Text

Requalification Retake Exam Rept 50-413/92-303 for Both Units on 921016 & 19.Exam Results:All Operators Passed Exams
	ML20128E117
Person / Time
Site:	Catawba
Issue date:	11/25/1992
From:	Aiello R, Ernstes M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20128E114	List: IR 05000413/1992303; ML20128E110;
References
	50-413-92-303, NUDOCS 9212080006
	Download: ML20128E117 (62)
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d "% UNITED STAT ES (0, WUCLEAR REGULATORY COMMisSIOrd

[ o REGION ll 5.

,y 101 MARIETT A STREET, ATLANT A.GEOHGtA 30323

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ENCLOSURE I EXAMitF .JN REPORT - 50-413/92-303 facility Licensee: Duke Power Company Facility Name: Catawba Nuclear Station Facility Docket Nos.: 50-413 and 50-414

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P.equalification examinations were administered at Catawba Nuclear Station near York, South Carolina, 'q l' .m ,

/ i Chief Examiner: [f_ r

-/V 't h/209-Ronald F. Aiello Date Signed Approved By: dh, t/ /Vlgt -or t ///H /'/L

_ [Miphael E. Ernstes, Chitef 'Date Signed

' Operator Licensing Section 2 Division of Reactor Safety SUMMARY

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Scope: A requalification retake examination was administered on October 16 and 19, 1992, to three Senior Reactor Operators (SR0s) and two Reactor-Operators (R0s) who failed the requalification examinations given during the weeks of May 4 and May 11, 199 Results: All of the operators passed the examination There was no program evaluation dut ' i the small sample siz PDR ADOCK 05000413 y PDR

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REPORT DETAILS Persons Contacted W. Barron, Director, Operator Training S. Bradshaw, Shift Operations Manager M. Brady, Shift Supervisor M. Geddie, Operations Superintendent R. Katalinich, Nuclear Instructor M. Tuckman, Catawba Site Vice President W. McCollum, Catawba Station Manager NRC Examiners R. Aiello, Region II, Chief Examiner T. Guilfoil, Sonalysts W. McGonegal, Sonalysts K. Parkinson, Sonalysts Other NRC Personnel Attending Exit Interview J. Zeller, Resident Inspector R. Watkins, Region 11 Discussion Proposed Examinations The proposed written, walkthrough, and simulator examinations were effective in testing the indiv: dual weak areas identified on the previous requalification examination Some critical tasks on the proposed simulator examinations needed to be modified. The events as written did not require any actions which met all of the criteria for a task to be critical. Four questions on the proposed written examination were changed in order to make the distractors more plausible, Operator Performante During the simulator examination the crew failed to recognize trehds prior to the sounding of the annunciator alarms. However, the crew's recognition of off-normal trends and status was timely and appropriate when the alarms sounde .. . .

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Report Details 2 Exit Meeting At the conclusion of the site visit, the examiners met with representa-tives of the plant staff indicated in paragraph 1 to discess the results of the examinations and inspection findings. This exit was conducted in conjunction wi+h the initial examination exit that was given during the week of October 19, 1992. The examiners further described the areas inspected and discussed in detail the inspection findings listed in report 50-413/92-30 The licensee did not identify any of the material prc3 ded to or -

reviewed by the exaniners as proprietar l

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ENCLOSURE 2 SIMULATOR FACILITY REPORT Facility Licensee: Catawba Nuclear Station facility Docket Nos.: 50-413 and 50-414 Operating Test Administered During: October 19, 1992 This form is used only to report observations. These observations do not constitute, in and of themselves, audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required solely in response to these observation During the conduct of the simulator portion of the operating test, no simulator fidelity items were identifie _ - - _ _ _

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O O PART A

.' LESSON PLAN:EHC NUMBER: 14 TOPIC: SSS21 REV DATE: 10/28/91 SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 1 TIME: Which nuclear instrument is providing input to the EHC Rx Power Limiter at this time? .

A. PR-N42 B. PR N43 C PR-N44 _

D. None- PR to EHC has bad quality

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ANSWER: A ATTACHMENTS:

KA NUMBER: 045/010/K4.21 RO: SRO: 3,2 KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: MC1 REFERENCE #2:

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PART A o

/ LESSON PLAN:ENB NUMBER: 22 TOPIC: SSS21- REV DATE: 10/28/91 SRO ONLY:- RO OBJ: 9 SRO OBJ: 9 POINT VALUE: 1.00 pt '

ISS OBJ: O PTRO OBJ: 7 TIME: 2,0 Which of the following describes the nature of the PR N43 failure?

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A. Upper detector reading abnormally low

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B. Total power gain set too low C. Instrument fuse blown D. Lower detector reading abnormally high-

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ANSWER: A ATTACHMENTS:

KA NUMBER: 015/000/A2.01 RO: SRO: KA NUMBER: ~/ / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: N15 REFERENCE #2: MC1

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O O PART A LESSON PLAN:lFE NUMBER: 2 TOPIC: SSS21 REV DATE: 10/28/91

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SRO ONLY: RO OBJ: O SRO OBJ: O POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 0 TIME: 2.0 l

Which of the following describes how the feedwater control valves will now respond to a CF isolation signal? .

A. Valves will close, regardless of DFCS status B. Valves must be closed by the operator l

C. Valves will close DFCS will override manual mode D. Valves are not required to close for adequate CF isolation

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ANS'NER: A ATTACHMENTS:

KA NUMBER: 059/000/A2.01 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

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O O PART A .

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/' LESSON PLAN:lFE NUMBER:- 3 TOPIC: SSS21 REV DATE: 09/09/92 SRO ONLY: RO OBJ: 7 SRO OBJ: 7 POINT VALUE: 1.00 pt ,

ISS OBJ: O PTRO OBJ: 9 TIME: Which of the following describes the current value and origin of the present DFCS program level setpoin A. 38%, N41 - ,

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B. 53%, N43 C. 59%, ARBITRATOR -

D. 59%, N42 ANSWER: B

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KA NUMBER: OS9/000/A3.02 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: OP/1/A/6100/10E REFERENCE #2:

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o PART A O

/ LESSON PLAN:lRX NUMBER: 24 TOPIC: SSS21 REV DATE: 10/28/91 *

SRO ONLY: RO OBJ: 10 SRO OBJ: 10. POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 9 TIME: Given present plant conditions, which of the following describes the proper rod control response to PR-N43 failure? -

A. Rods should have driven IN until blocked by 'EMERG LO TAVE'

B. Rods should have driven IN until POWER MISMATCH signal decays to C. Rods should have driven out until POWER MISMATCH signal decays to D. Rods should not have moved due to PR-N43 failur ANSWER: D ATTACHMENTS:

KA NUMBER: 015/000/K4.08 dO: SRO: 3.7

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KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

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OPART A O

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.' LESSON PLAN:NV NUMBER: 18 TOPIC: SSS21 REV DATE: 10/28/91 SRO ONLY: RO OBJ: 12 SRO OBJ: 12 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 9 TIME: Which of the following describes the location of the leak on the NV system?

