ML20138K009

Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28

ML20138K009
Person / Time
Site:	Palo Verde
Issue date:	05/06/1997
From:	Hurley L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
50-528-97-02, 50-528-97-2, 50-529-97-02, 50-529-97-2, 50-530-97-02, 50-530-97-2, NUDOCS 9705120002
Download: ML20138K009 (212)

Text

g8 "'4g UNITED STATES

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NUCLEAR REGULATORY COMMISSION f, #I y i REGION IV 3'

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611 RYAN PLAZA DRIVE, SUITE 400 AR LINGTON, TEXAS 760118064 May 6, 1997 NOTE T0: NRC Document Control Desk Mail Stop 0-5 D 24 FROM: Laura Hurley, Licensing Assistant Operations Branch, Region IV

SUBJECT:

OPERATOR LICENSING EXAMINATIONS ADMINISTERED ON MARCH 24-28, 1997,  :

AT PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2. AND 3 l

DOCKETS #50 528: 529: 530  !

On March 24 28, 1997, Operator Licensing Examinations were administered at the referenced facility. Attached you will find the following information for  !

3rocessing through NUDOCS and distribution to the NRC staff, including the NRC

)DR:

Itemfl# a)/LFacility subiliTtted outLi s d_initialcexWsubmittal, designated'for Mistfibution nder1 FIDS Code A070.

b) As given operatin examination, designated for distribution under RIDS Code i

Item #2 - ,E$minaionReportwiththeasgivenwrittenexaminationattached.

I designa ed for-dfstributjorfinder RIQ If you have any questions, lease contact Laura Hurley, Licensing Assistant, Operations Branch, Region I at (817) 860 8253, n9an,7 9705120002 970506 PDR ADOCK 05000520 V PDR g

ES-301 Administrative Topics Outline Form ES-301-1 Facility: PVNGS Date of Examination: Wh >7#7 Examination Lesel(Circle): ' SRO Operating Test Number: /

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Turnover Determine which individuals perform plant stabilization when reactor trips during turnover. (Nr w) 2.1.3 3.0 Determine if given staffing leve'.s are adequate to perform turnover. (New)

Reactor Startup Determine actions for given condition during dilution to Requirements estimated critical'voron concentration. (New) 2.1.23 3.9 Determine actions for a given criticality condition. (New)

A.2 Tagging and Requirements for technical reviewer changes to a tagout.

Clearance (New) 2.2.13 3.6 Demonstrate how a loose tag is rehung. (New)

A.3 Radiation Control PVNGS administrative exposure limit and authorization to exceed. (New) 2.3.4 2.5 Determine radiological posting requirement for a given area survey map. (Modified)

A.4 Emergency Plan Offsite notification time requirements. (New)

,' 2.4.39 3.3 Non-delegable responsibilities of the emergency coordinator.

(New)

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. I Examiners Standards Rev.8

GROUP #: ,

REACTOR OPERATOR

^

ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Shifl Turnover KSA#: 2M LP #: NKA01-01-RC-709-000 QUESTION 1.

You are a reactor operator on the off-going shift. Your relief has arrived and have completed all items on the turnover checklist with the exception of the control board walkdown. Your shift supervisor and control room supervisor have completed their turnover. During your control board walkdown with the oncoming crew, while turning over B04, the reactor automatically trips. Which individuals perform the standard post trip actions and event mitigation?

REFERENCE ANSWER:

The on-coming SS, CRS, and the off-going ROs.

EXAMINEE'S ANSWER:

REFERENCE:

Operations Management Expectation.

Y

GROUP #: i 1

REACTOR OPERATOR i ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Shift Tumover KSA#: 2.1.3 LP #: NKA01-01-RC-709-000 QUESTION 2.

i, i

The unit is operating at 100% power. You are one of three dayshift reactor operators. The night  !

shift crew arrives with two reactor operators. The other reactor operator is delayed and will be  !

here within one hour. Determine whether turnover may proceed at this time. Justify your answer.

1 REFERENCE ANSWER: I Turnover may proceed since minimum staffing levels are adequate, i

EXAMINEE'S ANSWER:

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REFERENCE:

40DP-90P33, Shift Turnover.

Technical Specifications 6.2.2 1

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REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Reactor Startun  ;

) K.SA#: 2.1.23 LP #NKA01-01-RC-203-000: +

c i QUESTION 3.

i '

1 You are diluting from an RCS boron concentration of 2500 ppm to the ECBC of 1530 ppm.  !

When RCS boron concentration is 1600 ppm you notice the startup channel count rate has increased from an inital count rate of approximately 85 cps to 110 cps.

Determine if this is an expected response and any action (s) which must be taken.

REFERENCE ANSWER:

Expected response, no action required.

EXAMINEE'S ANSWER:

REFERENCE:

400P-9ZZ03, Reactor Startup a

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GROUP #:

REACTOR OPERATOR

~

ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Reactor Startup KSA#: 2.1.23 LP #NKA01-01-RC-203-000:

QUESTION 4.  !

You are the reactor operator perfonning an initial criticality following a refueling. While l withdrawing Group 3 from 0 to 30 inches withdrawn, you determine the reactor is critical.

Determine if this is an expected response and any action (s) which must be taken.

REFERENCE ANSWER:

Not an expected response.

Trip the reactor, perform standard post trip actions, and initiate emergency boration. I EXAMINEE'S ANSWER:

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REFERENCE:

400P-9ZZO2, Initial Criticality Following kefueling v

GROUP #:

REACTOR OPERATOR

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ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.2 Tagging and Clearangs KSA#: 2.2.13 LP #: NKA01-00-RC-708-000 QUESTION 5.

You are a Reactor Operator assigned to Work Control. While performing a technical review of a clearance, you identify that the tagout does not provide adequate protection. You add three tags to the tagout and are now satisfied with the level of protection.

What must now be performed to continue processing this clearance?

l REFERENCE ANSWER: ,

Clearance must be tech reviewed by a third party (not the author or this reviewer).

(You are now the preparer)

EXAMINEE'S ANSWER:

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REFERENCE:

40DP-90P29, Tagout Generation.

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

GROUP #: '

REACTOR OPERATOR

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ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.2 Tagging and Clearance

, KSA#: 2.2.13 LP #: NKA01-00-RC-708-000 QUESTION 6.

i

' You are a Reactor Operator assigned to Work Control. You are notified by a fire watch that he has found a RED DANGER tag #3 for clearance E-97-0001. Using the attached tag assignment sheet, demonstrate your documentation of rehanging tag #3. Assume it is an active clearance with work in progress and valve 1-AFB-V021 is closed.

4 REFERENCE ANSWER:

]

1. Line through the entry for the tag on the Tag Assignment Sheet, write " unattached", and 4 initial and date.

l 2. Print the same tag number on the next available line and hang /vedfy the tag as normal.

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EXAMINEE'S ANSWER:

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REFERENCE:

40DP-90P30, Clearance Processing.  !

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Tan Assigninent Slicci (Sainnlc)

Iracility No: / v/v6JI Clearance No. 6 cf7-o'ni P. ige of . .___

TAG PLACEMENT TAG REMOVAL.

Tao Col. Equip ID/Desc Drawing No. & IIang Component Placed Verified Restoic No. Restoicd Restoicd Vei eicd Cooidinates Order Position By By Oider Position By 16y Il.d, +4 J, >1rr3 fcI e -g l Sed I.]-11F6-IiS-iO fx6 01-nidry-o st { lbstf(b,3ky hrfr/ (jfW Y w S k & k s rot E-8 kg ~ ~ ~ ~

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GROUP #:

REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.3 Radiation Control KSA#: 233 LP #NGW15:

QUESTION 7. l l

You are performing 73ST-9SIO3, Leak Test of SI/RCS Pressure Isolation Valves. Your current i dose for this year is 1490 mrem. It is estimated you will receive an additional 50 mrem during  !

this testing. What level of authorization is required for you to proceed with this task? I REFERENCE ANSWER:

RP Department Leader approval for exceeding 1500 mrem /yr. I EXAMINEE'S ANSWER:

s,  ;

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REFERENCE:

75DP-9RP01, Radiation Exposure and Access Control.

GROUP #: _ _ _

REACTOR OPERATOR m

ADMINISTRATIVE TOPIC /SUILIECT DESCRIPTION: A.3 Radiation Control KSA#: 133 LP #NGW15:

QUESTION 8.

You are entering charging pump "A" room.

Using the attached area survey map, determine what radiation posting is required for the room and why.

REFERENCE ANSWER:

High Radiation Area.12 inch reading above 100 mrem /hr.

EXAMINEE'S ANSWER:

REFERENCE:

75DP-9RP01, Radiation Exposure and Access Control.

4

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

,, GROUP #:

. REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.4 Emergency Procedures /Plar, KSA#: 2.4.39 LP #NKA01-00-RC-601-000:

QUESTION 9.

A reactor trip occurred at 0905.

The Shift Supervisor assumed the role of Emergency l Coordinator and declared an ALERT at 0910. At 0920 the Emergency Coordinator upgrades the i event to a SITE AREA EMERGENCY while you performing initial notifications.

l I

I What are your action (s) regarding the current notifications and what time must you begin the upgrade notifications to remain in compliance with the emergency plan?

REFERENCE ANSWER:

Inform current notification that event has changed and stop current notifications.

0935 (15 minutes from upgrade declaration)

EXAMINEE'S ANSWER:

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REFERENCE:

16DP-0EP14, Satellite Technical Support Center Actions.

161G-0EP053, Emergency Notification Forms.

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GROUP #: .

. REACTOR OPERATOR \

ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.4 Emercency Procedures / Plan KSA#: 1.419 LP #NKA01-00-RC-601-000:

QUESTION 10.

You are a work control Reactor Operator who has reported to the Satellite Technical Support j Center during an ALERT. The on-shift Emergency Coordinator is busy with the emergency plan  !

procedures and requests you to obtain current plant status, upgrade the event classification level, )

if appropriate, and initiate the upgrade notifications.  ;

i What action (s) would have to be completed before you could upgrade the event classification and perform the upgrade notifications? l REFERENCE ANSWER:

You would have to assume the Emergency Coordinator position.

i EXAMINEE'S ANSWER: '

1

REFERENCE:

16DP-0EP14, Satellite Technical Support Center Actions.

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ES-301 Administrative Topics Outline Form ES-301-1 1 Facility: PVNGS Date of Examination: 3 4c > V r>

Examination Level (Circle): RO /@ Operating Test Number: 4

Administrative Describe method of evaluation:

j Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Turnover Determine which individuals perform plant stabilization when j reactor trips during turnover. (New) 2.1.3 3.4 Determine if given staffing levels are adequate to perform turnover. (New) i Reactor Stanup Determine required actions for a given condition during a Requirements reactor startup. (New)

', 2.1.23 4.0 Determine required actions for a given critical condition during i an initial startup following refueling. (New) l A.2 Equipment Control Operabilility determination for a given condition on the plant protection system. (New) 2.2.24 3.8 Retest requirement determination for the plant protection

system. (New)

{ A.3 Radiation Control Determine if SS authorization is required for a given continuous i release permit. (New)

2.3.6 3.1 Identify requirements for RU-38 becoming inoperable during a

~, planned power access pcrge release. (New) i A.4 Emergency Plan JPM - Classify event and provide protective action j ..

recommendations. (New) j 2.4.38 4.0

/

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Examiners Standards Rev.8

, GROUP #:

, SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Shift Turnovn KSA#: 2 L4 LP #: NKA01-01-RC '709 -000 QUESTION 1.

You are the on-coming control room supervisor. You and your shift supervisor have completed the turnover process. Your reactor operators have completed all items on their turnover checklist with the exception of the control board walkdown. During their board walkdown, while receiving turnover on B04, the reactor trips. Which individuals perform the standard post trip actions and event mitigation?

REFERENCE ANSWER:

The on-coming SS, CRS (you), and the off-going reactor operators.

EXAMINEE'S ANSWER:

a

REFERENCE:

Operations Management Expectations.

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

c GROUP #: '

. SENIOR REACTOR OPERATOR

~

ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Shift Turnover KSA#: 2JJ LP #: NKA01-01-RC-709-00D i QUESTION 2.

The unit is operating at 100% power on a Saturday. The day shift crew consists of the SS, CRS, two ROs, three AOs, and the STA. At 1730 one of the ROs became ill and was released to medical. No replacement was called in due to the short time until shift change. The night shift .

crew arrives at 1830 with the SS, CRS, two ROs, two AOs and the STA. The third RO will not  !

arrive until around 2000. '

Determine whether shift tumover may proceed or any corrective action (s) which must be taken before tumover can commence.

REFERENCE ANSWER:

Turnover may proceed since oncoming shift meets minimum staffing. .

l 0 EXAMINEE'S ANSWER:

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REFERENCE:

40DP-90P33, Shift Tumover Technical Specification 6.2.2

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' GROUP #:

SENIOR REACTOR OPERATOR t l ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.1 Reactor Startun KSA#: 2.1.23 LP #:NKA01-01-RC-203-000 '

l QUESTION 3.

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The unit tripped 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago. Reactor restart has been authorized and currently the part-length ,

and shutdown CEA groups are fully withdrawn with the regulating groups withdrawn to Group 3 '

at 60 inches. The ECRP is Group 4 at 100 inches withdrawn. The current ECC was calculated I for criticality at 2130, and current time is 2215.

l As the CRS, determine your action (s) regarding continuing the reactor startup.

REFERENCE ANSWER:

i ne ECC needs to be calculated for a later time of criticality. )

EXAMINEE'S ANSWER:  !

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REFERENCE:

400P-9ZZ03, Reactor Startup.

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, SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DE9 ' RIP flON: A.1 Reactor Startun KSA#: 2.1.23 LP #:NKA01-01-RC-203-000 QUESTION 4.

1 You are performing an initial criticality following a refueling for Unit 1 Cycle 7. The ECRP is Group 5 at 75 inches withdrawn. It is determined the reactor is critical with Group 3 at 90 inches withdrawn.

Determine the required action /s) for criticality at this core condition.

REFERENCE ANSWER:

Perform post criticality actions.

EXAMINEE'S ANSWER:

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REFERENCE:

400P CZZ02, Initial Criticality Following Refueling Core Data Book, Unit 1 Cycle 7, Curve 2.8.1 v

GROUP #: , _

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, SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.2 Equinment control KSA#: 2 2.24 LP #: NKA01-01-RC-149-000 QUESTION 5.

During testinn in Mode 1 a problem is discovered concerning the K1 relay in the "A" train plant protection s, tem. The contacts for the K1 relay will not change state when the relay is deenergized, resulting in reactor trip circuit breaker "A" not opening on a reactor trip signal.

Which part of the plant protection system is affected and what is the Technical Specification action statement for this condition?

REFERENCE ANSWER:

1 The Initiation Logic is the affected section of PPS.

Technical Specification 3.3.1 Action 5 is applicable. (Operation may continue provided the affected breaker is placed in the tripped condition within one hour)

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EXAMINEE'S ANSWER:

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REFERENCE:

Technical Specification LCO 3.3.1.

PVNGS Simplified Control System Drawings page 18.

Technical Specification Interpretation 3.3.1.0-13-09-00.

1

GROUP #:

SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC /SUILIECT DESCRIPTION: A.2 Eauinment Control KSA#: 2.2.24 LP #: NKA01-01-RC-149-000 QUESTION 6.

A problem was discovered with the train "A" SIAS subgroup actuation relay K401 while at power. The relay has been replaced and you have been asked for a retest determination. The ur.it is still at power.

What is the Technical Specification required retest for this corrective maintenance?

REFERENCE ANSWER:

l 36ST-9SA01, ESFAS Train A Subgroup Relay Monthly Functional Test.

l EXAMINEE'S ANSWER:  !

1

REFERENCE:

73DP-9ZZO9, Technical Specification Surveillance Requirements Cross Reference.

36ST-9SA01, ESFAS Train A Subgroup Relay Monthly Functional Test.

v

' GROUP #:

SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.3 Radiation Control KSA#: 21fi LP #:NKA01-00-RC-701-000 QUESTION 7.

Determine the level of authorization required for the attached continuous release permit.

REFERENCE ANSWER:

Shift supervisor authorization is required.

EXAMINEE'S ANSWER:

- l

REFERENCE:

74RM-9EF20, Gaseous Radioactive Release Permits and Offsite Dose Assessment.

Attached Relase Permit #970230.

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LIVER THYROID LUNG SKIN GROUP W. BODY GI-TRACT BONE KIONEY _____---

8.83E-02 INFANT: 8.83E-02 8.83E-02 0.00E+00 8.83E-02 8.83C-02 8.B3E-02 8.83E-02 CHILD;: 2.02E-01 2.02E-01 0.00E+00 2.02E-01 2.02E-01 2.b2t-01 2.025-01 2.D25-01 l

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f. P A ISO VERDE NUCLEAR GENERATING STATION GASEOUS RADIOACTIVE EFFLUENTS  !

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RADIOACTIVE RELEASE PERMIT PAGE 1 I TODAY'S DATE = 03-01-1997 i, CURRENT TIME = 14:47:26 REVISION #: GASREL 1.6 )

UNIT #: 2 PERMIT #:972030 i

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l RELEASE TYPE: PLANT VENT PERMIT BEGINS: 03-04-97 0951 )

PERMIT EXPIRES:03-13-97 0951  :

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GAMMA BETA GAMMA B ETe\ MAX ORGAN M.\X ORGAN l l ---------. ------------- i i A SE: 2.50E-O'a 1.05E-03 2.50E-03 1.05E 03 3. 8 8 E- 31 t.8SE-01 10 20 7.50 8.33 l

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. . n t T'. . ..ii.if i WHOLE BODY SK[N ORGAN Ilus r flease : 1.63E+02 0.00E 00 4.82E+02-Permit #972028: 0.00E-00 0.00E.00 0.00E.00 i

Permit #972000: 0.00E-00 0.00E-00 0.00E.00 Tota 1 1.63E+02 0.00E-00 4.82E+02 LCO: 166.00 1000.00 500.00

' .L(:0 : 98.193 0.00E-00 96A00 3.0 Is the release expected to exceed: .

ADMINISTRATIVE LIMITS?(80% OF LCO) YES  !

LIMITING CONDITION FOR OPERATION? NO i (FRACTION ALLOTTED TO TilIS UNIT)

. a.

\

.. . <._v-c

.. .. --_.,.-__.an,euay-gag &d;wd.",

E 0 N* **

.s

. GROUP #:

. SENIOR REACTOR OPERATOR ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.3 Radiation Control KSA#: 2312 LP #NKA01-00-RC-701-000:

QUESTION 8.

4 A power access containment purge is in progress. Radiation monitor RU-37 was inoperable when the release permit was authorized. During the release RU-38 loses all communication with the radiation monitoring computer. Discussion with the effluents tech reveals the local and RIC indications are normal.

Determine the required action (s) concerning the release in progress.

REFERENCE ANSWER:

Release can continue.

EXAMINEE'S ANSWER:

m.

w I

i

REFERENCE:

74RM-9EF43, Actions For Inoperable Radiation Monitors: Preplanned Altemate Sampling Program.

74RM-9EF20, Gaseous Radioactive Release Permits and Offsite Dose Assessment.

v

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

EP019-J-PLT-00 PVNGS JOB PERFORMANCE .\lEASURE 1

JPM BASIS INFORMATION 4

TASK: 1240102002 Classify Events Requiring Emergency Plan Implementation TASK STANDARD: Event classified as a Site Area Emergency and Protective Action Requirements i specified.

] K/A: 2.4.41 K/A RATING: RO: 23 SRO: 4.1

< K!A: 2.4.44 K/A RATING: RO: 2.1 SRO: 4.0 l APPLICABLE POSITION (S): SRO VALIDAT10N TIME: 10 min.

j

REFERENCES:

16DP-0EP13, Emergency Classification i

161G-0EP161, Protective Actions j SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X APPROVAL DEVELOPER:

REVISION DATE:

John K. Aronson 01/29/97 TECli REVIEW:

APPROVAL:

! /7/t7 i - v 3

TESTING METIIOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTORY Time Stan Time Stop j

REMEDI AL TRAINING REQUIRED? YES NO

~

(SEE OTG-04)

OTG-02 Rev. O I AAEP01BPLT. DOC cgc Ol/29M7

EP019-J-Pl T-00 PVNGS JOli PERFORAIANCE A1EASURE l

l

1. SIMULATOR SETUP:

A. ICt! : N/A B. MALFUNCTIONS OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION

1. N/A

2. I

3. l 4.

C. SPECI AL INSTRUCTIONS:

= None D. REQUIRED CONDITIONS:

• None 1

2. SPECIAL TOOLS / EQUIPMENT:

• None 1

l l

l I

I i

l OTG-02 Rev. 0 2

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

E P019-J-Pl.T-00 PVNGS JOB PERFOR31ANCE SIEASURE d

TASK CONDITIONS 2

INFORMATION PRESENTED TO EXAMINEE:

SPECI AL CONSIDERATIONS:

• You may use ans source ofinformation normalls available. I INITI ATING CUE: ,

i j

You are directed to use the following inforrr.ation to classify this event and determine any protective action recommendations.  !

t An event occurred at Palo Verde 25 minutes ago.

An carthquake strong enough to actuate the Operating Basis Earthquake and Safe Shutdown Earthquake triggers occurred.

A total loss of offsite power resulting in a reactor trip was concurrent with the j earthquake.

A failure of the "B" emergency diesel on generator differential fo!!cwed, i e

Reactor coolant system pressure and pressurizer level indicate a leak, although containment parameters are normal for post-SIAS conditions.

Iligh pressure safety injection flow is currently 400 gpm total and adequate for system pressure, i

. 1 Steam generator #1 had level increasing with no feedwater and a main steam safety '

valve stuck open.

e i Radiation Protection personnel have measured a site boundary dose rate of 40 mrem /hr l DDE using portable monitors.

The crew estimates shutdown cooling will be in operation within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Wind is blowing from 83 .

INFORMATION FOR EVALUATOR'S USE:

• Denotes Critical Step e At the discretion of the Examiner /Esaluator, this JPM m' be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has serbalized completion of the JPM. l Any step marked UNSAT requires comments.

e if this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

Step sequence is not critical unless noted or will prevent achieving the task standard.

SAFETY CONSIDERATIONS:

• None OTG-02 Rev. 0 3

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

b h5 EPoI9.1 PLT-00 PVNG5 JDB PERFOR.MANCE .\lEASURE 53EP El.EM ENT STANDARD

1. Obtain 16DP-0EPl3, Emergency 16DP-0EPl3 obtained Classification l

SAT UNSAT (UNSAT requires comments) 1 5TEP E LD1ENT 5TANDARD

• j

2. O.mif) 'he es era. Classify the esent as a Sde Area Emergency i based on the following:

i

) e SGTR > 132 gpm with prolonged release

} of steam.

Release of contaminated secondary side to atmosphere with steam generator RCS leakage grc ter than tech. specs.

l SAT UNSAT (UNSAT requires comments)

J' STEP ELEMENT STANDARD 1 3,

• Determine protective action requirements. Determine the following PARS:

i e Shelter for a 2 mile radius, l 4

NOTE: Examinee may propose Evacuatica for j

2 mile radius and $ miles in sectors L-M-N P-Q, but this is not necessary due to site boundary dose ofless than 100 mrem.

l SAT UNSAT (UNSAT requires comments) l

)

NORM AL TERMINATION POINT i

COMMENTS:

OTG-02 Rev 0 4

EP019.1-Pl T-00

~~

PVNGS J011 PERFORMANCE SIEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 01,'29/97 6 New JPM l

l i

l REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column l

and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

l. j Vendor reference document upgrade l

2.

Plant modification (include number)

3. Procedure upgrade )

4.  !

