ML20058Q399

Exam Repts 50-324/OL-90-04 & 50-325/OL-90-04 on 900725 & 26. Exam results:1 of 2 Crews Evaluated & 9 of 12 Operators Performed Satisfactorily.One Operator Passed Requalification Exam

ML20058Q399
Person / Time
Site:	Brunswick
Issue date:	08/15/1990
From:	Munro J, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058Q397	List: ML20058Q396 ML20058Q399
References
50-324-OL-90-04, 50-325-OL-90-04, NUDOCS 9008220067
Download: ML20058Q399 (86)

Text

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3 g n' Rah n bNITED STATES d' " ', g*o i NUCLEAR REGULATORY COMMIS$10N:

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~ yi REGION 11 101 MARIETTA STREET,N.W.

~I 2- ATLANTA, GEORGI A 30323 l .

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-Report Nos. 50-324/90-04 and 50-325/90-041 h" Facility Licensee: Carolina Power and Light Company; '

P. O' Box 1551

~ Raleigh, NC- 27602 ll '

' Facility Docket Nos.: 50-325 and 50-324 4 +

H' ( Facility License Nos.: DPR-71'and DPR-62 l... h .,

(FacilityName: Brunswick 1 and 2' l i +

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'E' ' Inspector: ~ - -

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Date Signed-_ s

, , p John F. Munro #

i Team ~ Members: C. Payne, Region II ,

O C. Gratton, OLB, NRR g T. Bettendorf, PNL 4

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G. Hopper, Region 11 i-L( ,

Qppoved'By:

Thothafs A.- Peebles, Chief 21bfd Date Signed

)

I. L0perations Branch q l

Division of Reactor Safety 9 L

SUMMARY

]

(l Scope:

_This was a special announced inspection of crew evaluations on-the Brunswick.  ;

j simulator in accordance with NUREG-1021, ES-601. Both the facility and NRC L . evaluators assessed the ability of two crews of licensed operators to safely i function;and operate as a team prior to allowing their' return to licensed 1

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Results:

The NRC' determined that one of two crews evaluated, and nine of twelve ._ -l

. operators performed satisfactorily during-these evaluations. One operator was 1 administered a complete requalification retake examination and passed.

Significant weaknesses in' senior reactor operator command / control and d Emergency Operating Procedures were again demonstrated primarily by one crew.

900822OOg((j@$h24 ADO POR PDC v .l

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REPORT DETAILS

1. Persons2 Contacted R. Starkey, Brunswick Site.Vice President J~. Harness, Brunswick Site Manager J. Moyer, Assistant to Site Manager L. Martin, Corporate Training Director F. Blackmon, Manager of Operations

• R. Poulk, Project Specialist Operator Training Other instructors and technicians NRC Representatives J. Munro, Chief, OLS 1, ORS, Region II C. Payne, Examiner, Region II G. Hopper, Examiner, Region II T. Bettendorf, Examiner, PNL C. Gratton, Examiner, NRR R. Prevatte, Senior Resident Inspector .

W. Levis,. Resident Inspector j NOTE: Acronyms and initialisms used throughout this report are listed in the last section. -

2. June 9 - 10, 1990, Site Visit '

The evaluation team observed simulator performance of two shift crews.

The crews consisted of an S0S, SF, SCO, and.two R0s. One crew was administered three simulator scenarios, and one crew was administered two simulator scenarios. Scenarios were designed to evaluate previously demonstrated generic weaknesses and were administered and evaluated in i accordance with tie guidance of Revision 5 to the Examiner _ Standards, ,

NUREG-1021. '

The following list outlines the crews and the specific scenarios on which they were evaluated.

Crew C: Scenario #23 - PCIS Valve Failure, Main Turbine Oil Temperature Controller Failure, Turbine Bypass Valve Failure, HP Injection Failure, Loss of 480v Substation, -

Recirc Discharge Line Leak in Drywell, Failure of Drywell Sprays.  ;

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5 Scenario #24 - HPCI-CST Leval Switch Failure, Circulating Water Leak in the Turbine Building,- RPS' Electrical- Failure,. HPCI Injection Valve Failure, DW Floor and Equipment Drain Line Valve Failure, Recirc Suction Line Rupture in Drywell, Core Spray Loop Injection Failure.-  :

Crew F: Scenario #23 - See Above.

, Scenario #24 - See Above.

Scenario #7 - Stator Cooling Failure, BPV Failure, ATWS, Stuck Open Relief Valve, SPDS out of service,

a. Crew C (1) Scenario 23 i The SF failed to direct initiation of torus sprays (RHR 1 w o A) when torus pressure exceeded 1.8 psig. The SOS indicated to the SF that RHf. loop A torus sprays were operable and directed their initiation approximately four minutes later. During

-post-scenario questioning, the SF stated-in effect that he-did-not initiate torus sprays from RHR loop A because he simply forgot that they remained operable. The examination team reviewed the validation of this ISCT following the examination.- ::

The examination team determined that a delay,of approximately 15 seconds for initiation of torus sprays would-significantly >

change the mitigation strategy, i. e., unsafe area of HCTLH curve entered requiring an emergency depressurization. . Based on the potential different outcomes,- irrespective of torus spray initiation, the task was determined not to be critical within the context of this scenario, i

The: performance of the crew and individual operators-on.the.

scenario and related ISCTs was satisfactory. The failure of the SF and crew to initiate torus sprays in accordance with-E0P-02-PCCP was found to be a significant error, but not critical within the context of this scenario.

(2) Scenario 24

.The.SF failed to direct verification or manual initiation of group isolations in accordance with'E0P-01-EPP. This oversight allowed the failure to close of the Drywell and Equipment Drain Line Isolation Valves to go undetected until receipt of the "Drywell Equip Drain Sump Lvl Hi" and "Drywell Equip Drain Sump i Leak Hi" alarms. At this time, the SOS mitigated the error by directing the operator to close the isolation valves, i 1

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- The performance of the crew and individual operators on the- il scenario and related'ISCTs was satisfactory. 1

- The crew and all individuals were rated satisfactory by both NRC and licensee evaluators. It was tlso agreed that the weaknesses l displayed by the SF on E0P usage were significant, but did not merit H failure. '

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b. Crew F l (1) Scenario 23 The SF directed initiation of RHR loop A drywell and torus sprays when torus pressure exceeded 13 psig. This direction was in-error in that drywell sprays from RHR loop A were inoperable. Additionally, torus sprays from RHR loop A were-not initiated and shift management failed to exercise' proper command / control and redirect this action. Drywell and torus

. sprays were initiated later from RHR loop B following restoration of bus E-8.. During post-scenario questioning, the S0F incorrectly states that procedural concerns made it difficult to initiate torus sprays prior to drywell sprays for J

-a: rapid = increase in torus / containment pressure.  !

The performance of the crew and individual operators on the -i scenario and related ISCTs was satisfactory. The failure of -

the SF and crew to initiate torus sprays from RHR loop A was l".

found to be a significant error, but not critical within the context of the scenario.

(2) Scenario 24 The SF failed to direct verification or manual initiation of >

group isolations in accordance with E0P-01-EPP. This oversight allowed.the failure to close of the Drywell and' Equipment Drain Line Isolation Valves to remain undetected throughout' the scenario. ..The significance of the drywell level high and leak

- high alarms was not recognized. As a result, water was improperly pumped. from the containment- to radwaste. <

l The NRC and licensee evaluators graded the SF's and SOS's l performance-as unsatisfactory due to failure to properly exit E0P-01-FP3~and enter and direct activities of E0P-01-EPP,

i. e., failed to direct verifications of group isolations -

ISCTs #5 and #9. The NRC evaluators graded the S0S's performance as unsatisfactory due to his failure to exhibit proper command / control and assist the SF to mitigate significant safety-related adverse consequences - ISCT #1. The l

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111censee evaluators graded the SCO's performance as. l unsatisfactory-in that he was unable to display a proper j understandnig of the application of E0P Caution #1 (level '

indication).

.(3) Scenario 7 The SF did not properly direct three critical actions in accordance with E0P-01-LPC, E0P-01-EPP, and E0P-01-PCCP.

SLC initiation _was directed at 160 degrees F in the Suppression Pool (required at 110 degrees F) - ISCT #6. '

Lowering of RPV level to TAF was directed at 177 degrees F '

in the Suppression Pool.(required at 110 degrees F).

Suppression Pool temperature was in excess of.110 degrees F for approximately five minutes - ISCT #7.

Plant parameters were~ in the unsafe area of the HCTL curve i for approximately five minutes prior to the required l Emergency Depressurization,being directed - ISCT #10.. l 1

The SCO contributed to these errors by'not properly monitoring  ;

HCTL - ISCT #22.

u i The NRC and licensee evaluators graded the crew and individual operator's performance as unsatisfatory due to the failure to l

4 perform the following ISCTs:  !

SLC initiation not directed at 110 degrees F SF-1)

Suprression Pool temperature - ISCT #6. ]j

2) RPV level not lowered at TAF at 110 degrees'F  !

