ML20211J366
| ML20211J366 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/13/1987 |
| From: | Bill Dean, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20211J047 | List: |
| References | |
| 50-327-OL-86-03, 50-327-OL-86-3, NUDOCS 8702260423 | |
| Download: ML20211J366 (107) | |
Text
{{#Wiki_filter:. UNITED STATES [piac, 'o o NUCLEAR REGULATORY COMMISSION y" o REGION li g j 101 MARIETTA STREET.N.W.
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ENCLOSURE 1 EXAMINATION REPORT 327/0L-86-03 Facility Licensee: Tennessee Valley Authority Facility Name: Sequoyah Nuclear Plant Facility Docket No.: 50-327 Written and simulator examinations were administered at Sequoyah Nuclear Plant near Soddy-Daisy, Tenness'ee. /' ~ Chief Examiner: Willi-b/l M. Dean
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[7 ~ ~ .-2 //$ @ Date Signed Approved by: KL John F. Munro, 9 ction Chief dhh/
/ Date Signed Summary:
Examinations on December 15-18, 1986 Written and simulator examinations were administered to 4 licensed reactor operators (RO) and 8 senior reactor operators (SRO). Based on the results of these examinations, 1 of 4 R0s and 7 of 8 SR0s passed. e702260423 870210 PDR ADOCK 05000327 V PDR
REPORT DETAILS
- 1. Facility Employees Contacted:
*P. R. Wallace, Plant Manager
*L. M. Nobles, Plant Superintendent
*C. H. Noe, Chief, Operator Training
*C. O. Brewer, Operations Training Manager
- Attended Exit Meeting
- 2. Examiners: -
*W. M. Dean D. J. Nelson L. L. Lawyer _
C. Shiraki (llQ) J. Whittemore (RIV)
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided your training staff with a copy of the written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 3 to this report, and the NRC Resolutions to these comments are listed below,
- a. R0 Requal Examination (applicable SR0 questions in parenthesis)
- 1. Question 1.01(5.01)
! Comment accepted. Original answer key responses based on actual power vs. instrument vice instrument vs. actual power as stated in l the question, i
- 2. Question 1.03 (5.03)
Comment accepted. Typographical error in the answer key will be corrected.
- 3. Question 1.07 I
Comment accepted. Note that curves provided by utility showing temperature and doppler defects for cycle 4 core were not provided with original material sent to the NRC.
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- 4. Question 1.09 Recommended answer is equivalent to existing answer key. No change required.
- 5. Question 1.10(5.08)
Comment accepted. Question did not delineate between fast and thermal fission. The recommended additional answer will also be accepted with same tolerances as original answer key.
- 6. Question 2.03 H2 recombiners are referred to in FR-Z.1, " Response to High Containment Pressure" and in 501-8.3.1, " Containment H2 Recombiner System" for mitigation of excessive containment hydrogen concen-tration. Requalification examinations should be based primarily on requalification training material, per ES-601 of NUREG 1021, however, material considered pertinent to requisite operator knowledge is also appropriate as a source of information for examination questions. Due to the rei ttively low KA value (2.6) and the fact that Sequoyah has no requalification learning 4
objectives nor lesson plans for hydrogen recombiners (though they should if they are still an applicable system) the question is deleted.
- 7. Question 2.04 Comment accepted. Based on additional material provided by the tacility, recommended additional answers will also be accepted.
Lesson plan should be modified to reflect this information.
- 8. Question 2.06 Comment accepted. Based on information contained in Technical Specifications, the band for part c will be 1185-1285 psig.
l 9. Question 2.09 l Comment accepted. Recent changes to A01-3B are not reflected in the referenced system description. As there are no other ECCS related components removed from service, and the question asks for 4 responses, the candidates will not be penalized for listing the two components which are removed from service, but not necessarily tagged out.
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- 10. Question 2.11 (6.11)
The order of elements in the Air Cleanup Units is considered important to the overall effective operation of these accident mitigating components. However, based on facility supplied drawing, the electric heating element will be removed from the answer key. System description should be changed to reflect the
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actual plant conditions.
- 11. Question 3.03 Comment . accepted. Based on additional reference material provided, recommended answer will be accepted. System description should be changed to reflect this additional alarm.
- 12. Question 3.05 Comment accepted. Confusing wording in facility's system description resulted in erroneous answer key.
- 13. Question 3.07 (6.06)
Comment accepted. Based on system drawing provided, recommended answers will be accepted.
- 14. Question 3.10 (6.07)
Comment accepted. Based on system drawings provided by facility demonstrating an EDG lockout will not occur, question is deleted.
- 15. Question 4.05 (7.04)
Comment accepted. Question symbology could have confused candidates into responding to "2 out of 4" vice " numbers 2 and 4" S/Gs.
- 16. Question 4.10 Comment accepted. Additional recommended answer will be accepted.
- 17. Question 4.15 (7.12)
Coment accepted. Based on additional material provided, recommended answer will be accepted as 1 of 2 correct answers.
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- b. SR0 Requal Examination
- 1. Question 5.05 Comment not accepted. The question states use of a E0L critical boron concentration vice a BOL boron concentration. Typically, these values are different by hundreds of ppm.
- 2. Question 5.11 Recommended answers are equivalent to existing answer key. No change to answer key is required.
- 3. Question 6.04 Recommended answer is equivalent to existing answer key. No change required.
- 4. Question 7.08 Comment accepted. Even though fuel movement less than 100 hours is discussed in the referenced procedures, it is agreed that this answer may not be elicited as such an occurrence would not be feasible based on Technical Specification requirements.
Reasonable third answers will be accepted in lieu of this response.
- 5. Question 7.13 Comment not accepted. A key factor discussed in the Westinghouse Background Information for FR-H.1 " Response to Loss of Secondary Heat Sink", is the effectiveness of the energy removal of the PORVs during bleed and feed procedures . Though the specific phrase given in the answer key is not identically stated, this is a well known phenomenon discussed in Westinghouse accident analysis.
An additional answer that will be accepted, as stated on page 55 of the above reference is " higher pressure produced by RCP operation will reduce SI flow and increase inventory lost through the PORVs".
- 6. Question 8.03 Comment accepted. Question should have said "only plant Health Physicist" to elicit response in answer key. Answer will be changed as recommended.
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- c. Post Examination Review In addition to the changes made to the answer key due to facility comments, post examination review resulted in minor technical or administrative changes to questions 1.05(5.04), 2.12(6.13), 6.12, 7.07, and 8.14 in order to ensure the answer key reflects the response elicited by the questions.
- 4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. The submittal by the facility of some inadequate training material to the NRC was addressed. Fifty percent (9 of 18) of the changes made to the answer keys were a direct result of incomplete or insufficient training material. It was determined that training material presented to personnel prior to their pre-licensing training would, in selected instances, be suitable for submittal of material used in examination development. Additionally, a complete set of system drawings and logic prints should be made available to the examiners to supplement the system descriptions typically provided.
The cooperation given to the examiners and the effort to ensure an atmos-phere in the control room conducive to oral examinations was also noted and appreciated. The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
F gC' U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: _SEQUgYAH_1h2____________ REACTOR TYPE: _PWR-WEGd________________ DATE ADMINISTERED: _@bfigflg________________ EXAMINER: _ DEAN2 _W M_______________ CANDIDATE: _________________________ INSIBUCI19NS_IQ_CONDID8IE1 Read the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__VOLUE_ _IgI66 ___SCOBE___ _y86UE__ ______________C81EGQBY_____________ 75 u___I___ 2Ez1Z ___________ ________
- 1. PRIt(CIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
( .2 $' ___z_2__ _23298 ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS ' I C- 3 INSTRUMENTS AND CONTROLS i _49xtr__ 2Ez1Z ___________ ________ 3. f t } ')I PROCEDURES - NORMAL, ABNORMAL, _terrg__ _;5,1Z ___________ ________ 4. EMERGENCY AND RADIOLOGICAL CONTROL h M_ ___________ Totals I Final Grade l i i All work done on this examit 3 tion is my own. I have neither given nor received aid. Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: )
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must_ avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or-dark pencil ggly to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a gew page, write gn)y 90 goe sidg of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least tht ee lines between each answer.
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- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Ose abbreviations only if they are commonly used in facility litgcatute.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE DUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the e>2ami net onl y.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination hac been completed.
- 18. When you complete your ex ami nat i on , you shall:
- a. Assemble your e:: ami n at i on as follows:
(1) Exam questions on top. (2) E>:am ai ds - figures, tables, etc. (3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
Iz__EBINCIELED_9E_NUG6E88_EgWEB_E6@NI_9EEBGllgN, PAGE 2 IUEBd99XN801GS2_UE81_IB8NSEEB_6UD_ELU19_E69W OUESTION 1.01 (1.50) Indicate whether the f ollowing will cause the power r ange . i nstrument to be indicating HIGHER, LOWER or the SAME as actual power, if the instrument has been adjusted to 100% based on a calculated calorimetric. 1
- a. If the feedwater temperature used in the calorimetric was higher than actual feedwater temperature.
- b. If the reactor coolant pump heat input used in the calorimetric is omitted.
- c. If the steam flow used in the calorimetric was lower than actual.
QUESTION 1.02 (1.00) The reactor is critical at 10,000 cps when a S/G PORV fails open. Assuming BOL conditions, no rod motion, and no reactor trip, choose the answer below that best describes the values of Tavg and nuclear power for the resulting new steady state. (POAH = point.of adding heat).
- a. Final Tavg greater than initial Tavg, Final power above POAH. g
- b. Final Tavg greater than initial Tavg,' Final power at POAH.
- c. Final Tavg less than initial Tavg, Final power at PDAH.
- d. Final Tavg less than initial Tavg, Final power above POAH.
QUESTION 1.03 (1.00) Attached Figure # 219 shows a power history and four possible xenon traces (reactivity vs time). Select (a, b, c, or d) the curve that correctly displays the cupected xenon transient for the given power history. (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1x-_EBINglELES_gE_UyCLEGB_EQWEB_E6@NI_gEEB911gN 2 PAGE 3 ISEBdgpyy801CS _UE81_IB8NSEEB_@UQ_E691g_E6gW 3 OUESTION 1.04 (1.00) Which of the f ollowing correctly describes the projected changes in the worth of the Control Banks during cycle 4? BANK A BANK B BANK C BANK D
- a. Constant Constant Increase Increase
- b. Decrease Increase Increase Constant
- c. Constant Decrease Increase Constant
- d. Increase Increase Increase Increase
- e. Increase Increase Constant Decrease OUESTION 1.05 (1.00)
For the Cycle 4 core, what is the main core design reason that the pellet swell and clad creep effects override the Pu-240 buildup /U-238 depletion effects and make the Doppler Only Power Coefficient less negative? DUESTION 1.06 (1.00) Unit A is at EOL while Unit B has just been started up after a refueling. Assuming a rod speed of 48 spm, both reactors s are taken critical by pulling in 50 step increments and waiting 60 seconds before pulling again. Assuming all systems and parameters are identical at the commencement of the startup, and both units are initially shutdown by 2% (delta k/k): a) Which Unit will have the highest source range counts when criticality is reached? b) How will critical rod heights compare in the two Units? l OUESTION 1.07 Ei . D T (0.T) a) Wt , c h,pcuNG cK_1 ash 15P-ec1TtMN c L? M b) What is the major cause of the existence of a void defect? i 9 (*+*** CATEGORY 01 CONT INUED ON NEXT PAGE + * * * +)
it__EBINQ1ELES_QE_ NUCLE 88_EQWEB_EL8NI_QEEB811gN i PAGE 4
.IHEBdQDyNGdiggi_HE6I_ISBUSEEB_@NQ_ELylD_ELQW DUESTION 1.08 (1.50) a) Assuming a SBLOCA has occurred, what two FLUID FLOW related factors and what two HEAT TRANSFER related factors will dictate the behavior of RCS pressure? (1.0) b) What ~ is the driving force for the flow out of the break? (0.5)
OUESTION 1.09 (1.00) List the four most significant causes of Non-condensible gas formation in the RCS during the first hour following a LOCA. Assume the PZR empties after several minutes and forced convection flow is not available. Also, pressure does not drop to a level requiring any SI tank to inject and f uel rods have not ruptured. I l QUESTION 1.10 (1.50) } List the three main sources of fission neutrons in the core at end of life and indicate their approximate contribution (in %) to power. s I OUESTION 1.11 (2.00)
- a. During natural circulation, EXPLAIN how it is possible to f orm a bubble '
. in the reactor vessel head when indications show that the RCS is l subc ool ed? l b. How will pressuriner level respond, (INCREASE, DECREASE, or REMAIN THE SAME) if the backup heaters are energized with a bubble in the reactor vessel head? Assume normal pressurarer level and briefly EXPLAIN your answer. l l QUESTION 1.12 (1.50) Attached is a typical boiling curve for water as it approaches, then i enceeds, the DNB point. What are the thermodynamic conditi ons that cause: a) The decrease in heat transfer rate in Region III? b) The increase i re heat transfer rate in Region IV? (****+ CATEGORY 01 CONTINUED ON NEXT PAGE +****) l
1:__EB10CIELEg_gE_ NUCLE 68_EQUEB_ELONI_QEEBGIlgy, ,- PAGE 5
- ISEB59DyyBMJCS3_dEGI_JBANSEEB_99p_E6UJD_ELgg -
QUESTION 1.13 (2.00) Using the attached drawings, explain why the parameters below e.,nibit the behavior represented on the graphs which show the response'to-a rapid 50% load decrease from rated power with rod control in AUTOMATIC and Steam Dumps to the Condence- UNAVAILABLE. Assume NO operator action. , ;;- a) Why does rod mot,i o,n stop at point 8? (.75)
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b) Why are there osci11ations in steam _ flow, feed flow and S/G 1 9' 01 at points 11-137 (1.25) h DUESTION 1.14 (1.00) The calculated shutdown margin is 10% delta k/h, assuming-the most reactive control rod worth is 1000 pcm. The Source Range cour,t rate is 50 cps.,, The Shutdown Banks' rod worth is 5600 pcm. Calculate tre final count rante " after the Shutdown Banks are fully withdrawn. Show all work. '.f
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S PAGE 6 _,( 2. PLANT 2ESIGN INCLUDING SAFETY _AND_ EMERGENCY _ SYSTEMS 4 - . .,q
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I/f' IL ' OUESTIOfJ 2.01 (1.00) a 7.< , OWhich pje of the following correctly describes the detector construction
-of a yarticulate, Gas, Iodine ( F'I G ) radiation monitor?
