IR 05000302/1992301
| ML20126G561 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/17/1992 |
| From: | Baldwin R, Ernstes M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20126G218 | List: |
| References | |
| 50-302-92-301, NUDOCS 9301040134 | |
| Download: ML20126G561 (10) | |
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% UP51TED STATES
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[c $g MUCLEAR REGULATORY COMMISSION
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{o gEI 101 MARIETTA STRE ET. ATLANTA,OEORGI A 30323 49 ,o
- ENCLOSURE 1
UAMINATION REPORT - 50-302/92-301 Facility License: Florida Power Corporation l
Facility Name: Crystal River Nuclear Plant
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Facility Docket No.: 50-302
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Examinations were administered at the Crystal River Nuclear Plant near Crystal River, Florid Chief Examiner: - /J/// /f u
- ' Richard S. Baldwin Date Signed Approved By
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Michael E. Ernstes, Chief A//7h 2 Date Signed Operator Licensing 2 Division of Reactor Safety SUMMARY Scope: Requalification written examinations and operating tests were administered to nine Reactor Operators (RO) and six Senior Reactor Operators (SRO) during the week of November 16, 199 These operators were combined to form three crews for simulator examinations. Additionally, a requalification written examination retake was administered to an R0 who had failed the 1991 examinatio Results: Eight R0s and four SR0s passed these examinations. All others failed. One crew failed the examination. The R0 retake passed this examination. Based upon the above results, the Crystal River licensed operator requalification program has been determined to remain rated satisfactor Generic weaknesses identified were: Use of Emergency and Dose rate calculation procedures, paragraphs . SR0s failure to identify the PORV closed, paragraph DR ADOCK 0500
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} 3. SR0s keeping crews informed of which procedure was in effect, paragraph
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, REPORT DETAllS i
i Persons Contacted i
! *G. Boldt, Vice-President, Nuclear Production j *B. Conklin, Director, Materials j *B. Hickle, Director, Nuclear Plant Operations
- *L. Kelley, Director, Nuclear Operations Training
- J. Lind, Manager, License Operator Training 3 *T. Miller, Operations Evaluator
- D. Porter, Manager, Nuclear Operations
- J. Smith, Training Supervisor j *J. Springer, Training Supervisor
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Other licensee employees contacted included engineers, instructors, j operators, and office personnel,
i Examiners
- R. Baldwin, Chief Examiner, Region II 4 *J. Nickolaus, PNL Examiner
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- D. Faris, PNL Examiner j Other NRC Personnel Attending Exit
i *A. Gibson, Director, Division of Reactor Safety
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- R. Freuder,berger, Resident Inspector, Crystal River
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- Attended exit interview
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' Discussion j Examination Results
- Licensed operator requalification examinations were administered at
the Crystal River Nuclear Plant in accordance with NUREG-1021,
Operator Licensing Examiner Standards, Revision 7. Written examin-ations and operating tests were administered to nine Reactor
] Operators ar.d six Senior Reactor Operators. One additional Reactor
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Operator-was administered and passed a.requalification retake written: examination. One Reactor Operator failed the written
, examination-. -One Senior Reactor Operator failed the simulator examination, and one Senior Reactor Operator failed the Job
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Performance. Measures (JPMs)~ portion of the operating examinatio These.15 operators were combined to form 3 operating crews for the
- simulator portion of the operating test. One crew failed the simulator portion of the operating examination.
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Report Details 2 l
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l Licensed Operator Requalification Program Evaluation
Based on the examination results, the examination team found the i Crystal River Requalification program met the criteria established l in NUREG-1021, Operator Licensing Examiner Standards, ES 601 D.2
- (Revision 7), and thus was determined to be satisfactor The facility is permitted to administer the re-examinations-for l returning those individuals that failed this examination to licensed I duties. However, these individuals must still pass a subsequent NRC
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administered examination for license renewa c, Written Examination Preparation and Administration i
The examiners reviewed the reference material- supplied by the licensee and determined it to be adequate to support the
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examination.
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The licensee supplied a-sampling plan describing the requalifi-
. cation cycle topics and the selection process used for the topics to i be included in the examination. This sampling plan was-determined
to be adequate for developing comprehensive examinations used during the requalification cycle.
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The examination team changed or substituted approximately 20 percent
- of the questions. Based on written examination review, there were-three types of changes required. These included
- (1) Total replacement of the question (accounted for approxi-
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mately 13 percent of the changes to the SRO examination and 16 i
percent of the changes to the R0 examination, due to being
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direct look-ups in the reference material),
i l (2) Changed distractors to be more plausible,
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- (3) Changed the stem of the questions to remove unnecessary l informatio All of the questions in the question bank were time validate The
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entira examination was not- time validated as a complete exam. The I- time validation was accomplished by adding the individual test item -
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validation times to determine the length of the examination. This method while in principle would appear to be valid, however, in 4 reality it was no For example, one Part A examination administered took operators 26 to 38 minutes.to complete. These times included time for review. The Part A examination is designed
. to have a time validation of 45 minutes with a 15 minute
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Report Details 3
- review perio The Part B time validations exhibited similar
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result The range of times for this part of the written examination was between one hour and five minutes to two hours. The
- Part B examination is designed to take one hour and thirty minutes l with a thirty-minute review perio Time validation of future
' examinations needs to maintain Examiner Standard requirements.
l There were two written examination questions on the SR0 examination
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and one question on the R0 that indicated generic weaknesses in j operator knowledge. These are:
! (1) One of the questions of concern appeared on both examination This question required the use of EP-220, " Pressurized Thermal
! Shock", Enclosure 1. The question dealt with a steam generator
! tube rupture in conjunction with low Tave. Seven of the
! sixteen operators that took the written exarination were unable
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to determine the required actions.
(2) The other question concerned the use of EM-204A, "Off-site P,ose-
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Assessment During Radiological Releases". Four of the si': SR0s l and three of-the ten R0s answered the question incorrectl This question dealt with the determination of dose ratr at the
site boundary based upon the . initial conditions of'a large break LOCA coincident with core degradation. The o of
- EM-204A was identified as a weakness during the imtial
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examinations given in May of 1992 as described _in the June 23,.
l 1992, examination report.
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Three questions were changed to allow accepting two answers as correct. One question was deleted due to not having a correct 3 answer. The plant curves used to determine the correct answer were
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revised and tank levels changed making both emergency diesel
- generators inoperable. This change caused the question-to have no correct answer, thus requiring question deletion, Operating Test Preparation and Administrat' ion i
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The JPMs and simulator scenarios were reviewed onsite by the examination team.during the week of October 26, 1992. The NRC-
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reviewed simulator scenarios prior to preparation week in order to
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facilitate changes in an expeditious manner. The following types of l changes were made:
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(1) The exam team deleted a number of proposed critical tasks that
- were not critical based on Examiner Standards criterie.
, (2) The exam team made enhancements to ensure critical tasks met
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the Examiner Standards, these required significant changes
! during the preparation week.
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Report Details 4
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! Two scenarios were used during the examination wee The proposed i scenarios were good in their ability to access operator performance using facility abnormal, emergency and normal operating procedure l The scenarios were designed to average approximately 50 minutes of j contact time. The actual contact time was significantly greater.
1 All the simulator times were greater than 50 minutes, averaging ;
approximately 60 - 65 minutes. One simulator crew was required to
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- run approximately one hour and fifty minutes to afford the operators 1
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the opportunity to complete all required critical task The proposed JPMs covered high level tasks being performed inside
- and outside the control room. One of the five JPMs administered to
! each operator was an " alternate path" JPM. Four of six SR0s failed the " alternate path" JPM. This was considered to be a generic-
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- weakness among SR0s. These weaknesses represent a number of l
different areas. These are:
(1) SR0s. could not verify that the PORV was closed and allowed low
- pressure emergency core cooling systems to injact into.the-I Cor l (2) There was a misunderstanding by SR0s of how acoustic monitors j work and how they are reset.
) (3) The inability of the SR0s to use the plant computer in order to-1 plot and trend PORV tail pipe _ temperature ;- Another generic weakness identified among SR0s was in the use of
- EM-202, " Duties of the Emergency Coordinator", Enclosure 3, Event Notification Worksheet. Three of the six- SR0s did not completely fill in the worksheet in accordance with the JPM requirements. As a i result, the exam team determined that~ the critical steps originally i" marked were not all critical. Performance criteria changes had to be made during exam administration.
Two JPMs had to be re-reviewed because the determination of a
- critical step (s) was not clear. The JPM performance criteria was
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modified and more clearly delineated for these JPMs. For example, if one valve used as an isolation valve was closed, then the in-series control valve being closed in the JPM was not critical and
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visa versa.
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) Report Details 5-i l
The facility is reminded that critical steps should be chosen such
- that the task cannot be completed if the step is not accomplished.
i The criteria threshold should be to such a degree that if an i operator were to fail the operating examination when more than one
- JPM is failed, there would be no dispute if this criteria was used
- for the baric for an unsatisfactory requalification program based upon JPM failures. A thorough analysis of the facili ies' JPMs is
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j warranted to ensure all JPMs adhere to this criteri I An operating crew for the simulator examination was composed of three R0s, two SR0s, and an Shift Operating Technical Advisor
! (S0TA). The SOTA that normally works with the crew was used, but j was not directly evaluated. Each crew was evaluated using two
- scenarios. Generic weaknesses identified during the simulator
examinations are noted below:
! (1) 1he SR0s, as procedure readers, did not inform the crew what i procedures they were using. They did not read cautions or l notes to_ the crew while in these procedures, t
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(2) The use of place-keeping aids by the SR0s was basically-
- nonexistent while using Abnormal and Emergency Operating
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Procedures. The method of choice of most operators was to use .
j their fingers as place-keeping aids. This was described in the 4 initial examination report dated June 23, 1992. This problem
arises from the vast number of procedures an operator must use
- to combat an event. It-is recommended that the facility j analyze the nuiaber of procedures in use- and determine if too many are in use at one time, ,
! (3) One crew used the-S0TA solely for cooldown rate =detercination i rather than one of the crew members.being assigned. The S0TA l- acted as an intricate part of the crew, r.ot an independent backup of the crew's decisions. Cooldown rates of 500'F/ minute-
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were being reported based on one minute intervals. The ANSS used this parti _cular cooldown rate'and did not combat the' event
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aggressively due to misleading information provided by the
,SOT (4) The crews did not announce starting of major equipment' to the plant 'during normal or emergency operations,
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During the simulator examinations other significant operating errors
% the crew were abserved, however, not generic to the plant. These were s-follows:
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(1) The improper use of HPI/PORV cooling. One crew used only one MVP instead of two as required by procedure.
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Report Details 6 (2) Overcooling of the RCS due to inattentive use of the turbine bypass valves (TBVs). The crew did not observe the self inflicted overcooling event with the TBVs open until pointed out by the SOT (3) The crew's isolation of a OTSG during a steam generator tube rupture event at a temperature significantly below the 540'F allowed by the procedur Administration of the examinations went smoothly and according to the facility prepared schedule. However, the run times of the simulator examinations lengthened the two simulator days beyond the expected scheduling approximations. The facility scheduling, for the most part, and close attention to examination security, was effective, Evaluation of Facility Evaluators The NRC examiners monitored the facility evaluators for their ability'to function as objective and impartial evaluator The Crystal River evaluators were knowledgeable of the requirements depicting satisfactory operator knowledge / performance evaluation and of plant system operations. . Post-scenario questioning by the facility evaluators was r.ot accomplished until prompted by the NRC examiners. Follow-up questioning on one occasion lead to more of a training session than an investigative procedure for determining what and why the operators had performed in a particular manne The NRC pointed this out to the facility examiners and this practice was stoppe Post-scenario discussions with the facility evaluators concerning simulator scenario operator performance indicated that i the evaluators were thorough and unbiased.
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Evaluators administering JPMs were effective, however, not.all evaluators performed JPMs consistently. Some evaluators read the initial conditions to the operators while others handed the operator the initial condition sheet and let them read it to themselves. JPM examinations should be administered identically to each-operator in order to prevent misunderstandings and-errors in the-administration of the JP , Procedural Problems The administration of the operating test identified the following procedural problems that require additional guidance from the Operations department to ensure all operators perform procedures similarly when guidance is not explicitly contained in the procedure:
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(1) AP-380, " Engineered Safeguards Actuation", Step 3.21, allows starting of an RCP in each loop provided adequate Subcooling Margin (SCM) exists (50*F). All three crews performed this step differentl One crew required at least 60 70*F-SCM before an RCP could be starte Another crew required a different range before they would start an RC (2) AP-450, " Emergency Feedwater Actuation", Step 3.9, implies that an RCP is required before a " DRY" 0TSG can be fed when it may not be necessar (3) AP-450, " Emergency feedwater Actuation", Step 3.9, allows a " DRY" _
steam generator be fed at less than or equal to 500 gpm. Under similar conditions not all crews- fed the OTSG at the same rate. The feed rates varied from approximately 20 gpm to as high as 220 gp l (4) Entry conditions into EP-290, " Inadequate Core Cooling," are not l well understood by all operators. Some crews entered lCC-with minus 2 to minus 3 degrees of subcooling. While other crews knew that EP- !
290 should not be entered until at least minus 20 degrees.of subcooling is identifie . Material Condition of the Plant The examiners noted one problem concerning auxiliary battery room breakers labeled incorrectl . Exit Meeting At the conclu<lon of the site visit, the examiners met with representa-tives of the plant staff, listed in Enclosure 1, to discussLthe results of the examinations. The licensee did not' identify as proprietary any material provided to or reviewed by the examiners. There_were no dissenting comments from.the license . , _ - - - - . _ _ _ .._ _.~.
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ENCLOSURE 2 SIMULATOR F10FLITY REPORT Facility Licensee: Florida Power Corporation Facility Docket No.: 50-302 Operating Tests Administered On: November 16 - 20, 1992 This form is used only.to report observations. These observations do not constitute, in and of themselves, audit or inspection findings and are not,-
without further verification and review, indicative of noncompliance with-10 CFR 55.45(b). . These o'oservations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required solely in response to these observation During the conduct of the simulator portion of the operating test, the following items were observed:
ITEM DESCRIPTION EFW valves During the performance of a JPM concerning Emergency
, Feedwater, emergency feedwater valves would not be in the i same position each time that particular JPM was
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initialized. This did not hinder the performance of the JPM.
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O ATTACHMENT 3 V/.*Jof
! k) TDP.106 Rev 13 Page 23 of 71 i
! ANSWER KEY COVER SHEET
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TRAINING PROGRAM TITLE: LICENSED OPERATOR REQUALIFICATION
- EXAMINATION TITLE: LICENSED OPERATOR REQUALIFICATION - CATEGORY A -
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! EXAMINATION NAME OR NUMBER: 1992 CATEGORY A SRO EXAM i
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DATE: " #!SA APPROVAL: Ybe ;. hul , DATE: I - /o%
()(uclear Training Supervisor
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LJ INSTRUCTIONS FOR TAKING THE EXAMINATION Use black ink or dark pencil only to ensure legible copie . Ensure your name is printed in the blank provided on the cover sheet of the examination and the answer shee . Each question has only ONE correct answer. Mark your answers on the answer sheet provided and do not leave any question blank. If additional paper is required, use only the lined paper provided by the examine . All questions are worth 1.0 poin . If parts of the examination are not clear with respect to their intent, ask questions of the examiner onl . The examination is designed to take approximately 45 minutes to complete. You will be given 1 HOUR to complete the examinatio . The questions have been time validated by knowledgeable persons. You should be aware that not every answer needs to be verified by consulting a reference and excessive usage of reference material may cause you to not complete the examination in the allotted tim . Restroom trips are limited and only one examinee at a time may leav You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromis . Cheating on the examination could result in revocation of your license and may result in more severe penaltie . 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 complete . When you are finished and have turned in your completed examination, leave the examination are p
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i SCENARIO OVERVIEW h i The unit was operating at 100% power, MOL. I&C was preforming SP 110 m the "A* RPS channel. A large steam break occurred on the OTSG-1B outside j
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the RB and upstream of the MSIVs. FWP 2B failed to trip from the EFIC FW Isolation. CAV-5 failed to close on the ES actuation. RWP-2B failed to start on the ES actuatio i i
i INSTRUCTOR NOTE: Examines must not be present during setu i I INITIAL CONDITIONS:
Initialize the simulator to 100% power MOL.
III. CONTROL BOARD SETUP: Perform a lamp check using panel diagnostic . Un-freeze the simulator, Ensure SPDS screens are selected properly for current conditions. (A Flux on left screen and Normal on right screen) Ensure computer screens are selected for proper groups for current conditions. (Group 59 on the right screen and group 108 on the left screen) Freeze the simulato . Ensure all charts are inkin . Advance and mark all chart . Advance line printer pape . Advance annunciator typer paper and remove used sheet . Un-freeze the simulator and allow to run for 5 mi . Freeze the simulato . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
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IV. SCENARIO SETUP: Fall CAV-5 open (I/F page 742) Fall Open RWP-2B breaker (1/F page 654) Prevent the B MFWP from tripping (I/F page 638) Auto trip failure / . Arm, Numbered Malfunction MS-002B ("B" MS line break),
set to . Unfreeze the simulato . Place the "A" RPS channel into " Manual Bypass" and place the test module for RCS pressure in the "A" RPS channel into Test Operate positio . Freeze the simulator and take a snap-sho . Unfreeze the simulato 's Select PZR spray valve to manual and open value full (O 1 Activate the stack when the low RCS pressure alarm comes i . Perform the following procedural actions:
a) After HPI is actuated, select P7R spray valve to Aut . Allow the simulator to run until RCS pressure is 2200 psi as indicated on the lower portion I/F screen. Acknowledge annunciator alarms and freeze the simulator ensuring that all active armunciator alarms are o PRE-EXAM REVIEW: Verify validity of Exam answer key to the frozen simulato . Resolve any discrepancie (3 v
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VI. SIllFT TURNOVEIt Recall examinees into simulator roo . Review rules of the exa . IIandout Information Sheet to each examine . Review Information Sheet with examinee . Allow examinees to perform a 5 min. walkdown of the MCB.
, Ilandout the examinatio . Announce exam start tim Time: Announce exam stop tim Time:
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O O INFOlu1ATION SIIEET INITIAL CONDITIONS:
Tl plant operating at 100% power, at 210 EFP I&C preforming SP 110 in "A" ItPS channe l TE6HSIENT DESClllPTION:
s A large steamlino/feedline break has occurred on the "B" Steam j Generator. RM A12 is out of service.
