ML20207E609
| ML20207E609 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/03/1999 |
| From: | Michael B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9903110022 | |
| Download: ML20207E609 (650) | |
Text
{{#Wiki_filter:_ _ _ _ .. _. .. l March 3,1999 I 1 i NOTE TO: NRL ument Control Desk Mail Sicp 0-5-D _ l rROM: Beverly Michael,nsing Lice A }w/19 Afs~/L istalh, ~ Ope'rator Licensing and Human I Performance Branch, i Div}sTon of Reacter Safety, Region 11 l l
SUBJECT:
OPERATOR LICENSING EXAMINATIONS ADMINISTERED JUNE 1998 . AT THE ST. LUCIE NUCLEAR PLANT, DOCKET NOS. 50-335 AND 30-389 : During the period June 22 - 26,1998, operator licensing examinations were administered at the referenced facility. Attached, you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR: item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070. b) As given operating examination, designated for distribution under RIDS Code A070. - Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42. Attachmente: As stated l 9903110022 990303 PDR ADOCK 050003 5
E l AS GIVEN FINAL OPERATING EXAMINATION . (IN ITS ENTIRETY) 3 / /ac ciL VS - k'/ DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070 f j A070 c_ . }
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, ES-301 Administrative Topics Outline Form ES 301-1 facility: St. Lucie Date of Examination: 6-22-98 Examination Level (circle one): RO / SHO(l)
Operating Test Number: la Administrative Topic / Subject Describe method of evaluation: Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions 4
A.1 Verification of Valve JPM / Verify a valve lineup lineups K2.1.29 - 3.4/3.3 Shift Turnover Question 1/ Shift turnover during reactivity manipulation K2.1.3 - 3.0/3.4 Question 2 / Split shift turno,er requirements A.2 Tagging and JPM / Verify a Clearance Clearances K2.2.13 - 3.6/3.8 A.3 Knowledge of facility JPM / Determine posting requirements radiation control requirements K2.3.1 - 2.6/3.0 A.4 Emergency Plan
- Question 1/ Verification of EAL K2.4.29 - 2.6/4.0 Question 2 / Who relieves the NPS during emergency SRO JPM/ Make PARS SRO/ Make simulator EAL Classifications s
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DISTRIBUTION CODE , A070 l
l Conduct of Operations Knowledge of shift turnover practices KA 2.1.3 - 3.0/3.4 Question 1. Unit 1 is at 80% due to waterbox maintenance.' The RO has a 20 gpm continuous dilution in progress to counteract Xenon production. What must occur in order to perform a shift / crew turnover in this condition? Expected Response: The RO shall obtain the ANPS approval to perform a turnover.
. No Reference Question 2. The Board RO has an appointment for his license physical at the Site Medical Center. The physical will take approximately 2 hours. As the oncoming RO, what are your turnover requirements? l Expected Response: An individual / split shift turnover must occur. The .
following items must be accomplished: *
- 1. face to face control board walkdown must be performed
- 2. He must review the chronological log, Out of spec log readings and the Night order book ,
- 3. An entry must be made in the chronological log that he has assumed shift responsibilities No Reference t
4 a u l i f t t k
t 0
. t Unit 1 is at 80% due to waterbox maintenance. The RO has a 20 gpm continuous dilution in progress to counteract Xenon production. What must occur in order to 1 perform a shift / crew turnover in this condition?
No Reference
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- The Board RO has an appointment for his license physical at the Site Medical Center.
- The physical will take approximately 3 hours. As the relieving RO, what are your turnover requirements?
No Reference 4 9 e j
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o F Emergency Procedures / Plan i Knowledge of Fire Protection Procedures i KA 2.4.25 - 2.9/3.4 i Question 1 18 EDG was out of service for belt replacement when a LOOP occured. Tho Emergency Coordinator has declared an Alert. Is this the correct classification? Explain. 4 Expected Response: No, an Unusual Event is the correct classification due to
- LOOP with loss of one EDG. An Alert requires both EDGs
- to be lost. In this case, you still have an energized 4160 V <
1 bus. Reference allowed (EPIP-01) Question 2 Unit 2 is in an Alert due to an RCS leak. After the Tech Support Center becomes activated, who relieves the NPS as Emergency Coordinator? The following people are on site: Site Vice President, Services Manager, Operations Managf ;, Operations Supervisor, Maintenance Manager, Training Manager. Expected Response: Operations Manager Reference Allowed (EPIP-02) i
2
< 1B EDG was out of service for belt replacement when a LOOP occured. The Emergency Coordinator has declared an Alert. Is this the correct classification?
Explain. Reference Allowed
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i Unit 2 is in an Alert due to an RCS leak.' After the Tech Support Center becomes . activated, who relieves the NPS as Emergency Coordinator? : i The following people are on site: Site Vice President, Services Manager, Operations Manager, Operations Supervisor, Maintenance Manager, Training Manager. . Reference allowed 4 a L i
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l Page 15 o' 83
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ST. LUCIE PLANT ;
~
- ADMINISTRATIVE PROCEDURE NO 0010120, REVISION 102 .
T CONDULT OF OPERATIONS APPENDIX C CREW RELIEF / SHIFT TURNOVER. : ~ (Page 3 of 6) >
- 1. (continued) ,
- 12. (continued)
A. (continued)
- 3. Night Order Book.
- 4. Operator Status Log (NPS)
B. The on-coming RCO, SNPO, NPO, and ANPO shall review the followin; ; and acknowledge that review by initialing Check Sheet 1 of t OP 1(2)-0010125, Schedule of Periodic Tests, Checks, and Calibrationn.
- 1. Applicable Watchstation Chronological Log.
- 2. Applicable watchstation "out of spec' log readings.
- 3. Night Order Book. i C. Instructions for an individual Relief / Split-Shift Turnover '
i
- 1. If a specific watchstation shift is being split by two individual !
watchstanders, then the following instructions provide the minimum i requirements for shift relief: -
- a. The off-going watchstander shall review applicable plant togs to determine the existence of any off-normal condition or trends.
- b. The off-going watchstander shall complete a form similar to the applicable Tumover Check Sheet (Check Sheets 1 through 7) f or their watchstation, with the following exception:
- 1. Iff only one of the two individuals designated as a shift RCO is splitting the shift, Then the off-going RCO shall utilize tha ,
previous tumover check sheet and verbally discuss with th 9 l on-coming RCO any changes in status that have occurred 1 since that check sheet was completed. ] l l 1
f [ - Pig 916 cf 83
# ST. LUCIE PLANT .
ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 102 ; CONDUCT OF OPERATIONS
- - APPENDIX C i CREW REUEF/ SHIFT TURNOVER (Page 4 of 6) f ;
i 1. (continued) . i , ! 12. (continued) i i j C. (continued) i 1. (continued) i
- c. The off going watchstander shall verbally transmit and explain the j information as recorded on their applicable Turnover Check Steet j (Check Sheets 1 through 7) to the on-coming watchstander.'
i'
- d. On-coming and off-going control room watchstanders shall i conduct a face-to-face complete walkdown of the RTGBs and j control panels. i j~ e. The on-coming watchstander shall make a chronological log entry
- indicating he/she has assumed the responsibilities of the 1 watchstation.
)
}' f. The on-coming watchstander shall review the following and acknowledge that review by initialing Check Sheet 1 of l OP 1(2)-0010125, Schedule of Periodic Test, Checks, and , Calibrations. j 1. Applicable watchstation chronological log. 1
- 2. Applicable watchstation "out-of spec" log readings.
] ) 3. Night Order Book. i- 4. NPS, ANPS, and NWE (if manned) shall review equipment
- out-of-service log.
- g. The applicable unit ANPS and the NWE (if manned) shall be i notified immediately after the shift turnover has been completect.
q 4 1 k
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Peg 317 o' 83 ST. LUCIE PLANT ADMINISTAATIVE PRCCEDURE NO. 0010120; REVISION 102
-: CONDUCT OF OPERATIONS ' .
APPENDIX C CREW RELIEF / SHIFT TURNOVER ! (Page 5 of 6) i
- 1. (continued) .
- 12. (continued)
NOTE Control Room watchstanders with the responsibility of the Operator at the Controls or the Control Room Command functions shall comply with the ! following instructions regardless of the length of time or purpose of the need i for relief except as provided for in Step 1 of Appendix A and other approved procedures. D. Instruction for an interim or Short Term Relief.
- 1. If a specific watchstander requires a short term relief for a period ot ;
less than 2 hours, then as a minimum, the following must be verbally ; transmitted to and acknowledged by the individual assuming their responsibilities. :
- a. General watchstation status.
- b. Off-normal conditions.
i l c. Evolutions in progress. . ! 1. Control Room watchstanders shall conduct a walkdown of he l RTGB(s) affected by the evclution in progress. J i l 2. Field operators shall notify the applicable unit ANPS and the NWE .if
- mannsd) immediately after the shift turnover has been completed. q
, I i 3. If an individual is expected to be absent for period of greater than l l 2 hours, then an Individual Relief / Split-Shift Turnover shall be l l performed. l ! l l u
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m . ..m . . _ _ . . . . _ _ . . - - _ _ _ _ . . __ m _ _ _ _ . _ _ . . _ . _ ... . - . . _. k A A EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m o O 7.A. LOSS OF Loss of off-site power or g Station Blackout (Total Loss POWER loss of all on-site AC power of AC) Station Blackout (Total Loss of AC) for GREATER THAN NOTE g'$m oz O Refer m PMal Core . cm . 15 n*mtes Melt Event /Ctass 6.A. b O '
- 1. Losa ,,1or Cts
- 1. Loss of off-site AC /.C power. 1. Loss of offsite AC power.
- -er.- AND AND
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OR 2. Failure of both 2. Sustained failure of both 3 ,
- 2. Loss of capability to emergency d6esel emergency diesel power at least one vita generators to start or generators to start or 8
g 4.16 kw bus from g synchronize. synctwonize. C g available emergency AND 3 O diesel generator. Loss of all on-site DC
. 3. Failure to restore AC power to at least one g
m {m (f) power vital 4.16 kV bus within Z (D - 1$ minutes. O y :6
- 1. Drop in A and B DC bus 7[y g g 6 ,
voltages to less than tu 'O -f q y 70 VDC. Loss of all vital on-site DC for orester than 15 minutes
$I>
- d O
(n us @ a E
- 1. Sustained drop in A and g O Z B DC bus voltages to o Mm in O Z "T1
#vDC for greater than h d 'U m
da h 15 6tEmtes. g o Z m Z d 3 d O M m W Z O
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m m - u> E a 7.A. LOSS OF gg - m POWER A O AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR fo e r
9/ FPL This JPM For NRC Exam Use Only St Lucie Nuclear Pfar t Licensed Operator Training Program Administrative Job Performance Measure MAKE PROTECTIVE ACTION RECOMMENDATIONS SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS DE PERFORMED Job Applicability. SRO Administrative Topic: Emergency Procedures / Plan KA Statement: Knowledge of the Emergency Plan i KA: 2.4.29 l 1
Reference:
EPIP-02," Duties and Responsibilities of the Emergency Coordinator", EPIP-01," Classification of Emergencies" Developed / Revised by: Tim Bolanger / l Approved by Training Supervision: / I Examiner. / ; Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. 4
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a JOB PERFORMANCE MEASURE Department: Operations Task
Title:
MAKE PROTECTIVE ACTION RECOMMENDATIONS Trainee: Evaluator An X below indicates the applicable method (s) of testing that may be used: Perform X Simulate Estimated Time to Complete the JPM: 15 MINUTES Location of Performance: CONTROL ROOM UNIT 2 / SIMULATOR l Notes to the Evaluator: ;
- Pull the latest controlled copy of the applicable procedure l
. The last page of this JPM lists the initial conditions and initiating cue. l Tear that page off and give it to the trainee.
J
= Notify a Management Observer of the observation opportunity. !
1-1 l l l i Page 2 l l I
N i 4 JOB PERFORMANCE MEASURE , READ TO THE TRAINEE
. You are to perform / simulate this task.
4
. The task you ares to perform / simulate is:
, MAKE PROTECTIVE ACTION RECOMMENDATIONS
. i will describe the general conditions and tell you the tools and equipment l required to perform / simulate this task.
. Before starting I will state the task standards and initiating ci'es and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job
- P arformance Measure.
. You are required to perform the steps in the correct sequence.
. . Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM. i i' General / initial Conditions:
- A Site Area Emergency has been declared due to a LOCA/ impaired containment ;
on Unit 2. Chemistry has reported their OCDM data and using that data, you are required to, make protective action recommendations Tools and Eauioment: 1
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EPIP-02, " Duties and Responsibilities of the Emergency Coordinator", EPIP-01,
" Classification of Emergencies" Safety Considerations:
In accordance with the FPL Nuclear Division Safe Work Practices manual. Page 3
1 I i f JOB PERFORMANCE MEASURE ~l l 1 l j-Iask Standard (s.): ) 4
- In order for this job performance measure to be satisfactorily completed, l accomplish this JPM in accordance with the following standards:
A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie !
- Quality Instruction Ol-5-PSL-1.
1 B. Locate and operate all plant equipment correctly. . C. The system / equipment status reflects the overall intent of what the JPM , required upon completion. D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Opereting Procedure immediate actions will be from memory. i During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatino Cue (s): A Site Area Emergency has been declared due to a LOCA/ impaired containment on Unit 2. Chemistry has reported their OCDM data and using that data, you are required to make protective action recommendations
References:
EPIP-02," Duties and Responsibilities of the Emergency Coordinator" EPIP-01,
" Classification of Emergencies" ,
. During the performance of the task I will tell you which steps to simulate or i discuss. ,
Page 4 i
4 JOB PERFORMANCE MEASURE T
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used '
for verification.
. I will provide you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference matvials normally available in the execution of this Job Performance Measure, including logs.
. Do you understand these directions?
. If you have any questions, ask them now, and I will answer them. -
l . During the test I cannot answer questions.
. When you complete all steps correctly, you will pass this job performance measure.
. Begin the task now.
A Page5
JOB PERFORMANCE MEASURE - Provide this page to the' Candidate initial Conditions A LOCA is in progress with an impaired containment on Unit 2. CET temperature is 550*F and slowly increasing. A plant general emergency has been declared. Chemistry has completed their offsite dose calculations and have furnished the following data: Wind Direction: 191' Wind Speed: 16 mph Dose rates at: TEDE CDE 1 mile 4400 18000 2 miles 1900 7000 i 5 miles 1100 5100 10 miles 500 1200 Initiating Cue: Using the above data and EPIP-02," Duties and Responsibilities of the Emergency Coordinator", you are required to make protective action recomendations. a m Page 6
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i 4 r JOB PERFORMANCE MEASURE instructor Answer Key initial Conditions A LOCA is in progress with an impaired containment on Unit 2. CET temperature is - 550*F and slowely increasing. A plant general emergency has been declared. Chemistry has completed their offsite dose calculations and have furnished the following data: Wind Dimction: 191* Wind Speed: 16 mph Dose rates at: TEDE CDE 1 mile 4400 18000 2 miles 1900 7000 5 miles 1100 5100 10 miles 500 1200 Initiating Cue: Using the above data and EPIP-02, " Duties and Responsibilities of the Emergency Coordinator", you are required to make protective action recomendations. , Answer:
- 1. 0-2 miles Evacuate CR
- 2. 2-5 miles Evacuate (RABC) + Shelter (RS)
- 3. 5-10 miles Evacuate (RABC) + Shelter (RS) j i
- 4. 10 miles-TBD Shelter (RABC) l l
l l
)
Page 7 l
AEVistoR 20 : PROOEcuEE TITLE: PAGE: l 0 DUTIES AND RESPONSIBILITIES OF 1 PaocEcuaE no.. THE EMERGENCY COORDINATOR 41 of 49 , EPIP-02 ST. LUCIE PLANT ' ATTACHMENT 4 DETERMINATION OF SECTORS AFFECTED AND STABILITY CLASS (Page 1 of 1) A. Affected Sectors
- 1. Using the guide below, determine the Affected Sectors and enter in line 113 of the State Notification form.
NOTE If the wind direction is directly on the edge of two sectors (e.g.,11',33', 56', etc.), an additional sector should be added to the Protective Action Recommendation (PAR). For example, if the wind direction is from 78 , then the afIected sectors for ths PAR should be L, M, N and P. Wind Affected Wind Affected Wind Affected : From Sectors From Sectors From Sectors 348 - 11 HJK 123 - 146 POR 236 - 258 CDE 11 - 33 JKL 146 - 168 QRA 258 - 281 DEF 33 - 56 KLM 168 - 191 RAB 281 - 303 EFG ! 56 - 78 LMN 191 - 213 ABC 303 - 326 FGH l 78 - 101 MNP 213 - 236 BCD 326 - 348 GHJ 101 - 123 NPQ there is no O sector there is no I sector i i B. Stability Class i
- 1. Enter Detta-T (60 meter minus 10 meter temperatures) deg.F l 2. Using Delta-T (AT) and the guide below, determine the Stability Class j
- and enter in line 11D of the State Notification form. 1 Stability Stability Stability l Class Class Class l AT s -1.7 A -1.4 < AT s -0.5 D +1.4 < AT s +3.6 F
-1.7 < AT s 1.5 B -0.5 < AT s +1.4 E +3.6 < AT G 4
-1.5 < AT s -1.4 C l
{ END OF ATTACHMENT 4 ,
AEVisioN No.: PROCEDURE TITLE: PAGE: 0 DUTIES AND RESPONSIBILITIES OF enocEcusE no.: THE EMERGENCY COORDINATOR 42 of 49 EPIP-02 ST. LUCIE PLANT ATTACHMENT 5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARS) (Page 1 of 4) A. Guidelines for Protective Action Recommendation (PARS) to Off-site Authorities l
- 1. FPL is required to provide county and state govemmental authorities with recommendations for protective action to be taken by the public during radiological emergencies at the St. Lucie Nuclear Power Plant.
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- 2. The responsible authorities are the State of Florida Division of l Emergency Management (DEM) and St. Lucie and Martin County l Departments of Public Safety.
- 3. PARS should be made utilizing all of the available data. This includes plant conditions, off-site dose projections and/or field monitoring data.
The more conservative PARS should be made.
- 4. Due to the large political and legal ramifications of these recommendations and the potential impact on FPL, the following format I and content should be used: I i
- a. If any case where a GENERAL EMERGENCY has been declared, '
the minimum PAR shall be: Shelter all people within a 2 mile radius and out to 5 miles in the affected sectors. (Affected sectors are the downwind sector plus the two adjacent sectors, three in ' l total.)
- b. If a' GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control l Room or any other area (s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum PAR shall be: Evacuate all people within a 2 mile radius from the plant and out to 5 miles in the downwind sectors. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.
- c. If the emergency has not been classified as a GENERAL !
EMERGENCY and the offsite doses are LESS THAN 500 mrem Total Dose (TEDE) and 1000 mrem Thyroid Dose (CDE) at 1 mile , over the projected duration of the release, no protective action is recommended. This should be reported to DEM and other outside agencies who inquire as:
REVISloN NO.: PRCOEDURE Trn.E; PAGE: 0 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 43 of 49 EPIP-02 ST. LUCIE PLANT ATTACHMENT 5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARS) (Page 2 of 4) A. (continued) .
- 4. (continued) :
- c. (continued)
Based on our current assessment of all the information now available to us, Florida Power & Light Cornpany recommends that you consider taking the following protective actions (PA) - NONE. This recommendation may change in the future, but we cannot now say when it may change or what it may change to. B. Determining Protective Action Recommendations (PARS) l NOTE If a controlled release is necessary to stabilize piant conditions or an uncontrolled release is anticipated, determine the approximate source term and duration of the release and the projected off-site doses prior to making any PARS. I
- 1. In detem1ining PARS, both plant conditions AND off-site doses must be considered. However, if a release has not occurred, then determine PARS based on plant conditions.
- 2. PARS Based on Plant Conditions
- a. Refer to Attachment 6, Protective Action Recommendations,
- b. Begin with the General Emergency question and proceed through the flowchart answering the questions at each prompt.
- c. Upon completion of the flowchart, enter the PAR table and '
determine the PAR for each downwind distance.
- d. Enter PARS into Line 1 of the table in Section C below.
REVISION NO.: PROCEDURE TITLE: PAGE: 0 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 44 of 49 EPIP-02 ST. LUCIE PLANT ATTACHMENTS DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARS) (Page 3 of 4) i B. (continued)
- 3. PARS Based on Off-site Doses
- a. Refer to Attachment 6, Protective Action Recommendations,
- b. For each downwind distance, enter the PAR table at the appropriate dose level and determine the PAR for that distance.
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- c. Enter PARS into Lines 2a and 2b of the table in Section C below, i
EXAMPLE A release has occurred at the St. Lucie Plant. The wind direction is from , 22 degrees and the projected off-site integrated (2 hr) Thyroid Dose (CDE) l is 10,000 mrem at 1 mile, 2000 mrem at 2 miles and less than 1000 mrem ) at 5 miles. The plant is in a GENERAL EMERGENCY with no actual or } projected core damage and no loss of physical control of the plant. The following PAR should be made: Based on our current assessment of all the information now available to us, i Florida Power & Light Company recommends that you consider taking the l following protective actions: l
- i. Evacuate allpeople between a 0 and 2 mile radius from the plant.
ii. Shelter allpeople between a 2 and 5 mile radius from the plant who are in sectors J, K and L. iii. No protective action is recommended between a 5 and 10 mile radius i from the plant. l This recommendation may change in the future, but we cannot now say when it may change or what it may change to. I 4
- 4. When available, both plume calculations and off-site monitoring results I should be evaluated when making PARS. lf significant discrepancies l
- exist between field monitoring results and plume dispersion calculations, Then an evaluation of the discrepancy should be made, and the i
appropriate value should be selected in the determination of PARS.
- 5. PARS have been developed based on guidance in NUREG/BR-0150, Vol.1 and EPA 400-R 92 001.
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REWSION RO.: PROCEDURE Tm.E: PAGE:
. O DUTIES AND RESPONSIBILITIES OF
, PROCEDURE NO.: THE EMERGENCY COORDINATOR 45 of 49 EPIP-02 ST. LUCIE PLANT '
ATTACHMENT 5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARS) (Page 4 of 4) C. Protective Action Recommendations (PARS) NOTE Actual PARS shall be the most conservative PARS based on plant conditions or off-site doses.
- 1. Complete the table below:
Step 1. Determine PARS based on Attachment 6, Protective Action Recommendations, and enter into line 1. Step 2. Determine PARS based on Attachment 6, Protective Action Recommendations, and enter into lines 2a and 2b. Distance From Plant / Recommendation Protective Action Recommendations 0 - 2 Mile 2 - 5 Mile 5 - 10 Mile
- Line 1. Plant Conditions Line 2a. Total Dose (TEDE)
Line 2b. Thyroid Dose (CDE)
- 2. Choose the most conservative PARS and record in Section 12 of the State of Florida Notification Message Form.
o R e f END OF ATTACHMENT 5 ,, j
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REV1SiON NO.: PROCEDURE TITLE: PAGE: 0 DUTIES AND RESPONSIBILITIES OF )
, enocEcuaE NO.: THE EMERGENCY COORDINATOR 46 Of 49 )
EPIP-02 ST. LUCiE PLANT , ATTACHMENT 6 i PROTECTIVE ACTION RECOMMENDATIONS (Page 1 of 1) (3) General NO Emergency
?
I p YES 2 Acamlor Loes of 0-2 Mass:S (CR) Protected Sevo<e NO PW concel NO g ' 3 Core Damage of Plant? Note (1) Note (2) 510 Meles: None 1 j p YES y YES 0 2 Mene: E (CR) 2 5 Mdes: E (DW) + S (RS) - 510 Mens:S (CR) ) k U U j l Eveausse Further Proescow Accon Aer:ommendesons Bened on Ortses Dose Esameses.l Determes PAR for encn l NOTES: 1 co m go,, (1) Severe core damage is mecated try orthec ' Loes of cnocal flmctore remared for core preesceon (e.g., loss of mpeceon unen LOCA), ' mde venue. Note (3)
. Hgh core temperatures (CET e 700*F), or
, Tossi Does Thyroid Does
- CHRAM readeg of > 4J Ed W.
(TEDE) (COE) (2) Lose of W W of Coeures Room or vrtal reactor coeroeng areas to meruders e mrom m mrom (3) See g6adence for Doestmnng PARS m Aasenment 5 of EPIP<t2. i i 0 2 Mnes 2 5 Maes 510 uies 10 TBD y p use 1 Mee ve6ue Use 2 Mde Value Use 5 Mile Value Use 10 Mee Value , f
<500 mrom e1000 mrom NONE NONE NONE NONE 2500 mrom 21000 anrom SUT SUT S (CR) 5(DW) S (DW) $(OW)
<1000 mesm <5000 mnem UT BUT E (CR)
E + E (DM + EM+
<5000 m 6- S (RS) 5 (RS) S (RS) 25000 mm 22m mrom E + E +
E (CR) E (CR) i LEGEND OF SneDOLS & ASSREVIAT10NS:
< + Less Then; 2 = Groseer Then or Equal To None - No Protecew Accon h,...- M OW Downwind + 2 Adpnng Sectors S Siestonng Recommended AS . Romenng Secears E . Evacuseon Recommended CR Comoses Creas Around P' ant et Speaned Detence
, tetMPremRs oeo) END OF ATTACHMENT 6 ,
' j i
r This JPM For NRC Exam Use , Only ( l r ) \ FPL i l St Lucie Nuclear Plant ' l Licensed Operator Training Program 1 Administrative Job Performance Measure Verify a Waste Management Valve Lineup SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEoS BE PERPJ.:MED I Job Applicability. RO, SRO Administrative Topic: Conduct of Operations 1 K4 Statement: Knowledge of how to conduct and verify valve lineups I KA: 2.1.29; 3.4/3.9 i
Reference:
P&lD 2998-G-078, sheets 1608,168; 8770-G-078, sheets 160a,160b,160c l Developed / Revised by: Tim Bolander / ! l 1 Approved by Training Supervision: / ! l Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. l 1
l JOB PERFORMANCE MEASURE ' l l Department: Operations l l Task
Title:
Verify a Waste Management Valve Lineup ! Trainee: 1 Evaluator. An X below indicates the applicable method (s) of testing that may be used: Perform X Simulate Estimated Time to Complete the JPM: 20 Minutes Locatn.,i of Performance: Unit 1 Control Room, Training Building Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
l i 1 Page 2 of 7
! l i JOB PERFORMANCE MEASURE J READ TO'THE TRAINEE
= You are to perform / simulate this task.
. The task you are to perform / simulate is:
VERIFY A WASTE MANAGEMENT VALVE LINEUP
= l will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
a Before starting I will state the task standards and initiating cues and answer any 1 I questions you have.
. When you perform all the critical steos correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
- Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: 2B Holdup Tank is full and must be pumped to the 1B Holdup Tank Tools and Eauioment: None Safety Considerations: i l None j Page 3 of 7 1
r i J - I JOB PERFORMANCE MEASURE in order for this job performance measure to be satisfactorily completed, - I accomplish this JPM in accordance with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality lastruction Ol-5-PSL-1. B. Locate and operate all plant equipment correctly. ) l C. The system / equipment status reflects the overall intent of what the JPM { required upon completion. > D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from d memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indicatior.s available and in accordance with the facility's procedural guidance. Initiatina Cue (sk The Unit 2 SNPO has verified the valve lineup required to pump the 2B Holdup Tank to the 1B Holdup Tank. The ANPS has directed you to verify the Unit 2 SNPO's valve lineup.
References:
l' P&lD 2998-G-078, sheets 1608,168; 8770-G-078, sheets 160a,160b,160c
. During the performance of the task I will tell you which steps to simulate or discuss.
I
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
Page 4 of 7 1
)
r JOB PERFORMANCE MEASURE 1
. Verify the position or condition of equipment or components by pointing to the
- instrumentation and providing a brief explanation of how the indication is used
, for verification, i
- . I will provide you with the appropriate cues for st
- . which are simulated or discussed.
x
- . You may use any approved reference materials normally available in the j execution of this Job Performance Measure, including logs.
i
- . Do you understand these directions?
i
. If you have any questions, ask them now, and I will answer them.
a
. During the test I cannot answer questions.
I . When you complete all steps correctly, you will pass this job performance , measure. ! . Begin the task now. I I l 1 l: l Page 5 of 7
W > 4 JOB PERFORMANCE MEASURE Provide this page *.o the Candidate The following is the lineup to pump the 2B Holdup Tank to the 1B Holdup Tank: (assume 2B Hut is isolated and all other valves in their current PalD position) Unit 2 Valves: Unit 1 Valves: V6167 Open V06131 Open - V6184 Open V6304 Closed V6196 Open V6306 Open V6197 Closed : V6216 Open i V6217 Open V6234 Closed V6040 Open Start 2B Holdup Drain Pump, monitor Holdup tank 28 and 18 levels. I l 1 l I
)
1 l l I Page 6 of 7 l 1
c JOB PERFORMANCE MEASURE ANSWER KEY Initial Conditions: The Unit 2 SNPO has verified the valve lineup required to pump the 2B Holdup Tank to the 18 Holdup Tank. Initiating Cue: The ANPS has directed you to verify the Unit 2 SNPO's valve lineup. The following is the lineup to pump the 2B Holdup Tank to the 1B Holdup Tank: (assume 28 Hut is isolated and all other valves in their current P&lD position) Unit 2 Valves: Unit 1 Valves: V6167 Open V06131 Open V6184 Open (C) V6304 Open" i V6196 Open (C) V6306 Closed" V6197 Closed , V6216 Open ' i V6217 Open V6234 Closed l V6040 Open 4 l Start 28 Holdup Drain Pump, monitor Holdup tank 28 and 18 levels.
" These valves are mispositioned on the candidate lineup:
i Page 7 of7
l* r 3 This JPM For NRC Exam Use
@FPL '
Only St Lucie Nuclear Plant Licensed Operator Tra!ning Program Administrative Job Performance Measure Determine Radiation Postings SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO Administrative Topic: Radiation Control KA Statement: Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure KA: 2.4.10 2.913.3
Reference:
HP-2, "FPL Health Physics Manual" Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner / Prior to use, ensure referenced procedures are current revisiona if not, verify JPM is in accordance with current revision.
JOB PERFORMANCE MEASURE 1 l Department: Operations l Task
Title:
Determine Radiation Postings .i Trainee: Evaluator-4 An X below indicates the applicable method (s) of testing that may be used: , Perform X Simulate , Estimated Time to Complete the JPM: 20 Minutes l Location of Performance: Unit 1 Control Room, Training Building Notes to the Evaluator:
- Pull the latest controlled copy of the applicable procedure s . The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
t
. Notify a Management Observer of the observation opportunity. l 4
i i I d i Page 2 of 7 4
JOB PERFORMANCE MEASURE READ TO THE TRAINEE
. You are to perform / simulate this task.
. The task you are to perform / simulate is:
DETERMINE RADIATION POSTINGS
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
. Before starting I will state the task standards and initiating cues and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: Health Physics has performed a survey of the Unit 2 Charging Pump rooms and i hallway. Given a survey map, determine how each room and hallway should be posted. i Tools and Eauioment: None Safety Considerations: None Page 3 of 7
~
t JOB PERFORMANCE MEASURE i Task Standard (s): , in order for this job performance measure to oe satisfactorily completed, accomplish this JPM in accordance with the following standards: A. Carry out: tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ql-5-PSL-1. B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overall intent of what the JPM - required upon completion. 1 D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from ; memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedura: guidance , j Initiatina Cue (s): . Health Physics has performed a survey of the Unit 2 Charging Pump rooms and hallway. Given a survey map, determine how each room and hallway should be posted.
References:
St. Lucie Unit 2 Plant Physics Curves
- During the performance of the task I will tell you which steps to simulate or ;
discuss.
.- Verbalize each step before you do it. This gives you a chance to self-check t
Page 4 of 7 l.
JOB PERFORMANCE MEASURE and use STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the '
instrumentation and providing a brief explanation of how the indication is used for verification.
. I will provide you with the appropriate cues for steps which are simulated or discussed. . You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs. . Do you understand these directions?. . If you have any questions, ask them now, and I will answer them. . During the test I cannot answer questions. . When you complete all steps correctly, you will pass this job performance measure. - Begin the task now.
1 Page 5 of 7
1 JOB PERFORMANCE MEASURE 4 Provide this page to the Candidate i 4 Health Physics has performed a survey of the Unit 2 Charging Pump rooms and hallway. Given a survey map, determine how each room and hallway should be i posted. i J J 4 Page 6 of 7 ui
JOB PERFORMANCE MEASURE Answer Key 2A Charging Pump room - Radiation area I 2B Charging Pump room - Radiation Area, contaminated area 2C Charging Pump room - Contaminated area Charging Pump hallway - Radiation area, hot spot NOTE: To successfully pass this JPM, the candidate must correctly determine three of four postings. 1 d t i Page 7 of 7 1 i
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'7 FOR TRAINLNG USE ONL
O ( h This JPM Fo RC Exam Use t ) FPL St Lucie Nuclear Plant Licensed Operator Training Program Administrative Job Performance Measure VERIFY A CLEARANCE UNIT 2 l SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED l Job Applicability. ROISRO Administrative Topic: Equipment Control KA Statement: Knowledge of tagging and clearance procedures KA: 2.2.13; 3.6/3.8
Reference:
ADM-09.04, "In Plant Equipment Clearance Orders", P&lD 2998-G-078 sheet 120 l Developed / Revised by: Tim Bolander / Approved by Training Supervision: / l Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in ! accordance with current revision. l 1 l l l
4 . 4 . JOB PERFORMANCE MEASURE Department: Operatians Task
Title:
VERIFY A CLEARANCE UNIT 2 i Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perfnrm X Simulate Estimated Time to Complete the JPM: 15 MINUTES , Location of Performance: CONTROL ROOM UNIT 2 / SIMULATOR Notes to the Evaluator:
- Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
1 l l I 4 i Page 2 of 6 i
JOB PERFORMANCE MEASURE-READ TO THE TRAINEE
. You are to perform / simulate this task.
. The task you are to perform / simulate is:
VERIFY A CLEARANCE UNIT 2
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
. Before starting I will state the task standards and initiating cues and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: The 2B CVCS lon Exchanger resin will be replaced tomorrow. The TACTS system is out of service and a clearance has been manually written to isolate and drain the 2B CVCS lon Exchanger.. Tools and Eauipment: P&lD 2998-G-078 sheet 120 I Safety Considerations: In accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): in order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: Page 3 of 6 l l
^
JOB PERFORMANCE MEASURE A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality instruction Ol-5-PSL-1. B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overall intent of what the JPM , required upon completion. D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. . Performance of Off-Normal Operating Procedure immediate actions will be from < memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatina Cuefs): The ANPS has directed you to verify the clearance for the 2B CVCS lon Exchanger.
References:
P&lD 2998-G-078 sheet 120
. During the performance of the task I will tell you which steps to simulate or discuss.
. Verbalize each step before you do it. This gives you a chance to self-check l and use STOP during the performance of each task element.
l l
. Verify the position or condition of equipment or components by pointing to the )
instrumentation and providing a brief explanation of how the indication is used for 1 verification.
. I will provide you with the appropriate cues for steps which are simulated or discussed.
- You may use any approved reference materials normally available in the Page 4 of 6 I l
4
~
JOB PERFORMANCE MEASURE execution of this Job Performance Measure, including logs.
- Do you understand these directions? -
- If you have any questions, ask them now, and I will answer them.
- During the test I cannot answer questions.
- When you complete all steps correctly, you will pass this job performance ;
measure. ,
- Begin the task now.
+
l l 4 i J 1 2 f i i j e i i l ' Page 5 of 6
JOB PERFORMANCE MEASURE Provide this page to the Candidate J Initial Conditions: The 2B CVCS lon Exchanger resin will be replaced tomorrow. The j TACTS system is out of service and a clearance has been manually written to isolate and drain the 2B CVCS lon Exchanger.. Initiating Cue: The ANPS has directed you to verify the clearance for the 2B CVCS lon Exchanger. I 1 i l 1 I Page 6 of 6
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This JPM For NRC Exam Use ; Only ) I i FPL : St Lucie Nuclear Plant ; Licensed Operator Training Program Job Performance Measure RESPOND TO A DROPPED CEA AT UNIT 2 0821164, Rev 00 l SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO System: Control Rod Drive System Safety Function: 001
Reference:
ONOP 2-0110030, "CEA Off-Normal and Realignment",2-EOP-01, " Standard Post Trip Actions" Task: Operate the control rods manually while the Reactor is at power Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision.
4 I JOB PERFORMANCE MEASURE Department: Operations Task
Title:
RESPOND TO A DROPPED CEA AT UNIT 2 JPM No.: 0821164, Rev 00 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 20 Minutes Location of Performance: UNIT 2 CONTROL ROOM / SIMULATOR Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
. The next to last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
4 0821164, Rev 00 Page 2 of 15
?
d 4 - h -...a.,a.d.; m -.. 4A k. e f -.--4a -.42--+ 4j J -a- MA . -M
- 64- . 4-em+e
. JOB PERFORMANCE MEASURE i , READ TO THE TRAINEE i !
. You are to perform / simulate this task. ;
l . The task you are to perform / simulate is: 1 i i RESPOND TO A DROPPED CEA AT UNIT 2 - i
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate / discuss this task.
. Before starting I will state the task standards and initiating cues and answer any ,
j questions you have. l
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
i.
- Any safety infraction during this task performance evaluation will be corrected l
j immediately prior to continuing the JPM. l General / Initial Conditions l j , The plant is operating at 100% power, MOL, and the CEA periodic surveillance is in i progress. CEA 56 has dropped to the bottom while being exercised. The immediate Operator Actions have been performed. There have been no dropped rods in the previous 24 hours. j Tools and Eauioment j None Safety Considerationg ) 1 l 1 In accordance with the FPL Nuclear Division Safe Work Practices manual as appropriate to the task. l 4 Task Standard (s): 1 In order for this job performance measure to be satisfactorily completed, accomplish this l JPM in accordance with the following standards: Page 3 of 1s I 0821161, Rev 00 . I I
4 l JOB PERFORMANCE MEASURE i A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ol 5-PSL-1. B. - Locate and operate all plant equipment correctly.' C. The system / equipment status reflects the overallintent of what the JPM required upon completion. D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatina Cue (s) The ANPS has directed you to carry out the Subsequent Actions of the CEA Off-normalin order to realign CEA # 56 with the remainder of the Group 5 CEAs. l References ' l ONOP-2-0110030, Rev. 38 1
. During the performance of the task I will tell you which steps to simulate or discuss. . Verbalize each step before you do it. This gives you a chance to self-check and use i STOP during the performance of each task element.
1
. Verify the position or condition of equipment or components by pointing to the '
instrumentation and providing a brief explanation of how the indication is used for verification. l
. I will provide you with the appropriate cues for steps which are simulated or discussed. .' You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
l _0821164, Rev 00 Page 4 of 15 l l l 1 l r ,
\
JOB PERFORMANCE MEASURE
. Do you understand these directions?
. If you have any questions, ask them now, and I will answer them.
- During the test I cannot answer questions.
. When you complete all steps correctly, you will pass this job performance measure.
. Begin the task now. -
I l l l l l l 0821164, Rev 00 Page 5 of 15 l i
4 JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 1. Element / Step Notify Reactor Engineering, Operations Supervisor and Operations Manager of the time of CEA misalignment.
Standard: REPORT time of CEA misalignment to Reactor Engr., Ops Supv., and the Ops Manager Cue: REACTOR ENGR., OPS SUPV., AND THE OPS MANAGER ACKNOWLEDGE REPORT SAT UNSAT Comments:
- 2. (C) Element / Step Determine from symptoms and CEA position indication to use Appendix F for CEA recovery instructions Standard: REFER to Appendix F for CEA recovery instructions Cue: ACKNOWLEDGE USE OF APP. F SAT UNSAT Comments:
l 0821164. Rev 00 Page 6 of 15
i JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 3. (C) Element / Step Ensure the following:
A. Standard: CEDMCS panelin OFF Cue: CEDMCS IN OFF B. Standard: Turbine power adjusted to equal reactor power. Tavg/ Tref matched on TIR-1111 or TIR-1121. Cue: Tavg/ Tref MATCHED C. Standard: CEA motion inhibit. Cuo: ANNUNCIATOR LIT NOTE -IF QUESTIONED ON PREVIOUS DROPPED ROD HISTORY, REFER STUDENT TO INITIAL CONDITIONS SHEET PROVIDED AT THE START OF THE JPM, NO DROPPED RODS HAVE OCCURED WITHIN THE LAST 24 HOURS. SAT UNSAT r Comments:
)
1 0821164, Rev 00 Page 7 of 15 j
. , _ . - ~. _ _ _ _ _ . _ , _ - _ . , .. .. _ . _ _ _ _ ._ _ _ _ . _
JOB PERFORMANCE MEASURE i
~
4 (C) Indicates a Critical Step PERFORMANCE CHECKLIST
; 4. (C) Element / Step Determine the operability of the CEA in accordance with Appendix A. f
- Refer to App. A and perform t;,e following to determine operability
- ,
l
; A. Standard: Place the mode select switch in MANUAL INDIVIDUAL.
a Cue: MODE SELECT IN MANUAL INDIVIDUAL i i B. Standard: SELECT CEA 55 on the individual CEA selection switches. J
- i Cue: CEA 56 SELECTED i l l i :
- C. Standard
- SELECT GROUP 5 on the group select switch.
i Cue: CUE: GROUP 5 SELECTED { D. Standard: Enable CMI Bypass by: l
; Depress and HOLD the CEA motion inhibit bypass pushbutton.
i AND i DEPRESS then RELEASE the Bypass Enable pushbutton i Cue: BYPASS ENABLED , ( I ! E. Standard: WITHDRAW CEA 56 until rod bottom and LEL lights extinguish, , , ItgLa INSERT and WITHDRAW the affected CEA and check for smooth operation and normal indications. l . i Cue: CEA BEGINS TO WITHDRAW AND CONTINUES TO WITHDRAW EVEN IF THE CONTROL SWITCH IS RELEASED OR PLACED IN THE INSERT POSITION. i SAT UNSAT , Comments: f i 1 ' 0821164, Rev 00 Page 8 of 15 i t i
. . . . . - - . .. . -. . - - . - . _.. ~ - . ~ . _ . - . . . . . . - . - - -
I i i ! JOB PERFORMANCE MEASURE ! i k i , 1 . (C) Indicates a Critical Step PERFORMANCE CHECKLIST ! i
- 5. (C) Element / Step Place the CEDMCS panelin QEE. f a Standard: The CEDMCS panelis in QEE.
Cue: CEA 56 CONTINUES TO WITHDRAW. [ 4 i 6. (C) Element / Step Trip the Reactor and implement 2-EOP-01, " Standard Post Trip Actions". Standard: Manually trip the Reactor and perform " Standard Post Trip Actions" Cue: THE REACTOR TRIPS, THE TURBINE DOES NOT TR!P. 7 (C) Element / Step Manually trip the Turbine l Standard: Trip the Turbine Cue: TURBINE IS TRIPPED f e l SAT UNSAT Comments: ; f 1 i i
)
1 0821164. Rev 00 Page 9 of 15 i t
F JOB PERFORMANCE MEASURE
-l (C) Indicates a Critical Step PERFORMANCE CHECKLIST l t
- 8. Element / Step: Refer to Standard Post Trip Actions (2-EOP-1) and determine the course of action to take.
Standard: Implements 2-EOP-1 i Cue; SPTAS IN PROGRESS END Element / Step TERMINATION Standard: JPM is terminated when the Reactor and Turbine is tripped and 2-EOP-01 is being implemented. i SAT UNSAT Comments: P e 0821164, Rev 00 Page 10 of 15 r ;
6
- JOB PERFORMANCE MEASURE i
i! Knowledge Questions t
- Question #1.
i KA: 001K5.02 Importance: 2.9/3.4 -
Reference:
Unit 2 Plant Physics Curves i Question: Unit 2 has 6,000 EFPH on the core and experiences a dropped rod resulting in the NI power level changes from 100% to 93%, what is the approximate worth of the dropped rod? I Expected Response: Approximately 75 to 100 pcm.
- SAT UNSAT l
Comments: l , Question # 2. KA: 001KS.28 Importance: 3.5/3.8 i Rrference: Unit 2 Plant Physics Curves , 4 Question: In order to withdraw the same CEA without changing the power level or temperature
- of the RCS, how much would RCS boron concentration have to be changed?(PPM)
"If Question 1 is missed: Assuming the worth of a dropped CEA was 100 pcm, how much would boron concentration have to be changed to withdraw the rod without changing power level ;
or temperature? Expected Response: approximately 12 PPM (Boron worth for the present conditions is 8.38pcm/ ppm) . SAT UNSAT , Comments: , i
+
0821164, Rev 00 Page 11 of 12 l 5 i
! i + . JOB PERFORMANCE MEASURE , i ! Provide this page to the Candidate
- Initial Conditions
1 The plant is operating at 100% power, MOL, and the_CEA periodic surveillance is in l progress. CEA 56 has dropped to the bottom while being exercised. The immediate ' i Operator Actions have been performed. There have been no dropped rods in the previous 24 hours J
- Initiating Cue:
The ANPS has directed you to carry out the Subsequent Actions of the CEA Off-normal in order to realign CEA # 56 with the remainder of the Group 5 CEAs. i n821164. Rev 00 Page 12 of 1S l
. - . . - . . . - . - . ~ .. .. -
t JOB PERFORMANCE MEASURE , Provide this page to the Candidate i Unit 2 bcs 6,000 EFPH on the core and experiences a dropped rod resulting in the NI power level changes from 100% to 93%, what is the approximate worth of the dropped rod? ; f Reference allowed
+
i 3 f I F [ f r i 0821164 Rev 00 Page 13 of 15
- .-. . .. . . . . - . .. . . = . . . _ . = . .
JOB PERFORMANCE MEASURE 1 a Provide this page to the Candidate In order to withdraw the same CEA without changing the power level or temperature of the RCS, how much would RCS boron concentration have to be changed?(PPM) j- Reference allowed i i i c I i 4 A i s b e l l I 1 e
- f i
a
~
I , t l 0821164, Rev 00 Page 14 of : ,1
L y JOB PERFORMANCE MEASURE - 1
}
Provide this page to the Candidate Assuming the worth of a dropped CEA was 100 pcm, how much would boron concentration have to be changed to withdraw the rod without changing power level or ' temperature? Reference allowed , l i k i I r f 0621164, Rev 00 Page 15 of 1a
a This JPM For NRC Exam Use i Only i
@FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure OPERATE HYDROGEN PURGE SYSTEM - UNIT 2 0821058, Rev 06 l I
SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO , I System: HRPS l i Safety Function: 05
Reference:
2-EOP-99, APPENDIX N. Task: Start up the Hydrogen purge system j Developed / Revised by: Tim Bolander / Approved by Traini . Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in j accordance with current revision. l 1 l l l 1
JOB PERFORMANCE MEASURE Department: Operatic ns Task
Title:
OPERATE HYDROGEN PURGE SYSTEM UNIT 2 JPM No.: 082105E:, Rev 06 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 20 MINUTES Location of Performance: CONTROL ROOM UNIT 2, SIMULATOR Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
. The last r, age of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee,
. Notify a Management Observer of the observation opportunity.
l l l 0821058, Rev 06 Page 2 of 12 !
JOB PERFORMANCE MEASURE READ TO THE TRAINEE-
. You are to perform / simulate this task.
. The task yot are to perform / simulate is:
OPERATE HYDROGEN PURGE SYSTEM - UNIT 2 '
. I will describe she general conditions and tell you the tools and equipment required to perform / simulate this task.
. Before starting I will state the task standards and initiating cues and answer any questions you have. i
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to pe61orm the steps in the correct sequence.
- Any scfety infraction sluring this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: ! A loss of Coolant Accic ent has been diagnosed and is in progress in Unit 2. L Tools and Eouioment: NONE Safety Considerations: in accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): , in order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: A. ' Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality
- Instruction Ol-5-PSL-1.
0821058, Rev 06 Page 3 of 12 - I i t b
,,-.-. . . . . - = .. - . -- . - . . . - . . .. -. .- - .- n s JOB PERFORMANC85 MEASURE l B. Locate and operate all plant' equipment correctly. C. The system / equipment status reflects the overallintent of what the JPM required j upon completion. i
- D. Correctly perform all critical steps. >
l l j . All steps where procedural guidance exists may be considered critical. Performance of
- Off-Normal Operating Procedure immediate actions will be from memory, l !
j During the course of the JPM, there may b some tasks you will have to perform that will j require you to implement contingency action. in order to complete them. Even in these l [ cases, you are expected to make decisions and take actions based on the indications , ! available and in accordance with the facility's procedural guidance. - a j Initiatino Cue (s):
- i. ,
i ! Containment hydrogen concentration is greater than 3.5% and the Technical Support l Center has recommended that the hydrogen purge system be placed in operation. The i ! ANPS directs you to put the hydrogen purge system in operation using "B" side l components IAW 2-EOP-99, APPENDIX N. 1 4 j
References:
i 2-EOP 99, Rev 15, Appendix N i i l'
. During the performance of the task I will tell you which steps to simulate or discuss.
v
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
- Verify the position or wndition of equipment or components by pointing to the instrumentation and nroviding a brief explanation of how the indication is used for verification.
. I will provide,you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference materials normali available in the execution of this Job Performance Measure, including logs.
. Do you understand these directions?
. If you have any questions, ask them now, and I will answer them. l 0821058, Rev 06. Page 4 of'12 l I
l l
= . _
JOB PERFORMANCE MEASURE
- During the test I cannot answer questions.
. When you complete all steps correctly, you will pass this job performance measure. . Begin the task now.
0821058, Rev D6 Page 5 of 12
s JOB PERFORMANCE MEASURE. ) (C) indicates a Critical Step PERFORMANCE CHECKLIST i . 1, Element / Step Verify closed FCV-25-35, " Continuous Containment Purge Exhaust to Vent Stack." Standard: At NON-SAFETY VENTILATION HVAC PANEL: DETERMINE FCV-25-35 . key lock switch is in the LOCKED CLOSE position l Cue: GREEN LIGHT ON, RED LIGHT OFF SAT UNSAT 2,(C) Element / Step Open FCV-25-20, " Continuous Cntmt. Purge Isol. Valve" and FCV-25-21,
" Continuous CntmtJH2 Purge Makeup Valve."
A. Standard: At the A TRAIN EMERGENCY VENTILATION HVAC PANEL: POSITION FCV-25-20 control switch to OPEN Cue: GREEN LIGHT OFF, RED LIGHT ON B. Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: POSITION FCV-25-21 control switch to OPEN e Cue: GREEN LIGHT OFF, RED LIGHT ON SAT UNSAT 3.(C) Element / Step Open FCV-25-29, "H ,2 Purge Discharge to SBVS 'B'." Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: Obtain key ,
#95 and POSITION FCV-25-29 key lock switch to OPEN Cue: KEY OBTAINED, GREEN LIGHT OFF, RED LIGHT ON SAT UNSAT Comments: ,
0821058, Rev 06 Page 6 of 12 i
JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST ;
- 4. ElemenUStep Check closed FCV-25-9," Continuous ContainmenUHydrogen Purge Control Valve Filter inlet."
Standard: At the NON-SAFETY VENTILATION HVAC PANEL: VERIFY CLOSED FCV-25-9 Cue: 0%, GREEN LIGHT ON, RED LIGHT OFF , i SAT UNSAT 5.(C) ElemenUStep Throttle FCV-25-28," Continuous Containment / Hydrogen Purge Control ! Valve Bypass" to approximately 10% OPEN position. Standard: At the NON-SAFETY VENTILATION HVAC PANEL: POSITION FCV 28 to the open position UNTIL the valve position indicates 10% OPEN
- Cue
- 10%, BOTH RED & GREEN LIGHTS ON SAT UNSAT 4
6, (C) ElemenUStep Start HVE-68," Shield Building Exhaust Fan." i Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: POSITION HVE-6B control switch to START Cue: RED LIGHT ON, GREEN LIGHT OFF SAT UNSAT ! i a Comments: 4 k i J 0821058, Rev 06 Page 7 of 12 l
JOB PERFORMANCE MEASURE - ! (C) Indicates a Critical Step PERFORMANCE CHECKLIST i f
- 7. (C) Element / Step Select FCV-25-26 and FCV-25-36," Continuous Containment / Hydrogen ;
Purge Makeup Valves" to the OPEN position. { NOTE: FCV-25-26 & 36 WILL NOT OPEN UNTIL A NEGATIVE AP EXISTS BETWEEN CONTA NMENT AND OUTSIDE AIR PRESSURE i A. Standard: At the A TRAIN EMERGENCY VENTILATION HVAC PANEL: $ POSITION FCV-25-26 control switch to OPEN, then release the i switch : I Cue: SWITCH POSITIONED TO OPEN, GREEN LIGHT ON, RED i LIGHT OFF j B. Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: l POSITION FCV-25-36 control switch to OPEiN, then release the switch , Cue: SWITCH POSITIONED TO OPEN, GREEN LIGHT ON, RED : LIGHT OFF SAT UNSAT l 8.(C) Element / Step Start HVE-78, " Hydrogen Purge Fan." r Standard: At the NON-SAFETY VENTILATION HVAC PANEL: POSITION HVE-78 control switch to START Cue: RED LIGHT ON, GREEN LIGHT OFF i SAT UNSAT Comments: l
)
0821058. Rev 06 Page 8 of 12 I i t
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- - . ~ . . - -_. . .. .-. _.
I l JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 9. Element / Step Throttle FCV-25-28," Control Byp' ass Valve" to maintain a hydrogen purge l rate of approximately 100 CFM.
Standard: At the NON-SAFETY VENTILATION HVAC PANEL: MONITOR FI-25-2 j and simultaneously THROTTLE FCV-25-28, until F1-25-2 indicates 100 M , l Cue: 100 CFM INDICATED I SAT UNSAT Comments:
- 10. Element / Step Observe proper system operation by checking flows, hydrogen sample analysis concentrations, and plant vent monitor.
Standard: MONITOR parameters to determine effectiveness of hydrogen purge operation. Cue: PROPER FLOW INDICATED, H2 CONCENTRATION LOWERING, l PLANT VENT RAD LEVELS RISING , i SAT UNSAT END Element / Step TERMINATION i l Standare: The Hydrogen Purge System is in operation per the required steps of ; 2-EOP-99, APPENDIX N and the ANPS is informed. l Comments: I < l E 0821058, Rev 06 Page 9 of 12 ; I
JOB PERFORMANCE MEASURE Knowledge Questions Question #1. KA: 028K5.04 Importance: 2.6/3.2 Reference allowed (FSAR) i Question: Describe the process of hydrogen removal by the Hydrogen Recombiners. Expected Response: The Hydrogen Recombiners draw hydrogen from the containment atmosphere by natural convection. The gasses are then heated to approximately 700 F wher the hydrogen and oxygen are combned to form water, which is continuously drained. SAT UNSAT Comments: Question # 2. - KA: 028A4.01 Importance: 4.0/4.0
Reference:
P& ids Question: How is the Unit 1 Hydrogen Purge System different than the Unit 2 Hydrogen Purge System? Expected Response: Unit 1 Hydrogen Purge System must be manually aligned for oper.sn
- and uses its own filter train whereas Unit 2 Hydrogen Purge System can be aligned from the control room and uses the Shield Building Ventilation filter train.
~-
SAT UNSAT Comments: 0821058. Rev 06 Page 10 of 12 e
JOB PERFORMANCE MEASURE : Provide this page to the Candidate Initial Conditions: A loss of Coolant Accident has been diagnosed and is in progress in Unit 2.
. b
?
Initiating Cue;
. Containment hydrogen concentration is greater than 3.5% and the Technical Support Center has recommended that the hydrogen purge system be placed in operation. The ANPS directs you to l put the hydrogen purge system in operation using "B" side components IAW 2-EOP-99, APPENDIX N. !
I e u i i i 0821058, Rev 06 Page 11 of 12 P
i. i l
- JOB PERFORMANCE MEASURE'
- Provide this page to the Candidate
? Describe the process of hydrogen removal by the Hydrogen Recombiners.
i I Reference allowed i i 1 i ) i < 1 a i i I i e i 5 4 1 i 1 0821058, Rev 06 Page 12 of 12 1 . I s _.
)
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~ _ . - . - . . _ . . . _ - _ . _ _ . _ . . _ _ . ._ _. . . . _ _ _ _ _.
5 JOB PERFORMANCE MEASURE l Provide this page to the Candidate How is the Unit 1 Hydrogen Purge System different than the Unit 2 Hydrogen Purge System? , Reference allowed t i c i i j ' i 1 i. e l-l 0821058, Rev 06 -- Page 13 of 12 . t
- 6 r
e
4 This JPM For NRC Exam Use Only FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO CROSSTIE 0821129, Rev 02 SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED NON-CRITICAL STEPS MAY BE SIMULATED OR DISCUSSED TIME CRITICAL Job Applicability. RO, SRO System: AC Electrical Distribution Safety Function: 06
Reference:
2-EOP-99, TABLE 7, APP. V Task: Line up the AC electrical distribution system l Developed / Revised by: Tim Bolander / I Approved by Training Supervision: / ; 1 Examiner: / I Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. I
a JOB PERFORMANCE MEASURE Department: Operations Task
Title:
RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO CF:OSSTIE JPM No.: 0821129, Rev 02 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 10 minutes Location of Performance: Unit 2 Control Room / Simulator
, Notes to the Evaluator:
- . Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
NOTE: The trainee should be made aware that the JPM is TIME CRITICAL. 0821129, Rev 02 Page 2 of 16
,4 z
JOB PERFORMANCE MEASURE :I READ TO THE TRAINEE
. You are to perform / simulate this task. .l I
- The task you are to perform / simulate is:
RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO' CROSSTIE i
. I will describe the general conditions and tell you the tools and equipment required to'
~
perform / simulate this task.
- Before starting I will state the task standards and initiating cues and answer any questions you have.
l
. When you perform all the critical steps correctly, you will pass this Job Performance )
Measure. j l
. You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
1 General / initial Conditions: 1 A Station Blackout has occurred on Unit 2. Unit 1 is in a LOOP with both Emergency i Diesel Generators in service. The NPS and ANPS have determined the need to crosstie electrical power from the 1 A EDG to the 2A3 4.16 KV switchgear via the SBO AB Bus Crosstie. l Tools and Eauioment: ) 1 i None Safety Considerations: In accordance with the FPL Nuclear Division " Safe Work' Practices" manual as appropriate to the task. i Task Standard (s): In order for this job performance measure to be satisfactority completed, accomplish this I 0821129. Rev 02 Page 3 of 16 1
.-- . . - . , -. .- - -- . . _ - - = ..
I 1 l j JOB PERFORMANCE MEASURE JPM in accordance with the following standards: 4 A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality-t Instruction Ol-5-PSL-1. i B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overallintent of what the JPM required upon completion. l . D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of , i Off-Normal Operating Procedure immediate actions will be from memory, i i During the course of the JPM, there may be some tasks you will have to perform that will
; require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance.
e Initiatina Cue (sk ~ j 1 i The ANPS has directed you to accomplish the Unit to Unit crosstie to the 2A3 4.16 KV , Bus by performing 2-EOP-99, Table 7 and then 2-EOP-99, App. V within 10 minutes. 1 1
References:
2-EOP-99, TABLE 7, APP. V, Rev.15 , i 1 i
. During the performance of the task I will tell you ahl-b steps to simulate or discuss.
I
. Verbalize each step before you do it. This gives you a chance to self-check and use j STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the i instrumentation and providing a brief explanation of how the indication is used for verification.
- 1 i
. I will provide you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
'1 l
Page 4 of 16 ! 0821129. Rev 02 l
l l l JOB PERFORMANCE MEASURE
. Do you understand t'iese directions? . If you have any questions, ask them now, and I will answer them.
- During the test I cannot answer questions.
. When you complete all steps correctly, you will pass this job performance measure. . Begin the task now.
