IR 05000352/1988021
| ML20235Q704 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/17/1989 |
| From: | Conte R, Howe A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235Q702 | List: |
| References | |
| 50-352-88-21OL, NUDOCS 8903030002 | |
| Download: ML20235Q704 (125) | |
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'U.S. NUCLEAR REGULATORY COMMISSION
REGION I
OPERATOR LICENSING REQUALIFICATION PROGRAM EVALUATION
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-REPORT NO.: ' 50-352/88-21(0L)
FACILITY DOCKET NO.: 50-352 FACILITY. LICENSE NO. : NPF-39
- LICENSEE
- Philadelphia Electric Company 2301 Market Street Philadelphia, PA 19101 FACILITY: Limerick Generating Station, Unit-1 EXAMINATION DATES: November 28 - December 2, 1988 EXAMINERS: Todd H. Fish, Operations Engineer Sada V.'Pu11ani, Senior Operations Engineer Don Jarrell, Pacific Northwest Laboratories Dan Moon,. Pacific Northwest Laboratories CHIEF EXAMINER: MGtt3,v 1, n k$
Allen G1 Howe Date Senior Operations Engineer APPROVED BY: b Richard J>stonte, Chief Date M a f
BWR Section, Operations Branch, DRS
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SUMMARY: The licensed operator requalification training program was rated as satisfactory. Written and operating examinations were administered to nine Senior Reactor Operators (SRO) and four Reactor Operators (RO). The examinations were graded concurrently by the NRC and the facility training staff. As graded by the NRC: one of the R0s failed the simulator portion of the operating examination. As graded by the facility: the same R0
- 11ed the simulator portion of the examination. /.11 ettsrs passed all
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nortions of the examinations. All four crews were rated as performing satisfactorily during the simulator portion of the examination.
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REPORT DETAILS An entrance meeting was held with the licensee on October 4, 1988 in the Regional Office. The purpose of this meeting was to brief the licensee on the requirements of the new Requalification Program and to outline a prospective schedule for the week of the examination.
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1. INDIVIDUAL EXAMINATION RESULTS
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Grading l Pass / Fail l Pass / Fail l Pass / Fail l 1 l l l l Written l 4/0 l 9/0 l 13 / 0 l l l l l i j Simulator l 3/1 l 9/0 l 12 / 1 l l l l l l l Walk-Through l 4/0 l 9/0 l 13 / 0 l l l l I l l Overall l 3/1 l 9/0 l 12 / 1 l l l l l l l
l Facility l R0 l SRO l TOTAL l Grading l Pass / Fail l Pass / Fail l Pass / Fail l I I I l l Written l 4/0 l 9/0 l 13 / 0 l 1 l l l l l Simulator l 3/1 l 9/0 l 12 / 1 l l l l l l l Walk-Through l 4/0 l 9/0 l 13 / 0 l l l l l l l Overall l 3/1 l 9/0 l 12 / 1 l l l 1 l l 2. PROGRAM EVALUATION RESULTS 2.1 Overall rating: Satisfactory The program at Limerick for licensed operator requalification training was rated as satisfactory in accordance with the l criteria established in the draft revision of NUREG-1021, ES-601.
Those criteria are:
a. 90% pass / fail decision agreement between the NRC and facility grading of the written and operating examinations.
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'NRC grading resulted in thirteen operators passing the' written
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examination, Limerick grading resulted in thirteen ~ operators
- passing the written examination. This. meets criterion a.-NRC-grading resulted-in twelve operators passing the operating examination,: Limerick-grading resulted in twelve. operators-passing the operating examination. This meets criterion'a.
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b. At least'80%'of all operators' pass the examination.
NRC grading is the only consideration for this criterion.
Twelve of thirteen operators passed the examination overall.
This' meets. criterion b.
c. Failure of. no more than one crew during the simulator portion of the oper'a ting examination.
Again,-NRC grading is the only consideration for this criterion.
Four crews were evaluated and all crews passed the simulator po.rtion of the operating examination. This meets criterion c.
2.2 Programmatic Strengths and Weaknesses The'following strengths and weaknesses were noted either while preparing the examination or while administering the examination.
a. Strengths:
Ability of the facility instructors to identify crew ard individual strengths or weaknesses demonstrated during a scenario and identifying these duringl post-scenario critiques with the' crew and individual.
b. Weaknesses i The facility did not train and evaluate operations SR0's as R0's. The facility did not evaluate staff SR0's as R0's although they were trained as R0's. These practices show an inconsistent approach to training and evaluation of SR0's to perform all of their licensed duties (i.e. direct the manipulation of controls and manipulate controls).
The facility did not effectively control the time which the candidates had been given for completing the open-reference portion of the exam. This resulted in one group taking about one hour more than the two groups which followed.
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W-4-2.3 : Generic-Strengths and Weaknesses a. . Simulator portion of the exam:
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Strengths All crews demonstrated proficiency'in use.and knowledge of JTechnical Specifications and the Emergency Plan. They were also quick to recognize entry conditions into emergency procedures as well as symptons of plant casualties and equipment rr. malfunctions.
Overall, procedure use was good.
Weaknesses During implementation of T-102, Containment Control, there'was an inconsistency between the'SR0's on when to execute Step DW/P-5. This step states "Before suppression pool pressure reaches 10 psig, spray the suppression pool." Some operators *
interpreted (incorrectly) that the term "before" meant they should NOT initiate sprays in situations where suppression pool pressure had already exceeded 10 psig.
While crew communication was satisfactory during minor
- transients, there tended to be many communication breakdowns during major transients. Operators did not always acknowledge or carry out orders, orders were not given to a specific operator, more than one operator talked at a time, and annunciators were not silenced.
The approach of the role of each operator varied from crew to crew. Some crews had the R0 remain at his console'at all times while other crews allowed the R0 to aid in ECCS manipulations.
On some crews, the Shift Supervisor (SSV) controlled all actions with the Shift Superintendent (SST) simply making any required-notifications. On other crews, the SST was much more involved with shift activities, including control board manipulations.
b. Walk-through portion of the operating exam (JPM's):
Otrengths Candidates were proficient in knowledge and use of procedures j and demonstrated good familiarity with systems that were i operated from the Control Room. j l
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i-5-Weaknesses When asked-to manually. initiate Alternate Rod Insertion operators, were slow to locate the appropriate cabinet bays and slow to. select
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. the correct keys necessary to open those cabinets. Also, when asked to locally 69-energize .the scram solenoids, operators.were slow in
, locating the ccerect_cabir.et containing the fuses for doing this as well as identifying which fuses would be pulled.
Four of eight' operators-(2 R0s and 2 SR0s) did not know that a. a control rod would not scram from reactor pressure'alone if reactor
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pressure was 300 psig.
c. Written exam:
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One weakness was identified. The facility used severa1 examination questions which were not supported by any learning
. objectives. Examination questions are expected to be supported by facility learning objectives.
3. PERSONNEL ATTENDING EXIT MEETING DECEMBER 5, 1988 NRC Personnel D. Lange, Chief, BWR_Section, DRS
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A.-Howe, Senior Operations Engineer T. Fish, Operations Engineer L. Scholl,. Resident Inspector Limerick Personnel M. McCormick, Plant Manager W. Sokso, Licensing L. Hopkins, Assistant Superintendent, Operations E. Firth, Superintendent, Training R. Hampton, Shift Training Administrator R. Nunez, Supervisor, Operations Training S. Dufort, General Physics 4. SUMMARY OF COMMENTS MADE AT EXIT MEETING The Chief Examiner thanked the licensee training and operations staff for their participation in the examination. >
Access to the site was very smooth; no delays were experienced. The Examiners noted that plant housekeeping was good. j
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-6-Examination development and. examination conduct, generic strengths and weaknesses noted during the exam process, and programmatic strengths and weaknesses were discussed.-
The licensee committed to (1) clarifying procedur9 T-102, (2) improving the. human factors to help the operators locate.the cabinets and fuses involved with procedures T-214 and T-215, and (3) having learning objectives for all open-reference-questions used on future exams. The corrective' actions it has initiated are
. described in two letters to the Region, which'are Attachments 6 and 7
.to this report.
Attachments:
Simulator Examinations (cover sheets only)
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2. Job Performance Measures (cover sheets only)
3. - Written Examination' and Answer Key (RO)
4. Written. Examination and Answer Key (SRO)
5. Facility Examination results 6. Licensee Letter. dated December 16, 1988 from M. J. McCormick to A. G. Howe.
7 Licensee Letter dated December 23, 1988 from E. G. Firth to D. J. Lange.
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PHILADELPHIA ELECTRIC COMPANY -
LIMERICK GENERATING. STATION SIMUIATOR EXAMINATION SCENARIO Scenario Number:'SES-l'
'Date:
I. - BRIEF DESCRIPTION OF SCENARIO-A. The simulator will,be initialized to IC 11~ 1004 power, MOL,."B" CRD
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pump is Inoperable and HPCI surveillance is scheduled for the shift.
B. The scenario contains the following evolutions / malfunctions:
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1. HPCI surveillance with subsequent failure.
2. Loss.of "Ba Condensate Pump.
3 .' Loss of 13.2 KV bus 11. 'Resulting in a loss'of normal feed'to the reactor.
4 '. Failure of RCIC to auto start. '
C. ' Terminate the scenario'when reactor level has been stabilized above-161" and all emergency plan declarations have been made.
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" PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION SIMULATOR EXAMINATION SCENARIO'
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. Scenario Number: SES-3 Date:
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,. A. The simulator will be initialized to IC-11,.1004 power, MOL,_("C" N
Service Water Pump is designated "For Emergency: Use Only" due to abnormal noise generation while the pump is running) and power decrease per GP-3.is to commence due to both MSIV-LCS subsystems inop.
B. The scenario contains the following evolutions / malfunctions:
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1. 1 Power decrease per.CP-3 2. "A" EHC pressure regulator oscillation 3. Steam'line rupture in the drywell-4. ."A" RHR pump trip C..
Terminate the scenario when the RPV'is depressurized with all primary containment parameters indicating an improving trend and all emergency
. plan notifications have been made. '
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LIMERICK GENERATING STATION SIMUIATOR EXAMINATION SCENARIO Scenario Number: SES-4 Date:
I. BRIEF DESCRIPTION OF SCENARIO-A. The simulator will be initialized to IC-11, 100% power, MOL, "B" drywell chiller is blocked.
B. The scenario contains the following evolutions / malfunctions:
~A. "l. " 2a;ia y y :;;.2:::: ?! M ?r- '-- ' rip.
/. . #, Restart of the "A" Recirc pump.
2, R Failure of jet pumps # and # # '"
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3. 9/esm lea n in t he Oryws ll C. To minate the scenario when SST notifications are complete.
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LIMERICK GENERATING STATION SIMULATOR EXAMINATION SCENARIO Scenario Number: SES-6
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Date:
I. -BRIEF DESCRIPTION OF SCENARIO:
A. The simulator will be' initialized to IC-17, 100% power, EOL, "B" CRD pump.is. inoperable, and rod exercise testing is scheduled for the shift.
B. 'The scenario contains the following evolutions / malfunctions:
'1. Rod exercise test 21 Multiple stuck rods 3. "A" CRD pump trip C. Terminate the scenario post-scram, with efforts directed toward inserting the stuck rods.
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R:v. O JES/lal-Page'1 of 27 PHILADELPHIA ELECTRIC COMPANY-LIMERICK CENERATING STATION SIMUIATOR EXAMINATION SCENARIO Scenario Number: 'SES-8 Date:
I. BRIEF DESCRIPTION OF SCENARIO:
A. The simulator will be initialized to IC-11, 100% power, BOL with transferring D12 safeguard bus to the alternate power supply scheduled for the shift.
B. The scenario contains the following evolutions / malfunctions:
1. Transfer D12 safeguard bus to the alternate power-supply 2. "B" recire pump #2 seal failure 3. Steam leak in the drywell C. Terminate'the scenario when RPV parameters are stabilized and all actions per T-102 have been carried out.to stabilize Primary Containment.
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PHILADELPHIA ELECTRIC COMPANY
. LIMERICK GENERATING STATION SIMULATOR EXAMINATION SCENARIO
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~ Scenario Number:.SES-10 Date: i I. BRIEF DESCRIPTION OF SCENARIO:
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The simulator will be initialized to IC-ll, 1004 power, MOL, with a.
. suppression pool temperature of 93*F. Reduction of suppression pool temperature is expected to be done during the shift.
B. The scenario'contains'the following evolutiens/ malfunctions:
1. Reduction of Suppression Pool temperature 2. Single inward. control rod drift-y 3. Fuel element failure 4. NSSSS Group 1 isolation on-3XNFPBG.due to low setpoint C. Terminate the scenario when RPV parameters are stabilized and RPV depressurization is commenced, i
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II. BRIEF DESCRIPTION OF SCENARIOi A. The simulator will beLinitialized to'IC-17, 100% power, EOL, "B" instrument air compressor tagged out'for-maintenance and "A" core spray surveillance scheduled for the shift.
B. The scenario contaiss the following evolutions / malfunctions:
.1. "A" Core Spray surveillance. test with' subsequent trip of "A"-core-spray pump
'2. '"B" recire pump seizure _due to high vibration
'3. Recire Loop Failure (double-ended shear)
4 A RHR OUTBD injection valve fails to open
- C. ' Terminate the scenario when reactor water level has been' stabilized-above -161" and all emergency plan declarations have been made.
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.Page 1 of 26 PHI 1ADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION SIMULATOR EXAMINATION SCENARIO
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l Scenario Number:'SES-12 Date:
I. BRIEF DESCRIPTION OF SCENARIO:
A. The simulator will'be initialized to 10-11, 1004 power, MOL'with removal of.the'"A" CRD pump from service for maintenance scheduled on-this shift.
.B. The scenario contains the following evolutions / malfunctions:
1. Shift CRD pumps for maintenance.
2. RPS/NSSSS level transmitter fails low 3. RPS and ARI fail.to produce a reactor scram.
'C. : Terminate the' scenario when all emergency plan declarations have been made and reactor power is in the source range.
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- LIMERICK GENERATING' STATION
- ) .- SIMUIATOR EXAMINATION SCENARIO y
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Scenario Number: SES-13
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.Date:
l b I. BRIEF DESCRIPTION OF' SCENARIO!
A .' _ The simulator will be . initialized to IC-20, 80% power, MOL with the. "C" RWCU pump'inop for: maintenance.
B. The scenario ~contains thi following evolutions / malfunctions:
l'. "A" RWCU pump trip.
2. Restore-RWCU to normal'2 pump' operation:
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Main Steam.Line High Radiation' Trip
.C. . Terminate the scenario when the RPV pressure, levels and containment parameters have stabilized and all Emergency Plan Declarations have
'been made.
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ATTACHitENT 2 LOJPM-02
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i Philadelphia Electric Company '
Limerick Generating Station Licensed Operator Job Performance Measure
Title: Scram Reset Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
f Directions to Operator:
When I tell you to begin, you are to perform a Scram Reset. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 minutes Importance Rating: System Number:
3.8 K/A 212000 I Task Conditions:
1. RPS Deenergized on Turbine Trip from 40% Rx power -
2. Plant stabilized in OPCON 3 with RPV level at +32" and T-100 is complete 3. All scram valves open, SDV vent and drain valves shut 4. CRD pump operating ;
5. Normal Electrical Distribution available 6. GP-ll prerequisites satisfied General Tools and Equipment:
Key for SDV High level bypass switch.
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.LOJPM-3 (- Rov. 0,'7/25/88
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' Philadelphia Electric Company L Limerick Cenerating Station Licensed Operator' Job Performance Measure.
l Title: Manually Initiate Core Spray System'
Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
- Directions'to Operator
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When I tell you to begin, you are to manually initiate Core Spray. I will describe general conditions 'and provide you access: to the tools to complete this task. Before you' start, I will state the task standards and initiation cues and answer any questions.~ Successful completion of this task will'
require you to correctly perform or simulate each critical element.
Evaluation Method:
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Perform Simulate. 1
Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
6 minutes Importance Rating: System Number:
3.8 K/A 209001 Task Conditions:
1. -Reactor has scrammed, all rods inserted.
2. Reactor vessel water level is -100 inches.
3. RPV pressure is 300'psig.
4. .Drywell pressure is 1.00 psig.
Ceneral Tools and Equipment:
None l
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LOJPM-04 Rev. O, 7/28/88 WMT/dm Page 1 of 4 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: Perform a Group 1 NSSSS Isolation Reset Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to perform a Group 1 Isolation Reset.