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A. Letdown line, just after the letdown orifices B. Char 0i ng lino, downstream of 1NV309 ' Seal Water injection Flow'

C. Letdown line, prior to the Regenerative Heat Exchanger --

D. Charging line, at the NV pump discharge

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ANSWER: B ATTACHMENTS:

KA NUMBER: 004/000/G15 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: MC10 REFERENCE #2: OP/1/B/6100/10H

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OPART A O

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LESSON PLAN:ENB NUMBER: 23 TOPIC: SSS21 REV DATE. 10/28/91 4

' SRO ONLY: RO OBJ: 10 SRO OBJ: 10 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 8 TIME: Should either PR-N41 or PR-N43 be returned to ' OPERABLE' status. Could :

operation at this power level continue without restriction?

(consider the nuclear instrument failures independently from any other failure that may exist at this time.)

A. Yes; as long as the reactor trip bistables have been tripped, operation at this power level may continue indefinitel B. No; inability to adequately monitor one quadrants AFD would require power reduction to less than 50%.

C. Yes; as long as bistables are tripped and Reactor Group is not'fied to monitor OPTR every 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months '

D. No; inability to adequately monitor OPTR would require power reduction to less than 75%.

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ANSWER: C ATTACHMENTS:

, KA NUMBER: 015/000/A1.04 RO: _ SRO: 3.7 L RO: KA NUMBER: / / SRO:0.0 l KA NUMBER: / / RO: SRO:0.0 l

l REFERENCE #1: T.S. 3. REFERENCE #2: T.S. 3.2.4 L

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O O PART A

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LESSON PLAN:RN NUMBER: 26 TOPIC: SSS21 REV DATE: 09/09/92 SRO ONLY: RO OBJ: 12 SRO OBJ: 12 POINT VALUE: 1.00 pt ISS OBJ: 10 PTRO OBJ: 6 TIME: if RN pit 'A' level continues to decrease, which of the follow.ng is an automatic action that will occur on the RN system? -

A. 'A' pit RN screens will backwash B. 'A' train RN pumps wi!! trip at 559 ft pit level C. All four RN pumps will start at 557.5 ft. pit level 7--

D. 1RN488 and 1RN47A will receive an auto open signal ANSWER: C ATTACHMENTS:

KA NUMBER: 000/062/G5 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: OP/1/A/6100/10M REFERENCE #2:

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PART A

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LESSON PLANiRN NUMBER: 41 TOPIC: PSS REV DATE: 09/10/92 SRO ONLY: RO OBJ: 0 SRO OBJ: O POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 6 TIME: A large break LOCA has occurred on Unit 1. Given the following:

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1 A RN pump ON

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2B RN pump ON

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1 A NS pump ON

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18 NS pump ON ,

Determine the required PN to NS heat exchanger alignment when NS is transferred to Cold Leg Recirculation. (select one)

A. Establish 4600 gpm each to 1 A and 18 NS heat exchanger B. Close 2RN-47A or 2RN-488 (RN Supply X-over Isols) and align 4600 gpm to only 1 A NS heat exchange C. Establish 4600 gpm to only 1 A NS heat exchange D. Close 2RN-47A or 2RN-48B (RN Supply X-over Isols) and align 4600 gpm each to 1 A and 1B NS heat exchanger ANSWER: C ATTACHMENTS: TIME VAL MJB KA NUMBER: 026/000/K1.02 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/1C3 REFERENCE #2:

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Q O PART A

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LESSON PLAN:NV NUMBER: 1 TOPIC: PS REV DATE: 10/05/92 SRO ONLY: RD OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 2 TIME: Which of the following describes an interlock associated with the NV system?

A. To open 1NV1 and 2, the orifice isolation valves 1NV10,11, and 13 must be ope B. Closing the orifice isolation valves 1NV10,11, and 13 will cause 1NV1 and 2 to clos C. If all 3 charging pumps trip, the orifice isolation valves 1NV10,11, and 13 will clos D.1NV1 and 2 and the orifice isolation valves 1NV10,11, and 13 ciose on high levei in the VCT,

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ANSWER: C ATTACHMENTS:

KA NUMBER: 004/020/K4.03 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

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PART A

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LESSON PLAN:AM1 NUMBER: 5 TOPIC: TA REV DATE: 09/10/92 t

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SRO ONLY: RO OBJ: 1 SRO OBJ: 1 POINT VALUE: 1.00 pt '

ISS OBJ: O PTRO OBJ: 1 TIME: During a Large break LOCA, the primary core cooling method is . .

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A. the S/Gs via two phase natural circulation B. via subcooled natural circulation C. Reflux cooling D. via ECCS injection flow ANSWER: D ATTACHMENTS: TIME VAL GBI,MJB KA NUMBER: 000/011/EK1.01 RO: SRO: 4.4 l KA NUMBER: / / RO: SRO: 0.0 l KA NUMBER: / / RO: SRO: 0.0-REFERENCE #1: MC1, MC10, MC11 REFERENCE #2:

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o PART A o

LESSON PLAN:AM1 NUMBER: 6 TOPIC:" . REV DATE: 09/10/92 SRO ONLY: RO OBJ: 1 SRO OBJ: 1 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 1 TIME: Following establishment of subcooled natural circulation, steam dumping capability is lost. Which of the following describes the response of T-hot, *

T-cold, and loop delta T7 A. T-hot Increases, T-cold Increases, loop delta T Decrease B. T-hot Increases, T-cold Increases, loop delta T remains the sam C. T hot Increases, T-cold Decreases, loop delta T Increase D. T hot Decreases, T-cold Increases, loop delta T Decrease _

ANSWER: A ATTACHMENTS: TIME VAL GBl KA NUMBER: 002/020/K5.09 RO: SRO: KA NUMBER- / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

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-l ' LESSON PLAN:ND- NUMBER: 4 TOPIC: PS REV DAiF: 09/21/92 i

SRO ONLY: RO OBJ: 6 SPO OBJ: 6 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 5 TIME: During NC system mid Hop operations, which of the following describes an -.