0821129, Rev 02 Page 5 of 16
JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 1. (C) Element' Step OPEN and GREEN FLAG the following startup transformer breakers:
A. E.tandard: S.U. Transformer 2A (2-30102) Cue: GREEN LIGHT ON, FLAG GREEN B. Etandard: S.U. Transformer 2B (2-30202) C ue: GREEN LIGHT ON, FLAG GREEN C. Standard: S.U. Transformer 2A (2-20102) ; Cue: GREEN LIGHT ON, FLAG GREEN D. Standard: S.U. Trar.;former 2B (2-20302) , i Cue: GREEN LIGHT ON, FLAG GREEN
- 2. (C) Element / Step Ensure the following breakers are GREEN FLAGGED and OPEN:
A. Standard: Aux Transformer 2A (2-30101 ) (2W87) Cue: GREEN LIGHT ON, FLAG GREEN Standard: Aux Transformer 2B (2-30201) (2W85) Cue: GREEN LIGHT ON, FLAG GREEN Comments: I l
-I I
0821129. Rev 02 Page 6 of 16 . ,
, 1 I l JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 2. (Cont'd) B. Standard: Aux Transformer 2A (2-20101) (1W86)
Cue: GREEN LIGHT ON, FLAG GREEN Standard: Aux Transformer 2B (2-20301) (1W84) Cue: GREEN LIGHT ON, FLAG GREEN C. Element / Step Tie breakers between normal and emergency 4160V buses: Standard: 4.16 KV Bus Tie 2A2-2A3 (2-20109) Cue: GREEN LIGHT ON, FLAG GREEN Standard: 4.16 KV Bus Tie 2A3-2A2 (2-20209 Cue: GREEN LIGHT ON, FLAG GREEN Standard: 4.16 KV Bus Tie 2B2-283 (2-20309) Cue: GREEN LIGHT ON, FLAG GREEN Standard: 4.16 KV Bus Tie 283-2B2 (2-20411) Cue: GREEN LIGHT ON, FLAG GREEN D. Element / Step 4.16 KV Bus 2AB Tie breakers Standard: Feed to 4.16 KV Bus 2AB (2-20208) Cue: GREEN LIGHT ON, FLAG GREEN Standard; incoming feeder from 4.16 KV bus 2A3 (2-20505) Cue: GREEN LIGHT ON, FLAG GREEN 0821129. Rev 02 Page 7 of 16
.l
JOB PERFORMANCE MEASURE. (C) Indicates a Critical Step PERFORMANCE CHECKLIST 2.D. (Cont'd) Standard: Incoming feeder from 4.16 KV bus 2B3 (2-20504) Cue: GREEN LIGHT ON, FLAG GREEN l Standard: Feed to 4.16 KV Bus 2AB (2-20409) Cue: GREEN LIGHT ON, FLAG GREEN .
- 3. (C) Element / Step OPEN the following 4.16 KV feeder breakers to the station service transformers:
A. Standard: Station Service Transformer 2A1 (2-20110) Cue: GREEN LIGHT ON B. Standard: Station Service Transformer 2A5 (2-20210) Cue: GREEN LIGHT ON l C. Standard: Station Service Transformer 2A2 (2-20213) Cue: GREEN LIGHT ON I D. Standard: Station Service Transformer 281 (2-20310) Cue: GREEN LIGHT ON E. Standard: Station Service Transformer 2B2/285 (2-20402) Cue: GREEN LIGHT ON 0821129, Rev 02 - Page 8 of 16 i i i
l i JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 4. (C) Element / Step OPEN and GREEN FLAG the following 480V f'Ader breakers from the station service transformers:
A. Standard: 480V Bus 2A1 Feeder (2-40103) Cue: GREEN LIGHT ON, FLAG GREEN I B. Standard: 480V Bus 2A5 Feeder (2-40361) Cue: GREEN LIGHT ON, FLAG GREEN ! C. Standard: 480V Bus 2A2 Feeder (2-40219) Cue: GREEN LIGHT ON, FLAG GREEN i D. Standard: 480V Bus 2B1 Feeder (2-40419) Cue: GREEN LIGHT ON, FLAG GREEN E. Standard: 480V E.us 285 Feeder (2-40653) . Cue: GREEN LIGHT ON, FLAG GREEN F. Standard: 480V Bus 282 Feeder (2-40503) Cue: GREEN LIGHT ON, FLAG GREEN SAT UNSAT Comments: 1 I l 0821129, Rev 02 Page 9 of 16 8
- . - - - - - - - . - . - - - . . - .-- -+,--w . _ .-- -v - - -
- ,> -. 7
j 4 b JOB PERFORMANCE MEASURE (C) indicates a Critical Step PERFORMANCE CHECKLIST
- 5. (C) Element' Step OPEN the following 480V bus tie breakers l
l A. Standard: 480V Bus Tie 2A2-2AB (2-40220) ) Cue: GREEN LIGHT ON 4 i I B. E tandard: 480V Bus Tie 2AB-2A2 (2-40702) Cue: GREEN LIGHT ON 3 C. Standard: 480V Bus Tie 2AB-282 (2-40706) I ! Cue: GREEN LIGHT ON t D. Standard: 480V Bus Tie 2B2-2AB (2-40504) Cue: GREEN LIGHT ON k ] < SAT UNSAT i i l Comments: i I i II I i 1 l 5-
! 0821129. Rev 02 Page 10 of 16 s
9
l l 1 JOB PERFORMANCE MEASURE (C) indicates a Critical Step PERFORMANCE CHECKLIST
- 6. (C) Element / Step Establish communications with Unit 1.
Standard: ESTABLISH COMMUNICATIONS with Unit 1 via Gai-Tronics or ' plant radio (if available). Cue: COMMUNICATIONS ARE ESTABLISHED
- 7. Element / Step PLACE the following pump switches in the PULL TO LOCK position:
(C) A. Standard: 2A ICW Pump Cue: SWITCH IN PULL TO LOCK B. Standard: 2B ICW Pump Cue: SWITCH IN PULL TO LOCK C. Standard: 2C ICW Pump Cue: SWITCH IN PULL TO LOCK (C) D. Standard: 2A CCW Pump
- Cue
- SWITCH IN PULL TO LOCK 4
i j E. Standard: 2B CCW Pump Cue: SWITCH IN PULL TO LOCK 4 F. Standard: 2C CCW Pump Cue: SWITCH IN PULL TO LOCK SAT UNSAT . Comments: i j 0821129. Rev 02 Page it of 16 l 4
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I JOB PERFORMANCE MEASURE i (C) indicates a Critical Step PERFORMANCE CHECKLIST l
- e
- 8. (C) ElemenUStep Verify the EDG output breaker on the selected 4.16 KV bus is open
! Standard: VERIFY the EDG output breaker on the selected 4.16 KV tus (2-l 20211)is OPEN i Cue: GREEN LIGHT IS ON REPORT UNIT 1 IS READY TO l' CROSSTIE AB 4.16 KV BUSES. 4 a 9. (C) ElemenUStep Close in the Unit 2 SBO breaker l Standard: CLOSE IN the Unit 2 SBO breaker 2-20501. i j Cue: RED LIGHT ON i
- 10. (C) ElemenUStep Request the Unit 1 control room to close the Unit 1 SBO breaker .
Standard: REQUEST the Unit 1 control room to close the Unit 1 SBO breaker 1-20501. Cue: UNIT 1 ACKNOWLEDGES REQUEST. END ElemenUStep TERMINATION Standard: Student requests Unit 1 to close the Unit 1 SBO crosstie breaker. Comments: r I I, [ 0821129.Rev02 Page 12 of 16 l 1
t JOB PERFORMANCE MEASURE Knowledge Questions . Question #1. 2 : l KA: 062A1.03
- Importance: 2.5/2.8
Reference:
None . Question: What causes the RWT outlet valve (V 2504) to open when 480 V LC-2AB is i j deenergized? l l - Expected Response: Deenergizing 480 V LC 2AB results in the VCT Level circuitry ' i deenergizing. The VCT Level circuit's " low-low level" interlock then swaps the VCT suction path from the VCT to the RWT. i SAT UNSAT 1 Comments: e a Question # 2 i KA: 062AA1.01 . Importance: 3.4/3.8 Reference allowed (FSAR) Question: What is the limiting factor on the amount of current that can be passed from Unit 1 to 3 Unit 2 through the SBO crosstie? Expected Response: The electrical cable between the two units is the limiting factor. i SAT UNSAT Comments: ! l 0821129, Rev 02 Page 13 of 16 i
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i P JOB PERFORMANCE MEASURE Provide this page to the Candidate . What causes the RWT outlet valve (V-2504) to open when 480 V LC-2AB is . deenergized? No Reference i P l t i !' i l l l ! 0 0821129, Rev 02 Page 14 of 16 1 l _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . . - _ _ _ _ , _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ , , . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ . , , _ , . _ _,,l
i JOB PERFORMANCE MEASURE Provide this page to the Candidate ; What is the limiting factor on the amount of current that can be passed from Unit 1 to Unit 2 through the SBO crosstie? , Reference allowed I t 0821129, Rev 02 Page 15 of 16 1 i L _ _ _ _ . _ _ _ _ _ . . _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _
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i i 1 JOB PERFORMANCE MEASURE Provide this page to the Candidato
- initial conditions
i A Station Blackout has occurred on Unit 2. Unit 1 is in a LOOP with both Emergency Diesel ,
! Generators in service. The NPS and ANPS have determined the need to crosstie electrical power from the 1A EDG to the 2A3 4.16 KV switchgear via the SBO AB Bus Crosstie.
! Initiating Cue: i The ANPS has directed you to accomplish the Unit to Unit crosstie to the 2A3 4.16 KV j Bus by performing 2-EOP-99, Table 7 and then 2-EOP-99, App. V within 10 minutes. ; j P i i 8 0821129, Rev 02 Page 16 of 16 l 1
a This JPM For ;Jkc Exam Use 9 FPL Only St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure ESTABLISH ONCE-THROUGH COOLING UNIT 2 0821037a, Rev 02 l SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO System: Emergency Core Cooling System Safety Function: 002
Reference:
2-EOP-15, Sec 5.6, path 4, Rev.14 Task: Adjust HPSI Flow, Manually initiate Safety injection Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. l l
JOB PERFORMANCE MEASURE Department: Operations Task
Title:
ESTABLISH ONCE-THROUGH-COOLING UNIT 2 JPM No.: 0821037a, Rev 02 i Trainee: i Evaluator: 1 1 An X below indicates the applicable method (s) of tesung that may be used: 3 Perform Simulate Estimated Time to Complete the JPM: 15 Minutes i Location of Performance: CONTROL ROOM UNIT 2/ SIMULATOR Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
- . The next to last page of this JPM lists the initial conditions and initiating cue. Tear j that page off and give it to the trainee.
. . Notify a Management Observer of the observation opportunity, '1 4 g 0821037a, Rev 02 Page 2 of 18
_ _ _ _ __ ~ _ _ _ _ _ _ _ ._ _ _
. 1 l
! JOB PERFORMANCE MEASURE
- READ TO THE TRAINEE
. You are to perform / simulate this task.
i ! - The task you are to perform / simulate is: i ESTABLISH ONCE-THROUGH-COOLING UNIT 2 i . I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
- . Before starting I will state the task standards and initiating cues and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job Performance -
i Measure. i 4
. You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
Generaj/Lnitial Conditions i A Total Loss of Feedwater event has been diagnosed and is in progress on Unit 2. All l attempts to restore main and auxiliary feedwater have been unsuccessful and steam generator levels are indicating 15% on wide range indication. The ANPS has directed that j once-through-cooling be established. Tools and Eauioment . None siafety Considerations: l In accordance with the FPL Nuclear Division Safe Work Practices manual as appropriate to the task. 0821037a, Rev 02 Page 3 of 18 i
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i JOB PERFORMANCE MEASURE i Task Standard (s): In order for this job performance measure to be satisfactorily completed, accomplish this JPM in accorda1ce with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ol-5-PSL-1.
- 8. Locate and operate all plant equipment correctly.
~
C. The system / equipment status reflects the overallintent of what the JPM required upon completion. D. Correctly perform all critical steps. All steps where crocedural guidance exists may be considered critical. Performance of l Off-Normal Operating Procedure immediate actions will be from memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them._ Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. t inhmtina Cue (s) Establish once-through-cooling LAW 2-EOP-15. l - 1 l References I 3 2-EOP-15, Sec 5.6, path 4, Rev.14 2-EOP-99, Figure 2, Rev.15 1 i l
- During the performance of the task I will tell you which steps to simulate or discuss.
- Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
- i. I
'l
- Verify the position or condition of equipment or components by pointing to the 0821037a. Rev 02 Page 4 of 18 '
I
- 4
! JOB PERFORMANCE MEASURE 1 instrumentation and providing a brief explahation of how the indication is used for .
- i. verification.
a I will provide you with the appropriate cues for steps which are simulated or discussed.
- . You may use any approved reference materials normally available in the execution of this
- Job Performance Measure, including logs. .
l
'. Do you understand these directions?
I .
. If you have any questions, ask them now, and I will answer them.
1
. During the test I cannot answer questions, i
i . When you complete all steps correctly, you will pass this job performance measure. < t j . Begin the task now. e i i i I L i 3 i 3 .
?
- I 4 >
i-i [
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0821037a. Rev 02 Page s of 18' 3 I 1 s--- ,. . + -
i ! JOB PERFORMANCE MEASURE
- PERFORMANCE CHECKLIST i
(C) Indicates a Critical Step . ! i l 1. (C) Element / Step Ensure A and B Trains of SIAS and CIAS have actuated. ; Standard: Manually actuate SlAS and CIAS by depressing the 'Think' l pushbutton and turning the channel actuate switch ON t i BOTH TRAINS OF SlAS AND CIAS ACTUATED, BUT V3627 ('A' HPSI Cue: 2 HDR VLV) SHOWS GEEN LIGHT INDICATION AND 2B HPSI PUMP , SHOWS GREEN LIGHT INDICATION AND NO AMPS. i j Standard: QEEN V3627 j Cue: V3627 INDICATES RED LIGHT i l . l Standard: START 2B HPSI pump ! j Cue: 2B HPSI PUMP INDICATES RED LIGHT AND SUFFICIENT AMPS. f l SAT UNSAT Comments: I i
.i 0821037a. Rev 02 Page 6 of 18 L :_ . . . . - . :. - _ ..
JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST (C) Indicates a Critical Step .
- 2. Element / Step Open all SBCS Valves (if system available). i Standard: Select MANUAL on the Steam Bypass Permissive switch Cue: SWITCH IN MANUAL Standard: Depress the MANUAL pushbuttons on PIC-8010, HlC-8801, HIC-6802, HIC-8803, HIC-8804 Cue: CONTROLLERS IN MANUAL Standard: OPEN all SBCS valves using the knurled knobs Cue: RED LIGHTS ILLUMINATED . ,
SAT UNSAT Comments: NOTE: STEP IS CRITICAL IF MSIVs ARE OPEN.
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- 0821037a, Rev 02 Page 7 of 18 ,
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4 > JOB PERFORMANCE MEASURE. . PERFORMANCE CHECKLIST
' (C) Indicates a Critical Step
- 3. (C) Element / Step Open all Atmospheric Dump Valves (if available)
Standard: Place the AUTO / MANUAL selector switches for MV-08-18A and 19B in AUTO Cue: SELECTOR SWITCHES IN AUTO Standard: Place PIC-08-1 A and PIC-08-1B in MANUAL and hold the OPEN control signal output pushbuttons until the valves are FULLY OPEN Cue: VALVES INDICATE RED LIGHTS Standard; If ADV Auto controllers are unavailable, take MANUAL DC control I and position the valves FULLY OPEN Cue: VALVES INDICATE RED LIGHTS Standard: Repeat steps D thru F for MV-08188 and 19A Cue: VALVES INDICATE RED LIGHTS SAT UNSAT Comments: NOTE: CRITidAL ELEMENT IS ALL ADVs OPEN. i l 0821037a, Rev 02 Page 8 of 18 ' l
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I i JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST (C) Indicates a Critical Step i i, l 4. Element / Step Ensure all RCPs stopped ; Standard: Observe the green indicating lights illuminated for RCP's 2A1,2A2,
- 281,2B2 '
i 3 Cue: GREEN LIGHTS ILLUMINATED i i i , Standard: Observe the RCP ammeters AM-101, AM-109, AM-105, AM-113 $ indicate zero amperage i i
- Cue
- ALL AMMETERS INDICATE ZERO AMPERAGE SAT UNSAT f Comments:
4 i j 5. (C) Element / Step Ensure all available HPSI pumps running 1 3 Standard: Verify '2A' and '2B' HPSI red lights ONN and . pump ammeters AM-237 and AM-238 indicate running amps START the 2B pump if not done in step 1 of the JPM { Cue: PUMPS RUNNING NOTE: If not done in step 1, CUE the 28 not running I SAT UNSAT Comments: ; 1 i f 0821037a, Rev 02 Page 9 of 18
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JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST (C) Indicates a Critical Step
- 6. Element / Step Ensure all available charging pumps running Standard: Position all available charging pump control switches to START and observe red indicating lights illuminated Cue: CONTROL SWITCHES IN START AND RED LIGHTS ILLUMINATED Standard: Verify charging flow by observing FIA-2212 (Charging Flow to Regenerative HX)
Cue: CHARGING FLOW CONSISTENT WITH PUMP COMBINATION SAT UNSAT Comments:
- 7. (C) Element / Step Ensure HPSI pumps aligned for cold leg injection l Standard: Verify positions of the four "A" HPSI injection valves (HCV-3617, 3627,3637,3647) are OPEN I
OPEN V3627 if not done in step 1 of the JPM Cue: RED LIGHTS ILLUMINATED l NOTE: If not done in step 1, CUE valve V3627 not open Standard: Verify positions of the four "B" HPSI injection valves (HCV-3616, 3626,3636,3646) are OPEN Cue: RED LIGHTS ILLUMINATED SAT UNSAT Comments: l 4 0821037a, Rev 02 Page 10 of 18
3 i
- JOB PERFORMANCE MEASURE !
i PERFORMANCE CHECKLIST
- (C) indicates a Critical Step i
i j 8. (C) Element / Step Open both PORVs : 1 Standard: Complete the following steps ! i
- 8. (C) A. Element / Step Place the Off/ Override / Test switches for V1474 and V1475,~
PORVs to the OVERRIDE position. ; i ! Standard: Position the control switches for V1474 and V1475 to OVERRIDE Cue: SWITCHES IN OVERRIDE , ) i SAT UNSAT 4 Comments: i -
- 8. (C) 8. Element / Step Initiate a high pressure reactor trip signal by pulling two (2)
, RPS Hi Pzr. Press. trip bistables. 1. Standard: UNSCREW AND WITHDRAW the Hi Pzr. Press. trip unit bistables from any two channels of the RPS ] Cue: TRIP UNIT BISTABLES WITHDRAWN t SAT UNSAT Comments: ; 4 s
.. I b
I 0821037a, Rev 02 Page 11 of 18 l f
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JOB PERFORMANCE MEASURE 2 PERFORMANCE CHECKLIST (C) Indicates a Critical Step l 4
- 8. (C) C. Element / Step Verify open V1476 and V1477, "PORV Block Valves."
Standard: Observe the red position indicating lights illuminated for V1476 and V1477 i Cue: V1477 GREEN LIGHT ILLUMINATED , I V1476 RED LIGHT i Standarc: OPEN V1477 ; 1 l Cue: V1477 RED LIGHT ILLUMINATED l SAT UNSAT i Comments: , ^
- 8. (C) D. Element / Step Place the Off/ Override / Test switches for V1474 and V1475, .;'
PORVs to the OFF position 1 Standard: Position the control switches for V1474 and V1475 to OFF Cue: SWITCHES IN OFF SAT UNSAT Comments: 4 4 0821037a, Rev 02 Page 12 of 18
JOB PERFORMANCE MEASURE 4 i' I PERFORMANCE CHECKLIST (C) Indicates a Critical Step a j 8. (C) E. Element / Step Verify both PORVs OPEN ; ! Standard: Observe the BEQ position indicating lights for V1474 and V1475 - {. illuminated to verify the PORVs OPEN 2 i Cue: RED LIGHTS lLLUMINATED ) SAT UNSAT i NQIE: THE FOLLOWING INDICATION MAY BE USED IN ADDITION TO VALVE POSITION INDICATION TO VERIFY PORVs OPEN i RTGB 103: i Quench Tank parameters increasing on the following instrumentation: Pressure PIA-1116 j Level LIA-1116 j Temperature TIA-1116 PACB 2: Acoustic flow monitors Fl-01-1 and Fl-01-2 red LEDs indicate flow
- 9. Element / Step Verify safety injection flow per Figure 2, " Safety injection Flow
- _ versus RCS Pressure"in 2 EOP-99.
Standard: Ensure maximum available Safety injection flow by observing Fi-l 3311, F1-3321, Fl-3331, and F1-3341 and comparing to Figure 2 in i, 2-EOP-99 Cue: MAX AVAILABLE FLOW INDICATED SAT UNSAT 5 Comments: l 4 0821037a, Rev 02 . Page 13 of 18 I
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l 4 i JOB PERFORMANCE MEASURE i l
- 1 END Element / Step TERMINATION Standard: This JPM is complete when once-through-cooling is established and maximum safety injection flow to the RCS is
- verified.
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4 J i 0821037a, Rev 02 . Page 14 of 18 i, ! _ _ _ _ _ .:, . . ~ . . ._. - . _ . . . _ . , - _ _ _ _ --- -
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'.6 JOB PERFORMANCE MEASURE Knowledge Questions Question #1. 4 KA: K1.08 Importance: 3.613.9 j
Reference:
P &lD 8770-G-078,130A,120B i Question: Describe the flowpath (using P&lDs) of the first alternate method of Hot Leg injection use on Unit 1. Expected Response:The 1 A HPSI pump discharging to the charging header and through the auxiliary spray line to the pressurizer. SAT UNSAT i , Comments: i Question # 2. 1 KA: K6.03
- /mportance
- 3.6/3.9
Reference:
P&lD 8770-G-078,130A,120B Question: How could hot leg injection be accomplished if the 1 A HPSI was unavailable for use? Explain. ] Expected Response: It cannot. The 1B HPSI does not have a crossconection to the CVCS system. SAT UNSAT Comments: i 4 0821037a. Rev 02 Page 15 of 18 -
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i I
JOB PERFORMANCE MEASURE 3 l Provide this page to the Candidate 4 4
- Describe the flowpath (using P&lDs) of the first alternate method of Hot Leg Injection
- use on Unit 1.
? l Reference Allowed i i a v 4 i i j l $ r a i 0821037a, Rev 02 Page 16 of 18 i
1 l 1 JOB PERFORMANCE MEASURE Provide this page to the Candidate 1 How could hot leg injection be accomplished if the 1 A HPSI was unavailable for use?
! Explain.
1 1 Reference Allowed l 1 1 l i l i 1 [ l' 0821037a, Rev 02 Page 17 of 18 t w v. - 1, d. . ,.$_.- _-._________________________________..__.______._._i_".
I JOB PERFORMANCE MEASURE Provide this page to the Trainee Initial Conditions: A Total Loss of Feedwater event has been diagnosed and is in progress on Unit 2. All attempts to restore main and auxiliary feedwater have been unsuccessful and steam generator levels are indicating 15% on wide range indication. Initiating Cue: The ANPS has directed that once-through-cooling be established. LAW 2-EOP-15, RCS and Core Heat Removal, Success Path 4 l 0821037a, Rev 02 Page 18 of 18
l i i 1 This JPM for NRC Exam Use Only FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure PLACE LOW TEMPERATURE OVERPRESSURE PROTECTION IN SERVICE- UNIT 2 0821020, Rev 09 l SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO System: Pressuizer Pressure Control System Safety Function: 03
Reference:
NOP-2-0030127, Reactor Plant Cooldown-Hot Standby to Cold Shutdown Task: Perform lineup on the pressurizer pressure relief system (' Developed / Revised by: T'm Bolander / Approved by Training Supervision: / I l Reviewed by Instructor: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. .
4 JOB PERFORMANCE MEASURE Department: Operations l Task
Title:
PLACE LOW TEMPERATURE OVERPRESSURE PROTECTION IN SERVICE - UNIT 2 JPM No.: 0821020, Rev 09 Trainee: ! Evaluator l An X below indicates the applicable method (s) of testing that may be us. Perform Simulate Estimated Time to Complete the JPM: 10 MINUTES Location of Performance: CONTROL ROOM UNIT 2 / SIMULATOR Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
t 0821020, Rev 09 Page 2 of 12
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4 i
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JOB PERFORMANCE MEASURE READ TO THE TRAIMEE
. You are to perfonn/ simulate this task.
- The task you are to perform / simulate is:
PLACE LOW TEMPERATURE OVERPRESSURE PROTECTION IN SERVICE - UNIT 2
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
. Before starting i vrill state the task standards and initiating cues and answer any questions you have. ,
- When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected '
immediately prior to continuing the JPM. General / Initial Conditio.ns: Unit 2 is in the process of a plant cooldown in preparation for a refueling outage. RCS temperature is < 240 F and annunciators H-34 and H-35,PORV1474(1475)LTOP CONDITION - SELECT LTOP are in alarm. Tools and Eouioment: NONE Safety Considerations: In accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): In order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ol-5-PSL-1. B. Locate and operate all plant equipment correctly. P 0621020. Rev 09 Page 3 or 12 .
r i l JOB PERFORMANCE MEASURE C. The system / equipment status reflects the overallintent of what the JPM required l upon completion. D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of , Off-Normal Operating Procedure immediate actions will be from memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. 1 Initiatino Cue (s): The ANPS has directed that LTOP be placed in service IAW NOP-2-0030127, Reactor Plant Cooldown-Hot Standby to Cold Shutdown
References:
NOP-2-0030127 rev.12
. During the performance of the task I will tell you which steps to simulate or discuss.
. Verbalize each step before you do it. This gives you a chance to self-check and use i STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for i
verification.
. I will provide you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
. Do you understand these directions?
. If you have any questions, ask them now, and I will answer them.
. During the test I cannot answer questions.
. When you complete all steps correctly, you will pass this job performance measure.
. Begin the task now. <
o821020, Rev 09 Page 4 of 12
l JOB PERFORMANCE MEASURE , (C) Indicates a Critical Step PERFORMANCE CHECKLIST l 1. Perform the following for V1474, PORV
- A. ElemenUStep: Verify Annunciator H-30, "PORV 1474 LTOP CONDTN SELECT LTOP"is in alarm Standard: Verifies Annunciator H-30 is in alarm Cue: ANNUNCIATOR H-30 ILLUMINATED B. ElemenUStep: Verify Annunciator H-43,"LTOP CHNL A TRANSIENT"is not in alarm Standard: Verifies Annunciator H-43 is not in alarm Cue: ANNUNCIATOR H-43 NOT ILLUMINATED (C) C. ElemenUStep: CLOSE V-1476, PORV Block Valve Standard: Places the control switch for V-1476 to the CLOSE position Cue: V-1476 INDICATES GREEN LIGHTS (c) D. ElemenUStep: PLACE the PORV mode select switch for PORV 1474 in the LTOP position.
Standard: Places the control switch for V-1474 in the LTOP position. Cue: PORV 1474 CONTROL SWITCH IN LTOP E. ElemenUStep: Verify V-1474 did not open Standard: Observes indication for V-1474 (lights) Cue: V-1474 INDICATES GREEN LIGHTS (C) F. Element / Step: OPEN V-1476, PORV Block Valve Standard: Places the control switch for V-1476 to the OPEN position Cue: V-1476 INDICATES RED LIGHTS SAT UNSAT Comments: 0821020. Rev 09 Page 5 of 12
JOB PERFORMANCE MEASURE i (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 2. Perform the following for V-1475, PORV A. Element / Step: Verify Annunciator H-38, "PORV 1475 LTOP CONDTN SELECT LTOP"is in alarm Standard: Verifies Annunciator H-38 is in alarm ANNUNCIATOR H-38 ILLUMINATED Cue:
i B. Element / Step: Verify Annunciator H-47, "LTOP CHNL B TRANSIENT"is not in alarm r Standard: Verifies Annunciator H-47 is not in alarm 1 Cue: ANNUNCIATOR H 47 NOT ILLUMINATED (C) C. ElemenUStep: CLOSE V-1477, PORV Block Valve Standard: Places the control switch for V-1477 to the C' LOSE position (V-1477 MAY ALREADY BE CLOSED) Cue: V-1477 INDICATES GREEN LIGHTS 4 (c) D. Element / Step: PLACE the PORV mode select switch for PORV 1475 in the LTOP position. Standard: Places the control switch for V-1475 in the LTOP position. l Cue: PORV 1475 CONTROL SWITCH IN LTOP E. Element / Step: Verify V-1175 did not open Standard: Observes indication for V-1475 (lights)
- Cue
- V-1475 INDICATES GREEN LIGHTS (C) F. Element / Step: OPEN V-1477, PORV Block Valve Standard: Places the control switch for V-1477 to the OPEN position Cue: V-1477 INDICATES RED LIGHTS.
SAT UNSAT Comments: 0821020, Rev 09 Page 6 of 12 1
d JOB PERFORMANCE MEASURE I (C) Indicates a Critical Slep PERFORMANCE CHECKLIST NOTE: LEAKAGE IS INDICATED BY ACCOUSTIC MONITOR ALARM. CANDIDATE MAY ' ISOLATE V 1475 IMMEDIATELY OR REFER TO ONOP 2-0120036, " PRESSURIZER AND SAFETY VALVE"
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(C) 3 Element / Step: If V-1475 indicates flow, then close PORV block valve V-1477 and verify temperature decrease on TIA-1106.(candidate may check accustic monitor instead) Standard: Places the control switch for V-1477 to the CLOSE position and verifies temperature decrease on TIA-1106 and/or no flowindicated on Accustic Monitor. Cue: V-1477 INDICATES GREEN LIGHTS, NO RED LEDS INDICATED ON ACCUSTIC MONITOR AND/OR TIA 1106 TEMPERATURE TRENDING LOWER END Element / Step TERMINATION Standard: LTOP is established, annunciators H-34 and H-38 are extinguished AND V1477 is closed. SAT UNSAT Comments: I 1 l 1 0821020, Rev 09 . Page 7 of 12 l l
a I 1 1 JOB PERFORMANCE MEASURE Knowledge Questions Question #1. KA: 0102.03 ' Importance: 2.8/3.0
Reference:
None Question: How are the indications for PORV position and tailpipe temperature different between Unit 1 and Unit 27 , Expected Response: Unit 2 has separate tailpipe temperature indications for each PORV, Unit 1 has one common temperature indication for both; Unit 2 PORV light indication is provided by limit switches (positive valve position), Unit 1 lights indicate whether or not the solonoid is energized, , not valve position. . SAT UNSAT t Comments: Question # 2. KA: 010K5.02 , importance: 2.6/3.0
Reference:
Steam Tables Question: The RCS is at 2250 psia, Quench tank pressure is 3.5psig. If a smallleak developed in the seat of Code Safety V 1201, what temperature would you expect to see on TIA-1107? i Expected Response: 230 degrees Comments: L 1 1 r 0821020, Rev 09 Page B of 12 I k
l JOB PERFORMANCE MEASURE Provide this page to the Candidate l Initial Conditions-Unit 2 is in the process of a plant cooldown in preparation for a refueling outags. ; RCS temperature is < 240 F and annunciators H-34 and H- l 35,PORV1474(1475)LTOP CONDITION - SELECT LTOP are in alarm. l Initiating Cue-l The ANPS has directed that LTOP be placed in service IAW NOP-2-0030127, ! I Reactor P.lant Cooldown-Hot Standby to Cold Shutdown r i Page 9 of 11 L
l JOB PERFORMANCE MEASURE Provide this page to the Candidate How are the indications for PORV position and tailpipe temperature different between Unit 1 and Unit 27 No Reference l l l Page 10 of 11 l
. 1 i
i l l JOB PERFORMANCE MEASURE i Provide this page to the Candidate ! l l 4 The RCS is at 2250 pt;ia, Quench tank pressure is 3.5psig. If a small leak developed in the seat of Code Safety V 1201, what temperature would you expect to see on TIA-11077 Reference allowed f 1 Page 11 of 11 ; i
1 l REVIStoN No.: PRCOEDURE TrTLE: PAGE:
]
12 REACTOR PLANT COOLDOWN - PRoCEoVRE NO.: HOT STANDBY TO COLD SHUTDOWN 24 of 79 OPERATIONS PROCEDURE , NOP-2-0030127 ST. LUCIE UNIT 2 l I
7.0 INSTRUCTIONS
(continued) _ CAUTION Do NOT reduce RCS temperature below 240 F until both LTOP channels are demonstrated to be operable. 7.31 Prior to decreasing RCS temperature below 240 F, ensure a channel functional test has been performed on the PORV actuation. channels in accordance with l&C Procedure 2-1200054, " Low Temperature Overpressure Protection Setpoint Verification." (NOT required if performed within the previous 31 days.) ANPS CAUTION Do NOT reduce RCS temperature below 230 F until both PORVs have been placed in the LTOP mode. 7.32 When RCS temperature is less than 240 F, Annunciators H-34, "PORV V1474 LTOP Condtn Select LTOP," and H-38, "PORV V1475 LTOP Condtn Select LTOP," will alarm. As each annunciator alarms, place each PORV in the LTOP mode as follows:
- 1. Perform the following for V1474, "PORV":
A. Verify Annunciator H-34, "PORV V1474 LTOP Condtn Select LTOP" is in alarm. l' B. Verify Annunciator H-43, "LTOP Chnl A Transient," is NOT in alarm. C. CLOSE V1476, "PORV Block Valve." D. PLACE the PORV Mode Select switch for PORV V1474 in the LTOP position. E. Verify V1474, "PORV," did NOT open. F. OPEN V1476, "PORV Block Valve." i
REVISION NO.: ' PRCOEDURE Tm.E: PAGE: 12 REACTOR PLANT COOLDOWN - eRoceouRe no.: HOT STANDBY TO COLD SHUTDOWN 25 of 79 OPERATIONS PROCEDURE NOP-2-0030127 ST. LUCIE UNIT 2
7.0 INSTRUCTIONS
(continued) 7.32 (continued)
- 2. Perform the following for V1475, "PORV":
A. Verify Annunciator H-38, "PORV V1475 LTOP Condtn Select LTOP" is in alarm. B. Verify Annunciator H-47, "LTOP Chni B Transient," is NOT in alarm. C. CLOSE V1477, "PORV Block Valve." D. PLACE the PORV Mode Select switch for PORV V1475 in the LTOP position. i E. Verify V1475, "PORV," did NOT open. F. OPEN V1477, "PORV Block Valve."
- 3. Perform testing of PORVs V1474 and V1475 in accordance with Data Sheet 24, " Valve Testing Procedures" of OP-2-0010125A, " Surveillance Data Sheets."
CAUTION Motor Stator Temperatures of the operating RCPs should be closely , monitored as RCS temperature decreases. Stator temperature shall be maintained below 250 F. 7.33 Continue to operate the RCPs in conjunction with SDC to cool down the Steam Generators. l
REVIStoN No.: PROCEDURE TITLE: PAGE: ; I' 10 PRESSURIZER RELIEF / SAFETY VALVE PROCEoVRE NO.: 5 of 8 OFF-NORMAL OPERATING PROCEDURE 2-0120036 ST. LUCIE UNIT 2 1 7.0 OPERATOR ACTIONS: (continued) 7.2 (continued) INSTRUCTIONS CONTINGENCY ACTIONS
- 1. (continued) 1. (continued)
B. (continudd)
! 4. Quench tank 3
parameters. C. g PORVs start to show C. signs of leakage as indicated by either tailpipe temperature greater than i 210 F or tailpipe temperature greater than ' 190 F and other parameters indicate leakage (i.e., Quench Tank or acoustic parameters), Then
- . PERFORM the following as necessary :
l 1. H V-1474 indicates 1. If PORV leakage can flow, Then close NOT be isolated, Then: I PORV block valve V-1476 and verify a. Calculate RCS leak temperature decrease rate to determine i on TIA-1110. action required by Technical OR Specifications. j
- 2. If V-1475 indicates b. Refer to 2-0120031, flow, Then close " Excessive Reactor PORV block valve Coolant System l
V-1477 and verify Leakage" for temperature decrease additional guidance. on TIA-1106. I i i t______________._ _
. . . _ _ ~ . . - .- - . . . . . . -
REVISloN NO.: PROCEDURE TITLE: PAGE: 10 PRESSURIZER RELIEF / SAFETY VALVE 6 of 8 ! PROCEDURE No.: OFF-NORMAL OPERATING PROCEDURE 2-0120036 ST. LUCIE UNIT 2 ! I 7.0 OPERATOR ACTIONS: (continued) 7.2 (continued) l
- INSTRUCTIONS CONTINGENCY j ACTIONS j 1
- 1. (continued) 1. (continued)
! D. Place the attemate PORV in service if available. , E. H PORV position indication E. is :ost, Then PERFORM ] the following as 1 ne::essary: i l 1. H V-1474 position 1. H PORV leakage is indication is lost, Then indicated, Then: monitor quench tank
- a. Refer to Step 7.2.1.C
.i level, pressure and temperature, and above, monitor temperature on TIA-1110 for indications of leakage. OR
- 2. H V-1475 position indication is lost, Then monitor quench tank level, pressure and temperature, and monitor temperature on TIA-1106 for indications of leakage.
- 3. Document quench tank parameters and tailpipe reading on D.S. #30 of NOP 2-0010125 every eight hours.
r 3 i This JPM For NRC Exam Use
@FPL j
Only j St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure POSIT!ON REACTOR COOLANT GAS VENT SYSTEM CONTROLS - UNIT 1 0821090, Rev 03 SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability RO, SRO System: RCS Safety Function: 02 d
Reference:
ONP 10120037," Reactor Coolant Gas Vent System Off-Normal Operation" Task: Perform lineups on the RCS Developed / Revised by: Tim Aninnebr / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision.
e JOB PERFORMANCE MEASURE Department: Operaticns Task
Title:
POSITION REACTOR COOLANT GAS VENT SYSTEM CONTROLS - UNIT 1 JPM No.: 0821090, Rev 03 Trainee: Evaluator: An X below indicates then applicable method (s) of testing that may be used: Perform __ Simulate Estimated Time to Comolete the JPM: 15 MINUTES Location of Performance: CONTROL ROOM UNIT 1 Notes to the Evaluator: 4
- Pull the latest controlled copy of the applicable procedure
- The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
d
- Notify a Management Observer of the observation opportunity.
0821090, Rev 03 Page 2 of 10
9 JOB PERFORMANCE MEASURE READ TO THE TRAINEE
. You are to perform / simulate this task.
. The task you are to perform / simulate is:
POSITION REACTOR COOLANT GAS VENT SYSTEM CONTROLS - UNIT 1
. I will describe the general conditions and tell you the tools and equipment ' required to f perform / simulate this task. ,
- - Before starting I will state the task standards and initia ing cues and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
2
+ Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / initial Conditions: A Unit 1 LOCA has occurred and formed a non-condensible gas bubble in the Reactor Vessel Head. Pressurizer Level has been recovered and is currently at eighty per cent (80%) with Pressure at 650 psia. The Subsequent Actions of ONP 1-0120037 have been completed up to the point of venting. The void has been determined to be approximately 800 cubic feet (and the maximum vent time has been calculated to be t thirty one (31) minutes.) NOTE: SRO Candidates will be required to calculate vent time Tools and Eauioment: NONE Safety Considerations: In accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): i In order for this job perfor; nance measure to be satisfactorily completed, accomplish this JPM in accordance witP the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality 0821090. Rev 03 Page 3 of 10 l
4 i JOB PERFORMANCE MEASURE ; Instruction Ql-5-PSL-1. 8, Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overall intent of what the JPM required upon completion. D. Correctly perform all critical steps. ; All steps where procedural guidance exists may be considered critical. Performance of
~ Off-Normal Operating Procedure immediate actions will be from memory.
During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to mcke decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. " Initiatina Cue (s): The ANPS has directed you to(determine venting time and) commence venting the ! Reactor Vessel Head to Containment IAW ONP 1-0120037. NOTE: SRO Candidates will be required to calculate vent time
References:
ONP 1-0120037, Rev. 02
. During the performance of the task I will tell you which steps to simulate or discuss.
+ Verbalize each step before you do it. This gives you a chance to self-check and use t STOP during the performance of each task element.
- Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for .
verification. { ! - I will provide you with the appropriate cues for steps which are simulated or discussed.
- You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
~
l
. Do you understand these directions?
if you have any questions, ask them now, and I will answer them. ; l- - During the test I cannot answer questions. !
- When you complete all steps correctly, you will pass this job performance measure.
0821090. Rev 03 Page 4 of 10 t r k i n
a B JOB PERFORMANCE MEASURE
. Begin the task now.
i 0021090, Rev 03 Page 5 of 10
F JOB PERFORMANCE MEASURE (C) Indicates a Critical E.tep PERFORMANCE CHECKLIST
- 1. (C) Element / Step C ommence venting as follows:
A. Open V1442 to vent reactor vessel head. Standard: At CRAC, POSITION the key switch for V1442 to OPEN Cue: RED LIGHT ON, GREEN LIGHT OFF B. Open V1446 (Containment Isol) to commence venting. , Standard: At CRAC, POSITION the key switch for V1446 to OPEN Cue: RED LIGHT ON, GREEN LIGHT OFF SAT UNSAT Comments:
- 2. Element / Step Monitor time elapsed, Pressurizer pressure and level, RCS subcooling.
Standard: DETERMINE if continued venting criteria is satisfied Cue: ELAPSED TIME IS 27 MINUTES, PRESSURIZEJ. PRESSURE HAS DECREASED 120 PSIG, PRESSURIZER LEVEL IS 40%, RCS CET SUBCOOLING IS 30 F, OSPDS INDICATES NO SEGMENTS VOIDED, THE RATE OF CHANGE IN PRESSURIZER LEVEL AND PRESSURE
- HAS DECREASED.
NOTE - THE STUDENT SHOULD RECOGNIZE THAT VENT TERMINATION IS REQUIRED AFTER *'QSPDS INDICATES NO SEGMENTS VOIDED". SAT UNSAT Comments: 1 i 0821090, Rev 03 Page 6 of 10
-. . - .~ . . . .. . - . -
],
l l JOB PERFORMANCE MEASURE i (C) Indicates a Critical Step PERFORMANCE CHECKLIST - l 4 1
- 3. (C) Element / Step Terminate venting.
NOTE - STEP SEQUENCE IS NOT SPECIFIED BY PROCEDURE, BUT BOTH VALVES MUST BE CLOSED FOR THIS STEP TO BE SATISFIED. i Standard: At CRAC, POSITION key switch for V1442 to CLOSED Cue: GREEN LIGHT ON, RED LIGHT OFF Standard: At CRAC, POSITION key switch for V1446 to CLOSED Cue: GREEN LIGHT ON, RED LIGHT OFF J SAT UNSAT Comments: i END Element / Step TERMINATION Standard: THIS JPM IS COMPLETE WHEN THE OPERATOR VERIFIES THE VENT LINEUP IS SECURED. s 0821090, Rev 03 Page 7 of 10
. 1 I
1 JOB PERFORMANCE MEASURE I Knowlodge Questions I I J Question #1. KA: 002K6.04 Importance: 2.512.9
Reference:
P&lD 8770-G-078 sheet 107 Question: While venting to the containment,125 VDC Instrument Bus "A"is lost. Can venting continue? Explain. Expected Response: Yes, but not to Containment atmosphere. The Reactor Coolant Gas Vent System (RCGVS) has two parallel vent paths from the Reactor head and the pressurizer. With the loss of the 'A' DC Bus, the 'A' side valves will fail closed. the 'B' side valves can be used as the vent path. Venting can be directed to either the Quench tank or the Accumulator. SAT UNSAT Comments: i k l l 3 6 b 0821090, Rev 03 Page 8 of 10 4
. . . . 4
JOB PERFORMANCE MEASURE l l Question # 2. j l KA: 002K1.04 : Impcriance: 2.8/3.2 : Reference allowed (2-EOP-3) : Question: Given the Pressurizer trend below, state whether the non-condensible void existed in 1) The RV head, or 2) in the S/G U-tubes. Justify your answer. (Assume one Charging Pump ' is operating, letdown is isolated, no RCPs are running and the cooldown was secured.) Trend: When the head vent was opened, Pzr Level initially decreased rapidly, then started increasing slowly. Expected Response: RV Head. When the vent is opened the non-condensible gases escape allowing the head area to re-flood. When the head has refilled, level began increasing slowly due to the restriction in the vent path limiting the water release rate to less than the capacity of one charging pump. If the non-condensibles were in the S/G U-tubes, opening the vent would cause only water from the head to be discharged and level would have gone up slowly from the beginning. (Answer should be similar to the above paragraph) SAT UNSAT Comments: i i s 0821090, Rev 03 Page 9 of 10 __.__.______: _____.___._____.___1
JOB PERFORMANCE MEASURE Provide this page to the RO Candidate initial Conditions: A Unit 1 LOCA has occurred and formed a non-condensible gas bubble in the Reactor Vessel Head. Pressurizer Level has been recovered and is currently at eighty per cen':(80%) with Pressure at 650 psia. The Subsequent Actions of ONP 1-0120037 have been completed up to the point of venting. The void has been determined to be approximately 800 cubic feet and the maximum vent time has been calculated to be thhty one (31) minutes. Initiating Cue: The ANPS has directed you to commence venting the Reactor Vessel Head to Containment IAW ONP 1-0120037, step 5.3.14 I t i w Page 10 of 10
JOB PERFORMANCE MEASURE Provide this page to the SRO Candidate initial Conditions: A Unit 1 LOCA has occurred and formed a non-condensible gas bubble in the Reactor Vessel Head. Pressurizer Level has been recovered and is currently at eighty per cent (80%) with Pressure at 650 psia. The void has been determined to be approximately 800 cubic feet. Containment pressure is 35 psia, Containment temperature is 258 F. Containment hydrogen concentration is 2.2% initiating Cue: The ANPS has directed you to determine venting time and then commence venting the Reactor Vessel Head to Containment IAW ONP 1-0120037, step 5.3.14 i I I I l Page 11 of 10 1
v I JOB PERFORMANCE MEASURE l 1 Provide this page to the Candidate 1 I l While venting to the containment,125 VDC Instrument Bus "A"is lost. Can venting l continue? Explain. Reference allowed f Page 12 of 10
JO3 PERFORMANCE MEASURE Provide this page to the Candidate Given the Pressurizer trend below. state whether the non-condensible void existed in 1) l The RV head, or 2) in the S/G U-tubes. Justify your answer. (Assume one Charging Pump is operating, letdown is isolated, no RCPs are running and the cooldown was secured.) Reference allowed I t, , i 1
}
Page 13 of 10 l J
Page 1 of 13 rein;K g......_.__., i fl' j !o i FLORIDA POWER & LIGHT COMPANY " -y Fi ST. LUCIE UNIT 1 '
,M! ; 3'O' F F-NORMAL OPERATING PROCEDURE NO. 1-0120037 ,
I ' T"7 7-' : "
*.s.<
i REVISION 2 % l
- 1.0 TITLE
- ,
1 J REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION 2.0 REVIEW AND APPROVAL: j j Reviewed by Facility Review Group March 30,19 84 ' Approved by C. M. Wethy Plant Manager April 2,19 84 Revision _2f:eviewed by FRG /-/'7 aoc/ /-J V 19_f_Z Approved by G. J. Boissy Plant Manager 4 -. /, 19_ff,
)
THIS PROC:EDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING. /R2 3.0 PURPOSE AND DISCUSSION: 3.1 The purpose of this procedure is to provide a method of venting non-
) condensible gases from the Reactor Coolant System (RCS) which may inhibit core cooling during natural circulation.
3.2 Guidance an'd precautions are also provided for use in determining the size of the non-condensible void formation, when to initiate venting, and termination of venting operations. g 4.0 SYMPTOMS:
)
4.1 Abnormal RCS conditions such as large variations in Pressurizer level during normal charging and spraying operations have occurred. (Note this could also be an indication of a steam void in the Reactor Vessel head). l 4.2 Reactor vessel level display <100% and reactor vessel head temperature 2 ) saturation temperature, as indicated by Ouality Safety Parameter Display ; System (OSPDS). 4.3 Plant events have occurred (such as safety injection S 1 OPS
- tank [ SIT) discharge, rapid RCS cooldown, or core l uncovery events) that may result in the presence of a DATE l gasecus void in the vessel head.
00{ PROCEDURE g SYS
) COMP COMPLETED ITM 2 l
i
?
Page 2 of 131 ST. LUCIE UNIT 1 ls j 'j OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2
) REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION s: (
). !
2
4.0 SYMPTOMS
(continued) E-2r.:
>l 4.4 Loss of Pressurizer pressure control during normal Pressurizer condltions (i.e.,
bubble established, normal heaters / spray capabilities).
) )
6
Page 3 of 13 / ' f ST. LUCIE UNIT 1 9 OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 l
) REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION d f
5.0 INSTRUCTION.S_: I i. 5.1 Immediate Automatic Actions: None 5.2 Immediate Operator Actions: None 5.3 Subseauent Operator Actions: NOTE This venting procedure should be used ss the primary means to mitigate an
) inadequate core cooling event. .
NOTE Venting operations should be performed prior to the initiation of safety injection flow throttling during a Post-LOCA cooldown and depressurization. During venting " full flow" Safety injection capabilities must be maintained if
) needed. Steps marked by (*) are not applicable if safety injection has been initiated.
CAUTION DO NOT TRIP ANY RUNNING OR START ANY NON-OPERATING REACTOR COOLANT PUMPS DURING VENTING OPERATIONS.
) 1. If any of the above listed symptoms have occurred or it is suspected that there is a non-condensible void formation present in the RCS by other detection means, then any changes being made to the primary system should be terminated and a steady state condition established.
NOTE Sources of non-condensible gases are listed in the Fact Sheet attached to this procedure. .
~
- 2. Attempt to recombine any condensible gases by increasing RCS pressure through the use of Pressurizer back-up heaters. If this step is successful in condensing the gas volume in the vessel head (as indicated by a return to normal readings in those parameters used to determine the presence of J the gases) then return to the appropriate operating procedures.
)
Page 4 of 13 ST. LUCIE UNIT 1 OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 9
?
. REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION l ,
)
5
5.0 INSTRUCTIONS
(continued) I ! := 3 5.3 (continued) ' i j ~
- 3. Coordinate with appropriate on-site technical resources. (Technical Support Center [TSC] Supervisor if manned; Chemistry Department i representative if TSC is not manned).
1 !
- 4. Determine the recommended venting time required per Appendix A, if
, possible. i j , NOTE l Apperidix A " Venting Time Period" determines the maximum allowable time period for venting which will limit the Containment hydrogen concentration to ! ) < 3 volume percent.
- 5. Increase the RCS sub-cooling to at least 50 F by either pressurizing via Pressurizer Backup heaters or decreasing RCS temperature via dumping ,
, steam.
'J
- 6. Terminate Containment purge, if in progress. Start all available
= a Containment Fan Coolers,
- NOTE
- Containment purge should be isolated to prevent the release of any
] radioactive gases to the environment. { ) 7. Ensure that all available Hydrogen Recombiners are in service. i i NOTE i All available Containment air circulation equipment should be started to prevent any hydrogen from forming a gas pocket and to ensure a representative hydrogen concentration is obtained during sampling, i
- 8. Verify that Chemistry Department is pre' pared for monitoring the Containment atmosphere for hydrogen via the hydrogen analyzer and/or, grab sample.
- 9. Increase Pressurizer level to 80-85% in preparation for venting. This should provide inventory to displace approximately 900 ft3 before reaching pressurizer heater level.
1 Page 5 of 13 J' ST. LUCIE UNIT 1 s OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 !
) REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION j
5.0 INSTRUCTIONS
(continued) , 6 5.3 (continued)
- 10. If not already performed, manually block SIAS if the permissive is energized during the venting process.
- 11. Monitor Pressurizer pressure and level and OSPDS reactor vessel display during the venting period. Minimize the pressure and level decrease by selective use of Charging Pump combinations and letdown flow.
- 12. Destination of the gas when venting is optional. The decision as to which is used should be based on quantity of gas to be released. If recovery and processing to the Waste Gas System is desired, then vent to the
') Quench Tank. If thb quantity is large, then vent to containment atmosphere or via the accumulator to the ventilation system.
CAUTION UNDER NO CIRCUMSTANCES SHOULD BOTH VENT VALVES IS THE VENTING FLOWPATH BE POWERED FROM THE SAME ELECTRICAL TRAIN. THE REACTOR VESSEL HEAD AN PRESSURIZER SHOULD NOT
) .
BE VENTED SIMULTANEOUSLY.
- 13. Observe the Pressurizer level trend during the reactor vessel venting and, from the following conditions, determine the probable status of the RCS:
A. Controllable Pressurizer level - gaseous voids exist in the RCS other than the reactor vessel head or Pressurizer. The orifice in the head vent is sized to limit water relief to within the make-up capability of one Charging Pump (44 GPM @ 2250 psla). Therefore, if no gases are present in the vessel head, then the Pressurizer level should remain controllable. B. Decreasina pressurizer level- gaseous voids exist in the reactor vessel head. The venting of gases will result in a rapid decrease in Pressurizer , level due to the mass flow rate of the gases being greater than the ; mass input being provided by the Charging System.
)
Page 6 of 13 g ,
. ST. LUCIE UNIT 1 i' OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 3
) REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION l
5.0 INSTRUCTIONS
(continued) , 5.3 (continued) . CAUTION IF PRESSURIZER LEVEL DECREASES TO <20%, THEN ATTEMPT TO RESTORE LEVEL BY THE CVCS SYSTEM (ISOLATE LETDOWN, ' MAXIMUM CHARGING). IF LEVEL CANNOT BE RESTORED, THEN MANUA'_LY INITIATE SAFETY INJECTION.
- 14. Commence venting as follows:
A. Venting Pressurizer or reactor vessel head to Containment.
) Open V-1444 to vent Pressurizer, or Open V-1442 to vent reactor vessel head.
Open V-1446 (Containment isol) to commence venting.
) B. Venting Pressurizer or reactor vessel head to Quench Tank.
Open V-1443 to vent Pressurizer, or Open V-1441 to vent reactor vessel head. Open V-1445 (Quench Tank isol) to commence venting.
) C. Venting Pressurizer or reactor vessel head to accumulator.
Open V-1443 to vent Pressurizer, or Open V-1441 to vent reactor ves.cel head. Open V-1449 (Accumulator isol) to commence venting. I
Page 7 of 13 ST. LUCIE UNIT 1 i OFF NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 ' i
) REACTOR COOLANT GAS VENT SYSTEM OFF NORMAL OPERATION .
a
5.0 INSTRUCTIONS
(continued) { i 6, 5.3 (continued) i
- 15. Terminate venting when
A. TIME PERIOD DETERMINED IN STEP 5.3.4 IS MET, , i OR , j B. PRESSURIZER PRESSURE DECREASES BY 200 PSI, l OR C. PRESSURIZER I.EVEL DECREASES BELOW 25% LEVEL, J
- OR
! D. REACTOR COOLANT SUB COOLING LESS THAN 20 F i ! OR
)
E. THE REACTOR VESSEL HEAD IS REFILLED AS INDICATED BY ' QSPDS REACTOR VESSEL LEVEL DISPLAY. ,
- 16. Re-establish Pressurizer level and evaluate the response of the Pressurizer level trend to determine if a gas bubble existed in the head if a gas bubble existed and the venting was terminated prior to the vessel being completely refilled, then return to Step 5.3.12.
NOTE If multiple venting operations are required and the Containment hydrogen ' concentration is 2 3 volurne percent, then provisions must be made to remove or reduce the volume of hydrogen from the Containment prior to re-opening the reactor vessel head vent.
- 17. Return to the appropriate operating procedures following successful completion of the venting of the reactor vessel head. ,
l
..) :
i
+
_ . . . . .. __ . . _ . . _ _ _ . . m . . _ . _ _ . _ _ _ . _ _ _ _ _ . _ . . . ._ _ _ . . l Page 8 of 13 4 ST. LUCIE UNIT 1 % ' OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 s 1
) REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION l
) >
6.0 REFERENCES
- l l L
C-E " Final Report on the Reactor Coolant Gas Vent System". ; ) 7.0 RECORDS: i Completed Appendix A work sheet shall be maintained in the plant files in j accordance with Ol-17-PR/PSL-1, " Quality Assurance Records". 4 i s
- I '
! ) 1 i i i !, ) l )
) i J
4, [ ) < 6 t
. 1 I
l 1 l
Page 9 of 1 ST. LUCIE UNIT 1 f : OFF NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 g ! REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION - l 4
) !
t 5 APPENDIX A ! l VENTING TIME PERIOD < Page 1 of 3 NOTE ' ) During a core uncovery event, there exists the potential for a significant j amount of hydrogen to be generated in the reactor core which could be trapped in the reactor vessel and released to the Containment atmosphere during the venting operation. The Containment hydrogen concentration is a limited to <4 volume percent to prevent a potential explosive mixture with oxygen; therefore, the amount of hydrogen that can be vented to the .
- Containment is restricted. A maximum allowable time period for venting is
- determlied to limit the Containment hydrogen concentration.
)
NOTE
- This guide assumes that Containment conditions cre near normal.
- 1. Convert the Containment free-volume to Containment volume at standard
) temperature and pressure conditions as follows:
i 4
~ ^
Containment Pressurei y %2*R b #f@#"hTP f * ( .5 X to it') X 14.7 ' . . _Containmen! Temperature * , NOTE
) a. Delete term if Containment pressure is <2 PSIG.
- b. Temperature in degrees Rankine ( F + 460)
Containment Volume (ft @ STP) =
- 2. Determine Containment hydrogen concentration in volume percent units.
A. Obtain value from Chemistry Department. B. If there has been no leakage from the RCS into the Containment, assure a value of zero. C. Containment Hydrogen Concentration = % 1
Page'10 of 13 ST. LUCIE UNIT 1 E" i OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 i; REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION y
') [
i-APPENDIX A j I VENTING TIME PERIOD l Page 2 of 3 j 3. Calculate the maximum hydrogen volume that can be vented to the Containment j which will result in a Containment hydrogen concentration s 3 volume percent. Maximum Hydrogen Volume (ft') = (3.0% - Cont. H 2Conc & [ Step 2.C]) X (Cont. Vol. @ STP [ Step 1]) 100% Maximum Hydrogen Volume (ft') = . j -
- 4. Obtain from Curve #1 (next page) the hydrogen flow rate which will result at the predicted RCS pressure at time of venting.
)
A. Predicted RCS pressure = psia B. Hydrogen flow rate = SCFM
- 5. The maximum allowable venting time period which will limit the Containment
) hydrogen concentration to s 3 volume percent is determined by:
at a U e 9P M Venting period (min) , H2 Flowrato (Step 4] Venting period = minutes
s IO mm
>m O Z OO I I E
2500 T = 550*F O> Or
, T = 400* F I Oo
< O m T = 700* F 2000 -
$ Uy
@ m Oy Z m mg 55 ? O ~> N'g
-T - 250* F OO O 2 'O Zb"F 0_1500 m
c 2j m gj H o3 m H Z D m
> m< 1 gz gOg
" O m O m v> H g y 0
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5 tzc] Gy ee9e 9 o' 4 ST. LUCIE UNIT 1 : OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION ( j r I APPENDlX A i a!-e VENTING TIME PERIOD
- Page 1 of 3 NOTE q During a core uncovery event, there exists the potential for a significant a
amount of hydrogen to be generated in the reactor core which could be 3 trapped in the reactor vessel and released to the Containment atmosphere 4 during the venting operation. The Containment hydrogen concentration is limited to <4 volume percent to p_revent a potential explosive mixture with , , oxygen; therefore, the amount of hydrogen that can be vented to the Containment is restricted. A maximum allowable time period for venting is determined to limit the Containment hydrogen concentration. i NOTE This guide assumes that Containment conditions are near normal.
