IR 05000029/1989003
| ML20246G180 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/09/1989 |
| From: | Eselgroth P, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20246G177 | List: |
| References | |
| 50-029-89-03OL, 50-29-89-3OL, NUDOCS 8908310244 | |
| Download: ML20246G180 (83) | |
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U.S. NUCLEAR REGULATORY. .,0MMISSION REGION I 0PERATOR LICENSING REQUALIFICATION EXAMINATION REPORT -
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REQUALIFICATION EXAMINATION REPORT NO.' 50-029/89-03(01.-RQ)
FACILITY DOCKET NO.50-029 FACILITY LICENSE NO. DPR-3 LICENSEE: Yankee Atomic Electric Company n
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FACILITY: Yankee Nuclear Power Station EXAMINATION DATES: June 20 - 30,.1989.-
EXAMINERS: Larry Briggs,: Senior Operations Engineer Pete Isaksen, EG&G Bobby P er, E *
CHIEF EXAMINER: ,
,/ Eh Jam 6s Pre 11,'S'enior Operation's Engie eer
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APPROVED BY: [ M -
fMff Peterfselgroth/phief, PWR Section ' Date SUMMARY: Requalification written examinations.and operating tests were administered to six senior reactor operators'(SR0s) and six reactor operators (R0s). Three SR0s and six R0s passed these examinations. Three SR0s failed one or more portions of the examinations. The three SRO failures were all i- Shift Supervisor ._.
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l DETAILS-TYPE 0F EXAMINATIONS: Requalification H
1 EXAMINATION RESULTS:
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l l- l Pass / Fail- l . Pass / Fail l Pass / Fai l.
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'These results reflect 100% agreement between the facility and NRC evaluator . PERSONS CONTACTED:
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Yankee Nuclear Power Station Personnel
- Russell Clark Manager, Training
- Michael P. Des 11ets Operations Instructor
- Bruce L. Drawbridge Vice President & Manager of Operations
- Tim Henderson Assistant Plant Superintendent
' *Karl Jurentkuff Manager, Plant Operation * Leonard J. Laffond Operations Instructor
- Gregory A. Maret Assistant to Plant Superintendent
- Norman St.Laurent Plant Superintendent
- John Verbillis Operations Instructor
- David H.. Whit Operations Training Supervisor
. Nuclear Regulatory Commission
- Michael T; Markley Resident Inspector
- Denotes those present at the exit meeting conducted on June 30,198 _ _ - _ _ _ - _ - - _____-____-_--_-___- _ _ __ _
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- 3. . PROGRAM EVALUATION RESULTS:
3.1 Overall Ratingi Satisfactory The facility program for licensed operator requalification training
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.was rated satisfactory in accordance with.the criteria established l in ES-601, '! Administration.of NRC .Requalification' Program. Evalua-lL tion." Those criteria are:
,, Ninety percent pass / fail decision agreement bctween the NRC and the facility grading the. written and operating examination As'noted in paragraph 1. above, there'was 100% agreement on this criterio At least 75%.of all operators pass the examination; not including individuals selected who had previously passed the examinatio NRC grading is the only consideration for this criterio '
There were no individuals selected who had previously passed
.the. examination. Nine of twelve. operators (75%) passed the examinatio There shall be no more than one crew failure during the simulator portion of the operating examination, although the failure of one crew MAY cause the program to be considered unsatisfactor NRC grading is the only consideration for this criterio Three crews were evaluated and all three crews passed the simulator portion of the operating examinatio The requalification program meets the requirements of 10 CFR 55.59(c)(2), (3) and (4) or is based on systems approach to trainin The licensee's requalification program met these criteri .2 Programmatic Strengths and Weaknesses The following strengths and weaknesses were note Strengths:
The facility instructors did a good job of identifying indivi-dual and crew strengths and weaknesses which occurred during the scenarios. They also did a good job of relaying these strengths and weaknesses during the post-scenario critique .
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The' training department did a good job of planning'and admini-stering all phases of the requalification exam. .This was'
especially noteworthy since the simulator portion of-the exam was conducted at a facility near Chicago . Illinois:(Zion) on a simulator whose layout was totally different from the licensee's control room. Both the written and operating phases of the exam went as planned or when minor problems developed they were quickly resolve Weaknesses:
The principle weakness noted was not directly related to the training. department or the operators who were being examine Inadequate and poorly written plant operating procedures were found to be a source of confusion and inaccurate information as indicated below:
Indexes were found to have inaccurate references and were not'always correctly cross-indexe Inforn.ation found in reference material used in respondin to written questions was not always consistent with the informa-
. tion found in other, equally applicable, reference materia SR0s showed a general lack of familiarity with procedural use during performance of the Job Performance Measures (JPMs)
and simulator exams. This lack of procedure familiarity coupled with poorly written procedures was the main contributor to the three SRO failures. .The format, for example, used in OP 3300,
" Classification of Emergencies", was found to be poorly struc-tured and cross-referenced. This was directly attributable to the failure of one SRO operator. The particular scenario in question was a loss of both feedwater and emergency feedwate The SR0 referred to Event Number 15, " Loss of Feedwater" to classify the event. However, Event Number 15 does not have any
. emergency action levels for either " Alert" or " Site Area Emergency." The " Unusual Event" emergency does not address loss of both emergency feedwater. The " General Emergency" addresses loss of both feedwater and emergency feedwater, but only after an extended period of time where core melting would occur in a few hours if feedwater is not restored. The SRO realized he had an emergency higher than an Unusual Event, but less than a General Emergency. He, therefore, referred to Event No. 22. " General Events", and classified the emergency as an
" Alert", based on Shift Supervisor's opinion. Instead, the SRO should have referred to Event No. 7, " Loss of Ability to Reduce Operational Modes"'and classified the emergency as a " Site Area Emergency", based on no feedwater and no emergency feedwate There was, however, no reference in Event No. 15 to Event No. 7, so the SR0 failed to refer to the proper Event numbe _ _ _ - _ - - _ - _ - - _ _ _ _ _ _ _ - _ - - _ _ . . .
