIS B. CIAS and CPIS C. CIAS and SIAS D. SIAS and CRIS Answer: C.

Reference:

SD-SO23-720 Quest Type: MC Time Est: 4 System:-FPS Level: CR-SYS Graphic:

KA #:086-000-K3-01 KA Value: RO:2.7 SRO:3.2 Task #s: )

Written / Revised By:Lyke, W. Date:05/05/09 Verified: W !

Verified By: Date: l j

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XIR02 System: PZR Test Item #: 4209 -

Status: LCF Objective : 3.0 Point Value: 1.00 Question: The following plant conditions exist: ;

-s- Pressurizer heater cutout switch is selected to "X" and "Y"

-s- Pressurizer level Channel "X" is controlling.

-s- Pressurizer level Channel "Y" has failed LOW Which ONE of the following states the condition of the Pressurizer heaters, assuming they were all on prior to the Channel "Y" failure.

A. All heaters remain energized.

B. All Non-1E heaters de-energize while all 1E heaters remain energized.

C. All heaters de-energize.

D. All heaters de-energize EXCEPT Channel "X" 1E heaters.

Answer: D

Reference:

SD-SO23-360 PAGE 65 Quest Type: MC Time Est: 4 System: PZR Level: CR-SYS Graphic: ;

KA #:010-000-Al-07 KA Value: RO:3.7 SRO:3.7 !

Task #s:

Written / Revised By: Miller, D. Date:12/04/91 Verified: V

. Verified By: Exam Review Group Date:05/26/93 l

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1 Report - ALL "'IU" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XIR02 System: PZR Test Item #: 8287 Status: LCF Objective : 3.0 Point Value: 1.00 Question: The proportional heaters for the pressurizer are full on at a pressure deviation below setpoint and completely off at a pressure deviation above setpoint.

Which one of the following pressurizer pressures is the LOWEST pressure the proportional heaters be full off?

Assuming Pressurizer pressure setpoint is 2240 PSIA.

1 A. 2250 psia B. 2260 psia C. 2270 psia l D. 2280 psia Answer: C

Reference:

SD-SO23-360;FIGIII-8,P142 Quest Type: MC Time Est: 4 System: PZR Level: RO/SRO .

Graphic:

KA #:000-027-A2-05 KA Value: RO:3.2 SRO:3.3 Task #s:

Written / Revised By: Miller, D Date:10/11/95 Verified: W Verified By: Date:

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Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XIR05 System: SBCS Test Item #: 7711

' Status: LCF Objective : 6.0 Point Value: 1.00 Question: During a plant startup the BOP operator inadvertantly adjusts Steam Bypass Control System from 1000 PSI to 900 PSI.

Which one of the following is caused by this adjustment?

A. Increase in Main Feedwater Temperature B. Decrease in Main Feedwater Temperature C. Increase in Reactor Coolant Temperature D. Decrease in Reactor Coolant Temperature Answer: D

Reference:

SD-SO23-175 Quest Type: MC Time Est: 4 System: SBCS Level: RO/SRO Graphic:

KA #:041-020-A3-02 KA Value: RO:3.3 SRO:3.4 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

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Page: 91

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 3

i l Lesson Plan #: 2XIR06 System: FWCS Test Item #: 2781

{

Status: LCF Objective : 3.1.3 Point Value: 1.00-i 3 Question: Unit 2 is at 100% power with the status of FWCS as follows:

a

-a- FWCS # 1 is selected from "BOTH" to position "1"

{ (ie. on LI-1105) i Subsequently, LT-1105 fails high and a HLO is generated on j FWCS # 1.

Which ONE of the following statements best describes the FWCS # 1 system response to a HLO ?

l A. Main Feed Reg valve closes, j Bypass valve closes and the feed pump is controlled by the demand from the FWCS # 2.

B. Main Feed Reg valve closes, j Bypass valve goes to 50% position and the feed pump is controlled by the demand from the FWCS # 2.

i j C. Main Feed Reg valve closes, l- Bypass valve goes to 50% position and the feed pump is at

~

minimum speed.

i i D. Main Feed Reg valve closes, l Bypass valve closes and the feed pump is at minimum speed.

i I Ansv. .r: A i

j

Reference:

SD-SO23-250 Quest Type: MC Time Est: 4 j- System: FWCS Level: PPEO Graphic:

, KA #:059-000-K1-04 KA Value: RO:3.4 SRO:3.4 i Task #s:

3 Written / Revised By:Taufiq, A. -

Date:11/29/90 Verified: V l Verified By: Kuhner, P. Date:11/30/90 t .......................................................................

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ALL "TG" TAGGED ITEMS Print Date: 11/13/95 ,

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Lesson Plan #: 2XP207 System: AFW Test Item #: 8350 Status: LCF Objective : Point Value: 1.00 ;

l Question: The reactor has tripped from 100% power. The.following i conditions exist in the Steam Generators. H Level Pressure EO88 10% (NR) 710 PSIA EO89 12% (NR) 750 PSIA J Which one of the following is how feedwater is being supplied to the steam generators?

A. AFW is only feeding EO88 B. AFW is only feeding EO89 !

1 C. Both EO88 and EO89 are being fed with AFW and MFW D. Both E-088 and E-089 are being fed with MFW on RTO. .

Answer: B

Reference:

SD-SO23-780 Quest Type: MC Time Est:-4 1 System: AFW Level: CR-SYS Graphic:

KA #:061-000-K3-02 KA Value: RO:4.2 SRO:4.4 Task #s: ,

Written / Revised By: miller,D Date:10/12/95 Verified: W )

Verified By: Date: )

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l Page: 93 l

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4 j Report - ALL "TG" TAGGED ITEMS t-Print Date:- 11/13/95

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, Lesson Plan #: 2XP207 System: AFW Test Item #: 2746

Status: LCF Objective : 1.1 Point Value: 1.00 i

i

! Question: In the Auxiliary feedwater System, what is the purpose of having

! " cycling" relays in the EFAS actuation paths?

i I

i A. To allow EFAS to override MSIS.

t i

i B. To allow the operator to override EFAS.

4 i C. To allow the operator to manually restore S/G level.

1

! D. To allow control of S/G level with no operator action.

i Answer: D.

1

Reference:

SD-SO23-780 Quest Type: MC Time Est: 4 j System: AFW Level: PPEO Graphic:

j KA~#:061-000-K4-14 KA Value: RO:3.5 SRO:3.7

Task #s:

l Written / Revised By:Myers, C. Date:11/29/90 Verified: W j- Verified By: Date:

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XPR04 System: cond & fw Test Item #: 8193 Status: LCF Objective : 1.4 Point Value: 1.00 Question: Which one of the following steps is performed to prevent possible water hammer during starting of the first condensate pump?

A. Open condensate overboard system pressurization valve B. Open condensate pump discharge MOV 35%

C. Open condensate pump discharge valve's bypass valve D. Open condensate pump discharge vent valve Answer: B

Reference:

SO23-2-2, LP PG 35 Quest Type: MC Time Est: 4 System: cond & fw Level: RO/SRO Graphic:

KA #:056-000-K5-03 KA Value: RO:2.2 SRO:2.6 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 95

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Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95

! Lesson Plan #: 2XQ102 System: D&S Test Item #: 6737

Status: LCF Objective : 1.7 Point Value: 1.00

! l Question: What effect will a loss of Service Water have on the Salt Water j j Cool.it3 Pumps? ;

j i

i A. The pumps will need to be secured due to a loss of bearing flushing water B. The pumps automatically trip due to a loss of flushing water.

C. The pumps will supply their own bearing flushing water l upon a loss of Service Water.

D. The pumps have a backup supply from the Turbine Plant Cooling Water System.

Answer: C

Reference:

SD-SO23-580 Quest Type: MC Time Est: 4 i System: D&S Level: RO/SRO Graphic:

KA #:076-000-K1-01 KA Value: RO:3.4 SRO:3.3 Task #s:

Written / Revised By:Phillip, D. Date:02/24/93 Verified: W Verified By: Date:

Page: 96 _

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XR203 System: WRGM Test Item #: 2271 l Status: LCF Objective : 5.8 Point Value: 1.00 Question: Unit 2 is at 100 % power. The Wide Range Gas Monitor, 2RE-7865 aligned to the Plant Vent Stack for normal power operation. Waste gas release is in progress.

An alarm 61A08, " Airborne Radiation Hi" is received. j Concurrently, the Alert (Amber) LED associated with the Effluent i Channel is lit at the RM-23 Communication Module ( L-405). ;

Which one of the following best describes the automatic action (s) caused by the WRGM for the above set of conditions ?

A. Sample flow control shifts from Isokinetic flow control to manual flow control.

B. The monitor realigns to containment purge to sample that flow path.

C. The waste gas discharge flow control valve HV 7202 closes.

D. The outside containment mini & normal purge isolation valves close.

l l

Answer: C

Reference:

SO23-5-2.24; 4-0, PG 17 Quest Type: MC Time Est: 4 System: WRGM Level: PRI-PS Graphic:

KA #:071-000-K4-04 KA Value: RO:2.9 SRO:3.4 Task #s:

Written / Revised By:Dufresne, L. Date:01/20/92 Verified: V Verified By: Date:

Page: 97 i

Report -

ALL "TG" TAGGED ITEMS Print Date: 11/13/95 Lesson Plan #: 2XRLO7 System: ARMS Test Item #: 6496 Status: LCF Objective : 1.3 Point Value: 1.00 Question: During a large break Loss of Coolant Accident core uncovery occurred while sampling at the Post Accident Sample System.

Which one of the following will be indication of high radiation in the post accident sample system area.

i A. Isolated samples and coolers bypassed !

B. Local alarm and isolated samples I

C. Isolated samples only D. Alarm in control room only l

, l Answer: B.

2

Reference:

SD-SO23-810 Quest Type: MC Time Est: 2 System: ARMS Level: PRI-PS Graphic:

KA #:072-000-Al-01 KA Value: RO:3.6 SRO:3.6 Task #s:

Written / Revised By:McClellan, A. Date:01/29/93 Verified: V Verified By: Exam Review Group Date:02/23/91 i

Page: 98

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 )

1 Lesson Plan #: 2XRR08 System: rad monitors Test Item #: 6309 ,

Status: LCF Objective : 1.1 Point Value: 1.00 l l

Question: Main Steam Line Radiation Monitor detection system is made up of which one of the following:

A. Low Range GM Tube High Range GM Tube ;

B. Low Range Ion Chamber l High Range GM Tube l C. Low Range Ion Chamber ,

High Range Ion Chamber l D. Low Range Gm Tube High Range Ion Chamber Answer: D

Reference:

SD-SO23-690 Quest Type: MC Time Est: 4 System: rad monitors Level: RO/SRO Graphic:

KA #:000-061-K2-01 KA Value: RO:2.5 SRO:2.6 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page: 99

Report - ALL "TG" TAGGED ITEMS Print Date: 11/13/95 l

Lesson Plan #: 2XRR08 System: rad monitors Test Item #: 8194 Status: LCF Objective : 1.2 & 1.4 Point Value: 1.00 I Question: Which one of the following radiation monitors will cause the initiation of the Containment Purge Isolation Signal (CPIS)?

A. RE-7828 Containment Purge Stack Rad monitor B. RE-7804 Train "A" Containment Airborne Rad Monitor C. RE-7820 In Containment High Range Rad Monitor D. RE-7808 plant vent stack Rad Monitor Answer: B

Reference:

SD-SO23-690 Quest Type: MC Time Est: 4 System: rad monitors Level: RO/SRO Graphic:

KA #:029-000-K1-01 KA Value: RO:3.4 SRO:3.7 Task #s:

Written / Revised By: Miller, D. Date:10/24/95 Verified: W Verified By: Date:

Page:100

Simulatiori Facihty: SONGS "#3 Scenano No.: 1 Examiners : Applicants : l 1

l l

Initial conditions : Plant is at 86 % nower. boron concentration 144 nom. Tcold 552. croun 6 at 125" or ASI control Circulatine Water DP is between 8 and 9 PSID with Screen wash numn in serv ce Auxiliary Feedwater numn P-504 Out Of Settice for Boundary of the week expected retum in four hours.

l Turnover: Maintain power level I

Event Malf. Event Event K/A's No. No. Type

Description PEM P-504 Rack out Screen Wash Pump Auto Start i RO-R Increase Power to 100%

BOP-N 2 RC09A RO-l Reactor Coolant Pump Speed Sensor Failure 035010A203 36 3 RD03 RO-C Dropped CEA 000003A105 4.I ;

1 4 RO-M RCO3 Loss Of Coolant Accident 000011G011 BOP-M 4.5 5 RP0lli BOP-C Component Coolant Water Pump Auto Start Failure 008030A304 3.9 6 EC08D RO-C HPSI pump Over current ground 006000A202 4.3

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

'~

Exammer. , _

Chief Exammer: -WM- 1.,

pr j -

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/ -

e Scenario No: 1 Event No: 1 Page 1 Of 5 Event Description : Increase reactor oower to 100%

Time Position Applicant's Actions or Behavior RO/CRS Determine amount of dilution required for return to 100% power RO Use 5023 3-2.2 to determine amount of dilution RO Commence dilution by placing mode selector switch in dilute, verify primary makeup pump starts, and opening HV-9257 1

RO Withdraw CEA's as required for ASI control NOTES:

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

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l Scenario No: 1 Event No: 2 Page 2 Of 1. I

! - Event Description : RCS flow tranmitter failure RC09A. This malfunction activation cance= a slow decrease in Reactor Coolant Pmnn P003 speed from the selected cen=ar. The failure occun over a two minute interval.