Internal or External Agency Commitment (indicate item number) '

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comrnents) l l

1 l

I l

OTG-02 Rev. 0 5

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

i EP019-J-PLT-00

{^ PVNGS JOB PERFORMANCE MEASURE l INITIAL CONDITIONS 1

INFORMATION PRESENTED TO EXAMINEE:

SI'ECIAL CONSIDERATIONS:

You may use any source ofinformation normally available.

INITIATING COE:

You are directed to use the following information to classify this event and determine any protective action recommendations.

An event occurred at Palo Verde 25 minutes ago.

An earthquake strong enough to actuate the Operating Basis Earthquake and Safe Shutdown Earthquake triggers occurred.

A total loss of offsite power resulting in a reactor trip was concurrent with the earthquake.

• A failure of the "B" cmergency dicsci on generator differential followed.

Reactor coolant system pressure and pressurizer level indicate a leak, although containment parameters are normal for post-SIAS conditions.

liigh pressure safety injection flow is currently 400 gpm total and adequate for system pressure.

Steam generator #1 had level increasing with no feedwater and a main steam safety valve stuck open.

Radiation Protection personnel have measured a site boundary dose rate of 40 mrem /hr DDE using portable monitors.

The crew estimates shutdown cooling will be in operation within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Wind is blowing from 88 .

OTG-02 Rey,0 6

i

_ l l

ES-301 Individual Walk-Through Test Outline Form ES-301-2 l

1 Facility: PVNGS Date of Examination: 7/1c -2 7/U Examination Level (Circle):h / SRO Operating Test Number: 4' i System / JPM Tile / Type Safety Planned Follow-up Question:

Codes Function K/A/G // Importance // Description 1.AFW AF001 liR 061 A1.04 3.9 Restore AF following inadvertent Calculate the time remaining in Ilot AFAS. Standby based on condensate availability.

D/S (New) 061 K4.02 4.5 System response based on given conditions. (New) 2.CVCS CH003 RC 004 K5.26 3.1 Borate the RCS from the refueling Determine source of water for charging water tank. pumps given RWT and VCT parameters.

D/A/S (New) 004 A2.32 3.4 i Expected primary plant response of a j

~'

temperature change in letdown flow through an ion exchanger. (New) j

3. CSS S1044 CI EPE011 EK3.08 3.9 Restore Containment Spray "A" to Explain the source and cooling method of normal from a SDC lineup. the water pumped to the RCS post-RAS.

1 N/S/L (New) 022 A4.02 3.2*

Starting duty on containment spray pump.

(Bank)

4. PB PB004 Electrical 062 K4.03 2.8*

Deenergize PBB-SO4. Describe status of non-class electrical M/S/L busses for a given fault condition. (New) 062 Kl.04 3.7 Describe the path for supplying Unit 1 PBB-S04 from Unit 2 EDG "A". (New)

5. NNIS SF027 Instrument 016 A2.01 3.0*

Restore SBCS for normal operation. Explain effect of failed temperature input D/S on SBCS with a reactor trip. (New) 041 Kl.06 2.6 System response to a high condenser

- backpressure condition clearing. (New)

Examiners Standards f Rev.8

,Psv ES-301 Individual Walk-Through Test Outline Form ES-301-2 1

6. CPS CP002 Plant 029 Al.03 3.0*  ;

Initiate a Containment vent. Service Impact of stopping supply fans in negative '

N/S pressure mode. (Bank) 029 K1.01 3.4 System response to RU-37 trip during power access purge. (New)

7. ESFAS SB002 IC 013 Kl.06 4.2 Reset ESFAS after inadvertent Determine effect on ESFAS actuated SIAS. equipment for a given fuse failure. (New)

N/S 013 K4.04 4.3

• l Determine method of resetting AFAS-1 actuation relays given specific plant conditions. 04ew)

8. SG SG010 HR 039 A4.01 2.9

• Manually operate the atmospheric Effect on partial stroke of a main steam dump valves. isolation valve when the "B" solenoid is l

D/P failed. (New)

- 039 A2.04 3.4 Required actions for given stroke time test l

results of an ADV. (New) l

9. CVCS CH011 RC 004 Kl.15 3.8 Line up borated water source during Difference in the physical connection of a control room fire. charging pump discharge to the high D/P/R pressure safety injection system. (New)

APE 024 AA2.04 3.4 Number of charging pumps running vs.

RWTlevel. (New) '

10 EDG DG007 Electrical 064 Kl.01 4.1 Manual reset and start of DG "B". Expected response to a ground fault when D/P DG is supplying bus. (New) 064 A1.03 3.2 Load limits for a given power factor.

(New)

- Typer Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator,(L)ow power, (P)lant, (R)CA I

M Examiners Standards Rev.8

3 f REACTOR OPERATOR 1 INDIVIDUAL WALK TilROUGII -

J i

RELATED JPM: AF001 QUESTION: 1.

l A loss of off-site power has ocurred. Current conditions are as follows: )

i Time since reactor trip 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l Condensate Storage Tank Level 20 feet

~

Highest RCS T-Ilot 535*F You have been asked to determine the time remaining in Ilot Standby assuming a 75

'F/hr cooldown will be initiated. ,

J RELATED ANSWER:

{

1

, 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> t 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> k [ Additional Information: 20 ft x 12,700 gal /ft = 254,000 gal (535 *F - 335 F) x 400 gal / F = 80,000 gal j 254,000 - 80,000 = 174,000 gal available. .

Using Appendix 4, Attachment 4-A, for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> since reactor trip yields ~12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

EXAMINEE'S ANSWER:

4 I

I

REFERENCE:

40EP-9E010, Appendix 4, Condensate vs. Time Remaining In Hot v

Standby.

l

_ REACTOR OPERATOR -

INDIVIDUAL WALK THROUGH i

1  :

1 RELATEDJPM: AF001 '

)

1 QUESTION: 2. t 1

A reactor trip has occurred due to a spurious rnain steam isolation signal. The secondary I operator established acceptable feedwater flow using AFB-P01. A subsequent loss of l

. PBB-SO4 oc 'urred. The secondary operator now reports difficulty in controlling i feedwater flow using AFA-P01. l What is the cause of the difficulty in controlling AFA-P01 flow to the steam generators? l I

l RELATED ANSWER: "

I Open flowpath through "B" train auxiliary feedwater valves, allowing steam generator pressure

j. to affect feedwater flowrates.

j.

1 EXAMINEE'S ANSWER: I

\

{

r 1

i t

4 4

i i

REFERENCE:

DWG 01-M-AFP-001.

t a

REACTOR OPERATOR 3 INDIVIDUAL WALK TIIROUGli .

k RELATED JPM: CII003 QUESTION: 3.

\

Given the following conditions:

e Volume control tank pressure 5 psig

. Refueling water tank level 87% (elevation 150')

e CIIN-UV-536 opened for gravity feed to the charging pumps.

. CIIN-UV501 is ten open.

Determine the source of water to the charging pumps (RWT or VCT) and justify your ,

answer, i t

i

) RELATED ANSWER:

Refueling water tank.

(RWT = 150', VCT pressure =l 1.2' plus tank elevation equals ~125').

EXAMINEE'S ANSWER:

REFERENCE:

Tank Curve Book.

I L

4 i

REACTOR OPERATOR .

!

INDIVIDUAL WALK TIIROUGII i

4  !

1

. i RELATED JPM: C11003 I l QUESTION: 4. I

Given the following conditions

-

e Unit operating at 100% power.

. Charging pump suction is from the volume control tank.

. Letdown purification ion exchangers are in service. ,

Nuclear cooling water flow to letdown heat exchanger degrades. l j e Letdown heat exchanger outlet temperature rises from 100 F to 130 *F. l l

1 Assuming no change in letdown and charging lineup, what is the expected response of i primary T-cold and T-hot?

1  !

e

, RELATED ANSWER: '

2 Primary T-cold will drop, resulting in a drop in T-hot.

4  :

- 1 I

EXAMINEE'S ANSWER:

1 I

a

REFERENCE:

NLA03-05, Chemistry.

REACTOR OPERATOR S INDIVIDUAL WALK TIIROUGII RELATED JPM: SIO44 QUESTION: 5.

A break on a hot leg of the reactor coolant system caused a reactor trip with SIAS, CIAS, MSIS, and CSAS actuations. The break is sufficient size that shutdown cooling will not be initiated. Following the recirculation actuation signal, what is the flow path of water to the core and how is it cooled?

RELATED ANSWER:

Flow Path: Containment sump to HPSI pump (s) to reactor core to containment sump.

Cooling: Containment spray system via the shutdown cooling heat exchanger. '

EXAMINEE'S ANSWER:

REFERENCE:

Safety Injection System STM, Volume 40.

?

. REACTOR OPERATOR 6

+

INDIVIDUAL WALK TIIROUGli RELATED JPM: SIO44 QUESTION: 6. I Containment spray pump "A" is started for a surveillance test at 1100. The pump is secured at 1140 due to a suspect vibration reading. After obtaining a replacement vibration monitor, the pump is restarted at 1200. A small oil leak develops and the pump is secured at 1205. The oil leak is repaired by 1210. When is restart of the pump allowed by procedure?

RELATED ANSWER:

1250. (The pump did not run 15 minutes on the second start, so 45 minutes must elapse)

EXAMINEE'S ANSWER:

l l

l l

l l

REFERENCE:

73ST-9S106, Containment Spray Pumps Miniflow Inservice Test.

v i

i

1 l

REACTOR OPERATOR 7

+

INDIVIDUAL WALK TIIROUGII RELATED JPM: PB004 QUESTION: 7.

Given the following conditions:

• The unit is operating at 100% power.

. NAN-S01 and NAN-S02 are powered from the auxiliary transformer.

• NBN-S01 and NBN-S02 are powered from their respective normal service transformer.

NBN-X01, normal service transfomier, experiences a sudden pressure relay trip.

• All systems operate per design.

1 Determine the status of busses NBN-501, NBN-S02, and the power source for NAN-S01 and NAN-S02.

RELATED ANSWER:

NAN-S01 and NAN-S02 are energized from auxiliary transformer.

NBN-S01 and NBN-S02 are cross-tied.

EXAMINEE'S ANSWER:

i i

l 1

l I

l i

1

REFERENCE:

System Training Manual,4.16 KV Non-Class IE System, Vol. 29B.

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

. REACTOR OPERATOR 8 INDIVIDUAL WALK THROUGII

! RELATED JPM: P3004 QUESTION: 8.

1 Unit 1 is experiencing a blackout. It has been determined to use Unit 2 emergency diesel generator "A" to supply Unit 1 PBB-SO4. Using the mimic on B01, describe the path for '

supplying Unit 1 PBB-SO4 from Unit 2 EDG "A".

RELATED ANSWER:

Unit 2 EDG "A"-+ 2PBA-S03 -+ 2 NAN-S03 -+ 2 NAN-S05 -+

Unit 1 NAN-S06 -+ INAN-S04 -+ 1PBB-SO4

=i EXAMINEE'S ANSWER:

j 1

4 3

i 4

REFERENCE:

40EP-9E010, Standard Appendices, Appendix 83.

4 4

. REACTOR OPERATOR 9 INDIVIDUAL WALK TilROUGII RELATED JPM: SF027 QUESTION: 9.

Reactor coolant system loop 2 T-hot instrument 121X is failed low. Reactor regulating system is selected to AVERAGE and the steam bypass control system master controller is in REMOTE / AUTO. A reactor trip occurs from 100% power. Explain the response of

, the steam bypass control system, assuming no operator action.

]

i.

RELATED ANSWER:

The system will modulate valves open as demand signal increases.

(Quick Open block is generated).

.I EXAMINEE'S ANSWER:

i 1

4 l

A

REFERENCE:

PVNGS Simplified Control System Diagrams, page 37.

l 1

. REACTOR OPERATOR 10 1 INDIVIDUAL WALK TIIROUGII RELATED JPM: SF027 QUESTION: 10.

Unit 1 is experiencing a loss of condenser vacuum and reactor trip. During stabilization, '

alarm 6A16B, SBCS Condenser Interlock, actuates and then clears. Secondary pressure is being controlled by steam bypass control valve 1007 in automatic. Explain what must be performed to restore the steam bypass control system to allow the automatic use of valves 1001-1006.

RELATED ANSWER:

1. Place valve controller stations for 1001-1006 in MANUAL with zero output.

2. Reset using the EMERGENCY OFF RESET handswitch on B06.

3. Place valve controller stations for 1001-1006 to AUTO.

EXAMINEE'S ANSWER:

1 l

1 l

i i

REFERENCE:

40AO-9ZZ07, Loss of Condenser Vacuum.

i L __ __ _.-

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

REACTOR OPERATOR 11 l

INDIVIDUAL WALK TIIROUGII RELATED JPM: CP002 QUESTION: 11.  !

The unit is in Mode 5 with the equipment hatch and personnel airlocks closed. The  !

containment purge system is operating in the negative pressure mode. Instrument air to '

, dampers CPN-M02-A and CPN-M02-B is isolated in the field.

l 4

What operational concern exists when operating the containment in this configuration?

^

RELATED ANSWER:

i Containment pressure will be excessively negative.

l

EXAMINEE'S ANSWER

i j

i 3  !

4 i

I

REFERENCE:

400P-9CP01, Containment Purge System.

4

. REACTOR OPERATOR 12 lNDIVIDUAL WALK TIIROUGII '

RELATED JPM: CP002 QUESTION: 12.

A power access purge is in progress when RU-37 momentarily spikes high. Describe the response of the containment purge system to this condition.

NOTE: References may not be used for this question. j l

RELATED ANSWER:

Valves CPA-UV-4A/B and CPB-UV-5A/B , containment purge supply and exhaust isolation valves, close. {

. EXAMINEE'S ANSWER:

j

REFERENCE:

Drawing 01-M-CPP-001, Containment Purge System.

{

REACTOR OPERATOR 13 INDIVIDUAL WALK TIIROUGH RELATED JPM: SB002 QUESTION: 13.

The fuse on the valve group relay power return for SI AS train "A" blows while the unit is operating at 100% power.

Describe the response of the "A" and "B" train equipment which normally actuates on an SIAS initiation. <

RELATED ANSWER:

"A" train valves actuate, pumps do not.

"B" train valves and pumps do not actuate.

t EXAMINEE'S ANSWER:

l l

t

REFERENCE:

PVNGS Simplified Control System Drawings, ESFAS cabinet functional

_ diagram.

{

REACTOR OPERATOR 14.

a INDIVIDUAL WALK TIIROUGli l

RELATED JPM: SB002 QUESTION: 14. '

Given the following conditions:

Engineered safety features actuation system "B" bistable relay card for steam generator #1 wide range level fails in the tripped condition.

• Steam generator #1 wide range level indications:

e Channel "A" 58 %

. Channel "B" 57%

• Channel "C" 0%

• Channel "D" 58%

Determine how the AFAS-1 actuation relays can be reset.

RELATED ANSWER:

Bypass either channel "B" or "C", reset the actuation relays at the auxiliary relay cabinet.

EXAMINEE'S ANSWER:

l l

l l

l l

REFERENCE:

Plant Protection System /ESFAS STM, Volume 49.

~

l E - .

. REACTOR OPERATOR 15  !

INDIVIDUAL WALK TIIROUGII l i

RELATED JPM: SG010 l 1

QUESTION: 15. i A partial stroke test using the "A" train hydraulics of SGE-UV-170, main steam isolation ,

va ve, is to be performed at 100% power. Unknown to the crew, soleneid valve "B" is failed and will not energize. What effect will the failed "B" solenoid have on the partial stroke test?

I l

RELATED ANSWER:  !

l Valve closes to 90% open (10% closed) and will not open using the "A" train.  !

EXAMINEE'S ANSWER ,

I

3

, I l

l  !

r i

I v

l

REFERENCE:

PVNGS System Desciption Manual, Main Steam, Vol 9.

t r

1 l

• REACTOR OPERATOR 16 l

INDIVIDUAL WALK TIIROUGII i

RELATED JPM: SG010 QUESTION: 16.

During performance of 73ST-9XI20, Atmospheric Dump Valve Inservice Test, the following data was obtained for Unit 1 SGB-HV-178:

Stroke Open Time 56 seconds Stroke Closed Time 37 seconds i Determine the detion(s) required for this condition.

RELATED ANSWER: i Notify the CRS/SS of the test deficiency.  !

EXAMINEE'S ANSWER: ,

1 4

I

REFERENCE:

73ST-9X120, Atmospheric Dump Valve Inservice Test.

. REACTOR OPERATOR 17 INDIVIDUAL WALK TIIROUGH RELATED JPM: CH011 QUESTION: 17.

What is the difference between charging pump alternate discharge to HPSI "A" piping and IIPSI"B" piping?

RELATED ANSWER:

HPSI "A" discharge into cold leg injection pipe HPSI "B" discharge into hot leg injection pipe.

EXAMINEE'S ANSWER:

1

REFERENCE:

Drawing 01-M-CHP-001 Drawing 01-M-SIP-001 m

o

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

. REACTOR OPERATOR 18 INDIVIDii AL WALK TIIROUGli i

4 RELATED .IPM: CH0ll <

QUESTION: 18.

Suction to the charging pumps is lined up to the refueling water tank through CHB-V327.

The refueling water tank level is currently 28%. What is the maximum number of charging pumps that can be operating without causing a loss of suction?

RELATED ANSWER:

i 2

EXAMINEE'S ANSWER:

I I

i l

REFERENCE:

40AO-9ZZ01, Emergency Boration.

l

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

I REACTOR OPERATOR 19 INDIVIDUAL WALK TIIROUGII RELATED JPM: DG007 QUESTION: 19.

A loss of power has occurred to PBB-SO4. The diesel generator is supplying the loads on the bus. The essential cooling water polp "B" experiences a single phase to ground fault. What is the expected response of the diesel generator and the loads on PBB-SO47 RELATED ANSWER: .

Diesel continues to supply the bus, no loads trip off..

(Neutral grounding resistor limits current through the ground fault relay to ~5 aic, :)

EXAMINEE'S ANSWER:

. ~,

i l

REFERENCE:

41 AL-IDGBI, Emergency Diesel Generator B Local Panel Alarm Response.

l 1 l

. REACTOR OPERATOR 20 j INDIVIDUAL WALK TIIROUGII RELATED JPM

DG007 QUESTION: 20 The "A" diesel generator is running paralleled to the grid. It is operating at 5.0 MW and 3.6 MVAR lagging. You are directed to increase the load to 5.6 MW while maintaining 3.6 MVAR lagging. What is the maximum time the generator can run at this loading?

RELATED ANSWER:

j 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

1 EXAMINEE'S ANSWER:

i l

REFERENCE:

410P-IDG01, Emergency Diesel Generator A.

P.O2 4

. j i . l A i n

ES-301 Individual Walk-Through Test Outline Form ES-301-2 l

Facility: PVNGS Date of Examination: J /> c - 1 WW l I l ExaminationLevel(Circle): RO hOperating Test Number:

3 System / JPM Tile / Type Safety Planned Follow-up Question:

Codes Function K/A/G // Importance // Description 1.CVCS C11003 RC 004 K5.26 3.1  ;

Borate the RCS' from the refueling Determine source of water for charging  !

water tank. pumps given RWl'and VCT parameters. l D/A/S (New) 004 A2.32 3.4 Expected primary plant response of a temperature changeinletdown flow through an ion exchanger. (New)

2. CSS SIO44 CI EPE011 EK3.08 3.9 Restore Contaihent Spray "A" to Explain the source and cooling method of normal from a SDC lineup. the water pumped to the RCS post-RAS.

N/8/L (New)

~ 022 A4.02 3.2

• Starting duty on contalmnent spray pump, s (g4 3.ESFAS SB002 IC 013 Kl.06 4.2 Reset ESFAS aher inadvertent

• Determine effect on ESFAS actuated SIAS. equipment for a given fuse failure. (New)

N/S 013 K4.04 4.3

• Determine method of resetting AFAS 1 actuation relays given specific plant conditions. (New) 4.SO SOO10 HR 039 A4.01 2.9' Manually operfte the atmospheric Effect on partial stroke of a main steam dump valves. isolation valve when the "B" solenoid is D/P failed. (New) 3? A2.04 3.7 Required actions for given stroke time test time results for an ADV.(New)

5. EDG DG009 Electrical 064 Kl.01 4.1 Manual start and load of DO Expected response to a ground fault when "B"during contbl room fire. DG is supplying bus. (New)

M/A/P 064 A1.03 3.2 i Load limits for a given power factor.

(New)

• - Type: Codes: (D)irect from bank, (M)odified from bank, (N)cw, (A)lternate path, (C)ontrol roon), (S)lmulator, )owpower, )lant, (R)CA Examiners Str.adards Rev. 8

1 SENIOR REACTOR OPERATOR UPGRADE 1 1 INDIVIDUAL WALK TIIROUGli I l

RELATED JPM: CII003 QUESTION: 1.

Given the following conditions: j

• Volume control tank pressure 5 psig I

• Refueling water tank level 87% (plant elevation 150')

e Clin-UV-536 opened for gravity feed to the charging pumps. l

. CIIN-UV-501 is left open.

Determine the source of water for the charging pumps (RWT or VCT) and justify your answer.

i l

l RELATED ANSWER:

-w I

- Refueling water tank.

(RWT = 150', VCT pressure = 11.2' plus tank elevation equals ~125')

EXAMINEE'S ANSWER: l 1

l l

i i

l i

d

REFERENCE:

~

Tank Curve Book.

i I

. SENIOR REACTOR OPERATOR UPGRADE 2 INDIVIDUAL WALK TilROUGil RELATED JPM: CII003 QUESTION: 2.

Given the following conditions:

. Unit operating at 100% power. j

. Charging pump suction is from the volume control tank.

. Letdown purification ion exchangers are in service.

Nuclear cooling water flow to the letdown heat exchanger degrades.

. Letdown heat exchanger outlet temperature rises from 100 'F to 130 F.

Assuming no change in letdown and charging lineup, what is the expected response of primary T-cold and T-hot.

RELATED ANSWER:

Primary T-cold will drop, resulting in a drop in T-hot.

EXAMINEE'S ANSWER:

1 I

1 1

REFERENCE:

NLA03-05, Chemistry.

l l

L SENIOR REACTOR OPERATOR UPGRADE 3 INDIVIDUAL WALK TilROUGIl RELATED JPM: SIO44  :

i QUESTION: 3. l A break on a hot leg of the reactor coolant ystem caused a reactor trip with SIAS, CIAS, i

MSIS, and CSAS actuations. The break is sufficient size that shutdown cooling will not be initiated. Following the recirculation actuation signal, what is the flow path of water i; to the core and how is it cooled?

• i RELATED ANSWER: '

l Flow Path: Containment sump to HPSI pump (s) to reactor core to containment sump.  ;

Cooling: Containment spray system via the shutdown cooling heat exchanger.

1 EXAMINEE'S ANSWER:

REFERENCE:

Safety Injection System STM, Volume 40.

1 SENIOR REACTOR OPERATOR UPGRADE 4

-INDIVIDUAL WALK THROUGH

~

d d

RELATED JPM: S10 14 QUESTION: 4.

Containment spray pump "A" is started for a surveillance test at 1100. The pump is l secured at 1140 due to a suspect vibration reading. After obtaining a replacement i

vibration monitor, the pump is restarted at 1200. A small oil leak develops and the ptunp

is secured at 1205. The oil leak is repaired by 1210. When is restart of the pump allowed by procedure?

4 1

RELATED ANSWER

1250. (The pump did not run 15 minutes on the second start, so 45 minutes must elapse) ,

3 J

EXAMINEE'S ANSWER:

1 I

i

{

l i

I 4

REFERENCE:

73ST-9S106, Containment Spray Pumps Miniflow Inservice Test.

l 9 SENIOR REACTOR OPERATOR UPGRADE 5 INDIVIDUAL WALK THROUGli RELATED JPM: SB002 i

i l QUESTION: 5.