Suppression Pool temperature - ISCT #7.

3) React'or pressure not maintained in the safe area of L- HCTL curve -'ISCT #10. il L ,  !

SCO-1) HCTL not properly monitored ISCT #22.  :

S0S-1) Direction and/or assistance not provided to mitigate- ,

the safety-related errors previously noted - ISCT #1.

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-The crew was rated unsatisfactory on scenarios #24 and #7 and also' ,

due to a total of-seven ISCTs being performed unsatisfactorily. The '

three SR0s evaluated were rated unsatisfactory on scenarios #24 and

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3. Exit Interview a The Team Leader met with licensee management on July 26, 1990, after completion of the Operational Evaluations. . Licensee management was ,

informed of the individual and_ crew results. On July 31, 1990, licensee management was informed that two operators, whose final results were pending on July 26, had been evaluated, _ after additional NRC review, to have passed.

Additionally, licensee management was advised of two generic weaknesses exhibited by the operators in the use of the E0Ps. First, the operators did not properly prioritize the initiation of torus spray in accordance with E0P-02-PCCP. A similar weakness was noted in Examination Report No.

50-325/0L-90-01. The licensee has since conducted real_ time training for the operating shifts on the proper utilization of torus sprays and is including this subject in requalification training for all operators.

Second, the operators did not properly verify group isolations in accordance with E0P-01-EPP Step RC/L-03. The licensee has since indicated that the proper accomplishment of this step, under various scenarios, will be emphasized during requalification training. In

• addition, the. licensee is reviewing the information provided by ERFIS on -1 PCIS status to insure that is not misleading the operators, t

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Acronyms and Initialisms o

ADS Automatic Depressurization System ATWS Anticipated Transient Without Scram B0P Balance of Plut Operator BPV. Bypass Valve CST- Condensate Storage Tank DG Diesel Generator DRS- Division of Reactor Safety DW Drywell E0P Emergency Operating Procedure EPP End Path Procedure ERFIS Emergency Response Facility Information System High Pressure i HP i

HPCI High Pressure Coolant Injection  ;

ISCT Individual Simulator Critical Task  :

LOCA Loss of Coolant Accident LP Low' Pressure

l. LPC Level Power Control L'

MSIV Main Steam Isolation Valve NI Nuclear Instrumentation l

PCCP Primary Containment Control Procedures PCIS Primary Containment Isolation System l

RBCCW- Reactor Building Closed Cooling Water RCIC Reactor Core Isolation Cooling System L

ir j i.

6 RHR Residual Heat Removal System R0 Reactor Operator RPS- Reactor Protection System SCO Senior Control Operator

• Reactor Trip SCRAM SF Shift Foreman SLC; Standby Liquid Control SOS Shift Operating Spervisor ,

'SPDS Safety Parameter Display System SR0 Senior Reactor Operator STA Shift Technical Advisor TAF Top of Active Fuel i

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• ENCLOSURE ~2 - SR0 j

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NAME:

DATE: 07/23/90 CLASS: MIKE'S -

I EXAM: LOR-2 WK3 SRO-A4 PREPARED.BY: JERNIGAN i

GRADED BY: l ALTERNATE GRADER: {

TOTAL POINTS: 12.00 POINTS MISSED:-

SCORE:

o  ;

1. EXAM TIME LIMIT I8 1.0 HOURS

2. Do not' write on exam. (except on attachments)  ;

3. Do not write-on back of pages. Ll

4. A score of 80% is required for. passing.

l 5.- Use only black ink on this exam. Cross out all errors with a single line and initial and date.

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I have neither.given nor received help'on this exam. '

L All work is my own.

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Signature l

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Exam R iewer 1

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~**' HLOR-2 WK3 8RO-A4H EXAMINATION ** .

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. QUESTION '1- POINT VALUEt'1.00  ;

If no operator actions have.been taken or will take place, when will the 2B control building sump pump change states: -:

a. Approximately 10 minutes when the low level switch is made up.z .

b. Approximately 10 minutes when the high level clears.

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c. With no operator action it will not change state.

d. 15' minutes'when the pump timer times out.

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• • " LOR-2 WK3 BRO-14" EXANINATION ** ,

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,- QUESTION? 2 '. ' POINT.VALUE* 1.00

, If an E &'RC. analysis indicates a specific: activity of;the reactor l,  ; coolant of-0.25 pCi/gm dose equivalent I-131 for current plant , .

conditions. Assuming-the activity level remains unchanged.for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, Ethe plant may continue to operate in its current mode for: (select the w correct ~ answer.)

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a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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c. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

L d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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#6 HLQg.g gg3.SRO-A4" EIAMINATION

, QUESTION 31 POINT VALUE' 1.00 Assuming current condits ,ns lead to a reactor' scram, the operating crew .

~chould prevent-draining the scrna discharge volume by: (Select the  ;,

correct answer.)

Ha . resetting the scram.

3 placing the: discharge volume. vent and drain test switch to .. ISOLATE.

Eb. >

'c. placing the discharge volume high water trip bypass switch to BYPASS.

d. taking no action.

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• • HLOR-2. WK3 SRO-A4 EXAMINATION **

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I 'i L QUESTION ~ 4- . POINT.VALUE '1.00 1: 4 I? After assessing the' current status of the plant, the appropriate .

. classification of:the' event.would'be: (Select. the correct answer. ) .i lf e.. None' required' a jt u b. Unusual Event l'

L c.. Alert >i l-

' Site Emergency

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le..' General Emergency j h'

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• • - " LOR-2 WK3 SRO-A4" EIANINATION **

~ QUESTION 5 POINT VALUE: 1.00

On the current plant configuration, if the operator attempts to insert ,

c-control rod, the Drive Water Header Pressure Inidcator (Cl2-PI-R601) .

Will: (Select the correct answer.) I

a. remain. constant and the rod will insert at normal insert speed.

b.. decrease and the rod will insert at slower than normal insert  !

speed. '

c. increase and the rod will insert at faster than normal insert speed.

d. remain constant and the rod will insert at slower than normal insert speed.

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• • " LOR-2'NK3 SRO-A4" EXAMINATION **

l QUESTION- 6 POINT.VALUE: 1.00 During the. current evolution, additional power decreases would be

-011 owed by: (Select the correct answer.)

e. additional reduction of recirculation flow. q

b. a combination of recirculation flow reduction and control rod insertion..

c. injection of liquid poison. .

d. control rod insertion only..

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• • - HLOR-2 WK31SRO-A4" SIANINATION'- ** l

QUESTION- 7 POINT-VALUB 1.00 If at this time the operator depressed

the: Manual Isolation system ~A -

cwitch, which of the-following would occur?:

a. E41-F003 and E41-F041 will close.-

b. Nothing will happen. 1;

c. E43-F002 and E41-F042 will close,

d. E41-F003 steam supply only will close.

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• • HLOR-2 WK3-SRO-A4".EXANINATION- **

QUESTION 8l POINT VALU8t l.00

.Considering the condition-of the Suppression Chamber to Drywell Vacuum Breakers CAC-X18, a steam line rupture inside the primary containment ',

would probably cause which of the following? j

'a. The Pressure Suppression Pressure to be exceeded,

b. Contamination of the' secondary containment.

c. The suppression chamber air space to be filled with non-condensable gasses only at 13 psig.

d. No concern as the vacuum breakers only relieve from the suppression chamber to the drywell.  :

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- **.. HLOR-2 WK3 SRO-A4H-EXAMINATION. ** -

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- QUESTION 9 ' POINT : VALUE : 1. 00 - i U'nder' current' plant' conditions,.what automatic actions.should have occurred-but did.not? ,

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• • " LOR-2 WK3'SRO-A4" EXAMINATION **

QUESTION 10 POINT VALUEt 1.00

-If~the EHC pressure set INCREASE pushbutton is accidentally-depressed and then immediately released, the EHC system would:-

a '. cause the turbine bypass valves to go-fully open.

be swap reactor pressure regulators.

c.- cause the control valves to initially move towards closed, then j return to near their original positions.

d. : caur, the control valves to initially move towards open, then L return to near their original positions.

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• • -HLOR-2 WK3 SRO-A4".EXANINATION **

QUESTION 11 POINT VALUE: 1.00 How will the AOG System be affected by the' current event?

a. AOG-HCV-102 should have closed,

b. AOG-HCV-102 will close when the 15 minute' delay has elapsed.

c. The OG-V7 will close tripping both mechanical. vacuum pumps. ,

d. The standby filter.will atuomatically. align to reduce the ]

release rate. '

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• • . " LOR-2 WK3 SRO-A4" EXAMINATION **

[ . QUESTION, 12: POINT VALUE: 1.00 1 .o;- During.the--current evolution, if the reactuit coolant' activity. increased iby 90%,.the APRMs would: (Select the corrw . answer.). ,

a. ' spike up.then return to normal.

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b. increase by approximately 9%. ,

c. not be affected.

d. go'off-scale high, causing a scram.