ALTERNATE method for controlling ND loop flow? -

A. Manually throttle the ND pump miniflow control valves B. Place 1NI 173A or 1NI 1788 'ND Disch to Cold Legs' in

'THROT' mode and adjust as necessar C. Start /Stop ND pumps as necessary to maintain core exit thermocouples less than require D. Align to Hot Leg Injection flow path and place 1NI-1838

'ND Disch to Hot Legs' in 'THROT' mode and adjust as necessar ANSWER: B ATTACHMENTS: TIME VAL MJB KA NUMBER: 000/025/EK1.01 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: AP/1/A/5500/19 REFERENCE #2:

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LESSON PLAN:lSL NUMBER: 1 TOPIC: TA REV DATE: 10/05/92 ,!

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SRO ONLY: RO OBJ: -1 SRO OBJ: 1 POINT VALUE: 1.00. pts, ISS OBJ: 1. PTRO OBJ: -1 TIME: Which of the following defines an Inter System LOCA (ISLOCA)?

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A. A loss of coo! ant through a high pressure boundary valve into a low pressure system connected to the NC syste B. A loss of coolant through a low pressure system that results in a dilution of emergency boration source C. Loss of coolant through a high pressure boundary that will eventually allow the ECCS system to be transferred to cold leg recirculatio D. A loss of coolani from a low pressure system that will render that low pressure system inoperabl ANSWER: A ATTACHMENTS:

KA NUMBER: 002/000/K1.08 RO: SRO: KA NUMBEP / ./ RO: SRO: K \ NUMBE / / RO: SRO: REFERENCE #1: Memo 4/2/90 from OSM

. REFERENCE #2: RE:lSLOCA informati i

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s O O PART B

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LESSON PLAN:EP NUMBER: 3 TOPIC: EL REV DATE: 09/16/92 i SRO ONLY: RO OBJ: 24 SRO OBJ: 24 POINT VALUE: 1.00 pts.

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ISS OBJ: O PTRO OBJ: 13 TIME: 2.2 l

Unit 1 is at 50% powe If 4160V essential bus 1 ETA is faulted with D/G 1 A,1 ATC, and 1 SATA incapable of -

supplying power to 1 ETA, what action is required?

A: Restore 1 ETA within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or S/D B. Restore D/G 1 A within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or S/D C. Apply 3. D. Restore one offsite circuit to 1 ETA within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or S/D ANSWER: A ATTACHMENTS:

KA NUMBER: 062/000/A2.04 RO: SRO: KA NUMBER: 062/000/ GEN 11 RO: SRO: KA NUMBER: 062/000/ GEN 15 RO: SRO: REFERENCE #1: T.S. 3/4 8-1 TO 8-18 REFERENCE #2:

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O O PART B I -

LESSON PLAN:CP NUMBER: 7 TOPIC: CP REV DATE: 11/14/90 SRO ONLY: RO OBJ: 7 SRO OBJ: 7 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 4 TIME: Overlap between ranges of Nuclear Instrumentation should not be less than 1 decade to insure: -

A. The oncoming range's protective interlocks are enable B. The compensation circuit for the oncoming range has received a permissive to energiz C. The oncoming range is providing reliable indicatio D. Performance has time to verify the heat balance ratio between the two range _

ANSWER: C ATTACHMENTS:

KA NUMBER: 001/010/K5.10 RO: SRO: KA NUMBER: 001/ GEN /10 RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: OP/1/A/6100/01 REFERENCE #2:

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LESSON PLAN:CP NUMBER: 13 TOPIC: CP ' REV DATE:' 11/15/90 SRO ONLY: RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.09 pt ISS OBJ: O PTRQ OBJ: 2 TIME: During a plant heatup following refueling, NC System temperature is 220 de EMF 39L currently indicates 3500 cpm and is sampl!ng all sample locations. What

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should be the TRIP 1 and TRIP 2 setpoints for EMF 39L?

A. Trip 1 - 5215 cpm, Trip 2 - 5950 cpm d. Trip 1 - 5600 cpm, Trip 2 - 8032 cpm C. Trip 1 - 7350 cpm, Tr:p 2 - 10,50d cpcn D. Trip 1 - 8000 cpm, Trip 2 - 11,475 cpm i

ANSWER: C ATTACHMENTS:

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KA NUMBER: 029/000/K1.01 RO: SRO: KA NUMBER: 029/000/A1.02 RO: SRO: 3.7-KA NUMBER: / / RO: 0.0 - SRO: REFERENCE #1: OP/1/A/6100/01 REFERENCE #2: .

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O PART B o .

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LESSON FLAN:ND NUMBER: 7 TOPIC: PS REV DATE: 09/21/92 -

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SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 4 TIME: Unit 1 is in cold shutdown with the loops fille j

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There are no plans to drain the NC syste ?

ND Train A is in operatio Steam generators A and B have been draine Steam generators C and D are 15% and 25% respectivel Mechanical Maintenance has submitted a work request for approval to begin work on the B train ND pump which requires disconnecting the motor fiorn the pump to replace the mechanical sea Which of the following statements are justified?

(Select one)

A. Approve the work request, since Tech. Specs. require only one RHR loop to be in operation and 2 SG levels greater-than 12%.

B. Do NOT aoprove the work request. Even though Tec Specs, allow one RHR loop to be inop9rable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, this work request is NOT considered to be surveillance testin C. Do NOT approve the work request, Tech. Specs. require both RHR trains operable with one in operation in this plant conditio D. Approve the work request, since the C.~1LY Tech. Spec requirement in this plant condition for decay heat removal is one RHR Loop operable.

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ANSWER: A ATTACHMENTS:

KA NUMBER: 002/000/G 11 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: T.S. 3.4.1. REFERENCE #2:

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-LESSON PLAN:EP4 NUMBER: J TOPIC: EP REV DATE: 09/21/92

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SRO ONLY: RO OBJ: 2 SRO OBJ: 2 POINT VALUE: 1.00 pt !

.J ISS OBJ: O PTRO OBJ: 2 TIME: l

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During a S/G tube rupture event on "A" S/G, EP1E is desioned to cooldown and depressurize the NC system to stop break flow. You wouid HOLD and not continue -* !

in the procedure IF: 1 A. the ruptured S/G is determined to be faulted als l B. all NCP's are off and subcooling is greater than 0 de )

C. the ruptured S/G PORV cannot be close '

D. required core exit temperatures for initial NCS cooldown are greater than require ANSWER: D ATTACHMENTS:

KA NUMBER: 000/038/EK3.06 = RO: SRO: KA NUMBER: / / RO: 'SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/1E3 i REFERENCE #2:

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O O PARTB

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LESSOrJ PLAN:EP4 NUMBER: 4 TOPIC: EP REV DATW: 09/21/92

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SRO ONLY: RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.00 p'.$.

