ML20246H085
| ML20246H085 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/21/1989 |
| From: | Bettendorf T, Bielby M, Hopper G, Jordan M, Muth J, Nejfelt G, Orton R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20246H056 | List: |
| References | |
| 50-373-OL-89-02, 50-373-OL-89-2, NUDOCS 8909010080 | |
| Download: ML20246H085 (98) | |
Text
-, .
, 8 b :. 1 U.S. NUCLEAR REGULATORY COMMISSION REGION III
~ Report No. 50-373/0L-89 c Docket Nos. 50-373 and 50-374 Licenses Nos. NPF-11 and,NPF-18 Licensee: Commonwealth Edison Company Post Office Box'767 Chicago, IL 60690 Facility Name: LaSalle County Nuclear. Station Examinations Administered at: LaSalle County Nuclear Station Marseilles IL 61341 Examinations. Conducted: . August 1-4,.1989 NRC Examiners: T. Bettendorf ,Q 7/f -/7-J7 G. Hopper /.L. # 6Mg #T-/7-N
(#f"fV J. Muth A #I-/7-U Date
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G. Nejfelt ,4,/7 4?Y7-df7' h Date R. Orton L . ),7 ' (M O/-/7-/f Date Chief Examiner: M. Bielby,.Sr. Lb/ a,/[ -/78[
Approved By: M. J. Jordan, Chief 2/ [f 7 Operator Licensing Section Date 8909010000 090823
- PDR x_
ADOCK 05000373
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Examination Summary Examination administered on August 1-4, 1989 (Report No. 50-373/0L-89-02)
Written and operating requalification examinations were administered to nine Senior Reactor operators (SR0s) and six Reactor Operators (R0s). In conjunction with the simulator portion of these examinations, two shift crews and one non-shift crew were evaluated.
Results: The NRC failed one R0 and one shift crew, while the facility failed the sarae R0 and initially passed all crews on the simulator examinations. The NRC inserted an additional crew critical step in one of the simulator scenarios, and after reevaluation, the facility also failed the associated crew. The NRC passed all individuals on the written and walkthrough examinations. The facility final examination results satisfied the NRC criteria for parallel grading. The requalification program has been assigned an overall rating of satisfactory. However, a programmatic concern with procedural compliance has been identified (see Paragraph 4).
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REPORT DETAILS
- 1. Examiners M. Bielby, Sr., Chief Examiner, NRC, Region III T. Bettendorf, Examiner, Pacific Northwest Laboratory (PNL)
G. Hopper, Examiner, NRC, Region III J. Muth, Examiner, PNL G. Nejfelt. Examiner, NRC, Region III 1 R..Orton, Examiner, PNL
- 2. Exit Meeting l
An exit meeting was conducted on August 7, 1989, at the LaSalle County Nuclear Station. Follow-up telephone conference calls were also conducted August 8-11, 1989.
Commonwealth Edison Comp _any Representatives
+G. J. Diederich, Station Manager J. K. Walkington, Services Director L. E. Davis, Operations Program Director W. R. Huntington, Technical Superintendent W. R. Betourne, Quality Assurance Superintendent
- S. R. Harmon, Operations Training Group Leader
- J. H. Atchley, Operational Engineer
- J. V. Schmeltz, Operational Engineer l T. A. Hammerich,. Regulatory Assurance Supervisor D. J. Sheldon, Training Instructor J. K. Cox, Training Instructor l
NRC Representatives
+M. J. Jordan, Section Chief, Operator Licensing
- +M. E. Bielby, Sr., Chief Examiner i G. M. Nejfelt, Examiner l R. Kopriva, Resident Inspector
- Present during August 8-9, 1989 telecon calls.
- Present during August 10, 1989 telecon call.
+Present during August 11, 1989 telecon call.
l The following items were discussed during these meetings:
NOTE: At the' time of the exit meeting all of the evaluations and comments had not been finalized and, as a result, some of the I following items were not discussed at that time.
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- a. . The NRC recognizes the effort expended in the development of the requalification materials. The quantity of materials developed exceeded the regnired amount. The following comments were made about the quality of the examination materials:
(1) The simulator scenarios and Job Performance Measures (JPMs) were very good technically. A run through of the JPMs during preparation week uncovered several procedural deficiencies which were promptly corrected by the Training Staff. The simulator scenarios were challenging. Substantial. changes were necessary in the delineation of critical steps.
(2) A substantial portion of the JPM question were of the recall / recognition knowledge level. A greater emphasis needs to be placed on the higher knowledge levels such as comprehension, evaluation, and application.
- b. The following comments apply to the conduct of the examinations:
(1) In general, the facility evaluators performed in a satisfactory manner during the walkthrough portion. The NRC agreed to allow the facility evaluators to ask probing questions during performance of the JPMs to elicit necessary information as long as the questions did not interfere with, or glean a response from the operator. Several facility evaluators exhibited excellent technique.
(2) It was noted that one facility evaluator upon completion of the JPM promptly corrected and discussed problems encountered during performance of a JPM with the operator. The NRC feels this is an effective training tool.
(3) The NRC commends the facility evaluators for their technique of writing down, and repeating, the operator's responses to JPM questions. However, some evaluators did not demand the same level of response from all operators for similar items (one time actual performance (i.e., requiring a fuse puller) was required, another time a verbal response was acceptable).
Consistency on what is expected of the candidates needs to be established.
(4) Although the Training Staff cooperated in obtaining the necessary simulator time for the NRC during preparation week, the NRC felt they were being pressed for time. In the future the NRC would expect a minimum of five, eight hour days for simulator use, scheduled two weeks prior to the examination during the day shift.
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- 3. Examination Results Comparison A comparison of the examination results between the facility and the NRC grading identified the following:
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- a. :The facility and NRC passed all operators on the written and walkthrough portions of.the examinations.
b.- The facility failed one RO on the simulator for failure.to perform two critical steps. This agreed with the NRC results.
- c. The facility initially. passed all crews on the simuistor examinations while the NRC failed one of the shift crews. This crew performed satisfactorily on the'first and third scenarios, however; on the second scenario, a _ licensed SR0 acting as the Shif t Supervisor (SS) and directing the crew in the implementation of. Emergency Operating Procedures (EOPs), allowed reactor water level to go more than three feet below the top of active fuel (TAF) before regaining control.
In add.ition, he-did not follow a procedural step that requires rapid depressurization of the vessel if level cannot be maintained at or above TAF. In conjunction with this weakness in the SS the crew l failed to provide support by not ensuring proper actions of.the.EOPs-
! . were being implemented.
The crew had ample opportunities to recognize weaknesses and/or errors made by other crew members and to ensure that major safety
- items were implemented. During the briefing to the operators, the following instructions were given:
(1) Team work and communications between operators is evaluated.
(2) If an operator recognizes an incorrect decision, response, answer, analysis, action taken, or interpretation of the team of which the operator is a part but fails to correct, then the examiner may assume that the operator agrees with the incorrect item.
Follow-up discussions'with the Training Staff evaluators and Operating representatives indicated they supported the actions of the crew based on the SS responses to questions during the crew critique. After lengthy discussions between the facility and NRC, the NRC' identified a post-scenario crew critical step end required the facility to reevaluate the crew. Based on the new crew critical
- step the facility failed the crew.
- 4. Facility Requalification Programmatic Concerns
- a. The. facility's practice appeared to be one of condoning procedural noncompliance as long as the actions seemed to be~ acceptable or the individual / crew believed they could regaii control. The opportunity to evaluate this practice was afforded the NRC on several occasions during the simulator examinations:
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' (1),~During performance.of.a JPM to restart a tripped Reactor Recirculation Pump-(RRP), the procedure required the operator.to check certain interlock-switches'in the bypass position., The i operator verified this by observing the associated. interlock '
alarms were not annunciated.- The facility evaluator condoned the' operator actions, in. lieu of checking the switches.
(2) During an Anticipated Transient Without Scram (ATWS) scenario e with reactor water level decreasing just below zero (approximately -2) inches indicated, Shift Crew #1 chose to !
initiate vessel depressurization although the Emergency Operating Procedures (EOPs) require this step if water level cannot be maintained.above the Top of Active Fuel (TAF) (-136 i inches). This action was condoned by the Training Staff and Operations's evaluators.
(3) During simulator scenarios for Shift Crew #2, the NRC noted the i following: l (a) During a scenario, the.R0 was instructed to place the High :
Pressure Core Spray system in service for reactor water l 4
level control. Although not in the procedure, the R0 '
throttled the Test Bypass Line Valve to control the rate of injection into the-vessel. A Training Staff Evaluator l later remarked that this was the first time he had seen !
this method of water level. control performed. It was also i pointed out that this method would not have worked if i reactor. vessel pressure had.been higher. During the crew critique both the Training Staff and Operation's Evaluators praised the R0 for this method of level control. l (b) During a different scenario, the crew was responding to an i
" Anticipated Transient Without a Scram" (ATWS) event per the E0Ps, and the SS directed a water level range be i maintained above TAF; however, level continued below TAF i even .after Reacter Core Isolation Cooling (RCIC) was ,
reported in service. The SS and crew allowed level to !
decrease 40 inches below TAF in spite of the fact that E0Ps require the vessel to be rapidly depressurized if water level cannot be maintained above TAF. The crew was commended at the crew critique for regaining control of water level. The facility evaluators initially passed the crew while the NRC failed them. !
During follow-up discussions of the crew failure, the facility (Training Staff and Operations) disagreed with the NRC on the failed crew's response to the ATWS event.
The facility contended that although water level was q decreasing below TAF (reaching a maximum of 40 inches !
I below)
(10% openRCIC was injecting)and on bypass valve . In Feedwater addition, the was. being throttled facility agreed with the SS that reactor pressure was above the Minimum Alternate Flooding Pressure (MAFP), thus assuring adequate core cooling (irregardless of water level).
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The NRC noted that the E0Ps require water level to be maintained above TAF, otherwise the vessel is to be rapidly depressurized. E0Ps do not specify a range or time period for water level to be below TAF before restoring above TAF. In addition, according to E0Ps, MAFP criterion is not applied until after the vessel is depressurized (i.e., it does not apply at all times).
- b. The NRC is concerned that both the Training Group and Operations condone procedural noncompliance (especially in the E0Ps). Prcper ,
emphasis needs to be placed on procedural compliance during plant accident conditions. Operator / crew actions should be taken based on actual plant conditions using available indications and the procedures addressing those conditions.
- 5. Overall Requalification Program Evaluation The requalification program was assigned an overall program rating of satisfactory. The evaluation criteria of NUREG-1021, Revision 5, was mot.
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REQUALIFICATION PROGRAM EVALUATION REPORT Facility: LaSalle County Nuclear Station Chief Examiner: M. E. Bielby, Sr.
Dates of Evaluation: August 1-4, 1989 Areas Evaluated: Written, Oral, and Simulator Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M, or U)
Written Examination 6/0 9/0 15/0 S Operating Examination Oral 6/0 9/0 15/0 S Simulator 5/1 9/0 14/1 S Evaluation of facility written examination grading: S Crew 1 Crew 2 Crew 3 Evaluation Crew Examination Results Pass / Fail Pass / Fail Pass / Fail S, M, or U Simulator Examination Pass Fail Pass S Overall Program Evaluation Satisfactory - A major deficiency was procedural noncompliance (see Exam Report, paragraph 4)
Submitted: Forwarded: Approved:
f\ $1 g g) i M. E. Bielby, Sr. M. J. Jordan G. C. Wright Examiner Section Chief Branch Chief 08/z2/89 08/2.t/89 08/$/89 8
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LASALLE COUNTY STATION A1 TYPE STATIC SIMULATOR EXAM REQUAL 89-28 MODULE 5 1-l TOTAL POINTS 12.25 ANSWER KEY l
- M ' STER CCP APPROVAL:
LSCS TRAINING GROUP LEADER / DATE j
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ox A1 STATIC EXAM MOD 89-28 REV 1 7/27/89' INSTRUCTIONS TO INSTRUCTOR o
L OVERVIEW: The plant is at approximahiy 100% power.with failures
.present on various plant- systems.
PRESENTLY STORED IN IC d ON THE "A" DISK SIMULATOR SET-UP: .
o Road through instructions once before doing them, o~ Select IC 16 with timer FALSE.
-o . Align normal systems as described in NORMAL SYSTEM LINEUP.
o insert malfunctions and overrides as described in that section.
o- If it is necessary to delete dos to enter all the OVDOs, delete the H2Recombiner items.
o Snapshot into IC 51 NOTE: IF THE SCENARIO IS IN A ctE-STORED IC, BEGIN AT THIS POINT AND AECALL THE SPECIFIC IC lt. STEAD OF IC 51.
o Recall IC 51(or stored IC), with the timer FALSE, and go to RLM.
o Advance all charts until there are no traces of previous trends visible.-
o Verify all conditions specified in NORMAL SYSTEM LINEUP section exist.
o VERIFY that all control switch targets match pump and breaker condition.
o Recall IC 51 (or stored 10). Toggle the timer TRUE. DO NOT go to RUN yetit o Advance all control room typers to clear all information in the buffers and to provide a clear start point for information from this exam.
A1 STATIC EXAM MOD 89-28 REV 1. 7/27/89 o Go to RUN.
o Acknowledge alarms and FREEZE machine at 1:00 on CT clock.
o Verify the answer to each question is correct for the existing plant conditions. It is very important that this is done BEFORE the students enter the ' simulator. If the answer to any.
question is not correct for existing plant conditions change the answer' key or make a note of it for later consideration.
o After all answers are verified, SNAPSHOT existing plant conditions into a BLANK (UNUSED) IC.- This IC will be used to verify plant conditions if any questions arise during exam grading. Please note which 10 was used in the space below.
ACTUAL EXAM CONDITIONS STORED IN IC STUDENTTURNOVER o The plant is near 100% power o The simulator was stopped 1:00 after the beginning of the malfunctions.
L A1 STATIC EXAM MOD 89-28 REV 1 7/27/89 NORMAL SYSTEMS LINE-UP:
QUESTION A1.01 (0.75) Rev 1 7/12/89
- 1. Select simulator initial conditions so that core flow is obviously greater thari 70 %, 75.6 x 106 lbm/hr. - A ~1 ,,
- 2. Place both Reactor Recirculation loop flow controllers into
- O MANUAL
- 3. Adjust "B" loop flow controlle so that it is 3,500 GPM less ,
than "A" loop flow. m 3,.;;,2 OUESTION: A1.02 (0.75) Rev 1 7/12/89
- 1. Start OFP01KA, the "A" diesel fire pump.
- 2. Verify that the alarm R1013, for lo fuel level, has printed on the SOE typer after the Malf timer is true.
QUESTION A1.03 (1.0) Rev 1 7/12/89 -
- 1. Perform LOS RI-Q3 to step F.5.