- 1. Convert the Containment free-volume to Containment volume at standard
' ) temperature and pressure conditions as follows-(tf rn,m) k l2AIOSb X {'bS$2-)
~ ^
Containment Volume ContainmenEPressure*^ y 4M ft' @ STP = (2.5 X 10* tt') X 14.7 . ContainmentTemperature*_ 7/F 2 ) NOTE
) a. Delete term if Containment pressure is <2 PSIG.
j b. Temperature in degrees Rankine ( F + 460) Containment Volume (ft @ STP) = Y. / E
- 2. Determine Containment hydrogen concentration in volume percent units.
~
l A. Obtain value from Chemistry Department. j B. If there has been no leakage from the RCS into the Containment, assure a s value of zero. C. Containment Hydrogen Concentration = 22 %
) ,
4 f- w- - 3 - _ _ _ _ _ _ _ _ _ i _.___ _ _ __ _ ____.________ _ _ _.-___._._- ____ -_ _ ___ ______ _ m-_--
Page 10 cf 13 , ST. LUCIE UNIT 1 OFF-NORMAL OPERATING PROCEDURE NO. 1-0120037, REVISION 2 i REACTOR COOLANT GAS VENT SYSTEM OFF-NORMAL OPERATION l y ! } I APPENDlX A j VENTING TIME PERIOD i Page 2 of 3 1 4
- 3. Calculate the maximum hydrogen volume that can be vented to the Containment which will result in a Containtnent h dro en concentration s 3 volume pe(cent.
i 8 _ y ( L(. [ Y E b) 3 Maximum Hydrogen Volume (ft ) = (3.0% - Cont. H 2Conc.% [ Step 2.C)) X (Cont. Vol. @ STP [ Step 1]) i 100 % ! Maximum Hydrogen Volume (ft8 ) - 3- E , 1 ! 4. Obtain from Curve #1 (next page) th'e hydrogen flow rate which will result at the i predicted RCS pressure at time of venting. -
)
A. Predicted RCS pressure = 45~C psia B. Hydrogen flow rate = S rD - Trd SCFM I S. The maximum allowable venting time period which will limit the Containment hydrogen concentration to s 3 volume percent is determined by:
^)
i 3.2? g 4 Venting period (min) =
, Vlu e Step 3)
- H, Flowrate (Step 4) l Sn Venting period = 4/ minutes O
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l - " I O 4 i I,emm. .. --, u ; l____________________________________ ____ _ _ ___________________ -
6 1 This JPM For NRC Exam Use 9 FPL Only St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure RESPOND TO WIDE RANGE NI CHANNEL MALFUNCTION UNIT 1 0821036, Rev 07 SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability RO, SRO System: NIS Safety Function: 07
Reference:
ONOP 1-1210030, " Wide Range Nuclear Instrumentation Channel Malfunction" Task: Monitor the NIS Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision.
t JOB PERFORMANCE MEASURE Department: Operations Task
Title:
RESPOND TO WIDE RANGE Ni CHANNEL MALFUNCTION - UNIT 1 JPM No.: 0821036, Rev 07 Trainee: Evaluator An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 10 MINUTES Location of Performance: CONTROL ROOM UNIT 1 Notes to the Evaluator:
+
Pull the latest controlled copy of the applicable procedure
+
The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
+
Notify a Management Observer of the observation opportunity. 0021036, Rev 07 Page 2 of 10
f JOB PERFORMANCE MEASURE READ TO THE TRAINEE
. You are to perform / simulate this task.
The task you are to perform / simulate is: , RESPOND TO WIDE RANGE NI CHANNEL ' MALFUNCTION - UNIT 1
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task. !
. Before starting I will state the task standards and initiating cues and answer any questions you have. -
i When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
B
. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: ! Unit 1 is in a reactor startup at approximately 10-3 % power. Regulating group CEA withdrawal was in progress following the recording of critical data. The wide range NI l recorder suddenly indicated off-scale low and annunciator L-30 (Ni CHANNEL INOPERATIVE) illuminated. The operator stopped withdrawing CEAs and has stabilized l the power level. i Tools and Eauioment: t 1 L NONE : Safety Considerations: In accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): )- 4 0821036 Rev07 Page 3 of 10 , f
s ~ JOB PERFORMANCE MEASURE i ; in order for this job performance measure to be satisfactorily completed,' accomplish this JPM in accordance with the following standards: ; A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ol-5-PSL-1. ! . B. Locate and operate all plant equipment correctly. 1 < C. The system / equipment status reflects the overallintent of what the JPM required , upon completion. i D. Correctly perform all critical steps. ; ) All steps where procedural guidance exists may be considered critical. Performance of.
+ Off-Normal Operating Procedure immediate actions will be from memory.
I During the course of the JPM, there may be some tasks you will have to perform that will l require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatina Cuefst l l The ANPS has directed that the wide range NI probtem be diagnosed and addressed IAW ONP 1-1210030. l
References:
ONP 1-1210030, Rev 12 TECH. SPECS. 3.3.1.1,3.9.2
. During the performance of the task I will tell you which steps to simulate or discuss.
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification.
. ' I will provide you with the appropriate cues for steps which are simulated or discussed.
0821036. Rev 07 Page 4 of 10
JOB PERFORMANCE MEASURE
. You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
- Do you understand these directions?.
. If you have any questions, ask them now, and I will answer them.
- During the test I cannet answer questions.
. When you complete all steps correctly, you will pass this job performance measure.
. Begin the task now.
J i i l i-e i - 4 4 1 j.
- 0821036. Rev 07 Page 5 of 10
} [- _ . . -
JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 1. Element / Step Compare meter readings on all channels to determine the validity of the alarm / indication, Standard: Monitor channelindications on the RPS Cabinet local wide range drawer meters and/or wide range indications on RTGB-104 NOTE: THE WIDE RANGE RECORDER INPUT IS FROM THE SELECTED CHANNEL.
THE SELECTED CHANNEL IS THE ONE THAT HAS FAILED. ALL CUES MUST REFER TO THE SELECTED CHANNEL AS THE FAILED CHANNEL. Cue: THE SELECTED CHANNEL INDICATES DOWNSCALE SAT UNSAT Comments: 2.(C) Element / Step Place the failed channel high rate trip unit bistable in the bypassed or tripped condition , Standard: Using the appropriate key at the RPS cabinet, POSITION the hi rate trip l bypass key switch to the bypass position for the failed channel
- NOTE
- The operator should recognize the key must be logged out in the rack key log
, found in the ANPS office '
- Cue: IN BYPASS SAT UNSAT i l , Comments: 0821036, Rev 07 Page 6 of 10
4 JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST 3.(C) Element / Step Switch the wide range recorder and audio count rate (ifin the Start-Up or Shutdown modes) to the operable channel Standard: At RTGB-104, SELECT an alternate channel to display on the wide range NI recorder (JR-011) Cue: ALTERNATE WR NI CHANNEL SELECTED READING APPROXIMATELY 104 % POWER SAT UNSAT Comments: 4.(C) Element / Step Refer to Technical Specifications, Table 3.3-1 and section 3.9.2 to ensure compliance with all applicable actions Standard: Refer to Tech Spec 3.3.1.1 Table 3.3-1 (Functional Unit 11) , DETERMINE applicable action statement to be Action item 2. Refer to T.S. 3.9.2, DETERMINE not applicable (Mode 6 only) Cue: ACKNOWLEDGE T.S. 3.3.1.1 TABLE 3.3-1 ACTION ITEM 2 i APPLICABLE, T.S. 3.9.2 NOT APPLICABLE , SAT UNSAT Comments: 4 s 4 } l i 0821036, Rev 07 Page 7 of 10 , l l l
- I
-- - .. . - - -- = . .
i JOB PERFORMANCE MEASURE a PERFORMANCE CHECKLIST i i S. Element / Step Notify l&C Department as soon as practical. 1 Standard: CONTACT l&C to inform them of the failed channel wide range NI 4 > l ) NOTE: l&C SHOULD BE TOLD OF THE 48 HOUR REQUIREMENT TO TRIP THE ) AFFECTED CHANNEL LAW T.S. 3.3.1.1 ACTION 2 Cue: l&C ACKNOWLEDGES i SAT UNSAT ] Comments: i . END Element' Step TERMINATION i' Standard: This JPM is complete when the HI rate trip on RPS failed channel is in bypass, and l&C has been notified. i f i 0821036, Rev 07 Page 8 of 10 1 l l
JOB PERFORMANCE MEASURE Knowledge Questions Question #1. KA: 015K3.01 Importance: 3.9/4.3 Reference Allowed (CWDs) Question: At 100% power, with the "C" channel Hi SUR trip unit bistable pulled, is a trip signalin effect for this bistable? Explain. Expected Response: Yes. Although the actual SUR trip is bypassed at >_15% power, pulling of the bistable actually initiates its associated trip signal. SAT UNSAT Comments: Question # 2. KA: 015K4.03 Importance: 3.9/4.0 No Reference , Question: State the Nl channels that can be read at the Unit 1 and Unit 2 hot shutdown panels and the indications they provide. Expected Response: Unit 2 HSDCP has Appendix R Excore N1 indication (source range and startup rate) and A and B Wide Range Safety channelindication. Unit 1 has only Appendix R NI indication.(source range and startup rate) SAT UNSAT , 4
- Comments
i 0821036, Rev 07 Page 9 of 10 l l
JOB PERFORMANCE MEASURE Provide this page to the Candidate initial Conditions: Unit 1 is in a reactor startup at approximately 10 % power. Regulating group CEA withdrawal was in prcgress following the recording of critical data. The wide range NI recorder suddenly inclicated off-scale low and annunciator L-30 (NI CHANNEL INOPERATIVE)illum:nated. The operator stopped withdrawing CEAs and has stabilized the power level. Initiating Cue: The ANPS has directed that the wide range NI problem be diagnosed and addressed LAW ONP 1-1210030. I-ll 0821036. Rev 07 Page 10 of 10
JOB PERFORMANCE MEASURE - 1 Provide this page to the Candidate At 100% power, with the "C" channel Hi SUR trip unit bistable pulled, ;s a trip signal in effect for this bistable? Explain. Reference allowed s-Page 11 of 12
JOB PERFORMANCE MEASURE Provide this page to the Candidate State the Nt channels that can be read at the Unit 1 and Unit 2 hot shutdown panels and the indications they provide. No Reference 1 I 4 s Page 12 of 12
This JPM For NRC Exam Use Only FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure Locally Operate Unit 1 Atmospheric Dump Valve 0821053, Rev 03 [ SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job AppIlcability. RO, SRO System: Steam Dump and Turbine Bypass Control Safety Function: 04
Reference:
1-EOP-99, App. U. Task: Shift to and from various modes of SDS Developed / Revised by: Tim Aninnriar / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision.
JOB PERFORMANCE MEASURE Task
Title:
Locally Operate Unit 1 Atmospheric Dump Valve JPM No.: 0821053, Rev 03 Trainee: Evaluator; l An X below indicates the applicable method (s) of testing that may be used: Perform Simulate l Estimated Time to Complete the JPM: 20 Minutes Location of Performance: Steam Trestle Area Notes to the Evaluator: 1 l J
. Pull the latest controlled copy of the applicable procedure )
I
- The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee.
. Notify a Mant.sement Observer of the observation opportunity.
t 1 08210s3, Rev 03 Page 2 of 13
JOB PERFORMANCE MEASURE s READ TO THE TRAINEE You are to perform / simulate this task. The task you are to perform / simulate is:
. Locally Operate Unit 1 Atmospheric Dump Valve I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task. .
Before starting I will state the task standards and initiating cues and answer any ; questions you tave. When you perfcrm all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform tne steps in the correct sequence.
Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM. General / Initial Conditions T Unit 1 has just experienced a Loss of Offsite Power (LOOP), Instrument Air is unavailable j an/ :s not expected to be returned to service for several hours. i Tools and Eauipment Two-Way Radio, Flashlight, Hearing Protection, Operator Log and Safety Harness to i PERFORM. 1 Safety Considerations: In accordar.ce with the FPL Nuclear Division Safe Work Practices manual as appropriate to the task. t 08210s3, Rev 03 Page 3 of 13
_. __ _ . ~ _ _ . _ . ._. _ . . . _ _ _ _ ._. . _ ._ .. . _ . _ _. JOB PERFORMANCE MEASURE ! i P NOTE: If this JPM is to be a " PERFORM" JPM, ensure that the Candidate and Evaluator participate in a Tailboard meeting in accordance with AP-0010142, " Unit Reliability- Manipulation , of Sensitive Systems", prior to starting. Task Standard (s) in order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: - A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality , Instruction QI 5-PSL-1. , B. Locate and operate all plant equipment correctly, .
?
C. The system / equipment status reflects the overallintent of what the JPM required l upon completion. D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of l } Off-Normal Operating Procedure immediate actions shall be from memory. ! k ' , During the course of the JPM, there may be some tasks you will have to perform that will ! require you to implement contingency actions in order to complete them. Even in these ; cases, you are expected to make decisions and take actions based on the indications
. available and in accordance with the facility's procedural guidance.
l l a ! Initiatina Cue (s) ,
- I 1
The ANPS has directed you to take loca', manual control of Atmospheric Dump Valve (ADV), HCV-08-2A, using the local handwheel as directed by the control room, and return ADV control to remote when Instrument Air is restored, as directed by the control room, LAW 1 EOP-99, App. U. l j References l- 1-EOP-99, App. U, Rev.18 l 0821053, Rev 03 Page 4 of 13 4
e JOB PERFORMANCE MEASURE
. During the performance of the task I will tell you which steps to simulate or discuss.
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification.
. I will provide you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
- Do you understand these directions?
. If you have any questions, ask them now, and I will answer them.
. During the test I cannot answer questions.
. When you complete all steps correctly, you wil pass this job performance measure.
. Begin the task now.
)
I e a 0821053, Rev D3 Page 5 of 13 l 4
- _m __ _ r
'I l
'I JOB PERFORMA,NCE MEASURE PERFORMANCE CHECKLIST (C) Indicates a Critical Step
- 1. Element / Step Establish communications with the control room via radio, phone, page, or by runner.
Standard: COMMUNICATION IS ESTABLISHED WITH THE CONTROL ROOM. Cue: THE ANPS DIRECTS YOU TO THROTTLE OPEN HCV-08-2A TWO (2) TURNS AND NOTIFY HIM WHEN IT IS THROTTLED SAT UNSAT Comments:
- 2. (C) Element / Step Close T-V18032,"LocalInstrument Air Isolation to HCV-08-2A Positioner."
Standard: CLOSE T-V18032
- Cue: T-V18032 IS FULLY CLOCKWISE i
i SAT UNSAT ' Comments: i
- 3. (C) Element / Step Operate HCV-08-2A using local handwheel as directed by the i control room.
1 Standard: OPEN HCV-08-2A by turning the handwheel two turns counter-clockwise. ; ! Cue: HCV-08-2A IS TWO TURNS COUUTERCLOCKWISE i l SAT UNSAT i Comments: l l 08210s3. Rev 03 Page 6 of 13 j l 4' i r e -.
4 JOB PERFORMANCE MEASURE i i ; I PERFORMANCE CHECKLIST (C) Indicates a Critical Step l 4. Element / Step Notify Control Room of throttling HCV-08-2A two tums open via radio, phone, page, or by runner. l Standarc: The ANPS ACKNOWLEDGES the communication. t Cue: THE ANPS ACKNOWLEDGES AND REPORTS THAT INSTRUMENT AIR j HAS BEEN RESTORED AND DIRECTS YOU TO RETURN HCV-08-2A
- TO NORMAL OPERATION. THE ADV CONTROLLER PIC-08-1 A IS SET i FOR ZERO OUTPUT.
- SAT UNSAT 1
l Comments: ' 4 S. (C) Element / Step Locally CLOSE HCV-08-2A. i Standard: C10_SE S HCV-08-2A by turning the handwheel clockwise until the ADV seats closed. ? Cue: HCV-08-2A HANDWHEEL IS FULLY CLOCKWISE. SAT UNSAT ! Comments:
- 6. (C) Element / Step Open T-V18032, " Local Instrument Air Isolation to HCV-08-2A Positioner." .
Standard: OPEN T-V18032. Cue: T-V18032 IS FULLY COUNTERCLOCKWISE SAT UNSAT 0821053, Rev 03 Page 7 of 13
i
' JOB PERFORMANCE MEASURE Comments:
i PERFORMANCE CHECKLIST-l (C) Indicates a Critical Ste,n a l 7. Element / Step Notify Control Room HCV-08-2A has been configured for normal
- operation.
l Standard: Control Room NOTIFIED. { i i Cue; ANPS ACKNOWLEDGES AND DIRECTS YOU TO OBSERVE LOCAL OPERATION OF HCV-08-2A WHILE BEING OPERATED FROM THE I CONTROL ROOM. 1 SAT UNSAT a
- Comments:
i
- 8. Element / Step Observe'HCV-08-2A operation. -
- Standard
- OBSERVE and verify valve stem movement and/or steam exhaust ;
flow. Cue: HCV-08-2A STROKES SATISFACTORY 2 SAT UNSAT l t Comments: )
- 9. Element / Step Notify Control Room of satisfactory stroke of HCV-08-2A.
Standard: Communication ESTABLISHED Cue: ANPS ACKNOWLEDGES SAT UNSAT 0821053, Rev 03 Page 8 of 13 l i I
~
4 .; r JOB PERFORMANCE MEASURE Comments: PERFORMANCE CHECKLIST (C) Indicates a Critical Step i END Element / Step TERMINATION Standard: The JPM is complete when HCV-08-2A is returned to normal remote configuration and verified for proper operation. 1 0821053, Rev 03 . Page 9 of 13 F
JOB PERFORMANCE MEASURE l Knowledge Questions Question #1. KA: 041K1.06 Importance: 2.6/2.9
Reference:
None Question 1 A: Why were Atmospheric Steam Dumps used in local manual controlin this particular event rather than Steam Bypass Control valves in manual control ? Expected Response: Condenser vacuum is lost on a loss of offsite power, steam bypass control system cannot be used without a vacuum in the condenser. Question 18: What other conditions would make SBCS unavailable? Expected Response: System test switch not in OPERATE, Valve selecter switch not in , NORMAL, SBCS in emerpacy OFF, Loss of instrument bus power SAT UNSAT Comments: Question # 2. KA: 041K3.02 Importance: 3.8/3.9
Reference:
Steam Tables Question: In this event, what would be the temperature of the RCS if Atmospheric Steam Dumps could not be opened for an extended period of time? Expected Response: Approximately 545 degrees Comments: 0821053. Rev 03 Page 10 of 13 2 i
I j JOB PERFORMANCE MEASURE $ Provide this page to the Candidate I
; initial Conditions:
Unit 1 has just experienced a Loss of Offsite Power (LOOP), Instrument Air is unavailable and is nct expected to be returned to service for several hours. 1 l Initiating Cue: ) The ANPS has directed you to take local, manual control of Atmospheric Dump Valve j (ADV), HCV-08-2A, using the local handwheel as directed by the control room, and return ADV control to remote when instrument Air is restored, as directed by the control ! room, IAW 1-EOP-99, App. U. i i l I ! I 0821053,Rev03 Page 11 of 13 l
JOB PERFORMANCE MEASURE 4 Provide this page to the Candidate Part A: Why were Atmospheric Steam Dumps used in local manual control in this particular event rather than Steam Bypass Control valves in manual control ? Part B: What other conditions would make SBCS unavailable? - No Refer,ence t 0821053, Rev 03 - Page 12 of 13 l
F JOB PERFORMANCE MEASURE Provide this page to the Candidate in this event, what would be the temperature of the RCS if Atmospheric Steam Dumps could not be opened for an extended period of time? Reference allowed s l l 4 l l I I I I 0821053, Rev 03 Page 13 of 13 l l ,
This JPM For NRC Exam Use Only FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure ALIGN EMERGENCY COOLING WATER TO THE 1 A INSTRUMENT AIR COMPRESSOR 0821068, Rev 05 _ = SUCCESSFUL COMPLITION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO System: Instrument Air System Safety Function: 08
Reference:
1 EOP-99, App. H, " Operation of the 1 A and 1B Instrument Air Compressors" Task: Perform lineups on the IAS Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision.
JOB PERFORMANCE MEASURE Department: Operations Task
Title:
ALIGN EMERGENCY COOLING WATER TO THE 1 A INSTRUMENT AIR COMPliESSOR JPM No: 0821068, Rev 05 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 30 Minutes Location of Performance: Turbine Generator Building Unit 1 Notes to the Evaluator:
. Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee. .
. Notify a Management Observer of the observation opportunity.
i l I I l l l 0821068, Rev 05 Page 2 of 14
)
4 JOB PERFORMANCE MEASURE l 1 READ TO THE TRAINEE l l 1
. You are to perform / simulate this task. . The task you are to perform / simulate is:
ALIGN EMERGENCY COOLING WATER TO THE 1A INSTRUMENT AIR COMPRESSOR
. I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task. < - . Before starting I will state the task standards and initiating cues and answer any questions you have. . When you perform all the critical steps correctly, you will pass this Job Performance Measure. . You are required to perform the steps in the correct sequence. . Any sa:fety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM.
General / Initial Conditions: A loss of offsite power has been diagnosed and is in progress. Tools and Eouioment: Ladder Safety Considerationg
~
In accordance with the FPL Nuclear Division Safe Work Practices manual. Task Standard (s): In order for this job performance measure to be satisfactorily completed, accomplish this 08210fA Rev 05 Page 3 of 14
y ; 1 i1 JOB PERFORMANCE MEASURE JPM in accordance with the following standards: ] 1 l ' A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality instruction Ol-5-PSL-1. , 1 B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overallintent of what the JPM required , upon completion. D. Correctly perform all critical steps. i All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from memory. : During the course of the JPM, there may be some tasks you will have to perform that will - require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. i Initiatino Cue (st i The control room operator has just directed you to align the Emergency Cooling System , to the 1A Instrument Air Compressor IAW 1-EOP-99 Appendix H. He also informs you that MCC 1 AB is powered and breakers 42434 and 42435 are closed.
References:
i 1-EOP-99, App. H, Rev 19, " Operation of the 1 A and 1B Instrument Air Compressors" i
. During the performance of the task I will tell you which steps to simulate or discuss.
. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.
. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how'the indication is used for verification.
r
. I will provide you with the appropriate cues for steps which are simulated or discussed.
. You may use any approved reference materials normally available in the execution of this 0821068. Rev Os Page 4 of 14
3 1 i I 1 ! JOB PERFORMANCE MEASURE ' i i Job Performance Measure, including logs. e j . Do you understand these directions? , i i
- . If you have any questions, ask them now, and I will answer them, f j
. During the test I cannot answer questions. ;
I- . When you complete all steps correctly, you will pass this job performance measure. j . Begin the task now. r i 1 i i
\
i f 3 1 ; I t i 1 . 1 i 1 ! d a 1 ~ l i j 1 i I l l 4 i t 0821068, Rev 05 Page 5 of 14
- i i
f L;__.____:_.________________. - .-. - --_
- JOB PERFORMANCE MEASURE
- 1. Element / Step Appendix 'H' 2. If normal TCW is NOT available to the 1 A or 1B Instrument Air Compressors,lhan align emergency cooling
, water using the following steps: Standard: ACKNOWLEDGE control room operator direction to align the Emergency Cooling System to the 1 A lA compressor IAW 1-EOP-99, App 'H, and t QBTAIN the correct procedure. Cue: THE CONTROL ROOM OPERATOR HAS JUST DIRECTED YOU TO ALIGN THE EMERGENCY COOLING SYSTEM TO THE 1 A lA COMPR. , j LAW 1-EOP-99 APPENDIX H. HE ALSO INFORMS YOU THAT MCC 1 AB ; j IS POWERED AND BREAKERS 42434 AND 42435 ARE CLOSED, A. (C) Element / Step OPEN jacket cooling inlet to the 1 A (18) Instrument Air Compressor; 1 A V13197 or 1B (V13209).
- Standard
- POSITION only V13197 to OPEN.
Cue: AT THE 1 A INST. AIR COMPRESSOR, V13197 IS FULLY , COUNTERCLOCKWISE. SAT UNSAT 1 5 i i' B. (C) Element / Step OPEN jacket cooling outlet from the 1 A (1B) Instrument Air Compressor; 1 A V13201 or 1B (V13213). 1 ] Standard: POSITION oniv V13201 to OPEN. Cue: AT THE 1 A INST. AIR COMPRESSOR, V13201 IS FULLY COUNTERCLOCKWISE. SAT UNSAT Comments: E 0821068, Rev 05 Page 6 of 14 L__.__.._ _-
JOB PERFORMANCE MEASURE Performance Checklist C. Element / Step Ensure sufficient level exists in the instrument air compressor head
- tank.
t Standard: ENSURE the tank is full. Cue: THE HEAD TANK IS FULL.' SAT UNSAT D. Element / Step Ensure Bkr. 1-42434," Inst. Air Compressor Cooling Fan" and Bkr. 1-42435," Inst. Air Compressor Cooling System Water Pump" are CLOSED. Standard: QBSERVE the green lights illuminated above the 'STOP' pushbuttons for the Cooling Fan and the Water Pump. , i Cue: GREEN INDICATING LIGHTS ON LOCAL PANEL B-168A (MOUNTED ON SUPPORT BEAM SOUTH OF THE RADIATOR) ARE ILLUMINATED INDICATING THE BREAKER IS CLOSED. SAT UNSAT ,. E. (C) Element / Step CLOSE V13383, " Air Compressors Outlet Isol." and V13380, " Air Compressors Inlet Header isol." Standard: POSITION V13383 an.d V13380 to .C_LQ_S_E. Cue: V13383 AND V13380 (BELOW AND SOUTH OF V13417) ARE FULLY CLOCKWISE. SAT UNSAT . l Comments: ) 1 0821068. Rev 05 Page 7 of 14 l
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I l JOB PERFORMANCE MEASURE r
- Performance Checklist {
l' . . F. Element / Step Ensure the following valves are OPEN: .
- ' 1. V13417 " Air Compressor Cooler inlet From Recire. Pump Isol."
- 2.' V13420, " Air Compressor Cooler To Fan Cooler Isol."
j 3. V13424, "1 A Recirc. Pump From Head Tank Isol."
- 1. (C) Standard: POSITION V13417 to OPEN '
Cue: V13417 (g 8 FT ABOVE SOUTH END OF THE , EMERGENCY COOLING RADIATOR) IS FULLY ' .i COUNTERCLOCKWISE ; 1 SAT UNSAT e i i i 2.(C) Standard: ERSITIQN V13420 to OPEN. Cue: V13420 (DIRECTLY ABOVE V13417) IS FULLY ' COUNTERCLOCKWISE ; SAT UNSAT i 1 l t 3.(C) Standard: POSITION V13424 to OPEN
+
Cue: V13424 (FLOOR LEVEL SOUTH OF THE REClRC PUMP) l IS FULLY COUNTERCLOCKWISE r SAT UNSAT Comments: f i I 0321068. Rev 05 Page 8 of 14 i.
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--_____:_.---.--_--_.---._i__-----__.____'
JOB PERFORMANCE MEASURE : Performance Checklist i h G. (C) Element / Step OPEN SH13419, " Fan Cooler Inlet isolation" and SH13418, ,
"1 A Recirc. Pump Discharge Isol."
Standard: POSITION SH13419 and SH13418 to OPEN Cue: SH13419 (BELOW V13417) AND SH13418 (ABOVE V13417) ARE FULLY COUNTERCLOCKWISE , SAT UNSAT f H. (C) Element / Step Verify V18109 or (V18118), "1 A or 1B Instrument Air' Receiver Inlet From Aftercooler"is OPEN. Standard: POSITION pnly V18109 to OPEN i Cue: ONLY V18109 (AT THE 1 A COMPRESSOR) IS FULLY COUNTERCLOCKWISE SAT UNSAT l.(C) Element / Step Start Instrument Air Compressor Cooling System pump and fan. Standard: DEPRESS the pushbuttons for the lA Compressor Cooling System pump and fan a.rtd OBSERVE the red indicating lights illuminated. ' Cue: RED INDICATING LIGHTS ON AND GREEN OFF (LOCAL PANEL B-168A ABOVE THE PUSHBUTTONS) AS BOTH COMPONENTS j START SAT UNSAT Comments: l 0821068, Rev 05 Page 9 of 14 ) l i
t JOB PERFORMANCE MEASURE Performance Checklist J.(C) Element / Step CLOSE V18586,"1C/1D instrument Air Compressor Discharge Isolation". Standard: POSITION V18586 to CLOSE. Cue: V18586 (IN THE OVERHEAD ABOVE THE lA RECEIVER)IS FULLY CLOCKWISE SAT UNSAT K. ElemenUStep Notify Unit 1 Control Room that the 1 A or 1B Instrument Air
- Compressor is ready to start Standard: NOTIFY the Control Room that the 1 A lA Compressor is ready to start.
Cue: ACKNOWLEDGE AS THE RCO SAT UNSAT Comments: END Element / Step TERMINATION Standard: This JPM is complete when the Control Room has been notified that the 1 A Instrument Air Compressor is ready to start. 0821068. Rev 05 . Page 10 of 14
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JOB PERFORMANCE MEASURE I Knowledge Questions Question #1. l { KA: 078K4.03
- importance
- 3.1/3.3
Reference:
None (0711413 Plant Air Systems) 1 j Question: If the 1 A or 18 Instrument Air Compressor was to be run without cooling water j available, which automatic trip would shut the compressor down? 4 1 l Expected Response: The "high discharge air temperature" trip will automatically trip the j instrument air compressor. l 2 SAT UNSAT Comments: Question # 2. KA: 078K1.04 Importance: 2.6/2.9
Reference:
None (0711413, Plant Air Systems) Question: Why is all cooling water normally kept isolated from the 1 A and 18 Instrument Air Compressors? Expected Response: To prevent moisture build-up from condensing in the compressor internals. , SAT UNSAT Comments: 0821068. Rev 05 Page 11 of 14
i . JOB PERFORMANCE MEASURE i Provide this page to the Candidate
- Initial Conditions:
A loss of offsite power has been diagnosed and is in progress. Initiating Cue: The control room operator.has just directed you to align the Emergency Cooling System to the 1A instrument Air Compressor IAW 1-EOP-99 Appendix H. He also informs you that MCC 1 AB is powered and breakers 42434 and 42435 are closed. , t I l 1 I 0821068, Rev 05 Page 12 of 14 l
i JOB PERFORMANCE MEASURE 4 Provide this page to the Candidate if the 1 A or 1B Instrument Air Compressor was to be run without cooling water available, which automatic trip would shut the compressor down? No Reference ; 1 l l l l l l 0821068, Rev 05 Page 13 of 14
, _. _ . . . _ . _ - . . ~ . . . ...._ . .
1 JOB PERFORMANCE MEASURE i Provide this page to the Candidate. i 4 s .
. Why is all cooling water normally kept isolated from the 1 A and 18 Instrument Air 4 Compressors?
s No Reference J l t i I l. 1 r T 4 I i 1 i l 4 I i l 0821068, Rev 05 Page 14 of 14 -
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o JOB PERFORMANCE MEASURE Department: Operations Task
Title:
PERFORM A RELEASE OF THE 2C GAS DECAY TANK JPM No.: 0821163, Rev 00 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform __ Simulate Estimated Time to Complete the JPM: 20 MINUTES Location of Performance: UNIT 2 RAB Notes to the Evaluator:
- Pull the latest controlled copy of the applicable procedure
- The last page of this JPM lists' the initial conditions and initiating cue. Tear that page off and give it to the trainee.
- Notify a Management Observer of the observation opportunity.
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0821163, Rev 00 t l l l
, JOB PERFORMANCE MEASURE READ TO THE TRAINEE
. You are to perform / simulate this task.
. The task you are to perform / simulate is:
PERFORM A RELEASE OF THE 2C GAS DECAY TANK I will describe the general conditions and tell you the tocis and equipment required to perform / simulate this task. . s
- Before starting I will state the task standards and initiating cues and answer any questions you have.
. When you perform all the critical steps correctly, you will pass this Job Performance Measure.
. You are required to perform the steps in the correct sequence.
Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM. General / initial Conditions: 2C Gas Decay Tank pressure is 110 psig. Release permit # 98-007 has been prepared and approved for the release of the contents of 2C Gas Decay Tank. The ANPS has directed you to perform the release of the 2C Gas Decay Tank. Tools and Eauipment: 6' STEPLADDER Safety Considerations:
!l In accordance with the FPL Nuclear Division Safe Work Practices manual.
Task Standard (s):
/ l in order for this job performance measure to be satisfactorily completed, accomplish thic JPM in accordance with the following standards: j f j i
A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie r [ 0821163, Rev 00 - j l i j 1
l . JOB PERFORMANCE MEASURE I Instruction Ql-5-PSL-1, 1 B. Locate and operate all plant equipment correctly; C. The syt.temlequipment status reflects the overall intent of what the JPM required upon completion. D. Correct y perform al! critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal O,oorating Procedure immediate actions will be from memory. . During the course of the JPM, there may be some tasks you will have to perform that will require you to irnplement contngency actions in order to complete them. Even in these { cases, you are expected to make decisions and take actions based on the indications j available and in accordance with the facility's procedural guidance. 1 l l Initiatina Cue (sl: 1 The ANPS has directed you to perform the release of the 2C Gas Decay Tank.
References:
OP 2-0530021, Rev 23 During the performance of the task I will tell you which steps to simulate or discuss. Verbalize each step before you do it. This gives you a chanco to self-check and use STOP during the performance of each task element. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification. j I will piovide you with the appropriate cues for steps which are simulated or discussed. , You may use any approved reference materials normally available in the execution of jj this Job Performance Measure, including logs. Do you understand these directions 7 I If you have any questions, ask them now, and I will answer them. During the test I cannot answer questions. When you complete all steps correctly, you will pass this job performance measur 0821163. Rev 00
JOB PERFORMANCE MEASURE
- Begin the task now.
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0821163. Rev 00 -
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. JOB PERFORMANCE MEASURE (C) indicates a Critical Step PERFORMANCE CHECKLIST
- 1. Element / Step: Review the EOOS log and determine if channel RM-26-18 (PAG-203) has been declared out of service.
Standard: Verifies RM-26-18 is not out of service. Cue: RM-26-18 IS NOT OUT OF SERVICE
- 2. Element / Step: Check the Met Tower for operability Standard: Verifies Met Tower chart recorder working properly..
- Cue: MET TOWER CHART RECORDER TRACKING PROPERLY.
- 3. Element / Step: Verify gas release permit properly filled out and authorized, enter release permit number and tank to be released on procedure.
Standard: Verifies permit filled out properly and authorized, enters release permit number (98-007) and 2C GDT on procedure. Cue: 98-007 AND 2C GDT ENTERED ON PROCEDURE 4.(C) Element / Step: Verify the following valve alignment: V6745 Closed V06142 Open , V7071 Open V7070 Open ) V7072 Locked Closed l V6742 Locked Closed l Standard: Verify all above listed valves in proper positions l l
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Cue: V6745 FULLY CLOCKWISE V06142 FULLY COUNTERCLOCKWlSE / V7071 FULLY COUNTERCLOCKWISE V7070 FULLY COUNTERCLOCKWISE l V7072 FULLY CLOCKWISE WITH LOCK ATTACHED ! V6742 FULLY CLOCKWISE WITH LOCK ATTACHED SAT UNSAT
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, JOB PERFORMANCE MEASURE -
1 (C) Indicates a Critical Step PERFORMANCE CHECKLIST j
- 5. Element / Step: Refer to the valve list in the procedure and insert the i proper valve numbers in the appropriate spaces. i Standard: GDT to Gas collection header V6703 J GDT inlet V6597 )
, N2 to GDT V6599 l GDT drain V6598 l GDT to gas analyzer V6701 a ,
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! Cue: ALL APPROPRIATE VALVE NUMBERS ENTERED IN THE ; PROCEDURE 6.(C) Element / Step: Check closed V6597,2C GDT inlet
- Standard
- Closes V6597 i
Cue: V6597 FULLY CLOCKWISE
- 7.(C) Element / Step
- Check closed V6599, N2 to 2C GDT
]
s Standard: Closes V6599 i Cue: V6599 FULLY CLOCKWISE f 4. J 1 0821163, Rev 00 l
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. JOB PERFORMANCE MEASURE C) Indicates a Critical Step PERFORMANCE CHECKLIST 8 (C) ElemenVStep- Record pressures of 2A,28 and 2C GDTs Record date and start time of release a
Standard: Records pressures of 2A,28 and 2C GDTs Records date and start time of release Cue: 1 A GDT - 30 psig,1B GDT - O psig,1C GDT 110 psig P
- 9. (C) ElemenUStep: Open V6703 .'
1 Standard: Opens V6703 Cue: V6703 FULLY COUNTERCLOCKWISE 10.(C) ElemenVSteo: Open V7274 Standard: Opens V7274 i Cue: V7274 FULLY COUNTERCLOCKWlSE i i
- 11. ElemenVStep
- Notify Control Room to open V6565 Standard: Notifies Control Room to open V6565 Cue: CONTROL ROOM ACKNOWLEDGES V6565 OPEN 12.(C) ElemenUStep: Open V6745 and adjust to establish required flow on gas release permit.
2
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i Standard: Opens V6745 to establish 10 CFM ; i Cue: V6745 PARTIALLY COUNTERCLOCKWlSE; FLOW 10 CFM CUE: CONTROL ROOM NOTIFIES YOU THAT THE WASTE GAS MONITOR (PAG-203) IS IN HIGH ALARM, V-6565 STILL INDICATES RED LIGHT. [ ,
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i
. JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 13. Element / Step: Terminates Release by closing V-6745 or V-6703 or
- breaking the air connection on V-6565.
- Cue
- RELEASE IS TERMINATED (IF FLOW IS STOPPED) h
- 14. Element / Step: Notify ANPS gas release is terminated j - -
l Standard: Notifies ANPS gas release is terminated j Cue: ANPS ACKNOWLEDGES ,
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. JOB PERFORMANCE MEASURE Kno,wledge Questions Question #1.
KA 071K5.04 importance 2.5f3.1 Reference None (ONOP 1[2]-0530030, Waste Gas) Question: Chemistry reports that the Hydrogen concentration of the in-service gas decay tank , is 2.4% Oxygen concentration is 5.1%. What are your actions? , Expected Response: Immediately suspend all addi>3ns of waste gas to the system and begin reducing oxygen concentration to < 2%by the admission of Nitrogen. 4 SAT UNSAT Comments: Question # 2. KA 071K4.04 Importance 2.9/3.4 Reference None (0711601, RAB Ventilation) Question: State the condition (s) other than high rad, that will automatically terminate a waste gas release. Espected Response: High radiation ~on the gaseous release monitor, loss of the running RAB exhaust fan (s). (HVE-10A and HVE 10-B) / SAT- UNSAT
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Comments: [
., l 0821163. Rev 00 l
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JOB PERFORMANCE MEASURE Provide this page to the Candidate Initial Conditions: 2C Gas Decay Tank pressure is 110 psig. Release permit # 98-007 has been prepared and approved for the release of the contents of 2C Gas Decay Tank. The ANPS has . directed you to perform the release of the 2C Gas Decay Tank. ! Initiating Cue: The ANPS has directed you to perform the release of the 2C Gas Decay Tank. t
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0821163, Rev 00
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-=-: 1 -- - -e4, , . . JOB PERFORMANCE MEASURE Provide this page to the Candidate Chemistry reports that the Hydrogen concentration of the in-service gas decay tank is 2.4%. Oxygen concentration is 5.1%. What are your actions?
No Reference l i I i-
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. JOB PERFORMANCE MEASURE Provide this page to the Candidate !
i State the condition (s) other than high rad,- that will automatically terminate a waste gas release. -! No Reference , 4 f ) ) i 4 i l \ i l 1 ?
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FLORIDA POWER & LIGHT COMPANY r .. l ' ST. LUCIE UNIT 2 i . :- f#-- ! I OPERATING PROCEDURE REVISION 23 NO_._2-0_530021 l M I poa spogwagg g ) 4 , 10 TITLE: I'b 1 mentis not gny57ti[fs,iferede fnformaltron wtth a.contrb; CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE 2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 10/12 1982 Approved by C. M. Wethy Plant General Manager 10/10 1982 Revision 23 Reviewed by FRG 2/16 1998 Approved by J. Scarola Plant General Manager 2/16 1998
3.0 PURPOSE
3.1 This procedure provides instructions for making a controlled release of the contents of a Gas Decay Tank (GDT) and performing a containment purge. 4.0 PRECAUTIONS AND LIMITS: 4.1 Prior to a GDT release, the tank contents shall be sampled and analyzed or a post decay calculation made if the tank has been isolated since last sample and a Gas Release Permit issued and approved in accordance with Chemistry Procedure C-72, Processing Gaseous Wastes. NOTE in modes 1,2,3 and 4, no containment purges shall be initiated via the main purge lines. ; 4.2 Prior to a containment purge or a Containment Mini-purge, the containment atmosphere shall be sampled, analyzed and a Gaseous Release Perrnit issued and approved in accordance with Chemistry Procedure C-72, I j
" Processing Gaseous Wastes."
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DOCT PRO' / DOCN_2 SYS _ COMP ITM_ t 1
Pag: 2 of 14 y ST. LUCIE UNIT 2 d OPERATING PROCEDURE NO. 2-0530021, REVISION 23 CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE 4.0 PRECAUTIONS AND LIMITS: (continued) 4.3 The operator shall perform a release only after receip: e an approved Gaseous Release Permit. Form similar to Figure 1. 4.4 The gaseous Discharge Monitor, Channel 203 (RS-26-18) on the GDT gas discharge header shall be in operation or else the conditions of Chemistry Procedure C-200, "Offsite Dose Calculation Manual (ODCM)", section 3.3.3.9 shall be met. 4.5 During Normal Plant Operation the following applies to Plant Vent Monitor:
- 1. Chemistry Department personnel maintain the alarm point settings on the required channels and they do not require a special setting for a batch release.
- 2. Operations Department shall terminate any Batch Release immediately by closing V6565 on RTGB 205 if a High Alarm condition is received on any active Plant Vent Channel.
- 3. Operations Department should investigate and monitor the trend of any Alert Alarm on any activity channel. An unexplained and increasing count rate should dictate terminating the batch release.
4.6 A containment atmosphere radiation monitor (RS-26-25 or RS-26-26) should be in operation during a containment purge. 4.7 At least one RAB exhaust fan shall be in service during a release. 4.8 A containment purge batch release is defined as the first 10 hours of containment purge. After 10 hours activity discharged from containment is accounted for as a continuous release and the gaseous release permit may be administratively terminated beyond 10 hours.
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4.9 A containment purge batch release and a GDT release should not normally be / performed at the same time to prevent possibility of inadvertently exceeding / release limits. /
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ST. LUCIE UNIT 2
. OPERATING PROCEDURE NO. 2-0530021, REVISION 23 J CONTROLLED GASEOU_S BATCH RELEASE TO ATMOSPHERE 4.0 PRECAUTIONS AND LIMITS: (continued) 4.10 Notify Health Physics Department prior to commencement of a containment
. purge for containment entry considerations.
4.11 Meteorological channels listed below or their back up channel, shall be operable to perform a Gas Decay Tank release and should be operable to perform s. Containment Purge release. Refer to Operating Procedure 1400051, " Meteorological Data System Daily Channel Check," for specifics relating to instrument operability / minimum number of channels. TEMPERATURE WIND SPEED WIND DIRECTION 32 foot elevation 32 foot elevation 32 foot elevation 190 foot inovation Altemate indications may be used. 4.12 A gas release may be terminated at any time by closing V6565 on RTGB 205. 4.13 A containment purge may be terminated at any time by stopping HVE-8A or HVE-88. 4.14 If a gas release is terminated, manually or automatically, due to a valid high radiation alarm a new permit must be obtained before restarting release. 5.0 RELATED SYSTEM STATUS: 5.1 Gas Decay Tank:
- 1. RAB Ventilation Exhaust System shall be in service.
5.2 Containment Purge:
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i 1. The instrument Air System shall be in operation supplying air j to solenoid valves. !
- 2. The Containment Vacuum Relief System shall be operable.
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- 3. The Containment Cooling System shall be in operation. /
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Paga 4 of 14
. n ST. LUCIE UNIT 2 *
- OPERATING PROCEDURE NO. 2-0530021, REVISION 23
- , CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
6.0 REFERENCES
6.1 Final Updated Safety Analysis Report (FUSAR) Section 11.3 and 12.2.1.6.3 6.2 Operating Procedure 1400051, " Meteorological Data System Daily Channel Check" 6.3 Chemistry Procedure C-200, "Offsite Dose Calculation Manual (ODCM)" 6.4 P&lD 299P G 078, Sheet 163 6.5 Chemistry Procedure C-72, " Processing Gaseous Waste"
, 6.6 CR 97-1045 7.0 RECORDS REQUIRED:
7.1 A completed Gaseous Release Permit with the final activity page attachment shall be maintained in the plant files in accordance with Ol 17-PR/PSL-1,
" Quality Assurance Records." The signature Reviewed by the Assistant Nuclear Plant Supervisor on Section V of the GRP shall denote his/her review
. of this proceduro for correct performance of the release and that the system (s) j were retumed to normal. The Reviewed by signature of the Chemistry Supervisor on Section V of the GRP shall denote his/her review of the release for correct performance as per Chemistry Department Procedures. 7.2 Normal log entries. I l i l l
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Pago 5 of 14 ST. LUClE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 23 CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
8.1 Release of a GDT to Atmosphere CAUTION If Waste Gas Monitor is Out of Service, C-200, ODCM Control 3.3.3.10 requires two independent tank sample / analysis and two independent valve alignments to verify the discharge valve lineup.
, 1. Review the Equipment Out of Service Log and determine if Channel RM-26-18 (PAG-203), Waste Gas Monitor has been declared Out of Service.
A. If Channel PAG-203 is Out of Service: YES NO
- 1. Has the Monitor been Out of Service for less than 14 days? /
- 2. Has Chemistry attached two independent Radioactivity analysis of the tank to the Release Permit?
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- 3. Has Chemistry attached two independent Release Rate Calculations for the tank on the Release Permit?
- 4. Have you arranged for independent verification of the discharge vale lineup?
jf the answer to any of the above questions is "No", Then STOP, do not release the Gas Decay Tank. i i l 1 l 1
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Page 6 of 14 ST. LUCIE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 23
. CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
INITIAL 8.1 (continued) CAUTION A MET Station indicator channel that is drawing straight lines should be suspected to be failed and investigated for operability.
- 2. Check the operability of the MET Station by looking at the ERDADS display of the previous 24 hours, or by looking at the chart recorder in the Unit 1 Control Room for the last 24 hours. E the MET Station is INOPERABLE, Then STOP, do not release the tank.
MET Station Verified OPERABLE by RCO
- 3. On Section Ill, AUTHORIZATION of the Gas Release Permit,
" Release Conditions Approved by ANPS", has the ANPS Authorized the release? H the answer is "No", Then STOP.
- 4. Enter the Gaseous Rele .se Permit Number: DDM
- 5. Enter the GDT to be released: lb
- CAUTION If Channel RM-26-18 (PAG-203), Waste Gas Monitor is Out of Service,
, independent verification of the discharge valve lineup is required for Steps 8.1.6 through 8.1.12.
- 6. Check the following valves in the indicated position:
V6745 (closed) Gas coll hdr needle valve from GST , l & GDTs. /
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V06142 (open) Isolation valve upstream of FIT-6648 j V7071 (open) Inlet valve to RT-26-18 gas release RAD monitor.
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ST. LUCIE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 23 CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
(continued) INITIAL 8.1 (continued)
- 6. (continued)
V7070 (open) Outlet valve from RT-26-18 gas release RAD monitor. < V7072 (Locked closed) Bypass valve for RT-26-18 gas release RAD monitor. /R23 V6742 (Locked closed) Gas Surge Tank to plant vent.
- 7. Refer to the below valve list and insert proper valve numbers for GJT to be released, in the appropriate spaces.
Valve Description 2A 2B 2C Gas Decay Tank to Gas Collection Header 6584 6594 6703 GDT Inlet 6579 6589 6597 N, (Nitrogen) Supply to GDT 6588 6596 6599 GDT Drain 6580 6590 6598 GDT to Gas Analyzer 6582 6592 6701- I
- 8. Check closed V . GDT inlet. /R23
- 9. Check closed V . N, supply to GDT. /R23
{ i 10. At the start of the release, record: 1
- 2A 2B 2C GDT Pressure:
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- 11. Open V , GDT to gas collection header. /
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Pege 8 of 14 ST. LUCIE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 23
. CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
(continued) INITIAL 8.1 (continued)
- 12. Open V7274, GDT isolation to discharge header.
- 13. Open V6565 (Waste Gas Release Valve) on RTGB 205.
NOTE Pressure reducing valve V6587 should control discharge gas pressure at 10 psig as inaicated on PI-6648.
- 14. Open needle valve V6745 and adjust to establish the required flow rate as specified on the Gaseous Release Permit.
- 15. Record discharge flow rate from flow recorder FR-6648 on RTGB 205.
CFM CAUTION Secure the gas release if the non-releasing tanks exhibit a pressure decreass of 4 psig or more and notify ANPS.
- 16. Verify that the other two gas decay tanks are NOT decreasing in gas pressure.
1
- 17. Record the 2A,28 and 2C gas decay tank pressures
.approximately every 30 minutes during the release.
J , Time 2A GDT Pressure 2B GDT Pressure 2C GDT Pressure 4 ! l
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Paga 9 of 14 i I l ' . . -"' ST. LUCIE UNIT 2 - OPERATING PROCEDURE NO. 2-0530021, REVISION 23 l i CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE i i
- 8.0 INSTRUCTIONS
- (continued) INITIAL 8.1 (continued)
- 17. (continued)
Verify that the two remaining gas decay tanks NOT being released exhibit stable pressure. M it appears that one or both tanks are losing pressure, Then terminate the release and '
; notify the Assistant Nuclear Plant Supervisor to determine the cause of the problem and resolution.
4
- 18. If a drop in the two remaining tanks NOT being released occurs, Then notify Chemistry to determine whether an unplanned gas release has occurred.
ANPS
- 19. H an unplanned gas release has occurred, Then notify Senior Plant Management.
ANPS J
- 20. During actual release perform channel check on Plant Vent PlG A (423), PIG B (433) and WRGM (621) for expected response and indicate by initials on Permit.
- 21. When GDT reaches approximately 10 psig, terminate the release as follows:
4 1. Close V . GDT to gas collection header. /R23
- 2. When PI-6648 indicates O psig, close V6745, gas coll header needle valve from GST & GDTs.
- 3. Close V6565, waste gas release valve.
4.
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Close V7274, GDT isolation to discharge header. /
/ ,
- 22. Record stop time, date and pressure. __
j
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! i Stop Time: '
i Stop Date: /
/
1 GDT Pressure: / s
/
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- n. . .- - .. . .- . - . -.- .. _ .
Paga 10 of 14 ST. LUCIE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 23
, CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE 8,0 INSTRUCTIONS: (continued) INITIAL 8.1 (continued)
- 23. Drain the gas decay tanks in the following manner:
CAUTION The gas decay tank drains should never be open at the same time as the gas surge tank drain. CAUTION - The gas decay tank drains should only be opened after completion of the gas release when gas decay tank pressure is the minimum value. A. Check V6569 closed, gas surge tank drain. /R23 B. Open V . gas decay tank drain. C. Observe the drain discharge to equipment drain sump located , inside the gas surge tank cubicle. If gas issues from this drain, stop draining by isolating V . gas decay tank drain. D. Drain until water stops issuing from the drain. When draining is complete, close V gas decay tank drain.
- 24. Route this section of the procedure with the Gaseous Release Permit to the Assistant Nuclear Plant Supervisor for his review.
Performed by (Operator) Date / / l , ! /
/
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Pag @ 11 of 14 ST. LUCIE UNIT 2 " '7:n OPERATING PROCEDURE NO. 2-0530021, REVISION 23 CONTROLLED GASEOUS ' BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
(continued) INITIAL 8.2 Performing a Containment Purge NOTE Whenever the containment integrity is required, emphasis should be placed on operating the containment in a passive mode as much as possible and on limiting all purging and venting times to as low as achievable. To justify venting or purging, there must be an established need to improve working conditionti to perform a safety related surveillance or safety related maintenance procedure. (Examples of improved working conditions would include reducing temperature, humidity and airbome activity sufficiently to permit efficient performance or to significantly reduce occupational radiation ; exposureti). ~
- 1. Notify security of the intent to conduct a containment purge and the approximate length of time.
- 2. Check to be closed containment purge Flow Control Valves (FCV):
FCV-25-1 FCV-25-4 FCV-25-2 FCV-25-5 FCV-25-3 FCV-25-6
- 3. Check to be closed containment vacuum relief valves:
FCV 25 7 FCV 25-8
- 4. Check containment purge refueling switch to be in the '
purge position. '
- 5. If purge is for refueling operation, the containment purge ,
refueling damper switch should be in the refueling position / before the vessel head is removed. __
- 6. Have an approved Gaseous Release Permit. !
m Permit number i l
Paga 12 of 14
~'
ST. LUCIE UNIT 2 . OPERATING PROCEDURE NO. 2-0530021, REVISION 23 . CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
(continued) INITIAL 8.2 (continued) - .
- 7. At the start of the release, record:
Date: / / , 1 Time: 8. A. Start one containment purge fan; observe that FCV-25-4, FCV-25-5 and FCV-25-6 open before fan starts. B. Observe the containment Differential Pressure PDIS-25-1 A. and PDIS-25-18. As indicator reaches -0.5 inches water pressure differential between containment and outside, ! FCV-25-1, FCV-25-2 and FCV-25-3 should open. If these valves do not open before containment to outside pressure reaches -1.0 inches water pressure, stop purge fan and call I & C Department. If containment pressure reaches :
-4.0 inches water pressure, the purge fans will trip. j
- 9. Observe plant vent and containment monitors frequently during purge to ensure readings decrease as expected, after the initial increase from the purge fan starting the release and initial the channel check sections of release permit for PlG A (423),
PIG B (433) and WRGM (621). f-
- 10. Continue purge until no longer required or preparations are i commenced for plant start-up. A purge may be terminated at i any time by tuming off the purge fan (both fans must be off). l FCV-25-1,2,3,4,5, & 6 valves should automatically close when /l the fan is tumed off. If the purge is going to run continuously, the gaseous release permit should be administratively terminated
/l '
after 10 hours with the stop time as 10 hours from the start of / the purge start time. __
- 11. Notify security that the containment purge is completed.
/
/ -
Paga 13 of 14
.. M S ST. LUCIE UNIT 2 .' " ' U; -
OPERATING PROCEDURE NO. 2-0530021, REVISION 23 ' '
, , CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE
8.0 INSTRUCTIONS
(continued) ' INITIAL 8.2 (continued)
- 12. Record stop time and date on the Gas Release Permit.
(
- 13. Route this section of the procedure together with the Gaseous Release Permit to the Assistant Nuclear Plant Supervisor for his review.
Performed by (Operator) Date / / l 4
Paga 14 Of 14 m ST. LUCIE UNIT 2 -- l . OPERATING PROCEDURE NO. 2-0530021, REVISION 23
.- CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE FIGURE 1 S- 2 OPS GASEOUS' RELEASE PERMIT UNIT 2 DATE ! DOCT DOCN ; SYS COMP ' iTM
{ l. GASEOUS PERMIT NUMBER SAMPLE DATE AND TIME GDT NAME OR PURGE
; IL LIMITS ACTUAL CONCENTRATION q GDT = 20 pCVec pCi/cc Containment Purge = 4.76E-03 Ci/cc pCi/cc Containment Mini-Purge = 0.01 pCVcc NA nCi/cc Maximum Discharge Flow Rate 1j GDT #/hr GOT Decreases or C.F.M. Flow Setting
) Waste Gas Monitor Setpoints: Alert uCVcc High: uCi/cc Waste Gas Monitor Source Check Performed By- Signature GRP LIMS # 21078 MONITOR SOURCE CHECK LIMS # PRE-RELEASE REMARKS: lll REVIEW - APPROVAL (PRIOR TO RELEASE) Main Purge or Mini-Purge 2 5.00E-03 gCi/cc Chemistry Supervisor Signature i Mini-Purge < 5.00E-03 pCi/cc and meets the requirements of STS 3.6.1.7.b Permit Preparer Signature GDT 2 25% of Secton 11. Chemistry Supervisor Signature GDT < 25% of Secton 11. Permit Properer Signature i Assistent Nuclear Plant Supervisor Signature ! IV. Start Date Start Time Stop Date Stop Time .'
/
, Start GDT Pressure Stop GDT Pressure / b Channel Check of Plant Vent Monitors during release. 1 PlG A (423) P!G B (433) WRGM (621)_ _ Inital ini6al l' [' ) j 1 V. REVIEW- APPROVAL (POST RELEASE) Assistent Nuclear Plant Supervisor Chemistry Supervisor I
1 FACILITY SUBMITTED OUTLINE AND THE FACILITY INITIAL EXAM SUBMITTAL (WRITTEN & OPERATING PORTIONS) S f Ltecs E F8 .30/ DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070 A070 g i
4 ES-401 PWR SRO Examination Outline Form ES-401-3 :. Facility: St. Lucie Date of Exam:6-22-98 Exam Leveh SRO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 A1 A2 A3 A4- G Total-
- 1. 1 4 3 5 5 5 2' 24
**'U*" Y 2 3 2 4 2 3 2 16 Abnormal Plant Evolutions 3 1 1 1 3 l-6 Tier Totals 8 5 9 8 8 5 43 1 3 2 1 1 1 2 3 2 1 2 1 19 2 2 2 1 2 2 1 2' 2 '1 1 1 17 '
Plant Systema 3 1 1 1 1 4 Tier Totals 5 4 2 4 3 3 5 4 3 4 3 40 .
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 5 4 '4 4 -
Note:
- Attempt to distribute topics among all K/A categories: select at least one topic from every K/A category within each tier.
- Actual point totals must match those specified in the table.
- Select topics from many systems; avoid selecting more than two or three K/A topics from a Given system unless they relate to plant specific priorities.