ISS OBJ: O PTRO OBJ: 3 TIME: The following plant conditions exist:

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- 'B' S/G is ruptured

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NC system pressure m 1900 psl0 and 'B' S/G pressure is 950 psig Pr ictor cofant system temperature must be reduced to prior to

.nitiating de ressurizatio A, ,8 degF core exit T/C indication gM , p/ do0F highest Thot !ndication -D#

C. 500 degF core exit T/C indication M D. 500 degF highest Thot indication u. +

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ANSWER: A ATTACHMENTS: TIME VAL MJB KA .4 UMBER: 000/038/EK3.06 RO: SRO: KA NUMBER: 000/038/E A1.36 RO: SRO: KA NUMBER: / / RO: SRO: ,

REFERENCE #1: EP/1/A/5000/1E Rev14 REFERENCE #2:

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O O PARTB .

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LESSON PLAN:EP4 N'JMBER: 6 TOPIC: EP REV DATE: 08/27/510 SRO ONLY: RO OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt '

ISS OBJ: O PTRO OBJ: 4 TIME: i

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During a S/G tube rupture (EP1E), concurrent with a loss of off site power, the

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heat sink used is: (Select one)

A. Main condenser e B. Letdown heat exchanger C. Steam generator vie the PORV's l'

D. Pressurizer via the PORV's ANSWER: C ATTACHMENTS:

KA NUMBER: 000/038/EA2.08 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP 4 Lesson Plan -

REFERENCE #2:

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O O l PARTB >

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LESSON PLAN:EP4 NUMBER: 10 TOPIC: EP REV DATE: 08/07/90 SRO ONLY: RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.00 pt .

ISS OBJ: O PTRO OBJ: 3 TIME: ,

Following a SGTR,why must S/l be terminated as quickly as possible when PZR *

level recovers? (Select one)

A. Provent Head Vold Misdlagnosis B. Maintain Subcooled conditions in the PZR C. Provent over filling the ruptured S/G D. Provent occreasing < 5% in the ruptured S/G due to rapid backfill, i

ANSWER: C ATTACHMENTS: .

KA NUMBER: 000/038/EK3,06 RO: SRO: '

KA NUMBER: 000/038/E A2.15 RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/1E REFERENCE #2:

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O O 1 PARTB d

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. LESSON PLAN:EP4 :e.;MBER: 32 TOPIC: EP REV DATE: 10/05/92 SRO ONLY: RO O- 5 SRO OBJ: 2 POINT VALUE: 1.00 pt ISS OBJ: 0 PTRO OBJ: 2 TIME: ;

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DURING a SGTR on Unit 1 the operator has isolated S/G "A". The following conditions / indications exist: *

1) NCS subcooling 23 deg. F -

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2) NCS pressure 1080 psig stablo 3) Ruptured S/G "A" pressure 480 psig decreasing 4) Ruptured S/G "A" NR level 67 %

5) FWST level 45%

6) Containment Sump Level 1.5 ft Select the procedure flowpath the operator will be usin9 O lven the above information: (Select one)

A. EP/1E, EP/1E1, EP/164 B. EP/1E, EP/1E2, EP/1E3 C. EP/1E, EP/01, EP/1D D. EP/1E, EP/1E3, EP/1E4 ANSWER: D ATTACHMENTS:

KA NUMBER: 000/038/EA2.07 RO: SRO: '

KA NUMBER: 000/038/G-11 RO: SRO: 4,3 KA NUMBER: 000/038/G 12 RO: SRO: REFERENCE #1: EP/1/A/5000/1E3 REFERENCE #2:

i

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O O \

PART B

.ESSON PLAN:EP4 NUMBER: 11 TOPIC: EP REV DATE: 09/21/92 SRO ONLY: Y RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 3 TIME: A Unit 1 Reactor trip has occurred. ALL rod bottom lights are verified LI j

. !

Which ONE of the following evolutions would have the most restrictive Shutdown Margin requirements?

A. Natural Circulation cooldown following a Loss of Offsite powe B. Cooldown using Steam Generator Backfil C. Cooldown following a faulted steam generato D. Cooldown from the Auxiliary Shutdown panel ANSWER: B ATTACHMENTS:

KA NUMBER: 000/038/EA1.40 RO: SRO: KA NllMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/1E2 REFERENCE #2:

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PARTB )

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LESSON PLAN:EP4 NUMBER: 34 TOPIC: EP REV DATE: 09/14/92 -

SRO ONLY: RO OBJ: 1 SRO OBJ: 1 POINT VALUE: 1.00 pt ~

ISS OBJ: O PTRO OBJ: 1 TIME: Unit 1 was operating at 100% power with a tube leak in ~

'B' S/G of 75 gallons por DAY per OAC point P018 Over the last thirty minutes, the leak has increased to 135 gallons por DAY por P018 The propor response to this event would be to :

A. notify the Shift Manager and continue operation; leak rate is below Tech Spec limit B. notify Chemistry to sample to verify the OAC is correct prior to initiating shutdow C. initiate shutdown to bo in Modo 3 in G hour D. Initiate shutdown to be in Mode 3 in 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

ANSWER: C ATTACHMENTS:

KA NUMBER: 000/037/EK3.05 RO: SRO: KA NUMBER: // RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: SD 3,0.13 REFERENCE #2: > _

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O O PARTB

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LESSON PLAN:NI NUMBER: 8 TOPIC: ECCS REV DATE: 01/16/86 SRO ONLY: RO OBJ: 12 SRO OBJ: 12 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 10 TIME: The Nl pump recirc valve must be closed prior to swapping Ni pump suction from the FWST to the ND heat exchan0er discharge to: (Select one) *

A. Raise the NI pump discharge pressure B. Prevent pumping water from the containment sump to the FWS C. Allow pump suction and discharges pressures to stabilize prior to re openin0 rechc valv D. Prevent pumping water to the containment sum ANSWER: B ATTACHMENTS:

KA NUMBER: 006/020/A4.02 RO: SRO: KA NUMBER: 006/020/ GEN 7 RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: NI Lesson Plan REFERENCE #2: EP/1C3

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PARTB

LESSON PLAN:NI NUMBER: 11 TOPIC: ECCS REV DATE: 02/12/86 ,

SRO ONLY: RO ODJ: 16 SRO OBJ: 1 POINT VALUE: 1.00 pt ,

ISS OBJ: O PTRO OBJ: 10 TIME: With Tavg < 285 dog. F, a maximum of one centrifugal chargin0 pump and one safety injection pump may be operable. The basis for this is to assure that a *

mass addition:

A. pressure transient can be relieved by the operation of a single pressurizer safety valv B. pressure transient can be relieved by the operation of a single pressurizer POR C. of water from the FWST does not result in a positive rnoderator temperature coefficient at low temperature D. of water from the FWST does not result in vessel temperatura being reduced to a value below RTNDT.