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• • .HLOR-2 WK3 SRO-A4" ANSWER KEY **  ;

i QUESTION: 1 RECORD: 825,- LSA0427' POINT VALUE: 1.00 LESSON PLAN: 00-..Objectivest-01 ,

If no operator actions have been taken or will take place, when will the'2B control building sump pump change states:  ;

a. Approx'imately 10 minutes when the low level switch is made up.

b. Approximately 10 minutes when the high level clears,

c. With-no operator. action it will'not change state.

d. 15 minutes'when the pump timer times out.

-ANSWER: 1 i

c.

QUESTION '2 RECORD: 317, LSA0405 POINT VALUE: 1.00 LESSON PLAN: 07-2B Objectives: 05 , ,

If an E & RC analysis' indicates a specific activity of the reactor.  ;

coolant of 0.25 pCi/gm dose 1 equivalent I-131 for current plant conditions. Assuming the activity level remains unchanged for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the plant may. continue to-operate in its current mode for: (Select the correct answer.),

a. .4. hours. 1

b. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t L ANSWER: 2 1

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• • l " LOR-2 WK3 SRO-A4H ANGWER REY CONTINUED **

t fQUESTION :31 RECORD:~811, LSA0417 POINT VALUE: 1.00 .

LESSON PLAN: 07-2K-7 Objectives: 00-,

' Assuming current conditions lead to a reactor scram,.the operating crew'  ;

-should prevent draining the scram discharge volume by: (Select the +

correct answer.)

a. .. resetting the. scram.

i placing the discharge volume. vent and drain test switch to I.COLATE.'

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b.

c. placing lthe discharge volume high water trip bypass switch tv '!

BYPASS.

L d. taking no action.

ANSWER: 3 L 'b.

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QUESTION: 4- RECORD: 338, LSA0407 POINT VALUE: 1.00 LESSON PLAN: 07-;1 Objectives: _13 ,

After assessing the current status of the plant, the. appropriate classification- of the event would be: (Select the correct answer.)

a.- None required

b. Unusual Event-

c. Alert

-d' . Site Emergency ,

e.. . General Emergency i

ANSWER: 4 b.

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• • " LOR-2 WK3 SRO-A4" ANSWER KEY CONTINUED **

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. QUESTION: 5' RECORD: 819, LSA0422 1 .00 POINT VALUE: .

LESSON PLAN: 09-2B Objectives:=06 ,

In the current plant configuration, if 'he c operator attempts to insert

a. control rod, the Drive Water Mcader Pressure Inidcator (C12-PI-R601) will: (Select the correct answer.)

a. remain constant and the rod will insert at normal insert' speed. ,

b. . decrease and the rod will insert at slower than normal insert speed.

c.- increase and the rod will insert at faster than normal insert speed.

l d. remain constant and the rod will insert at slower than normal L insert speed.

ANSWER: 5 b.

QU88 TION: 6 RECORD: 812, LSA0418 POINT VALUE: 1.00 LESSON PLAN: 10-2A Objectives: 05 ,

During the current evolution, additional power decreases would be allowed by: -(Select the correct answer.)

a. additional reduction of recirculation flow,

b. a combination of recirculation flow reduction and control rod-insertion.

c. injection of liquid poison.

d. control rod inaertion only.

ANSWER: 6 ,

l d.

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• ** " LOR-2-WK3 8RO-A4"lAN8WER KEY CONTINUED- **' 4 i

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. QUE8 TION: 7 . RECORD: 824, LSA0426 LESSON PLAN;.14-2B POINT VALUE:~1.00. j Oojectives:.01 , 1 N 'If!atrthic time the. operator depressed the Manual = Isolation system A. t switch, which,of theafollowing-would occur?-

a. E41-F003 and E41-F041 will close, ,

b. Nothing wil' happen. ,

c. E41-F002'and E41-F042 will close.

d. E41-F003 steam. supply only will close. .;

d ANSWER: -7 l

l b.- j y . . ...... ..............................................'..............

j . QUESTION: 8 I RECORD:~ 823, LSA0425 ' POINT VALUE: 1.00 LESSON PLAN: 15-2A Objectives: 01' ,

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1Considering the condt; ion of the suppression Chamber to:Drywell Vacuum Breakers CAC-X18, P. steam line. rupture inside the primary containment T would probably~cause whichlof the following? "l

a. The. Pressure Suppression Pressure to be exceeded. '

b. Contamination 1of the secondary conta'inment.

c. The suppression-chamber air space to be filled with non-condensable. gasses only at 13.psig.  ; ;;

d. No concern as the' vacuum breakers only relieve from the suppression' chamber to the drywell.

L .AN8WER: C l

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. QUESTION c9 RECORD: 810, LSA0416 POINT VALUE:.1.00 3 LESSON PLAN:-15-25 Objectives: 05 ,

Under current plant conditions,'what automatic actions.*,JouldLhave:

occurred-but did>not?-

ANSWER: 9 j

.l. ~ group 6 isolation 1

:2 e reactor building HVAC isolation-

3. . automatic start-of.both SBGT trains j eoeeeeeeeeeeeeeeoeeeeeeeee .eeeeoe...eee .eeeeeeeoeee. ee. ee .eoe.. ,

QUESTIONS,10 RECORD: 818, LESSON PLAN: 17-2B LSA0421 POINT VALUE: 1.00 Objectives: 07 - , ]

'If'the:EHC pressure set INCREASE pushbutton'is accidentally depressed

-and then-immediately released, the EHC system would:

it ao cause'the turbine bypass valves-to go fully open. 'i be swap reactor pressure regulators. s!

co- cause the control valves to-initially move towards closed, then:

return to near their original positionse de cause the control valves to initially move towards open, then return to near their original positions. .

-l ANSWER: 10  !

c.

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• • "IAR-2 WK3 SRO-A4H ANSWER KEY ?X)NTINUED **

i QUESTION: 11 RECORD: 822, LSA0424 POINT VALUE: 1.00 LESSON PLAN: 24-2A Objectivest 01 ,

How will the AOG System be affected by the current event?

a. AOG-HCV-102 should have closed.

b. AOG-HCV-102 will close when the 15 minute delay has elapsed.

c. The OG-V7 will close tripping both mechanical vacuum pumps.

d. The standby filter will atuomatically align to reduce the release rate.

ANSWER 11 b.

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• • " LOR-2 WK3 SRO-A4H ANSWER REY CONTINUED **

QUESTION: it RECORD 814, LSA0420 POINT VALUEt 1.00 LESSON PLAN: 25-2D Objectivest 00 ,

During the current evolution, if the reactor coolant activity increased by 90%, the APRMs wouldt (Select the correct answer.)

a. spike up then return to normal.

b. increase by approximately 9%.

1 L c. not be affected.

. d. go off-scale high, causing a scram.

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ANSWER 12 c.

eeoe................................................................-

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• • END OF EXAM **

12.00 POINTS 100% VALUE, 9.600 POINTS 80% VALUE ESTIMATED TIME TO COMPLETEt 46 MINUTES REQUIRED

REFERENCES:

.i i

i PAGE'7 OF 7 l 1

l 1

=ba ENCLOSURE 2-SRO 9 .

O NAME:

DATE: 07/23/90 CLASS: MIKE S.

EXAM: LOR-2 WK3 SRO-E3' PREPARED BY: PITT JERNIGAN GRADED BY:

ALTERNATE GRADER:

E (if required)

TOTAL POINTS: 12.00 t- . POINTS MISSED:

fj SCORE 1

1. EIAM TIME LIMIT Z8 1.0 MOUR8

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

m 4.. A score of 80% is required for passing.

5. Use only black ink on this exam. Cross out all errors with a single line and initial and date.

I have neither given nor received help on this exam.

All work is my own.

I Signature

_t TYb e i J4b Exam R . ewer Approver N i

n i == =-- - --

.o ,,

-e

)

• • " LOR-2 WK3 8R0-33" EIANINATION **

QUESTION 1 POINT VALUE: 1.00 For the current transient, assuming RPV pressure is 900 psig, what are the reactor water level upper and lower limits in inches? -

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• • HLOR-2 WK3 SRO-33" EEAMINATION **  ;

i QUESTION 2 POINT VALUE 1.00 During the current evolution (EOP-02-PCCP) requires a reactor cooldown.

This may be commenced when: (Select the correct answer.)  ;

o. all control rods, except one, have been fully inserted,

b. the entire contents of the SLC tank have been injected.

c. emergency depressurization is anticipated.

d. emergency depressurization la required.

)

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• • MLOR-2 WK3 SRO-33" EEANINATION ** l QUESTION 3 POINT VALUE 1.00 For current plant conditions, if the reactor water level was returned to the normal range, the reactor power should: (Select the correct Cnswer.)

o. not change.

b. ' increase to approximately 60%.

c.- increase to approximately 30%.

I

d. decrease.