QUESTION A1.07 (0.5) Rev 1 7/12/89
- 1. Verify the Main Turbine is on line.
QUESTION A1.08 (0.75) Rev 1 7/12/89
- 1. Close the ADS valves' air supply solenoid operated valves (11N100 and 11N101) on the 1PM13J panel.
QUESTION A1.11 (0.75) Rev 1 7/14/89
- 1. 'A' RHR running in any mode of operation.
- 2. The division I (one) ADS inhibit switch in the INHIBIT position.
QUESTION A1.41 (0.5) Rev 1 7/12/89
- 1. Ensure both TDRFPs are in three element control
- 2. The Actuator Selector Switch is selected to "A" TDRFP
- 3. The FRV M/A station is in MANUAL at 50% demand.
- 4. The Startup Controller is at 0% demand.
- 5. Put an orange ring on the Actuator Selector Switch.
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1 A1 STATIC EXAM MOD 89-28 REV 1 7/27/89 QUESTION A1.48 (1.0)'
Rev 1 7/12/89
- 1. Start SBGT QUESTION A1.79 (0.5) Rev 1 7/12/89
- 1. Start "A" RHR in full flow test.
l QUESTION A1.81 (1.0) Rev 1 7/12/89
- 2. Adjust governor to 3000 kw
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' A1 STATIC EXAM MOD 89-28 REV 1 7/27/89 lo OVDO-CD-17-O-Set, F423B Open. Lamp -
o OVDO-CD-17-N-Reset, F423B Close Lamp o OVDO-RI-4-P-RESET, Stm Ln Drn Viv E51-F025 PCIS Sta s
o OVDO-RI 5-A-SET,- Stm Ln Drn Viv E51-F025 PCIS Sta o' OVDO RI-5 B-RESET, Stm Ln Drn Viv E51-F026 PCIS Sta 0 OVDO-RI-5-C-SET, Stm' Ln Drn Viv E51-F026 PCIS Sta o OVDO-VG-3 B-Set, Trip 1 (*C" VC rad monitor high high) o OVGO;VG-3 C-Set, Amber Trip 2 ("C" VC rad monitor high rad) o OVDO-VG-3-E-Set, Trip 1 ("D" VC rad monitor high high rad) o OVDO-VG-3-F-Set, Amber Trip 2 ("C" VC rad monitor. high rad) o DMAL-CR-1-J-0:00, Fail: the SJAE PCV o DMAL-NI-4-E-125%, APRM "E" out of cal Hi o DMAL-NI-4-1-25%, APRM "C" out of cal Low o OVDI-CD-17-B-Set, F423B Closes o OVAN-06-1-E-Reset, ADS accumulator low pressure alarm.
o- OVAN-06-1-F-Reset, ADS accumulator low pressure alarm.
o- OVAN-06-1-G-Reset, ADS accumulator low pressure alarm.
o OVAN-06-1-H-Reset, ADS accumulator low pressure alarm.
o OVAN-06-1-1-Reset, ADS accumulator low . pressure alarm.
o OVAN-06-1-J-Reset, ADS accumulator low pressure alarm, o OVAN-06-1-K-Reset, ADS accumulator low pressure alarm.
o OVAN-07-2-C-SET, Generate RR seal stage flow alarm o OVAN-18-2-1-Set, Control room HVAC CAM trouble o .OVAN-18-2-K-Set, Control room HVAC CAM trouble o OVAN-24-1-G-Set, Control room HVAC Sys o OVAN-20-3-J-SET, R1013 for Diesel fire pump fuel level lo.
o OVAO-RR-1 0.86000,' INCREASE "A" RR seal # 2 pressure.
o OVAO-PC-1-A-0.90, INCREASE DWEDS temperature.
o OVAO-RS-1-H-0.90, increase fire header pressure.
o OVAO-VG-1-F-0.4000, SBGT outlet flow recorder - 2000 scfm o CANA-SL-1-D-1.00, Open the SBLC test tank outlet valve.
o CDIG-MI-3-1-ON, Deactivate the printer freeze permissive.
o CDIG-RM-2-O-on, Place the "A" RHRSW rad monitor in service.
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a A1 STATIC EXAM MOD 89-28 REV 1 - 7/27/89 OUESTION A1.01' (0.75) Rev 1 7/12/89 SIMULATOR SET -UP:
- 1. Select simulator initial conditions so that core flow is obviously greater than 70 %, 75.6 x 106 lbm/hr.
- 2. Place both Reactor Recirculation loop flow controllers into MANUAL c 3. Adjust "B" loop flow controller so that it is 3,500 GPM less than "A". loop flow.
QUESTION: A1.02 (0.75) Rov 1 7/12/89 SIMULATOR SET-UP:
- 1. Start OFP01KA, the "A" diesel fire pump.
- 2. Increase fire header pressure: OVAO-RS-1-H-0.90
- 3. Insert OVAN-20-3-J-SET, R1013 for fuel level lo.
- 4. Verify that the alarm (3. above) has printed on the SOE typer.
QUESTION A1.03 (1.0) Rev 1 7/12/89 Simulator Set-up
- 1. OVDO-RI-4-P-RESET - Stm Ln Drn Viv E51-F025 PCIS Sta
- 2. - OVDO-RI-5-A-SET - Stm Ln Drn Viv E51-F025 PCIS Sta
- 3. OVDO-RI-5-B-RESET - Sim Ln Drn Viv E51-F026 PCIS Sta
- 4. OVDO-RI-5-C-SET - Stm Ln Drn Viv E51-F026 PCIS Sta
- 5. Perform LOS-RI-03 to step F.5.
QUESTION A1.04 (0.75) Rev 1 7/12/89 Simulator Set-up:
- 1. DMAL-NI-4-E-125% - APRM "E" out of cal Hi
- 2. DMAL-NI-4-1-25% - APRM "C" out of cal Low QUESTION A1.07 (0.5) Rev 1 7/12/89 SIMULATOR SET-UP:
With the Main Turbine on line:
- 1. OVDO-CD-17-O-Set F423B Open Lamp
- 2. OVDO-CD-17-N-Reset F423B Close Lamp
- 3. OVDI-CD-17-B-Set F423B Closes
- 4. Run the simulator for 30 seconds to allow F423B to repostion.
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A1 STATIC EXAM MOD 89-28 REV 1 7/27/89 7
QUESTION A1.08 (0.75) Rev 1 7/12/89 SIMULATOR SET-UP:
- 1. Close the ADS valves' air supply solenoid operated valves (11N100 and ilN101) on the 1PM13J panel.
- 2. OVAN-06-1-E-Reset, ADS accumulator low pressure alarm.
- 3. OVAN-06-1-F-Reset, ADS accumulator low pressure alarm.
- 4. OVAN-06-1-G-Reset, ADS accumulator low pressure alarm. '
- 5. OVAN-06-1-H-Reset, ADS accumulator low pressure alarm.
- 6. OVAN-06-1-1-Reset, ADS accumulator low pressure alarm.
7.- OVAN-06-1-J-Reset, ADS accumulator low pressure alarm.
- 8. OVAN-06-1-K-Reset, ADS accumulator low pressure alarm.
QUESTION A1.11 (0.75) Rev 1 7/14/89 SIMULATOR SET-UP:
- 1. 'A' RHR running in any mode of operation.
- 2. The division I (one) ADS inhibit switch in the INHIBIT position.
QUESTION A1.14 (0.75) Rev 1 7/12/89 SIMULATO3 SET-UP:
- 1. From rated vessel pressure, INCREASE "A" RR seal # 2 pressure: OVAO-RR-1-0-0.86000.
- 2. INCREASE DWEDS temperature: OVAO PC-1-A-0.90
- 3. Generate seal stage flow alarm: OVAN-07-2-C-SET.
QUESTION A1.41 (0.5) Rev 1 7/12/89 SIMULATOR SET-UP:
- 1. Both TDRFPs are in three element control
- 2. The Actuator Selector Switch is selected to "A" TDRFP
- 3. The FRV M/A station is in MANUAL at 50% demand.
- 4. The Startup Controller is at 0% demand.
- 5. Put an orange ring on the Actuator Selector Switch.
QUESTION A1.46 (0.75) Rev 0 5/19/89 SIMULATOR SET-UP:
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- 1. Open the SBLC test tank outlet valve: CANA-SL-1-D-1.00
- 2. Allow 1 minute for the valve to open fully.
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A1 STATIC EXAM MOD 89-28 REV 1 7/27/89 QUESTION A1.48 (1.0) Rev 1 7/12/89 SIMULATOR SET-UP:
- 1. Start SBGT
- 2. Fail the outlet flow recorder to 2000 scfm:
(OVAO-VG-1 -F-0.4000) .
QUESTION' A1.51 (0.5) Rev 1 7/12/89 ,
SIMULATOR SET-UP:
- 1. Select IC 16
- 2. Fail the SJAE PCV: DMAL-CR-1-J-0:00 QUESTION A1.58 (1.0) Rev 1 7/12/89 SIMULATOR SET-UP:
OVDO-VG-3-B-Set, Trip 1 ("C" VC radiation monitor high high rad)
OVDO-VG-3-C-Set, Amber Trip 2 ("C" VC radiation monitor high rad)
OVDO-VG-3-E-Set, Trip 1 ("D" VC radiation monitor high high rad)
OVDO-VG-3-F-Set, Amber Trip 2 ("C" VC radiation monitor high rad) ,
OVAN-18-2-1-Set, Control room HVAC CAM trouble OVAN-18 2-K-Set, Control room HVAC CAM trouble OVAN-24-1-G-Set, Control room HVAC Sys OUESTION A1.79 (0.5) Rev 1 7/12/839 SIMULATOR SET-UP:
'1. Start "A" RHR in full flow test.
- 2. Place the "A" RHRSW rad monitor in service:CDIG-RM-2-O-on.
QUESTION A1.81 (1.0) Rev 1 7/12/89 SIMULATOR SET-UP: -j
- 2. Adjust governor to 3000 kw I
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>- SIMULATOR SET -UP:
i 1, . Select simulator initial' conditions so that core flow is obviously greater than 70 %, 75.6 x-10 6 lbm/hr.
'2. Place. both- Reactor Recirculation. loop flow controllers into MANUAL
- 3. Adjust."B" loop flow controller so that it is 3,500 GPM less than:"A" loop flow.-
QUESTION A1.01 (0.75) Rev 1 7/12/89 ,
Given current plant. conditions, which gne of the following Technical Specifications LCO(s) is(are) NOT met?
- a. 3.4.1.1. Recirculation loops
- b. 3.4.1.3. Recirculation loop . flow
- c. 3.4.1.5. Thermal hydraulic stabilty
- d. 3.4.6.1. Reactor cooiant . system ANSWER:
- b. 3.4.1.3. Recirculation loop flow K/A : 202602 A2.09, G.5, G.11 202001 K4.11, A1.01, A4.04, A4.12, G.5, G.11 202002.G.6, G.11 201004 G.6, G.11 TKO/TPO: C-294001-2.08 / C-294001-03 TRO- 89:A.3., 89:B.4.G ESTIMATED TIME: 5 Minutes
REFERENCE:
LOS-AA-D1 Step F.7. (2360 GPM,4720 GPM)
Tech Spec 3.4.1.3. Recirculation Loop Flow
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SIMULATOR SET-UP:
- 1. Start OFP01KA, the "A" diesel fire pump.
- 2. Increase fire header pressure: OVAO-R S-1 -H-0.90
- 3. Insert OVAN-20-3-J-SET, R1013 for fuel level lo.
- 4. Verify that the alarm (3. above) has printed on the SOE typer.
QUESTION: A1.02 (0.75) Rev 1 7/12/89 By inspection of indications available in the control- room, the "A" '
diesel fire pump is NOT operable. Why?
ANSWER:
Fuel tank level is too low by alarm indication.
K/A: 286000 G.11, A4 01 .
TKO/TPO: D-286000-1.03 / D-286000-01 TRO-. 89:B.27.1.
ESTIMATED TIME: 2 Minutes
REFERENCE:
Tech Spec 3/4.7.5.1. Fire Suppression Water System LOA 1PM10J-B501 R Point R1013
l Simulator' Set-up
- 1. OVDO-RI-4-P-RESET - Stm Ln Drn Viv E51-F025 PCIS Sta
- 2. OVDO-RI-5-A-SET - Stm Ln Drn Viv E51-F025 PCIS Sta
- 3. . OVDO-RI 5-B-RESET - Stm Ln Drn Viv E51-F026 PCIS Sta
- 4. OVDO-RI-5-C-SET - Stm Ln Drn Viv E51-F026 PCIS Sta
- 5. Perform LOS-RI-O3 to step F.5.
QUESTION A1.03 (1.0) Rev 1 7/12/89 LOS-RI-03 is completed to step F.5. _ Which gne. of the following correctly describes the operation of the automatic valves?
- a. All automatic valves have operated as designed.
Answer:
K/A: 217000 A3.01 TKO/TPO: C-217000-3.02 / C-217000-03 TRO. 89:A.5.
ESTIMATED TIME: 2 Minutes
REFERENCE:
System Description Chapter 41 LOS-RI-O3 Step F.4.d.2)
I' 4
g Simulator Set-up:
l
- 1. DMAL-NI-4-E-125% - APRM "E" out of cal Hi l
- 2. DMAL-NI-4-1-25% - APRM "C" out of cal Low QUESTION A1.04 (0.75) Rev 1 7/12/89 APRM "C" is currently indicating lower than actual power. Given current plant conditions, which one. of the following conditions correctly describes the status of APRM "C"?
- a. The high neutron flux scram function for APRM "C" is less conservative than required by Tech Speu.
- b. The low output of APRM "C" will affect the plant heat balance calculation.
- c. The LCO for APRM rod blocks is NOT met.
- d. None of the above.
Answer:
K/A 215005 A1.07. A2.08, G.5, G.6 TKO/TPO: C-215005-1.01, 1.02, 1.08 / C-215005-01 TRO' . 89:A.5.
ESTIMATED TIME: 3 Minutes
REFERENCE:
Tech Spec 3.3.1 and Table 4.3.1.1-1 Note (d)
System Description Chapter 14 ,
M l q
<- SIMULATOR SET-UP: 4 With the Main Turbine on line: i 1'. OVDO-CD-17-O-Set F423B Open Lamp
- 2. OVDO-CD-17-N-Reset F423B Close Lamp !
p 1
- 3. OVDI-CD-17-B-Set ~F423B Closes
- 4. Run the simulator.for 30 seconds to allow F423B to repostion.
l QUESTION ' A1.07 (0.5) Rev 1 7/12/89
'The. following statement is TRUE. -High pressure steam is currently supplying the "B" turbine. driven reactor feed pump. How was this determined _ using . current plant indications?
ANSWER:
"B" TDRFP Control valve position (>50% open) indicates the High.
Pressure steam control valve is open.