,

ANSWER: B ATTACHMENTS:

KA NUMBER: 006/020/SG 6 RO: SRO: KA NUMBER: 006/050/A1.01 RO: SRO: KA NUMBER: 006/050/A4.04 RO: SRO: 4,3 REFERENCE #1: NI Lesson Plan REFERENCE #2: T.S. 3.5 and 3.5.3 l

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O O PARTB ,

LESSON PLAN:CSF NUMBER: 29 TOPIC: EP REV DATE: 09/16/92 SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 5 TIME: '

At 1200, a Unit 1 Safety injection has occurred. Given the following plant conditions at 1206 -

Reactor pwr 10( 7) amps IR NC Tc A 321 do >

- Startup rate 03 dptn NC Tc B 301 do Core Exit T/C's 340 do NC Tc C 310 dog F NC Tc D 240 dog,F NC Subcooling(ICCM) 35 dog,F NC pressure 622 psig NC pumps All OFF Containment pressure 4.2 psig RVLIS L/R 40 % Conteinment H2 Conc.1.0%

- PZRlevel 0% Total CA flow 585 gpm

. S/G A N/R Level 15% S/G A pressure 900 psig S/G B N/R Level 16% - S/G B pressure 896 psig S/G C N/R Level 20% S/G C pressure 903 psig

- S/G D N/R Level 0% - S/G D pressure 891 psig Select the highest priority critical safety function recovery procedure to be implementu A. EP/2D1 Imminent Pressurized Thermal Shock Condition B. EP/2E1 High Containment Pressure C. EP/2B1 Inadequate Core Cooling i D. EP/2C1 Loss of Secondary Heat sink ANSWER: A A iTACHMENTS:

KA NUMBER: 000/074/EK3.11 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: ' REFERENCE #1: EP/02 REFERENCE #2:

,

')

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O O PARTB s

LESSON PLAN:CSF

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NUMBER: 31 TOPIC: EP REV DATE: 09/21/92 SRO ONLY: RO OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt ISS OBJ: O PTRO 08.: 4 TIME: '

A Unit 1 Safety injection has occurred. Given the following plant conditions

,

NC Subcooling negative 15 do NC pressure 900 asig and stable .

RVLIS L/R 70% nereasing Containment pressure 3.4 psi Pzr level 60 % Containment H2 conc.1.3% g '

- Containment temo. 200 de PRT Rupturo Disk INTACT Which of the following is true concerning reactor vessel void remova; for this event?

A. NC System pressure must be increased to 2100 psig to collapse reactor vessel voids B. Vent reactor vessel head not to exceed 50 psig PRT pressure C. Vent reactor vessel head not to exceed 5.3 minutes vent time D. Roactor vessel head void will NOT be removed until subcooling is greater than 0 deg ANSWER: D ATTACHMENTS:

KA NUMBER: 000/009/EA2.38 RO: SRO: KA NUMBER: 000/009/EK3.11 RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/01 REFERENCE #2: EP/1/A/5000/02 .

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PARTB

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LESSON PLAN:CSF NUMBER: 61 TOPIC: EP REV DATE: 11/19/90

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SRO ONLY: RO OBJ: 2 SRO OBJ: 2 POINT VALUE: 1.00 pt i ISS OBJ: O PTRO OBJ: 2 TIME: ;

,

The main reason in attempting to maintain loop flow as long as possible during a >

PTS ovent is to: '

A. Utilize heat added by NC pump ;

B. Utilize pump seal flow for mixin C. Prevent natural circulation flo D. Provide mixing of cold water sources with loop wate i i

ANSWER: D ATTACHMENTS:

KA NUMBER: 000/040/EK3.04 RO: SRO: KA NUMBER: / / RO' SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/2D1 REFERENCE #2:

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OPART B O !

. LESSON PLAN:SEP NUMBER: 45 TOPIC: EP REV DATE: 09/21/92 -

SRO ONLY: Y RO OBJ: O SRO OBJ: 8 POINT VALUE: 1.00 pt *

ISS ORJ: O PTRO OBJ: 9 TIME: Units 1 and 2 are operating at 100% power when the following events occur:

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A tremor is felt in the control room

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"OBE Exceeded" annunciator is lit

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Lake Wylic levelis trending down

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What actions are reauired?

A. Immediately trip both Units and initiate SM isolation as secondary integrity cannot be ensure B. Immediately trip both Units and transfer RN to the SNSW C. Rapidly shutdown and cooldown both Units to Mode >

D. Shutdown both Units to Mode 3 ond transfer RN to the SNSW ;

ANSWER: D ATTACHMENTS: TIME VAL MJB,GBI i

KA NUMBER: 194/001/A1.16 RO: . SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: RP/07 REFERENCE #2: ONS 9281

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LESSON PLAN:SEP NUMBER: 28 TOPIC: EP REV DATE: 10/06/92

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SRO ONLY: Y RO OBJ: O SRO OBJ: 8 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 8 TIME: ' ,

Select one action based on the following situation: '

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National Weather Service has issued a Tornado Warning Northern York County

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Outsido rounds person radios a report of funnel clouds forming over the Nuclear Service Water Pon A. Transfer the RN suction and discharges to the Standby Nuclear Service Water Pcn B. Immediately begin a shutdown to Hot Standby C. Declare an Alert and conduct a Site Assembly D. Shutdown a!! Auxiliary, Spent Fuel and Containment Building ventilation systems that have outsido air intakes and exhaust duct ANSWER: D ,

ATTACHMENTS:

KA NUMBER: 194/001/A1.16 RO: SRO: 4.4 - -

KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: RP/0/A/6000/09

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REFERENCE #2:

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O O l PARTB ,

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LESSON PLAN:EP1 NUMBER: 61 TOPIC: EP REV DATE: 02/04/91 -

SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ,

ISS OBJ: O PTRO OBJ: 5 TIME: During testing of the Solid State Protection System an l&E Technician inadvertently actuated safety injection. The criteria to enter the " Termination *