g* (. I- , a) l Otse scintillation detector utilizing three dif f erent -tiergy
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; [l bandwidths (windows) for sensitivity to different isotopes.
,1: a b) One scintillation detector utilizing two different energy.
'J bandwidths for particulate and Iodine detection and a GM tube for gasenus detection.
4 I c) Two separate scintillation detectors f or particulate and Iodine _ # detection and a GM tube for gaseous detection. yl, )
- d)d >Tryce separate scintillation detectors for EBCh monitored i ho -,g+ ioup of radio nuclides.
J a. l' i i I GkKSTION 2.02 (1.00)
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*- 't .', . .) h l RHF4 inleti.is61ation, valves 74-1 and 74-2 each have an independent RCS j pressure tp*hnsmitter associated with them. Which of the following l statesmentVdescribing the ef f ects of the transmitter associated with 74-1 f ailiE;f,9-
'high is correct?
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- a. If both 74-1 and 74-2 are open, they will shut.
- b. If open, 74-1 will shut and if closed, 74-2 will not be able to j be npened.
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rl If tyoth 74-1 and 74-2 are shut, nei ther one will be able to be j V opened. I j I f open, 74-1 will shut, but 74-2 can be positioned as desired.
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t ( e.f 74-1 can be positioned as desired by the operator, but 74-2 I will not be able to be opened if it is shut.
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2t__ELGUI_ DESIGN _lNCLUDIN@_@@ Eely _8ND_ EMERGENCY _SYSIEMS PAGE 7 DUESTIpN 2.03 (1.00)
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'Which of the follow 2ng-desc .s the basic flowpath through the Hydrogen Recombiners?
a.. Mixing chamber pre heater, recombination region '
- b. Mixing chamb- , recombination region, heater section
- c. Pre heater, recombination region, mixing chamber
- d. Pre heate , mixing chamber, recombination region
- e. Pre hea r, mixing chamber, heater section QUESTION 2.04 (2.00) a) For the f ollowing loads, indicate what combination of ERCW headers (1A, 1B, 2A and/or 2B) is the NORMAL source of cooling water:
- 1) CCS Heat Exchanger "C" 1
- 2) EDG Heat Excnanger 2A-A
- 3) Containment Spray Heat Exchanger 1B
'l< b) What 5 criteria / interlocks must be met for ERCW pump KA to auto start?
\
j -DUESTION 2.05 (2.00) L i. st the four AUTOMATIC trips of the AFW Terry Turbine trip and throttle
; valve and whether the trip has to be reset MANUALLY or NOT.
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; OUESTION 2.06 (1.00)
( , Provide the system pressures at which t u? 71 aing ECCS components will start to inject following a LOCA: (use e ite 4 stated in EOPs)
'.,, a) SI Pumps I
b) RHR pumps , c) Upper Head Injection 4
- S QUESTION 2'.07 (1.50) including applicable setpoints List the three interlocks for switchover to the Recirculation which must be met..
Mode of core cooling to occur. (**+++ CATEGORY O2 CONTINUED ON NCXT PAGE *****)
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2 2$_ELONI_ DESIGN _ INCLUDING _SOEgly_8ND_ EMERGENCY _Sy@IEd5 PAGE 8 QUESTION 2.08 (1.00) List the four locati ons f rom which the Post Accident Sampling System c,an draw samples. DUESTION 2.09 (1.00) What 4 different ECCS related components are tagged out at low pressures to help prevent inadvertant over pressurization at low temperatures? g DUESTION 2.10 (1.50) (
, Recent modifications to the S/G PORVs added manual operator extensions for remote operation of the valves on 2 S/Gs.
a) Which 2 S/Gs were affected by this modification? (0.5) b) What is the basis for this modification? (Include discussion of why only 2 S/G PORVs were modified) OUESTION 2.11 b g a) Describe the order of processing elements in the Air Cleanup Units through which air is drawn by the Air Cleanup Subsystem. 66e@+ (.f} T) b) How are the processing elements in an INACTIVE air cleanup unit loaded with radioactive materi al kept cool? (0.5) i Ot:ESTION 2.12 (1.50) l gd Describe the flow paths f or hot leg recirculation, from the recirculation sumps to the RCS. Identify major components and any valves which can be operated from the control room. (Use only the A Train) l i l l l l (**-*** CATEGORY O2 CONTINUED ON NEXT PAGE +++++) l
~ 2 __ELONI_DESIQU_lNCLUD10G_EGEEIY_@UD_EMEBGENCY_Sy@IEMS PAGE 9 DUESTION 2.13 (1.50) Provide the bases for the following precautions relating to turbine and generator operation during a plant startup: a) Operation at less than 5% rated load should be avcided. b) The main generator field should not be energized at less than 90% rated speed. c) EHC f l ui d should be > 70 degrees when starting an EHC pump. (****+ END OF CAlEGORY O2 +++**)
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3 t__IN@lBUMENIS_ONQ_CQN18QL@ QUESTION 3.01 (1.00) Which one of the following describes how the AFW system is prevented from feeding a faulted S/G7 a) Operator action is required to isolate AFW when a faulted S/G is detected. b) Pressure switches on the AFW discharge lines will automatically close the loop level control valves when low AFW discharge pressure is detected. c) Level transmitters on the S/G wide range level instrun ent will automatically close the loop level control valve when s low level is detected in a S/G. d) Flow transmitters on the AFW discharge lines will automatically close the loop level control valves when e::cessive flow is detected in AFW discharge piping. QUESTION 3.02 (1.00) Which one of the graphs in figure 603 correctly depicts the Pressurizer Pressure c trol system, Master Controller output signal, based upon the deman signal shown? g QU5STION 3.03 (1.25) Describe what happens to the coils associated with the CRDMs and what 2 alarms / indications actuate on an Urgent Failure of the rod control system. QUESTION 3.04 (1.50) Indicate whether the following situations will ARM ONLY, ARM AND ACTUATE or HAVE NO EFFECT on the steam dump system. a) 80% power, 7.5%/ min ramp decrease in turbine load for 3 minutes, Tavg> Tref by 7 degrees F, steam dumps in Tavg mode of cperation b) Hot Zero Power, Tavg=549 degrees F, steam dumps in STM PRESS mode with 1005 psig set into the steam pressure controles, steam dumps in Tavg mode, c) Turbine trip, Tavg=542 degrees, steam dumps in Tavq mode ,, (++++6 CATEGORY 03 CONTINUED ON NEXT PAGE *++++)
~ 3c__INSIBUMENIS_QND_CgNIBQLS PAGE 11 QUESTION 3.05 ( .50) TRUE or FALSE: If the upper detector on a power range NI fails low while at 75% power, the operation of the upper detector current comparator is defeated. DUESTION 3.06 (1.50) While at 100% power with rod control in automatic, the Turbine Impulse Channel supplying the rod control logic fails high. What is the effect on the following rod control system components? a) Variable Gain Unit b) Tavg-T r ef mismatch c) Rod speed QUESTION 3.07 (1.50) What 4 signals will automatically initiate the operation of the Auxiliary Building Gas Treatment System? OUESTION 3.08 (1.50) List ALL of the signal inputs to the OT Delta T trip point calculator. OLIESTION 3.09 (1.75) List ALL the Main Steam Isolation Signals and their setpoints. DUESTION 3.10 (1.50 An SI signal was generate due to a transient caused b: an undervoltage condition on the 2A-A e 9KV Bus. During this transient, the 2A CHG Pump breater steyed closed ~ausing an EDG lockout.(all other loads were removed) What 5 actions must he operator take to load equipment on that bus using the 2A-A EDG7 (***** CATEGORY 03 CONTINUED ON NEXT PAGE +**+*)
32__INSTBUdENIg_AND_CONIBOLS PAGE 12 OUESTION 3.11 (2.50) Describe all events / alarms that occur due to the following instrument failures until the reactor either trips or stabilizes. Assume no operator actions and all controls are in automatic. a) Pressurizer Level Reference Signal (Tavg) fails high while at 50% power. (0.75) b) Selected Secondary Pressurizer Level Control Channel signal fails low while at 70% power. (1.75) DUESTION 3.12 (1.00) Unit 1 is at 60% power with all controls in automatic, operating normally when Par Pressure protection Channel III is taken out of service for testing (all associated bistables are tripped). Subsequently, the upper detector for NI42 fails HIGH. What happens to the turbine? Explain your answer. QUESTION 3.13 (1.50) Describe the operation of the 6.9 VAC Emerge'ncy Bus Degraded Voltage Protection System. Include in your discussion coincidences, setpoints and any time delays that apply. 1 (***** END OF C Al EGDF(Y 03 +++++)
'41- EBgCgpuBgS_:_NQBM963_9BNgBM963_EMEBggNCY_9ND PAGE 13 889196991C66_C9 NIB 96 OUESTION 4.01 (1.00)
Which one of the f ollowing situations does NOT require emergency boration per ADI-34.A, " Emergency Boration"? a) One rod stuck in the fully' withdrawn position following a rx trip. b) ROD BANK D LOW LIMIT alarm actuates as rods are driving in automati cal l y, c) A steady, sustained increase in source range counts with keff=.95 with no rod motion or planned dilution in progress. d) RCS Tavg falls below 525 degrees at a rate of 30 degrees /hr after a reactor trip. (No manual cooldown in progress) DUESTION 4.02 (1.00) Which one of the following conditions are the correct MINIMUM requirements for starting "B" RHR pump while swapping RHR pumps during normal MODE 5 operations? Pump A status RCS. Level a) On 695' y b) Off 695' c) On 695' 6" d) Off 695' 6" e) On 696' t DUESTION 4.03 (1.00) I Which one of the following is addressed in FR-Z.2, " Containment Flooding", as a potential source of excessively high containment sump levels? I l a) Condensed steam from a steam break b) RCS water from a LOCA c) RWST l d) Accumulators i e) CCW l l l l l l (*++++ CATEGORY 04 CONTINUED ON NEXT P AGE + + + * + )
r 42__EBgCEDUBgS_;_NQBU663_6BNgBd86,_EdEBGENCy_9Ng PAGE 14
- 86DJ969GICe6_CgNIBg6 OUESTION 4.04 (1.00)
-Which one of the following statements correctly describes the use of NOTES and CAUTIONS in an EOP?