K/A: 259001 K1.20 TKO/TPO: C-295001-2.01 / C-259001-02 M O: 89:A.S.
ESTIMATED. TIME: 2 Minutes REFEFENCE: LOS-FW-SR1 Step F.3.f. CAUTION and NOTE System Description Chapter 29 e
1
. 1 I
i SIMULATOR SET-UP:
- 1. Close the ADS valves' air supply solenoid operated valves (11N100 and ilN101) on the 1PM13J panel.
- 2. OVAN-06-1-E-Reset, ADS accumulator low pressure alarm.
- 3. OVAN-06-1-F-Reset, ADS accumulator low pressure alarm.
- 4. OVAN-06-1-G-Reset, ADS accumulator low pressure alarm.
- 5. OVAN-06-1-H-Reset, ADS accumulator low pressure alarm.
- 6. OVAN-06-1-1-Reset, ADS accumulator low pressure alarm.
- 7. OVAN-06-1-J-Reset, ADS accumulator low pressure alarm.
- 8. OVAN-06-1-K-Reset, ADS accumulator low pressure alarm.
QUESTION A1.08 (0.75) Rev 1 7/12/89 Which .qne_ of the following air supplies is presently available to operate the ADS valves by energizing the ADS solenoids?
- a. The air receiver of the drywell pneumatic system.
- b. -The nitrogen bottles in the reactor building.
- c. The emergency pressurization station in the aux building.
(Assume that the correct local valve manipulations have been made, and that the bottles are hooked-up.)
- d. The accumulators of the individual valves.
ANSWER:
- d. The accumulators of the individual valves.
K/A: 218000 K4.04 TKO/TPO: D-295019-2.01, 2.11 / D-295019-02 TRO. 89:B.12.C.2.
ESTIMATED TIME: 3 Minutes REFERENCE- P & ID M-66 and M-81 LOP-PC-03 Attachments A & B System Description Chapter 68
J, 4
L'" SIMULATOR SET-UP '
- 1. 'A' RHR running in any mode of operation.
- 2. .The division I (one) ADS inhibit switch in the INHIBIT position.
p
- QUESTION . A1.11 - (0.75) Rev 1 7/14/89 Which QNE of the following ' correctly describes the'. response of the ADS system if all four initiation pushbuttons for ADS were armed and depressed simultaneously?
The seven ADS valves ...
- a. Will open from the Division I (one) and Division 11 (two) ADS' solenoids immediately.
- b. Will open from the Division I (one) and Division 11 (two) ADS solenoids after'a time delay.
- c. Will NOT open until a' low pressure ECCS pump is running.
- d. - Will NOT open.
ANSWER:
- a. Will open from the Division I (one) and Division ll (two) ADS solenoids immediately.
K/A: 218000 K1.01, K4.02, K4.03, K5.01
- TKO/TPO 3-295031 TRO- 89:B.12.E.1., 89:8.12.E.2.
ESTIMATED TIME: 4 Minutes
REFERENCE:
1 E-1-4201 (AH)
System Description Chapter 37, TKO 6.a. ,10.a.
a s
^
SIMULATOR SET-UP:
- 1. From rated vessel pressure, INCREASE "A" RR seal # 2 pressure: OVAO-RR-1-0-0.86000.
- 2. INCREASE DWEDS temperature: OVAO-PC-1-A-0.90
- 3. Generate seal stage flow alarm: OVAN-07-2-C-SET.
QUESTION A1.14 (0.75) Rev 1 7/12/89 The NSO noticed an increase in the DWEDS temperature. Which gng of '
the following correctly describes the cause of the increased temperature?
With respect to "A" Reactor Recirculation Pump...
- a. ...the number one seal has failed.
- b. ...the number two seal has failed.
- c. ...the breakdown flow restriction between the seals has plugged.
- d. ...the seal staging valve has closed.
ANSWER:
- a. ...the number one seal has failed.
K/A: 202001 K4.04, A1.09, A2.10 TKO/TPO: D-202001-1.01, 1.03 / D-202001-01 TRO. 89:A.5.
ESTIMATED TIME: 3 Minutes i i
REFERENCE:
System Description Chapter 5, TKO 3.
LOA-RR 02 Step 5 I
_ _ - _ _ _ _ _ _ . _-__-___-____-_____D
f.
.w SIMULATOR SET-UP:
- 1. Both TDRFPs are in three. element control
- 2. The Actuator Selector Switch is selected to "A" TDRFP
- 3. The FRV M/A station is in MANUAL at 50% demand.
- 4. The Startup Controller is at 0% demand.
- 5. Put an orange ring on'the Actuator Selector Switch.
QUESTION A1.41 (0.5) Rev 1 7/12/89
^
Which ang of the following would correctly describe the response of the MDRFP and the FRV if both TDRFPs were to trip?
- b. The MDRFP would NOT auto start.
ANSWER:
K/A: 259001 K1.08, K3.02,K4.01 259002 K1.05 TKO/TFO: D-259002-3.03 / D-259002-03 TRO- 89:8.8.A.
ESTIMATED TIME: 2 Minutes
REFERENCE:
1 E-1-4208 LOP-RL-01 Steps E.7. and 8 System Description Chapter 29, TKO 9 System Description Chapter 31, TKOs 6 & 9.
)
. , 1
-4' SIMULATOR SET-UP: l
- 1. Open the SBLC test tank outlet valve: CANA-SL-1-D-1.00
- 2. Allow-1 minute for the valve to open fully.
QUESTION A1.46 (0.75) Rev 0 5/19/89 Which gna of the following correctly describes the response of the SBLC system if the "A" SBLC System initiation Switch were turned to INITIATE?
i
- a. Both suction valves would open, both squib valves would fire, and "A" SBLC pump would start when either suction was fully open.
- b. The 'A" suction valve would open, both squib valves would fire, and "A" SBLC pump would start when the suction valve was fully open
- c. Both suction valves would open, the "A" squib valve would fire, and "A" SBLC pump would start when either suction was fully open.
- d. Neither suction valve would open, both squib valves would fire, and "A" SBLC pump would start.
ANSWER:
- d. Neither suction valve would open, both squib valves would fire, and "A" SBLC pump would start.
K/A: 211000 K4.08 TKO/TPO: D-211000-1.04 / D-211000-01 TRO' . 89:A.5.
I ESTIMATED TIME: 2 Minutes
REFERENCE:
1E-1-4209 AA, AB, AC System Description Chapter 10 TKO 9.b l
0- i g
- 4 SIMULATOR SET-UP:
- 1. ' Start SBGT
- 2. Fail the outlet flow. recorder to 2000 scfm:
(OVAO-VG-1-F-0.4000)-
QUESTION A1.48 (1.0) Rev 1 7/12/89 At panel 1PM07J,' check that the SBGT system is functioning properly. Identify any discrepancies or abnormalities. . NONE may be '
.an acceptable answer.
ANSWER:
The outlet flow recorder indicates low flow. ,
K/A: 261000 A1.01 TKO/TPO: C-261000-3.02, 3.08 / C-261000-03 TRO: 89:A.5.
ESTIMATED TIME: 2 Minutes REFERENCE- LOP-VG-03 Step F.1.f
! SIMULATOR SET-UP:
1 L 1. Select IC 16
- 2. Fail the SJAE PCV: DMAL-CR-1-J-0:00 l
QUESTION A1.51 (0.5) Rev 1 7/12/89 L Which gns. of the following correctly describes the reason for the closure of the off-gas suction valves,1N62-F300 A and B?
- a. Low air pressure at the valve i.
- b. Low steam flow
- c. Control switches NOT in OPEN
- d. Control power failure ANSWER:
- b. Low steam flow K/A: 271000 K4.01 K4.08 TKO/TPO: C-271000-02 TRO' . 89:A.1.
ESTIMATED TIME: 2 Minutes
REFERENCE:
LOA-OG-05 Step C.1.
i.
n.
,c..
l SIMULATOR SET-UP:
- 1. Place A" or "B" RHR in suppression pool cooling mode per LOP-RH-13 ;
- 2. LEAVE heat exchanger bypass valve F048A/B OPEN
- 3. . Place "A" or "B" RHRSW rad monitor in service: CDIG-RM-2-O(P).
QUESTION A1.56- (1.0) Rev 1 7/12/89 RHR ' suppression pool coolingLis operating-in accordance with "
- LOP-RH-13. Check the system for proper operation. State any failures or abnormalities. NONE may be an acceptable answer.
~
ANSWER:
The heat exchanger bypass is not closed. f lh
- MJ W f K/A: 219000 K3.01 A2.04 A4.02 e " "'
TKO/TPO: C-219000-02 / C-219000-2.02 TRO: 89:B.11.C.6.
ESTIMATED TIME: 2 Minutes REFERENCE LOP-RH-13 Step F.d.1)
. 1
. f i
I I
SIMULATOR SET-UP:
OVDO-VG-3 B-Set, Trip 1 (*C" VC radiation monitor high high rad)
OVDO-VG-3-C-Set, Amber Trip 2 ("C" VC radiation monitor high rad) j OVDO-VG-3-E-Set, Trip 1 ("D" VC radiation monitor high high rad)
OVDO-VG-3-F-Set, Amber Trip 2 ("C" VC radiation monitor high rad)
OVAN-18-2-1 Set, Control room HVAC CAM trouble OVAN-18-2-K-Set, Control room HVAC CAM trouble OVAN-24-1-G-Set, Control room HVAC Sys ,
OUESTION A1.58 (1.0) Rev 1 7/12/89 Check that the control room ventilation system has properly responded to plant conditions. Identify any failures or abnormalities. NONE may be an acceptable answer.
ANSWER:
The emergency make-up train has not started.
K/A: 29003 K1.01 K4.01 A1.05 A3.01 A4.01 TKO/TPO: C-29003-01 / C-290003-1.04, 1.13 TRO. 89:A.1.
ESTIMATED TIME: 2 Minutes
REFERENCE:
LOA-VC-01 Step B.1.a.
SIMULATOR SET-UP:
1 Start "A" RHR in full flow test.
- 2. Place the "A" RHRSW rad monitor in service:CDIG-RM-2-O-on.
QUESTION A1.79 (0.5) Rev 1 7/12/89 Why is the common diesel generator cooling water pump running?
ANSWER:
The "A" RHR area cooler is operating.
(The answer should be modified based on the equipment running. Any of the following will also auto start the common diesel generator cooling water pump. Therefore, if any of the following conditions also exist full credit should be given if any one of the following is listed instead of "A" RHR area cooler running.
.- m
,___m,
. . . .- . m . m .. ..___.
.m.
- % 3.r e ,d .-g.+L.> c> e . u p ,
o kC C on MD l
I- o "A" RHR pump running i
K/A: 203000 K1.10 A1.09 G.7 TKO/TPO: C209002-1.02 C-209002-02 TRO: 89:A.5.
1 ESTIMATED TIME: 2 Minutes 1
l REFERENCE- 1E-0-4412 AC 1E-1-4089 AA LOS-RH-01 Step F.8.f System Description Chapter 40 TKO 9.c.
l SIMULATOR SET-UP:
- 2. Adjust governor to 3000 hw l
QUESTION A1.81 (1.0) Rev 1 7/12/89 The HPCS diesel generator is running for surveillance. Check the HPCS diesel generator for proper operation. Identify any failures or abnormalities. NONE may be an acceptable answer.
ANSWER:
The output is too high ( > 2860 kw)
K/A: 264000 - A2.03, G.10 TKO/TPO: C264000-2.20 / C-264000-02 TFIO. 89:B.14.B.
ESTIMATED TIME: 2 Minutes
REFERENCE:
LOS-DG-M3 Step F.7.c.6) l l
a,
~
- o'.
LASALLE COUNTY STATION A2 TYPE STATIC SIMULATOR EXAM REQUAL 89-28 MODULE 5 !
TOTAL POINTS RO 11.25 SRO 11.75 ANSWER KEY NOTE: All questions pertained to R0s and SR0s except for Question A2-4.36 which pertained to SR0s ONLY.
(sCTED t sJ i i_ tx U^ O t APPROVAL.
/
~'r k--ir - = - r ~7 / 31/89 LSCS TRAINING GROUP LEADER / DATE
i
" STATIC EXAM NUMBER 4 REV 1 .7/25/89 INSTRUCTIONS TO INSTRUCTOR OVERVIEW: A 20% feedwater line rupture occurs with RHR and RCIC
'in abnormal line-ups. Other failures include; loss of Bus 141X, stuck rod, SDV vents and drains fail open, failure of RR runback, and 1E12-F049A fails to close.
PRESENTLY STORED IN IC j O ON THE
- P1r" DISK SIMULATOR SET-UP:
o Read through instructions once before doing them.
o Select IC 16 with timor FALSE.
o Align normal systems as described in NORMAL SYSTEM LINEUP.
o insert malfunctions and overrides as described in that section.
o if it is necessary to delete dos to enter all the OVDOs, delete the H2 Recombiner items.
o Snapshot into IC 51 NOTE: IF THE SCENARIO IS IN A PRE-STORED IC, BEGIN AT THIS POINT AND RECALL THE SPECIFIC IC INSTEAD OF IC 51.
o Recall IC 51(or stored 10), with the timer FALSE, and go to Rt.N.
o Advance all charts until there are no traces of previous trends visible, o . Verify all conditions specified in NORMAL SYSTEM LINEUP section exist.
o VERIFY that gli control switch targets match pump and breaker condition.
o Recall IC 51 (or stored IC). Toggle the timer TRUE. DO NOT go to RUN yetil o Advance all control room typers to clear all information in the buffers and to provide a clear start point for information from this exam.
.. STATIC EXAM NUMBER 4 REV 1 7/25/89 o Deactivate the printer freeze permissive: CDIG-Ml-3-1-ON.
o Go to RUN.
o When a scram signal is received,
... arm and depress two RPS manual scram pushbuttons,
... place mode switch to shutdown,
... select IRM on the recorders, and
... range IRMs to range 6. 2 o Acknowledge alarms and FREEZE machine at 1:05 on CT clock.
o Verify the answer to each question is correct for the existing plant conditions. It is very important that this is done BEFORE the students enter the simulator. If the answer to any question is not correct for existing plant conditions change the answer key or make a note of it for later consideration.
o After all answers are verified, SNAPSHOT existing plant conditions into a BLANK (UNUSED) 10. This IC will be used to verify plant conditions if any questions arise during exam grading. Please note which IC was used in the space below.