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' Note: At the' June 30, 1989,'NRC exit meeting, the Vice-President'&
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Manager of Operations committed to establishing an.0perations Support Group whose task would be to review and revise all operating proce-dures to be consistent with the plant design and normal operation This group would consist of licensed operators and engineers familiar.
L with plant conditions.
L 3.3 General' Observations: Simulator portion of the exam:
All three crews demonstrated proficiency in the use and know-ledge of Technical Specifications and the Emergency Operating-Procedures. The crews were able to quickly recognize the entry conditions into the Emergency Operating Procedu'res (E0Ps)'and the symptoms related to plant casualties and equipment malfunction Generally, communications between the crew members were timely and professional. There were instances however where the communications broke down. These instances mostly occurred where the SR0 failed to read the Precautions or Limitations found in the Emergency and Abnormal Procedures to the rest of the cre Overall crew performance during the scenario portion of the exam was very good. This was in spite of the fact that newly revised E0Ps had been issued just two weeks prior to the exam and the operators were tested on a simulator whose main control boards layout was very different than that found in the plan Walk-through portion of the exam:
All the operators did a good job of discussing the expected results of actions taken during a JPM. The facility evaluators also dic a good job of contro11ing and administering the JPM Handing the operators a copy of the initiating cues used in many of the JPMs was'a posiLive action which helped assure that the operators had a good understanding of the initial condition A weakness was noted with the Shift Supervisors performance of the JPMs. Two of the three Shift Supervisors failed the JPM Although these failures may have partially been caused by the poor procedures as discussed in paragraph 3.2 there were also indications of plant unfamiliarity with component location Note: The licensee indicated that in the future SR0s will be required to perform more plant tour _ _ _ _ _ _ - _ _ _ - _ - _ _ _ _ _ - _ _ - _ _ _ _ - _ - _ _ _ _ _ _ _ _ - _ _ _-
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, Written exam:
The static simulator portion of the exam was slightly too long in comparison with the limits and' controls portion of:the exa The. static' simulator portion of the exam consisted of 20 questions worth 14.65 points, while the limits and controls portion of the exam consisted of 16_ questions worth 8.4 point This caused:the overall written exam results to be slightly scewed toward the static simulator portion where the results tended to be poore Some of'the questions. developed for the written examinations did -
not elicit the expected answer. This partially contributed t the one SRO failur There were a couple examples.where " double jeopardy"' type questions were used. Thus, an operator who missed the first question also missed the follow-up questio Overall, both portions of the written exam went as planned with few problem . EXIT MEETING On June 30, 1989, at the conclusion of the requalification examination, the NRC conducted an exit meeting. Those facility personnel in attend--
ance are noted in paragraph 2 of this report. Examination development
.and conduct, general observations noted during the exam and programmatic strengths and weaknesses were discussed. At the exit meeting, the licensee provided the NRC with the final requalification test results for each candidat Attachments: Written Examination and Answer Key (R0 & SRO had same exam) Simulator Examinations (cover sheets only)
l Job Performance Measures (cover sheets only)
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l , * 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
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SCENARIO NUMBER: 1
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SCENARIO #1:
MCB PANALARMS:
(N-A21) " CHARGING PUMP AUTO START" , followed shortly by:
(N-A24) " MAIN COOLANT LOW PRESSURE" (N-A23) " PRESSURIZER LOW PRESSURE" (N-C45 and 48) "MCS LOW PRESSURE REACTOR TRIP TRAIN A" (and B)
(N-A6) " REACTOR SCRAM" and other accompanying alarm REACTOR / MAIN COOLANT SYSTEM: .
Reactor Power: 1x10E-7 IR Chan. 1 and 1.5x10E-7 IR Cha ,
MCS Tave: 515*F, PZR Level: 70", Charging Flow: 95 gpm, Bleed Flow: 20gpm, MCS Pressure (Loops 1-3): 1700psig decreasing, MCP Status: #1 and #4 operating, Highest Core Exit T/C: 520*F, Trends: PZR Level steadily decreasing, MCS Tave has decreased from 532*F to 510*F following scram and is slowly increasein CONTAINMENT: Press.: 1.3 psig, Temp.: stable, Humidity: stabl SECONDARY SYSTEMS: Turbine Throttle Vlvs: closed, BFPs: tripped, SG NR Ievel(#1): +15", SG Press.(#1): 830 psig, SG NR Levels (#2,3, & 4): -10", SG Press.(#2,3,& 4): 760 psi PROCESS RADIATION ALARMS: Air Ejector (150,000 cpm increasing)
AREA RADIATION ALARMS: None(all stable)
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QUESTION NUMBER 1 SCENARIO: 1 0.75 POINT (S)
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QUESTION FOR SCENARIO QUESTION:
A. Using the information provided, identify the Steam Generator with the ruptured tube (s). (.25)
B. In addition to the information provided, list two(2)
other parameters which could be used to determine the S/G with the tube rupture? (.5)
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QUESTION NUMBER 2- SCENARIO: 1 0.5- POINT (S) l
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QUESTION FOR-SCENARIO l
QUESTION:.
Assuming the plant is at the conditions stated, and no operator action has been taken, except to initiate E-O'. At what step
'of E-0 would the operator transition out(.25), AND to what procedure (.25)?
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______________________ __________ _______________________________ . QUESTION NUMBER 3 SCENARIO: 1 0.5 POINT (S).
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- QUESTION FOR SCENARIO QUESTION:
If the Safety Injection System:is manually actuated at a MCS Pressure of 1700 psig g the MCS depressurization rate will-increase until SI initiates and flow is achieved'.
What automatic feature of'the SI System will~ increase this initial MCS depressurization-rate?
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QUESTION NUMBER 4 ' SCENARIO: 1 0.5 POINT (S)
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-QUESTION FOR SCENARIO l '. I
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DU'-STION:
In accordance with Step 20 of EOP E-0, verification of proper
.SI System valve alignment is performed satisfactoril What subsequent change to this alignment will be required by procedure in response to this accident?