OPEllATOR ACTIONS TAKEN:
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None ELAPSED TIME:
Approximately 5 min since the rapid de pressurization of the B OTSG.
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I Test item: SSE 02/01 Lesson Plan: ItOT 5-63 Objective No.: B3 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given symptom, immediate or follow up action.
Reference: AP 380 K/A: 000 Emergency Plant Evolutions 000 Small Break LOCA EA1.18 Balancing IIPI loop flows 7'ask: 0040501002 Control Illgh Pressure injection flow rate Importance: 3.4/3.2 Expected 2.0 Time (min):
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. Test Itemt #1 (SRO A) Point Value (1.0)
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i j Based on current plant conditions, which ONE of the following ( statements correctly describes the steps required to BALANCE IIPI flows? ,
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j a) Select "llPI RC 1", "IIPI RC 2" and "IIPI RC 3" hand switches to " BYPASS"; close MUV 27 and adjust IIPI flows as
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l 1-l b) Select "IIPI RC 1", _"IIPI RC 2". and "IIPI RC 3" hand switches j to RESET"; close MUV 27 and adjust IIPI flows as necessary.
I i c) " RESET" 1500# bistables in ES channels'1,2 and 3, close MUV 27 and adjust IIPI flows as necessary.
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t j d) Close MUV 27 and adjust 11PI flows as necessary; no additional steps are required.
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Test item: SSE 02/02 Lesson Plan: ROT 5-65 Objective No.: 13 2 State the Immediate Actions of this abnormal procedur I Objective:
Heference: AP-460 K/A: 000 Emergency Plant Evolutions 040 Steam Line Rupture EA1.02 Feedwater isolation Task: 0190401002 Perform required actions for a malfunction of the EFIC system including spurious actuation and failure to actuate Importance: 4.5/ Expected Time (min): .
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Based on current plant conditions, which ONE of the following statements with respect to the "B" Main Feedwater Pump (FWP 20) is correct?
a) "B" MFWP (FWP 2B) should be tripped due to actuation of
"B" train Main Feedwater Isolatio b) "B" MFWP (FWP-28) should be tripped due to actuation of
"B" train Main Steam Line Isolatio c) "B" MFWP (FWP 2B) should be tripped due to actuation of
"B" train Emergency Feedwater, d) "B" MFWP (FWP 2B) should NOT be trippe Answer: a O
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13 2 Objective: List from memory the inunediate actions required by this Abnormal Procedur Iteference: AP 380 K/A: 000 Emergency Plant Evolutions 000 Small 11reak LOCA EK3.20 Maintenance of ItCS subcooling Task: 0000501006 Perforrn the actions to ensure core cooling and subcooling margin are rnaintained during an emergency even Importance: 4.4 / Expected Time (rnin):
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O O Test ItemLf 3 (SitO Al Point Vahte (1,(O llased on current plant conditions, which ONE of the following is the required sub cooling margin?
a) 20*F b) 30*F c) 50*F d) In accordance with the SPDS curvo Answer: b O
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Test Item: SSE 02/05 O
Lesson Plan: ItOT 5 01 Objective No.: A1 Objm:tive: Given a copy of Technical Specifications and Technical Specification Interpretations clarify and/or interpret STS
' requirement Ileference: STS 3. K/A: 035 Steam Generator System 010 Startup/ Shutdown System Ability to recognize indications for system Generic #8 operating parameters, which are entry conditions for Technical Specification Task: 3410103037 Apply STS direction for safety limits, safety system settings, and LCOs Importance: 3.4/ Expected Time (min):
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- lest item #14 (SitO II) Pulpt Value (1.0)
i Given the following plant conditions:
1 - The plant is in Mode 1.
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- The Diesel Fuel Storage Tank readings are as follows:
- The "A" ES 4160 V bus is powered from the Unit 3 Aux
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Transformer (BKR 3207 closed with 3211 and 3205 open).
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Which ONE of the following describes required action (s) for this
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situation?
n) Hestore two off site circuits to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least IIot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 /> b) Declare "A" EDG inoperable and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify i operability of the remaining AC sources and once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verify that "B" EDG will start
, and accelerate to rated speed.
t c) Declare one off site circuit and one EDG inoperable and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to place the unit in Ilot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Be in Hot Shutdown within the following 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 subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
,
'
d) Verify the operability of two offsite A.C. circuits within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable diesel generators to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least hot standby within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two diesel generators to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of the initial loss or be in at least hot standby within the next 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
>
Answer: b
. -_ .. . . . - .
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _______________ _ __- _ _ __-__ _
O O Test Item: 092 I.esson Plan: llOT-5-01 Objective No.: Illo l
Objective: Given any plant condition and a copy of Technical Specifications, identify those conditions which are violations of a limiting condition for operation and discuss the required corrective action Iteference: STS 3. K/A: 000 Emergency Plant Evolutions 033 Loss of Intermediate-Range Instrumentation EA2.10 Tech-Spec limits if both intermediate range channels have failed Task: 1190301015 Apply Technical Specification requirement Importance: 3.1/ Expected Time (min):
O l
l
.. .. ..
_ _ _ .
.. - _ - . . . . - . . ._ _ _ _. - . . - .
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O O q Test Itern #15 (SRO II) J'olnt Value (1.0)
NJ The following plant conditions exist:
- The plant is at 100% powe Interrnediate range "B"(NI 4) is inoperable due to a failure of the detecto An electrical failure has caused the de energization of VBDP It is estiinated that it will take 2 to 3 days to place VBDP 5 back in servic Which ONE of the statements below gives the required action (s) for this situation?
a) Reduce and maintain power s 5% full powe b) Must maintain power = 5% full power.
O V
c) Restore VBDP 5 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in hot standby within the next 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) Within one hour action must be initiated to place the unit in Ilot Standby with the CRD breakers open within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Answer: d O
. . .-
'
O O
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Test Itein: 377 Lesson Plun: HOT 147 Objective No.: 113 Objective: Explain how tual why changes in the inoderator affect core reactidt Reference: OP 103C K/A: 001 Control Rod Drive System 000 Generic K5.20 Definition of moderator ternperature coefficient : application to reactor control Task: 10CFH55 Importance: 3.3/ Expected , Time (inin):
O O!
_ _ _ _ _ _ _ _ _ - - - .
.
.
O O n Test Item #10 (SRO 111 Esthtt Value (1.0)
O >
A reactor startup is in progress and the nuclear operator hasjust announced that the reactor is critical. At this point an adjustment is made to the feedwater Gow to both OTSGs which inadvertently causes a slight overfeeding such that Tave decreases from 532*F to 525' Assuming middle of life conditions. RCS boron concentration is 800 ppm, and no automatic or operator action occurs, which ONE of the following describes the response of the reactor to this event?
a) Reactor power will increase to and stabilize at - 5 x 10' amps on the intermediate rang b) The reactor will be suberitical and power will decrease to the point of steady state suberitical multiplication.
<
n c) Reactor power will increase and stabilize at *. 9?c full powe V d) Because criticality is achieved below the point of adding heat, reactor power will not be affected by the temperature chang Answer: a
'
_ _ _
!
O O l
!
l Test Item: 241 l
Lesson Plan: ItOT-4 03 -
Objective No.: Ill Objective: State the purpose of and the breakers associated with cross-tie blockin lleference: AR 702 K/A: 002 AC Electrical Distribution 000 Generic K1.02 Ernergency Diesel Generator Task: 0620101004 Monitor the AC Electrical Distribution System importance: 4.1/ Expected , Time (min):
O O
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O O Test item #17 (SHO B) Point Value (1.0)
Which ONE of the following is a condition which will cause the " Diesel Gen B Parallel Block Act" light to be illuminated if the "A" DG Breaker is closed?
a) Offsite Transformer is closed in to both ES buse b) The Feeder to "A" 4160 ES bus from the Unit 3 Aux Transformer is closed with the Feeder to "B" 4160 ES bus from the Unit 3 S/U Transformer close '
The Feeder to "A" 4160 ES bus from the Offsite Transformer is closed with the Feeder to "B" 4160 ES bus from the Unit 3 S/U Transformer closed.
O a) The reeaer te "^ 428o es n# rrem the u it a ^=x Transformer is closed with the Feeder to "B" 4160 ES hus
.
from the Offsite Transformer close Answer: a h
.
_ __-
- . __ -
O O Test Itenu 392 Lesson Plan: ItOT 5 43 Objective No.: B2 & B4 Objective: List from memory the federal quarterly whole body dose limits for radiation workers, non radiation workers and persons under 18 years of ag Demonstrate the use of the formula 5(N 18) to determine an l individual's exposure limit Iteference: IIPP 300 l
K/A: Plant Wide Knowledge of 10 CFit 20 and related ,
Generic #15 facility radiation control requirements '
Task: 1190301010 Apply radiation and contamination safety procedure Importance: 3.4/ Expectetl Time (min): ,
O
.
. _
__ ._.- __ _ - . . .- - - - . O O Test item #18 (SitO II) hdnt Value (1.0)
O A dose limit extension has been granted for a radiation worker at Cit 3 who has the following cornpleted Whole llody dose history:
(NRC FoltM FOUlt)
AGE: 20 years old as of 6 6 91 ACCUMULATED DOSE: 9 Rem as of 12 3191 No dose for current quar ter (assume today is 1 192)
Which ONE of the following is the maximum whole body exposure which this person could receive in the current quarter and not exceed the federal whole body dose limits? .0 Rem (v .25 Rem .5 Rem .0 Rem Answer: b l
l
/
Q)
l l
_ __ _ _ - _ . ..
O O Test Itein: 328 Lesson Plan: ItOT 516 Objective No.: 3 Objective: Given a copy of the Abnorinal Procedure, be able to state a basic reason for any given Sytnptorn, Innnediate or Follow up action.
Iteference: EP 140 K/A: 000 Emergency Plant Evolutions 024 Ernergency lloration EA2.00 When boration dilution is taking place Task: 0000501018 Perforrn recluired actions for Einergency Iteactivity Control linportance: 3.6/3.7 Expected 2.0 Time (inin):
O O
-
_ _ _ _ _ _ _ _ - - - - ..
O O InLitem #19 (sito Ill l'.n!nt Valtic (1.0)
O Which ONE of the following is the reason DW to the Ill3 is isolated if 11CS pressure is < 140 psig while in EP 140 "Einergency Itenctivity Control"?
<
a) lleduces the possibility of dilution frorn abnornial evolution b) iteduces the possibility of over filling the ItCS at low pressures and ternperatures, c) Iteduces the possibility of filling the ItCDT with DW and allowing that water to be transferred to a feed source supply tank for the llCS.
^
d) Iteduces the possibility of DW interfering with the sarnpling process for true boron concentration deterrninatio Answer: a
_ -
.-
,
O O Test Iter.i: 385
'
Issson Plan:
_-
ItOT.5 20
_ Ohjective No.: 2 Chjective: Given a copy of the Abnorinal Procedure, be able to state a basic reason for any given Symptorn, lunnediate, or Follow up actio Itefere. ace: EP 390
.K/i'a 000 Einergency Plant Evolutions OM Steam Generator Tube Leak
'
EK3.07 Actions contained in EOP for S/G tube leak Task: 0000501022 Perform the required . ctions following a Steam Generator tube ruptur Perforrn actions required for excessive lleactor Coolant system leakag .
Importurice: 4.2/ Expectet! 1.75 Time (rnin):
,
f
___ _ __ _ __ _ _ . _ _
O O q Test Item #20 (SI(O ID P9h1LYnhw (1,0)
V The plant is in a forced shutdown condition due to a stetun generator tube leak. The leak is getting progressively worse and pressurizer level is becoming increasingly more diflicult to maintain. El' 300, Steam Generator Tube Leak, provides guidance which directs the reactor to be tripped if pre.vurizer level cannot be maintained = 100" with IIP Which ONE of the following conditions would result due to the tripping of the reactor at this point?
a) A loss of adequate ItCS pressure contro b) The PZit insurge can cause the PZit cooldown limits to be exceeded, f
'
c) If an MSSV should lift and fall to rescat, site boundary dose rates could be exceede d) The reactor coolant system would become saturate Answer: d O
V
._ _
O O
-
Test Itenu 307 Lesson I'lan: ItOT 5 25 Objective No.: 3 Objective: Given a copy of the Abnormal Procedure be able to state a basic reason for any given Syinptorn, Iminediate, or Follow.up actio lieference: AP 530 AP 380 K/A: 000 Emergency Plant Evolutions 000 Small 13reak LOCA EKl.01 Natural circulation and cooling, including reflux boiling Task: 0000501010 Perform the actions required following an Engineered Safeguards System Actuatio Importance: 4.2/
Expected Time (min):
5,0 g
t i
,
0
_ _ _ __ __ _ _ _ _ . . - _ ___ _ _ - _ _ _
,
O O
Test itein #21 (SHO H) Pojnt ValueJLO_1 i
Given the following sequence of events:
' - While operating at 100% FP, a small break LOCA occur ,
- The reactor trips and flPI actuate ,
-
Upon loss of SCM the RCPs are tripped.
i -
EFIC initiates and feeds both OTSGs to 95% on EFIC Iligh Rang ; -
The reactor has a maximum decay heat outpu Natural circulation can unt be verified.
. Which ONE of the following should be done to enhance natural circulation?
\
a) Lower RCS pressur ;
b) Bump RCP c) Throttle IIPI flow, Vent pressurizer.
'
d)
)
Answer: b
.
Ov v)
Test Item: 141 Lesson Plan: ItOT 5 73 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure be able to state a basic reason for any given Symptom, Immediate, or Followup Actio Heference: EP 220 K/A: Til 193010 K1.06 Task: 0000501019 Perform required actions for Pressurized Thermal Shock conditions Importance: 3.6/ Expected Time (min):
O O
.
- -__ - _ . . ..
l O O
,
, Test item #22 (Sito In Point Vahte (1.0)
l Given the following conditions:
- An overcooling event has occurred due to a failed MSS An OTSG tube leak was created by the MSSV failur A reactor trip resulted from the overcoolin Twenty minutes after the reactor trip the plant conditions are:
Tc............. 365 * F RCS pressure..,1650 psig Which ONE of the following actions must be taken?
a) Reduce RCS pressure so the plant returns to the PTS operating region and continue plant cooldown maintaining emergency cooldown rate limit (Oj b) Reduce RCS pressure so the plant returns to the PTS operating region and perform a three hour soa c) Reduce RCS pressure so the phmt returns to the PTS operating region and continue plant cooldown maintaining allowable cooldown rate limits, d) Allow the RCS to heatup to 475aF so the plant returns to the
,
PTS operating region and perform a three hour soak.
l Answer: c i
!
l O
v
.. . - . -
- _
O O Test Item: 380 Lesson Plan: ItOT-5 78 Objective No.: B11 Objective: Given a copy of OP 301, explain what is being accomplished including the reason for any notes or cautions, as you respond to increased reactor coolant syste:n leakage,
'
lleference: OP 301 K/A: 002 Itcactor Coolant System 000 Generic
>
A2.01 Loss of coolant inventory Task: 0020401001 Perform actions required for excessive lleactor Coolant system leakag Importance: 4.3/ Expected Time (min):
O
, - . , .
_ _ _ _ . _ . . . _ . _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ . . . _ _
.
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O O Test Item #23 (SRO B) Point Valne_LLO_1 O
The plant is operating at 100% power. SP 317, RC System Water Inventory Balance, is being performed daily due to a large amount of identified leakage. The leakage data from the past week is as follows:
Day 1. . . 3.5 gpm Day 2. . . 3.7 gpm Day 3. . . 4.1 ginn -
Day 4 . . . 4.3 gpm Day 5 . . . 4.5 gpm Day 6, . . 4.9 gpm Day 7, . . 6.0 gpm Which ONE of the following describes the correct course of action based on the above listed data? -
-,
a) Enter the Technical Specification action statement on identified lerlage and continue operatio b) Perform SP 317 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and continue operation until Technical Specification limits are reache c) Notify the Man on Call and consider a plant shutdown, d) Commence an immediate plant shutdown to Mode Answer: e
.
O O Test Item: 372 h lesson Plan: ROT 5 31 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given Symptom, immediate or Follow up actio Iteference: AP 990 K/A: 062 AC Electrical Distribution System 000 Generic A2.06 Keeping the safeguards buses electrically separate Task: 0000501002 Perform the required actions to ensure plant safety during an
, emergency / abnormal event Importance: 3.4/ Expected g P Time (min): W O
_
,
O O Test Item #24 (SRO IU Point Value (1.01 Step 3.7 of AP 990, Shutdown From Outside Control Room, directs the operator to " Ensure Bkrs 3207 and 3208 are open and DC control power is off." Which ONE of the following is the reason for this step?
a) Ensure local manual control of breakers 3207 and 3208 is available following Control Room evacuation.
,
i b) Ensure an inadvertent ES bus overload condition will not be created due to closure of multiple source feeder breakers.
'
c) Ensure a fire induced fault would not cause closure of breakers 3207 and 3208, paralleling the Auxiliary transformer
, with the Start-up transformer.
< O,
- V d) Ensure ES buses are not supplied by unprotected source feeder breakers since relay protection of breakers 3207 and
3208 is lost when control is transferred from the Control
-
Room.
>
Answer: c (m
O O Test Item: ! 413 Lesson Plan: ROT 5 36 Objective No.: B3 Objective: Given EM 204A and the required data, be able to complete a dose assessmen Reference: EM-204A K/A: 000 Emergency Plant Evolutions 000 Accidental Gaseous Waste Release EK3.03 Actions contained in the EOP for accidental gaseous waste release Task: 1150501001 Estimate off site dose during a radiological
, release using EM 204 (A)
Importance: 3.8/4.2
, Expected Time (min):
O
,
O
. -
. - . . - . . - . .. -- - . _ . - - . . . - . . . - .- . . - . - . . .
-
o
.
-
.o
.
J i
Test Item #25 (SRO B) Point Value (1.0)-
!;
- A large break LOCA has occurred. The present plant conditions are as follows:
! OTSGs . . . . . . . . . . . . - dry and filling RCS Pressure . . . . .-... - 725 psia l '
- Tincore . . . . . . . . . . . . . 690 * F
-
j RB Pressure . . . . . . . 15 psia
!'