ACTUAL EXAM CONDITIONS STORED IN IC STUDENTTURNOVER o The plant was at 100% power when the transient began.
o LOS-RI-03 had been completed through Step F.4.s when the transient began. "A" RHR had just been placed in suppression pool cooling.
o ALL control switch targets were placed in the correct position for system status PRIOR to the beginning of the transient.
o Steps F.1, 2, and 4 of LGP 3-2 were performed before the simulator was stopped 1 minute and 5 seconds after the beginning of the transient.
i
.- STATIC EXAM NUMBER 4 REV 1 7/25/89 ,
NORMAL SYSTEMS LINE-UP:
o Place RHR loop A into suppression pool cooling mode iaw LOP-RH-13 and associated procedures, EXCEPT THAT the RHR flow shall be as high as possible and the RHR service water PRM shall NOT be started.
o Place RCIC into test mode iaw LOS-RI-03, STOPPING at step F.4.e. (DO NOT increase flow controller demand past 20% )
o Verify that the following are running: '
- a. 1 A service water pump
- b. Unit one station air compressor '
- c. 1 A heater drain pump
- d. 1C heater drain pump
- e. 1 A circulating water pump
- f. Waste water treatment facility feed breaker o Place the Div Ill DG voltmeter control switch in the "D Gen" position. ALSO, verify the Engine Control Selector switch is in the " Remote Manual" position.
o Place the Div i and Div 11 DG voltmeters in a position other than OFF.
OVERRIDES AND MALFUNCTIONS:
o DMAL-ED-1-1-0:00, Loss of Bus 141X o DM AL-FW-1-P-20%-0-0:00, Feedwater rupture outside DW o DMAL-RD-9-O-0:00, CRD 58-39 Stuck rod o DMAL-RD-10 A-0:00 , SDV drain & vent viv fail open o DMAL-RR-3-C-0:00, Runback Failure < 2 RFP & Lo Lvl o OVAO-RR-1-K-0.075-0:00, RR pmp A mtr speed o OVAO-RR-2-B-0.075-0:00, RR pmp B mir speed o OVDO-CD 1-C-Reset-0:00, Disc pos actuator pos OPN o OVDO-CD-1-G-Reset-0:00, Disc pos actuator pos OPN o OVDO-RH 6-H-Set-0:00, RHR to radwst viv 1E12-F049A OPN o CANA-CF-2 C 0.50, FRV isol stop
__.______.___._.___________.____m______
.s
- e OUESTION: A2-4.01 (0.5) Rev 1 7/25/89 What was the INITIAL reactor scram signal? Setpoint. not required.
ANSWER:
Low vessel level
- K/A: 295006 AA2.06 TKO/TPO: D-295006-01 TFD. 89:B.18.C
. ESTIMATED TIME: 2 Minutes
REFERENCE:
LAP 200-7 Attachment A LGP 3-2 i
l l
l l
l l
\
u i
]
. l QUESTION: A2-4.02 (1.5) Rev 1 .7/25/89 t
List THREE (3) PCIS groups which PRESENTLY have isolation signals {
present? )
ANSWER:
0.5 pt each for listing any three of the following; PCIS groups I, !!,111, IV, V. VI, Vil 1
NQIE:
If more answers are given than those required, the total point value of the question shall be divided by the number of answers given, ro!nts w!!! thea, be taken c!f for each wrong answer baseG on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt. (1.0 divided by 3). One answer is wrong so 0.66 pt. is given to this question.
- K/A: 223002 K1.01 K1.08 205000 K4.03 239001 K1.17 K4.01 215001 K1.05 K6.04 TKO/TPO: C-223002-1.10 C-223002-01 TFO. 89:A.5 ESTIMATED TIME: 5 Minutes REFERENCE- LOP-PC-03 Attachment C System Description Chapter 49 i
l C-m_.-______ _ _ _ _ _ .
L 0
OUESTION: A2-4.03 (0.5) Rev 1 7/25/89 Which of the LGAs presently have entry conditior.s met? More than one answer may be correct. NONE may be an acceptable answer.
l ANSWER; -
LGA-01 (Do NOT discredit for also listing LGA-02)
, NOTE:
if more answers are given than those required, the total point value of the question shall ,;
be divided by the number of answers given. Points will than be taken off for each wrong answer based on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers !
are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt.'(1.0 divided by 3). One answer is wrong so 0.66 pt. is given to this question.
K/A: 295031 G5,G7,G11 TKO/TPO: E-295031-1.04 TR2 89:C.3.A.6.a ESTIMATED TIME: 4 Minutes
REFERENCE:
LGA-01
d
. i QUESTION: A2-4.04 (1.0) Rev 1 .7/25/89 Identify four (4) 4160 volt loads which were running prior to the transient but tripped due to undervoltage.
l ANSWER:
O.25 pt each for any FOUR of theI w following W 1 FA
/ 'd ~
- a. 1' A service water pump ,
- b. Unit one station air compressor IGA a W '-1~ -
- c. 1 A heater drain pump lu o or m /r4i G
- d. 10 heater drain pump i H b 0 ' k N )
- e. 1 A circulating water pump iC w o 1 P A O 4 ' '.
- f. Waste water treatment facility feed breaker IO.E:
If more answers are given than those required, the total point value of the question shall be divided by the number of answers given. Points will then be taken off for each wrong answer based on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt. (1.0 divided by 3). One answer is wrong so 0.66
~
pt. is given to this question.
i K/A: 262001 K3.01 A2.04 295003 AK2.04 TKO/TPO: D-295003-04 TRV. 89:B.1.D., 89:B.1.C.
ESTIMATED TIME: 5 Minutes
REFERENCE:
LOA-AP-07 1E-1-4000 AJ System Description' Chapter 42
r; . , . .
" OUESTION: A2-4.05 - (1.0) Rev 1 7/25/89 Check the CRD system and_ associated components (excluding CRD drives) for proper operation following a reactor scram. Describe any failures or abnormalities. NONE may be an acceptable answer.
ANSWER:
The scram discharge volume vent and drain valves are open.
(DO NOT discredit for also listing high CRD pump amps) .
K/A: 201001 K1.07 K4.06 A1.05 295006 AA1.06 212000 K1.06 TKO/TPO: D-295006 TRO: 89:A.5 ESTIMATED TIME: 3 Minutes
REFERENCE:
LGP 3-2 1E-1-4215 AK System Description Chapter 8 TKO 6.d.9) & 7.b.3) e
T*
w- -
OUESTION: A2-4.06 (0.75) Rev 1- 7/25/89 Check that the "A" RHR service water and associated systems are L
properly aligned and operating in accordance with operating I- procedures. Describe any abnormalities. NONE may be an acceptable answer..
1 ANSWER:
The RHR service water PRM has improper flow. ,
.K/A: 219000 K1.11
.272000 K3.01, A1.01, G.8 TKO/TPO: ' C-219000-4.02 / C-219000-04 TTK). 89:B.24.A.3 ESTIMATED TIME: 3 Minutes
REFERENCE:
LOA-1H13-P601 B502 ( "R" points R1328 & R1333)
LOP-RH-05 rev 6
r
- QUESTION: A2-4.07 (0.75) Rev 1 7/25/89 Check that'the "A" RHR system is properly aligned and operating in accordance with operating procedures. Describe any abnormalities.
NONE may be an acceptable answer.
ANSWER:
RHR flow is excessive.
DO NOT discredit for also listing high pump amps and abnormal pump discharge pressure. ALSO, do not discredit for listing the FO49A valve being open.
NOTE:
If more answers are given than those required, the total point value of the question shall be divided by the number of answers given. Points will then be taken off for each wrong answer based on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt. (1.0 divided f' , One answer is wrong so 0.66 pt. is given to this question.
K/A: 219000 A1.02, A4.07 TKO/TPO: C-219000-2.02 / C-219000-02 TRO- 89:A.1 i
ESTIMATED TIME: 3 Minutes l
REFERENCE:
LOP-RH-13 l
l
)
I
)
-1 QUESTION: A2-4.08 (1.0) Rev 1 7/25/89 RCIC has received an auto initiation signal. At a minimum, which action (s) 'must the operator take to assure that the RCIC system properly aligns and injects 4 :: ..e e :s ;,,;tle:e? NONE may be an acceptable answer.
ANSWER:
1 Place the system (flow control) Into AUTO.
LOJE:
if more answers are given than those required, the totai point value of the question shall -
be divided by the number of answers given. Points will then be taken off for each wrong answer based on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt. (1.0 divided by 3). One answer is wrong so 0.66 pt. is given to this question.
K/A: 217000 A2.01 TKO/TPO: C-217000-3.01 / C-217000-03 M O. 89:B.13.H ESTIMATED TIME: 3 Minutes
REFERENCE:
LOS-RI-Q3 rev 14 O
i 6
1 QUESTION: A2-4.09 (0.5) Rev 1 7/25/89 l
l Which gna. of the following correctiv describes the type and location of the-leak?
- a. Steam leak inside the primary containment.
- b. Steam leak inside the ~ secondary containment.
l L c. Feedwater leak inside the primary containment.
- d. Feedwater leak inside the secondary containment.
- e. Steam or feedwater leak outside BOTH secondary and primary containment.
ANSWER:
- d. Feedwater leak inside the secondary containment.
K/A: 295032 EK3.03 EA2.03 TKO/TPO: D-295032-1.13 / D-295032-01 TRO: 89. A.5 ESTIMATED TIME: 4 Minutes REFEFIENCE: LGA-02 rev 6 i
_____________-_________m _______._______m____m
p .x
!?
OUESTION: A2-4.14 -(1.0) Rev 1 .7/25/89
~
'Which of the following INJECTION SYSTEMS are presently. injecting into the reactor vessel? More than one response may be correct. All correct . responses are required for full credit.
- a. Condensate / feedwater
- b. 00
- c. RClC
- d. High pressure. core spray- '
- e. Low pressure core spray
- g. B low pressure coolant injection ANSWER:
(0.5 pt each- for listing the following)
- b. 00'
- d. High pressure core spray hKZIE:
if more answers are given than those required, the total point value of the question shall be divided by the number of answers given. Points will then be taken off for each wrong answer based on this amount. EXAMPLE: A question is worth 1.0 point and 2 answers -
are required. The student provides 3 answers,1 of which is wrong. Each answer will be worth 0.33 pt. (1.0 divided by 3). One answer is wrong so 0.66 pt. is given to this question.
K/A: 295031 EA1.11, EA1.12
- TKO/TPO: E-295031-3.01 / E-295031-03 TRO: 89:A.5 ESTIMATED TIME: 5 Minutes REFERENCE LGA-01
p n
+. ,
OUESTIONL A2-4.17 (0.5) Rev 1 7/25/89 I
Which gna of the following CORRECTLY describes the present status of the RWLC system? 3
- a. TDRFPs are-in three element control, attempting to control at 36"
- b. TDRFPs are in three element control, attempting to control at 18"
- c. ' FRV is in single element control, attempting to control at 36" *
- d. FRV is in single element control, attempting to control at 18" ANSWER:
- d. FRV is in single element control, attempting to control at 18" K/A: 259002 K4.12, K3.01, A3.06, G8 TKO/TPO: C-2590021.01 / C-259002-01 TRCX 89:B.8.A ESTIMATED TIME: 3 Minutes REFERENCE- LOP-RL-01 Steps E.7 and 8 1 E-1 -4208 System Description Chapter 31 i
QUESTION: A2-4.19 (0.5) Rev 1. 7/25/89 Given present plant conditions, the NSO performs the following actions to reset the reactor scram.
- Places the "Disch Vol Hi Wtr Level" switch in BYPASS
- Moves the " Reactor Scram Reset" switch first to the GP I/4 position and then to the GP 2/3 position.
The reactor scram DOES NOT reset. Why? I ANSWER:
A reactor scram signal (Iow water level) is still active K/A: 212000 K1.02 K1.14 295006 AA1.01 AA2.06 TKO/TPO: D-295006-01 THO: 89:B.18.C., 89:8.18.E ESTIMATED TIME: 2 Minutes
REFERENCE:
LGP 3-2 Step 15 1 E-1 -4215 AA-AL 1E-1-4216 AA & AB System Description Ch 20 i
/
F '.
l 2 1
OUESTION: A2-4.24 (0.75) Rev 1 7/25/89 Concerning the CRD pumps, flow control valves, and flow controller, f
which ONE of the following CORRECTLY describes the present operation 'of the system?
l
- a. The CRD flow controller output has failed to its maximum value.
- b. The CRD flow control valve has failed full open and the flow controller is operating as expected. '
- c. The CRD pump flow is 30 to 40 gpm and the flow control valve has failed closed.
- d. The CRD pumps, flow control valves, and flow controller are i operating as expected.
ANSWER:
- d. The CRD pumps, flow control valves, and flow controller are operating as expected.
K/A: 201001 K5.02, A1.03, A2.04, G15 TKO/TPO: D-201001-1.03 / D-201001-01 W. 89:A.5 ESTIMATED TIME: 2 Minutes REFERENCE. LOA-RD-04 Rev 2 System Description Chapter 8 3
l QUESTION: A2-4.25 (1.0) Rev 1 7/25/89 Based ONLY on CURRENT plant conditions, an automatic depressurization system blowdown (ADS)...
1
- a. ...will occur 'immediately if a low pressure ECCS pump is started.
- b. ...will occur in less than 645 seconds.
l- c. ...will occur in less than 105 seconds. l 1
- d. ...will NOT occur.
l ANSWER:
- d. ...will NOT occur.
K/A: 218000 K4.03 K5.01 A1.05 A2.06 A4.02 A4.10 A4.12 TKO/TPO: D-218000-1.04 TRO: 89:B.12.C.1 ESTIMATED TIME: 3 Minutes
REFERENCE:
1 E-1 -4201 AH System Description Chapter 37 TKO 6.a.
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SRO ONLY OUESTION: A2-4.36 (0.5) -Rev1 7/25/89 Why doesn't the TSC have to be manned based on present plant q conditions? (include any applicable references you feel will support :
.your answer.) ,
ANSWER:
The TSC does not have to be manned for an Unusual Event. (EAL 2.C -
most probable classification for this event) LZP 1110-1 If the student feels an ALERT would be declared because the SDV vents and drains are open OR because there is possibly greater than 50.GPM leakage, the following answer may also' be accepted.
LZP-1110-1 states that the TSC manning is required for an Alert.
K/A: 294001 A1.16 TKO/TPO: H-294001 -30.01 H-294001 -30.02 B O: 89:C.5.6 ESTIMATED TIME: 10 Minutes
REFERENCE:
LZP 1110-1 LZP 1200-1 W
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February 28, 1989 i 4
23 J l
LASATff COUNTY NUCLEAR STATION ]
LICENSED OPERATOR REOUALIFICATION EXAMINATION SECTION B .
Written by:
h' dND#
License Type '%
Approved * \ '
Date Administered: /
hf
/
Name:
INSTRUCTIONS TO EXAMINEE:
Write answers on one side only The passing grade requires 80% averaged between Sections A and B. Failure to achieve this grade will require additional evaluation and enrollment in an accelerated requalification p rograin. Examination papers will be picked up two 12) hours.after the examination starts.
Total Points !N Points missed Points received FINAL GRADE . %
All work done on this examination is my own. I have neither given nor received assistance. I agree that I will not knowingly divulge details of the requalification exam to any unauthorized persons. I understand.that cheating on this examinat.lon will result in automatic denial of my ' license renewal by the NRC.and could result in more severe penalties.