I i i Time Position Applicant's Actions or Behavior RO/CRS Respond to alarms 1

li

! CRS Review SO23 13 18 Plant Protection System Failure a

I

, CRS Determine functional unit to be placed in bypass (channel A LPD & DNBR) j 4

j RO Review S023-3-2,13 Core Protection / Control Element Assembly 1

RO Determme RCP speed sensor failure l 1 l 1 RO Use SO23-3-2.13 CPC to detennine which RCP has speed sensor failure I

CRS Direct extra RO to placc DNBR & LPD in bypass on channel A

] j RO Verify correct units are placed in bypasses CRS Review Technical Specifications NOTES:

I 1

RFIRP Line 77 (1)& 78(1)

Scenario No: 1 Event No: 3 Page 3 Of 5 +

Event Description : DROPPED CEA ,

l Time Position Applicant's Actions or Behavior i

ALL Respond to Dropped CEA CRS Initiate Abnormal Operating Instmetion, SO23 13-13, Misaligned CEA.

RO Ensure CEDMCS mode select switch is in OFF, determme which CEA has dropped and inform CRS.

BOP Stabilize plant power BOP Position CVOL to maintain RCS cold leg temperature within the operating band RO Determme change in power after power is stabilized using the non-affected CPC channels for delta T power. PID 177 SRO Notify Reactor Engmeenng, STA, Management SRO Direct initiation of attachment 2, Required Power Reduction.

RO Perform SO23-5-1.7 guidelines SRO Direct STA to perfonn calculation for shutdown margin NOTES:

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Scenario No: 1 Event No: 4 Page 4 Of 5 j

Event Description : LOSS OF COOLANT ACCIDENT (300 GPM (a) 5 minutes) ;

l -

Time Position Applicant's Actions or Behavior RO/SRO Crew recogmzes Pzr. level decreasing / additional charging pumps stan.

SRO Implement RCS leak AOI, SO23-13-14.

RO Monitor Pressunzer level to detenrdne RCS leak rate RO Isolate Letdown j 1

RO Determines RCS leak is in excess of charging pump capacity and reports to CRS need to !

trip reactor. I SRO Directs tripping reactor.

RO/ BOP Manually Trip Reactor and trip turbine. l i'

NOTES:

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!l j, Scenario No: 1 Event No: 4 Page 5 Of 5 4

Event Description : CONTINUE LOSS OF COOLANT ACCIDENT i Time Position Applicant's Actions or Behasior j j ALL Cany out the immediate operator actions for a reactor / turbine trip per SO23-12 1

~

RO Determme P-018 over current ground and start P-017 BOP Determme P-026 auto start failure and start P-026 RO Prior to RCS pressure reaching 1740 psia manually initiate SIAS CRS Diagnosis Loss Of Coolant Accident and enter SO23-12-3 CRS Request STA to perform Srfety Function Status Check

! CRS Direct RO toinitiate Maximum SIDow

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RO When Containment Pressure reaches 3.4 PSlG ensure CiAS actuated or manually actuate CIAS and secure all runnmg RCP's RO Monitor for natural circulation

]

4 NOTES:

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, i Simulation Facility: SONGS 2/3 Scenario No.: 2 i t

Examiners : Applicants :

r r

initial conditions : IQ2L l

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Turnover: 86% Power. Boron 144 PPM. T-Cold 551 Den F. Mwe 985 i Circulatine Water DP is between 8 and 9 PSID with Screen wash numn in senice. Auxiliary Feedwater numn P-504 Out Of Service for Boundary of the week exnected retum in four hours. >

Event Malf. Event Event K/A's !

No. No. Type

Description .l PEM P-504 Rack out !

Screen Wash Pump Auto Stan ,

I SG03E RO-l Steam Generator Pressure Transmitter Failure 035010A203 l 3.6 .l 2 FWl2 BOP-C Condensate Pump Sheared Shd 056000A204 i 2.8 ;

i 2 RX05A RO-1 Pressunzer Level Setpoint Failure 000028A108 l 36 j 3 SG01A RO-R Steam Generator Tube Leak 000037G008 BOP-N Down power required 3.9 4 CV17A RO-C Bone Acid Makeup pump failure OC GRD (P-174) 004000A401 )

3.9 )

l 5 SG02A RO-M Steam Generator Tube Rupture 000038A132 !

BOP-M 4.7

(N)onnat, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (PEM) Preexistmg Malfunctions

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Examiner: _ s ,

ChiefExaminer: 'M W '

V J' f

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Scenario No: 2 Event No: 1 Page 1 Of 3 Event Description : Pressurizer Level Setooint Failure Time Position Applicant's Actions or Behavior RO Respond to pressunzer level low alarm RO Match charging and letdown, secure two charging pumps RO Review ARP and enter SO23-3 1,10 Pressunzer Pressure and Level Control Procedure CRS Direct transfer of Pzr level from setpoint one to setpoint two RO Transfer pzr level setpoint using SO23-3-1.10 Pzr level & Pressure control procedure CRS Request 1 & C to investigate pressuruer level setpoint failure 1

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NOTES:

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l Scenano No: 2 Event No: 2&3 Page 2 Of 3 i Event Description : Steam Generator Tube Leak With a loss of boric acid maketro cumo during down oower l

Time Position Applicant's Actions or Behasior i

BOP Respond to Air / ejector / containment Radiation Hi alarm I

i BOP Verify increase on RE-7870 and RE-7818 CRS Direct RO to monitor pzr level and letdown and charging -

CRS Enter SO23-1314 RCS leak procedure CRS Request STA to perform leak rate calculation t

.. . __ . _ _ . . . , _ _ _ . . ___...._ _._ _ _ - _. . _ _ _ _ . . . _ . . . m _ ._ . _ _ ..-

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BOP Inform CRS leak rate has increased greater than 60 GPD in one hour l i

.: CRS Direct rapid plant shutdown to 35% power and then trip the reactor f

, RO Commence boration with one boric acid makeup pump, HV9247, and one charging ;

Pmnp I i

RO Determine OC/GRD on botic acid makeup pump and start backup pump ,

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j RO/CRS Detemine leakrate increasing and greater than capacity of charging pumps NOTES:

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._ ._ _ _ . . _ _ _ . . . _ . . . _ ..._._ . _ _. _ . -. _.-.___ - .. _m_.. __... ___.

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l Scenario No: 2 Event No: 4 Page 3 Of 3

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Event Description : Steam Generator Tube Ruot re i

Time Position Applicant's Actions or Behavior ,

CRS Direct crew to trip the reactor and canyout SPTA"s !

CRS Make Plant notification via PA, call for STA,infonn plant management ,

ALL

~

Complete SPTA's CRS Diagnosis Steam Generator Tube Rupture and enter SO23-12-4 CRS Direct action per S023-12-4 RO/ BOP Perfonn attachment 3 cooldown and depressunzation of the RCS 1

l RO Verify emergency boration and secure 2 RCP's i

l BOP Open two steam bypass valves to commence cooldown l i

l CRS Direct isolation of affected steam generator when T hot is < 530 deg F NOTES:

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7 -

Simulation Facility: SONGS 2/3 Scenano No.: 3 Examiners : VM Applicants : M db2 M wt M '

LL -M

!GA -#f Initial conditions : IC 76 l

)

l Tumover: Audliarv Feedwater rumo P-504 is Out Senice for Boundary of the week ewected return in four ;

hours

]

1 Event Malf. Event Event K/A's '

No. No. Type

Desenption )

PEM P-504 Rack out Screen Wash Pump Auto Start !

1 RC10B RO-1 RCS T cold Temperature Transtmtter Failure 002000A103 3.8 2 CWO5C BOP-C Loss of Circulating Water Pump P-117 overcurrent ground 075000A202 BOP-N Downpower requtred 2.7 i RO-R 2UA0064A(alml2) alarm _on i 3 ED03A RO-C Loss of 4160 Emergency Bus RO secure 2G-0002 BOP 062000A201 {

BOP C restore NCL to Cunt 3S I 4 ED01 RO-M Loss of Offsite Power 0000562448 MS01D BOP-M 4.5 I 5 FW25 BOP-C Overspeed trip of P-140 061000A204 3.8 l

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (PEM) Preexisting Malfunctions ,

Examiner: M _

Chief Examiner #,~ -- 7dA. VrM,, -

- i 1

i I

. M 'lt Scenario No: 3 Event No: 1 Page 1 Of 4 Event Description : RC10B RCS T cold Temnerature transmitter failure affect 016s-es level setooint Time Position Applicant's Actions or Behasior RO Respond to Pzr level error Hi and Tavg LOW alarms RO Determme failure of TI-Olll AY RO Match charging andletdown CRS Direct transfer of Pzr level from setpoint one to setpoint two RO Transfer pzr level setpoint using SO23-3 1.10 Pzr level & pressure control procedure NOTES:

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.. . _ L .. .-- -

i l Scenario No: 3 Event No: 2 Page 2 Of 4 l 1

Event Description : Loss of Cirenhvina Water Pumn P-117 i i

l Time Position . Applicant's Actions or Behavior j

BOP Respond to Cire Water Pump motor brg HI temperature alarm CRS Dispatch an operator to investigate alarm BOP '

Verify condenser vacuum not degrading BOP Report trip of Circulating water pump P-117 CRS direct downpower to 75% :

CRS Enter SO23 12-10 Loss of Condenser Vacuum I

RO Commence downpower using boration, start boric acid makeup pump and place mod selector switch in borate position ALL Maintain power at 75% power 1

NOTES: l I

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Scenano No: 3 Event No: 3 Page 3 Of 4

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i Event Description : Loss of 4160 Fmaience Bus 2AO4 i l Time Position Applicant's Actions or Behasior ll l BOP Respond to Loss of 1E electrical bus 2AO4 i l BOP Restore CCW non-critical loop for RCP seals i

BOP Verify OC alarm on 63B25 Supply brk 2A0418 OC l l BOP Place diesel generator 20002 in maintenance lockout i I

BOP Transfer non-critical loop and letdown heat exchanger to opposite loop (will get help from RO because of problems on electrical boards) f CRS Review T.S. 3.0.3. for loss ofinveners and 3.7.1.2.1 for auxiliary feedwater system NOTES

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Scenario o: 3 Event No: 4 Page 4 Of 4 Event Description : LOSS OF OFFSITE POWER Time Position Applicant's Actions or Behasior ALL Respond to Loss of Offsite Power ALL Carry out SPTA's l CRS Make plant announcement of reactor trip & call for STA BOP Report Overspeed trip on steam driven auxiliary feedwater pump ALL - Complete SPTA's ALL Recognize lower RCS pressure, verify SIAS & CCAS actuations RO Recognize auto start failure of P013 and manually start CRS Diagnosis Loss ofFeedwater Event CRS Enter S023 12-6 Loss of Feedwater Procedure CRS Direct STA to perform Safety Function Status Check (SFSC)

NOTES:

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I e.n. m W- * 'M

ES-301 Administrative Topics Outline Form ES-301-1 Examination Level: SRO Facility: San Onofre Nuclear Generating Station Week of Examination: 27 November 1995 Examiner's Name (print):

Administrative Describe Method of evaluation:

Topic / Subject 1. ONE Administrative JPM,OR Description 2. TWO Administrative Questions A.1 Estimated Critical J106S - ECP Calculation Position 001-010-A4-03 3.9 l l

Logs & security During declared emergencies, information not directly entered into the CO or SS log is kept on numbered note l

sheets. Afler this information is transferred to the logs, what is the disposition of the numbered sheets?

194-001-A 1-06 3.4 While touring the plant you observe an individual with a security photo-ID and an orange non-photo security ID. l What does the orange non-photo security ID mean? I 194-001-K1-05 3.4 A.2 Tagging & Who is required to initial the CO log pnor to giving a l

clearances significant verbal approval to a worker?

194-001-K1-02 4.I How is a SSAM (Shift Superintendent Accelerated Maintenance) item tracked?

194-001-K1-02 4.I A.3 Radiation Control You are the Emergency Coordinator. An emergency exposure to protect valuable property is necessary. What is the maximum exposure authorized?

194 001-K1-03 3.4 A special repair must be made to the plant. Only one individual is available who is qualified to perform the repair.

The expectedjob exposure is 1200 mrem. The worker has n.o exposure this year and a cumulative exposure over theiast five (5) years of 9 rem. Whose approval for exposure extension is required?