IGi A2 Low Range . . . . off scale high RM A2 Mid Range . . . . 70 mR/hr
! RM A2 Iodine . . . . . .-.- 1000 epm 1 An off site dose assessment must' be complet6d. The meteorological 1 stability class has been determined to be F,G.' Which ONE of the I following would be the dose rate at the site boundary based on the
_
- listed data? -
i
! a)- 2.0E+3 mR/hr i
. '
l b) 2.6E+3 mR/hr i
c) 7.9E+4 mR/h 'l ' '
!
I d) 1.1E+5 mR/hr a
i Answer: d --
- -
,
[.
- .. . .. ....,,__,_,...,.._m.- -
.b.,.... .. . , _ , .
O O
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,
Q Q Test Item: 415 Lesson Pinn: TRE-007
_
ROT 5 36 Objective No.: 7 B3 Objective: Explain the duties and responsibilities of the Emergency Coordinator as described in EM 202, Duties of the Emergency Coordinato Given EM 204A and the required data, be able to complete a dose assessmen Reference: EM 204A, EM 202 K/A: 000 Emergency Plant Evolutions 038 Steam Generator Tube Rupture EA2,04 Radiation levels
'
System Generic #10 Ability to recognize abnormal indications for system operating parameters, which are h
entry level conditions for emergency and Plant-Wide abnormal operating procedure Generic #36
,
Ability to take actions called for in the facility Emergency Plan, including supporting or acting as Emergency Coordinato Task: 3440403005 Classify Emergency events requiring E-Plan implementation and take actions to activate appropriate emergency response facility Importance: 3.9/4.2*
4.5/ .9*/ Expected Time (min):
. -. -_ . - - _ - - -. .- . _ . -- -. . . - . . _ . . - . . _ - . ---
'
O O Test Item #26 (SRO B) Point Value (1.0)
A steam generator tube rupture has occurred coincident with a stuck open main steam safety valve (MSSV) on the same OTSG. The MSSV had opened 15 minutes ago and the maintenance department estimates that it will take an additional 15 minutes before the valve will be close The OTSG tube leak rate has been determined to be 160 gpm. The present plant conditions are as follows:
RCS Pressure . . . . . . 1200 psia Tincore . . . . . . . . . . . .
.
650 a F -
RMG-25 . . . . . . . . -. . 18 mR/hr RMG-26 . . . . . . . . . . 0.8 mR/hr RMG 27 . . . . . . . . . . 16 mR/hr RMG-28 . . . . . . . . . . 0.9 mR/hr Wind Speed . . . . . . . . . IM m/sec Stability Class . . . . . . . . D Which ONE of the following would be the proper emergency classification for this event?
a) Unusual Event b) Alert c) Site Area Emergency _
d) General Emergency-Answer: - c i
I O !
l
-- - - - - . . .-. . - - . - . - , - . - . - . - , . - - , - . . . - - . . . - . . - ,
't O O Test Item: 315
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Lesson Plan: TITE-007 Objective No.: 7 Objective: Explain the duties and responsibilities of the Emergency Coordinator as described in EM 202, Duties of the Emergency Coordinato Iteference: EM-202 K/A: Plant Wide Ability to take actions called for in the Generic #36 Facility Emergency Plan, including supporting or acting as the Emergency Coordinato Task: 3440403005 Classify emergency events requiring E-plan implementation and take actions to activate appropriate emergency response Importance: 2.9'/ Expected Time (min):
O
O O Test Item #27 (SHO B) Point Value (1,0)
(3 v
A severe nuclear accident has occurred at the plant. An initial off-site dose assessment has been performed. The estimated doses are as follows:
Whole Body (mr) Child Thyroid (mr)
0.83 miles 5.60 7.0 E + 3 2.00 miles 1.80 2.2 E + 3 5.00 miles 0.52 653 10.00 miles 0.21 264 Which ONE of the following statements is the recommended protective actions for these estimated doses?
a) 0 - 2 mile 3600 evacuation / 2 - 5 mile evacuation of downwind sectors / 2 - 5 mile shelter of remaining sectors /
5 - 10 mile evacuate downwind sectors h-b) 0 - 2 mile 360a evacuation / 2 - 5 mile evacuation of downwind sectors / 5 - 10 mile shelter of remaining sectors c) 0 - 2 mile 360a evacuation / 2 - 5 mile evacuation of downwind sectors / 2 - 5 mile shelter of remaining sectors /
5 - 10 mile shelter of downwind sectors d) 0 - 5 mile 360o evacuation / 5 - 10 mile evacuation of downwind sectors / 5 - 10 mile shelter of remaining sectors Answer: c in b
i
O O Test Item: 390 Lesson Plan: ROT-5 38 Objective No.: B4 Objective: State the requirements for the " Operator at the Controls" to remain in the red-carpeted general area of the Control
.
Cente Reference: AI-500
'
K/A: Plant Wide Ability to coordinate personnel activities Generle #29 inside the control roo Task: NTS Importance: 3.1/ Expected Time (min):
O
.
(
W
1 I
l 9'
l l
l
_ . . - . . . - - - . . . -.. - .. - ~ . - -. --. -- . -. . .
[ o: o i l
- -
!- Test Item #28 (SRO B) Point Value (1.0)
iO i
i !
l
!
l- While in mode l', with another reactor operator and the assistant shift j supervisor present in the control room, a plant transient occurs.- The
'
j-i
ANSS directs the other reactor operator to leave the control room to- ,
'
'
complete a task that has some urgency. The ANSS then goes to get MET tower data to complete EM-204A. _ You now notice that the NNI X'
-
power supply light on the redundant instrument' panel is off.
'
Which ONE of the following statements describes your administrative ability to leave the red carpeted area to check the status of this power supply?
i'
.
l You _cannot leave the area; at least one operator must be in -
! the red carpeted area at all tines while in mode 1.
i-
!
j You can leave the area as long as you have SSOD permission, iO 3 You cannot leave the area since an unobstructed view of the
! main control board cannot be maintained.
- - -
-
! You can leave the area; there are no obstructions between
! the NNI power supplies and the main control board.
!
!
e
,'
l- Answer: 'c i-
!
i-
f f '
+
d
!
a
-- ,
.r.v-.- ,. ,.~# .w . -5.-2,.i.'c- .r,+,,,v.e- ..r,t - ., wr +. , ' . , .=F-
_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ ._-
.
O O Test Item: 396 Lesson Plan: ROT 5-02 Objective No.: B1 Objective: Given a limit and precaution from one of the operating procedures, explain the basis:
d.OP-204 Reference: STS 3.7.1.5 and 3.7.1.1 K/A 039 Main and Reheat Steam System 000 Generic System Knowledge of the Technical Specifications Generic #5 bases and definitions related to limiting conditions for operation and safety limits.
Task: 0390101009 Monitor the Main and Reheat Steam System Importance: 3.1/ g Expected 3.6 Time (min):
O
-- -
.. - . . .- - - . . . . . .- . .- . .
- O -O i-II Teft Item #29 (SRO B) Point Value (1.0)
.
O
!
i
- A plant startup is in progress with reactor power at 40%. A problem in
- the Intermediate Building has caused damage to MSV-38 and MSV-43
(MSSVs). It has been estimated that it will be 2 days before these two i
. valves will be returned to service. MSV-40 (a MSSV) was slightl damaged during the same incident however it can be repaired and
'
returned to service within the next 2W hours. MSV-412 (a MSIV) has
- also been damaged and is in the closed position "It will be 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> j before MSV-412 can be opened.
j Which ONE of the following is the correct course of action based on the i above conditions? a) Power escalation may continue to 67% but will require the-
!
overpower trip set point to be set at 67.5%.
.
b) Power escalation must be halted and MSV-412 returned to j operable status or the plant must be taken to Hot Shutdown -
i within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t c) Power escalation must be halted prior to reaching 67.5% until
! either MSV-40 and either MSV-38 or MSV-43, or MSV-412 is returned to operable status, or STS 3.0.3 must be applied; i
d) Power escalation may continue to 60%, MSV-412 must be
} declared inoperable, and the high flux trip setpoint must be
,
,
set to 81%,
hI
'
Answer: d i
'
{ --
-,-e - , ---.---w , , - - - + v , ~ ,-
O ,n,
% *J Test Item: 368 Lesson Plan: ROT-5-78 Objective No.: B1 Objective: Apply limits and precautions from OP-301, including their basi Reference: OP-301 K/A: 000 Emergency Plant Evolutions
,
074 Inadequate Core Cooling EK1.03 Processes for removing decay heat from
, the core Task: 0020101005 Drain and nitrogen blanket the Reactor Coolant Syste Monitor the Reactor Coolant Syste Importance: 4.5/ Expected Time (min): g O
. _ _ _ _ _ _ -
[)
m f
g Test Item #30 (SRO H) "olnt Value (1.0)
V Given the following conditions:
-
The reactor was shutdown at 0000 (midnight) on Dec. 2,199 Today is Dec. 8,1990 and the time is 080 The RCS has been depressurized in preparation for head remova The vessel has been drained to a leveljust above the flange but not yet low enough for head remova In preparation for refueling the incore instruments have been withdrawn from the core regio A total loss of Decay Heat Removal has occurre Just prior to the loss of Decay Heat Removal RCS temperature was '70* Which ONE of the following is the approximate time it is expected to take to reach 212aF (boiling) in the core?
(m a) 22 minutes d
b) 27 minutes c) 35 minutes d) 39 minutes Answer: d n
%)
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O O Test Item: 351 Lesson Plan: ROT-5-81 Objective No.: B1 Objective: State the entry level conditions for this Abnormal Procedur Reference: AP-581 K/A: 016 Non Nuclear Instrumentation System 000 Generic A2.02 Loss of power supply Task: 0160401002 Perform required actions for a loss of power to the NNI syste Importance: 2.9* /3.2 *
Expected Time (min):
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- Test Item #31 (SRO B) Poin't Value (1,0)
Which ONE of the statements below is correct concerning a loss of NNI X?
a) A failure of the NNI-X ABT output is considered a loss of -
NNI- b) Only components powered from VBDP 1, VBDP 3, and-VBDP-5 will be affected by a loss of NNI 'I c) The interlock functions associated with MUV-49 are unaffected by a loss of NNI X DC powe d) A loss of NNI X DC power can be confirmed by the absence of any 1 of the 4 indicating lights located in NNI Cabinet Answer: a O _ - - - . . - . . . _.._ . -
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j g p ATTACHMENT 3 9.a . a of
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TDP 106 Rev 13
,I Page 23 of 71 ANSWER KEY COVER SHEET i
i TRAINING PROGRAM TITLE: LICENSED OPERATOR REQUALIFICATION EXAMINATION TITLE: LICENSED OPERATOR REQUALIFICATION - CATEGORY A
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EXAMINATION NAME OR NUMBER: 1992 CATEGORY A RO EXAM i
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I PREPARER: 10 - e d- DATE: " #!9d APPROVAL: /vid - 'VMRO DATE: / l-/O -9 2_.
- puclear Training Supervisor O
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V INSTRUCTIONS FOR TAKING THE EXAMINATION 1. Use black ink or dark pencil only to ensure legible copie . Ensure your name is printed in the blank provided on the cover sheet of the examination and the answer shee . Each question has only ONE correct answer. Mark your answers on the
, answer sheet provided and do not leave any question blank. If additional paper is required, use only the lined paper provided by the examine . All questions are worth 1.0 poin . If parts of the examination are not clear with respect to their intent, ask questions of the examiner onl . The examination is designed to take approximately 45 minutes to (_)
v complete. You will be given 1 HOUR to complete the examinatio . The questions have been time validated by knowledgeable persons. You should be aware that not every answer needs to be verified by consulting a reference and excessive usage of reference material may cause you to not complete the examination in the allotted tim . Restroom trips are limited and only one examinee at a time may leav You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromis . Cheating on the examination could result in revocation of your license and may result in more severe penaltie . 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 complete . When you are finished and have turned in your completed examination, leave the examination area.
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. SCENARIO OVERVIEW h The unit was operating at 100% power, MOL. I&C was preforming SP-110 in the "A" RPS channel. A large steam break occurred on the OTSG-1B outside the RB and upstream of the MSIVs. FWP-2B failed to trip from the EFIC FW Isolation. CAV 5 failed to close on the ES actuation. RWP 2B failed to start on the ES actuatio INSTRUCTOR NOTE: Examines must not be present during setup.
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IL INITIAL CONDITIONS:
Initialize the simulator to 100% power MO III. CONTROL BOARD SETUP:
, Perform a lamp check using panel diagnostic . Un freeze the simulator, Ensure SPDS screens are selected properly for current conditions. (A Flux on left screen and Normal on right screen) Ensure computer screens are selected for proper groups for current conditions. (Group 59 on the right screen and group 108 on the left screen) Freeze the simulato . Ensure all charts are inkin . Advance and mark all chart . Advance line printer paper, Advance annunciator typer paper and remove used sheet . Un-freeze the simulator and allow to run for 5 mi . Freeze the simulato .- - -.- .- - . . . - - ---.-. - _.- - - - - -.
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IV. SCENARIO SETUP:
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1, Fall CAV-5 open (I/F page 742) Fall Open RWP 2B breaker (I/F page 654) Prevent the B MFWP from tripping (I/F page 638) Auto trip failure / . Arm, Numbered Malfunction MS-002B ("B" MS line break),
set to . Unfreeze the simulato . Place the "A" RPS channel into " Manual Bypass" and place the test module for RCS pressure in the "A" RPS channel into Test Operate positio . Freeze the simulator and take a snap-sho . Unfreeze the simulato O seiectezasereiveivete me ei aeve ve>#erei . Activate the stack when the low RCS pressure alarm comes i . Perform the following procedural actions:
a) After HPI is actuated, select PZR spray valve to Aut . Allow the simulator to run until RCS pressure is 2200 psi as
- indicated on the lower portion I/P screen. Acknowledge annunciator alarms and freeze the simulator ensuring that all active annunciator alarms are o PRE-EXAM REVIEW:- Verify validity of Exam answer key to the frozen simulato . Resolve any discrepancie .. .- . .- .
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VI. SIIIFT TURNOVER l Recall examinees into simulator roo . Rulew rules of the exam.
4 Handout Information Sheet to each emame . Review Information Sheet with examinee . Allow examinees to perform a 5 min, walkdown of the MC . Handout the examination.
.' Announce exam start tim Time: Announce exam stop tim Time:
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! INITIAL CONDITIONS:
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j The plant operating at 100% power, at 210 EFPD.
I&C preforming SP-110 in "A" RPS channel.
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TRANSIENT DESCRIPTION:
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1 L A large steamline/feedline break has occurred on the "B" Steam
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' Generator. RM A12 is out offervice.
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i OPERATOR ACTIONS TAKEN:
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i- ELAPSED TIME:
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j - Approximately 5 min since the rapid de-pressurization of the B OTSG.
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Test Item: SSE-02/01 O
Lesson Plan: ROT 5-63 Objective No.: B3 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given symptom, immediate or follow up actio Reference: AP-380 K/A: 000 Emergency Plant Evolutions 009 Small Break LOCA EA1.18 Balancing IIPI loop flows Task: 0040501002 Control IIigh Pressure Injection flow rate Importance: 3.4/ Expected Time (min):
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C Test Item: #1 (RO A) Point Value (1,0)
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i i Based on current plant conditions, which ONE of the following
] statements correctly describes the steps required to BALANCE HPI j flows?
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j i a) Select "HPI RC-1", "HPI RC-2" and "HPI RC-3" hand switches i to " BYPASS"; close MUV-27 and adjust HPI flows as
! necessary.
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4 b)- Select "HPI RC-1", "HPI RC-2" and "HPI RC-3" hand switches -
l to " RESET; close MUV-27 and adjust HPI flows as necessar c) " RESET" 1500# bistables in ES channels 1,2 and 3, close l- MUV-27 and adjust HPI flows as necessary.
O d) Close MUV-27 and adjust HPI flows as necessary; no additional steps are required.
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Test Item: SSE-02/02 Lesson Plan: ROT-5-65 Objective No.: 82 Objective: State the Immediate Actions of this abnormal procedur Reference: AP-460 K/A: 000 Emergency Plant Evolutions 040 Steam Line Rupture EA1.02 Feedwater isolation Task: 0190401002 Perform required actions for a malfunction of the EFIC system including spurious
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actuation and failure to actuate Importance: 4.5/ Expected 1,5 Time (min):
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Test item: #2 (RO A) Point Value (1,0)
Based on current plant conditions, which ONE of the following statements with respect to the "B" Main Feedwater Pump (FWP-2B) is correct? ,
l a) "B" MFWP (FWP 2B) should be tripped due to actuation of
"B" train Main Feedwater Isolatio b) "B" MFWP (FWP-2B) should be tripped due to actuation of
"B" train Main Steam Line Isolatio ,
c) "B" MFWP (FWP-2B) should be tripped due to actuation af
"B" train Emergency Feedwater, d)- "B" MFWP (FWP-2B) should NOT be trippe Answer: a O
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V 'd Test Item: SSE-02/04 h
Lesson Plan: ROT-5-63 Objective No.: B2
Objective: List from memory the immediate actions required by this Abnormal Procedur Reference: AP-380 K/A: 000 Emergency Plant Evolutions 009 Small Break LOCA EK3.26 Maintenance of RCS subcooling Task: 0000501006 Perform the actions to ensure core cooling and subcooling margin are maintained during an emergency event, Importance: 4.4/ Expected Time (min):
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Test Item: #3'(RO A) . Point Value 0,0)
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Based on current plant conditions, which ONE of the following is the required sub-cooling margin?