a) BOTH Notes and Cautions apply ONLY to the step which they precede-(Unless otherwise stated in the Note / Caution). b) Notes apply ONLY to the step they precede, whereas Cautions apply to ALL subsequent steps (Unless otherwise stated in the Note / Caution). c) Notes apply to ALL the steps they precede, whereas Cautions ONLY apply to the step they precede (Unless otherwise stated in the Note / Caution), d) Notes and Cautions apply to ALL steps which they precede (Unless otherwise stated in the Note / Caution). QUESTION 4.05 (1.00) The loss of which one of the following 125 VDC Vital Battery Boards will cause a reactor trip and also number 2/4 S/G NSIVs and main feed regulating bypass valves to close? a) Unit 2, Board I b) Unit 1, Board II c) Unit 2, Board III d) Unit 1, Board IV i OUESTION 4.06 ( .50) TRUE or FALSE: The turbine should be tripped as an immediate action if the reactor trip breakers fail to open upon a legitimate trip signal. i. l i l l i (+*+** CATEGORY 04 CONTINUED ON NEXT PAGC *****) c (
1
~
4 3__ PROCEDURES - NORMAL 2_ABNQRMAL 3_EMERGENgY_AND PAGE 15'
- -8091969GIC86_CQNIBg6 DUESTION 4.07 (1.00)
Indicate whether each of the following statements regarding EOP usage is TRUE or FALSE: a) If an expected response of an EOP can NOT be verified and the Response-Not Obtained action can NOT be performed, the operators may continue
- with the procedure.
b) If a task is in progress when a transition to another procedure takes place, that task need NOT be completed. QUESTION 4.08 (1.00) Indicate whether the following statements are TRUE or FALSE: a) Neglecting-emergency situations, it is not permissable f or a TVA employed individual to receive occupational exposure during a calender quarter if he has already received 3 Rem during that time. b). An RWP is necessary to enter a Regulated Area. QUESTION 4.09 (1.00) Put the following actions associated with starting the FIRST Control Rod Drive MG set in the correct order:
- 1) Flash th'e field
- 2) Close the Auxiliary 150 VAC supply breaker to rod drivec
- 3) Adjust generator voltage l
- 4) Close the motor circuit-breaker j 5) Close the generator circuit breaker QUESTION 4.10 ( .75)
Aside from the on-shift SE (Shift Engineer), what othcr 3 personnel may 1 authorize clearances at Sequoyah Nuclear Plant? i i i I 1 i i (++*** CATEGORY 04 CONTINUED ON NEXT PAGE ***++)
4:__PSOGEpuBES_ _NOBd862_8BNOBMG63_EDEBgENgy_GND PAGE 16 B89196991G86_G9NIBQL
.00) ~
QUESTION 4.11 u) g gg What are all the immediate actions / verifications if ther e is a need to evacuate the control room due to the presence of smoke in the control room? Assume the reactor and turbine have been tripped already. DUESTION 4.12 (2.00> What are ALL the actions contained in the RESPONSE NOT OBTAINED col umn in FR-S.1, "ATWS", for the steps listed below? Ensure you discuss any contingency actions stated within the RNO step itself. a) Turbine is NOT verified as tripped. b) Pressurizer pressure exceeds 2335 psig. QUESTION 4.13 (1.50) List 5 acceptable methods by which Independent Verification of electrical breaker alignments may be accomplished. s DUESTION 4.14 (1.00) Why is the S/G atmospheric PORV NOT isol ated whil e perf orming E-3, "SGTR", but is only verified shut < 1040 psig and that its controller is in AUTO? DUESTION 4.15 (1.00) EOP E-3, "SGTR", r eqiti r es the cperator to maintaan AFW flow to the ruptured l S/G until narrow range level is established. Provide two reasons for this l procedural reqtnrement. l l OUESTION 4.16 (1.00) l Why i s a MINIMUM of 0.2 gpm #1 seal leat off flow important when preparing to start an RCPO Include in your discussion the primary cause preventing i establishment of this flow rate during startup preparations. I i l t***** END OF CATEGORY v4 *****) (++e********** END OF EXAMINATION ++*******+.**+++)
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# 'I___EBIUCIELES_9E_UyCLE68_EgNEB_E68UI_QEEB8IIGN2 PAGE 17 IUEByggyN8MICS 2 _SE@I_IB80SEEB_8ND_ELylp_E6gW ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 1.01 (1.50)
Laat&
- a. : :. g her (+.5 ea)
- b. LowerH%dW
- c. Highcrbad*
REFERENCE NUS Vol 4, pp 2.2-4 015/000; A1.01(3.5/3.8) ANSWER 1.02 (1.00) d REFERENCE Westinghouse Reactor Physics, Section I-5, MTC and Power Defect DPC, Fundamentals of Nuclear Reactor Engineering St Lucie Reactor Physics, Section 7.6 & 7.7 039/000; A2.05(3.3/3.6) ANSWER 1.03 (1.00) b REFERENCE EIH: GPNT,Vol VII, Chapter 10.1-83-86 BSEP: L/P O2-2/3-A, pp 172 - 176; O2-OG-A, pp 57 - 60 Westinghouse Nuclear Reactor Theory, pp. I-5.77 - 79 Turkey Point, Reactor Core Control, pp. 4 28 OO1/OOO -K5.13 (3.7/4.O) ANSWER 1.04 (1.00) b REFERENCE SON Reactor Physics Review, pp 21/22 001/000; K5.02(2.9/3.4)
gy ,, c' it__EBINQlELEQ_QE_UQCLE88_EQWEB_E(@NI_QEEB@IlgN 2 PAGE 18 ISEBdQQYN@d1GS2 _Ug8I_IB8NSEEB_@ND_E6y1Q_E(QW ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 1.05 -( 1. 00 ) ( A low leakage loading pattern has been employed whi places) new fuel assemblies loaded in the center of the core Fer5TGl' hese assemblies see a higher flux for a longer period &&rS51, accelerating the of ects of pellet swell and clad creep relative to earlier cycles .25) REFERENCE SON Reactor Physics Review, pp 18/19 l 001/000; K5.49(3.4/3.7) ANSWER 1.06 (1.00) i a) Will be the same (+.5 ea) i b) Unit B will be higher REFERENCE Westinghouse Reactor Core Control, pp 6-23/26 Westinghouse Fundamentals of Nuclear Reactor Theory, pp G-48/60 001/010; K5.08(2.9/3.2) L 001/000: K1.05(4.5/4.4) i ANSWER 1.07 11. UOr [0 f) i =\ b)
~ %pple: d a w ;.
Nucleate boiling H.a> W REFERENCE l Westinghouse Reactor Core Control, pp 3-38/42 001/000; K5.49(3.4/3.7) t
.~
ANSWER 1.08 (1.50) i i a) tians flow out vs. SI flow in (+.5 ea) onergy producud by decay heat vs. energy removed j b) Delta P between RCS and containment REFERENCE SON SBLOCA Analysis, pp 5
y!.
. Iz__BBINQ1ELEQ_QE_UMQLEQB_EQWEB_E68NI_QEEB@IlgN 2 PAGE 19 ISEBdQRYU8d1GS1 _SE81_IB8NSEE8_@NQ_E6ylp_E6QH ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM EPE-009;EK1.01(4.2/4.7)
ANSWER 1.09 (1.00)
- 1) Dissolution of H2 (due to mass loss and pressure drop) (+.25 ea)
- 2) Radiolysis
- 3) PZR vapor space expansion
- 4) Zirc-water reaction REFERENCE SON EGT 222.006, pp 23 EPE-009; EK3.11(4.4/4.5)
ANSWER 1.10 (1.50) Pu-239 37% (+/~3) (+.3 for isotope, +.1 for %, +.1 for correct order) t U-235 35.5% --thermal fission j U-235 8% --fast fission g g Lgf 4 %*/o pa - 1. % MC 'la Vg A"(og3l(WM i REFERENCE ~ u-1gg g*/. SON /WBN License Cert Trng, " Reactor Kinetics", pp 6 i St Lucie Reactor Physics Section 7.6.7; SD 1, pp 33 ! 001/000; K5.47 (2.9/3.4) l ANSWER 1.11 (2.00) ! a. Subcooling is based on core e::i t T/Cs or hot leg RTD readings. During i natural circulation the mass of metal in the head can retain heat and keep local temperatures above saturation.-The temperature indicators would not reflect this local saturated condition. (1.0)
- b. Pressuriner level decreases beccuse the pressuriner pressure increase
- will compress the vessel void and force water out of the pressuricor.
(1.0) i REFERENCE i G.P.. Heat Transfer and FF Pp 355-350 i f EPE-074; EA2.05(3.4/4.2) & EA2.07(4.1/4.7) ( l ?. l .I
. It__EB10GIELES_QE_NQQ6E88_EQWE8_ELONI_QEg6@IlgN i PAGE 20 ISEEdQQYNGdlC@2_SE81_IB8NSEE8_QNQ_E6UlQ_ELQW ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 1.12 (1.50) a) > DNB, have partial film boiling, where the fuel rod is alternately covered with steam and water (+.25). Steam has poor thermal conductiv-ity capabilities (+.25), so heat transfer rate drops and Delta T rises
(+.25) b) As fuel surface temperatures rise, stable steam layer forms (+.25) causing a further increase in fuel rod temperatures (+.25). Eventually, significant radiative heat transfer occurs causing heat xfer rate to incarease (+.25) REFERENCE Westinghouse Thermal / Hydraulic Principles II, pp 13-10/20 EPE-074; EK1.02(4.6/4.8) ANSWER 1.13 (2.00) a) Nuclear power is decreasing faster than turbine load, calling for a rods "out" to compensate exactly for the Tref-Tavg mismatch (+.75) b) Steam pressure is periodically exceeding atmospheric steam dump setpoint because Tavg increased due to decreased heat removal (+.75) This causes steam flow oscillations and feed flow follows steam flow (+.25). The S/G oscillations are due to nhrint: and swell an the PORV opens and shuts. (+.25) REFERENCE SON Transient Analysis by NRC TTC 001/000; K4.03(3.5/3.8) & 035/010; K1.09(3.0/4.0)
iz__EBINQ1E6gg_QE_Ugg6586_EQWEB_ELONI_QEEB8IlgN i PAGE 21 IBEBdQRYN6dlGQ2_Uggl_IB8N@EgB_QNQ_E6ylp_E6gW ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 1.14- (1.00) p (i) = .1 (delta k/k) -
.01(delta k/k) = .11(delta k/k) (+.25) k (i) = 1/ (1-p (i ) ) = 1/(1-C .11]) = .9009 (+.25) p (f ) = .11 + .056 = .054(delta k/k) (+.125) k (f) = .949 (+.125)
Cf = Ci (1-k (i ) / C 1-k (f ) ] = 97 cps (+.25) REFERENCE SON Reactor Physics review, pp O-10 001/000. A1.06(4.1/4.4) i i ( i I l l .<- 1 l l l L.
, 2t__E68NI_DE@lGN_1NGLUQ1N@_@@EEIY_8NQ_EMEBGENGY_QYQIEMS PAGE 22 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 2.01 (1.00) d REFERENCE SON Requal 1986, week 4, day 5, " rad monitors", pp 5 073/000; K6.01(2.2/2.4) ANSWER 2.02 (1.00) d REFERENCE FNP, RHR Lesson Plan, pp. 8L9 NA NCRODP 88.2, "RHR System" SONP lesson plan "RHR System" pp 5 OOS/000-K4.07 (3.2/3.5) ANSWER 2.03 (1.O , C /
,/
/
REFERENCE Surry ND-88.,4-LP-8, pp 8.6 Westinghouso Systems Manual, pp 4.5-20 028/000i K6.01(2.6/3.1)
' 8t__ELOUI_DESIGU_1Ng69Q1NG_@@EETY_GUQ_EUEBGENgy_SygIEdg PAGE 23 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 2.04 (2.00)
O a) (1) 2D (+.33 ea) (2) 1A (3) IB b) (1) SI from Train 1A or 2A ( +. 2 ea >6H- dag f) (2) No blackout signal (3) Transfer switch on swgr in Nermal (4) KA selected for operation (3) g,4 w gr (5) Pump RA not running (g) c.e genac 4penserw #9 Mo (f) CouM*t h*d8# gg#ggggy REFERENCE SON Requal 1986 week 1, day 4, "ERCW", pp 4-9 ,* S t4 A/ 4W4 W M 7 W-' T 076/000; K1.01(3.4/3.3), K1.05(3.8/4.0), K1.19(3.6/3.7), K4.02(2.9/3.2) ANSWER 2.05 (2.00)
-Mechanical Overspeed (+.4), manual reset (+.1)
-Electrical Overspeed (+.4), NO manual reset (+.1)
-Thermal Overload (+.4), manual reset (+.1)
-Steam Supply Transfer (+.4), NO manual reset (+.1) .