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• • HLOR-2 WK3 BRO-E3H EEANINATION ** 1 QUEST.'ON 4 POINT VALUE: 1.00 During the current evolution the operator may avoid unnecessary rod blocks ey bypassing the RWM, (Select the correct answer.)

o. bypassing the SDV high water level trip and using the emergency rod in override switch.

b. positioning the RSCS switches to bypass and using the emergency rod in overrido switch. I

c. placing the mode switch to refuel and using emergency rod in override switch.

d. repositioning the RSCS RTGB switches to normal-normal and use the l continuous rod insert switch.

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(

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• • HLOR-3 WE3 SRO-33H EEAMINATION **

1

)

QUESTION 5 POINT VALUE 1.00 i For present plant conditions, the reactor power is at its current l value because: (Select the correct answer.) j O. LEP-02 is not being executed. l

b. RPV water level was deliberately lowered.

c. the liquid poison pumps were started too late.

d. LEP-03 takes a long time to execute due to routing hoses. j l

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• • " LOR-2 WK3.8RO-33H EEANINATION **

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QUESTION 6 POINT VALUEt 1.00 Assume that the suppression pool temperature continues to increase and ,

the reactor pressure remains at its current value. Which one of the  ;

following critical steps would you use to avoid exceeding the heat '

capacity temperature limit? (select the correct answer.)  ;

l

0. Decrease the reactor pressure per EOP-02-PCCP. j

b. Decrears the reactor pressure per EOP-01-EPP.

1

c. Activate Emergency Depressurir.ation Anticipated, EOP-01-EPP. l L 'd. Activate Emergency Depressurization Required, EOP-01-EPP. I I

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• • " LOR-3 WK3 SRO-53" EXANINATION **

f

-QUESTION 7 POINT VALUE: 1.00 After assessing the current status of the plant, the appropriate

classification of the event would bet (Select the correct answer.)  ;

c. None Required

b. Unusual Event O. Alert i

d. Site Emergency  !

O. General Emergency t

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• e HLQg.g gg) ggO.g3H EEANIMATION ** l QUESTION 8 POINT VALUE 1.00 r

The following NRC notifications are required as a result of the current l' plant conditions: (Select the correct answer.)

O. No report required.  !

b. One hour red phone report. >

c. Four hour red phone report. [

d. Twenty four hour red phone report.

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• . l et HLOR-2 WK3 SRO-E3" EEAMINATION **

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QUESTION 9 POINT VALUEt 1.00 Concerning the present osition of the Reactor Recirc Pump Discharge l valves, which of the fo lwing statements is true?

1

a. The valves have been closed in preparation for shutdown I cooling, l

b. The valves closed when the pumps.were. shutdown.

c. The valves closed on RPV low leve1. ,

d. The' valves were closed by operators to reduce natural circulation per the Level Power Control Procedure.

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! l et HLOR-2 WK3 SRO-E3H EXANINATION **

QUESTION 10 POINT VALUEt 1.00 I

t Due to the suppression pool high temperature, A Loop RHR was placed in SP cooling prior to the SCRAM. The o perator is directed by PCCP to return RHR to SP cooling. Which of tae followig statements are correct concerning A Loop RHR?

a. When the timer times out, close E11-F017A to prevent injection and restart SP cooling per hard card.

b. Place the 2/3 core height switch in Manual override then place the Think Switch in manual and start system in SP cooling.

c. Place Think Switch to manual then place the 2 switch to Manual Override and start system in/3 SPcore height cooling.

d. The system cannot be returned to suppression pool cooling mode.

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• • HLOR-2 WE3 SRO-E3H EXANINATION **

QUESTION 11 POINT VALUE '1.00 Which of the following would cause 2B RHR pump to start?

a. A loss of off-site power resulting in sequence loading of the DG's.

b. Low RPV pressure with High DW pressure,

c. ADG logic actuation.

d. Manual start.

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• • " LOR-3 WK3 SRO-E3H EXANINATION **

i QUESTION 13 POINT VALUE: 1.00 The proper operation of the D m ell Floor and Equipment Drain System for the current conditions would bei

a. The pumps run only if started in manual recirc mode. l

b. The pumps will neither run in discharge or recirc mode. j

c. The DW Equi ment Drain Pumps should be running in recirc mode due to the igh temperature. l t

d. The DW Floor and Equipment Pumps will only start on High High '

sump level.

• • END OF EXAN ** ,

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• • HLOR-2 WK3 SRO-E3H ANSWER KEY **

QUESTION: 1 RECORD: 816, LSE0322 POINT VALUEt 1.00 LESSON PLAN: 07-2K-1 Objectivest to ,

For the current transient, assuming RPV pressure is 900 psig, what are the reactor water level upper and lower limits in inches?

ANSWER 1 Upper limit -36 inches 0.50 accept ~36 to 40 inches Lower limit -60 inches 0.50 QUESTION: 2 RECORD: 255, LSE0307 POINT VALUE: 1.00 LESSON PLAN: 07-2K-5 -Objectivest 07 ,

During the current evolution (EOP-02-PCCP) requires a reactor cooldown.

This may be commenced whens (Select the correct answer.)

a. all control rods, except one, have been fully inserted.

b. . the entire contents of the SLC tank have been injected,

c. emergency depressurization is anticipated.

d. emergency depressurization is required.

ANSWER 2 b.

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• e HLOR-2 WR3 SRO-33" ANSWER KEY CONTINUED **

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QUESTION: 3 RECORD: 447, LSE0314 POINT VALUE: 1.00  !

LESSON PLAN: 07-2K-6 Objectives 04 ,

=For current plant conditions, if the reactor water level was returned '

to the normal range, the reactor power shouldt (select the correct answer.) ,

a. not change. >

l

b. increase to approximately 60%.  ;

c. increase to approximately 30%. J i

d. decreasc.

ANSWER: 3

-t

d. >

7

...ee...eeee ..eeee..............................e....ee......eeeee. p QUESTION: 4 RECORD 765, LSE0320 POINT VALUE: 1.00 r LESSON PLAN: 07-2K-7 Objectives 03 ,

{

During the current evolution the operator may avoid unnecessary rod blocks by bypassing the RWM, (Select the correct answer.)

l' a. bypassing the SDV high water level trip and using the emergency rod  !

in override switch. I be positioning the RSCS switches to bypass and using'the emergency rod j in. override switche ,

t c.. placing'the mode switch to refuel and;using emergency rod in  ;

override switch.

d. repositioning the RSCS RTGB switches to normal-normal and use the continuous rod insert switch.

ANSWER: 4 l c..

e.. ..e.............................................................

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• • HLOR-2 WK3 3RO-33H AN8WER REY CONTINUED **

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. QUESTION: 3 RECORD: 388, LSE0310 POINT VALUE: 1.00 i LESSON PLAN: 07-2K-9 Objectives 08 ,  ;

For present plant conditions, the reactor power is at its current value because (Select the correct answer.)

-a . LEP-02 is not being executed.

-b. RPV water level was deliberately lowered.

c. the liquid poison pumps were started too late.

d. LEP-03 takes a long time to execute due to routing hoses.

AN8WERt 5

b. ,

QUESTION: 6 RECORD: 750, LSE0319 POINT VALUE: 1.00-LESSON PLAN: , ' ' - 2 K- 9 Objectives: 08 , i Assume that the suppressioi al temperature continues to increase and the reactor pressure remalt e.t its current value. Which one of the following critical steps weald you use to avoid exceeding the heat ,

capacity temperature limit? (Select the correct answer.)

a. Decrease the reactor pressure per EOP-02-PCCP. l

b. Decrease the reactor pressure per EOP-01-EPP.

c. Activate Emergency Depressurization Anticipated, EOP-01-EPP.

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d. Activate Emergency Depressurization Required, EOP-01-EPP.

AN8WER: 6 b.

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• • HLOR-2 WK3 SRO-E3H ANSWER KEY CONTINUED **

QUESTION: 7 RECORD: 13, LSE0101 POINT VALUEt 1.00 LESSON PLAN: 07-2L Objectivest 08 ,

After assessing the current status of the plant, the appropriate  !

classification of the event would bet (Select the correct answer.) .

l

a. None Required l

b. Unusual Event

c. Alert l i

d. Site Emergency

e. General Emergency 1 ANSWERt 7 j

c.  !

l QUESTION: 8 RECORD: 168, LSE0304 POINT VALUE: 1.00 I LESSON PLAN: 07-2L Objectives: 08 ,  ;

The following NRC notifications are required as a result of the current )

plant conditions: -(Select the correct answer.)

a. No report required.

b. One hour red phone report,

c. Four hour red phone report.

l

d. Twenty four hour red phone report. l ANSWERI.8 l b.

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1 to HLOR-2 WK3 SRO-33" ANSWER KEY CONTINUED **

I QUESTION: 9 RECORD: 827, LSE0324 POINT VALUE: 1.00 LESSON PLAN: 10-2A Objectives: 01 , 1 I

Concerning the present position of the Reactor Recirc Pump Discharge  ;

valves, which of the follwing statements is true? )

a. The valves have been closed in preparation for shutdown l cooling.

b. The valves closed when the pumps were shutdown.  !

c. The valves closed on RPV low level.  !

d. The valves were closed by operators to reduce natural J circulation per the Level Power Control Procedure.