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Given a copy of the Abnormal Procedure be able to state a basic reason for any given Symptom or Follow up actio Iteference: AP-460 K/A: 000 Emergency Plant Evolutions 040 Small Break LOCA EK3.04 Actions contained in the EOP for a steam line rupture Task: 0000501002 Perform the actions required to ensure the plant safety during an emergency / abnormal even Importance: 4.5/ Erpected Time (min):
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Test Itentt #4 (SitO A) Ih11nL%ihie (1.0)
- Based on current plant conditions, which ONE of the following i staternents is correct concerning OTSG operability as defined in STS?
a) No actions are required, both OTSGs are operable
! b) No actions are required due to current plant Mode t
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c) Both OTSG are inoperable, STS requires both OTSGs be restored to operable status prior to increasing Tave d) OTSG "B"is inoperable, STS requires Cold Shutdown within
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the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />
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O O l Test Item SSE 02/00 Lesson Plant 110T 5 65 Objective No.: 11 3 i Objective: Given a copy of the Abnorinal Procedure be able to state a l basic reason for any given Symptom or Follow up actio Iteference: AP-460 K/A: 000 Emergency Plant Evolutions 010 Small Ilreak LOCA EE.S.04 Actions contained in the EOP for a steam
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line rupture i Task: 0000501002 Perform the actions required to ensure the l plant safety during an
- emergency / abnormal event, Importunee
- 4,5/ Expectet! 1,5 Time (min): g
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1 f Test itenu #5 (SitO A) Point Vahio 0.o)
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l In response to the OTSG de. pressurization, you enter AP-460, Steam l i Generator isolation Actuation. Step 3.0 requires the' both CC chillers j and their chilled water pumps are secured. Which ONE of the following
- statements describes the reason for this step?
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a) Chilled water pump motors may be damaged due to high i humidity, b) Increased SW flow to the chillers can cause excessive cooling of the penetrations.
l c) Chillers have control circuits located in the intermediate
, building which may be affected by high humidity.
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, from the penetration cooling system.
Answer: d
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Lesson Plant itOT 5-65 Objective No.: 11 3 Ob,lective: Given a copy of the Abnormal Proceduro, be able to stato a basic reason for any given syrnptom or follow up action.
Iteference: AP-460 K/A: 035 Steam Generator Systein 010 Startup/ Shutdown A2.01 Faulted or ruptured SG Task: 0000501012 Perform the required actions following a steam generator isolation actuation.
Importance: 4.5/ Expected 2.25 Time (min):
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Ipst item: #6 (SitO A). BilnLYithic (1,0)
A plant cooldown will be required to repair the break. Ilased on current plant conditions, which ONE of the following correctly identifies the OTSG Tube to Shell Delta T limit?
a) 60 ~F b) 70 *F c) 100 * F d) 150 * F i
Answer: c l
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O O Test item: SSE 02/10 Lesson Plan: IlOT 5-47 Objective No.: 19 Objective: Given Enclosure 1 of EM 202, correctly identify the emergency classification froin a list of specific conditions.
Reference: _
EM 202 K/A: 000 Emergency Plant Evolutions 040 Steam Line Rupture System Knowledge of which events related to Generle #3 system operation / status should be reported.
Task: 0000501001 Analyze indications to determine that an emergency / abnormal plant event is in progress.
Importance: 3.7 Expected Time (min):
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[ If a 60 gpm tube leak in the "A" OTSG were to occur simultaneously
with the current plant conditions, which ONE of the following j Emergency Classifications should be declared?
j a) Unusual Event l
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Lesson Plan: IlOT 415 Objective No.: B12 Objective: Briefly describe the operator actions required to:
Manually initiate EFW
- Regain control of EPIC /EFW cornponents after EFW has been autornatically or manually initiated
- Shutdown the EFW systern after initiation Reference:
K/A: 001 Auxiliary / Emergency Feedwater Systern 000 Generic A3.04 Autornatic AFW isolation Task: 0190401003 Reset / bypass EPIC logic following EFIC actuation.
Irnportunee: 4.1/4.2 Expected Tline (min): $
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O- O Test item: #8 (SRO Al Point Value (1.0)
Based on current plant conditions, which ONS of the following statements correctly describes the minimurn actions which must be taken to regain control of EFV 147
- a) EFIC channel "A" " Test Results Reset" P/B must be- '
depresse b) EPIC channel "A"" Man Permissive" P/B must be depresse c) Both EFIC channels " Tests Results Reset" P/Bs must be depresse d) Both EFIC channels " Man Permissive" P/Bs must be depresse Answer: d
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! O O Test Itein: SSE-02/15 Lesson Plan: ItOT-412
- Objective No.
- B3 (II)
Objective: Describe the location and/or operation of the following cornponents:
II. Itcactor Trip Module Reference:
K/A: 012 Reactor Protection System 000 Generic A3.07 Trip breakers Task: 0120101005 Monitor the Iteactor Protection System.
] Importance: 4.0/ ; Expected 2.25 Time (inin):
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O O Test item: #4 (RO Al PoinLYplue (1.0)
In response to the OTSG de pressurization, you enter AP-460, Steam Generator Isolation Actuation. Step 3.6 requires that both CC chillers and their chilled water pumps are secured. Which ONE of the following statements describes the reason for this step?
a) Chilled water pump motors may be damaged due to high humidity, b) Increased SW Gow to the chillers can cause excessive cooling of the penetration c) Chillers have control circuits located in the intermediate building which may be affected by high humidit O d) Chillers could become overloaded by increased heat loads from the penetration ecoling syste Answer: d i
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! Test Item: SSE 02/07 Lesson Plan: ROT 5 65 Objective No.: 11 3 ,
Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given eymptom or follow up actio Itsference: AP-460 K/A: 035 Steam Generator System
010 Startup/ Shutdown A2.01 Faulted or ruptured SG Task: 0000501012 Perform the required actions following a stcain generator isolation actuatio Importance: 4.5/ Expected 2.25 Time (min):
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O re t item: a <no ^> reini v ine < >.o>
A plant cooldown will be required to repair the break. Based on current plant conditions, which ONE of the following correctly identifies the OTSG Tubo to Shell Delta T limit?
a) 60 * F b) 70 * F c) 100 * F d) 150 * F O
Answer: c i
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O SSE 02/12 Lesson Plan: ItOT 415 Objective No.: 1312 Objective: 13riefly describe the operator actions required to:
Manually initiate EFW llegain control of EFIC/EFW components after EFW has been automatically or manually initiated Shutdown the EFW system after initiation Iteference:
K/A: 001 Auxiliary / Emergency Feedwater System 000 Generic A3.04 Automatic AFW isolation Task: 0190101003 Iteset/ bypass EFIC logic following EFIC actuation, importance: 4.1/ Expected Time (min): h O
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i Based on current plant conditions, which ONE of the following
{ statements correctly describes the minimum actions which must be i taken to regain control of EFV 14?
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i j a) EFIC channel "A"" Test Results Roset" P/B must be '
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b) EFIC channel "A" " Man Permissive" P/B must be depressed.
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114 Objective: Describe the operation of the Einergency Diesel Generator:
a) Stattup 1) Antoinatic 2) Manual b) Shutdown Iteference: SP-354A K/A: 004 Einergency Diesel Generator System 000 Generic A2.03 Parallel operation of the ED/Gs Task: 0000501014 Perform the required actions following an Emergency Diesel Generator actuation.
Importance: 3.1/3.1 Expectet!
Time (min):
2.25 g O
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0 O InLikm: #9 (Sit 0 A) Point Value (1.01 f]
Based on current plant conditions, which ONE of the following statements describe what is indicated by the ItED "Itcactor Trip" light inside the "C" ItPS channel on the 880 Trip module br.ag bright?
a) "C" ItPS Channel is tripped b) Three ItPS channels are tripped c) "C" CitDM breaker is open Oil the "E" Electronic Trip has actuated d) "C" CItDM breaker is open AND the "E" Electronic Trip has actuated Answer: d q
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Test Item: SSE-02/10 Lesson Plan: ItOT-4 28 Objective No.: 1117(a)
Objective: Discuss the indications and the effects of the following lamps on the Diamond Control Pancl:
a. Trip Confirm iteference:
K/A: 001 Control Rod Drivo 000 Generic K6.03 Reactor trip breakers including controls Task: 0010101009 Monitor the Control Rod Drivo System
Importance: 3.7/ Expected Time (min):
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O .O Test listnu #10 (Sito A) EginLYalue_(LQ1 Based on current plant conditions, which ONE of the following statements correctly describes the condition that is causing the TRIP CONFIRM larnp on the CHDM control panel to be *0N'7 a) "Three RPS channels are tripped, b) Rx Trip Lockout is tripped, c) All control rods (groups 1 through 7) are fully inserte d) All CRDM breakers (A, B, C, D) are open and both Electronic Trips (E, F) are presen O Answer: d
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O O Test Itemt SSE 02/new O I Lesson Plant itOT 4 06 ,
l Objective No.: H2 Objective: Describe the location / function of the controls and indications available for the diesel generator l
Iteference:
N/A: 004 Einergency Diesel Generator Systein 000 Generic A3.03 Indicating lights, meters, and recorders Task: 0640101004 Monitor the Etnergency Diesel Generator 0640101002 Start an Einergency Diesel Generator Importance: 3.4/3.4 Expected 1.5 Time (min):
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O O Test Item #11 (!i1LQAl l'olitLYahie (10)
Ilased on current plant conditions, if breaker 3209 were closed, which ONE of the following 4100V ES bus "13" feeder breakers would be blocked by the cross tie blocking logic?
a) 3206 b) 3208 c) 3210 d) 3212 O
Answer: c
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O O Test Item: SSE 02/18 O
Lesson Plan ItOT-410 Objective No.: 11 3 Objective: Froin meinory, list all protective interlocks and control
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features associated with the NIS.
Iteference: OP 210 K/A: 015 Nuclear Instrumentation System 000 Generic K4.01 Source ihmgo detector power shutoff at high powers Task: 0150101001 Verify function operation of the Nuclear Instruinentation System Importance: 3.1/3.3 Expected 3.0 Time (min):
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Test item: #12 (SRO A) Point Value (1.0) j
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Based on current plant conditions, which ONE of the following ;
statements correctly describes the mininnun conditions necessary for ;
source range NIs (NI 1, NI 2) to re energizo? j
a) Both NI 3 and NI 4 will have to drop to s 1 x 10* amps -
b) Both NI 3 and NI 4 will have to drop to s 5 x 10* amps
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c) Only NI-3 or NI 4 will have to drop to s 1 x 10* amps i d) Only NI 3 or NI 4 will have to drop to s 5 x 10* amps t
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O i Answer: d l
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O O Test Item: SSC-02/24 O
Lesson Plan: It0T 5 80 Objective No.: A2 Objective: Given a copy of the Abnormal Procedure be able to state the basic reason for any given Symptom or Follow up step and determino the applicability of the step for various transient scenario Iteference: ,
AP-700 K/A: 002 AC Electrical Distribution System 000 Generic K4.01 Ilus lockouts Task: 0620101001 Lineup the electical distribution system importance: 2,G/ Expected Time (min):
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Test item: #13 (SRO A) Point Value (1.Q1
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- r i Based on current plant conditions, if breaker 3209 ("A" EDG output l breaker) were closed, which ONE of the following would be the j expected? ;
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a) Only the "480 ES Bun 3A UV Lockout" would trip.
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j would actuat c) Both the "480 ES Bus 3A UV Lockout" would trip and the j
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-, "4160 ES Bus 3A ES/UV Block Lockout Actuated" would l actuat :
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! d) Neither the "480 ES Bus 3A UV Lockout" would trip nor the i "4160 ES Bus 3A ES/UV Block Lockout Actuated" would 1 actuate.
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Questions 14 through 18 are GENEltlC question J1Q NOT base your answers on the static freeze point.
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O O Test Item: SSE-G031 Lesson Plan: ROT-4 03 Objective No.: Ill Objective: DESCRIllE TILE LOCATION AND/Olt OPERATION OF Tile FOLLOWING SYSTEh! INSTilUhfENTATION:
i A. RAf A1, Itenctor llullding Purge
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Duct hionitor -
j lieferencet f(/A: 029 Containment Purge System 000 Generic K4.03 Automatic purgo isolation Task: 0880401000 Verify proper operation of the plant ventilation system following high radiation in the reactor buildin Importance: 3.2/ Expected Time (min):
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O O Test itenu #14 (SitO Al Poln1 Vahic (1.0)
Which UNE of the following describes the expected response when RM.Al actuates during shutdown operations (Mode 5)?
a) Purge supply fans will continue to run and the exhaust fans will stop, and purge supply and thn exhaust valves will remain ope b) Purge supply and exhaust fans will stop and purge supply and the exhaust valves will close, c) Purge supply fans will stop and the exhaust fans will continue to run, and purgo supply and the exhaust valves will remain ope d) Purge supply and exhaust fans will continue to run and the supply and exhaust valves will close.
ANSWER: d
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Test Item: SSE-G084 g
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Lesson Plan: ROT-415 Objective No.: 131 8 Objective: Describe the interlocks that exist in the EFIC system, and between the EFIC system and the RPS with regard to the
, L channel maintenance bypass functio ,
3 t}teference:
3 K/A: 061 Auxiliary / Emergency Feedwater System
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000 Generic System Knowledge of system purpose and/or
Generic #4 function Task: 0190101001 Monitor the EFIC system Importance: 4.0/ Expected Time (min):
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I i O OL h,; Item: #15 (SRO A) Point Value (1.31 4-
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j When the RPS is placed in shutdown bypass, which ONE of the t following statements describes the interlock that exists between the j RPS and EFIC systems.
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! a) Only the "0TSG Low Level" interlock is bypassed.
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- interlocks are bypassed.
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- . d) Both the "OTSG Low Pressure" and "Both Main Feed Pumps
! Tripped" interlocks are bypassed.
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O O Test Item: SSE-G033 Lesson Plan: ROT-4-07 Objective No.: G13 Objective: Describe the Halon System including the following items at a minimum:
A. Number of cylinder B. Number of bank C. Type of halon use D. Number of detectors needed to actuate the syste '
Reference:
K/A: 086 Fire Protection System 000 Genede K4.05 Halon Task: 0860104003 Monitor the fire protection system 0860204007 Perform SP-363, Fire Protection System &
W tests
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Importance: 3.0/ Expected Time (min):
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O O Test item: #16 (SRO A) Point Value (1.0)
O Which ONE of the following describes the minimum required to actuate the Halon Fire Suppression System in the Cable Spreading room?
a) An alarm from any two detectors in the same zone, b) An alarm from one detector in either zone, c) An alarm from one detector in each zon d) An alarm from two detectors from each zon O V ANSWER: c
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pi (a~'s v Test Item: SSE-G053 Lesson Plan: ROT-2-05 Objective No.: B2 Objective: Sketch the RCS and steam temperature profiles for 0% to 100% power and explain the shape of the curve Reference:
K/A: 002 Reactor Coolant System 000 Generic K5.15 Relationships between effects in the primary coolant system and the secondary coolant system Task: 10 CFR 55 Importance: 4.0/ Expected Time (min):
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O o Test item: #17 (SRO A) Point Value (1.0)
O Which ONE of the following statements describes the effect on the i primary system parameters as power is increased in the 0 -+ 15% power range with the Turbine Header Pressure controller incorrectly set to control at 850 psig?
I a) Initial Tc would be the same. RCS AT would be increased for a given power level. A lower power would be required to reach a Tave of 579' i b)- Initial Tc would be the same. RCS AT would remain the same for a given power level. The higher power would be required to reach a Tave of 579a c) Initial Tc would be lower. RCS AT would be increased for a given power level. A lower power would be required to reach O a Tave of 579aF.-
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d) Initial Tc would be lower. RCS AT would remain the same for a given power. A higher power would be required to '
reach a Tave of 579a ANSWER: 'd ,
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i Test Item: SSE-G047 Lesson Plan: ROT-4-56 Objective No.: B3 Objective: State the controls, interlocks, function, location, and power supply of the following:
a. SW Pumps (SWP-1A/1B/10)
Reference:
K/A: 008 Component Cooling Water System 000 Generic K4.01 Automatic start of standby pump Task: 0080101004 Start the SW system-0080101006 Operate the nuclear services booster pumps 0080101009 Monitor the SW system h Importance: 3.1/ Expected 2.0
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O O p Test item: #18 (SRO A) Point Value (1.0j V
Which ONE of the following describes how the SW pump will respond when a loss of offsite power occurs coincident with HPI actuation?
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a) The pumps will be prevented from auto start until all ES equipment has loaded on to the bus, b) As soon as power is restored the SW pumps (IA/1B) will automatically start due to the low pressure condition, c) The automatic start on low pressure will be prevented, but the pumps will auto start when block loaded by the ES syste p d) The operator will have a permissive to restart either SWP-1A or SWP-1B, but the automatic start will be totally blocked.
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ANSWER: c l
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l Maahn f 4 3W ATTACHMENT 3 - 4 ef, d TDP 106 Rev 13 i
- Page 23 of 71 ANSWER KEY COVER SIIEET
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TRAINING PROGRAM TITLE: LICENSED OPERATOR REOUALIFICATION
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EXAMINATION TITLE: __ LICENSED OPERATOR REOUALIFICATION - CATEGORY B i
j EXAMINATION NAME OR NUMBER: 1992 CATEGORY B SRO EXAM
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PREPARER: ,'[ w _
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DATE: '/j e A
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APPROVAL: vut hwuh DATE: I l - l o -9 2. -
(Aluclear Training Supervisor
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INSTRUCTIONS FOR TAKING TIIE EXAMINATION Use black ink or dark pencil only to ensure legible copie . Ensure your name is printed in the blank provided on the cover sheet of the examination and the answer shee . Each question has only ONE correct answer. Mark your answers on the answer sheet provided and do not leave any question blank, if additional paper is required, use only the lined paper provided by the examine . All questions are worth 1.0 poin . If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 6. The examination is designed to take approximately 90 minutes to
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b complete. You will be given 2 HOURS to complete the examination, 7. The questions have been time validated by knowledgeable persons. You should be aware that not every answer needs to be verified by consulting a reference and excessive usage of reference material may cause you to not complete the examination in the allotted tim . Restroom trips are limited and only one examinee at a time may leav You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromis . Cheating on the examination could result in revocation of your license and may result in more severe penaltie . 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 complete . When you are finished and have turned in your completed examination, leave the examination are ,a
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l Test Item: 133 Lesson Plan: ROT-5-36 Objective No.: B3 Objective: Given EM 204A and the required data, be able to complete a dose assessment.
Reference: EM 204A K/A: 000 Emergency Plant Evolutions 038 Steam Generator Tube Rupture System Knowledge of system status criteria which Generic #2 require the notification of plant supervisors or off plant personnel.
Task: 1150501001 Estimate off-site dose during a radiological release using EM-204(A).
Importance: 3.0/3.9 Expected 4.5 Time (min): g I
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- O- Test Item #1-(SRO B) ' Point Value (1.0) .