194-001-K1-04 3.5 A.4 Emergency J126S - Determine Protective Action Recommendation Procedure 194-001-Al-16 '

4.4

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Examiner: Chief Examiner:

Y

/V l

l

ES-301 Individurl Walk-through Test Outline Form ES-301-2 Examination Level: SRO Facility: San Onofre Nuclear Generating Station Week of Examination: 27 November 1995 Examiner's Name (print):

System / JPM Safety Planned Follow-up Questions:

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

1. 3036S - Align four finger 1 001-010-K4-08 // 2.5 // Why are the 4-finger CEAs ;

CEA misaligned from the rest of Shutdown Group A when !

001-000-G0-13 3.6 the CEAs are initially withdrawn?

l 000-003-K2-05 // 2.8 // Will a single rod drop cause a reactor trip?

2. 3033FS - Rad Monitor IX 073-000-K1-01 // 3.9 // Using elementary 30817, Surveillance determine how many continuous exhaust units must be 073-000 A4-01 3.9 deenergized to cause FV-7202 to close?

073-000-K3-01// 4.2 // Besides a high radiation alarm, what other action / event on 2/3RE7808C will cause FV-7202 to close?

3. J027S - Start RCP IV 003-000-K6-02 // 3.1// SCE expects that RCP seals 002-000-G0-09 3.4 will remain intact with RCS in Hot Standby for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months without CCW cooling. What condition (or conditions) must be met at the end of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period?

000-011-K3-14 // 4.2 // Why is it necessary to trip one I RCP in each loop if RCS pressure falls to 1430 psia l following a SIAS during SPTAs?

4. J113S - RAS Actuation II 006-020-K4-03 // 3.6 // How could a low Containment Verification Emergency Sump level lead to a potential radiological 006-020-A3-04 4.3 release on a Recirculation Actuation Signal?

006-020-K4-01// 3.0 // What is the purpose of maintaining minimum Si flow after RAS?

5. JlISS - Transfer Charging Ill 004-000-K1-06 // 3.1// Under what circumstances Pump Suction post-LOCA would the Bone Acid Makeup pump NOT stop during l 000-011-A 1-05 3.9 this evolution?

006-020-A1-05 // 3.4 // Why is the charging pump suction shifled from the Boric Acid Makeup Tanks to the Refueling Water Storage Tank post-LOCA? "

6. 3017 - Secure CEDMCS MG I 001-000-G0-07 // 3.3 // If you had opened the Set generator output breaker on panel L-046 instead of L-001-000-G0-09 3.6 045 during the shutdown of MG set L-85, what would be the effect on plant status?

001-010-K6-03 // 3.3 // Why do you verify that amps have increased on MG set L-867

7. J019 - Perform actions as VIII 062-000-G0-07 // 3.2 // What is the purpose of the CRS outside Control Room Fire Isolation switches?

000-068-A 1-10 3.9 062-000-A2-01// 3.9 // What is the purpose of transferring the power supply for the source range neutron flux monitor from Train 'B' to Train 'A'?

8. Jl17 - Restore Non-qualified VII 062-000-K4-04 // 2.9 // Since the equipment being Loads from Outside Control restored is "Important-to-safety" why is it de-Room energized initially?

062-000-A2-01 3.9 062-000-K4-03 // 3.1// If a degraded grid voltage condition occurs and the diesel generator is parallelled with the preferred source, what action is required and why is it necessary?

9. 304IS - Continue Startup of V 000-007-GO-10 // 4.1// SO23-12-1 requires Reactor Main Feedwater Pump Trip Override (RTO) actuated when verifying RCS K-005 Heat Removal. What conditions are required for 059 000-AO-01 3.1 correct RTO actuation?

059-000-G0-07 // 3.2 // Using elementary 30901 or 30902, explain the interlocks necessary for the MFWP turning gear to start.

10. JO13S - Transfer Shutdown IV 005-000-K4-11// 3.9 // How is shutdewn cooling Cooling from Parallel Pump & flowrate affected if a 16" flowpath is not available?

Heat Exchanger Operation to 005-000-K3-07 // 3.6 // Shutdown Cooling is in Single Pump & Heat Exchanger service with one (1) pump and one (1) heat exchanger 005-000-A1-01 3.6 in operation. Temperature is 165 F. 2HV 9339 is found closed. What is the required saturation pressure margin?

Examiner: Chief Examiner:

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e JPM INFO ~RMATION SHEET l l

JPM NUMBER 1

J013S INITIAL PLANT CONDITIONS Unit 2 is cooling down. Both Shutdown Cooling (SDC) pumps and both SDC heat exchangers are in operation.

l TASK TO BE PERFORMED Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016 and E-003 from service per SO23-3-2.6.

REV 1-6, 10/17/95 Page 1 of 10

1 l

JOB PERFORMANCE MEASURE J013S l

SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR l i

ACTUAL TESTING METHOD: PERFORMED SIMULATED i l

i I OPERATOR'S NAME: i (Print) j The operator's performance was evaluated against the standards 1

] contained in this JPM and is determined to be '

SATISFACTORY: l l

l UNSATISFACTORY:

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E REV 1-6, 10/17/95 Page 2 of 10

DOCUMENTATION J013S l

JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 15 minutes 1

TIME CRITICAL JPM: CRITICAL TIME: minutes '

POSITION: ACO TASK NUMBER: 007814

, TASK DESCRIPTION:

Transfer from parallel to single shutdown cooling heat exchangers KA NUMBER: SO4S-005-000-Al-01 KA VALUES: RO 3.5 SRO 3.6 ER-0122 CATEGORY: III 10CFR55.45 APPLICABILITY: 2, 4, 6, 7, 10, 12,

REFERENCES:

i l

SO23-3-2.6, Shutdown Cooling System Operation, TCN 8-4. l AUTHOR: S Hollinger DATE: 08/11/92 OPERATIONS REVIEW: M. Cooper DATE: 10/13/93 !

APPROVED BY: M Kirby DATE: 10/14/93 1

1 REV 1-6, 10/17/95 Page 3 of 10

MODIFICATION HISTORY O

REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Changed task number to HJW 10/05/93 MJK properly reflect task performed by JPM. NR-0122 <

Group III system approved for '

use as JPM due to KA value

>3.0.

1-1 Changed setup page; minor HJW 03/22/94 n/a editorial corrections to standards for clarity.

1-2 Compared against SO23-3-2.6, HJW 05/27/94 n/a TCN 7-18 with no changes l required. I 1-3 Compared against SO23-3-2.6, HJW 09/24/94 n/a TCN 7-18 with no changes ;

required. I 1-4 Changed setup page to HJW 10/26/94 n/a position valves HV-8150 &

8151 to 32% open instead of .

80% open. I i

1-5 Compared against SO23-3-2.6, HJW 05/03/95 n/a ,

TCN 8-2 with minor changes !

required for step reference I and flow limit updates.

1-6 Compared against SO23-3-2.6, HJW 10/17/95 n/a TCN 8-4 with minor changes to '

step reference numbers and 1 parameters. Corrected some !

standards to comply with '

actual plant components. l Deleted step 3. )

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l REV 1-6, 10/17/95 Page 4 of 10 l

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M Use IC-4. The following keys are required: 13, 14, 15, 16, 19, 21,

. 22,-28, 29, 30, 31, 34, 35, 36. I 3- 1 i Open 2HV-9325 & 2HV-9328.

Start LPSI 2P015.

Position 2HV-8150 & 2HV-8151 to 32% open.

i Allow conditions to stabilize.

Check 2FI-0306 between 8000 and 8300 gpm.

Provide copy of SO23-3-2.6.

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REV 1-6, 10/17/95 Page 5 of 10

JPM: J013S TITLE: Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016 and E-003 from service.

Derutes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 1 Notify Health Physics that Notify Health Physics that radiation levels in the SDC radiation levels in the SDC heat exchanger and LPSI heat exchanger and LPSI pump pump areas may change. areas may change.

CUE: Health Physics acknowledges the notification. .

2 Transition to step 6.6.9 Transition to step 6.6.9 for securing LPSI pump P-016 EXAMINER CUE: If asked, inform the examinee that the RCS filled with a bubble in the pressurizer.

3 Select recorder TR-0351A, Select recorder TR-0351A, SDCS Temperature Recorder, SDCS Temperature Recorder, to to FAST speed. FAST speed by opening door of recorder and moving lever at ,

bottom from left position to the right position.

REV 1-6, 10/17/95 Page 6 of 10

JPM: J013S TITLE: Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016 and E-003 from service.

Denotes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat) 4* Slowly close LPSI Header Examinee should push and hold Isolation valve HV-9322. the " JOG CLOSE" push button for HV-9322 until the RED light is out and continue to hold it depressed for 15 seconds after the RED light is out.

5* Slowly close LPSI Header Examinee should push and hold Isolation valve HV-9331. the " JOG CLOSE" push button for HV-9331 until the RED light is out and continue to hold it depressed for 15 seconds after the RED light is out.

6* Stop LPSI pump P-016. Push "STOP" push button for P-016.

7 Throttle the in-service SDC HV-8160 should be throttled heat exchanger bypass flow to achieve 2200 to 4500 gpm valve, HV-8160, to control with an optimum value of 3500 SDCS flow as required by gpm.

present Mode and RCS level conditions.

NOTE: The examinee may not perform the next step since immediately following this step the second heat exchanger is removed from service. This is acceptable as long as temperature is monitored.

REV 1-6, 10/17/95 Page 7 of 10

JPM: J013S TITLE: Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016 and E-003 from service.

Dcortes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Uneat) 8 Throttle the SDC heat HV-8150 for E-004 and HV-8151 exchanger outlet to LPSI for E-003 should be throttled header valves, HV-8150 and to maintain temperature HV-8151, to achieve the relatively constant.

desired RCS cooling conditions.

CUE: Cooling requirement at this time is only to maintain present RCS conditions until evolution completed.

NOTE: The following two steps should be performed alternately to remove the second heat exchanger from service.

9* Throttle close on HV-8151, Examinee should turn and hold SDC heat exchanger E-003 the keyswitch for HV-8151 outlet to LPSI header until the GREEN light is valve. illuminated.

Examiner note: Examinee should identify if the next step is not required. If he does the step is satisfactory. If not, it is failed.

10* Throttle open HV-8150, SDC Examinee should turn and hold heat exchanger E-004 outlet the keyswitch for HV-8151 to to LPSI header valve. achieve the desired valve position.

REV 1-6, 10/17/95 Page 8 of 10

JPM: J013S TITLE: Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016-and E-003 from service.-

Denotes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments '

(Required for Unsat) 11 Throttle the in-service SDC Throttle the in-service SDC heat exchanger outlet to heat exchanger outlet to LPSI LPSI header valve, HV-8150, header valve, HV-8150, to to achieve the desired RCS achieve the desired RCS cooling conditions. cooling conditions.

12 After the off-going SDC After the off-going SDC heat I heat exchanger outlet valve exchanger outlet valve is ,

is fully closed, readjust fully closed, readjust SDCS ,

SDCS flow to same value as flow to between 3500 and 4500 before by throttling gpm. s HV-8160.

TERMINATING CUE: THIS JPM IS COMPLETE.

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I REV 1-6, 10/17/95 Page 9 of 10 L

_. ._ _. ...m.__.m _ ___...___ _ _ . . _ . . _ _ . _ _ m____m_. __ _ . . __ _ _ _ _ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

___m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- - - -_ _

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JPM INFORMATION SHEET ;

4 INITIAL PLANT CONDITIONS Unit 2 is cooling down. Both Shutdown Cooling (SDC) pumps and both SDC heat exchangers are in operation.

TASK TO BE PERFORMED Perform the actions required to place the Shutdown Cooling System in a single pump / single heat exchanger lineup. Remove P-016 and E-003 from service per SO23-3-2.6.

.l REV 1-6, 10/17/95 Page 10 of 10

% l JPM INFORMATION SHEET JPM NUMBER J017 INITIAL PLANT CONDITIONS Unit 2 is at Power.

CEDM MG Set L-85 is to be cleared for Maintenance to inspect a noisy bearing.

The SRO Operations Supervisor has directed the Auxiliary Operator to shutdown MG Set L-85 per SO23-3-2.19.1 while the clearance is being prepared by Equipment Control.

TASK TO BE PERFORMED As the Auxiliary Operator, shutdown MG Set L-85 per SO23-3-2.19.1.

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1 REV 1-5, 09/11/95 Page 1 of 9 l i

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O JOB PERFORMANCE MEASURE J017 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the str.ndards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

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REV 1-5, 09/11/95 Page 2 of 9

DOCUMENTATION J017 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 9 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: RWOP i TASK NUMBER: 005792 TASK DESCRIPTION:

1 Shutdown a CEDM MG Set KA NUMBER: S01S-001-000-G0-09 KA VALUES: RO 3.6 SRO 3.6 BR-0122 CATEGORY: I l 10CFR55.45 APPLICABILITY: 6, 9 )

REFERENCES:

SO23-3-2.19.1, CEDM MG Set Operation, TCN 6-18.