L '

l ANSWER: 9 I

c.

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I QUESTION: 10 RECORD: 828, LSE0325 POINT VALUE: 1.00  ;

t LESSON PLAN: 14-2D Objectives 01 ,

i SP cooling prior to the SCRAM.Due toThe the operator suppression pool high temperature,is directed by P return RHR to SP coolin Which of the followig statements are correct .

concerning A Loop RHR? g. ,

a. When the timer times out, close E11-F017A to prevent injection 5 and restart SP cooling per hard card,

b. Place the 2/3 core height switch in Manual override then place the Think Switch in manual and start system in SP cooling.

• L c. Place Think Switch to manual then place the 2/3 core height L switch to Manual Override and start system in SP cooling.

de The system cannot be returned to suppression pool cooling mode.

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l ANSWER: 10 d.

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• • HLOR-2 WK3 SRO-E3" ANSWER KEY CONTINUED **

l QUESTION _ 11 RECORD: 829, LSE0326 POINT VALUE: 1.00 l LESSON PLAN: 14-2D Objectives 01 ,

Which of the following would cause 2B RHR pump to start?

a. A loss of off-site power resulting in sequence loading of the l DG's. ,

b. Low RPV pressure with High DW pressure.

c. ADS logic actuation.

d. Manual start.

AN8WER: 11 d.

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• • HLOR-2 WK3 BRO-E3H ANSWER KEY OONTINUED **

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QL]STIOWs 12 RECORD: 826, LSE0323 POINT VALUE: 1.00 ,

LESSON PLAN: 15-2A Objectives: 01 , I The proper operation of the D m ell Floor and Equipment Drain System for the current conditions would be:

a. The pumps run only if started in manual recirc mode.

b. The pumps will neither run in discharge or recirc mode.

c. The DW Equipment Drain Pumps should be running in recirc node I due to the high temperature.

d. The DW Floor and Equipment Pumps will only start on High High sump level.

ANSWER: 12 l b.

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• • END OF EKAN **

12.00 POINTS 100% VALUE, 9.600 POINTS 80% VALUE 1 i FSTIMATED TIME TO COMPLETE: 48 NINUTES REQUIRED

REFERENCES:

PAGE 7 OF 7

, ENCLOSURE 2- RO l

l NAME:

DATE: 07/23/90  ;

CLASS: MIKE S.

I EXAM: LOR-2 M l l

PREPARED BY: JERNIGAN GRADED BY: {

ALTERNATE GRADER:

(if required)

TOTAL POINTS: 21.00 i

POINTS MISSED:

SCORE.

l

1. EXAN TIME LIMIT IS 2.0 NOUR8-

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

4. A score of 80% is required for passing. .

5. Use only black ink on this exam. Cross out all errors with a single line and initial and date. >

I have neither given nor received help on this exam.

All work is my own.

l I

Signature h v Exam Re. war Approve y '

• • HLOR-2 M'8 EIAMINATION **

QUESTION 2 POINT VALUE: 1.00 ,

During powrr operation while having troutla with reactor water chemistry 'R RC reports that the reactor coolant conductivity is 5.5 gmho/cm 9 25'C. Which of the following woab? be the correct crew cction. (Select the correct answer.)

c. Reduce conductivity belott the action level limit within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />,

b. Reduce conductivity below the action level limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '

or be in hot shutdown in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (unless directed otherwise by the Plant General Manager).

c. Shutdown immediatly and reduce the coolant temperature to less than 212*F (unless directed otherwise by the PNSC group). i

d. Shutdown immediatly and reduce the coolant temperature to less than 212*F (unless. directed otherwise by the Plant General Manager).

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• • " lok ( "M 'dATION

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l QUESTION 2 POINT VALUE 1.00 The plant is operating at 100%

Reactor pressure is 1005 psig. power, recireand An SRV opens flowsticks control is inFrom open. manual.

the following scenarios, select the one that describes the plant's response to the SRV failure, assuming no operator action.

O. Indicated steam flow exceeds indicated feed flow. Reactor water level remains constant. Reactor pressure remains constant.  !

1

b. RPV water level increases, then stabilizes at a level lower than '

the original level. EHC reduces generator load to mainatin reactor pressure.

c. Reactor power decreases and remains at approximately 95%.

Megawatts electrical from the generator decrease. Suppression pool temperature rises. Turbine throttle pressure decreases,

d. Reactor power remains constant. Me Suppression pool temperature rises.gawatts Turbineelectrical throttle decrease.

pressure remains constant.

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• • HLOR-2 W" EIANINATION **

QUESTION 3 POINT VALUE 1.00 Unit 1 is shutdown and in a long term outage. Unit 2 has been recently ,

chut down and is in cold shutdown; the cooldown was completed last chift. The shut down of unit 2 was necessitated by a requirment to drain and visually inspect the suppression pool. The following plant conditions / requirements have bean established

• core spi 3y systen is aligned to the CST with an operable flow path cs e vole of transferring water through the spray sparger to the reaL";or vessel.

a reactor mode switch is locked in the shutdown position.

. no operations affecting the reactor vessel or.with the possibility of draining the vessel are in progress or planned.

a the only outstanding deficiency is #4 diesel which is inoperable due to in-progress repairs. ,

The SOS directs that the draining of the suppression pool will commence cs soon as all the technical specifications are met. Which of the following actions most correctly detail the allowances and/or '

limitations imposed by the technical specifications in this instance?

O. Commence suppression pool draining as soon as practical since.all tech spec LCO requirements are met,

b. Commence suppression pool draining only after DG #4 is repaired and declared operable. ,

c. Commence suppression pool draining as soon as you insure that no j positive reactivity c1anges will occur during this condition.

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d. Commence suppression pool draining as soon as you insure that no positive reactivity caanges will occur and that one LPCI subsystem is operable.

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• • " LOR-2 N" IIANINATIog ee QUESTION 4 POINT VALUE: 1.00 In an emergency condition in which the suppression pool-water level is decreasing, identify all Primary Containment Limit (Graph (s)) that may be exceeded.

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t 4 lt te HLQgeg NH REANINATION **

QUESTION 5 POINT YALUE: 1.00 The use of containment sprays irrespective of whether adequate core cooling)is answer. assured may be authorized in order to: (Select the correct

c. provide thorough mixing of the containment atmosphere.

b. maintain primary containment integrity.

c. lower primary containment temperature.

i

d. minimize chugging.

4 PAGE 5 4

d

• • - HLOR-2 N" EIANINATION **

1 k

QUESTION 6 POINT VALUE 1.00 During a fire emergency in the reactor building, the reactor may continue to operate under which one of the following conditions?

(Select the correct answer.)

12'. RWCU HX room temperature 250'F / RWCU pump-room temperature 232*F.

b. HPCI steam tunnel temperature 298'F / EQ envelope exceeded in the RCIC-steam tunnel,

c. South RHR room temperature 296'F / RCIC equipment room temperature 166*F and 20 foot elevation can be entered.

d. North RHR room 305'F / North core spray room temperature 170'F and-20 foot elevation cannot be entered.

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• • ' HLQg.g;MH'EXANINATION- **

. QUESTION 7- POINT VALUE: J1.00

~

During EOP execution,jtheLoperating crew is directed to maintain that

. reactor water level between +170 and +200 inches. Maintaining the. '

water level above thist-lower limit allows-the-use of.the-normal chutdown cooling system for establishing and mairraining cold shutdown conditions and permits the: (Select-the correct answer.) ,

a. scram to be reset.-

b. operators to leave'thet e%orgen y operating procedures.-

j c. feed pumps to be usedifor reactor water level ecntrol.

d.- use of the'RNCU system to augment level control.

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'** ' " LOR-2 M" EXAMINATION: **

-1 s . QUESTION- 8 POINT VALUE: 1.00

.In an emergency. condition when the RPV injection systems are degraded,.

the. operating crew is forced to use alternate injection-s

= restore RPV water level to the normal controlling range. ystems.to If reactor .

p ' pressure was 400 psig, which one of the following systems should be:

oligned for injection

- (select the correct answer.)

3-

e. condensate transfer

b. CRD  !

c .- .demin: water

d. -standby liquid control l

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• • " LOR-2 MH EEAMINATION ** ,

4 QUESTION 9 POINT VALUEt 1.00 The operating crew-is allowed to defeat the low water level group 1 isolation interlocks in which one of the following cituations?

(Select the correct answer.)

a. To minimize containment challenges during failure to scram emergency conditions. ,

b. When reactor water level is decreasing near TAF and there is no high pressure injection.available,

c. To avoid emergency depressurization by reestablishing the main condenser as-the heat sink, d.. When the water level is between the minimum steam cooling water.

level and the zero injection RPV water level.