Following Spurious Sl" procedure has been met. Sl and trie D/G load sequencers :

have boon reset. Once the RO stops all Si pumps except one NV pump, the following information is noted:

NC System Pressure 1830 psig decreasino slowly All NC Loop T Hot's 600 deg. F stablilzing Pressurizer Level 15% decreasing slowly 3 Based on the above information what action should the RO take? (Select one) ,

A. Restart other NV pump and monitor NCS pressure and Pzr leve B. Continue on with the procedure in effect unth pressurize levei decreases to 5%, then manually initiate S C. Close NI 9 and NI 10 and restart other NV pum '

D. Manually reinitiate St. Go to EP/1/A/5000/01 Safety injection, step ;

ANSWER: D ATTACHMENTS:

KA NUMBER: 000/009/EK1.02 RO: SRO: KA NUMBER: 000/009/EA2.01 RO: SRO: KA NUMBER: 000/009/EA2.04 RO: SRO: REFERENCE #1: EP/1/A/5000/1B REFERENCE #2:

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O O PARTB ;

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LESSON PLAN:EP1 NUMBER: 60 TOPIC: EP REV DATE: 03/30/92 SRO ONLY: RO OBJ: 7 SRO ODJ: 7 POINT VALUE: 1.00 pt ISS OBJ: O PTRQ OBJ: 7 TIME: l l

l A natural circulation cooldown is in progress because offsite power has been {

lost. The CRDM Cooling Fans cannot be loaded onto the AC Blackout Buse * '

How will tho inoperability of the CRDM Fans affect the cooldcwn and 9 depressurization? i

'

A. It has little affect because the amount of NC Systern Heat removed by running the fans is of little significance compared to that removed by steaming the secondary plan B. Transfer to EP-2F3 " Void in Reactor Vessel" will be required because cooldown and depressurization will cause formation of a ste6m void in the vessel hea C. Pressure must be reoused more rapidly to avoid a possible proe.surized thermal shock transien D. Greater minimum subcooling must be maintained, and the total upper head cocidown rate will be less.

,

ANSWER: D ATTACHMENTS:

KA NUMBER: 000/056/EK3.02 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/1 A1 RLFERENCE #2:

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oPARTr

. - LESSON PLAN:EP2 NUMBER: 52 TOPIC: EP REV DATE: 07/03/91 SRO ONLY: RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 3 TIME: A reactor trip and Sl occurred at 0100 with the reactor initially at 100% powe The control room operators were directed by EP/1C3. " Transfer to Cold Leg *

Recirculation", to EP/1C5," Loss of Emergency Coolant Recirculation", due to the inability to open NI 184 and 185 (Containment Sump Suction Valves). The following conditions currently exist at 0400:

. Total Si Flow Rate: 500 GPM

.

ECCS System allpned for injection mode

. FWST level: 6%

. Subcooling: negative 5 deg F

, All NC pumps are OFF

.

Attempts are be!ng made to open NI 184 & 185 locally

. RVLIS LR 61%

Based on these conditions the control room operators should:

A. Maintain 500 GPM flo B. Reduce total Si flow to approximately 115 GPM C. Stop all ECCS pumps aligned to the FWS D. Reduce total Si flow to approximately 225 GPM ANSWER: D ATTACHMENTS:

KA NUMBER: 000/011/G-12 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: "

REFERENCE #1: EP/1/A/5000/1CS REFERENCE #2: :

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O O PARTB

LESSON PLAN:EP2 NUMBER: 44 TOPIC: EP REV DATE: 12/10/85 SRO ONLY: RO OB SRO OBJ: 1 POINT VALUE: 1.00 pt ISS OBJ: 1 PTRO OBJ: 1 TIME: l

l The purpose of entering EP-1C1 (Si Termination following high energy lino break inside containment) is to: (Select one) *

A. Rapidly cooldown the NCS to less than 400 dog. B. Restore recirculation capabilit C. Terminate Si and place the plant in a stable conditio D. Terminate Si to prevent overfilling the containment sum ANSWER: C ATTACHMENTS:

KA NUMBER: 000/011/EA2.08 RO: SRO: KA NUMBER: / /- RO: SRO: KA NUMBER: / / RO: SRO: REFEPENCE #1: EP-2 LESSON PLAN REFERENCE #2:

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O O PARTB

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LESSON PLAN:EP3 NUMBER: 6 TOPIC: EP REV DATE: 09/21/97

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SRO ONLY: RO OBJ: 3 SRO OBJ: 3 POINT VALUE: 1.00 pt ,

ISS OBJ: O PTRO OBJ: 3 TIME: Given the following conditions, following a Unit 1 Safety injection: ,

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'A' S/G Pressure is 20 psig

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'B, C, D' S/G pressure is 500 psig

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CA flow to B, C, D S/G is 1960 gpm

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NC System pressure is 1100 psig and increasing

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Pzr levelis 56% and increasing

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'A' Tc is 300 deg F and increasing

-

'B, C, D' Tc is 420 dog F and increasing

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Containment pressure is 3.1 psig and decreasing

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What action should be taken to respond to these conditions?

A. Maintain current NC pressure and temperature to limit any further stresses on the plant, ,

B. Current limits are boing violated, immediately reduce pressure to < 800 psi C. Monitor the repressurization and do not allow NC pressure to exceed 1000 psi D. Allow NC System to heatup as pressure increases to maintain within allowable limit .

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ANSWER: B ATTACHMENT KA NUMBER: 000/040/G 12 RO: SRO: . KA NUMBER: / / RO: SRO: l KA NUMBER: / / RO: SRO: 0.0 t

REFERENCE #1: EP/2/A/5000/101 l- REFERENCE #2:

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O Q PART B

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LESSON PLAN:EP5 NUMBER: 9 TOPIC: EP REV DATE: 10/05/92 SRO ONLY: RO OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt .

ISS OBJ: O PTRO OBJ: 4 TIMd: .

A Unit 1 Reactor Trip has occurred. The following plant conditions are noted: ,

"

AD11 CO ' Zone A Lockout Trip' in alarm

- AD11 F3 ' Zone B Lockout Trip' in alarni '

D/G 1 A breaker falls to close D/G 1B fails to start Containment Pressure 1.5 psig 30 minutes later, the ' Zone A Lockout Trip' is cleared. Select the correct procedure flowpat '

A. EP/01 Reactor Trip or Safety injection EP/1 A Reactor Trip Response EP/1 A1 Natural Circulation Cooldown B. EP/03 Loss of All AC Power .