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A steam generator tube rupture has occurred. There is a release in i progress through the condenser exhaust line. The plant has been placed in a stable condition and an off-site initial dose assessment is to be completed. The following data is provided:
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Avg. Wind Direction 315*-
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Wind Range- 500 i -
Wind Speed - 3 m/sec.
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Delta T- -1.2aF
- - Which ONE of the following is the weather condition " Stability Class"? ;
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a) Stability Class "B"
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b) Stability Class "C"
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- c) Stability Class "D"
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d) Stability Class "F,G" i-
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(mu) v Test Item: 036 Lesson Plan: ROT 5-62 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure be able to state a basic reason for any given Symptom or Follow up actio Reference: AP-360 K/A: 000 Emergency Plant Evolutions 025 Loss of Residual Heat Removal System EK3.01 Shift to alternate flow path Task: 0050401001 Perform the required actions for a loss of decay heat remova Importance: 3.1/ Expected Time (min):
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O P L/ U Test Item #2 (SHO B) Point Value (1,0)
O Given the following conditions:
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A loss of both Decay Heat removal pumps has occurred
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RCS pressure is 125 psig
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RCS temperature is 130aF
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Both OTSGs are available
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The RCS is completely filled and PZR level is 60 inches Which ONE of the following alternate cooling methods should the operator use?
a) OTSG cooling b) Spent Fuel cooling t'
t ) c) HPI cooling d) BWST drain through LPI to vessel Answer: a l
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I Test Item: 374 O, Lesson Plan: ROT-5-64 Objective No.: B3 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given Symptom, Immediate or Follow up action.
Reference: AP-450 K/A: 059 Main Feedwater System 000 Generic K1.03 Steam Generators Task: 0000501010 Perform the required actions following an Engineered Safeguards actuatio Perform the actions to ensure that core cooling and subcooling margin are maintained during an emergency event.
Importance: 3.1/ g Expected 2.5 Time (min):
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i-j-. Test Item #3 (SRO B) Point Value (1,0)
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Following a loss of the Unit 4160 VAC and 6900 VAC buses due to a fire, ,
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i Emergency Feedwater is lost. The decision is made to use Main
{ Feedwater to feed the OTSGs. The following plant conditions exist:
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o- Levelin both OTSGs = 12 inches o Pressure in both OTSGs = 800 psig
! o "A" Unit 4160 VAC Bus energized i (other unit buses are de-energized)
o- "A" MFP operating in recirculation l Which ONE of the following would be the correct method for feeding
- the OTSGs?
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- a) Feed OTSGs through the high nozzles at - 1000 gpm/OTSG.
!O j b) Feed OTSGs through the lower nozzles at - 1000 gpm/OTSG
c) Feed OTSGs through the high nozzles at - 1500 gpm/OTSG
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, d) Feed OTSGs through the lower nozzles at ~ 500 gpm/OTSG i
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- Answer; a
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U, V Test Item: 096 Lesson Plan: ROT-5-01 Ob.lective No.: Al
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Objective: Given a copy of Technical Specifications and Technical Specification Interpretation, clarify and/or interpret STS requirement Reference: STS 3.0.4/3.9.2, TSI 8610, Table K/A: 015 Nuclear Instrumentation System 000 Generic t
System Knowledge of Technical Specifications Generic #5 bases and definitions related to limiting conditions for operations and safety limit Task: 3410103036 Evaluate plant systems performance and coordinate actions per STS in the event a LCO is entered /not satisfie Importance: 3.3/ Expected Time (min):
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Test Item #4 (SRO B) Point Value (1.0)
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The following conditions exist:
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The plant is in Mode 5 and refueling preparations are underway.
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Due to problems.with the Public Address System, audible source range l indication is ng1 operable in the' Reactor Building,
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The outage shift manager wants to start detensioning the head bolts, i
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! a) The head bolts may be detensioned. Audible source range
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indication is only required during core alterations or positive-
) reactivity insertions.
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b) The head bolts may be detensioned if visual source range
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indication is available in the control room and direct
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cem menicetienieestesitehed betweenthecentreireem end the refueling station.
i l c) The head bolts may be detensioned if audible source range-
! indication can be made operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of
! detensioning the head bolts.
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d) The head bolts must no't be detensioned. 'Detensioning.would
[ involve a Mode change and Technical Specifications does not -
allow discretionary Mode changes unless required equipment for that Mode is operabl :
Answer: - d
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o n V V Test Item: 361 Lesson Plan: ROT-4-09 Objective No.: B9 Objective: Discuss the operation of the Controlling Temperature Select Switch and the Auto / Manual Tave Select Switch, including inputs and output Reference: OP 501 K/A: 016 Non Nuclear Instrumentation System
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000 Generic A2.03 Interpretation of transmitted signal Task: 0160101002 Monitor the non nuclear instrumentation syste Importance: 3.0/ Expected Time (min):
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O The unit is operating at 100% power with all ICS stations in automati During a transfer of the RC flow plug in the "A" RPS cabinet, the operator on the MCB notes a prolonged rod insertion. Which ONE of the following is a probable cause of this event?
a) The plug transfer has caused a re ratio of feedwater due to the temporary loss of the "A" loop flow signa b) The AUTO / MANUAL (Tave) transfer switch transferred to an alternate signal which deviated from the controlling signa c) The loss of the RC flow signal generated a variable flow runback signal which reduced the ULD deman d) The feedwater total flow circuit modified reactor demand
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based on the new RC flow signa ,
Answer: b O
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Test Item: 389
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Lesson Plan: ROT-4-13 -
Objective No.: B8 Objeellve: Given the associated procedure, discuss the following evolutions:
J. Place ES Channelin a tripped condition - OP-507 Reference: OP 507 K/A: 013 Engineered Safety Features Actuation System 000 Generic A3.01 Input channels and logic Task: 0130101004 Bypass Engineered Safety Features 0130101009 Align the Engineered Safety Features Actuation Systern as required for various plant mode g 0130401002 Place an Engineered Safety Features Actuation System channel in the tripped conditio Importance: 3.7/ Expected Time (min):
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During operation at full power, it is determined that the pressure transmitter feeding the RC1 channel of ES is inoperable due_to=
calibration problems and that the channel must be placed in a tripped -
condition to comply with Technical Specifications. Which ONE of the:
following action statements below is correct for this condition?
a) On the RC pressure test module for the affected channel, you should select._the " TEST OPERATE" position, _This will result in a trip.of the HPI and LPI systems for that channel.-
b) On the RC pressure test module for the_affected channel, you should select the "T2" position and adjust the setpoint until both the IIPI and LPI systems trip for that channe 'l c) - On the RB pressure test module for the affected channel, you O should select the " TEST OPERATE" position. This will result in a trip of the HPI, LPI, and RBIC systems for that channe d) On the RC pressure test module for th'e affected charmel, you should select the "T2" position and adjust the setpoint until the HPI, LPI and RBIC systems trip for that channel.-
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O O Test Item: 038 Lesson Plan: ROT-4 91 Objective No.: F5 Objective: Discuss the procedure for transferring a vital instrument bus power supply.
Reference: OP 703 K/A: 062 AC Electrical Distribution System 000 Generic K4.10 Uninterruptable ac power sources Task: 0620401001 Direct the transfer of a vital power supply Importance: 3.1/3.5 Expected 2.0 Time (min):
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O O Test Item #7 (SHO II) Point Value 0,0)
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V While the plant is in Mode 3, Inverter 3D trips off the line due to an internal electrical failure. Which ONE of the following statements describes the result of this failure?
a) The VBXS will automatically swap to the alternate AC source, b) The bus will be de-energized for 7 to 10 seconds and then be automatically re-energized by the VBX c) The bus must be manually swapped to the alternate power sourc .
d) The VBXS will lose control power and fail to transfe Answer: a
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. Test Item: 383 h Lesson Plan: ROT-4-91 Objective No.: Al Objective: Discuss the Technical Specifications associated with the Electrical Distribution syste Reference: STS 3.8. K/A: 062 AC Electrical Distribution System 000 Generic System Knowledge of the Technical Specifications Generie #5' bases and definitions related to limiting condition for operations and safety limit Task: 3410103037 Apply STS directions for safety limits, safety system settings and LCO Importance: 3.0/ Expected Time (min):
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The plant is at 3% power during a return to power following an outag Due to problems with wiring, the B and D inverters have just been shutdown and will be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The respective transfer switches are selected to the alternate sources. Which ONE of the following would be the correct course of action based on the above information?
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a) Restore the inverters within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in Hot Standby within the next 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
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following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> b) Enter Technical Specifications and maintain the present power level until the inverters are returned to servic c) Enter Technical Specifications and continue power escalatio (~)g
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d) Technical Specification action 3.0.3 must be applied and the plant must be placed in Hot Standby within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Answer: b
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Test Item: 033
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Lesson Plan: ROT-4 54 Objective No.: B13 Objective: Describe the limits and precautions of OP-404.
Reference: OP-404, SP-422 K/A: 005 Residual Heat Removal System 000 Generic A1.01 IIeatup/cooldown rates Task: 0050101016 Regulate Decay Heat flowrate 0050101008 Monitor the Decay IIeat Removal System Importance: 3.5/3.6 Expected 2.5 Time (min):
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O O Test item #9 (SRO H) Point Value (1.0)
The Decay Ileat system is operating nearing the completion of a cooldown. The following readings were recorded on the cooldown surveillance:
RCS RCS Pressure Temperature (psig) (oF)
1300 hrs 105 110 1400 hrs 103 106 1500 hrs 100 105 1600 hrs 95 105 A Which ONE of the following statements describes the correct actions to V be taken based on the above data?
a) The plotting of cooldown must be continued for one additional shift, b) The plotting of cooldown must be continued for an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, c) Plotting can be secured if no further cooldown is required and 3 consecutive readings of temperature agree within i 2oF d) Plotting can be secured as long as RCS temperature does not vary by more than i loF per hour during the remainder of the.cooldown.
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O O Test Item: 381 I.esson Plant itO T 4-54 Objective No.: 11 8
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Objective Describe the lirnitations on Decay IIcat flo Iteference: OP-404 K/A: 005 Itesicinal IIcat Itcinoval Systein 000 Generic K4.02 Motles of operation Task: 0050101010 Establish auxiliary spray flo Importance: 3.2/ Expected Time (min):
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O O Test item #10 (SEO ID PnhtLLihte (Idu Cooldown and depressurization of the itCS is in progress using the Decay IIcat itemoval system. DilP-1 A is in operation and Dil auxiliary spray is being provided to the pressurizer. Pressurizer heater banks A, B, and C are in AUTO; banks D and E are OFF. The following conditions exist:
ItCS Pressure 90 psin ItCS Th . . . . 229aF DII Flow . . 3000 ginn Which ONE of the following conditions would present a problem during operation in the above configuration?
a) Non condensable gases will not be removed from the pressurizer causing accumulation in the systein and pressure control problem b) Fluid stratification in the pressurizer surge l'no will occur due to the flow in the auxiliary spray line, c) Excessive pressurizer spray in combination with pressurizer heater operation will cause gases in the pressurizer to be driven into solution and deposited in the RCS loop d) The flow aligmnent will increase the fluid stratification and possibly cause steam bubble formation in the RCS hot leg Answer: d
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O O Test Itein: 425 1.esson Plan: It0T 412 Objective No.: 111 1 Objective: Given pertinent details froin any of the following industry events reports, discuss its relevance to Cit 3 operations:
a. 1989 Shearon llartis ItPS iniscalibration (SOElt 08 90)
Reference: OP 204 K/A: 002 Itcactor Coolant Systern 000 Generic K5.10 Itelationship between reactor power and ItCS differential ternperature Task: 0150101001 Verify functional operation of the Nuclear lustruinentation systern.
Innportance: 3.6/4.1 Expected Tirne (inin): g O
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O O Test item #11 (SitO II) hdnLynlue (1.0)
The initial power escalation following a refueling outage is being performed. The reactor power level is stabilized. The following indications are available to the operator at the control board:
NI 5 100! NI 0 1007c NI 7 100'io NI 8 997o Th Loop A 603.5' F Th Loop 11 603.5' F Tc Loop A 553.5' F Tc Loop 13 553.0*F ItCS Tave 578'F Which ONE of the following describes the action required based on the information provided?
a) lleduce power to < 757o and request immediate calibration of the excore nuclear instrutnentatio b) Reduce power to s 757o and reduce the overpower trip setpoint to s 857c of rated thermal power within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, c) Immediately commence a plant shutdown and have the plant in Mode 3 within I hour, d) Immediately reduce power < 1007o RTP and have the excore nuclear instruments calibrated, or, within I hour commence plant shutdown to Mode 3 to be completed within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Answer: c
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O O Test Itein: 134 Lesson I'lant itOT 4 69 Objective No.: G4 Objective: Describe the basic operation of the following control systerns:
c) Condensato Dernineralizer llypasa Valves iteference: OP 601 K/A: 050 Main Feedwater Systern 000 Generic Systein Ability to locate, explain, and apply all Generic #7 liinits and precaution Task: 0570104002 Perforin lineups of the condensate dernineralizer systern
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Irnportance: 3.1/ Expected Time (inin):
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Given the following comlitions:
. The plant is at 100% powe ;
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- An unexplained air system failure has caused the inlet valves to all 6 condensate demineralizers to fail close Which ONE of the following statements describes the effect and reason -
for the effect the above conditions will have on Main Feedwater?
a) Main Feedwater will ng be affected. The Condensate pumps will automatically reduce 0,w allowing time for the bypass valves to be opene . .
b) Main Feedwater will ad be c!tc .. d. There are two bypass valves which will automatically open st 80 psi .
O c) - Main Feedwater will be lost. The bypass valves can ad be opened quickly enough with a differential pressure of 80 psi, and the Condensate Pumps will shutdown-
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d) Main Feedwater may be lost. The bypass valves must be opened by the Turbine Building Operator and condensate -
flow restored prior to a loss of the MFW Booster Pump Answer - b
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_
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O O I
Test item: 395 Lesson Plan: ItOT 318 Objeettve No.: 1 Objective: Describe symptorns that can distinguish LOCAs from other transient Reference: TBD K/A: 002 Pressurizer Pressure control System 000 Generic A2.01 Ilenter failures A2.02 Spray valve failures Tusk: 0000501001 Analyze indications to determine that an emergency / abnormal plant event is in progress 0000501003 Analyze events to determine the cause of Importance: 4.3/ .2/ Expected Time (min):
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Iest Itern #13 (SILO II) Poltti Value (1.0)
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- After receiving the ItCS low pressure alarin. the nuclear operator scans the control board indicators and observes the following
ItCS Tave ...... 579'F llCS pressure . . . . 2100 psig and 4 at 100 psig/inin
. PZR teniperature . 643*F and 4 at 6*F/inin
P7It level . . . . . . . constant
,
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Makeup flow . . . . . 8 to 10 gpm higher than normal ItCPs running ... 4 j llB pressure ..... nortual and constant Reactor power ... 40%
RCP seal injection normal I
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Which ONE of the following describes the developing scenario based on the provided data?
'
,
r a) Loss of all pressurizer heaters
. b) Stuck open pressurizer spray valve
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c) Pressurizer steam space leak i
d) Letdown line leak
.
l Answer: c O
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O O Test Itern: 258 Lesson Plan: ROT 5-01 Objective No.: 111 0 !
Objective: Given any plant condition and a copy of Technical Specifications, identify those conditions which are violations of a lirniting condition for operation and discuss the required i corrective actions, j
__
Heference: SP 321, STS 3.0.3, STS 3.8.1.1b, STS 4.8.1.1.la K/A: 002 AC Distribution Systern 000 Generic System Knowledge of the Technical Specifications Generic #5 bases and definitions related to lhniting conditions for operation and safety limit Kl.04 Off site power sources Task:
Importance:
1190301015 Apply Technical Specification requirernents g
3.1/ .7/4.2 Expected 4.5 Time (min):
O f
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O O Test item: #7 (HO A) Point Value (1.0)
You have been instructed to load the "A" EDO. Based on current plant conditions, which ONE of the following statements describes the result of this loading assuming the speed droop setting is left in the ES standby position? (Assume the operator takes no action other than closing the EDO output breaker.)
a) Breaker 3211 will automatically open when the EDO reaches overload conditions, b) The EDO output breaker will automatically open due to an overcurrent conditio c) Breaker 3211 will automatically open due to an overcurrent conditio O The EDO output breaker will automatically open and the d)
engine will trip due to a reverse power conditio Answer: a O
g .1 . . . . . . . . _ .
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O O Test Itenu O
SSE 02/15 Lesson Plan: ItOT-412 Objective No.: B3(II)
Objective: Describe the location and/or operation of the following components:
II. Reactor Trip Module Iteference:
K/A: 012 Itcactor Protection System 000 Generic A3.07 Trip breakers Task: 0120101005 Monitor the Reactor Protection Syste Importance: 4.0/ Expected 2.25 Time (min):
O G
l . -
t O
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O O T *it -> *=<ao ^) "ei"* v tu tta>>
Based on current plant conditions, which ONE of the following statements describe what is indicated by the RED " Reactor Trip" light inside the "C" RPS channel on the 880 Trip module being bright?
a) "C" RPS Channel is tripped b) Three RPS channels are tripped c) "C" CRDM breaker is open QB the "E" Electronic Trip has actuated d) "C" CRDM breaker is open AND the "E" Electronic Trip has actuated O
_ Answer: d
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Test Item: SSE-02/16 Lesson Plan: ItOT-4 28 Objective No.: B17(a)
Objective: Discuss the indications and the effects of the following lamps on the Diamond Control Panel:
a. Trip Confirm Iteference:
K/A: 001 Control llod Drive 000 Generic KG.03 Itcactor trip breakers including controls Task: 0010101009 Monitor the Control Itod Drive System Importance: 3.7/4.2 Expected 1.5 Time (min):
O O
_ _ _ _ _ - - _ _ . _ _ -
-__ -_ ~ . . .
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O T *it -> *a<no ^> eei i v i <> a)
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Ilased on current plant conditions, which ONE of the following .
'
statements correctly describes the condition that is causing the TRIP CONFIRM lamp on the CRDM control panel to be *0N"?
.
a) Three RPS channels are trippe .
.
b). Rx Trip Lockout is trippe ,
c) All control rods (groups 1 through 7) are fully inserte I d) All CRDM breakers (A, B, C, D) are open and both Electronic Trips (E, F) are presen ,
O Answer: !