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ee =esLOR-2 N"'EIANINATION **

QUESTION 10 POINT VALUE: 1.00 If the drywell sprays are initiated while a LOCA signal is present and the DW: temperature is 410*F and the pressure /20 psig, the DW pressure:

(Select.the correct answer)

a. Will quickly decrease below 2 psig.

b. Decrease can be controlled by closing the spray valves.

! c. Will decrease-rapidlyfcausing a 10 psig differential pressure across the torus ring header.

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-d. Decrease cannot be controlled by operator action..

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-** " LOR-2 M" EXAMINATION **

' QUESTION' 11: POINT VALUE: 1.00 _;

During a: serious ATWS condition, the MSIVs.may be' reopened}if--there is no indication of a steam line. leak, fuel damage or:. (Select', the.

correct. answer. )- 1 a.--Condenser' tube leak- .

b.- Pneumatic: leak-on the MSIVs' '

c.. RPV-water low-low level Ld. EHC system failure-i i

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• • " LOR-2 N" EIANINATION **

QUESTION POINT VALUES l.00 -

Plant Conditions:

ATWS, i Reactor Power 10%

Reactor Pressure 1000 psig Reactor Water Level + 1" '

SLC. injecting Torus Water Temperature 165'F Torus Water Level - 2 feet suppression Chamber Pressure 2 psig Given the. plant conditions above, which of the following statements describes the crew response:

a. The Heat Capacity Level Limit is being exceeded. The crew j;; should emergency depressurize the reactor.

1

b. The Heat Capacity Temperature Limit is being exceeded. The crew should open HsIVs and rapidly depressurize to the condenser.

c. The Pressure Suppression Pressure limit is being exceeded. The crew should vent the drywell.

d. :The Heat Capacity Temperature limit is being exceeded. The crew should emergency depressurize the reactor.

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• • " LOR-2:M":EIANINATION ** j QUESTION-- 13 POINT VALUE 1.00 -

' Plant Conditions Reactor Pressure 950 PSIG Reactor Water Level +180 inches ['

All Rods In A Group One Isolation has occurred due to Main Steam Line.High' Radiation.- The current plant conditions are listed above. Subsequent plant degradation results.in the requirment to Emergency Depressurize the reactor. Upon commencing emergency depressurization the crew  !

determines that no SRVs will open. The crew should..(select.one) i L a. Terminate injection to the reactor.until reactor pressure is

-below the Minimum Alternato Flooding Pressure. *

b. Start HPCI and maintain Reactor Pressure at it's current value until SRVs can be restored to operation.

c.. Bypass MSIV interlocks and reopen MSIVs to depressurize.the' ]

reactor to the-Main Condenser.

d. Allow Reactor Pressure to be controlled by SRV cycling. When-

,- SRVs are returned to service, open'seven SRVs. =;

V .

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• • ' HLOR-2.N" EIANINATION **

. QUESTION 14  : POINT VALUE::1.00

-Currant Plant Conditions .

t 4 Primary Containment 02= Conc -

3.1%

Drywall Temperature 350

• F increasing ' at 2

• F/ min Drywell Pressure . . 66 psig increasing at-1 psig/ min 3 -Suppression Pool Level 0 inches' L Reactor. Water Level +170-inches.

.All Rods-In i

o =Given that an event has occurred to cause an increase in Drywell.

p = Pressure with the current conditions as listed-above, the crew should.,

a.- Purge the. Primary Containment with Nitrogen

'b.. Vent the Primary Containment regardless of off-site release rate

c. Spray the Drywell l d. Emergency-Depressurize the Reactor and establish minimum (

' Alternate Flooding, Pressure 't I

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• • HLOR-2 M" EXAMINATION **

[ QUESTION 15 ' POINT VALUBt 1.00 The reactor has been shutdown for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 20 minutes. the crew has completed flooding the Reactor Vessel per procedure and is currently draining the vessel to bring level instrumentation on scale. Draining-has been.in progress for 7 minutes and instrumentation is still-not on ccale. This... (Select the correct answer) f

a. Is an acceptable time for draining the' reactor during these conditions and will maintain peak clad temperature between 1500 and 1800'F

b. Is an acceptable time for draining the vessel and will maintain peak clad temperature < 1500*F

c. Is an unacceptable time for draining the vessel and will cause ,

peak clad temperature to exceed 1500'F o

d. Is an unacceptable time and will cause peak clad tempurature to be maintained between 1800 and 2200*F PAGE 15 1

7 .

i si ee' esLOR-2-M" EIAMINATION l QUESTION: 16 POINT VALUEt 1.00 i A steam line rupture has occurred in the "A"' Main- Steam Line ~ (MSL) in-the turbine building.- Containment isolation has occurred, but theresis etill steam flow. indicated on "B" MSL. Reactor Pressure Vessel .

pressure and-water level are decreasing slowly.- This - condition (RPV) '!

requires: (Select.the correct answer.)

n.. Declaration of an Unusual Event with all-accompanying ,

notifications.

l.

b. Declaration of an Alert with all' accompanying notifications. .:

c. . Declaration of a Site Emergency with all accompanying- .

L notifications.

'd. Declaration of a. General Emergency with all accompanying' ,  :

l notifications.

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• • " LOR-2 M" EIANINATION **

I QUESTION 17 POINT VALUE: 1.00 The plant has been operating at 100% power on the design flow control L line for more than a month. Reactor recirculation pump 2B must be removed from service for necessary maintenance. Maintenance is expected to take approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Which one of the following-actions is correct under these conditions?

l p G. Reduce speed of both recirculation pumps-to 50%, then trip pump 2B, L- b. Reduce speed of both rapirculation pumps to 50%, the reduce the l

speed of pump 2B to 28% and shutdown pump 2B.

c. Reduce speed of both recirculation pumps to 50%. Lower pump 2B

. speed to 28% and insert rods to maintain power less than 35%, then trip pump 2B.

d._ Reduce speed of both recirculation pumps to 50%. Lower pump 2B speed to 28% while inserting control rods and increasing flow on pump 2A to maintain power less than 35% and core flow greater than 35' albs /hr, then trip pump 2B.

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i ee' etLOR-2'MH EIANINATION **

h- GUESTION 18 POINT VALUE: 1.00

, 'You are attempting to establish alternate shutdown' cooling. Reactor L vessel water level is +254 inches. One Core'S L' one SRV is'o Reactor pressure is 85 psig. pray pump is running and Suppression-chamber-

. pressure is pen.-11 psig. As the core. Spray.

reactor pressure increases.to 178 psig. pump discharge.

Under valve.is opened, these conditions you

[ :chould: (Select the correct answer.)

l c.- open an additional SRV. This'will increase flow through the i L vessel' l

b., shut off the core-spray pump. This will reduce reactor pressure.

l

-c. get cut of alternate shutdown cooling. You may cause brittle L failure of the vessel walls.

L i d'.- allow the plant to cool _down.under these~ conditions.

All' operating.

requirements have been met. -

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• • - " LOR-2'M" EXAMINATION **

QUESTION 19. . POINT. VALVE '1.00 A steam 1-ine rupturr,has caused Emergency' Core: Cooling Systems.(ECCS) to actuate.,-All svstems have activated properly. The control Operator

' cees reactor vesse.l water level recovering and four minutes after'ECCS

-activation, decidas to secure the A loop'of. Low Pressure Coolant Injection (LPCI). He r$ ops the A loop'LPCI pump and shuts the associated LPCI Outboate injection Valve, E11-F017A. Select the correct-ctatement below.

a. . The.LPCI System has responded properly.

b.. The injection valve should not have closed.

c.- The pump has a timer preventing. shutdown for five minutes after an ECCS start. -4

d. The pump will automatically restart as long as the LPCI initiation signal is present.

e f

l PAGE 19 l

• • HLOR-2 MH EXAMINATION- **

QUESTION 20- POINT VALUE 1.00

'After completing a diesel generator test-the operator inadvertently pressed the EMERGENCY STOP button, Which of the following statements is correct?

a. The diesel generator lockout relay will prevent'the diesel from-atuomatically starting until reset.

b. The diesel generator can be started'by depressing the local PRELUBE START button,

c. A diesel generator auto-start signal will attempt to start the diesel one time,

d. The diesel generator can be started by turning the control room start switch to START.

D PAGE 20

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66- HLOR-3 M" EIAMINATION- * * -

QUESTION.- 31 POINT.VALUE:-1.00

.The-plant (Unit 2) had been operating at rated power for several days-when an EHC malfunction caused reactor pressure to decrease to 750

-psig. The Group I isolation logic failed and the group isolation did

.not occur. The mode switch is still in RUN. Which one'of the follwing things-would be likely to occur under these conditions? (Select _the correct answer.)

a. -Loss of integrity of the nuclear process barrier.

b.- A= main-turbine trip on low reactor pressure,

c. Reference leg flashing of RPV water level instrumentation..

d. Loss of integrity of the nuclear fuel.