- Systems / evolutions within each group are identified on the associated outline. )
- The shaded areas are not applicable to the category / tier. l l
! )
1 NUREG-1021 23 of 39 Interim Rev. 8, January 10 7 i l 1 ~
\
l 4 s. I i ! DISTRIBUTION CODE A070 1
. . . - .- ~ . - . . - + -,. - . . - . , - - - - . , , - - - . . -
4 ES41 PWR SRO Examinston Outhne Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 1 E/ APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) Imp Points 000001 Continuous Rod Withdrawal I t X AK1.03 / CRW effects on DNB requirements 38 1 000003 Dropped Control Rod / l X X AK2 OS / Movement of CEA when on the hold bus / dropped rod 2.8 1 AK3 04 / Actons for 2 drooped rods in mode 3 4.1 1 000005 incoerable/ Stuck Control Rod / I X AA101 / Control rod interiocks 34 1 000011 Large Break LOCA / til X EK101/ Cnteria for 2 phase natural circulation 4.4 1 000015/17 RCP Malfunc' ions / IV X AA1.22 / RCP para nenter limits to trip usnt 42 1 i BW/E09: CEIA13; W/E09&E10 Natural Cire. / IV X AK1.2 / Cooldown rate w/SG isolated 3S 1 000024 Emergency Boration / I X X AK2.01/ Loss of power, method of Emergency Boration 2.7 1 4.0 1 G2 4 49 / Entry cond:tions to EB procedure 000026 Loss of Component Coolina Water / Vitt X AA2 01/ Locaten of CCW Icak 35 1 000029 Anticipated Transient w/o Scram / t X EA1.12 / Actions on ATWS 39 1 000040 (BW/E05; CE/EOS; WiE12) Steam Line X AA1.04 / Closure logic of MSIVs 4.3 1 Ruoture - Excessrve Heat Transfer / IV CE/A11; W/E08 RCS Overcooling - PTS / IV X AK3 01/ Loss of subcooling durino ESDE 35 1 000051 Loss of Condenser Vacuum / IV X AA2.01/ Reactor trip on less of condenser vacuum 41 1 000055 Station Blackout / VI X EK3 02 / Exit conditions for Station Blackout 46 1 000057 Loss of Vital AC Elec. Inst Bus / VI X AA214 / Loss of normal and afternate power supplies 36 1 000059 Accidental Liquid RadWaste Ret /IX 000062 Loss of Nuclear Service Water /IV X AA1.06 / Loss of ICW train / actions 29 1 000067 Plant Fire On-site / IX X X AA216 / Source of fire water in containment 4.0 1 G2.4.26 / Fire team leader requirements 3.3 1 000068 (BW/A06) Control Room Evac. I Vtil X X AK2 01/ Differences in Unit 1 and Unit 2 HSDCP 40 1 AK3 03 / Status of AFW controls after isolaton 4.3 1 000069 (W!E14) Loss of CTMT Inteority / V X AA2.01/ Identification of loss of containment integnty 4.3 1 000074 (W/E06&E07) Inad Core Coo!ing / tV X EK1.02 / Degree of seventy of zircatoy oxidation 48 1 i 000076 High Reactor Coolant Activity / tX X AK3 06 / Operator response to RCS high activity 3.8 1 BW/A02&A03 Loss of NNi-XN / Vil K/A Cateoory Totals: 4 3 5 5 5 2 Group Point Total: 24 I
P l l l ES-401 PWR SRO Examinaten Outhne Form ES-401-3 Emergency and Abnormat Plant Evolutons - Tier 1/ Group 2 E/ APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) tmp. Points ! 000007 f BW/E02&E10; CE/E02) Reector Trip - X EK2.1/ Venfcaten of Safety Functions with power loss 3.7 1 l Stabshration - Recovery / I i BW!A01 Piant Runback / I BW/A04 Turbine Trip / IV 000008 Pressurizer Vapor Space Accident / ill l 000009 Small Break LOCA /111 X EK3 24 / Limiting factor for HPSI throttling in SBLOCA 46 1 l BW!E08; W/E03 LOCA Cooldown - Depress. / IV W/E11 Loss of Emeroency Coolant Recirc. / IV 000022 Loss of Reactor Coolant Makeup /11 X AK3 02 / Attemate Boration lineup 38 1 t 000025 Loss of RHR System / IV X AA1.10 / SDC suction operation with instrument failure 29 1 000027 Pressurizer Pressure Control System X AK2.03 / Effect on sohd operation with letdown failure 32 1 Malfunction /111 000032 Loss of source Range Ni / Vil 000033 Loss of intermediate Range NI / Vit X AA2 09 / Whch RPS channets to bypass on tailure 37 1 000037 Steam Generator Tube Leak / til X AK3 07 / difference between teak and rupture procedures 44 1 000038 Steam Generator Tube Rupture / til X EK103 / Inverted detta t after SG isolation 42 1 000054 (CE/E06) Loss of Main Feedwater / IV X X AA2.05 / System in manual with plant change 37 1 4.3 1 G2.4 21 / SG indications on TLOF 000058 Loss of DC Pov.er / VI X G2.4 49 / IOAs for loss of DC bus 40 1 000060 Accidental Gaseous Radwaste Ret / tX X AA102 / Failure of RAB ventilation during release 3.1 1 000061 ARM System Atarms / Vil X X AK1.01/ New fuel detector hmitations 2.9 1 AA1.01/ Logic for automatic actons of FHB ventitation 36 1 W/E16 High Containment Rsdiation / IX 000065 Loss of instrument Air / Vill X AK3 04 / Safety functions impacted by loss of IA 3.2 1 CEE09 Functional Recovery X EK1.2 / entry to EOP-15 40 1 K/A Cateoory Point Totals: 3 2 4 2 3 2 Group Point Total: 16
;l s
3-1 s 0 dr 4 io S P 1 1 E 1 3 m r o p F 1 2 0 I m 3 3 4 n t o a r r o te t t s i e m r s s n t x a r t _ t g n . ) le o n s p w ( c e o _ c m d _ ip n u t _ o e r p u T h . fe W s A/ e r t n K n C_ I a i g l p 3 k n r p a it r o u le a f o n ts e g r o a G p to
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1 io 7 2 P - otov 1 0 0 1 p ta 1 u nE it 1 K 1 A 2 o r mn ala A A G G _ EI xP O c. G X 1 R Se Rt 2 WA A d Pna 1 y c A X 1 n e or e 3 K _ m _ E 2 K - 1 K X 1 _ li i V n i V io t n s I t c 1 1 e e r I V / n I d u I e r u n ic s n u F o c lo o s s y i A I c e t c V n ta l f e n u g I E u i f r p- V a f in r d t c e r / S ta l d e n A g e y
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E / / A u u 0 / E v v 0 B B B C W W K ll ll lfI lI l I ll Il Il
___ ._. _. _ _m._. _. . . . __ - _ . . 1 ( l ES-401 PWR SRO Examina:m Outhne Plant Systems - Tser 2/ Group 1 Form ES-401-3 System # 1 Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic (s) imp. Points 001 Control Rod Drive X K6 02 / Function of ACTM modules 33 1 003 Reactor Coolant Pump X A4 01 / unit drfference in seal injection 25 1 004 Chemical and Volume Control X X K3 05 / Charging pump failure 42 1 A1.11 I Auto actms for Letdown leak 30 1 013 Engineered Safety Features Actuation X A2 04 I Conditons causing ESFAS actu. A2 1 014 Rod Position Indcation X A2 04 I Difference of indration of RPIS 39 1 015 Nuclear instrumentation X At 03 i adjustment of nuc-delta t 3.7 1 017 In-core Tempe ature Mondor X K101/ Actions on loss of DDPS 32 1 022 Contcinment Cochng X K2 01 I Unit differences of power strpplies 31 1 025 fce Condenser 026 Containment Spray X G2 2 22 i Tech spec requirements for CSS 4.1 1 056 Condensate X K1.03 / Low flow affect on MFW 26 1 059 Main Feedwater X A103 / Permissives for LPFWS 29 1 061 Auxiliary / Emergency Feedwater X X K5 01/ Reason for cooldown after LOOP /SIAS 3.9 1 A3 04 / AFW lockout on LOOP t- 42 1 063 DC Electrical Destribution X K4 01/ alignment of AB bus 30 1 068 Liquid Radwaste X K6.101 Actions if rad monitor is lost 2.9 1 071 Waste Gas Desposal X K1.04 / Auto termination of release 28 1 072 Area Radiation Monitonng X X K2.05 / main steam hne indications post trip 2.9 1 3.1 1 A4 03 I Containment evac alarm logic K/A Category Point Totals: 3 2 1 1 1 2 3 2 1 2 1 Group Point Total: 19
ES-401 PWR SRO Examination Outhne Form ES-401-3 Plant Systems - Tier 2/ Group 2 System # / Name K1 K2 K3 K4 K5 K6 At A2 A3 A4 G K/A Topic (s) Imp Points 002 Reacter Coolant X A1.03 / Function of Teo!d loop switches 38 1 006 Emergency Core Cochng X K2 01/ LPSI loading on power loss 39 1 010 Pressuriter Pressure Control X A4 02 / Heater restoration ESDE/ LOOP 34 1 011 Pressu-izer Level Controt X K2 02 / Avaliabihty of heaters on bus loss 32 1 012 Reactor Protection X K5 01/ ASGT trip pammeters 38 1 016 Non-nuclear instrumentation 027 Containment todine Removat X K1.01/ Unit 1 IRS on toss of DC 37 1 028 Hydrocen Recombiner and Purge Control X 38 A101/ Actions for H2 levets (%) 1 029 Containment Purge X A2 03 / Method of purge in Mode 4 31 1 033 Spent Fuel Pool Cooling X K4 01/ Bases for water leve- 32 1 034 Fuel Handhng Equipment 1 035 Steam Generator X K5 01/ Affect of SGBD adjustment 39 1 039 Main and Reheat Steam X A3 02 / isolation of aux steam 35 1 055 Condenser Air Removat X G2.1.23 / Support systems needed for CARS 40 1 062 AC Electrical Distribution X K3 02 / undervotatage response by EC3 44 1 064 Emergency Diesel Generator X X K6.07 / EDG start w/ air recievers oos 2.9 1 A2.16 / Tnpped diesel w/ LOOP /SIAS 37 1 . 073 Process RaMation Monitoring X K1.01/ loss of containment PIG 39 1 075 Circulating Water X K4 01/ Actions for loss of cooling canal 28 1 079 Station Air 086 Fire Protection i 103 Containment
. 4 lategory Point Totals: 2 2 1 2 2 1 2 2 1 1 1 Group Point Total: 17 i
l _-_-____-_ __ - -_- - - _. -. . __ _ ___ -- - ,_. _ _ - ._ - _-___
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_ 0 1 0 0 i. n u o 3 4 4 2w r = A K A Gre G G X 1 A4 X 1 e3 n . ip l t um 3 Or t A X 1 nG r t e2 a r 2 nie A d iT m . a-xs Eme 1 A Ot Rsy SS 6 Rtn K - Wl a _ PP 5 u K m 4 K X 1 3 K 2 K m 1 K _ l o r . t n k o . n C a s e T s m h r p a a c e y N ! n ta B r o
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o u e t a s O o r e !a m m / f n br n to e e ie h e R c u T ts le o T G t y t s R C / p e r e ir n S e n A i o r t n m ta P H e e u i b t n l a d r n D r u W e y r u u o T e m o _ d s p m ic u g is s m a n v r e 1 e e r o te a r e t s ta 0 R P C S M S in C _ 4-S 5 7 8 1 5 6 8 A 0 0 0 4 4 7 7 / E 0 0 0 0 0 0 0 K _
FLani Comprin VanvA Mna and Ahil#ipt nip!iae fTier m Fnem FM do1 A Facility- St Lucie Date of Exam- 6 22-98 Exam levet SRO Category K/A # Topic imp. Points 2 1.12 Bases for minimum temperature for enticality 40 1 Conduct of 21.1 , Overtime limitations 38 1 213 Shift turnover during a surveillance 34 1 2 1.12 Operator action on power excursion 4.0 1 2.1. 7 Overriding ESFAS signals 44 1
) 2.1.
Total I 2213 Process for lifting leads 38 1 1 2212 Action for a pump in alert range 34 1 Equipment Control 2211 Time limit for Temporary Changes 34 1 2213 Human Clearance requirements 38 1 22 22 Total 231 Exit requirements for RCA 30 1 232 Screening of RWPs (ALARA) 29 1 4 Radiation Control 234 Dose limits for turkey point people working at PSL 3.1 1 2310 Cnterial for local evacuation 33 1 l 23 23 Total 2422 Pnonty of Safety Functions in EOP 15 40 1 Emergency 244 RCS leak at a low mode condition 43 1 Procedures and Plan 2443 Communications dunng an emergency 35 1 4 2440 Event leading to Alert classification 40 1 24 1 l Total 17 Tier 1 Target Point Total (RO/SRO) - 13/17 l l
- I i
v.-.-.~-. ~- ~ . - - - . . . . - - . - . -- F 4 i l ES-401 PWR RO Examination Outline Form ES-401-4 3 I
)
a
~
Facility: St. Lucie Date of Exam: 6/22/98 Exam Level: RO ~ I K/A Category Points - ; Tier Group . Point - K K K K K K .A A .A A G '
-Total 1 2 3 4 5 -6 1 2 3 4 -
1 1 2 2 3- D T - M 4 3 & e% -2 16 , Emergency & 2 3 2 4 N ' 4 2 0;Id '2 '2 17 Abnormal Plant ., e g l
. 3 1 1
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- @,, 1 3 >
Evolutions r Tier Totals 6 4 8 @ ' 8 5' 5 36 1 3 2 2 2 1 2 3 2 2 2 2 23 - 2- 2 3 2 2 2 2 20 2 1 1 1- 3 1
ant 3 2 1 1 1 2 1 8 ns _
;i w,,.x w:
Tier Totals 7 3 3 4 4 3 7 4 5 6 -5 51 l
,. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 ;
13 I 4 3 3 3 Note: . Attempt to distribute topics among all K/A categories; select at least one topic from l I every K/A category within each tier.
. r j -
Actual point totals must match those specified in the table. j j . Select topics from many systems; avoid selecting more than two or three K/A topics i
- from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline. ! j - The shaded areas are not applicable to the category / tier. l I I + i l NUREG-1021 - 30 of 39 Interim Rev. 8, January 1997 i ,, i
- e i
i t i < l' ! l. , i DISTRIBUTION CODE i .. A070 j
- . - - - - , - . - . . . . ._- . - _ - _ _ _ _ _ _ _ _ . - - - _ _ _ - - - - - - - - - - - - - - - _ _ - ~ _ - -
E ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutons - Tier 1/ Group : E/ APE # / Name / Safety Functxan K1 K2 K3 A1 A2 G K/A Topic (s) Imp. Points 000005 inoperable / Stuck Cont.~>l Rod / I X AA101/ Controf rod interlocks 36 1 000015/17 RCP Malfunctions / IV X X AA1.02 / CIAS effect on RCPs 28 1 AK101/ Actions that would inhibit natural circ 44 BW/E09, CE/A13 W/E09&E10 Natural Circ. / IV X AK1.2 / Cooldown rate w/SG isolated 32 1 000024 (mergency Briation / I X X AK2.01/ Loss of power, method of Emergency Boraton 27 1 40 1 G2 4 49 / Entry cond:tions to E B procedure 0000.Y> Loss of Component Cooling Water / Vill X AA2 01/ Locaton of CCW leak 29 1 000027 Pressurizer Pressure Control System X AK2 03 / Effect on sohd operation with letdown failure 26 1 Malfuncton / lil 000040 Rupture(BW/E05;
- ExcessweCE/EOS WiE12)/ Steam Heat ransfer IV Line X AA1.04 / Closure logic of MSIVs 43 1 CE/A11; W/E08 RCS Overcoohng - PTS / IV 000051 Loss of Condenser Vacuum / IV 000055 Station 531ackout / VI X E K3 02 / Exit conditions for Staton Blackout 43 1 000057 Loss of Vital AC Elec Inst. Bus / VI X AA214 / Loss of normal and altemate power supplies 32 1 000062 Loss of Nuclear Service Water / IV ,
000067 Plant Fire On-site / IX X G2.4 26 / Fire team laader requirements 29 1 000068 (BW/A06) Control Room Evac / Vill X AK3 03 / Status of AFW controls after isolaten 37 1 000069 (W/E14) Loss of CTMT Integnty / V X AA2 01/ Ident:fcaten of loss of containment integnty 37 1 000074 (W/E06&E07)Inad Core Coonng / IV X EA1 16 / Abil:ty to identify core uncovery 44 1 BW/E03 Inadeouate Subcoolino Margin / IV 000076 High Reactor Coolant Actrwity / IX X AK3 06 / Operator response to RCS high actwity 32 1 BW!A02&A03 Loss of NNi-XN / Vil K!A Category Totals: 2 2 3 4 3 2 Group Point Total 16 i
ES-401 PWR RO Examination Outhne Form ES-401-4 Emergency and Abnormal Flant Evolutions - Tier 1/ Group 2 E/ APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) Imp. Points 000001 Continuous Rod Withdrawal / I X AK103 / Effects of continuous rod withdrawal on Rx power 39 1 000003 Droppa d Control Rod / I X AK3 04 / Actions for 2 dropped rods in mode 3 38 1 000007 (BW/E02&E10; CE/E02) Reactor Trip - X EK2.1/ Venficahon of Safety Functions with power loss 3.3 1 Stabilization - Recovery / 4 000008 Pressunzer Vapor Space Accident / lil X AK3 03 / Shutdown requirements for PORV ieakage 41 1 000009 Small Break LOCA /111 X EA2 01/ Reindiation of Si fkr.v upon loss of subcoolina 42 1 000011 Large Break LOCA / Ill X EA1 11/ Long term coolina method 42 1 W/E04 LOCA Outside Containment / Ill BW/E08; W/E03 LOCA Cooldown/ Depress / IV W/E11 Loss of Emergency Coolant Recire / IV W!E02 Si Termination I til 000022 Loss of Reactor Coolant Makeup /11 X AK3 02 i Alternate Boration kneup 32 1 000025 Loss of RHR System / IV X AA1 10 / SDC suction operation with instrument failure 31 1 000029 Anticipated Transient w/o scram / I 000032 Loss of Source Range NI / Vil X AK2 01/ Boron dilution alarm from source rance failure 27 1 000037 Steam Generator Tube Leak / Ill X AK3 07 / difference between leak and rupture proc.edures 42 1 000038 Steam Generator Tube Rupture /111 X X EK1.03 / Inverted dena t a'ter SG isolation 39 1 EA t 02/ Indications of SGT R/ feed flow, steam flow 42 1 000054 (CE/E06) Loss of Main Feedwater / IV X X AA2 05 / System in manual with plant change 35 1 37 1 G2 4 21 / SG indications on TLOF BW/E04. W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / IV 000058 Loss of DC Power / VI X G2 4 49 / IOAs for loss of DC bus 40 1 000059 Accidental Liquid RadWaste Ret / IX 000060 Accidental Gaseous Radwaste Ret /IX 000061 ARM System Alarms / Vil X AA101/ Loc for automanc actons of FHB ventdabon 36 1 W/E16 Hgh Containment RadiatKm / IX CE/E09 Funct:onal Recovery X EK12 / entry to EOP-15 32 1 ,l K!A Category Point Tota:s' l3 2 4 4 2 2 Group Po:nt Total 17 b _ _ __ ,.
I K W W C B B B 0 0 0 0 0 0 0 0 E 9 / A / / E W W W 0 0 0 0 S E E / A 0 0 0 0 4 l ! / C 1 5 1 3 1 A A E 6 5 3 2 at 6 0 0 1 5 6 6 8 1 e C S 7 5 3 ( g E & L L B P _ o o t e x F E E o o e r E _ r n a c ol m s s s s W s / y t a m e o e 1 4 / s A _ P ni s s d g r o o A u P _ E i f f oi m G n e 0 r E . n e e R g n O ni O 8
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F ES-401 PWR RO Examination Outline Form ES-40H Plant Systems Tier 2/ Group 1 System 8 / Name K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G K/A Topic (s) Imp Points 001 Control Rod Drive X X K6 02 / Function of ACTM modules 28 1 A212 / Actions for eroneous ECP 36 1 003 Reactor Coolant Pump X X K4 04 / Cookiown after trip, reason 2.8 1 A4 01/ und dWerence in sealiniection 2.8 1 004 Chemical and Volume Control X X K3.05 / Charging pump failure 38 1 A1 11/ Auto actions for Letdown leak 30 1 013 Engineered Safety Features Actuation X X K5.02 / SIAS block logiu 2.9 1 K2 04/ Cond:tions causing ESFAS actu 36 1 015 Nuclear instrumentation X X K410 / operation of comparator averager 3.2 1 A103 / adjustment of nuc-delta 1 37 1 017 in-core Temperature Monitor X K101/ rnethod of monitoring LHR at low 32 1 power 022 Containment Cochng X X K2 01/ Unit differences of power supplies 3.0 1 A4 01/ response to SIAS 36 1 025 Ice Condenser 056 Condensate X X K103 / Low flour, affect on MFW 2.6 1 G2128 / C pump transfer perm;ssive 32 1 059 Main Feedwater X X A103 / Permissrves for LPFWS 2.7 1 G2 4 48 / Feed system response to powM loss 35 1 061 Auxihary/ Emergency Feedwater X X K3 02 / reset after manualinitiaton 4.2 1 A3 04 / AFW lockout on LOOP 41 1 068 Liquid Radwaste X K610 / Actions if rad man.1or is lost 25 1 071 Waste Gas Disposal X K104 / Auto termination of release 31 1 . 072 Area Raduation Monitoring X X K2 05 / main steam kne indications post inp 28 1 A4 03 / Containment evac alarm lon:c 31 1 K/A Categorv Point Totals: 3 2 2 2 1 2 3 2 2 2 2 Group Point Total- 23
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ES-401 PWR RO Examination Outhne Form ES-401-4 Plant Systems - Tier 2/ Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic (s) Imp Points 002 Reactor Coolant X X K5.11/ RCS ch es on turbine change 40 1 A105 / RCS tow f trrp inputs 34 1 006 Emergency Core Cooling X A107 / Effect of transmitter failure 33 1 010 Pressurizer Pressure Control X A4 02 / Heater restoration.ESDE/ LOOP 36 1 011 Pressurizer Level Control X K2.02 / Avaliability of heaters on bus loss 31 1 012 Reactor Protection X K5 01/ ASGTinp parameters 33 1 014 Rod Position indication X A2 04 / Difference of ind cation of RPIS 34 1 016 Non-nuclear Instrumentation 026 Containment Spray X G2 2 22 / Tech spec requirements for CSS 34 1 029 Containment Purge X A3 01/ CPS rsolation on CIAS 38 1 033 Spent Fuel Pool Cooling X A2 02 / SFPCS response to LOOP 2.7 1 035 Steam Generator X K5 01/ ATfect of SGBD adjustment 34 1 039 Main and Reheat Steam X X K1.02 / Operation of ADVs with MSIS 3.3 1 3.1 1 A3 02 / isolation of aux steam 055 Condenser Air Remova! 062 AC Electrical Distributen X K3 02 / undervolatage response by EDG 41 1 063 DC Electrical Distnbution X K4 01/ clignment of AB bus 27 1 064 Emergency Diesel Generator X X A4 01/ control of EDG in isochronts mode 40 1 K6 07 / E DG start w!ar recievers oos 27 1 073 Process Rad.ation Monitonng X K101/ less of containment PIG 36 1 1 075 Circulating Water X G2 4 4 / DP between condensers trip 40 1 079 Station Air 086 Fire Protection X A105 / Unit 2 FPS water source 29 1 K/A Category Point Totals: 2 1 1 1 3 1 3 2 2 2 2 Group Point Totat 20 iw
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t ES-401 Generic Knowledge and Abihties Outline (Tier 3) Form ES-401-5 Facility- St Lucie Date of Exam: 6-22-98 Eram Level: RO Category K/A # Topic imp Points 2.1.1 Fitness for duty on overtime callout 37 1 g 2.11 Overtime hmitations 3.7 1
""* 213 Shift turnover during a surveillance 30 1 21.1h Operator action on power excursion 2.9 1 2.1.
2.1. Total 2 2.13 Process for hfting leads 36 1 2.212 Action for a pump in alert range 30 1 C 01 2 2.11 Time limit for Temporary Changes 2.5 1 22. 22 22 Tota! 2.31 Exit requirements for RCA 26 1 23.2 Screening of RWPs (ALARA) 2.5 1 Radiation Control 234 Dose limits for turkey point people working at PSL 25 1 23 23 23 , l Total 2422 Priority of Safety Functions in EOP 15 30 1 244 RCS leak at a low mode condition 40 1 Emergency edures and 2442 Communications during an emergency 2.8 ha 1
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24 l l 24 l l 24 Total 13 Tier 1 Target Point Total (RO/SRO) 13/17 l l
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i U.S. Nuclear Regulatory Commission i Site-Specific i Written Examination :
)
Applicant information Name: Region; 11' Date: Facility / Unit: St. Lucie 1/2 l License Level: RO Reactor Type: CE j Start Time: Finish Time: I instructions
- Use the answer sheets provided to document your answers. Staple this cover
- sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected four hours after the i examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results .* Examination Value Points 1 I Applicant's Score Points Applicant's Grade Percent DISTRIBUTION CODE A070
~. . .. . ._ -,
t NRC RULES AND GUIDELINES FOR WRITTEN EXAMINATIONS During the administration of this exam, the following rules apply: PART A - GENERAL GUIDELINES ,
- 1. Cheating on any part of the examination will result in a denial of your- ,
application and/or action against your license.
- 2. If you have any questions concerning the administration of any part of the ,
examination, do not hesitate asking them prior to starting that part of the test. '
- 3. SRO applicants will be tested at the level of responsibility of the senior shift position (ie NPS, ANPS) t
- 4. You must pass every part of the examination to receive a license or to -
continue performing license duties.
- 5. The NRC examiner is not allowed to reveal the results of any part of the-examination until they have been reviewed and approved by NRC management. Grades provided by the facility licensee are preliminary until approved by the NRC. You will be informed of the official examination results -
about 30 days after all examinations are complete. PART B - WRITTEN EXAMINATION GUIDELINES
- 1. After you complete the examination, sign the statement on the cover sheet -
indicating that the work was your own and you have not received or given assistance in completing the examination. 1
- 2. To pass the examination, you must achieve a grade of 80 percent or greater.
Every question is worth one point. k
- 3. For initial examinations, the time limit for completing the examination is FIVE ,
hours.
- 4. You may bring pens, calculators or slide rules into the examination room. Use only black ink to ensure legible copies. i
- 5. Print your name in the blank provided on the examination cover sheet and I answer sheet. You may be asked to provide the. examiner with some form of positive identificaticn.
- 6. Mark your answers on the answer sheet provided and do not leave any question blank. Use only the answer sheet provided and do not write on the ' l back side of the.pages. If you decide to change yout original answer, draw a single line through the error, enter the desired answer, and initial the change.
I 1
- _ . _ ~ . _ _ _ . _ . _ _ __ _ . . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ _ _ _ . f L
- 7. If the intent of the question is unclear, ask questions of the examiner only.
- 8. Restroom trips are permitted, but only one applicant at a time will be permitted to leave. Avoid all contact with anyone outside the examination room to eleiminate the appearance or. possibility of cheating. -
- 9. When you complete the examination, assemble a package including the examination questions, examination aids, answer sheets and scrap paper and give it to the proctor. Remember to sign the statement on the cover sheet i indicating that the work was your own and you have not received or given assistance in completing the examination. The scrap paper will be disposed of immediately after the examination.
- 10. After you have turned in your examination, leave the examination area as defined by the proctor. If you are found in this area while the examination is still in progress, your license may be denied or revoked. i
- 11. Do you have any questions?
5 (
k USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 1 f An l&C Technician performing an ESFAS periodic has given Unit 2 an inadvertent CIAS on the "B" train. Numerous Reactor Coolant Pump alarms'are now present on RTGB 203. Which one of the following is an immediate cause of some of the alarms?
- a. ' Low CCW flow caused by isolation'of the RCP CCW valves.
- b. Low seal pressures caused by isolation of controlled bleedoff.
- c. Low oil reservoir level caused by isolation of instrument air.-
- d. High seal temperatures caused by isolation of seal cooler inlet valves.
e 1
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 2 A large break LOCA has occurred on Unit 1. Due to a loss of offsite power and subsequent emergency diesel generator failures, ECCS flow has been nonexistent for 20 minutes. Containment pressure is 20 psig. Which of the following indications could best be used by the ROs to confirm core uncovery is occurring?
- a. Excore neutron detectors indicate offscale high.
- b. QSPDS RCS saturation margin indicates 23 F superheat.
- c. Core exit thermocouple temperature indicate 350 F.
- d. All reactor vessel monitors (1-8) indicate voids.
2
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 3 Unit 2 tripped from 100% power. Reactor power is 5X10"% as indicated on Wide Range Instrumentation. Which of the following correctly describes the status of the Nuclear Startup Channels at this time? The Startup Channels:
- a. are energized. They automatically energize at 10% power.
- b. are not energized. They will energize if the switches are placed in "on".
- c. are energized. They automatically energize on the reactor trip signal.
- d. are not energized. They will not energize if the switches are placed in "on" 3
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 4 , Unit 1 is in Mode 2 with a reactor startup in progress. The "A" channel Boron Dilution Monitor is in alarm due to an instrument power supply failure. Which of the following instruments is deenergized?
- a. The Boronometer
- b. The "A" Log Startup Channel
- c. The "A" Wide Range Log Safety Channel
- d. The "A" Appendix R Neutron Monitor e
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 5 . 1 The following conditions exist: Unit 1 is performing a plant cooldown due to an unidentified RCS leak of 3 gpm.
- ESFAS channel MC Low Pressurizer Pressure SIAS has failed high and has been BYPASSED.
No other malfunctions or bypassed channels exist Which of the following correctly describes the SIAS block permissive logic considering current plant conditions? The SIAS block permissive will activate:
- a. when three ESFAS channels are <1700 psia.
- b. when two ESFAS channels are <1836 psia.
- c. when two ESFAS channels are <1700 psia.
- d. when three ESFAS channels are <1836 psia.
5
'USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 6 f Unit 1 has come off line due to a CCW leak on 'the seal heat exchanger on 182 RCP.
'After the reactor was tripped, the 182 RCP was stopped. The ANPS has directed a plant depressurization to 1850 psia. Which of the following is the reason for this ;
direction? !
- a. To meet pressure requirements for 3 pump operation. !
i
- b. To ensure seal integrity after CCW is isolated to the seal heat exchanger-
- c. To reduce lower seal cavity temperature.
- d. To allow adequate seal' injection flow. l
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 7 The following conditions exist for the reactor startup of Unit 1: Estimated Critical CEA position: Gp. 7 @ 60" Current CEA position: Gp. 5 @ 74" ICRR indicated Critical CEA position: Gp. 6 @ 40" Which of the following correctly describes the action to be taken by the RO performing the reactor startup?
- a. Insert CEAs to -500 PCM of current position
- b. Continue to withdraw CEAs, resample RCS C3.
- c. Position CEAs to ECC - 500 pcm.
- d. Continue until Criticality or ECC + 500 pcm.
I i 7 I l I l l l
. - l
I USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 8 Unit 2 is at 80% steady state power. Number four turbine governor valve strokes fully open. Assuming no operator action, which of the following correctly describes primary plant response?
- a. Delta-T power increases, ASI becomes more negative, letdown flow decreases
- b. Delta-T power decreases, ASI becomes more negative, letdown flow increases
- c. Delta-T power increases, ASI becomes more positive, letdown flow increases
- d. Delta-T power decreases, ASI becomes more positive, letdown flow decreases 8
-i i
1 USNRC REACTOR OPERATOR LICENSE EXAMINATION .l l 1
- Question 9 j
'l The bistable for RCS Low Flow reactor trip has been removed from RPS channel"D"
- for I&C work.. Which one of the following identifies the instruments and direction of ~ !
failure that would cause a reactor trip on RCS Low Flow with the RPS in its current configuration?
- a. "A" channel Reactor Coolant Pump differential pressure (PDT 1110 & !
1112) deenergizes. ,.
- b. "A channel Steam Generator differential pressure (PDT 1111 & 1121) ;
fails low
- c. "A" channel Reactor Coolant Pump. differential pressure (PDT 1110 &
1112) instrument tap develops a leak j
- d. "A" channel Core differential pressure (PDT 1124W & 1124Z) :
deenergizes. i
?
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USNRC REACTOR OPERATOR LICENSE EXAMINATION , Question 10 5 P t ] l- A loss of offsite power has occurred on Unit 2. Both Emergency Diesel Generators 1 are running. .Which of the following correctly describes the diesel generator control adjustments that can be made by the operator at this time?
, -i The operator; i
i a, cannot adjust diesel generator frequency or voltage,
- b. can adjust diesel generator frequency, cannot adjust diesel generator '!
voltage,
- c. can adjust diesel generator frequency and voltage. ,
- d. cannot adjust diesel generator frequency, can adjust diesel generator voltage.
b s-10 j q ____a . c .-
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 11 The following conditions exist: Unit 2 is in the process of a power ascension following a refueling outage. Generator output is 170 MW The transfer from single to sequential valve has just been comp loted The impulse feedback loop is in service While withdrawing control rods for ASI control, a 30 second continuous rod withdrawal occurs until the RO places the CEDMCS panel in "Off" No other operator action is taken and no reactor trip occurs Which one of the following parameters will return to essentially the same value as it was prior to the event?
- a. RCS Tavg
- b. Reactor Power
- c. Pressurizer level
- d. Steam Generator Pressure l
I 11
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 12 The following conditions exist: Unit 2 is operating at 100% power V 1202 Code Safety tailpipe temperature is increasing Quench tank volume is increasing at a rate of 2 GPM Which of the following correctly describes the Technical Specification leakage type and the requireme:it for this situation?
- a. Pressure boundary leakage that requires shutdown.
- b. Identified leakage that does not require shutdown.
c, Pressure boundary leakage that does not require shutdown. 2
- d. Identified leakage that requires shutdown.
e 12 l l I
USNRC REACTOR OPERATOR LICENSE EXAMINATION i Question 13 I A large break LOCA has occurred on Unit 1. All of the actions of 1-EOP-3 have been performed, and the NPS is consulting with the TSC as to the initiation of long term cooling. Which of the following correctly describes the method of long term core l cooling in this situation? I l l l a. Operation of the Shutdown Cooling System. l
- b. Cooled Containment Spray water directed to the suction of the HPSI pumps.
- c. Simultaneous Hot and cold leg injection in conjunction with RAS. J
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- d. Full HPSI flow per Figure 2 of 1-EOP-99.
l ' l I l 1 I 13
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- USNRC REACTOR OPERATOR LICENSE EXAMINATION
.i ! j Question 14 1 i 1- l J
- A 150 gpm RCS leak has resulted !n a reactor trip on Unit 2. An RCS cooldown and -
2 depressurization is being performed . HPSI throttling criteria has been met, HPS! { throttled and LPSI secured. While performing safety functions, the RO notes the ; following parameters: 1 l . Pressurizer pressure: 1400 psia 4 RCS That temperature: 586 F , RVLMS level: 3-8 covered 3 SG levels: 12% NR with feed available ; { Cooldown Rate: 75 F/hr , Considering current plant conditions, which of the following would be the correct
- operator action at this time?
l i a. Continue the cooldown at the present rate. i ! b. Manually initiate SIAS, continue the cooldown. 1 l c. Increase the cooldown rate to < 100 F/hr. 1 l d. Manually start both HPSI pumps, open all header valves, continue the . 1 cooldown. I l 2 J i l 14 2 t.
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USNRC REACTOR OPERATOR LICENSE EXAMINATION , Question 15 s a The following conditions exist: Unit 1 is at 60% power FCV-9011 (1 A Main Feed Reg Valve) has been pinned in place for controller changeout FCV-9005 (1 A 15% bypass valve) is in auto at 75% output for level control No other equipment malfunctions exist if power is lost to FCV-9005, which of the following describes the response of 1 A Steam Generator level? (assume power remains constant and no operator action) 1 A Steam Generator level will: i
- a. increase until the high level override setpoint is reached.
a
- b. decrease until low level reactor tri.: is reached.
1 . c. increase until high level turbine trip is reached.
- d. rernain constant.
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, USNRC. REACTOR OPERATOR LICENSE EXAMINATION i i
- Question 16 ,
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- =;
i : The 18. condensate cump has been taken out of service for motor replacement.. The i NPO is in the process of transferring the 4.16KV power to the 1C condensate pump. l Which one of the following actions must the NPO perform to enable the transfer key to l' 1 be released from its switch and energize the transfer permissive circuit? i ! ). a. insertion of the Close Fuses in the 1B condensate pump breaker. i' ,i <
- b. Removal of the Trip Fuses from the 18 condensate pump breaker.
t l c. Removal of the Close Fuses from the 18 condensate pump breaker.
- i
- d. Insertion of the Trip Fuses in the 18 condensate pump Dreaker.
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I ' USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 17 4 Which of the following correctly describes the configuration of the Unit 1 Containment Cooling System during normal, full power conditions? Three fans running:
- a. in fast speed, with CCW supplied to three coils.
- 5. in normal speed, with CCW supplied to four coils.
- c. in fast speed, with CCW supplied to four coils.
- d. in normal speed, with CCW supplied to three coils.
17 l l
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 18 Unit 2 has tripped from 100% power. A full AFAS actuation has occurred, and the RO has throttled AFW to 150 gpm per S/G. The 2A Steam Generator Narrow Range instruments on the A and C channels have failed low. Assuming no operator action, which of the following describes the response of the A side AFW system?
- a. At 29% NR indication, AFW flow to the 2A S/G automatically isolates, the header valves must be manually opened to reestablish flow,
- b. AFW flow to the 2A S/G remains in service and will continue to fill the 2A S/G until it is filled solid.
- c. AFW flow to the 2A S/G automatically isolates on Rupture ID due to the failure of the level channels, AFAS-1 must be manually actuated to reestablish flow
- d. At 29% NR indication, AFW flow to the 2A S/G automatically isolates, the header valves automatically re-open at 19.5% NR.
l l 18 1
USNRC REACTOR OPERATOR LICENSE : EXAMINATION Question 19 The following conditions exist: Unit 1 is at 100%, steady state power Condenser Air Ejector monitor is in alarm
- 18 Steam Generator Blowdown Monitor is trending up Which of the following Main Feedwater control system indications would the RO most likely see?
- a. Feed flow greater than steam flow with level increasing.
- b. Feed flow and steam flow matched with level increasing.
- c. Feed flow less than steam flow with level constant.
- d. Feed flow greater than steam flow with level constant.
19
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 20 J l Unit 2 is in Mode 5, RCS pressure is at 275 psia. Which of the following would cause a Safety injection tarik outlet valve (s) to go open? (assume valves are energized and closed)
- a. RCS pressure is raised to 400 psia.
3 l
- b. The PIC Bypass keyswitch is taken to the bypass position.
- c. Pressunzer low pressure transmitter PIC-1104 fails high
- d. I&C inadvertently injects a low pressurizer pressure SIAS signal into the MA ESFAS cabinet.
l 20
. _ . . - - . .-. .. . . - . . - . ~ - . . . - . . . - - . . - _ - . - - - . - . - - . .
1 j USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 21 I I l The following conditions exist: l Unit 2 is at 100% steady state power. All plant systems are in their normal configuration 28 Spent Fuel Pool Cooling Pump is in service ; If a loss of offsite power occurred and the 28 Emergency Diesel Generator failed to start, which of the following statements correctly describes the status of the Spent Fuel Pool Cooling System?
- a. The 2A SFP Cooling pump autornatically starts on failure of the 2B pump. ,
to start, CCW flow is being provided to the in-service heat exchanger at this time. :
-t
- b. The 2A SFP Cooling pump must be started locally, CCW flow is being .
i provided to the in-service heat exchanger at this time,
- c. The 2A SFP Cooling pump automatically starts on failure of the 2B pump to start, CCW must be realigned from the opposite CCW header to ,
provide cooling flow. ' i
- d. The 2A SFP Cooling pump must be started locally, CCW must be j realigned from the opposite CCW header to provide cooling flow. -
i i i' 21 I t i il
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 22 The following conditions exist: ' Unit 2 tripped from 100% power due to a LOOP The 2A Emergency Diesel Generator tripped on overspeed SPTAs are complete Which one of the following is the method the board RO would use to maintain RCS heat removal from the PACB?
- a. "A" atmospheric steam dump in Auto / Manual, "B" atmospheric steam dump in Auto / Manual.
- b. "A" atmospheric steam dump in Manual / Manual, "B" atmospheric steam dump in Auto / Auto. ,
- c. "A" atmospheric steam dump in Auto / Auto, "B" atmospheric steam dump in Manual / Manual.
- d. "A" atmospheric steam dump in Auto / Auto, "B" atmospheric steam dump in Auto / Auto.
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 23 e Unit 2 is in Mode 6, returning from a refueling outage. The RO is performing a valve stroke test on HCV-15-1, primary makeup water to containment isolation valve. After stroking the valve closed, it fails to reopen. Which of the following is an immediate concern if HCV-15-1 cannot be opened? RMW is the source of water for ;
- a. pressurization of nozzle dams.
- b. the fire protection system in containment.
- c. makeup to the Quench Tank.
- d. RCS makeup for fill and vent.
23 l
. USNRC REACTOR OPERATOR LICENSE EXAMINATION , Question 24 The following conditions exist: Unit 1 is in Mode 6
- "A" train containment purge system is in service with suction aligned to the refueling cavity A fuel tundle has been damaged and bubbles are escaping from the l refueling cavity water level.
HP reports containment atmosphere activity levels of 100 MR. Which of the following describes the response of the Containment purge system? The containment purge system:
- a. remains in its current configuration.
- b. discharge is automatically aligned to the shield building exhaust system.
- c. suction is automatically aligned to the containment ring header.
- d. is automatically secured. ,
s. 24 1 1
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 25 The following conditions exist: Unit 2 is in Mode 6 Refueling upper cavity level is 4' Reactor head lift is in progress B train shutdown cooling is in service The ANPS directs the RO to maintain a minimum of 3000 gpm SDC flow Which of the following correctly describes the bases of Grection given by the ANPS? To provide:
- a. sufficient flow for RCS level reduction as the head is lifted.
- b. sufficient RCS mixing in the event of a RCS dilution event.
- c. sufficient RCS mixing to maximize SDC purification as the head is lifted.
- d. minimum flow requirements for one pump operation.
1 25
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 26 The following conditions exist: Unit 1 turbine startup is in progress Turbine speed is 1800 rpm Reactor power is 12% and holding for synchronization Which of the following correctly describes plant response if turbine speed was increased to 1910 rpm?
- a. The governor and reheat stop valves close.
- b. A turbine and reactor trip is generated.
- c. The governor and intercept valves close.
- d. A turbine trip only is generated.
26
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 27 The following conditions exist: i An ESDE has occurred on Unit 2 Containment pressure is 5.7 psig The 2B Containment Spray pump has failed to start No other equipment malfunctions exist Which of the following statements correctly describes the present status of the lodine Removal System? f
- a. The A and B Hydrazine pumps are running and providing flow to the suction of the A Containment Spray pump.
, b. Only the A Hydrazine pump is running and providing flow to the suction of the A Containment Spray pump. . c. The A and B Hydrazine pumps are running and providing flow to the discharge of the A Containment Spray pump,
- d. Only the A Hydrazine pump is running and providing flow to the discharge of the A Containment Spray pump.
27
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 28 OP 2-0640020 " Intake Cooling Water System Normal Operation" states that when starting an ICW pump on a depressurized header, the discharge valve should be AT LEAST 10 turns open. Which one of the following is the reason for that statement? To prevent:
- a. motor overheating
- b. seal damage to the pump
- c. water hammer in the system
- d. heat exchanger tube sheet damage 4
+
I 28 1
2 L USNRC REACTOR OPERATOR LICENSE EXAMINATION i Question 29
. A spurious switchyard fault has deenergized both 6.9 KV busses. The operators are .
maintaining the plant in Hot Standby on natural circulation. Which one of the following operator actions would reduce natural circulation flow? (consider each action serarately)
- a. Atmospheric steam dump controllers are adjusted from 30% output to 20% output.
b, Steam Generator level setpoints are adjusted from 65% WR to 50% WR
- c. Pressurizer spray is operated to reduce subcooling from 90 F to 40' F
- d. A second charging pump is started with no letdown bias adjustment.
l t g v. 29
.4 m
USNRC REACTOR OPERATOR LICENSE EXAMINATION , Question 30 Unit 1 is at 80% steady state power due to repairs to the 181 Circulating Water Pump. The RO notes the following indications while taking his hourly logs: Condenser Backpressure: (PI-10-78): 4.3"hg. Manometer Reading: 1.7"hg According to 1-01-21-02, " Circulating Water Normal Operations", which of the following describes the required action (s) to be taken by the control room crew?
- a. Place the 181 Steam Jet Air Ejector in service.
.b. Commence a power reduction until 1B condenser backpressure is<3.5"hg.
- c. Trip the Reactor and Turbine
- d. Expedite the restoration of the 181 Circulating Water Pump.
30
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 31 The following conditions exist: Unit 1 i; in Mode 3, reactor startup in progress Reg Graup 3 has been fully withdrawn The RCS is at critical boron concentration CEA #61 dropped fully into the core While attempting to recover CEA #61, CEA #69 slipped to 120" Which of the following actions would be the correct response for the present plant conditions?
- a. Notify I&C, realign both CEAs.
- b. Trip the reactor,
- c. Emergency borate to ensure adequate shutdown margin.
- d. Insert Reg Group 3 to LEL, notify I&C.
l i 31 i
l USNRC REACTOR OPERATOR LICENSE EXAMINATION - Question 32 Unit 1 is at 100% power when the 18 Steam Generator Low pressure MSIS measurement channelin the MA ESFAS cabinet fails low. Assuming no operator action, which one of the following events would cause the reactor to trip?
- a. The MA 1 A low stearn generator pressure MSIS measurement channel fails low.
- b. The MB 1 A low steam generator pressure MSIS measurement channel fails low,
- c. The MD 120V Instrument inverter trips due to an electrical fault
- d. The MC 18 MSIS measurement channel bistable is removed.
32 l i
I USNRC REACTOR OPERATOR LICENSE EXAMINATION l l Question 33 . The Unit 2 Low Power Feedwater System is dependant upon two parameter inputs to provide a permissive to the "X-FER TO MAIN" lights on the feedwater transfer switch. Which of the following parameters are the input to this permissive?
- a. SG Narrow Range Level and Feedwater Temperature l
- b. SG Wide Range Level and Neutron Flux
- c. SG Narrow Range Level and Neutron Flux
- d. SG Wide Range Level and Feedwater Temperature i
s l 4 I e 33
.USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 34 -
The Unit 1 RO is preparing to release the contents of the 1B waste monitor tank. The Unit 1 Liquid Rad Waste Monitor (channel R-6627) appears to be failed low. Which of the following is a correct statement concerning the status of a pending liquid release?;
- a. The Plant General Manager must approve the release permit.
- b. Two independent samples and rejet.se rate calculations must be performed :
prior to the release,
- c. The liquid release can be performed using Unit 2 Liquid Rad Waste Monitor.
- d. The liquid release cannot be performed until channel R-6627 is determined to be operable.
i r k A i- 34 E
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l l USNRC REACTOR OPERATOR LICENSE EXAMINATION , r > Question 35 l 4 l Unit 1 is in the proce.ss of a reactor / turbine startup. The RO is withdrawing group 7 CEAs at 128" when CEA #9 becomes mechanically bound. Assuming no other operator action, which one of the following correctly states the reason CEA group motion will stop if withdrawal continues?
- a. Upper Electrical Limit I
- b. CEA Motion Inhibit
- c. Group Out of Sequence I
- d. Upper Group Stop i
l 35 i
- . . . . .. . . . . - ..- .. . - . - .. - . . . . . . .~ , ~. .
t f USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 36 The following conditions exist:
- Unit 1 has tripped from 100% power due to a LOOP >
- 1 A Emergency Diesel has failed to start CEAs 42 and 39 are indicating UEL The ANPS directs the RO to perform an emergency boration 28 charging pump is running Which one of the following statements describes the correct actions IAW ONOP 1-0250030, " Emergency Boration"?
- a. Start 2B BAMT Pump, open V2514 (Emergency Borate Valve). .
- b. Hold close V2501(VCT Outlet Valve), hold open V2504 (RWT Makeup Valve)
- c. Start 2B BAMT Pump, open V2508 or V2509 (Gravity Feed Valves).
- d. Open V2508 o /2509 (Gravity Feed Valves), hold close V2501(VCT Outlet Valve)
I i l k l ! l
. 1 36 4
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USNRC REACTOR OPERATOR LICENSE EXAMINATION i Question 37 Which ONE of the following states a' condition in which the indicated pressurizer level would indicate HIGHER than actual level? -
- a. Pressurizer temperature greater than the temperature for which the level-transmitter was calibrated. i
- b. Rupture in the diaphragm of the Pressurizer level transmitter.
- c. Containment temperature lower than normal. ,
- d. Leak in the variable leg of the Pressurizer level transmitter.
)
a i i 37 I j
4 USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 38 Unit 2 is performing the actions of EOP-15. The RO has just aligned the 2A Charging pump to the A HPSI header. Which one of the following is the Safety Function that this lineup would be used to satisfy?
- a. RCS Inventory Control
- b. RCS Pressure Control
- c. Reactivity Control
- d. RCS and Core Heat Removal JI J
1 i 38
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 39 Unit 2 control room has been evacuated due to a fire. The operators manually tripped the reactor and turbine from 100% power and have carried out all IOAs of ONOP 2-0030135, " Control Room inaccessibility" prior to their exit. They are now performing their respective appendices. If all AFW normal / isolate switches were placed in isolate two minutes after steam generator levels reac7ed 19% NR indication, which of the following would be the condition of the AFW system when they arrive at the Hot shutdown Panel?
- a. All AFW header isolation valves open, no AFW pumps running
- b. No AFW header isolation valves open, all AFW pumps running
- c. All AFW header isolation valves open, all AFW pumps running
- d. No AFW header isolation valves open, no AFW pumps running I
l 4 i i i sL i i: 4 39 4 l l
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 40 An electrician, working on a 480V feeder breaker has deenergized the 1 AB MCC. Which one of the following correctly describes the condition of the 120VAC Vital SUPS at this time? , a. The static switch ABT has transferred to the alternate source and is supplying the Vital Bus.
- b. The Battery Charger is being directly supplied by its alternate source and is supplying the Inverter, which is supplying Vital Bus.
4 i
- c. The Inverter is being directly supplied by its alternate source and is supplying the Vital Bus.
- d. The 125 VAC Vital SUPS is in its normal configuration and supplying the Vital Bus 4
1
.l 40
USNRC hEACTOR OPERATOR LICENSE EXAMINATION Question 41 While operating in MODE 5 with the presscrizer solid and the RCS in an isothermal condition at 150 F, RCS prersure rapidly irecreases. Which one of the following could cause this pressure increase?
- a. Letdown pressure control valve diaphr gm ruptures
- b. Pressurizer heaters energize
- c. Shutdown cooling flow is inadvertently increased
- d. Letdown level control valve setpoint is inadvertently increased m
M L k 41
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 42 The followirg conditions exist: 1 A 125 VDC bus has been deenergized due to an electrical fault The ROs are performing Standard Post Trip Actions A cteam line break has developed on the 1 A Steam Generator 1A Steam Generator Pressure is 570 psig 18 Steam Generator Pressure is 890 psig No other failures are present Which of the following statements correct!y describes the status of the Main Steam isolation valves as reported by the board RO?
- a. The A MSIV is open, the B MSIV is closed.
- b. The B MSIV is open, the A MSIV is closed.
- c. Both A and B MSIVs are open,
- d. Both A and B MSIVs are closeJ.
l l 42 i
.1 1
USNRC REACTOR OPERATOR LICENSE EXAMINATION
. Question 43 ,
i Which one of the following conditions represents a loss of Containment Vessel ~ - Integrity for Unit 1 as defined in Technical Specifications? ,
- a. While at 100% power, a mechanic opens the outer containment airlock door to perform maintenance activities on the CLOSED INOPERABLE inner containment door without prior approval.
I
- b. While performing operability tests on the redundant containment vent header- :
valves (V-6554 and V-6555) at 100% power, one of the two valves (V-6554) , fails to completely close. ? l
- c. While at 100% power, the nitrogen supply valve to the Safety injection Tanks - '
isolation valve (V-6741) fails its required stroke time.
- d. While at 100% power, the outer containment airlock . door fails its leak rate test l and has to be opened to facilitate repairs that will take 2 hours.
l l l 1 ( I 1 P 43 f
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l l l l USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 44 l The following conditions exist: Unit 2 is at 100% power 2B QSPDS is out of service for electrical work A spurious switchyard fault has caused a loss of offsite power The 2A EDG failed to start All other equipment functioned as required Which Safety Function cannot be confirmed in EOP-1 by the ROs?
- a. RCS Pressure Control
- b. RCS Heat Removal
- c. Containment Isolation
- d. Maintenance of Vital Auxiliaries 44
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 45 The following Unit 1 conditions exist:
- The Reactor Coolant Letdown Monitor (channel 41) is in high alarm lodine 131 indication is steadily increasing Chemistry reports DEQ-131 is at .05 Micro Ci/ gram According to ONOP 1-0120032, " Excessive Reactor Coolant System Activity", which one of the following set of actions are required to be taken at this time?
- a. Reduce Rx power to <70%. Notify Chemistry to increase sampling frequency.
- b. Minimize letdown flow. Notify HP to survey the VCT area for increased radiation levels.
- c. Divert letdown flow to the Hold-up Tanks. Notify HP to survey the -5 RAB area for increased radiation levels.
- d. Maximize letdown flow. Notify Chemistry to increase sampling frequency.
k 45
USNRC REACTOR OPERATOR ' LICENSE EXAMINATION Question 46 Unit 2 is in a Station Blackout and the NPS is considering exiting 2-EOP-10 to an approved procedure that has been designated by the TSC. All safety functions for 2-EOP-10 are being maintained. Which of the following conditions would allow transition from 2-EOP-10 to the approved procedure?
- a. Unit 2 2A16.9 KV bus energized from a Unit 2 startup transformer.
- b. Unit 2 2A2 4.16 KV bus energized from a Unit 2 startup transformer.
- c. Unit 2 2A3 4.16 KV bus energized from 2A EDG.
- d. 1 A EDG supplying 2A3 4.16 KV bus via the SBO crosstie.
1 } 46
1 1 l I USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 47 The following Unit 1 conditions exist:
- Annunciator S-16, "CCW SURGE TK LEVEL COMP. B LOW' is in alarm.
The SNPO reports the CCW Surge Tank level is decreasing 1/2" every two . minutes The ANPS has directed entry into ONOP 1-0310030, " Component Cooling Water Off-Normal Operation", Appendix A, "CCW Leak Search" No other CCW alarms are present.
- Which one of the following CCW supplied components would be a possible source of the system leakage?
- a. Fuel Pool Heat Exchanger
- b. Containment Cooler HVS 1B i
- c. Sample Heat Exchanger 16
- d. Containment Cooler HVS 1D i l I
4 l L 47
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 48 The following conditions exist: A total loss of feedwater event has occurred on Unit 1 S/G levels are 14% on wide range indication
- The control room crew has exited EOP-6 and entered EOP-15,"RCS and Core Heat Removal", Success Path 4, "Once through Cooling" , After Success Path 4 is fully implemented, which one of the following is the correct i
action by the control room crew?
- a. Imple.nent EOP-6 and continue with feedwater restoration.
- b. Implement in EOP-15 starting at step 1.
- c. Remain in Success Path 4 until feed is recovered.
- d. Implement EOP-3, RCS inventory is now decreasing.
e 48
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 49 The following conditions exist: 1B Steam Generator has been diagnosed with a tube rupture An RCS cooldown to 523 F is completed 1B Steam Generator has been isolated per 1-EOP-99, Appendix R All RCPs are off ^ $ With cooldown in progress for an additional 30 minutes, which one of the following RCS That temperatures is correct if the maximum recommended cooldown rate is utilized? 'l
- a. 473 F
- b. 485.5 *F
- c. 498 "F
- d. 508 F i
a 49
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 50 Due to a condenser tube leak, The ANPS has directed entry into 1-ONP-22.01, " Rapid i Downpower", and has directed the ROs to commence a downpower at 20 MW/ minute. i Which one of the following is the procedurally correct method of reducing RCS Tavg? (Assume one BAM pump running)
- a. Open Boric Acid Load Control Valve V2525; cycle the running BAM pump to maintain Tavg. within 6.6 F of Tref.
- b. Open Emergency Borate Valve V2514; cycle V-2514 to maintain Tavg. within 6.6 F of Tref.
- c. Open Boric Acid Load Control Valve V2525; cycle V2525 to maintain Tavg.
- within 6.6 F of Tref.
- d. Open Emergency Borate Valve V' 514; cycle the running BAM pump to
. maintain Tavg. within 6.6 F of Tref. f t 4 50
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 51 A SBLOCA occurred on Unit 1 twelve hours ago. RCS pressure is currently 265 psia, and the ANPS had c'irected the ROs to place Shutdown Cooling in service when LT-1103 (RCS low range pressure indicator) failed high. Which one of the foliowing statements correctly describes the actions that must be taken to establish Shutdown Cooling (SDC) flow?
- a. Both A train SCC suction valves can be opened from the control room; the SNPO must manually open both B train SDC suction valves.
- b. Both A train and both B train SDC suction valves can be opened from the control room.
- c. One A train and one B train SDC suction valve can be opened from the control room; the SNPO must manually open one SDC suction valve on each train.
- d. One A train and one B train SDC suction valve can be opened from the control room; the SDC suction crosstie can be opened to establish SDC flow.
1 1 51 I
1 i 1 i i USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 52 Concerning the Unit 2 Fuel Pool Area Radiation Monitors: SA SB GAG 007 GAG 008 GAG 009 GAG 010 GAG 011 GAG 012 Which one of the following is the minimum condition that would cause automatic actions to occur in the Spent Fuel Pool Ventilation System?
- a. GAG 007 in ALERT, GAG 009 in ALARM
- b. GAG 009 in ALARM, GAG 012 in ALARM
- c. GAG 007 in ALERT, GAG 011 in ALERT
- d. GAG 008 in ALARM, GAG 010 in ALARM 52
- , - - - . - - . . - - - . . . - . - - .- ---. -. . - - . - ~ - . . . . . -
USNRC REACTOR OPERATOR LICENSE' EXAMINATION ; Question 53 f Unit 2 has tripped from 100% power. Upon AFAS actuation, the 2C AFW pump-tripped on overspeed, and the RO closed its associated header valves. The RO has_ throttled the A and B header valves so that flow to each S/G to 150 gpm. A system - disturbance causes the following sequence: 0000 Loss of offsite power 0009 2A EDG starts and loads 0010 2B EDG starts and loads 0040 2A EDG fully loaded 0042 2B EDG fully loaded
- Assuming no operator action, which of the following correctly describes the status of' the AFW system header valves at 00607
- a. All header valves (A, B, and C) fully open. .
~
- b. A and B header valves at the 150 gpm position, C header valves closed.
- c. A header valve open, B Header valve closed, C header to A open, C header to B closed.
4 i j d. A header valve closed, B header valve open, C header to A closed, C header
- to S open.
l i F l ..a 4 2 t L 53 W - , - , - >.!-,, , ,,,.' n e , -- . ,
l l USNRC REACTOR OPERATOR L: CENSE EXAMINATION l I Question 54 ; 1 i
- A large instrument air leak has occurred on Unit 1. As PCV-18-5 (Unit 2 to Unit 1 Instrument Air Crosstie) is stroking open, it becomes mechanically bound in the full open position. Assuming no operator action, which one of the following statements correctly describes the system response?
- a. Unit 1 (PCV-18-6) crosstie will close at 85 psig decreasing, isolating i instrument air to Unit 2.
- b. Unit 2 instrument air depressurization is prevented by a check valve located in the crosstie line.
- c. Unit 1 station tu instrument air crosstie will automatically open at 85 psig decreasing to supply compressed air to Unit 1.
- d. Unit 2 instrument air system will depressurize as Unit 1 instrument air system depressurizes.
54
USNRC REACTOR OPERATOR OCENSE' EXAMINATION l Question 55 i P Unit 2 is at 100% power,2A charging pump was running with 2B charging pump
- selected as backup. 2A charging pump tripped due to a faulty breaker. The following conditions now exist:
28 charging pump was started to replace 2A charging pump 2A charging pump control switch was placed in the "OFF" position if pressurizer level setpoint is increased to 69%, which of the following is a correct description of the current CVCS configuration (assume no other operator actions)? :
- a. 28 charging pump running with no change in letdown flow ;
i I
- b. 2B and 2C charging pumps running with minimum letdown flow. +
- c. 2B charging pump running with minimum letdown flow.
P
- d. 28 and 2C charging pumps running with no change in letdown flow. ,
i 5 4 i l i 3 l .' i
- . 55 h
a
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 56 Unit 2 is at 100% power. The feedwater control for 2A S/G is in manual for I&C calibration. 2A steam generator level is currently 65% WR. Which of the following would be the response of the plant if turbine power was reduced to 90%7 (Assume no operator action) 1 A Steam Generator Level will:
- a. stabilize at a higher level with feed flow greater than steam flow,
- b. remain constant at 65% WR as the Main Feed Reg Valve cycles.
- c. increase to 82% WR and and remain at approximately that level as the Main Feed Reg Valve cycles,
- d. increase to HI-Hi Level resulting in a Turbine / Reactor trip.
56
~ l l l 1 USNRC REACTOR OPERATOR LICENSE EXAMINATION l Question 57 ! Unit 2 is in Mode 3 Which one of the following conditions will automatically terminate a Waste Gas release on Unit 27
- a. I&C inadvertently initiates a full SlAS
- b. Waste Gas Radiation Monitor (PAG-203) in Alert
- c. Loss of power to Met Tower equipment
- d. Loss of Fire and Security SUPS inverter 57
l USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 58 Which of the statements correctly describes the power supply arrangement of the Unit 1 and Unit 2 Containment Cooling Systems?