AUTHOR: D Daily DATE: 09/16/92 OPERATIONS REVI.'Of: J Salinger DATE: 10/08/93 APPROVED BY: M Kirby DATE: 10/10/93 REV 1-5, 09/11/95 Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL l

1 New Format. SW 07/05/93 MJK l

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1-1 Compared to SO23-3-2.19.1, HJW 12/27/93 n/a '

TCN 6-18; no changes required.

1-2 Added cue prior to step 3 for HJW 01/25/94 n/a digital indication; added instrument numbers to standards; corrected breaker position labels in cues for j steps 5, 6, & 7.

l 1-3 Changed setup page; changed HJW 03/17/94 n/a estimated time from 13 to 9 minutes based on history. ,

1-4 Corrected KA number and HJW 08/04/'5 n/a values.

1-5 Corrected KA number. HJW 09/11/95 n/a l I

REV 1-5, 09/11/95 Page 4 of 9

SET-UP Provide copy of SO23-3-2.19.1.

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i REV 1-5, 09/11/95 Page 5 of 9

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

JPM: J017 TITLE: Shutdown MG Set L-85.

Denates a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat)

NOTE: Proceed to the RCA entry, then provide operator with a current copy of SO23 2.19.1 and allow review prior to RCA entry.

CUE: Ensure all actions for this JPM are simulated as this is in a critical components area. All requirements for CAUTION to work on Critical Circuits are satisfied.

CUE (if asked) : Rx 'TCB #9 is closed.

1* Depress ' LOCAL LOAD OFF' At L-045 simulate depressing L for MG set L-85. MG set L-85 ' LOCAL LOAD OFF' pushbutton, HS-J144AB 2 Check amber ' LOAD ON' Observe amber ' LOCAL LOAD ON' indication extinguished, indication, 2ZLL-J144A, extinguished for MG set L-85.

l CUE: Amber ' LOAD ON' indication lite extinguished.

NOTE: The operator must select the digital display meter to AMPS for the next step.

i 3 Check MG set L-86 for Check for increased amps by increased amps. observing indication, 2UI-J147B at L-045 or 2UI-J167A at L-046, for MG set L-86. ,

REV 1-5, 09/11/95 Page 6 of 9

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JPM: J017 TITLE: Shutdown MG Set L-85.

+ oce .camCALSTEP NO PERFORMANCE STEP STANDARD S/U Countents (Required for Unsat)

CUE: MG set L-86 has increased amps.

4* Depress and hold ' LOCAL Simulate depressing and MOTOR OFF' pushbutton for holding 2HS-J143AB until red MG set L-85. ' LOCAL MOTOR ON' indication, 2ZLH-J143A, extinguishes.

CUE: Red ' MOTOR ON' indication is extinguished.

5 Open Generator Output Simulate opening Generator breaker. Output breaker at panel L-45.

CUE: Breaker indicates OFF.

6 Open Generator Neutral Simulate opening Generator breaker. Neutral breaker at panel L-45.

CUE: Breaker indicates OFF.

REV 1-5, 09/11/95 Page 7 of 9

JPM: J017 TITLE: Shutdown MG Set L-85.

pax =. camCAl,SEP NO PERFORMANCE STEP STANDARD S/U Comuments .

(Required for Unsat) 7 Open Motor Input breaker. Simulate opening Motor Input breaker at panel L-45.

CUE: Breaker indicates OFF.

TERMINATING CUE:' Inform operator that CO will make log entry on securing the MG set. This JPM is complete.

REV 1-5, 09/11/95 Page 8 of 9

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l JPM INFORMATION SHEET )

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INITIAL PLANT CONDITIONS Unit 2 is at Power.

CEDM MG Set L-85 is to be cleared for Maintenance to inspect a noisy bearing.

The SRO Operations Supervisor has directed the Auxiliary Operator to shutdown MG Set L-85 per SO23-3-2.19.1 while the clearance is being prepared by Equipment Control.

TASK TO BE PERFORMED As the Auxiliary Operator, shutdown MG Set L-85 per SO23-3-2.19.1.

REV 1-5, 09/11/95 Page 9 of 9

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JPM INFORMATION SHEET JPM NUMBER l J019 l 1

INITIAL PLANT CONDITIONS You are the Unit 2 CRS.

Both plants were operating at full power when dense smoke began filling the control room.

The immediate actions have been taken in I accordance with SO23-13-2, Shutdown From Outside the Control Room.

l The control room is being evacuated.

TASK TO BE PERFORMED Evacuate the Control Room per SO23-13-2.

Initiate attachment 2 and perform required duties of Unit 2 CRS.

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REV 1-5, 10/17/95 Page 1 of 14 l

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l JOB PERFORMANCE AEASURE J019 l l

I SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

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SATISFACTORY:

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UNSATISFACTORY:

REV 1-5, 10/17/95 Page 2 of 14

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DOCUMENTATION J019 i

JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes

,. POSITION: CRS l TASK NUMBER: 006891 1

TASK DESCRIPTION: I 4

Perform tasks during a shutdown from outside the control room KA NUMBER: S08E-000-068-Al-10 KA VALUES: RO 3.7 SRO 3.9 GR-0122 CATEGORY: I i

10CFR55.45 APPLICABILITY: 3, 6, 8, 12

REFERENCES:

8023-13-2, Shutdown From Outside the Control Room, TCN 2-23.

AUTHOR: S Hollinger DATE: 08/07/92 OPERATIONS REVIEW: D. J. Turner DATE: 11/11/93 APPROVED BY: M. J. Kirby DATEt 11/12/93 j

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REV 1-5, 10/17/95 Page 3 of 14

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MODIFICATION HISTORY F

l REV DESCRIPTION OF CHANGE MODIFIED DATE SOL 3 BY MODIFIED APPROVAL

} 1 New format. Added clarifying JW 11/4/93 MJK notes for examiner; specific names for breakers. Split

, steps for locking out Train B #

supply breakers and opening l DC power supply breakers.

Made steps 17, 19, 21, 23, &

.i 26 critical.

i 1-1 Checked JPM against SO23-13-2 SW 11/29/93 n/a

TCN 2-17. No changes required.

1-2 Changed setup page. HJW 03/17/94 n/a I 1-3 Compared against SO23-13-2, HJW 09/08/94 n/a TCN 2-18 with no changes required.

1-4 Compared against SO23-13-2, HJW 05/02/95 n/a TCN 2-20 with no changes required.

1-5 Compared against SO23-13-2, HJW 10/17/95 n/a TCN 2-23 with no changes required. Minor additional information provided for examiner.

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REV 1-5, 10/17/95 Page 4 of 14

, SET-UP Provide copy of SO23-13-2, attachment 2 and 21.

JPM keyset is required.

REV 1-5, 10/17/95 Page 5 of 14 1

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JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and .

perform required duties of Unit 2 CRS.

Denote. . tsmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comutents (Required for Unsat) j NOTE: Proceed to the Control Building Lobby; then provide a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachments 2 and 21.

NOTE: Identifying the CRS 2 keyset is critical in the step below.

NOTE: When the examinee indicates how to gain access to the Safe Shutdown locker, unlock the Safe Shutdown Locker.

1* Proceed to Control Examinee should identify SSD i Building. 50' Safe Shutdown KIT: CRS 2 and simulate locker and identify removal from locker.

equipment to be taken.

2 Proceed to 2D2 Vital Power Locate Room AC-310D.

Distribution Room.

3 Verify closed ESF LC Locate breaker 2D2P101, Power control power at 2D2P1. to Sw Gr 2A06, in Panel 2D2Pl.

CUE: Breaker 2D2P101 is closed.

4 Verify closed ESF DC Locate breaker 2D2P102, Power control power at 2D2Pl. to LC 2B06, in Panel 2D2P1.

REV 1-5, 10/17/95 Page 6 of 14

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JPM: J019 TITLE 9 Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: Breaker 2D2P102 is closed.

5 Verify closed ESF DC Locate breaker 2D2P111, Power control power at 2D2Pl. to 2G003 2L-161, in Panel 2D2P1.

CUE: Breaker 2D2P111 is closed.

6* Open 2D2P103. Simulate opening 2D2P103, Power to 2L-33, in Panel 2D2P1.

CUE: Breaker 2D2P103 is open.

7* Open 2D2P104. Simulate opening 2D2P104, Power to 2LO71-3R, in Panel 2D2P1.

CUE: Breaker 2D2P104 is open.

REV 1-5, 10/17/95 Page 7 of 14

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

JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

Dences a CRITICAL 5TEP NO PERFORMANCE STEP STANDARD S/U Comments

- (Required for Unsat) 8* Open 2D2P105. Simulate opening 2D2P105, Power to 2L421, in Panel 2D2P1.

CUE: Breaker 2D2P105 is open.

9* Open 2D2P108. Simulate opening 2D2P108, Power to 2L-345, in Panel 2D2Pl.

CUE: Breaker 2D2P108 is open.

10* Open 2D2P109. Simulate opening 2D2P109, Power to NSSS Flood Alarms, <

in Panel 2D2Pl.

CUE: Breaker 2D2P109 is open. ,

11* Open power supply breaker, Simulate opening breaker '

2D205, to HV-4706 and 2D205, Power to 2HV-4706 &

HV-4715. 4715, in Panel 2D2, 125 VDC Bus.

REV 1-5, 10/17/95 Page 8 of 14

. _. . . _ _ _ _ _ . . _ . __ __ _._ _ _ . . _ _ . _ . _ _ _ . . . . _ _ _ -_ _ .. . _ . .. m . ._ .

6

JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

Denotes a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat)

CUE: Breaker 2D205 is open.

12 Proceed to Unit 2 Train B Proceed to Unit 2 Train B Switchgear Room. Switchgear Room 302A.

NOTE: The key for Fire Isolation Panel 2L-413 is not on the JPM key ring.

13* Unlock and open Fire Simulate unlocking and Isolation Panel 2L-413. opening Fire Isolation Panel "B" 2L-413.

14* Select all Fire Isolation The examinee must simulate or Switches to LOCAL. indicate one of the following:

1) placing all Fire Isolation switches to LOCAL, or

2) placing all Fire Isolation switches except SPARES to LOCAL.

CUE: All Fire Isolation Switches are in LOCAL.

s-REV 1-5, 10/17/95 Page 9 of 14

JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments '

(Required for Unsat) 15* Open Second Point of Open Second Point of Control Control cubicle 2A0601. cubicle 2A0601.

16* Select all control switches Simulate placing all Second to stop. Control Point switches to STOP.

CUE: All control switches are in STOP.

The following cue should NOT be provided until the examinee has proceeded to bus A06 and looked at the breakers.

CUE: Bus A06 status is: 2A06-13, 2G003 output breaker GREEN light is on; 2A06-18, Reserve Aux Transformer breaker RED light is on; 2A06-19, 1E 4kV bus tie GREEN light is on.

17* Lockout 2A0613, 2G003 Simulate removing cover to output breaker. overcurrent lockout relay 186-2, DSL GEN 2G003 LOCKOUT, (located on A0614 cubicle) and use insulated cover to actuate relay.

CUE: 2A0613 is open.

'i REV 1-5, 10/17/95 Page 10 of 14

JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

+ o==. . camCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Regaired for Unsat) 18* Turn off DC control power Simulate opening front panel to 2A0613, 2G003 output of breaker and opening DC breaker. control power breaker.

CUE: DC control power switch is off.

19* Lockout 2A0619, 1B Bus Tie Simulate removing cover to breaker. overcurrent lockout relay 186-1 and use insulated cover to actuate relay.

CUE: 2A0619 is open.

20* Turn off DC control power Simulate opening front panel to 2A0619, 1E Bus Tie' of breaker and opening DC breaker. control power breaker.

CUE: DC control power switch is off.

21* Lockout 2A0618, 1E Reserve Remove cover to overcurrent Aux Transformer breaker. lockout relay 186-1 and use insulated cover to actuate relay.

REV 1-5, 10/17/95 Page 11 of 14

JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

+ pemne . camCA1,SW NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat)

CUE: 2A0618 is open.

22* Turn off DC control power Simulate opening front panel to 2A0618, 1E Reserve Aux of breaker and opening DC Transformer breaker. control power breaker.

CUE: DC control power switch is off.

23* Select Transfer Switch Simulate selecting Transfer 2XS539B for Train B Source Switch 2XS539B for Train B Range Neutron Flux Monitor Source Range Neutron Flux power supply to ALTERNATE Monitor power supply to SOURCE. ALTERNATE SOURCE. (Transfer switch located in southeast corner of room).

CUE: Transfer Switch is in ALTERNATE SOURCE.

24* Remove key from Transfer Simulate removing key from Switch 2XSS39B. Transfer Switch.2XS539B.

REV 1-5, 10/17/95 Page 12 of 14

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JPM: J019 TITLE: Evacuate the Control Room per SO23-13-2, initiate Attachment 2 and perform required duties of Unit 2 CRS.

Dendes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Cometents (Required for Unsat) 25* Insert key in Isolation Simulate inserting key in Switch 2XS539A. Isolation Switch 2XS539A.