, i i

The fuse on the valve group relay power return for SIAS train "A" blows while the unit is operating at 100% power. .

1 Describe the response of the "A" and "B" train equipment which normally actuates on an SIAS initiation.

RELATED ANSWER:

"A" train valves actuate, pumps do not.

"B" train valves and pumps do not actuate.

EXAMINEE'S ANSWER: l l

I l

l l

REFERENCE:

PVNGS Simplified Control System Drawings, ESFAS cabinet functional )

diagram.

SENIOR REACTOR OPERATOR UPGRADE 6

' INDIVIDUAL WALK TIIROUG11 -

)

RELATED JPM: SB002 1

QUESTION: 6. J Given the following conditions:

e Plant protection system "B" bistable relay card for steam generator #1 wide range level fails in the tripped condition.

. Steam generator #1 wide range level indications:

. Channel "A" 58 %

. Channel "B" 57 %

. Channel "C" 0%

e Channel "D" 58 %

Determine how the AFAS-1 actuation relays can be reset.

~

RELATED ANSWER:

Bypass either channel "B" or "C", reset the actuation relays at the aux relay cabinet.

EXAMINEE'S ANSWER:

4 l

l 1

REFERENCE:

Plant Protection System /ESFAS STM, Volume 49.

~

\

l l

s. , y - + s - -- -r- -

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

SENIOR REACTOR OPERATOR UPGRADE 7 i

INDIVIDUAL WALK THROUGli RELATED JPM: SG010 >

QUESTION: 7.

A partial stoke test using the "A" train hydraulics of SGE-UV-170, main steam isolation valve, is to be performed at 100% power. Unknown to the crew, solenoid valve "B" is ,

failed and will not energize. What effect will the failed "B" solenoid have on the partial stroke test?

RELATED ANSWER:

Valve closes to 90% open (10% closed) and will not open using "A" train.

EXAMINEE'S ANSWER

,m 1 -w

REFERENCE:

MSIV Control System Drawing System Training Manual, Volume 9, Main Steam.

i s

u

SENIOR REACTOR OPERATOR UPGRADE 8 INDIVIDUAL WALK TIIROUGII '

t

.i.

RELATED JPM: SG010 i i

QUESTION: 8.

)

i i

i During performance of 73ST-9XI20, Atmospheric Dump Valve Insenice Test, the l following data was obtained for Unit 1 SGB-HV-178: I l

Stroke Open Time 56 seconds Stroke Closed Time 37 seconds

Determine the action (s) required for this condition. l 2

RELATED ANSWER:

t 4

Notify CRS/SS of test deficiency.

']-

EXAMINEE'S ANSWER:

l I

i i

i i

I

REFERENCE:

73ST-9XI20, Atmospheric Dump Valve Inservice Test.

v

O SENIOR REACTOR OPERATOR UPGRADE 9 f INDIVIDUAL WALK TIIROUGli .

I l

RELATED JPM: DG007 QUESTION: 9.

A loss of power has occurred to PBB-S04. The diesel generator is supplying the loads on l

the bus. The essential cooling water pump "B" experiences a single phase to ground fault. What is the expected response of the diesel generator and the loads on PBB-SO4?  !

RELATED ANSWER:  ;

Diesel continues to supply the bus, no loads trip off.

(Neutral grounding resistor limits current through ground fault relay to ~5 amps)

EXAMINEE'S ANSWER:

t n

r i

l l

l I

REFERENCE:

41 AL-IDGB1, Emergency Diesel Generator B Local Panel Alarm Response.

s

i . SENIOR REACTOR OPERATOR UPGRADE 10 l INDIVIDUAL WALK THROUGII E

d RELATED JPM: DG007 1

QUESTION: 10.

" The "A" diesel generator is running paralleled to the grid. It is operating at 5.0 MW and 3.6 MVAR lagging. You are directed to increase the load to 5.6 MW while maintaining 3.6 MVAR lagging. What is the maximum time the generator can run at this loading?

RELATED ANSWER:

l 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

EXAMINEE'S ANSWER:

'?)

REFERENCE:

410P-1DG01, Emergency Diesel Generator A.

- . . _ . _ _ _ . _ . - _ _ -.__ _ _ _ _ - -_ - .____ ~ _. _ _ ___-__ __ _ _ _ - _ . _ _ . _ . - _ _ _ . _

j d>-

j. Al'001-J.C/ R-12 PVNGF JOB PERFOR.\ LANCE .\1EASURE i

l

.)PAI IIASIS IN FOR31 ATION i

TASK: 1250320:01 P rfouh required actions fo!! awing an inadsertant AFAS

, TASK STANDARD: Al A-P01 and AFB-P01 stopped. AFA-P01 steam supply valves closed and the Essential 4

AF control valves to the SGs are closed l K'A: 3.4-061 - A2.05 K/A RATING: RO: 3.1 SRO: 3.4 K!A: K/A RATING: RO: SRO:

! APPLICABLE POSITION (S): RO/SRO VALIDATION TIN 1E: 10 min

REFERENCES:

41 AO-lZz32, Inadsertent AFAS l SUGGESTED TESTING ENVIRONNIENT: SINIULATOR X PLANT

! APPROVA L

81/

) DEVELOPER:

REVISION DATE:

W. Hendricsen 02/12.'97 TECH REVIEW: MBW M"f)

APPROVAL: p TESTING AIETIIOD

\

ACTUAL TESTING ENVIRONNIENT: SINIULATOR PLANT i TESTING NIETHOD: SINIULATE PERFORN1 l EVALUATION 1, EXAN11 NEE NAN 1E:

(print) l EVALUATOR NANIE:

(print)

, SATISFACTORY UNSATISFACTORY Time Start Time Stop i

REN1EDI AL TRAINING REQUIRED? YES NO (sEE OTG-04)

)

4

'l

}

O FG-02 Rev. O I J W \WORDAIO0lCR DOC cgc 02/lF97 i

i A F001-J-C/ R-12 PVNGS JOB PERFOlGIANCE MEASURE

1. SIMULATOR SETUP:

A. IC#: 20 B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT CO3131AND DESCRIPTION l.

2.

3.

4.

C. SPECIAL INSTRUCTIONS:

. Reset to IC-20

. Go to RUN on the Simulator

. Ensure AFA-P01 placard reads 9.61

• Take AFAS-1 and AFAS-2, Actuation switches (B05) to " Initiate" and then back to normal and RESET the actuation at the AUX RELAY CABINETS (May need a Key)

. Acknowledge alarms then FREEZE the Simulator

. Provide Initiating Cue

. Go to RUN D. REQUIRED CONDITIONS:

• None

2. SPECIAL TOOLS / EQUIPMENT:

• None l

l I

1 OTG-02 Rev. 0 2

A

• #~ ' #~

AF001-J-C/R 12 PVNGS JOB PERFOIOLANCE MEASURE i

TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

I I

SPECIAL CONSIDERATIONS:

Operation ofin-plant equipment is to be SD1ULATED ONLY, DO NOT OPERATE any equipment.

. Inform the control room staff of any discovered deficiencies.

. You may use any source ofinformation norm:.lly available.

INITIATING CUE:

. An inadvertent AFAS has occurred.

• Verification checks have been performed and it has been verified that AFAS I and 2 were not required.

The AFAS signal has been reset and the CRS directs you to restore actuated equipment to standby in accordance with 41 AO-lZZ32, Inadvertent AFAS.

1

• INFORMATION FOR EVALUATOR'S USE:

.

• Denotes Critical Step At the discretion of the Exarniner/ Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

. Any step marked UNSAT requires comments.

If this is the first IPM of the set then ensure the examinee has been briefed IAW OTG-01.

Step sequence is not critical unless noted or will prevent achieving the task standard.

. Notify unit Shift Supervisor of in-plant JPM perforTnance.

SAFETY CONSIDERATIONS:

. None m

OTG-02 Rev. 0 3

AF001-J-C/R-12 PVNGS JOB PERFORMANCE SIEASURE l l

ST EP ELEMENT STANDARD l

1. Obtain procedure 41 AO-lZZ32. 41 AO-lZZ32 obtained. i SAT UNSAT (UNSAT requires comments)

I STEP ELEMENT STANDARD

2. Check closed the feedwater regulating and AFB-HV-30 closed. 1 isolation valves for AF Pump B.  !

AFB-HV-31 closed.

a. AFB-HV-30 AFB-UV-34 closed.

b. AFB-HV-31 AFB-UV-35 closed.

c. AFB-UV-34 If requested CUE: All valves indicate closed. I

d. AFB-UV-35 SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

3. Check closed the feedwater regulating and AFA-HV-32 closed.

isolation valves for AF Ptunp A.

AFC-HV-33 closed.

a. AFA-HV-32 AFC-UV-36 closed.

b. AFC-HV-33 i AFA-UV-37 closed.

c. AFC-UV-36 If requested CUE: All valves indicate closed.

d. AFA UV-37 SAT UNSAT (UNSAT requires comments)

COMMENTS:

4

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

w*

AF001-J-C/R-12

PVNGS JOB PERFOR31 ANCE SIEASURE

?

. STEP ELEMENT STANDARD -

4,

• Close SG2 STM SPLYS to AFW Pump SGA-UV-138 and SGA-UV-138A closed.  !

"A" SGA UV-138 and verify closed SGA-UV-138A. If requested CUE: Both valves indicate  !

closed. t SAT UNSAT (UNSAT requires comments) .

STEP ELEMENT STANDARD

5. Close SGI STM SPLYS to AFW Pump SGA-UV-134 and SGA-UV-134A closed.

"A" SGA-UV 134 and verify closed SGA-  ;

UV-134A. If requested CUE: Both valves indicate i closed. i When requested CUE: AFA-P01 has ,

stopped rolling and did not run at < 1000  !

rpm for > 5 minutes.

SAT UNSAT (UNSAT requires comments)  !

i STEP ELEMENT STANDARD

6. Override and stop AFB-P01. AFB-P01 is stopped. .

If requested CUE: llandswitch indicates green and white lights on, red light off. i When requested CUE: Diesel generators have been shutdown.

SAT UNSAT (UNSAT requires comments)

I COMMENTS:

5 i

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

l s' "

\

i AF001-J-C/R 12 PVNGS JOB PERFOlGIANCE MEASURE '

?

i >

l' STEP ELEMENT STANDAIID .

i

7. Ensure AFB-HS-10 returns to AUTO and AFB-HS-10 in AUTO and power available.  :

power is available Inform CUE: All 41 AO-lZZ32 appendices are being performed by another RO. l

\

SAT UNSAT (UNSAT requires comments) '

STEP ELEMENT STANDARD

8. Ensure AFA-P01 Turbine Speed Control AFA-SK-52A on B06 set at value indicated on dial is set at the 3590 to 3600 RPM speed "41ST-1 AF02 Dats" placard. If not at placard position. setting, Examinee will retum dial to placard setting.

If requested CUE: AFA-P01 Turbine Speed Control dialis set at the 3590 to 3600 RPM speed position.

5 SAT UNSAT (UNSAT requires comments) '

~

STEP ELEMENT STANDARD  !

9. Open AFA-144, Steam Trap AFN-M03 Nuclear Operator directed to open AFA-144,

~~

Bypass,1/4 turn. 1/4 turn.

f When requested CUE: Essential chilled water is required. t When requested CUE: Steam Generator blowdown and sampling is being restored by another RO.

i SAT UNSAT (UNSAT requires comments)

NORMAL TERMINATION POINT COMMENTS:  !

w' 6

AF001-J-C/R-12 PVNGS JOll PERFOR31ANCE 31EASURE l

RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED CONiMENTS 9 10/10/96 6 New Format per OTG-02 l 10 01/16/97 6 Revised task standard to be more descriptive, changed the setup ,

to initiate both AFAS-1 and AFAS-2 11 02/12/97 6 Change the inform cue in step 5 to be less confusing to the operators l 12 03/12/97 6 Changed inform cues to when requested cues to aid the evaluator.

l I

l l

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column j and brief description of changes in Comments Column. Comments are to be numbered i consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

OTG-02 Rev. 0 7

i AF001-J-C/R-12  !

! PVNGS JOB PERFOR31ANCE SIEASURE  !

l  :

! 1 l INITIAL CONDITIONS l

l ,

i INFORA1ATION PRESENTED TO EXAMINEE- >

i i

SPECIAL CONSIDERATIONS:

• Operation of in-plant. equipment is to be SINIULATED ONLY, DO NOT OPERATE any equipment.  ;

• Inform the control room staff of any discovered deficiencies. j

• You may use any source ofinformation normally available. .

E  !

l INITIATING CUE: l l

• An inadvertent AFAS has occurred. j l i j

• Verification checks have been performed and it has been verified that AFAS I and 2 were not required.

• The AFAS signal has been reset and the CRS directs you to restore actuated equipment {

! to standby in accordance with 41 AO-lZZ32, inadvertent AFAS.

l  :

l i

SAFETY CONSIDERATIONS-  !

. None  !

l' l

l

)

i i

I t i 1 1 I

OTG-02 Rev. 0 8 l'

C11003-J-C/ R-23' PVNGS JOB PERFORMANCE MEASURE j

\

JPM BASIS INFORMATION TASK: 0150030801, Perform a Boration of the RCS  :

TASK STANDARD: Boration of 75 (+25) gallons performed.  !

K/A: 004 A4.01 K/A RATING: RO: 3.8 SRO: 3.9 K/A: 004 A2.23 K/A RATING: RO: 2.6 SRO: 2.7 APPLICABLE POSITION (S): RO VALIDATION TIME: 15 min.

REFERENCES:

410P-lCH01, CVCS Normal Operations,41 AL-lRK3A, Panel B03A Alarm Response SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT APPROVAL l DEVELOPER: John K. Aronson TECH REVIEW: e74/// o JN9[f7 REVISION DATE: 02/18/97 APPROVAL: /

V

~

TESTING METIIOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE _

PERFORM EVALUATION  :

EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE OTG-04)

OTG-02 Rev. 0 1 W3 WORD'Cil0(3CR DOC cge I t/07/96

C11003 .I-C/ R-23' PVNGS . LOB PERFORMANCE MEASURE A. SIMULATOR SETUP:

1. IC# 20

2. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

l EVENT COMMAND DESCRIPTION I l 1. IMF CV09100 30 Clog boron injection filter (see below) l 2. MMF CV09 01:00 See Special Instructions.

3.

4.

1. SPECI AL INSTRUCTIONS:

. After Examinee increases setpoint on CH-FIC-210Y to 25 gpm (JPM Step 7), enter: IMF CV09 100 30 (This clogs the Boron injection filter)

• When Examinee requests AO to open filter bypass valve CHV-V164 (JPM Step 10), then (MMF CV09 01:00} (This simulates opening CHN-V164 slowly so CH-527 and CH-512 don't close on high D/P.

2. REQUIRED CONDITIONS:

• None.

A. SPECIAL TOOLS / EQUIPMENT: l

• NONE i

OTG-02 Rev.0 2

Cii003-3-C/R-23' PVNGS JOll PERFOIDIANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECI AL CONSIDERATIONS:

• Operation of equipment is to be performed on the simulator.

• The examiner will provide all responses and indications required from outside the control room.

• You may use any source of infermation nonnally available.

INITIATING CUE:

The CRS directs you to borate the RCS by using 410P-lCII01. The quantity to be added has been determined to be 75 gallons from the RWT at a rate of 25 gpm. Use CIIN-FIC-210Y in automatic to the charging pump suction.

All Prerequisites are complete.

INFORf. ATION FOR EVALUATOR'S USE:

• Denotes Critical Step

• At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

• Any step marked UNSAT requires comments.

• If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

• Step sequence is not critical unless noted or will prevent achieving the task standard.

• NOTE: This is an altemate path JPM.

S AFETY CONSIDERATIONS:

• NONE OTG-02 Rev. 0 3

l

1. # Cif 003-3-C/R-23' PVNGS Jolt PERFORMANCE MEASURE ST EP ELEMENT STANDARD Set boric acid makeup now controller Examinee verifies controller setpoint <

3 0 and " Auto" selected.

CHN-FIC-210Y to "0" pm and place controller to AUTOMATIC.

If requested CUE: Controller CilN-FIC-210Y auto light is on, set to "0" gpm.

SAT UNSAT (UNS AT requires comments)

STEP ELES1ENT STANDARD Set boric acid flow totalizer to desired Examinee sets the totalizer to 75 gals.

y volume (75 gallons).

If requested CUE: Totalizer set to 75 gallans.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD Select " BORATE" on makeup mode Examinee selects " Borate" 3 selector switch, CifN-HS-210.

If requested CUE: Makeup mode selector is in " Borate".

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD Verify BAMP pump starts. Examinee verifies BAMP Pump 4

running If requested CUE: BAMP red light is on.

SAT UNSAT (UNSAT requires comments)

COMMENTS:

OTG-02 Rev. 0 4

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

1 i

• j  !

C11003-J C/R-23' PVNGS JOll PERFOR31ANCE MEASURE  !

i l ST El* ELE 31ENT ST ANi> A RD .,

Verify CHN-FV-210X is closed Examinee verifies CHN-FV-210X is l 3

closed and no Dow indicated. l

! If requested CUE: CllN-FV-210X ]

4 signal is 0, flow is 0. '

SAT UNSAT (UNSAT requires comments)  ;

ST El' ELE 31ENT STANDARD )

Verify CHN-UV-527 is open. Examinee verifies CHN-UV-527 is 6

open. i If requested CUE: CilN-UV-527 red light is on.

SAT UNSAT (UNSAT requires comments)

STEP ELE 31ENT STANDARD Adjust CHN-FIC-210Y to the desired Examinee adjusted the Auto setpoint to 7

Dow rate (25 gpm). 25 gpm ( 5 gpm).

NOTE: Simulator driver action reauired to plug BA Filter.

If requested CUE: CHN-FIC-210Y adjusted to 25 gpm.

SAT UNSAT (UNSAT requires comments) l COMMENTS:  ;

3 OTG-02 Rev. 0 5 j

C11003-J-C/R-23' j PVNGS JOB PERFOIO!ANCE 31EASURE 1

l STEP ELI: MENT STANDARD

g Verify the proper flow rate is indicated. Examinee identifies that the flow is not responding properly and informs the CRS.

INFORM CUE: Alarm 3 A06A is

, alarming. Alarm CRT has " Boric

Acid Filter fligh dp". CRS directs you to respond to the alarm, j

i SAT UNSAT (UNSAT requires comments)

l j

l STEP ELEMENT STANDARD

! Verify alaim 3 A06A; by directing Examinee directs operator to check J 9

1 operator to read Boric Acid Filter local filter differential pressure.

differential pressure locally on CHN-i PDIS-260.

When requested CUE: Filter DP is j

) pegged high. I SAT UNSAT (UNSAT requires comments) i t

i J j s

l 1

COM51ENTS:

OTG-02 Rev.0 6

1 T

C ' "i Cil003-J-C/R-23' l

PVNGS JOB PERFOIDIANCE MEASURE  ;

STEP ELEMENT STANDARD ,

• Direct operator to open Filter Bypass Examinee directs operator to open i 10 Valve CHN V!64 and close CHN- CHN-V164 and close CHN-V 161.

V161.

When requested CUE:  ;

• CIIN-V164 is open, CilN-V161 is closed.

• The operator will remove the BA -

filter from service as directed by j procedu re.  ;

NOTE: Simulator driver action required to delete malfunction per SPECIAL INSTRUCTIONS.

SAT UNSAT (UNSAT requires comments) ,

STEP ELEMENT STANDARD

. When the desired amount of acid has Examinee ensures FIC 210Y is closed gg been added, ensure FIC-210Y is closed. and no excessive flow indicated after i desired 75 gallons (125) of acid is added.

If requested CUE: FIC-210Y output is 0,00w is 0. .

SAT UNSAT (UNSAT requires comments) ,

STEP ELEMENT STANDARD f Selects Auto on makeup mode select Examinee selects Auto on the Makeup 33 switch, CHN-ilS-210. Mode Select Switch.

If requested CUE: Makeup mode I select is ir. " AUTO" SAT UNSAT (UNSAT requires comments) l l

l COMMENTS:

OTG-02 Rev. 0 7 1

.j

1 e

i Cil003 .1-C/R-23' PVNGS JOB PERFOlOIANCE MEASURE l l

l I

STEP ELEMENT STANDARD l Verify tha: CIIN-UV-527 closes. Examinee verifies CHN-UV-527 33 {

closed.  !

If requested CUE: CilN-UV-527 green light is on.

l SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD y Ensure boric acid pump stops. Examinee ensures BAMP Pump stops.

INFORM CUE: BAMP green light is on. Steps to flush, sample, change set ,

points and realign system are not I necessary at this time.

SAT UNSAT (UNSAT requires comments)

NORMAL TERMINATION POINT I

COMMENTS:

i OTG-02 Rev,0 8

l l@

CII003-J-C/R-23' PVNGS JOB PERFOR31ANCE 31EASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 22 08/28/96 6 New Format 23 02/19/97 6 Updated CUE format I

l l

l l

l l

I REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment findicate item number)

5. Technical Specitication Change (indicate amendment number)

6. Other (explain in comments)

OTG-02 Rev. 0 9

g C11003 .I-C/R-2f PVNGS JOli PERFORMANCE MEASURE l -INITIAL CONDITIONS J

4 INFORMATION PRESENTED TO EXAMINEE:

j SPECIAL CONSIDERATIONS:

= Operation of equipment is to be performed on the simulator.

f j = The examiner will provide all responses and indications required from outside the

, control room.

l = You may use any source ofinformation normally available.

]

j INITIATING CUE:

The CRS directs you to borate the RCS by using 410P-1CIl01.The quantity to be

, added has been determined to be 75 gallons from the RWT at a rate of 25 gpm. Use j CIIN-FIC-210Y in automatic to the charging pump suction.

4

All Prerequisites are complete.

l.- -

i SAFETY CONSIDERATIONS:

• NONE 4

]

OTG-02 Rev. 0 10

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

,W i i I S1044-3-C/ R-00 '.

s j PVNGS J011 PERFOR31ANCE MEASURE

! .J P31 IlASIS IN FOR31ATION 1

1 i TASK: 0120030401 Restore Containment Spray and LPSI "A" to norma! operating lineup.

TASK STANDARD

Containment Spray "A" lined up through shutdown cooling heat exchanger and  !

j LPSI "A" lined up for injection. i

K/A

026 A4.01 K/A RATING: RO: 4.5 SRO: 4.3 j K/A: 005 A4.01 K/A RATING: RO: 3.6

• SRO 3.4 i APPLICABLE POSITION (S): RO/SRO VALIDATION TIME: 10 minutes j

REFERENCES:

400P-9S102, Recovery from Shutdown Cooling to Normal Lineup i SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT s

1 APPROVAL DEVELOPER: J. K. Aronson TECH REVIEW:

REVISION DATE: 01/17/97 APPROVAL: -

TESTING 31ETIIOD l ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM i

EVALUATION I EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE OTG-04)

OTG-02 Rev. 0 1 A",S1044CR tXX' egc 01/03'97 i

s I #

SIO44-J-C/R-00

PVNGS J011 PERFOR31ANCE 31EASURE

1. SIMULATOR SETUP:

A. ICii4 B. MALFUNCTIONS, OVERRIDES & ' REMOTE FUNCTIONS:,

EVENT CO3131AND DESCRIPTION

1. imf b205:siap03 out(in) Cycle control power for CS pump "A"

2. imt b205:siap01 out(tn) Cycle control power for LPSI pump "A" 3.

4. i C. SPECI AL INSTRUCTIONS:

• Ensure control power is on for SIA-UV-672, containment spray header isolation valve.