- a. The 2A2 480\ .oad Center provides power to 2 containment coolers; the 1 A2 480V Load Center provides power to 2 containment coolers.
- b. The 2A2 480V Load Center provides power to 1 containment cooler; the 1 A2 480V Load Center provides power to 1 containment cooler.
- c. The 2A2 480V Load Center provides power to 2 containment coolers; the 1 A2 480V Load Center provides power to 1 containment cooler.
- d. The 2A2 480V Load Center provides power to 1 containment cooler; the 1A2 480V Load Center provides power to 2 containment coolers.
58
- - -.- - ._- . ....--...~.- .- -
s, USNRC REACTOR OPERATOR ' LICENSE EXAMINATION Question 59 ! The following conditions exist: Unit 1 Turbine Startup is in progress ; Generator output is 150 MW + 1 A Condensate pump and 1A Main Feed pump are in service Total feedwater flow is 10,500 gpm 1 A Main Feed pump control switch is in the " Auto Recirc" position Which of the followirg correctly describes the system response if FCV-12-1
' (condensate recirc regulator) stroked to its full open position? 3
- a. 1 A Condensate pump recirc valve strokes full open and maintains system flow.
- b. 1 A Condensate pump trips on low flow.
- c. 1 A Main Feedwater pump recirc valve strokes full open and maintains system flow.
i
- d. 1 A Main Feedwater pump trips on low flow.
t 59 {
l USNRC REACTOR OPERATOR LICENSE EXAMINATION ! l Question 60 I Unit 1 is in the process of a Reactor Startut .he RO is withdrawing Group 7 in Manual Sequential when Annunciator K-26, "CEDMCS TRBL/ CONT GRIPPER VOLTAGE HIGH" locks in. Which of the following correctly describes the probable , cause of this alarm?
- a. The Coil Power Programmer for a specific CEA has failed and any further movement to Group 7 will result in a dropped CEA.
- b. Continuous group motion was for >30 seconds, the gripper coils are experiencing a high voltage condition.
- c. The ACTM module for a specific CEA has sensed an abnormal condition, holding voltage is being applied to its Upper Gripper.
- d. The Coil Power Programmer has sensed a fault to a specific CEA., the faulted CEA has been transferred to the Hold Bus.
1 60 ! l l
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 61 Which one of the following statements correctly describes the RCP Oil Lift Pump system following a LOOP /SIAS with both Diesel Generators supplying power to their associated emergency busses? , Each RCP:
- a. will have no oil lift pumps running, but only one will be available for manual start.
- b. will have both oil lift pumps running.
- c. will have no oil lift pumps running, but both will be available for manual start.
- d. will have one oil lift pump running P
e d 61
j USNRC REACTOR OPERATOR LICENSE EXAMINATION' ,
- _ Question 62-
- i
!- I 4 4
- 2-EOP-6, " Total Loss of Feed" addresses the use of a Condensate pump to establish.
feed to the steam generators if certain conditions are met.. ~ Which one of the following
- situations would warrant the use of a Condensate pump? ,
4
- a. - A loss of both non-vital 4160 KV busses has occurred and steam generator pressures are 600 psig.
1 l b. A trip from 80% power has occurred and Steam Generator levels are 45% ;
- wide range.
e
- c. A trip from 30% power has occurred and Steam Generator levels are 35% -
! narrow range. $ d. Steam Generator levels are 25% wide range and steam generator pressures l are 650 psig. i F 4 T 5 62
i USNRC REACTOR OPERATOR LICENSE EXAMINATION i Question 63' isolating a faulted SG during implementation of 1-EOP-04, " Steam Generator Tube Rupture" may result in Control Room indication of an " inverted AT" (T-cold > T-hot). Which one of the following statements describes how this indication would be developed?
- a. During forced circulation with only two RCPs, reverse flow in the idle loops inverts the indicated AT.
- b. During forced circulation with only two RCPs, reverse heat transfer from the isolated SG to the RCS inverts the indicated AT.
- c. During natural circulation using only one SG for cooldown, reverse flow in the idle loops inverts the indicated AT.
1 , d. During natural circulation using only one SG for cooldown, reverse heat transfer from the isolated SG to the RCS inverts the indicated AT. i 4 63
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 64 Unit 2 is performing a rapid unit shutdown due to a Steam Generator tube leak on the 2A Steam Generator. According to ONOP 2-0800030, " Steam Generator Tube Leak", under what conditions would the ROs be required to trip the reactor and turbine?
- a. Three of four TMLP pretrips are in alarm on the RPS.
- b. Pressurizer level cannot be maintained with 28 gpm letdown and all available charging pumps running.
c The difference between actual Pressurizer level and Pressurizer level setpoint exceeds 6 6%.
- d. Pressurizer level cannot be maintained with V-2522 closed and all available charging pumps running.
64
l I 1 USNRC REACTOR OPERATOR LICENSE EXAMINATION Ouestion 65 A fire has been reported in Me Unit 1 Turbine Switchgear room. The NWE (fire team leader) is currently at the si.e medical facility after being taken ill. Which of the following individuals can b6 used to fill the team leader vacancy? (assume shift is at minimum complement IAW AP 0010120, " Conduct of Operations")
- a. Unit 1 Desk RCO (qualified as SRCO)
- b. Unit 1 SNPO (qualified as SNPO)
- c. Unit 1 NPO (qualified as NPO)
- d. Unit 1 ANPO (qualified as SNPO) l I
l l 1 I ( 65 I
USNRC REACTOR OPERATOR LICENSE EXAMINATION i
!l Question 66 l
l I 1 The Unit 2 CCW Radiation Monitor has gone into an alarm condition. Further investigation revealed the solenoid flow control valve closed and isolated flow. Which of the following is the probable cause of this condition?
- a. Low CCW flow to the monitor
- b. High CCW radiation to the monitor
- c. Low CCW pressure to the monitor
- d. High CCW temperature to the monitor i
66
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 67 While inserting CEA Group 5 for ASI control at 132" , CEA #8 slips to 121" Which of l the following are the rod position indications for CEA #8 as seen by the RO7 1 l
- a. ADS - 132", DDPS - 121", Digital backup-132"
- b. ADS - 121", DDPS - 132", Digital backup-132"
- c. ADS - 132", DDPS - 121", Digital backup-121"
- d. ADS - 121", DDPS - 132", Digital backup-121" I
j 67 , l l
I USNRC REACTOR OPERATOR LICENSE EXAMINATION
. Question 68
~
The plant is at 65% steady state power to perform maintenance on a leaky turbine EH , line. Due to an increase in the EH leak,' the RO manually trips the reactor and ! turbine. Which of the following correctly describes the response of the Steam Bypass l Control System S seconds after the trip? (assume system in auto) l
)
- a. Rx trip quick open, followed by pressure modulation only; j 1
- b. No Rx trip quick open, temperature and pressure modulation only. ]
- c. Rx trip quick open, followed by temperature and pressure modulation.
- d. No Rx trip quick open, pressure modulation only.
'I 1
)
68
~1
s- - - - ___- _ _ - - ,---4, - - - - - -
A A USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 69 Unit 1 is at 100% power, steady atate.1 A and 18 steam generator pressures are at 890 psig. If a small steam leak inside containment were to occur, which of the } following ;s the minimum value that 1 A steam generator pressure would have to change to cause a reactor trip strictly on steam generator parameters?
- a. 13%
- b. 15%
- c. 30 %
- d. 33 %
69 i
USNRC REACTOR OPERATOR LICENSE EXAMINATION Quesdon 70 The following Unit 2 conditions exist: CCW surge tank Lo-Lo level switch (LS-14-6A) is valved out for replacement 2A CCW pump develops a large discharge flange leak The leak exceeds the capacity of makeup flow Assuming no operator action, which of the following correctly describes FIRST response of the system?
- a. "A" side N header valves (HCV-14-8A and HCV-14-9) close,
- b. 2A CCW pump trips on low suction pressure.
- c. "B" side N header valves (HCV-14-88 and HCV-14-10) close.
- d. 2A CCW trips on thermal overload.
i 70
J USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 71 i Unit 1 is in mode 3, RCS cooldown and depressurization in progress in preparation for l a refueling outage. Which one of the following actions must be taKan by the operators l if a safety related 125 VDC bus became deenergized? The operator must MANUALLY:
- a. close the Main Steam isolation Valves to prevent an uncontrolled cooldown of the RCS.
- b. Close the PORV block valves to prevent an uncontrolled depressurization of the RCS.
- c. close the Atmospheric Steam Dump Valves to prevent an uncontrolled cooldown of the RCS.
- d. close the Pressurizer Spray valves to prevent an uncontrolled depressurization of the RCS.
l 4 i
)
71
4 USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 72 The following conditions exist: Unit 2 is at 100% power Charging and letdown are in normal configuration Regen HX inlet pressure is 2250 Regen HX outlet pressure is 2200 if a 10 gpm leak occurs in the letdown line downstream of the regenerative heat exchanger, which one of the following automatic actions will occur as a result of the leak? (assume system in auto) Letdown flow:
- a. will decrease due to LCV-2110P closing.
- b. will isolate due to V-2516 closing.
- c. will increase due to LCV-2110P opening
- d. will isolate due to V-2515 c,osing.
72 I l I;
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 73 Unit 2 is in the process of a turbine startup, holding at 12% power. Which of the following correctly describes the method of monitoring linear heat rate at the reduced power level? Linear heat rate: a must be monitored using excore NI indication only.
- b. can be monitored using either DDPS or excore Ni indications.
- c. must be monitored using DDPS indication only.
- d. must be monitored using the Beacon computer.
)
1 1 l i 73 i i
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 74 The following conditions exist: Unit 1 is at 100% power Linear Range Control Channel # 9 is out of service for l&C repair Linear Range Channel # 10 is supplying the RPS Power Ratio Calculator Which of the following would be the system response if Channel 10 upper detector , failed high?
- a. Actual ASI as indicated on the Power Ratio Recorder would violate the negative setpoint, an alarm would be generated.
- b. The lower setpoint for ASI as indicated on the Power Ratio Recorder would become more negative, no alarm would be generated.
- c. Actual ASI as indicated on the Power Ratio Recorder would violate the positive setpoint, an alarm would be generated.
- d. The upper setpoint for ASI as indicated on the Power Ratio Recorder would become more positive, no alarm would be generated.
74
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 75 Which one of the following events would cause the ' Unit 2 Containment Evacuation Alarm to be automatically sounded?
- a. The Fire anc Security SUPS looses all power.
. b. An HP team moves a 5500 MR source past MA and MB CIS monitors during Mode 5 operations.
- c. An RO depresses the " Check Source" pushbutton on the MA CIS monitor.
- d. A full Unit 1 CIAS is initiated.
75
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 76 Which one of the following Unit 1 radiation monitors utilizes a different type of detector than the same monitor on Unit 27
- a. Control Room Outside Air intake Monitor
- b. Main Steam Line Monitor
- c. Containment Atmosphere Monitor
- d. Letdown Radiation Monitor >
'l i 1 1 i 1 l I 76 l
--.\
USNRC REACTOR OPERATOR LICENSE EXAMINATION 1 1 Question 77 l l i l 2 l ] The 1B 125VDC bus has been lost due to a wiring fault. The control room crew is carrying out the actions of ONOP 10030136, " Loss of a Safety Related D.C. Bus". The ANPS has directed the ROs to align the 1D 125 VDC bus to the 1B 125 VDC 4 non-safety bus. Which of the following statements correctly describes the process of bus alignment? J ! a. The 18125 VDC bus can be fed directly from the 1D 125VDC bus only by aligning the keyswitches on RTGB 101.
- b. The 1B 125 VDC bus can be fed from the 1D 125VDC bus throuch the 1 AB
- 125 VDC bus only by unlocking and aligning loca, breakers.
- c. The 18125 VDC bus can be fed directly from the 1D 125VDC bus only by unlocking and aligning local breakers.
i 1
- d. The 1B 125 VDC bus can be fed from the 1D 125VDC bus throuch the 1 AB 125 VDC bus only by aligning the keyswitches on RTGB 101.
s g a 4 77
. . . - . . - __. . _ . _ = _ . . - - .__
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 78 Unit 2 is at 100% steady state power. Annunciator B-13, "2A2 4.16 KV A Current Trip" has just gone into alarm. Which one of the following correctly describes the effect of this condition on the 2A Emergency Diesel Generator? The 2A Emergency Diesel Generator:
- a. starts, but does not load on the 2A3 bus.
- b. does not start. It will only start on 2A3 bus undervoltage.
- c. starts and loads on the 2A3 bus.
- d. does not start, but will start and load on the 2A3 bus when the diesel lockout relay is reset.
(
'/8 i
l USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 79 An uncomplicated reactor trip has occurred on Unit 1. One minute after the trip, offsite power is lost. No post trip operator actions have been performed. Which of the following correctI/ describes the status of the MSR block valves at this time? The MSR Block Valves:
- a. are open and must be manually closed by the control switches on RTGB 102.
- b. are closed aJtomatically on the turbine trip signal.
- c. are open and must be closed manually by the potentiometer on the Reheat Control Panel.
- d. are closed automatically on low steam pressure to the MSRs.
79
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 80 The following conditions exist: Unit 1 is at 20% power, returning from a refueling outage, turbine on hold MTC is +1 pcm/ F The RO initiates steam generator blowdown at 120 gpm/SG Which of the following describes the immediate plant response to this evolution? Assume no operator action.
- a. Reactor power increases, letdown flow increases, feedwater flow increases
- b. Reactor power decreases, letdown flow decreases, feedwater flow decreases
- c. Reactor power increases, letdown flow decreases, feedwater flow decreases
- d. Reactor power decreases, letdown flow increases, feedwater flow increases 4
1 t 1 80 l i
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 81 I l l l l Unit 1 is in Mode 1,100% power. The SNPO is preparing the 1B Containment Spray l Pump for its quarterly surveillance run. Which of the following correctly describes an additional manipulation that the SNPO must perform on Unit 1 but not on Unit 2?
- a. Open the CCW isolation valve to the 1B Containment Spray pump seal heat exchanger,
- b. Open 1B Containment Spray pump manual recirc valves.
- c. Close MV-07-3B, B CS Header isolation
- d. Close the Sodium Hydroxide tank vent to atmosphere.
i 81 i
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 82 The following conditions exist: An ESDE/ LOOP has occurred on Unit 1 LIC 1110X (selected for pressurizer level control) failed low on the trip the ESDE was terminated when the MSIVs were closed RCS pressure dropped to 1600 psia during the event RCS pressure is now 1720 psia and stable. Pressurizer level is 29% Other than swapping to the operable Pressurizer level channel, which of the following correctly describes the minimum actions required to regain pressurizer heaters with the plant in its current configuration? i a. Block SIAS, reset the 1 A3 and 183 4.16 KV pressurizer heater breakers, i place the low level cutout switch to the X position, reset all backup heaters 1 .: b. Reset SIAS , place the low level cutout switch to the X position, reset backup i heaters 81 and B4.
- c. Reset SIAS, place the low level cutout switch to the Y position, reset all backup heaters.
- d. Block SIAS, reset the 1 A3 and 1B3 4.16 KV pressurizer heater breakers, place the low level cutout switch to the Y position, reset backup heaters 81 and 84.
J 82
)
USNRC REACTOR OPERATOR LICENSE EXAMINATION 1 Question 83 j l i l l 1 The 2A Emergency Diesel Generator air receivers 2A1 and 2A2 have been olaced on a clearance for valve replacement. The receivers are completely depressurized, when a loss of offsite power occurs. Assuming that the 2A EDG has no other existing ) clearances or deficiencies when the LOOP occurs, which of the following describes the response of the 2A EDG air start system to the LOOP?
- a. Air start mo': ors will engage on both engines, there is sufficient pressure to start the 2A EDG.
- b. Air start monors will engage on only one engine, there is insufficieg pressure
, to start the 2A EDG. P
- c. Air start motors will engage on only one engine, there is sufficient pressure to start the 2A EDG.
- d. Air start motors will engage on both engines, there is insufficient pressure to start the 2A EDG.
s._ 83 i
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 84 Unit 2 is at 100% steady state power. Total RCS leakage has been determined to be 11.3 gpm. The following data is available to the operators: 2.3 gpm leakage into the Quench tank 1.4 gpm leakage into the Reactor Drain Tank 1.8 gpm leakage past all check valves from RCS to Si system 450 gpd 2A S/G primary to secondary leakage 375 gpd 2B S/G primary to secondary leakage 1.7 gpm charging pump seal leakage Which one of the following identifies the type of RCS leakage that will require the plant to be shut down?
- a. Pressure Boundary Leakage
- b. Unidentified Leakage
- c. Identified Leakage
- d. Primary to Secondary Leakage e
84 r
i USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 85 i Unit 1 operators have manually tripped the reactor and turbine from 100% power due to an unrecoverable loss of instrument air. As the Board RO is performing his SPTAs,
- he notices a higher levelin the Quench Tank than previous to the trip. Assuming no
. other failures, which of the following correctly describe the most probable cause of Quench Tank higher level?
- a. RCP seal bleedoff.
I b. PORVs lifted momentarily on the manual trip from 100% power. c The Quench Tank level detector drifts high as instrument air precsure decreases,
- d. Water in the quench tank heats up and expands due to loss of CCW cooling to the quench tank.
i 85 l l
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USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 86 The following conditions exist: A large break LOCA has occurred on Unit 1 1-EOP-3, " Loss of Coolant Accident"is being implemented Hydrogen Analyzers initially indicated 0.7% Hydrogen concentration has increased another 2.6% since the initial reading No equipment is out of service Which of the following actions are required to satify the Containment Combustible Gas Control safety function?
- a. Ensure both Hydrogen Recombiners and Containment Spray in service.
- b. Ensure the Hydrogen Purge System in service.
- c. Ensure both Hydrogen Recombiners and Hydrogen Purge System in service.
- d. Ensure both Hydrogen Recombiners in service.
l 86 1 4
I l l 1 USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 87 Given the following: The NWE rr akes a call for overtime at 1515 hours The contacted employee states that he had 1 alcoholic beverage at around 1345 hours Which of the following is the earliest time that the employee may report to work?
- a. 1815 hours
- b. 1900 hours
- c. 1945 hours
- d. 2015 hours I
l l 1 l 87
_ _- _- . _ - - ~ 5 I USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 88 Unit 1 has tripped from 100% power due to a feedwater problem. According to AP-0010120," Conduct of Operations", which of the following is the approved method of chronological log entries during this event?
- a. The events can be reconstructed at a later time using all available references, but nust be made in chronological order when making an entry.
- b. The desk RO will record all events in the RCO chronologicallog as they occur, after performing SPTAs.
- c. The events can be reconstructed at a later time using all available references, chronological order is desired but not necessary when making an entry.
- d. A designated person, preferably tne STA, will record all events in the RCO chronological log as they occur.
88-l 1
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 89 An l&C tech has been instructed to lift a lead in RTGB 202 as part of a NPv/O package to replace an AFW flow transmitter. Which of the following correctly describes all the requirements of lifting the lead? The I&C Tech:
- a. may lift the lead at any time with the permission of the ANPS, since the lead is covered under a PWO.
- b. must identify the lead by highlighting it on the CWD, a second person independently verifies the correct lead has been identified, the lead can then be lifted.
- c. must identify the lead using proper reference material (CWD, Schematic) to the ANPS, the ANPS must sign the NPWO, the lead can then be lifted.
- d. must identify and tag the lead, a second person independently verifies the correct lead has been identified, the lead can then be lifted.
i e 89
I USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 90 l According to ADM-29.02, "ASME Code Testing of Pumps and Valves", which of the following criteria is used if a pump falls into the " Alert" range due to low discharge pressure during a surveillance test? The pump shall:
- a. be placed out of service until the cause of the deviation has been determined and the condition corrected.
- b. be tested monthly until the cause of the deviation has been determined and the condition corrected.
- c. be tested at double the frequency until the cause of the deviation has been determined and the condition corrected.
- d. be re-tested after the baseline discharge pressure is changed to reflect current pump performance data.
i l 4 90
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 91 l l The Unit 1 SNPO was in the process of performing a valve lineup when he discovered . an incorrect valve number and valve position. To correct this condition, he generated a temporary change (TC) to the procedure IAW ADM-11.03, " Temporary Change to Procedures". Whict of the following describes the status of the TC sixty five days later, assuming no PCR was written? The Temporary Change;
- a. was reviewed by FRG and permanently incorporated into the procedure.
- b. still exists in the TC log
- c. was cancelled after 45 days
- d. was automatically incorporated into the procedure after 60 days.
91
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 92 4 4 The Unit 2 RO is in the process of performing the 2A AFW pump surveillance. The surveillance has to be run for 1 hour due to temperature data requirements. The on'- coming shift is arriving. According to AP 0010120, " Conduct of Operations", which of the following correctly describes the requirements concerning shift turnovers and surveillances?
- a. Surveillances must be completed prior to shift turnover.
- b. Surveillances cannot be performed within one hour of shift turnover time.
- c. Surveillances must be stopped and continued after shift turnover.
4
- d. Surveillances must be in a steady state condition prior to shift turnover.
i 4 e 92
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 93 The 1B CVCS lon Exchanger has been placed in service following resin replacement. Although the RO rinsed the ion exchanger for 1 hour, after 10 minutes of in service time, the following conditions exist: RCS Tcold 548.9 Reactor Power 100.6 %
~
According to AP 0010120, " Conduct of Operations", which of the following is the correct action to be taken by the control room crew? '
- a. Immediately implement ONOP 1-0250030, " Emergency Boration"
- b. Reduce reactor power to 5100% within 15 minutes. (
- c. Reduce reactor power to 5100% within 30 minutes.
- d. Trip the Reactor and Turbine.
I I 93
USNRG REACTOR OPERATOR LICENSE EXAMINATION Question 94 When processing an RWP, which one of the following is the MINIMUM criteria that requires the RWP to be processed through a pre-job ALARA review?
- a. Dose estimate of the job exceeds ten (10) Manrem.
l b. Any work to be performed inside Containment.
- c. Dose estimate of the job exceeds one (1) Manrem.
- d. Any work to be performed in contaminated areas.
l 94
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 95 For entry into a VERY HIGH RADIATION AREA, which of the following correctly describes aj requirements that must be met?
- a. Continuous HP coverage, a high range dosimeter, HP department head approval, NPS approval.
i
- b. A specific RWP, continuous HP coverage, HP department head approval, NPS approval.
- c. A specific RWP, a hand held survey instrument, a high range dosimeter, HP department nead approval.
- d. Continuous HP coverage, a hand held survey instrument, HP department head approval, NPS approval.
I e 95
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 96 An FPL employee from Turkey Point has arrived at St. Lucie to support the Unit 2 refueling outage. Upon arrival, he presents HP with the following dose records: Time Period Facility TEDE January 1-February 19 Crystal River 675 MR February 23-March 31 St. Lucie 210 MR April 7-June 19 Turkey Point 115 MR Which one of the following correctly describes the status of this worker in regard to the amount of exposure he can receive at St. Lucie Plant?
- a. He may receive an additional 3800 MR at St. Lucie but will need a dose extension.
- b. He may not work at St. Lucie this year, he has already exceeded Florida Power and Light guidelines for TEDE.
- c. He may receive an additional 1300 MR at St. Lucie but will need an extension.
- d. He may receive an additional 3300 MR at St. Lucie, with no extension necessary.
l l l
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96
USNRC REACTOR OPERATOR LICENSE EXAMINATION Question 97 The followhg conditions exist: \ - Unit 2 is in Mode 3, cooling down for a refueling outage. RCS pressure and temperature are 1400 psia and 497 F, respectively 2C Charging pump is OOS for accumulator depressurization i Which of the following would be the correct procedure selection to mitigate a 120 gpm , RCS leak occurring inside containment? 3 ) The operating crew should:
- a. Enter 2-EOP-3, " Loss of Coolant Accident".
- b. Enter 2-ONP-01.01 " Plant Condition 1 - Steam Generator Heat Removal LTOP not in Effect"
- c. Enter ONOP 2-0120031, " Excessive Reactor Coolant System Leakage" in conjunction with 2-EOP-3, " Loss of Coolant Accident"
- d. Enter ONOP 2-0120031, " Excessive Reactor Coolant System Leakage" in conjunction with 2-ONP-01.01 " Plant Condition 1 - Steam Generator Heat Removal LTOP not in Effect" 97
1 1 USNRC REACTOR OPERATOR LICENSE EXAMINATION Queshon 98 EOP-15 has been implemented and the following success paths are in service: RCS and Core Heat Removal Success Path 3 is not being met RCS Inventory Control Success Path 2 is not being met RCS Pressure Control by Success Path 3 Reactivity Control by Success Path 3 Which of the following correctly describes the order in which each success path should be addressed in this event?
- a. Reactivity Contrd, success path 3; RCS Inventory Control, success path 2' RCS and Core Heat Rernoval, success path 3; RCS Pressure Control, success path 3.
- b. RCS and Core Heat Removal, success path 4; RCS Inventory Control, success path 3; RCS Pressure Control, success path 3; Reactivity Control, ,
success path 3.
- c. RCS Inventory Control, success path 2; RCS and Core Heat Removal, success path 4; Reactivity Control, success path 3; RCS Pressure Control, success path 3.
- d. Reactivity Control, success path 3; RCS and Core Heat Removal, success path 4; RCS Inventory Control, success path 3; RCS Pressure Control, success path 3.
l a s 98 ,
i t t,
- USNRC REACTOR OPERATOR i.' CENSE EXAMINATION
. Question 99 I
- i 1 4
) l The Site has been placed under a Hurricane Warning, and the NPS has declared an !
- Alert. He has tasked you, the Unit 1 RO, with making the State notification call. All phone lines are down due to high winds. While using the Hot Ring Down Phone, you get no response from State Warning Point (SWP). - Which of the following is the'next proper course of action in accordance with EPIP-02, " Duties and Responsibilities of.
j the Emergency Coordinator"? , i l a. Ask the Unit 2 control room and make the call using their HRD, 2 l
- b. Use the cellular telephone in the Unit 1 control room.
l '
- c. Use the ESATCOM system in the Unit 1 control room. .
- d. Use the Local Government Radio in the Unit 1 control room.
i I i r h i i si i W 99 - i r m, a + -ew.
)
l USNRC REACTOR OPERATOR LICENSE EXAMINATION l Question 100 j l l The following conditions exist: Unit 2 is at 100% power An electrician, performing a surveillance, deenergizes the 283 4.16 KV bus The 2B EDG successfully starts and loads All plant equipment is operable Assuming no operator action aside from resetting individual pressurizer heater l! banks on RTGB 203, which of the following correctly describes the TOTAL , pressurizer heater availability at this time? l 1
- a. Two proportional banks, six backup banks a
- b. One proportional bank, three backup banks
- c. One proportional bank, four backup banks
- d. Two proportional balks, four backc banks 100
- . . - - . . _ - . _ . . . . . ~ . . - -
V v Figure A!6 PSL-1FJF-97-165 Rev 0 St. Lucie Unit 1 Cycle 15 Attachment 1 Page 4 HZP Sequentialintegral CEA Worth 1000 EFPH, Rev 2 e 7600 -
! ' 9 9 i
' ARO = 7o16 pcm l l
7400 j I i , l i l l ! I i i 7200 - i .
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t 7000 / I i
/ '~ T ,~~i-
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/ -
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6800- . -}- - f--- 7
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s
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/ l l6600-
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--- b - 1 1"-l - -
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l ' 5800 0 20 40 60 80 100 120 137 0 20 40 60 80 -100 .120. 137 Bank 5 0 20 40 60 80 100 120- 137 Bank 7 Bank 6 NI bh. e> ,
.i k1' i
Dare of whAre.-i^/5 /fY
, - -. . . . , - . . ~
USNRC REACTOR OPERATOR EXAMINATION . ANSWER KEY
- 1. C
- 2. C
- 3. D
- 4. D
- 5. A
- 6. C
- 7. A
- 8. A
- 9. B 10.D 11.B
- 12. B 13.C 14.D 15.B 16.D 17.B 18.B 19.C 20.C
~
- 21. D 22.C 101
USNRC REACTOR OPERATOR EXAMINATION ANSWER KEY
- 23. B 24.D 25.B 26.C 27.B 28.B 29.A 30.C 31.A 32.C
- 33. B 34.B 35.D 36.D 37.B 38.C 39.D 40.C 41.A 42.A .
43.B 44.C 102
USNRC REACTOR OPERATOR EXAMINATION ANSWER KEY 45.D 46.C 47.D 48.B 49.D 50.D 51.C 52.D
- 53. C
- 54. D 55.C 56.C 57.A 58.D 59.D 60.C 61.D
, 62.C 63.D 64.D 65.B 66.C 103
USNRC REACTOR OPERATOR EXAMINATION ANSWER KEY 67.D 68.B
- 69. B 70.C
- 71. B 72.A 73.A 74.A 75.C 76 A 77.B 78 C 79.B 80.D
- 81. B 82.C 83.A 84.B 85.A 86.D
~
87.B 88.A 104 i
i USNRC REACTOR OPERATOR EXAMINATION ANSWER KEY 89.D 90.C 91 B 92.D 93.B 94.C
- 95. B 96.C 97.D 98.C 99.C 100.B 1
I 105
U.S. Nuck Regulatory Commission Site-Specific Written Examination ' Applicant Information Name: Region: 11 Date: Facility / Unit: St. Lucie 1/2 E License Level: SRO Reactor Type: CE Start Time: Finish Time: Instructions t Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected four hours after the examination starts. Applicant Certification All work done on this examination is my own. I have neither given nor received , aid. Applicant's Signature ; Results Examination Value Points l Applicant's Score Points Applicant's Grade _ Percent DISTRIBUTION A070 CODE
!- NRC RULES AND GUIDELINES FOR WRITTEN EXAMINATIONS During the administration of this exam, the following rules apply.- !~ PART A - GENERAL GUIDELINES ) 1. Cheating on any part of the examination will recult in a denial of your , application and/or action against your license.
- 2. If you have any questions concerning the administratiofi~of any part of the 3
examination, do not hesitate asking them prior to starting that part of the test. { 3. SRO applicants will be tested at the level of responsibility of the senior shift
- position (ie. NPS, ANPS) i'
- 4. You must pass every part of the examination to receive a license or to j continue performing license duties.
i
- 5. The NRC examiner is not allowed to reveal the results of any part of the examination until they have been reviewed and approved by NRC 4 management. Grades provided by the facility licensee are preliminary until ,
- approved by the NRC. You will be informed of the official examination results
- about 30 days after all examinations are complete.
l PART B - WRITTEN EXAMINATION GUIDELINES l 1. After you complete the examination, sign the statement on the cover sheet ! indicating that the work was your own and you have not received or given j assistance in completing the examination, i
- 2. To pass the examination, you must achieve a grade of 80 percent or greater.
Every question is worth one point.
- 3. For initial examinations, the time limit for completing the examination is FIVE hours.
- 4. You may bring pens, calculators or slide rules into the examination room. Use ,
only black ink to ensure legible copies.
- 5. Print your name in the blank provided on the examination cover sheet and answer sheet. You may be asked to provide the examiner with.some form of positive identification.
- 6. Mark your answers on the answer sheet provided and do not leave any question blank. Use only the answer sheet provided and do not write on the back side of the pages. If you decide to change your original answer, draw a single line through the error, enter the desired answer, and initial the change.
;T
- 7. If the intent of the question is unclear, ask questions of the examiner only.
- 8. Restroom trips are permitted, but only one applicant at a time will be permitted to leave. Avoid all contact with anyone outside the examination room to eleiminate the appearance or possibility of cheating.
- 9. When you complete the examination, assemble a package including the examination questions, examination aids, answer sheets and scrap paper and give it to the proctor. Remember to sign the statement'on the cover sheet indicating that the work was your own and you have not received or given assistance in completing the examination. The scrap paper will be disposed of immediately after the examination.
- 10. After you have turned in your examination, leave the examination crea as
; defined by the proctor. If you are found in this area while the examination is stillin progress, your license may be denied or revoked.
- 11. Do you have any questions?
i e 1 1 1
- -- -. . . . . . _ ._ . = . -- - . . _ - . . .
l l l USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 1 l l l The following conditions exist: ! Unit 1 is at 100% power. A large school of jellyfish has been reported to be in the area of the intake canal.
- Annunciators E-17 and M-21," Intake Structure Low Water Level" are in alarm.
The ANPO reports intake water level is -10.7 feet. Which of the following actions must be taken by the control room crew at this time? Immediately:
- a. trip the reactor and turbine.
- b. commence a shutdown to mode 3.
4
- c. remove two circulating water pumps from service.
1 i
- d. open the ultimate heat sink barrier valves.
i l l f l 1 1
i I
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1 USNRC SENIOR REACTOR OPERATOR EXAMINATION l Question 2 j Unit 2 was performing a rapid power reduction due to an RCS leak inside containment when the reactor was manually tripped. SIAS actuated 1 minute following the manual j trip. The operators have completed'their SPTAs and the following conditions exist 12 ] minutes after trip: l l - RCS pressure 750 psia RCS Thot 476 F Pressurizer level 0% Containment Pressure 2 psig
- SG levels 43% WR with feed available Which of the following is the correct RCP trip strategy for the current conditions? ,
- a. Trip all four RCPs
- b. Trip one RCP in each loop
- c. Leave all four RCPs running
- d. Trip one RCP 1
l 1 2 l l
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 3 1 A Emergency Diesel Generator was in the process of a surveillance run when it tripped on high engine water temperature. Prior to the SNPO arriving at the 1A EDG to check its status, LOOP /SIAS occurred. Which of the following correctly describes the status of the 1 A EDG when the SNPO arrives? The 1 A EDG has:
- a. started and loaded on the 1 A3 4.16 KV bus
- b. not started, bot will start when the lockout relay and shutdown relay are reset.
- c. started and will load on the 1 A3 4.16 KV bus when the lockout relay and shutdown relay are reset.
- d. not started, but will start if engine temperature is <205 F and the lockout relay is reset.
l 3 l
USNRC SENIOR REACTOR OPERATOR EXAMINATION t Question 4 SE-07-1 A, (todine Removal System eductor valve) is closed and deenergized for solenoid replacement. Which of the following correctly describes the flowpath of Sodium Hydroxide if a full CSAS occurred with the system in its current configuration?' Sodium Hydroxide would flow:
- a. through 2 eductor solenoid valves to the discharge of the 1B Containment Spray Pump.
- b. through 1 eductor solenoid valve to the discharge of 1 A and 18 Containment Spray Pumps.
- c. through 2 eductor solenoid valves to the suction of 1A and IB Containment Spray Pumps.
- d. through 1 eductor solenoid valve to the suction of the 18 Containment Spray Pump.
4 l _ _________ - _ -- _ J
M USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 5 W The following conditions exist: Unit 2 is at 100% power The 2A HPSI is being used to fill the 2A2 SIT The 2A3 4.16 KV bus is deenergized Which one of the following will occur when the 2A EDG starts and loads on the bus'- The 2A HPSI will:
- a. auto sequence onto the bus six seconds after the EDG output breaker closes.
- b. auto sequence onto the bus thirty seconds after the EDG output breaker closes.
- c. will not sequence onto the bus and will have to be manually started.
- d. loads onto the bus immediately after the EDG output breaker closes.
5 l 1 l
USNRC SENIOR REACTOR OPERATOR EXAMINATION I l Question 6 i l
- Unit 1 le returning from a refueling outage. The ANPS has directed you to place the Steam Jet Air Ejectors (SJAE)in service to draw a vacuum in the condenser..
According to OP 1-0610029, " Condenser Air Removal System Operation", which of , the following set of conditions must exist prior to placing the SJAEs in service? i , a. 200 psig ; team pressure and gland sealing steam in service.
- b. 400 psig steam pressure and a minimum of 3, feet water levelin the hotwell .
l
- c. 200 psig steam pressure and the turbinc must be on turnin;: pear.
- d. 400 psig steau pressure and one condensate pump in operation.
6
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f USNRC SENIOR REACTOR OPERATOR EXAMINATION Question.7 Unit 2 has come off line in preparation for a refueling outage. . RCS temperature is 210 F. Health Physics has asked the control room to perform a containment purge prior to personnel entry due to high particulate activity in containment. Which of the following correctly describes the method of purging the containment building under these conditions?
- a. Operation of HVE 8A and 8B, nuoJ containment purge system.
l
- b. Operation of HVE 7A and 7B, through the hydrogen purge filter train.
- c. Operation of HVE 1 and HVE 2, airborne radioactivity removal system.
- d. Operation of HVE 7A and 7B through the shield building ventilation filter train.
E s e 7 1
d i I USNRC SENIOR REACTOR OPERATOR EXAMINATION -
- Question 8 f
i i i i The following conditions exist:
- Unit 2 is at 1b0% power 2A DEH pump is running
~
- 2B DEH pump control switch is in the " auto" position 1 -
An unisolable DEH leak has developed on the #4 Governor valve
- Annunciator D-58, "DEH RESERVOIR LOCKOUT TRIP / FAIL" locks in.
1 Considering the sequence of events, which of the following correctly describes the status of the DEH system at this time? i ] a. 2A DEH pump trips and both DEH pumps cannot be restarted. i j b. 2A DEH pump continues to run,28 DEH pump has auto started. j c. 2A DEH pump continues to run,2B DEH pump must be started j manually. i
- d. 2A DEH pump trips and both DEH pumps can be restarted manually.
a 8 I !
l 1 USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 9 , 4 l A trip from 100% power due to a main steam line rupture has occurred on Unit 2. 4 The leak was isolated when the MSIVs were closed. RO has been directed to stabilize RCS pressure and temperature. After 15 minutes, the following parameters exist: RCS Pressure: 1850 psia and stable RCS Temperature: 489 *F and stable AFW flow 150 gpm/ Steam Generator ADVs Auto / Manual,40% output Shortly after stabilizing RCS conditions, a loss of offsite power occurs and both diesels successfully start and load. While assessing safety functions, the RO notices RCS temperature decreasing. Assuming no operator action or further plant degradation, which of the following is the most probable reason for the cooldown?
- a. Safety injection flow to the RCS
- b. ADVs are full open
- c. AFW valves are full open
- d. MSIVs have reopened.
s 9
. . . .. .. . .. - -- . - . . .- . . - . - .- . - = - . . . .- - - .
i'
~ L'SNRC SENIOR REACTOR OPERATOR EXAMINATION Question 10 ,
4 l Unit 2 is in Mode 6, refueling in progress. A leak has developed in the suction line of l the in service Fuel Pool Cooling pump, upstream of the suction isolation valve . Which of the following conectly describes the status of fuel pool water level if no j action is taken to isolate the leak? ! Fuel pool water level will decrease: i 4 I a. to 23 feet above the top of the fuel assemblies. 1 i b. to the bottom of the fuel transfer canal gate. I c. to the bottom of the skimmer suction. l to approximately 52 feet. l d. 4"* 10 L. .
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 11 4 Unit 1 is at 100% power, steady state. The RO takes HS 1111, Tcold selector switch, to the " Alternate" position. Which of the following describes the effect of this manipulation?
- a. An alternate Tcold safety channel will provide input to the dual scale Thot/Tcold recorder on RTGB 103.
- b. An alternate Tcold control channel will provide input to the LTOP circuit.
- c. An alternate Tcold control channel will provide input to the dual scale Thot/Tcold recorder on RTGB 103.
- d. An alternate Tcold safety channel will provide input to the LTOP circuit.
1 i i i 11 1 1
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' USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 12 - - A large ESDE has occurred on Unit 2. The RO, performing safety function status -checks for 2-EOP-05, reports that RCS temperature is 350"F and RCS pressure is 1290 psia. The crew should:
- a. secure all running RCPs, initiate seat injection.
f
- b. stabilize RCS temperature, depressurize the RCS.
- c. reduce RCS temperature to establish 20 F subcooling.
- d. stabilize.RCS pressure and temperature at current values.
I s '.
'l b
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 13 Which one of the following accidents would generate the greate'st amount of hydrogen and the reason why?
- a. SBLOCA, due to increased heat input from running RCPs.
- b. LBLOCA, due to greater steaming rates in the core.
- c. SBLOCA, due to lower steaming rates in the core.
- d. LBLOCA, due to lower pressures in the RCS.
i
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 14 1 l Which one of the following actions would be permissible according to AP 0010120,
" Conduct of Operations"?
- a. Manud i:iitiation of AFAS due to a LOOP at 25% power.
- b. Blocking SIAS during a plant shutdown due to a 100 gpm RCS leak inside containment.
- c. Blocking MSIS during a plant shutdown due to a 100 gpm SGTL.
- d. Manual actuation of SIAS prior to auto actuation due to a 200 gpm LOCA.
( 14 2
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 15 According to EPIP-07, " Conduct of Evacuations / Assembly", which one of the following instances would require a local evacuation?
- a. A new fuel element being received is dropped and smears indicate 65 DPM/100CM2 in a 10' X 10'section of the fuel handling building.
- b. A resin transfer causes a 300 MR source at an ion exchanger outlet elbow in the valve gallery.
- c. An RCS sample line leak results in smears of 800 DPM/100CM' in a 10' X 10'section of the pipe penetration room.
- d. HP detects airborne radiation levels of 5 X 10'"in the charging pump hallway, s
1 1 15 l i l l L. _ _ _. . . _ _ _ _ - . _
1 i i USNRC SENIOR REACTOR OPERATOR EXAMINAT!ON Question 16 According to ADM-09.04, "In Plant Equipment Clearance Orders", a " Human Clearance" would be acceptable in which one of the following situations?
- a. A mechanic requests a bypass valve opened while he changes a clogged filter on the DEH system at 100% power.
- b. An I&C spec requests instrument air to a SBCS valve isolated whila he repairs a leak during a plant shutdown,
- c. A mechanic requests a breaker opened while he makes repairs to the traveling screens during a jellyfish run.
- d. A mechanic requests a breaker opened while he cleans the suction strainer of the equipment drain pump with flooding in the -5 RAB.
l l l 1 1 1 l A 16
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 17 Which one of the following events would require all non-essential site personnel to report to their respective staging areas? (assume all plant equipment available)
- a. A 150 gpm RCS leak / LOOP has occurred on Unit 1
- b. An ESDE inside containment that raised containment pressure to 12 psig.
- c. A Security Alert has been declared
- d. A fire in the switchyard requiring offsite assistance.
17
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 18 Unit 1 is at 100% steady state power. The 18 Intake Cooling Water (ICW) pump has tripped due to a failed lower motor bearing. The 1C ICW pump is on a clearance and unavailable for use. According to ONOP 1-0640030, " Intake Cooling Water System", which one of the following actions should be taken by the control room crew?
- a. Close MV-21-3 to maximize ICW flow to the CCW heat exchanger.
l
- b. Isolate CCW flow to ti.
- Shutdown Cooling heat exchangers.
- c. Crosstie the 1 A and 1B ICW headers through the 1C ICW pump connection.
- d. Isolate CCW flow to the Fuel Pool heat exchanger.
a 1 18 I
l USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 19 Unit 1 is in the process of a reactor startup. Which of the following conditions correctly describes the point in the startup where a continuous CEA withdrawal accident would result in the highest peak power?
- a. BOC, lead group CEA continuously withdraws after reaching 2% power.
- b. EOC, lead group CEA continuously withdraws at a point 2" prior to criticality,
- c. EOC, lead group CEA continuously withdraws after reaching 2% power.
- d. BOC, lead group CEA continuously withdraws at a point 2" prior is criticality.
19
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 20 Unit 1 is at 100% power, steady state. The 1C 120V Instrument bus becomes j deenergized due to an electrical fault. Which of the following correctly describes the
- status of the Diverse Scram System (DSS) at this time?
i j a. The MG set input breaker will open if ONE aaditional DSS channel becomes actuated. l
- b. A line contactor will open if TWO additional DSS channels become actuated.
4
- c. The MG set input breaker will open if TWO additional DSS channels become actuated,
- d. A line contactor will open if ONE additional DSS channel becomes actuated.
i l s 1 20 l S
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 21 1 A Large Break LOCA has occurred on Unit 2. The ANPS has: asked the RO to verify i- two phase naturai circulation. According to 2-EOP-3, "LOCA", which one of the following parameters would be used to confirm two phase natural circulation? (Assume all equipment available)
- a. Core Exit thermocouples indicate less than 700*F.
- b. That - Tcold delta T is less than 50*F.
- c. Core Exit thermocouples indicate less than 22*F superheat.
i
- d. That and Rep CET temperatures <20 F different.
i i 1
?
o 21 4
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 22 A LOOP has occurred on Unit 1. The 1A EDG failed to load due to a differential current lockout on the 1 A3 4.16 KV bus. ONOP 1-0910054, " Loss of a Safety Related AC Bus" gives guidance to place the 1 A ICW pump control switch in the "STOP" position prior to resetting the lockout relay. Which of the following correctly describes the reason for this guidance?
- a. Diesel loading considerations; the 1 A ICW pump could cause an overcurrent situation when it loads on the diesel,
- b. To protect personnel; the 1 A3 4.16 KV lockout relay is located on the 1 A ICW pump breaker cubicle which will close when the 1 A ICW pump loads on the diesel.
- c. ICW flow considerations; ICW header isolation valve MV-21-3 has closed on loss of power and will restrict flow when the 1 A ICW pump loads on the diesel.
i
- d. To protect ICW piping; water hammer could occur when the 1 A ICW pump loads on the diesel.
l 1 l I i 22 1
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 23 A stuck open Pressurizer Safety valve has caused a reactor trip and SlAS to occur on Unit 2. The ANPS is implementing 2-EOP-3, "LOCA" and asks the RO to verify HPSI throttling criteria is met. Which one of the following parameters would likely prohibit HPSI throttling in this specific event?
- a. RCS Subcooling
- b. Reactor Vessel Level -
- c. RCS Leak Flow
- d. Pressurizer Level 23
USNRC SEN'JR REACTOR OPERATOR EXAMINATION Question 24 The following conditions exist: -
- Unit 2 is at 12% power, returning from a refueling outage.
The RO is preparing to sync the main generator to the grid "C" Linear Range channel upper detector fails high , Which of the following correctly describes the RPS channels that will have to be bypassed prior to continuing on with the plant startup. l a. Variable high power, TMLP, Local Power Density, Loss of Load. l b Variable high power, High Startup Rate, Local Power Density, Loss of i Load. ,
- c. Vt4riable high power, TMLP, Local Power Density, High Startup Rate.
- d. Variable high power,TMLP, Loss of Load, High Startup Rate.
i 1 24 '
i i l USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 25 , The refueling supervisor has called the control room and reported a new fuel assembly has been dropped and severely damaged on the 43' elevation of the Unit 2 Fuel Handling Building. After announcing the evacuation of the FHB, the RO checks for increasing trends on the FHB area radiation monitors. Which of the following correctly describes what the RO will see on the monitors?
- a. No increase in activity due to the location of the detectors.
. b. Increase in activity due to the release of Alpha particles. 4 c. No increase in activity due to type of radiation detector.
- d. Increase in activity due to the release of fission products.
4 1 i l 25 . I 1 I
i l USNRC SENIOR REACTOR OPERATOR EXAMIN/sTION l Question 26 A gas release is in progress on the 2C Gas Decay Tank. According to OP 2-0530021, " Controlled Gaseous Batch Release to Atmosphere", which one of the following events would require termination of the release?
- a. The 28 gas decay tank pressure drops 4 psig.
- b. The running RAB supply fan trips, the standby fan will not start.
- c. The 32' Met Tower wind oirection indication fails low.
- d. HP detects Noble Gas in the gas decay tank area.
i t l l l 26
1 l USNRC SENIOR REACTOR OPERATOR EXAMINATION 1 l Question 27 1 Unit 2 is in mode 6, refueling is in progress. A fire has been reported on the 43' elevation of containment and the fire team has been called out. Which of the following equipment would the RO check to be running to ensure the fire team has a water S Jpply?
- a. Primary Water Pumps
- b. Fire Pumps
- c. Service Water Pumps
- d. Demin Water Pumps 4
4 4 27
i
. USNRC SENIOR REACTOR OPERATOR EXAMINATION l l
Quer'. ion 28 i i Which of the following can be performed on the Unit 2 Hot Shutdown Control Panel?
- a. P; ace shutdown cooling in service.
- b. Depressurize with main spray. ,
1
- c. Block SIAS.
- d. Borate the RCS s
n 'I 28
USNR0 SENIOR REACTOR OPERATOR EXAMINATION Question 29 i The following conditions exist: Unit 1 i:; at 100% power, steady state
- CEA #30 is on the hold bus
- I&C is troubleshooting a defective lower gripper coil No othEr CEA malfunctions exist 4
Which of the following conditions would cause CEA #30 to drop into the core?
- a. The RO depresses one reactor ti!p pushbutton on RTGB 102.
- b. The RO selects CEA #30 in manual individual and attempts to insert it.
4
- c. The four pole circuit breaker for CEA #30 is taken to the "OFF" position.
l I
- d. The 1 A 120 VAC Instrument bus becomes deenergized.
29
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 30 4 The following conditions exist: -e
- Unit 2 is in the process of a return to power from a SNO Generator output is 255 MW, increasing at 3 MW/ Min The NPO reports a broken hotwell gauge glass
- Condenser backpressure is 3.7" Hg Which one of the following is the required actions to be taken by the operators under j these conditions?
- a. Place both Hogging Ejectors in service.
4
- b. Place turbine in manual and hold power constant until leak is isolated.
a
- c. Ensure condenser backpressure does not exceed 5.5" Hg.
J
- d. Trip the Reactor and Turbine, carry out 2-EOP-1, " Standard Post Trip Actions"
't 4 4 30 4
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 31 The following conditions exist:
- Unit 1 is in Mode 3, reactor startup in progress
- Reg Group 3 has been fully withdrawn The RCS is at critical boron concentration CEA #61 dropped fully into the core While attempting to recover CEA #61, CEA #69 slipped to 120" Which of the following actions would be the correct response for the present plant conditions?
- a. Notify l&C, realign both CEAs.
- b. Trip the reactor.
- c. Emergency borate to ensure adequate shutdown margin.
- d. Insert Reg Group 3 to LEL, notify I&C.
31
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 32 4 I Unit 1 is at 100% power when the 18 Steam Generator Low pressure MSIS , measurement channel in the MA ESFAS cabinet fails low. Assuming no operator
- action, which one of the following events would cause the reactor to trip?
4
- a. The MA 1A low steam generator pressure MSIS measurement channel fails low.
- b. The MB 1 A low steam generator pressure MSlS measurement channel fails
. Iow.
- c. The MD 120V Instrument inverter trips due to an electrical fault
- d. The MC 18 MSIS measurement channel bistable is removed.
l l 32
i-j USNRC SENIO'R REACTOR OPERATOR EXAMINATION ' 1 4 Question 33 *
.1 i
i i The Unit 2 Low Power Feedwater System is dependant upon two parameter inputs to l provide a permissive to the "X-FER TO MAIN" lights on the feedwater transfer _ switch. Which of the following parameters are the input to this permissive? . 4 l a. SG Narrow Range Level and Feedwater Temperature ' 4
- b. SG Wide Range Level and Neutron Flux.
l . 1 I c. SG Narrow Range Level and Neutron Flux 5
- d. SG Wide Range Level and Feedwater Temperature i
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m USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 34 The Unit 1 RO is preparing to release the contents of the 18 waste monitor tank. The Unit 1 Liquid Rad Waste Monitor (channel R-6627) appears to be failed low. Which of the following is a correct statement concerning the status of a pending liquid release?
- a. The Plant General Manager must approve the release permit.
- b. Two independent samples and release rate calculations must be performed prior to the release.
- c. The liquid release can be performed using Unit 2 Liquid Rad Waste Monitor,
- d. The liquid release cannot be performed until channel R-6627 is determined to be operable.
i t 34 i
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 35
~
Unit 1 is in the process of a reactor / turbine startup. The RO is. withdrawing group.7 CEAs at 128" when CEA #9 becomes mechanically bound. Assuming no other operator action, which one of the following correctly states the reason CEA group motion will stop if withdrawal continues?
- a. Upper Electrical Limit
- b. CEA Motion Inhibit
- c. Group Out of Sequence
- d. Upper Group Stop 35
l USNRC SENIOR REACTOR OPERATOR EXAMINATION i
-Question 36 l'
The following conditions exist:
. Unit 1 has tripped from 100% power due to a LOOP 1 A Emergency Diesel has failed to start -
CEAs 42 and 39 are indicating UEL-The ANPS directs the RO to perform an emergency boration 2B charging pump is running Which one of the following statements describes the correct actions IAW ONOP.1-0250030, " Emergency Boration"?
- a. Start 2B BAMT Punip, open V2514 (Emergency Borate Valve),
- b. Hold close V2501(VCT Outlet Valve), hold open V2504 (RWT Makeup Valve)
- c. ' Start 2B BAMT Pump, open V2508 or V2509 (Gravity Feed Valves).
- d. Open V2508 or V2509 (Gravity Feed Valves), hold close V2501(VCT Outlet
, Valve) t 36
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 37 Which ONE of the following states a condition in which the indicated pressurizer level would indicate HIGHER than actual level?
- a. Pressurizer temperature greater than the temperature for which the level transmitter was calibrated.
- b. Rupture in the diaphragm of the Pressurizer level transmitter.
- c. Containment temperature lower than normal.
- d. Leak in the variable leg of the Pressurizer level transmitter.
4 37
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 38 e Unit 2 is performing the actions of EOP-15. The RO has just aligned the 2A Charging pump to the A HPSI header. Which one of the following is the' Safety Function that this lineup would be used to satisfy?
- a. RCS Inventory Control
- b. RCS Pressure Control
- c. Reactivity Control s
- d. RCS and Core Heat Removal 1
1 ? J i 1 1 38
l
-i USNRC SENIOR REACTOR OPERATOR EXAMINATION
" Question 39 4
i Unit 2 control room has been evacuated due to a fire. The operators manually tripped .i
- the reactor and turbine from 100% power and have carned out all IOAs of ONOP 2- !
- l. 0030135, " Control Room inaccessibility" prior to their exit. They.are now performing : l their respective appendices.
[ If all AFW normal / isolate switches were placed in isolate two minutes after' steam generator levels reached 19% NR indication, which of the following would be the l.. condition of the AFW system when they arrive at the Hot shutdown Panel? < a. All AFW header isolation valves open, no AFW pumps running-
- b. No AFW header isolation valves open, a!I AFW pumps running 4
j
- c. All AFW header isolation valves open, all AFW pumps running f-
- d. No AFW header isolation valves open, no AFW pumps running l
l 1 I i t m. Y k 39 , L- ..mu_ s . - - - . . .
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USNRC SENIOR REACTOR OPERATOR EXAMINATION l Question 40 An electrician, working on a 480V feeder breaker has deenergized the 1 AB MCC. Which one of the following correctly describes the condition of the 120VAC Vital SUPS at this time?
- a. The static switch ABT has transferred to the alternate source and is supplying the Vital Bus.
- b. The Battery Charger is being directly supplied by its alternate source and is supplying the Inverter, which is supplying Vital Bus.
- c. The Inverter is being directly supplied by its alternate source and is supplying the Vital Bus.
I
- d. The 125 VAC Vital SUPS is in its normal configuration and supplying the Vital l Bus i
40
i. USNRC SENIOR REACTOR OPERATOR EXAMINATION j Question 41 While operating in MODE 5 with the pressurizer solid and the RCS in an isothermal condition at 150" F, RCS pressure rapidly increases. Which 6ne of the following could cause this pressure increase?
- a. Letdown pressure control valve diaphragm ruptures
- b. Pressurizer heaters energize
- c. Shutdown cooling flow is inadvertently increased j
- d. Letdown level control valve setpoint is inadvertently increased 1
I I 41
1 I USNRC SENIOR REACTOR OPERATOR EXAMINATION l Question 42 I The following conditions exist: 1A 125 VDC bus has been deenergized a - ' an electrical fault The ROs are performing Standard Post Trip actions l A steam line break has developed on the 1 A Steam Generator 1 A Steam Generator Pressure is 570 psig ; 18 Steam Generator Pressure is 890 psig i No other failures are present ! Which of the following statements correctly describes the status of the Main Steam isolation valves as reported by the board RO?
- a. The A MSIV is open, the B MSIV is closed.
- b. The B MSIV is open, the A MSIV is closed.
- c. Both A and B MSIVs are open.
- d. Both A and 8 MSIVs are closed.
l 1 42
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 43 Which one of the following' conditions represents a loss of Containment Vessel Integrity for Unit 1 as defined in Technical Specifications?'
- a. While at 10C% power, a mechanic opens the outer containment airlock door to perform maintenance activities on the CLOSED INOPERABLE inner containment door without prior approval.
i b. While performing operability tests on the redundant containment vent header i valves (V-6554 and V-6555) at 100% power, one of the two valves (V-6554)
- fails to completely close.
1 I c. While at 100% power, the nitrogen supply valve to the Safety Injection Tanks isolation valve (V-6741) fails its required stroke time. .o i j d. While at 100% power, the outer containment airlock door fails its leak rate test and has to be opened to facilitate repairs that will take 2 hours. l i I i 3
- 1 s 5 j
i 43
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 44 The following conditions exist: Unit 2 is at 100% power 2B QSPDS is out of service for electrical work A spurious switchyard fault has caused a loss of offsite power The 2A EDG failed to start All other equipment functioned as required Which Safety Function cannot be confirmed in EOP-1 by the ROs?
- a. RCS Pressure Control
- b. RCS Heat Removal
- c. Containment isolation f
- d. Maintenance of Vital Auxiliaries i
4 4 44 i f
)
l
i l USNRC SENIOR REACTOR OPERATOR EXAMINATION [ Question 45 i i r The following Unit 1 conditions exist: _ [
- The Reactor Coolant Letdown Monitor (channel 41) is in high alarm i lodine 131 indication is steadily increasing j Chemistry reports DEQ-131 is at .05 Micro Ci/ gram .
According to ONOP 1-0120032, " Excessive Reactor Coolant System. Activity", which ; one of the following set of actions are required to be taken at this time?
- a. Reduce Rx power to <70%. Notify Chemistry to increase sampling frequency. ,
- i
- b. Minimize letdown flow. Notify HP to survey the VCT area for increased ;
radiation levels. ! t
- c. Divert letdown flow to the H.old-up Tanks. Notify HP to survey the -5 RAB ,
area for increased radiation levels.
- d. Maximize letdown flow. Notify Chemistry to increase sampling frequency.
i 4 t
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l l 4- USNRC SENIOR REACTOR OPERATOR EXAMINATION 1 j Question 46 1^ i
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} Unit 2 is in a Station Plackout and the NPS is considering exiting 2-EOP-10 to an
- approved procedure t.iat has been designated by the TSC. All safety functions for 2- ;
f EOP-10 are being maintained. Which of the following conditions would allcw :
- transition from 2-EOP-10 to the approved procedure? ,
i
- a. Unit 2 2A16.9 KV bus energized from a Unit 2 startup transformer.
! b. Unit 2 2A2 4.16 KV bus energized from a Unit 2 startup transformer. J' ; 4 :
- c. Unit 2 2A3 4.16 KV bus energized from 2A EDG.
( i ,
- d. 1A EDG supplying 2A3 4.16 KV bus via the SBO crosstie. ;
i ! i . i ; 5 i' l 4 i i f I e , 6 Y' 46 4' ____~________;_i._^______ . _ . .
I USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 47 The following Unit 1 conditions exist: Annunciator S-16 "CCW SURGE TK LEVEL COMP. 8 LOW'is in alarm. The SNPO reports the CCW Surge Tank levelis decreasing 1/2" every two minutes The ANPS has directed entry into ONOP 1-0310030, " Component Cooling Water Off-Normal Operation", Appendix A, "CCW Leak Search". No other CCW alarms are present. Which one of the following CCW supplied components would be a possible source of the system leakage?