(Transfer switch located in southeast corner of Room 308A Train A Switchgear Room).

26* Select 2XSS39A to CLOSED. Simulate selecting 2XS539A to CLOSED. i 27 Proceed to EVSD. Proceed to Evacuation Shutdown Panel and simulate establishing communications.

TERMINATING CUE: This JPM is completed.

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REV 1-5, 10/17/95 Page 13 of 14

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JPM INFORMATION SHEET I l

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INITIAL PLANT CONDITIONS You are the Unit 2 CRS.

Both plants were operating at full power when dense smoke began filling the control room.

The immediate actions have been taken in accordance with SO23-13-2, Shutdown From Outside the Control Room.

The control room is being evacuated.

TASK TO BE PERFORMED Evacuate the Control Room per SO23-13-2.

Initiate attachment 2 and perform required duties of Unit 2 CRS.

t REV 1-5, 10/17/95 Page 14 of 14

e JPM INFORMATION SHEET JPM NUMBER J027S INITIAL PLANT CONDITIONS Unit 2 is in Mode 3.

RCP P-001 has been off for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for meggering and inspection.

All clearances have been removed.

1 An operator is stationed at the pump and all actions through SO23-3-1.7, step 6.1.13 are completed. l l

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TASK TO BE PERFORMED '

l Start RCP P-001 in accordance with SO23-3-1.7. l l

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REV 1-5, 05/04/95 Page 1 of 10 1

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, i JOB PERFORMANCE MEASURE J027S l J

I SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X !

ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED f

) OPERATOR'S NAME:

I (Print) l The operator's performance was evaluated against the standards l 4 contained in this JPM and is determined to be: 1 I

SATISFACTORY: i i i l I UNSATISFACTORY:

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REV 1-5, 05/04/95 Page 2 of 10

DOCUMENTATION

, J027S JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes 2

POSITION: UACO TASK NUMBER: 005946 TASK DESCRIPTION:

Start a Reactor Coolant Pump.

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KA NUMBER: SO4S-002-000-AO-05 KA VALUES: RO 3.8 SRO 3.8 KR-0122 CATEGORY: II 10CFR55.45 APPLICABILITY: 3, 6, 7 i

REFERENCES:

SO23-3-1.7, Reactor Coolant Pump Operation, TCN 9-21.

AUTHOR: S Hollinger DATE: 09/16/92 OPERATIONS REVIEW: M. Cooper DATE: 10/13/93 l APPROVED BY: M Kirby DATE: 10/14/93 I

REV 1-5, 05/04/95 Page 3 of 10

MODIFICATION HISTORY :

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i REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Incorporated changes to RR 10/01/93 MJK procedure and testing comments.

1-1 Changed setup page; minor HJW 03/22/94 n/a editorial corrections to standards for clarity.

1-2 Compared against SO23-3-1.7 HJW 09/30/94 n/a with minor rewording to l

initial condition statement I for clarity. I 1-3 Changed setup page. HJW 10/03/94 n/a 1-4 Changed initial conditions HJW 11/03/94 n/a for completed steps to

... step 6.1.12..."

1-5 Compared against SO23-3-1.7, HJW 05/04/95 n/a TCN 9-21 with no changes required.

REV 1-5, 05/04/95 Page 4 of 10

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s li n e 1 Use IC 10.

Bypass'S/G.Lo' Flow Trip on all 4 channels (RP69-4 and RP70-4). i Stop P001.

Place ARRD & Lift pumps in OFF.

Provide copy of SO23-3-1.7.

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I REV'l-5, 05/04/95 Page 5 of 10 -

JPM: J027S TITLE: Start RCP P-001

De a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Cossents (Required for Unsat) 1* Start one H.P. Oil Lift Depress the NORMAL pushbutton Pump by selecting the on either 2HS-9108A, 2P001 NORMAL mode. Oil Lift Pump 2P260, or i 2HS-9109A, 2P001 Oil Lift Pump 2P261.

2 Verify the RCP P003 OIL Observe the RCP P001 OIL LIFT LIFT FLOW LO and the RCP FLOW LO, 56C24, and the RCP P003 OIL LIFT PRESS LO P001 OIL LIFT PRESS LO,'

alarms clear. 56C34, alarms.

3* After the Oil Lift System Depress the NORMAL pushbutton has run approximately 2 on either 2HS-9166, 2P001 minutes, then start one ARRD Pump 2P399, or 2HS-9167, ARRD Lube Oil Pump by 2P001 ARRD Pump 2P400. i selecting the NORMAL mode.

CUE: Operator at P-001 reports oil levels are satisfactory and no oil leaks.

4 Verify the RCP P001 ARRD Observe the RCP P001 ARRD LUBE OIL FLOW LO alarm LUBE OIL FLOW LO, 56C43, clears. alarm.

5 After the Oil Lift and ARRD Depress the STANDBY Pumps have run at least 1 pushbutton on either i minute, align the second 2HS-9108A, 2P001 Oil Lift Oil Lift Pump for AUTO Pump 2P260, or 2HS-9109A, operation by placing it in 2P001 Oil Lift Pump 2P261, the STANDBY mode. whichever was not pushed in step 1.

REV 1-5, 05/04/95 Page 6 of 10

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JPM: J027S TITLE: Start RCP P-001

Demmes a CRITICALSTEP NO PERFORMANCE STEP STANDARD' S/U Comuments (Required for Unsat) 6 Align second ARRD Lube Oil Depress the STANDBY Pump for AUTO operation by pushbutton on either '

placing it in the STANDBY 2HS-9166, 2P001 ARRD Pump mode. 2P399, or 2HS-9167, 2P001 ARRD Pump 2P400, whichever was not pushed in step 3.

7 Verify the following alarms Observe the following alarms on Panel CR56 are clear: on Panel CRS6:

- RCP P001 Thrust Brg Temp - RCP P001 Thrust Brg Temp Hi, 56C03 Hi, 56C03

- RCP P001 Reverse - RCP P001 Reverse Rotation, 56C14 Rotation, 56C14

- RCP P001 CCW Flow Hi/Lo, - RCP P001 CCW Flow Hi/Lo, 56C34 56C34

- RCP P001 Oil Lift Flow - RCP P001 Oil Lift Flow Lo, 56C23 Lo, 56C23

- RCP P001 Oil Lift Press - RCP P001 Oil Lift Press Lo, 56C33 Lo, 56C33 ,

- RCP P001 ARRD Lube Oil - RCP P001 ARRD Lube Oil Flow Lo, 56C43 Flow Lo, 56C43 8 Verify the following alarms Observe the following alarms on PMS are clear: on PMS:

- Computer trend Groups - Computer trend Groups

- RCP Controlled Bleed-off - RCP Controlled Bleed-off ;

Flow Flow

- CCW Seal Heat Exch&nger - CCW Seal Heat Exchanger ;

Temperature Hi Temperature Hi -

9 Monitor RCS pressure and Monitor RCS pressure and check status of RCS check status of RCS pressure pressure control. control.

REV 1-5, 05/04/95 Page 7 of 10

1 JPM: J027S TITLE: Start RCP P-001

Denotes a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat)

CUE: RCS at 2250 psia with pressure control in automatic.

10 Ensure RCP P-001 is not Observe RCP P-001 2SL-9107, rotating. Zero Speed indicator.

11* Start RCP P-001. Depress the START pushbutton on 2HS-9160A, 2P001.

12 Observe that motor amps Observe RCP P-001 Motor Amps come out of starting meter.

current and stabilized between 470 and 800 amps.

13 Closely monitor RCS Observe RCS pressure pressure. indications. l 14 Reset the Lube Oil Flow Lo Reset the Lube Oil Flow Lo alarms and check that any alarm (56C13) and observe any other plant or computer other plant or computer annunciators associated annunciators associated with with RCP P-001 remain clear RCP P-001.

or are reset.

REV 1-5, 05/04/95 Page 8 of 10 ;

i L------- - - - - - - _ _ - - - - - - - - - n.--- _ _ . - - . - . - - - - - - - - - - . - . - - - - - - , . - - - - - - - - - - - , _ - - - - - - _ _ _ . _ . - - - - _ _ - _ _ _ - --

JPM: J027S TITLE: Start RCP P-001

+ oencies a camCALSTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 15 Observe that the Oil Lift Observe the 2HS-9108A, 2P001 and ARRD Pumps Oil Lift Pump 2P260, or automatically Stop. 2HS-9109A, 2P001 Oil Lift Pump 2P261 indicating lights and ARRD Pump Indicators 2HS-9166, 2P001 ARRD Pump 2P399, or 2HS-9167, 2P001 ARRD Pump 2P400, indicating lights.

16 Direct an operator to Direct an operator to observe observe RCP P-001 Oil RCP P-001 Oil Reservoir Reservoir levels and check levels and check for leaks.

for leaks. '

TERMINATING CUE: Operator at the pump reports oil levels are satisfactory and no oil leaks.

This JPM is complete.

REV 1-5, 05/04/95 Page 9 of 10

JPM INFORMATION SHEET l

1 INITIAL PLANT CONDITIONS Unit 2 is in Mode 3.

RCP P-001 has been off for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for meggering and inspection. l All clearances have been removed.

An operator is stationed at the pump and all actions through SO23-3-1.7, step 6.1.13 are completed. l TASK TO BE TSRFORMED Start RCP P-001 in accordance with SO23-3-1.7.

l REV 1-5, 05/04/95 Page 10 of 10

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JPM INFORMATION SHEET l

.IPM NUMBER !

J033FS INITIAL PLANT CONDITIONS l Preparations are in progress for a radioactive gas release of a decay tank.

RE-7808C sample alignment has been completed per 1 SO23-3-2.24.12. '

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_ TALE _TO BE PERFORMED Verify operability of RE7808C, Plant Vent Stack Airborne Gas Monitor, for the release per SO23- l 8-15, attachment 1, step 2.2.4.

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I REV 1-6, 10/03/95 Page 1 of 10

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. JOB PERFORMANCE MEASURE J033FS i

SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED l

OPERATOR'S NAME:

(Print) l 4

The operator's performance was evaluated against the standards 4

contained in this JPM and is determined to ber 4

! SATISFACTORY:

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., UNSATISFACTORY:

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i REV 1-6, 10/03/95 Page 2 of 10 1

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DOCUMENTATION J033FS JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 13 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: CACO TASK NUMBER: 007926 TASK DESCRIPTION:

Perform process radiation monitor (RI-7808C, RI-7818, RI-7817, RI-7821, RI-7813) operability verification.

KA NUMBER: SO9S-073-000-A4-01 KA VALUES: RO 3.9 SRO 3.9 IR-0122 CATEGORY: II 10CFR55.45 APPLICABILITY: 8, 9, 12

REFERENCES:

SO23-8-15, RADWASTE GAS DISCHARGE, TCN 7-17.

AUTEOR: S Hollinger DATE: 09/16/92 OPERATIONS REVIEW: M. Cooper DATE: 10/13/93 APPROVED BY: M Kirby DATE: 10/14/93 REV 1-6, 10/03/95 Page 3 of 10

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MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL 4

BY MODIFIED APPROVAL 1 Step 4- Added contact RW SGA 10/02/93 MJK operator and made & SW verification like procedure step. Split step 5 into two steps (5 & 6). Took RT-7814 being defeated out of cue before step 7 and added step 7 (critical step). Corrected typos / wording and added j specific locations !

throughout. Check source is insufficient to close i FV-7202. Converted this JPM to a Faulted version. The i

examinee has to request I&C 1 support.

1-1 Compared against SO23-8-15, HJW 01/03/94 n/a l TCN 7-14; added cue for '

s completion of sample alignment and moved cue from step 8 to atep 7 for clarity.

1-2 Corrected setpoint in cue HJW 01/05/94 n/a

, prior to step 6 to 400; added note after step 14 for removal of override; added removal of override and placing RT-7814 in " alarm i defeat" to setup page.

1-3 Changed setup page; changed HJW 03/23/94 n/a i estimated time from 15 to 13 minutes based on history; minor editorial corrections to standards for clarity.

I 1-4 Compared against SO23-8-15, HJW 09/26/94 n/a TCN 7-16 with some step sequence changes at step 11 and 12.

1-5 Corrected " Position" on HJW 02/09/95 n/a Documentation page.

1-6 Compared against SO23-8-15, HJW 10/03/95 n/a TCN 7-17 with no changes required.

REV 1-6, 10/03/95 Page 4 of 10

SET-UP When directed by the evaluator override 7808C ior s23ri7808C[SW7] on and off when directed.

Place " Calibration" sticker on RT-7808C.

Place FV-7202 in AUTO with output at O.

Provide copy of SO23-8-15, attachment 1.

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i REV 1-6, 10/03/95 Page 5 of 10

JPM: J033FS TITLE: Verify operability of RE7808C, Plant Vent Stack Airborne Gas Monitor, for the release.

Denoses a CRMCALETEP NO PERFORMANCE STEP STANDARD S/U Cosuments (Required for Unsat)

NOTE: Provide a copy of SO23-8-15, attachment 1, filled out as required to step 2.2.4.