D. REQUIRED CONDITIONS:

• Heat removal established with reactor coolant pumps and/or train "B" shutdown cooling with train "A" SI in standby shutdown cooling lineup. "A" containment spray system lined up to bypass shutdown cooling heat exchanger. Shutdown cooling heat exchanger outlet temperature is less than 200 F.

2. SPECIAL TOOLS / EQUIPMENT:

. None l

l i

s l

1 i OTG-02 Rev. 0 2 l

l

4 S1044-J C/R-00" PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS 4

2 INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS

e Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

• Inform the control room staff of any discovered deficiencies.

j e You may use any source ofinformation normally available.

r INITIATING CUE:

• A plant heatup is in progress. The CRS directs you to restore Safety Injection train "A" to its normal operating lineup per 400P-9SIO2, Recovery from Shutdown Cooling to Normal Operating Lineup.

• Shutdown purification is not aligned to train "A".

. There is no flushing to be performed.

• All prerequisites are complete.

INFORMATION FOR EVALUATOR'S USE:

• Denotes Critical Step

. At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

• The complete load shed and manual sequencing ofloads will not be performed.

• Any step marked UNSAT requires comments.

. If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

• Step sequence is not critical unless noted or will prevent achieving the task standard.

• Notify unit Shift Supervisor of in-plant JPM performance.

. At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Elements ,

and Standards are met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. j S AFETY CONSIDERATIONS: )

• None OTG-02 Rev. 0 3  !

I l

4

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

j e

S1044-J-C/R-00

PVNGS JOB PERFOR31ANCE 51EASURE l

l STEP ELEMENT STANDARD  ;

1. Obtain procedure 400P-9S102. Procedure 400P-9S!02 obtained.

SAT UNSAT (UNSAT requires comments) 1 l

i STEP ELEMENT. STANDARD

2. Direct an Area Operator to place the Examinee directs Area Operator to place the ,

control power UC fuse for PBA-S03F, LPSI "A" UC fuse to OFF. I LPSI "A" supply breaker, to OFF.

If r. quested CUE: LPSI pump "A" control l power UC fuse is in OFF.

NOTE: Simulator driver must input: i imf b205:siap01 out. l SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

3.

• Direct an Area Operator to place the Examinee directs Area Operator to place  ;

control power UC fuse for PBA-S03D, the CS "A" UC fuse to OFF.

CS "A" supply breaker, to OFF.

If requested CUE: Contianment spray pump "A" control power UC fuse is in OFF. '

NOTE: Simulator driver must input:

imf b205:siap03 out.

SAT UNSAT (UNSAT requires comments) l CO5151ENTS:

OTG 02 Rev. 0 4

a SIO44-J-Cat-00"

, PVNGS JOB PERFOR31ANCE SIEASURE I STEP ELE 31ENT STANDARD

] 4. Close SIA-HV-655, Loop 1 SDC-LPSI Examinee. closes SIA-HV-655.

j pump "A" suction valve.

If requested CUE: Handswitch indicates i green light ON, red light OFF.

4 SAT UNSAT (UNSAT requires comments) j i

i STEP ELE 51ENT STANDARD

5. Close SIA-HV-691, SDC loop "A" Examinee closes SIA-HV-691, SDC loop 3 warmup bypass valve. "A" warmup bypass valve.

f

) If requested CUE

IIandswitch indicates i

green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments) 5 j STEP ELEN1ENT STANDARD

6. Ensure SI A-UV-672, Containment Examinee ensures SIA-UV-672 is closed.

J spray "A" discharge valve is closed.

If requested CUE: IIandswitch indicates green light ON, red light OFF.  ;

SAT UNSAT (UNSAT requires comments) j l

STEP ELE 31ENT STANDARD l

7. Ensure SI A-UV-184, SDC return to CS Inform CUE: 40AC-0ZZ06 shows SIA-is locked closed and SIA-UV-105, CS UV-184 is locked closed and SIA-UV-105 "A" suction isolation is locked open. is locked open.

SAT UNSAT (UNSAT requires comments) i l

1  !

COMMENTS:

l i-J 1

i i

1 i.

OTG-02 Rev. 0 5

i

1 i

~

S1044-J-C/R-0(*

PVNGS JOB PERFORMANCE SIEASURE SIEP ELEMENT STANDARD S. Ensure SIA-UV-664, CS pump "A" Examinee ensures SIA-UV-664 is open.

recirculation valve is open.

If requested CUE: Handswitch indicates green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

9. Ensure SIA-UV-660, Train "A" Examinee ensures SIA UV-660 is open.

combined recirculation valve is open.

If requested CUE: Handswitch indicates green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments) l 1

STEP ELEMENT STANDARD l

10. Open SIA-HV-678, CS "A" discharge Examinee opens SI A-HV-678.

to shutdown cooling heat exchanger valve. If requested CUE: IIandswitch indicates green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

11. Close SIA-HV-686, SDCHX "A" Examinee closes SIA-HV-686.

outlet valve to RC loops 1 A/lB.

If requested CUE: Handswitch indicates green light ON, red light OFF.

SAT UNGAT (UNSAT requires comments)

COMMENTS:

i l

l OTG-02 Rev. 0 l 6

l 1

S104&J-C/R-00

)

PVNGS JOli PERFOIGIANCE SIEASURE STEP ELEMENT STAN DAllD

12. Ensure SI A-HV-657, SDCHX "A" Examinee ensures SIA-HV-657 is closed. I outlet valve to RC loop 1 A/1B is closed. If requested CUE: Handswitch indicates green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

13. Open SIA-HV-687, LPSI-CS from Examinee opens SI A-HV-687.

SDCHX "A" crosstie valve.

If requested CUE: Handswitch indicates green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments) 4 I

I STEP ELEMENT STANDARD 1

14. Close SIA-HV-685, LPSI-CS to Examinee closes SIA-HV-685.

l SDCHX "A" crosstie valve.

If requested CUE: Handswitch indicates l green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments) i COSIBIENTS:

l \

l l

l i

OTG-02 Rev. ,0 l 7

4 SIO44-J-C/R-00

PVNGS JOB PERFOlulANCE MEASURE

~

STEP ELEMENT STANDARD

15. Open SI A-HV-684, CS "A" discharge Examinee opens SIA-HV-684.

to SDCILX valve.

5 If requested CUE: Handswitch indicates j green light OFF, red light ON.

$,AT UNSAT (UNSAT requires comments)

,i l STEP ELEMENT STANDARD

16. Close SIA HV-688, CS "A" bypass Examinee closes SIA-HV-688.

around SDCHX valve.

i If requested CUE: Hamtswitch indicates -

green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

17. Ensure CHA-UV-531, RWT to SI train Examinee ensures CHA-UV-531 is open.

j "A" valve is open.

4 If requested CUE: Handswitch indicates

! green light OFF, red light ON.

j SAT UNSAT (UNSAT requires comments) i 1

t i

i COMMENTS. i

.i 4

OTG-02 Rev. 0 8

j J

S1044-J-C/R-00

PVNGS JOB PERFOR5 LANCE MEASURE

! STEP ELEMENT STANDARD I

) 18. Direct an Area Operator to restore the Examinee directs Area Operator to place ,

control power UC fuse for PBA-503D, the CS "A" UC fuse to ON.

to ON. '

If requested CUE: Containment spray

) pump "A" control power UC fuse is in l i ON.

NOTE: Simulator driver must input:

1 imf:b205:siap03 in.

i Inform CUE: Another operator will perform the independent verification.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

- 19,

• Open SIA-HV-306, SDCHX "A" Examinee opens SIA-HV-306.

bypass valve. .,

If requested CUE: Handswitch indicates t green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD I J *

20. Open SIA-UV-669, LPSI "A" recirc Examinee opens SIA-UV-669.

valve. I If requested CUE

Handswitch indicates

green light OFF, red light ON.

j SAT UNSAT (UNSAT requires comments) l 1

l COMMENTS:

i, l

3 1 I i

< i I

OTG-02 Rev. 0 9

S1044-J-C/R-00'*

PVNGS JOB PERFOIGIANCE SIEASURE STEP ELEMENT STANDARD

21. Open SI A-liv-683, LPSI "A" RWT Examinee opens SIA-HV-683.

suction ve.lve.

If requested CUE: IIandswitch indicates green light OFF, red light ON.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

22. Direct an Area Operator to restore the Examinee directs Area Operator to place control power UC fuse for PBA-S03F, the LPSI "A" UC fuse to ON.

to ON.

If requested CUE: LPSI pump "A" control power UC fuse is in ON.

NOTE: Simulator driver must input:

imf:b205:siap01 in.

Inform CUE: Another operator will perform the independent verification and complete the other actions of Section 4.

SAT UNSAT (UNSAT requires comments)

NORMAL TERMINATION POINT COMMENTS:

OTG O Rev, 0 10

• l S1044-J-C/R-00 '*

PVNGS JOB l'ERFOIDIANCE MEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 02/19/97 6 New REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor teference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments) l l

OTG-02 Rev. 0 11

a esk #

SIO44-J-C/R-00

PVNGS JOB PEllFOR31ANCE SIEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SFFCI AL CONSIDERATIONS:

Operation of in-plant equipment is to be SIAIUL ATED ONLY, DO NOT OPERATE any equipment.

e inform the control room stafTof any discovered deficiencies.

=

You may use any source ofinformation normally available.

INITIATING CUE:

A plant heatup is in progress. The CRS directs you to testore Safety Injection train "A" to its normal operating lineup per 400P-9SIO2, Recovery from Shutdown Cooling to Normal Operating Lineup.

• Shutdown purification is not aligned to train "A" e There is no flushing to be performed.

SAFETY CONSIDERATIONS:

• Nonc OTG-02 Rev. 0 12

I 1

,' PH004-J-C/R-00

PVNGS JOB PERFOR31ANCE SIEASURE l i

2 JPM BASIS INFORMATION l i

t l TASK: 0720030601, De-energize 4.16 kv Dus PBB-SO4 l

! TASK STANDARD: Bus PBB-SO4 de-energized and Diesel Generator"B" not running. ,

K/A: 062 A4.01 K/A RATING: RO: 3.3 SRO: 3.1 l K/A: K/A RATING: RO: SRO: 1 APPLICABLE POSITION (S): RO VALIDATION TIME: 20 min. I

REFERENCES:

410P-IPB01,4.16kv Class IE Power

SUGGESTED TESTING ENVIRONMENT

SIMULATOR X PLANT j

! l i APPROVAL l DEVELOPER: T. Stabler TECH REVIEW: [ 2dfd7 i REVISION DATE: 01/03/97 APPROVAL: j i l v

TESTING METIlOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT l

j TESTING METilOD: SIMULATE PERFORM i

EVALUATION l

EXAMINEE NAME:

2 (print)

! EVALUATOR NAME:

i (print) l SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO

j Reset the SBCS Emergency Switch SGN-HS-1010 to " RESET"(spring return 9 j Off by going to ' Reset' on to neutral). I I SGN-HS-1010.

If requested CUE: Switch SGN-IIS-1010 is

" RESET" and Annunciators "SBCS 1 ABNORMAL" and "SBCS COND INTLK" are clear.

1 i NOTE: Annunciators "SBCS ABNORMAL" and "SBCS COND INTLK" clear.

1 >

3 i SAT UNSAT (UNSAT requires comments) i 1

5 COMMENTS:

J 1

I OTG-02 Rev. 0 6

SF027-J-C/R-09 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARP 10 Verify the 'SBCS Abnormal' Verify "SBCS ABNORMAL" alarm clear.

alarm is (Window 6A 16A) is clear. If requested CUE: Annunciator "SBCS ABNORMAL" is clear. L SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD Verify the 'SBCS COND Verify "SBCS COND INTLK" alarm clear.

11 INTLK' alarm (Window 6A16B) is clear. If requested CUE: Annunciator "SBCS COND INTLK" is clear.

Inform CUE: No adjustment of the SBCS master controller is desired.

SAT UNSAT' (UNSAT requires comments)

NORMAL TERMINATION POINT t

COMMENTS:

OTG-02 Rev. 0 7

SF027-3-C/ R-09 PVNGS J011 PERFOIO1ANCE MEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 6 06/27/96 6 FORMAT CHANGED 7 10/10/96 6 More Format changes per OTG-02 8 10/16/96 6 More Format changes per OTG-02 9 02/19/97 6 Changed Task Standard REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade 4 Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

OTG-02 Rev. 0 8

1 e

SF027-J-C/R-09 PVNGS JOB PERFORSIANCE .TIEASURE INITIAL CONDITIONS INFORM ATION PRESENTED TO EXAMINEE: l e

SPECIAL CONSIDERATIONS:

• Operation of in-plant equipment is to be SISIULATED ONLY, DO NOT I OPERATE any equipment.

• Inform the control room staff of any discovered deficiencies.

. You may use any source of information normally available.

INITIATING CUE:

• The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to reconnect the Steam Bypass Control System in  !

accordance with 410P-ISF05, Operation of Steam Bypass Control System. i SAFETY CONSIDERATIONS: I e NONE I

i -

.1 I

1 1 I

l

! l l

l i l I

I OTG-02 Rev. 0 9

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

L.

e E CP002-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE

, JPM BASIS INFORMATION TASK: 0500010401 Initiate a containment vent.

TASK STANDARD

Containment purge system in operation in the VENT mode.

l K/A: 029 A2.03 K/A RATING: RO: 2.7 SRO: 3.1 K/A: K/A RATING: RO: SRO:

3 APPLICABLE POSITION (S): RO/SRO VALIDATION TIME: 10 min j

REFERENCES:

400P-9CP01, Containment Purge System i SUGGESTED TESTING ENVIRONMENT: SIMUL.ATOR X PLANT k

l APPROVAL DEVELOPER: J. K. Aronson TECH REVIEW: / at REVISION DATE: 01/16/97 APPROVAL:

! TESTING METHOD l

! ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT i

l TESTING METHOD: SIMULATE PERFORM EVALUATION I

EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTOR'Y Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE OTG-04)

OTG-02 Rev. 0 J \OP5TRNGVPMiCP001 DOC rim 3/13/97

, I

i CI'002-J-C/R-00' PVNGS JOll PERFOR31 ANCE SIEASURE

1. SIMULATOR SETUP:

A. IC#: Reset to IC-20 B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION

1. mrf ch04 open Opens IA-BV45, air supply to CPB-UV-5B.

2. unf tr01:hcbpt493 0.3 Sets containment pressure to 0.3 psig.

3.

4.

C. SPECIAL INSTRUCTIONS:

• Modify the following remote functions:

MRF CH04 (open IA supply to CP-UV-58, IA-VB45)

• Provide initiating cue.

l

= Go to run on simulator.

D. REQUIRED CONDITIONS:

2. SPECIAL TOOLS / EQUIPMENT:

2

l sA O**

CP002-J-C/R-00" i

PVNGS JOB PERFORSIANCE SIEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE: 1 I

I SPECI AL CONSIDERATIONS: j

=

Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. ,

1 l

The examiner will provide all responses and indications required from outside the control '

room.  !

i

= Inform the control room staff of any discovered deficiencies. j i

• You may use any source of information normally available.

INITIATING CUE:

1 l

• The CRS has directed you to initiate a containment vent in accordance with 400P-9CP01, Containment Purge System. An area operator is standing by in the RCA to ,

assist you.

)

e RU-34 is available.

• All prerequisites are complete.

INFORMATION FOR EVALUATOR'S USE:

,

• Denotes Critical Step

• At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be

tenninated when the Examinee has verbalized completion of the JPM.

• Any step marked UNSAT requires comments.

= If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

• Step sequence is not critical unless noted or will prevent achieving the task standard. I

= Notify unit Shift Supervisor ofin-plant JPM perforrnance.

SAFETY CONSIDER.ATIONS:

• None l

l 3 l

_ _ ___ _ _ . . _ _ _ .. _ .___m . . _ _ _ - . . _ . _ _ _ _ . . _ _ _ _ - . _ . . _ _ _ _ . _ _ . _

i I

' E j j CP002-J-C/R-00  !

PVNGS JOB PERFOR31ANCE SIEASURE 1 STEP ELEMENT STANDARD

1. Obtain procedure 400P-9CP01, Examinee obtains procedure.  ;

i Containment Purge System l SAT UNSAT (UNSAT requires comments) i 1

l STEP ELEMENT STANDARD

2. Verify closed IA-VB47, IA supply to CP- Examinee directs AO to verify IA-VB47 is UV4A. closed.

When requested CUE: IA-VB47 is closed.

1 SAT UNSAT (UNSAT requires comments) l l

l

\

STEP ELEMENT STANDARD I

! 3. Unlock and open IA-VB45, air supply to Examinee directs AO to unlock and open IA-l CPB-UV-5B and CP-PV-43. VB45.

I When requested CUE: lA-VB45 is open.

l SAT UNSAT (UNSAT requires comments)  !

STEP ELEMENT STANDARD I

4. Open/ check open CP-V024 ISOL to RU- Examinee directs AO to open/ check open CP-

34. V024.

When requested CUE: CP-V024 is open.

i l SAT UNSAT (UNSAT requires comments)

I 1

1 COMMENTS: j l

t A

4 l

l ,

CP002-J-C/R-00' PVNGS JOB PERFOR.\ LANCE 31EASURE STEP ELEMENT STANDARD

5. Close/ check closed CP-V023 ISOL to RU- Examinee directs AO to close/ check closed CP-

34. V023 ISOL to RU-34.

When requested CUE: CP-V023 is closed.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

6. Ensure Channel Check is current on RU-37 When requested CUE: Channel checks are and/or RU-38 prior to each system startup. current on RU-37 and RU-38.

SAT UNSAT (UNSAT requires commenu)

STEP ELEMENT STANDARD

7.

• Stan venting containment by placing the Examinee places CPN-HS-1 in VENT position.

Containment Purge Mode Selector Switch CPN-HS-1 on B07 to VENT. Damper If requested CUE: CPN-ilS-1 is in VENT CPN-M06 opens. position and CPN-M06 is open, green light OFF and red light ON.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

8. Open the Containment Power Access Purge Examinee opens CP-UV-4B.

Upstream isolation valve CP-UV-4B by placing CPA-HS-4 to OPEN. If requested CUE: CPA-IIS-4 indicates green light ON and red light ON.

NOTE: Handswitch will have dual indication due to CP-UV-4A remaining closed.

SAT UNSAT (UNSAT requires comments)

COND1ENTS: ,

I l

w 5

j

• v C P002-J-C/R-00 PVNGS JOB PERFOR31ANCE SIEASURE STEP ELE 51ENT ST AN DARD

9. Open the Containment Power Access Purge Examinee opens CP-UV-5B.

Downstream isolation valve CP-UV-5B by placing CPB-HS-5 to OPEN. If requested CUE: CPB-flS-5 indicates green light ON and red light ON.

NOTE: Handswitch will have dual indication due to CP-UVSA remaining closed.

SAT UNSAT (UNSAT requires comments)

STEP ELE 51ENT STANDARD

10. Log time the 8 inch valves were opened on Time logged on permit.

the release permit.

Inform CUE: Time has been logged.

SAT UNSAT (UNSAT requires comments)

STEP ELE 31ENT STANDARD

11. Notify RMS/Eftluent Section and Effluents and RP notified.

Radiation Protection of stan time of release. Inform CUE: Notifications acknowledged.

SAT UNSAT (UNSAT requires comments)

STEP ELE 51ENT STANDARD

12. When pressure decreases to less than 0.5 CP-PV-43 indicates open.

psig then ensure CPN-PV-43 is open.

If requested CUE: CPN-PV-43 indicates green light OFF and red light ON.

SAT UNSAT (UNSAT requires comments)

NOR31AL TERS11 NATION POINT COMMENTS:

I I

l 6

CP002-J-C/R-00' PVNGS JOll PERFOR31ANCE SIEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 02/19/97 6 New REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

, 3. Procedure upgrade l

4. Internal or External Agency Commitment (indicate item number) l S. Technical Specification Change (indicate amendment number)

6. Other (explain in comments) l l

l l

OTG.02 Rev. 0 7

I CP002-J-C/R-00*

i PVNGS JOB PERFOR31ANCE MEASURE l INITIAL CONDITIONS  ;

i INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

• Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

2 The examiner will provide all responses and indications required from outside the control room.

• Inform the control room staff of any discovered deficiencies.

• You may use any source ofinformation normally available.

INITIATING CUE:

• The CRS has directed you to initiate a containment vent in accordance with  ;

400P-9CP01, Containment Purge System. An area operator is standing by in i the RCA to assist you, e RU-34 is available.

• All prerequisites are complete.

SAFETY CONSIDERATIONS:

i

• None l

I 1

l l

1 OTG-02 Rev. 0 8 i

-. ._ . ... __ . . ___ .~ - ._ .. . .. - - ._ - - - . - -. -. .- -

k SB002-J-C/R-00" PVNGS JOB PERFOIGIANCE MEASURE JPM BASIS INFORMATION TASK: 1250280401 Perform actions to reset SIAS TASK STANDARD: SIAS initiation and actuation relays reset on all four PPS channels.

K/A: 013 A4.02 K/A RATING: RO: 4.3 SRO: 4.4 K/A: K/A RATING: RO: SRO APPLICABLE POSITION (S): RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

41 AO-lZZ27, Inadvenent SIAS and/or CIAS SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT APPROVAL -

DEVELOPER: J. K. Aronson TECH REVIEW: d ,l//d/f*/

REVISION D_ ATE: 01/17/97 APPROVAL:

TESTING METHOD

~

] ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT _ _ _ .

]

TESTING METHOD: SIMULATE PERFORM i -

EVALUATION i

l EXAMINEE NAME:

~

(print)

EVALUATOR NAME:

j (print)

! SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE 010-04) i i.

OTG-02 Rev. 0 1 W:\ WORD \SB002CR. DOC cgc 01/03/97 4

4 l

A S B002-J-C/R-00

PVNGS JOB PERFOR31ANCE MEASURE i

1. SIMULATOR SETUP: 1 A. IC# (any at power IC)

B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

)

EVENT COMMAND DESCRIPTION ,

1. l 1.

3.

4.

C. SPECIAL INSTRUCTIONS: _

• Manually initiate SIAS on all four ESFAS channels from B05.

• Silence alarms after equipment start.

~

D. REQUIRED CONDITIONS:

SIAS "A" and SIAS "B" actuated with pressurizer pressure abose current SIAS setpoint and containment pressure below 3.0 psig.

2. SPECIAL TOOLS / EQUIPMENT:

-

• PPS initiation reset panel key.

I l

w OTG-02 Rev. 0 2 l

i

C s

SB002-J-C/R-00" PVNGS JOB PERFOIOfANCE SIEASURE TASK CONDITIONS INFOIO1ATION PRESENTED TO EXAMINEE: _

SPECIAL CONSIDERATIONS:

Operation ofin-plant equipment is to be SI51ULATED ONLY, DO NOT OPERATE any equipment.

+ inform the control room staff of any discovered deficiencies.

You may use any source ofinformation normalty available.

INITIATING CUE:

An inadvertent SIAS was received due to testing. The CRS directs you to reset the SIAS signalin accordance with 41 AO-lZZ28, Inadvertent SIAS a6d/or CIAS.

Other operators are restoring actuated equipment.

INFORMATION FOR EVALUATOR'S USE:

_ t Denotes Critical Step 1

' At the discretion of the Examiner /Evaluater, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shallbe i terminated when the Examinee has verbalized completion of the JPM. -

4 =

The complete load shed and manual sequencing ofloads will not be performed.

Any step marked UNSAT requires comments.

l If this is the first JPM of the set then ensure the examinee has been briefed LAW OTG-01._

Step sequence is not critical unless noted or will prevent achieving the task standard. l Notify unit Shift Supervisor ofin-plant JPM performance.