EP/3A Loss of All AC Power Recovery Without S/l required EP/1 A1 Natural Circulation Cooldown C. EP/01 Reactor Trip or Safety injection EP/1C High Energy Line Break loside Containment EP/1C1 S/l Termination Following Hi0h Ener0y Line Break inside Containment D. EP/03 Loss of All AC Power EP/3B Loss of All AC Power Recovery With S/l Required EP/01 Reactor Trip or Safety injection ANSWER: D ATTACHMENTS:

KA NUMBER: 000/05C/EA2.37 RO: SRO: KA NUMBER: 000/056/EK3.02 RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: EP/1/A/5000/03 REFERENCE #2: EP/1/A/5000/3B

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O O PART A

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LESSON PLAN:lPX NUMBER: 17 TOPIC: SSS07 REV DATE: 09/09/92

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SRO ONLY: RO OBJ: 10 SRO OBJ: O POINT VALUE: 1.00 pt ~

ISS OBJ: O PTRO OBJ: 7 TIME: Of the present plant failures, which one of the following must be repaired prior to entry into Mode 2? *

A. Pressurizer level CH I B. Manual Reactor Trip C. S/G 'C' Main Feed Regulating Valve D. Automatic Turbine Trip ANSWER: B ATTACHMENTS: TIME VAL GBl

- KA NUMBER: 012/000/G5 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: 0,0 REFERENCE #1: T.S 3. REFERENCE #2: MC1

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O O PART A

LESSON PLAN:SEP NUMBER: 14 TOPIC: SSS07 REV DATE: 09/05/92 SRO ONLY: Y RC OBJ: 1 SRO OBJ: 1 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 1 TIME: Prior to the reactor being shutdown, attempts to manually insert control rods were unsuccessful. Classify this event per the Station Emergency Plan. (select -

one)

A. Notification Of Unusual Event B. Alert C. Site Area Emergency D. General Emergency

,

ANSWER: C ATTACHMENTS: TIME VAL GBl KA NUMBER: 194 /000/A1.16 RO: 3,1 SRO: KA NUMBER:- / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: !!P/0/A/5000/01 REFERENCE #2:

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O O PART A

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LESSON PLAN.CSF NUMBER: 14 TOPIC: SSS07 REV DATE: 09/09/92 - *

SRO ONLY: RO OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 2 TIME: ,

,

Following the ATWS, why was it necessary to IMMEDIATELY trip the main turbine?

A. To preserve S/G weier inventory for heat sin B. To satisfy Reactor / Turbine trip logi C. To prevent exceeding the Tech. Spec. cooldown limit of 100 degF/h D. To prevent exceeding core design power peaking factor ,

,

/.NSWER: A '

ATTACHMENTS: TIME VAL GBl,MJB KA NUMBER: 000/029/EK3.06 RO: SRO: KA NUMBER: / / RO: SRO: .KA NUMBER: / / RO: SRO: REFERENCE #1: '

REFERENCE #2:

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O O PART A LESSON PLAN:CSF NUMBER: 13

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TOPIC: SSS07 REV DATE: 09/09/92 SRO ONLY: RO OBJ: 2 SRO OBJ: 2 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 2 T!ME: Which of the following describes the method by which heat was being removed from the reactor IMMEDIATELY prior to the reactor trip? *

A. Steam release to the atmosphere via S/G safeties onl B. Steam release to the atmosphere via S/G PORVs onl C. Steam release to the condenser via the condenser dumps onl D. Steam release to the condonser and atmosphere via condenser and atmospheric dump ANSWER: C ATTACHMENTS: TIME VAL MJB

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KA NUMBER: 041/020/K1.05 RO: SRO: KA NllMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: MC2 REFERENCE #2: Sl18

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O O !

PART A

'-

LESSON PLAN:CSF NUMBER: 8 TOPIC: SSS07 REV DATE: 01/01/91 FRO ONLY: RO OBJ: O SRO OBJ: O POINT VALUE: 1.00 pt ISS OBJ: O P1RQ OBJ: 3 TIME: Why is the " Heat Sink" Critical Safety Function in it's current status?

A. 'C' S/G N/R level < 18% 'C' S/G N/R level < 5%

C. Total feedwater flow > 450 gpm 'B' S/G Pressure < 1175 psig I

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,

' ANSWER: B '

ATTACHMENTS:

KA NUMBER: 059/000/A3,02 RO: SRO: 3,1 KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

. , . , _ , . . _ . . . _ . . . _ . _ _ _ _ _ _ _ _ _ . . _ . . _

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O O PART A '

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LESSON PLAN:NV NUMBER: 26 TOPIC: SSS07 REV DATE: 09/09/92 SRO ONLY: RO OBJ: 10 SRO OBJ: 10 POINT VALUE: 1.00 pt ISS OBJ: O Pi 10 OBJ: 8 TIME: *

Assume normal pressurizer spray is unavailable. While attempting to place NV *

auxillary pressurizer spray in service, the operator has determined present conditions do not allow its use. What must he do to make NV aux spray available?

(select one)

A. Rostore power to 1LXD B. Restore letdown flow '

C. Close 1NV312A and 1MV314A ' Charging Line Cont isol'

valves O. Ensure time since Reactor trip is greater than fifty (50) minutes

'!

ANSWER: B ATTACHMENTS: TIME VAL MJB KA NUMBER: 004/000/A2.07 . RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: 0.0 -

REFERENCE #1: OP/1/A/6200/01 REFERENCE #2: MC4 l

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O O l PART A r

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LESSON PLAN:NC NUMBER: 27 TOPIC: SSS07 REV DATE: 09/09/92 [

SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt I ISS OBJ: O PTRQ OB:1: 1 TIME: Which of the followinD si true regarding present NC cystem operating conditions? *

A. Pressure drop on the reactor trip has resulted in a toss of subcoolin B. Safety injection block on Low Steam Line Pressure should be inserte C. Pressure and Temperature are within required limits D. Unable to determine pressure / temperature relationship due to ICCM failur i ANSWER:- C l

! ATTACHMENTS: TIME VAL GBl,MJB l

KA NUMBER: 002/020/A3.01 RO: SRO: KA NUMBER:- / / RO: SRO: KA NUMBER:- / / RO: SRO: REFERENCE #1: OP/1/A/6700/01

' REFERENCE #2: DATA BOOK FIG 1.5 l-i

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PART A S

' *

LESSON PLAN:NC NUMBER: 26 TOPIC: SSS07 REV DATE: 09/09/92 SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 5 - TIME: Following restoration of ns.- wi letdown, which of the following would be of *

r concern to the operator?