I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and Initiating cues and answer any questions. Successful completion of this task, will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
8 minutes Importance Racing: System Number:
3.6 K/A 223002 Task Conditions:
1. Group 1 NSSSS Isolation signals cleared 2. Switches HSS-57-191A, HSS-57-191B, HSS-57-1916, HSS-57-191b in
" NORMAL" General Tools and Equipment:
None
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LOJ PM-6 Rsv. 0,,7/27/88 JES/lal Page.1 of 5 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: Manually Initiate SBLC Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
' Directions to Operator:
When I tell you to begin, you are to manually initiate the SBLC system. 'I will describe general conditions and provide you access to the tools to-complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of.this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room i Approximate Completion Time:
5 minutes Importance Rating: System Number:
4.2 K/A 211000 Task Conditions: i
1. SBLC system setup per S48.1.A 2. SBLC injection required by T-101 3. Suppression Pool temperature is 107'F 3 4. Main Turbine tripped, reactor power is 47%
General Tools and Equipment: )
Keys for keylock controls l
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LDJPM-7 Rcv. O, 7/27/88 WMT/lal Page 1 of 6 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: Transfer House Loads to the Unit Auxiliary Transformer Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to transfer House Loads to the Unit Auxiliary Transformer. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
5 minutes Importance Rating: System Number:
3.6 K/A 262001 Tasks Conditions:
1. 11 and 12 Unit Auxiliary Buses powered from offsite sources.
General Todls and Equipment:
Synchronizing switch removable handle
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1DJPM-8 R2v. 0,.7/27/88 WMT/lal~
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Philadelphia Electric Company Limerick Generating Station-Licensed Operator' Job Performance Measure lt Title: Perform a Remote Manual Start of the D12 Diesel Generator and Load it to-2000 KW
. Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell.you to begin, you are to perform a remote manual start of the D12 Diesel Generator and load it to 2000 KW. I will describe general conditions and provide you a'ccess to the tools to complete this task.
Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
15 minutes Importance Rating: System Number:
3.7 ,
K/A 264000 Task Conditions:
1. Procedure S92.1.0 completed up to and including step 8.3.1 2. D12 Safeguard Bus supplied from 201 Safeguard Transformer General Tools and Equipment:
Synchronizing Switch Removable Handle
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Rav. 0, 7/28/88 L . JAG /lal Page 1 of~6 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure iTitle: ~ Manually Start HPCI.
Operator.: (RO/SRO)' Evaluator:
Evaluator Signature: Date:
Directions to Operator:
- When:1. tell you to begin, you are to. place the HPCI system in service using the quick start method to control reactor pressure. ;I will describe general-conditions and provide you accessLto the-tools to complete this task.
Before'you start,' I will state'the task standards and initiation cues'and-answer any' questions; . Successful completion of this-task will require you to correctly-perform or simulate each critical-element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate' Completion Time:
10 minutes Importance Rating: System Number:
4.0 K/A 206000 Tasks Conditions:
1.
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Reactor scram has occurred accompanied by an MSIV isolation.
2. SRV's are cycling to control reactor pressure.
3. Suppression Pool cooling is in service.
4 All prerequisites are met. ,
General Tools and Equipment: (
None
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LDJPM-10 R v. O, 7/28/88 TGF/lal Page 1 of 5 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: Secure LPCI Following an Automatic or Manual Initiation l
Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Ditections to Operator:
When I tell you to begin, you are to secure LPCI following an automatic or manual initiation. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
5 minutes Importance Rating: System Number:
3.9 K/A 203000 Tasks Conditions:
1. ' Reactor scrammed, all rods inserted.
2. RHR System is operating in LPCI mode.
3. Reactor pressure is 200 psig.
4. Drywell pressure is 1.0 psig.
5. Reactor water level is 50 inches.
General Tools and Equipment:
None
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LOJPM-12
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Rev. O, 8/1/88 TGF/lal Page 1 of 5 Philadelphia Electric Comprny Limerick Generating Station Licensed Operator Job Performance Measure Title: Conduct ADS Valve Test Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to operate ADS valves per ST-6-050-760-1.
I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 minutes Importance Rating: System Number:
4.4 KA 218000 Tasks Conditions:
1. Reactor pressure is 550 psig.
2. The generator is off-line, 3 Main Steam Bypass valves are open.
3. Suppression Pool Level is 23'-0" and Suppression Pool temperature is l 85'F.
4. RHR is operating in the Suppression Pool cooling mode, General Tools and Equipment: i'
i None
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j LOJPM- 16 -
R2v. 0, 8/16/88~
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JAG /lal Page'l'of 5-I t
Philadelphia Electric Company
,
" Limerick Generating Station
.
Licensed Operator' Job Performance Measure Title: Shutdown of an Operating Diesel' Generator
. Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
'i Directions.to' Operator:
When.I tell you to begin, you.are to shutdown'the selected operating diesel-generator.. I will describe general conditions'and provide you~ access to the tools to complete,this. task. Before you start, I will' state'the task standards and initiation cues and answer any questions. Successful-completion of this task.will require you to. correctly perform or simulate each critical element.
. Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
15 minutes Importance Rating: System Number:
3.7 -264000 Tasks Conditions:
1. The diesel generator has been operating in parallel with the safeguard bus for one and one half hours at 2000 KW and is to be shutdown from the control room General Tools and Equipment:
None
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LDJPM-17 Rev. O, 8/2/88 WMT/lal Page 1 of 6 Philadelphia Electric Company
Limerick Generating Station Licensed Operator Job Performance Measure Title: Place RHR' Loop A in Suppression Pool Cooling Operator: (RO/SRO) ' Evaluator:
Evaluator Signature: .Date:
Directions to Operator:
. When I tell you to begin,'you are to place.RHR Loop A in Suppression Pool Cooling. I will describe general conditions and provide you access to the tools to' complete this task. Before you start, I will state the task standards and initiation cues and answer'any' questions. ' Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform _ Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 minutes Importance Rating: System Number:
3.9 K/A 219000 Tasks Conditions:
1. RHR lined up per $51.1.A 2. RHR Service Water available General Tools and Equipment:
None
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10JPM-18 Rsv. O, 8/18/88 JAG /lal Page 1 of 5'
Philadelphia Electric Company.
Limerick Generating Station Licensed Operator Job. Performance Measure
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-Title: Manual ~ Initiation of Redundant Reactivity Control System (RRCS)
Operator: (RO/SRO)- Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to manually initiate RRCS. I will describe general conditions and provide you access to the tools-to complete this task. Before you start, I will state the task' standards and initiation cues and answer any. questions. Successful completion of this task will~
require you to correctly perform or simulate each critical. element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
5 minutes Importance Rating: System Number:
4.4 212000 Tasks Conditions:
1. The reactor has received a valid scram signal.
2. . Reactor power is 45%.
3. Recire pumps tripped, turbine on line, RPS not deenergized.
General Tools and Equipment:
None l
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LOJPM-22
.Rav. O, 8/4/88 TGF/lal Page 1 of 5 Philadelphia Electric' Company Limerick Generating Station Licensed Operator Job Performance-Measure Title: Resetting a 75% Recirculation System Runback Operator: (RO/SRO) Evaluator:
Evaluator Signature: 'Date:
Directions to Operator:
When'I tell<you to begin, you are to resec'a 75% Recirculation System runback. I will describe' general conditions.and provide'you access-to the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant. Simulator X., Control Room Approximate Completion Time:
5 minutes Importance Rating: System Number:
3.7 K/A 202001 Task Conditions:
1. Plant was operating at 100% when a condensate pump was inadvertently tripped.
2. Received a 75% Runback of Recirculation.
3. Condensate pump has been returned to service General Tools and Equipment:
None l
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'LOJPM-26
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Rev. O,'9/20/88 APY/cmk Page 1 of 5
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Philadelphia Electric Company
.. Limerick Generating Station-Licensed Operator Job Performance Measure.
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. Title: Manually Initiate Refuel' Floor Secondary Containment Isolation 3. . lOparator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to~0perator:
LWhen I tell you to begin, you are to manually initiate a Refuel' Floor!
~
-Secondary. Containment Isolation and verify completion of the isolation. I
-
will describe general' conditions and provide you access to.the toolsLto; completeethis task.
Before you start,.I,will state the task' standards and initiation cues and answer any' questions.. Successful completion of this.
task will require you to correctly perform or simulate each critical
. element.
Evaluation-Method:
Perform X Simulate Evaluation Location:
Plant Simulator X Control Room Approximate Completion Time:
5 Minutes Importance Rating: System Number:
3.9 223002 Task' Conditions:
1. Refueling Operations are in Progress 2.
3. -Refuel Floor Ventilation Exhaust Radiation Level is 2.4 mR/hr j Refuel-Floor Ventilation in Normal, Unisolated Configuration J Genaral Tools and Equipment:
)
None
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iDJPM-27 Rsv. 0, 8/08/88 c WMT/lal'
Page 1 of 5
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Philadelphia Electric Company L Limerick Generating Station I Licensed Operator Job Performance Measure Title: Recouple an Uncoupled Control Rod Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date: .
Directions to Operator:
When 1.te11 you'to begin, you are to recouple an uncoupled control rod.
,
I will describe general conditions and provide you accessEto the tools to complete this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you'to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate-Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
5 minutes Importance Rating: System Number:
3.5 K/A 201002 Tasks Conditions:
1. Plant startup in progress.
2. The first rod in RWM GP-2 is fully withdrawn (Rod 02-31).
3. " Rod Overtravel" annunciator illuminated.
4. " Rod Drift" annunciator illuminated.
General Tools and Equipment:
None
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LOJ PM- 28 ' .
Rev 0,-8/4/88
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JES/lal Page 1 of- 4 l
Philadelphia' Elect'ric Company Limerick Generating Station Licensed Operator Job Performance Measure L
L l
Title: Lower Suppression Pool Level Using T-233
- Operator: (RO/SRO) Evaluator:
L Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to. reduce suppression pool inventory intof the normal band using T-233. .I will describe general conditions and provide you access to the tools to complete this task. Before you start. I will state the task standards and initiation cues and answer any questions.
Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform X Simulate Evaluation Location:
Plant Simulator X Control Room Approximate Completion Time:
15 minutes
.fmportance Rating: System Number:
3.9 K/A 219000 Tasks Conditions:
1. Drywell Pressure: 1.0 psig 2. RPV Level: 32 inches 3. Suppression Pool Temperature: 91*F 4 Suppression Pool Level: 24'6" 5. .T-233 prerequisite conditions are met General Tools and Equipment:
None
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'LOJPM-291 L"
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.Rsv. 0, 7/28/88 d'
' JAG /lal Page-1Lof-5 Philadelphia' Electric Company; Limerick Generating Station
.. v Licensed Operator Job Performance Measure
"
! Title: ' Shift:HPCI" Suction From the CST to.the Suppression-Pool l
' Operator: (RO/SRO) Evaluator:
-Evaluator Signature: Date:
Directions to Operator:
' Suppression Pool. ;I.will describe general' conditions and provida-you access to the. tools'to. complete,thisitask. ~Before you start, I will state.the" task:
standards and initiation cues and answer any questions. . Successful
~ completion of this task'will require you to' correctly perform or simulate each critical' element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate. Completion Time:
15 minutes
,Importance_ Rating: System Number:
3.7 206000 Task Conditions:
1. HPCI.is operating in the full flow test mode from CST.to-CST pressure General Tools and~ Equipment:
None
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LOJPM-33 ,
R v. O, 8/16/88 !
TGF/lal. ;
Page 1 of 5 i PhiladelphiaLElectric Company Limerick Generating Station-Licensed Operator Job Performance Measure j
Title: ' Place "A" RHRSW.in Service From the Remote Shutdown Panel (RSP)
Operator: TRO/SRO) Evaluator:
Evaluator Signature: Date:
Directions.to Operator:
When I tell you to begin, you are to place "A" RHRSW in service from RSP.
I will. describe general conditions and provide you access to the tools to complete.this task. Before you start, I will state the task standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
7 minutes Importance Rating: System Number:
3.9 K/A 295016 Tasks Conditions:
1. The Main Control Room in uninhabitable due to toxic gas.
2. The plant is being controlled at the Remote Shutdown Panel.
3. The reactor is shutdown, level is being controlled using RCIC, and pressure is controlled using A, C, and N SRV's as necessary.
General Tools and Equipment:
None
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i hI' LOJPM-62 Rev. O, 9/21/88 MDB/cak Page 1.of-4 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure
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Title: "B" ESW Pump Start from 4 KV Emergency Switchgear -
Operator: (RO/SRO)
i Evaluator:
. Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to start the "B" ESW Pump from the 4 KV Emergency Switchgear. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I.will state the task standards and initiation cues and answer any questions. Successful completion of this task will'rsquire you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate
' Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 Minutes Importance Rating: System Number:
3.1/3.2 295016 AA1.04 Task Conditions:
Plant in hot shutdown, cooldown is desired, the Main Control Room has been evacuated, and Shift Supervision directs operator to start the "B" ~
ESW Pump from the 4 KV Emergency Switchgear.
Ganeral Tools and Equipment:
None Ganeral References:
1. SE-6, Rev. 2, Alternate Remote Shutdown
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LOJPM-63 Rev. O, 9/22/88 MDB/cmk Page 1 of 4 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: Individual Control Rod' Scram / Solenoid De-Energization Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to perform a single rod scram of control rod 30-07. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task
.,.
standards and initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element.
. Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 Minutes Importance Rating: System Number 3.9/4.0 K/A 295037 Task Conditions:
1. Scram condition with reactor power above 4% or unknown.
2. Failure of scram valves to open.
4, You have been directed to perform a single rod scram of control rod 30 07 per T-213.
General Tools and Equipment:
None
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LOJPM-64 Rev. O, 9/22/88 MDB/cmk Page 1 of 4 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure Title: De-Energization of Scram Solenoids Operator: (RO/SRO) Evaluator:
-Evaluator Signature: Date:
Directions to Operator:
When I tell you to begin, you are to perform a full core scram by de-energizing the scram solenoids from the Aux. Equipment Room. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and anstrer any questions. Successful completion of this task will require you to correctly perform or simulate each critical element. ;
'
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
10 Minutes Importance Rating: System Number:
4.6 295037 EAl.01 Task Conditions: 1 1. Reactor power above 4% or unknown with scram condition.
2. Scram valves closed.
3.
You have been directed to perform a full core scram by de-energizing the scram solenoids, per T-215.
Gsneral Tools and Equipment:
Fuse removal tool
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b LOJPM-69 m
'R:v.~0, 9/22/88
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MDB/cak'
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Page 1 of 4 f-l.
I Philadelphia. Electric Company
.
. Limerick Generating Station
' Licensed. Operator Job Performance Measure-Title: Local Manual Startup of a Diesel Generator-(<
-Operator: (RO/SRO) Evaluator:
Evaluator Signature: ' Date:
' Directions.to Operator:
,
When I tell:you.to begin, you are to start a Diesel Generator locally. I wi11' describe general conditions and provide you access to the. tools to complete this task. .Before you start, I will state the task' standards and
' initiation cues and answer any questions. Successful completion of this task will require you to correctly perform or simulate each critical
' element.
. Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate-Completion Time:
10 Minutes Importance Rating: System Number:
3.6 262001 Task Conditions:
- l'. Main Control Room Abandoned 2. Remote Shutdown Panel inaccessible General Tools and Equipment: .j j
None J General References:
1. S92.1.0, Rev. 3, Local Manual Startup of a Diesel Generator Task Standards:
Diesel Generator running at approximately 900 rpm from a local manual start.
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LOJPM- 72 Rev. O, 9/23/88-HDB/cmk.
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Page 1 of 4 Philadelphia Electric Company Limerick Generating Station Licensed Operator Job Performance Measure i
' Title: Manual Initiation of ARI Operator: (RO/SRO) Evaluator:
Evaluator Signature: Date:
\;
,Dir'ections to Operator:
.
When I tell you to'begin, you are to perform a manual initiation of ARI. I
. ,
will describe general conditions and provide you access to the-tools to complete this task. Before you start, I will state the task standards and initiation c tes and answer any questions. Successful completion of this-task will require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
Plant Simulator Control Room Approximate Completion Time:
5 Minutes
]s Importance Rating: System Number:
4.1 295037 Task Conditions:
1. Scram condition with reactor power above 4% or unknown
'2. .Fpilure of scram valves to open 3. You have been directed to manually initiate ARI per T-214.
. Ceneral Tools and Equipment:
Utility Key 208 (2)
i General References: ,
1. T-101, Rev. 2, RPV level control ;
2. T-214, Rev. 1, Manual Initiation of ARI
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a LOJPM-73 Rev.-0, 9/22/88.
HDB/cmk
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Page 1-of 51 Philadelphia Electric Company. "
Limerick Generating Station Licensed Operator Job Performance Measure Title: Wide Range Accident Monitor Channel Value and Trend Determination from Panel 00C691-a Operator: (RO/SRO) Evaluator: ;
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l' Evaluator Signature:' Date:
_ Directions to Operator:
When I tell you to begin, you are to obtain the most recent North Stack Total Effluent Channel value and the most recent hourly trend value. I will describe general conditions and provide you access to the tools to complete this task. Before you start, I will state the task standards and initiation cues and' answer any questions. Successful completion of this task will n
. require you to correctly perform or simulate each critical element.