At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Elements and Standards are met or adequate time has been allowed to complete the JPM. It shall be

, terminated when the Examinee has verbalized completion of the JPM.

SAFETY CONSIDERATIONS:

, . None

%c l

. OTG-02 Rev. 0 3 e

4 "

S11002-J-C/R-@f PVNGS JOB PERFOR3IANCE SIEASURE STEP ELEMENT STANDARD

1. Obtain procedure 41 AO-lZZ28 Examinee obtains procedure.

Inadvertent SIAS and/or CIAS.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

2. Unlock the Initiation Reset Panel for Examinee unlocks the Initiation Reset channel "A" Panel for channel "A".

NOTE: JPM steps 2-17 may be performed for any channel order. All steps must be completed for each channel.

SAT UNSAT (UNSAT requires comments)

~~

STEP ELEMENT STANDARD

3. Press the SIAS reset pushbutton. Examinee depresses the SIAS reset -

pushbutton. I SAT UNSAT (UNS AT requires comments) -

CO51MENTS:

OTG-02 Rev. 0 4

i SB002-J-C/R-00

PVNGS JOB PERFOR31ANCE SIEASURE STEP ELEMENT STANDARD

4. Check the SIAS Initiation Signal Examinee checks the SIAS Initiation indicating lamp illuminates on the PPS Signal indicating lamp is illuminated.

Status Panel.

If requested CUE: SIAS indicating lamp channel "A" is illuminated.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANL)ARD

5. Lock the Initiation Reset Panel for Examinee locks the Initiation Rest Panel j channel "A" for panel "A" SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

6.

• Unlock the Initiation Reset Panel for, . ,

Examinee unlocks the Initiation Reset channel "B" Panel for channel "B" SAT UNSAT (UNSAT requires comments) 1 STEP ELEMENT STANDARD l

7. * - Press the SIAS reset pushbutton. Examinee depresses the SIAS reset

~

pushbutton.

SAT 'UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

8. Check the SIAS Initiation Signal Examinee checks the SIAS Initiation indicating lamp illuminates on the PPS Signal indicating lamp is illuminated.

Status Panel.

If requested CUE: SLAS indicating lamp channel "B" is illuminated.

SAT UNSAT (UNSAT requires comments)

COSIMENTS:

OTG-02 Rev.0 5

S11002-J-C/R-00

• 4 PVNGS JOB PERFOR3IANCE SIEASURE a

4 STEP ELE 31ENT STANDARD '

9. Lock the Initiation Reset Panel for Examinee locks the initiation Rest Panel channel "B". for panel "B" SAT UNSAT (UNSAT requires comments) 9 STEP ELE 31ENT STANDARD

10. Unlock the Initiation Reset Panel for 1

Examinee unlocks the Initiation Reset channel "C" Panel for channel "C" SAT UNSAT (UNSAT requires comments)

STEP ELE 51ENT STANDARD ,

11. Press the SIAS reset pushbutton. Examinee depresses the SIAS reset pushbutton.

SAT UNSAT (UNSAT requires comments)_ ,

STEP ELE 31ENT -

STANDARD 1

12. Check the SI AS Initiation Signal Examinee checks the SIAS Initiation Signal indicating lamp illuminates on the PPS indicating lamp is illuminated.

Status Panel. -

i If requested CUE: SIAS indicating lamp

_ channel "C" is illuminated.

SAT UNSAT (UNSAT requires comments)

~

STEP ELE 31ENT STANDARD

13. Lock the Initiation Reset Panel for Examinee locks the initiation Rest Panel f channel"C" for panel "C".

~

SAT i UNSAT (UNS AT requires comments) i COM5fENTS:

I OTG-02 Rev. 0 6

l l

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

SB002-J-C/R-00

PVNGS JOB PERFOR31ANCE 31EASURE STEP ELEMENT STANDARD

14.

• Unlock the initiation Reset Panel for Examinee unlocks the initiation Reset l channel "D" Panel for channel "D" '

SAT UNSAT (UNSAT requires comments)

_ i l

STEP ELEMENT STANDARD

15. Press the SIAS reset pushbutton. Examinee depresses the SIAS reset 1 pushbutton.

SAT UNSAT (UNSAT requires comments) l STEP ELEMENT STANDARD -

16. Check the SIAS Initiation Signal Examinee checks the SIAS Initiation i indicating la.mp illuminates on the PPS Signal indicating lamp is illuminated. '

Status Panel. _

If requested CUE: SIAS indicating lamp channel "D" is illuminated.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD -

t

17. Lock the Initiation Reset Panel for Examinee locks the initiation Rest Panel channel "D" for panel "D".

SAT l UNSAT _LUNSAT requires comments)

COMMENTS: I e

t i

e 3

'W OTG-02 Rev. 0 ,

7

.-g

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

SB002-J-C/Rd PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD

18. Press the SIAS LOCKOUT RESET Examinee depresses the SIAS LOCKOUT pushbutton at the "A" auxiliary relay RESET pushbutton.

cabinet.

NOTE: JPM steps 18-23 may be performed for any channel order. All steps must be completed for each channel.

SAT ____ UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

19. Check the red ON light above the reset Examinee checks the indicating lamp is pushbutton is illummated.

illuminated.

~

If requested CUE: Red indicating lamp is illuminated.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT - STANDARD

20. Check the SIAS leg 1-3 Actuation Examinee checks the SIAS leg 1-3 lights ~

. Signal lights are illuminated for are illuminated.

channels "A" and "B" PPS Status -

Panels. If requested CUE: SIAS leg 1-3 lights are i!!uminated on channels "A" and "B" PPS Status Panels. -

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

21. Press the SIAS LOCKOUT RESET Examinee depresses the SIAS LOCKOUT pushbutton at the "B" auxiliary relay RESET pushbutton.

cabinet. ,,

SAT UNSAT (UNSAT requires comments)

COMMENTS:

1 J

l OTG-02 Rev. 0 8  ;

SB002-J-C/R-00" PVNGS JOB PERFORSIANCE SIEASURE STEP ELEMENT STANDARD

22. Check the red ON light above the reser Examinee checks the indicating lamp is pushbutton is illuminated. illuminated.

~

If requested CUE: Red indicating lamp is illuminated.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

23. Check the SIAS leg 2-4 Actuation Examinee check _s the SIAS leg 2-4 lights Signal lights are illeminated for - are illuminated.

channels "A" and "B" PPS Status Panels. If requested CUE: SIAS leg 2-4 lights

~~

are illuminated on channels "A" and "B" PPS Status Panels. -

Inform CUE: Another RO will perform

- indepent verification.

SAT UNSAT (UNSAT requires comments)

' ~

NORMAL TERMINATION POINT J

COMMENTS:

OTG-02 9ev. 0 9

I $

SB002 J-C/R-00

PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 02/19/97 6 New i

l c _ .

~

i l l REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

l 1. Vendor reference document upgrade l -- 2. j Plant modification (include number) _

3. Procedure upgrade -

4. Internal or External Agency Commitment (indicate item number) i j

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments) t i

i i

i l

b r

A I v-

! i l

OTG-02 Rev. 0 10 i

k

SB002-J-C/R-00 '

PVNGS JOB PERFORMANCE MEASURE i

INITIAL CONDITIONS '

1 l INFORMATION PRESENTED TO EXAMINEE:  !

I i l l SPECIAL CONSIDERATIONS: l Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

4

- . Inform the control room staff of any discovered deficiencies.

=

j You may use any source ofinformation normally available.

INITIATING CUE: -

An inadvertent SIAS was received due to testing. The CRS directs you to reset the SIAS signal in accordance with 41AO-1ZZ28, Inadvertent SIAS and/or CIAS.

. Other operators are restoring actuated equipment.

i SAFETY CONSIDERATIONS:

• None -

i

~

?

f 1

i i

,i i

l' OTG-02 Rev. 0 11

4 SG010-J-PLT-13" PVNGS JOB PERFOR.\LWCE MEASURE l

JPM BASIS INFORMATION i

i TASK:- 1230010401 Perform Manual Operation of Air Operated Valves i TASK STANDARD: The operator places ADV SGB-HV 178 in manual and throttles open the valve per i 410P-LOP 01 K/A: 3.4-039- A4.08 K/A RATING: RO: 3.0 SRO: 3.1  !

} K/A: K/A RATING: RO: SRO:

l .iPPLICABLE POSITION (S): AO/RO/SRO VALIDATION TIME: 15 min j~

REFERENCES:

4 IOP-LOP 01, Manual Operation of Air Operated Valves i SUGGESTED TESTING ENVIRONMENT: SIMULAT.OR PLANT X l I

APPROVAL __

DEVELOPER: W. Hendricsen TECH REVIEL 4 -

REVISION DATE: 01/22/97 APPROVAL:

TESTING METHOD

~ --.

ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION EXAMINEE NAME: -

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTORY ,

Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE OTG-04)

OTG-02 Rev. 0 1 J.\OPSTRNG\JPM\SG010 PLT. DOC wth 01/22/97 m _.

'e SG010-J-PLT-13" PVNGS JOB PERFORMANCE MEASURE

1. SIMULATOR SETUP:

A. IC#: N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION 1.

2.

3.

4.

C. SPECIAL INSTRUCTIONS:

D. REQUIRED CONDITIONS:

2. SPECIAL-TOOLS / EQUIPMENT:

-~

OTG-02 Rev. 0 2

, ,, m e me

1 d

SG010-J-PLT-13" PVNGS JOB PERFOR31ANCE MEASURE TASK CONDITIONS i

INFORMATION PRESENTED TO EXAMINEE: -

1 i

SPECI AL CONSIDERATIONS.

Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any l equipment.  !

l

. Inform the control room staff of any discovered deficiencies. i

. You may use any source ofinformation normany available.

. You are to demonstrate how procedare steps are performed.

. Independent verification is waived for this JPM.

~

INITIATING CUE:

A plant shutdown is in progress. The Plant is in Mode 3 with the RCS at 572 degrees and 2250 psia. SBCS has just become unavailable. Main Steam Safeties are lifting.

The CRS directs you to manually open the ADV locally for Steam Generator #1,line 2, I

_ SGB-IIV-178,in accordance with procedure 410P-LOP 01, Appendix B. j

. Preiequisites are satisfied.

INFORMATION FOR EVALUATOR'S USE: _

• Denotes Critical Step

. At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is rnet or adequate time has been allowed to complete the JPM. It shall be terminated when the Examiriee has verbalized completion of the JPM. -

. Any step marked UNSAT requires comments.

l .

If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

l .

Step sequence is not critical unless noted or will prevent achieving the task standard.

. Notify unit Shsft Supervisor of in-plant JPM performance.

Provide Examinee with copy of appropriate section of Appendix B of 410P-LOP 01 after providing CUE.

t S AFETY CONSIDERATIONS:

I Possible operation of equipment in case of Unit Trip.

4 OTG-02 Rev. 0 3

SG010-J-PLT-13" PVNGS JOB PERFOR31ANCE 31EASURE STEP ELEMENT STANDARD

1. Close SG-V963 (Air Supply Valve to Examinee simulates closing SG-V963.

SGB-HV-178 and SGB-HV-185).

NOTE: Located South ADV Rm 140' MSSS.

If requested CUE: Valve is closed.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD  !

2. Ensure Closed SG-V353, filter bypass

~ Examinee simulates check closed SG-V353.

valve.

If requested CUE: Valve is closed.

l SAT UNSAT (UNSAT requires comments) '

STEP ELEMENT STANDARD

3. Unlock and Close SG-V354 Accumulator Examinee Simulates unlocking and closing Si).

_ Nitrogen valve.

V354 (located on catwalk next to ADV).

If requested CUE: Valve is closed.

SAT UNSAT (UNS AT requires comments) -

STEP - ELEMENT STANDARD

4. Unlock and Open SGB-HCV 178 - _ Examinee simulates unlocking and opening equalizing valve (betWen the piston sides). SGB-HCV-178 equalizing valve.

If requested CUE: Valve is open.

SAT UNSAT (UNSAT requires comments) I l

COMMENTS:

4

4 SG010-J-P1,T-13" PVNGS JOB PERFOR31ANCE 31EASURE STEP ELEMENT STANDARD

5. Unscrew and remove the clevis from the Examinee simulates unscrewing and removing manual override shaft. clevis.

If requested CUE: Clevis is removed.

SAT UNSAT (UNSAT requires comments) l STEP ELEMENT STANDARD I

6. Unlock handwheel and turn CLOCKWISE, Examinee simulates unlocking handwheel and i lowering the manual override shaft to lowering shaft to expose the actuator shaft I expose the actuator shaft above the manual above the manual override shaft. -

override shaft. _

l If requested CUE: The actutfor shaft is showing above the manual everride shaft.

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDAIU)

7. Slide the clevis onto actuator shaft and Examinee simulates sliding clevis on actuator

~

l

. ensure it is engaged. shaft.

~

The clevis is securely engaged ifit reaches the end of the clevis slot.

If requested CUE: The clevis is engaged on to the actuator shaft. j i

Inform CUE: The Control Room directs you to open the valve three (3) turns SAT UNSAT (UNSA quires comments) l CO3151ENTS:

5

l4 SG010-J-PLT-13" PVNGS JOB PERFO.DIANCE MEASURE STEP ELEMENT STANDARD

8. Rotate handw heel COUNTER- Examinee simulates turnir.g valve handwheel 3 CLOCKWISE to open. turns counter clockwise.

1 If proper action is taken, If requested CUE: Valve is open.

J 5 Inform CUE: The Control Room directs you to leave SG B-flV-178 in the current position.

i SAT UNSAT (UNSAT requires comments) i NORMAL TERMINATION POINT 3 .

i -

t l

4 J

4 i

l COMMENTS:

i l ,

i I

I 6

i

4

' ' ~ ~

• SG010-J-PLT-13" PVNGS JOB PERFOR31ANCE SIEASURE RECORD OF REVISIONS REVISION P EVISION REASON NUMDER DATE~ REVISED COMMENTS 13 01/22/97 6 New format per OTG-02, Changed the task standard to better describe the JPM requirements l

I l

~

\

REASON REVISED Enter the numbers correspondirig to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

I. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

OTG-02 Rev. 0 7 i

l

. . . _ . _ . _ _ . . . _ . = . _ _ _ _ _ _ _ . _ . _ _ . . _ . _ . _ . _ _ _. . __ _ _ _ _

..s e

SG010-J-PLT-13" PVNGS JOB PERFOR31ANCE MEASURE f INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

l SPECI AL CONSIDERATIONS:

Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment, a Inform the control room staff of any discovered deficiencies.

You may use any source ofinformation normally available.

• Independent verification is waived for this JPM.

INITIATING CUE: --

. A plant shutdown is in progress. The Plant is in Mode 3 with the RCS at 572 degrees and 2250 psia. SBGS hasjust become unavailable. Main Steam Safeties are lifting. The CRS directs you to manually open the ADV locally for Steam Generator #1,line 2, SGB-IIV-178,in accordance with procedure 410P -

IOP01, Appendix B.

SGB-IIV-178 is in the condition listed under Appendix B p~rerequisites SAFETY CONSIDERATIONS: - l e

Possible operation of equipment in case of Unit Trip.

l' l

l I

l 4

4 i

t l

OTG-02 Rev. 0 8 i

r 1 - CII0ll-J-PLT-05' '

PVNGS JOB PERFOR51ANCE MEASURE JPM BASIS INFOIO1ATION

, TASK: 1250440301 Perform Primary Operator Duties to Stabilize the Plant for Control _ Room Fire TASK STANDARD: CHN-HV-536 is de-energized and open to supply a borated flowpath to the charging Pumps j K/A: 4.2-068- AA2.02 K/A RATING: RO: 3.7 SRO: 4.2 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION (S): AO/RO/SRO VALIDATION TIME: 15 min

REFERENCES:

41 AO-lZZ44 Control Room Fire 42AO-2ZZ44 Control Room Fire _

43AO-3ZZ44 Control Room Fire SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X ,

APPROVAL DEVELOPER:

REVISION DATE: 02/12/97 W. Hendricsen TECH REVIEW: [

APPROVAL:

TESTING METHOD l ACTU L TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM -

_ EVALUATION EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print)

SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO (SEE OTG-04) l I

OTG-02 Rev. 0 1 l

J \OPSTRNGUPMTCH0llPLT DOC cge 02/13/97

r C11011-J-PLT-05' PVNGS JOB PERFOIDIANCE SIEASURE I. SISIULATOR SETUP:

A. IC#: N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION 1.

2.

3.

4.

C. SPEC. IAL INSTRUCTIONS:

• NONE D. REQUIRED CONDITIONS:

• NONE

2. SPECIAL TOOLS / EQUIP 51ENT: ~

• NONE OTG-02 Rev. 0 2

CII011-3-PLT-05' PVNGS JOB PERFORafANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECI AL CONSIDERATIONS:

Operation ofin-plant equipment is to be SI51ULATED ONLY, DO NOT OPERATE any equipment.

Inform the control room staff of any discovered deficiencies.

You may use any source ofinformation normally available.

Comply with the REP. Do not-enter contaminated, airbome, or high radiation areas. You may be required to discuss actions to be taken.

• Independent verification is waived for tIlis JPM.

INITIATING CUE: _

~

The control room has been evacuated due to a fire. -

.You have been directed by the CRS to perform the Miscellaneous AO duties that are necessary to align a borated water source to-the charging pump via CIIE-HV-5% per 4XAO-XZZ44, Control Room Fire, Appendix E.

INFORMATION FOR EVALUATOR'S USE:

• Denotes Critical Step

=

At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbaliiid completion of the JPM.

Any step marked UNS AT requires comments.

. Comply with REP requirements, if not, failure of JPM.

This JPM may be conducted using all Unit's procedures.

If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01. l l

Step sequence is not critical unless noted or will prevent achieving the task standard.

Notify unit Shift Supervisor ofin-plant JPM performance.

SAFETY CONSIDERATIONS:

. NONE 1

OTG-02 Rev. 0 3

CII0Il-J-PLT-05' PVNGS JOB PERFORMANCE MEASURE 4 STEP ELEMENT STANDARD l.

Obtain a portable lantern from the Examinee simulates obtaining a lantern from E-

Emergency Equipment Cabinet, FPN-C02, located in the "B" switchgear room ,

4 E-FPN-C02. NW comer.

Inform CUE: DO NOT break the seal on E-

) FPN-C02

] If requested CUE: You are in possession of a portable lantern.

SAT UNSAT (UNSAT requires comments) -

4

~

STEli ELEMENT STANDARD

2. Open breaker NHN-M7209, Power Supply Examinee simulates opening breaker NHN-to CHN-HV-536. M7209. -

NOTE: Located at 120' Aux Bldg., East corridor.'

If requested CUE: The red and green lights are OFF on breaker NHN-M7209.

SAT UNSAT (UNSAT require:. comments) i ~

STEP ELEMENT STANDARD -

j 3.

• Ensure CHN-HV-536 is open, RWT Examinee simulates opening CHN-HV-536.'

Gravity Feed to charging pumps suction

valve.

NOTE: Located at 70' Aux. Bldg. BAMP Room.

If requested CUE: CHN-HV-536 is open.

SAT UNSAT (UNSAT requires comments)

W

, COMMENTS:

i i

i OTG-02 Rev. O 4

CH011-J-PLT-05' PVNGS JOB PERFOR31ANCE SIEASURE i STEP ELEMENT STANDARD

4. Notify the Aux Bldg AO that CHN-HV- Examinee simulates notifying the Aux Bldg AO 536 is open. that CHN-HV-536 is open.

When requested CUE: Aux Bldg AO is aware that CHN-HV 536 is open.

1 NOTE: Examinee can simulate notification using a radio or phone (ext.1258). {

SAT UNSAT (UNSAT requires comments)  !

1 I

NORMAL TERMINATION POINT _

~

b.

i l

I l

l CO31MENTS: j l

OTG-02 Rev. 0 5

l

~

CII011-J-PLT-05' PVNGS JOB PERFORMANCE MEASURE RECORD OF REVI3!GNS REVISION REVISION '

REASON NUMBER DATE REVISED COMMENTS 03 10/10/96 6 New Format per OTG-02 04 01/10/97 6 Changed Task Standard 05 02/12/97 6 Change the initiating cue to better define when the task would be complete.

~

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

l. Vendor reference document upgrade

2. - Plant modification (include number)

3. Procedure upgrade 4 Internal or Extemal Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments) l OTG-02 Rev. 0 6

4 o 1

'_ CH011-J-PLT-05' i PVNGS JOB PERFORMANCE MEASLTE i

3 INITIAL CONDITIONS i <

' INFORMATION PRESENTED TO EXAMINEE

_

i SPECI AL CONSIDERATIONS:

]

. Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT 1

} OPERATE any equipment.

)

l

• Inform the control room staff cf any discovered deficiencies. I

- 1 You may use any source ofinformation normally available. -

1 i e Comply with the REP. Do not enter contaminated, airborne, or high radiation areas.

j You may be required to discuss actions to be taken.

• Independent verification is waived for this JPM.

1 l

l INITIATING CUE-l e The control room has been evacuated due to a fire.

j- .s .

. You have been directed by the CRS to perform the Miscellaneous AO duties l

, that are necessary to align a horated water source to the charging pump via a

CHE-HV-536 pef 4XAO-XZZ44, Control Room Fire, / ppendix E.

]

l SAFETY CONSIDERATIONS:

? . NONE i

i

+

k i

i ,

i l

j 1

4

'v 4

OTG-02 Rev. 0 7

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

i

. t DG007-J-Pl.T- 10 j PVNGS JOB PERFOR.\ LANCE NIEASURE i

JPM BASIS INFOllMATION l, TASK: 1240025301, Restore DG "B" to PBB-504 .

{ TASK STANDARD: Diesel Generatar 'B' is runnina. '

j K'A: EPE EA1.02 K!A RATING: RO: 4.3 SRO: 4.4 1 K/A: EPE EAl.06 K/A RATING: RO: 4.1 SRO: 4.5 j APPLICABLE POSITION (S): RO VAllDATION TIM E: 20 min.

REFERENCES:

40EP-9E010, Appendi) 56, Restore DG B to PBB-SO4 i SUGGESTED TESTING ENVIRONNtENT: SINIULATOR PLANT X i _

l APPitOVAL l DEVELOPER: W. K. Hendricsen TECil REVIEW: --

REVISION DATE: 01/29/97 APPROVAL: b g 1 (

TESTING METIIOD

~

! \

j ACTUAL TESTING ENVIRONNIENT: Sl\tULATOR PLANT I

~

! ~

4 TESTING NtETHOD: SINIULATE PERFOR\1

}

i i EVALUATION -

j EXA.\llNEE NANIE:

! (print)

EVALUATOR NAME:

1 -

j (print) 4 j SATISFACTORY UNSATISFACTORY j Time Start Time Stop 4

i REMEDI AL TRAINING REQUIRED? YES NO l (SEE OTG-04)

F i

i i

4 i

i l

OTG-02 Res . 0 1 e

J 'OPSTP3GUPM DG007 PLT DOC wkh 2!00/97 1

1

DG007-J-PLT-10 PVNGS JOB PERFOR31ANCE 31EASURE

1. SISIULATOR SETUP:

A. IC# : NA B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION

1. NA 2.

3.

l C. SPECIAL INSTRUCTIONS:

• NA -

D. REQUIRED CONDITIONS: _

e NA

2. SPECIAL TOOLS /EQUIPMEN I: -

• None -

N ase W

OTG-02 Rev. 0 2

I DG007-J-PLT-10 PVNGS JOB PERFOR31ANCE SIEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

Operation ofin-plant equipment is to be Sl>IULATED ONLY, DO NOT OPERATE any equipment.

. Inform the control room staff of any discovered deficiencies.