• • END OF EXAM **

PAGE 21 OF 21

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• • HLOR-2 M" ANSWER K3Y **

l LLN0121 QUESTION: 1 RECORD: 486, POINT VALUE: 1.00 LESSON PLAN: 01-20 Objectives: 19 ,

During power operation while having trouble with reactor water l chemistry E&RC reports that the reactor coolant conductivity is 5.5 ymho/cm 9 25'c. Which of the following would be the correct crew [-

action. (Select the correct answer.) ->

a .- Reduce conductivity below the action level limit.within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

l b '. Reduce conductivity below the action level limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ,

L or be in hot shutdown in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within l the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (unless directed otherwise by the Plant, General f Manager). [

c. Shutdown immediatly and reduce the coolant temperature to less than h 212*F (unless directed otherwise by the PNSC group).  ;

d. Shutdown immediatly and reduce the coolant temperature.to less.than i 212'F funless directed otherwise by the Plant General Manager) ., ,

l ANSWER: 1  !

d.

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• • " LOR-2'M" ANSWER KEY _CONTINUF.D ** .

i t

-QUESTION: 2 RECORD: 463, LLN0115 POINT VALUE: 1.00 LESSON PLAN: 05-2A Objectives: 03 ,

The plant is operating at 100% power, recirc flow control is'in --

manuale b Reactor pressure is 1005 psige An SRV opens and sticks opene From the following scenarios, select-the one that describes the plant's response to the SRV failure, assuming no operator _actione ao Indicated steam flow exceeds indicated feed flows Reactor water level remains constante Reactor pressure remains constant. t be- RPV water level increases, then stabilizes at a level lower than I the original levele EHC reduces generator load to mainatin reactor pressuree ce Reactor power decreases and remains at approximately 95%4 Megawatts _ electrical from the generator decreasee Suppression pool temperature rises. Turbine-throttle pressure decreasess ,

l de Reactor power remains ~constante Megawatts electrical decreasee l Suppression pool temperature risese Turbine throttle pressure remains constante-ANSWER: 2 be ,

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• • " LOR-2 M" ANSWER KEY CONTINUED **

QUE8 TION: 3 RECORD: 809, LLA0055 POINT VALUE: 1.00 LESSON PLAN: 07-2B Objectives: 05 ,

Unit 1 is shutdown and in a long term outage. Unit 2 has been'recently s shut down and is in cold shutdown; the cooldown was completed last shift. The shut down of unit 2 was necessitated by a requirment to drain and visually inspect the suppression pool. The following plant >

conditions / requirements have been established:

+ core spray system is aligned to the CST with an operable flow

• path capable of transferring water through the spray sparger to the reactor vessel.

reactor mode switch'is locked in the shutdown position.

. no operations affecting the reactor vessel or with the possibility of. draining the vessel are in progress or planned.

the-only outstanding deficiency is #4 diesel which is inoperable ,

due to in-progress repairs.

The SOS directs that the draining of the suppression pool will commence as soon as all the technical-specifications are met. Which of the following actions most correctly detail the allowances and/or-limitations imposed by the technical specifications in this instance?

a. Commence suppression pool draining as soon as practical since all tech spec LCO requirements are met. ,

b. Commence suppression pool draining only after DG #4 is repaired and declared operable,

c. Commence suppression pool draining as soon as you insure that no positive reactivity changes will occur during this condition.

L d. Commence suppression pool draining as soon'as you insure that no L positive reactivity changes will occar and that one LPCI subsystem is operable.

ANSWER: 3 l

b.

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.i i W1 hQUESTION: 4 RECORD :438,: LLE0095 .

POINT VALUE::1.00 g LESSON PLAN: 0 7-2 K-1' Objectives:<06-, .c  ;

In:an emergency condition in which the suppression pool water level is dp, . decreasing, identify all Primary Containment Limit (Graph (s)) that.may  :

be exceeded.

t ANSWER: 4. 2

1. ; Pressure Suppression Pressure Limit

.f

) 2. Heat Capacity-Level Limit i E.....................................................................

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l QUESTION: 5 RECORD: 806, LLN0193 POINT VALUE:-l.00 -+

LESSON PLAN: 07-2K-1 Objectives: '20 ,

i j H

i The use'of containment sprays irrespective of whether adequate core -

4 cooling-is assured may be authorized in order to: '(Select the correct answer.) ,

a. provide thorough mixing of the containment atmosphere.

b. maintain primary containment integrity.

c. lower primary containment temperature.

\

d. minimize. chugging.

ANSWER: 5' l-L '

'b.

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• • '" LOR-2 MH ANSWER KEY CONTINUED **

QUESTION: '6 RECORD: 390,- LLE0082 POINT VALUE: 1.00~

LESSON PLAN: 07-2K-2 Objectives: 25 ,

During-a fire emergency in the reactor building, the reactor may NOT continue to operate under which one of the following conditions?.

-(Select the correct answer.) ,

i

a. RWCU HX room temperature 250'P / RWCU pump. room temperature'232'F. i

b. HPCI steam tunnel temperature 298'F / EQ envelope exceeded in the i RCIC steam tunnel,

c. -South RHR room temperature 296*F / RCIC. equipment room temperature 166'F and 20 foot elevation can be entered.

d. North RHR room 305'F / North core spray room temperature 170'F and 20 foot elevation cannot be entered.

ANSWER: 6 d.

QUESTION: 7 RECORD: 374, LLE0078 POINT VALUE: 1.00 LESSON PLAN: 07-2K-5 Objectives: 08 ,

During EOP execution, the operating crew is directed.to maintain the reactor water level between +170 and +200 inches. Maintaining the water level above this lower limit allows the use of the normal shutdown cooling system for establishing and maintaining cold shutdown conditions and permits the: (Select the correct answer.)

a. scram to be reset,

b. operators to leave the emergency operating procedures.

c. feed pumps ~to be used for reactor water level control.

d. use of the RWCU system to augment level control.

l ANSFER: 7 a.

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• • - " LOR-2 MH ANSWER KES OONTINUED **

QUESTION: 8 RECORD:.160, LLE0026 POINT VALUE: 1.00-LESSON PLAN: 07-2K-9 Objectives: 07 ,.

In an emergency _ condition when the RPV injection systems are' degraded, c

- the operating crew is forced to use alternate injection systems to restore RPV water level:to-the normal controlling range. If reactor presLure was 400 psig,-which one of the following systems should be aligned for= injection: (Select the correct answer.)

a. condensate transfer e I:

L

b. CRD

c. domin water >

d.. standby liquid control ANSWER: 8 L d.

l-3 QUESTION: 9 RECORD: 608, .LLE0147 POINT VALUE: 1.00 '

LESSON PLAN: 07-2K-9 ' Objectives: 08 , 4 i

- The operating crew is allowed to defeat the low water level group 1 =.

isolation interlocks in which one.of the following situations? 4

. (Celect the" correct answer.) '

. i

a. To minimize containment. challenges'during failure to scram

.. emergency. conditions. .

. b. When: reactor water level is decreasing near TAF and there is~no high pressure injection available, c.- To avoid! emergency:depressurization by reestablishing the main condenser as'the heat sink.

d. When the water level is'between the minimum steam cooling water

. level and the zero injection'RPV water level. '

ANSWER "9 a.

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• • " LOR-2 NH ANSWER KEY CONTINUED **  ;

. QUESTION: 10 RECORD: 8 3 5 ,- LLE0166 POINT-VALUE: 1.00

? LESSON PLAN: 07-2K.01 Objectives: 27',. -

If the drywell sprays are initiated while a LOCA signal is present and

-the DW temperature is 410'F and the pressure 20 psig, the DW pressure:

(Select the correct answer)  ;

a. Will quickly. decrease below 2 psig.

b. Decrease can be controlled by closing the spray valves, i

L c. Will decrease rapidly causing a 10 psig differential pressure l, across the torus ring header.

L d. Decrease cannot be controlled by operator' action.

l ANSWER: 10 b

QUESTION: 11 RECORD: 834, LLE0165 POINT VALUE: 1.00-LESSON PLAN: 07-2K.05 Objectives: 19 ,  !

During a serious ATWS condition, the MSIVs may be reopened if there is L

no indication of a steam line leak, fuel damage or: (Select-the correct answer.)-

a. Condenser tube leak

b. Pneumatic leak on the MSIVs ,

c. RPV water low-low level

d. EHC system failure ANSWER: 11 d

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• * ~ " LOR-2 M" ANSWER KEY. CONTINUED ** l j

i

' QUESTION 12 RECORD: 833,. LLE0164 POINT VALUE: 1.00 LESSON PLAN: 07-2K.06 Objectives: 031 ,- I

-Plant Conditlons:

ATWS i Reactor Power-10%

~ Reactor Pressure 1000 psig.