Evaluation Method:
Perform Simulate Evaluation Location:
,
Plant Simulater- Control Room Approximate Completion Time:
10 Minutes
'
Importance Rating: System Number:
3.6/3.5 K/A 272000 3.6/3.8 K/A 295017 Task Conditions: ;
1. ' Wide Range Accident Monitor (RIX26-076A) in service, 6HD >
2. RM-11 consolo is unavailable and North Stack Radioactivity Release in progress.
Ganeral Tools and Equipment:
)
None
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LOJPM-76 . j Rev. O, 9/26/88 j RAN/cmk 4
, Page 1.of'4 )
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Philadelphia Elec'tric Company Limerick Generating Station Licensed. Operator Job Performance Measure. {
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Title: Manual Operation of Scoop Tube Positioner
L Operator: (RO/SRO) Evaluator:
Evaluator. Signature: Date:
l Directions'to Operator:
When I tell you to begin, you are to decrease Recirculation pump speed 46 ;
rpm by manually positioning the. scoop tube. I will describe general '
conditions and provide you access to the tools.to complete this task.
Before you start, .I will state the task standards and initiation cues and answer any questions.
_
Successful completion of this task will require you to correctly perform or simulate each critical element.
Evaluation Method:
-Perform Simulate Evaluation Location:
Plant Simulator '
Control Room Approximate Completion Time:
.
14 minutes.
Importance Rating: System Number: I 3.1 202002 Task Conditions:
1. Scoop Tube Control Room M/A Station inoperable 2. Recirculation flow decrease required Gsneral Tools and Equipment:
Scoop, tube handcrank ,
G neral References:
1. S43.7.A, Rev. 4, Manual Operation of Scoop Tuber Positioner i
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[ _ ATTACHMENT 3.
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' REACTOR OPERATOR REQUALIFICATION EXAMINATION L
. FACILITY: LIMERICK GENERATING STATION REACTOR TYPE: GE-BWR 4 DATE ADMINISTERED:
OPERATOR:
NOTE TO' OPERATOR A grade .of 80% overall for Sections A gnsl'B combined is the standard for successful completion of the written examination, t OF SECTION CATEGORY OPERATOR'S CATEGORY VALUE SCORE VALUE
.A Plant. Proficiency
.B Limits and Controls Total Final Grade All work done on this examination is my own. I have neither given nor received aid.
Operator's Signature
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LCS - NUCLEAR TRAINING SECTION RULES AND CUIDELINES FOR ANNUAL LICENSE OPERATOR REOUALIFICATION EXAMINATIONS During the-administration of this examination the following rules apply:
1. Cheating on the examination means an automatic failure of your examination and could result in more severe penalties.
2. Restroom trips are.to be limited and only one candidate at a time may leave the room. You must avoid all contact with anyone-outside the examination room to avoid even the appearance or possibility of cheating.
I 3. Use black ink or dark pencil galy to facilitate legible reproductions. '
4. Print your name in the blank provided on the cover sheet of the examination.
5. Fill in the date on the cover sheet of the examination (if necessary).
6. Use'only the paper provided for answers.
7. Print your name in the upper right-hand corner of each page'of the answer sheet.
8. Consecutively number each answer sheet.
9. I Skip at least three lines between each answer.
10. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
11. Use abbreviations only if they are commonly used in facility literature.
12. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
<
13. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not. Calculators are authorized for use if desired.
14. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION 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.
16. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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17. k'h n y:u complets y:ur cxaminatien, y:u chall:
a. Assemble your examinations as follows:
,
(1) Exam questions on top.
?
(2) Exam aids - figures, tables; etc.
(3) Answer pages including figures.which are part of the answer..
b. Turn in your. copy.of the examination and all pages used to answer the examination questions.
c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
d. Leave the' examination area, as defined _by the examiner.
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SECTION A: PLANT PROFICIENCY'
SCENARIO'1 REACTOR. OPERATOR-
-
SIMULATOP OPERATIONS SlMMARY SHEET 1. Plant' initially operating at 1006 power.
-
2. . Equipment known to be inoperable at beginning of.the' scenario: NONE
'3. Simulator differences which. affect'the exam:
l . .
a. All annunciator panels ' displaying an "F" cannot' be used as indication, On these panels ' the - annunciators making the "T" will be On and 'all others Off regardless.of plant conditions.
b. Do not use the Off/ Gas' system lineup for indication,.-Off/ Gas is not i . operational in the simulator.
4 l Operator actions.taken in the scenario: NONE 5. The RPS first in annunciator was'" Turbine Stop Valve Closure Trip".
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iJ SECTION A: PLANT PROFICIENCY EXAM SCENARIO 1
' EXAMINER-INSTRUCTIONS
'
l. BRIEF hi3CRIPTION OF' SCENARIO:
A. Simulator Status:
1. The simulator was initially set to IC-ll, 100% power. The following' Malfunctions / Remote Functions will be used:
a. MAL-261 Loss of Offsite Power b. MAL-453 HPCI Injection to Feedwater, F105 Valve, fails as is c. ' MAL-455 HPCI Lube Oil Cooler Inlet Valve, F059, fails as is d. MAL-90,A ESW Pump Trip "A" B. Examinations will be made up of:
1. . Rules and Guidance for Examinees 2. Simulator Operations Summary Sheet 3. RO and SRO Exams (Questions and Answer Key)
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EXAMINER INSTRUCTIONS (cont'd)
SCENARIO 1 Static Simulator Setup and Validation 1. Setup A. Reset the'aimulator to IC #11.
B.
Rotate all chart recorder a minimum of 3 inches and ensure sufficient paper for the examination.
C.
Insert malfunctions / remote functions as described below.
(Note: After scram place the Mode Switch in shutdown.)
Time Malfunction Desired Parameter Value ._
I 0000 l MAL-455 HPCI Lube Oil Cooler I
.l Valve remains shut following l l Inlet Valve, F059, fails as is l HPCI initiation l 1 1 0000 l MAL-453 HPCI Injection Valve I l Valve remains shut following l l to Feedwater, F105, fails as is l HPCI initiation l l
0003 l MAL-261, Loss of Offsite Power 1 l
[ Diesels all start and pick up l l their respective buses l I
I 0005 l MAL-90,A Trip of the "A" I $
l "A ESW PUMP MOTOR OVERCURRENT" l l ESW Pump l alarm l
1 I I I
i D.
Display Special Log 3 on one CRT and Control Rod Position on another CRT.
E. At the desired Rey Parameter Values Freeze the simulator and secure recorder power and place Mode Switch in "RUN".
s
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e '
EXAMINER ' INSTRUCTIONS ;- (cont ' d) .
[; >
SCENARIO 1.
O ff, ':II Validation' .
, A.
" For the following examination,ethe.following parameters must.be'in the# 9
- allowed band.
Xt
"
Critical Parameter Allowed Band'
. ,
l l
'
Reactor Vessel. Level l -39" to -50"' l I l-
. Reactor Pressure -l 700 psig.to 750 psig l
'l I-Instrument Gas l OFF
. compressors l l- l l .
I Dies ~els -l Running' supplying their'
..
l l- respective buses l
"A" ESW Pump I
.
l.' _
Tripped.. l'
l' '
I HPCI
.
i
.l'. Running.with F105:and F059 -l l. closed l.
l RCIC.
.
l-
,
l Running l L
' l' l l
-B, check,all-traces and. parameters'.for reasonable values and trends for
. existing simulator conditions.
C.
If any critica1' parameter is outside the " Allowed Band", the simulator must be reinitialized, st' art at Step I.A.
D,
'If all' indications are satisfactory, the exam may begin,
,
,
..t,
_ _ _ _ _ _ - _ _ _ - _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
g,
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Rl" ES AND CL'IDANCE FOR ' EXAMINEES
.w 1". Use. blank ink or dark' pencil ONI.Y to facilitate le ible. reproductions.
2. Frint your name in.the' blank provided on the cover sheet of=lthe examination.
3. Till in the date on the cover sheet of the examination, if~necessary.
4 Use only the lined paper provided by the examiner.
5. Use abbreviations only if they are commonly used'in facility literature.
.6. The point value for each. question is indicated in parentheses after the question and can be used as a guide'for the depth of answer required.
7. 'Show all calculations, methods, or assumptions used to obtain an answer to a';
mathematical problem, whether asked for in the question or not.
Unless solicited, the location of references need'not be stated.
'
8.
9. Partial credit may be given. Therefore, ANSUER A1.1. PARTS'0F THE QUESTION AND DO NOT 1. EAVE ANY ANSUERS BLANK.
10. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
11'. You must sign the statement on the cover sheet.that indicates.the work on .
the examination is your own and that you have not rkceived or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
12. Rest room trips are to be limited.dnd only one examinee at a time may leave.
You must avoid all contact with anyone outside the examination room to avoid even the. appearance or possibility of examination compromise.
'
13. ' Cheating on the examination can result in a revocation of your license and could result in more severe penalties.
14. Each section of the examination is designed to take approximately 90 minutes to complete. You will be S i ven two hours to complete each section for a total of four hours.
15. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
16. Enen you are finished and have turned in your completed examination, leave the examination area.
- .. --. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _
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,. 4 ,
p l SECTION-A:~ -PIANTPROFICIENCh.
! i SCENARIO l'-
,
REACTOR OPERATOR
,
h.
'
All questions should be answere'd for,the static plant conditions as they, presently exist unless'otherwise' stated.
.o 3 [ (1.0')'
~
l. ' For. thel present' plant conditions, state all procedures that are.
-
required to.be' entered. (Except S, ST, GP, EP,'. ARC's, and A procedures)'.
. ? l; .
- (1.0) 2. Why are the Drywell Chillers unusable for
- cooling the Drywell?
(2.0)- 3. Explain.what plant condition'is causing the following alarms. "
. n (Should describe what is causing;the alarm not the alarm setpoint)
.a. " CORE SPRAY LINE INTERNAL BREAK" panel 113 window B-5 b. '"DIV I/II RRCS POTENTIAL ATWS" panel 004~, window F-5-
. c( .
s b $;
'
'(0.5) .4. a '. .What plant condition caused the Instrument Gas Compressors to*
..
i
- trip?? (Assume load sequencing has been completed.)
(0.5) b. What is supplying the ADS Instrument Gas. Headers?.
.;.
-(1.0) 5. For present plant conditions, what:ESW loads need manual valve manipulations to provide cooling flow? e
,
.,
(2.0) 6.
Did the following systems operate properly for the present plant
., conditions? If not,1, identify any component which did.not operate as
~% designed, a. HPCI y b. RCIC
.. (l .'0) 7.
Is there sufficient cooling to continue operation of both Dll and D13 diesels? Explain your answer.
p:y
?
- - _ - _ - _ _ _ - - _ _ _ _ - _ - - _ - _ - _ - _ = _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - .
.,
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- l,; , (2.0) 8. For each of the following systems / components, state whether or not 1 they should have isolated and why.
.Q .
a. MSIV's b. RUCU-
,
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1 0; , i:
~SECTION A: PLAN'S PROFICIENCY -
!
SCENARIO 1 REACTOR OPERATOR , ,
g! Answer Key
.n;
-
-
r .
y.
'D All: questions'should be answered for the static plant conditions as.they
. presently exist unless otherwise stated.
(1.0)- 1. For the present plant conditions, state all procedures that are required to be entered. (Except S , ST, GP, EP, ARC's ,- and A 1 procedures)
Answer:
(
T 101 (.5)
l E 10/20 (.5)
References: K/A Catalog ' Obj ectives-295003 Generic #11 RO 4.1 SRO 4.3 87-06-A Obj. 3 87-05-C Obj. 2
' ty
?? (1.0)' 2. Why are the Drywell Chillers unusable for cooling the Drywell?
Answer:
Drywell chill water pumps are unavailable since powered from non safeguard AC (1.0)
" References: K/A Catalog Obj ectives 295003 AK 2.04 RO 3.4 SRO 3.5 (2.0) 3. Explain what plant condition is causing the following alarms.
(Should describe what is causing the alarm not the alarm setpoint) .
a. " CORE SPRAY LINE INTERNAL BREAK" panel 113 window B-5
.
b. "DIV I/II RRCS POTENTIAL ATUS" panel 004, window F-5 Answer; a. HPCI is running and injectin5 to Core Spray causing a differential pressure between Core Spray lines (1.0)
b. RRCS initiation caused by Low Low Reactor Level (1.0)
References: K/A Catalog Obj ectives 295003 Generic #5 RO 3.7 SRO 3.6
_ _ - _ _ . - - _ -
"'
q;g' ! r - ;i.p.
y
- +'-
' d Rsector Op2ratori- Scan rio 1 - Ans@r; Key Pegs'2 of 3
.h
'"
.(0.5) :4; a. What plant condition caused the Instrument' Gas Compressors to.
trip? (Assume load sequencing has been completed. )
,j 1(0,5)- b. What is supplyingLthe ADS Instrument Gas Headers? ..
[ Answer:
a a. Loss of cooling water. flow (.5)
b. Instrument Gas Rece.<ers (.5)
'
References: J K/A Catalog' Objectives 223001. K 1.10 -RO 3.0 SRO 3.1 (1.0) 5. For present plant conditions, what ESW loads need manual valve manipulations to. provide cooling flow?-
Answer:
RECW (.5).
t.
'
.
'TECW (.5)
References: K/A Catalog Objectives 295028 EA 1.03. RO 3.9 SRO 3.2 223001 K 1.10 RO 3.0 SRO 3.1 (2.0) 6. Did the following systems operate properly for the present plant conditions? If not, identify the component (s) which did not operate as designed, s. HPCI b. RCIC Answer:
a. NO (.5)
F105 Injection Valve to Feedwater did not open. (.5)
l F059 Lube Oil Cooling Water Valve did not open. (.5)
b. Yes (.5)
References: K/A Catalog Obj ectives 206000 A2.11 RO 4.1 SRO 4.2 87-03-B Obj. 1 217000 A2.01 RO 3.8 SRO 3.7 87-03-C Obj . 1 l'
,
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ .
_ - _ - _ _
o e. -w ig(,r O'
22U .Rsdctor Opsrator;- Sczn rio 1.- An: war Kay Pega ?I of 3- pq
- C S. x (l'. 0) 7. Lls there sufficient cooling to continue operation of both D12 and'D14
, q. diesels? Explain your answer. ,
-
.;o
'
a . Answer:
Yes (0.5), One.ESV pump will supply adequate flow. (0,5)
i References: K/A Catalog Objectives t
'
(2.0). 8. For each of.the following systems / components,' state whetherior not they should have isolated and why.
.J: a. MSIV's
b. RWCU
- '" Answer:
a. Yes (0.5), Due to Mdtn Steam 1.ine Low Pressure (<765#) and Mode Switch in RUN (0.5)
b. Yes (0.5), Due to RPV water dropping below the Reactor Low Low Level (-38) serpoint (0.5)
References: K/A CataloS l Obj ectives i
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P .
.I l
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,g SECTION A: PLANT PROFICIENCY * EXAM SCENARIO 2 EXAMINER INSTRUCTIONS
.
I. BRIEF DESCRIPTION OF SCENARIO:
A. Simulator Status:
1. The simulator was initially set to IC-ll, 100% power. The following Malfunctions / Remote Functions will be used:
a. ' Isolate the "5A" Feedwater Heater (Manually),
b. MAL-194, 65% Steam Leak in RWCU Pump Room.
c. Suppression Pool Cooling is established improperly. (Heat Exchanger Bypass Valve left open).
d. MAL-434, A Failure of the "A" Recire Pump #2 seal.
B. Examinations will be~made up of:
1. Rules and Guidance for Examinees '
2. Simulator Operations Summary Sheet 3. RO and SRO Exams (Questions and Answer Key)
i ,
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EXAMINER INSTRUCTIONS (cont'd)
SCENARIO 2
,
STATIC SIMULATOR SETUP AND VALIDATION I. Setupc
.A. Recet the simulator to IC #11' .
B.
l
' Rotate all chart recorder a minimum of 3 inches and ensure sufficient paper for.the examination.
C.
Insert malfunctions / remote functions as described below.
Time Malfunction
'
Desired Parameter Value 1 l -l
.
0000 l MAL-194, 65% Leak 'in the RWCU
.
l Div I and IV Steam Leak l l Pump Room l Detection alarms and RWCU-system-l l
l l isolated l-
! l- .
.
l 1 0003 l Manually isolate the steam to l Drop in FW Temp. and approx. 5%
.
ai l 5A FW Heater, shut HV02-118A l-l power increase on APRM l 1 .
I-JAny 1 l MAL-434a,'"A"'Recire Pump #2 l Pressure on #2 seal goes to l l Seal Failure. l <500 psig and seal stage [
l =l Hi/ Low Flow Alarm l-I l
g -Any l Ertablish-SuppressioniCooling
.