You may use any source of information normally available. -

~

INITIATING CUE: -

The plant has experienced an electrical blackout condition. The emergency diesel generators are not running: The Shift Supervisor has directed you to recover and start Emergency Diesel Generator B using 40EP-9EO10, Standard Appendices, Appendix 56.

INFORMATION FOR EVALUATOR'S USE:  :

~

• Denotes Critical Step

- )

At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate timT has been allowed to complete the JPM. It shall be j terminated when the Examinee has verbalized completion of the JPM. -

. Any step marked UNSAT requires comments.

If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.

Step sequence is not critical unless noted or will prevent achieving the task standard.

Notify unit Shift Supervisor ofin-plant JPM performance. 1

. Do not allow any operation of equipment.

SAFETY CONSIDERATIONS:

When checking / identifying equipment on the diesel avoid placing yourself or examinee in precarious positions. Use available drawings of equipment as appropriate to discuss operation where possible (eg - intake air butterfly valve).

l l

l OTG-02 Rev.0 3 1

1 DG007-J-PLT-10

{

PVNGS JOB PERFORNIANCE SIEASURE STEP ELEMENT STANDARD

1. Determine annunciator panel status. Examinee observes annunciator panel.

1

)

. Inform CUE: Annunciator panel indicates "OVERSPEED ENGINE".

(DGB-07A)

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

2. PEu "STOP" on DGB-liS-30 "DGB Examinee simulates pressing DGB-HS-30.

Emergency Stop" -

SAT UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD '

3. Press the plunger on DGB-UV-238 Examinee simulates pressing plunger on DGB-l "overspeed trip valve" UV-238.

NOTE: Located generator platform southeast -

of the diesel.

~

SAT UNSAT (UNSAT requires comments)

CO31MENTS:

5 l

1 l

l

]

I i

i 1

DG007-J-PLT-10 -

PVNGS JOB PERFORMANCE MEASURE t

l STEP ELEMENT STANDARD 1

4. Reset the intake air butterfly valve; Examine- locates and simulates / explains Ensuring handle is latched.

t resetting Intake Air Butterfly Valve by referring ,

to Attachment 56-A. (Resetting intake air

butterfly valve). -

1, When the Examinee has identified the valve i and verified per Attachment 56-A Inform

} ,

CUE: Intake Air Butterfly Valve is reset and  ;

( handle is latched.

- SAT UNSAT (UNSAT requires comments) i j STEP ELEMENT STANDARD

5. Inform the responsible operator that the --

D/G may start.

Examinee simulates informing responsible operator that "B" D/G may start. l l

If Requested CUE: Control Room  ;

acknowledges Diesel Generator "B" may sta rt. ..

SAT UNSAT (UNSAT requires comments) l STEP ELEMENT STANDARD

6. h " Reset" on DGB-HS-30 "DG B Examinee simulates pressing DGB-HS-30.

Emergency Stop" to start the diesel {

generator. If Requested CUE: "B" diesel generator is  !

running. '

SAT UNSAT (UNSAT requires comments)

COMMENTS:

5 l

_ m__. . - _ _ _

l I

DG007-J-PLT-10 PVNGS JOB PERFORMANCE MEASURE  :

1 l

STEP ELEMENT STANDARD 7, Inform the responsible operator that this if Requested CUE: Control room is appendix is complete.

informed that Appendix 56 is complete.

SAT UNSAT (UNSAT requires comments)

NORMAL TERMINATION POINT j

' ~~

COMMENTS:

i 6

DG007-J-PLT-10 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 09 08/30/96 6 New Format 10 01/29/97 6 Re-formatted the cues to "If Requested" or " Inform", made resetting the air intake butterfly valve a critical step.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

___ l. Vendor reference document upgrade

2. Plant modification (include number)

~

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

OTG-02 Rev. 0 7

DG007 J-PLT-10 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS

_INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

. Inform the control room staff of any discovered deficiencies.

You may use any source ofinformation normally available.

INITIATING CUE: -

The plant has experienced an electrical blackout condition. The emergency diesel generators are not running. The Shift Supervisor has directed you to recover and _

start Emergency Diesel Generator B using 40EP-9E010, Standard Appendices, Appendix 56. .

SAFETY CONSIDERATIONS:

When checking / identifying equipment on the Diesel avoid placing yourself or examinee in precarious positions. Use available drawings of equipment as appropriate to discuss operation where possible (eg - intake air butterfly valve). _

OTG-02 Rev. 0 8 -

v j e.es !

t

.~ DG009J-PLT-00'*

PVNGS JOB PERFORMANCE MEASURE JPM BASIS INFORMATION TASK: 1250440201 Perform Event Control Actions for a Control Room Fire.

TASK STANDARD: Diesel Generator *B" supplying loads on PBB-SO4.

K/A: 4.2-068 'AAl.10 K/A RATING: RO: 3.7 SRO: 3.9 K/A: 4.2-068-A Al.31 K/A RATING: RO: 3.9 SRO 4.0 i VALIDAllON TIME: 25 min.

APPLICABLE l OSITION(S): AO/RO/SRO TIME CRITICAL - 15 MINUTES FROM THE TIME D/G B" IS STARTED UNTIL SP

. B"1S STARTED

REFERENCES:

'41 AO-lZZ44, Control Room Fire,42AO 2ZZ44, Control Room Tire i

{

! 43AO 3ZZ44, Control Room Fire l SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X APPROVAL DEVELOPER: J. K. Amnson TECliREVIEW: 6t<//4

] REVISION DA E: 01/03/97 APPROVAL:

TESTING METHOD U l:

ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT 4

TESTING METHOD: SIMULATE PERFORM I

6 EVALUATION i

I EXAMINEE NAME:

(print)

EVALUATOR NAME:

(print) 4 SATISFACTORY UNSATISFACTORY l Time Start Time Stop REMEDIAL TRAINING REQUIRED? YES NO "'

(SEE OTO-04)

OTO-02 Rev, O' 1

, W;iWORDtG009 PLT. DOC esc 01/03/97 I

I

I e . v e.

! i l

• l

i DG009-J PLT-00

i PVNGS JOB PERFORMANCE MEASUPE l

1 i I

! INITIAL CONDITIONS i i

l l  !

INFORMfTION PRESENTED TO EXAMINEE:

i SPECI AL CONSIDERATIONS:

Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

• Enform the control room staff of any discovered deficiencies.

[ou may use any source ofinfonnation normally available.

INITIATING CUE:

' he control room has been evacuated due to a fire.

There has been a loss of offsite power. No automatic start and loading of the Emergency Diesel Generators, or load shed has occurred.

l e

The CRS directs you to complete Appendix E of 4XAO-XZZ44 as the D/G AO to manually start and Iond the "B"lhesel Generator.

e ssume you have a portable lantern.

SAFETY COfSIDERATIONS:

• None THIS JPM CONTAINS A TIME CRITICAL ELEMENT.

)

i l

l I

l OTG-02 Rev. 0 14 i

r.04 0

_, DG009-J. PLT-00

PVNGS JOB PERFORMANCE MEASURE

1. SIMULATOR SETUP: '

A. jC# : N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNC110NS: ,

EVENT COMMAND DESCRIPTION I 1.

2.

3.  !

4.

C. $PECIALINSTRUCTIONS:

i

• None D. REQUIRED CONDITIONS:

• None

2. SPECIAL TOOLS / EQUIPMENT:

• None l

l

i l

l

\

OTG-02 Rev. 0 2

P.U5 0

DG0094-PI,T-00'*

PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS l INFORMATION PRESENTED TO EXAMINEE:

, SPECIAL CONSIDERATIONS:

. Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

• Inform the control room staff of any discovered deficiencies.

. You may use any source ofinfonnation nonnally available. l INITIATING CUE:

• The control room has been evacuated due to a fire.

• There has been a loss of offsite power. No automatic start and loading of the

Emergency Diesel Generators, or load shed has occurred, l e The!CRS directs you to complete A pendix E of 4XAO-XZZ44 as the D/G AO to manually start and load the "B" DiesefCenerator.

e Assdme you have a portable lantern.  !

. INFORMATION FOR EVALUATOR'S USE:

• Denotes Critical Step s At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or ndequate time has been allowed to complete the IPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

. The complete load shed and manual sequencing ofloads will not be performed, a e Any step marked UNSAT requires comments.

If this is the first JPM nf the set then ensure the examinee has been briefed IAW OTG-01.-

Step; sequence is not critical unless noted or will prevent achieving the task standard.

-

• Notify unit Shift Supervisor ofin-plant JPM performance.

• At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Elements and Standards are met or adequate time has been allowed to complete the JPM. It shall be terminated when the Ev9minee has verbalized completion of the JPM.

SAFETY CONSIh)ERATIONS:

• None OTG-02 Rev.0 3 i

r . e e, c

DG0094 PLT-0(/*

PVNGS JOB PERFOIO!ANCE MEASURE STEP EL,EMENT STANDARD

1. Evaluate the Diesel Generator Status and Examinee obtains 41 AO lZZ44 and determines GO TO the applicable step per the given step 1.8 is the applicable step per Appendix "E" conditions by addressing the Table in Section 1.4 of 41 AC4ZZ44, Appendix E NOTE: The "B" Diesel Generator is not running and there is a Loss of Offsite Power.

SAT UNSAT __

(UNSAT requires comments) i STEP ELEMENT STANDARD

2.

• Place J DGB-HS-2A to local. Examinee simulates placing J-DGB-HS-2A in local, r

If requested CUE: J-DGB-HS 2A is in local.

SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD

3.

• Pl5ce J-DGB-HS-2B to local. Examinee simulates placing J.DGB41S-2B in local.

If requested CUE: J-DGB-HS-2 B is in local.

SAT i UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

4. Place E-PEB-HS-2 to local Examinee simulates placing E-PEB HS-2 in local.

l If requested CUE: E-PEB-HS-2 is in local.

SAT UNSAT (UNSAT requires comments)

COMMENTS:

i i

i i

OTG-02 Rev. O, i 4 1

- _ _ - _~ . _ . __.

r.or t

DG009-J. PLT-00" PVNGS JOB PERFORMANCE MEASURE l

STEP ELEMENT SI ANDARD

• Place J ilDB-IIS-14 A to local Examinee shnulates placing J ilDB.IIS-14A in 5.

local. i If requested CUE: J-IIDH-IIS-14A is in local, i SAT UNSAT (UNSAT requires comments)

S'IEP } LEMEN I STANDARD

6. Place J DFB-IlS-22C to local.

Examinee shnulates placing J DFB-HS 22C in local.

If requested CUE: J-DFB-IIS-22C is in local.

SAT UNSAT (UNSAT tvquires comments)

STEP ELEMENT STANDARD

7.

• Pldre disconnect (CS-3)in LOCAL & Examinee simulates placing disconnect (CSJ)

Brhker OPEN for PBB-504B. D,G B in LOCAL and the breaker handswitch (CS-1) breaker. for PBB-504B verified OPEN.

If requested CUE: PBB-504B disconnect is in LOCAL, breaker indicates open by green light ON, red light OFF.

SAT i UNSAT (UNSAT requires comments) i, I

COMMENTS: !

i t

I i

OTG-02 Rev,0 f

' 5 t

e.ua

~

DG0094-PLT-00 #*

PVNGS JOB PERFORMANCE MEASURE STEP ELE MENT STANDARD 8,

• Place disconnect (CS 3)in LOCAL & Examinee simulates placing disconnect (CS-3)

Breaker OPEN for PBB 504C, Spray Pond in LOCAL and the breaker handswitch (CS 1)

Pump B breaker. for PBB-504C verified OPEN.

If requested CUE: PBB-SO4C disconnect is in 4 t LOCAL, breaker indicates open by green light ON, red light OFF.

SAT ' .UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

9.

• Examinee simaistes placing disconnect (CS-3)

Plice disconnect (CS-3)in LOCAL &

lirkaker OPEN for PDB-504G, Ess Chiller in LOCAL and the breaker handswitch (CS 1)

B breaker. for PBB-5040 wrified OPEN.

i If requested CUE: PBB-504G disconnect is in LOCAL, breaker indicates open by green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments) t l

STEP ELEMENT STANDARD

10. Pl$ce disconnect (CS-3)in LOCAL & Examinee simulates plachg disconnect (CS-3)

Brhaker OPEN for FBB SO4K, PBB-SO4 in LOCAL and the breaker handswitch (CS-1)

Norm Supply breaker. for PBB.SO4K verified OPEN.

If requested CUE: PBB-504K disconnect is in LOCAL, breaker indicates open by green

light ON, red light OFF.

SAT  ! UNSAT (UNSAT requires comments) 4 COMMENTSt '

4 i

i l

t i

OTG-02 Rev. 0 6

e.ut o

l l

l DG009-J-PLT-00" PVNGS JOB PERFORMANCE MEASURE

?

STEP ELEMENT STANDARD

11. Pla'c e disconnect (CS-3) in LOCAL & Examinee simulates placing disconnect (CS-3)

Breaker OPEN for PBB-SO4L. PBB-504 in LOCAL and the breaker handswitch (CS-1)

Alternate Supply breaker. for PBB-SO4L verifled OPEN.

If requested CUE: PBB-504L disconnect is in LOCAL, brer ;r indicates open by green light ON, red light OFF.

SAT UNSAT (UNSAT requires commen'.s)

I SILP ELEMENT STANDARD

12.

• Pla'ce disconnect (CS 3)in LOCAL & Examinee simulates placing disconnect (CS-3)

Br/aker OPEN for PBB 504M, ESS in LOCAL and the breaker handswitch (CS 1)

Cohling Water Pump B breaker. for PBB SO4M verified OPEN.

If requested CUE: PBB-SO4M disconnect is in LOCAL, breaker indicates open by green

! light ON. red light OFT.

SAT l UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD I

13.

• Pl/cc disconnect (CS 3)in LOCAL & Examinee simulates placing disconnect (CS-3)

Brdaker OPEN for PBB-SO4S, AFW in LOCAL and the breaker handswitch (CS-1)

Pubp B breaker. for PBB-504S verified OPEN.

If requested CUE: PBB-504S disconnect is in LOCAL, breaker indicates open by green light ON, red light OFF.

SAT UNSAT (UNSAT requires comments)

I I

COMMENTS: l l

i i

__ i OTG-02 Rev. 0' 7

i

P.U2

. l  :

u i DG009 J-PUP-C3

, PVNGS JOB PERFOR31ANCE MEASURE l

STEP EL.EM ENT STANDARD

14.

• Examinee simulates placing disconnect (CS-Pla'ce disconnect (CS-2/C4) in LOCAL &

Br aker OPEN Br PGH L32C4, Charging 2/C4)in LOCAL and the breaker L32C4 Pt p 2 Breaker verified OPEN.

l If requested CUE: L32C4 disconnect is in j LOCAL, breaker indicates open by green light ON. red light OFF.  !

SAT l UNSAT (UNSAT requires comments) i I

i STEP ELEMENT STANDARD j

15. P1 e disconnect in LOCAL & Breaker Examinee simulates placing disconnect in l 0 N for PHB-M3209, Battery Charger LOCAL and PHB-M3209 breaker verified 1 PK H14 Supply Breaker. OPEN.

l If requested CUE: PHB M3209 disconnect is in LOCAL, breaker indicates open by green i light ON. red light OFF.

SAT l UNSAT (UNSAT requires comments)

STEP ELEMENT STANDARD

16. a Opp' n Voltage Regulator PND-V28 Supply Examinee simulates opening PHB M3210 Brdaker, PHB-M3210. breaker.

I I

If requested CUE: PHB M3210 indlestes OPEN by green light ON, red light OFF I 1

Inform CUE: All other breakers required to  ;

be load shed per attachment E-2 have been I opened, continue on with procedure, SAT UNSAT (UNSAT requires comments)

I, I

t COMMENTS:

1 l

l i

CTG 02 Rcv. 0'.

g l . _ . _ __. -

P.U3

, i l

I

! l DG009-J. PLT-00

! i PVNGS JOB PERFOR3fANCE MEASURE

! 1 j l l SILP EL,EM ENT STANDARD Ma'nually start D/G 'B' by pressing I l 17. Examinee simulates starting 'B' D/G by EMERGENCY START (SIMULATED depressing DGB-HS-31.

LOP), DGB-HS-31, push butten. i inform CUE: D/G 'B' did not start.

l SAT UNSAT (UNSAT requires comments) )

i ,

SIEP ELEMENT STANDARD I 8.

• If fhe Diesel generator did NOT start, cycle open and close the following breakers

' I Examinee simulates positioning 72 DCl to

,,,,, 72 Dr s (inside panel DGB-B01) open then closed.

if requested CUE: 72 DCI has been cycled Examinee simulates positioning 72 DC2 to )

_ 72 DC2 (inside panel DGB-B01) open then closed. ,

If requested CUE: 72 DC2 has been cycled Examinee simulates positioning 72 CPI to open j 72 CPI (inside panelDGB-B02) then closed.  ;

i IIrequested CUE: 72 CPI has been cycled. j SAT i UNSAT (UNSAT requires comments) 1 I

I j

COMMENTS:

I l l

1 1

I OTG 02 Rev.0, I

P.04

• I 4

l l

t

- DG009-J PLT-00

PVNGS JOB PERFORMANCE MEASURE STEP EI.EM LNT STANDARD

19.

• Ma'pually start D/G 'B' by pressing Examinee simulates starting 'B' D/G by i EMERGENCY START (SIMULA1TD depressing DGB-HS-31. 1 LOf), DOB-HS 31, push button. l Inform CUE: D/G 'B' has started, i l

Voltage is 4240 vac, and frequency is 60 Hz.

NOTE: Time critical portion starts here.

l START Time SAT UNSAT (UNSAT requires comments)

STEP elf. MENT STANDARD l

20. PERFORM DieselGenerator B Examinee goes to Attachment E-3. i Secuencing, Attachment E-3.

SAT UNSAT (UNSAT requires comments)

I i i  !

STEP ELEMENT STANDARD

21.

• Ci se the D/G output breaker PHB-504H Examinee simulates positioning ' local' breaker using CS 1 control switch on PUB.SO4B. PHB.SO4B CS 1 handswitch to 'close'.

If requested CUE: Red light on, green light off on PBB-50dB. Volinge is 4240; frequency is 60 Hr.

NOTE: JPM steps 21-24 are performed by Att.

E-3.

SAT UNSAT (UNSAT requires comments) l COMMENTS:

t I

1 i

l OTG-02 Rev. 0 10 I

P.05 1

1 I

.  ! DG009 J. PLT-00 '

PVNGS JOB PERFORMANCE MEASURE i

STEP ELEMENT S I AN11ARD

22. Staf t Spray Pond Pump 'B' by using control Examinee simulates positioning ' local' breaker switch CS-1 at PBB-SO4C. PBB-SO4C CS-1 handswitch to START.

If requested CUE: PBB-SO4C indicates Red light ON, green light UFF NOTE: Spray pond pump must be started within 15 minutes following D/G start with no load.

NOTE: TIME CRITICAL PORTION ENDS HERE.

FINISH Time SAT UNSAT (UNSAT requires comments)

STEP STANDARD

• ELfMENT

23. Start AFB-P01 by using control switch CS- Examinee simtilates positioning ' local' breaker 1 al PBB-504S. PBB-5045 CS-1 handswitch to ' start'.

If requested CUE: PBB-504S indicates red light ON, green light OFF.

SAT UNSAT (UNSAT requires comments) l I

1 COMMENTS:

l l

1 l

OTG-02 Rey, O l g;

i

P.06 l

' s DG0094. PLT-00 *

! PVNGS JOB PERFOIGIANCE MEASURE

! I S'I E P ELEMENT STANDARD l

24.

• Sta'n HDB J01. D/G Bldg. ESS IIVAC Examinee simulates positioning HDB HS-14 EXH Fan by using HDB-HS-14. handswitch, located on the D/G local panel to l START. l l If requested CUE: HDB401 is running.  ;

. l l

Inform CUE: The remaining sections of Attachment E-3 have been completed. '

SAT UNSAT (UNSAT requires comments) i STEP ELfMENT STANDARD <

25. En$ure Jacket Water Make41p Valve. Examinee verifies DGB V013 is closed by l DGB.V013,is closed simulating going to the closed direction on l

valve.  ;

I If requested CUE: DGB-V013 is closed.  !

SAT '

UNSAT (UNSAT requires comments) i NORMAL TERMINATION POINT I l

4 COMMENTS: a l

l OTG-02 Rev. 0 12 4

OTG 02 Rev,0 12 l

I k

t i

f

l. ,

t.

1 I

OTG-02 Rev. 0 13 i

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l l

l l l

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I 1

i l

i

t

4

/

- 2 CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 Page 68 of 133 PVNGS

Appendix E Page 1 of 16 1.0 D/G AO Duties This appendix provides instructions for the D/G AO following a control room evacuation due to a fire. Portions of this appendix are only p

:r-formed if it is necessary to use the diesel generator. If offsite power is available, the diesel generator will not be staned. If there is a subwqoent loss of offsite power, the D/G AO will be required to return to this appendix and manually start the diesel generator.

ACTIONS DETAILS 1.1 Obtain a portable lantern from the Emergency Equipment Cabinet, E-FPN-C02 located in the "B" Swn .hgear Room, NW corner.

1.2 Determine DG status. Discuss with the CRS/SS the desired DG configuration with respect to offsite power.

1.3 1F a loss of power has not occurred, THEN perform the following to disconnect the B Train Diesel Generator from the control room:

1

1. Place the LOCAIJREM & LOCAL switches for the DG control to the LOCAL position by performing Component Disconnect Switches For B Train Diesel Generator, Attachment E-1. .:

l

2. Shutdown the diesel generator ifit is running using the A. Push the red STOP pushbutton DGB-HS60.

Emergency Stop pushbutton DGB-HS-30.

B. Push the black RESET pushbutton_D_GB-HS-3_0._

3. Ensure that Jacket Water Make-up Valve, DGB-V013 is closed.

4. Return to Step I.2 of this appendix if there is a subr-equent loss of offsite power.

5. Exit this appendix.

i-- ' - > ' -

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e g CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS Page 69 of 133 D/G AO Duties (cont.) j Appendix E Page 2 of 16 ACTIONS i DETAILS '

l.4 Evaluate the Diesel Generator status and GO TO the applicable step per the following table. I Diesel Generator running Diesel Gencrutor not running or tripped

• Diesel Generator Diesel Generator output output breaker closed breaker open GO TO Step 1.5 GO TO Step 1.7 GO TO Step 1.8 in this Appendix. in this Appendix. in this Appendix.

)

i CAUTION i

The Spray Pond Pump must be started within 15 minutes following a D/G stan with no lor ~ to provide diesel engine cooling. Severe  ;

engine damage may occur if proper cooling is not established. The Spray Pond Pump must be started within 2.6 minutes if the DIG s fully loaded.

1.5 If a loss of power has occurred, A. Place the LOCAIJREM & LOCAL switches for the DIG AND diesel generator B output breaker has closed, control to the LOCAL position by performing Component ,

THEN perform both of the following; Disconnect Switches For B Train Diesel Generator.

• Attachment E-1.

1. Ensure that the equipment required to shutdown the

__ _ _ ___. . . _ _ _planthassequenced.to iis-proper 4ondition, - -. _

B._PerfertnDiesel Generator.B-Sequencing,-Attachment- ,

E-3, beginning with Step 1.4.

2. GO FO Step 1.12 of this Appendix.

h e

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i CONTROL ROOM FIRE 41AO-1ZZ44 Revisi'on 12 PVNGS Page 70 0f 133 D/G AO Duties (cont.) Appendix E Page 3 of 16 ACTIONS DETAILS 1.6 IF all of the following conditions exist at anytime during this procedore:

1. Diewi generator B auto started.

2. Component Disconnect Switches For B Train Diesel Generator, Attachment E-1, has NOT been performed.

3. Die el Generator B has tripped.

THEN GO TO Sicp I.8 of this Appendix.