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QUESTION NUMBER 5 SCENARIO: 1 POINT (S)
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. QUESTION FOR SCENARIO QUESTION:-
Procedure E-3 is in progres Assuming the Safety-Injection System has actuated and all six(6)
SI Pumps are operating with MCS Pressure. presently at 1600-psi Determine which, if any, Main. Coolant Pump (s) must be tripped under.these conditions (.5) (Assume all other parameters are as given).
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SCENARIO #2:
INITIAL CONDITION:
l THE' PLANT WAS IN THE PROCESS OF RETURNING TO POWER AFTER A REFUELING. THE TURBINE WAS PHASED ON THE LINE AND BROUGHT TO A MINIMUM LOAD OF APPROXIMATELY 14 MWe AND HOLDIN THE FOLLOWING ALARMS ANNUNCIATE IN THE CONTROL ROOM:
(N-A19) MAIN COOLANT LOOP 1, 2, 3, & 4 DP LOW FLOW (N-A25) 2400 VOLT MOTOR (N-A31) 2400 VOLT MOTOR AUTO TRIP (N-C3) MC LOW FLOW SCRAM (T-A34) 2400 VOLT BUS SECTION 1, 2 OR 3 OVERLOAD OVER CURRENT THE OPERATOR CONFIRMS THE ALARMS AS VALID BY NOTING THAT MAIN COOLANT PUMPS #2 & #3 HAVE TRIPPE _ _ _ _ _ _ - __ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-
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QUESTION NUMBER 6 SCENARIO: 2 1.0 POINT (S)
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QUESTION FOR SCENARIO *
QUESTION:
By the given indications.'and observations, A. What 2400 volt bus is the most likely bus with the problem?
(.5)
B. Explain.(.5)
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. O.75 POINT (S).
i QUESTION'FOR SCENARIO . QUESTION:
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A.--Should the reactor have tripped automatically in.this
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',' B. EXPLAIN. . ( . 5)_ _i.
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!- QUESTION: NUMBER.-8 SCENARIO: 2 0.7.5 POINT (S):
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QUESTION:
A. Would the: boiler, feed pumps have. automatically tripped in this situation?-(.25) (Assume no operator action)
B. Explain. -(;5)
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QUESTION NUMBER 9 SCENARIO:-2- POINT (S)'
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' QUESTION FOR SCENARIO: 2.
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QUESTION:
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I' A. Would there be a'ny Technical ; Specifications acti'ons to take in this situation? (.25).
B. EXPIAIN.- (.75)
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SCENARIO NUMBER: 3
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SCENARIO #3:
INITIAL CONDITIONS:
Reactor Power: 600 MWt, Tave: 532*F, MCS Pressure: 2000 psi All other indications normal and stabl THE FOLLOWING ALARMS ANNUNCIATE IN THE CONTROL ROOM:
(N-C42) MCS Low Pressure Channel Trip Train "A" (N-C39) MCS Low Pressure Channel Trip Train "B" (N-C41) MCS High Pressure Channel Trip Train "A" (N-C38) MCS High Pressure Channel Trip Train "B"
- Main Coolant System Loop 2 pressure channel meter indication on the MCB indicates off-scale lo All other loop and pressurizer pressure channels indicate normal and stabl The reactor does not scra Safety Injection does not auto-initiat _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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, tw s-QUESTION NUMBER.10 ' SCENARIO: c3= . 1. 0 : - POINT (S) .
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QUESTION: .
Diagnose'this occurrence and-determine the most probable initiating '- event. - (1. 0)-
(Include' specific-discussion of your-reasoning)
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QUESTION NUMBER 11 SCENARIO: 3 1.0-
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QUESTION FOR SCENARIO '
QUESTION:-
Discuss whether the following systems responded as designed under these" conditions ~. (Include instrumentation logic, setpoints not required)
A. Reactor Protection System. (.5) - _
B. Safety Injection System. (.5)
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QUESTION NUMBER 12 SCENARIO: 3 0.5 POINT (S)
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QUESTION FOR SCENARIO QUESTION:
l Write.an "X", in the line provided, next to the letter of the I selection which best answers the following questio What Technical Specifications Actions are required under the given conditions? Be in at least HOT STANDBY within one hour and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> STARTUP and POWER OPERATION may proceed provided the inoperable channel is placed in trip within an hou Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> .D . No Technical Specifications Actions are regoire _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _
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QUESTION NUMBER 13 SCENARIO: NONE POINT (S)
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- THIS QUESTION HAS NO ATTACHED SCENARIO. **
QUESTION:
Write the letter corresponding to the statement which best completes the following statement. With the plant operating at full power, the bleed line temperature is observed to be decreasing several degrees per minute. The bleed line flow indication has remained the same as prior to this temperature decrease, and the bleed line radiation indication is decreasin The most likely cause of these conditions is:
A. Tube side failure of a feed and bleed heat exchange B. Shell side failure of a feed and bleed heat exchange C. Bleed line rupture between the feed.& bleed heat exchangers &
the bleed line flow transmitte D. Inadvertent closure of LCV-TV-222.
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QUESTION NUMBER 14 SCENARIO: NONE __-___-___--____-____-__--__--___--__--____-___---__ POINT (S) -_-_--__
- THIS' QUESTION HAS NO ATTACHED SCENARIO. **
QUESTION:
Diagnose the following situation and determine the most probable initiating event.
,. -While the plant is operating at 100% power, the #1 Main Coolant l Pump-Low component Cooling Flow alarm (N-B2) on the Main Control Board (MCB) annunciate The main coolant pump (MCP) bearing temperature indications l on the main control board indicate stable temperatures for MCP's 2, 3 and 4.While the #1 MCP bearing temperature is is decreasing slowl The Component Cooling Surge Tank Level is decreasin _ _ _ _ _ - _ - _ - _ _ _ - _ - - _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _- - _ - _ _ _ _ - _ _ _ _ _ . - . - _ . _ _ _ __ ___ __ __ ___- ___ _
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l * 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
__________________________________________________________________
QUESTION NUMBER 15 SCENARIO: NONE 0.8 POINT (S)
__________________________________________________________________
l
- THIS QUESTION HAS NO ATTACHED SCENARIO. **
j QUESTION:
During normal full power operation, the auxiliary operator reports the following tank levels:
-Safety Injection 27'3"
-ADD Tank 16'3"
-Primary Water Storage Tank 15.2'
-Demineralized Water Tank 6.08 l -Boric Acid Mix Tank 6'4" l
l What actions, if any, must the control room crew take in the first hour after receiving these tank levels?