REFERENCE SONP Sy. stem Descrip. "AFW", pp 6 061/000; K4.07 (3.1/3.3) ANSWER 2.06 (1.00) a) 1500 psig (+/- 25 psig) (+.03 ea) b) 100 psig ( + /- tips tj ) c) 1250 prig (+ w/ g,p pg, ) REFERENCE SON E-0, pp 3, Westinghouse Gyctemu !1anual, pp 4-1 -33 ' T.5 3. f.1. 7 j EPE-011; EK3.12(4.4/4.6)
n - 1 2 t__EL8NI_ DESIGN _INCLyQ[NG_EGEEIY_6ND_EMEBGEUCY_SYSlEMS PAGE 24 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 2.07 (1.50)
- 1) RWST level < 29% (+.5)
- 2) Containmeret sump level > 11.25%
- 3) SI signal present REFERENCE SON "ECCS Review", pp 8 EPE-011; EK3.15(4.3/4.4)
ANSWER 2.08 (1.00)
- 1) Hot leg loop 1 (+.25 ea)
- 2) Hot leg loop 3
- 3) RHR upstream of HXers
- 4) Containment atmosphere REFERENCE SON Requal 1986, week 4 day 1, "PASF", pp 4 ANSWER 2.09 (1.00)
-SI PumpsW(+.25 ca)
-ONE Centrifugal Charging Pump Je ,46y E r eg'd (a f . f ra)
-UHI Gags
-Cold Icg Accumulator Isolation Valves *"
REFERENCE SONP System Descrip. "RCS", pp 9 010/000; K1.02 (3.9/4.1) ANSWER 2.10 (1.50) , a) S/Gs #1 and 4 (+.5) b) (Appendix R requirement) PORVs were inaccessible for fire in the West Valve Room (+.5) Only 2 S/Gs are required for safe shutdown (+.5) REFERENCE SON Requal 1986 week 2, day 1, " Major Modifications", pp 5
7 .. 1 __E60dI_DEgl@N_INCLUplNG_SOEEIy__AN_D_EMER@gNCY_gY@TEMg PAGE' 25 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM 035/010; K4.05(3.1/3.4) j , LT ANSWER 2.11 '1."^' a) demister >>> relative humi di ty - heater >>>prefil ter bank >>>HEPA filter bank
>>> Carbon adsorber bank >>> 2--m. au ..mL...y ml-_ ;.t>>>ccriar cd:crber berrTP"7>>HEPA f i l ter bank (+.125 ea) b) Two cross over air-flow ducts draw air from the active air cleanup unit
(+.5) REFERENCE-SONP Sys Descrip. 4.4, " Containment Air Purif and Cleanup System" pp 7-8 027/000; A2.01 (3.0/3.3) ANSWER 2.12 (1.50) SUMP via 63-72 to suction of A RHR pump thru A RHR HX (+.5) and either to 63-8 > >>63-6 (7) >>SI pump sucti on (+.25) or 63-172 to loops 1 and 3 (+.25)
-after the SI pump >>63-156 to hot legs ,Z and-( (+.5)
(- 3 REFERENCE SON ES-1.3 EPE-011; EX3.08(3.9/4.1) ANSWER 2.13 ( 1. 50) - a) Prevent overheating turbine blading due to dow steam flow (+.5 ea) b) Prevent reaching the overvoltage/underfrequency setpoint on the mainbank transformers. c) Prevent excessive load on EHC pump due to trying to pump heavy fluid. REFERENCE SON GOI-2, pp 3-5; SON GOI-2 " Plant Startup", pp 7/8 045/050; PWG-7(2.9/3.3)
1
. 3c__INEIByMENIQ_6ND_QQNIBQLS PAGE .26
. ANSWERS -- SEQUOYAH 1&2- -86/12/15-DEAN, WM .
ANSWER 3.'01 (1.00) Q REFERENCE SON Requal 1986 week 2, day 1, " Major Modifications", pp 8/9 061/000; K4.04(3.1/3.4) ANSWER 3.02 (1.00) d. REFERENCE SON Requal 1986 Week 5/6, day 7, " Control System Theory" 202002 K4.08 3.3/3.4 5.03 2.4/2.4 ANSWER 3.03 (1.25) The stationary and movable grippers energize and the lift coil deenergizes (+.75); ROD URGENT FAILURE Alarm and red lamp at power cabinet actuate (+.5) o f' Orte4+ failurt it y ,a (og st. et be* net @g REFERENCE ~ SON " Rod Control System", pp 12 OO1/050;A2.01(3.7/3.9) ANSWER 3.04 (1.50) a) Arm and actuate
- b) Arm and actuato c) Arm only '
j , , - i REFERENCE l -Farley SD, " Steam Dump System", pp 23-28
- SONP System Descrip. " Steam Dump System", pp 6-8 i
! 041/020; K4.11 (2.8/3.1) & K4.14 (2.5/2.0) L K4.17 (3.7/3.9)3 L i l
3 2__IUSIBydEUIS_OND_GQNIB96@ PAGE 27 ANSWERS'-- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 3.05 ( .50) ( AL$ie Jw=nr (+.5) REFERENCE SON "Excore NIs", pp 18 015/000; 6.04(3.2/3.4) ANSWER 3.06 (1.50) a) Output remains at the low end of the gain (+.5 ea) b) 0 degree mismatch c) Goes high to 72 steps per minute REFERENCE SON Requal 1986, week 3, day 4, " Instrument Failures"; " Rod Control" 001/000; K4.03(3.5/3.8) ANSWER 3.07 (1.50) kdq f
-Phase A Containment 1 solation signal from either Unit (+.375 eaI
-High Radiation signal from fuel handling b1dg area rad monitors ;
Aux Bldg e::haust vent rad monitors qf ,
-High Temperature in Aux Bldg Supply Fan Suction y(3 cg,gg gph+
M&o REFERENCE p.go ,,g , yig,4 SONP Sys Descr. 4.4, " Cont Air Purif and Cleanup Sys" pp 15 ggy p y g u 6,M -y M *3 'O MM O EPE-060; PWG-10 (4.1/4.4) ANSWER 3.08 (1.50) Tavg; PZR Pressure; Delta Flu::; Delta T at rated powor; Tavg at rated power (+.3 ea) REFERENCE Westinghouse PWR Systems Manual "RPS", pp 9-10 SONP TS Table 2.2-1 012/000; K6.11 (2.9/2.9) & A2.05 (3.1/3.2)
3
, Ji__INSIBWDENIS_0BD_G9NIBgLS PAGE 28 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 3.09 (1.75)
Hi-Hi containment pressure > 2.81'psig (+.5) High Steam Line Flow Coincident with Low Steam Line Pressure <600 psig or Lo-Lo Tavg <540 deg F. (+.75) High Steam Flow setpoint is at 40% flow from 0-20% load (+.25) then linearly from 40-110% flow from 20-100% load (+.25) REFERENCE SONP PLS pp 9-11 013/000; K4.03 (3.9/4.3) e ANSWER 3.1 (1.50)
- 1) Open CCW mp breaker (+.3 ea)
- 2) Roset SI
- 3) Reset G lockout
- 4) Star EDG
- 5) Man ally load equipment REF ENCE 5 ELEDST
/ PE 055; EA2.06(3.7/4.1), PWG-11(4.3/4.4)
ANSWER 3.11 (2.50) a) P:r level Hi-Low Alarm (+.25 ea) Charging Flow increases Level increases to 60% (Limited to 100% power program) , b) One Ltdn isolation valve shuts All orifice valves shut P:r Lovel Law, Htes Off. Ltdn Secured alarm Heatern turn off Level rises as charging flow reduced to flow through neals >- P:r level Hi/ DU htrs en alarm Rx trip on high level REFERENCE Sqn Requal 1986 week 3, day 4, " Instrument Failures", pp 31/34 011/000; K1.01(3.6/3.9), A2.11(3.4/3.6)
. Es-_ldSIBQUgMI@_6ND.CONIBQLS PAGE 29 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 3.12 (1.00) Turbine Trips (+.5) due to 2/4 OTDelta T logic being made up (+.5) (Rx trip >>>> Turbine trip) REFERENCE TPT DWG 5610-T-D-14 [q d M MoA M W'4vetsa4 Av W sf f Iflto 012/000; PWG-10(4.4/4.7) ANSWER 3.13 (1.50) 2/3 relays < 95% for 10 seconds if an signal present (+1.0) for 5 minutes without SI(.+.5) REFERENCE SON " Diesel Generators", pp 13 062/000; K3.02(4.1/4.4) m y*e
jE' 4. PRQCEDURES - NORMAL _G@NQBMAL 1 3_gME8GENQY_ANQ PAGE 30 8891960 GIG 86_GRNIBQL ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 4.01 (1.00) b REFERENCE-
. SON AOI-34A, pp .1 EPE-024; EK3.01(4.1/4.4)
ANSWER 4.02 (1.00) d REFERENCE SON LER 85-040-000; SON "RHR", pp 13 005/000; PWG-7(3.5/3.8) ANSWER 4.03 (1.00) , e REFERENCE FR-Z.2 EPE-069; EK3.01(3.8/4.2) ANSWER 4.04 (1.00) b REFERENCE Westinghouse Users Guide, pp 2-5 - PWG-22(4.2/4.2)
-)
J 0 */
)
, -4. PROCEDURES _ _NQBMAL2 _AgNQBMAL 1_EMERQENCY_ANQ PAGE 31 i BOD 196QGICB6_CQNIBQ6' ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 4.05 (1.00) c gcb REFERENCE
. SON ADI-21.7, pp 1
- EPE-058; PWG-10(4.1/4.2)
ANSWER 4.06 ( .50) false (+.5) REFERENCE SON FR-S.1, step 3 EPE-029; PWG-11(4.5/4.7) ANSWER 4.07 (1.00) a) True (+.5 ea) b) False REFERENCE Westinghouse User's Guide, pp 5, 17, 18 PWG-22(4.3/4.3) ANSWER 4.08 (1.00) a) True (&.5 ea) b) Falso REFERENCE SON RCI-1, pp 2,10 PWG-15(3.4/3.9)
j , 1 p~ s. . 4 .' b___EBQGEQWBEg_ _NgBd66 _6BNgBd861_EMERGEMGY AND PAGE 32 88QlR6QGIG86_GQNIBQL , ANSWERS --- SEQUOYAH 1h2 -86/12/15-DEAN, WM- .e
- e-
, i h' '
( , 6 ANSWER 4.09 (1.00) , ,, . 1 I 4,'1, 3, 5, 2 ( .2 for each. swap required to put in correct order)>
,/ /
2' REFERENCE )) g SONP SOI-85.1A, pp 3 } 4,
.c /
001/010; A4.01 (3.7/3.4) /
..t // L.s,..k.
I.
, , , ' D' ANSWER 4.10 ( .75) # ' '
+
- 1) ASE (+.25 ca)N N 3 '
, p ,
- 2) Outage Coordinator ,,
e -
- 3) Other SEs assigned to the shift ['
- 4) (kuka % .aedl bipakker"
( /.J REFERENCE '
. SON AI-3, pp 2 ,
i PWG-14(3.6/4.O) '
/" ,
i, t / ANSWER 4.11 (2.25) Q W[ a r-,
-Verify steam stbps closed (+.25 ea)
-VerifyAFWpu%crunningandflowestablished 4
-Verify PZR pr,ossure within 1906-2235 . ,p
-Verify PZR 1 vel within 24-60% ,
2 3, ,
-Verify Tavg controlling at 547 degrees
-Verify con ainment pressure and temperature normal j
-Veri f y geryerator breakers open and 6. 9 KV uni t station service '
n f erred
-Verify M.in fcod isolation z' r.
-Verify m in feed pump,s tripped .