---

NOTE HVAC cooling to B train equipment areas should be established within approximately 30 minutes after equipment is placed in service so pre"ent room overheating.

J.7 JE diesel generator B has staned, A. Place the LOCAIJREM & LOCAL switches for the D/G

, AND the output breaker has NOT closed, control to the LOCAL position by performmg Component TilEN perform both of the following: Disconnect Switches For B Train Diesel Generator, Attachment E-1.

1. Manually load bus PBB-SO4 B. Perform Diesel Generator B Load Shed, Attachment E-2, to manually strip allof the loads.

~~P irform Diesel Generator B Sequencing.

Attachment E-3.

2. GO TO Step L12 of this Appendix.

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CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS Page 71 of 133 ,

__ D/G AO Duties (cont.)

Appendix E Page 4 of 16 ACTIONS DETAllS 1.S E diesel generator B has NDIstarted.

QR diesel generator B has started and tripped, ___ A. Place the LOCAL / REM & LOCAL switches for the D/G T_ HEN manually open a]! of the breakers on PBB-SO4. control to the LOCAL position by perfonning Conrponent Disconnect Switches For B Train Diesel Generator, Attachment E-1.

_B. Perfonn the Lead Shed column in Diesel Generatar B Load Shed, Attachment E-2.

1.9 Manually start diesel generator B.

Perfonn the following:

__ a. Press the EMERGENCY START- SIMULATED : OP, DGB-HS-031, pushbatton, on the DG B local panel.

._._ b. JE the diesel generator did NOT start, TIIEN perform the following to restore power to the local control panels: (CRDR 920674)

Cycle open and close breaker 72DCI locared inside panel 3-DGB-B01.

Cycle open and close breaker 72DC2 tocated inside pane! J-DGB-BOI.

Cycle open and close breater 72 CPI located inside panel J;DGB2307 ~

Press the EMERGENCY START - SIMULATED LOP, DGB-HS-031, pushbutton, on the DG B. local panel.

1.10 E diesel generator B .staned, Check t!ut the following parameters am met THEN check for acceptable voltage and frequency.

Voltage is between 3740 and 4580 Vac.

Frequency is between 58.8 and 61.2 Ilz.

, \qj 3

41AO-1ZZ44 Revidon 12 PVNGS Page 72of 133 5 CONTROL ROOM FIRE D/G AO Duties (cont.) Appendix E Page 5 of 16 l

ACTIONS DETAll S NOTE 11VAC cooling to B train equipment areas should be e.stablished within appmximately 30 minutes after equipment is placed in service to prevent toom ovedicating.

l.1) lE diesel generator B voltage and frequency are acceptable, THEN PERFORM Diesel Generator B Sequencing, Attachment E-3 to manually load diese] generater B.

1.12 Ensure that Jacket Water Make-up Valve, DGB-Vol3 is closed.

End of Appendix m

M ***** W e-e **gm e se .*mep,e..

O 9

_._____.____.____m_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ . _ - _ _ . _ _ _ _ _ _ _ _ __ ._ . _ _ ._ _ _.. __ _ _ _ _ _ . . - _ _______..m__ _ _ _ . __ . _ _ . _ . . _ _ _ _ _ _ _

d s -, ,, /

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$ PVNGS Page 73 of 133 4

CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 ATTACHMENT E 1 ' Appendix E Page 6 of 16 4

1.0 Compoinnt Disconnect Switches For B Train Diesel Generator DETAILS ACTIONS Place a;l of the following LOCAUREM & LOCAL switches 1.1 Ensure that the disconnect switches located in the B Train located in the B Train Switchgear Room, on DG DISC CAB Switchgar Room are in the LOCAL position.

DGB-C01, in the LOCAL position, Initials Location Equipment Description ,

Switch Number ; Effect When Placing Switch In Local J-DGB-HS-2A All manual Control Room signals are bypassed.

Class Swgr Rm Diesel Engine Control North end of PBB-SO4 1-DGB-IIS-2B A_l! auto start signals are bypassed. If a LOP Class Swgr km Diesel Engine Control occurs the operator must manually stan the North end of diesel-PBB-SO4 E-PEB-flS-2 Diesel output breaker must be manually closed.

Class Swgr Rm Diesel Generator Control North end of PBB-SO4 Class Swgr Rm Diesel Generat5r Es ExhTan J-HOB-HS-14A-The farrwill-not-auto start-if-diesel-starts.

Operator must start the fan at DG control panel.

North end of PBB-SO4 J-DFB-HS-22C No effect.

Clau Swgr Rm Diesel Generator Fuct Oil Transfer Pump North end of PBB-SO4 End of Attachment i

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g CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS Page 74 of 133 ATTACHMENT E-2 Appendix E Page 7 of 16 i LO Diesel Generator B Load Shed

--NOTE-- '

Most of the breaken or switches listed below ase located in the B class switchgear room,100 ft. control building. Coonlinate with the Aux Bldg AO to check the leads on MCC M34 and M36. '

l Initials Load Shed Equipment Name Breaker /Dise Switch Number Disconnect in LOCAL

& Diesel Generator B Breaker PBD-SO4B Breaker OPEN i

_ _ _ _ Di' .onacci in LOCAL.

& Spray Pond Purnp B Breaker PEB-SO4C i Breaker OPEN

__ Disconnect in LOCAL

& ESS Chiller B Bn:aker PBB-SO4G

Breaker OPEN i

Disconnect in LOCAL 4

& PBB-SO4 Norm Supply Breaker PBB-SO4K

! Breaker OPEN i -. . - . _ - - - - - - .

Disconncet in LOCAL

& PEB-SO4 Alternate Supply Breaker PBB-SO4L -

Breaker OPEN

{ Disconnect in LOCAL i & ES.S Cooling Water Pump B Breaker PBB-SO4M Breaker OPEN

_ , , _ . . , ,m..-- , . , v* - -- ew - ' - - - * "

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g CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS Page 75 of 133 Diesel Generator B Lead Shed (conL) ~ ATTACIIMENT E-2 Appendix E Page 8 of 16 l

Initiah Load Shed Equipment Name Breaker / Disc Switch Number Disconnect in LOCAL

& AFW Pump B Breaker PBB-SO4S Breaker OPEN Disconnect in LOCAL PGB-L32Cl Compartment CS-2/C4 Breaker OPEN Charging Pump 2 Breaker PGB-L32C4 Disconnect in LOCAL

& Battery Charger PKD-H14 Supply Breaker PHB-M3209 Breaker OPEN Breaker OPEN Voirage Regulator PND-V28 Supply Breaker PIIB-M3210 ,

. _ _ Breaker OPEN Voltage Regulator PNB-V26 Supply Breaker PHB-M3626 (Contact Aux Bldg AO to perform)

D

_____ __ . pcon_necQn10CA_L

-BatteryCharger:B PKU;FDTSITRTy~Bresker

" # ^"* E^ PHB-M3627 Breaker OPEN Disconnect in LOCAL Battery Charger-BD, PKB-lil6 Supply Breaker (Contact Aux B!dg AO to perform) PHB-M3425 Breake OPEN End of Attachment 4 5

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CONTROL ROOM FIRE 41AO-1ZZ44 Revidon 12 1 PVNGS Page 76 cf 133 l

ATTACHMENTE-3

~

Appendix E Page 9 of 16 j I.0 Diesel Generator B Sequencing ACTIONS DETAILS

)

! CAUTION l

j The Spray Fond Pump must be started within 15 minutes following a DG stan with no load to provide diesel e engine damage may occur if proper cooling is not established. The Spray Pond Pump must be started within 2.6 minute i

fully loaded.

i i.! Close the Die.sel Generator Output breaker.

! a. Check that the following parameters are met:

Voltage is between 3740 and 4580 VAC.

Frequency is between 58.8 and 61.2 Hz_

l bt Close the diesel generator output breaker PBB-SO4B using CS-1 control switch on PBB-SO4B.

1

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

E 1 1

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w i CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS Page 77 of 133 Diesel Generator B Sequencing (cont.)

ATTACHMENT E-3 Appendix E Page 10 of 16 ACTIONS DETAILS 1.2 IE the Diesel Generator Output breaker woulcated on the DG Local Control Panel.

, o

_ - - . _--_._ .-_- ___._.-_-____-.-_- -.- --.__-- - -__._ _ __ _- -~ . - , v + -v,.

f .

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a. CONTROL ROOM FIRE 41AO-1ZZ44 ' Revision 32 PVNGS Page 80 of 133 Diesel Generator B Sequencing (cont.)

ATTACHMENT E-3 Appendix E Page 13 of 16 l

ACTIONS 4

DETAILS CAUTION Allow bus voltage to recover between load additions.

NOTE-Aux Bldg AO to check the loads on MCC M34, M36 and M38.Most of the breakers or switches li 1.8 Coordinate with the Secondary RO and Aux B!dg AO to sequence loads by performing the actions listed in the n. Allow hus voltage to recover between load additions, following table.

b. After all the leads have been sequenced on, ensum that the diesel g nerator B parameters are not exceeded for the capabihty curve. Refer to the Estimated Diesef Generator Capability Curve, Attachment E-4.

Initials Sequence Breaker / Disc Equipment Name .

a Component Condition Switch Number

1. Close Breaker ESS Cooling Water Pump B Breaker PBB-SO4M Breaker Closed 4

2. Close Breaker ESS Chiller B Breaker PBB-SO4G Breaker Closed

3. Close Breaker Contro! Bldg Battery Rm D ESS Exhaust PHB-M3206 Breaker Closed Fan Switch to START at MCC Switch to Start 7

9

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CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12 PVNGS i

' Page 81 of 133 Diesel Generator B Sequencing (cont.)

ATTACHMENT E-3 Appendix E Page 14 of 16 Initials Sequence Equipment Name Breaker / Disc Component Condih.on Switch Number

4. Close Breaker Control Bldg Battery RM B ESS Eahaust PilB-M3207 Breaker Closed Fan Switch to START at MCC Switch to Start

5. Close Breaker Battery Charger PKD-H14 Supply Bmaker PHB-M3209 Breaker Closed

6. Close Breaker Voltage Regulator PND-V28 Supply PHB-M3210 Breaker Closed Breaker

7. As directed by CRS Charging Pump 2 Breaker PGB-L32C4 Close Breaker Breaker Closed

8. Ensum Breaker Closed Spray Pond Pump flouse HVAC PHB-M3214 Breaker Closed 4 Contact Aux Bldg AO to Battery Charger PKB-H12 Supply Breaker PHB-M3627 Breaker Closed -

Close Breaker

10. Contact Aux Bldg AO to '

Battery C~ urger PKB-H16 Supply Breaker PHB-M3425 Breaker Closed ---

Close-Breaka

11. Contact Aux Bldg AO to Voltage Regulttor PNB-V26 Supply PHB-M3626 Breaker Closed Close Breaker Breaker

CONTROL ROOM FIRE 41AO-1ZZ44 Revision 12

a. PVNGS Page 82 of 133 Diesel Generator B Sequencing (cont.)

ATTACHMENTE-3 Appendix E Page 15 of 16 Initials Sequence ** *#

Equipment Name #

Canponent Conditics Switch Number

12. Contact Aux Bldg AO to Aux FeedwaterPump Rm B Essendal ACU Close Breaker PHB-M3827 Biraker Closed i

Return to Step 1.12 of this appendix.

End of Attachment 4

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CONTROL ROOM FIRE 41AO-IZZ44 '

Revision 12 PvNos Page 83 of 133 I i

ATTACHMENT E-4 Appendix E Page l6 cf 16

, ESTBIATED .

DIESEL GENERATOR CAPABILITY CURVE .

7 00 7 7- - ;:

- ,-_ -- -"-['  : ' 2 2 -"" "'I'_ 4 A 1) Extracted from Log M018-451-1.

6.00 h, -

1; 0 80 l'F lag 2) Assumes Generator Terminal Voltage 4.leKV

---

_----MQ

:::::!g t

%  ;-----p 5.00 -----------~~-w-_____--~~~~W . _%_%h

._4 -"Z.N_% D 4.00

---

'~"--[-

____.____.-___.--_q--4

_--_-_--s--__-2 y ----

3.00  :----------~~--'-~~'-:-' 7/_~2--

,  ::s g_-_-

2.00 -:+-__ _s ____.___---a ,

-~~::y_.-_-_----------W

- _ __s ,

/ CURVE AB: 2 Hour Ove:ioad Field Umit j ______________-______@ 1* CD; Rated Field Limit 1.00 :---- ;;t:-::::::::::::::

g

- ,;d--:::::::::::::::: :E 23 BE: 2 Hour Overload DP: Continuous Daty 0'00 (-'- ---------- -

>( -e-

~ ~ " """----"'

- ~ "'" EG: Steady State Stability Limit At Rated %1tage MW

""5'.00 -

"4 --%-w_c-:2.00 ___:1_ -- 3.00~ L.C::_L.~ 4.00-- L.ClF 6.00 7 L _____ :L s  !

__-_y

-1.00 ---n__________.__.

s_. ,_

____ . __________.y

• ___________4 5

______ __A____________-- ---; SHADE

____._ ____s ____.________----

-2.00 ---------::::q3[ -

g:::_'"::::::

____- --- ES.5_to_6.05_MW The_dieselmay-beoperated

__._5(-:::::: for no more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

-3'00 ---------------~~--* 5 ---~~"-~!

in this region.

-5E  : Zl 4 00

______._______g5::l E > 6.05 MW- The diesel may not le operated

- -----------------~ in this region except as dilected and c;m_:J ---u__ -

d,M

.. ..--== monitored by engineering.

-5.00L--"--'-----'"-_"_"_"_._____, " -"""""

osoepie,a End Of Attachment

. - _ - _ _ - _ _ - _ _ _ _ _ _ - . - _ - _ . .__ _ _ - _ _ _ _ _ - ._ D

e Appendix D Scenario Outline Form ES-D-1 y

Facility: PVNGS Scenario No.: 2 Op-Test No:

Examiners: 3 #f '# /a/ V Operators: Ed Bowers CRS 11 MFZLef Scott Gary PO M1 # f 4// / W V John Leonard SO Objectives: Evaluate the crew's response to a pressurizer pressure control system failure.

Evaluate the crew's response to high vibration on a main feedwater pump.

Evaluate the crew's response to a feedwater control system failure.

Evaluate the crew's ability to diagnose an excess steam demand.

Evaluate the crew in transitioning to the FRP to recover containment spray.

Initial Conditions: 100% power, equilibrium xenon, middle of cycle Turnover: The following equipment is out of service:

. SIB-P02, high pressure safety injection pump, has been out of service 121. f'or seal replacement. Estimated return is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

• NCN-P01B is out of service for motor replacement. Estimated return in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Charging pump "A" will be tagged out early in the shift for normal maintenance. Shift running order to place "A" as the standby pump.

Event Malf. Event Event Description No. No. Type

• j 1 N Shift running order of the charging pumps. l 2 TR01: 1 Controlling pressurizer pressure instrument fails low.

RCNPT100X 3 FW15A C/R Main feedwater pump "A" increased vibration over two minute ramp.

4 TR01: I Steam generator #2 steam flov transmitter fails low over 30 second ramp.

SGNFTl022 l

5 FW15A C Main feedwater pump "A" trip. j 6 MS01C M Main steam line break in containment resulting in reactor trip.

BS01:BSCNT C

• Auto initiation of CSAS fails. j PRSHHA .

i MV06:SIAUV C e SIA-UV-672 mechanically bound closed.  !

672 l R1101B C e SIB-P03, CS "B" pump, trips.

Implement 40EP-9EOO9, Functional Recovery Procedure, to use LPSI "B" for containment spray.

• (N)ormal, ;R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards t

7 Rev.8

Appendix D Operator Actions Form ES-D-2 v

Op-Test No: Scenario No.: 2 Event No: 1 Page 1 of J Event

Description:

Select "A" charging pump as the STANDBY pump.

Time . Position Applicant's Actions or Behavior CRS Directs use of 410P-ICH01, CVCS Normal Operations, to shift the running order of the charging pumps from 1-2-3 to 2-3-1.

PO Obtains procedure 410P-lC1101.

Performs Section 11 to shift the running order of charging pumps:

e Places backpressure controller CHN-PDIC-240 in MANUAL.

. Ensures green flag on the "E" charging pump handswitch, e Selects 2-3-1 on CHN-HS-4.

• Returns CHN-PDIC-240 to AUTO after flow oscillations have stabilized.

l SO Monitors plant parameters. 1 i

l s_

Examiner Standards Rev.8

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

l

) Appendix D Operator Actions Form ES-D-2 e

Op-Test No: Scenario No.: 2 Event No: 2 Page 1 of J j Event

Description:

Controlling pressurizer pressure instrument fails low.

i i

Time Position Applicant's Actions or Behavior i

PO Respond to alarm 4A01 A and 4 A01B.

Diagnose PT-100X as failed low.

Place pressurizer pressure control system in the "Y" channel position.

Refer to alarm response procedure for 4A01 A and 4A02B.

Restore pressurizer heaters to operation as needed for pressure control.

CRS Direct recovery per alarm response procedure.

Concur with PO actions for selecting the unaffected channel ("Y").

Contact I&C to troubleshoot / repair.

Direct response to alarm 4A12B.

SO Monitor control boards, assist diagnosis.

I I

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l Examiner Standards Rev 8

Appendix D Operator Actions Form ES-D-2 e

Op-Test No: Scenario No.: 2 Event No: 2 Page 1 of _t Event

Description:

Controlling pressurizer pressure instrument fails high.

Time Position Applicant's Actions or Behavior PO Respond to alarm 4A01 A and 4A01B.

Diagnose PT-100X as failed high.

Place pressurizer pressure control system in the "Y" channel position.

Refer to alarm response procedure for 4A01 A and 4A028.

Restore pressurizer heaters to operation as needed for pressure control.

CRS Direct recovery per alarm response piocedure.

Concur with PO actions for selecting the unaffected channel ("Y").

Contact I&C to troubleshoot / repair.

Direct response to alarm 4Al28.

Evaluate impact of failure on steam bypass control system.

l SO Monitor control boards, assist diagnosis.

f Identify steam bypass control valves have 100% demand signal.

l Examiner Standards Rev.8

Appendix D Operator Actions Form ES-D-2 e

Op-Test No: Scenario No.: 2 Event No: 1 Page 1 _of _t Event

Description:

Main feedwater pump "A" increased vibration.

Time Position Applicant's Actions or Behavior CRS/SO/PO Identify high vibration condition on main feedwater pump "A" by alarm CRT or alarm 6A04C.

CRS Direct response per alarm response procedure 6A04C.

Direct unit downpower in accordance with 400P-9ZZ05, Power Operations, to approximately 65% power to allow removing main feedwater pump from service.

. initiate boration Place pressurizer in " boron equalization" mode.

Maintain T-ave to T-ref mismatch less than 3 'F.

SO Refer to alarm response procedure 6A04C.

Decrease turbine load to maintain T-ave to T-ref mismatch less than 3 'F.

Continue to monitor main feedwater pump "A" vibration.

PO May calculate boration for power chuge (~2100 gallons to 50% power).

Initiate boration at CRS specified flow rate.

Place pressurizer in " boron equalization" mode, e

SETPOINT OVERRIDE all heater banks.

Adjust pressurizer pressure control system setpoint to 2220 psia.

Verify main spray valves open as necessary for pressure control.

Examiner Standards Rev.8 1

I l

f Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 2 Event No:_ 4 Page 1 of _t  !

l Event

Description:

Steam generator steam flow transmitter Fa '022 fails low to #2 feedwater control  :

system. i l

Time Position Applicant's Actions or Bd,4vior  !

SO Diagnose problem with SG #2 level, FWCS #2 and FT1022.

Refer to alarm response for 6A06A on low level, i Take manual control of FWCS #2 and restore SG #2 level to 50%. I 1

Determine failed instrument as FT1022. '

Restore FWCS #2 to AUTO after instrument has completely failed and level I is controlled. j i

l I

CRS Assist diagnosis.

Direct SO activities from alarm response procedures to recover SG #2 level. :

Contact I&C to troubleshoot / repair.  ;

PO Monitor control boards, assist diagnosis.

1

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Examiner Standards Rev.8 i

- . _ _ . - . _ . _ _ _ _ . . _ __ _ _-l '

I Appendix D Operator Actions l'orm ES-D-2 l

. I I

Op-Test No: Scenario No.: 2 Event No: 5 Page 1 of J .

i l

i Event

Description:

Main feedwater pump "A" vibration degradation causing pump trip.

I l

Time Position Applicant's Actions or Behavior l CRS/PO/SO Diagnose and respond to increased vibration on main feedwster pump "A".

CRS Direct manual trip of feedwater pump "A".

Verify reactor power cutback system actuates.

Direct plant stabilization per 40AO-9ZZ09, Reactor Power Cutback (Loss of Feedpump).

Remove reactor power cutback system from service.

Clear the turbine increase inhibit signal.

SO Manually trip main feedwater pump "A".

Verify reactor power cutback actuates.

Clear turbine increase inhibit by lowering turbine load control potentiometer until AT SET LOAD illuminates.

PO Monitor plant parameters and verify stabilization.

PO/SO Remove reactor power cutback from service.

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Examiner Standards Rev.8

j Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 2 Event No: 6 Page 1 of _2 Event

Description:

Main steam :?.e rupture in containment with constainment spray system failures.

~

Time Position Applicant's Actions or Behavior CRS/PO/SO Diagnose and respond to excess steam demand in containment.

CRS Direct Reactor Trip. May direct SMS, CIAS and/or MSIS.

, Direct PO/SO into Standard Post Trip Actions and Contingency Actions.

Direct manual CSAS when ;rew identifies containment pressure is greater than 8.5 psig.

Diagnose Containment Temperature and Pressure Control (CTPC) as jeopardized.

Enter 40EP-9EOO9, F.metional Recovery Procedure, to regain CTPC.

Use CTPC-2 to align low pressure safety injection pump "B" to containment spray header.

Use selected lleat Removal (IIR) success path to stabilize primary T-cold when steam generator #2 has blown dry.

SO Take Standard Post Trip Actions and Contingencies. ,

e Diagnose failure of CSAS to automatically actuate.

• Manually actuate CSAS.

Stabilize primary T-cold using steam generator #1, essential auxiliary feedwater and atmospheric dump valves.

PO Take Standard Post Trip Actions and Contingencies e Diagnose containment spray "A" header isolation valve failure to actuate.

• Diagnose containment spray pump "B" trip.

• Trip all reactor coolant pumps after manual CSAS and isolate controlled bleedoff from the seal packages.

Align low pressure safety injection pump "B" to containment spray "B".

Assist in stabilizing T-cold when steam generator #2 has blown dry.

Throttle high pressure safety injection when throttle criteria are satisfied.

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Examiner Standards Rev.8

i .

Appendix D Operator Actions Form ES-D-2 Op-Test No: __ Scenario No.: 2 Event No: 6 Page 2 _of J 1

Event

Description:

Main steam line rupture in containment with containment spray system failures (continued). ,

4 Time Position Applicant's Actions or Behavior i

Scenario may be terminated when containment pressure is stable or decreasing and primary T-cold is controlled by the crew, or when deemed appropriate by the exam team.

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Examiner Standards Rev.8

=

l Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 3 Op-Test No:

l

l.  !

o  !

l- Examiners: J /4%Lcf Operators: Greg Reynolds CRS  !

M4 8M8//// John Leonard PO 3 /// 5 d/'O // Scott Gary SO L Objectives: Evaluate the crew's response to a plant protection system instrument failure.

Evaluate the crew's response to a volume control tank level system failure.

Evaluate the crew's response to a steam generator tube leak.