CUE: Monitor sample alignment for placing RT-7808 in service has been completed.

1 Verify only HV and PWR Verify only HV and PWR pushbuttons depressed. pushbuttons depressed on RI-7808C module at 2/3 L104.

2 Verify IF (instrument Verify IF (instrument failure) LED extinguished failure) LED extinguished and and HV and PWR LEDs HV and PWR LEDs illuminated illuminated. on RI-7808C module at 2/3 L104.

3 Verify no hi-flow or Verify FLH-7808B (High Flow) lo-flow alarm lights and FLL-7808B (Low Flow) illuminated. lights not lit at 2/3 L104.

4 Depress HR-RST pushbutton Depress HR-RST pushbutton on and record setpoint. RI-7808C module at 2/3 L104 and record setpoint.

5 Verify setpoint less than Verify alarm setpoint less or equal to cal sticker than or equal to cal sticker value. value.

REV 1-6, 10/03/95 Page 6 of 10

JPM: J033FS TITLE: Verify operability of RE7808C, Plant Vent Stack Airborno Gas Monitor, for the release.

Denates a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required fer Unsat)

CUE: The setpoint calibration sticker value is 400, and the CAL due date is next year at this time.

6 Record RI-7808C reading and Record reading.

verify satisfactory Observe the instrument operation. indication (eg. in-range, no ,

major oscillations).

7 Record RI-7808C sample flow Call Radwaste Operator for from local sample flow sample flow and the range of gauge. calibration sticker values.

CUE: Radwaste Operator reports flow gauge reading 2.5 inches H 2 O and calibration ,

range is 2 to 3 inches H 20.

8 Verify sample flow recorded Verify sample flow within value within range of range of calibration sticker.

calibration sticker.

9* Open FV-7202. Place 2/3 FV-7202 control at CR61 in manual, use thumbwheel to increase output to 100%, then depress 2/3 FV-7202 open pushbutton.

REV 1-6, 10/03/95 Page 7 of 10 ,

JPM: J033FS TITLE: Verify operability of RE7808C, Plant Vent Stack Airborne Gas Monitor, for the release.

. ocoe. . camCAI, STEP NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat) 10 Depress NOR-CS pushbutton Depress NOR-CS pushbutton at at 2/3 L104 and observe 2/3 L104 and observe upscale upscale movement. movement.

CUE: (if needed) No upscale movement is observed.

11* Request I&C to inject a Request I&C to inject a simulated signal. simulated signal.

CUE: IEC acknowledges.

NOTE: Have the machine operator override 7808C.

12* Determine FV-7202 does Observe FV-7202 indicating close. lights.

13 Verify FV-7202 closes and Verify FV-7202 closes and control room alarms control room alarms annunciate. annunciate.

14 Request I&C to remove the Request I&C to remove the simulated signal. simulated signal.

REV 1-6, 10/03/95 Page 8 of 10

JPK: J033FS TITLE: Verify operability of RE7808C, Plant Vent Stack Airborne Gao Monitor, for the release.

Deacoes a CRITICAL 5TEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat)

NOTE: Have machine operator remove override 7808C.

15 Place FV-7202 in AUTO. HR-RST pushbutton depressed Reset monitor and control at RI-7808C module on 2/3 room alarms. L104 and alarms reset at CR61.

16* Monitor determined Monitor determined operable, operable.

TERMINATING CUE: This JPM is cossplete.

REV 1-6, 10/03/95 Page 9 of 10

JPM INFORMATION SHEET :

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INITIAL PLANT CONDITIONS Preparations are in progress ter a radioactive i gas release of a decay tan).. l RE-7808C sample alignment haa be.en completed per SO23-3-2.24.12.

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TASK TO BE PERFORMED I

Verify operability of RE7808C, Plant Vent Stack j Airborne Gas Monitor, for the release per SO23- !

8-15, attachment 1, step 2.2.4. '

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REV 1-6, 10/03/95 Page 10 of 10 1

5 Io JPM INFORMATION SHEET JPM NUMBER J036S INITIAL PLANT CONDITIONS Reactor startup is in progress.

Shutdown Group A has just been withdrawn to 20" in accordance with SO23-3-2.19 section 6.7 TASK TO BE "RFORMED Align the four-finger CEAs with the rest of l Shutdown Group A in accordance with SO23-3-2.19 l section 6.7. '

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REV 1-4, 09/11/95 Page 1 of 11

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] JOB PERFORMANCE MEASURE J036S 4

SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT _ SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be SATISFACTORY:

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i UNSATISFACTORY:

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i REV 1-4, 09/11/95 Page 2 of 11 l

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DOCUMENTATION J036S 1

JPM LEVEL: RO l ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes l POSITION: UACO TASK NUMBER: 007840 TASK DESCRIPTION:

Align Four-fingered CEAs.

1 KA NUMBER: S01S-001-000-G0-13 KA VALUES: RO 3.7 SRO 3.6 BR-0122 CATEGORY: I 10CFR55.45 APPLICABILITY: 2 and 6 1

REFERENCES:

1 SO23-3-2.19, Control Element Drive Mechanism Control System (CEDMCS) l Operation, TCN 5-16.

AUTHOR: S Hollinger DATE: 09/16/92 OPERATIONS REVIEW: E. Sengstacken DATE: 03/27/94 APPROVED BY: M. J. Kirby DATE: 05/19/94 REV 1-4, 09/11/95 Page 3 of 11

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MODIFICATION HISTORY l

REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 New format. Incorporated RR 09/23/92 MJK changes to procedure and testing comments.

1-1 Changed setup page. HJW 09/23/93 n/a 1-2 Changed setup instructions. HJW 09/12/94 n/a 1-3 Compared against SO23-3-2.19, HJW 05/05/95 n/a TCN 5-16 with no changes required.

1-4 Corrected KA number. HJW 09/11/95 n/a i

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t REV 1-4, 09/11/95 Page 4 of 11

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l SET-UP '

Use IC-9.

Manually trip reactor; reset trip breakers using RP57 to RST and at K078 turn keys to unlock and reset RPS 1,3,5,&7.

Withdraw Shutdown Bank A to 20 inches.

Provide copy of SO23-3-2.19.

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REV 1-4, 09/11/95 Page 5 of 11

i JPM: J036S -TITLE: . Align the four-finger CEAs with the rest.of Shutdown Group A in ;

accordance with SO23-3-2.19 section 6.7.

w . camCAI. STEP L i

NO PERFORMANCE STEP STANDARD S/U C - ts (Required for Unsat) 1*- Position the Mode Select Place the Mode Select switch switch to MI. to MI.

2 Verify that Manual Observe'that the Manual !

Individual selected light Individual selected light is is illuminated. illuminated.

3* Position.the Group Select Place the Group Select switch i switch.to A. to A. i 4 Verify that Group A group Observe that the Group A-indicator lamps are group indicator lamps are illuminated. illuminated.

I 5* Position the Individual CEA Place the Individual CEA Tens !

Tens Selection switch to 8. Selection switch to 8. [

i 6* Position the Individual CEA Place the Individual CEA Units Selection switch to Units Selection switch to 8.

8. t 7 Verify CEA 88 individual Observe CEA 88 individual CEA CEA light is illuminated. light is illuminated. I t

1 REV 1-4, 09/11/95 Page 6 of 11

JPM9 J036S TITLE: Align the four-finger CEAs with the rest of Shutdown Group A in accordance with SO23-3-2.19 section 6.7. .

Denases a CRmCALSTEP NO PERFORMANCE STEP STANDARD S/U Commsents (Required for Unsat) 8* Move the control switch to Place the control switch to the INSERT position to INSERT.

insert CEA 88.

9 Verify CEA 88 is moving in Observe CEA 88 position by observing CEA 88 indicator.

position indicator.

10* Release the control switch Release the control switch.

when the desired CEA position is reached.

11 Verify CEA 88 has stopped Observe CEA 88 position moving by observing CEA 88 indicator.

position indicator.

12 Verify the Individual CEA Observe the Individual CEA Tens Selection switch to 8. Tens Selector switch to 8.

13* Position the Individual CEA Place the Individual CEA Units Selection switch to Units Selection switch to 9. j

9. '

14 Verify CEA 89 individual Observe CEA 89 individual CEA CEA light is illuminated. light is illuminated.

REV 1-4, 09/11/95 Page 7 of 11

_. . - _ _ ___ - _ _ - _ - ______ _-___ _ =________ __ -__ ____-___________- _____ __-________-___ - ______ ____ . - --

__.. . _ _ _ _ .=. ._ __. ..

JPM: J036S TITLE: Align the four-finger CEAs with the rest of Shutdown Group A in accordance with SO23-3-2.19 section 6.7.

+ Deanes a camcAL sm NO P'~' ' P.MANCE STEP STANDARD S/U Comments (Required for Unsat) 15* Move * * ' trol switch to Place the control switch to the si pnsition to INSERT.

insett _ ua 8 : .' .

15 Verify CEA 89 is moving in Observe CEA 89 position -

4 by observing CEA 89 indicator. ,

position indicator. !

i 17* Release the control switch Release the control switch.

when the desired CEA position is reached.

18 Verify CEA 89 has stopped Observe CEA 89 position moving by observing CEA 89 indicator. l position indicator.

19* Position the Individual CEA Place the Individual CEA Tens i Tens Selection switch to 9. Selection switch to 9.

20* Position the Individual CEA Place the Individual CEA Units Selection switch to Units Selection switch to 0.

O.

21 Verify CEA 90 individual Observe CEA 90 individual CEA CEA light is illuminated. light is illuminated.

REV 1-4, 09/11/95 Page 8 of 11

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

JPMB J036S TITLE: Align the four-finger CEAs with the rest of Shutdown Group A in accordance with SO23-3-2.19 section 6.7.

Denoses a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 22* Move the control switch to Place the control switch to the INSERT position to INSERT.

insert CEA 90.

23 Verify CEA 90 is moving in Observe CEA 90 position by observing CEA 90 indicator.

position indicator.

24* Release the control switch Release the control switch.

when the desired CEA position is reached.

25 Verify CEA 90 has stopped Observe CEA 90 position moving by observing CEA 90 indicator.

position indicator.

26 Verify the Individual CEA Observe the Individual CEA Tens Selector swith to 9. Tens Selector switch to 9. t 27* Position the Individual CEA Place the Individual CEA Units Selection switch to Units Selection switch to 1.

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28 Verify CEA 91 individual Observe CEA 91 individual CEA CEA light is illuminated. light is illuminated.

,REV 1-4, 09/11/95 Page 9 of 11

JPM: J036S TITLE: Align the four-finger CEAs with the rest of Shutdown Group A in accordance with SO23-3-2.19 section 6.7.

+ oe ose. . camCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 29* Move the control switch to Place the control switch to the INSERT position to INSERT.

insert CEA 91.

30 Verify CEA 91 is moving in Observe CEA 91 position by observing CEA 91 indicator, position indicator.

31* Release the control switch Release the control switch.

when the desired CEA position is reached.

32 Verify CEA 91 has stopped Observe CEA 91 position moving by observing CEA 91 indicator.

position indicator.

TERMINATING CUE: This JPM is complete.

REV 1-4, 09/11/95 Page 10 of 11

JPM INFORMATION SHEET INITIAL PLANT CONDITIONS Reactor startup is in progress.

Shutdown Group A has just been withdrawn to 20" in accordance with SO23-3-2.19 section 6.7 TASK TO BE PERFORMED Align the four-finger CEAs with the rest of Shutdown Group A in accordance with SO23-3-2.19 section 6.7.

REV 1-4, 09/11/95 Page 11 of 11

e JPM INFORMATION SHEET JPM NUMBER J041S l

INITIAL PLANT CONDITIONS Unit 2 is approximately 3% power and holding for various maintenance items to be completed.

The Aux Feedwater System is maintaining Steam i Generator Level. '

The ACO is monitoring / operating the FWCS per SO23-9-6 and controlling the rest of the plant to maintain stable conditions.

Main Feedwater Pump K005 start-up is in progress. SO23-2-1, Main Feedwater Pump and Turbine Operation, Attachment 1, is completed up to and including step 2.7.7.

i TASK TO BE PERFORMED I As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

g REV 1-5, 10/03/94 Page 1 of 13

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JOB PERFORMANCE MEASURE J041S SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR l ACTUAL TESTING METHOD: PERFORMED SIMULATED l

OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards

contained in this JPM and is determined to be

SATISFACTORY:

l UNSATISFACTORY:

1 REV 1-5, 10/03/94 Page 2 of 13

DOCUMENTATION J041S JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 24 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: UACO TASK NUMBER: 005931 TASK DESCRIPTION:

Startup a main feedwater pump.

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KA NUMBER: S05S-059-000-A0-01

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KA VALUES: RO 3.1 SRO 3.1 GR-0122 CATEGORY: I 10CFR55.45 APPLICABILITY:

2, 6

REFERENCES:

SO23-2-1, Main Feedwater Pump and Turbine Operation, TCN 7-31.