- a. Fuel Pool Heat Exchanger
- b. Containment Cooler HVS 18
- c. Sample Heat Exchanger 1B
- d. Containment Cooler HVS 1D 47
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 48 , The following conditions exist: A totalloss of feedwater event has occurred on Unit 1 S/G levels a e 14% on wide range indication The control room crew has exited EOP-6 and entered EOP-15,"RCS and Core Heat Removal", Success Path 4, "Once through Cooling" After Success Path 4 is fully implemented, which one of the following is the correct action by the control room crew? i
- a. Implement EOP-6 and continue with feedwater restoration.
- b. Implement in EOP-15 starting at step 1.
- c. Remain in Success Path 4 until feed is recovered.
- d. Implement EOP-3, RCS inventory is now decreasing.
48
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o USNRC SENIOR REACTOR OPERATOR EXAMINATION. 4 l Question 49 +
- i 1
t ' The following conditions exist: j j - 1B Steam Generator has been diagnosed with a tube rupture. , l.
- An RCS cooldown to 523 F is completed- !
~18 Steam Generator has been isolated per 1-EOP-99, Appendix R ;
j All RCPs are off : I i t ! With cooldown in progress for an additional 30 minutes, which one'of the following ' RCS Thot temperatures is correct if the maximum recommended cooldown rate is utilized? l
- s.
- a. 473*F 1
- b. 485.5 *F
- c. 498 F i 1 .
- d. 508 F ,
l ) 6 i r [ l $ h v* f l i i
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 50 Due to a condenser tube leak, The ANPS has directed entry into 1-ONP-22.01," Rapid Downpower", and has directed the ROs to commence a downpower at 20 MW/ minute. Which one of the following is the procedurally correct method of reducing RCS Tavg? (Assume one BAM pump running)
- a. Open Boric Acid Load Control Valve V2525; cycle the running BAM pump to '
maintain Tavg. within 6.6 F of Tref.
- b. Open Emergency Borate Valve V2514; cycle V-2514 to maintain Tavg. within 6.6*F of Tref.
- c. Open Boric Acid Load Control Valve V2525; cycle V2525 to maintain Tavg.
within 6.6 F of Tref. i
- d. Open Emergency Borate Valve V2514; cycle the running BAM pump to maintain Tavg. within 6.6 F of Tref.
50
f i l USNRC SENIOR REACTOR OPERATOR EXAMINATION - Question 51' I L 'A SBLOCA occurred on Unit 1 twelve hours ago.' RCS pressure is currently 265 psia,. i and the ANPS had directed the ROs to_ pl. ace Shutdown Cooling in service when LT-- 1103 (RCS low range pressure indicator) failed high. i i ! Which one of the following statements correctly describes the actions that must be taken to establish Shutdown Cooling (SDC) flow? - i
- a. Both A train SDC suction valves'can be opened from the control room; the SNPO must manually open both B train SDC suction valves. '
l. i b. Both A train and both B train SDC suction valves can be opened from the I j control room. , i } c. One A train and one B train SDC suction valve can be opened from the ' } control room; the SNPO must manually open one SDC suction valve on each ; train.
- d. One A train and one B train SDC suction valve can be opened from the
- control room; the SDC suction crosstie can be opened to establish SDC flow.
i
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51
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 52 Concerning the Unit 2 Fuel Pool Area Radiation Monitors: SA SB GAG 007 GAG 008 GAG 009 GAG 010 GAG 011 GAG 012 Which one of the following is the minimum condition that would cause automatic actions to occur in the Spent Fuel Pool Ventilation System?
- a. GAG 007 in ALERT, GAG 009 in ALARM
- b. GAG 009 in ALARM, GAG 012 in ALARM
- c. GAG 007 in ALERT, GAG 011 in ALERT
- d. GAG 008 in ALARM, GAG 010 in ALARM 4
I e 52
i i USNRC SENIOR REACTOR OPERATOR EXAMINATION - Question 53 7 Unit 2 has tripped from 100% power. Upon AFAS actuation, the 2C AFW pump tripped on overspeed, and the RO closed its associated header valves. The RO has - throttled the A and B header valves so that flow to each S/G to 150 gpm. A system disturbance causes. the following sequence: 0000 Loss of offsite power 0009 2A EDG starts and loads 0010 2B EDG starts and loads . 0040 2A EDG fully loaded 0042 2B EDG fully loaded Assuming no operator action, which of the following correctly describes the status of. the AFW system header valves at 0060?
- a. All header valves (A, B, and C) fully open.
- b. A and B header valves at the 150 gpm position, C header valves closed. '
- c. A header valve open, B Header valve closed, C header to A open, C header to B closed. '
- d. A header valve closed, B header valve open, C header to A closed, C header ,
to B open. l 53 ) I i
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- USNRC SENIOR REACTOR' OPERATOR EXAMINATION Question 54
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l: A large instrument air leak has occurred on' Unit 1. As PCV-18-5 (Unit 2 to Unit 1 4 Instrument Air Crosstie) is stroking open, it becomes mechanically bound in the full , open position. Assuming no operator action, which one of the following statements . correctly describes the system response? !
- a. Unit 1 (PCV-18-6) crosstie will close at 85 psig decreasing, isolating i
instrument air to Unit 2.
- b. Unit 2 instrument air depressurization is prevented by a check valve located in '
the crosstie line.
- c. Unit 1 station to instrument air crosstie will automatically open at 85 psig decreasing to supply compressed air to Unit 1. !
- d. Unit 2 instrument air system will depressurize as Unit 1 instrument air system depressurizes.
1 l I e 1 I
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i , USNRC SENIOR REACTOR OPERATOR EXAMINATION f Question 55 i Unit 2 is at 100% power,2A charging pump was running with 2B charging pump selected as backup. 2A charging pump tripped due to a faulty breaker. The following- ; conditions now exist: 2B charging pump was started to replace 2A charging pump 2A charging pump control switch was placed in the "OFF" position If pressurizer level setpoint is increased to 69%, which of the following is a correct i description of the current CVCS configuration (assume no other operator actions)? ;
- a. 2B charging pump running with no change in letdown flow
- b. 28 and 2C charging pumps running with minimum letdown flow. -
- c. 2B charging pump running with minimum letdown flow.
- d. 28 and 2C charging pumps running with no change in letdown flow.
f s r h t 55 . 1
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a F : i , e USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 56 ! Unit 2 is at 100% power. The feedwater control for 2A S/G is in manual for. I&C calibration. 2A steam generator level is currently 65% WR. Which of the following , would be the response of the plant if turbine power was reduced to 90%? (Assume no operator action) 1A Steam Generator Level will: t
- a. stabilize at a higher level with feed flow greater than steam flow.
r
- b. remain constant at 65% WR as the Main Feed Reg _ Valve cycles.
- c. increase to 82% WR and and remain at approximately that level as the Main Feed Reg Valve cycles.
- d. increase to HI-Hi Level resulting in a Turbine / Reactor trip.
( i I r h 56
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 57 Unit 2 is in Mode 3 Which one of the following conditions will automatically terminate a Waste Gas release on Unit 27
- a. I&C inadvertently initiates a full SlAS
- b. Waste Gas Radiation Monitor (PAG-203)in Alert
- c. Loss of power to Met Tower equipment
- d. Loss of Fire and Security SUPS inverter 57
i USNRC SENIOR REACTOR OPERATOR EXAMINATION : Question 58
~
! i ^, _ Which of the statements correctly describes the power supply arrangement of the Unit - ) 1 and Unit 2 Containment Cooling Systems? } t i a. The 2A2 480V Load Center provides power to 2 containment coolers; the 1 A2 i 480V Load Center provides power to 2 containment coolers. l.
- b. The 2A2 480V Load Center provides power to 1 containment cooler; the 1A2 480V Load Center provides power to 1 containment cooler.
- c. The 2A2 480V Load Center provides power to 2 containment coolers; the 1A2 i 480V Load Center provides power to 1 containment cooler.
1 ) ! d. The 2A2 480V Load Center provides power to 1 containment cooler; the 1A2 1 480V Load Center provides power to 2 containment coolers. j e 1 l-t k I 1 f 2 d 58 l .
- ,- e _ __ _ .___ ____ ______.__,___i____________i_
k USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 59 The following conditions exist: I Unit 1 Turbine Startup is in progress Generator output is 150 MW 1A Condensate pump and 1 A Main Feed pump are in service Total feedwater flow is 10,500 gpm i 1 A Main Feed pump control switch is in the " Auto Recirc" position ! i Which of the following correctly describes the system response if FCV-12-1 ! (condensate recirc regulator) stroked to its full open position? .
- a. 1 A Condensate pump recirc valve strokes full open and maintains system flow.
- b. 1A Condensate pump trips on low flow. !
- c. 1 A Main Feedwater pump recire valve strokes full open and maintains system flow. L
- d. 1 A Main Feedwater pump trips on low flow.
l a 59 j i
1 l q 1 USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 60 Unit 1 is in the process of a Reactor Startup, the RO is withdrawing Group 7 in Manual Sequential when Annunciator K-26,"CEDMCS TRBL/ CONT GRIPPER VOLTAGE HIGH" locks in. Which of the following correctly describes the probable .I cause of this alarm?
- a. The Coil Power Programmer for a specific CEA has failed and any further movement to Group 7 will result in a dropped CEA.
- b. Continuous group motion was for >30 seconds, the' gripper coils are experiencing a high voltage condition.
- c. The ACTM module for a specific CEA has sensed an abnormal condition, holding voltage is being applied to its Upper Gripper.
1
- d. The Coil Power Drogrammer has sensed a fault to a specific CEA, the faulted l CEA has been tiansferred to the Hold Bus. 1
-1 i
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I 60 - - - _ _ _ _ _ _ - . . _ _ - _ . _ _ - _ . - . . ,- - . . , - , , . . l
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 61 Which one of the following statements correctly describes the RCP Oil Lift Pump system following a LOOP /SIAS with both Diesel Generators supplying power to their associated emergency busses? Each RCP:
- a. will have no oil lift pumps running, but only one will be available for manual start.
- b. will have both oil lift pumps running.
- c. will have no oil lift pumps running, but both will be available for manual start. ;
- d. will have one oil lift pump running
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61 i i
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 62 2-EOP-6, " Total Loss of Feed" addresses the use of a Condensate pump to establish feed to the steam generators if certain conditions are met.. Which one of the following situations would warrant the use of a Condensate pump?
- a. A loss of both non-vital 4160 KV busses has occurred and steam generator pressures are 600 psig.
- b. A trip from 80% power has occurred and Steam Generator levels are 45%
wide range.
- c. A trip from 30% power has occurred and Steam Generator levels are 35%
narrow range.
- d. Steam Generator levels are 25% wide range and steam generator pressures are 650 psig.
i 62 l I
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 63 ; i i isolating a faulted SG during implementation of 1-EOP-04, " Steam Generator Tube Rupture" may result in Control Room indication of an " inverted AT" (T-cold > T-hot). Which one of the following statements describes how this indication would be- i developed?
~
- a. During forced circulation with only two RCPs, reverse flow in the idle loops '
inverts the indicated AT. , i
- b. During forced circulation with only two RCPs, reverse heat transfer from the isolated SG to the RCS inverts the indicated AT.
- c. During natural circulation using only one SG for cooldown, reverse flow in the idle loops inverts the indicated AT. *
)
- d. During natural circulation using only one SG for cooldown, reverse heat ;
transfer from the isolated SG to the RCS inverts the indicated AT. 1 E
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 64 Unit 2 is performing a rapid unit shutdown due to a Steam Generator tube leak on the 2A Steam Generator. According to ONOP 2-0800030, " Steam Generator Tube Leak", under what conditions would the ROs be required to trip the reactor and turbine?
- a. Three of fou- TMLP pretrips are in alarm on the RPS.
- b. Pressurizer level cannot be maintained with 28 gpm letdown and all available charging puraps running.
c The difference between actual Pressurizer level and Pressurizer level setpoint exceeds 6.6%.
- d. Pressurizer level cannot be maintained with V-2522 closed and all available charging pumps running.
+.
64 l l
- _ 'USNRC SENIOR REACTOR OPERATOR EXAMINATION E ~ Question 65 I
! -A fire has been reported in the Unit 1 Turbine Switchgear room. The NWE (fire team t leader) is currently at the site medical facility after being taken ill. Which of the 3-following individuals can be used to fill the team leader vacancy? (assume shift is at' minimum complement IAW AP 0010120," Conduct of Operations")
- a. Unit 1 Desk RCO (qualified as SRCO)
- b. Unit 1 SNPO (qualified as SNPO)-
I
- c. Unit 1 NPO (qualified as NPO)
U
- d. Unit 1 ANPO (qualified as SNPO)_
b
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65 I
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USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 66 The Unit 2 CCW Radiation Monitor has gone into an alarm condition. Further investigation revealed the solenoid flow control valve closed and isolated flow. Which of the following is the probable cause of this condition?
- a. Low CCW flow to the monitor
- b. High CCW radiation to the monitor
- c. Low CCW pressure to the monitor
- d. High CCW temperature to the monitor 1
66
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 67 While Inser1!ng CEA Group 5 for ASI control at 132", CEA #8 slips to 121". Which of the following are the rod position indications for CEA #8 as seen by the RO7
- a. ADS - 132", DDPS - 121", Digital backup-132"
- b. ADS - 121", DDPS - 132", Digital backup-132"
- c. ADS - 132", DDPS - 121", Digital backup-121"
- d. ADS - 121", DDPS - 132", Digital backup-121" i
67
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w , 9 USNRC SENIOR REACTOR OPERATOR EXAMINATION l Question 68 I The plant is at 65% steady state power to perform maintenance on a leaky turbine EH line, Due to an increase in the EH leak, the RO manually trips the reactor and turbine. Which of the following correctly describes the response of the Steam Bypass Control System 5 seconds after the trip? (assume system in auto)
- a. Rx trip quick open, followed by pressure modulation only.
- b. No Rx trip qJiCk open, temperature and pressure modulation only,
- c. Rx trip quick open, followed by temperature and pressure modulation.
- d. No Rx trip quick open, pressure modulation only.
68
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 69 ( i i l I Unit 1 is at 100% power, steady state.1 A and 1B steam generator pressures are at l 890 psig. If a small steam leak inside containment were to occur, which of the ! following is the minimum value that 1 A steam generator pressure would have to change to cause a reactor trip strictly on steam generator parameters?
- a. 13 %
l l l
- b. 15%
- c. 30%
- d. 33%
69
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USNRC SENIOR REACTOR OPERATOR EXAMINATION i Question 70 The following Unit 2 conditions exist: CCW surge tank Lo-Lo level switch (LS-14-6A) is valved out for replacement 2A CCW pump develops a large discharge flange leak ; The leak exceeds the capacity of makeup flow Assuming no operator action, which of the following correctly describes FIRST response of the system?
- a. "A" side N header valves (HCV-14-8A and HCV-14-9) close.
- b. 2A CCW pump trips on low suction pressure.
- c. "B" side N header valves (HCV-14-8B and HCV-14-10) close.
- d. 2A CCW trips on thermal overload.
J l l 70
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 71 Unit 1 is in mode 3, RCS cooldown and depressurization in progress in preparation for a refueling outage. Which one of the following actions must be taken by the operators if a safety related 125 VDC bus became deenergized? The operator must MANUALLY:
- a. close the Main Steam Isolation Valves to prevent an uncontrolled cooldown of the RCS.
- b. close the PORV block valves to prevent an uncontrolled depressurization of the RCS.
- c. close the Atmospheric Steam Dump Valves to prevent an uncontrolled cooldown of the RCS.
- d. close the Pressurizer Spray valves to prevent an uncontrolled depressurization of thE RCS.
71
i USNRC SENIOR REACTOR OPERATOR EXAMINATION , 1' Question 72 The following conditions exist: Unit 2 is at 100% power Charging and letdown are in normal configuration . Regen HX inlet pressure is 2250 Regen HX outlet pressure is 2200 if a 10 gpm 8 'ak occurs in the letdown line downstream of the regenerative heat exchanger, wnich one of the following automatic actions will occur as a result of the leak? (assume system in auto) Letdown flow;
- a. will decrease due to LCV-2110.' closing.
- b. will isolate due to V-2516 closing.
- c. will increase due to LCV-2110P opening
- d. will isolate due to V-2515 closing. ,-
I' 6 72
USNRC SENIOR REACTOR OPERATOR EXAMINATION
. Question 73 The following conditions exist:
Unit 2 is at 100% power DDPS computer #1 is out of service for I&C repair The power supply for DDPS computer #2 has failed Which of the following correctly describes the actions that must be taken by the control room crew and the reason for those actions? Within four hours, reduce power to:
- a. 85%. If the DDPS cannot be restored within 24 hours, the Unit must be
- placed in mode 3. The power reduction is due to linear heat rate monitoring, the shutdown is due to CEA position indication.
- b. 88%..lf the DDPS cannot be restored within 72 hours, the Unit must be placed in mode 3. The power reduction is due to linear heat rate monitoring, the shutdown is due to CEA position indication.
- c. 85%. If the DDPS cannot be restored within 72 hours, the Unit must be placed in mode 3. The power reduction is due to CEA position indication, the shutdown is due to linear heat rate monitoring.
- d. 88%. If the DDPS cannot be restored within 24 hours, the Unit must be placed in mode 3. The power reduction is due to CEA position indication, the shutdown is due to linear heat rate monitoring.
l 1 1
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g USNRC SENIOR' REACTOR OPERATOR EXAMINATION Question 74 ) i d The following conditions exist: ' Unit 1 is at 100% power 1 - Linear Range Control Channel # 9 is out of service for I&C repair. . . - Linear Range Channel # 10 is supplying the RPS Power Ratio Calculator > 4 l : Which of the following would be the system response if Channel 10 upper detector
- failed high?
i i [ a. Actual ASI as indicated on the Power Ratio Recorder would violate the negative setpoint, an alarm would be generated. . i b. .The lower setpoint for ASI as indicated on the Power Ratio Recorder would
- become more negative, no alarm would be generated. ;
i 1 i
- c. Actual ASI as indicatec on the Power Ratio Recorder would violate the 'l
- positive setpoint, an alarm would be generated. '
. r
- d. The upper setpoint for ASI as indicated on the Power Ratio Recorder would :
become more positive, no alarm would be generated. t 1 E g.. I. 4 4 i 74 . 4 4 4
l l USNRC SENIOR REACTOR OPERATOR EXAMINATION I Question 75 Wtin one of the following events would cause the Unit 2 Containment Evacuation Alarm to be automatically sounded?
. a. The Fire and Security SUPS looses all power.
- b. An HP team moves a 5500 MR source past MA and MB CIS monitors during Mode 5 operations.
- c. An RO depresses the " Check Source" pushbutton on the MA CIS monitor,
- d. A full Unit 1 CIAS is initiated.
i
%a 9 75 f
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 76 Which one of the following Unit 1 radiation monitors utilizes a different type of detector than the same monitor on Unit 2?
- a. Control Room Outside Air Intake Monitor
- b. Main Steam Line Monitor
- c. Containment Atmosphere Monitor
- d. Letdown Radiation Monitor 76 1
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 77 The 18125VDC bus has been lost due to a wiring fault. The control room crew is carrying out the actions of ONOP 1-0030136, " Loss of a Safety Related D.C. Bus" The ANPS has directed the ROs to align the 1D 125 VDC bus to the 1B 125 VDC non-safety bus. Which of the following statements correctly describes the process of bus alignment?
- a. The 1B 125 VDC bus can be fed directly from the 1D 125VDC bus only by aligning the keyswitches on RTGB 101.
- b. The 1B 125 VDC bus can be fed from the 1D 125VDC bus throuah the 1 AB 125 VDC bus only by unlocking and aligning local breakers. ,
- c. The 19125 VDC bus can be fed directly from the 1D 125VDC bus only by unlocking and aligning local breakers.
- d. The 1B 125 VDC bus can be fed from the 1D 125VDC bus throuah the 1 AB 125 VDC bus only by aligning the keyswitches on RTGB 101..
4 77 I
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 78 Unit 2 is at 100% steady state power. Annunciator B-13, "2A2 4.16 KV A Current Trip" has just gone into alarm. Which one of the following correctly describes the effect of this condition on the 2A Emergency Diesel Generator? The 2A Emergency Diesel Generator:
- a. starts, but does not load on the 2A3 bus.
- b. does not start. It will only start on 2A3 bus undervoltage.
- c. starts and loads on the 2A3 bus.
- d. does not start, but will start and load on the 2A3 bus when the diesel lockout relay is reset.
- i n
d 4 1 78 l
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i. i USNRC SENIOR REACTOR OPERATOR EXAMINATION Y - Question 79 J
- An uncomplicated reactor trip has occurred 'on Unit 1. One minute after the trip,
- offsite power is lost. No post trip operator actions have been performed. Which of . ,
the following correctly describes the status of the MSR block valves at this time? ' , The MSR Block Valves: ~ t j a. are open and must be manually closed by the control switches on RTGB 102. , i ! b. are closed automatically on the turbine trip signal. 1 j c. are open and must be closed manually by the potentiometer on the Reheat ' ! Control Panel. 4 : i p d. are closed automatically on low steam pressure to the MSRs. ] 4 nt i 4 I j '79 1 i i
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k - ,i h USNRO SENIOR REACTOR OPERATOR EXAMINATION
-t
!- Question 80 ! 1 4. 4 ; i 4 j- The following conditions exist: 5 i ' { Uet 1 is at 20% power, returning from a refueling outage, turbine on hold - j - MlC is +1 p0m/ F - I The RO ;,-iiiates steam generator blowdown at 120 gpm/SG -l ! Which of the following describes the immediate plant response to this evolution? f ! Assume no operator action. i i 4 l a. Reactor power increases, letdown flow increases, feedwater flow increases l J I b .- Reactor power decreases, letdown flow decreases, feedwater flow decreases - , I
- c. Reactor power increases, letdown flow decreases, feedwater flow decreases i
- c 4
l d. Reacto: power decreases, letdown flow increases, feedwater flow increases
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USNRC SENIOR REACTOR ^PERATOR EXAMINATION Question 81 . Unit 1 is in Mode 1,100% power. The SNPO is preparing the 1B Containment Spray Pump for its quarterly surveillance run Which of the following correctly describes an additional manipulation that the SNPO must perform on Unit 1 but not on Unit 27
- a. Open the CCW isolation valve to 'e 1B Containment Spray pump seal heat exchanger.
- b. Open 1B Containment Spray pump manual recirc valves.
- c. Close MV-07-38, B CS Header Isolation i d. Close the Sodium Hydroxide tank vent to atmosphere.
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USNRC SENIOR REACTOR OPERATOR EXAMINATION l i t .; 4 Question 82 l 1 l The following conditions exist: j An ESDE/ LOOP has occurred on Unit 1 LIC 1110X (selected for pressurizer level control) failed low on the trip the ESDE was terminated when the MSIVs were closed RCS pressure dropped to 1600 psia during the event - , RCS pressure is now 1720 psia and stable. Pressurizer level is 29% Other than swapping to the operable Pressurizer level channel, which of the . following correctly describes the minimum actions required to regain pressurizer ' heaters with the plant in its current configuration?
- a. Block SIAS, reset the 1 A3 and 183.4.16 KV pressurizer heater breakers,- .
place the low level cutcut switch to the X position, reset all backup heaters.
- b. Reset SIAS , place the low level cutout switch to the X position, reset backup heaters 81 and 84.
- c. Reset SIAS, place the low level cutout switch to the Y position, reset _all backup heaters.
. d. Block SIAS, reset the 1 A3 and 183 4.16 KV pressurizer heater breakers, place the low level cutout switch to the Y position, reset backup heaters B1 and B4.
l' i 82 8
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. USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 83 -
+
4 - The 2A Emergency Diesel Generator air receivers 2A1 and 2A2 have been placed on i i a clearance for valve replacement. The receivers are completely depressurized, when i a loss of offsite power occurs. Assuming that the 2A EDG has no other existing ' , 4 clearances or deficiencies when the LOOP occurs, which of the following describes i
- the response of the 2A EDG air start system to the LOOP?
4 I i a. Air start motors will. engage on both engines, there is sufficient pressure to start the 2A EDG. ,
- b. Air start motors will engage on only one engine, there is insufficient pressure to start the 2A EDG.
- c. Air start motors will engage on only one engine, there is sufficient pressure to start the 2A EDG.
- d. Air start motors will engage on both engines, there is insufficient pressure to start the 2A EDG, I
1 a ) 1 83 j
' 1 y
- i i
4 USNRC SENIOR REACTOR OPERATOR EXAMINATION 1
- Question 84 -
! Unit 2 is at 100% steady state power Total RCS leakage has been determined to be 11.3 gpm. The following data is available to the operators: 2.3 gpm h ekage into the Quench tank 2 1.4 gpm . leskage into the Reactor Drain Tank 1.8 gpm leskage past all check valves from RCS to Si system l 450 gpd 2A S/G primary to secondary leakage l
- l. 375 gpd 28 S/G primary to secondary leakage
! 1.7 gpm charging pump seal leakage > } Which one of the following identifies the type of RCS leakage that will require the plant to be shut down? j i
- a. Pressure Bc>undary Leakage l
i
- b. Unidentified Leakage ..:
- c. Identified Leakage l
- d. Primary to Secondary Leakage 4
+
1 i s:
- f 84 ,
(
)
G- - - - - . . .:-- -- _ _ __-- -- -
- -- - - - - - - - - v
_. . __ . _ . _. . _ _ . _ . - . . . _ . . _ _ _ _ - _ _ _ _ _ _ .. ~ _ . _ ._. USNRC SENIOR REACTOR OPERATOR EXAMINATION . Question 85 } l ' Unit 1 operators have manually tripped the reactor and turbine from 100% power due ;
- - to an unrecoverable loss of instrument air. As the Board RO is performing his SPTAs, he notices a higher level in the Quench Tank than previous to the trip.. Assuming no l other failures, which of the following correctly describe the most' probable cause of 1 Quench Tank higher level? ,
e a. RCP seal bleedoff. ! l .
! b. PORVs lifted momentarily 'on the manual trip from 100% power.
l
- c. The Quench Tank level detector drifts high as instrument air pressure-i decreases.
i I d. Water in the quench tank heats up and expands due to loss of CCW cooling - to the quench tank. e L e s m' I 85-t
.5-._,-_._._ _ _ _ . _ m_.1______ m.__., ._ _ . -. - . . . e
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 86 5 The following conditions exist: A large break LOCA has occurred on Unit 1 1-EOP-3, " Loss of Coolant Accident" is being implemented Hydrogen Analyzers initially indicated 0.7% Hydrogen concentration has increased another 2.6% since the initial reading No equipment is out of service Which of the following actions are required to satify the Containment Combustible Gas Control safety function?
- a. Ensure both Hydrogen Recombiners and Containment P' iy in service,
- b. Ensure the Hydrogen Purge System in service.
- c. Ensure both Hydrogen Recombiners and Hydrogen Purge System in service.
- d. Ensure both Hydrogen Recombiners in service.
I 86
- __ .- . _. . . . _ - , .._. ~ ._ . _ . ._. . _ -_ . _ _ . ._ . - .
! USNRC SENIOR REACTOR OPERATOR EXAMINATION l Question 87 l u A reacator startup is about to commence on Unit 2; The ANPS has directed the RO i to verify RCS temperature is greater than 515'F. ~ Which of the following is the bases ! for the ANPS direction?
- a. To ensure the pressurizer is operable with a steam bubble 'and adequate ;
shutdown margin exists in the event of an uncontrolled steam release. I
- b. To ensure the protective instrumentation is within its normal range and the .
pressurizer is operable with a steam bubble.
- c. To ensure the pressure vesselis above the minimum RT, temperature and FTC is within its analyzed temperature range. t
- d. To ensure adequate shutdown margin exists in the event of an uncontrolled -!
steam release and MTC is within its analyzed temperature range. I r P v s> 87 j l
-a - . ~ . __ _ - - --+ _ _ __ - - - - - - - - - - - - - - - - - - -t -
~ > , - --
. . - . - - . . . - . - .---. ~ . - .
; USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 88 ;
Unit 1 has tripped from 100% power due to a feedwater problem. 'According' to AP-0010120, " Conduct caf Operations", which of the following is the approved method of chronological log entries during this event?
- a. The events can be reconstructed at a later time using all available references, . I but must be made in chronological order when making an entry.
- b. The desk RO will record all events in the RCO chronological log as they occur, after performing SPTAs. ;
- c. The events can be reconstructed at a later time using all available' references, chronoingical order is desired but not necessary when making an entry. >
. i
- d. A designated person, preferably the STA, will record all events in the RCO chronological log as they occur.
i i l i I j i 1 l I I I l 1 r j 88 i l
)
o 1 j
. . . - , - ~ , . - ,
i
1 I USNRC SENIOR REACTOR ' OPERATOR EXAMINATION Question 89 1 An l&C tech has been instructed to lift a lead in RTGB 202 as part of a NPWO
- package to replace an AFW flow transmitter. Which of the following correctly j describes all the requirements of lifting the lead?
- The I&C Tech
4
- a. may lift the lead at any time with the permission of the ANPS, since the lead -;
i is covered under a PWO. ;
- b. must identify the lead by highlighting it on the CWD, a second person i independently verifies the correct lead has been identified, the lead can then <
be lifted. } c. must identify the lead using proper reference material (CWD, Schematic) to j- the ANPS, the ANPS must sign the NPWO, the lead can then be lifted. 3
- d. must identify and tag the lead, a second person independently verifies the correct lead has been identified, the lead can then be lifted. ,
4 4 f 3 4 r i 89 i 9 y i ___ -_- - - - - -ma _mm'.+--'_1- - ~ ed -._ --_ t___ a_.a ___m _ _
, - . . . - _ - = -.- . .. .- -
1 USNRC SENIOR REACTOR OPERATOR EXAMINATION' - Question 90 4 1 According'to ADM-29.02, "ASME Code Testing of Pumps and Valves", which of the following criteria is used if a pump falls into the " Alert" range due to low discharge'- l pressure during a surveillance test? l The pump shall:
- a. be placed out of service until the cause of the deviation has been determined ' ;
and the condition corrected, I b.' be tested monthly until the cause of the deviation has been dete'rmined and the condition corrected.
- c. be tested at double the frequency until the cause of the deviation has been determined and the condition corrected. -
- d. be re-tested after the baseline discharge pressure is changed to reflect ;
current pump performance data.
- i A
i e f r i g e 90 } P
?
.. -- - - ._ . _ - - _ - _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
._ _ . _ . . ~ _ . _. _.. _ _. _ . . . . . _ _ _ . . ..
l .i USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 91 I i i
)
i The Unit 1 SNPO was in the process of performing a valve lineup when he discovered an incorrect valve number and valve position. To correct this condition, he generated ; a temporary change (TC) to the procedure IAW ADM-11.03, " Temporary Change to .t Procedures". Which of the following describes the status of the TC sixty five days , later, assuming no PCR was written? r The Temporary Change: ; P
- a. was reviewed by FRG and permanently incorporated into the procedure. L
- b. still exists in the TC log
- c. was cancelled after 45 days -
- d. was automatically incorporated into the procedure after 60 days.
I I L r i e h i 91 l
- - . - . . . - - _ - . . .. -.- -.. _ . - - . . ~ _ . -
t ! I
- USNRC SENIOR REACTOR OPERATOR EXAMINATION j 1
- Question 92 1
1 I , The Unit 2 RO is in the process of performing the 2A AFW pump surveillance. The ,-;
- surveillance has to be run for 1 hour due to temperature data requirements. The on- '
coming shift is arriving. According to AP 0010120," Conduct of Operations", which of . the following correctl/ describes the requirements concerning shift turnovers and-surveillances? .[,
- a. Surveillance:; must be completed prior to shift turnover.
i
. b. Surveillance:; cannot be performed within one hour of shift turnover time. ;
i
- c. Surveillances must be stopped and continued after shift turnover.
- d. Surveillances must be in a steady state condition prior to shift turnover.
i t L L 92
USNRC SENIOR REACTOR' OPERATOR EXAMINATION Question 93 t 1 The 1B CVCS lon Exchanger has been placed in service following resin replacement. Although the RO rinsed the ion exchanger for 1 hour, after 10 minutes of in service
- time, the following conditions exist
RCS Tcold 548.9 Reactor Power. 100.6 % According to AP 0010120, " Conduct of Operations", which of the following is the correct action to be taken by the control room crew?
- a. Immediately implement ONOP 1-0250030, " Emergency Boration".
- b. Reduce reactor power to 5100% within 15 minutes.
- c. Reduce reactor power to 5100% within 30 minutes.
- d. Trip the Reactor and Turbine.
s I 93
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 94 When processing an RWP, which one of the following is the MINIMUM criteria that requires the RWP to be processed through a pre job ALARA review?
- a. Dose estimate of the job exceeds ten (10) Manrem.
- b. Any work to be performed inside Containment.
- c. Dose estimate of the job exceeds one (1) Manrem.
- d. Any work to be performed in contaminated areas.
l 94
h USNRC SFNIOR REACTOR OPERATOR EXAMINATION i Question 95 , t For entry into a VERY HIGH RADIATION AREA, which of the following correctly .- describes ajl! requirements that must be met?
- a. Continuous HP coverage,~ a high range dosimeter, HP department head approval, NPS approval.
- b. A specific RWP, continuous HP coverage, HP department head approval,.
NPS approval.
- c. A specific RWP, a hand held survey instrument, a high range dosimeter, HP.
department head approval.
- d. Continuous HP coverage, a hand held survey instrument, HP department head approval, NPS approval.
95
l USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 96 1 l l An FPL employee from Turkey Point has arrived at St. Lucie to support the Unit 2 refueling outage. Upon arrival, he presents HP with the following dose records: Time Period FLeility TEDE January 1-February 19 Crystal River 675 MR February 23-March 31 St. Lucie 210 MR April 7-June 19 Turkey Point 115 MR Which one of the following correctly describes the status of this worker in regard to the amount of exposure ne can receive at St. Lucie Plant?
- a. He may receive an additional 3800 MR at St. Lucie but will need a dose extension.
- b. He may not work at St. Lucie this year, he has already exceeded Florida Power and Light guidelines for TEDE.
- c. He may receive an additional 1300 MR at St. Lucie but will need an extension.
- d. He may receive an additional 3300 MR at St. Lucie, with no extension necessary.
96
l USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 97 The following~ conditions exist: i
- Unit 2 is in Mode 3, cooling down for a refueling outage. .
RCS pressure and temperature are 1400 psie and 497"F, respectively.
- 2C Charging pump is OOS for accumulator depressurization Which of the following would be the correct procedure selection to mitigate a 120 gpm RCS leak occurring inside containment?
The operating crew should:
- a. Enter 2-EOP-3, " Loss of Coolant Accident".
l
- b. Enter 2-ONP-01.01 " Plant Condition 1 - Steam Generator Heat Removal LTOP not in Effect" !
- c. Enter ONOP 2-0120031, " Excessive Reactor Coolant System Leakage"in conjunction with 2-EOP-3, " Loss of Coolant Accident"
- d. Enter ONOP 2-0120031, " Excessive Reactor Coolant System Leakage" in conjunction with 2-ONP-01.01 " Plant Condition 1 - Steam Generator Heat Remova! LTOP not in Effect" .
g+# 97
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 98 EOP-15 has been implemented and the following success paths are in service: RCS and Core Heat Removal Success Path 3 is not being met RCS Inventory Control Success Path 2 is not being met i RCS Pressure Control by Success Path 3 Reactivity Control by Success Path 3 Which of the following correct;y describes the order in which each success path should be addressed in this event?
- a. Reactivity Control, success path 3; RCS Inventory Control, success path 2; RCS and Core Heat Removal, success path 3; RCS Pressure Control, success path 3. .
l
- b. RCS and Core Heat Removal, success path 4; RCS Inventory Control, ;
success path 3; RCS Pressure Control, success path 3; Reactivity Control, success path 3. : i
- c. RCS Inventory Control, success path 2; RCS and Core Heat Removal, success path 4; Reactivity Control, success path 3; RCS Pressure Control, success path 3.
- d. Reactivity Control, success path 3; RCS and Core Heat Removal, success path 4; RCS Inventory Control, success path 3; RCS Pressure Control, success path 3.
98
USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 99 The Site has been placed under a Hurricane Warning, and the NPS has declared an Alert. He has tasked you, the Unit 1 RO, with making the State notification call. All phone lines are down due to high winds. While using the Hot Ring Down Phone, you get no iesponse from State Warning Point (SWP). Which of the following is the next proper course of action in accordance with EPIP-02, " Duties and Responsibilities of the Emergency Coordinator"? -
- a. Ask the Unit 2 control room and make the call using their HRD.
- b. Use the cellular telephone in the Unit 1 control room.
- c. Use the ESATCOM system in the Unit 1 control room.
- d. Use the Local Government Radio in the Unit 1 control room.
l I e 4 4 l'- 99 i i
i USNRC SENIOR REACTOR OPERATOR EXAMINATION Question 100 The following conditions exist: Unit 2 is at 100% power An electrician, performing a surveillance, deenergizes the 283 4.16 KV bus The 2B EDG successfully starts and loads All plant equipment is operable Assuming no operator action aside from resetting individual pressurizer heater banks on RTGB 203, which of the following correctly describes the TOTAL pressurizer heater availability at this time?
- a. Two proportional banks, six backup banks
- b. One proportional bank, three backup banks
- c. One proportional bank, four backup banks
- d. Two proportional banks, four backup banks 100 l
__ . m. _ . _ . ..__.m . . .._ . . _ . . . . . . _ . . - m -. -m..m_ _m.- . _ . _ _ . . - . . _ . _ . . . . _,_
"v- v EVENT / CLASS b
O k< UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY g Q @ 1.A. ADNORMAL Reactor Coolant System "O o O RCS Leakage GREATER LOCA GREATER THAN A release has occurred or is PRIMARY (RCS) Leakage THAN SO opm capacity of charging pumps in progress resulting in: 5, Q m O LEAK RATE o (Page 1 of 2) 1. RCSleakage 1. Charging / letdown 1. RCS leakage greater 1. Containment High Range 3 $ GREATER THAN mismatch or measured than 132 gpm occurring Radiation monitor greater 10 gpm as Indicated . RCS leakage ira 1icates with RCS pressure by-than 1.46 X 10' Rcht (If greater than 50 gpm above HPSI shutoff CHRRM Inoperable. Post- p but less than 132 gpm head. LOCA monitors greater A. Control Room RCS leak. 8 observation
@ than 1000 mR/hr). Q
- 2. RCS isakage greater OR c
@ than available makeup 2. Performan7c of EPIP-09 OE B. Inventory balance occurring with RCS calcutation OR pressure below HPSI (O"-site Dose Calculations) or g
m hd (f) # shutoff head. measured dose rates Z CD !" C. Fie!d3servation OR trom off-site surveys O y '
@ 3. Loss of RCS subcooted ]
D. Emergency margin due to RCS indicate site boundary (1 mite) exposure levels g Om q g g Coordinator ga y 3> leakage (saturated have been exceeded es r.O FM d judgement OR conditions). OR Indicated by either A. B. C or D below: $ E O Z
- 2. Indication of leaking 4. Containment High Range (f} g ~g O, 5m RCS safety or relief Radiation Monitors A. 1000 mrem /hr m O valve which causes indicate to g~ ZH T *n (total dose rate) O y RCS pressure 'o drop m below 1600 p-7.3 X 10* R/hr (if CHRRM inoperable.
-4 a h g Post-LOCA monitors B. 1000 mrem (total dose - TEDE) 6 Z d
m 33 Z indicate between C 100 and 1000 mR/hr). C. 5000 mrem /hr (thyroid dose rate) []) r-g M h D. 5000 mrom (thyroid dose - CDE) (continued on next page) L 1.A. A9 NORMAL PRIMARY A LEAK RATE @ k O AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
]
m
i __ m _ m. . . . _ m. _ . _ _ . . _ . . . . . . _ . . . _ _ - . . - . _ _ . . .. - _.. , . . _ _ . _ , _ . . = . . _ . _ _ _ . _ . . . _ . . _. . w t-
$ v3 EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY g hl 1.A. ABNORMAL m 8 5; PRIMARY Loss of 2 of the 3 fission product barriers with 5 ' 22 oi b'
LEAK RATE imminent loss of the third 6
" O (Page 2 of 2)
(any two of the foRowing , exist and the third is imminent). ,I
- 1. Fuel element falture $I g ct i
(con!!rmed DEO l-131 g E! activity greater than-275 pCi/mL). m 2] o 5i t' i AND O E{
- 2. LOCA or Tube rupture on m CD r, unisolable steam 2 @ ,
generator. )> 'T1 MO m m O l
- 3. Containment integrity, Breached.
g hy ya H l o g_. - ! ts) CD I C O ; NOTE O E O Also refer to Potential -- @ [ Core Melt Event / O y --( T m I Class 6.A. ya h Z g j
- O_ m z H I
-4 l D Z s W O r- -
m m ! CD l [ 1.A. ADNORMAL PRIMARY g[ LEAK RATE o:
^ S!
O AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
- o. ;
to , 03 1 I
. - . _ _ . . _ _ __ _ - m.. _
. .c _ ~ . . = - - . . - . - - -- - . . . - . - _ - . _ . _ . . . . - - . - - _ - - - - . .
9 w -. ' $ n! EVENT / CLASS UNUSUAL EVENT ERT O
- SITE AREA EMERGENCY GENERAL EMERGENCY m M 5i 1.B. ABNORMAL RCS PRt!SEC Leakage Rapid cross failure of one Rapid cross falture of steam g o 5L Loss of 2 of the 3 fission PRIMARY TO steam generator tube generator tubes (GREATER product barriers with g Q m
O $5 SECONDARY (7
- 1. Measured RCS to (WITHIN charging pump THAN charoina pump 9
LEAK RATE secondary leakage capacity) with loss of offsite capachy) with a loss of imminent loss of the third (any two of the fo!!owing 3 y
'l (Page 1 of 2) exceeds Tech. Spec. power offsite power
' exist and the third is limits. imminent). AND 1. Measured RCS to . 1. Measured RCS to
- 2. Secondary plant activity 3 secondary leakage Is detected. greater than Tech. Spec.
sex ndary leakage is r/ eater than charging
- 1. Fuel element failure (confirmed DEO h131 m [l n:
Lim!ts and within pump capacity. activity greater than E c' ,
- charging pump capacity.
AND M 275 pCVmL). O $! 2 Secondary plant activity
- 2. Secondary plant activity is detected.
AND
- 2. LOCA or Tube rupture g
m h: CD E Is detected. AND on unisolable steam Z CD ". l AND 3. Loss of both Non-Vital O
- 3. Loss of both Non-Vital 4.16 KV buses.
generator. 5y 'h 4.16 KV buses. AND g 9'y g 6
- 3. Containment integrity breached. O m ' --I>
y
>--i (continued on next page)
(continued on next page) { d gg g Z NOTE - 3m in O I Also refer to Potential Core Melt Event / *
$ O A
p M Class 6.A.
" {
7 z H m d Q
> m Z ;
O
~
m m ; CD 1.D. ABNORMAL PRIMARY TO m :- SECONDARY gj LEAK RATE a mr AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR fo CD
. - . . .~ . .-w . _- - -.. - . - - -. - . -- - --. . ..- .- . - . . _ . - . . . - . = . . . . . .
%. v T
EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY g Q j: 1.B. ABNORMAL Rapid failure of steam T O !. Rapid fa!!ure of steam PRIMARY TO generator tubes (GREATER generator tube (s) (GREATER g, Q m O {; SECONDARY THAN charginq pump THAN ch.arging pump LEAK RATE capacity) capacity) with steam release 3 'i (Page 2 of 2) in prooress *
- 1. Measured RCS to '
secondary leakage 1. Measured PCS to greater than charging $[ secondary leakage pump capacity. greater than charging [. AND pump capacity. {;
- 2. Secondary plant activity AND m is detected. 2. Secondary plant activity D O S'i '
is detected. m g hi (f) E' AND Z (/) P'
- 3. Secondary steam release O ~
m in progress from affected dy ; generator (i.e., ADVs, g O1 q g 5 : Steam Safety (s) or m u3 F> y > , H Unisolable.) E O EE O 2 o
- mm Ri O m
S udoz " m m d^ b z K o m Z d I i d O ,
> m CD z
g t
!N Ri rn I
1.0. ABNORMAL PRIMARY TO SECONDARY si O-LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR R i m Oo 6 1
-...n .n - , - . ., - . ,,
J V v I e !
$ h5 EVENT / CLASS UNUSUAL EVENT ALERT O a t SITE AREA EMERGENCY GENERAL EMERGENCY m M 5f 1.C. LOSS OF Rapid depressurization of Ma!or steam teak with Major steam leak with 0 0 $!
A release has occurred or is in - O $; SECONDARY secondary plant GREATER THAN 10 opm GREATER THAN 50 apm Q prooress resultino in: . m (( COOLANT 3 (Page 1 of 2) 1. Rapid drop in sither primary / secondary leakage primary / secondary leakage and fuel damage indicated 1. Contalnment High Range 3 y -
'L steam generator 1. Rapid drop in either Radiation monitor greater pressure to less than steam generator 1. Rapfd drop lr. 47.et iinan iA6 X iu H/nr pt 600 psia. pressure to less than steam generator pressure CHRRM inoperable. Post-3-
, 600 psia. to less than 600 psia. - LOCA monitors greater than AND AND 1000 mR/hr), [{
- 2. Known prt/sec leak of nj
- 2. Known prt/see leak of OR greater than to gpm.
c: greater than 50 gpm. 2. Performanc7e f EPIP-09
- AND AND g)
O E{ (Off-site Dose Calculations) :: j
- 3. Secondary plant activity is detected.
- 3. Secondary plant activity is detected.
or rnaasured dose rates from off-site surveys indicate s te m Z {FF (n " ! CD - AND boundary (1 mile) exposure O
<y
~
n
- 4. Fuel element damage is Totalloss of feedwater indicated (Refer to Fuel levels have been exceeded as indicated by either A. D. C m g Om q g 6
*] )> ,
Element Falture or D below: C I> -4 *
- 1. No main or auxiliary Event / Class 4.A). O feedwater flow available A. 1000 mrem /hr *
(t) g g { Z for greater than 15 minutes when (total dose rate) E Mm M O TLOF with once-throuah
- S $Z l\) "T1 req'iired for heat removal.
coolina initiated D. 1000 mrern yH T m AND 1. No main or auxiliary (total dose - TEDE) A h g
- 2. Steam Generator levels feedwater flow available. C. 5000 mremhr 6 Z d
m i are less than 40% wide AND Z 'D i (thyro 8d dose rate) q C
, range. 2. PORV(s) have been p m opened to factitate core D. 5000 mrem
! CD g heat removal (thyroid dose-CDE) F - m m i (contmoed on next page) , r i ! l l 1.C. LOSS OF SECONDARY uf COOLANT 0; !' -A mt ca ! AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR o ( - ' f\) l 03 i
. . . .- ~~- . . , . . . . . _ . -
i
_ .. . . .;-.. ~ --.. -. -- - - - . - - - - - - - -
'V v I
1 m :i EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 8 . GENERAL EMERGENCY m M 5 O !t 1.C. LOSS OF Loss of 2 of the 3 fission -O SECONDARY product barriers with Q m O I
. (;
COOtANT (Page 2 of 2) trnminent loss of the third (any two of the lonowing 3 y
'{ '
exist and the third is ; trnminent). ,!
- 1. Fuelelement failure iI (confirmed DEO I-131 activity greater than m
E [! [ ,' 275 pCVmL). O j[ AND
- 2. LOCA or Tube rupture g {y m g :
on uniso!able steam Z m nj generator. AND O 4> y
~
- 3. Containment Integrity 3 O E g q Breached. to F> -
--i G >O r- -
O m mI c ; NOTE y) g g Z Also refer to Potential Cor* E Mm M O S $Z Melt Event / Class 6.A. M T1
> -I " m H' % g
' 5 Z H
m 33 Z H Q
> m .
@ Z F O t
m m < m ' i 1.C. LOSS OF s ci SECONDARY a !" i COOLANT A I AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR E m - (D
+
%' w EVENT / CLASS UNUSUAL EVENT
$ f ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m b m
f, 2.A. UNCONTROLLEO Radiological effluent A refease has occurred or A retease has occurred or is in A release has occurred or is in T @ EFFLUENT Ilmits exceeded is in prooress that is RELEASE 10 times the efftuent limit prooress resulting in: progress resulting In: 7 g O g
- 1. Plant effluent O z '
- 1. Containment High Range 1 Containment High Range "
monitor (s) 1. hnt effluent Radiation Monitor greater P Radiation monitor greater than , exceed atarm monitor (s) significantly than 7.3 X 10' R,hr 1.46 X 10' Rhr (if CHRRM setpoInt(s). exceed alarm (Post-LOCA morntors inoperable. Post-LOCA rnonitors AND setpoirds. Indicate between 100 and greater than 1000 mRhr). ] (
- 2. Confirmed AND 1000 mRhr,if CHRRM analysis results 2. Confirmed ana!ysis OR m h for gaseous or results for gaseous or inoperable). 2. Performance of EPIP-09 (Off-site E [
M liquid release liquid release which OR_
- 2. Measured Dose Rates or Ocss Calculations) or measured dose rates from off-site surveys Og which exceeds exceeds 10 times ODCM timits. ODCM limits.
Offsite Dose Calculation (EPtP-09) worksheet values indicate site boundary (1 mile) exposure levels have been m gy at one mile in excess of: exceeded as indicated by either z g n, NOTE A. B. C or D below: O> g N m -< - If analysis is not analysis is not A. 50 mrem /hr (total dose- T M O available within one hour and it is 888 " "8 TEDE) or 250 mrenVhr (thyroid dose-CDE) for A.1000 mrem /hr (total dose rate)
$ >o (D
r- > O t-
~
expected that 8***
- O ha re ase s equal to 1/2 hour. N @I C 7
release is greater r grea er h n 10 Umes OR B. 1000 mrem o NE O than ODCM limit' M CI3SS 88 B. 500 mTr m,hr (total (total dose - TEDE) 3m m O classify as UNUP,UAL EVENT. ALERL dose-TEDE) or 2500 mrern/hr (thyroid C. 5000 mrem /hr *
$ Oh dose-CDE) for two (thyroid dose rate) a {7 minutes at one mile. 7 g 7 -{ y D. 5000 mrem 9
(thyroid dose-CDE) [ m W O r- - m m ODCM - refers to Chemistry Procedure C-200. Ortsite Dose Calcidation Manual (ODCM) ' l l 2.A. UNCONTROLLED EFFLUENT m RELEASE g i a rp (n i AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EPERGENCY COORDINATOR O i fG (D l-- . - _ _ - _ - -- -. - - -
V v I EVENT / CLASS UNUSUAL EVENT ALERT ! SITE AREA EMERGENCY G5NERAL EMERGENCY i 2 B. HIGH RADIATION m N High radiation levels or hioh LEVELS IN PLANT alttorne contamination which 3 0 i _ Indicates a severe degradabon 7 m ii in the control of radioactive 3 ' J rnatorials
- 1. Any valid area monitor
i a: arm from indeterrrdnable source VAth meter near or k*
, m l) greater than full scate E {t deflection (10' mR/hr).
O gi
- 2. Unexpected tant iodine or particulate airbome f-concentration of 1000 DAC z (g p' O g as seen in routine surveying or sampling.
- <> CO OR e
[n r- > q _.g I 3 Unexpected direct radiation dose rate reading or O MO F { ' CD g unexpected airbome o g radioactivity concentration g - m O y from an indeterminable , source in excess of 0 .7 o 3g .l 1000 times normallevels. qa p g ; O Z m Z d B '
-4 O ,
> m !
W Z t- O m m CD l L 2.0. HIGH RADIATION m I LEVELS IN PLANT y[ a n.t l ' '* 0) ! AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ' to CD l L f n- - - - ,, .- - - -
. . . . . - . ~ - . . _ . . < . . . - - . . - -.-. ..-- - - . . -. _ _ . - . . . - . . ~ . . . . . . . _ - , , - - - - - . .
V v - 1I EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY g Q *!
- 3. FIRE Uncontrolled fire within the Uncontrolled fire Fire compromising the -y a i*
plant lasting more than function of safety systems NOTE U E
- o to minutes. 1. Potentia:ty affecting 0 e., bcth trains rendered RW b PMM h Matt 6^ 'i safety systems. Inoperabte). Event /Ctass 6.A. h AND *
- 2. Requiring off-site support in the opinion of the NPS/EC. ,
m F. il:: i! EXPLOSION Occurrence of en Damage to facility by
$ O l[
explosion within the Severe damage to safe O i explosion which affects shutdown equipment from Owner Controtted Area. plant operation. explosion. l[ g -
^ <>
n OG in 21 O ' c to --4 >
-4 l e >r-O> r- -
e mI C O o EE O
-- nm Ri O S o z ro ' m
> -4 m d^ 9 I o z m z d I O
d m D z r- -O m m
- 3. FIRE EXPLOSION I!
C. AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR G o to CD _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ .~, . . _ - - _ _ .
. _. _ - . . . - .- - .. . . - ~~ - . -- ~-- --
A- v EVENT / CLASS UNUSUAL EVENT i ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.A. FUEL Fuel element damage m Fuel efement failure ' ELEMENT Fuel element faRure with inadequate core cooling A release has occurred or is in 2 O FAILURE progress resultino in: 3 m O
- 1. Process monitors or 1. Process rnonitors or ;
area radiation surveys O z area radiation surveys 1. RCS DEO l.131 activity 1. Containment High Range
" O Indicate increased indicato increased greater than or equal to j
letdown activity Radianon monitor greater than-letdown activity and 275 pCVmL. AND confirmed RCS Samples 1.46 X 10' FWr (if CHRRM AND inoperable, Post-LOCA
- 2. Confirmed RCS sample indicating DEO l-131 2. Highest CET per core j
Indicating: monitors yeater than ( activity greater than or equal to 275 pCVmL quadrant indicates greater 1000 mR/hr). m j A. Coolant activity than 10*F superheat or g E [- 700*F. 2. Pei6e6 of EPIP-09 greater than the Oy l- Toch Spec limit for - (Off-site Dose Calculations) or g {- todine spike (Tech rneasured dose rates from m off-site surveys indicate site (n i Spec Figure 3.41.). Z (f) f S boundary (1 rnile) exposure O y
' NOTE 4yy B. Coolant activity if analysis is not available levels have been exceeded as ^g indicated by either A. B. C or to O y
greater than q y-pWgram within one hour and it is expected that RCS activity D bok y {>H - d , specific activity. for DEO I-131 is greater A 1000 mrem a cn g-o (a g E g O Z than 275 pCVmL, classify (t tal dose rate) as an ALERT. R Mm iii O B. 1000 mrom g 6Z T m NOTE o pH m it analysis is not available (total dose - TEDE)
- H .a h "g within one hour and it is C. 5000 mremMr 6 Z
-4 m
D expected that activity is (thyroid dose rate) 7
, greater than Tech Spec q G) limit, classify as y m ,
j tJNUSUAL EVENT. D. 5000 mrem ' (D Z (thyroid dose - CDE) r-g ! I m -m ! Ch L 4.A FUEL ELEMENT FAILURE
$f AFTER CLASSIFYlNG, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES Oi: THE EMERGENCY COORDINATOR s $[
O . k f fo 0) 4 c<w-+ . , ,w,.c - . m. r. . . . ~ . - - + - -_ - . _ _ _ _ .
. _ ._ . .~. ._ . . . _ _ . . . _ _ _ . . . . .. . . . . .. . _ . . .
g, w ~
$ s!
EVENT / CLASS UNUSUAL EVENT ALERT o SITE AREA EMERGENCY GENERAL EMERGENCY g Q jl 4.8. FUEL HANDLING -Fuel handling accident which Major damage to irradiated ACCIDENT results in the release of fust in Contaltvent or Fuet m O
. i; radioactivity to Containment or 3 y
^
Hand!!no Building Fuel Hand!!nq Build!ng: '
- t. Step increase in the *
- 1. NPS/EC determines that an reading of radiation irradiated fuel assembly rnay monitors in the plant ..
have been damaged. vent andlbr in the Fuel AND l5 Handling Buliding. j!
- 2. Associated area or process AND ti radiation rnonitors are in alarm.
- 2. Damage to more than one irradiated fuel g O il
{(O?!Ii 1 assembly. m
- (f)
OR Z Uncovering of one or O 5 4yq more irradiated fuel 3 OM *4 g 6 assernblies in the Spent . CD Fuel Pool.
$ >I M 0 r-H i i
" U) : C O 5G E O 2 SL ri m f5 O m
m OZ m i S -i r- m
>1 ' >
E: , O Z m - z -i 33 .
-4 O I i
> m '
@ Z r- O m m '
(D l I 4 8. FUEL HANDLING [ ACCIDENT q) k{ AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR E m CD
.- . , - - . . . _ . . - .~ . - _ . = . . - . .~ . . _ . , . _ - . . . .. .
v v A t EVENT / CLASS UNUSUAL. EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m b m i[ 5A EARTHOUAKE A confirmed earthquake A confirmed earthquake occurs wh8c*) A confimmd earthquake occurs which I has occurred registers GREATER THAN O 05 g. registers GREATER THAN 0.1g with NOTE y hm o, m
- 1. A confirmed plant net at cold shutdown Refer to Potential Core Met Event /Ctass 6.A.
g 9, O earthquake has beert expertenced within the Owner Control!ed . Area. I
- 2. An eart ke is detected by plant seismic monitor m I instruments. g O r g) m h
U) r
-l 5.B. HURRICANE Hurricane Waming Z U) I.
Hurrtcane waming with winds near Hurricane waming with winds design basis OREATER THAN design basis NOTE ^ > Refer to Potential Core [g U) O Met Event / Class 6A to g- y .d q O >O F- ~
- 1. Corrtmed hurricane 1. Confirmed hurricane waming is in 1. Plant not at cold shutdown. O
@zg cO waming is in eff ect. effect and winds are expected to
-A (f)
@ M 2-exceed 175 rnph within the Owner Controtted Area.
- 2. Confirmed hunicane warr4ng is in effect and winds are expected to O
n yg m y Q exceed 194 mph within the Owner g ]Z yH
*T)
Controlled Area. O f- m
-44 > g
' NOTE At FPL's request, NOAA will provide NOTE b At FPl's request, NOAA will provide Z an accurate projection of wind speeds an accurate projection of wind onsite 24 hours prior to the onset of 4 m speeds onsRe 24 hours prior to the D Z hurricane force winds. If that onset of hurricano force winds. If m '
projection is not ava3able within that projection is not available within O 12 hours of entering into the waming, 12 hours of entering into the warning, j g classify the event using current track g) classify the event using current track L and wind speeds to project ensite art? wind speeds to project ensite conditions. For example, projected conditions. For example, projected or: site wind speed would be less than onsite wir'd speed would be less than maximum hurricane wind speed if the maximum hurricar:e wind speed if *he track is away from PSL track is away from PSL 5.A. EARTHOUAKE b; 5.0. HURRICANE M I' : O O AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR f m
_ _ _ _ _ _ _ . . ._m _ _ _ . _. .. _ __ _ . . . . _ _ _ _ _ _ _ _ _ . _ . _ . . ._m . . _ . -_ .m. . . .
?
EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY O GENERAL EMERGENCY 5.C. TORNADO m Q . Notification of a tornado Any tomado striking facility. sighted in the Owner NOTE i m O Contro!!]d Area Refer to Potential Core ; Melt Event /Ctass 6.A. 3 h
~
A E m o 2 5.D. ADNORMAL Abnorrnal water level ' Flood, low water hurricane surge or Flood, low water, hurricane surae er O E WATER LEVEL conditions are expected ITI U) 4 other abnormal water tevel other abnormal water teven Z U) '! or occurrino conditions constions causwa failure of vitat O y equtoment _ V g 3' g
- 1. Low intake canal 1. The storm drain capacityis G O H >
level of -10.5 ft. MLW for 1 hour or exceeded during hurricane surge or known flood corditions,
- 1. Flood / surge water level reaching $ hg y d more. OR elevation +19.5 ft (turbine " mI c- O ,
OR buildng/ RAD ground floor). (4 gg Z
- 2. Visual sightings by
- 2. Low intake canal level of -10.5 ft.