Evaluate the crew in using the EOPs during a steam generator tube rupture.

Initial Conditions: 50% power, equilibrium xenon, middle of cycle Turnover: The following equipment is out of service:

• SIB-P02, high pressure safety injection pump, has been out of service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for seal replacement. Estimated return is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

-.

• NCN-P01B is out of service for motor replacement. Estimated retum in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Previous shift halted power ascension at 50% for tumover. Dilution rate was 60 gpm and total gallons left to dilute is 14,300. Continue power ascension to 100% power in accordance with 400P-9ZZ05, Power Operations, at step 5.3.37.

Event Malf. Event Event Description No. No. Type

• 1 N/R Continue power ascension.

2 TR01:RCDT I Plant protection system channel "D" temperature instrument fails  !

Tl12HD low. )

3- TROI:CHNL ' I Volume control tank level instrument fails low.

T227 1 i

4 TH06A C Steam generator #1 tube leak of-50 gpm.

5 T1106A M Steam generator #1 tube rupture resulting in reactor trip.

ED10A C e NBN-XO3 transformer fails.

RP07A C e Sequencer train "A" fails.

RD031 and C Two CEAs stick out of core.

RD03M implement 40EP-9EOO4, Steam Generator Tube Rupture, to j isolate steam generator #1, l

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards / Rev.7

j- Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 3 Event No: 1 Page 1 of_1 Event

Description:

Continue power ascension.

l Time Position Applicant's Actions or Behavior CRS Directs use of 4 IOP-lCIl01 to initiate dilution at the desired rate.

Directs SO to raise turbine load to maintain T-ave to T-ref mismatch less than 3 *F.

l PO Initiates dilution to the suction of the charging pumps per 410P-lCIl01, Section 9.0.

Sets CIIN-FIC-210X to 0 setpoint with 0 output demand.

Selects DILUTE on makeup mode selector switch.

Checks reactor makeup water pump running, CIIN-UV 527 OPEN.

Adjusts CilN FIC-210N eatput to desired dilution rate.

SO Monitors T ave to T-ref mismatch on B04.

Increases turbine load to maintain T-ave to T-ref mismatch less than or equal to 3 *F.

l Examiner Standards Rev.7

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 3 Event No: 2 Page 1 of._1 Event

Description:

Channel "D" T-cold plant protection system instrument fails low.

1 Time Position Applicant's Actions or Behavior PO/SO/CRS Diagnose Channel "D" loop 2 T-cold failed low.

CRS Direct references to alarm response procedures for SA13B,5A13C/D, and 5A14C/D.

Determines Technical Specificat;on impact to LCO 3.3.1, declares CPC "D" INOPERABLE.

Directs SO to bypass parameters 3 and 4 of channel "D" plant protection system.

SO Refers to alarm response procedures for 5A13B, SA13C/D, and 5A14C/D.

Obtains bypass key for PPS cabinet "D".

l Bypasses parameters 3 and 4 (LO DNBR and HI LPD) on channel "D".

PO Monitors plant parameters while SO is performing bypass.

Independently verifies correct parameters are bypassed.

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Examiner Standards Rev,7 i

\

Appendix - D Operator Actions Form ES-D-2 l 1

lI Op-Test No: Scenario No.: 3 Event No: 3 Page 1 _ of _t Event

Description:

Volume control tank level instrument LT-227 fails low. l J

Time Position Applicant's Actions or Behavior CRS/PO Respond to alarms 3A09A and 3A08B.

CRS l Directs response to alarms 3A09A and 3A08B. '

Directs SO to maintain T-ave to T-ref mismatch less than 3 *F using turbine load.

Directs AO to open breakers for appropriate valves per the alarm response  !

procedure.

l PO Diagnose CHN-LT-227 failed low.

liolds CIIN-UV-501 OPEN and CHN-UV-514 CLOSED until AO opens i breakers.

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SO May reduce turbine load to compensate for boration.

May refer to alarrn response procedure for alarms 3 A09A and 3A08B.

May direct AO to open appropriate b' reakers.

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1 Examiner Standards Rev.7

, Appendix D Operator Actions Form FS-D-2

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J Op-Test No: Scenario No.: 3 Event No: 4 Page 1 of _1 i

Event

Description:

Steam generator #1 tube leak of approximately 50 gpm.

l l Time Position Applicant's Actions or Behavior CRS/SO Respond to radiation monitoring system alarms for RU-142 and RU-139. l

CRS Direct actions per 40AO-9ZZ02, Excess RCS Leakage, Section 4.

Directs PO to perform Appendix A, leak rate determination.

Directs SO to perform Appendix B, minimize release to atmosphere.

Determines plant shutdown required in less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

PO Performs Appendix A.

e Isolate makeup to the volume control tank.

• Obtain intial data.

• Monitor leak rate for up to 15 minutes.

l Determines leak rate is ~50 gpm. l i

SO Responds to RU-142 and RU-139 alarms. l Stops steam generator blowdown per alarm response procedure for RU-139.  !

Performs Appendix B.

• Place ARN-IIS-19 in THRU FILTER MODE.

• Select OFF for steam bypass control valves 1007 and 1008. I e Direct AO to perform Attachment 1.

• Throttle OPEN CDN-HV-275 and CLOSE CDN-V099.

• Align auxiliary steam from another unit.

Examiner Standanis Rev.7

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 3 Event No: s Page 1 of_t Event

Description:

Steam generator #1 tube rupture, loss of NAN-X03, sequencer"A" stall.

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t Time Position Applicant's Actions or Behavior l

CRS/PO/SO Diagnose steam generator #1 tube leak degradation to rupture.

CRS Direct Reactor Trip. May direct SIAS and CIAS. '

Direct PO/SO into Standard Post Trip Actions and Contiagency Actions.

Direct PO to initiate boration by either closing breakers from event #3 or  !

manual lineup. 1 Diagnose Steam Generator Tube Rupture, enter SGTR procedure.

Direct rapid cooldown to T-hot less than 550 F.

)'

Direct depressurization of reactor coolant system.

Direct isolation of steam generator #1.

SO Take Standard Post Trip Actions and Contingencies.

Cooldown to T-hot less than 550 F using steam bypass control system.

Isolate #1 SG.

Maintain #1 SG pressure less than 1135 psia after isolation.

Continue cooldown using #2 SG and steam bypass control system.

PO Take Standard Post Trip Actions and Contingencies

• Manually start train "A" equipment which does not auto-start.

• Stop 2 reactor coolant pumps when RCS pressure is <!837 psia. j e Initiate boration by either directing AO to reclose breakers opened in event #3 or initiating manual boration to charging pump suction using normal lineup. j Depressurize RCS to within 50 psid of #1 SG using main or auxiliary spray l while maintaining NPSH for reactor coolant pumps.  !

Throttle high pressure safety injection flow when throttle criteria is met.

Scenario may be terminated when #1 SG is isolated, llPSI is throttled, and RCS pressure is within 50 psid of #1 SG, or when deemed appropriate by the i exam team. ,

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l Examiner Standards Rev.7

l Appendix D Scenario Outline Form ES-D-1 O

I Facility: PVNGS Scenario No.: 4 Op-Test No:

Examiners: /// 4 b (4 /' M Operators: Rich Johnson CRS l A 48W/#/V Greg Reynolds PO 3 /// # 6/d/[ Ed Bowers SO Objectives: Evaluate the crew's response to a letdown controller failure.

Evaluate the crew's response to a pressurizer pressure controller failure.

Evaluate the crew's response to a feedwater control system failure.

Evaluate the crew's respoase to a dropped CEA.

Evaluate the crew in using the EOPs during a loss of all feedwater.

Evaluate the crew in transitioning to the FRP to recover feedwater.  !

Initial Conditions: 100% power, equilibrium xenon, middle of cycle l Turnover: The following equipment is out of service:

• SIB-P02, high pressure safety injection pumo has been out of service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for seal replacement. Estimated retum is 16 houn.. .;

e NCN-P01B is out of service for motor replacement. Estimated return in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Continue 4IST-1DG01, from Step 8.14, to parallel EDG "A" to grid for a normal load test.

Event Malf. Event Event Description No. No. Type

• 1 N Parallel diesel generator "A" with grid 2 CN02: C CHN-TIC-223 controller auto output fails low.

CHNTIC223 i 3 TR01: 1 Controlling pressurizer pressure instrument fails low.

RCNPT100X 4 RD02F C/R CEA #89 drops fully into the core.

5 TROI: I Steam generator #2 feedwater flow instrument fails low.

SGNFTl122 6 FWOS M Feedwater line break in turbine building resulting in reactor trip.

ED05B M

• Loss of NAN-S06.

EG06B C

• Emergency diesel generator "B" trip.

MV06:SGAU C

• AFA-P01 will not start.

V134 FW21A C

• AFN-P01 trip.

Implement 40EP-9EOO). Functional Recovery Procedure, tn cross-tie NBN-X03 to PBB-SO4 to regain feedwater.

• (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards y ,

W Rev.7

t Appendix D Operator Actions Form ES-D-2 l

Op-Test No: Scenario No.: 4 Event No: 1 Page 1 of_1 f

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livent

Description:

Parallel emergency diesel generator "A" to the grid.

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Time Position Applicant's Actions or Behavior ,

i CRS Directs use of 41ST-lDG01 to parallel EDG "A" to the grid, beginning at i Step 8.14.

PO Obtains procedure 41ST-lDG01.

Places diesel in DROOP mode.

j Places synchronizing scope ON.

! Matches incoming and running voltages using the voltage adjust switch.

Adjusts engine speed to obtain the synchronizing scope moving slowly in the FAST direction.

Closes diesel output breaker when synchronizing scope is approximately at the 12 o' clock position.

Raises load to approximately 1.4 MW while maintaining a power factor of l.0 or lagging.

! SO Monitors plant parameters.

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l Examiner Standards Rev.7 l

Appendix D Operator Actions Form ES-D-2 -

J t Op-Test No: Scenario No.: 4 Event No: 2 Page 1

_ of J .

i Event

Description:

Letdown heat exchanger outlet temperature controller CHN-TIC-223 fails.  !

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Time Position Applicant's Actions or Behavior  ;

) PO Respond to alarms 3A10A and 3A10B.  ;

Determine letdown is isolated.

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CRS Direct actions per 40AO-9ZZ05, Loss of Letdown.

e Direct single charging pump operation.

• Direct closure of CH-UV-515,516, or 523.

. Assist in diagnosis of CHN-TIC-223 auto output failure. i

e Direct operation of CHN-TIC-223 in MANUAL.

.

• Direct restoration ofletdown.  !

~~

i PO Diagnose CHN-TIC-223 auto output failed.

i ,_. Stop one charging pump.

Close CH-UV-515,516, or 523.

j Operate CHN-TIC-223 in MANUAL to restore nuclear cooling water flow

. to letdown heat exchanger.

Restore letdown.

• CLOSE letdown control valves by placing RCN-LIC-110 in .

MANUAL with 0 output. ,

• OPEN backpressure control valves by placing CHN-PIC-201 in MANUAL with 100% output. '

• OPEN letdown isolation valve previously closed. i

[

• Throttle open letdown control valves using RCN-LIC-110.

I e Establish ~450 psi on CHN-PIC-201.

4 e Restore systems to automatic as time allows. i SO Monitor plant parameters.

m Examiner Standards Rev.7

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 4 Event No: 3 Page 1 of J Event

Description:

Controlling pressurizer pressure control instrument fails low.  :

Time Position Applicant's Actions or Behavior PO Respond to alarms 4A01 A and 4A01B.

Diagnose RCA-PT-100X failed low.

Select channel "Y" on pressurizer pressure control system.

Refer to alarm response procedure for 4A01B.

CRS Assist diagnosis.

Direct response per alarm response procedure for 4A01B.

Evaluate impact on steam bypass control system.

SO Monitor plant parameters, assist diagnosis, l

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l Examiner Standards Rev.7

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 4 Event No: 4 Page 1 of _ ,_L 1 Event

Description:

CEA #89 drops into core.

i Time- Position Applicant's Actions or Behavior PO/SO/CRS Diagnose CEA #89 drops into core.

I CRS Direct references to alarm response procedures for 4A04B and 4A06B.

Directs action and recovery from 41 AO-lZZ11, dropped or slipped CEA.

Directs actions to stabilize the plant e- Rod control to standby.

Stabilize RCS temperature by reducing turbine load.

• Dilute RCS for xenon effects only.

Directs power reduction IAW Appendix A.

• Begin reduction within 10 minutes.

• Reduce 20% within I hour.

~

• Refer to Tech Spec 3.1.3.1 action C.

Cue: Another reactor operator will perform COLSS Functional Verification ,

and Shutdown Margin procedures. i Determine cause of dropped CEA.

l PO/SO Identify dropped CEA as #89, monitor plant for effects.

Refer to alarm response procedures for 4A04B and 4A06B.

l SO If necessary, take actions to reduce turbine load to maintain T-ave to T-ref mismatch less than 3*F.

Reduce turbine load to reduce power per Appendix "A".

PO Place rod control in " standby". i I

Borate RCS to reduce power IAW Appendix "A".

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Examiner Standards Rev.7 1

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 4 Event No: 5 Page 1 _of _l Event

Description:

Steam generator #2 feedwater flow instrument fails low.

Time Position Applicant's Actions or Behavior CRS/SO identify feedwater control system #2 n.a1.' unction by level rising or alarms 6A06A and/or SA01C/D.

CRS Direct plant stabilization per alarm response for 6A06A.

SO Diagnose feedwater flow instrument fail low.

Place feedwater control #2 master controller SGN-LIC-1112 to MANUAL.

Lower controller output to control and restore ievel in #2 SG.

Return feedwater control system #2 master controller to AUTO as time allows.

PO Monitor plant parameters. -

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1 Appendix D Operator Actions Form ES-D-2 a

l Op-Test No: Scenario No.: 4 Event No: 6 Page 1 of._2 l I

i Event

Description:

Feedwater line break in turbine building, reactor trip, loss of NAN-S06, j failure of emergency diesel generator "B" and AFN-P01.

Time Position Applicant's Actions or Behavior CRS/PO/SO Diagnose and respond to indications of a feedwater line break.

CRS Direct Reactor Trip. May direct MSIS.

Direct PO/SO into Standard Post Trip Actions and Contingency Actions.

Diagnose Loss of All Feed, enter LOAF procedure.

Direct use of Appendix 37 for operation of AFN-P01 after MSIS.

PO Take Standard Post Trip Actions and Contingencies. i e Ensure at least one charging pump is running.

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SO Take Standard Post Trip Actions and Contingencies.

• Ensure MSIS initiated. Ensure heat removal through ADV operation.

• Attempt start on AFA-P01, recognize failure to start.

Perform Appendix 37 for use of AFN-P01 after MSIS.

Inform CRS of failure of AFN-P01, i I

l CRS Transition to Functional Recovery Procedure to recover PBB-SO4 due to loss of MVAC.

• Determine MVAC-1 and HR-2 asjeopardized success paths.

• Direct cross-tic of NBN-X03 to PBB-S04. i e Direct start of AFB-P01 and feeding of SG's.  ;

PO Perform cross-tie of NBN-X03 to PBB-SO4.

SO Start AFB-P01 and ensure adequate feedwater flow to steam generators.

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Examiner Standards Rev.7 )

)

I Appendix D Operator Actions Form ES-D-2 i 3

Op-Test No: Scenario No.: 4 Event No: 6 Page ? of J 4

Event

Description:

Feedwater line break in turbine building, reactor trip, loss of NAN-506, failure of emergency diesel generator "B" and AFN-P01.

Time Position Applicant's Actions or Behavior Scenario may be terminated when PBB-S04 is energized and AFB-P01 is supplying feedwater to the steam generators, or as deemed appropriate by 4

the exam team. .

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Examiner Standards Rev.7

\l Appendix D Scenario Outline Form ES-D-1 l

1 Facility: PVNGS Scenario No.: 5 (standby) Op-Test No:

Examiners: Operators:

Objectives: Evaluate the crew's response to a reactor regulating system instmment failure.

Evaluate the crew's response to a reactor power cutback / loss of feedwater pump.

Evaluate the crew's response to a feedwater control system instrument failure.

Evaluate the crew's response to an anticipated transient without a scram.

Evaluate the crew in using the EOPs during a loss of coolant accident.

Initial Conditions: 75% power, equilibrium xenon, middle of cycle Turnover: The following equipment is out of service:

SIB-P02, high pressure safety injection pump, has been out of service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for seal replacement. Estimated return is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. -

l

• NCN-P01B is out of service for motor replacement. Estimated return in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. I Previous shift halted power ascension at 75% for turnover. Dilution rate was 60 gpm and total gallons remaining to dilute are 7,350. Continue power ascension to 100% power in )

,. accordance with 400P-9ZZ05, Power Operations, at step 5.3.39. j Event Malf. Event Event Description  !

. No. No. Type' 1 N/R Continue power ascension.

2 TROI:RCNT I RCS T-hot instrument fails low.

Tl1IX 3 FWO4B C Main feedwater pump "B" tnp.  !

4 TROI:SGNL 1 Steam gene.ator #1 level instrument fails high.

Till2 5 TCl1 M Turbine control failure resulting in pressurizer pressure high trip.

CAE C e ATWS.

6 RV02:RCEP M Pressurizer safety valve fails open.

SV202 MV04:SIBU C = HPSI "A" injection valves do not auto open.

V616 7 C Pressurizer safety valve rescats at 1200 psia.

Implement 40EP-9EOO3, Loss of Coolant Accident, to stabilize plant and initiate controlled cooldown.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards ' ls y R .8 u___. _ -. _ __

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

i Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 5 Event No: 1 Page 1 of _1 Event

Description:

Continue power ascension.

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_ i Time Position Applicant's Actions or Behavior CRS Directs use of 410P-lCif01 to initiate dilution at the desired rate.

Directs SO to raise turbine load to maintain T-ave to T-ref mismatch less than 3 *F. I PO Initiates dilution to the suction of the charging pumps per 410P-lCII01, Section 9.0.

Sets CIIN-FIC-210X to 0 setpoint with 0 output demand.

Selects DILUTE on makeup mode selector switch.

Checks reactor makeup water pump running, CIIN-UV-527 OPEN.

Adjusts CilN-FIC-210X output to desired dilution rate.

SO Monitors T-ave to T-ref mismatch on B04.

Increases turbine load to maintain T-ave to T-ref mismatch less than or equal to 3 'F.

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I Examiner Standards Rev.8

-- - - . .- .1

Appendix D Operator Actions Form ES-D-2

~

Op-Test No: Scenario No.: 5 Event No: 2 Page 1 ofJ Event

Description:

Reactor coolant system T-hot instrument fails low.

Time Position Applicant's Actions or Behavior PO/SO/CRS Diagnose RCN 'IT-11IX is failed channel.

CRS Direct references to alarm response procedures for 4A01A, 4A080 and 4A10B. Directs action and recovery from 41 AO-12Z34, Reactor Regulating System Malfunction.

Directs actions to stabilize the plant

+

Operate pressurizer level control system and/or charging pumps to maintain pressurizer level.

• Ifletdown isolates, direct restoration ofletdown.

Direct SO to select T-avg #2 on reactor regulating system cabinet.

PO/SO Refer to alarm response procedures for for 4A01 A,4A08B and 4A10B.

PO Place pressurizer level control system in LOCAL-AUTO with setpoint at

~53%.

May start additional charging pumps to maintain letdown.

If letdown isolates on high regenerative heat exchanger outlet temperature, perform steps to restore letdown.

• CLOSE letdown control valves using RCN-LIC-110.

• OPEN backpressure control valves using CHN-PIC-201.

• After opening CH-UV-515, slowly restore letdown flow and return controllers to desired status.

SO Assist in diagnosis of RCN TT-11IX failure.

Select T-avg #2 on reactor regulating system cabinet.

v Examiner Standards Rev.8

Appendix D Operator Actions Form ES-D-2 Op-Test No: Scenario No.: 5 Event No: 3 Page 1 of __[

Event

Description:

Main feedwater pump "B" trip, reactor power cutback.

Time Position Applicant's Actions or Behavior CRS/SO/PO Dia; nose loss of feedwater pump "B", reactor power cutback by plant idicm : ions and alarm 6A09A.

CRS Direct plant stabilization using 40AO-9ZZ09, Loss of Feedpump. -

Direct removing reactor power cutback system from service.

Direct clearing turbine increase inhibit.

SO Monitor steam generator levels, feedwater flow, and steam flows to ensure proper feedwater control system response.

Assist in monitoring pressurizer pressure.

Lower turbine control potentiometer until the LOAD LIMIT light is on.

PO Monitor pressurizer pressure.

Take reactor power cutback system out of service by depressing the OUT OF SERVICE and TEST / RESET buttons.

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Examiner Standards Rev.8

l l .

i .- Appendix D Operator Actions Form ES-D-2 1

Op-Test No: Scenario No.: 5 Event No: 4 Page 1 of_1 i 1

l Event

Description:

Steam Generator Level Transmitter LT 1112 fails high to #1 Feedwater Control System.

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l Time Position Applicant's Actions or Behavior SO Diagnose problem with SG #1 level, FWCS #1 and LTl112.

i Refer to alann response for 6A06A "FW CONT SYS TRBL" on lesel channel deviation.

l Take manual control of FWCS #1 and restore SG #1 level to 50R Determine failed instrument as LT-1112.

Select unaffected channel (LT-lll2) at 1 WCS #1 panel.

Restore FWCS #1 to AUTO.

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CRS Assist diagnosis.

Direct SO activities from alarm response procedures to recover SG #1 level.

l Contact I&C to troubleshoot / repair.

PO Monitor control boards, assist diagnosis.

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l Appendix D Operator Actions Form ES-D-2 i t

i Op Test No: _ Scenario No.: 5 Event No: 5 Page 1 _of__1 i

! i Event

Description:

Turbine control system malfunction, ATWS.

)

Time Positian Applicant's Actions or Behavior CRS/PO/SO Diagnose and respond to indications of a loss ofload on the turbine. l Recognize reactor trip signals on high pressurizer pressure. I i

CRH Direct Reactor Trip.

Direct PO/SO into Standard Post Trip Actions and Contingency Actions. )

SO Take Standard Post Trip Actions and Contingencies.

• Manually trip reactor using pushbuttons on B05.

l PO Take Standard Post Trip Actions and Contingencies e Open feeder breakers for NGN LO3 and NGN-LIO until CEAs drop into the core.

Examiner Standards Rev.8

y . .-. -- .. .- - . . . - - - . - _ - _. . - . - . ... -

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I Appendix D Operator Actions Form ES-D-2 i Op-Test No: Scenario No.:_ 5 Event No: 6 Page 1 of J l

l Event

Description:

Pressurizer safety valve sticks open, degraded high pressure safety injection, pressurizer safety valve rescats.

i Time Position Applicant's Actions or Behavior PO/CRS/SO Diagnose pressurizer safety valve open.

l CRS Diagnose loss of coolant event, enter LOCA procedure.

Direct maximum charging and safety injection flow.

Direct a rapid cooldown to shutdown cooling entry.

Direct throttling ofinjection flow after valve has rescated. '

PO Ensure maximum charging and safety injection flow.

Recognize and correct failure of HPSI "A" injection valves.

Trip reactor coolant pumps as required (2 on pressure <1837 psia.)

Recognize pressurizer safety valve has reseated.

Throttle IIPSI when throttle criteria is met.

SO Ensure proper feedwater flow to each steam generator.

Cooldown using main / auxiliary feedwater and and steam bypass control system or atmospheric dump valves.

Increase heat removal from the secondary side while PO is throttling HPSI flow.

The scenario may be terminated when HPSI flow is throttled, RCS pressure is under control, and a controlled cooldown to shutdown cooling entry is in progress, or as deemed appropriate by the exam team.

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