REFERENC- ' SON AOI 27A, pp 1/2 - < r
.r EPE-06( ; PWG-11(4.5/4.5) j e
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*4, PROCEDURE 9 - NORMAL1_OBNgRMAL1_EijsRGENCY_ANQ PAGE 33 E8910 LOGIC 86_CgNIEg6 ANSWERS -- SEDUOYAH 162 -86/12/15-DEAN, WM s
ANSWER 4.12 (2.00) l a) -Close MSIVs andybypasses (+.5 ea) Ij ,
-Trip turbine from main turbine front standard
, -Stop and pull-to-lock both EHC pumps at the pump control station b) (1) Verify PORV and block valves open (+.25 ea)
(2) Verify; containment purge air exhaust isloated REFERENCE FR-S.1 EPE-029; PWG-11(4.5/4.7) ANSWER 4.13 (1.50)
- 1) Visual inspection of breaker posi ti on (+.3 ea for any 5)
- 2) Breaker light indication
- 3) Functional Test (eg. voltmeter)
- 4) Local (or Remote) Instrumentation
- 5) Annunciators
- 6) Switch position REFERENCE TPT AP 031, pp 8 ,
SDN (CAF) FWG-13: Conduct / Verify Valve Lineups (3.7/4.0) ANSWER 4.14 (1.00)
?<
I This allows S/G Pressure protection withcut having to depend on the code' safeties (+.75) which could lift and not reseat causing an unisolable steam leak (+.25) REFERENCE Westinghouse Background Document; (TP T OBNK E-16) EPE-033; EK3.06(4.2/4.5) i e
r-3 4: ?
- o. .
- d. _PBQQEQQBES_ _UQBUGL2_8@NQBd862_guESQEUQY_6NQ PAGE 34 E8019690lG86_QQNIBQL ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER' 4.15 (1.00)
- 1) (Promote thermal stratification) so ruptured S/G doesn't depressurize during cooldown (+. 5 eafer am 1,)
- 2) Ensures S/G available as a heat sink if required
& 3edst SsNbbh 4 tM m'% RL) $h54 REFERENCE Westinghouse ERG Background Document; (TPT QBNK 18)
EPE-038; EK3.06(4.2/4.5) ANSWER 4.16 (1.00) Adequate seal film (+.5) Clogging of the seal (+.5) REFERENCE SON AOI-23, pp 6 003/000; A2.01(3.5/3.9)
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- U. S. NUCLEAR REGULATORY COMMISSION
/h/f SENIOR REACTOR OPERATOR REDUALIFICATION EXAMINATION FACILITY: _SEgygyAH_1k2____________
REACTOR TYPE: _PWR-WEG8________________ DATE ADMINISTERED: _g6/1gfig_________________ EXAMINER: _ DEAN3 _W M_______________ CANDIDATE: _________________________ JNSIByCIlgNS_IQ_CONQ198IE1 Read the attached instruction page caref ully. This examination replaces the current cycle facility administered requalification examination. ! Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff. Points for each question are indicated in parentheses after the question. The passing gr-ace requires at least 70% in each category and a final grade of at least 80%. Ex ami nati on papers will be picked up four (4) hours after the examination starts. i
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__Y8LUE_ _I9I86 ___SCQBE___ _y@(UE__ ______________g81EQQBy_____________ AG. L _lesgg__ _@ftff ___________ ________ 5. THEO.RY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND f THERMODYNAMICS ut 7n .D , \ I _Y5xyy__ _&4-93~ ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION gj,7 f OI. 'L- _ __ _ ___________ ________ 7. F CE RES NDRMAL Erm MAL, CONTROL qa S 8 A .'n.' y P Rd C v3E 5, (ou b tTeo WS ,Lt M s T.A ir,W5 i _ga_ J O__ ___________ Totals Final Grade f All wori: done on this examination is my own. I have neither given nor received aid. Candidate's Signature J
I NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination I
room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil gnly to f acilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the ex ami nati on.
t
- 5. Fill in the date on the cover sheet of the e::ami nati on (i f necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper ri ght-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each_ category on a Ogw page, write gnly 90 gee sidg j of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least tht gg lines between each answer.
4 s
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
( 12. Use abbreviations only if they are commonly used in facility literatute.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the exami nation are not clear as to intent, ask questions of the e:J aminer only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
- 18. When you complete your e:: ami nat i on , you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still i n pr ogress, your license may be denied or revoked.
l l l l 1
=
1 I
. -5. THEORY OF NUCLEAR POWER _ PLANT _QPEB811QN 3 _ELVIDS3 _8ND PAGE 2 IUEBbgpyN801CS QUESTION 5.01 (1.50)
Indicate whether the following will cause the power range instrument to be indicating HIGHER, LOWER or the SAME as actual power, if the instrument has been adjusted to 100% based on a calculated calorimetric.
- a. If the feedwater temperature used in the calorimetric was higher than actual feedwater temperature.
- b. If the reactor coolant pump heat input used in the calorimetric is omitted.
- c. If the-steam flow used in the calorimetric was lower than actual.
DUESTION 5.02 (1.00) The reactor is critical at 10,000 cps when a S/G FORV fails open. Assuming BOL conditions, no rod motion, and no reactor trip, choose the answer below that best describes the values of Tavg and nuclear power for the resulting new steady state. (POAH = point of adding heat).
- a. Final Tavg greater than initial Tavg, Final power above POAH. g
- b. Final Tavg greater than initial Tavg, Final power at POAH.
- c. Final Tavg less than initial Tavg, Final power at POAH. ,
- d. Final Tavg less than initial Tavg, Final power above POAH.
QUESTION 5.03 (1.00) Attached Figure # 219 shows a power history and four possible xenon traces (reactivity vs time). Select (a, b, c, or d) the curve that correctly displays the expected xenon transient for the given power history. QUESTION 5.04 (1.00) For the Cycle 4 core, what is the main core desi gn reason that the pellet swell and clad creep effects override the Pu-240 buildup /U-238 depletion effects and roa k e the Doppler Only Power Coefficient less negative? (*k*** CATEGORY 05 CONTINUED ON NEXT PAGE **+++)
0 __ISE0BY_9E_ NUCLE 98_EgWEB_E6@NI_gEEBOllgN g _ELylDS3 _8ND PAGE 3 ISEBdgDYN@dlGS OUESTION 5.05 (1.50) An ECC is calculated for a startup following a reactor trip from 50% power equilibrium xenon (BOL). Indicate if the actual critical rod position will be HIGHER, LOWER or the SAME f rom the calculated position f or each of the following situations. Use attached curves as appropriate and treat each case individually, a) Xenon reactivity curve for trip from 100% is used to calculate conditions to startup 20 hours after the trip. b) Boron worth at EOL is used vice BOL worth.(Dilution is required to reach desired Boron concentration in both cases) c) The EOL critical Baron Concentration is used instead of the BOL critical Boron concentration. QUESTION 5.06 (1.50) Unit 1 is at 90% power with control rods in MANUAL when the turbine is ramped down to 60%. Indicate whether the parameters below will increase,. decrease or remain the same during both the initial response (first 30 seconds of the transient) and after turbine power has stabililzed relative to the initial conditions. (Assume the following: No changes to boron / xenon Loop transport time is 10 seconds No operator actions) NOTE: No answer required where it is already filled in below. Initial Response Steady State a) S/G Pressure NO ANSWER RORD b) Reactor Power NO ANSWER RORD c) Tcold d) Tavg QUESTION 5.07 (1.00) What two fuel rod related parameters. excluding power limitations, should i be maintained within limits to minimize cladding stress and strain? (setpoints not required) OUESTION 5.08 (1.50) List the three main sources of f i ssi on neutrons in the core at end of life l and indicate their approximate contribution (in %) to power. , (**+++ CAlEGORY 05 CONTINUED ON NEXT PAGE *+***)
i l , pt THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS 2 _8ND PAGE 4- , INEBMODyN8MICS j
'OUESTION 5.09 (1.00)
What is the reason that Tech Specs allow up to two hours of operation with a Duadrant Power Tilt Ratio in excess of 1.02? DUESTION 5.10 (2.00)
- a. During natural circulation, EXPLAIN how it is possible to f orm a bubble in the reactor vessel head when indications show that the RCS is subcool ed?
- b. How will pressurizer level respond, (INCREASE, DECREASE, or REMAIN THE SAME) if the backup heaters are energized with a bubble in the reactor vessel head? Assume normal pressurizer level and briefly EXPLAIN your
; answer.
1 OUESTION 5.11 (1.00) The attached figure shows the change in pressure across a pressuri er PORV and its associated upstream and downstream piping for various valve positions. EXPLAIN why the major pressure drop occurs in piping segment P1-P2 when the valve is slightly open, whereps the major #ressure drop occurs in piping segment P2-P4 by the time the valve is fully open. QUESTION 5.12 (1.50) I Assume the plant is at a steady state power level of 75%, with rod control l in MANUAL and the plant in BOL, when a 15% step increase in turbine load I occurs. DESCRIBE and EXPLAIN the behavior of the f ollowing parameters during the first several minutes of the transient. Assume MTC is -3 pcm/F and NO RX TRIP occurs. a) Tstm b) margin to DNB i , i (*+++* CATEGORY 05 CONTINUED ON NEXT PAGE *****)
., _51 THEORY OF NUCLEAR POWER PLANT OPERATION 3 _FLUIQS3,6ND PAGE 5 IHEBdQQyN901G5 DUESTION 5.13 (1.50) a) Why is 2200 degrees F qiven as the 10CFR50 peal: cladding limitation during an accident condition? (0,5) b) The Tech Spec limit on F(n) Delta h is 1.49E1.0 + .3(1-P)] where P represents fraction of rated power. Why does this limit increase as power decreases for a given RCS fl ow rate? (1.0)
OUESTION 5.14 (1.50) Attached is a typical boiling curve for water as it approaches, then e:: c eed s , the DNB point. What are the thermodynamic conditions that cause: a) The decrease in heat transfer rate in Region III? b) The increase in heat transfer rate in Region IV? s { i l (+**** END OF CATEGOR( 05 +****)
. . .- ~. - . . - . .. ._. . _ .
A __EL8NI_Sy@ led @_QE@lGN2 _QQNIBQ62_@NQ_IN@IBUdENI@llgN PAGE 6 DUESTION 6.01 (1.00) Which one of the f ollowi ng describes how the AFW system is prevented from feeding a faulted S/G7
, a) Operator action is required to isolate AFW when a f aulted S/G is detected. ,
b) Pr essure swi tches on the AFW discharge lines will automatically close the loop level control valves when low AFW discharge pressure is detected. c) Level transmitters on the S/G wide range level instrument will automatically close the loop level control valve when a low level is detected in a S/G. d) Flow transmitters on the AFW discharge lines will automatically close the loop l evel control valves when e::cessive flow is detected in AFW discharge piping. QUESTION 6.02 (1.00) RHR inlet isolation valves 74-1 and 74-2 each have an independent RCS pressure transmitter associated with them. Which of the following statements describing the effects of the trapsmitter associated with 74-1 failing high is correct?
- a. If both 74-1 and 74-2 are open, they will shut.
i , b. If open, 74-1 will shut and if closed, 74-2 will not be able to , l be opened, i
- c. If both 74-1 and 74-2 are shut, neither one will be able to be opened.
- d. If open, 74-1 will shut, but 74-2 can be positioned as desired.
- e. 74-1 can be positioned as desired by the operator, but 74-2 will not be able to be opened if it is shut.
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) i I
-![
6 __E66MI_Sy@IEMS_ DESIGN 3_GONIBQ6i_6ND_INSIBUMENI611QN PAGE 7 OUESTION 6.03 (1.50) Indicate whether the following situations will ARM ONLY, ARM AND ACTUATE or HAVE NO EFFECT on the steam dump system. a) 80% power, 7.5%/ min ramp decrease in turbine load for 3 minutes, Tavg> Tref by 7 degrees F, steam dumps in Tavg mode of operation b) Hot Zero Power, Tavg=549 degrees F, steam dumps in STM PRESS mode
+sith 1005 psig set into the steam pressure controles, stcom dumpm in-T g.n n na e, c) Turbine trip, Tavg=542 degrees, steam dumps in Tavg mode OUESTION '6.04 (1.50)
Fill in the blanks in the statement below concerning the Containment Air Return System: Both fans are actuated upon an _____ actuation signal but are delayed starting for _____ minutes. They continuously drau air from the dome of the containment vessel and from the following pocketed spaces _____, _____, _____ and _____. QUESTION 6.05 (1.00) What are the 5 analyses that can be performed online by the Post Accident Monitoring System? DUESTION 6.06 (1.50) What 4 signals will automatically initiate the operation of the Auxiliary Building Gas Treatment System? QUESTION 6.07 (1.50) l An SI signal was generated due ta'a tranni ent c (Id by an undervoltage condition on the 2A-A 6.9KV Bus. During this t nsient, the 2A CHG Pump breaker staped closed causinf' an EDG lockout < (all other loads wer r6 moved) i What 5 act' ions must the opdrator take to Idad equipment on th us using the 2A A EDG? / /
/
i i . i (***** CATEGORY 06 CONTINUED ON NEXT PAGE *++++) k
sz__BL9NI_SySIEDS_ DESIGN 3_GONIB063_@ND_INSIBUDENI6119N PAGE 8 L QUESTION 6.08 (2.50) Describe all events / alar ms that occur due to the following instrument failures until the reactor either trips or stabilizes. Assume no operator actions and all controls are in automatic, a) Pressuriner Level Reference Signal (Tavg) fails high while at 50% power. (0.75) b) Selected Secondary Pressuriner Level Control Channel signal fails low while at 70% power. (1.75) OUESTION 6.09 (1.00) a) What is the damage that the exciter field breaker Volts /Hert: relay (59/81) is designed to protect against?