(Include procedure number (s), if applicable)
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- - 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
. __________________________________________________________________
QUESTION NUMBER 16 SCENARIO: NONE O.5 POINT (S)
_________________________________ ________________________________
' ** THIS QUESTION HAS NO ATTACHED SCENARIO. **
QUESTION:.
While operating at 100% power, the " Pressurizer Low Pressure",
" Main Coolant System Low Pressure", " Reactor Scram", and " Low T Average" panalarms on the MCB annunciate (N-A23, N-A24, N-A6, and N-A42 respectively). The reactor scrams on low MCS pressure,
'
and Main Coolant System temperature and pressure continue to decreas What is the most probable initiating event?
(From the list below write the letter of the best response) Steam line' break' Loss of turbine load Loss of coolant accident Steam generator tube rupture
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- 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
..-------------------------------------------
,
QUESTION NUMBER 17 SCENARIO: NONE POINT (S)
. --------------------
t
'
- THIS OUESTION HAS NO ATTACHED SCENARIO. **
QUESTION:
While operating at 100% power, the " Pressurizer Low Pressure",
" Main Coolant System Low Pressure", and " Reactor Scram" panalarms on the MCB annunciat The reactor has scrammed on low MCS pressure L all MCS pressure channels indicate a continued decreas The " Change in Saturation Condition" pa). alarm annunciate At 1660 psig the Safety Injection (SI) system initiates & MCS pressure stablizes at 1600 psig, SI header-pressure is stable at 1550 psig & SI flow is O gp The VC pressure 3 6.9 psig, and the highest core exit thermocouple readir, e ; 5608 Determine whether the main coolant pumps must be tripped under these condition (SHOW ALL WORK and STATE ALL ASSUMPTIONS.)
. _ _ - _ _ _ _ _ _ _ _ -
,
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.*;1989 LICENSED OPERATOR REQUALIFICATION EXAM *
.
QUESTION NUMBER-18- -SCENARIO: 'NONE POINT (S):
__________________________________________________________________
' **L.THIS. QUESTION HAS NO ATTACHED SCENARIO. **
QUESTION:
Pressul-izer pressure channel' PR-P-700 receives its ' signal from pressure transmitter PR-PT-700.
I; A..If. power,is lost on PR-PT-700,' describe the effects, if any, on plant operations. (.5)
B.' EXPLAIN. (.5)
- -
.
- _ _ _ . _ _ _ __ _ _ _ . - . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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, jf . i*(1989-LICENSED OPERATOR REQUALIFICATION EXAM *-
' __________________________.._______________________________________
-QUESTION NUMBER 19 SCENARIO: NONE 1.O POINT (S)~
__________________________________________________________________
- THIS QUESTION HAS NO ATTACHED SCENARIO. **
'
QUESTION:
The reactor has been brought-to critical and reactor power has been increased to 1x10E-8 amps on the intermediate range channel The source range detectors indicate zero(0) cp EXPLAIN whether this is.as expected for_the conditions give .
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
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- 1989 LICENSED OPERAT0R REQUALIFICATION EXAM _*
-__________________________________________________________________
~ QUESTION NUMBER 20- SCENARIO: NONE 1.0 POINT (S)^
.__________________________________________________________________
'
g ** THIS QUESTION.HAS NO~ ATTACHED SCENARIO. **- '
-QUESTION:-
.During the monthly surveillance of the Electrically Driven
._',
Emergency Boiler Feed Pump, #1 pump is declared inoperable due to a fault in its controlle What, if any, Technical Specification-actions are required under these conditions? (.25)
B. Explain your answer and state any assumptions. ( .7 5)
_ ___ _____ - - _______ - ______ - -
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- 1939 LICENSED OPZRATOR REQUALIFICATION EXAM *
__________________________________________________________________
l
!
QUESTION NUMBER 21 POINT (S)
__________________________________________________________________
QUESTION:
While' frisking, you get an indication of contamination on your body. There are no RP personnel immediately available at the control poin Discuss the correct actions you should take in the situation described abov l l
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'QUESTIONINUMBER)22 . O.5e . POINT (S)
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--
l During Safety: Injection:;(SI) termination following;a! spurious;SI'
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actuation:-
- Explain in/ detail:how thel charging pumps can-be restarted
.. after: they have. beenL tripped from the SI actuation.
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- '1989 LICENSED OPERATOR REQUALIFICATION EXAM *
__________________________________________________________________
QUESTION NUMBER.23 POINT (S)
__________________________________________________________________
-QUESTION:
The plant is operating in MODE 1, 85 % powe The " Heater Drain Pump Low Pressure Auto. Start"(T-B13) Panalarm is received in the control roo The Secondary Auxiliary Operator (AO) reports:
-the Heater Drain-Pump with local control switch in "CLOSE" position has tripped due to mechanical failure and-the Heater Drain Pump with local control switch in " AUTO" position is still. runnin The Boller Feed Pumps have.not trippe WHAT is the action required by control room personnel for this situation, in order to prevent a scram?
.
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'*>1989. LICENSED OPERATOR REQUALIFICATION EXAM'*
___------___-__-___ ---___-_____--____________________----_--____-
' QUESTION NUMBER;24 1 POINT (S)
__-_-__---___________--______________-_________--_______-_________
QUESTION:
A radiation' worker needs to finish a job which repires work in a'high radiation area reading 425-mrem / hour. The job will take L , - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (All. doses are Whole Body)
l L -His current dose: for the year is 3.25 Re His current. dose for.the quarter:is.130-mre His age is.25 years ol ~
i -His lifetime. accumulated; dose'is 17 Re What external radiation exposure limits, if any, would bei i
exceeded?