Applicant's Signature
/
Signature of Grader Date ATTACHMENT E-1 page 2 of 4 i 4ASin COPi DOCUMENT ID 0617L/0286A E - - - - _ _ - - -- _ - - - - - - - - _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _
- . o FACILITY RULES AND GUIDELINZS FOR LICENSE REQUALIFICATION During the administration of,this examination the following rules apply:
g
- 1. Cheating on the examination means an automatic suspension from license duties and could result in more severe penalties such as revocation of your license.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Till in the date on the cover sheet of the examination (if necessary) and perform a page count to ensure your exam contains the right number of questions. .
- 6. Answer each question on the examination. If additional paper is required, use only the lined paper provided by' the examiner.
- 7. Initial each page of the exam.
- 8. The point value for each question is indicated in parentheses before the question and is based upon the questions importance to safety as well as a guide for the depth of answer required.
- 9. Unless solicited, the location of references need not be stated.
- 10. This section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete this section.
- 11. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is ,
worth one point and asks for four responses, each of which is worth 0.25 l points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even through you got the four correct answers.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 14. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION
', AND DO NOT LEAVE ANY ANSWER BLANK.
h 15. If parts of the examination are not clear as to intent, ask questions of l'
the examiner only.
DOCUMENT ID 1629L
. r
- .' :., s
, [ 4. - ,
6:
- 16. You must sign the statement on the cover sheet that indicates that the work is your c<n and you have not received or been given assistance in completing the examination. You must also certify that'you will not divulge details of the exam to any unauthorized persons. This must be done af ter the examination has been completed. Due to the nature of open ,
reference examinations, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
- 17. When you complete your examination, you shall
- a. Turn in your copy of the examination and all pages used to answer the examination questions.
- b. . Turn in all scrap and unused paper (if any).
- c. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your exam may be invalidated requiring reexamination.
6 O
4 DOCUMENT ID 1629L e _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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ofREPORT'R2.4 R0 Requot Section B 'PAGE: 1 EXAMINATION KEY DATE: 07/31/89
- 01 L RQMX 89 EXAM' NUMBER: 01 L RQMX 89-0004-89 EXAM COUNT : 1.
LOCAT10N:
POINT VALUE : 1Sr50 // 2.5 N
' TOTAL QUESTIONS : 23 TOTA,L DIFF LEVEL: 138.00
====sr===============================================================
PT. VALUE EB NUM: 01 024185 EL4531 C#ERATOR EXPERIENCE '
tl: LICENSE MASTER QUESTION ADD KA217 KA: RCIC ,
t ,ECCS/RCIC RHR/LP/ ADS /HP/RCIC SPECIAL OPEX; TMl; CHERNOBYL; AND MODULE SPECIFIC 1568/89
~ (1.00)1 .1. A loss of and subsequent return of power to the RCIC teak oetection logic g result in: (Select the most correct action.) (Note: The answer to this question moy not be found in the reference meterints provided.).
- a. spurious initiation of RCIC.
- b. RCIC turbine trip.
- c. loss of the auto furetion of the minima flow valve.
- d. Isolation of the inboard steam supp6y vetve (F063). ..
- d. Isolation of the inboard steam s p ly valve (F063).
I ANSWER:
TP0/TK03 D 217001-01
- KA: 217000A2.05 RO: 3.3 SRO: 3.3 REFER ACES: Elect. dis., L RRR7-88 TRO-89-D.12.D.1.
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' .' REPORT R2.4- R0 Re p t Section B PAGE: 2 EXAMINATION KEY DATE: 07/3t/89
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'PT. VALUE EB-NUM: 01 021106 EL4331 LGP'S L1 LICENSE MASTER QUESTION ADD N00 3 89 Question for use on Module 3.1989 KA214 KA: RPl$
REACTIVITY RR/RD MECH /RD HYD/SC/ FUEL / REFUEL LGP LASALLE GENERAL OPERATING PROCEDURES (0.75). 2. After each control rod is fully inserted what nust be verified operable?
ANSWER: Full core display " FULL IN" indication.
L KA: 214000 G.5 2.9/3.8-
. Mod 3 89 Ref LGP-2-1 TRO-89'C.4.A EB-NUM: 01-022698 EL4114 LGA USAGE GRAPHS, STEPS,DEF,ETC EL7114 LGA USAGE GRAPHS, STEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD E295037R307 _
MOD 6-88 THIS QUESTION COULD HAVE BEEN USED DURING MOD 6-88 7 /
LGA LASALLE GENERAL ABNORMAL PROCEDURES ( , *C KA295028 NIGH DRYWELL TEMPERATURE
- EMERGENCY, EVOLUTION r' (0.75) 3. You are performing step C.3.f. of LGA 03. Att controls ,are futty inserted. Wide range levet instrumentation is unavailable. Reactor pressure is 50 pois. Drywell temperature is 330*F. Based solely on the above information, what procedure shcatd you go to?
, ANSWER: Go to LGA-05 (Flood) (Also accept appropriate steps of LGA-05)
TK0/TPO E295037R307 K/A 295028 Generic 12 3.8/4.3 LGA ATWS 03 TRO 89:3.A.3 i
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1 REPORT R2.4 R0 Requel Section B PAGE: 3 EXAMINATION KEY DATE: C7/31/89 PT. VALUE Es-NUM: 01 022700 EL4114 LGA USAGE GRAPHS, STEPS,DEF,ETC EL7114 LGA USAGE GRAPHS, STEPS,DEF,ETC Li LICENSE. MASTER QUESTION ADD E295037R107 MOD 6 88 THIS QUESTION COULD HAVE BEEN USED DURING MOD 6 88 KA295026 $UPPRES$10N POOL HIGN WATER TEMPERATURE EMER EVO'
'LGA LASALLE GENERAL ASNORMAL PROCEDURES (0.75) 4. Reactor power is 6.5%. At what suppression pool water temperature wilt the boron injection temperature limit be reached?
ANSWER: it0*F TK0/TP0 E295037R107 K/A 295026 Generic 12 3.8/4.5 (CA*ATWS-01 TRO-89:3.A.3 EB-NUM: 01 022746 EL4112 LGA SUPPORT PROCEDURES L1 LICENSE MASTER QUESTION ADD. ,
E295031R203 MOD 1 89A LGA SUPP, LAP 1600-2 MDRFP SEAL CLG MOD KA295031 REACTOR LOW WATER LEVEL LGA LASALLE GENERAL ASWORMAL PROCEDURES LOA .LASALLE OPERATING ABNORMAL PROCEDURES ECCS/RCIC RHR/LP/ ADS /HP/RCIC (0.75) 5. Through which system does the fuel Poot Emergency Makeup Puup inject into the reactorf
- e. RNR *B"
- b. RNR "C"
- c. RCIC -
- d. Fee & ster
- e. Fire hose connected to instrument top ANSWER: e. RHR *B" TKO E295031R203 K/A 29507,1EA1.08 SR0 3.8/R0 3.9 REF: LOA-FC-03 TRO 89:C.3.A.10.C.2; A.1
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,' REPORT R2.4 RC Regast section B PAGE: 4-EXAMINATION KEY DATE: 07/31/89 I'.
sees emmassessmenemensammess===emessemassmeessemammes...... ss.......... ......
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PT. VALUE EB NUM: 01-022743 EL7114 LGA USAGE
- GRAPHS, STEPS DEF,ETC EL4114 LGA USAGE-GRAPHS,$TEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD MM 6-88 TH18 OUESTION COULD HAVE BEEN USED DURING MOD 6-88 LGA- LASALLE GENERAL ABNORMAL PROCEDURES KA295031 REACTOR LOW WATER LEVEL
.(1.00) 6. An ATWE has occurred. RPV tevel comot be maintained above -161".
You have terminated and prevented M injection into the RPV except from boron injection systems & E CRD. Your effort to ADS has failed but you are able to get 4 $RV's open. RPV pressure prior to opening
-.these 4 SRV's was'et 925#. Detow gb31 nressure (in pels) should
. you commence and slowly refoe injection into the RPV7
' ANSWER: .210 psig TK0/TPO E295037R4.11 K/A 295031 Generic 12 RD 3.9/sR0 4.5 295037 C 12 3.9 4.6 TR0 89:C.3.A.3 REF: LGA-ATWs-04
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e RIPORT R2.4 R0 Regaal Section 8 ~. PAGE: 5 EXAMINATION KEY DATE: 07/31/89
. ..... .......r..................a.....
PT. VALUE.
i
'EB IIUN: 01 022889
.EL7114 LGA USAGE-GRAPHS,$TEPS DEF,ETC EL4114 LGA USAGE GRAPHS,5fEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD LGA LASALLE GENERAL ABNORMAL PROCEDukES KA295037 SCRAM COND PRESENT AND RK AT POWER OR UNKNOWN ATWS. ,
(1.00) 7. An ATWS has occurred.
The following plant conditions exists
- RPV power is SE and increasing
- RPV water level is 30" and rising slowly
- S8 and 'U' SRV's are OPEN
- Fwpression Pool water temperature is 120*F.
Which of the follow" $ statements would best describe actions reestred by statior procedures:
- s. Attempt to maintain level above 161" and between +12.5" and ,
+55.5" with condensate /feedwater, CRD and RCIC.
b.' Lower RPV tevet by terminating and preventing injection into the RPV except from boron injection systems and CRD until RPV water tevet . reaches -161" or RX power is below 5% or att SRV's remain closed and drywell pressure remains below 1.69 psig. .
- c. Terminste and prevent all injection into the RPV except from boron injection systems and CRD. Open all ADS velves. Verif y 7 SRV's M.
- d. None o'f the above.
ANSWER: 8.
s REF: LGA ATWS-04
, TKO E295037R411 K/A '295037 Generic 12 Ro 3.9 SRO 4.6 TRO:89-C.3.A.14 y
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-4 y RE' PORT R2.4 R0 Requel Section B 'PAGE: 6 EXAMINATION KEY DATE: 07/31/89 guessssssssssssssssssssssssssssssssssssssssssssssssssssssssesemassessessassamasse PT. VALUE EB-WUM: 01 022696 EL4114 'LGA USAGE-GRAPHS,$TEPS,DEF,ETC EL7114' LGA UEAGE GRAPNS, STEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD E295037R307 M00 6-88 THIS QUESTION COULD HAVE BEEN USED Duk!NG MOD 6-88
-LGA- LASALLE GENERAL ABNORMAL PROCEDURES KA295024 HIGH DRYWELL PRESSURE EMERGENCY EVOLUTION
. (0.75) 8. Fitt in the blankt Suppression chenber air tencerature is 210*F and
< steady. Suppression chamber pressure is 46 psig and f atiing. If suppression chenber pressure fatts below psig (t 1 pais),
drywell sprey inittetton will be prohibited.
ANSWER: 30 psig (s 1)
- TK0/TP0 E295037R307 K/A 295024 Generic 12 3.9/4.5 LGA-03 TRO-89:3.A.3 Es-NUM: 01 022886 l EL4114 LGA USAGE-GRAPHS,$TEPS,DEF ETC L1 LICENSE MASTER QUESTION ADD MOD 6-88 THIS QUESTION COULD HAVE BEEN USED DURING MOD 6 88 E295031R108 LGA LASALLE GENERAL ABNORMAL PROCEDURES KA295007 NIGH REACTOR PRESSURE ABNORMAL EVOLUTION KA239 KA: MAIN AND REHEAT STEAM SUPPLY; SRV; MSIV-LCS (0.75) 9. You are controlling reactor pressure during a transient by manually operating Relief Valves. In what sequence would you operate the relief vetves in order to distribute the heat eventy aromd the s w ession pool? +
ANSWER: Alphabetically or per the map of the suppression pool.
l LGA-01 Step C.8.a TKO E295031A108--
.K/A 295007 AA1.03 3.5/3.7 I
239002 K4.04 3.4/3.6 TRO-89:C.3.A.3 6
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h'IEPORTR2.4- R0 Recpol Section B PAGE: 7
' EXAMINATION KEY DATE: 07/31/89
.+
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PT. WJ.UE ~
i f9-WVMt 01-0?4183 EL3024 RPV INST
'EL2241 AC DisT -
Lt. LICENSE MAETER QUEST 10W ADD ^
l PLANT INST ARM /PRM/LD/RPV INST /CX/RX/CM '
ELECTRICAL .
AC/DC/DG/ MAIN GEN / GENERATOR AUX /f4N EXCITATION KA216- KA: RPV INSTRUMENTATION LM LASALLE OPERATING ABNORMAL PROCEDURES
' (1.50) 10. During a transient AC power is lost and De diesel starts. As Nso, what I Mication would be operable for the following?
- a. Reactor water level (2 reesired)
- b. Rea: tor pressure (1 recpired)
' ANSWER: a. Any two (2) of the folsowing (0.5 each)
- 1. "B" narrow rence level
- 2. "C" narrow range level
- 3. wide range level at the ree.ote shutdown penet
- b. Any one (1) of the folto ing: (0.5 pt.)
- 1. RCIC eteen line pressure
- 2. wide range pressure et the remote shutdown panel 4
. - TP0/TK0: D295003R7.01 9
- KA: 216J00K6.01 1
I Ron 3.1 SRD:
3.3 REFERENCES
- LOA-AP 05 and T. E. 3.3.7.4 TRO-89 8.6.C f
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.PT.VALUEl SS-NUM: 01 024112 EL4217 LGA FA-RD EL7217 LOA PA RD' L1 LICENSE MASTER QUESTION ADD .
MOD-3-89 Ouestion for use on Module 3 1989 LOA LASALLE OPERATING ASNORMAL PROCEDURES -
KA201, . . KA: RD;RMCS;RSCS;RWM (1.00) 11. A roector startup is in progress with reactor power at 15%. A control
- red is withdrawn to paltion 48. While performing the coupling verification the rod is discovered to be uncoupled. The attempt to reco gle the rod is unsuccessful. Determine the operator actions
. required prior to further rod movement.
'ANSW R 1. Insert the rod to the full in position (position 00). (If necessary, bypass the rod in RSCS in accordance with LOP RS-017,
- 2. Declare the rod inoperable and either electrically or hydraulically disers the rod. (Ensure compliance with Tech Specs.)
l 3. (Prior to further rod isovement,) Inform the Nuc Engineer (who will determine if any rod segaence changes are necessary.)
REF: L04 RD 02 Subsequent Operator Action 2.s KA: '201001 System Generic #13 3.6/3.3 TK0; 0201003-2.13 TR0-89A.1; B.3.A.2 l
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i PT VALUEL EB WuM: 01-0241?0 EL6314 .APRM EL3014 APRM L1 LICENSE MASTER GUESTION ADD NUCLEAR INST. SRM/IRM/LPRM/APRM/TIP KA215 KA: TIP$;RBh;IRM;$RM;APRM p LOA . LASALLE OPERATING ABNORMAL P CCEDURES (1.00) 12. Unit one is at 100K power with the following LPRMs inoperable 16 17A 32-33A 40-573 32 17C 16-49A 08-41B 16-33C 08-41A LPRM 32 49C has just fatted and has also been declared (noperable.