.b) What actions occur (include time delays) if this relay operates?
(Only discuss the 59/81 relay with the low setpoint) OUESTION 6.10 (1.50) s Recent modifications to the S/G PORVs added manual operator extensions - for remote operation of the valves on 2 S/Gs. a) Which 2 S/Gs were affected by this modification? (0.5) b) What is the basis for this modification? (Include discussion of why l only 2 S/G PORVs were modified) l OUESTION 6.11 10.LC;(I17T) l a) Describe the order of processing elements in the Air Cleanup Units through which air is drawn by the Air Cleanup Subsystem. 44 "M (- f77) b) How are the processing elements in an INACTIVE air cleanup unit loaded with radioactive material kept cool? (0.5) t ( ++ + + + CATEGORY 06 CONTINUED ON NEXT PAGE **.***)
- . _ _ _ _ .__ -, , _ _ . _ _ _ - . ~ _ _ ____.____ _. . . . _ _ . , , _ . . . . _
6I__ELONI_SYSIEUS_DEglGU3_CONIBQL,_8ND_INSIBUDEUI611gN PAGE 9 OUESTION 6.12 (1.00) While transf ering a new fuel assembly from the upender to the core, the Dillon Cell fails high. What actions must the operator take to disengage the gripper from the iuel when the assembly is properly placed in the core? (Include location of any controls / components operated) DUESTION 6. 3 (1.50) V Describe the flow pattofor hot l eg recircul ation , from the recirculation sumps to the RCS. Identify major components and any valves which can be operated from the control room. (Use only the A Train) i I i (N**** END OF CATEGORY 06 ***++) I
g -
. 'Z __EB9GEDUBgS_:_NQBMB6,_8BNQBM863_EMEBGENQY_@NQ PAGE 10 q -80919690lGOL_GQNIBQL QUESTION 7.01 (1.00) ,
Which one of the following_ situations does NOT require emergency boration per AOI-34.A, " Emergency Boration"7 a) One rod stuck in the f ully withdrawn position f ollowing a rx trip, b) ROD BANK D LOW LIMIT alarm actuates as rods are driving in automatically. c) A steady, sustained increase in source range counts with keff=.95 with no rod motion or planned dilution in progress. d) RCS Tavg falls below 525 degrees at a rate of 30 degrees /hr after a reactor trip. (No manual cooldown in progress) DUESTION 7.02 ( 1.~ 00) Which one of the following conditions are the correct MINIMUM requirements for starting "B" RHR pump while swapping RHR pumps during normal MODE 5 operations? Pump A status RCS Level a) On 695* g b) -Off 695* c) On 695* 6" d) Off 695* 6" e)
~
On 696' OUESTION 7.03 (1.00) Which one of the f ollowing is addressed in FR-Z.2, " Containment Flooding", as a potential sour ce of excessively high containment sump levels? a) Condensed steam from a steam break b) RCS water from a LOCA c) RWST d) Accumulators e) CCW i l i
'(++*** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
r .1 7, PROCEDURES _ _NQRMAL2 _ABNQRMAL3 _EMERGENQy_AND PAGE 11 6091969GIC86_CQNIBQL QUESTION 7.04 (1.00) The loss of which one of the f ollowing 125 VDC Vital Battery Boards will
-cause a reactor trip and also number.2/4 S/G MSIVs and main feed regulating bypass valves to close?
a) Unit 2, Board I b) Unit 1, Board II c) Unit 2, Board III d) Unit 1, Board IV QUESTION 7.05 ( .50) TRUE or FALSE: The turbine should be tripped as an immediate action if the reactor trip breakers fail to open upon a legitimate-trip signal . QUESTION 7.06 (1.00) Indicate.whether each of the following statements regarding EOP usage is TRUE or FALSE: a) If an' expected response of an EOP can NDY be verified and the Response l Not Obtained action can NOT be performed, the operators may continue j' , with the procedure. L ! b) If a task is in progress when a transition to another procedure takes l place, that task need NOT be completed. QUESTION 7.07 (2.00) List, in their order of preference. the four recovery techniques stated in FR-C.'1, " Inadequate Core Cooling". QUESTION 7.08 (1.50) AOI-29, " Dropped or Damaged Fuel Assembly", discusses the " Worst Case" event of a dropped and damaged fuel assembly. What are the 3 criteria, that if met, could result in a radioactive release high enough to require implementation of the REP? - (ie. the worst case) l (***** CATEGORY 07 CONTINUED ON NEXT PAGE * + + ** ) i
. Zz__EB9CEDUBES_ _NgBD962_8BNQSD962_EDEBOENgY_8ND PAGE 12 68D1969GIGOG_G9NIBg6 OUESTION 7.09 ( .75)
Aside from the on-shift SE (Shift Engineer), what other 3 personnel may authorire clearances at Sequoyah Nuclear Plant? OUESTION 7.10 y Z. 60) an/A % [ What are all the immediate actio ritications if t need to evacuate the control r ooi - to the presence of smot:e in the control room? Assume the reactor - turbine have been tripped already. QUESTION 7.11 (1.00) Why is the S/G atmospheri c PORV NOT isol ated while perf orming E-3, "SGTR", but is only verified shut < 1040 psig and that its controller is in AUTO? 4 OUESTION 7.12 (1.00) EDP E-3, "SGTR", requires the operator to mafntain AFW flow to the ruptured ,
- S/G until narrow range level is established. Provide two reasons for this procedural requirement.
t QUESTION 7.13 (1.50) i ! .The Response Not Obtained for step 1 of FR-H.1, " Response to Loss at Secondary Heat Sink" states: _If ALL S/G Wide Range levels < 25%, then [ STOP ALL RCPs and immediately initiate feed and bleed per steps 11 to 13. l Why are the RCPs tripped prior to inititing feed and bleed, aside from the fact that heat input from the pumps will be removed? l I l l l QUESTION 7.14 (1.00) What is the major ADVANTAGE and the major DISADVANTAGE of using ES-3.3,
" Post SGTR Cooldown by Ruptured S/G Depressurization"?
(****+ CATEGORY 07 CONTINUED ON NEXT PAGE +*++*)
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Z:__EB9GEpuB[J_r_NQBd863_8DNgBd863_EdgBGENGY_800 PAGE 13 B091969 GIG 86_GQNIBQL DUESTION 7.15 (1.50) AOI-23, "RCP Seal Abnormal i ti es" , states that the #2 seal should last 24 hours under full system pressure. Why then does this procedure require shutdown of an RCP within 30 mi nutes of shutting the #1 seal 1eak-off valve? s i (***** END OF CATEGORY 07 *****)
@z__9pplyJgJg8))yg_P6pghpyBg@,_ggypJllgN@,_ONp_LJg1J9))pyg PAGE QUESTION O.O[ (1.00)
When would an injured worker with contamination be considered an Unusual Event?
- a. If the worker is sent home,
- b. If the worker is transported to an offsite hospital.
- c. If the contamination is internal.
- d. If in addition to being contaminated, the worker's exposure is above the 10CFR2O quarterly limit.
QUESTION 8.02 (1.00) Which of the f ollowing conditions requires action according to Tech Specs in less than 1 hour if in Mode 2 on Unit I?
- a. The shutdown margin is 1.B.
- b. One Boric Acid Transfer pump is inoperable.
- c. One Shutdown rod not f ully wi thdrawn. g
- d. Primary Containment average air temperature is 140 deg. F. in the lower compartment.
i 1 m QUESTION 8.03 (1.00) l l True or False:
- a. Rad Tumbler Sets are installed on doors leading directly to high r adi ati on areas but not exceeding 1000 mr/hr.
- b. The Plant Health Physicist controls the keys to the Rad Security Locks.
i l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) - l l L
PAGE 91__990]NJSIB@))VE_PBQCEQUBES3 _CQNpl}}QNSg_@Np_LJD}}@lJQNS QUESTION 8.0# (1.50) True or Falser
- a. Category "B" SDI's do NOT require the maintenance of the system status file since Category "B" SDI's may not change a system's status,
- b. Category "A" SOI's are NOT required to be present for performing tasks of a frequent or routine nature.
- c. Valve and Power Availibility Checklists contained wi thi n SOI 's are NOT categorized as "A" or "B"; therefore they SHOULD be present during checklist performance.
QUESTION 8.06 ( .50) Fall in the blank: According to AI-2, Authorities and Responsibilities For Safe Operation and Shutdown of Sequoyah Nuclear Plant, in the event of a reactor trip or an unexplained power reduction, it is the responsibility of the _________ to analyze the cause and determine that operations can continue saf ely bef ore returning the reactor to power. s QUESTION B.06 (1.50)
~
I List FIVE parameters /syst ems /condi ti ons that have Tech Spec LCO's based upon IOCFRIOO, Reactor Site Criteria. QUESTION B.07 f 2 Oyj 3 (,y,,,,,, g,7 , gg n,7 g_ ppmg 2V o, List the parameters needed to calculate a total plant noble gaseous radiation release rate per TI-30. QUESTION B.06 (1.00) In accordance with AI-3, Clearance Procedure, state whose instructions must be obtained prior to the operation of equipment or controls tagged with a blue operating permit tag. . (***** CATEGORY OB CONTINUED ON NEXT PAGE *****)
9:__9901N]p]B9))VE_BBgCEQUBE@,_QQNQJJJgN@3,@NQ_LJDJJ9]JgN@ PAGE f I QUESTION B.09 (1.00) l
- a. What procedure is used to determine the classification of an emergency? l
- b. According to the REP, which emer gency cl assi f i c at i on l evel has as one of i its purposes to "ini ti ate predetermi ned actions for the public?"
QUESTION B.10 (1.50) What are the three boron injection flow paths that can be considered to meet the requirements of Tech Spec 3.1.2.2 (attached)? QUESTION 8.11 (1.00) According to Tech Spec 6.7, Saf ety Limit Vi ol at i on , what two actions must take place within one hour in the event a Safety Limit is violated? , QUESTION B.11 (1.00) s i l l During Mode 1 operation of unit 1 it is found that 2 of 4 channels for Pressurizer Pressure High Reactor trip are inoperable due to a generic material deficiency (repair time 14 days). Using Tech Spec LCO's provided, determine what actions must be taken as a result of this ~ failure? State specific LCO/ action steps which apply. QUESTION 8.13 (1.00) What is the basis f or the upper limit of containment temperature? 1 l -
*****)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE
E r PAGE e 0 __0901N1516@llyE_P6QCEQU6ESt_CQNQlliQNS ,@NQ_g Lid 11611QNQ QUESTION 8.1 Y (2.00)
-If an MR (maintenance request) made a Temporary Alteration to inoperable CSSC (Critical Systems, Structures, and Components) equipment, what must be done (administrative 1y) if the Temporary Alteration must remain in effect after completion of the MR? Include in your explanation any review / approval cycles or other admi ni strative steps as appropri ate.