I
" l RHR SW running and~"A" RHR loop- [
. l except leave the- Heat Exchanger l flow 9000 to'9500 gpm l l Bypass valve open l l
.[
I I I
l I l'
I I D. Run a OD-3 option 1 prior to isolating the steam to the'FW Heater.
E.
Run a OD-3 option 1 after power has stabilized at the higher level (approx. 10 minutes following heater isolation) .
.
F.
Display CRT .,
special Log 3 on one CRT and Control Rod position on another G.
,p At recorder the desired power.Parameter Valves FREEZE the simulator and secure
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e *
EXAMINER INSTRUCTIONS.(cont'd)
SCENARIO 2 II. Validation A. For the followin'g examination, the-following parameters must be in the allowed band.
Critical Parameter Allowed Band i I APRM power. l 103 to 107%
>
l l I Thermal Power on OD 3 l Greater than 3350 MWt. l 1 I RWCU l Isolated with Div 1-and Div 4 l l Steam Leak detection alarms l l l RHR Loop A l 9000 to 9500 gpm flow with- l l Heat Exchanger Bypass Valve l 1 open j i I
"A" Recirc Pump #2 l <500 psig l seal pressure l l
B. Check all traces and parameters for reasonable values and trends for existing simulator conditions.
C. If any critical parameter is outside the " Allowed Band", the simulator must be reinitialized, start at Step I. A.
D.
If all indications are satisfactory, the exam may begin.
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.SECTION'A: PLANT PROFICIENCY SCENARIO 2 REACTOR' OPERATOR SIMU1ATOR OPERATIONS SUMMARY SHEET l '.' Plant initially operating at 100% power.
2, Equipment known to be inoperable at beginning'of the' scenario: NONE 3. Simulator differences which affect the exam:
a. Those annunciator panels displaying an "F" cannot be used as
-
indication. .On these panels.the annunciators making the "F" will be.On and all others 0ff regardless of plant ; conditions.
b. Do not use the Off/ Gas system lineup for indication, Off/ Gas'is not operational in.the simulator 4 , Operator actions taken in the scenario, a. P 1 was run after initialization,
-b. :0D-3 option l~was run approx. 10 minutes later.
.c. Suppression Pool Cooling was established using the "A" loop of RHR.
l l.
l I
[c
~'
- _ _ _ _ _ _ _ _ _
. .
RULES AND GUIDANCE FOR EXAMINEES 1. Use blank ink or dark pencil ONLY to facilitate legible reproduct' ions.
2. Print your name in the blank provided on the cover sheet of the examination.
3. Fill in the date on the cover sheet of the examination, if necessary.
4 Use only the lined paper provided by the examiner.
5. Use abbreviations only if they are commonly used in facility literature.
6. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth'of answer required.
7. Show all calculations, methods, or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.
8. Unless solicited, the location of references need not be stated.
9. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
10. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
11. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
12. Rest room trips are to be limited and only one examinee at a time may leave.
You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
14. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for a total of four hours.
15. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating. '
16. When you are finished and have turned in your completed examination, leave the examination area.
l
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1,- .
SECTION A: PLANT PROFICIENCY
~ SCENARIO 2
--;
REACTOR OPERATOR.
l SIMULATOR OPERATIONS SUMMARY SHEET-1. -Plant initially' operating at 100% power.
L2.
Equipm'ent known~to be inoperable at beginning of the. scenario: NONE.
3. Simulator differences which. affect'the exam:
- a. .Tho-e annunciator panels' displaying'an "F".cannot.be'used as indication. On these panels the annunciators making the "F" will be On.
and all others Off'regardless of plant conditions.
.b.
Do not use the Off/ Gas system: lineup for indication,-Off/ Gas is.not operational in'the simulator 4 Operator actions taken in the' scenario, a. OD-3 option 1 was run;after initialization.
b. OD-3 option 1 was run approx. 10 minutes later.
c. Suppression Pool Cooling was established using the "A" loop of RHR.
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SECTION A: PLANT PROFICIENCY SCENARIO 2 REACTOR OPERATOR l
All questions should be answered for the static plant conditions as they.
presently exist unless otherwise stated.
(1.5) 1. Identify the cause of the reactor power change, and state the control
. panel indications to justify your answer.
'(2.0) 2. Based on your assumptions of the cause, what immediate action (s) are required.by procedure to mitigate the unexpected power change?.
Include any procedure (s) and step (s) these actions are based on.
(2.0) 3. Based on the control room indications available, - state the area (s)
(i.e. location) that may be affected by the steam leak. -State the reason (s) for selecting these area (s).
(1.0) 4 What. procedure (s) should be entered because of the steam leak?
(Except S, GP, EP, and A procedures.)
(1.0) 5. ' Suppression pool cooling was placed in service. incorrectly. State the action (s) required to place suppression pool cooling in service correctly. Include any procedure (s) these actions are based on.
(1.5) 6. Does using the "A" RHR Pump for Suppression Pool Cooling make the "A" LPCI Loop INOP for automatic LPCI injection? Why or why not?
(1.5) 7. On the "A" Recire Pump, which seal failed? State all indications used to determine which of the seals failed.
(1.5) 8. State three indications that you would expect to see if the other seal failed (i.e. both seals have failed).
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M ...
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'SECTION A: ' PLANT PROFICIENCY s
SCENARIO 2 REACTOR OPERATOR
- Answer Key
'
- All questions should be answered for the static plant conditions.as.they.
L presently exist unless otherwise stated.
(l'5) ~
. 1. Identify the cause ofithe reactor power change, and state-the' control panel indications to justify your answer.
Answer:
l -
-Reduction in feed water heating (.75) indicated'by'
Steam valve to the Sa feed water heater' closed. (.75)
'
' References: K/A Catalog Objectives
.295014 AA 2.03 RO 4.0 SRO 4.3 :87-06-C Obj. 4 (2.0), 2. Based on your. assumptions of the cause, what immediate action (s) are required by procedure to mitigate the unexpected power change?.
Include any procedure (s) and step (s) these actions are based on.
.
Answer:
Reduce power to eliminate a scram (.5), OT-104f 2.1-(,5)
~
Runback Recire flow'to 800 MWe (.5), OT-104' 3.5 (.5)
References: K/A Catalog' Obj ectives 295014 Ceneric #11 R0-4,2 SRO 4.4 87-06 C Obj. 1, 2, and 4 (2,0) 3. Based on the control room indications available, state the area (s)
(i.e. location) that may be affected by the steam leak. State the reason (s).for selecting these area (s).
Answer:
Div 1 and Div 4 Steam Leak Detection (0.5) combined with the RUCU isolation (0.5) indicates the leak is in either:
One of the RWCU Pump Rooms (.5)
One of the RUCU Heat Exchanger Rooms (.5)
References: K/A Catalog Obj ectives 223002 A 2.10 RO 3.9 SRO 4.2 88-02-B Obj. 2
_ _ _ _ _ _ _ _ _ __-_________n
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f st so
-
.
p, n yc Racetor Oparctor Scenario:2. .An2 war Kay ~Paga 2 of 3
'
~
q -
I-(', .. p.
-(1,0) . <4 What procedure (s).should be+ entered because of~the steam leak?
,(Except S, GP,.EP, and A procedures.)~
s
Answer: i l
'
l! ' ( l '. 0 ) ' T - 103. .
!
l ~ References: K/A Catalog Objectives 223002- Cenerie 15 RO 4.1 SRO 4.3' 88-02 A Obj. 2 :
1 4 1(1.0) 5. Suppression pool cooling was placed in service incorrectly. -State 'l the action (s)= required to place suppression pool. cooling.in service correctly. Include any procedure (s) these. actions are based on.
' Answer:
..
7-
.
Heat Exchanger Bypass . Valve must be ' gds ( .5) .
ClO5eYS-
.S51.8.A (.5) 1 References: .K/A Catalog- Objectives 219000 A l'.08 RO 3.7 SRO 3'.6 87 04-C Obj . 2
-
L (1.5). 6. .Does using the "A" RHR Pump-for Suppression Pool Cooling make the "A" LPCI Loop INOP for automatic LPCI injection? Why:or why not?
Answer:
No -(.5)
The test return valve will automatically close allowing the system to inject suppression pool water via the normal LPCI flow path. (1.0)
References: K/A Catalog Obj ectives 203000 K 4.01 RO 4.2 SRO 4.2 87-04-C Obj. 3
_ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ . _ _ . . _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ . _ . . _ _ _ . . _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ . .
s i,
.~ y h R6 ctsr_Op;rcter.- Sctnario 2 - An2 war Key. Pcg2.3.sf 3-
" ~
'
(2.0)- 7. On the 'A" Recirc Pump, which seal failed 7; . State all indications used to determine which of the seals failed.
Answer: '!
- 2 seal failed (.5)
.#2 Seal-pressure decreased to zero (.5)
"1A RECIRC PUMP SEAL STAGE HI/LO FLOW" annunciator (.5)
"lA RECIRC PUMP SEAL LEAKAGE HI FLOW"' annunciator (.5)
Re'ferences : :K/A Catalog Obj ectives 202001 A 2.10' RO 3.5 SRO 3.9-(1.5) 8. State three indications that you would expect to see if the other seal failed (i.e. both seals have failed).
Answer:
Any 3' listed below (0.5 each)
<
Decrease in #1 seal pressure increase in drywell temperature-Increase-in drywell pressure.
Increase =in drywell leakage flow rates 1A recire pump high leakage flow References: K/A Catalog Obj ectives 202001 A 2.10 RO 3.5 FR0 3.9 87-06-C Obj. 4
.:
,
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SECTION B: LIMITS AND CONDITIONS Ouestion 1 (1.75)
A fire has necessitated evacuation of the Main Control Room. All immediate and follow-up actions required to be performed from the Main Control Room have been complet<,d. Upon reaching the Remote Shutdown Panel (RSP) it is discovered that the Remote Shutdown Static Inverter is not energized preventing operation of the RCIC system from the RSP.
(.75) a. What actions should be taken as a result of RCIC not being available for use?
(1.0) b. The C0 notes that drywell temperature is stable at 145 F,
At this point the CD performs the following:
1) Open SRV "A" 2) RPV pressure decreases from 1050 psig to 400 psig over the next 5 minutes 3) Close SRV "A" Did the CO carryout the correct actions? (YES or NO)
Explain your answer.
Question 2 (1.25)
What administrative requirements must be performed when safety related equipment is returned to service during an outage and more than one permit is applied?
ouestion 3 (1.5)
Concerning GP-8 and NSSSS, answer the following statements TRUE or FALSE and include in your answer the Section and Page used for your answer:
(0.5 a. Depressing E51-S23 (RCIC Manual Isolation Pushbutton) will cause a RCIC each) Turbine Trip as well as a closure of HV-49-F007, F008, and F076.
b. Should a failure occur which prevents a Group IIA (Shutdown Cooling)
Isolation initiation, all four (4) NSSSS Manual Isolation Pushbuttons (S28A thru D) must be depressed to ensure completion of the isolation.
c. There is no bypass capability for the TIP Vithdrawal Signal and ball valve isolation.
. _ _ _ _ _ _ _ _ _ _ _ _
_ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ __
_ _ _ _ _ _ _ . _
. .
- Sseticn'B: -Lidita cnd Ctnditicns. Pcgs 2 of 4- s
Ouestion'4 (1.25) q The following data was ,obtained during the performance of a reactor startup:
IlmR SRM A SRM B SRM C SRM D l 0815 200 200 200 220 0816' 390 410 400 400 0817 600 600 550- 650 0818 1200 1200 1100 -1300 0819 2400 2400 2300 2500 0820 4500 4600 4500 4700 The. logs indicate the reactor was critical at 0817. What was reactor period at the time the reactor went critical? (Show all work)
Ouestion 5- (2.0)
For each of the following situations, state (YESjor NO) whether or not the individual would be allowed to make changes to Reactor-Recirculation Pump speed, at full power, without direct supervision? If no; briefly explain-why not, a. A Test Engineer with an inactive license to check control system response, provided the consent of the reactor operator at the controls and the shift supervisor.is obtained.
b. An unlicensed individual in the Licensed Operator Training Program.
c. The oncoming Shift Supervisor, provided the knowledge and consent of reactor operator at the controls is obtained, d. The oncoming Shift Superintendent, provided the knowledge and consent of the reactor operator at the controls and the Shift Supervisor is obtained.
Ouestion 6 (2.0)
While operating at 100% power, the " CORE SPRAY LINE INTERNAL BREAK" annunciator alarms. List two (2) systems other than Core Spray which could be adversely affected and briefly explain how the operation of each is affected.
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_.m_m___ _ _ _ _ _ _ _ - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - " - - - - - ' - ' - - ' ' ^ - ' - ' " ' ~ ~ ^ ^ ' " " " ' ' - - ~ - ' - " - " - - - - - ' " - - - - - - - - - ^ ' - ' ' ^ - - - - ' ' ' - - - ' - - - - - - - - ' ' - ' -
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'l Ssetion B: Liaits cnd 'Cenditiens , ,Pe ga 3 of . 4
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Ouestion 7 (2.0)
The reactor must be shutdown and cooled down from the Remote Shutdown Panel (RSP) because the Main Control Room became uninhabitable. Assume all equipment is operable and the immediate operator actions were carried out.
(1.0) a. Injection to the vessel is set at 560 gpm from RCIC only.
Pressure is being maintained in band with SRV's. . Ten minutes-later the operator notices RPV level to be +60 inches and increasing. Assuming no RCIC malfunctions, why is this condition occurring?
(1.0) b. When reactor pressure is below 75 psig and shutdown cooling is being established at the RSP, it is not possible to shut HV-43-IF023A, (Recire Pump Suction Valve). . What action must be taken to establish shutdown cooling to overcome this problem, and why is this action necessary to ensure core decay heat removal?
Ouestion 8 (1.25)
Consider the following accident scenario which occurs with the reactor at 50% power:
T - O sec. -
Small line break LOCA occurs T - 25 sec. -
Level at -38" and decreasing
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HPCI and RCIC fail to automatically initiate T - 130 sec. -
Level at -129" and slowly decreasing
-
Low pressure ECCS pump running on minimum flow T - 155 sec. -
Drywell pressure at 1.68 psig and increasing T - 200 sec. -
HPCI manually initiated and injecting at 5500 gpm T - 230 sec. -
Level at -120" and increasing For the conditions given and assuming no other operator actions than those stated, should ADS have initiated? Briefly explain your answer.
'
Ouestion 9 (.75)
A sudden increase in Drywell Pressure prompts entry into OT-101, High Drywell Pressure. It has been determined that venting the drywell is necessary. The following conditions exist:
Dryvell pressure - 1.5 psig Suppression pool pressure - 0.2 psig Suppression pool air temperature - 125'F Drywell_ temperature - 130'
Determine the Minimum Drywell Pressure allowed after venting is commenced.
(Assume DW temperatures remain constant.)
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J' Szction B: Limits and Conditions Pags 4 of 4
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Que.stion 10 (1.5)
A loss of all AC Power has occurred. The immediate actions of E-1 are complete and the followup actions are being performed. HPCI has been initiated with the following conditions indicated:
Instrument Readinc Narrov range RPV level (LI C42-lR606 A) 0 inches. . steady Narrow range RPV level (LI-C42-lR606 C) 20 inches, steady Wide range RPV level recorder (XR-lR623 B)
.
35 inches, steady.
Wide range RPV pressure recorder (XR-lR623 B) 800 psig, steady HPCI turbine steam supply pressure (PI-55-lR602)l000 psig, steady Are reactor pressure and level within the required bands? State the reason for your answer.
Question 11 (1.75) +-
The A Reactor Recirculation Pump has tripped while at 100% power. During plant recovery, the reactor operator was directed to restart the A R : ire Pump. The pump was restarted at 10:28 after the following data was taken at 10:15:
TRIP SETPOINT, SCRAM 48%
APRM READINGS, AVG. 33%
Reactor Pressure from PI-42-lR605 920 psig Bottom Head Drain Temp. from T 55-44-lN601 510 F Recire Loop A Temp. from B0 55 4800F Recirc Loop B Temp. from RO 57 510 F Loop Flow from FR 43-lR614 10000 gpm Did the reactor operator meet the acceptance criteria for starting the idle pump? Justify your answer.
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SECTION B* LIMITS AND CONDITIONS ANSWER KEY l
Ouestion l' -(1.75) .;
. . . l A fire has necessitated evacuation of the Main Control Room. All immediate H and follow-up actions required to be performed from the Main Control Room have been completed. Upon reaching the Remote Shutdown Panel (RSP) it is q discovered that the Remote Shutdown Static, Inverter is not. energized *'
> "
preventing' operation of the RCIC system from the.RSP.
-( 75) a. What actions should be taken as a result of RCIC not being available-for use?