Evoluete the above information and determine if any APRMs must be
[
declared inoperable. Justify your answer.
ANSWER: APRM C m ut be declared inoperable (0.5). There are less thren 2 inputs from the C tevel to APRM C (or similar words). (0.5)
Reft LDA-NR 02 KA: 215005 Generic K/A5 3.3/4.2 215005 K1.04 3.6/3.6 TK0 D215005R01 D215005R113 TRO-89:A.1; A.3; B.15.A.4 n
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- REbfR2.4 R0 Roomt Section 3 PAGE: 10
-1 EXAMINATION KEY- CATE: 07/31/89
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PT. VALUE.
EB-NUM: 01 024221 EL2234 RD HYD L1 LICENSE MASTER QUESTION ADD LDA --LASALLE DPERATING ABNORMAL PROCEDURES i
.KA201 KA: RD;tNCS;RSCS;RWM -l REACTIV!!T. M/RD MECH /RD MYD/S:'31EL/ REFUEL ti.00) 13. Both CRD Flow Centrol vetves have felled. In eroer to increase CRD
' cooling water flow, the artve water PCV is opened. . Explain why there is a 70 psid limit for cooling water dP when performing this evolution.
ANSWER: To prevent the rods from drifting in.
REFERENCE:
LSD88, LOA RD-04 TP0/TK0: C201001Rt.11 D201001R1.13 KA: 201001A4.04 R0: 3.1 SRO: 3.0 TRO-89:8.3.A.4 4 d
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I~ PT, VALUE l
j EB-NUM: 01 024265 p- EL2113 ADS
' L1 ' LICENSE MASTER QUESTION ADD j, KA218 KA: ADS ECCS/RCIC RNR/LP/ ADS /HP/RCIC LOP - LASALLE OPERATIhG PROCEDURES.
' (0.50) 14. Wich one of the following statements is correct concerning the ADS r Inhibit switches?
- a. Only one of the two is needed to inhibit ADS.
- b. They will only inhibit if there is high drywell pressure.
- c. Once the vetves open, the inhibit switches cannot close them.
- d. They will prevent manust initiation when in the INHIBIT position.
' ANSWER: . c. Once' >,t* velves open,' tha itMbit switches connot close them.
TP0/TKos D218000R1.03 KA:. 218000K4.01 R0: 3.7 SRO: 3.9 REFLhiWCE: LOP MS 03, LSD #37 TR0 89:B.12.E.2
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y* s R$0RT'R2.4 'R0 Requol section B . PAGE: 12 EXA141 NATION KEY DATE: 07/31/89 PT. VALUE EB NUN: 01 024262 EL2115. RH-KA205 - KA: $NUTDOWN COOLING LOP LASALLE OPERATING PROCEDURES
- ECCS/RCIC RNR/LP/AD$/W/RCIC (0.75) 15. When operatin0 the 'B' RNR toop in the shutdown cooling pede f rom the Remote Shutdoom Penet," identify the SDC interlock that is stiLL in offact.
- d. SP suction and full floes test return valves (F0048 and F0248) nust be closed prior to the SDC suction volve (F0066) being opened.
ANSWER: d. SP suction and full flow tett return valves (F004B and F02'8) aust be closed prior to the SDC suction vetve (F0068) being opened.
TPC/TK0: 'C205000R1.02 KA: 205000K4.33 kO 3.8 SRO: 3.8
REFERENCE:
LOP-RX-08, LOP-RN-07, LSD #39 and 74 TRO 89:8.7.E
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RIPORT'#2.4 R0 Reque! Section S . PAGE: 13
' EXAMINATION KEY DATE: 07/31/89
' PT. VALUE
. EB-NUN 01-024247 EL4314 : LOP GC NP
- L1 LICENSE MASTER QUESTION ADD LOP LASALLE OPERATING PROCEbdRES ECCS/RCIC RNR/LP/ ADS /NP/kCIC lL KA209 KA: LPCS; HPCS l: (0.75) 16. Pressing the NPCS "HI DRYWL PR LO L'TR LEVEL" push button with a high drywett signal present wills
- a. trip the NPCS pump.
b.' . close the injection valve (F004).
I c. Lockout the low levet initiation signet.
- d. attow HPCS to be stopped without overriding low level autostart feature, j ANSWER : d. allow NPCS to be stopped without overriding low level autostart feature.
TPO: C,203000R02 C 203000Rt.05 KA: 209002K4.07 RO: 3.5 SRO: 3.7
REFERENCE:
LOP-NP 03 ,
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R . RO Regual section 5 PAGE: 14 t~ EXAMINAT10N KEY,. DATE: 07/31/89 s.
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. L1 LICENSE MASTER QUESTION ADD -
KA223 KA PCIS; PRIMARY CONTAINMENT,AND AUXILIARIES CONTA!INENT PRIMARY / SECONDARY /PCIS/PCACS/VP/VQ/PCCW LOP- LAGALLE OPERATING PROCEDURES'
, (0.50) 17J Both the 858 and the 'C' VP chillers have tripped on low chill water
-: temperature. Fif teen minutes toter chilt water temperature is 65'F.
' Identify which chiller (s) will auto-start.
- e. 8 and C b.' neither B or C ;
I
- c. C only
- d. 5 only e
' ' ANSWER: d. B only i 4
TPC/TK0 C223001RI.05 ,
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REFERENCE:
LOP VP 02, Ls0 852 TRO 89:3.25.A 1
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_ EXAMINATION KEY DATES 07/31/89
semesses masser. sesssssssssssssssssssssssssssssssssssssses l PT, VALUE
~
EB NuRs 09 024277 EL6325- CX EL3025' CX '
EL6273 CX
'EL22T3 CX
. L1 ' LICENSE MASTER QUESTION ADD'.
G296: Plantwide Generic objectives PLANT INST ARM /PRM/LD/RPV INST /CX/RX/CM LOP LASALLE OPERAT!NG PROCEDURES (0.50) 18. Problems with the Drywell Cooling System have resulted in drywell
. pressure increasing from 0 pels to 1.1 psig. The bar graph display color for drywell pressure on SPOS (Safety Portmeter Display System) will bei
- s. cyon (blue)
- b. _. red
- c. block
- d. green -
ANSWER: d. green TP0/TK0: C2"83000Rt.02 KA: ~296001A1.15 RO: 3.2 SRO: 3.4
REFERENCE:
. LOP CX 102
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-EB NUM: 01-022950-L1 LICENSE MASTER QUESTION ADD MIB 1894 - LGA SUPP, LAP-1600-2,leRFP SEAL CLG MOD -
EL4428 ' LAP 1600'S LAP LASALLE ADMINISTRATIVE PROCEDURES u295006- SCRAM KA294 ' PlantwideGenericObjectives-(1.00') 19. At what points or under what 2 conditions does the operator have the authority and responsibility to shut down the reactor?
. M CRt When two of the follo6&fj occur- (concept worth pts os.)
- 1) The R0 determines'the safety of the reacto'r is in jeoperdy, or'
Also accept - When LSSS is being approached)
REF: LAP 1600-2, REV 34, STEP F.2.a TK0/TP0: D295006R113 F294001R006 K/A: 295006 GENERIC #11 R0: 4.3 Sto: 4.5 TR0-89:C.6.B.1; A.1 EB-NUM: 01 021138 EL4445 SELECTED LCO's ,
L1 LICENSE MASTER QUESTION ADD TECH SPECS - LASALLE TECHNICAL SPECIFICATIONS KA223 . KA: PCIS; PRIMARY CONTAINMENT AND AUXILIARIES CONTAINMENT PRIMARY / SECONDARY /PCIS/PCACS/VP/VQ/PCCW (0.75) 20. Followirg a TIP trace, the "C" Tip Ball vetve did not auto close.
' - Rowever,'the belt valve was subsequently fully closed by "jogginga it
, to close. Primary containment integrity requirements are not presently met. What must be done to the "C" Tip Belt valve to satisfy primary containment integrity agirosents?
I ANSWER: Deactivate the ball valve in its isolated position.
Ref Tech Specs 3.6.3 TKos C215001R1.08
- TR0-89: A.3
[ KA: 223002 G.5 3.1/4.1 r
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f'RE40RTR2.4 R0 Requal Section s PAGEt 17-EXAMINATION KEY DATE: 07/31/89 e me------.............................
Pfi VALUE-EB-lWN 01 022707
~EL4443 TECH SPEC USAGE / APPLICABILITY / CLARIFICATIONS EL8013- TECH SPEC USAGE / APPLICABILITY / CLARIFICATIONS
' L1 LICENSE MASTER QUESTION ADD MS-6 88 THIS GUEST 10N COULD HAVE BEEN USED DURING MOD 6-80 C261000R308-C261000R03
. TECH SPECS LASALLE TECHNICAL SPECIFICATIONS KA261. KA: VG
' RAD RELEASE OG/MSIV LCS/VG/L10 RADWASTE/SQLID RADWASTE
.(0.75) 21. Initlet conditions:
U 1, D.C. 1 U 2, O.C.'1 A-S8GT is DOS.
B SSGT does not meet its surveillance requirements.
Anatyre the given information and determine correct actions in accordance with the Technical Specifications.
ANSWER: 1. Per T.S. 3.0.3, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action ti place both units g7 '
in a condition in which the SSGT spec does not apply ty placing
- the mits in:
Startup within the next 6 hrt..
Not Shutdown within the following 6 hrs. and Cold Shutdown within the sseequent 24 hrs. (Take actions per Tech Spec 3.0.3 is acceptablejorcredit) ~~"
REF: T. S. 3.0.3 TK0 C261000R3.08
-K/A 261000 G.11 TRO:89 A.3
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PRIMARY RT/CD CS/FW/HD/MS/RPV KA259 KA: FW; RWLC.
LOA LAGALLE OPERATING ABNORMAL PROCEDURES SPECIAL OPEX; TMI; CHERNOBYL; AND MODULE SPECIFIC 1988/89 (1.00) 22. One of the insnedlete actions for a toes of Feedwater Heaters is to reduce total core flow. The same stop contains a caution not to
' redace total core flow below 45%. The reason for the caution is to (Select the most correct.)
- a. ' stay out of the instability regions.
- b. maintain MCPR above the safety limit.
- c. amintain PC10MR timits in the lower core region.
- d. prevent binding of the Flow Control valve.
< e. prevent cavitation of the flow Control Valve.
' ANSWER: a. stay out of the instability regions. . .
TP0/TK0: D259001R1.11 ,
KA: 259001K3.12 R0: 3.8 -SRO: 3.9 -
REFERENCES:
LOA FW-01 4 Tao-89: D.12.A.2.
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REPORT R2.4- ko Requal Section 8 PAGE: 19 -
EXAM!kATION KEY DATE: 07/31/89
..... .. . .. . .. ..s ........................... ..........
, PT. VALUE EB-NUM: 01*C23954 EL4216- LOA RN-RR EL2231 RR L1 LICENSE MASTER QUESTION ADD MOD 2 89 Module 2 1989 Raquet euestion MOD *3-89E LQA's/ LOP's-KA295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRC.
LOA LASALLE OPERATING ABNORMAL PROCEDURES REACTIVITY RR/R0 MECN/RD HYD/SC/ FUEL / REFUEL (0.75) 23. The plant was initially at 90% power. Following a reactor recirculation single pump trip from the 97% flow control line, stable plant conditions are W4 power and 50% core flow. What imediate
' actions are required. ,
ANSWER: Maintain norinal reactor pressure and level.
(No action neccessary is also en acceptable answer since maintaining norsel reactor pressure and tevet are implied operator duties)
REF: LOA RR-06, 09 TK0/TP0: 0295001R113 D202001R213 K/At 295001 AA2.01 Ros 3.5 Sto: 3.8
~
G.10 3.8 3.7 TR0189-C.7.A 4
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- End of Printa
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l Requ21. ACHI-
- ~ R;vicies 4 5
February 28, 1989 23 l
MSALLE COUNTY NUCLEAR STATIN LICENSED OPERATOR REQUALIFICATI N EKAMINATI M SECTIN B 1
EdeLh -C~WE License Type: O Written by:
i Approved: \ q //
.x #w%
i m Date Administered: g.y.e9 -
Names INSTRUCTIONS TO EKAMINEE:
Mrite answers on one side only The passing grade requires 80% averaged be*. ween Sections A and B. Failure to achieve this grade will require additional evaluation and enrollment in an accelerated requalification program. Examination papers will be picked up two (2) hours after the examination starts.
Total Points k!.
Points missed Points received t.l
['
.;' FINAL GRADE: %
All work done on this examination is my own. I have neither given nor ,
received assistance. I agree that I will not knowingly divulge details of the requalification exam to any unauthorized persons. I understand that cheating on this examination will result in automatic denial of my license renewal by the NRC and could result in more severe penalties.
Applicant's Signature j
/
Signature of Grader Date ATTACHMENT E-1 page 2 of 4 .
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TACILITY RULES AND GUIDELINES TOR LICENSE REQUALITICATION During the administration of this examination the following rules apply q
- 1. Cheating on the examination means an automatic suspension from license duties and'could result in more severe penalties such as revocation of your license.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink only to facilitate legible reproductions.
- 4. . Print your name in the blank provided on the cover sheet of the examination.
- 5. Till in the date on the cover sheet of the examination (if necessary) and perform a page count to ensure your exam contains the right number of questions.
- 6. ' Answer each question on the examination. If additional paper is required, use only the lined paper provided by the examiner.
- 7. ' Initial each page of the exam.
- 8. The point value.for each question is indicated in parentheses before the question and is based upon the questions importance to safety as well as a guide for the depth of answer required.
- 9. Unless solicited, the location of references need not be stat'ed.
- 10. This section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete this section.
- 11. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even through you got the four correct answers.
- 12. Use abbreviations only if they are commonly used in facility literature.
L
- 13. Show all calculations, methods, or assumptions used to obtain an answer to j.
mathematical problems whether indicated in the question or not.
2' 14. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION l AND DO NOT LEAVE ANY ANSWER BLANK.
, 15. If parts of the examination are not clear as to intent, ask questions of the examiner only.
i i
DOCUMENT ID 1629L
. j
- a. l 1
- 16. You must sign ~the statement on the cover sheet that indicates that the l' work is your own and you have not received or been given assistance in completing the examination. You must also certify that you'will not divulge. details of the exam to any unauthorized persons. This must be done af ter the examination has been completed. . Due to the nature of open reference examinations, particular cars must be taken to maintain individual examination security and avoid any possibility.of compromise or appearance of cheating.