QUESTION 8.If (1.00) With reactor power above 50% and AFD within the " doghouse" l i mi t s (Tech Spet figure 3.2-1; AFD limi ts as a function of rated thermal power): What operator action is required by Tech Specs 3/4.2.1 (Axial Flux Difference) if the AFD monitor alarm becomes inoperable? s a 9 (***** END OF CATEGORY OB *****) (************* END OF EXAMINATION ***************)
PAGE 14 48Y_QE_UQQLE68_EQWER_EL6NI_QEE86IlOU1_ELQ1QS2_8NQ
' dQRYN8dlGS
/tS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM j6WER 5.01 (1.50)
Low (A-
- c. Highcr (+.5 ea)
- b. tu r. m , H1490L
-c. 4 h g h cr oow tet, ,
REFERENCE . NUS Vol 4, pp 2.2-4 015/000; A1.01(3.5/3.8) l 1 I ANSWER 5.02 (1.00) E l REFERENCE Westinghouse Reactor Physics, Section I-5, MTC and Power Defect DPC, Fundamentals of Nuclear Reactor Engineering St Lucie Reactor Physics, Section 7.6 & 7.7 039/000; A2.05(3.3/3.6) 3 ANSWER 5.03 (1.00) b REFERENCE EIH: GPNT,Vol VII, Chapter 10.1-83-86 BSEP: L/P 02-2/3-A, pp 172 - 176; 02-OG-A, pp 57 - 60 Westinghouse Nuclear Reactor Theory, pp. I-5.77 - 79 - Turkey Point, Reactor Core Control, pp. 4 28 001/000-K5.13 (3.7/4.0)
+
h
- b. Y PAGE 14 1 5 __IHE0BY_QE_NWGLE68_EQWEB_E(8NI_QEEBQIlgN2_ELylQS t 2_6NQ ISEBdQDYN8 digs ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 5.01 (1.50)
Loa t$-
- a. ' t i g.. .- (+.5 ea)
- b. im-- . Ht4g0A
- c. ? lighcr oowit ,
t REFERENCE NUS Vol 4, pp 2.2-4 015/000; A1.01(3.5/3.8) ANSWER 5.02 (1.00) d REFERENCE Westinghouse Reactor Physics, Section I-5, MTC and Power Defect DPC, Fundamentals of Nuclear Reactor Engineering St Lucie Reactor Physics, Section 7.6 & 7.7 039/000; A2.05(3.3/3.6) ANSWER 5.03 (1.00) 6 REFERENCE EIH: GPNT,Vol VII, Chapter 10.1-83-86 BSEP: L/P O2-2/3-A, pp 172 - 176; O2-OG-A, pp 57 - 60 Westinghouse Nuclear Reactor Theory, pp. I-5.77 -.79 - Turkey Point, Reactor Core Control, pp. 4 28 OO1/OOO-K5.13 (3.7/4.0) i I ym
.;* l
- Qs__IBEQ8Y_QE_NUQLEGB_EQWEB_ELONI_QEEBBIlQUz_ELylDS 2_8MQ PAGE 15 ISEBdQQYN001CS ANSWERS -- SEQUOYAH_1&2 -86/12/15-DEAN, WM 1
ANSWER 5.04 (1.00) (A low leakage loading pattern has been employed which places) new fuel assemblies loaded in the center of the core (+&O) . (Theseassembliessee a higher flux for a longer period ( *rE6-) , accelerating the e ects of _ pellet' swell and clad creep relative'to earlier cycles 6*MBE) REFERENCE SON Reactor Physics Review, pp 18/19 001/000; K5.49(3.4/3.7) ANSWER 5.05 (1.50) a) Lower (+.5 ea) b) Lower c) Higher REFERENCE ST Lucie OP 0030126 and Plant Curves CNTO Reactor Core Control, Section 7 001/000; A2.07(3.6/4.2) ANSWER -5.06 (1.50) a) increase; (no answer) (+.25 ea response) b) (no ans); decrease } c) increase; increase d) increase; increase REFERENCE i CNTO " Thermal / Hydraulic Principles II", pp 12-39-45 039/000; A2.05(3.3/3.6) -
,,.- . . , , , ...m,. _ , - - , . - - , . , -_ .-, , - - . -
e ,' . ' , a Vd
- 5. TUERBY_QE_NUQLEGR POWEB_E68MI_QEEB8I1QN 2 _ELUlp@2_8NQ PAGE 16 ISEBdQQYU851Cg ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM r
ANSWER 5.07 (1.00)
- 1) Internal Fuel Rod Gas Pressure (+.5 ea)
- 2) Average Clad temperature REFERENCE SON HCF review, pp 5 001/000; K5. 46 (2. 3/3.~ 6 )
ANSWER 5.08 (1.50) Pu-239 37% (+/-3) (+.3 for isotope, +.1' for %, +.1 for correct order) U-235 35.5% --thermal fission U-235 8% --fast fission OR (A-1 % f 4 1 'lo Aw - L3T 40*/o REFERENCE q.t gg ( 8/. SON /WBN License Cert Trng, " Reactor Kinetics", pp 6 St Lucie Reactor Physics Section 7.6.7; SD 1,'pp 33 001/000; K5.47 (2.9/3.4) ANSWER 5.09 (1.00) Allows for time to identify and correct a dropped or misaligned rod (+1.0) REFERENCE SON TS B 3/4.2.4 EPE-OO3; PWG-5 (2.7/3.9)
, ,,, - -, - ,, , .- -- r - - , - - - , , - - - + - - - - -. - e - - ~ - -
m
.1, i L___IBEQBy_QE_UQCLg88_EQWEB_E66NLQEEB6!1gN i _E(QlDS2 _8ND 17, f "'
PAGE N IMEBdQDXN6dlCS ANSWERS -- SEQUOYAH 1&2 -86/12/;1b-DEAN, WM ,
]N - C
]
ANSWER 5.10 (2.00) t
"/[
.- ; ,'1 Q .
- a. Subcooling is based on core exit T/Cs or hot leg RTD,chadi'/ ige Q During I natural circulation the mass of mdtal in the head can retiin heat and keep local temperatures above saturation. The temperature i'dicbtors n would not reflect this local saturated condition. '( 1. 0 % ,-
( }. :,i
- b. Pressurizer level decreases bec'ause the pressur.izer pressure. increase will compress the vessel vc'id and force" water out of the pr Essu/i::er. f
'j (1.0)
REFERENCE G.P. Heat Transfer and FF Pp 355-358 - EPE-074; EA2.05(3.4/4.2) &- EA2. 07 (4.1/4. 7) 7 ANSWER 5.11 (1.00)_ When slightly open, the pressure dEop is across the valve itself as there is isenthalpic expansion . (+.5) . As the valve i s' 'f ul'l y opened , head losses in the piping become more.significant (+.5) [^
/
REFERENCE c Westinghouse Thermal / Hydraulic Principles, pp 10-71/73-010/000; K5.02(2.6/3.0) 4 ANSWER 5.12 (1.50) s a) Tstm will drop rapidly (+.25) as Tavg> decreases in order to mainfain the Delta T across the S/G tubetr to1 provide the heat transf er to '; support 90% load demand (+.5) N ., s b) Even though pressurizer pressure decreases and power increases, HMich'
- decreases the margin to saturation, the large cooldown of the RCS' 'i+15)"
l overcompensates for this and the margin to DNB increnas (+.25) REFERENCE Westinghouse Transient and Accident Analijsis j 035/010; Kl.09(3.8/4.0) t w r i , g 3 \
' ~
u .-
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ps ' na _ ; ,- y^
. a
- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONi _FLUIQS 2_ANQ PAGE 18 7'e g^ THERMODYNAMICS g G p>
yZ't ANSWERS -- SEQUOYA,H 1&2 -86/12/15-DEAN, WM n e L t s} N ANSWER 5.13 (1.50) a) prevent significant occurrence of =irc-water reaction (+.5) b) as power drops, the enthalpy rise across the core will be less (+.25) with smaller enthalpy increase, the coolant is'further from DNB, allowing a higher F(n) Delta h (+.75) (This allows changes in the radial power shape for all permissable rod insertion limits) REFERENCE SON TS B3/4 2.2 Westinghouse Thermal / Hydraulic Principles II, pp 13-15/16 001/000; K5.46(2.3/3.6) ANSWER 5.14 -- (1.50) a) > DNB, have partial film boiling, where the fuel rod is alternately covered with steam and water (+.25). Steam has poor thermal conductiv-ity capabilities (+.25), so heat transfer rate drops and Delta T rises (+.25) b) As fuel surface temperatures rise, stable steam layer forms (+.25) causing a further increase in fuel rod temperatures (+.25). Eventually, significant radiative heat transfer occurs causing heat ufer rate to e incarease (+.25) i L REFERENCE e pestinghouse Thermal / Hydraulic Principles II, pp 13-18/20 amt Hrn PP M-Vi EPE-074; EK1.02(4.6/4.8)
}, * ,
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i c ' .' - . O r' 6z__ELGUI_EYSIEUS_DEQ1QU1_QQNIBQ61_8BD_INSIBUdENIQIlgN 3 PAGE 19 ANSWERS - -SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER Si 1 (1.00) OL REFERENCE , SON Requal 1986 week 2, day 1, " Major Modifications", pp S/9 061/000; K4.04(3.1/3.4) ANSWER 6.02 (1.00)' d REFERENCE FNP, RHR Lesson Plan, pp. 8&9 NA NCRODP 88.2, "RHR System" SQNP lesson plan "RHR System" pp 5 OOS/OOO-K4.07 (3.2/3.5) ANSWER 6.03 (1.50) , 1 a) Arm and actuate b) Arm and actuate c) Arm only ; REFERENCE <' /' Farley SD, " Steam Dump System", pp 23-28 SONP System Descrip. " Steam Dump System", pp 6-8 041/020; K4.11 (2.8/3.1) & M4.14 (2.5/2.8) & K4.17 (3.7/3.9)] < ANSWER 6.04 (1.50) , i Containment Hi-Hi pressure; 10; S/G enclosures; oZh enclosure; .,- accumulator spaces; instrument room (+.23 ea) REFEPEW..E Westinghouse PWR Systems Manual, sect 4.5, pp 14 022/000; PWG-4 (3.5/3.8)
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i O'- . ,
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p' 6. ~ PLfiNI_@ySIEMS_QEglGN 2 _GQNIBQL 2 _@NQ_INSIBut1EtjI@IlgN PAGE 20 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM y
!./
ANSWER 6.05 (1.00)
- 1) Chloride ~ concentration (+.2 ea)
- 2) pH
- 3) Dissolved O2
- 4) Entrained H2
- 5) Conductivity REFERENCE SON Requal 1986 week 4, day 1, "PASF", pp 7 ANSWER 6.06 (1.50) foremy 9
-Phase A Containment Isolation signal from either Unit (+.375 eai
-High Radiation signal from fuel handling bldg area rad monitors---l Au? Bldg exhaust vent rad monitors V
-High Temperature in Aux Bldg Supply Fan Suction -
n u. ca w 4e Splei m fo REFERENCE AM4o-tote p h SONP Sys Descr. 4.4, " Cont Air Purif and Cleanup Sys" pp 15 g g p .,o p pg fd u DaJ4 4fA/ 630-Y EPE-060; PWG-10 (4.1/4.4) ANSWER 6.07 (1.50) 1 Open CCW pump brem r (+.3 ea)
- 2) R cet SI
- 3) Res t EDG lo ,out -
- 4) Start EDG
- 5) Manual oad equipmen a
REFERENpd' SON E EDST EP 055; EA2.06(3.7 .1), PWG-11(4.3/4.4) l/ 9)
a 6:
.. pc PAGE '21 37 6 __E60NI_gygIgdg_ peg 1GN2_CONIB06,_8ND_INSIhydENIATION ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER ~6.08. -(2.50) a) Pzr level Hi-Low Alarm (+.25 ea)
Charging Flow increases Level increases to 60% (Limited to 100% power program) b) One Ltdn isolation valve shuts All orifice valves shut Pzr Level Low, Htrs Off, Ltdn Secured alarm Heaters turn off Level rises as charging flow reduced to flow through seals
-Pzr level Hi/ BU htrs on alarm Rx trip on high level REFERENCE Sqn Requal 1986 week 3, day 4, " Instrument Failures", pp 31/34 011/000; K1.01(3.6/3.9), A2.11(3.4/3.6)
ANSWER 6.09 (1.00) a) (Supersaturating cores causing high hysteresis losses) resulting in damage to generator and transformer windings from overheating (+.5) b) -After 15 seconds, base adjust runs to AFNL (amps field no load) and
~
the regulator is tripped off (+.25)