MLW for 1 hour or rnore with OR
- 2. Low intake canal level has O mm m-g O station personnel emergency barrier valves open. caused the loss of all ICW flow.
g O 6Z yd "T1 that water levels are p m approaching storm
' > K
'C.a sy: tem 6 Z S
Ill capacity. Z _{
> Z W O m III m
5.C. TORNADO 5.0. ABNORMAL WATER LEVEL
!s) . -0; a
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SL m CD -
V v 1 ( i Y . NOTE o $ Activation of the Emergency Response Facilities does not r3 quire decfarahon of an emergency or entry into a Wfic emergency cfassification. m Q ! T
~
O j SITE AREA 7 2 O . EVENT / CLASS rn UNUSUAL EVENT ALERT EMERGENCY 3 GENERAL EMERGENCY Emergency Coordinator's Emergency Coordinator's Emergency Coordinator's judgement thaf . todqement that plant judgement that plant plant conddions exist that make release or cond;tions exist which conditions exist wt9ch large amounts of radioactivity in a short warrant: warrant: ; period appear possibfe or hkely. (Any core { met situation.)
- 1. Increased awareness 1. Activation of m j and activation of emergency response g t, -
- 1. LOCA with lailure of ECCS leading to m Emergency Response personnet facilibes and severe core degradation or melt. 3}
g$r Emernency Coordinstor's tudgement that plant monitoring teams or a precautionary M
- 2. LOCA with inillally successful ECCS aiut G) m h3 CD r notification to the subsequent failure of containment heat 2 (O P conditions exist which public rear the site, warrant increased awareness on the part of removat systems for several hours.
M m y g 3 g the opeinting statt and/or 3. Totalloss of feedwater fonowed by failure ID O *g local authorttles. of once-through-cooung (ECCS) to
$ FM --(
adequately cool the core. E
, h
- 1. The plant is shutdown
- 4. Faiture of oft-sita and on-site power along A mg o Z l under abnormal with totalloss of emergency feedwater .
o
- Mm @ O conditions (e.g.,
maket, capabihty for several hours. fO g q j exceeding cooldown OR v O d m l rates or primary system pipe cracks are 5. ATWS occurs which results in core qa
- {
i damage or causes failure of core cooling 7 found during and makeg systems. q g operation). g ] M M M m
- 6. A. INCREASED 2. Any plant shutdown 6. Any major intamai or extemal event (e g., D Z AWARENESS required by Technical fire, earthquake of tornado substantially OR beyond design basis) which in the ECs O~
Spectilcations in which m m POTENTIAL the required shutdown opinion has or could cause massive - (j) CORE MELT is not reached within damage to plant systems resutting in any (Page 1 of 2) of the above. action Emits. (continued on next page) 6.A. INCREASED AWARENESS GR 1 POTENTIAL .f CORE MELT g g to O 4 AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR to 0)
.. .. . _. . ~ - _ . . . - -. . . . . ~ . . ..- -. . -
V v as EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY *; m Q 6.A. INCREASED y o a: AWARENESS NOTES
- 1. Most likely containment failure 5 g O ;;
OR POTENTIAL CORE MELT mode is molt-through with 6 A 2 O (Page 2 of 2) release of gases only. Ouicker ; releases are expected for failure of containment isolation system. j
- 2. General Emergency mst be ; i.
declared for the atxwe listed m jt events. The likelihood of g j;; corrective action (repair of ARV m g ':! pump, etc.) should not be E ,i consklered. :
] ,l Z co !:
'O kbd (f) b O
W Om > 0 f- > t O >O r-
--{
O
^
(n r C O 2 0 ME O
'I! m in O ro OZ o T C >d r- m d" > E O Z m Z d I d O !
> m 1
CD Z r- O m ' m ' (/) ; l l 6.A. INCREASED i r AWARENESS OR POTENTIAL CORE MELT }!
@[
ca AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR o, to 00
s-
.V ~
EVENT / CLASS UNUSUAL EVENT ! ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 7.A. LOSS OF Loss of oft-site power or m h 5 Station Blackout (Totat Loss Station Blackout (Totalloss g O 5i POWER loss of e!! on. site AC power NOTE ' capabintv. of AC) of AC) for GREATER THAN Refer to Potential Core E o !! 1S minutes
- 1. Loss of off-site Mett Event /Ctass 6A 9 $
- 1. Loss of off-site AC AC power. 1. Loss of offsite AC power.
- power. AND AND OR 2. Failure of both 2. Sustained failure of both
- 2. Loss of capability to emergency diesel :
power at least one vital generators to str.rt cr emergency dieset generators to start or N
); ;
k 4.16 kw bus from any available emergency synchronize. synchronize. E {[ (; AND diesel generator.
- 3. Failure to restore O ni Loss of a!! on-site DC AC power to et least one g : <
power vital 4.16 kv bus within m { E^ y) Z U) I' ' 15 minutes. O
- 1. Drop in A and B DC bus 4y 5 voltagt.s to loss than 3ID O1 q g) ~O 5
70 VDC. *y >
- Loss of att vital on-site DC for creater than 15 minutes
$ IM H a
E O O 2
- 1. Sustained drop in A and U) M O l B DC bus voltages to Mm
~
m O 70 VOC for greater than g2 T Tl i o yH m 15 minutes. da h g O Z m Z H I 4 C)
> m '
W Z i r- O m m + U) l. l A 7A LOSS OF O! ! POWER N f" l i A . ! 9 i AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR M i e { E_______-_____-.__--- ._- _ _ _ _ . _ . _ . _ __
. .-_ .- ~- - - - -
l l v v l { EVENTICLASS UNUSUAL EVENT s $: ALERT SITE AREA EMERGENCY O *' GENERAL EMERGENCY y( g Q
- 8. A. LOSS OF PLANT Loss of Plant Control Criticalloss of Plant Control CONTROL Functions FUNCTIONS Functions NOTE T g O
{i Refer to Potential Core O 2 *'
- 1. Complete loss of any 1. Loss of any function or ,
Met EventClass 6.A. " 9 function needed for plant system which, in the cold shutdown. opinion of the Emergency M Coordinator, precludes
- 2. Failure of the Reactor - placing the plant in Hot };
Protection System to Sheldown. bring the reactor g m y subcritical whern needed. g C
- 2. Falture of the RPS to trip OR
~ the reactor when needed m
'D g E, 2'
- 3. Control Room is and operator actions tan to O $l evacuated (for other than bring the reactor m driS purposes) with control CD i subcritical 2 M_ { "
established locally at the Hot Shutdown Control
@ O) 3
- 3. Control Room is evacuated T Panet. (for other than drill W O m O q 3>
purposes) and control cannot be established
$ d j
Loss of Shutdown Cooling locally at the Hot Shutdown a N mz gc mg O Z i Control Panel within o~
- 1. Complete loss of 15 minutes.
o
- ri m m O functions needed to 7 m ,
maintain cold shutdown. v
$ qa y "U g
y A. Fa!!ure of shutdown o Z
-{
m y cooling systems, 7 resulting in loss of g
*"I m cold shutdown conditions. Z ela O ,
D. RCS sutacooling can m m , i NOT be maintained CD i greater than O*F. 8.A. LOSS OF PLANT CONTROL i \ FUNCTIONS g, 9 ny i Un AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR o - m CD
i V v EVENT / CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 8.B. LOSS OF ALARMS / Significant loss of effluent g Q { ! loss of atanns Loss of alarms t} O $ COMMUNICATtON / monitoring capabil!!y, -- MONITORING communications, ind6 cation , Q m O 5(
- 1. Unplanned loss of all, 1. Inability to monitor a
' and alarm panets, etc, which impairs abl!ity to perform safety system s!gni5 cant transient in 3 $ annunciators. progress.
- accident or emergency AND assessment. 2. Plant transient in '
progress. 3'
- 1. Loss of effluent or [n radiological monitoring
. M capability requiring plant E h shutdown. 3 O n QR g h-
- 2. Loss of a t primary and m (D i" backup communica5 Z (D i
capability with offsite O
^ Sy ~Tl locations. t)
Om q g 6
- 3. UnplannaEss of most OR U CD IM 'y >
H or all Safety System h { 2 annunciators for greater CD (f) g g than 15 minutes. o 5m m - O o g 32
>d r-m
- m
-4 " > E 5 ZH m JD Z
O
> m W Z O
m III en 8.B. LOSS OF ALARMS / COMMUNICATION / MONITORING A O fo I" c)- AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR o fo 0) m m____m. _ . _ ____ . _ _m. _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ m ___ - , W
-... ._m ._.__..__m. m __ . _ _ . . . . . _ . _ . _ . _ _ . . . _ _ ._._._m __. _ . . . . . _ . . .
G - EVENT / CLASS UNUSUAL EVENT b i;
, ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m
Unusual aircraft activity Aircraft / missile impact Damage to vita! systems g O !" from aircraft /missHes Q
- 1. Aircraft crash in the 1. Aircraft crash in the
. m O'it.
Owner Controffed Area C, Owner Contro!!sd Area 1. Aircraft crash in the or unusual aircraft damaging plant Owner Controtted Area
- actuity over facility that structures. damaging vital plant in the opinion of the systems. ,
OF1 NPS/EC could 2. Visual or audible OR :l ( threaten the safety of indication of rnissile 2. Damage Eafe M 9.A. AIRCRAFT / the plant or personnel. Impact on punt shutdown equipment MISSILE structures. from any rnissile. k 3 O /[ i o m 9 it cn r ; 9.B. TURBINE Turbine rotating Z Co " i Visual indication that the O y ) FAILURE component failure causino turbine casing has been ]"T1 rapid plant shutdown. penetrated by blading. T O (g () g
= >n e -
S (n r C O Z
@g O R 3m f5 O ro O
oZ-i m 'l
- r m 9.C. TOXIC OR Unplanned /uncontro!!ad Entry of toxic or f!ammable Toxic or flammable oas has >4
- ^
> g Ft.AMMARL E GAS
'; toxic or flammable cas release in the Owner gas into areas potentially affectino plant operation.
diffused into vitat areas 3 g z H y y affecting access to or the ' controned Area that could operation of safe shutdown d G) affect plant /personnet equipment. m safety. Z r- _ 9.A. A!RCRAFT / m m MISSILE 9.0. TUR8INE FAILURE 9.C. TOXtC OR FLAMMADLE A GAS g
-q hI AFTER CLASSIFYlNG, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR R to 03
b v s L w'+ $ EVENT / CLASS UNUSUAL EVENT . ALERT SITE AREA EMERGENCY GENERAL EMERGENCY o g Q
- 10. SECURITY A SECURITY ALERT has A SECURITY tj o
- A SECURITY EMERGENCY A successful takeover of the ---
THREAT , beert called by the Security EMERGENCY has been involving Irnrninent Q O plant including the Control m Force in response to one g called by the Security occupancy of the control Room or any other area (s) i or rnare of the items listed Force as defined in the room or other ares (s) wital vital to the operation of the below. Safeauards Continaency to the operation of the ,* reactor (as per the Security ~ Plan. reactor as defined in the Plan).
- 1. Bomb threat Safeauards Continaency
- 2. Attack threat Plan. .,
8'
- 3. Civil disturbance M !!
- 4. Protected area . E MMM !
S. Sabotage attempt y O
- 6. Intemaldisturbance
- 7. Vital area intrusion g
m { il m ;i l
- 8. Security force strike Z (n fi O -
T 4) O
-n ,
m OG O t- > 4 in y
* >O r- -i
- +
ro t c O o (n 92 g o Z 9 2] m Ri O to O Z " o >d (m -- m d" P Z O m z -1 3) d Q D m W 7 r- d m m in
- 10. SECURITY THREAT t gj to W AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
- o to G
USNRC SENIOR REACTOR OPERATOR EXAMINATION ANSWER KEY
- 1. B
- 2. A 4 3. D
- 4. C
- 5. D
- 6. D
- 7. B
- 8. C
- 9. C 10.D 11.B
- 12. B 13.C 14.C 15.A 16.D 17.D 18.D 19.D 20.B
- 21. C 101
USNRC REACTOR OPERATOR EXAMINATION
- 22. D ANSWER KEY 23.A
' 24.C 25.C 26.A 27.A 28.C 29.B 30.D 31.A 32.C 33.B
- 34. B 35.D 36.D 37.B 38.C 39.D 40.C 41.A j
42.A 43.B 1 l l 4 102
USNRC SENIOR. REACTOR OPERATOR EXAMINATION ANSWER KEY 44.C 45.D 46.C 47.D
- 48. B 49.D
- 50. D
- 51. C 52.D 53.C
- 54. D 55.C 56.C 57.A 58.D 59.D 60.C 61.D 62.C 63.D 64.D 103-
O
- e .. -* -
USNRC SENIOR REACTOR OPERATOR EXAMINATION ANSWER KEY 65.B 66.C 67.D 68.B 69.B 70.C
- 71. B l 72.A
- 73. B 74.A 75.C 76.A
- 77. B 78.C
- 79. B ;
80.D 81.B 82.C 83.A
- 84. B 85.A .
86.D 104
'tC SENIOR REACTOR OPERATOR EXAMINATION ANSWER KEY 87.13 l
l 88.A t 89.D r 90.C I
,91. B 92.D 93.B 94.C 95.B 96.C 97.D 98.C 99.C 100.B I
l l 105
1 S 2 OPS l E^'C1enOCeouse O R@DA NW8 & UMT DOCN 2-0110030 SYS COMP COMPLETED ST. LUCIE PLANT ITM 38 Pi. , UNIT NO. 2- , raww_
/ T Q juy: = .m
, verityinformatorHvith a blod dc cumert ,
2-0110030 PROCEDURE PPODUCTION REVISION
~
38 I r-- m r m% r, r3 -r- in
' F f
(n e
,Q a =
g. n n- _m Sr
\' f
- Jf ~ lI
/
U U li U \ U L_L-CEA OFF-NORMAL OPERATION AND REALIGNMENT OFF-NORMAL OPERATING PROCEDURE REVISION REVIEWED BY APPROVED BY DATE FRG ON 0 3/10/83 C. M. Wethy 3/10/83 Plant General Manager 38 10/23/97 J. Scarola 10/23/97 Plant General Manager P" OPERATIONS Departm t TJB 10/27/97 DISTRIBUTION CODE A070
- - - . .- . . . - - .-. .. .. . _ - - - . - - . . ~ ~ .
REV!SloN No.: PRCOEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE No.: AND REALIGNMENT 2 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2
1.0 TITLE
CEA OFF-NORMAL OPERATION AND REALIGNMENT
2.0 PURPOSE
l 4 This procedure provides instructions for operator action during abnormal
- operation ara realignment of Control Element Assemblies (CEA) while in
- Modes 1,2 or 3 and failure of CEA position indication.
1 3.0 REFERENCE _S_ - NOTE One or more of the following symbols may be used in this procedure: , ! 1. s Indicates a Regulatory commitment made by technical
- specifications, condition of license, audit, LER, bulletin, etc. and should NOT be revised without Facility Review Group approval.
- 2. Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be
- revised without consultation with the plant staff.
j 3. 9' Indicates a step that requires a sign off on a data sheet. ' l @i 3.1 St. Lucie Unit 2 Technical Specifications. , 3.2 St. Lucie Plant Unit 2 UFSAR, Accident Analysis, Section 15.2.3. 3.3 St. Lucie Plant Unit 2 UFSAR, Section 7.7.1.2.1. 3.4 OP 2-0030125, " Turbine Shutdown - Full Load to Zero Load." 3.5 2 OSP-10.0.14, " Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical)." 3.6 OP 2-0020123, " Reactor Operating Guidelines During Steady State and Scheduled Load Changes " 3.7 ONOP 2-0250030, " Emergency Boration." l l ____________________1
REi!!SloN NO.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEcuRE No.: AND REALIGNMENT 3 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2
3.0 REFERENCES
- (continued) 3.8 FOP-89-054, Multiple Slipped / Dropped CEAs.
3.9 In House Event Report 89-077. j @2 3.10 FRN-89-536, PSL-2 Double CEA Misalignment Evaluation. i @3 3.11 License Event Report 97-009-0, Recovery of Dropped CEA in Excess of Technical Specification Action Statement Time Requirements. , 4.0 RECORDS REQUIRED: 4.1 Normal log entries. 5.0 ENTRY CONDITIONS: Conditions indicate that one or more CEAS are misaligned or dropped. Any one or more of the following conditions may exist: i 5.1 CEA position Deviation Motion Block (ADS) alarm (K-30). 5.2 CEA position Deviation Waming (DDPS) alarm (K-22). 5.3 CEA position Deviation Limit (DDPS) alarm (K-38). 5.4 CEA motion inhibit alarm (K-11). I 5.5 Dropped CEA (CEDMCS) alarm (K-35). ! 5.6 Automatic CEA withdrawal prohibit alarm (K-18). - 5.7 CEA PDIL (K-21) and PPDIL (K-20) (DDPS) alarms. ! 5.8 CEA PDi(. (K-29) and PPDIL (K-28) (ADS) alarms. 5.9 Group out-of-sequence (ADS) alarm (K-27)l
- 5.10 Group out-of-sequence (DDPS) alarm (K19).
5.11 Reg. CEA short term steady state insertion alarm (L-24). 5.12 Continuous gripper voltage hi alarm (K-36). i i
_ . _ . _ _ . . . _ _ _ - . _. . . . _ . . _ _ . . _ _ . . - _ . . . _ . _ . . ~ . . I REVISION NO.: PROCEDURE TITLE: PAGE: 38 CEA~ OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 4 of 29 - ; OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 6.0 EXIT CONDITIONS: 6.1 CEAs are realigned to within the limiting condition for operation (LCO). OR 6.2 Conditions warrant a unit shutdown and an approved procedure exists to implement. 4 4 e i e 5 I i l 1 ! l l I s
- l f.
l i . . l l.
REVISloh3 No.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO,: AND REALIGNMENT 5 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS: 7.1 Immediate Operator Actions: INSTRUCTIONS CONTINGENCY ACTIONS
- 1. Place CEDMCS panel in CFF.
- 2. H continuous CEA withdrawal is indicated, while CEDMCS panel is OFF, Then trip the 2 reactor and turbine and carry
- out 2-EOP-01, " Standard Post Trip Actions."
- 3. H a mismatch between reactor
] power and turbine power (T-avg and T-ref) exists, Then l adjust turbine power to equal reactor power.
- 4. H 3 or more CEAs are misaligned from any other CEA in their group by greater than 15 inches and/or dropped, Then manudly trip the reactor and turbine and carry out 2-EOP-01, " Standard Post Trip Actions."
]
. REVISION No.: PROCEDURE TITLE: PAGE: , 38 CEA OFF-NORMAL OPERATION PROCEDURE NO,: AND REALIGNMENT 6 of 29 -
OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS: (continued) 7.2 Subsequent Operator Actions: 1 INSTRUCTIONS CONTINGENCY ACTIONS ,
- 1. If continuous CEA insertion is indicated, while the CEDMCS panel is OFF, Then locally open the disconnect for the affected CEA(s) at the CEDM coil power supply panels in the cable spreading room.
- 2. Notify Reactor Engineering, Operations Supervisor and Operations Manager of time of CEA misalignment. (NOT required if in Mode 3.) (If unable to reach the Operations Manager, notify the Plant ,
General Manager or any of his direct reports.) O b
REVislON No.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION l PROCEDURE No.: AND REALIGNMENT 7 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS: (continued) 7.2 (continued) 1 INSTRUCTIONS CONTINGENCY ACTIONS
- 3. Refer to the appropriate
, appendix listed below and apply the instructions as required. NOTE More than one appendix may be required. CEA MALFUNCTION APPENDIX ! CEA investigation for operability A One or more CEAs inoperable B One or more CEAs misaligned greater than 7 inches but C less than or equal to 15 inches. One CEA misaligned greater than 15 inches. D Two CEAs dropped or misaligned greater than 15 inches. E One dropped CEA F CEA position indication malfunction G CEA realignment (Modes 1,2 and 3) , H Realignment of one dropped CEA (Mode 1) 1 Hi gripper voltage alarm J
- 4. [f conditions require a unit shutdown (per Tech Spec),
Then implement the E-Plan as required,
l l REVISloN No.: PROCEDURE TITLE: PAGE: i l 38 CEA OFF-NORMAL OPERATION PROCEDURE No.: AND REALIGNMENT 8 of 29 OFF-NORMAL OPERATING PROCEDURE I 2-0110030 ST. LUCIE UNIT 2 l < APPENDIX A CEA INVESTIGATION FOR OPERABILITY (Page 1 of 3) CAUTION Reactor power shall npot be increased above the power level present a' the time of the CEA(s) misalignment. l
..w l
- 1. For the affected CEA(s), perform the following to determine opes.oility:
CAUTION I Criticality shall be anticipated any time CEAs are being withdrawn. A. Place the mode select switch in the manual individual mode. 1 B. Select the affected CEA on the individual CEA selection switches. 1 C. Select the group of the affected CEA on the group select switch. D. if CEA motion inhibit is present, Then:
- 1. Depress and hold the CEA motion inhibit bypass pushbutton.
- 2. Depress then release the bypass enable pushbutton.
E. If the CEA was dropped, Then first withdraw the affected CEA until core mimia CEA bottom light and lower electrical limit lights both deenergizo. CAUTION Do NOT exceed 10 inches of the original position without permission from the ANPS. . F. Insert and withdraw the affected CEA and check for smooth operation and normal indications. G. If CEA is determined to be operable proceed to the applicable appendix for CEA realignment.
. -.. ~ .-. .- . . ... . . _ . . - ~. -
l , REVISloM NO.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 9 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX A l i CEA INVESTIGATION FOR OPERABILITY . (Page 2 of 3) i l j
~
NOTE : Tripped CEA disconnect and/or loss of CEA subgroup logic function will - l 2 cause dropped CEAs. l
- 2. H the CEA(s) does NOT operate, Then check the status of the CEDM coil power supply panels in the cable spreading room:
A. Symptoms:
- 1. CEA disconnect in OFF; red light off, green light on.
- 2. CEA disable lights are red for the affected CEA.
- 3. Timer failure lights are red for the affected CEA.
B. Trouble Shooting:
- 1. H CEA disconnect is off, Then:
- a. Tum ON disconnect switch.
- b. Reset ACTM card toggle switch. (located inside cabinet, top switch, UG ENGD light should remain on).
- 2. If CEA disconnect is not off, Then:
- a. Reset ACTM card toggle switch.
C. Check the air conditioning system for proper operation. D. Checi< the coolin'g fans for proper operation. E. Contact the l&C Dept. for assistance and notify them of the problem and any abnormalities found.
- 1. Check the CEDMCS and CEA drive system for alarms that might indicate the CEA problem.
~
, REVISION No.: PROCEDURE TITLE: PAGE:
38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 10 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX A CEA INVESTIGATION FOR OPERABILITY (Page 3 of 3)
- 2. (continued)
E. (coltinued) CAUTION Do NOT ex:eed 10 inches of original position without pemlission from the ANPS.
- 2. Withdraw and insert the CEA(s) in manual individual or manual group at the direction of I&C to support troubleshooting.
F. Have I & C perform the following as necessary.
- 1. Check associated power supplies and fuses.
- 2. Obtain coil current traces and voltage measurements to determine the location of trouble.
G. Proceed to the applicable Appendix for CEA realignment or to Appendix B if CEA is determined to be inoperable. e t 1 l END OF APPENDIX A I e
, REVISloN NO.: l PROCEDURE TrrLE: PAGE:
38 CEA OFF-NORMAL OPERATION PROCEDURE No.: AND REALIGNMENT 11 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 __ APPENDIX B ONE OR MORE CEA(S) INOPERABLE (Page 1 of 2)
- 1. Ensure the fol!owing:
A. CEDMCS panel in OFF. B. Turbine power adjusted to equal reactor power.
- 2. Ensure Appendix A CEA investigation for Operability has been performed.
CAUTION , Emergency boration may be required if one CEA is NOT fully inserted, and known to be untrippable or immovable due to mechanical interference or excessive friction.
/R38
&, 3. With one CEA NOT fully inserted, and known to be untrippable or immovable due to excessive friction or mechanical interference, immediately ensure adequate shutdown margin as per 2-OSP-100.14,
" Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical)" and be in Hot Standby within six hours, as per OP ;
2-0030125, " Turbine Shutdown - Full Load to Zero Load." /R38
@, 4. With more than one CEA known to be untrippable or immovable due to excessive friction or mechanical interference immediately commence emergency boration, as per ONOP 2-0250030, " Emergency Boration" and be in Hot Standby within six hours, as'per OP 2-0030125, " Turbine Shutdown-Full Load to Zero Load." Ensure adequate shutdown margin, as per 2-OSP-100.14, " Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical)." i @, 5. With one CEA inope'rable for reasons other than those stated in Step 3 above, but within 7 inches of all other CEAs in its group and (a) fully withdrawn or (b) within the long term steady state insertion limits if CEA is in group 5 or (c) inserted beyond the long term insertion limits as restricted by specification 3.1.3.6, operation in Modes 1 and 2 may continue. Ensure adequate shutdown margin within one hour and at least once per B hours per 2-OSP-100.14, " Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical)."
. REVISION NO : PRCOEDURE TITLE: PAGE:
38 CEA OFF-NORMAL OPERATION l PROCEDURE NO.: AND REALIGNMENT 12 of 29 i
'OFF-NORMAL OPERATING PROCEDURE 1 2-0110030 ST. LUCIE UNIT 2 APPENDlX B ONE OR MORE CEA(S) INOPERABLE (Page 2 of 2)
Si 6. With more than one CEA inoperable for reasons other than those stated in Step 4 above, be in Hot Standby within six hours, as per
" Turbine Shutdown-Full Load to Zero Load", OP 2-0030125. Ensure adequate shutdown margin within one hour, as per 2-OSP-100,14, ;
" Surveillance Requirements for Shutdown Margin, Modes 1 and 2 I (Critical)."
- 7. Refer to applicable CEA position deviation appendix as condition warrants.
I l
\
I l i END OF APPENDIX B l
REVISloM No.: PROCEDURE TrrLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 13 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX C ONE OR MORE CEA(S) MISALIGNED FROM ANY OTHER CEA IN ITS GROUP BY GREATER THAN 7 INCHES BUT LESS THAN OR EQUAL TO 15 lNCHES (Page 1 of 2)
- 1. Ensure the following:
A. CEDMCS panelin OFF. B. Turbine power adjusted to equal reactor power. C. CEA motion inhibit.
- 2. Determine from symptoms and CEA position indications, the operability of the CEA in accordance with Appendix A. During determination of the
- cause of the misaligned CEA, maintain reactor power constant.
- 3. If CEA(s) determined to be inoperable for any reason, refer to Appendix B and continue with the steps of this appendix as applicable.
NOTE I If this procedure is employed while in Mode 3, the one hour time restriction does NOT apply.
@, 4. .lf CEA(s) are operable, Then realign the CEA(s) within one hour in accordance with Appendix H.
, @i 5. If CEA inoperable: A. Realign the remainder of operable CEAs in the group within 7 inches of inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown in Fig.1 (Tech Spec. Fig,3.1-2). The thermal power level shall be restricted pursuant to cpecification 3.1'.3.6 during subsequent operation.
@, 6. If unable to perform Step 4 or Step 5 then be in at least Hot Standby within six hours.
6
, REVISION No.: 2RoCEDURE TTTLE: PAGE:
38 CEA OFF-NORMAL OPERATION i PROCEDURE NO.: AND REALIGNMENT 14 of 29 l OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX C ONE OR MORE CEA(S) MISALIGNED FROM ANY OTHER CE A IN ITS GROUP BY GREATER THAN 7 INCHES BUT LESS THAN OR EQUAL TO 151NCHES , (Page 2 of 2)
'7. E a CEA becomes misaligned greater than 15 inches, but does NOT drop while performing the above section, Then proceed to Appendix D.
H the CEA drops while performing the above section, Then proceed to Appendix F.
- 8. Upon ascertaining that plant conditions are normal, continue with the reactor startup or retum to the desired operating power level in accordance with OP 2-0030123, " Reactor Operating Guidelines During Steady State and Scheduled Load Change." The guidelines for ASI oscillation control should be implemented appropriately.
i 4 l END OF APPENDIX C
, REVISION NO.: PROCEDURE TrrLE: PAGE. l 38 CEA OFF-NORMAL OPERATION I PROCEDURE NO : AND REALIGNMENT 15 of 29 i OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX D ONE CEA MISALIGNED BY GREATER THAN 15 INCHES BUT NOT A DROPPED CEA
- (Page 1 of 3)
- 1. Ensure the following. i 1
A. CEDMCS panel in OFF.
- B. Turbine power adjusted to equal reactor power.
C. CEA motion inhibit. NOTE If in the previous 8 hours a dropped or slipped CEA hcs been successfully retrieved, upper plant management will make the decision to retrieve the CEA and continue operation.
- 2. Maintain reactor power constant.
- 3. Determine from symptoms and CEA position indications, the operability of the CEA in accordance with Appendix A. During determination of the cause of the misaligned CEA, maintain reactor power constant.
- 4. If CEA determined to be inoperable for any reason, refer to Appendix B.
NOTE jf difficulty is experienced in CEA realignment, Then a power reduction to , less than or equal to 70% rated thermal power,should be initiated.
- 5. If in Mode 3, realign the CEA in accordance with Appendix H and proceed to Step 7.
@, 6. If in Modes 1 and 2,'Then refer to plant curve book and obtain the most recent Fl value. This value, when interpreted on the technical specification Fig. 3.1-1a, will indicate the amount of time to restore the CEA within 7 inches of all other CEAs in its group.
__._________..________________._______s
. REVISloN No.: PROCEDURE TrrLE: PAGE:
38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 16 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX D ONE CEA MISALIGNED BY GREATER THAN 15 INCHES BUT NOT A DROPPED CEA (Page 2 cf 3)
- 6. (continued)
A. Within the time allowed by technical specification Fig. 3.1-1a, restore the CEA (per Appendix H) to within 7 inches of all other CEAs in its group. 53 NOTE Technical Specification Bases, B 3/4.1.3, requires a prompt realignment of the misaligned CEA. Therefore, it is expected that the remainder of this step is completed within 1 hour following expiration of the time allowed by Technical Specification Figure 3.1-1a in order to be in full compliance with Specification 3.1.3.1. B. I.f the CEA has not been realigned within the time allowed, Then reduce power to less than or equal to 70% of rated thermal power. CAUTION During the unit downpower, CEA realignment shall NOT be performed unless reactor power is stabilized.
&, C. When reactor power is less than or equal to 70% of rated thermal power, Then COMPLETE either of the below substeps.
- 1. Realign the CEA (per Appendix H) to within 7 inches of all the other CEAs in its group.
OR i l'
~
. REVISION No.: PROCEDURE TrrLE: PAGE:
. 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 17 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX D ONE CEA MISALIGNED BY GREATER THAN 15 INCHES BUT NOT A DROPPED CEA (Page 3 of 3)
- 6. (continued)
C. (continued)
- 2. Declare the CEA inoperable and PERFORM the following:
- a. CHECK pre-misalignment ASI.
- b. If pre-misalignment ASI was tr' ore negative than -0.15, Then reduce power to less than 70% of the Thermal Power level prior to the misalignment.
i c. ALIGN the remainder of the CEA's in the group to within 7 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 1 (Tech. Spec. Fig 3.1-2).
- d. MAINTAIN thermal power level restrictions in accordance 4 with Technical Specification 3.1.3.6 during subsequent operation.
- 7. Upon ascertaining that plant conditions are normal, continue with the
- reactor startup or retum to the desired operating power level in i accordance with OP 2-0030123, " Reactor Operating Guidelines During Steady State and Scheduled Load Change." The guidelines for ASI
oscillation control should be implemented appropriately. , l I
. 1 END OF APPENDIX D
, , REVISloN NO.: PROCEDURE T(TLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 18 of P9 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 1 APPENDIX E , I TWO CEA(S) DROPPED OR MISALIGNED BY GREATER THAN 151NCHES (Page 1 of 1) l NOTE ! If two CEAs are misaligned, with one misaligned greater than 15 inches ! and the otter misaligned greater than 7.0 inches, the actions of this appendix will apply. 1 1
- 1. Ensure the following: l A. CEDMCS panel in OFF.
l B. Tu tine power adjusted to equal reactor power. 1 C. CEA motion inhibit. NOTE ! If in the previous 8 hours a dropped or slipped CEA has been successfully l retrieved, upper plant management will make the decision to retrieve the - CEA and continue operation.
- 2. H in Modes 1 or 2, Then refer to the plant curve book and obtain the most recent Fl value.
@, A. H F;is LESS than 1.65 and 2 CEAs misaligned from any other
' CEA in its group by greater than 15 inches (indicated position),
Then immediately initiate a plant shutdown to Hot Standby, without - attempting to withdraw any misaligned CEA and be in Hot Standby within 1 hour. At the discretion of the ANPS/NPS, manually trip the reactor and implement 2-EOP-01, " Standard Post Trip Actions."
@2 B. H FI'is GREATE!R than 1.65 and 2 CE,As misaligned from any ,
other CEA in its group by greater than ~15 inches (indicated l position), Then manually trip the reactor and implement 2-EOP-01,
" Standard Post Trip Actions." j
- 3. H a reactor startup is in progress (Mode 3), Then, notify I&C and realign the CEAs in accordance with Appendix 1.
j END OF APPENDIX E
I REVISloN NO.: PROCEDURE TTTLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE No.:
- AND REALIGNMENT 19 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX F ONE DROPPED CEA (Page 1 of 3)
- 1. Ensure the following:
A. CEDMCS panel in OFF. B. Turbine power adjusted to equal reactor power. C. CEA motion inhibit. NOTE If in the previous 8 hours a dropped or slipped CEA has been successfully retrieved, upper plant management will make the decision to retrieve the CEA and continue operation.
- 2. Maintain reactor power constant.
- 3. Determine from symptoms and CEA position indications, the operability of the CEA in accordance with Appendix A. During determination of the cause of the misaligned CEA, maintain reactor power constant.
- 4. E the CEA determined to be inoperable for any reason, Then refer to Appendix B.
NOTE H difficulty is experienced in CEA realignment, Then a power reduction to less than or equal to 70% rated thermal power,should be initiated. i
- 5. H in Mode 3, recover the dropped CEA in accordance with Appendix l Then proceed to Step 8.
4 s, 6. H in Modes 1 and 2,' refer to plant curve book and obtain the most recent Fl value. This value, when interpreted on the technical specification Fig. 3.1-1a, will indicate the amount of time to restore the CEA within 7 inches of all other CEAs in its group, i o i
i
, REVISION No.: PROCEDURE TITLE: PAGE: i 38 CEA OFF-NORMAL OPERATION l PROCEDURE NO.: AND REALIGNMENT 20 of 29 l OFF-NORMAL OPERATING PROCEDURE i 2-0110030 ST. LUCIE UNIT 2 j APPENDIX F ONE DROPPED CEA I (Page 2 of 3) j l
G. (continued) i I A. Within the time allowed by technical specification Fig. 3.1-1a, l realign the CEA (per Appendix I) to within 7 inches of all other l CEAs in its group, l 03 NOTE Technical Specification Bases, B 3/4.1.3, requires a prompt realignment of the misaligned CEA. Therefore, it is expected that the remainder of this step is completed within 1 hour following expiration of the time allowed by Technical Specification Figure 3.1-1a in order to be in full compliance with i Specification 3.1.3.1. B. If the CEA has not been realigned within the time allowed, Then reduce power to less than or equal to 70% of rated thermal power. CAUTION During the unit downpower, CEA realignrnent shall NOT be performed un'ess reactor power is stabilized. 1
@, C. When reactor power is less than or equal to 70% of rated thermal l power, Then COMPLETE either of the below substeps. i
- 1. Realign the CEA (per Appendix 1) to within 7 inches of all the other CEAs in its group.
OR 4 i I l l
- j l
REVISION NO.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION
) PROCEDURE NO.: AND REALIGNMENT 21 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDlX F ONE DROPPED CEA (Page 3 of 3)
- 6. (continued)
C. (continued)
- 2. Declare the CEA inoperable and PERFORM the following:
- a. CHECK pre-misalignment ASI.
- b. .lf pre-misalignment ASI was more negative than -0.15, Then reduce power to less than 70% of the Thermal Power level prior to the misalignment.
- c. ALIGN the remainder of the CEA's in the group to within 7 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 1 (Tech. Spec. Fig 3.1-2).
- d. MAINTAIN thermal powe level restrictions in accordance with Technical Specification 3.1.3.6 during subsequent operation.
- 7. Upon ascertaining that plant conditions are normal, continue with the reactor startup or retum to the desired operating power level in accordance with OP 2-0030123, " Reactor Operating Guidelines During Steady State and Scheduled Load Change." The guidelines for ASI i oscillation control should be implemented appropriately.
4 I l 4 END OF APPENDIX F i I l l
~ -- _- - . . .. . -. -- , .. . REVISloN No.: PROCEDURE TITLE: PAGE: . 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 22 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 i
APPENDIX G , CEA POSITION INDICATION MALFUNCTION (Page 1 of 1)
- 1. Verify CEA position utilizing all other means available, including CEDMCS, DDPS, UEL and/or LEL lights and CEA bottom light.
- 2. Notify l&C and Reactor Engineering departmen+s.
- 3. If pract cal, position CEA at its upper or lower electrical limit to provide independent position indication.
- 4. Independent verification of CEA position can be determined using the incore detectors in the CEAs vicinity. This method will only provide gross indication of insertion.
@i 5. Verify compliance with technical specifications.
O END OF APPENDIX G
REVISION Noa PROCEDURE TrrLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE No.: AND REALIGNMENT 23 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDlX H CEA REALIGNMENT (MODES 1,2 AND 3) (Page 1 o.f 2)
- 1. While realigning CEAs, observe the following:
A. Regulating CEAs shall be withdrawn in sequence and overlap between groups shall NOT exceed 54 inches. B. Do NOT exceed a sustained SUR of 1.4 DPM (alarm 1.3 DPM). C. Criticality shall be anticipated any time CEAs are being withdrawn. D. If deviation between CEAs in any group approaches 3 inches, stop group withdrawal and realign CEAs. E. While CEA is misaligned, individual CEA positions within the group shall be determined at least once per 8 hours except when the CEA position deviation circuit is out of service, then verify CEA positions at least once every four hours.
- 2. Misaligned CEA(s) while in Modes 2 and 3 (suberitical).
A. Place the mode select switch in the manual individual mode. B. Select the misaligned CEA on the individual CEA selection switches. C. Select the group of the misaligned CEA on the group select switch. D. .lf CEA motion inhibit is present then:
- 1. Depress and hold the CEA motion inhibit bypass pushbutton.
- 2. .Qepress then release the bypass enable pushbutton.
E. Realign the CEA to the group position. F. Check the position of all CEAs in the group for proper alignment , (CEDMCS and DDPS). 4
REVislON NO.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 24 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDlX H CEA REALIGNMENT (MODES 1,2 AND 3) (Page 2 of 2)
- 3. Misaligned CEA(s) while in Modes 1 and 2'(critical).
CAUTION Reactor power shall .n_ot be increased above the power level precent at the time of the CEA(s) misalignment. A. Prior to realigning of CEA, contact Reactor Engineering and supply them with the following information.
- 1. Power level at which recovery is to be made.
- 2. Rate of CEA movement during recovery.
- 3. Movement of other CEAs to support recovery.
B. Place the mode select switch in the manual individual mode. C. Select the misaligned CEA on the individual CEA selection switches. D. Select the group of the misaligned CEA on the group select switch. E. jf CEA motion inhibit is present, Then:
- 1. Depress and hold the CEA motiori inhit it bypass pushbutton.
- 2. Depress then release the bypass enable pushbutton.
F. Realign CEA to ,the group position. G. Check the position of all CEAs in the group for proper alignment (CEDMCS and DDPS). H. Using manual group mode, readjust the group positions for proper automatic sequencing as necessary. END OF APPENDIX H
l REVl"lON No.: PRoCECURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE No.: D E R G W ENT E of M OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDlX l REALIGNMENT OF ONE DROPPED CEA (Page 1 of 2) NOTE For alignment of CEA(s) while in Mode 3, only Step 3 of this appendix must be performed.
- 1. The CEA should be recovered by a slow, smooth withdrawal using small increments of movement. Preferably, the movement increments should be three steps (21/4") or less. The period of time for recovering the CEA should be at least 10 minutes, but within the time allowed by Tech Specs.
- 2. Reactor power must be maintained constant by boration while withdrawing the dropped CEA.
- 3. Realign the dropped CEA by performing the following: l A. Place the mode select switch in manual individual mode.
B. Select the dropped CEA on the individual CEA selection switches. C. Select the group of the dropped CEA on the group select switch. D. Depress and hold the CEA motion inhibit bypass pushbutton. E. Depress then release the bypass enable pushbutton. F. Withdraw the affected CEA and check'for smooth operation and normal indications.
- 4. Following the retum of.the CEA to its group, operation should be maintained at the existing power level until advised by Reactor Engineering in orde:'to allow assessment .of resultant power distributions and/or azimuthal tilts.
l
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. REVISloN NO.: PROCEDURE Tm.E: PAGE: . 38 CEA OFF-NORMAL OPERATION I PROCEDURE No.: AND REALIGNMENT 26 of 29 OFF-NORMAL OPERATING PROCEDURE ~
2-0110030 ST. LUCIE UNIT 2
, APPENDIX l REALIGNMENT OF ONE DROPPED CEA (Page 2 of 2)
NOTE ' It may be necessary to operate at this reduced power for as long as 24 to 36 hours in order to reduce the azimuthal oscillation and the resulting values of Fj, T,, F( and ASI resulting from a dropped CEA.
- 5. Notify the Reactor Engineering supentisor when CEA is realigned.
- 6. Upon ascertaining that a normal power distribution is present and that the plant conditions are normal, retum to the desired operating level in accordance with OP 2-0030123, " Reactor Operating Guidelines During Steady State and Scheduled Load Changes." The guidelines for ASI oscillation control should be implemented appropriately.
- 7. To monitor BOC azimuthal (cross core) power shifting caused by a dropped peripheral CEA, Reactor Engineering should continue as needed to verify a normal power distribution following retum to the desired operating power level.
4 l l l I 3
- END OF APPENDIX l l
., REVISION No.: 3 PROCEDUhE TITLE: PAGE: . 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 27 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 APPENDIX J CONTINUOUS GRIPPER VOLTAGE Hi(ANNUNCIATOR K-36) ALARM (Page 1 of 2)
CAUTION The following must be performed within 10 minutes after receiving annunciator K-36 to prevent damaging the upper gripper coils. 3 _( AUTION If more than one CEA subgroup is in the high voltage condition, (more than 2 continuous gripper high voltage lights illuminated) notify the Control Room to trip the reactor and implement 2-EOP-01, " Standard Post Trip Actions." . A. Placing a Subgroup on the Hold Bus
- 1. Determine which subgroup (s) is in high voltage condition by the illuminated Continuous Gripper High Voltage lights (located at the bottom of each subgroup cabinet).
t
- 2. Energize the Hold Bus by placing the appropriate Subgroup Maintenance toggleswitch to the ON position.
- 3. Slowly and firmly depress the appropriate (red) Hold Bus HV 4
pushbutton four (4) times.
- 4. Open all CEA Disconnect Breakers for the' appropriate subgroup.
- 5. Contact I&C Department and inform them of the plant condition.
- B. Removing a Subgroup fro,m the Hold Bus
- 1. CLOSE disconnect breakers for the appropriate subgroup.
- 2. Reset appropriate Automatic CEA Timer Modules (ACTMs).
, REVISloN NO.: PROCEDURE TrrLE: PAGE:
38 CEA OFF-NORMAL OPERATION ; PROCEDURE No.: - AND RE!J lGNMENT 28 of 29 OFF-NORMAL OPERATING PROCEDURE 2-011G030 ST. LUCIE UNIT 2 APPENDIX J CONTINUOUS GRIPPER VOLTAGE HI(ANNUNCIATOR K-36) ALARM (Page 2 of 2) NOTE While the subgroup is on the Hold Bus, it is possible that the High Voltage light and the Upper Gripper or the Lower Gripper LEDs will be on simultaneously.
- 3. Ensure that the Upper Gripper LED or the Lower Gripper LED is lit.
- 4. H the Lower Gripper or the Upper Gripper LED is NOT lit, Then DO NOT remove the Subgroup from the HOLD Bus and contact the l&C !
Dept.
- 5. H the Lower Gripper or the Upper Gripper LED is lit on ALL the ACTMs <
for the appropriate subgroup, Then de-energize the Hold Bus by placing the appropriate Subgroup maintenance toggleswitch to the OFF ; position. I
- 6. H any ACTMs indicate a Lower Gripper condition, Then reset the ACTMs and verify an Upper Gripper condition.
- 7. Lf ACTMs have been reset and continue to indicate a Lower Gripper 1 condition, Then contact the l&C Dept.
I 1
. l 1
END OF APPENDIX J I 1 j
REVISION NO.: PROCEDURE TITLE: PAGE: 38 CEA OFF-NORMAL OPERATION PROCEDURE NO.: AND REALIGNMENT 29 of 29 OFF-NORMAL OPERATING PROCEDURE 2-0110030 ST. LUCIE UNIT 2 FIGURE 1 ,
% CEA INSERTION (INCHES CEA WITHDRAWN)
(T.S. FIGURE 3.1-2) l 0 FRACTION OF RATED THERMAL POWER o o o o o o o o o a
=
$ o N N Nb 5 8N 8 NN x
go- . . . . . . . . . 8 - - Group 5 e 25% insertion - (1.0. Group 5 0 g gh - C ET
- ffgg / -
25% insernon) _ (0.75. Group 5 0 50% inseruon) Qo- f8 - - g@ (0.70. Group 5 0 80% insertion) gg _ g _ _ Group 4 0 20% inserbon j g Sg _ gg_ S _c
/ (0.65. Group 5 0 85% insernon)
' g _
$ A
_ $ 2 (0.56. Group 4 0 50% ;noorbon) {8 - yo- - g - E 5 Ea sg ss - . . _ 3 _b gg E8 - - -
? u l(0.20. Group 3 0 60% insertion)
}o- {8 - -
N8 - 8 - - - a - 2 S Eb _w gg- -
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"_g8 gg 58 s
E8 S gg. i e , , , i i i i l 1 i
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1 l l JOB PERFORMANCE MEASURE Knowledge Questions Question #1. KA: 001K5.02 Importance: 2.9/3.4
Reference:
Unit 2 Plant Physics Curves , ks 44 Question: 4f Unit 2, with 6,000 EFPH on the core;/, experiences a dropped rod resulting in the Ni power level changes from 100% to 93%, what'is the approximate worth of the dropped rod? Expected Response: Approximately 75 to 100 pcm. SAT UNSAT Comments: Question # 2. KA: 001K5.28 Importance: 3.5/3.8
Reference:
Unit 2 Plant Physics Curves Question: In order to withdraw the saine CEA without changing the power level or temperature of the RCS, how much would RCS boron concentration have to be changed 7(PPM) Expected Response: approximately 12 PPM (Boron worth for the present conditions is 8.38pcm/ ppm) , W' )ppS W Comments; pcsh e b b
- p. E l' .
y)& f#' b~ 0821164, Rev 00 Page 11 of 12 h y e --
JOB PERFORMANCE MEASURE P Verification of Completion Trainee: Trainee's Department: Evaluator: Please Print JPM
Title:
RESPOND TO A DROPPED CEA AT UNIT 2 JPM Number: 0821164, Rev 00 INDICATE TESTING METHOD: Perform Simulate Questions Asked: Question #: SAT / UNSAT Question #: SAT / UNSAT Actual Time to Complete JPM: Start Time Stop Time The trainee's performance was evaluated against the standards contained in this JPM and determined to be: 1 SATISFACTORY UNSATISFACTORY Trainee's Signature: Date: Evaluator's Signatura- Date: l l l Reason, if unsatisfactory I 0821164. Rev 00 Page 12 of 12
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' 0621164, Rev 00 Page 13 of 12 ;
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JOB PERFORMANCE MEASURE Provide this. page to the Trainee initial Conditione. The plc.d is operatirg at 100% power, MOL, and the CEA periodic surveillance is in progress. CEA 56 has dropped to the bottom while being exercised. The immediate Operator Actions have been performed. There have been no dropped rods in the previous 24 hours. Initiating Cue: The ANPS has directed you to carry out the Subsequent Actions of the CEA Off-normalin order to realign CEA # 56 with the remainder of the Group 5 CEAs. Page 14 of 12
JOB PERFORMANCE MEASURE
\
SIMULATOR JPM SETUP 0821028a
- 1. RESTORE IC-1,
- 2. UNFREEZE and run the simulator for a few minutes.
- 3. FREEZE the simulator.
- 4. Select CONFIGURE and change to JPM Configuration.
- 5. Select appropriate lesson and START the lesson.
~ 6. UNFREEZE and run tre simulator.
- 7. TRIGGER steps as necessary during the JPM scenario.
- 8. After triggering the rod drop, ensure CEDMCS is in OFF. Put DEH DEMAND at 810 and enter a load rate of 20 MW/ min; this will match Tave and Tref when the DEH computer goes to HOLD.
I 1 0821028a, Rev 02 Page 15 of 12 ,
l r , O FPL e This JPM For NRC Exam Use Only St Lucie Nuclear Plant
; Licensed Operator Training Program Job Performance Measure RESPOND TO A DROPPED CEA AT UNIT 2 0821164, Rev 00 i
SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job AppIlcability. RO, SRO System: Control Rod Drive System Safety Function: 001
Reference:
ONOP 2-0110030, "CEA Off-Normal and Realignment",2-EOP-01, " Standard Post Trip Actions" Task: Operate the control rods manually while the Reactor is at power Developed / Revised by: Tim Bolander / Approved by Training Supervision: /
- Examiner /
1 Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. i t i
JOB PERFORMANCE MEASURE Department: Operations Task
Title:
RESPOND TO A DROPPED CEA AT UNIT 2 JPM No.: 0821164, Rev 00 Trainee: Evaluator: An X below indicates tFe applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 20 Minutes Location of Performance: UNIT 2 CONTROL ROOM / SIMULATOR Notes to the Evaluator:
- Pull the latest controlled copy of the applicable procedure
. The next to last page of this JPM lists the initial conditions and initiating cue.
Tear that page off and give it to the trainee.
. Notify a Management Observer of the observation opportunity.
0821164, Rev 00 Page 2 of 12
l JOB PERFORMANCE MEASURE READ TO THE TRAINEE
- You are to perform / simulate this task.
The task you are to perform / simulate is: RESPOC TO A DROPPED CEA AT UNIT 2 I will describe the general conditions and tell you the tools and equipment required to perform / simulate / discuss this task. Before starting I will state the task standards and initiating cues and answer any questions you have. When you peiform all the critical steps correctly, you will pass this Job Peiformance Measure. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM. General / Initial Conditions The plant is operating at 100% power, MOL, and the CEA periodic surveillance is in progress. CEA 56 has dropped to the bottom while being exercisec'. The immediate Operator Actions have been performed. There have been no dropped rods in the previous 24 hours.
.T_qols and Equipment None Safety Consideraliant in accordance with the FPL Nuclear Division Safe Work Practices manual as appropriate to the task.
1
- Task Standard (sk .
I i in order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality i
, Instruction Ol-5-PSL-1.
- t. l 0821164, Rev 00 Page 3 of 12 !
I i
. JOB PERFORMANCE MEASURE B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overallintent of what the JPM required upon completion. , D. Correctly perform all eritical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from memory. During the enurse of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance.
- initiatino Cue (s) 1 The ANPS has directed you to carry out the Subsequent Actions of the CEA Off-normal in order to realign CEA # 56 with the remainder of the Group 5 CEAs.
References
- ONOP-2-0110030, Rev. 38 During the performance of the task I will tell you which steps to simulate or discuss.
i
. Verbalize each step before you do it. This gives you a chance to self-check and use l STOP during the performance of each task element.
Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification. I will provide you with the appropriate cues for steps which are simulated or discussed. You may use any approved reference materials normally available in the execution of , this Job Performance Measure, including logs. ,.
. Do you understand these directions?
If you have any questions, ask them now, and I will answer them.
. During the test I cannot answer questions.
0821164. Rev 00 Page 4 of 12
\
l JOB PERFORMANCE MEASURE
. When you complete all steps correctly, you will pass this job performance measure.
4
. Begin the task now.
3 i F i t I i l f .i 1 t a b 4 f # 5
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i . r g. i 0821164, Rev 00 Page 5 of 12 t j- r !- l 4, 't 4
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JOB PERFORMANCE MEASURE
- 1. Element / Step Notify Reactor Engineering, Operations Supervisor and Operations Manager of the time of CEA misalignment.
Standard: ItEPORT time cf CEA misalignment to Reactor Engr., Ops Supv., and the Ops Manager Cue: REACTOR ENGR., OPS SUPV., AND THE OPS MANAGER ACKNOWLEDGE REPORT , SAT UNSAT Comments: -
- 2. (C) ElemenUStep Determine from symptoms and CEA position indication to use Appendix F for CEA recovery instructions Standard: REFER to Appendix F for CEA recovery instructions Cue: ACKNOWLEDGE USE OF APP. F SAT UNSAT Comments:
'i 0821164, Rev 00 Page 6 of 12
/i
I 1 l JOB PERFORMANCE MEASURE
- 3. (C) Element / Step Ensure the following:
A. Standard: CEDMCS panelin OFF Cue: CEDMCS IN OFF B- Standard: Turbine power adjusted to equal reactor power. Tavg/ Tref matched on TIR-1111 or TIR-1121. Cue: Tavg/ Tref MATCHED C. Standard: CEA motion inhibit. Cue: ANNUNCIATOR LIT NOTE -IF QUESTIONED ON PREVIOUS DROPPED ROD HISTORY, REFER STUDENT TO INITIAL CONDITIONS SHEET PROVIDED AT THE START OF THE JPM, NO DROPPED RODS HAVE OCCURED WITHIN THE LAST 24 HOURS. SAT UNSAT Comments: i I t 0821164. Rev 00 Page 7 of 12
i JOF, PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 4. (C) Element / Step Determine the operability of the CEA in accordance with Appendix A.
Refer to App. A and perform the following to determine operability: A. Standard: Place the mode select switch in MANUAL INDIVIDUAL Cue: MODE SELECT IN MANUAL INDIVIDUAL B. Standard: SELECT CEA H on the individual CEA selection switches. Cue: CEA 56 SELECTED C. Standard: SELECT GROUP 5 on the group select switch. Cue: CUE: GROUP S SELECTED D. Standard: Enable CMI Bypass by: Depress and HQLQ the CEA motion inhibit bypass pushbutton. AND DEPRESS then RELEASE the Bypass Enable pushbutton Cue: BYPASS ENABLED E. Standard: WITHDRAW CEA 56 until rod bottom and LEL lights extinguish, ; Ihan INSERT and WITHDRAW the affected CEA and check for
- smooth operation and normalindications. l i
4 Cue: CEA BEGINS TO WITHDRAW AND CONTINUES TO WITHDRAW EVEN IF THE CONTROL SWITCH IS RELEASED OR PLACED IN THE l lNSERT POSITION. 4 l SAT UNSAT Comments: - 4 e 4 0821164, Rev 00 Page 8 of 12 I
JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 5. (C) Element / Step Place the CEDMCS panelin REE.
Standard: The CEDMCS panelis in REE. Cue: CEA 56 CONTINUES TO WITHDRAW.
- 6. (C) Element / Step Trip the Reactor and implement 2-EOP-01," Standard Post Trip Actions".
Standard: Manually trip the Reactor and perform " Standard Post Trip Actions" Cue: THE REACTOR TRIPS, THE TURBINE DOES NOT TRIP. ,
- 7. (C) Element / Step Manually trip the Turbine Standard: Trip the Turbine Cue: TURBINE IS TRIPPED SAT UNSAT Comments:
1 0821164. Rev 00 Page 9 of 12 l l
i l I I
.'I JOB PERFORMANCE MEASURE l
i (C) Indicates a Critical Step PERFORMANCE CHECKLIST l
- 8. Element' Step: Refer to Standard Post Trip Actions (2-EOP-1) and l determine the course of action to take. i Standard: Implements 2-EOP-1 l Cue: SPTAS IN PROGRESS END Element / Step TERMINATION Standard: JPM is terminated when the Reactor and Turbine is tripped and 2 EOP-01 is being implemented.
I l J s l e 1 i 4 l 1 l
- i. 0821164. Rev 00 Page 10 of 12 l l
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S 2 OPS WE DOCT PROCEDURE ~ DOCN 2-EOP 01 FLORIDA POWER & LIGHT SYS COMP _ COMPLETED ~ ITM 16 ST. LUCIE PLANT 4
- m. . -anA., os uny !
UNIT NO. 2
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2-EOP-01 REVISION
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STANDARD POST TRIP ACTIONS SPTA EMERGENCY OPERATING PROCEDURE REVISION REVIEWED BY FRG ON APPROVED BY DATE O 12/23/85 _ D. A. Saoer 12/23/85 Plant General Manager - 16 2/5/98 : J. Scarola ! 2/6/98 ! Plant General Manager Responsible Department: OPERATIONS 1 i TJB 2/11/98
REVISloN 90.: PROCEDURE TITLE: PAGE: )
- 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 3 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:
! REACTIVITY CONTROL INSTRUCTIONS CONTINGENCY ACTIONS O 1. Verify Reactivity Control is 1. If Reactivity-Controlis NOT established by the following: established, Then do the following as necessary: A. Reactor power decreasing. A. Manually TRIP the AND Reactor. B. A maximum of one CEA B. H more than one CEA is NOT fully inserted. NOT fully inserted, Then emergency borate in accordance with ONOP 2-0250030, " Emergency Boration." i C. Locally OPEN TCB-1 through TCB-8, "240V AC Reactor Trip Switchgear." D. Locally deenergize the CEDM MG sets by j OPENING breakers: LC 2A2, Bkr. 2-40212 "CEA Drive MG Set 2A." AND
.. LC 2B2, Bkr. 2-40511 "CEA Drive MG Set 28."
E. Consider 2-EOP-15,
" Functional Recovery".
REVISloN NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS ' PROCEDURE NO.: 4 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) MAINTENANCE OF VITAL AUXILIARIES (AC & DC POWER) INSTRUCTIONS CONTINGENCY ACTIONS O 2. Verify plant electrical power 2. jf electrical power requirements requirements are satisfied by are NOT satisfied, Then do the the following: following as necessary: A. Turbine tripped (GVs and A. Manually TRIP the Turbine TVs CLOSED). and ensure GVs and TVs CLOSE. AND B. jf GVs and TVs do NOT B. 8W49 and 8W52 " Generator close, Then: No. 2 East and Mid Breakers" are OPEN. 1. CLOSE the MSIVs, HCV-08-1 A and AND HCV-08-1 B, " Main Steam Hdr A and B C. FB 2, " Exciter Supply isolation Valves." Breaker" is OPEN. l 2. Dispatch an operator to AND locally TRIP the Turbine (at front standard). D. Electrical auxiliaries transfer from Auxiliary to Start up 3. When the Turbine is Transformers, tripped, Then ensure the following: AND
- a. 8W49 and 8W52 E. Verify at least one vital DC " Generator No. 2 bus (2A or 28) is energized. East and Mid Breakers" are OPEN.
AND
- b. FB 2, " Exciter Supply Breaker" is OPEN. .
I (Continued on Next Page) i
l REVISICZ NO.: PROCEDURE TITLE: C8 AGE: l 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 5 of 19 I EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) MAINTENANCE OF VITAL AUXILIARIES I (AC & DC POWER) ! l INSTRUCTIONS CONTINGENCY l ACTIONS
- 2. 2. (continued) l C. Ensure the EDG(s) are !
started with output breakers CLOSED, energizing only the emergency buses. D. Reenergize at least one vital DC bus:
- 1. CLOSE 2A Battery Bkr.
2-61107, " incoming Main."
- 2. CLOSE 2B Battery Bkr.