,
,
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Test Item: SSE-02/new Lesson I'lant HOT 4 06 Objective No.: B2 Objective: Describe the location / function of the controls and indications available for the diesel generators.
Reference:
K/A: 064 Ernergency Diesel Generator System 000 Generic A3.03 Indicating lights, meters, and recorders Task: 0640101004 Monitor the Emergency Diesel Generator 0640101002 Start an Emergency Diesel Generator Importnnce: 3.4/3,4 Expected 1.5 Time (min):
O O
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.. - -- .- - - - _ . - . . . . - . - _ . _ . . - . . - . - - - _- --._ -- ._ . .-
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T_ts.Lilein: #10 (ILO.A) 1>oinLLihie (1.m I
!
! Ilased on current plant conditions, if breaker 3209 were closed, which
.
ONE of the following 4160V ES bus "B" feeder breakers would be !
'
l blocked by the cross tic blocidng logic?
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t l a) 3206
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I b) 3208
!
c) 3210 t
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j d) 3212 k
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- Answer: e
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Test Item: SSE-02/18 Lesson Plan: It0T 410 Objective No.: 13 3 Objective: From memory, list all protective interlocks and control features associated with the NI Iteference: OP 210 K/A: 015 Nuclear Instrumentation System 000 Generic K4.01 Source llange detector power shutoff at high powers Task: 0150101001 Verify function operation of the Nuclear instrumentation System Importance: 3.1/ Expected Time (min):
O O
g - . - . - - ,
_ _ - ._ - -.~_- __ . _ _ _ - . . . . . _ _ _ _ _ _ _ . . _ . . ..
O o O re i iternteai <no ^> "ei"< v t"> <noi llased on current plant conditions, which ONE of the following statements correctly describes the minimum conditions necessary for sourco range NIs (NI 1, NI 2) to re energize?
a) Both NI 3 and NI 4 will have to drop to s 1 x 10* amps b) 130th NI 3 a . NI 4 will have to drop to s 5 x 10" amps c) Only NI 3 or NI-4 will have to drop to s 1 x 10' amps d) Only NI 3 or NI 4 will have to drop to s 5 x 10' amps O
O Answer: d
I
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o O -
O Test Itern: SSE-02/08 Lesson Plan: ItOT-4 60 Objective No.: 13 3 Objective: Describe the alarins, indications, control functions, and protective functions associated with ItCS pressure.
Reference: OP 204 K/A: 010 Pressurizer Pressure Control Systein 000 Generic A4.02 PZit heaters Task: 0100101004 Monitor the ItCS Pressure Contbl Systern Irnportance: 3.6/3.4 Expected 1.5 Tirne (rnin):
O l
_ _ _ . _ _ _ . . .. _ _ _ _ _ _ _ . _ . . - .._ . _ . _ _ _ _ . . ._ _
-
O o O re iiie-, ,i2 <ito 61 r1, int vn11,e < >.o, llased on current plant conditions, if ItCS pressure is decreased to 2000 psig, which ONE of the following statements correctly describes the response of the PZit heaters?
a) All PZit heaters will energize autoinatically, b) Only banks D and E will energize automaticall c) All PZit heaters will remain de energized until I(C 3 PIC PZit IIcater Control lland/ Auto station demand is increase d) Only banks D and E will energize if IIC 3 PIC PZIt lleater Control lland/ Auto station demand is increased.
O Answer: b (v
_ _ _ . . . . . , . _ . . _ . _ . . _ .
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Test Item: SSE 02/20 h
Lesson Plan: ItO T 4 15 Objective No.: 111 8
,
Objective Descrit he interlocks that exist in the EFIC System, and between wie EFIC System and the ItPS with regard to the channel maintenance bypass function.
lleference: AR 403 K/A: 061 Auxiliary / Emergency Feedwater System 000 Generic System Knowledge of operator responsibilities Generle #1 during maintenance, tests, and surveillance
,
activities Task: 0610101042 Monitor the Emergency Feedwater System Importance: 3.7/4.0 Expected 1.5 Time (min): g W
G
_ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ . . _ _ _ _ _ _ . _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ . . _ _ _ _ _ _ . _ . . _ _ . _ .
i,
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j Test itenu #13Jf(O A) PoinLMthte (1,0)
l i
l Ilased on current plant conditions, which ONE of the EFIC channels
- could be placed into " Maintenance Ilypass" at this tinne?
i j a) EFIC channel "A" l
b) EFIC channel "B"
!
!
j c) EPIC channel "C"
- l
{ d) EFIC channel "D"
lV Answer: a i
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i j Questions 14 through 18 are GENERIC cluestions.
t l DQ NSJ hase your answers on the static freeze point.
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n O u Test Itein: SSE G031 Lesson Plan ItOT 4 03 Objective No.: 111 Objective DESCftlllE Tile LOCATION AND/Olt OPEltATION OF Tile FOLLOWING SYSTEM INSTitUMENTATION:
A. ItM A1, Iteactor Iluilding Purge Duct Monitor Iteference:
K/A: 029 Containment Purge System 000 Generic K4.03 Automatic purgo isolation Task: 0880401006 Verify proper operation of the plant ventilation system following high radiation in the reactor buildin Importance: 3.2/ Expected Time (min):
O
.. . . _ . _ _ _ . _ _- - - . - _ _ _ _ _ _ . _ _
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O o O Te ite- "' 42no ^) t"< v u=1'ni Which ONE of the following describes the expected response when ItM Al actuntes during shutdown operations (Mode 5)?
a) Purge supply fans will continue to run and the exhaust fans will stop, and purgo supply and the exhaust valves will remain ope b) 1 urge supply and exhaust fans will stop and purge supply and the exhaust valves will clos c) Purge supply fans will stop and the exhaust fans will continue to run, and purge supply and the exhaust valves will remain ope O d) Purge supply and exhaust fans will continue to run and the supply and exhaust valves will clos ANSWEIt: d O -
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O O -
O Test Itenu SSE G084 Lesson Plan: ROT 415
.
Objective No.: B18 Objective: Describe the interlocks that exist in the EFIC system, and between the EFIC system and the itPS with regard to the channel maintenance bytmss function.
Itererence:
K/A: 001 Auxiliary / Emergency Feedwnter System 000 Generic System Knowledge of system purpose and/or Generic #4 function Task: 0190101001 Monitor the EFIC system Importance: 4.0/4.0 Expected 4.0 Time (min): g O
_ _
- - - . - - - _ - - - - . - . - _ . - . - - . - - _ - - - - - . . . - . . - - . -
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When the HPS is placed in shutdown bypass, which ONE of the
following statements describes the interlock that exists between tho itPS and EFIC systems, a) ' Only the *0TSG Low Level" interlock is bypasse ,
b) Only the EFIC "Both Main Feed Pumps Tripped" interlock is bypasse ,
c) Both the "0TSO Low Pressuro" and "0TSO Low Level" interlocks are bypasse d) Both the "0TSG Low Pressure" and "Both Main Feed Pumps ;
O Tripped" interlocks are bypasse .;
Answer: b
.
.
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O O Test Item: SSE-G033 O
Lesson Plan: ItO T 4-07 Objective No.: 013 Objective: Describe the IIalon System including the following items at a minimum:
A. Number of cylinder B. Number of bank C. Type of halon use D. Number of detectors needed to actuate the syste Hererence:
K/A: 080 Fire Protection System 000 Generic K4.05 Halon Task: 0860104003 Monitor the fire protection system 0860204007 Perform SP 363, Fire Protection System tests g
Importance: 3.0/ Expected Time (min):
O
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~ . - _ _ . - _ . _ . . _ _ _ . . . _ _ . _ . _ _ . _ . - _ _ _ _ . . _ . _ _ _ _ . . _ . _ . _ . . _ . _ . . . _ . . _ . _ _ _ . _ _ _ . .-
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Test item: #16 (R0 A) .. Point Value (1.0): .
Which ONE of the following describes the minimum required to actuate -
tho Salon Fire Suppression System in the Cablo Spreading room?
-
l a) An alarm from any two detectors in the same zon ,
e .
!
! b) An alarm from one detector in either zone.
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c) An alarm from one detector in each zone, i
!
! d) ' An alarm from two detectors from each ' zone.
-
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ANSWER: c
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Test Item: SSE-G053 h
_
Lesson Plan: ROT-2-05 .
Objective No.: B2 Objective: Sketch the RCS and steam temperature profiles for 0% to 100% power and explain the shape of the curve _
Reference: , .,
K/A: 002 Reactor Coolant System 000 Generic K5.15 Relationships between effects in the
primary coolant system and the secondary coolant system Task: 10 CFR 55 Importance: 4.0/ Expected Time (min): g
,
W a
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O o Test item: #17 (RO A) Point Value (1.0)-
Which ONE of the following statements describes the effect on the primary system parameters as power is increased in the 0 - 15% power range with the Turbine Header Pressure controller incorrectly set to >
control at 850 psig?
a) Initial Tc would be the same. : RCS AT would be increased for a given power level.1 A lower power would be required to-reach a Tave of 579aF. _
b) -Initial Tc would be the same. RCS AT would remain the -
same for a given power level. The higher power would be
~
required to reach a Tave of 579a c) Initial Tc would be lower. RCS AT would be increased for a O eive re erievei. ^ >e-erre-er e ia serea ireatereech a Tave of 579a d) Initial Tc would be lower. RCS AT would remain the same for a given power. A higher power would be required to -
reach a Tave of 579aF.-
- ANSWER: d O
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_ . . . _ .._ ._._.; _ . _ - 2_ _ _ - _
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O Test Item: SSE-G047
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Lesson Plan: ROT-4-56
.
Objective No.: B3 Objective: State the controls, interlocks, function, location, and power supply of the following:
a. SW Pumps (SWP 1A/1B/1C)
Reference:
K/A: 008 Component Cooling Water System 000 Generic
- K4.01 Automatic start of standby pump
!
Task: 0080101004 Start the SW system 0080101006 Operate the nuclear services booster pumps 0080101009 Monitor the SW system Importance: 3.1/ Expected _ Time (min):
O
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to v Test item: #18 (110 A) Point Value (1.0)
Which ONE of the following describes how the SW pump will respond when a loss of offsite power occurs coincident with HPl actuation?
a) The pumps will be prevented from auto start until all ES equipment has loaded on to the bu b) As soon as power is restored the SW pumps (IA/1B) will automatically start due to the low pressure conditio c) The automatic start on low pressure will be prevented, but the pumps will auto start when block loaded by the ES syste fh V d) The operator will have a permissive to restart either SWP-1A or SWP-1B, but the automatic start will be totally blocke ANSWElt c n
V
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,
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O o Cny,4/ #islu ATTACllMENT 3 ##$ #N.soi#Y#
TDP-106 Rev 13 Page 23 of 71 ANSWER KEY COVER SIIEET TRAINING PROGRAM TITLE: LICENSED OPERATOR REQUALIFICATION EXAMINATION TITLE: LICENSED OPERATOR REQUALIFICATION - CATEGORY B EXAMINATION NAME OR NUMBER: 1992 CATEGORY B RO EXAM _
/
b PREPARER: r -
/ DATE: // ' /O -/77 k
/ u APPROVAL: uA _ wLtk DATE: / I-/d - 92 (/fuelear Training Supervisor (")
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Q O INSTRUCTIONS FOR TAKING THE EXAMINATION- Use black ink or dark pencil only to ensure legible copie . Ensure your name is printed in the blank provided on the cover sheet of the examination and the answer shee . Each question has only ONE correct answer. Mark your answers on the answer sheet provided and do not leave any question blank. If -
additional paper is required, use only the lined paper provided by the examine . All questions are worth 1.0 poin . If parts of the examination are not clear with respect to their intent, ask questions of the examiner onl . The examination is designed to take approximately 90 minutes to complete. You will be given 2 HOURS to complete the examinatio .-O The questions have been time validated by knowledgeable persons. You should be aware that not every answer needs to be verified by--
consulting a reference and excessive usage of reference material may cause you to not complete the examination in the allotted tim . Restroom trips are limited and only one examinee at a time may leav You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.= Cheating on the examination could result in revocation of your license and may result in more severe' penaltie . -You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have n_ot received or been given any assistance in completing the examination. This must be signed AFTER the examination has been complete . When you are finished and have turned in your completed examination, leave the examination are vO
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Test Item: 133 Lesson Plan: ROT-5 36 Objective No.: B3 Objective: Given EM 204A and the required data, be able to complete a i
dose assessmen Iteference: EM 204A K/A: 000 Emergency Plant Evolutions 038 Steam Generator Tube Rupture System Knowledge of system status criteria which Generic #2 require the notification of plant supervisors or off-plant personne Task: 1150501001 Estimate off site dose during a radiological release using EM-204(A).
Importance: 3.0/ Expected Time (min):
g J
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Test Item #1 (HO 10 ' Point Value (1,0)
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j A steam generator tube rupture has occurred. There is a release in i progress through the condenser exhaust line. The plant has been placed
~
in a stable condition and an off site initial dose assessment is to be completed. The following data is provided:
l
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Avg. Wind Direction 315*
j - Wind Range Soo j -- Wind Speed .3 m/sec-
! -
- Delta T ' -1.2 = F
-
Which ONE of the following is the weather condition " Stability Class"? -
p a) Stability Class "B
i
!
[ b) . Stability Class "C"
!-
j c) Stability Class "D" i.
! d)- Stability Class "F,G"'
!
Answer: [b- opcl0
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Test Item: 036 Lesson Plan: ROT.5-62 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure be able to state a basic reason for any given Symptom or Follow up action.
Reference: AP 360 K/A: 000 Emergency Plant Evolutions 025 Loss of Resicinal IIcat Removal System EK3.01 Shift to alternate flow path Task: 0050401001 Perform the required actions for a loss of decay heat removal.
Importance: 3.1/3.4 Expected 4.0 Time (min):
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l; Test Item #2 (RO B) Point Value (1.0) ,
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l .Given the following conditions:
1-
! -
A loss of both Decay Heat removal pumps has occurred j -
RCS pressure is 125 psig -
- . -
RCS temperature is 130aF
! -
Both OTSGs are available
} -
The RCS is completely filled and PZR level is 60 inches i .
l Which ONE of the following alternate cooling methods should the
} operator use?
i-jL a) OTSG cooling
!
1-
b)- Spent Fuel cooling l
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c) HPI cooling
,
t-d) -BWST.~ drain through LPI to vessel i.
i-l Answer: a
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O O Test Item: 374 Lesson Plan: ROT-5-64 Objective No.: B3 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given Symptom, Immediate or Follow up actio Reference: AP-450 K/A: 059 Main Feedwater System 000 Generic Kl.03 Steam Generators Task: 0000501006 Perform the actions to ensure that core cooling and subcooling margin are maintained during an emergency even Importance: 3.1/. Expected Time (min): _
O l
- _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ __
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O o Test Item #3 (RO B)' Point Value (1.0)
O Following a loss of the Unit 4160 VAC and 6900 VAC buses due to a fire,
-
Emergency Feedwater is lost. Tlie decision is made to use Main' '
Feedwater to feed the OTSGs. The following plant conditions exist:
o Levelin both OTSGs = 12 inches o Pressure in both OTSGs = 800 psig o RCS temperature = 525aF o Feedwater temperature = 135cF
"
o - A" Unit 4160 VAC Bus energized-(other unit buses are de-energized)
o "A" MFP operating in recirculation Which ONE of the following would be the correct method for feeding the OTSGs?
a) Feed OTSGs through the high nozzles at - 1000 gpm/OTSG b) Feed OTSGs through the lower nozzles at;- 1000 gpm/OTSG-c) Feed OTSGs through the high nozzles at - 1500 gpm/OTSG d) Feed OTSGs through the lower nozzles _at - 500 gpm/OTSG Answer:. a LO:
____:______--_-____
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Test Item: 361 Lesson Plan: ROT-4-09 Objective No.: B9 Objective: Discuss the operation of the Controlling Temperature Select Switch and the Auto / Manual Tave Select Switch, including inputs and output Reference: OP-501 K/A: 016 Non Nuclear Instrumentation System 000 Generic A2.03 Interpretation of transmitted signal Task: 0160101002 Monitor the non nuclear instrumentation syste Importance: 3.0/ Expected Time (min):
O
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_ . - _ _ _ _ _ _ _ .___ _ ._ . . _._._.-. __ .- _ _ _ . . _ _ . . . _ _ -,_ . . - -
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. Test Item #4 (HO B1 Point Value (1.0)
i l The unit is operating at 100% power with all ICS stations in automatic.
- During a transfer of the RC flow plug in the "A" RPS cabinet, the _
'
- operator on the MCB notes a prolonged rod insertion. Which ONE of l the following is a probable cause of this event?
!
F a) The plug transfer has caused a re-ratio of feedwater due to -
l the temporary loss of the "A" loop flow signal, i-
! b) The AUT0/ MANUAL (Tave) transfer switch transferred to an
'
alternate signal which deviated from the controlling signal.
!
c) -The loss of the RC flow signal generated a variable flow j runback signal which reduced the ULD demand, i
.
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h d). The feedwater total flow circuit modified reactor demand based on the new RC flow signal.
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i Answer: b
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'
O O Test Item: 389 Lesson Plan: ROT-413 Objective No.: B8 Objective: Given the associated procedure, discuss the following evolutions:
J. Place ES Channel in a tripped condition - OP 507 Iteference: OP-507 K/A: 013 Engineered Safety Features Actuation System 000 Generic A3.01 Input channels and logic Task: 0130101004 Bypass Engineered Safety Features 0130101009 Align the Engineered Safety Features Actuation System as required for various plant mode Place an Engineered Safety Features Actuation System channel in the tripped conditio Importance: 3.7/ Expected Time (min):
l l
,
O
-
O O Test Item #5 (HO B) Point Vnlue (1,01 O
'
During operation at full power, it is determined that the pressure transmitter feeding the RC1 channel of ES is inoperable due to calibration problems and that the channel must be placed in a tripped
-
condition to comply with Technical Specifications. Which ONE of the
,
following action statements below is correct for this condition?
a) On the RC pressare test module for the affected channel, you should select the " TEST OPERATE" position. This will result in a trip of the HPI and LPI systems for that channel.