,
. - _ _ _ _ - _ _ _ - - _ _
-
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- 1989 LICENSED OPERATOR REQUALIFICATION EXAM.*=
__________________________________________________________________
QUESTION NUMBER 25- 0.4 POINT (S)
__________________________________________________________________
QUESTION:
.DuringLa plant start-up from cold shutdown, a dedicated operator must becassigned to the control board prior to reaching a Main
. Coolant System temperature of 300*F to monitor Main Coolant System pressure, the status of pressurizer. heaters, bleed flow,.
and the status of the safety in]ection pumps.and the safety injection valve lineup A. WHY is the. operator assigned to monitor these parameters? (.2)~
B..At WHAT point during the startup is this operator no longer required? (.2)
!
_ _ _ _ -_-_ _--- _ _ _ _ _-
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- 1989. LICENSED-OPERATOR REQUALIFICATION EXAM *
- _________________________________________________________________ . QUESTION NUMBER 26 POINT (S)
_________ ________________________________________________________
QUESTION:
The plant :is:.at 100% : powe Following an Air Ejector Proces Radiation alarm, ' chemistry reports ^ leakage through the tubes in #1 steam generator of 0.5 gallons per. minute. Also it has been. determined:that a' leak through.the packing.of #2. loop
.T-hot isolation. valve is up to 2.5 gallons per minut '
What' actions,~if any, are. required-of the' control room crew?
.
.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
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- 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
__________________________________________________________________
QUESTION NUMBER 27 ., POINT (S)
__________________________________________________________________
QUESTION:
The plant is in Mode 6, fuel _ movement is in progres #1 spe'nt ,
'
fuel pit cooling pump is off si.te for repairs. #2 spent fuel pit cooling pump had developed a.short in.the motor and the motor burned u What alternate cooling method is available? (.5)
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-*'1989iLICENSED OPERATOR REQUALIFICATION EXAM *
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- __________________________________________________________________
QUESTION NUMBER 281 - O. 6 - POINT (S)
__________________________________________________________________
l? QUESTION:
a
, Safety Injection has initiated, and.-the. operating crew has-
..
.
-
. ,
- determined.it to'be spurious.
i State six(6) ' parameters which would be checked to. verify .it is:
-
.
} spurious. -(.1 each)
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f ' QUESTION; NUMBER'.29' O.5; POINT (S)-
n ------------------------------------------------------------------
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- QUESTION:
' The: plant has' undergone a-loss of coolant. accident (LOCA) and,is
. currently on.VC' Recirculation.
L - Determine the min'inumEflow; rate.that would be required to remove-decay heat,.' twenty-(20). hours after the acciden .
--_-_____.-.____,_._____..,_~_______
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- 1989 LICENSED OPERATOR REQUALIFICATION EXAM *
__________________________________________________________________
-QUESTION NUMBER 30 0.5 POINT (S)
__________________________________________________________________
QUESTION:
-
During full power operation it becomes necessary to make up to
.
the low pressure surge tank. The shift supervisor requests a 350 gallon blended make-up. If the Main Coolant System boron is at 1340 ppm and the safety injection tank is at 2255, the volumes to be pumped will be (choose the correct response): gal of DW and 124 gal of SI gal of SI and-124 gal of DW gal of SI and 142 gal of DW gal of DW and 142 gal of SI
_ _ _ _ -
- - - - - - _ - _ -
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- 1989 LICENSED OPERATOR REQUALIF1'.ATION EXAM *
___________________________________________.______________________
QUESTION NUMBER 31 0.5 POINT (S)
__________________________________________________________________
l QUESTION:
Due to a loss of MCS pressure, the Safety Injection (SI) System initiates automatically. The following plant conditions are observed at Step 30 of EOP E-0:
- SI tank level: 27 feet
- SI pump discharge pressure: 1550 psig
- MCS pressure: 1660 psig(stable)
- Pressurizer WR level: 50 inches
- SI flow rate: 0 gpm
- Feed Water flow rate: 90 gpm
- MCS subcooled margin: 26 *F
- VC Pressure: 6 psig WHAT procedural step should be performed next? (procedure # and step # must be included in the answer)
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- .1989' LICENSED OPERATOR REQUALIFICATION EXAM * 1
__________________________________________________________________
QUESTION NUMBER 32 0.5 POINT (S)
__________________________________________________________________
l QUESTION:
. .
The plant.is in MODE 6, with fuel movement in progres During-operation of the spent fuel pit cooling system a-pipe ruptured
'in the system in the cubicle are Explain why.this accident will not cause the. uncovering of fuel stored in.the upper racks of the spent fuel pi _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - - _ _ _ _ _
_ _ - _ _ - _ _ . _ _ _ _ _ - - . . - _ _ . , . _ _ _ - _ _ _ _ _ _ - - _ _ . _ - _ . - _ _ _ _ _ . - - _ _ _ _ . - - _ - _ . _ _ _ _ _ _ . - _ - _ _ - - _ _ _ _ _ - _ - _ _ - - - - .
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- 11989' LICENSED OPERATOR REQUALIFICATION EXAM * -
__________________________________________________________________-
QUESTION NUMBER 33-. POINT (S)
__________________________________________________________________ q QUESTION:
The. plant is in Mode 6 refueling when the control room receives a' low level alarm on the shield tank cavit Personnel in the Vapor container report the level of the cavity is dropping rapidly. The control room operators initiate make-up to the cavity but can not keep up with the level. drop.
'
Based on the above information, what emergency classification, if any, should be declared? Include the event number, if applicable.
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- 1989 LICENSED. OPERATOR REQUALIFICATION EXAM *
.
__________________________________________________________________
QUESTION NUMBER 34 1. O . POINT (S)
-__________________________________________________________________
QUESTION:
During normal. full power operations.the chemistry department informs the control room that the check valve in-#3 emergency
~ feed'line is stuck ope '
A. What actions, if'any, are' required of the. control room crew?
(.5)
'
'
B. Explain your answer. (.5)
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- '1989' LICENSED' OPERATOR':REQUALIFICATION. EXAM *
-
.