(1.0) b. The C0 notes that drywell temperature is' stable at 1450F. At this point the C0 performs the following:
1) Open SRV "A" 2) RPV pressure decreases from 1050 psig to 400 psig over the-next 5 minutes 3) Close SRV "A" Did the C0 carryout the correct actions? (YES or NO)
Explain your answer.
ANSWER: '(1.75)
a. (Not required - with RCIC unavailable from the Remote Shutdown Panel, use SE-6 Step 4.4, to) Verify HPCI automatic operation (.75).
-b. No (.25), SE-1 (.25), Step 4.11 requires pressure control between 950 and 1115 psig (0.5). (Optional - Depressurization at greater than 1000F per hour is not authorized except to prevent exceeding drywell temperature of 340 F Procedure T-102 should be checked to determine if rapid depressurization is required.)
References Used To Answer:
SE-1 (Page 4, 4.11)
SE-6 (Page 3, 4.4)
B2 182 K/A Reference: (295/016/ System Generic wil) 4.1 4.2 (295/016/AA 1.08) 4.0 4.0 Lesson Plan Reference:
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LOR-8705-B
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?Ssetion.B: IbimitsandfConditions-AnrwarKay. Pags 2 of.11l
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Ouestion 2 (l'25)
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What administrative' requirements must-_be performed when safety related i- equipment is returned to service'during an outage land more than one. permit-is-applied?
1; ANSWER: (1.25)
'Two copies'( .25) of the applicable procedure ( .25), which ' establishes the :
. system in the normal configuration, shall be independently performed;(.5)
and signed off (.25). Section 5.4.1 Re'ferences Used To Answer:
1A-41 Procedure for' Control of Plant Equipment (Page 12,-5,4.1)
EQ I SED K/A Reference: (294001/Kl.02) 3.9 4.5 (294001/K1,07) 3.3 3.6 Lesson, Plan Reference:
' LOR-8704-G Objective - 1 l
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Section B: ; Limits cnd Conditions - Answar Key Pegs-3 of-11:
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'Ouestion 3 (l'5)~
.
- Concerning GP-8 and.NSSSSi answer the following statements TRUE or FALSE and'
l -iinclude in your. answer the Section and Page used for your answer:
1.
!~ -(0.5 a. Depressing E51-S23.:(RCIC Manual Isolation Pushbutton)~will'cause'a RCIC
'anch){ -Turbine Trip as well as a. closure of HV-49-F007, F008, and F076.
.b. Should a failure occur which prevents a Group IIA (Shutdown Cooling)
. Isolation' initiation, all four (4) NSSSS Manual Isolation Pushbuttons
_(S28A thru D)~must be. depressed to ensure completion of the isolation.
c' ' There is no bypass. capability for the TIP Withdrawal Signal and ball
~ valve isolation.
ANSWER: '(1.5)-
a. FALSE (.25),'Section 3.3 Page 79 (.25) '
b. FALSE. (.25), Section 3.2 Page 5 (.25)
l G l+ u'l -
l c. TRUE (.25), Section 3.2 Page 24 (.25)
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ci .o GM. 2 {p Q References Used'To: Answer:
GP-8 ' Primary and Secondary Containment Isolatiion Verification'and Reset (Page 79, 5, 24)
E.00 18.0 K/A Reference: (223002/Kl.07) 3.4 3.6 (223002/Kl.08) 3.4 3.5 (223002/K4.03) 3.5 3.6 (223002/K4.04) 3.2 3.6 Lesson Plan Reference:
LOR-88-02-B Obj ective -2
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- Limits cnd Conditicns - An2 war Key .Paga 4 of 11
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Question 4 (1.25).
The following data was obtained during the performance of a reactor startup:
Ilma SRM A SRM B SRM C SRM D 0815 '200 200. 200 220 .,
0816 390 410 400 400.
'0817 600 600 '550 650 0818 1200 1200 1100 1300-0819 2400 2400 2300 2500 0820 4500 4600 4500 4700 The logs indicate the reactor was critical at 0817. What was reactor period at the time the reactor went critical? (Show all work) -
ANSVER: (1.25)
Doubling Time - 1 minute (0.5), therefore Period - 1.44 * 60 second (0.5) - 86.4 seconds (0.25)
References Used To Answer:
GP-2, App. 1. E2t1 preceeding Step 3.1.7 E9 EED K/A Reference: (294001/A1.02) 4.2 4.2 (292008/K1.06) 4.2 4.2 l
i Lesson Plan Reference:
LOR-87-02-C Objective - 2 LOR-87-02-A Objective - 4 LOR-87-05-F No objective i
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-Section B: Limits and Conditions - Answer K2y Page 5 of 11 f
Ouestion 5 (2.0).
For each of the following situations, state (YES or NO) whether or not the {
individual would be allowed to make changes to Reactor Recirculation Pump speed, at full power, without direct supervision? If no, bricfly explain why not.
a. A Test Engineer with an inactive license to check control system response, provided the consent of the reactor operator at the controls and the shift supervisor is obtained.
b. An unlicensed individual in the Licensed Operator Training Program.
c. The oncoming Shift Supervisor, provided the knowledge and consent of reactor operator at the controls is obtained.
d. The oncoming Shift Superintendent, provided the knowledge and consent of the reactor operator at the controls and the Shift Supervisor is obtained.
ANSWER:
a. No (.25), Inactive license holder is not allowed to manipulate controls without direct supervision (.5),
b. No (.25), LOT trainees are not allowed to manipulate controls without direct supervision (.5).
c. Yes (.25)
d. Yes (.25)
References Used To Answer:
A-7 (5.2.2)
EO SRO K/A Reference: (294/001/A 1.03) 2.7 3.7 (294/001/A 1.09) 3.3 4.2 Lesson Plan Reference: '~
LOR-8801-C Objective - 3.b
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}SsetionB: Limits and Ccnditions).- Answar Key'
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L p EOuestion'6' '(2.0)
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g-a While' operating at 100% power,- the ' " CORE . SPRAY LINE INTERNAL BREAK"
' annunciator alarms'. List.two (2) systems other than Core' Spray'which.could
,
.be adversely. affected and briefly explain how the operation of 'each in-affected.
, ANSVER: . '(2.0)L
.. . . .
..
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SLC (.5) and HPCI (.5) .- This. could prevent injection (.5);by 'these' two
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systems-into the core shroud'(.5).
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' References.Used To Answer:
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- P&ID M52 Sheet 1, Rev. 34-
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E2 S.EQ
'K/A Reference: (209001/A2.05) 3.3 3.6 Lesson Plan Reference:
LOR 87-04-E Obj ective - 4
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- LS ctien B: . Liniits and Conditions' - ~ An:wsr Kay
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Pags.7 cf.llre
"
ouestion i (2.0)
. The, reactor must be shutdown and cooled down from the Remote Shutdown Panely (RSP) because..the Main Control Room'became uninhabitable. Assume all equipment is operable.and the immediate'.. operator actions were: carried out.
-(1.0)- a. Inj ection to. the' vessel is set . at '560 gpm from RCIC only' .
.
Pressure is being maintained in band with SRV's. Ten minutes later the operator. notices RPV level:to be +60 inches and'
L increasinge Assuming no RCIC malfunctions, why is this. condition 1 occurring?'
(1.0): b. When reactor pressure is below 75'psig and shutdown cooling is being. established ~at the RSP, it is'not possible.to' shut HV-43 1F023A, (Recire Pump Suetion' Valve). -What action'must be taken to establish; shutdown cooling to overcome this problem, and why is this action necessary to ensure core decay heat' removal?-
ANSWER:
a. When operating from the RSP, the RCIC Turbine; Steam Supply Valve.:(.5)'.
(F045) will'not shut on RPV high level-(+54 inches).(O.'5).
b. LPCI injection valve will be~ opened (0.5) instead of the Shutdown 1 Cooling Return valve to prevent shutdown cooling flow from. bypassing the core.(0.5).
.(The valve lineup would allow shutdown cooling flow to bypass the core.)
References:Used To Answer:
SE-1, (Page15, 17)
P & ID M-51'
ED 'fE2'
- K/A Reference: 205/000/K1.08 3.9 3.9 205/000/K6.03 3.1 3.2 217/000/A3.01 3.5 3.5 l 217/000/A3.05 3.9 3.9 295/016/AA1.06 4.0 4.1 295/016/AK2.01 4.4 4.5 295/016/AA2.06 3.3 3.5
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Lesson Plan Reference:
LOR-87-05-B Obj ective - 4.a LOR-87-04-C Objective 2.d I
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l L Ssetion B: Limits and Conditions - An war Kay Pags 6 of 11 f.
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i . 1 Ouestion 8 (1.25)
Consider the following accident scenario which occurs with the reactor at 50% power:
l T - O sec. -
Small line break LOCA occurs l r - 25 sec. -
Level at -38" and decreasing
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HPCI and RCIC fail to automatically initiate j l T - 130 sec. -
Level at -129" and slowly decreasing i j -
Low pressure ECCS pump running on minimum flow T - 155 sec. -
Drywell pressure at 1.68 psig and increasing {
T - 200 sec. -
HPCI manually initiated and injecting at 5500 gpm T - 230 sec. -
Level at -120" and increasing For the conditions given and assuming no other operator actions than those stated, should ADS have initiated? Briefly explain your answer.
ANSWER: (1.25)
NO (.5). (ADS requires a low level of -129" in conjunction with either a high drywell pressure of 1.68 psig or the 420 second timer being timed out and a confirmed low level of +12.5" and a time delay of 105 seconds. At the end of the 105 second time delay, low pressure pumps must be running.) As stated above, level was above -129" before the 105 second timer timed out, thereby preventing automatic initiation (.75).
References Used To Answer:
M-1-B21-1060-E-003.13 EO EE.Q K/A Reference: (218000/A4.04) 4.1 4.1 (218000/K4.02) 3.8 4.0 (218000/K4.03) 3.8 4.0 Lesson Plan Reference:
LOR-87-04-F Objective - 1
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$2ctien B: Licits,cnd Canditiens - An: war Ksy. '
Pcg2 9.of 11
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[ Ouestion 9 (.75)
,A sudden increase in Drywell Pressure prompts entry into OT-101, High-i Drywell Pressure. It'has'been determined that venting the drywell is necessary. The following conditions exist:
,
Drywell pressure .1.5 psig "
Suppression pool pressure - 0.2 psig
'
-Suppression pool' air. temperature - 125'F-Drywell temperature - 130
Determine the Minimum Drywell Pressure allowed after venting is commenced.
(Assume DW temperatures remain constant.)
ANSWER: (.75)
Minimum Drywell Pressure allowed is'approximately -25 psig. .
(Enter Table.1 with the values of-suppression' pool pressure and' air
- temperature and read.off corresponding value of suppression pool N2 mass,
_
rounding downwards.)
(Using Figure 1, enter the curve with the' closest.(but not greater than)
value of suppression pool N2 mass.)
References Used To Answer:
OT-101, High Drywell Pressure (Step 3.9.2 and 3.9.3)
BS EBE K/A Reference: 295009 (Generic 12) 3.8 4.4 Lesson Plan Reference.:
LOR-8706-C
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Section B: Limits and Conditions -'Answar/ Key Page.10 of 11 l
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Ouestion 10 .(1.5)
i A loss of cll AC Power has occurred. The immediate actions of E-1 are complete and the followup actions are being. performed. HPCI has been e, initiated with the following conditions indicated:
Instru'Djug; Readinc Narrow range RPV level (LI-C42-1R606 A) 0' inches, steady i Narrow range RPV level (LI-C42-1R606 C) 20 inches, steady-Wide range RPV level recorder (XR-1R623 B) 35 inches, steady-Wide range RPV pressure recorder'(XR-1R623 B) 800 psig, steady.
HPCI turbine steam supply pressure'(PI-55 1R602)1000 psig, steady
.
Are reactor pressure and level within the required bands?. State the reason for your answer.
' ANSWER: (1.5)
Yes (,5),.(Appendix I lists the indications available during a station blackout). LI-C42-1R606 C (.5) and PI-55-1R602 (.5) are the only
' indications available. (Level'is within +12.5 and +54 inches and pressureHis between 950 and 1115 psig.)
References Used To Answer:
E-1,-(Pagei4)
P&ID M 42 RO SRO K/A Reference: (295/003/AA1.03) 4,4 4.4 (295/003/AA2.02) 4.2 4.3 Lesson Plan Reference:
LOR-87-05-C Objective - 4
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Sscrion o: Linits end Conditions - Antwer Key. .Page 11 of 11 Ouestion 11 (1.75)
The A Reactor Recirculation Pump has tripped while at 100% power. During plant recovery, the reactor operator was directed to restart the A Recire Pump. The pump was restarted at 10:28 after the following data was taken at 10:15:
TRIP SETPOINT,' SCRAM 48%
APRM READINGS, AVG. 33%
Reactor Pressure from PI-42-1R605 920 psig Bottom Head Drain Temp. from T-55 44-1N601 510 F Recire Loop A Temp. from B0 55 480 F Recire Loop B Temp. from RO 57 510 F Loop Flow from FR-43-1R614 10000 gpm Did the reactor operator meet the acceptance criteria for starting the idle pump? Justify your answer.
ANSWER: (1.75)
Yes (0.5). Scram Margin > 12% (.25). Temperature differential between steam space and bottom head drain line s 145 F (533-510 - 23 F) (.25).
Temperature differential between idle and operating loop $ 50 F (510-480 -
30DF) (.25). Operating loop flow is s 50% of rated (.25). Data taken within 15 minutes of pump start (.25).
References Used To Answer:
ST-6-043-390-1 (Page 2, 7, 8, 9)
OT-112 Steam Tables EO SRO K/A Reference: (209/001/A2.03) 3.6' 3.7 (209/001/AA1.01) 3.5 3.6 (295/001/AA2.06) 3.2 3.3 Lessen Plan Reference:
LOR-87-06-C ~-1 l
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[ ATTACHf1Ef1T- 4 i
- M ,, .
, gj; SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION
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4 : FACILITY: LIMERICK GENERATING STATION" 1'.
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' REACTOR TYPE: GE-BWR-4
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,.DATE ADMINISTERED.;,
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OPERATOR:
NOTE TO OPERATOR A gradeLof 80% overall for Sections A and B combinediis the standard for-successful completion of the written' examination.
t OF SECTION. CATEGORY OPERATOR'S CATEGORY
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VALUE . SCORE' .VALUE A. Plant Proficiency __
B Limits and Controls Total Final Grade All work done on this examination ~is my own. I have neither given nor received aid.
Operator's Signature i
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.. 2 14S - NUCLEAR TRAINING SECTION .
RULES AND GUIDELINES FOR ANNUAL LICENSE OPERATOR REOUALIFICATION EXAMINATIONS l During the administration of this examination the following rules apply:
1. Cheating on the examination means an automatic failure of your examination and could result in more severe penalties.
2. Restroom trips are to be limited and only one candidate at a time may leave the room. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3. Use black ink or dark pencil anly to facilitate legible reproductions.
4. Print your name in the blank provided on the cover sheet of the examination.
i 5. Fill in the date on the cover sheet of the examination (if necessary).
6. Use only the paper provided for answers.
7. Print your name in the upper right-hand corner of each page of the answer sheet.
8. Consecutively number each answer sheet.
9. Skip at least three lines between each answer.
10. Separate answer sheets from pad and place finished answer sheets face down on your desk or table, 11. Use abbreviations only if they are commonly used in facility literature.
12. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
13. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not. Calculators are authorized for use if desired.
14 Partial credit may be given. Therefore, ANSUER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSUER BLANK.
15. If parts of the examination are not clear as to intent, ask questions of the examiner only.
16. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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17. ' Whin ytu .completa ytur cxaminiaticn, ytu chs11:
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a. -Ass [emble'yourexaminations-asfollows:
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(1) Exam questions on top.
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- (2) Exam aids - figures, tables, etc.
i (3) Answer pages including figures which are part'of the answer. dO['s
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~ b. Turn in.your copy of the examination and all pages used to answer the
. examination questions.
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c. Turn in all scrap paper and the balance of the' paper that you did not use -
for answering the questions.
d. Leave the examination area, as ~ defined by the examiner.
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n SECTION A: PLANT PROFICIENCY EXAM SCENARIO 1 !
EXAMINER INSTRUCTIONS
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f,) ' I. BR$EF DESCRIPTION OF SCENARIO:
,=r-
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A. Simulator Status:
1. The simulator.vas initially set to IC-11, 100% power. The
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following Malfunctions / Remote Functions:will be used:
a. MAL-261 Loss of Offsite Power b. MAL-453 HPCI Injection to, Feedwater, F105: Valve, f$ils as is c. MAL-455 HPCI Lube 011 Cooler Inlet Valve, F059, fails as is t:n ,
d. MAL-90,A ESW Pump Trip "A" !