A. Reduction in pressurizer level may result in a loss of pressure contro B. Reduction in presssurizer level would result in exceeding 'B loop NC heatup rate limi C. Letdown flow requirod to reduce pressurizer level mey damage resin bed D. Reduction in pressurizer level could result in exceeding the pressurizer heatup rate limi ANSWER: D ATTACHMENTS: TIME VAL GBl KA NUMBER: 002/000/A1.03 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: OPS PROF REFERENCE #2: MC10

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* -

.o PART A *

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NUMBER: 9

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LESSON PLAN:EHC TOPIC: SSS07 REV DATE: 09/09/92 SRO ONLY: RO OBJ: O SRO OBJ: O POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 2 TIME: Why was it necessary to trip the Main Turbine manually?

. -;

A. Failure of automatic trip sl nal 0 on low ETS pressure !

B. Reactor power dropped below P-9 before a trip signal was generate '

C. Failure of AMSAC to generate an automatic turbine tri D. Due in Rx Trip breakers failing to open, there was no turbine trip signal generate .

!

ANSWER: D ATTACHMENTS:

KA NUMBER: 012/000/K1.06 RO: SRO: .XA NUMBER: / / RO: SRO: . KA NUMBER: / / RO: SRO: REFERENCE #1: MC1 REFERENCE #2:

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h PART A

LESSON PLAN:ISL NUMBER:- 3 TOPIC: TA REV DATE: 09/12/92 SRO ONLY: RO OBJ: 4 SRO OBJ: 4 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 4 TIME: 1,0

"

Unit 1 is presently in Mode 5 at 0 psig NC W/P pressure. As the operator begins 3ressurizing the NC system, he discovers that NC W/R pressure on both B And C *

r + responding properly. Which of the following would be a valid ci -

7 tion of NC pretsure trend A '

atdown pressure p discharge pressure *

.initors D. NCDT pressure ANSWER: J ATTACHMENTS: TIME VAL GBI KA NUMBER: 002/000/A1.01 RO: SRO: KA NUMBER: / -/ RO: SRO: KA NUMBER: '/ / RO: SRO: REFERENCE #1:

REFERENCE #2:

.. .. - .. . . .. . . . - - -., -- . .

'

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PART A ,

LESSON PLAN:ISL- NUMBER: 4 TOPIC: TA REV DATE: 09/03/92

'

SRO ONLY: RO OBJ: 4: SRO OBJ: 4 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 4 TIME: ,

Unit 2 is in Mode 5. The 'A' ND suction relief has opened and failed to

.

'

reclose, Which of the following is a rollable indication of this event?

,

A. Radwaste Chemistry notices additional input to the RHT B. PRT Hi level alarm comas in: PRT level increasing C. ND system temperatures are abnormally high D. Containment Floor and Equipment sump pumps are starting frequently ANSWER: 8

.~ ATTACHMENTS: TIME VAL GBl KA NUMBER: 000/025/EA1,02 RO: SRO: K A' NUMBER: /- / RO: SRO:0.0-KA NUMBER: / / RO: SRO: REFERENCE #1: Memo 4/2/90 from OSM REFERENCE #2: RE: ISLOCA infor .

.

*

oPART A O

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. LESSON PLAN:EHC NUMBER: 2 TOPIC: GEN REV DATE: 09/12/92 SRO ONLY: RO OBJ: 6 SRO OBJ: 6 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 2 TIME: How will operation of the main turbine in the ' EMERGENCY MANUAL' mode affect the .W turbine's ability to respond to a reactor trip? '

A, All Turbine Controls are frozen; SM isolation would -

be performed B. No effect, Turbine will trip as required C. Manual Turbine trip would be required D, Turbine wiu not trip; depress ' Control Valves Lower'

to close control valve .

ANSWER: B ATTACHMENTS: TIME VAL MJB KA NUMBER: 045/050/K1.01 RO: 3 4 - SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: OP/1/A/6100/10B REFERENCE #2:

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.. e PART A -

" LESSON PLAN:CA ' NUMBER: 50 TOPIC: CF

'

REV DATE: 09/10/92 SRO ONLY: RO OBJ: 7 SRO OBJ: POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 5 TIME: Given the following:

.

-

Safety injection has occurre CA 58A 'CA Pump A Disch to S/G 18 Isol' has automatically close Which of the following could have caused 1CA-58A to close?

A. 1 A Motor driven CA pump has failed to start, B.18 Motor driven CA pump has failed to star C. The Turbirie driven CA pump has failed to star D. 1B Motor driven CA pump discharge flow is greater than 780 gp ANSWER: B ATTACHMENTS: TIME VAL MJB KA NUMBER: 061/000/K4.05 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

O

'

. .

O PART A

LESSON PLAN:CA NUMBER: 23 TOPIC: CF REV DATE: 09/10,92 SRO ONLY: RO OBJ: 5 SRO OBJ: 5 POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 5 TIME: The " Auto-start defeat" switch for the CA system will r reat or Block which one of the following Auto Starts? -

A. Safety injection B. AMSAC C. Blackout D. Low WR level in 'C' S/G i

_

ANSWER: B ATTACHMENTS:

KA NUMBER: 061/000/K4.06 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1:

REFERENCE #2:

J

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O O

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PART A LESSON PLAN:TS NUMBER: :5 TOPIC: ADM REV DATE: 10/05/92 SRO ONLY: RO OBJ: O SRO OBJ: O POINT VALUE: 1.00 pt ISS OBJ: O PTRO OBJ: 3 TIME: Assurne that #1 Main Turbine Control valve was discovered to be stuck full ope "

,

Which of the following describes an action that would satisfy Tech. Spe r9quirements? (m m,6 is presen6/r at 90% F,wer) 7 A. Close the #1 Main Stop valve within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Close all Main Stop valves within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Close the #1 Main Stop valve within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. Be in Mode 3 within 78 hour9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months ANSWER: B ATTACHMENTS:

KA NUMBER: 045/010/A3.01 RO: SRO: KA NUMBER: / / RO: SRO: KA NUMBER: / / RO: SRO: REFERENCE #1: T.S.3. REFERENCE #2:

v t e Inspection Report - Catawba - 1992303 (Operator Exams)
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
1992 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 24(0) 26(0) 27(0) 28(0) 29(0) 30(0) 31(0) Security Operator Exams 302(0) 303(0) Emergency Planning Other

IR 05000413/1992303

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