AUTHOR: D Daily DATE: 09/16/92 OPERATIONS REVIEW: J. Kennel DATE: 10/02/93 APPROVED BY: M Kirby DATE: 10/14/93 REV 1-5, 10/03/94 Page 3 of 13

. I MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 New format. Deleted first 10 SW 09/21/93 MJK step of the JPM and brought the examinee into the procedure at step 2.7.8.

This will reduce the time to complete this JPM, which in the past has been excessive. ,

1-1 Checked against SO23-2-1, TCN HJW 12/27/93 n/a 7-28; no changes required.

1-2 Minor changes to simulator HJW 01/11/94 n/a setup page based on examiner's comments.

1-3 Minor changes to cues for HJW 02/09/94 n/a I lube oil temperature based on input from examiners.

1-4 Changed setup page; changed HJW 03/23/94 n/a estimated time from 20 to 24 minutes based on history.

1-5 Compared against SO23-2 1, HJW 10/03/94 n/a TCN 7-31 with no changes required.

l 1

REV 1-5, 10/03/94 Page 4 of 13

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

4 .

. SEI:llE Use IC-13 i

Open discharge valve HV-4011; H.P. Stop Valve Below Seat Drain Valve, 2HV-8229 and L.P. Stop 9

Valve Below Seat Drain Valve, 2HV-8618 should be shut.

Machine or extra operator to maintain AFW and SG levels.

! Provide marked up copy of SO23-2-1, attachment 1, filled out to i step 2.7.8. Mark step 2.7.8.5 as NA.

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REV 1-5, 10/03/94 Page 5 of 13

)

._._~. ..

JPM: J041S TITLE: As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

Deactes a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 1* Reset Main Feedwater Pump Depress Main Feedwater Pump Turbine K005. Turbine K005, 2HS-4523 RESET push button.

2 Verify H.P. Stop Valve Observe H.P. Stop Valve i 2HV-8206 opens. 2HV-8206 indicating lights.

i 3 Verify L.P. Stop Valve Observe L.P. Stop Valve 2HV-8614 opens. 2HV-8614 indicating lights.

4 Verify MFWP Turbine speed Observe MFWP Turbine Speed does not exceed 200 RPM. Indicator, 2SI-4561.

5 Verify Mini-flow Control Observe Mini-flow Control Valve, 2FV-3433 is open. Valve, 2FV-3433 indicating ,

lights.

t 6 Set FIC-3433 to minimum of Direct an Operator to set 7000 gpm. FIC-3433 to a minimum of 7000 gpm. '

REV 1-5, 10/03/94 Page 6 of 13 l t

JPM: J041S TITLE: As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

i

Denotes a CRITICALSTEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: PEO reports FIC-3433 set to 7000 gym.

EXAMINER CUE: Fast-time advance to step 2.7.8.6.

7 Verify Main Feedwater Pump Observe Main Feedwater Pump Turbine K005 is reset. Turbine K005, 2HS-4523 indicating lights.

8 Ensure open S21305MU204, Call.PEO to ensure open Miniflow Control Valve S21305MU204, Miniflow Control

, Isolation. Valve Isolation.

CUE: PEO reports S21305MU204 is open.

9 Verify Mini-flow Control Depress Mini-flow Control Valve 2FV-3433 to open. Valve 2FV-3433 OPEN push button (if required).

10 Direct an Auxiliary Direct an Auxiliary Operator Operator to close Mini-flow to close Mini-flow Bypass Bypass Valve, S21305MU350. Valve, S21305MU350.

CUE: The PEO reports S21305MU350 is closed.

REV 1-5, 10/03/94 Page 7 of 13

I . .,

JUM: JC41S TITLE: As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

Denotes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 11 Open H.P. Stop Valve Below Depress the H.P. Stop Valve Seat Drain Valve, 2HV-8229. Below Seat Drain Valve, 2HS-8229 OPEN push button. i 12 Oper. L.P. Stop Valve Below Depress the L.P. Stop Valve Seat Drain Valve, 2HV-8618. Below Seat Drain Valve, 2HS-8618 OPEN push button.

13 Ensure lube oil temperature Call PEO to check lube oil at the bearings is 60*F. cooler outlet temperature.

CUE: Lube oil cooler outlet temperature is 72*F. ,

14* Slowly raise turbine speed Depress MFWP K005 Speed to 500 RPM by operation of Control, 2HS-4531 RAISE push MSC SPEED RAISE. button until speed as indicated on 2SI-4561 indicate 500 RPM.

15 Verify the Turning Gear Observe Turning Gear disengages and Turning Gear engage / disengage 2HS-4537-Motor stops. indicating lights, and .

Turning Gear Motor 2HS-4525 indicating lights. ,

REV 1-5, 10/03/94 Page 8 of 13

I JPM: J041S TITLE: As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

= omacs a CRmCA1, STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 16 Reset the Turning Gear Depress the Turning Gear Lockout circuit. Lockout, 2HS-4537 RESET-LOCKOUT push button. ,

17 Place the Turning Gear in Depress the Turning Gear, auto. 2HS-4537 AUTO push button.

18 Monitor feedwater Observe the Main Feedwater pump / turbine bearing pump bearing temperatures on temperatures. 2TJR-8799.

EXAMINER CUE: All bearing temperatures indicate between 105* and 115'F on K005.

19 Monitor PO63/K005 bearing Observe vibration indication vibration. on 2NR-4502 recorder.

EXAMINER CUE (if asked) : Highest vibration is 2.2 mil and ',ceady.

REV 1-5, 10/03/94 Page 9 of 13

.. . .[

i i

JPM9 J041S' TITLES. As the Auxiliary Operator, continue-with the start-up of Main ,

Feedwater Pump K-005.

o==. . cunCALSTEP

~

NO PERFORMANCE STEP STANDARD S/U Comments '[

(Required for Unsat) [

20 Direct an Auxiliary Direct an-Auxiliary Operator -

Operator to close Pump to close Pump Casing Warmup Casing Wannup Line to Line to Condenser Inlet, :

Condenser Inlet, S21305MU1074, Downstream ,

S21305MU1074, Downstream Block S21305MU455, and Block S21305MU455, and Upstream Block S21305MU454. t Upstream Block S21305MU454.

[

CUE: The PEO reports the valves are closed.

f; 21* Increase speed to 1000 RPM. Depress MFWP K005 Speed Control, 2HS-4531 RAISE push !

button until speed as !

indicated on 2SI-4561 !

i indicate 1000 RPM.

i 22 Close H.P. Stop Valve Above Depress the H.P. Stop Valve Seat Drain Valve, 2HV-8228 Above Seat Drain Valve, t and L.P. Stop Valve Above 2HS-8228 and L.P. Stop Valve [

Seat Drain Valve, 2HV-8617. Above Seat Drain Valve, 2HS- l 8617, CLOSE push button-i 23 Close H.P. Stop Valve Below Depress the H.P. Stop Valve !

Seat Drain Valve, 2HV-8229. Below Seat Drain Valve, ,

2HS-8229 CLOSE_ push button.

.l

! 24 Close L.P. Stop Valve Below Depress the L.P. Stop Valve t Seat Drain Valve, 2HV-8618. Below Seat Drain Valve, 2HS-8618 CLOSE push button.

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REV 1-5,-10/03/94 Page 10 of 13 !

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JPM: J041S TITLE: As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

Denee a CRTTICALSTEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 25 Check lube oil temperature Call PEO to check lube oil ahe bearings greater than temperatures.

110*F.

CUE: PEO reports lube oil temperature at the bearings is 125*F & all bearing lube oil temperature rises < 50*F.

26* Increase speed to Low Speed Depress MFWP K005 Speed Stop (LSS) of EAP. Control, 2HS-4531 RAISE push button until speed as indicated on 2SI-4561 indicate approximately 3400 RPM.

27* Run MSC to High Speed Stop. Depress MFWP K005 Speed Control, 2HS-4531 RAISE push button until the green LOWER light is off.

28 Verify MFWP Turbine speed Observe MFWP Turbine speed remains constant. indicator 2SI-4561.

l REV 1-5, 10/03/94 Page 11 of 13

JPM: J041S TITLE: As the Auxiliary Operator, continue with the start-up of F9 tin Feedwater Pump K-005.

Denases a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat) 28 Close MFWP Turbine 1st Depress MFWP Turbine 1st Stage Drain Valve, Stage Drain Valve, 2HV-8619 2HV-8619. CLOSE push button.

TERMINATING CUE: The remaining parts of this procedure will be completed by Auxiliary Operators. This JPM is complete.

REV 1-5, 10/03/94 Page 12 of 13

JPM INFORMATION SHEET 1

1 INITIAL PLANT CONDITIONS l 1

l l

Unit 2 is approximately 3% power and holding for I various maintenance itens to be completed. '

The Aux Feedwater System is maintaining Steam l Generator L( al. '

The ACO is monitoring / operating the FWCS per SO23-9-6 and controlling the rest of the plant .

to maintain stable conditions.

Main Feedwater Pump K005 start-up is in l

progress. SO23-2-1, Main Feedwater Pump and l Turbine Operation, Attachment 1, is completed up to and including step 2.7.7.

TASK TO BE PERFORMED As the Auxiliary Operator, continue with the start-up of Main Feedwater Pump K-005.

REV 1-5, 10/03/94 Page 13 of 13

JPM INFORMATION SHEET JPM NUMBER J113FS INITIAL PLANT CONDITIONS The plant has undergone a major LOCA accident.

The operating crew has transitioned to SO23 3.

RWST level has lowered below 19%. The CRS has directed you to implement Attachment 5, RAS Actuation.

TASK TO BE PERFORMED Perform attachment 5 of SO23-12-3, RAS Actuation.

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REV 0, 09/29/94 Page 1 of 10 l

JOB PERFORMANCE MEASURE J113FS SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR

] ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards

, contaiuca in this JPM and is determined to bet i

SATISFACTORY:

UNSATISFACTORY:

REV 0, 09/29/94 Page 2 of 10

1 l DOCUMENTATION l

J113FS JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: n/a CRITICAL TIME: n/a minutes POSITION: UACO TASK NUMBER: 007852 TASK DESCRIPTION:

Verify proper actuation of the recirculation actuation system, i

KA NUMBER: S02S-006-020-A3-04 KA VALUES: RO 4.2 SRO 4.3 i BR-0122 CATEGORY: II i 10CFR55.45 APPLICABILITY: 4, 6, 7 l

REFERENCES:

SO23-12-3, Loss of Coolant Accident, Rev. 12 l

AUTHOR: H. J. WURTZ DATE: 09/29/94 OPERATIONS REVIEW: E. SENGSTACKEN DATE: 09/12/95 APPROVED BY: M. J. Kirby DATE: 10/19/95 1

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l REV 0, 09/29/94 Page 3 of 10 1

i MODIFICATION HISTORY i

l REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 New JPM l i

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i REV 0, 09/29/94 Page 4 of 10

SET-UP Use IC-22.

Enter "imf rp04".

Start 3rd HPSI Pump.

Need key # 8, 9, 10, 23, 24 & 25 REV 0, 09/29/94 Page 5 of 10

o .

JPM: J113S TITLE: Verification of RAS Actuation

Denames a CRITICAL 5TEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 1 Verify RAS conditions Observe RWT 2T006 LEVEL LI- Time Start: _

established by checking 0305-1, -2, -3, -4 and RWT RWST level <19%. 2T005 LEVEL 2LI-0301.

2 Check Containment Emergency Observe CNIMT EMER SUMP LEVEL Sump level >18' 4". 2LI-9386-1 OR 2LI-9389-2 '

greater than 18' 4".

3* Ensure Containment Open CNTMT EMER SUMP OUTLET Emergency Sump Outlet ISO VALVE 2HV-9303.

Valve, HV-9303, open. ,

4* Ensure Containment Open CNTMT EMER SUMP OUTLET Emergency Sump Outlet ISO VALVE 2HV-9305.

Valve, HV-9305, open.

1 5* Ensure Containment Open CNTMT EMER SUMP OUTLET Emergency Sump Outlet ISO VALVE 2HV-9302.

Valve, HV-9302, open.

6* Ensure Containment Open CNTMT EMER SUMP OUTLET Emergency Sump Outlet ISO VALVE 2HV-9304.

Valve, HV-9304, open.

REV 0, 09/29/94 Page 6 of 10 .

- _ - - - - - - - _ _ - - - _ _ _ - _ _ _ - . - - - - - _ - _ - - - - - - - - _ . - - _ _ _ - - _ _ _ _ _ _ _ _ - - _ _ _ - - _ -__.-_.-w_ --

JPM: J113S TITLE: Verification of RAS Actuation

Dmates a CRmCALSTEP NO PERFORMANCE STEP STANDARD S/U Conussents (Required for Unsat) 7* Ensure LPSI Pump P015 Depress SIAS OVERRIDE stopped. pushbutton and then the STOP pushbutton for LPSI PUMP P015 (E) 2HS-9390-1.