B. Examinations will be.made up of:
1. Rules and Guidance for Examinees 2. Simulator Operations Summary Sheet 3. RO and SRO Exams (Questions and Answer Key)
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' EXAMINER INSTRUCTIONS'(cont'd),
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ESCENARIO.1
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'4 Static Simulator Setun and Validation': 4 gp X i
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. Setup ,. [ T
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A. 6.l Reset.' the ~-simulator. to 1C.~#11. l L : B.
Rotate all chart recoider a minimum of-3 inches and ensure sufficient
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paper for the examination. '
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Cr ' Insert malfunctions / remote functions as described below.
(Note: Af ter scram place the Mode Switch in shutdown.)
Time Malfunction Desired Parameter Value I.. .
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I. 1 0000, .
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l. MAL 455 HPCI Lube Oil Cooler
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.l Valve ' remains shut-following lL lj l Inlet: Valve, F059, fails as is l-HPCI initiation l
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.0000- l' MAL-453 HPCI Injection Valve
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' ,/ [ Valve remains' shut following'
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').to Feedwater, F105g fails as is l HPCI initiation l
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0003 1 l MAL-261, Loss of Offsite Power _l Diesels all start and' pick up ,
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0005 1. .
'l MAL-90,A (Trip of the "A"-
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l l "A ESW PUMP MOTOR OVERCURRENT" l l ESW Pump l alarm l-l l' ^
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Display CRT. _SpecialLog3ononeCRTandControlRodPositih[onanother E.
At'the desired Key Parameter Values Freeze the simulator and secure recorder power and place Mode Switch in "RUN".
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. EXAMINER INSTRUCTIONS (cont'd)
SCENARIO 1
II. . Validation A. For the following examination, the following parameters must be in the.
allowed band.
Critical Parameter Allowed Band l I Reactor Vessel Level l -39" to -50" l ,
I I Reactor Pressure l 700 psig to 750 psig l l I Instrument Cas l OFF l
Compressors [ l i I Diesels l Running supplying their l l respective buses l
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"A" ESW Pump Tripped l l l
HPCI l l Running with F105 and F059 l-z'
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I RCIC I l Running l !
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Check all traces and parameters for reasonable values and trends for-existing simulator conditions.
C.
If any critical parameter is outside the " Allowed Band", the simulator must be reinitialized, start at Step I.A. l D.
If all indications are satisfactory, the exam may begin.
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RUtdS AND GUIDANCE FOR EXAMINEES' <cy- a y,
, -W. $
1 Use' blank. ink or' dark pencil.ONLY to facilitate legible reproductions.
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.2 . Print your name in the blank.provided on the cover. sheet of the-T ' examination. "
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3; . Fill'in the date on the cover sheet of the examination,.'if necessary.
'* ,4 . Use only'the lined paper provided by the examiner.
5. . Use : abbreviations .only if they are commonly used in facility literature. '
6. The point value for each question is indicated in parentheses;after the.
question and c'an.be used as'a guide for the depth of answer required.N L 7. Show all calculations? methods, or assumptions used to obtain an answer to a mathematical problem, whether.' asked for in the-question or.not, o+
.8. .Unless' solicited, the. location of references need'not be stated.
9. Partial _ credit may.be givene Therefore, ANSWER ALL PARTS OF THE QUESTION.
AND DO NOT LEAVE ANY ANSWER $ BLANK.
- 10. If. parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
11. You must. sign the. statement'on the cover sheet that indicates the work on s
the examination is your own and that you have not received or been given-any assistance in completing the examination. This must be signed AFTER the examination has been completed.
' 12. Rest room trips are to be limited and only one examinee at a time may.
leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination '
compromise.
13. Cheating on the examination can. i result in a revocation of your license and could result in more severe penalties.
U 14. Each section of"the. examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for-a total of four hours.
i 15. Due to the existence of questions that will require all examinees to reftr to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
16. When you are finished and have turned in your completed examination, leave the examination area.
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b' 4: %SECTION A: PIANT PROFICIENCY '
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- SCENARIO _l'
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. REACTOR OPERATOR
- SIMU1ATOR OPERATIOh3 SUMMARY SHEET -
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l '1. Plant initially operating at 100% power.
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Equipment known to be. inoperable'at beginning of the scenario:
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NONE'
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l- .3. Simulator differencestwhich affect the exam:
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- a. All . annunciator. panels displayin'g an "F" ."dannot be used as indication.
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- On these. panels the annunciators making the "F" will be On.and all
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L- others Off regardless'of plant conditions.
l: b '. Do not use the Off/ Gas system lineup for. indication .Off/ Gas.is not operational in the' simulator. ,
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.4 Operator actions taken in the scenario: NONE r.. ,
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MI 5; The,RPS first in annunciator was " Turbine'Stop. Valve Closure Trip".
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-SECTION A: PLANT PROFICIENCY p SCENARIO 1 i SENIOR REACTOR OPERATOR
^All questions should be answered for the static plant conditions as.they presently exist unless otherwise stated.
-(1,0) .l. For the'present plant conditions, state all procedures that are required to be entered. (Except S, ST, GP, EP, ARC's, and A procedures)
(1.0) 2. Would you recommend activation of the Emergency Plan? If so, at what
, Emergency Action Level?
3. Explain what plant condition is causing the following alarms.
(Should describe what is causing the alarm not the alarm setpoint)
(1.0)- a. " CORE SPRAY LINE INTERNAL BREAK" panel 113 window B-5 (1.0) b. "DIV I/II RRCS POTENTIAL ATWS" panel 004, window F-5 (0.5) 4 a. What plant condition caused the Instrument Gas Compressors to trip? (Assume Load sequencing has been completed)
(0.5) b. What is supplying the ADS Instrument Gas Headers?
(1.0) 5. For present plant conditions, what ESW loads need manual valve manipulations to provida cooling flow?
(2.0) 6.
Did the following systems operate properly for the present plant conditions? If not, identify any component which did not operate as designed.
a. HPCI b. RCIC (1.0) 7. Is there sufficient cooling to continue operation of both D11 and D13 diesels? Explain your answer.
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(2.0) 8. For each of the following systems / components, state whether or not i i they should have isolated and why.
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SECT 20N A: ' PLANT PROFICIENCY EXAM SCENARIO 2-l
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EXAMINER INSTRUCTIONS-o I. BRIEF DESCRIPTION OF SCENARIO! '
A. -Simulator Status:
1 ~. The simulator was initia11y' set to-IC-11,.100% power. The l following Malfunctions / Remote Functions will be used:
a. Isolate the "5A" Feedwater Heater.-(Manually').
, b. ' MAL-194,'65% Steam Leak in RUCU Pump Room.
c. Suppression Pool. Cooling-is established improperly. .(Heat l Exchanger Bypass Valve left open).-
d. ' MAL-434, A Failure of the "A" Recire Pump #2 seal.
'B. Examinations will be made up of:
1. Rules and Guidance for Examinees
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2. Simulator' operations Summary Sheet 3. .RO and SRO Exams (Questions.and Answer Key)
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EXAMINER INSTRUCTIONS (cont'd).
SCENARIO 2 STATIC SIHULATOR SETUP AND VALIDATION 1. Setup A. Reset the simulator to IC #11.
B. Rotate all chart recorder a minimum of 3 inches and ensure sufficient paper for the examination.
C. Insert malfunctions / remote functions as described below.
Time Malfunction Desired Parameter Value l I 0000 i l MAL-194, 65% Leak in the RWCU _l Div I and IV Steam Leak l l Pump Room l Detection alarms and RWCU system l l l isolated l l l l 1 0003 l Manually isolate the steam to l Drop in FW Temp. and approx. 5% l l 5A FW Heater, shut HV02-118A l power increase on APRM l 1 l I
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Any l MAL-434a, "A" Recire Pump #2
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l Pressure on #2 seal goes to l l Seal Failure l <500 psig and seal stage l l l Hi/ Low Flow Alarm l 1 I Any I l Establish Suppression Cooling l RHR SW running and "A" RHR loop l l except leave the Heat Exchanger l flow 9000 to 9500 gpm l
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l Bypass valve open l l l
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I I D. Run a OD-3 option 1 prior to isolating the steam to the FW Heater.
E.
Run a OD-3 option 1 after power has stabilized at the higher level (approx. 10 minutes following heater isolation).
F. Display special Log 3 on one CRT and Control Rod position on another CRT.
G.
At the desired Parameter Valves FREEZE the simulator and secure recorder power.
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EXAMINER INSTRUCTIONS (cont'd)
SCENARIO 2 II. Validation *
A. For the following examination, the following parameters must be in the
. allowed band.
Critical Parameter Allowed Band i I APRM power l 103 to 107% 1 1 1 Thermal Power on OD 3 l Greater than 3350 MWt. l l 1 RWCU l Isolated with Div 1 and Div 4 l l Steam Leak detection alarms l l l RHR Loop A l 9000 to 9500 gpm flow with l l Heat Exchanger Bypass Valve l l open [
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"A" Recire Pump #2 l <500 psig l seal pressure l l B. Check all traces and parametars for reasonable values and trends for existing simulator conditions.
C. If any critical parameter is outside the " Allowed Band", the simulator must be reinitialized, start at Step I.A.
D. If all indications are satisfactory, the exam may begin.
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. --RULES AND CU2 DANCE FOR EXAMINEES
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1. Use blank ink or dark' pencil ONLY to facilitate legible reproductions.
2. Print'your name.in the blank provided on the cover sheet of the examination.
3. Fill in the date on the coverisheet of the' examination, if necessary.
4 Use only the lined paper provided by the examiner.
- 5. Use abbreviations.only if they are commonly used~in facility literature.
6. The point value for each question is indicated in parentheses after the
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question and can be used as a guide for the depth of. answer required.
7. Show all calculations, methods, or assumptions used to obtain an answer to a mathematical problem, whether asked for'in the question or not.
8. Unless solicited, the location of references need not be stated.
9. Partial credit may be given. Therefore , ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
10. If parts of the ' examination are not clear with respect to their intent, ask questions of the examiner only.
11. You must sign the statement on the cover sheet that indicates the work on-the examination is your own and that you have not received or.been given any assistance in completing the examination. This must be. signed AFTER the examination has been completed.
12. Rest room trips are to be limited and only one examinee at a-time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
14 Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for a total of four hours.
15. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
16. When you are finished and have turned in your completed examination, leave the examination area.
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- s, Ssnior Racetor.Op3rator - Scanario:1 - Answar Key!
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- (l'. 0) . 7. .IsL.there sufficient cooling to' continue operation of both D12 and D14 diesels? Explain your answer.
- Answer.:
.Yes-(0.5), One ESW pump will-supply adequate flow. (0,5)
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l. Referencesi K/A Catalog Obj ectives L *
a L 264000 'A 3.06 'RO-3.1. SRO 3.2 -
' (2. 0)' 8. For each of the following systems / components, state whether or not=
they.should have isolated and why.
f a. -MSIV's
'b. RWCU Answer; a. Yes-(0.5), Since. Mode Switch is in Run with Reactor Low Pressure..
'(<765) (0.5)
-b. Yes .(0.5). Since! Reactor Water level dropped below the. Reactor:
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Low Low Level ~(<-38) (0.5)
1 References: 'K/A Catalog Obj ectives 223002 .~A 1.02 RO 3.7 SRO 3.7 b
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SECTION A: PIANT PROFICIENCY SCENARIO 1-SENIOR REACTOR OPERATOR- ,
Answer Key
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All! questions should be answered for the static plant conditions as they presently exist unless otherwise stated.
(1.0) . -1. .For the present plant conditions, state all procedures that'are required to be entered. .(Except S,.ST, GP, EP, ARC's, and A procedures)
Answer:
T-101 (0.5)
j. E-10/20:(0.5)
References: K/A Catalog. Obj ectives 295003 Generic #11 RO 4.1 SRO 4.3 87-06-A Obj . 3 .
87-05-C Obj. 2 (1.0) 2. 'Would.you recommend activation of the Emergency Plan? If so at what .
Emergency Action Level?
. Answer:
Yes: (0.5)
Unusual Event (0,5)
References: K/A Catalog Objectives'
295031 Generic #11 SRO 4.6 3. Explain what plant condition is causing the following alarms.
(Should describe what is causing the alarm not the alarm setpoint)
(1.0) a. " CORE SPRAY LINE INTERNAL BREAK" panel 113 window B-5 (1.0) b. "DIV I/II RRCS POTENTIAL ATWS" panel 004, window F-5 Answer: I a. HPCI is running and injecting to Core Spray causing a differential pressure between Core Spray lines (1.0)
b. RRCS initiation caused by Low Low Reactor Level . (1.0)
References: K/A Catalog Obj ectives 295003 Generic $5 RO 3.7 SRO 3.6
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l Senior Reactor Operator - Scenario 1.- Answer Key. Page:2 of 3
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(0,5) 4 a. What plant condition caused.the Instrument Gas Compressors to trip?.
.(0.5)' b. What is supplying the ADS Instrument Gas Headers?.
Answer; a. Loss offcooling' water' flow (0.5)
b. Instrument Gas Receivers (0.5)
References: K/A Catalog Obj ectives
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223001 K 1.10 RO 3.0 SRO 3.1 (1,0) 5. For present plant conditions,:what ESW loads need manual valve'
manipulations to provide cooling flow?
Answer:
'RECW (0.5)
TECW (0.5)
References: K/A Catalog Objectives
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295028 EA 1.03 RO 3.9 SRO 3.2 223001 K 1.10 RO 3.0 SRO 3.1 (2.0) 6. Did the following systems operate properly for the present plant
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conditions? If not, identify any component which did not operate as designed.
a. HPCI b. RCIC Answer; a. NO (0.5)
F105 Injection Valve to Feedwater did not open. (0.5)
F059 Lube 011 Cooling Water Valve did not open. (0.5)
b. Yes (0,5)
References: K/A Catalog Obj ec tives 206000 A2.11 RO 4.1 SRO 4.2 87-03-B Obj. 1 217000 A2.01 RO 3.8 SRO 3.7 87-03-C Obj . 1
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J SECTION A:" :. PLANT PROFICIENCY ;
. SCENARIO'2:
e- r
' SENIOR' REACTOR OPERATOR-SIMULATOR OPERATIONS' SUMMARY SHEET
~ l '. - -Plant initially operating-at 100%^ power. .
2. . Equipment known to be:inop'erable at'beginning of the scenario: NONE-3. Simul tor differences which: affect the: exam:-
a. Those.' annunciator panels': displaying-an'"F" cannot be'used as -
indication. On these. panels.the' annunciators making.'the "F" will be 10n and all.others Off regardless of plant. conditions.
.b.
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Do not use the.Off/ Gas system. lineup for indication,-Off/Cas.is.not:
operational in the simulator
- 4. . Operator actions taksn.in the scenario, a. OD-3 opt-lon!l' was run af ter initialization.
b'.. OD'3' option.1'was run approx. 10' minutes'later.
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- c. ' Suppression Pool Cooling'was established using.the "A" loop of RHR.'
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SECTION A: PIANT PROFICIENCY SCENARIO 2
--SENIOR REACTOR OPERATOR All questions.should be answered for the static' plant conditions as they j' '
presently exist unless otherwise stated.
l. .(1.5) 1. Identify the cause~'of the reactor power change, and state the control panel indications to -justify your answer
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~(2.0) 2.
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. Based-'on your assumptions of the cause, what immediate action (s) are
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i required by procedure to mitigate the unexpected power change?-
Include any procedure (s) and step (s) these actions are' based on.
-(2.0) 3. Based on the control room indications available, state the area (s).
(i.e. location) that may.be affected by the steam leak. State the-reason (s) for sele ~cting these area (s).
(1.0) 4 What procedure (s) should be entered because of the steam ' leak?
(Except S, CP, EP, and A procedures.)
(1.0)' 5. Suppression pool cooling was placed in service incorrectly.- State the action (s) required to place suppression pool cooling in service correctly. Include any procedure (s) these actions are based on.
(1.5) 6. What, if any, reports need to be made to the NRC based on present plant conditions. Include the type of report;.1.e., I hr., 4 hr., 24 hr. List your procedural references. (Assume no reports have been made.)
,(1.5). 7. On the "A" Recirc Pump, which seal failed? State all indications used to determine which of the seals failed.
'(1.5) 8. State three indications that you would expect to see if the other seal failed (i.e. both seals have failed).
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.SECTION A: ' PLANT PROFICIENCY
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' SCENARIO 2; l- '
SENIOR REACTOR OPERATOR Answer Key All questions-should be. answered for the static plant conditions as they.
presently exist unless otherwise stated.
(1.5). 1. . Identify the cause of the reactor power change,-and state the control <
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tl panel indications to justify your answer.