- 17. When you complete your examination, you shall
- a. Turn in your copy of the examination and all pages used to answer the examination questions.
- b. Turn in all scrap and unused paper (if any).
- c. Leave-the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your exam may be invalidated requiring reexamination.
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9 DOCUMENT ID 1529L
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.oLREPORT.R2.4' Sto Requot Section B PAGE: 1
- EXAMINATION KET DATE: 08/03/89 ;
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EXAM WUMBER: 01 L ReMK 89-0006 89 LOCATION : 01 L RQMX 89 ,
POINT VALUE : Gib+0. 2 l,*7[ b 2E U ENAM COUNT.' . 11 TOTAL QUEST!0NS : 24 TOTAL DIFF LEVEL: 144.00 PT. VALUE
- t EB NUM: 01 022817 EL4114 LGA USAGE GRAPHS, STEPS,DEF,ETC-L1 LICENSE MASTER QUESTION ADD E295037R411 MOD 6 88 THIS QUESTION COULD HAVE BEEN USED DURING MOD 6 88 KA295037 SCRAM COND PuESENT AND RX AT POWER OR UNKNOWN-ATWS LGA ~LASALLE GENERAL ABNORMAL PROCEDURES
-(0.75) 11.
- 75 control rods are stuck at position 48.
- Reactor power 7% and rising.
- Suppression pool water temperature 115'F and rising.
- Suppression chamber pressure 10 PSIG and rising.
- Drywell pressure 20 PSIG and rising.
Analyze the above concurrent plant conditions. Determine the actions you should take to control reactor level. (Select the one best answer.)' (Assume multiple indications confirm the stated conditions.)
- a. Allow levet to return to the normal bend and control at 36".
- b. Terminate att injection except for CR0 and boron injection, OPEN 7 ADS SRVs, disregard level, do not reinject until RPV pressure is below the MAFP.
- c. Reduce injection and maintain RPV level et its current value.
- d. Tereinste att injection except CRD and boron injection until reactor power is below 5% or RPV tevet reaches -161" or all SRVs are closed and drywell pressure remains below 1.69 psig.
ANSWER: d.
TK0/TPO E295037R0411
. K/A 295037 Generic 12 R0 3.9 SR0 4.6 TR0 89: C.3.A.3 Reft LGA ATWS 04 9
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.....o . .............................. ..............................
- PT. VALUE s 5 EB mish 41 024144 EL4114~ LGA USAGE GRAPMS, STEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD MOD 6-88' THIS QUESTION COULD HAVE BEEtt USED DURING MOD 6 88 KA295031 REACTOR LOW WATER LEVEL. '
LGA LASALLE GENERAL ABNORMAL PROCEDURES
!(1.00). 2. A toes of all AC power has occured (both off site and on site including all D/G's) teaving you with no motor driven p eps. Reactor -
level is being maintained by RCIC. Stgipression Pool Level is low due to e break in the containment well. Conditions cannot be maintained above the HCLL and ADS is manually initiated per LGA 03. Select the best answers
- a. ADS velves should not be closed totit the vesset is completely depressurized.
- b. ADS velves should be closed prior to exceeding the 100 degree per hour cooldown rate limit.
- c. ADS valves should be closed immediately when conditions can be maintained above the HCLL (on the safe side).
- ANSWER: d. ADS volves should be closed to maintain RPV pressure above 578.
REF: LGA 03; LGA Gen. Precautions KA: E295031 EK2.04 4.0/4.1 4 TK0: E295031R108-TRO:89 C.3.A.1 l
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>= .... . ......... .................................... ..... .... ..
PT. VALUEJ EB NUM: 01 022746
'EL4112 LLt 9UPPORT PROCEDURES L1 LICENSE MASTER QUESTION ADD E295031R203 MtD 1 89A 'LGA SUPP, LAP-1600-2,@ RFP BEAL CLG MOD '
KA295031 REACTOR LOW WATER LEVEL
-LGA LASALLE GENERAL ABNORMAL PROCEDURES LOA LASALLE OPE' RATING ASNORMAL PROCEDURES ECCS/RClc RNR/LP/ ADS /MP/RCIC
- (0.75) 3. Through which system does the Fuel Pool Emsroency Makeg Ptap inject into the reactor?
, s. RNR "B"
- b. RHR "C"
- c. RCIC
. d. Feedwater -
- e. Fire hose connected to instrument tap ANSWER: a. RHR "B" TKO E295031R203 K/A 295031EA1.08 SRO 3.8/R0 3.9
-REF: LOA FC 03-TRO-89:C.3.A.10.C.2; A.1 EE. NUM: 01 024213 EL3024 RPV INST EL4114- LGA USAGE-GRAPHS, STEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD PLANT INST ARM /PRM/LD/RPV INST /CX/RX/CM LGA LASALLE GENERAL ASNORMAL P.0CEDURES KA216 KA: RPV INSTRUMENTATION (1.00) 6. During en accident efter drywell temperatures have gotten very high and the RPV has depressurf red, you see several RPV tevet instruments peg high. When this occurs, which instrument would you expect to stay on scate?
ANSWER: Wide range vessel level instruments (and recorders 4 totst) should stay on scale (1.0 pt).
4
REFERENCE:
LGA 03, RPV Set Temp Limit Curve l
TPD/TK0: E295024R1.11 l' -
? KA: 216000 RO: 3.5 SRO: 3.6 TR0 89:B.6.D.3 and A.6 t,
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PT.'VALUE EB NUM: 01 022700
'EL4114 LGA USAGE GRAPHS. STEPS,DEF,ETC Et7114 LGA USAGE GRAPHS,$TEPS,DEF,ETC L1 LICENSE MASTER QUESTION ADD E295037R107 MOD 6 88 - THIS QUESTION COULD NAVE BEEN USED DURING MOD 6-88 KA295026 SUPPRESSION POOL HIGH WATER TEMPERATURE - EMER EVO LGA LASALLE GENERAL ABNORMAL PEDCEDURES
-(0.75) 5. Reactor power is 6.51. At what suppression pool water temperature
'will the boron injection temperature limit be reached?
. ANSWER: 110'F.
c\
'TK0/TP0'E295037R107 K/A 295026 Generic 12 3.8/4.5 LGA ATWS 01 TRO-89:3.A.3 ES-NUM: 01 021097 EL4113 LGA ENTRY CONDITIONS L1 LICENSE MASTER QUESTION ADD KA295031 REACTOR LOW WATER LEYEL KA295037- SCRAM COND PRESENT AND RX AT POWER OR UNKNOWN-ATWS LGA LASALLE GENERAL ASNORMAL PROCEDURES (1.50) 6. The reactor was et 98% power before a Fee & ater Level Control Melfurstion causes a Low Level Reactor Scram Signal to occur. The operator enters LGA-01. What determines whether he w1LL stay in LGA-01, Level / Pressure Control, or enter LGA-ATWS 01, Power Control?
- ANSbMR: If the reactor is still critical (0.75) or power cannot be determined (0.75) enter the ATWS procedures. (Also acceptable are the other entry conditions to the ATWS procedures 1.e. - boron has been injected and level, D/W pressure or RPV pressure exceeding entry limits.)
- TK0: E295000R0.01 K/A 295031 Generic #11 RO 4.2 SRO 4.6 295037 Generic #11 4.4 4.7 TRO-89: C.3.A.1; C.3.A.6 Reft LGA ATWS 01
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' REPORT'R2.4. SRO Requal Section B PAGE: 5
, EXAMINATION KEY. DATE: 08/03/89
.... sa s.ne. ames===... .... .... . ........ ...................
PT VALUE i Es KUM: 01 020582
- KA295037 - SCRAM COND PRESENT AND RX AT POWER OR UNKNOWN ATWS-LGA LASALLE GENERAL A& NORMAL PROCEDURES LOA LASALLE OPERATING ABNORMAL PROCEDURES REACTIVITY RR/RD MECN/RD HYD/SC/ FUEL / REFUEL j L1 LICENSE MASTER QUESTION ADD EL7218 LOA RH RR EL7112 LGA SUPPORT PROCEDURES EL7216 LOA MC-0G MCD 1 89A LGA SUPP, LAP-1600 2,m RFP SEAL CLG MCD N00 6 88 THIS QUESTION COULD NAVE BEEN USED DURING MOD 6 88
'(1.00)- 7. A levet transient coupled with an incomplete scram has occurred. Both CRD pe ps were lined up and are injecting in accordance with LDA RD-07, " Simultaneous Operation of Both CRD Pa ps." CRD injection is no longer required to maintain RPV tevel. Tou have been assigned the task of realigning the CRD system to drive the 20 rods that are still not futt in using method 2 of LOA NS 09. What three actions con you take to restore CRD drive ater pressure to normatf ANSWER: 0.33 points each
- 1. Close the pressure control bypass valve (C11 F004)
- 2. Throttle the pressure control valve (C11 F003)
- 3. Close the charging water header ste.p volve (C11 F034)
Reft LOA NO 09 LOA-RD-07 LGA-ATWS-01 TK0/TP0: E295037R01 KA: 295037 EK 2.05 4.0/4.1 T'Q-89:A.1; C.3.A.12.B t I j.- !
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REPORTR2.6 - SP.0 Requot Section B l :PAGE: 6
-EXAMINATION KEY. Daft: 06/03/89 f..
g PT.,VALUE .j Es NUM: 01 022854-EL7211 LOA AA-CG EL6241 AC DIST EL4211 LO4 AA-CG ]
- EL2241 AC DIST L1 LICENSE MASTER QUESTION ADD MOD 3 89 Question for use on Module 3 1989 LO4 LASALLE OPERATING ABNORMAL PROCEDURES ELECTRICAL AC/DC/DG/ MAIN GEN / GENERATOR AUX / GEN EXCITATION KA262- KA: AC; UPS KA264 KA: DG (1.00)~ 8. Unit une is in NOT SHUTDOWN with att electrical power being s e lled from the Systom Aux Trensiormer ($AT). Assuming ati equipuent operates as designed, predict the status (energized or de-energized) of the following buses 30 seconds after a trio of the SAT.
. (assuse no operator action)
Sus 135Y -
Bus 132Y -
Sus 142Y -
sus 141X -
ANSWER: Bus 135Y - energized ,
F e
Bue.132Y - de energized (fed from 142X)
Bus 142Y onergized Bus 141X de-energized LOA AP 02, 04, Lasslie System Description Chapter 42, Electrical prints 1E 1 4000AJ > AN TK0/TPO D295003R204 K/A 262001 K6.02 3.6/3.9 A2.09 3.9/4.3 264000 A2.09 3.7/4.1 TRO:89-8.1.D 4
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REPORT R2.4? SR0 Requel Section 8 'PAGEt 7 .
EXAMINATION KEY DATE: 06/03/89 ;
LPT.~VALUE l
EB NUM: 01 024185 -
EL4531 OPERATOK EXPERIENCE.
L1 LICENSE MASTER QUESTION ADD KA217 KA: RCIC ECCS/RCIC RNR/LP/ ADS /MP/RCIC SPECIAL OPEX; TMI; CHERNOBYL; AND MODULE SPECIFIC 1966/89 (1.00) 9. A loss of and subsequent return of power to the RCIC leek detection logic gy result ins (Select the most correct action.)- (Note: The answer to this question key not be found in the reference meterials provided.)
- a. spurious initiation of RCIC.
- b. RCIC tv.bine trip.
- c. loss of the auto f metion of the minim a flow valve.
- d. foolation of the irboard steam sply valve (F063).
ANSWER: d. isolation of the inboard steam supply valve (F063).
TPC/TK0: D 217001 01 KA: 217000A2.05 RO: 3.3 SRO:
3.3 REFERENCES
- Elect. Dia., L RRR7-88 TR0-89-D.12.D.1.
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' Li LICENSE MASTER QUESTION ADD
.ECCS/RCIC RHR/LP/ ADS /MP/RCIC.
KA217 KA: RCIC LOP - LASALLE OPERATING PROCEDURES l LOA LASALLE OPERATING ABNORMAL PROCEDURES (0.75) 10. What system feature provides overpressure protection for the
. RCic turbine exhaust header?
!' -!1 ANSWER: High exhaust pressure turbine trip (25#)
also accept:
Rupture diaphrages (1508) or !
System foolation (10# between diaphragus)
(.S.A L haum Wyzb t rs$d E6l' fdb N*Y G% Ib Ytwl U.d& ~ [ A ~T J$ s TPC/TKos' C217000R2.06 D217000R1.03 ,
KA: 217000K4.04 !
Ros 3.0 SRO:
3.1 REFERENCES
- LOP RI-04 LOA-RI-03 LSD Ch. 41 1
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EB lut: 01 022685 EL4443 TECH SPEC USAGE / APPLICABILITY / CLARIFICATIONS EL8013 TECH SPEC USAGE / APPLICABILITY / CLARIFICATIONS L1 LICENSE MASTER QUESTION ADD MOD 6-88 TH!$ QUET, TION COULD HAVE BEEN USED DURING MOD 6-88 TECH SPECS, LASALLE TECHNICAL SPECIFICATION REACTIVITY RR/RD MECH /RD HYD/SC/ FUEL / REFUEL LO4 LASALLE OPERATING ASNORMAL PROCEDURES KA295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRC.
l ~ ~ (1.00) 11.~ A sinete recirc punp trips f rom the 981 FCL toeving the plant at 42MW/HR . core flow and 50% core thernet power. It is not anticipated that the puip will be recovered. Identify correct actions from the List below. More than one response may be required.
A. Increase the MCPR safety limit to 1.08 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. Inunediately SCRAM.
C. Redre the APRM scram and rod block trip setpoints and allowable values.
D. Insert cram arrays.
E. Increase core flow mder the diention of a Nuclear Engineer or continue inserting rods in sequence to reduce power to below the 80% FCL.
F. Exit the restricted zone within 2 minutes or scram the reactor.
ANSWER: (Proportional grading applies)
A,C,D,E REF: LOA RR-06, 09 TK0:- D2950001R1.13, 1.07 K/A 295001 C.8,'295001 G11 TR0:59-C.7.A
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EB NUM: 01 022820 i
EL1023 PRES \ TEMP CHARACTERISTICS OF FLUIDS EL4219 LOA RS SC
,. - L1- LICENSE MASTER QUESTION ADD I' D295016R113 MOD 1 893 CHERN, APP R, RX PANEL ,
i, PLANT INST ARM /PRM/LD/RPV INST /CX/RX/CM LOA LASALLE OPERATING ABNORMAL PROCEDURES KA295016 CONTROL ROOM ABANDONMENT
- (1.50) 12. You are currently performing a cooldown from the remote shutdown
!- panel. 'N' SRV is open. The valve was opened at 1200 AM to initiate the cooldown. You have been keeping track of the following
- inf or1mstion.