8* Ensure LPSI Pump P016 Depress SIAS OVERRIDE stopped. pushbutton and then the STOP pushbutton for LPSI PUMP P016 (N) 2HS-9390-1.

9* Ensure SI Pump & CNTMT Close SI Pump & CN' INT Spray Spray Pump mini-flow HV- Pump mini-flow iso valve 2HV-9306 closed. 9306.

10* Ensure SI Pump & CNTMT Close SI Pump & CNTMT Spray Spray Pump mini-flow HV- Pump mini-flow iso valve 2HV-9307 closed. 9307.

11* Ensure SI Pump & CNTMT Close SI Pump & CNTMT Spray Spray Pump mini-flow HV- Pump mini-flow iso valve 2HV-9347 closed. 9347.

12* Ensure SI Pump & CNTMT Close SI Pump & CNTMT Spray Spray Pump mini-flow HV- Pump mini-flow iso valve 2HV-9348 closed. 9348.

REV 0, 09/29/94 Page 7 of 10

[- . .

JPM: J113S TITLE: Verification of RAS Actuation

= % camCAI, STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 13 Notify SS/ Ops Leader to Inform SS/ Ops Leader to notify personnel in SEB of inform personnel of possible possible high radiation high radiation area in SEB.

levels.

EXAMINER CUE: The Ops Leader will notify personnel of potential high radiation levels in the SEB.

14 Check Containment Spray Observe Containment Spray Hdr flow >1625 gpm. No. 1 & No.2 flow indicators 2FI-0338-1 and 2FI-0348-2.

15 Check Containment Emergency Observe CNTMT EMER SUMP LEVEL Sump level >18' 4". 2LI-9386-1 OR 2LI-9389-2 greater than 18' 4".

16* Close RWST outlet Isolation Insert key and close RWT valve HV-9300. 2T005 Outlet Iso Valve 2HV-9300.

17* Close RWST outlet Isolation Insert key and close RWT valve HV-9301. 2T005 Outlet Iso Valve 2HV-9301.

REV 0, 09/29/94 Page 8 of 10

JPM: J113S TITLE: Verification of RAS Actuation

Denotes a CRmCALSTEP NO PERFORMANCE STEP STANDARD S/U Ccamments (Required for Unsat) 18 Verify HPSI Flow criteria: Observe'HPSI FLOW TO COLD

>160gpm/ operating pump with LEGS 2FI-0321-1, 2FI-0331-1, CLI only; >160 2FI-0311-2, & 2FI-0341-2 and gpm/ operating pump with HPSI HDR 1 & 2 TO LOOP FLOW, simultaneous hot / cold leg 2FI-9421-1 & 2FI-9435-2 to .

injection. determine total' flow.

19 Close CCW to Letdown Heat Depress the CLOSE pushbutton Time Stop:

Exchanger valve Train A HV- CCW CLA LTDN HX 2E062 6293B/A and Train B HV-6522 Supply / Return valves 2HV-A/B.. 6293B/A.and verify 2HV-6522A/B indicate shut. ,

TERMINATING CUE: This JPM is complete.

t REV 0, 09/29/94 Page 9 of 10 ,

1 1

1 JPM INFORMATION SHEET !

l t

INITIAL PLANT CONDITIONS i

The plant has undergone a major LOCA accident. l The operating crew has transitioned to SO23 l 3.

RWST level has lowered below 19%. The CRS has directed you to implement Attachment 5, RAS Actuation.

TASK TO BE PERFORMED I

Perform attachment 5 of SO23-12-3, RAS Actuation. 1 REV 0, 09/29/94 Page 10 of 10

1 I

JPM INFORMATION SHEET ;

JPM NUMBER J115S INITIAL PLANT CONDITIONS The reactor tripped and safety injection was initiated 1 - 1/2 hours ago. The CRS directs you to transfer charging pump suction per floating step 14 of SO23-12-3.

TASK TO BE PERFORMED Transfer charging pump suction per floating step 14 of SO23-12-3.

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i REV 0, 11/21/94 Page 1 of 9 ;

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JOB PERFORMANCE MEASURE J115S SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

l SATISFACTORY:

UNSATISFACTORY:

REV 0, 11/21/94 Page 2 of 9

DOCUMENTATION J115S JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 minutes I TIME CRITICAL JPM: n/a CRITICAL TIME: n/a minutes POSITION: UACO TASK NUMBER: 008624 TASK DESCRIPTION:

Transfer charging pump suction KA NUMBER: S032-000-011-Al-05 i KA VALUES: RO 4.3 SRO 3.{

ER-0122 CATEGORY: II 10CFR55.45 APPLICABILITY: 6, 7

REFERENCES:

SO23-12-3, Loss of Coolant Accident, Rev. 11 AUTHOR: H. J. Wurtz DATE: 11/21/94 OPERATIONS REVIEW: E. Sengstacken DATE: 09/12/95 APPROVED BY: M. J. Kirby DATE: 10/19/95 REV 0, 11/21/94 Page 3 of 9

I MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 New JPM 1

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REV 0, 11/21/94 Page 4 of 9

SET-UP Use IC-21.

Ensure VCT level is above auto makeup setpoint by entering:

imf cvi6a (0) 52 0 imf cvi6b (0) 52 0 i

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REV 0, 11/21/94 Page 5 of 9

JPM: J115S TITLE: Transfer charging pump suction l

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 1 Check elapsed time from Initial conditions state that SIAS actuation between 1- 1-1/2 hours have elapsed.

1/2 and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2 Verify RWST level greater Observe RWT 2T006 Level, 2LI- 3 than 2%. 0305-1 through 4.

3 Ensure LV-0227C, RWST to Open 2LV-0227C, RWT 2T006 Charging Pumps gravity feed Gravity Feed Valve.

valve open.

4* Override BAMU Pump 2P174. Depress the override pushbutton for BAMU Pump 2P174 (E).

5* Stop BAMU Pump 2P174. Depress the stop pushbutton for BAMU Pump 2P174 (E).

6* Override BAMU Pump 2P175. Depress the override pushbutton for BAMU Pump 2P175 (W).

7* Stop BAMU Pump 2P175. Depress the stop pushbutton for BAMU Pump 2P175 (W).

REV 0, 11/21/94 Page 6 of 9

. o JPM: J115S TITLES ~ Transfer charging pump suction a neome. . camcA1.STTS NO PERFORMANCE STEP STANDARD S/U .

Comments (Required for *Jnsat) 8* Override and close gravity Depress the override feed valve HV-9235. pushbutton for 2HV-9235, BAMU Tank 2T072 Gravity Feed Valve.

9* Close gravity feed valve Depress the close pushbutton HV-9235. for 2HV-9235, BAMU Tank 2T072 Gravity Feed Valve.

10* Override and close gravity Depress the override feed valve HV-9240. pushbutton for 2HV-9240, BAMU Tank 2T071 Gravity Feed Valve.

11* Close gravity feed valve Depress the close pushbutton HV-9240. for 2HV-9240, BAMU Tank 2T071 Gravity-Feed Valve.

12* Override the emergency Depress the override boration isolation valve pushbutton for 2HV-9240, BAMU HV-9247. Tank 2T071 Gravity Feed Valve.

13* Close emergency boration Depress the close pushbutton isolation valve HV-9247. for 2HV-9240, BAMU Tank 2T071 Gravity Feed Valve.

REV 0, 11/21/94 Page 7 of 9

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

. .o JPM8 J115S TITLES. Transfer charging pump suction

Dmotes a CRmCAL STEP NO PERFORMANCE STEP STANDARD S/U Comunents (Required for Unsat) 15 Close the Volume Control Verify 2LV-0227B, Volume Tank Outlet Valve LV-0227B. Control Tank Outlet Block Valve, closed.

Terminating Cue: This JPM is completed.

REV 0, 11/21/94 Page 8 of 9 I

l JPM INFORMATION SHEET j l

1 l

INITIAL PLANT CONDITIONS The reactor tripped and safety injection was initiated 1 - 1/2 hours ago. The CRS directs ;

you to transfer charging pump suction per floating step 14 of SO23-12-3.

l TASK TO BE PERFORMED l

Transfer charging pump suction per floating step 14 of SO23-12-3. l REV 0, 11/21/94 Page 9 of 9

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1 JPM INFORMATION SHEET l

1 JPM NUMBER l l

J117 I

INITIAL PLANT CONDITIONS 1

A reactor trip has occurred with the initiation '

of safety injection. The Shift Superintendent has directed the restoration of non-qualified !

loads. l i

TASK TO BE PERFORMED l Restore non-qualified loads outside the Control Room in accordance with SO23-12-3, attachment 11.

REV 0, 11/29/94 Page 1 of 9

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JOB PERFORMANCE MEASURE J117 l

SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR '

ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S .NAME: l (Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

l l

UNSATISFACTORY:

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REV 0, 11/29/94 Page 2 of 9 l

J

DOCUMENTATION J117 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: n/a CRITICAL TIME: n/a minutes POSITION: PPEO TASK NUMBER: 009440 TASK DESCRIPTION:

Perform non-qualified load restoration during emergency conditions.

{ KA NUMBER: S07S-062-000-A2-01 _

KA VALUES: RO 3.4 SRO 3.9 ER-0122 CATEGORY: II 10CFR55.45 APPLICABILITY: 6, 12

REFERENCES:

SO23-12-3, LOCA, Rev. 11 AUTHOR . H. J. Wurtz DATE: 11/29/94

^

OPERATIONS REVIEW: E. Sengstacken DATE: 09/18/95 APPROVED BY: M. J. Kirby DATE: 10/19/95 l

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i REV 0, 11/29/94 Page 3 of 9 l

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 New JPM l

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1 REV 0, 11/29/94 Page 4 of 9

SET-UP Provide copy of SO23-12-3, attachment 11.

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REV 0, 11/29/94 Page 5 of 9

JPM: J117 TITLE: Restore non-qualified loads outside the Control Room

Denaces a CRTUCAL STEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat)

NOTE: The following steps are not required to be performed in sequence.

NOTE: All MCCs located in 50' Control Building.

CUE: MCC BS is energized.

1* Energize the Fire Place the override switch on Time Start:

Detection and Actuation breaker 2/3BS-11, FIRE Systems and the UHF Radic- DETECTION AND ACTUATION System. SYSTEMS AND UHF RADIO SYSTEM PANEL 2L-414, & 2/3BS-12, FIRE DETECTION AND ACTUATION SYSTEMS AND UHF RADIO SYSTEM PANEL 3L-414, to the OVERRIDE position.

CUE: Amber light on 2/3BS-11 is lit, CUE: Amber light on 2/3BS-12 is lit.

2* Energize Essential Lighting Place the override switch on System (LP-35). breaker 2BY19, CONTROL ROOM ESSENTIAL LIGHTING PNL 2/3LP35B VIA TRANSFER SW 2/3LD101B, & 2BZ11, CONTROL ROOM ESSENTIAL LIGHTING PNL 2/3LP35A VIA TRANSFER SW 2/3LD101A, to the OVERRIDE position.

REV 0, 11/29/94 Page 6 of 9

JPM: J117 TITLE: Restore non-qualified loads outside the Control Room

Dendes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: Amber light on 2BY19 is lit.

CUE: Amber light on 2BZ11 is lit.

3* Energize the Health Physics Place the override switch on Computer Battery Charger. breaker BQ17, FEEDS BATTERY CHARGER B014, to the OVERRIDE position.

CUE: Amber light on BQ17 is lit.

4* Energize the Health Physics Place the override switch on Computer Air Conditioner. breaker BQ11, HEALTH PHYSICS HVAC DIST PNL 2/3-437, to the OVERRIDE position.

(

CUE: Amber light on BQ11 is lit.

5* Energize OSTSC Inverter Place the override switch on Y010 Alternate AC Source breaker 2BY33, OTSC COMPUTER (TSC Computer and EPPM L- INVERTER ASSEMBLY 2YO10, to 411). the OVERRIDE position.

CUE: Amber light on 2BY33 is lit.

REV 0, 11/29/94 Page 7 of 9

JPM: J117 TITLE: Restore non-qualified loads outside the Control Room

Daxtes a CRfflCALsTEP NO PERFORMANCE STEP STANDARD S/U Comuments (Required for Unsat) 6* Energize EPPM L-411. Place the override switch on Time Stop: ,

breaker 2BY23, MANUAL TRANSFER SWITCH 2XS411 EPPM PANEL 2L411, to the OVERRIDE position.

TERMINATING CUE: Amber light on 2BY23 is lit. This JPM is complete.

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i REV 0, 11/29/94 Page 8 of 9 l

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JPM INFORMATION SHEET INITIAL PLANT CONDITIONS A reactor trip has occurred with the initiation of safety injection. The Shift Superintendent '

has directed the restoration of non-qualified i loads.

TA$K TO BE PERFORMED i

Restore non-qualified loads outside the Control Room in accordance with SO23-12-3, attachment 11.

I REV 0, 11/29/94 Page 9 of 9

_

ML20129E641

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