Answer:
Reduction in feed water heating ( 75) indicated by Steam valve to the 5a feed water heater closed. (.75)
References: K/A Catalog Objectives 295014 AA 2.03 RO 4.0 SRO 4.3 87-06-C Obj . 4 (2.0) 2. Based on your assumptions of the cause, what immediate action (s) are required.by procedure to mitigate the, unexpected power change?
Include any procedure (s) and step (s) these actions are based'on.
Answer:
Reduce power to eliminate a scram (.5), OT 104 2 1 (.5)
Runback Recirc flow to 800 MWe (.5), OT-104 3.5 ( 5)
References: K/A Catalog Objectives 295014 Generic #11 RO 4.2 SRO 4.4 87-06-C Obj . 1, 2, and 4 (2.0) 3. Based on the control room indications available, state;the area (s)
(i.e. location) that may be affected by the steam leak. State the reason (s) for selecting these area (s).
Answer:
Div 1 and Div 4 Steam Leak Detection (0.5) combined with the RWCU isolation (0.5) indicates the leak is in either:
One of the RWCU Pump Rooms (.5)
One of the RUCU Heat Exchanger Rooms (.5)
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References: K/A Catalog Obj ectives 223002 A 2.10 RO 3.) SRO 4.2 88-02-B Obj . 2 l
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[L =Sanior Raccter Op2rstor - Scentrio 2:- Answar Kay. 'Page 2 of 3
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1 'What. procedure (s):should be entered because of the steam' leak?-
,(Except S, GP, EP, and A procedures.).
Answer:
- (1.0) .T-103-References: .K/A. Catalog Objectives?
223002 Generic- 15 RO 4.1 SRO 4.3- 88-02- A . Obj .12
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.w (1.0); '5.. Suppression pool cooling was placed.in service incorrectly. State theLaction(s) required,to place suppression pool. cooling in. service:
correctly. . Include:any' procedure (s).these-actions are based on.
. Answer:
m Heat Exchanger Bypass Valve must g d. (.5)
- S51.8.A (.5) 6 /cSe cbL References: .K/A Catalog Obj ectives 219000 A 1.08' RO 3.7 SRO 3.6 87-04-C L 0bj . 2 (1.5) _ 6. What,.if any, reports need to be made to the NRC based on present'
. plant conditions. Include the type of report;' i e., 1 hr., 4 hr.. 24 hr. List your procedural references. (Assume no reports'have been made.)
Answer:
4 hr. notification (.5)
ESF actuation (or RWCU isolation) (.5)
'A-31 (.5)
References: K/A Catalog Objectives 223002 Generic w3 SRO 4.4 88-01-C Obj. 5
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- (2.0) 7 On the "A" Recire Pump, which seal failed?' State all indications
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used to determine which'of.the-seals failed.
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Answer:
, #2 seal-failed (.5)
, #2 Seal pressure. decreased to zero (.5)-
L "lA RECIRC PUMP SEAL STAGE HI/LO FLOW" annunciator.(.5)
"lA RECIRC PUMP SEAL LEAKAGE HI FLOW" annunciator (.5)
~ References: K/A Catalog ' Objectives-202001 A 2.10' R0-3.5 SRO 3.9-(l'5)
. 8. State three indications that you would expect to see if the second seal failed (i.e. both seals have failed).
Answer:
Any 3 listed below (0.5 each)
Decrease in #1 seal pressure Increase in drywell temperature Increase in drywell pressure Increase-in drywell leakage flow rates 1A recire pump high leakage flow References: K/A Catalog ' Objectives 202001 A 2.10 RO 3.5 SRO 3.9 87-06-C Obj . 4 q l
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4- ,1 SECTION B LIMITS AND CONDITIONS
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~Ouestion 1. .(1.75)'
.A Loss of Coolant' Accident has occurred. The' reactor has scrammed I- automatically. RPV-leve11immediately following the LOCA was below TAF and. .
-returned to.-120 inches within 2 minutes. Plant parameters are' currently:
RPV Level - -120 inches.
i SP Pressure - 24 psig SP Water Temperature - 140 F'
SP Air Space Temperature - 1200F.
SP Level - 41 feet DW Pressure - 25 psig DU Temperature.- 2600F The shift supervisor orders DW cooler fans shutdown and one loop of DW spray to be initiated.
(1.0) a. Has the shift supervisor taken the correct action in accordance with procedures?. Explain your answer.
-(.75) b. Considering the information given above, what is the correct Emergency Classification at this time 7 ouestion 2 (1.25)
What administrative requirements must be performed when safety related equipment is returned to service during an outage and more than one permit is applied?
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Ouestion 3 (1.5)
Concerning GP-8 and NSSSS, answer the following statements TRUE or FALSE and include in your answer the Section and Page used for your answer:
(0.5 a. Depressing E51-S23 (RCIC Manual Isolation Pushbutton) will cause a RCIC each) Turbine Trip as well as a closure of HV-49 F007, F008, and F076, b. Should a failure occur which prevents a Group IIA (Shutdown Cooling)
Isolation initiation, all four (4) NSSSS Manual Isolation Pushbuttons .
(S28A thru'D) must be depressed to ensure completion of the isolation. .I c. Thera is no bypass capability for the TIP Withdrawal Signal and ball f v43.* isolation.
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.Ssetion B: Lktits-cnd Canditiens Pega 2 cf[4~
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Question 4 (1.5)
From the events listed below, itidicate (YES or NO) whether or not a one hour
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notification to the NRC is required. Include in your answer. references, section and page.used.
(.75) a. While executing procedure T-112, reactor pressure was
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intentionally decreased from 1015 psig to 360 psig in 15 minutes.
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( .' 75 ) b. While the Reactor is at 100% power, plant chemistry. reports that primary coolant specific activity is equal to 120/E microcuries-per gram.
.ppestion 5~ (2.0)
For each of the following situations, state (YES or NO) whether or not the individual would be allowed to make changes to Reactor Recirculation Pump.
speed, at full power, without direct supervision? If no, briefly explain why not, a. A Test Engineer.with an inactive license to check control system response, provided the consent of the reactor operator at the controls and the shift supervisor is obtainsd.
b. An unlicensed individual in the li.:ensed Operator Training Program.
c. The oncoming Shift Supervisor, provided the knowledge and consent of-reactor operator at the controls is obtained.
i d. The oncoming Shift Superintendent, provided the knouledge and consent of the reactor operator at the controls and the Shift Supervisor is obtained.
Question 6 (1.5)
Unit 1 is operating at 100% power with all plant equipment operable when a plant operator reports that the North Stack Radiation Monitor's sample pump has tripped. Subsequently, it is determined that the pump motor will have to be replaced which will take approximately thcae (3) days. State the action (s) required to satisfy Technical Specifications for the given condition (be specific) and reference the Tech. Spec. sections used for your answer.
Question 7 (2.0)
During operation at 100% reactor power, it is determined by a ST that the A and B MSL Rad Monitors are inoperable. State the two possible courses of action you may take to satisfy the requirements of Technical Specifications.
Reference the Technical Specification section used.
- - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ - _ _ . _ _ _ _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -______-__-___-______-___________---_a
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Section .B: Lirits and Condition 3 Pega 3 of 4 Ouestion 8 (1.0) !
!
The plant experienced a transient and the following is observed: '
o Suppression Pool Temperature increases to 1300F.
o Suppression Pool level decreases to 14 feet, o Reactor Pressure is 1000 psig.
Answer YES or NO to the following and include reference, section, and applicable step to answer the question.
(0.5) a. Is there sufficient NPSH for RHR and Core Spray Pumps?
(0.5) b. Is suppression pool heat capacity sufficient?
Question 9 (.75)
A sudden increase in Drywell Pressure prompts entry into OT-101, High Drywell Pressure. It has been determined that venting the drywell is necessary. The following conditions exist:
Drywell pressure - 1.5 psig Suppression pool pressure - 0.2 psig Suppression pool air temperature - 125'F Drywell temperature - 130'
Determine the Minimum Drywell Pressure allowed after venting is commenced.
(Assume DW temperatures remain constant.)
Ouestion 10 (1.75)
The plant is operating at power and shift change is in progress. The I oncoming reactor operator has called and he will not be in due to illness.
No replacement personnel are available, and this is your crew's first day back on shift following four days off.
(.75) a. How long can the on-duty reactor operator remain on duty?
(1.0) b. What action is required if the on-duty reactor operator remains 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> beyond his normal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift?
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< r Secticn B:' Linits end.Cenditions' Pogs 4 of 4
.
Question 11 (1.5)
Given the following plant parameters; Reactor Pressure - 500 psig Suppression Pool temperature - 150*F.
Suppression Pool Level - 20 feet and decreasing Determine the Minimum-Safe Suppression Pool Water. Level.- Show all work.
Question 12 (1.5)
The monthly RPS "A" Manual ~ Scram Channel. Functional' Test Past: Performance dates are as follows:
May 15 June 15 July 16 Today is August 31 and you have just been informed that this test has not been performed this month. Is the equipment associated with this surveillance test OPERABLE or INOPERABLE at this time? State the reason for
.your answer and state any actions required by Technica1' Specifications.
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SECTION B: LIMITS AND CONDITIONS j ANSWER KEY
'
Ouestion 1 (1.75)
A Loss of Coolant Accident has occurred. The reactor has scrammed automatically. RPV level immediately following the LOCA was below TAF cnd returned to -120 inches within 2 minutes. Plant parameters are currently.
RPV Level - -120 inches SP Pressure - 24 psig SP Water Temperature - 140 F SP Air Space Temperature - 1200F SP Level - 41 feet DW Pressure - 25 psig DU Temperature - 2600F The shift supervisor orders DW cooler fans shutdown and one loop of DW spray-to be initiated.
(1.0) a. Has the shift supervisor taken the correct action in accordance with procedures? Explain your answer.
(.75) b. -Considering the information given above, what is the correct Emergency Classification at this time?
ANSWER: (1.75)
a. No (.2), per T-102, Caution #3, DW sprays should not be initiated (.4)
with SP Level at 39 feet or higher (.4).
b. Site Emergency (.75)
References Used To Answer:
T 102, (Caution #3)
EP-101, (Page 16)
RO SRO K/A Reference: (295/024/EA 1.11) 4.2 4.2 (295/024/ System Generic *12) 3.9 4.5 (295/029/EK 2.05) 3.1 3.3 (295/029/ System Generic #7) 3.6 3.9 (295/029/ System Generic =12) 3.6 4.4 (294/001/A 1.16) 2.9 4.7 Lesson Plan Reference:
LOR 87-06-A Objective 7 EPP-0200 Objective 12
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- Ssetion Bb Limits'end Condit'icnsL- Answsr Kay. Pags 2 of;12-
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Ouestion 2'- >-(1.25)j
-
'
What administrative' requirements, must be performed when safety related'
equipment is returned to._ service 1 during an ~ outage and more than one . permit I
is applied?.
'
ANSWER: ' (1.-25) :
Two copies (.25)'of'the' applicable procedure 1( 25), which. establishes the.
. system in:the normal configuration, shall be independently performed.(.5)
and signed off (.25). Section 5.4.1 a
References.Used To Answer:
L A-41 Procedure for Control of Plant Equipment (Page 12, 5.4.1)
EQ EED.
K/A Reference: (294001/Kl.02). 3.9 4.5 (294001/Kl.07) . 3.3 3.6
>
Lesson Plan Reference:
LOR-8704-G Objective - 1 l
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r., Sseticn B: Linits cnd Conditiens -LAnsvar.Kay Pega 3 of 12.
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-Question 3' (1. 5 ) .
4Concerning GP-8 Land NSSSS, answer the'following statements'TRUE or FALSE and'
include in;your. answer the Section and Page used for your answer.:
L(0.5' ;a. Depressing E51-S23 (RCIC Manual-1 solation Pushbutton) will cause a RCIC esch). Turbine Trip as:well as a closure of_HV-49-F007, F008, and F076.
- b. 'Should a failure. occur which prevents a Group IIA (Shutdown Cooling) .
- . Isolation initiation, all four'(4) NSSSS Manual Isolation Puchbuttons (S28A thru;D) must be depressed to ensure completion of:theLisolation.
c.- There-is'no bypass' capability for the TIP Withdrawal Signal and ball.
valve' isolation.
' ANSWER: (1.5)
.a.; FALSE (.25), Section 3.3 Page 79 (.25).
-b. FALSE' (.25),.Section 3.2'Pa,ge.5 (.25)_
GIdil c. TRUE (,25), Section 3.2 Page 24 (.25)
- It
' References'Used To Answeri CP-8 . Primary and Secondary Containment Isolation Verification and Reset (Page 79, 5, 24)
E.Q 1B.0 ,
K/A Reference: (223002/Kl.07) 3.4 '3 . 6 (223002/Kl.08) 3.4 3.5 (223002/K4.03) 3.5 3.6 (223002/K4.04) 3.2 3,6 Lesson Plan Reference:
-LOR-88-02-B Objective - 2
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Sccticn B: LititsendCbnditien3.- An: war K;y . Pegs 4 cf 12 -
Ouestion 4 (1.5)
-Fron the events listed b'elow, indicate (YES or NO) whether.or.not a one' hour-p , notification to the NRC is, required. Include.in your answer-references,.
section and'page'used.
(.75) a. While executing procedure T-112, reactor pressure was
~
intentionally decreased from 1015 psig to 360 psig in-15. minutes.
j' ' ( . 7 5 ).' b. While the Reactor is at 1006 power,. plant chemistry reports'that primary coolant specific activity is. equal to 120/E microcuries per gram.
ANSWER: (1.5)
a. Yes (.5), EP-101, Page 17 and A-31 5.1.5 1 Page 3l(.25)
.
b. Yes (.5),. Tech. Specs. 3.4.5.a.3 Page 3/4 4 15 and A-31 5.1.5.4 Page 3 (.25)
Not' Required - a - Tech. Spec.
b - Tech. Spec., Emergency Plan References Used To Answer:
A-31,1(Page-3)
Technical Specifications (Page 3/4, 4-15)
EP-101 (Page 17)
EQ EEQ K/A Reference: (295/010/ System Generic #2) 3.0 4.5 (295/006/ System Generic #2) 3.0 4.5 (286/000/ System Generic #3) 3.0 4.3~
Lesson Plan Reference:
LOR-88-01-C Objective - 5 i
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Szction B: Limits end Conditions - Answsi- Key Paga 5 of 12 Ouestion 5 (2.0)
For each of the following situations, state (YES or NO) whether or not the individual would be allowed to make changes to Reactor Recirculation Pump speed, at full power, without direct supervision? If no, briefly explain why not, a. A Test Engineer with an inactive license to check control system i response, provided the consent of the reactor operator at the controls and the shift supervisor is obtained.
b. An unlicensed individual in the Licensed Operator Training Program, c. The oncoming Shift Supervisor, provided the knowledge and consent of reactor operator at the controls is obtained.
d. The oncoming Shift Superintendent, provided the knowledge and consent of the reactor operator at the controls and the Shift Supervisor is obtained.
ANS'w'ER : (2 0)
a. No (.25), Inactive license holder is not allowed to manipulate controls without direct supervision (.5).
b. No (.25), LOT trainees are not allowed to manipulate controls without direct supervision (.5).
c. Yes (.25)
d. Yes (.25)
References Used To Answer:
A-7 (5.2.2)
E9 ERO K/A Reference: (294/001/A 1.03) 2.7 3.7 (294/001/A 1.09) 3.3 4.2 Lesson Plan Reference:
LOR-8801-C Obj ective - 3.b b
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Section B: Limits and Conditions - Answar Kay ~ Page 6 of.12
.
Ouestion 6 (1.5)
Unit 1 is operating at 100% power with all plant equipment ~ operable when a plant operator reports that the North Stack Radiation Monitor's sample pump has tripped. . Subsequently, it is determined that the pump motor will'have to be replaced which will take approximately three (3) days. State the
. action (s) required to satisfy Technical Specifications for the given condition (be. specific) and reference the Tech. Spec.' sections used for your answer.
.
ANSWER: (1.5)
T.S. 3.3.7.12 (states that.at least one North Stack Monitor must be operable at all times). With no North Stack Radiation Monitor operable, Actions 114 (.5), 113 (.5), and 112 (.5) apply. (However, T.S. Porc Position 24 states that in lieu of the North Stack Monitor, the WRAM Low Range Channel may be used te sa:isfy this T.S. LCO) (1.5). Either answer is acceptable.
References Used To Answer:
Technical Specifications'(3.3.7.12)
Technical Specifications PORC Position 24 M 182 K/A Reference: (272000/ Generic 5) 2.9 3.9 Lesson Plan Reference:
LOR-88 01-B Objective - 11 I
4
,
___m . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . . _ _ _ _ . _ _ . _ _ _ _ _ _ . . . . _ _ . _ . _ _ _ _ _ _ _ _ . _ . . . . _ _ _ _ _ _ . - . _ _ . _ _ . _~ . _ _ . _ _ . . . _ . . _
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Se ction .'B :* Linits cnd Conditions - An:wsr.Ksy Pegs 7 of.12
/
c Question 7 '(2.0) g[
h i '*t. During~ operation at;100%' reactor power, it. is determined by' a' ST that the A and B.MSL Rad Monitors'are inoperable. : State the two possible. courses'of-action you may take to satisfy thel. requirements of Technical' Specifications,--
-Reference the Technical Specification section used; ANSWER: .(2.0)' 3 E
Place one.channei in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ( . 5) .