,
QUESTIONJNUMBER-35 0.5 POINT (S).
.
.------------------------------------- ..--------------------------
'f '. QUESTION:
-
' Step'3.j of OP-3018' PART A instructs the Shift Supervisortto'.
~
,
wait.at-least 15 minutes = post-scram before completing Step l-3'. 'What is the basis for this' timing requirement?
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. QUESTION: NUMBER 36_ s
'
.0.3'- POINT (S);
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Whilefoperating .the Safe Shutdown. System -(SSS) in Hot . Standb conditions, with-a' secondary pressure of:850.psig, the'SSS steam
-
'
generator level. indications-indicate 12~ feet.
l What_is-the'actualisteam generator level?
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.. . _ - . -_ .-_ .- _
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c ArMcdMENT E
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Scenario 1 -
- Generator Level Control problem -
' Loss of Vacuum Power Range #7 Fails Higp wd 7 Reactor-Scram-due-tc ! 04ech-ErrorA
.
Scenario 12 Loop *1 SGTR Loop *1 MCIV Failurc
- 3 HPSI Pump Fails to Start '
'J Crem 2
. Scenario 4 t t 5 '
' Charging Pump Failure
.
. Steam Flow Instrument Failure Turbine Vibr& tion-e- -
Reactor Scram -
Scenario 9 Large Break LOCA
'
Transfer to VC Recirculation Loss.of Emergency Coolant Recirculation Crem 3 7 -
r Scenario 8 Total Loss of Service Water '
s ATWS '-
Small Break LOCA Scenario 15
. Loss of.Feedwater Reactor Scram Loss of Emergency Feedwater .
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[ SYSTEM: .Nuclehr.-Instruments o
TASK: : iAdjust gain: potentiometer ,
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- OPERATOR'S NAME: -
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Print .
- ORGANIZATION:
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The operator's. performance was evaluatedLagainst the standards. contained-
'in this'JPM and determined:to be: (Circle One)L SATISFACTORY UNSATISFACTORY *
- Reason,-if unsatisfactory:
' OPERATOR'S SIGNATURE:- (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
' EVALUATION LOCATION:
CONTROL. ROOM PLANT OTHER SIMULATOR MOChTP APPROX. TIME: '10 minutes JTA: RO IV.L-8, 7, 3 REFERENCES: OP-4201, Rev. 16 KA REFERENCE (S): 015-000-A4.02 KA VALUE: RO SRO b-1-
. _ - - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _
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' SYSTEM: Safety Injection System TASK: Makeup to the SI accumulator OPERATOR'S~NAME: SSN:-
Print POSITION:
EVALUATOR'S NAME:-
' ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained in this JPM and determined to be: (Circle One)
-
SATISFACTORY UNSATISFACTORY *
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 15 minutes JTA: RO IV.F-2, AO IV.E-3 REFERENCES: OP-2650, Rev. 12 KA REFERENCE (S): 006-000-A4.03 KA VALUE: RO SRO Akh 62C.i2 w_
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'
SYSTEM: Safety Injection and. Containment,. Isolation System
,.
- TASK:: Realignment of.SI after spurious actuation
' OPERATOR'S'NAME:' SSN: _
?.
'
- POSITION:'-
' EVALUATOR'S NAME:
Print .
ORGANIZATION:-
If other than YAEC)
The' operator's performance was evaluated against the standards contained
.
in this JPM and determined to be: (circle One)
ve: SATISFACTOR UNSATISFACTORY *
1ry .
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
' EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:-
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX.. TIME: 40 minutes JTA: RO IV.F-6-REFERENCES:- OP-26SS,.Rev. 11, OP-3051, Rev. 12 KA REFERENCE (S): 006-050-A4.01 KA VALUE: RO SRO ;
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g SYSTEM: Main Steam '
'
TASK:. : Block auto trip'of NRV's" ,
OPERATOR'S NAME:- SSN:
Print 4 : POSITION:
l EVALUATOR'S NAME:-
Print .
ORGANIZATION: '
If other than YAEC).
The' operator's performance was evaluated against the standards contained-in this'JPM and determined to be: (Circle One)
[ SATISFACTORY UNSATISFACTORY *
- Reason, if' unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
'
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 10 minutes JTA: RO IV.0-5 REFERENCES: OP-2256, Rev. 12, OP-2105, Rev. 33
~KA REFERENCE (S): 012-000-A4.03
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[' SYSTEMI . Emergency Diesel. Generator is ' i
'
- . TASK:
. Start / load /stop. diesel' manually-- . , ,
, . OPERATOR'S NAME: . SSN : -
' POSITION: '
,
EVALUATOR'S'NAME:
-Print .
. ORGANIZATION:
-If other than YAEC)
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~in1this JPM and determined'to,be:'(Circle.One)
~
SATISFACTORY UNSATISFACTORY *
- Reason',- if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
l EVALUATOR'S. SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 20 minutes JTA: RO IV.V-1, --2 , -3
, -. REFERENCES: OP-4207, Rev. 25 KA REFERENCE (S): 064-000-A4.06 KA'VALUE: RO SRO . %a - ,
_ _ _ _ _ . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ - - - - - - - - - - - _ _ . - - - - - _ _ - - - - - - - - - -
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[4 SYSTEM:- Safe' Shutdown System l-TASK: Perform primary RO actionsifor Safe Shutdown System operation..
. .
OPERATOR'S NAME: SSN:
Print-
' POSITION:
EVALUATOR'S NAME:-
' ORGANIZATION:
If other than YAEC)
The: operator's performance was evaluated against the standards contained'
1n this JPM and determined to be: (circle one)'.
. SATISFACTORY UNSATISFACTORY *
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOChTP APPROX. TIME: 20 minutes JTA: RO IV.AC-1, 2, 3, 4
' REFERENCES: OP-3017, Rev. 11, OP-3018, Rev. 10 KA' REFERENCE (S): 194001-A1.02 VALUE: RO SRO _-_ ___
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l, -l SYSTEM:. Safe Shutdown System.