Reactor Water Level-+ 1" SLC injecting Torus Water Temperature 165'F 1 Torus Water Level - 2 feet Suppression Chamber Pressure 2 psig 1

'l Given the plant conditions above, which of the following statements describes the crew response: q

a. The Heat Capacity Level Limit is being exceeded. The crew .

should emergency depressurize the reactor, a

b. The Heat Capacity Temperature Lir.it is being exceeded. The l crew should open MSIVs and rapidly;depressurize to the Condenser.  :

c. The Pressure Suppression Pressure limit is being exceeded. The:

crew should vent the:drywell.  ?

d. The Heat Capacity Temperature limit-is being exceeded. -The crew should emergency depressurize the reactor.

l:

ANSWER: 12 i

d

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• • HLOR-2 MH' ANSWER. KEY CONTINUED **-

QUESTION _ 13 - RECORD: 832, -LLE0163- POINT VALUE: 1.00-LESSON PLAN: 07-2K.05 Objectives: 05 , 04

~

Plant Conditions Reactor Pressure. 950 PSIG Reactor Water-Level- +180 inches All Rods In A Group.One Isolation has occurred due to Main' Steam Line High

-Radiation. - The current plant conditions are listed.above.. Subsequent plant degradation results in the 'requirment to Emergency.Depressurize

.the reactor. . Upon commencing emergency depressurization the crew determines:that no SRVs will open. . The crew should..(select one)  ;

1 l

a. Terminate injection'to the reactor until reactor pressure is ,

L below the Minimum' Alternate Flooding Pressure, j

b. Start-HPCI and maintain Reactor Pressure at it's current value -

until SRVs can be restored'to operation. a

c. Bypass MSIV interlocks and reopen MSIVs to depressurize the

-reactor to1the. Main Condenser, i

d. Allow Reactor Pressure to be controlled by'SRV-cycling. When SRVs are returned to service, open.seven SRVs.

ANSWER: 13

c o................................................................... ,,

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• • " LOR-2.'M"IANSWER KEY CONTINUED' **

~ QUESTION: 14 RECORD: 431,- LLE0162 POINT VALUE::1.00i f

. LESSON-PLAN

1 0 7-2K.08 Objectives::03>,

Current Plant conditions-PrimaW' Containment 02 ConcL 3.1% .

Drywell Temperature 350*F increasing at 2*F/ min >

. Drywell. Pressure o66 psig increasing at 1 psig/ min.

Suppression Pool Level 0 inches

-Reactor Water' Level- +170. inches 1' All-Rods In

? ,

L - Given that an event has occurred to=cause an increase in Drywell' '

Pressure with the: current conditions as listed above,- the crew'should..

a.: Purge the: Primary. Containment with Nitrogen -( r b.- Vent'the Primary' containment regardless of off-site release- ,

rate <

3

'c. Spray the Drywell: ,;

d. Emergency Depressurize the Reactor and establish minimum:

Alternate 1 Flooding Pressure  :*

i ANSWER: 14' .

t

.b

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• • ' " LOR-2 M" AN8WER KEY CONTINUED **

QUESTION: 15- RECORD: 830, LLE0161 POINT VALUE: 1.00 LESSON' PLAN: 07-2K.11 Objectives: 03 , 09

. .The reactor has'been-shutdown for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 20 minutes. the crew has ,

N completed flooding the Reactor vessel per procedure and is currently draining the vessel to bring level instrumentation on scale. Draining has been in progress for 7 minutes and instrumentation is still not on

,1 scale. This... (select the correct answer)

a. Is an acceptable time for draining.the reactor during these conditions and will maintain peak clad temperature between 1500 and 1800'F

b. Is an' acceptable time for draining the vessel and will maintain peak clad temperature < 1500'F

c. Is an unacceptable time for draining the vessel and will-cause peak clad temperature to exceed 1500'F

d. Is an unacceptable time and will cause peak clad tempurature to be maintained between 1800 and 2200'F ANSWER: 15 c

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• • " LOT: N" ANSWER KEY- OONTINUED **

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. QUESTION e16. . RECORD: 331,f LLN0079 POINT VALUE:ci.00 . 5 LESSON PLAN: 07-2L Objectives: 13 ,

h 1 AL steam line ru ture has occurred in the "A" Main SteamDLine (MSL) in "i

-the turbine bui ding. Containment isolation has occurred, but there is' j still steam flow indicated on "B" MSL. Reactor-Pressure Vesseln(RPV)1

pressure and water level are decreasing slowly. This condition-requires: (Select the correct answer.) , ,

a. Declaration'of an' Unusual Event with all accompanying l' notifications.

lv ..

I

'b. . Declaration of an Alert with all accompanying notifications.

c. Declaration of a Site Emergency with all accompanying.

-notifications.

d.- Declaration of a General Emergency with all accompanying i

! notifications.  ;

L ,

ANSWER: 16

'c. <

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1 et HLOR-2 M" ANSWER KEY CONTINUED **

QUESTION: 17 RECORD: 807, LLN0194 POINT VALUE: 1.00 LESSON PLAN: 10-2A Objectives: 05 ,

The plant has been operating at 100% power on the design flow control line for more than a month. Reactor recirculation pump 2B must be removed from service for necessary maintenance. Maintenance is expected to take approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Which one of the following actions is correct under these conditions?

a. Reduce speed-of both recirculation pumps to 50%, then trip pump 2B.

l

b. Reduce speed of both recirculation pumps to 50%, the reduce the speed of pump 2B to 28% and shutdown pump 2B,

c. Reduce speed of both recirculation pumps to 50%. Lower pump 2B speed to 28% and insert rods to maintain power less than 35%, then j trip pump 2B.

d. Reduce speed of both recirculation pumps to 50%. Lower pump 2B speed to 28% while inserting control rods and increasing flow on L pump 2A to maintain power less than 35% and core flow greater than 35 mlbs/hr, then trip pump 2B.

AN8WERt 17 i

c.

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• • HLOR-2 NH ANSWER REY CONTINUED ** -l l

QUESTION: 18 RECORD: 7, LLA0002 POINT VALUE: 1.00 LESSON PLAN: 14-2D Objectives: 05 ,

You are attempting to establish alternate shutdown coolinge Reactor ,

vessel water level is +254 inchese One core S  !

one SRV is opene Reactor pressure is 85 psig. pray pump is running Suppression chamberand  !

pressure is 11 psige As the core Spray 1 reactor pressure increases to 178 psig. pump Underdischarge valve is opened, these conditions you should: (select the correct answere) 1

-ae open an additional SRVe This will increase flow through the 1 vessel. ,

b. shut off the core spray pump. This will reduce reactor pressures ce got out of alternate shutdown cooling. You may cause brittle failure of the vessel walls,

d. allow the plant to cool down under these conditionse All operating 1 requirements have been met.

ANSWER: 18 i l

a.

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• • HLOR.3 MH ANSWER REY CONTINUED ** i i

QUESTION: 19 RECORD: 506, LLN0130 POINT VALUE: 1.00 I LESSON PLAN: 14-2D Objectivest 08 , '

A steam line rupture has caused Emergency Core Cooling Sfstems.(ECCS) l to actuate. All systems have activated properly. The Control Operator  :

sees reactor vessel water level recovering and four minutes after ECCS l activation, decides to secure the A loop of Low Pressure Coolant {

Injection (LPCI). He stops the A loop LPCI pump and shuts the "

associated LPCI Outboard Injection Valve, E11-F017A. Select the correct statement below. l l

a. The LPCI System has responded properly.  ;

b. The injection valve should not have cloped. l

c. The pump has a timer preventing shutt .: for five minutes after an l ECCS start.

d. The pump will automatically restart as long as the LPCI initiation ,

signal is present.  !

1

' ANSWER 19 b.

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• • HLOR-2 M" ANSWER REY OONTINUED - ** l QUESTIOWs 20 RECORD: 808, LLN0195 POINT VALUE: 1.00 .

LESSON PLAN: 20-2D Objectivest 04 ,

After completing a diesel generator test the operator inadvertently '

pressed the EMERGENCY STOP button. Which of the following statements is correct?

i

a. The diesel generator lockout relay will prevent the diesel from atuomatically starting until reset.  ;

b. The diesel generator can be started by depressing the local PRELUBE START button. ,

c. A diesel generator auto-start signal will attempt to start the ,

diesel one timo.

d. The diesel generator can be started by turning the control room start switch to START. i t

AN8WER: 20 1 c.

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QUESTION: 21 -RECORD: 803, LLN0190 POINT VALUE: 1.00 LESSON PLAN: 28-2A Objectives: 01 ,

The plant (Unit 2) had been operating at rated power for several days when an EHC malfunction caused reactor pressure to decrease to 750 psig. The Group I isolation logic failed and the group isolation did not occur. The mode switch is still in RUN. Which one of the follwing things would be likely to occur under these conditions? (Select the correct answer.)

a. Loss of integrity of the nuclear process barrier.

t

b. A main turbine trip on low reactor pressure.

c. . Reference leg flashing of RPV water level instrumentation.

d. Loss of. integrity of the nuclear fuel.

AN8WER: 21 L d.

l ....................................................................

• • END OF EXAM **

l 21.00 POINTS 100% VALUE, 16.800 POINTS 80% VALUE ESTIMATED TIME TO COMPLETE: 91 MINUTES REQUIRED

REFERENCES:

l l

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