AND Be in. Condition 2 with MSIV's*and MSL drains closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (.5) ..
'
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Be in Condition 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition 4 in next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (1.0).
T.S. 3.3.2.c
'
..
,
References Used To Answer:
Technical. Specifications (3.3.2.c)
EQ EEQ K/A-Reference: (223001/ Generic 5) 3.1 4.1 Lesson Plan Reference:
LOR 88-02-B Objective - 6
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'S'ac tion ' B : _L ,imits ind Conditions -~ Answar Key: ,
..PagsE8 of 12-l
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Ouestion 8 (1.0)
,
- , a.+
The plant experienced a transient and the following is observed:
~
J o Suppression Pool Temperature' increases to 130 F.
,.
.
o Suppression-Poolilevel decreases'to 14' feet.
l
.-
lo ' Reactor > Pressure is 1000 psig.
a
% q
- Answer YES or NO to the following and include reference, section,' and' -
.
]
= applicable step to answer the' question. ,.
l (0.5) a. Is there sufficient NPSH for RHR and Core Spray Pumps?
(0,5) =b. Is suppression pool heat capacity sufficient?'-
n'
'
. ANSWER: (1,0) y a. Yes . ( .25),: T-102 Curve SP/L-2. ( .25)
$ 'b. Yes (.25), T-102, you are-in the safe region on curve SPL-1 (.25)-
.
_
Note: Candidate must use heat' capacity curve (SP/T-1),..and NPSH 3 M curve (SP/L-1.)
y lieferences Used To Answer: ,
T-102 v
- -
LQ S.EQ K/A Reference: (223/001/A1.08) 3.5 3.6 (223/001/A1.09) 3.5 3.6 (223/001/A2.11) '3.6 3.8 (223/001/A2.'12) 3.7 3.8 (219/000/A1.01) 4.0 4.0 (219/000/A2.13) -
3.5 3.7
Lesson Plan Reference:
'
LOR-87-04-C l
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- Sachien'B: [Li2itancnd'Cenditiens 'An: war Kay Pego 9 of;12'
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Ouestion 9.. ( '. 7 5 ) ' '"
- Afsudden~ increase in'Drywell Pressure prompts entry'into OT 101',LHigh 1 Drywell
- Pressure It ha's been determined that venting the drywell is-
~
. necessary. j Th'e following conditions exist:
.
.
Drywell pressure 'l.5 psig ;w
+
Suppression pool' pressure - 0.2 psig Suppression pool air; temperature - 125'F
r Drywell temperature -f130'
'
"'*
DeterminetheMinimumDrywellPressureallowed'afterventing$s' commenced. '
(Assume DW temperatures remain. constant.)
ANSWER: (.75)' #
r ,,
Minimum Drywell. Pressure-allowed is approximately ;25 psig. *
- (Enter Table 1~with the values of' suppression pool pressure and air temperature and read off corresponding value of. suppression pool N2 mass,.
rounding downwards.) *'
(Using Figure 1, enter the curve with.the closest (but not greater'than)~
value of suppression pool N2 mass.).
References Used To Answer:
OT-101, High Drywell Pressure (Step 3.9.2 and:3.9.3)
EQ EED y
K/A Reference: 295009 (Generic 12) 3.8 4.4 i
Lesson Plan Reference: l l
LOR-8706-C
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t 4.5 x
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Scctien B: Limits cndyCan'diticn3 ..Answar Ksy Pags 10 of 12
,
.
'Ouestion 10 (1;75)-
'-
.
.
n The plant is operating at power and shift change is in progress. The '
oncoming reactor operator has called and he will not be. in due to illness.
No replacement. personnel'are available, and this isLyour crew's'first' day back on shift following four days off.
- f' (.75)- - a. .How long can the on-duty reactor operator remain on duty?
(1.0) b. Whatinction is required'if the on-duty reactor. operator remains 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> beyond his normal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift?
ANSWER: (1.75) s lh .
a. The RO.*,at remain on duty.for 8 additional hours-(.75) (or a total of 16 ho ,.s) '(not required -i per A 40, Section .5.1.2.1)
-
b. The RO should be periodically relieved (.5) by Shift Supervision.
This relief must occur prior to exceeding (.25) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (.25) of
.
!
duty at the control boards (not required - per-A-7, Section 5.9.7.E)
e References Used To Answer:
Administrative Procedure A-7 (Page 31, 5.9.7.e)
A-40 (Page 4, 5.1.2)
[
EQ EEQ K/A Reference: (294/001/A1.03) 2.7 3.7
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Lesson Plan Reference:
LOR-8801-C I
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3;Dc41 ,.
o<v Section B:: Li3its'cnd Canditioni -'Antwar Kay' .
Page 11 of 12 '
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Ouestion 11 (1.5)
Given the following plant parameters;
'
Reactor Pressure - 500 psig Suppression Pool-temperature - 150*F Suppression Pool Level - 20 feet and decreasing De'termine the Minimum Safe Suppression Pool Water Level. Show all work.
' ANSWER: (1.5)
THC - 1800F (.25) (From T-102 curve SP/1-1) -1500F'(.25) - 30 F ( 5)
Minimum level from curve SP/L-1 is therefore 13.5 ft. ( . 3 ft.) (.5)
' References Used To Answer:
T-102 go EED K/A Reference: 295030 Generic #12 3.7 4.4 Lesson Plan Reference:
LOR-87-06-A Objective - 6
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Section B: Limits end Conditions - Answar Key Pags 12 of 12 Ouestion 12 (1.5)
The monthly RPS "A" Manual Scram Channel Functional Test Past Performance-dates are as follows:
May 15 June 15 July 16 Today is August 31 and you have just been informed that this test has not been performed this month. Is the equipment associated with this surveillance test OPERABLE or INOPERABLE at this time? State the reason for your answer and state any actions required by Technical Specifications.
ANSWER: (1.5)
INOPERABLE (0.5), due to testing intervals exceeded Tech. Spec. Surveillance requirements (0.5) and place that trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (0.5).
(Technical Specification 3.3.1)
(Surveillance requirements may be exceeded by up to 125%. This surveillance was exceeded by over 130%.)
References Used To Answer:
LCS Technical Specifications (4.0.2)
EO SRO K/A Reference: (212/000/ System Generic *5) 3.8 4.5 Lesson Plan Reference:
LOR-88-01-A Objective - 9
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ATTACHMENT 5 L- PHILADELPHIA ELECTRIC: COMPANY (IMERICK GENER ATING STATION P O. BOX A SAN ATOG A, PENNSYLV ANI A 19464 (215) 3271200, EXT. 3000
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February 3,1989
,,, m o y, , ,
,, ...:".:::::::',,,,,..
.Mr. Robert M. Gallo, Chief Operations Branch Division of Reactor Safety.
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA~ 19406
Dear Mr. Gallo:
Enclosed are the formal results of the grades, pass / fail status, identified areas'of weakness and planned corrective actions for the set of Licensed Operator Requal- (LOR) Examinations conducted at Limerick Generating Station' Units 1 and 2 for the week of November 28,'1988.
Overall, all those licensed personnel who took these exams satisfactorily completed this evaluation process except for one reactor operator who ' ailed his simulator operating examination. This operator has been removed from licensed duties and is presently undergoing an extensive re-training program prior to his reassignment to the shift as a licensed operator.
Thank you for the courtesy that you and your examining staff showed during your parallel evaluation effort during that week.
"Any questions with these results should be directed to my Superintendent-Training, E. G. F.irth, at extension 2080.
Very truly.yours,
'
.
.
EGF:mgd Enclosures c.c. M. J. McCormick, Jr.
J. Doering L. A. Hopkins E. G. Firth R. A. Nunez
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AREAS OF IDENTIFIED WEAKNESS 1. (R0 only) System interrelationships between the Diesel Generators and the Emergency Service Water System 2. (R0'& SRO) System interrelationships between the Automatic Depressurization System and the Instrument Gas System 3. (SR0 only) OT-101 (High Drywell Pressure) procedure usage 4. (R0 & SRO) Control Room Communications o Inconsistent use of definitive statements by R0's and SR0's.
o SR0 did not ensure all commands carried out as '
ordered.
o Improper R0 reports to SRO.
o Some specific alarms not identified by R0 and SRO.
o SR0 volume not of sufficient volume to be heard by all. Main Control Room personnel.
5. (R0 only) Control Board Manipulations o R0 had difficulty in manipulating EHC Load Set. )
i o R0 had difficulty operating RHR valves with LOCA l signal present.
o R0 started HPCI without operating vacuum pump. l o R0 misoperated HPCI valves during HPCI ST. j o R0 difficulty in starting suppression pool cooling !
promptly. !
o R0 improper verification of RFP discharge valve closure. !
6. (R0 & SRO) Awareness of Key Plant Parameters j i
o SSV unaware of rapid suppression pool pressure increase.
-
l o R0 dif ficulty locating containment parameter indications when normal indication lost due to LOCA j load shed. l
.
i o R0 showed improper attention to level during rapid I level increase. j o Reactor level changes
, -n, ca -na not identified from R0 to SR0 ;I
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7.;(R0 & SRO)- 'RPV High' Level. Control'
.o timproperly; controlling RPV level after Reactor ~ scram to' ensure no steam' line or. turbine damage. .
o ReactorLhighilevel'not identified by R0/SR0 until
. trip for high. level occurred.
8.-(SR0 only) T-102 Step DW/P-5 (Suppression Pool Spray) procedural-step ._. interpretation .
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' CORRECTIVE ACTION
' Items 1, 2,~ 3 will be addressed in LOR Cycle 89-01 Training set for:
completion no'.later than June 12, 1989.
Items 4, 5, 6, 7 will be identified as common student errors in 1989 LOR Simulator Training Scenarios,'and stressed during simulator training within the entire 1989 LOR Program.
>
Item 8 will be addressed during LOR Cycle 88-06 Training on. TRIP procedures set for completion no later than March 6,1989.
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___ _-____-__- _ __ _ _ __- -
_ _ _ _ -
, -
CodeNa Tm -
ComW dad Sec. Sec. Written Sim. s JM ITEM NO.(S) A B Exam Exam "* C "" 'I *
Overall Pass ' Fail 10 #conect/1G i
DATE m w. ws, a l
Of E WC P- A 90.4 100 94.4 P 10/ 19/
""*
10 20 I m ww w. m Ge rmTct 6 86.8 81.8 84.7 F 10/
' '"* 14/
10 20 m wswe a cfERAtoa C 94.3 95.6 94.8 P 10/ 19/
soc ac ec 10 20 m w. ww. m CPcRATcr_ D 92.8 92.6 92.7 P 10/ 16/
""*
10 20 i
m w w. m CFER6Tec. 6 93.6 95.3 94.3 P 10/10 19/20 uu, .- W e
m LAE., WW. m
{pF 95.7 85.6 91.3 P 10/ 19/
10 2(
w w. we. m ofERArea G 94.7 91.1 93.1-soc u en P 10/ 17/
10 2(
m w. ww m OPEMTcR H 84.0 75.0 80.1 soc e m P 10/ 19/
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ATTACHMENT 6
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PHILADELPHIA ELECTRIC COMPANY'
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. LIMERICK GENER ATING STATION P. O. BOX A -
SAN ATOG A, PENNSYLV ANI A 19464 ~
December 16, 1988 Mr. Allan Howe-
, Senior Operations' Engineer U.S. Nuclear Regulatory Commission Region 1, dale Road 475 Allen King Prussia, PA 19406
Dear Mr. Howe:
During the recent licensed requalification exam several concerns were identified. The following two items are described below with the resolution:
1) During implementation of procedure T-102 there was-uncertainty exhibited by operators concerning step DW/P-5 which states "Before.. suppression pool-pressure-reaches 10'psig, spray the suppression pool." The-question was whether the suppression pool sprays should be initiated if suppression pool pressure is equal to or greater than 10 psig.
To resolve this issue Trip Procedure step T-102 step DW/P-5 has been clarified in the attached memo OPS-
~0675. This memo has been distributed to all licensed operators'at Limerick. Training on this item will be.
incorporated in the next requalification cycle. !
2) It was observed that the -operator 's ability to implement T-214 an:3. T-215 would'be greatly enhanced with the addition of operator aids identifying the appropriate cabinet and equipment to be operated.
The attached memo describes those actions which have been completed to resolve this concern. l If you have any questions or concerns please do not hesitat'e to contact Larry Hopkins or..myself.
l Sincer ly, ,
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M. J. McCormick Plant Manager LAH/smk Attachments p3 g)gJ
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s. 7 . LIMERICK! GENERATING STATION-Ap * 4' '
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Plant" Division ~ "
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Technical Section'
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December- 13,11988'
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.FROM:: K.'J. Walsh
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SUBJECT:; T-102, T-214, and T-215; Implementation; Improvements i. ,
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Th'e f fo11owing actions 'have been completed to . address '-NRC A ,
examiner concerns. expressed during-the-exit 1 interview of 12/5/88,:
regarding T-102 step DW/P-5,.T-214, and T-215. ,
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- T-102: Bases has been revised to clarify the' term ?. ?
"Before" in theitwo applicable' steps.(i.e. DW/P-5 ^6.?
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5i and SP/T-8).
- T-214:(Manual' Initiation of ARI) hasi.been revised.,..
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toidesignate the appropriate bays.in the procedure-
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as .well' as' therkeys necessary :to open those ? bays.
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. T--215 (de-energization of Scram Solenoids) has - had ." *
1avender. fuse.: labels applied to.the C71-F14A (B) '
' fuses in Units 1 and 2, 609'and'611 panels (RPS).
The procedure, T-215, has been' revised to.2 designate the specific bay that.contains V,
R
. .The appropriate. cabinet' bays h.the fuses.
ave been labeled. 1 (i.e.' Bay A, Bay B, etc).
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In addition to'the above' items when T-102 Bases was revised,.
I the. concern with SPOTMOS sensors azid suppression ' pool level was -
' addressed in both SP/T and SP/L'(Low) branches.
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K. J. Walsh Performance Engineer PBG:mbg .
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?3 ' memo 121388.4:550 y !
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', LIMERICK GENERATING STATION '
Plant Division Operations.SectionL 4 1 OPS-0675 December' 13, 1988
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FROM: L.ah. Hopkins I
TO: E. Firth V
l SUBJECT: T-102 Step DW/P-5
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l Step DW/P-5. states, "Before suppression pool pressure i-
- reaches 10 psig, spray'the suppression pool." The intent of the step is to mitigate the primary containment pressure l-
.r rise. The definition of the term, "before", is, "any time prior to",,which is not to be interpreted as preventing
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- stated. action, "after". For example; step RC/Q-48 reads,
- "If not. shutdown with rods, then' inject SLC before
' suppression pool temperature reaches 110 F.". Should-O suppression pool temperature increase to lil F and SLC
.
- -hasn't been-initiated,-the operator should.still start boron l, injection.
i.~
- Changes have been initiated to remove the ambiguity of,
"before", by clarifying in the bases'of T-102, T-101, and TRIPS Bases Introduction,;the intent.of the~ term.
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t Please incorporate this information in the next requalification cycle. ~
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' L. A. Hopkins
' Assistant Superintendent -
Operations I PBG/smk
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PHILADELPHIA ELECTRIC COMPANY o, LIMERICK GENER ATiNG STATION P. O, BOX A ' j SAN ATOG A PENNSYLV ANI A 19464 -
December 23, 1988 ;
Mr. David J. Lange, Chief BWR.Section Operations Branch Division of Reactor Safety U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA .19406
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Dear Mr. Lange:
During.the Limerick Licensed Operator Requalification examination administered during the week of 11/28/88, some
' examination questions were used which did not directly
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relate to learning objectives for Licensed Operator <
Requalification Training for the past. year.
Due to the transition to the new format for testing as outlined in ES-601,, the Limerick Licensed Operator Training program is in'the process of converting to the "open reference" testing format. This transition had not been fully implemented prior to the annual examination process in November, 1988.
Previously, Licensed Operator Requalification learning objectives had not been geared'towards the open reference type of examinations. This resulted in a shortage of objectives which could be used as a reference for "open reference" questions.
The Limerick LOR Training section has fully implemented the conversion of future learning objectives to those which will support "open reference" examinations; thus, the need to use non-objective based questions on annual examinations will be reduced in the future.
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Sincerely,
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E G "7J } k )_6y 7..poucdF M ,
perintendent-Training tex '
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