,
, b) On the RC pressure test module for the affected channel, you i
should select the "T2" position and adjust the setpoint until both the HPI and LPI systems trip for that channel, o c) On the RB pressure test module for the affected channel, you I
! should select the " TEST OPERATE" position. This will result in a trip of the HPI, LPI, and RBIC systems for that channe d) On the RC pressure test module for the affected channel, you should select the "I'2" position and adjust the setpoint until the HPI, LPI and RBIC systems trip for that channe Answer; a g
s
.
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O V U Test Item: 038 Lesson Plan: ROT-4-91 Objective No.: F5 Objective: Discuss the procedure for transferring a vitalinstrument bus power suppl Ileference: OP 703 K/A: 062 AC Electrical Distribution System 000 Generic K4.10 Uninterruptable ac power sources Task: 0620401001 Direct the transfer of a vital power supply Importance: 3.1/ Expected Time (min):
O l
,
O
__..~._ .._ ..__ _ __ _ _. __ _. _. _ _ . . _ _ _ . _ . . _ . - - - - - . - . _ . _ . _ _ . _ . _ . . . . _ - .
' ~
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Test Item #6 (HO B) -Point Value (1.0) .
,
While the plant is in Mode 3, Inverter 3D trips off the line due to an internal electrical failuree Which ONE of the following statements +
describes the result'of this failure? >
a) The VBXS will automatically swap to the alternate AC Sourc b): The b'us will be de-energized for 7 to 10 seconds and then b'e -
automatically re-energized by the VBX c) The bus must be manually swapped to the alternate power source.-
d)- The VBXS will lose control power and fail to transfe ,
Answer: a
.
-
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.
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O Test Itenu 033 Lesson Plan: ItOT-4-54 Objective No.: B13 Objective: Describe the limits and precautions of OP-40 Reference: OP-404, SP-422 K/A: 005 Residual lient Removal System 000 Generic A1.01 IIcatup/cooldown rates Task: 0050101016 Regulate Decay IIcat flowrate 0050101008 Monitor the Decay IIcat Removal System Importance: 3.5/ Expected Time (min):
O
,
'
O
_ _ _ _ _ _ _ __
-.
--
O
.
O Test Item #7 (ItO Ill J'olnt Value (1.0)
The Decay Heat system is operating nearing the completion of n -
cooldown. The following readings were recorded on the cooldown
.
surveillance:
RCS RCS ,
Pressure Temperature (psig) (aF)
1300 hrs 105 110 1400 hrs 103 106 1500 hrs 100- 105 1600 hrs 95 - 105 -.
O v
Which ONE of the following statements describes the correct actions to be taken based on the above data?
- a) - The plotting of cooldown must be continued for one-additional shif J b) The plotting of cooldown must be continued for an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, c) Plotting can be secured if no further cooldown is required and 3 consecutive readings of temperature agree within i 2aF d)- Plotting can be secured as long as RCS temperature does not vary by more than i laF per hour during the remainder of -
the cooldow _
O . Answer: c
_ _ _ _ _ _ - ____ -- ,
.I-
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V
}
U Test Itern: 381 Lesson Plan: ROT-4 54 Objective No.: B8 Objective: Describe the limitations on Decay Heat flo Reference: OP-404 K/A: 005 Residual Heat Removal System 000 Generic K4.02 Modes of operation Task: 0050101010 Establish auxiliary spray flow Importance: 3.2/ Expected Tirne (min):
O I
J
!
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,
__ _
G n G Q)
g Test hem #8 (HO B) Point Value (1.0)
O Cooldown and depressurization of the RCS is in progress using the Decay Heat Removal system. DHP 1A is in operation and DH auxiliary spray is being provided to the pressurizer. Pressurizer heater banks A,
,
B, and C are in AUTO; banks D and E are OFF. The following conditions exist:
RCS Pressure 90 psia RCS Th . . . . 229aF Dil Flow . . 3000 gpm Which ONE of the following conditions would present a problem during operation in the above configuration?
a) Non condensable gases will not be removed from the pressurizer causing accumulation in the system and pressure control problem n V
b) Fluid stratification in the pressurizer surge line will occur due to the flow in the auxiliary spray lin c) Excessive pressurizer spray in combination with pressurizer ,
heater operation will cause gases in the pressurizer to be driven into solution and deposited in the RCS loop d) The flow alignment will increase the fluid stratification and possibly cause steam bubble formation in the RCS hot leg Answer: d p)
\_
- ___ . - - -
o
'J O
Test Item: 134 Lesson Plan: ROT-4-69 Objective No.: G4
'
Objective: Describe the basic operation of the following control systems:
c) Condensate Demineralizer Bypass Valves Reference: OP-601 K/A: 059 Main Feedwater System 000 Generic System Ability to locate, explain, and apply all Generic #7 limits and precaution Task: 0570104002 Perform lineups of the condensate
,
demineralizer system Importance: 3.1/ Expected Time (min): g l
!
_ _ _ _ _ _ _ - _ _ _ _ _ _
.
U,-~
O Test Item #9 (HO B1 Point Value (1.0_1 O
V Given the following conditions:
-
The plant is at 100% powe An unexplained air system failure has caused the inlet valves to all 6 condensate demineralizers to fail close Which ONE of the following statements describes the effect and reason for the effect the above conditions will have on Main Feedwater?
a) Main Feedwater will not be affected. The Condensate pumps will automatically reduce flow allowing time for the bypass valves to be opene b) Main Feedwater will not be affected. There are two bypass valves which will automatically open at 80 psi m U c) Main Feedwater will be lost. The bypass valves can not be opened quickly enough with a differential pressure of 80 psi, and the Condensate Pumps will shutdow d) Main Feedwater may be lost. The bypass valves must be opened by the Turbine Building Operator and condensate flow restored prior to a loss of the MFW Booster Pump Answer b n
/
. _ _ _ _ _ - _ _ - _ -_ ___ _ _. _ _ _ - - __ _ _
e, v O Test Item: 395 Lesson Plan: ROT-318
_
Objective No.: 1 Objective: Describe symptoms that can distinguieh LOCAs from other transient Reference: TBD K/A: 002 Pressurizer Pressure control System 000 Generic A2.01 Heater failures A2.02 Spray valve failures Task: 0000501001 Analyze indications to determine that an emergency / abnormal plant event is in progress 0000501003 Analyze events to determine the cause of abnormal / emergency events 0000501005 Determine ifindications of fuel damage are present Importance: 4.3/ .2/ Expected 3.0
-
Time (min):
O
_ -
_ _ . . . . _ . - _ . . . _ . __. _. . _ _ . _ _ _ _ . _ __ o
-
o Test Item #10 (RO B) Point Value'(1.0)
After receiving the RCS low pressure alarm, the nuclear operator scans .
the control board indicators and observes the following:
RCS Tave ...... 579aF RCS pressure . . . . - 2100 psig and 4 at 100 psig/ min PZR temperature . 643*F and 4 at 6oF/ min PZR level . . . . . . . constant -
Makeup flow . . _. . . 8 to 10 gpm higher than normal-RCPs running . . . 4 _
RB pressure . . . . . normal and constant
'
Reactor power . . . 40%
RCP seal injection normal -
Which ONE of the following describes the' developing scenario based on the provided data?
a) Loss of all pressurizer heaters h) Stuck open pressurizer spray valve c) Pressurizer steam space leak -
d) Letdown line leak Answer: c
,
O
. - - - -. _ - . .
___-___ ____ _ ___ __ ____ _ _-____ _ __ _ ___ _ _ _ _ - _ -
o
'
O Test Item: 377 Lesson Plan: ROT 1-47 Objective No.: B3 Objective: Explain how and why changes in the moderator affect core reactivit Reference: OP 103C K/A: 001 Control Rod Drive System 000 Generic K5.26 Definition of moderator temperature coefficient : application to reactor control Task: 10CFR55 Importance: 3.3/ Expected Time (min):
O O
__ - -_ --
-. _ . - .- . - _ - - - .
'
O o q Iest Llein #1l_{itO II) EoinLYnlun.1120 A reactor startup is in progress and the nuclear operator has just announced that the reactor is critical. At this point an adjimtment is inado to the feedwater flow to both OTS0s which inadvertently causes a slight overfeeding such that Tave decreases froin 532*F to 525' Assuining iniddle oflife conditions, ItCS boron concentration is 800 ppui, and no automatic or operator action occurs, which ONE of the following describes the response of the reactor to this event?
a) Itcactor power will increase to and stabilize at - 5 x 10# amps on the intermediate rang b) The reactor will be suberitical and power will decrease to the point of steady state suberitical multiplicatio c) Itcactor power will increase and stabilize at a 9% full powe d) llecause criticality is achieved below the point of adding heat, rear'or power will not be affected by the temperature chang Answer: a p
d
_
O O Test Itern: 241 h
Lesson Plan: ItOT 4 03 Objective No.: 111 Objective: State the purpose of tuid the breakers associatect with cros tie blockin Iteference: Alt 702 K/A: 002 AC Electrical Distribution 000 Generic Kl.02 Einergency Diesel Generator Task: 0620101001 Lineup the electrical distribution systern 0620101004 Monitor the AC Electrical Distribution Systern Innportance: 4.1/ Expected 2.0
. Tlrne (inin): g!
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_ _ . ~ . . _ _ . . . _ - - - - - . . . - -
-_ . - ._- -~.-.._-
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Test Item #12 (RO II) Eulut Value (1.0)
Which ONE of the following is a condition which will cause the Diesel Gen B Parallel Block Act" light to be illuminated if the "A" DG Breaker is closed?
l a) Offsite Transformer is closed in to both ES buse b) The Feeder to "A" 4160 ES bus from the Unit 3 Aux Transformer is closed with the Feeder to "B" 4160 ES bus :
from the Unit 3 S/U Transformer close ;
c) The Feeder to "A" 4160 ES bus from the Offsite Transformer is closed with the Feeder to "B" 4160 ES bus from the Unit 3 S/U Transformer close O d> The Feeder te ^ 4ie0 ES ses frem the Unit 3 ^ex Transformer is closed with the Feeder to "B" 4160 ES bus from the Offsite Transformer closed.
,
1 Answer: a l
a--*--ar5 mr -g*y y v y g yt N etqr'w f 'PN'-e-Tw"Y f Y gwi'M-W'TV'"'T*FPN9F1N 4='be F *1WFW'eN-t-4'w'*^*M4'm* *' TWT *- "
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O O Test Itein: 392 Lesson Plan: IlOT 5-43 Objective No.: 132 & 134 Objective: List froin inernory the federal quarterly whole body dose lhnP ' a adiation workers, non radiation workers and persons under 18 years of ag Dernonstrate the use of the formula 5(N 18) to determine tui l individual's exposure limits.
Iteference: IIPP 300 K/A: Plant Wide Knowledge of 10 CFit 20 and related l Generle #15 facility radiation control requirements Tusk: 1190301010 Apply radiation and contamination safety procedure Importance: 3.4/3.9 Expected 4.0 Time (min):
O
_
___. _ _ . _ _. . _ _ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ .
,
o
- - -
9 l l
Test item #13 (HO B) 18oint Value (1.0) ;
O !
I A dose limit extension has been granted for a radiation worker at CH3 ,
who has the followhig completed Whole Body dose history: {
(NRC FORM FOUR)-
,
AGE: 20 years old as of 6 6 91 ACCUMULATED DOSE: 9 hm as of 12 3191- :
No doso for current quarter (assume today is 1 192)
Which ONE of the following is the maximum whole body exposure which this person could receive in the current quarter and not exceed the federal whole body dose limits?
I .0 Rem
.
O .2s - - .5 km d, 3,0 . hm Answer:. b
.
,
. .
- ur -y* wt'y urypy w v(-w-Pyq qww wy p m We r mvr y-y y w W T w-'-M *'utpr-vg y w 9- r --- -y, ,qy9_yy,mgy,--p gy ,9 ,,_99999_,.yn,q.,g .vg 9,9, , , .,_gyg. Y ,wgy99. p g y p,iy avA9-mipv-yeeyyyy- VF r e = *v f-*FfgW,WN'1- ' -T'N-"'
.
.
O O Test lienn: 328 1,esson Plant itOT 516 Objective No.: 3 Objective: Given a copy of the Abnorinal Procedure, he able to state a basic reason for any given Syinptorn, lintnediate or Follow up action, lleference: EP 140 K/A: 000 Einergency Phuit Evolutions 024 Einergency Boration EA2.06 When boration dilution la taking place Tusk: 0000501018 Perforin required actions for Ernergency iteactivity Control Irnportance: 3.0/3.7 Expected 2.0 Tline (rnin):
O O
- . - . . - . - . . . - . _ . . _ - - - . - . . - . _ - - - . - - . . . - - - - _ - . ~ - _ . _
i ,
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,
Test Item #14 (HO l.11 Point V.atue (1,0) .
!
!
'
I RCS pressure is < 140 psig while in EP 140 " Emergency Reactivity
!
Control"? -
i
,
j a) Reduces the possibility of dilution from abnormal evolutions, t F
i b) Reduces the possibility of over filling the RCS at low !
) pressures and temperatures, t
c) Reduces the possibility of filling the RCDT with DW and allowing that water to be transferred to a feed source supply i
-
tank for the RCS.
,
!
d) Reduces the possibility of DW interfering with the sampling
- O process for true boron concentration determinatio Answer
- . a
,
'l O
.
-, , - , . - . . - . . - - , . . . . . . - . _ - . , . - . . _ - - - . - . . - , _ . . . . . - - . - _ -
Q b (v Test Item: 385 Lesson Plan: ROT 5 20 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure, be able to state a basic reason for any given Symptorn, Inunediate, or Follow up actiol Reference: EP 390
K/A: 000 Emergency Plant Evolutions 037 Steam Generator Tube Leak EK3.07 Actions contained in EOP for S/O tube leak Task: 0000501022 Perform the required actions following a Steam Generator tube ruptur Perform actions required for excessive Reactor Coolant system leakag Importance:
Expected 4.2/ .75 g
i Time (min):
<
'
)
l l
l l
l l
{
l O
_ _ _ _ . _ _ . . _ . _ _ _ _ _ _ _ _ _ - . . _ _ _ _ - _
_ _ - _ .. _ ._ _ _
u ,
l O O l
.
Test item #15 (RO 111 Point Value (1.0)
lO
,
!
j The plant is in a forced shutdown condition due to a steam generator i tube leak. The leak is getting progressively worso and pressurizer level
'
is becoming increasingly more difficult to maintain. EP 390, Steam j i
Generator Tube Leak, provides guidance which directs the reactor to be !
tripped if pressurizer level cannot be maintained = 100" with IIP l
- Which ONE of the following conditions would result due to the tripping
} of the reactor at this point?
!
i-a)- A loss of adequate RCS pressure control.
j b) The PZR insurge can cause the PZR cooldown limits to be -
'
exceeded.
- -i e
i
'
i c) If an MSSV should lift and fail to rescat, site boundary dose -
O rete ce"ia 'e exceeaea.
i d) The reactor coolant system would become saturated.
J.
'
,
.
Answer: d
a
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.
.
k' _ :_ _ _ .
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._,,.,-_.-_.,-_.._._......_._.-..--_.-_._._--;
-
_ _ . . _ _ - . . . _ . . - . . - . . - _ - , . . ~ . - _ . ..
_ .
O O Test Itcint 307 Lesson Plan: ItOT 5 25 Objective No.: 3 Objective: Given a copy of tbc Abnorinal Procedure be able to state a basic reason for any given Syinptorn, lintnediate, or Follow up actio Reference: AP.530 AP 380 K/A: 000 Einergency Plant Evolutions 000 Sinall Break LOCA EKl .01 Natural circulation and cooling, including reflux boiling Task: 0000501010 Perform the actions required following an Engineered Safeguards Systein Actuatio Innportance: 4.2/ Expected Time (inin):
l 1 0
_ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ . _ _ . . _ _ _ _ . . _ . . _ - . . . _ _ _ . _ _ _ _ . . _ _ .
. . ,
.
O O !
Test Item #16 (HO il) Point Value (1.0) i O ,
Given the following sequence of events:
'
- While operating at 100% FP, a small break LOCA occur i - -The reactor trips and IIPI actuates.- "
-
Upon loss of SCM the RCPs are trippe EFIC initiates and feeds both OTSGs to 95% on EFIC liigh Rang !
-
The reactor has a maximum decay heat outpu !
-
Natural circulation can unt be verifie :
Which ONE of the following should be done to enhance natural circulation?
a). Lower RCS pressure, b) Bump RCP c) Throttle IIPI ilow.
- d) Vent pressurizer.
I l
Answer: b l
!
u l
l'
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x + - -
, , . . . _ . . , ,,-.....-m., , . . , . . . , . . . _ - , . . . , - , . , .._...._-.,-..,._,,.___-.--.-,,_,m,... ..~
._ ._ _ _ . _ . - _ -
.
O O Test Itein: 141 Lesson Pinn: IlOT 5 73 Objective No.: 2 Objective: Given a copy of the Abnorinal Procedure be able to state a basic reason for any given Symptoin,1:ninediate, or Followup Actio Iteference: EP 220
'
H/A: Til 193010 Kl .06 Task: 0000501019 Perforrn required actions for Pressurized Thermal Shock conditions Importance: 3.6/ Expected 2.5
'
Time (min):
O O
.-_ _ - . -
' '
O O Test Item #17 (ItO II) Point Vnhie (1.0)
Given the following conditions:
-
An overcooling event has occurred due to a failed MSS An OTSG tube leak was created by the MSSV failur A reactor trip resulted from the overcoolin Twenty minutes after the reactor trip the plant conditions are:
Tc............. 365 o F RCS pressure..1650 psig Which ONE of the following actions must be taken?
a) Reduce RCS pressure so the plant returns to the PTS operating region and continue plant cooldown maintaining emergency cooldown rate limit b) Heduce RCS pressure so the plant returns to the PTS operating region and perform a three hour soak.
I c) Reduce RCS pressure so the plant returns to the PTS
, operating region and continue plant cooldown maintaining allowable cooldown rate limits, d) Allow the RCS to heatup to 475aF so the plant returns to the PTS operating region and perform a three hour soa Answer: c l
O
/
. .
O O l
Test Itein: 372 Lesson Plant ROT 5 31 1 Objective No.: 2 Objective: Given a copy of the Abnormal Procedure, be able to state a l basic reason for any given Symptom, humediate or Follow up action.