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TASK:1.' Secondary RO' actions'for.' Safe Shutdown System' Operation.
l l
l . OPERATOR'S NAME:. SSN::
Print POSITION:
,
. EVALUATOR'S-NAME:
Print ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against.the standards contained
'in.this JPM and determined to be: (Circle One)
-
SATISFACTORY ' UNSATISFACTORY *
- Reason, if unsatisfactory:
. OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE:- DATE:
' EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 25 minutes JTA: RO IV.AP-1
' REFERENCES: OP-3017, Rev. 11, OP-3018, Rev. 10 KA REFERENCE (S): 000-068-EK3.12 KA VALUE: RO SRO @
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'. SYSTEM:- . Safe Shutdown Syste P:
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cTASK: - Perform S/S. actions ' for Safe Shutdown Systeni Operation yl .
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, EVALUATOR'S NAME: ~
ORGANIZATION:
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-
.. SATISFACTORY UNSATISFACTORY *-
- t -
1 4 '
- Reason, if unsatisfactory:
I OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S~ SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT- OTHER SIMULATOR MOCKUP APPROX.-TIME: 10 minutes JTA: RO IV.AP-3 REFERENCES: OP-3017, Rev. 11, OP-3018 Rev. 10-l l- 000-068-EA1.10 KA REFERENCE (S):
..
__- - - _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - -
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'YAEC - A0 JOB PERFORMANCE MEASURE
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SYSTEM: Generic TASK: Secondary Auxiliary Operator actions when the plant scram OPERATOR'S NAME: SSN:
Print POSITION:
EVALUATOR'S NAME:
Print ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained
,m s in this JPM and determined to be: (Circle One)
!' ') SATISFACTORY UNSATISFACTORY *
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 30 minutes JTA: AO.IV.A REFERENCES: -EWAtt . 10 op ~2 cot Rrv,-Rev-O o
KA REFERENCE (S): 001-010-A2.02 KA VALUE: RO SRO ,
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AO - 042 iSYSTEM: ' Waste Disposal TASK: Dump Test Tank No. ,
. OPERATOR'S NAME: SSN: ~ ^ ~
-Print-POSITION: _
EVALUATOR'S'NAME:
Print ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained
in this JPM and determined to be: (Circle.One)
. SATISFACTORY UNSATISFACTORY *
' '
- Reason,-if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP
, APPROX.' TIME: 15 Mi JTA: AO IV. AC. : REFERENCES: . OP-2379 Rev. 1 KA REFERENCE (S): 194-000-A1.02
-
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SRO - 045
- Th)gP i; E-SYSTEM: Administration
>
TASK: Notify N.R.C. per OP-000 OPERATOR'S NAME: SSN:
! POSITION:
EVALUATOR'S NAME:
Print ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained in this JPM and determined to be: (circle One)
Jdk SATISFACTORY UNSATISFACTORY *
?'f * Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOChTP APPROX. TIME: 15 Mi JTA: SRO IV. C. l REFERENCES: AP-2016, Rev. O, OP-0008 Rev. 2 KA REFERENCE (S): 194001-A1.16 KA VALUE: RO SRO ._ _ - -_____-____________-__-_a
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SYSTEM:: Control Room Emergency Air Cleaning System
'
TASK:. . . Start the, Control. Room Emergency Air Cleaning System during an'
emergenc OPERATOR'S NAME: SSN:-
"
POSITION:
L-EVALUATOR'S~NAME:
Print .
' ORGANIZATION:
If other.than YAEC)
The operator's performance was evaluated against the standards contained in this-JPM and determined to be: (Circle One)
el *: SATISFACTORY UNSATISFACTORY *
. * Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
-EVALUATOR'S' SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP
~ APPROX. TIME: 3 minutes JTA: IV AC-2 REFERENCES: OP-2604, Rev. 6 KA REFERENCE (S):- 000-067-EA1.05
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? SYSTEM: Rod ~ Control System.-
TASK: . Perform Immediate Actions'on Continuous' Rod Motio a ,
' OPERATOR'S NAME: SSN:
Print:
!
POSITION:
,. EVALUATOR'S'NAME:
P Print .
, ORGANIZATION:
,If other than YAEC)
. The' operator's-performance was evaluated against the standards contained e
in.this JPM and determined to be: (Circle One)
- '
3 . SATISFACTORY UNSATISFACTORY *
fp a
- Reason, if' unsatisfactory:
. OPERATOR'S SIGNATURE: (REVIEWED)
!
' EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP
' APPROX. TIME: 15 minutes JTA: IV.A REFERENCES: OP-3102, Rev 8
KA-REFERENCE (S): 001-050-AB.05 KA VALUE: RO SRO ~ , .4p;g. -
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, RO!- 06 iSYSTEM: Emergency Plant) Evolutio : t ... . TASK:' Perform {operat'or action-for.an ATWAS' event.' ,
-OPERATOR'S'NAME: 1 'SSN:
Print POSITION:-
t
, EVALUATOR'S NAME:
Print .
ORGANIZATION:
.If other than.YAEC)
'
'The operator's performance was-evaluated against the standards contained
'in::this JPM and-determined to be: =(Circle'One):
.
, . , SATISFACTORY UNSATISFACTORY *
.,
_
.
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
'lEVALUATOR'S SIGNATURE: DATE:
'
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP c
APPROX.-~ TIME: 5 minutes JTA: IV.A REFERENCES: OP-2000 Em' 22-
' 9,0 4FGS-(
.Ka. REFERENCE (S): 000-029-EA1.14 KA NALUE: RO- SRO jr (;.G 1\ggy-1-m
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. . ,. JOB l PERFORMANCE MEASURE <
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,, SYSTEM: Emergency. Boiler Feedwater; System.
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?.e . TASK: : .Line up Emergency Nitrogen supply,to the. Emergency- '
Boiler Feed-Pump,(EBFP). Steam' Pressure Controlle .