2-61207, " Incoming Main." j l
- - - - - _ - _ _ - - _ - _ _ - - _ _ _ _ - _ - _ - - _ _ - - - - - - _ _ _ _ _ _ _ - _l
REVISloN No.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE No.: 6 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) RCS INVENTORY CONTROL INSTRUCTIONS CONTINGENCY ACTIONS U 3. Verify RCS Inventory Control is 3. if. RCS Inventory Control is NOT established by the following: established, Then do the following as necessary: A. Pressurizer level A. Ensure proper operation of
- 1. Between 10% and 70% the Pressurizer level controls.
AND B. Manually control Charging
- 2. Trending to between and Letdown to restore and 27% and 35% maintain Pressurizer level 27% to 35%.
AND C. Adjust RCS pressure and B. RCS Saturation Margin is temperature as necessary between 20 F and 200 F to maintain required subcooled. subcooling. AND C. Reactor Vessel level 100%, if available. /R16 4 l 1 l
REVISloN NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS l 7 of 19 PROCEDURE No.: l EMERGENCY OPERATING PROCEDURE ; 2-EOP-01 ST. LUCIE UNIT 2 ' 5.0 OPERATOR ACTIONS:(continued) RCS PRESSURE CONTROL INSTRUCTIONS CONTINGENCY ACTIONS O 4. Verify RCS Pressure Control is 4. H RCS Pressure Controlis NOT established by: established, Then do the following as necessary: A. Pressurizer pressure. A. Ensure proper operation of
- 1. Between 1800 and 2300 the Pressurizer pressure psia. controls.
AND B. Manually control Pressurizer heaters and
- 2. Trending to between sprays.
2225 and 2275 psia. C. Ensure V1474 and V1475 AND "PORVs" are CLOSED when pressure is less than B. RCS Saturation Margin is 2300 psia, H NOT, Then: between 20 F and 200 F subcooled. 1. Place the control switch (es) for the l affected valve (s) to the OVERRIDE position. OR 1 l
- 2. CLOSE V1476 and/or l V1477, "PORV Block l Valves", for the corresponding affected ,
valve (s), D. H Pressurizer pressure decreases to 1736 psia, Then ensure an SlAS has I actuated. 1 (Continued on Next Page)
l REVISION No.: PROCEDURE TITLE: PAGE: 1 16 STANDARD POST TRIP ACTIONS EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) 1 RCS PRESSURE CONTROL 1 INSTRUCTIONS CONTINGENCY ACTIONS
- 4. 4. (continued) -
E. If Pressurizer pressure decreases to less than 1300 psia following an SlAS, Then:
~1. STOP 1 RCP in each loop.
i AND
- 2. INITIATE sealinjection to the RCPs if available:
- a. Ensure charging flow is available.
- b. OPEN V2185, ,
" injection Actuation Viv."
i 4 4 y- ----- ___m-_-
l REVISloM Wo.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS 9 of 19 PROCEDURE No.: EMERGENCY OPERATING PROCEDURE ; 2 EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) , CORE HEAT REMOVAL l lNSTRUCTIONS CONTINGENCY ACTIONS O 5. Verify Core Heat Removal 5. H Core Heat Removalis NOT using forced circulation by: being maintained, Then do the following as necessary: A. At least one RCP is operating and supplied with A. H CCW is NOT CCW. reestablished to the RCPs within 10 minutes, Then AND STOP all RCPs. B. Loop AT is less than 10 F. B. H forced circulation core heat removal is NOT AND Possible, Then 5 to 15 minutes after stopping C. RCS Saturation Margin is RCPs ensure natural between 20 F and 200 F circulation is developing by: subcooled.
- 1. Loop AT is less than 50 F.
- 2. T-cold constant or decreasing.
- 3. T-hot constant or decreasing.
- 4. No abnormal difference (greater than 20 F)
.. between T-hot and Rep CET Temp.
- 5. CET Saturation Margin indicates at least 20 F subcooling.
l
REVISION NO.: PROCEDURE TITLE: PAGE: , 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 10 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) RCS HEAT REMOVAL INSTRUCTIONS CONTINGENCY ACTIONS O 6. Verify RCS Heat Removal by 6. H RCS Heat Removalis NOT the following: being maintained, Then do the following as necessary: A. At least one S/G with level greater than 40% (wide A. Ensure Auxiliary Feedwater range) and main feedwater flow after AFAS time delay, available. B. E all feedwater has been AND stopped, Then do NOT exceed a flow rate of 150 B. RCS T-avg is between or 9Pm per S/G, for trending to 525 F and 5 minutes. 535 F. C. H A or B AFW Pump is the AND only source of feedwater, Then do the following: C. Steam Generator pressure is between 750 and 950 psia. 1. STOP one RCP in each loop AND AND D. Ensure the four "MSR TCV Block Valves" are CLOSED: 2. INITIATE sealinjection to the RCPs if available: MV-08-4 MV-08-6 MV-08-8 MV-08-10 a. ENSURE Charging flow !s available,
- b. OPEN V2185,
" injection Actuation Viv."
(Continued on Next Page)
REVISloM No.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE No.: 11 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) RCS HEAT REMOVAL 1 INSTRUCTIONS CONTINGENCY , ACTIONS l l
- 6. 6. (continued)
D. If Main or Auxiliary Feedwater flow can NOT , be reestablished, Then:
- 1. STOP one RCP in each loop.
AND
- 2. INITIATE sealinjection to the RCPs if available:
' a. Ensure charging flow is available.
- b. OPEN V2185,
" injection Actuation Viv."
E. jf RCS T-avg is greater than 535*F, Then do the following:
- 1. Ensure Main or Auxiliary Feedwater is controlling or restoring level to at least one S/G.
- 2. Operate SBCS to control RCS T-avg eetween 525 F and i 535*F.
(Continued on Next Page)
AEVISION RO : PROCEDURE TirLE: PAGE: 16 STANDARD POST TRIP ACTIONS l PROCEDURE No.: 12 of 19 ) EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) RCS HEAT REMOVAL INSTRUCTIONS CONTINGENCY ACTIONS
- 6. 6. (continued) -
E. (continued)
- 3. H SBCS is NOT available, Then use ADVs to control T-avg between 525 F and 535*F, F. H RCS T-avg is less than 525*F, Then ensure feedwater flow is NOT excessive. Control Main or Auxiliary Feedwater flow as necessary.
G. H RCS T-avg decreases to less than 525*F, Than_:
- 1. Ensure no more than three RCPs are operating prior to T-cold decreasing to less than 500 F.
AND
- 2. INITIATE sealinjection to the RCPs if available:
- 3. Ensure charging flow 4
is available.
- b. OPEN V2185,
" Injection Actuation Viv."
(Continued on Next Page)
REVISION NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 13 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS: (continued) RCS HEAT REMOVAL INSTRUCTIONS CONTINGENCY ACTIONS
- 6. 6. (continued) -
', H. H S/G pressure is less than 750 psia, Then CLOSE the following as necessary to avoid excessive cooldown:
- 1. MSIVs, HCV-08-1 A and 18, " Main Steam Hdr A and B isolation Valves."
OR
- 2. ADVs, "SG 2A and 28 Atmos Dump Vivs."
- 1. H pressure decreases to 600 psia, in either S/G, Then ensure MSIS has actuated.
J. H all four "MSR TCV Block Valves" did NOT CLOSE, Then PLACE Reheat ' Control Valve TCVs in MANUAL and CLOSE the TGVs. 9
REVISIOM NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS 1 PROCEDURE NO.: 14 of 19 EMERGENCY OPERATING PROCEDURE 2 EOP-01 ST. LUCIE UNIT 2 S.0 OPERATOR ACTIONS: (continued) ] I CONTAINMENT ISOLATION i INSTRUCTIONS CONTINGENCY i ACTIONS O 7. Verify normal Containment 7. H normal Containment conditions by: conditions are NOT indicated, Then: A. Containment pressure is less than 2 psig. A. H Containment pressure is greater than 3.5 psig, Then AND ensure SlAS and CIAS have actuated. B. No Containment radiation alarms or increasing trends. B. H Containment radiation is greater than 10 R/hr or AND SIAS actuated, Then ensure CIAS has actuated. C. No secondary plant radiation alarms or increasing trends (Condenser Air Ejector, Blowdown or Main Steamline Monitors). t 4 9
REVISloN NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PRocEcuRE No.: 15 of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 5.0 OPERATOR ACTIONS:(continued) CONTAINMENT TEMPERATURE, PRESSURE AND COMBUSTIBLE GAS CONTROL INSTRUCTIONS CONTINGENCY ACTIONS C 8. Verify normal Containment 8. H normal Containment temperature and pressure temperature and pressure parameters by the following: parameters are NOT indicated, Then do the following as A. Containment temperature is necessary: less than 120 F. A. Ensure all available AND Containment Coolers are operating. B. Containment pressure is less than 2 psig. B. H Containment pressure is greater than 5.4 psig, Then ensure CSAS has actuated with Containment Spray flow greater than or equal 1 to 2700 gp,m. 1 I l I l
l REVGloN Ro.: PROCEDURE TrrLE: PAGE: i6 i STANDARD POST TRIP ACTIONS PROCEDURE NO.: 16 of 19 EMERGENCY OPERATING PROCEDURE . 2-EOP-01 ST. LUCIE UNIT 2 ! 50 OPERATOR ACTIONS: (continued) l l l lNSTRUCTIONS CONTINGENCY i ACTIONS l O 9. Notify NPO to perform Secondary Plant Post Trip i Actions in accordance with . Appendix X of 2-EOP-99,
" Appendixes / Figures / Tables."
C 10. Verify all safety function 10. H all safety function acceptance acceptance criteria are criteria are NOT satisfied, Then satisfied. H all safety function the following guidance shall be acceptance criteria are utilized: satisfied, Then GO TO 2-EOP-02, " Reactor Trip A. Refer to Chart 1, Recovery." " Diagnostic Flow Chart." g a diagnosis is apparent, The_n GO TO the appropriate Emergency Operating Procedure. AND B. Implement the Emergency Plan as required in accordance with EPIP-01
" Classification of Emergencies."
C. E a diagnosis is NOT possible, Then GO TO 2-EOP-15, " Functional Recovery." i END OF TEXT i l l l
REVISION NO.: l PROCEDURE TirLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 17 of 19 ~ ' EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 FIGURE 1 4 RCS PRESSURE TEMPERATURE CAUTION When below the RCP Seal Requirement Curve, RCP instrumentation should be monitored for indication of pump cavitation. For minimum seal g requirements, RCP operation below 250 psia should be avoided.
.... .3, >
g EEE :~l j j i.: II. :' i RCP cperation is Irnited !!!(Acceptable];ifj by 5ealrequirements which are
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REVISION NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 18 Of 19 EMERGENCY OPERATING PROCEDURE 2-EOP-01 ST. LUCIE UNIT 2 CHART 1 DIAGNOSTIC FLOW CHART (Page 1 Of 2) PE REA OR ,M EOP41 WM GO TO NO REACTIVITY O YES FUNCTIONS ' REACTOR TRIP j CONTROL RECOVERY' y ? SATISFIED EOP-02 CONSIDER "FUNCTr;'NAL YES RECOVER.* r EOP 15 AT N LEAST ONE NO VITAL DC BUS ENERGIZED 7 YES AT LEAST ONE CONSIDER VITAL 4.16 KV BUS ~ ENERGlZED B EOP 10
?
YES V AT LEAST ONE CONSIDER RCP NO ' LOSS OF l7 OPERATING OFSE N R' A EOP 09 7 YES 1I AT CONSIDER T ONE NO " TOTAL LOSS OF WITH FEEDWATE FEEDWATER* AVAILABLE EOP-06 7 YES 4 1 w .a-, V (
REVISION NO.: PROCEDURE TITLE: PAGE: 16 STANDARD POST TRIP ACTIONS PROCEDURE NO.: 19 Of 19 EMERGENCY OPERATING PROCEDURE
- 2-EOP-01 ST. LUCIE UNIT 2 CHART 1 ,
DIAGNOSTIC FLOW CHART (Page 2 of 2) NOTE
~If die 0nosis indicates LOOP concurrent with LOCA SGTR ESD, or TLOF, Then GO TO the Emergency Operating Procedure for LOCA.
SGTR, ESD, or TLOF, 3 PRE YES GREATER THAN 1 1000 PSM AND LEVEL SEING ESTORED
- 1 Y"
CONSIDER R S/G ESS. TUNCT'M YES LESS THAN RECOVERP 4 4 750 PSM OR EOP-15 0 DECREAS4NG EOP45 ? A NO NO IS CONSIDER Agy Op GE YES SECONDARY NO TAJNMENT TCFt RADIATION OR ES8URE GREATE N EVENT N O APPARENT ] _ RUFTURE INCREASING TRENDS THAN 2 PSIG OR INCREASIN
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@FPL This JPM For NRC Exam Use-Only St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure OPERATE HYDROGEN PURGE SYSTEM - UNIT 2 0821058, Rev 06 SUCCESSFUL CO_NPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Appilcability: RO. SRO System: HRPS Safety Function: 05
Reference:
2-EOP-99, APPENDIX N. Task: Start up the Hydrogen pur0e system Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. O
.I JOB PERFORMANCE MEASURE Department: Operations Task
Title:
OPERATE HYDROGEN PURGE SYSTEM UNIT 2 JPM No.: 0821058, Rev 06 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 20 MINUTES Location of Performance: CONTROL ROOM UNIT 2 SIMULATOR Notes to the Evaluator: Pull the latest controlled copy of the applicable procedure The last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee. Notify a Management Observer of the observation opportunity. J l l l 9 o821058, Rev 06 Page 2 of 12 l
I JOB PERFORMANCE MEASURE READ TO THE TRAINEE
. You are to perform / simulate this task. . The task you are to perform / simulate is:
OPERATE HYDROGEN PURGE SYSTEM - UNIT 2 I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task. 1 Before starting I will state the task standards and initiating cues and answer any questions you have. When you perform all the critical steps correctly, you will pass this Job Performance i Measure. l You are required to perform the steps in the correct sequence. Any safety infraction during this task performance evaluation will be corrected immediately prior to continuing the JPM. General / Initial Conditions: A loss of Coolant Accident has been diagnosed and is in progress in Unit 2. Tools and Equipment: l NONE l l Safety Considerations: In accordance with the FPL Nuclear Division Safe Work Practices manual. 1 Task Standard (s): In order for this job performance measure to be satisfactorily completed, accomplish this JPM in accordance with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality I Instruction Ol 5-PSL-1. B. Locate and operate all plant equipment correctly. C. The system / equipment status reflects the overallintent of what the JPM required upon completion. i t 0821058, Rev 06 Page 3 of 12
JOB PERFORMANCE MEASURE D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these - cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatina Cue (s): Containment hydrogen concentration is greater than 3.5% and the Technical Support
- Center has recommended that the hydrogen purge system be placed in operation. The ANPS directs you to put the hydrogen purge system in operation using "B" side components LAW 2-EOP-99, APPENDIX N.
References:
2-EOP-99, Rev 15, Appendix N During the performance of the task I will tell you which steps to simulate or discuss. Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element. Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification. I will provide you with the appropriate cues for steps which are simulated or discussed. i You may use any approved reference materials normally available in the execution of this ; Job Performance Measure, including logs. i l . Do you understand these directions? 1 { If you have any questions, ask them now, and I will answer them. 4 During the test I cannot answer questions. When you complete all steps correctly, you will pass this' job performance measure.
. Begin the task now.
0821058, Rev 06 Page 4 of 12
.- - ._ =- .. .- . .. - . .- . . .. . .
JOB PERFORMANCE MEASURE ; (C) Indicates a Critica Step PERFORMANCE CHECKLIST 1
- 1. Element / Step Verify closed FCV-25-35, " Continuous Containment Purge Exhaust to Vent .
Stack." . Standard: At NON-SAFETY VENTILATION HVAC PANEL: DETERMINE FCV-25-35 key lock switch is in the LOCKED CLOSE position Cue: GREEN LIGHT ON, RED LIGHT OFF ' SAT UNSAT i Comments:
; 2. (C) Element / Step Open FCV-25-20," Continuous Cntmt. Purge isol. Valve" and FCV-25-21,
" Continuous Cntmt./H2 Purge Makeup Valve."
A. Standard: At the A TRAIN EMERGENCY VENTILATION HVAC PANEL: POSITION FCV-25-20 control switch to OPEN . 4 , Cue: GREEN LIGHT OFF, RED LIGHT ON
- 8. Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL:
; POSITION FCV-25-21 control switch to OPEN Cue: GREEN LIGHT OFF, RED LIGHT ON .j i
i SAT UNSAT - i I Comments: I
! 3. (C) Element / Step Open FCV-25-29, "H2 Purge Discharge to SBVS 'B'."
Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: Obtain key
#95 and POSITION FCV-25-29 key lock switch to OPEN Cue: KEY OBTAINED, GREEN LIGHT OFF, ikED LIGHT ON SAT UNSAT Comments:
0821058, Rev 06 Page 5 of 12 I
--s s,, , . - .- - e . .=++ys s _
pm , , . p ,- ' . \ l 1 JOB PERFORMANCE MEASURE l (C) Indicates a Critical Step PERFORMANCE CHECKLIST - !
.l e
- 4. ElemenUStep Check closed FCV-25-9," Continuous ContainmenUHydrogen Purge Control Valve Filter inlet."
Standard: At the NON-SAFETY VENTILATION HVAC PANEL: VERIFY CLOSED FCV-25-9 Cue: 0%, GREEN LIGHT ON, RED LIGHT OFF
~
SAT UNSAT Comments: 5.(C) ElemenUStep Throttle FCV-25-28," Continuous ContainmenUHydrogen Purge Control
; Valve Bypass"to approximately 10% OPEN position.
j Standard: At the NON-SAFETY VENTILATION HVAC PANEL: POSITION FCV j 28 to the open position UNTIL the valve position indicates 10% OPEN i 4
- Cue
- 10%, BOTH RED & GREEN LIGHTS ON SAT UNSAT 1
Comments: i i , 6. ElemenUStep Start HVE-68," Shield Building Exhaust Fan." Standard: At the B TRAIN EMERGENCY VENTILATION HVAC PANEL: POSITION HVE-6B control switch to START Cue: RED LIGHT ON, GREEN LIGHT OFF SAT UNSAT , Comments: i 0821058. Rev J6 Page 6 of 12
F 81 JOB PERFORMANCE MEASURE r (C) Indicates a Critical Step PERFORMANCE CHECKLIST ; 7.(C) Element / Step Select FCV-25-26 and FCV-25-36," Continuous Containment / Hydrogen Purge Makeup Valves" to the OPEN position. NOTE: FCV-25-26 & 36 WILL NOT OPEN UNTil A NEGATIVE AP EXISTS BETWEEN CONTAINMENT AND OUTSIDE AIR PRESSURE A. Standard: At the A TRAIN EMERGENCY VENTILATION HVAC PANEL: POS! TION FCV-25-26 control switch to OPEN, then release the switch Cue: SWITCH PCS1TIONED TO OPEN, GREEN LIGHT ON, RED , U Ciri ~u rF B. Standard: At 'he B TRAIN EMERGENCY VENTILATION HVAC PANEL: POSIT!ON FCV-25-36 control switch to OPEN, then release the switch Cue: SWITCH POSITIONED TO OPEN, GREEN LIGHT ON, RED LIGHT OFF SAT UNSAT Comments: 8.(C) Element / Step Start HVE-78," Hydrogen Purge Fan." Standard: At the NON SAFETY VENTILATION HVAC PANEL: POSITION HVE-78 control switch to START Cue: RED LIGHT ON, GREEN LIGHT OFF SAT UNSAT Comments. I 1 l 0821058, Rev 06 Page 7 of 12 t_____m _ . . _ _ _ _ _ _ _ . . _ _ _ - - - . _
)
1 i JOB PERFORMANCE MEASURE i (C) Indicates a Critical Step PERFORMANCE CHECKLIST i
- 9. Element / Step Throttle FCV-25-28," Control Bypass Valve" to maintain a hydrogen purge rate of approximately 100 CFM.
Standard: At the NON-SAFETY VENTILATION HVAC PANEL: MONITOR F1-25-2 1 and simultaneously THROTTLE FCV-25-28, until FI-25-2 indicates 100 CFM Cue: 100 CFM INDICATED SAT UNSAT Comments: 4 s b
- 10. Element / Step Observe proper system operation by checking flows, hydrogen sample
) analysis concentrations, and plant vent monitor. l Standard: MONITOR parameters to determine effectiveness of hydrogen purge operation. 4 . Cue: PROPER FLOW INDICATED, H CONCENTRATION LOWERING, PLANT VENT RAD LEVELS RISING 1 SAT UNSAT
- Comments
1 i
. END Element / Step TERMINATION Standard: The Hydrogen Purge System is in operation per the required steps of 2-EOP-99, APPENDlX N and the ANPS is informed.
0821058, Rev 06 Page 8 of 12
REVISION No.: PROCEDURE TITLE: PAGE: 15 APPENDIXES / FIGURES / TABLES ! PROCEDURE No" 9 ' EMERGENCY OPERATING PROCEDURE # ,; , ! 2-EOP-99 ST. LUCIE UNIT 2 FORINFORhATION ONufaSc HYDROGEN PURGE SYST M 0" w $*g (Page 1 of 1)
]
' ~
- 1. Operate the Containment Hydrogen Purge System as follows: 0 A. Verify CLOSED FCV-25-35, " Continuous Containment Purgo Exhaust to Vent StEck."
NOTE l The following valves receive a close signal on CIAS but may be opened with a CIAS present. B. OPEN FCV-25-20, " Continuous Cntmt. Purge Iso!. Valve" and FCV-25-21,
" Continuous Cntmt./H2 Purge Makeup Valve."
C. OPEN FCV-25-34, "H 2Purge Discharge to SBVS 'A' " if using SBVS 'A' Train o.r FCV-25-29, "H2 Purge Discharge to SBVS 'B' " if using SBVS 'B' Train. D. Check CLOSED FCV-25-9, " Continuous Containment / Hydrogen Purge Control Valve Filter inlet." i E. Throttle FCV-25-28, " Continuous Containment / Hydrogen Purge Control Valve Bypass" to approximately 10% OPEN position. F. Start either HVE-6A or HVE-6B, " Shield Building Exhaust Fan." NOTE FCV-25-26 and FCV-25-36 will NOT open until a negative differential exists between the containment and outside air. G. Select FCV-25-26 and FCV-25-36, " Continuous Containment / Hydrogen Purge Makeup Valves" to the OPEN position. ! 1 H. Start either HVE-7A of HVE-7B, " Hydrogen Purge Fan."
- 1. Throttle FCV-25-28, " Control Bypass Valve" to maintain a hydrogen purge rate of approximately 100 CFM.
l J. Observe proper system operation by checking flows, hydrogen sample analysis concentrations, and plant vent monitor. I END OF APPENDIX N 1
I I I JOB PERFORMANCE MEASURE Knowledge Questions Question #1. pto Na
** j(jj )
KA: 028G2.1.12 Importance: 2,9/4.0
Reference:
Unit 2 Technical Specifications Question: There are two systems available on Unit 2 to remove hydrogen from the containment atmosphere. Which system is addressed in the Unit 2 Technical Specifications? l Expected Response: The Hydrogen Recombiners, T/S 3/4.6.4.2 o SAT UNSAT Comments: Question # 2. KA: 028A4.01 \ Importance: 0
Reference:
one Question: How is the Unit 1 Hydrogen Purge System different than the Unit 2 Hydrogen Purge System? l Expected Response: Unit 1 Hydrogen Purge System must be manually aligned for operation and uses its own filter train whereas Unit 2 Hydrogen Purge System can be aligned from the control room and uses the Shield Building Ventilation filter train. SAT UNSAT I' Comments: 0621058, Rev 06 Page 9 of 12
l l JOB PERFORMANCE MEASURE l Verification of Comnletion ! 4 Trainee: Trainee's Department: Evaluator: Please Print JPM
Title:
OPERATE HYDROGEN PURGE SYSTEM - UNIT 2 JPM Number: 0821058, Rev 06 INDICATE TESTING METHOD: Perform Simulate , Questions Asked: Question #: SAT / UNSAT Question #: SAT / UNSAT Actual Time to Complete JPM: Start Time Stop Time The trainee's performance was evaluated against the standards contained in this JPM and determined to be: SATISFACTORY UNSATISFACTORY Trainee's Signature: Date: I Evaluator's Signature- Date: Reason,if unsatisfactory: Forward to Training Records Technician 0821050, Rev 06 Page 10 of 12
JOB PERFORMANCE MEASURE 1 il Provide this page to the Trainee ' , initial Conditions: 4 A loss of Coolant Accident has been diagnosed and is in progress in Unit 2. I initiating Cue: Containment hydrogen concentration is greater than 3.5% and the Technical Support Center has recommended that the hydrogen purge system be placed in operation. The ANPS directs you to put the hydrogen purge system in operation using "B" side components IAW ) 2-EOP-99, APPENDIX N. ) i 1 i l 4 [ J f Page 11 of 12 b
1 1 l JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP 0821058 1
- 1. RESTORE 1C-38.
- 2. UNFREEZE and run the simulator for a few minutes, i
. 3. FREEZE the simulator.
- 4. Select CONFIGURE and change to JPM Configuration.
- 5. Select appropriate lesson and START the lesson.
- 6. UNFREEZE and run the simulator.
- 7. TRIGGER steps as necessary during the JPM scenario.
v. 0821058. Rev 06 Page 12 of 12
l l 1 ( l 1 This JPM For NRC Exam Use Only j u > \ FPL l St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure RESTORE FOWER TO 2A3 4160 SWITCHGEAR VIA SBO CROSSTIE 0821129, Rev 02 SUCCESSFUL COMPLETlON REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED , NON-CRlTICAL STEPS MAY BE SIMULATED OR DISCUSSED I I i TIME CRITICAL Job AppIlcability. RO, SRO System: AC Electrical Distribution i Safety Function: 06
Reference:
2-EOP-99, TABLE 7, APP. V Task: Line up the AC electrical distribution system Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner: / Prior to use, ensure referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. I
JOB PERFORMANCE MEASURE Department: Operations Task
Title:
RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO CROSSTIE JPM No.: 0821129, Rev 02 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 10 minutes Location of Performance: Unit 2 Control Room / Simulator Notes to the Evaluator:
+ Pull the latest controlled copy of the applicable procedure
. The last page of this JPM lists the initial conditions and initiating cue. Tear that
- page off and give it to the trainee.
Notify a Management Observer of the observation opportunity. NOTE: The trainee should be made aware that the JPM is TIME CRITICAL. l l 1 0821129. Rev 02 Page 2 of 14
t JOB PERFORMANCE MEASURE 4 READ TO THE TRAINEE -
+ You are to perform / simulate this task.
- The task you are to perform / simulate is:
l RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO CROSSTIE
- I will describe the general conditions and tell you the tools and equipment required to perform / simulate this task.
Before starting I will state the task standards and initiating cues and answer any questions you have. When you perform all the critical steps correctly, you wil! pass this Job Performance ! Measure.
- You are required to perform the steps in the correct sequence.
. Any safety infraction during this task performance evaluation will be corrected l Immediately prior to continuing the JPM.
- General / Initial Conditions
A Station Blackout has occurred on Unit 2. Unit 1 is in a LOOP with both Emergency Diesel Generators in service. The NPS and ANPS have determined the need to crosstie electrical power from the 1 A EDG to the 2A3 4.16 KV switchgear via the SBO AB Bus Crosstie. 4
. Tools and Eauioment:
None Safety Considerations: 4 i in accordance with the FPL Nuclear Division " Safe Work Practices" manual as appropriate to the task. Task Standard (s): in order for this job performance measure to be satisfactoiily completed, accomplish this JPM in accordance with the following standards: A. Carry out tasks in adherence to procedures as directed by Plant St. Lucie Quality Instruction Ol-5-PSL-1. B. Locate and operate all plant equipment correctly. 0821129. Rev 02 Page 3 of 14
. - .- . . . . - . = = - _ __ . - .. . -
i
- JOB PERFORMANCE MEASURE C. The system / equipment status reflects the overallintent of what the JPM required upon completion.
?
D. Correctly perform all critical steps. All steps where procedural guidance exists may be considered critical. Performance of-Off-Normal Operating Procedure immediate actions will be from memory. During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in these cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's procedural guidance. Initiatino Cue (s): The ANPS has directed you to accomplish the Unit to Unit crosstie to the 2A3 4.16 KV Bus by performing 2-EOP-99, Table 7 and then 2-EOP-99, App. V "A** "' ttaa. -
References:
2-EOP-99, TABLE 7, APP. V, Rev.15
+
During the performance of the task I will tell you which steps to simulate or discuss.
+ Verbalize each step before you do it. This gives you a chance to self check and use STOP during the performance of each task element.
+
Verify the position or condition of equipment or components by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification.
- I will provide you with the appropriate cues for steps which are simulated or discussed.
+
You may use any approved reference materials normally available in the execution of this Job Performance Measure, including logs.
+
Do you understand these directions? If you have any questions, ask them now, and I will answer them. During the test I cannot answer questions. When you complete all steps correctly, you will pass this job performance measure. Begin the task now. 0821129, Rev 02 Page 4 of 14
4 i
' JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
, 1
- 1. (C) Element / Step OPEN and GREEN FLAG the following startup transformer i breakers: )
A. Standard: S.U. Transformer 2A (2-30102) Cue: GREEN LIGHT ON, FLAG GREEN I B. Standard: S.U. Transformer 2B (2-30202) ! Cue: GREEN LIGHT ON, FLAG GREEN C. Standard: S.U. Transformer 2A (2-20102) Cue: GREEN LIGHT ON, FLAG GREEN D. Standard: S.U. Transformer 2B (2-20302) Cue: GREEN LIGHT ON, FLAG GREEN SAT UNSAT 4 Comments:
- 2. (C) Element / Step Ensure the following breakers are GREEN FLAGGED and OPEN:
5 A. Standard: Aux Transformer 2A (2-30101 ) (2W87) Cue: GREEN LIGHT ON, FLAG GREEN Standard' Aux Transformer 2B (2-30201) (2W85) Cue: GREEN LIGHT ON, FLAG GREEN a 0821129, Rev 02 Page 5 of 14 1
l i JOB PERFORMANCE MEASURE i (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 2. (Cont'd) B. Standard: Aux Transformer 2A (2-20101) (1W86) l l
Cue: GREEN LIGHT ON, FLAG GREEN Standard: Aux Transformer 2B (2-20301) (1W84) 1 Cue: GREEN LIGHT ON, FLAG GREEN C. Element / Step Tie breakers between normal and emergency 4160V buses: Standard: 4.16 KV Bus Tie 2A2-2A3 (2-20109) Cue: GREEN LIGHT ON, FLAG GREEN l Standard: 4.16 KV Bus Tie 2A3-2A2 (2-20209 Coe: GREEN LIGHT ON, FLAG GREEN Standard: 4.16 KV Bus Tie 2B2-2B3 (2-20309) Cue: GREEN LIGHT ON, FLAG GREEN { l I Standard: 4.16 KV Bus Tie 283-2B2 (2-20411) I Cue: GREEN LIGHT ON, FLAG GREEN ,
)
D. Element / Step 4.16 KV Bus 2AB Tie breakers Standard: Feed to 4.16 KV Bus 2AB (2-20208) Cue: GREEN LIGHT ON, FLAG. GREEN Standard: Incoming feeder from 4.16 KV bus 2A3 (2-20505) Cue: GREEN LIGHT ON, FLAG GREEN 0821129, Rev 02 Page 6 of 14 1
JOB PERFORMANCE MEASURE , (C) Indicates a Critical Step PERFORMANCE CHECKLIST 2.D. (Cont'd) Standard: Incoming feeder from 4.16 KV bus 283 (2-20504) Cue: GREEN LIGHT ON, FLAG GREEN Standard: Feed to 4.16 KV Bus 2AB (2-20409) Cue: GREEN LIGHT ON, FLAG GREEN SAT UNSAT Comments:
- 3. (C) Element / Step OPEN the following 4.16 KV feeder breakers to the station .
service transformers: A. Standard: Station Service Transformer 2A1 (2-20110) Cue. GREEN LIGHT ON i B. Standard: Station Service Transformer 2A5 (2-20210) Cue: GREEN LIGHT ON C. Standard: Station Service Transformer 2A2 (2-20213) Cue: GREEN LIGHT ON D. Standard: Station Service Transformer 2B1 (2-20310) Cue: GREEN LIGHT ON l E. Standard: Station Service Transformer 282/285 (2-20402) l Cue: GREEN LIGHT ON SAT- UNSAT l Commec: 0821129, Rev 02 Page 7 of 14
i l l JOB PERFORMANCE MEASURE I (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 4. (C) Element / Step OPEN and GREEN FLAG the following 480V feeder breakers from the station service transformers:
A. Standard: 480V Bus 2A1 Feeder (2-40103) Cue: GREEN LIGHT ON, FLAG GREEN B. Standard: 480V Bus 2A5 Feeder (2-40361) Cue: GREEN LIGHT ON, FLAG GREEN C. Standard: 480V Bus 2A2 Feeder (2-40219) Cue: GREEN LIGHT ON, FLAG GREEN D. Standard: 480V Bus 2B1 Feeder (2-40419) , Cue: GREEN LIGHT ON, FLAG GREEN E. Standard: 480V Bus 285 Feeder (2-40653) Cue: GREEN LIGHT ON, FLAG GREEN
- F. Standard
- 480V Bus 282 Feeder (2-40503)
Cue: GREEN LIGHT ON, FL/G GREEN SAT UNSAT Comments: 1 i l 0821129, Rev 02 Page 8 of 14
l JOB PERFORMANCE MEASURE (C) Indicates a Critical Step PERFORMANCE CHECKLIST
- 5. (C) Element / Step OPEN the following 480V bus tie breakers A. Standard: 480V Bus Tie 2A2-2AB (2-40220)
Cue: GREEN LIGHT ON B. Standard: 480V Bus Tie 2AB-2A2 (2-40702) Cue: GREEN LIGHT ON C. Standard: 480V Bus Tie 2AB-2B2 (2 40706) Cue: GREEN LIGHT ON l D. Standard: 480V Bus Tie 2B2-2AB (2-40504) - Cue: GREEN LIGHT ON SAT UNSAT Comments:
- 6. (C) Element / Step Establish communications with Unit 1 Standard: ESTABLISH COMMUNICATIONS with Unit 1 via Gai-Tronics or plant radio (if available).
Cue: COMMUNICATIONS ARE ESTABLISHED SAT UNSAT s Comments: 4 0821129. Rev 02 Page 9 of 14 l r
- - - . - - - - _ - - - . - - - . - - - . . - - - - - _ - - - . _ . . ~ ,
i JOB PERFORMANCE MEASURE l (C) indicates a Critical Sten PERFORMANCE CHECKLIST l 7. [ Element / Step PLACE the following pump switches in the PULL TO LOCK position: A. Standard: 2A ICW Pump Cue: SWITCH IN PULL TO LOCK B. Standard: 2B ICW Pump Cue: SWITCH IN PULL TO LOCK C. Standard: 2C ICW Pump Cue: SWITCH IN PULL TO LOCK D. Standard: 2A CCW Pump Cue: SWITCH IN PULL TO LOCK E. Standard: 28 CCW Pump Cue: SWITCH IN PULL TO LOCK F. Standard: 2C CCW Pump Cue: SWITCH IN PULL TO LOCK SAT UNSAT Comments: , 0821129. Rev 02 Page 10 of 14
'l i JOB PERFORMANCE MEASURE
, (C) Indicates a Critical Step PERFORMANCE CHECKLIST f
- 8. (C) Element / Step Verify the EDG output breaker on the selected 4.16 KV bus is open Standard:_ VERIFY the EDG output breaker on the selected 4.16 KV bus (2-20211)is OPEN Cue: GREEN LIGHT IS ON. REPORT UNIT 1 IS READY TO CROSSTIE AB 4.16 KV BUSES.
SAT UNSAT Comments: j ! 9. (C) Element / Step Close in the Unit 2 SBO breaker Standard: CLOSE IN the Unit 2 SBO breaker 2-20501. Cue: RED LIGHT ON
- SAT UNSAT Comments
- 10. (C) Element / Step Request the Unit 1 control room to close the Unit 1 SBO breaker Standard: REQUEST the Unit 1 control room to close the Unit 1 SBO breaker 1-20501.
Cue: UNIT 1 ACKNOWLEDGES REQUEST. SAT UNSAT _ l Comments: END Element / Step TERMINATION Standard: Student requests Unit 1 to close the Unit i SBO crosstie breaker. 0821129, Rev 02 Page 11 of 14 a
. - - - . . . - _ - . - . .- - ~
REVISION Nd,: PROCEDURE TrrLE: PAGE: , 15 APPENDlXES/ FIGURES / TABLES ^ 1 PR CEDURE NOJ 73 of 117 ' EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 1 of 11) /R15A
' INITIAL
- 1. Establish communications with Unit 1 via Gai-Tronics or plant radio (if available).
- 2. To bring AC power from Unit 1 to Unit 2 via the SBO crosstie bus:
NOTE Selection should be based on eqt'pment availability necessary to stabilize the RCS, i.e., if the 2A Charging Pump is out of service, the 2B3 4.16 KV Bus should be considered, or the electrical train LEAST likely to be restored by either offsite power or EDG. Due to 10 CFR 50 Appendix R considerations, the 'A' side is preferable. A. Select the 4.16 KV vital bus to be energized on Unit 2. Circle selected bus: 2A3 2B3 B. Place the following pump switches in the PULL TO LOCK position: 2A ICW Pump 2B ICW Pump 2C ICW Pump 2A CCW Pump /R15A 2B CCW Pump' /R15A 2C CCW Pump . /R15A C. Perform the following steps:
- 1. Ensure Table 7, " Vital Power Breaker Configuration /
Station Blackout" of 2-EOP-99 has been completed. -
- 2. Verify the EDG output breaker on the selected 4.16 KV bus is OPEN 2-20211 (2-20401).
(Continued on Next Page) 4
REVISloN No.: PROCEDURE TITLE: . PAGE: f7 15 APPENDIXES / FIGURES / TABLES PROCEDURE No" EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 2 of 11) /R15A i
- 2. (continued) INITIAL
)
C. (continued) CAUTION The following step will render a Unit 1 EDG inoperable. Refer to Unit 1 Technical Specifications 3.8.1.1 and 3.8.1.2.
- 3. If Un:t 1 will supply power from a 4.16 KV Transformer l (Auxiliary or Startup), Then disable the Unit 1 EDG associated !
with the Unit 14.16 KV Emergency Bus that will be crosstied to Unit 2 as follows:
- a. Disable the 1 A Emergency Diesel Generator as follows:
- 1. Place the 1 A Diesel Generator Start Control Norm / isolate switch in ISOLATE.
I
- 2. OPEN the Control Power knife switch.
OR
- b. Disable the 1B Emergency Diesel Generator as follows:
- 1. Place the 1B Diesel Generator Start Control Norm / isolate switch in ISOLATE.
- 2. OPEN the C'ontrol Power knife switch.
I i I 1 I (Continued on Next Page)
REVISION No.: PROCEDURE TITLE: PAGE: 15 APPENDlXES/ FIGURES / TABLES PR CEWRE Noa 75 of 117 EMERGENCY OPERATING PROCEDURE 2-EOP 99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 3 of 11) /R15A
- 2. (continued) INITIAL NOTE if SBO crosstie from Unit 1 is unavailable or is NOT successful in subsequent steps, consider crosstie from Unit 1 per 2-EOP-99, Appendix F, "Altemate Method of Crosstying Unit 1 Diesel or Startup Transformer to Unit 2."
D. When the Unit 1 Control Room is ready to crosstle AB 4.16 KV Buses, Then CLOSE in the Unit 2 SBO Breaker (2-20501). E. Request the Unit 1 Control Room to CLOSE the Unit 1 SBO Breaker (1-20501) F. Place the RTGB control switches on the selected 4.16 KV vital bus for the HPSI, LPSI, CS and AFW pumps in the OFF position. ' NOTE [f 2C AFW Pump is NOT available, Then feedwater must be restored using a motor driven AFW pump as soon as a vital 4.16 KV bus is restored.
- G. Align the selected 2A3 or (2B3) 4.16 KV vital bus'to the 2AB 4.16 KV Bus by closing 2-20208 and 2-20505 or (2-20409) and (2-20504). Verify proper bus voltage on the selected vital bus.
, (Continued on Next Page) 3 s - ! 3 i
REMSION No.: @AOCEDURE TITLE: PAGE: 4 15 APPENDIXES / FIGURES / TABLES PRCCEDURE No.: W8E Y OPEMTM PEGNE i 2-EOP-99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2
- (Page 4 of 11) /R15A
- 2. (continued) l NOTE Up to this point, this appendix has one 4.16 KV Emergency Bus energized from Unit 1 via both units' AB 4.16 KV Buses. It may be energized by the only operating EDG on plant site, thus limiting the load capability available for use on Unit 2. Close coordination between the units is required to
, prevent exceeding the operating EDG maximum loading. Refer to Table 11, " Emergency Diesel Generator Loading (SBO)," load list of 2-EOP-99 as necessary. H. If the power source from Unit 1 is from the only operating EDG on plant site, Then GO TO Step 3. I. g the power source from Unit 1 is one of two operating EDGs, Then GO TO Step 4. 1 J. H the power source from Unit 1 is a 4.16 KV Transformer (Auxiliary or Startup), Then GO TO Step 5. INITIAL i
- 3. Hine Unit 1 EDG energizing the Unit 2 vital 4.16 KV bus is the !
only operatin.g EDG on plant site, Then restore loads as follows: l 1 CAUTION Notify the Unit.1 Control Room to monitor the operating diesel. H the loading causes bus load instabilities, Then Unit 2 480V L.C. feeder breakers and 4.16 KV loads may be tripped to protect the diesel. i Maximum loading on the SBO (2AB 4.16 KV), bus is 550 continuous amps, as indicated on AM 942 on RTGB 101.'
~
A. Tum the RCP oil lift pump switches to the OFF position. B. Have Unit 1 verify the crosstied EDG is canying less than or equal to 2500 KW load. (Continued on Next Page) a
REVISION NO.: PROCEDURE Tm.E: PAGE: - 1 15 APPENDIXES / FIGURES / TABLES PR cEDURE NOJ EMERGENCY OPERATING PROCEDURE
- 2-EOP-99 ST. LUCIE UNIT 2 4 2 APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 5 of 11) /R15A
- 3. (continued) _ INITIAL C. Energize the 2A2 or (2B2) 480V L.C. powered by the selected 4.16 KV vital bus by closincj or ensuring CLOSED the following:
2A2 20213," Station Service Transformer Feeder 2A2' and 2-40219, '480V 2A2 L.C. Feeder." 4 OR 2B2 - (2-20402, ' Station Service Transformer Fee der 285' , and 2-40503, "480V 2B2 L.C. Feeder.") D. Ensure all containment fan coolers are stopped. E. Start the 2A or 2B Charging Pump and initiate seal injection if available. CAUTION Additional charging pumps operation may exceed diesel / bus loading capacity.
~
F. If the 2C Charging Pump is required for operation, Then:
- 1. CLOSE Bkr. 2-40220, " Feed to 480V Vital Load Center 2AB' and CLOSE Bkr. 2-40702, " Supply from 480V Vital L.C.'2A2."
OR (CLOSE Bkr. 2-40504, " Feed to 480V Vital L.C. 2AB" and CLOSE Bkr. 2-40706, " Supply from 480V Vital L.C. 282.')
- 2. Start the 2C Charging Pump, if it did NOT auto start.
(Continued on Next Page)
REVISloN No.: PROCEDURE TITLE: ) PAGE: a i 15 APPENDIXES / FIGURES / TABLES PPOCEDURE NO,: 78 of 117 Y OPEWM P%GNE
- 2-EOP-99 ST. LUCIE UNIT 2
, APPENDIX V
' SBO CROSSTIE FROM UNIT 1 TO UhiY 2 (Page 6 of 11) /R15A
- 3. (continued) ,
INITIAL 1 G. Energize the 2A5 or (2B5) 480V L.C. powered by the selected 4.16 KV vital bus by ensuring CLOSED:
)
2A5 20210, "480V L.C. Station Service Transformer 2AS" and 2-40361, " Feeder from Station Service Transformer ) 2A5." OR 285 - (2-20402, "480V L.C. Station Service Transformer 2B5" and 2-40653, " Feeder from Station Service Transformer 285.") H. Exit this Appendix. l
~
NOTE The following actions will energize the 2A2 and 2A5, or 282 and 285 480V L.C.s and subordinate MCCs. Loads will sequence on bus per LOOP load sequence within 35 seconds following the closure of the 480V L.C. feeder breaker. Refer to Table 11, " Emergency Diesel Generator Loading l
- (SBO)", load list of 2-EOP-99 as necessary.
4
- 4. H two Unit 1 EDGs are running and one EDG is being' used to supply Unit 2, Then restore loads as follows:
s CAUTION ' Notify the Unit 1 Control Room to monitor the operating diesel. H the , l loading causes bus load instabilities, Then Unit 2 480V L.C. feeder breakers and 4.16 KV loads may be tripped td' protect the diesel. Maximum loading on the SBO (2AB 4.16 KV) bus is 550 continuous amps, as indicated on AM 942 on RTGB 101. , A. Tum the RCP oil lift pump switches to the OFF position. (Continued on Next Page)
. _ _ . _ _ . _ _ _ _ _ _ _m REVISloN NO.: PROCEDURE TITLE: PAGE: - -+-
15 ~ ~.' 1 APPENDIXES /FlGURESTTABLES ! PR CEDURE Noa 79 of 117 EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2 a -
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 7 of 11) /R15A
- 4. (continued) INITIAL i
B. Have Unit 1 verify the crosstied EDG is carrying less than or equal to 2500 KW load. , C. Energize the 2A2 or (2B2) 480V L.C. powered by the selected
- 4.16 KV vital bus by closing or ensuring CLOSED
i i 2A2 20213, " Station Service Transformer Feeder 2A2" and 2-40219, "480V 2A2 L.C. Feeder." , OR 282 - (2-40402, " Station Service Transformer Feeder 285" and 2-40503, "480V 2B2 L.C. Feeder.") D. Energize the 2A5 or (285) 480V L.C. powered by the selected 4.16 KV vital bus by closing or ensuring CLOSED: l 2A5 20210, "480V L.C. Station Service Transformer 2A5" and 2-40361, " Feeder from Station Service i Transformer 2AS." OR 285 - (2-20402, "480V L.C. Station Service Transformer
- 2B5" and 2-40653, " Feeder from Station Service Transformer 285.")
E. Ensure all containment fan coolers are stopped. F. Start the 2A or 2B Charging Pump and initiate seal-injection if available. i (Continued on Next Page)
REVISION NO.: PROCEDURE TITLE: PAGE: h ~' 15 APPENDIXES / FIGURES / TABLES - PR EWRE NO" EMERGENCY OPERATING PROCEDURE 2 EOP-99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 8 of 11) /R15A
- 4. (continued) INITIAL G. If the 2C Charging Pump is required for operation, Then:
- 1. CLOSE Bkr. 2-40220, ' Feed to 480V Vital Load Center 2AB" and CLOSE Bkr. 2-40702, " Supply from 480V Vital L.C. 2A2."
OR (CLOSE Bkr. 2-40504, " Feed to 480V Vital L.C. 2AB" and CLOSE Bkr. 2-40706, " Supply from 480V Vital L.C. 282.")
- 2. Start the 2C Charging Pump, if it did NOT auto start.
H. Start an available ICW pump.
- l. Start an available CCW pump.
CAUTION l I Additional equipment operation may exceed dies J. Start HPSI, LPSI, CS, and AFW pumps as _necessary. K. Exit this Appendix. 1 1 l l
REVIStoN NO.: PROCEDURE TITLE: PAGE: y 15 APPENDIXES / FIGURES / TABLES PR cEwRE n " 81 of 117 EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2
, APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 9 of 11) /R15A NOTE The following actions will energize the 2A2 and 2AS, or 282 and 285 480V L.C.s and subordinate MCCs. Loads will sequence on bus per LOOP load sequence within 35 seconds following the closure of the 480V L.C. feeder breaker. Refer to Table 11, " Emergency Diesel Generator Loading (SBO)," load list of 2-EOP-99 as necessary.
- 5. If a Unit 14.16 KV Transformer (Auxiliary or Startup) is being used to supply power to Unit 2, Then restore loads as follows:
CAUTION Maximum loading on the SBO (2AB 4.16 KV) Bus is 550 continuous amps, as indicated on AM 942 on RTGB 101. INITIAL A. Tum the RCP oillift pump switches to the off position. B. Energize the 2A2 or (2B2) 480V L.C. powered by the selected 4.16 KV vital bus by closing or ensuring CLOSED: 2A2 20213, " Station Service Transformer Feeder 2A2' i and 2-40219, "480V 2A2 L.C. Feeder..' OR 2B2 - (2-40402, " Station. Service Transformer Feeder 2B5" and 2-40503, "480V 2B2 L.C. Feeder.") l (Continued on Next Page) l l
REVISION NO.: PROCEDURE TITLE: .:, PAGE:
- 15 '
APPENDIXES / FIGURES / TABLES Ps cEouaEN " 82 of 117 ' EMERGENCY OPERATING PROCEDURE 2 EOP-99 ST. LUCIE UNIT 2 . i APPENDIX V SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 10 of 11) /R15A
- 5. (continued) INITIAL
$ C. Energize the 2A5 or (285) 480V L.C. powered by the selected 4.16 KV vital bus by closing or ensuring CLOSED: 2A5 20210, "480V L.C. Station Service Transformer 2A5" and 2-40361, " Feeder from Station Service Transformer 2A5." OR 285 - (2-20402, "480V L.C. Station Service Transformer 2B5" and 2-40653, " Feeder from Station Service Transformer 2B5.")
- D. Ensure all containrnent far coolers are stopped.
E. Start the 2A or 2B Charging Pump and initiate seal injection if available. , F. If the 2C Charging Pump is required for operation, Then:
- 1. CLOSE Bkr. 2-40220, " Feed to 480V Vital Load Center 2AB" and CLOSE Bkr. 2-40702, " Supply from 480V Vital
- L.C. 2A2."
~ OR ! i (CLOSE Bkr. 2-40504, " Feed to 480V Vital L.C. 2AB" and CLOSE Bkr.2-40706,t" Supply from 480V Vital L.C. 2B2.")
- 2. Start the 2C Charging Pump, if it did NOT auto start.
G. Start an available ICW pump. H. Start an available CCW pump, (Continued on Next Page)
REVISION NO.: PROCEDURE TITLE: PAGE: 15 APPENDIXES / FIGURES / TABLES - EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2 l
, APPENDIX V l i
SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 11 of 11) /R15A !
- 5. (continued) . INITIAL l
1 CAUTION Additional equipment operation may exceed bus loading capacity. l ]
- 1. Start HPSI, LPSI, CS and AFW pumps as necessary.
1 END OF APPENDlX V i l I 1 b
I REVIStoN NO.: PROCEDURE TITLE: PAGE: 15 APPENDIXES /FIGURESTTABLES PR EDURE NO" EMERGENCY OPERATING PROCEDURE 2-EOP-99 ST. LUCIE UNIT 2 TABLE 7 M* VITAL POWER BREAKER CONFIGURATION / STATION BLACKOUM , (Page 1 of 2) ~-
- l A TRAIN V B 17iiin,7 r
- 1. OPEN and green flag the following startup transformer breakers:
A. S.U. Transformer 2A (28) 2-30102 (2-30202)
- 8. S.U. Transformer 2A (28) 2-20102 (2-20302)
- 2. Ensure the following breakers are green flagged and OPEN:
A. Aux Tr.ansformer 2A (2B) 2-30101 (2-30201) (2W87) (2W85) B. Aux Transformer 2A (28) 2-20101 (2-20301) (1W86) (1W84) C. Tie breakers between normal and emergency 4160V buses 4.16 KV Bus Tie 2A2 - 2A3 2-20109 4.16 KV Bus Tie 2A3 - 2A2 2-20209 4.16 KV Bus Tie 2B2 - 283 (2-20309) 4.16 KV Bus Tie 283 - 2B2 . (2-20411) D. 4.16 KV Bus 2AB Tie Breakers Feed to 4.16 KV Bus 2AB 2-20208 incoming feeder from 4.16 KV Bus 2A3 2-20505 Incoming Feeder from 4.16 KV Bus 283 (2-20504) Feed to 4.16 KV Bus 2AB (2-20409) (Continued on Next Page) -
REVISION NO.: DROCEDURE TrrLE: PAGE: 15 APPENDIXES / FIGURES / TABLES EMERGENCY OPERATING PROCEDURE j 2-EOP-99 ST. LUCIE UNIT 2 TABLE 7 g' VITAL POWER BREAKER CONFIGURATION / STATION BLACKOutw (Page 2 of 2) j A TRAIN V B ,
- 3. OPEN the following 4.16 KV feeder breakers to the station service transformers.
Station Service Transformer 2A1 2-20110 Station Senice Transformer 2A5 2-20210 Station Senice Transformer 2A2 2-20213 Station Senice Transformer 2B1 (2-20310) Station Senice Transformer 2B2/285 (2-20402)
- 4. OPEN and green flag the following 480V feeder breakers from the station service transformers.
480V Bus 2A1 Feeder 2-40103 480V Bus 2A5 Feeder 2-40361 480V Bus 2A2 Feeder 2-40219 480V Bus 2B1 Feeder (2-40419) 480V Bus 285 Feeder (2-40653) 480V Bus 2B2 Feeder (2-40503)
- 5. OPEN the following 480V bus tie breakers 480V Bus Tie 2A2-2AB 2-40220 480V Bus Tie 2AB-2A2 2-40702 480V Bus Tie 2AB-2B2 (2-40706) 480V Bus Tie 2B2-2AB (2-40504)
END OF TABLE 7 i I l
l REVISION NO.: PROCEDURE TITLE: PAGE-15 APPENDIXES / FIGURES / TABLES EMERGENCY OPERATING PROCEDURE l 2-EOP-99 ST. LUCIE UNIT 2 - APPENDIX V .7 SBO CROSSTIE FROM UNIT 1 TO UNIT 2 (Page 1 of 10) j
! l
- 1. Establish communications with Unit 1 via Gai-Tronics or plant radio (if available).
- 2. To bring AC power from Unit 1 to Unit 2 via the SBO crosstie bus:
NOTE Selection should be based on equipment availability necessary to stabilize the RCS, i.e., if the 2A Charging Pump is out of service, the 283 4.16 KV Bus should be considered, or the electrical train LEAST likely to be restored by either offsite power or EDG. Due to 10 CFR 50 Appendix R considerations, the 'A' side is preferable. A. Select the 4.16 KV vital bus to be energized on Unit 2. Circle selected bus: 2A3 2B3 B. Place the following pump switches in the PULL TO LOCK position: 2A ICW Pump 2A CCW Pump 2B ICW Pump 2B CCW Pump 2C ICW Pump 2C CCW Pump - C. Perform the following steps:
- 1. Ensure Table 7, " Vital Power Breaker Configuration /
Station Blackout" of 2-EOP-99 has been completed.
- 2. Verify the EDG output breaker on the sslected 4.16 KV bus is OPEN 2-20211 (2-20401).
i
=
l (Continued on Next Page) - i i
! JOB PERFORMANCE MEASURE .i Knowledge Questions i Question #1. KA: 062A1.03 ImportancegB .8 y{d cwy & W (2arpr~ kbh' We k i
Reference:
Qone
- Question:dhiien 480 V LC-2AB is deenergizedeths Charging Pump suciLnn pe+h "'"! chift to the
, -RWIwithout operciar lritervention. Expiain wh7tnis occurs?- i Expected Response: Deenergizing 480 V LC 2AB results in the VCT Level circuitry . t deenergizing. The VCT Level circuit's " low-low level" interlock then swaps the VCT suction path from the VCT to the RWT. ? SAT UNSAT ! Comments: Question # 2. pgo / be d2'A b - (p 4 M-. N M 2 gg KA: 062A2.06 Importance: 3.4/3.9 m coes# 8 0 lbrou f Y' Yb h *
Reference:
None p ver & GV Question: Or)/ nit U 2, what' interlock norrrially prevents't s; tying oyA2'and 2B280L Load Centers gh'the 2ABgV' Load Center? U Expected Response:The Unit 2 2A2 and 2B2 480 V Load Centers can not be cross-tied through the 2AB 480 V Load Center due to the mechanicalkeyinterlocks on the 2AB to 2A2 (2h and the 2AB to 2B2 (2-40706)_ control switches of RTGB 201. g cfddf ' NOTE: THE MECHANICAL KEY INTERLOCK IS BACKED-UP BY ELECTRICAL INTERLOCKS BETWEEN 2AB - 2A2 (2-40702) AND 2AB - 2B2 (2-40706). SAT UNSAT Comments: 1 0821129. nev 02 Page 12 of 14 4
~ -
JOB PERFORMANCE MEASURE When 480 V LC-2AB is deenergized, the Charging Pump suction path will shift to the RWT without operator intervention. Explain why this occurs? 0821129. Rev 02 Page 13 of 14
JOB PERFORMANCE MEASURE On Unit 2, what interlock normally prevents the cross-tying of the 2A2 and 282 480 V Load Centers through the 2AB 480 V Load Center? 0821129, Rev 02 Page 14 of 14 l
JOB PERFORMANCE MEASURE Verification of Completion Trainee: Trainee's Department: ! Evaluator: Please Print JPM
Title:
RESTORE POWER TO 2A3 4160 SWITCHGEAR VIA SBO CROSSTIE JPM Number: 0821129, Rev 02 INDICATE TESTING METHOD: Perform Simulate _ Ouestions Asked: Question #: SAT / UNSAT Question #: SAT / UNSAT Actual Time to Complete JPM: Start Time Stop Time The trainee's performance was evaluated against the standards contained in this JPM and determined to be: SATISFACTORY UNSATISFACTORY Trainee's Signature: Date: Evaluator's Signature- Date: l Reason,if unsatisfactory: Provide this page to the Trainee Page 15
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i JOB PERFORMANCE MEASURE 1 Initial Conditions: A Station Blackout has occurred on Unit 2. Unit 1 is in a LOOP with both i Emergency Diesel Generators in service. The NPS and ANPS have ! determined the need to crosstie electrical power from the 1 A EDG to the 2A3 4.16 KV switchgear via the SBO AB Bus Crosstie. Initiating Cue: The ANPS has directed you to accomplish the Unit to Unit crosstie to the 2A3 4.16 KV Bus by performing 2-EOP-99, Table 7 and then 2-EOP-99, App. V within 10 minutes. l I PNe 16
JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP 0821129
- 1. RESTORE 1C-48.
- 2. UNFREEZE and run the simulator for a few minutes.
- 3. FREEZE the simulator.
- 4. No lesson is necessary for this JPM.
- 5. UNFREEZE and run the simulator when ready to start the JPM.
0821129 Rev02 Page 17 a l i a
This JPM Fo C Exam Use FPL St Lucie Nuclear Plant Licensed Operator Training Program Job Performance Measure ESTABLISH ONCE-THROUGH-COOLING UNIT 2 0821037a, Rev 02 SUCCESSFUL COMPLETION REQUIRES THAT ALL CRITICAL STEPS BE PERFORMED Job Applicability. RO, SRO System: Emergency Core Cooling System Safety Function: 002
Reference:
2-EOP-15, Sec 5.6, path 4, Rev.14 Task: Adjust HPSI Flow, Manually initiate Safety injection Developed / Revised by: Tim Bolander / Approved by Training Supervision: / Examiner; / Prior to use, ensura referenced procedures are current revisions; if not, verify JPM is in accordance with current revision. t
JOB PERFORMANCE MEASURE Department: Operations Task
Title:
ESTABLISH ONCE-THROUGH-COOLING UNIT 2 JPM No.: 0821037a, Rev 02 Trainee: Evaluator: An X below indicates the applicable method (s) of testing that may be used: Perform Simulate Estimated Time to Complete the JPM: 15 Minutes Location of Performance: CONTROL ROOM UNIT 2/ SIMULATOR Notes to the Evaluator: Pull the latest controlled copy of the applicable procedure The next to last page of this JPM lists the initial conditions and initiating cue. Tear that page off and give it to the trainee. Notify a Management Observer of the observation opportunity. i j i
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