Iteference: AP 990 K/A: 002 AC Electrical Distribution System 000 Generic A2.00 Keeping the safeguards buses electrically
'
separate Task: 0000501002 Perform the required actions to ensure plant safety during an emergency / abnormal event Importance: 3.4/ Expected Time (min):
O
. - . - - - - - - - - - . - . . . . . - .- -
- . . . . . - . - . - - . . . - - - . - - .
,
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i
! Tant Iterp #18 (RO H) PoinLYalue (1.0)
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!
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! Step 3.7 of AP 990, Shutdown From Outside Control Room, directs the i
'
operator to " Ensure Ukrs 3207.amd 3208 are open and DC control power is off." Which ONE of the following is the reasor. for this step? !
! 1
'
!
a) Ensure local manual control of breakers 3207 and 3208 is- !
i available following Control Room evacuatio .
?
,
b)- Ensure an inadvertent ES bus overload condition will not be created due to closure of multiple source feeder breaker ?
c) Ensure a fire induced fault would not cause closure of !
' ~
breakers 3207 and 3208, paralleling the Amdliary transformer ~
.
with the Start up transforme ,
.
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'
a) ees re es 6 ses re et s#vviiea ur vretectea se rce feeder breakers since relay protection of breakers 3207 and 3208 is lost wb- ;t control is transferred from the Control !
Roo .
Answer: c t
,
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LO n
.
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= = -_
.,-_-.. .-._._a._,.._..-.. - - . - . _ , - . , . - , . _ - , - - _ _ . . _ , . < -. . _ _a_ c , _. , . - ....,_-.a- - . , ,_i '
.
O O Test Itent: 413 Lesson I'lan: ItOT 5 36 Objective No.: H3 Objective: Given EM 204A and the required data, be able to complete a dose assessment.
Ite rerence: EM 204A K/A: 000 Entergency Plant Evolutions 000 Accidental Gaseous-Waste llelease EK3.03 Actions contained in the EOP for accidental gaseous waste release Task: 1150501001 Estiinate off site dose during a radiological release using EM 204 (A)
Importance: 3.8/4.2 Expected 4.5 Time (min):
O O
.
O O Test Item #19 (HO 111 Point Value_(L(J1 ,
A large break LOCA has occurred. The present plant conditions are as l follows: .
OTSGs . . . . . . . . . . . . . dry and filling RCS Pressure . . . . . . 725 psia :
t Tincore . . . . . . . . . . . . 690 * F RB Pressure _. . . . . . . 15 psia >
RM A2 Low Range . . . . off scale high RM A2 Mid Range . . . 70 mR/hr RM A2 Iodine . . . . . . 1000 epm
'
An off site dose assessment must be completed. The meteorological stability class has been determined to be F,0. Which ONE of the-following would be the dose rate at the site boundary based on the listed data?
a) 2.0E+3 mR/hr O ,.
b) 2.6E+3 mR/hr j c) 7.9E+4lmR/hr
I
!
. d) 1.1E+5 mR/hr
'
i.
,
! Answer: d
!
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LO:
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4 y -s-qr-w+rv gw g -yar-g y, , g ,m.y.--a 5.r ysp -.,e-as ,9p.w.a,.m ap .
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- - _
.
O O Test liein: 390 Lesson I'lan: It0T 5 38 Objective No.: B4 l
Objective: State the requirements for the ' Operator at the Controls" to reinain in the red carpeted general area of the Control Center.
Reference: Al 500 K/A: 181 ant Wide Ability to coordinate personnel activities Generic #20 inside the control roorn.
Task: NTS Innportance: 3.1/4.7 Expected 1.5 Time (min):
O O
.. _ _ _ . . . ._ _ . _ __ . . . .. _ _ _ . __ . _ _ . .- __
O O !
!
i Test item #20 (RO 111 Point Value (1.01 O
,
i While in mode 1, with another reactor operator and the assistant shift supervisor present in the control room, a plant transient occurs. The -
ANSS directs the other reactor operator to leave the control room to cornplete a task that has some urgency. The ANSS then goes to get MET tower data to complete EM 204A. You now notice that the NNI X power supply light on the redundant instrument panel is of Which ONE of the following statements describes your administrative ability to leave the red carpeted area to check the status of this power ,
supply?
, You cannot leave the area; at lead one operator must be in the red carpeted area at all lines while in mode . You can leave the area as long as you have SSOD permissio O You cannot leave the area since an unobstructed view of the I main control board cannot be maintained, You can leave the area; there nre no obstructions between the NNI power supplies and the main control boar '
Answer: c
<
. *
O .
_
__,; _. _ ' _ . -
--
" -95--------"eyygren-wcrr-'y ?r-w-t-?v=-'s-e**'-y u--- *-v's'- +-ri'Y r ~* * ~5 r- wrrr*s-rT-~----=rw-e,e ms' -- --
_ __
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Test Itcin: 368 h Lesson Plan itOT 5 78 Objective No.: 111 Objective: Apply liinits and precautions froin OP 301, including their basis.
Iteference: OP 301 K/A: 000 Einergency Plant Evolutions 074 Inadequate Core Cooling EKl.03 Processes for reinoving decay heat froin the core Task: 0020101005 Drain and nitrogen blanket the Itcactor Coolant Syste Monitor the Iteactor Coolant System.
Importance: 4.5/4.9 Expected g Time (inin): W O
. .. . . . _ . . _- . - _ - - - _ - _ . _ - .
O O Test item #21 (110_l)J j'olnLLilnelldll Given the following comillions:
-
The reactor was shutdown at 0000 (niidnight) on Dec. 2,199 Today is Dec. 8,1990 and the thne is 080 The ItCS has been depressurized in preparation for head remova The vessel has been drained to a leveljust above the finnge but not yet low enough for head remova In preparation for refueling the incore instrutnents have been withdrawn from the core regio A intal loss of Decay llent itemoval has occurre Just prior to the loss of Decay llent Hemoval RCS temperature was 70 * Which ONE of the following is the approxhnate time it is expected to take to reach 212*F (boiling) in the core? s, .
,
,
>P '\ Qy a) 12 minutes b) 27 minutes c) 35 minutes d) 39 minutes Answer: d or c
, ,O V
'
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O O Test Iteins 351 Lesson I'lan: ItOT 5 81
,
Objective No.: HI Objective: State the entry level conditions for this Abnornial l*rocedur Iteference: Al' 581 K/A: 010 Non Nuclear Instrurnentation Systein 000 Generic A2.02 Loss of power supply Task: 0160401002 l'erforrn required actions for a loss of
._
pnwar to the NNI systei Ituportance: 2.9 * /3.2'
Expected Tline (min):
O O
. - -____- - . _ _ - . _ _ - _ - -- . - _ . .
. .
O O Inst Item #22 (llO_R) l'olnt Vidite (1.0)
,
Which ONE of the stateinents below is correct concerning a loss of NNI X?
I i
a) A failure of the NNI X AllT output is considered a loss of NNI b) Only coinponents powered froin VllDP 1, VBDP 3, and j VilDP 5 will be affected by a loss of NNI ;
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c) The interlock functions associated with MUV-49 are unaffected by a loss of NNI X DC power.
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i d) A loss of NNI X DC power can be confirmed by the absence of any 1 of the 4 indicating lights located in NNI Cabinet 3.
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Answer: a
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O O Test item:
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Lesson Plan: ItOT 414 Objective No.: D2 Objective: Describe the location and/or operation of the following
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systein controls and interlocks: Integrated Master subsection including control station Reference: AP 545, FSAlt
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K/A: 059 Main Feedwater System 000 Generic K1.07 ICS Task: 0410101001 Monitor the ICS syste Operate the ICS to affect plant power changes while operating with 3 ItCP __
Importance: 3.2/ Expected Time (min):
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O O lest item #23 O(O 11) EnitiLYnine (1.0)
The following sequence of events occur:
d
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The plant is at 85% FP and ItCP 1O trips.
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The plant runs back to 75%
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The narrow range Tc instrument la in he transferred from TT-1 to TT A recommendation is made to place the "SO/Itx hand auto station"
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into manual prior to transferring the narrow range Tc instrument.
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, Which ONE of the following statements is correct regarding the recommendation to place the "SG/Rx hand auto station"into manual?
I a) Placing the "SG/Ih hand auto" station to manual will place ICS in Track and block any effects of changing the Tc instrument.
>
G V b) When the "SO/Rx hand auto" station is in manual, variations in Tc will only affect the Tave correction circuit for the reactor deman c) The "SG/Rx hand-auto" station is upstream of the Tc input to FW and Rx. This will not prevent Tc from changing feedwater or reactor power demand signal d) Taking the "SG/Rx hand auto" station to manual will place ICS in Track ensuring power level will not increase above 75% due to variations in the Tc input to IC Answer: e
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O O Test Item: 142 Leeson Flant itOT 414 Objective No.: H9 Objective: Discuss tlie systeni response and required operator action for the abnorinal conditions listed below: Failure of ICS input signals or controlled devices Reference: FSAlt K/A: 000 Ernergency Plant Evolutions 001 Continuous Itod Withdrawal EKl.14 Interaction of ICS control stations as well as ptupose, function, and inodes of operation of ICS Task: 0160401001 Perform required actions for a analfunction of a Non Nuclear instrumentation detector or channe Perform required actions for reduction in Main FW flow at any power level, including a loss of 1 or both Main FW pumps.
Importance: 3.4/3.7 Expected 3.0 Time (min):
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_____ _ ____._._ _ _ _ _._ _ ..__._ _ _ _ -- .
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O o Test Item #24JHO H) Point Value (1.0)
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The plant is operating at 75% FP with all ICS stations in Auto when the following sequence of events occurs:
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Suddenly the operator observes: .
rods are receiving a continuous IN ' command both F.W. demands are increasing
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FW Limited by Reactor" annunciator alarm '!
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The Rx demand II/A station, when placed in measured variable, shows a zero error (on the caret).
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The diamond panel is operating correctl '
Which ONE of the following malfunctions would cause the above sequence of events?
The Feedwater to Reactor cross limiting circuit fails lo '
a)
t-O b) The actual neutron power signal going to the ICS falls hig c) The Reactor Demand input signal fails high, d) The Tave input signal fadis lo .
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l Answer: b l
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l Test Itenu 207 O-
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Lesson I'lan:
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HOT 5 28 :
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- Objective No.
- 13 1 Objective: State the entry levei conditions for this Abnormal Procedur Heference: AP 580 K/A: 000 Einergency Plant Evolutions 007- Reactor Trip System Ability to perforin those actions, without
- Generic #11 reference to procedure, for all casualties which require immediate operation of systern components or control Task
- 0000501001 Analyze indications to determine that an emergency / abnormal plant event is in progres Importance: 4.1/ Expected &
Time (min): W O
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Iest item #25 (RO B1 Point Value (1.0) .
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, From the various conditions listed below, which ONE would cause an
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- - a) Th'is 597'F and RCS pressure is 1820 psig
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l b) Th is 588aF and RCS pressure is 1850 psig i
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! c)L 3 RCPs operating, power 72%, imbalance -17%
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'd) 4 RCPs operating, power 95%,-imbalance -22%
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U Test Item: 168 Lesson Plan: IlOT-519 Objective No.: 3 Objective: Given a copy of the EP-290 state the operator actions required to accomplish each procedural ste _
Ileference: EP-290 K/A: 000' Emergency Plant Evolutions 074 Inadequate Core Cooling EA1.04 Turbine bypass or atmospheric dump valves, to obtain and maintain the desired pressure Task: 0000501021 Perform required actions for Inadequate Core Coolin Perform actions to ensure that core cooling and subcooling margin are maintained Importance: 3.9/ Expected Time (min):
4 O
. _ . _ _ _ . _ . . _ _ . _ _ _ _ . . _ . _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ . _ . _ . . _ . _ _ _
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Test Item #26 (RO B) Point Value'(1.01 O
A LOCA has occurred and primary plant' parameters are:
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RCS pressure: 600 psig-
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Incore Thermocouples: 975' Which ONE 'of the following describes the OTSG pressure requirements for the above conditions?
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a). Atmospheric b) 25.to 50 psig below saturation pressure of the RCS c) '25 to 50 psig above saturation pressure of the RCS
'd) Equivalent to 100aF.below RCS saturation temperature -
Answer:. a-
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U U Test Item: 386 Lesson Plan: IlOT-5-07 Objective No.: B2 & B3 Objective: Discuss the acceptance criteria for the Surveillance Procedure and the actions to be taken if acceptance criteria is not met, Using the procedure, discuss or walk through the procedural steps of the Surveillance Procedure.
Iteference: SP-312B, STS 3.3.1.1 K/A: 012 Reactor Protection System 000 Generic System Ability to recognize indications for system Generic #8 operating parameters which are entry level conditions for Technical Specification Nuclear Instrumentation System 000 Generic O A1.05 Imbalance (axial shape)
Task: 0150201003 Perform a power imbalance calculation.
Importance: 3.7/ .7/3.9 Expected 4.0 Time (min):
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_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ - - -
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Test Item #27 (RO B)
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Point-Value (1.0):
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In preparation for the performance of SP-312B, Monthly NI Imbalance l Comparison, the following data is observed on computer Group 59:
j~ . NI 5 Inibalance -5.8%
F NI 6 Imbalance -3.9%
[ - NI 7 Imbalance -8.2%
- NI 8 Imbalance -
5.1% .
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Incore Imbalance . -
6.3%
! Thermal Power 2350 MWth i
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- Based on the above data, which ONE of the following is the
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i recommended course of action?
k I a) Notify I&C to perform SP-113, Power Range Nuclear.
- Instrumentation Calibration, then repeat data gathering and i
performance of SP-312B.
1O j b) Reduce power to < 75%, trip the inoperable RPS channel, _
- and reset all high flux trip setpoints to s 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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c) Trip the inoperable RPS channel within 1- hours and monitor -
! core quadrant power tilt 'at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- d) Take action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to ensure a plant shutdown to Hot l Standby is completed within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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Answer: c-
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O v kJ Test Item: 418 Lesson Plan: ROT 5-02 Objective No.: B1 Objective: Given a limit and precaution from one of the following operating procedures, explain the basi c. OP-203 Reference: OP-203 K/A: 000 Emergency Plant Evolutions 003 Dropped Control Rod EKl.03 Relationship of reactivity and reactor power to rod movement.
Task: 0000501001 Analyze indications to determine that an emergency / abnormal plant event is in progress.
Importance:
0010101009 3.5/ Monitor the Control Rod Drive syste g Expected 2.5 Time (min):
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[ 01 1 Test Item #28 (RO H) -
Point Value (1.0)- '!
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} The reactor is at 104amps on the Intermediate Range during a plant:
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startup when control rod 5 6 drops to the fully inserted positio Control board instruments indicate the following:
i l NI 3 amps decreasing-L SUR -0,3 dpm and steady -
l NI 4 amps decreasing j- ,SUR :-0,3 dpm and steady
- - Tave - 530aF and decreasing
[ RCS Pressure 2150 psig and decreasing
!.
I Which ONE of the following describes the proper course of action based-
[ on the data provided? -
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- a) Trip the reactor to ensure adequate shutdown margin and '
prevent inadvertent criticality.
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b) Fully insert all regulating rod groups and establish Mode 3, i
c) Maintain stable plant conditions at the present power level:
and recover the dropped rod in accordance with OP 502.
t-i i d) Reduce power to 10'8 amps on the Intermediate Range and
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I recover the dropped rod in accordance with OP-502.
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Answer: -b .
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Test Item: 420 h Lesson Plan: ROT-5-02 Objective No.: B2 Objective: Given a copy of one of the following operating procedures, explain the action completed in each step:
a. OP-202 Reference: OP-103F K/A: 002 Reactor Coolant System 020 Normal Operations K4.03 Contraction and expansion during heatup and cooldow Task: 0020101011 Heatup the Reactor Coolant System (with RCPs and the reactor).
Importance: 3.1/ Expected 3.25 Time (min):
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, Test Item #29 (RO B) Point Value (1.0)
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The Reactor Coolant System is being heated up from 300aF to 532aF.
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Which ONE of the following describes the amount of water that must
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be accommodated by the Radwaste System due to the heatup of the Reactor Coolant System?
a) 2,300 gal
.
- b) 2,500 gal j c) 12,750 gal
.
d) 15,500 gal
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Answer: .c i
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Test Item: 023 Lesson Plan: ROT-5-01 Objective No.: B10 Objective: Given any plant condition and a copy of Technical Specifications, identify those conditions which are violations of a limiting condition for operation and discuss the required corrective actions.
Reference: AP-545, STS 3.1.3.1 K/A: 000 Emergency Plant Evolutions 003 Dropped Control Rod EK3.04 Actions contained in EOP for dropped control rod Task: 1190301015 Apply Technical Specification requirements.
Importance: 3.8/4.1 Expected g Time (min): W O
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Test item #30 (HO Ill Eoint Value (1,0)
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While operating at 75% FP with 3 reactor coolant pumps operating. A control rod drops into the core. Assuming the control rod can not be recovered for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, which ONE of the following is the maximum power level at which operation may continue?
a) 36%
b) 45%
c) 47 %
.
d) 60%
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Answer: c
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Test Item: 407 Lesson Plan: ROT-4-60 g Objective No.: B5 Objective: Explain how to :nanually control PZR heaters and spra Reference: OP-305
,
K/A: 010 Pressurizer Pressure Control System 000 Generic K6.03 PZR sprays and heaters Task: 0100101001 Control Reactor Coolant System pressure by manual control of pressurizer heaters and spray, Importance: 3.2/ Expected Time (min):
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Test Item #31 (RO B) Point Value (1.0)
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a The plant is being cooled down and the decision has been made to use the high pressure auxiliary spray line to the pressurizer. The valve line-up has been completed and spray has been initiated. The following
,
, indications are observed on the main control board:'
- -
j Pressurizer level - . . . . . . 100"
- Makeup flow . . . . . . 60 gpm a .-Letdown flow . . . . . . 110 gpm
.
Total seal injection flow . . . . . 74 gpm
- RCP-1A seal injection flow . . . . . . 8 gpm -
RCP-1B seal injection flow . . . . . . 10 gpm RCP-1C seal injection flow . . . . . . - 7 gpm
! RCP-1D seal injection flow' . . . . . , _ 9 gpm
! HPI flow . . . . . . O gpm (total)
Auxiliary spray flow . . . . . O gpm -
Which ONE of the following would be the spray flow to the pressurizer from the Makeup system?
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l a) _0 gpm b) 40 gpm L
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d) 74 gpm l
, ' Answer: b t
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