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/ OPERATORS NAME: SSN:
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. POSITION:'
' EVALUATOR'S,NAME:
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. ORGANIZATION:
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,?The' operator's performance was evaluated against the standards contained in this JPM and determined to be: (Circle One)-
gft SATISFACTORY- UNSATISFACTORY *-
'* Reason, if unsatisfactory:
OPERATOR'S-SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATIO.N LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP
' APPROX. TIME: 15. Mi JTA: AO IV. Y. 7
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E REFERENCES: ECA O.0 Attachment fI I.
-KA REFERENCE (S): 061-000-A2.07 KA VALUE: RO SRO %
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-YAEC;- ' JOB' PERFORMANCE. MEASURE-
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SYSTEM: ; Safety 'Inj ection'. . ,
L iTASK:' . Manual operation of a: Motor . Operated Valve (MOV). ,
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- w LOPERATOR'S-NAME: -SSN:
- POSITION:
EVALUATOR'S NAME: ,
-Print .
ORGANIZ'ATION:
-If other than.YAEC)
-Thel' operator's performance was evaluated against the standards containe '
iLin this JPM and. determined.to be:'(Circle One)
I SATISFACTORY UNSATISFACTORY *
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- Reasonj..if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
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EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 15 Mi JTA: AO. IV. .
REFERENCES: OP-2653 Rev. 22
- KA' REFERENCE (S): 006-SG-A9
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RO - 069 a
SYSTEM: Main Steam Syste ~
TASK: Reset Main Steam Non-Return Valve (NRV) Cabinet after a Tri OPERATOR'S NAME: SSN:
Print POSITION: ~
EVALUATOR'S NAME:
Print ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained-in'this JPM and determined to be: (Circle One)
a SATISFACTORY UNSATISFACTORY *
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- Reason, if unsatisfactory:
-OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
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EVALUATION LOCATION:
CONTROL ROOM PLANT ~
OTHER SIMULATOR MOCKUP APPROX. TIME: 10 Mi JTA: RO IV. .
REFERENCES: OP-2101 Rev. 34, e zde nev. 12 o9-9too h (> 37-KA REFERENCE (S): 039-000-A3.02 KA VALUE: RO SRO [Iy;% c.i;r Qsyy f
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., ' SYSTEM:: ' Main.Feedwater System.-
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R' [ TASK:! Local Operation of Feedwater Regulating Valve (FRV).- .
[iH ' ? OPERATOR'S NAME:
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SSN:-
. Print POSITION:
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EVALUATOR'S-NAME:
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' ORGANIZATION:
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' The operator's: performance was evaluated against the standards containe 'in.this JPM-and determined ^to be: (Circle One)
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- Reason, if unsatisfactory:
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OPERATOR'S-SIGNATURE:- (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
- EVALUATION LOCATION:
L CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP-APPROX.- TIME: 10 Mi JTA: AO IV. W. 11 REFERENCES: OP-2255 Rev. 18 KA. REFERENCE (S): 059-000-A2.12 KA VALUE: RO SRO ; jg?
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YAEC - AO JOB PERFORMANCE MEASURE ,
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AO - 072 SYSTEM: Vital Bus TASK: Transfer Vital Bus to Bypass. Power Suppl OPERATOR'S NAME: SSN:
Print POSITION:
EVALUATOR'S NAME:
. ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated'against the standards contained in this JPM and determined to be: (Circle One)
L,-w) SATISFACTORY UNSATISFACTORY *
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- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 3 minutes JTA: AO IV-2 REFERENCES: OP-2502, Rev 9 KA REFERENCE (S): 062-SG-A9 KA VALUE: RO SRO hh,
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YAEC - AO JOB PERFORMANCE MEASURE }
AO - 074
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SYSTEM: Condensate and Feedwater TASK: Reset feed reg. vulve after " Position Lock" alarm is actuate OPERATOR'S NAME: SSN:
Print POSITION:
EVALUATOR'S NAME:
. ORGANIZATION:
If other than YAEC)
The operator's performance was evaluated against the standards contained-in this JPM and determined to be: (Circle One).
- 83 SATISFACTORY UNSATISFACTORY *
-kt/ * Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOChTP APPROX. TIME: 2 minutes JTA: AO IV.W-10 REFERENCES: OP-3750, Rev 9 KA REFERENCE (S): 059-000-A4.08 KA VALUE: RO SRO . Wr,
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YAEC - AO JOB PERFORMANCE MEASURE
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LO - 076
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SYSTEM: A.C. Electrical TASK: Transfer EMCC to its Emergency Power Supply.
! OPERATOR'S NAME: SSN:
Print POSITION:
i-EVALUATOR'S NAME:
Print ,
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ORGANIZATION:
If other than YAEC) s
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The operator's performance was evaluated against the standards contained 1 fm, .in this JPM and determined to be: (Circle One) !
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- Reason, if unsatisfactory: !
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OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE:
EVALUATION LOCATION:
CONTROL ROOM PLANT OTHER SIMULATOR MOCKUP APPROX. TIME: 8 minutes JTA: AO.IV.Z.1, 4 REFERENCES: OP-3256, Rev 6 I
J KA REFERENCE (S): 062-000-A4.01 KA VALUE: RO SRO k1 w
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YAEC - AO JOB PERFORMANCE MEASURE
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SYSTEM:- Control Air System TASK: Valve in Emergency Nitrogen to CC Trip Valves 205 and 2,08.
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OPERATOR'S NAME: SSN:
Print POSITION:
EVALUATOR'S NAME:
Print .
ORGANIZATION:
If.other than YAEC)
'The operator's performance was evaluated against the standards contained in this JPM and determined to be: (Circle One)
'9 [3 l-f( SATISFACTORY UNSATISFACTORY *
- Reason, if unsatisfactory:
OPERATOR'S SIGNATURE: (REVIEWED)
EVALUATOR'S SIGNATURE: DATE: 1 l
EVALUATION LOCATION- !
CONTROL ROOM PLANT OTHER 1 SIMULATOR MOCKUP j APPROX. TIME: 5 min, from CR JTA: AO IV.AG-8 l
i REFERENCES: OP-3002, Rev 15 KA REFERENCE (S): 008-SG-A9 !
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