, Time RPV Pressure 1200 AM 985 PSIG 1215 AM 585 PSIG
- a. Determine the cooldown rate in 'F per Hr.
- b. Assuning the cooldown continues at its current pace, predict the latest time at which the cooldown must be secured in order to prevent exceeding the cooldown Technical Specification.
ANSWER: a. 985 pets + 14.7 999.7 PSIA; using steam table . ).4}*f,15'F (.25 pts) 8 585 psig + 14.7 599.7 PSIA; using steam table = tg(*1 5'F i
(.25 pts) gggg*f, = (486-5451*F = -236*F/Hr 140*F(.25 pts)
'; delta Mr .25 Hr l ( .25 If forgot to add 14.7 to PSIG) i~
- b. Tech Spec 100*F in any one hour (.25 pts) 1 i 236'F/Hr X THr = 100'F THr . 100'F = .423 Hr X 60 min /Hr .25,1 5 min (.25 pts) 236*F/Hr 1200 AM + 25 min . 12:25 AM i 5 min. (.25 pts)
TK0/TP0 D-295016 R 1.13 K/A 295016 AA 2.06 i RO 3.3 Sao 3.5
$ LOA-RX-01
- Thorinodynamics Lesson Plan
. TRD-89: A.1; B.7.B i
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~ EXAMINATION KEY DATE: 08/03/89 l 'PT. VALUE' ES NUM: 01-024250 EL7331 'LGP's EL4331 LGP's
' L1 LICENSE MASTER SUESTION ADD-KA204 - -KA: RT LOP LASALLE GENERAL OPERATING PROCEDURES-
' PRIMARY RT/CD CS/FW/MD/MS/RPV
- (0.50)'13. Durins a startup, the operator'is cautioned to maintain RwCu return flow as high as possible. What is the boats for,this caution?.
'/ ll ,\ ,\ i o e
LANSWER:
'To minimite feedwater nozzle, sporger and header thermal stress at low.' ,',
flow conditions.
REFERENCE:
LGP 1 1, F.1.1 TK0: B-1.05
'TR0: C.4.A KA: '204000K1.03~ RO: 3.1 SR0: 3.1 204000A4.07 Ron. 3.1 sR0: 3.1
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'ES-NUM: 01 024248
, EL7331- LGP'S EL4331- LGP88' EL6319 RPS/ARI-EL3019 ' RPS/ARI
. L1 LICENSE MASTER QUESTION ADD LGP LASALLE GENERAL OPERATING PROCEDURES KA295037- SCRAM COND PRESENT AND RX AT POWER OR UNKNCM ATWS R@ CONTROL RMCS/RSCS/RWM/ ROM /RPS (1.00) 14. ARI needs to be reset after en automatic initiation. Which one of the
,following g gi occur prior to resetting ARI?
- c. All rods are futt in.
- d. Scram Discharge Volume Bypass switch in bypass.
ANSWER: b. ARI initiation signal no longer present.
TP0/TK0 295006R1.02
' KA: 295037EK3.05 R0: 3.6 SRO: 3.9 4 .295c37EA1.03 RO: 4.1 SRO:
4.1 REFERENCES
- LGP 3-2 TRO A.6 I
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EB-NUM: 01 024252 j
EL8013 TECH SPEC USAGE / APPLICABILITY / CLARIFICATION $ '
EL7318 LOP RE-RR L1 LICENSE MASTER QUESTION ADD LOP LASALLE OPERAlING PROCEDURES -
ROD CONTROL RMCS/RSCS/RWM/RBM/RPS KA212 KA: RPS
' (0.75) 15. During transfer of power for the "B" RPS bus from the alternate to the normal supply, reley 1(2)R21H-K35B (INBOARD ISOLATim INITIATION) is required to be blocked in the energized position. Determine the most limiting Tech Spec that would be in effect during the time that the relay is blocked in the energized position.
. ANSWER: Tech spec 3.0.3 TPC/TK0: C212000S1.06 KA: 212000 Generic 5 RO: 3.8 SRO: 4.5
REFERENCE:
LDP-RP 04-TRO-89:A.3 4
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EXAMINATION KEY. DATE: 08/03/89 l,l . = === =... .............. . ... ... . ........
l;1PT.VALUE EB MLat: 01-024277 EL6325. CX EL3025 CX
'EL6273 CX EL2273 CX -
L1 LICENSE MASTER QUESTION ADD l- - KA2% : Plantwide Generic objectIwes it PLANT INST' ARM /PRM/LD/RPV INST /CX/RX/CM
' LOP LASALLE OPERATING PROCEDURES (0.50) 16. Problems with the Drywell Cooling System have resulted I* wLt pressure increasing from 0 psis to 1.1 pois. The her pr.pn display color for drywett pressure on $POS (Sofety Parameter Display System) will ben i
- s. cyon (blue)
- b. red
- c. block
- d. preen.-
' ANSWER: ' d. green TP0/TK0: C283000R1.02 KA:' 294001A1.15 RO: 3.2 sRO: 3.4 REFERENCEi LOP CX 102 TRO-89:B.20 A I
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. EXAMINATION KEY' DATE: 08/03/89 i- .
- PT.=WALUE Es NUM
- 01-024236 EL8022 LAP 200's
.L1 LICENSE MASTER QUEFTION ADD-LAP LASALLE ADMINISTRATIVE PROCEDURES KA294 Plantwide Generic Objectives' (1.25) 17. Which two departments, (other then the Operations department),
s4 ject to defined constraints, may meinteln a sply cf japers, lif ted tend tese, relay blocks and terminal block contact extenders for use during surveittence procedures?
ANSWER: Instrument e d Electrical Maintenance REF: LAP 240 6 TK0: H294001 10.01 IdO*89: C.4.A; C.9.A.1 KA: 294001K1.02 R0: 3.9 SRO: 4.5 294001A1.03 Roz 2.7 SRO: 3.7 294001A1.06 R0: 3.4 SRO: 3.6 i
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Eg-IRm: 01 024285 .
EL8022 LAP 200's L1 LICENSE MASTER ouESTION ADD LAP LLAELLLE ADMINISTRATIVE PeoCEDUCES KA294 Plantwide Generic Objectivesi (0.75) 18. You are the offpolte Shift Engineer. The oncoming Shift Engineer tetts you that he hast perfor1ned his visuet control room penet check; reviewed the unit, conter desk,' Shift Engineer.'s Deity order and Degraded Equipment Logs; end verified alntoun manning requirements.
What action remains to be performed prior to his assuming the shift?
- a. Discuss plant status, planned evolutions, maintenance and surveltlances with the offooing Shift Engineer.
- b. . Verify control rod segaence against present rod positions.
c.' Review confined spaces tog.
- d. AEER penet check, zANSWER:~ e. Discuss plant status, planned evolutions, maintenance and surveillences with the offgoing shift Engineer.
REFERENCE; LAP 200 3, F.1 TK0: H29400156.02 TRO: (.4.A 10 3 : 294001A1.03 RD: 2.7 SRO: 3.7
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l EXAMINATION KEY DATE: 08/03/89 i
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i ES Num: 01 022732
- EL4443' TECH SPEC USAGE / APPLICABILITY / CLARIFICATION $
-ELB013 TECH SPEC USAGE / APPLICABILITY / CLARIFICATIONS L11. LICENSE MASTER QUESTION ADD MOD 6 88 THIS GUESTION COULD HAVE FEEN USED DURING MOD 6-88 TECH SPECS LASALLE TECHNICAL SPECIFICATIONS KA295004 PARTIAL OR COMPLETE LOS$ OF DC POWER ELECTRICAL AC/DC/DC/ MAIN GEN / GENERATOR AUX / GEN EXCITATION.
(0.50) 19. Concerning the 125 VDC setteries -
At What resistance across the corroded terminal should the bettery be dos,tered inoperable?
ANSWER ' When the resistence across the terminets is greater then
- 150 micro-ohns. (0.5)
TK0/TPo 3-20 004s2.07/4 294001$06 K/A 295004 G.11 REFT Tech Spec 4.8.2.3.2.b.2 Tech Spec clarif. 6 88
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l" PT. VALUE-EB-NuM: 01-022702
-EL4441 TECM SPEC DEFINITIONS '!
EL8011 TECH SPEC DEFINITIONS.
L1 LICENSE MASTER QUESTION ADD
'M00-6 88 :TMl$ QUESTION COULD HAVE BEEN USED DURING MOD 6-88 F294001R06 KA294 Plantwide Generic Objectives CONTAINMENT PRIMARY / SECONDARY /PCIS/PCACS/VP/VQ/PCCW TECH SPECS LASALLE TECHNICAL SPECIFICAT!DNS
-(1.00) 20..The unit is in D.C. 1. Anatyre each of the following situations to oetermine impact on Prunary Containment integrity.
A. The inboard MSIV LCS is inoperable. All isolation valves are stooed.
' B. Suppression pool levet has' increased to +4 inches.
C. The LPCS min flow valve (E21 F011) is out of service in the open
. position.
D. Stan 6y Ces Treatment is inoperable. ,
. ANSWER: -(CONCEPT)
A. No impact on containment integrity.
B. Containment integrity is not maintained.
- C. Containment integrity is not maintained.
D. No impact on containment integrity.
TK0/TPO F294001R06 K/A 223001 K1.01 223001 K1.02 Ref: TS Definition 1.29-TRO-89:A.3 4
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.EL4444 ~1 HR ACT!DNS L1 LICENSE MASTER ouESTION ADD AUX SUPPORT SA/IA/IN/ AUX STEAM / FIRE PR1TECTION TECH SPECS .LASALLE TECHNICAL SPECIFI MTIONS KA294' Plantwide Generic objectives KA286 KA: FIRE PROTECTION (1.00) 21. With respect to the Fire Setection System Instri.nentation:
- 1. When are they required to be operable per Tech Specs? (0.5)
- 2. What action (s) is(ore) regaired to be taken within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, per Tech Specs if the ruuber of operable fire detection instruments are Less than required? (Answer only per Tech spec actions. Do not include reporting requirements.) (0.5)
' ANSWER: 1. Whenever equipment protected by the fire detection instrument is required to be operable. (0.5)
- 2. Establish's fire watch petrol to inspect the zone (s) with the ligerebte instrument (s) et toast once per hour, (unless the instrument (s) is located inside the primary containment, then
' nsaect i the primary containment at toast once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or moref ter the conteirment air temperature et toast once per hour et ine locations listed in spec 4.6.1.7.). (0.5)
REFERENCE:
Tech Spec 3.3.7.9, p 3/4 3 75 TRO 89:A.3; B.27.1 TK0: D286000R1.07 KA: 294001K1.16 3.5/3.8 286000G5 3.1/3.9 1:
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PT,. VALUE, EB-Ntsl: 01-020250:
EL1026. CORE THERMAL LIMITS :
L1 LICENSE MASTER QUEM ION ADD M -2 89 . Module 2.t989 Requot euestion, TECH SPECS LASALLE TECHNICAL SPECIFICATIONS PLANT INST ARM /PRM/LD/RPV INST /CX/RX/CM CMC Core Monitoring Code KA294 Plantwide Generic Objectives LOS LASALLE OPERATING SURVEILLANCE
.(1.00) 22. LASALLE CD. UNIT 2 SEQUt.*E No 5 CORE PARAMETERS CORE MONITORING CUDE 21-FEB '089 04:59 CALCULATED POWER MWT 3300 PERIODIC LOG 21 FEB-1. W 05:28 PRINTED POWER MWE 1107 CASE ID f 151890221045946 -
WT ML8/NR 108 CALC RESULTS RESTART Ft .51890221045928
'LPRM SNAPE FULL CORE DNS STU/LsN 25.76 Keff 1.0001 .
'PR PSIG 985.1 XE% - 2.29. LOAD LINE LIMITS 113.7%
CORE M /T. 10664.8 XE/E0 1.05 CORE POWER 99.3%
CYCLE M /T 119.9 XE/ RATED 0.97 CORE FLOW (WT) 100.0%-
CRD 0.051 EPSI 0.0030 LOAD LINE .99.0%
KF MANUAL MOST LIMITING LOCATIONS (NON-SYMETRIC)
MFLCPR~ LOC MFLPD. LOC MAPRAT LOC P-PC LOC 0.900 17 34 1.000 21-12-4 1.011 21 12 4 0.60 21-14-5 0.888 27 18 0.748 11 22 4 0.742 11 22-4 .*0.71 23-16-5 0.888 19 36 0.746 '23-10-4' O.741 23-10-4 0.71 15 24 5 0.886 . 25 20 . 0.744 25-12 4 0.740 25-12 4 -0.73 13-22 5 0.885' 29-20 0.740 11 26 4 0.736 11-26 4 -0.79 21 14-4 0.881 19-32 0.737 9 24-4 0.732 9 24-4 -0.83 15 24-4 0.879 13 0.731 41-44 4 0.729 21 12-5 -0.88 13-22-4 .
-0.877 27 22 0.731 21 12 5 0.726 41 44 4 0.89 23 16 4 0.874 21 34 0.729 43-42-4 0.726 11 22-5 -0.95 21 10-4 0.873 19 14 0.729 11 22-5 0.724 43 42-4 -0.99 25 10-i From the above part'st CMC printout, determine the thermal limit (s) that is (are) being EXCEEDED.
i ANSWER: APLHGR (also accept MAPRAT) l REF: TS 3.2.1; LOS-AA-S1, Core Thermel hydraulic Review TRO: CMC regant lecture K/A: 294001 A1.08 RO: 3.1 SRO: 3.6 1.15 3.2 3.4 j
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, EXAMINATIch KEY DATE: 08/03/89
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EB sam 01 022880 EL8032 LZP 1200-1 TO 1200-4
'1 LicEWSE MASTER QUESTION ADD N0D 1 89C CSEP; RCRA LZP LASALLE EMERGENCY PROCEDURES KA294 .
Plantwide Gencric Objectives (0.75) 23. A feed -iter nemier transient results in the reactor water level droming to eight inches when no automatic scram occurs. The reactor is menuelty scranmed when LGP 3-2 is performed. Classify this event by condition runber and EAL tetter.
ANSWER: Condition 3 [AL *f LZP 1200-1 TK0/TP0 N29400153004 K/A 294001 A1.16 R0 2.9 SRO 4.7 TRD-89:C.5.4 EB RJM: 01-024151 L1 LICENSE MASTER QUESTION ADD EL8031 LZP 1100's LZP LASALLE EMERGENCY PROCEDURES KA294 Plantwide Generic Objectives (0.75) 24. What Is the minimum GSEP classification level which requires that a
$lte Assembly be conducted?
- a. Alert
- b. Unusual Event
- c. Site Emergency
- d. General Emergency
- e. Recovery ANSWER: c. Site Emergency Ref: LZP 1110 1 TP0/TK0 H294001526 KA: 294001 A1.16 2.9/4.7 TRO 89: A.1; C.5.3
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