-30 seconds later(45 seconds), field breaker is tripped (if generator-PCBs are open) and trips the turbine (+.25)
REFERENCE Requal 1986 week 3, day 2, " Excitation System", pp 6-13 045/000; K6.02(1.7/1.9) Note: emphasized as a learning obj in requal ANSWER 6.10 (1.50) a) S/Gs #1 and 4 (+.5) b) (Appendin R requirement) PORVs were inaccessible for fire in the "- , West Valve Room (+.5) Only 2 S/Gs are required for safe shutdoun (+.5) i- REFERENCE SON Requal 1986 week 2, day 1, " Major Modifications", pp 5 4 035/010; K4.05(3.1/3.4) 4
..e 9
r' 6- PL8NI_gXSTEMS_pg@l@N1 _QQtjlBQL_2_8NQ_INSIBUMENIAIION PAGE 22 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 6.11 6.dsY M,@H a) demister>>> relative humidity heater >>>prefilter bank >>>HEPA filter bank
>>> Carbon adsorber bank >>>;;__i... P. atin; _1 - .... . . s > > hc ar b o. - _d r ~ b-r Aartt:t>>HEPA filter bank (+.125 ea) b) Two cross over air flow oucts draw air from the active air cleanup unit
(+.5) i REFERENCE SONP Sys Descrip. 4.4, " Containment Air Purif and Cleanup System" pp 7-8 027/000; A2.01 (3.0/3.3) ANSWER 6.12 (1.00)
] -Operate the solenoid bypass switch to the " Bypass" position on the console L175 ) Aew
-Use the gripper control knob on the consolo to operate the grippgr (F7.i/
REFERENCE SON LP OPL271C014, SON FHI 1-4A 034/000; PWG-6(2.7/3.3) ANSWER 6.13 (1.50) 4 l' SUMP via 63-72 to suction of A RHR pump thru A RHR b( (+.5) and either to 63-8)> >63-6 ( 7) > >S I pump suction (+.25) or 63-172 to loops 1 and 3 (+.25) after the SI pump >>63-156 to hot ' legs /('and JP (+.01 3 REFERENCE SON ES-1.3 EPE-011; EX3.08(3.9/4.1) 1
e
~Z___EB9GEDUBES_:_N9Bd862_8BN9Bd862_gdEBGENgy_8NQ PAGE' 23 8891969 GIG 86_GONIB96 ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 7.01 (1.00) b REFERENCE SON AOI-34A, pp 1 EPE-024;'EK3.01(4.1/4.4)
ANSWER 7.02 (1.00) d REFERENCE SON LER 85-040-000; SON "RHR", pp 13 005/000; PWG-7(3.5/3.8) ANSWER 7.03 (1.00) G REFERENCE FR-Z.2 EPE-069; EK3.01(3.8/4.2) ANSWER 7,04 ( 1. 0' 0) c pc h REFERENCE SON AOI-21.7, pp 1 "-- EPE-058; PWG-10(4.1/4.2)
s-Z ._ PRQQgpUBgg_- _NQBMA62_8@NQBMAL2_EMEBGENQ'(_8NQ PAGE 24' 88D1060 GIG 06_QQNIBQL J ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM 4 ANSWER .7.05 ( .50) false (+.5) REFERENCE SON FR-S.1, step 3 EPE-029; PWG-11(4.5/4.7) ANSWER 7.06 (1.00) a) True (+.5 ea) b) Fa1se REFERENCE Westinghouse User's Guide, pp 5, 17, 18 PWG-22(4.3/4.3) I ANSWER 7.07 (2.00) 4 g 1) Increase Injection Flow (+.3 for technique, +.2 for position) g 2) Depressurize S/Gs c#g# 3) Start RCPs i.M 4) Open RCS vent paths (PORVs) REFERENCE FR-C.1; (TPT QBNK H-5) EPE-074; EK1.03(4.5/4.9) l ANSWER 7.08 (1.50) , . , eq
- 1) cccept-retuonW
< inn s e _- r owar rtcr emaN' a ti...,caersFW (+.5 WWW ea) # d-a kud M ,
- 2) Assembly from the highest core power region #cch uad df A
(
- 3) All fuel rods damaged REFERENCE SON AOI-29, pp 5, 8 j TQM TS J 9.5 EPE-036; EK3.03(3.7/4.1) i
u . 4' Zs__BBQGEQUBES-- NQBM863_8BNQBd@62_EMEEGENCY AND PAGE 25 8091960 GIG 86_GQNISQL ANSWERS--- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 7.09 (. 75).[ec- M 3
- 1) ASE (+.25 ea)
- 2) Outage Coordinator
- 3) - Other SEs assigned to the shift
-b C M *%s.hedb$g W REFERENCE SON AI-3, pp 2 PWG-14(3.6/4.O)
.0b ANSWER 7.10 h+2. 2 J Q,b-fpo)K. h!V (M]e
-Verify steam st ps closed (+.25 ea) 664pf -h// AURW op.2-
-Verify AFW pu s running and flow established ,
gP gMPg 0
-Verify PZR p essure within 1900-2235
-Verify PZR evel within 24-60% ~ N d N /fl Ni Ji44Il w Q
-Verify T g controlling at 547 degrees
-Verify ntainment pressure and temperature normal
-Verify generator breakers open and 6.9 KV unit station service xferred
-Verif Main feed isolation
-Ver y main feed pumps' tripped (OIf (f. 3 3pc)
I REFERENCE SON AOI-27A, pp 1/2 f[ovi[f[F( pp,d1 e wJeg EPE-069; PWG-11(4.5/4.5) ANSWER 7.11 (1.00) This allows S/G Pressure protection without having to depend on the code safeties (+.75) which could lift and not reseat causing an unisolable steam leak (+.25) REFERENCE ,- Westi7hhouse Background Document; (TPT QBNK E-16) EPE-038; EK3.06(4.2/4.5)
e
- 7. PROCEDURES - NORMALx_ABNQRM862_EMEBGENgY_AND PAGE 26 E8 Dig 6QGIG86_GQNIBQL ANSWERS -- SEQUOYAH 1&2 -86/12/15-DEAN, WM ANSWER 7.12 (1.00)
- 1) (Promote thermal stratification) so ruptured S/G doesn't depressurize during cooldown (+. 5 eafor esy 2)
- 2) Ensures S/G available as a heat sink if required 3)
E FERENCE-fodth JCw WM 3+ M(*MIM Iff 4D'd Westinghouse ERG Background Document; (TPT QBNK 18) EPE-038; EK3.06(4.2/4.5) ANSWER 7.13 (1.50) RCPs will keep 2_ phase flow mixture (+.75) and the PORVs will not be able to release as much steam (energy) (+.75) ce Uk< Wit PMirvel wru. Devuor rr reow C+-)r) eb putngse ywrintropy coss our Mh O'? REFERENCE i Westinghouse background document l EPE-074; EK3.08(4.1/4.2) ANSWER 7.14 (1.00)
- 1) Faster cooldown (+.5 ea)
- 2) Maximum radiological release REFERENCE SON ES-3.1, pp 10 EPE-138; EK3.06(4.2/4.5)
ANSWER 7.15 (1.50)
. , ~
Normal wear reduces this design criteria of a new seal, making it hard to predict how long it will last.(+.5) So by removing the pump from service, minimize the chance of a #2 neal failure. (+1.0) REFERENCE SDN AOI-23, pp3 003/000; PWG-7(3.5/3.9)
.________________.__=_=a_t=e=t_uuw_scuilc11wc2 PHbt 6
e ANSWER 3 -- CEQUOYAH'1L2 -86/12/15-DEAN, WM ? ANSWER B.01 (1.00) b. REFERENCE SONP, IP-1 ANSWER B.02 (1.00) c. REFERENCE North Anna TS 3/4 1-1,-9,-12,-22 Farley TS 3//4 Sequoyah TS 3/4 ANSWER B.03 (1.00)
- a. false
- b. f ;; ;; 7nur REFERENCE SONP Requal Trng. Inst. Notes -
ANSWER B.04 (1.50)
- a. false
- b. false
- c. true REFERENCE SONP AI-4, 12.1 ANSWER B . Of' ( .50)
SE, Shift Engineer REFERENCE SONP AI-2, 1.1
a PAGE f0__e901N1SlB@llVE_PQQCEQUBE@t_CQNQlligNSt_QNQ_Lidll@llgN@ , ANSWERS -- SEQUDYAH 1&2 -86/12/15-DEAN, WM t ANSWER 8. 4% (1.50)
- 1. Seismic Instrumentation
- 2. RCS Operational Leakage or SG tube leakage
'3. RCS Speci fi c Acti vi ty
- 4. Containment Systems or Containment Vent Systems
- 5. Plant Systems Specific Activity or Secondary Plant Activity
- 6. Flood Protection
- 7. Snubbers any 5 CO.33 each REFERENCE SQNP TS Bases SONP Requal Trng. Inst. Notes ANSWER B.07 (2.00)
- 1. U-1 and U-2 shield b1dg. gas monitors count rate.
- 2. U-1 and U-2 shield b1dg. stack flow rate.
- 3. Aux b1dg. gas monitor count rate.
- 4. Aux b1dg. stack flow rate.
- 5. Service bldg. gas monitor count rate.
- 6. Service bldg. stack flow rate.
- 7. U-1 and U-2 condenser vacuum exhaust monitors count rate.
- 8. condenser vacuum exhaust assumed to be 45 %cfm each. CO.253 each REFERENCE SONP TI-30 SONP Requal Trng. Inst Notes ANSWER 8.06 (1.00)
Person holding the operating permit. , N REFERENCE > SONP Al-3; 3.1.7.1.
Ut__e901Nig16811yE_P6QgEDYSESg_QQNDillQNS _@ND_ i Lid 11011QNQ PAGE r ANSWERS -- SEQUOYAH 1&2 -C6/12/15-DEAN, WM ANSWER 8.og (1.00)
- a. SDN IP-1, Emergency Plan Classification Logic
- b. General Emergency REFERENCE SON IP-1 SONP Requal Trng. Inst. Notes; REP ANSWER O.10 (1.50) one path from boric acid tanks via a boric acid transfer pump and a charging pump to the RCS. [0.53 two paths f rom the RWST via charging pumps to the RCS. [1.03 REFERENCE SQNP TS 3.1.2.2 ,
- ~
ANSWER B .11 (1.00)
- a. the unit shall be placed in at least Hot Standby within one hour,
- b. the NRC Operations Center shall be notified (by telephone as soon as possible and in all cases) within one hour. CO.53 each REFERENCE SONP TS 6.7 ANSWER B.17, (1.00)
LCO 3.0.3 applies REFERENCE "- North Anna LCO 3.0.3. FNP 3.0.3 SONP 3.O.3
c - 4 }
, 9t__eDDINIS16@llyE,P6QQEDQ6E@t_QQNDil1QNS i ,@ND_(ldll@llQNS PAGE o
. ANSWERS -- SEQUOYAH 1&2 -C6/12/15-DEAN, WM h
ANSWER 8. 13 (1.00) temp. does not exceed that temp. allowable (for the continuous duty rating specified) for equipment and instrumentation. REFERENCE SONP TS 83/4.6.1.5 SONP Requal Trng. Inst. Notes ANSWER 8 ly (2.00) [030 The TA shall be entered on a PORC r evi ewed 4 0. Ji, Plant Manager[c. 2 s) 40.33 approved TACF [O.53 gnd +=gged i r, occardance ith ^I o EO_5' & REFERENCE SONP AI-9 s ANSWER 8.J$ (1.00) AFD ( f or each operable channel) must be monitored and logged [0.53 at least once per hour CO.53 (for the first 24 hours and at least once per 30 minutes thereafter). REFERENCE SONP TS 3/4.2.1 p
ENCLOSURE 3 (86-03) a tf d QUESTIONS - RO Requal 1.01 (1.50) R0 License 1.03 (1.50) SRO Requal 5.01 (1.50) SRO License 5.02 (1.50) Indicate whether the following will cause the power range instrument to be indicating HIGHER, LOWER or;the SAME as actual power, if the instrument has been adjusted to 100% based on a calculated calorimetric.
- a. If the feedwater temperature used in the calorimetric was higher than actual feedwater temperature,
- b. If the reactor coolant pump heat input used in the calorimetric is omitted.
- c. If the steam flow used in the calorimetric was lower than actual.
ANSWER
- a. Higher
- b. Lower
- c. Higher i REFERENCE NUS Vol 4, pp 2.2-4 015/000; A1.01 (3.5/3.8)
Answer to part a. should be lower. Using a higher feedwater temperature would cause the ah across the S/G to be lowar resulting in a lower calculated (indicated) power than actual power Q = moh Answer to part b. should be higher. Calorimetric calculation uses the following equation reactor power
~
Reactor Power = NSSS power - Reactor Coolant Pump Energy Input Neglecting RCP input would make indicated (calculated) power greater than actual power (Reference TI-2; attached) Answer to part c. should be lower. The S/G heat balance uses the following equation to calculate NSSS power Q = moh Using a lower m would cause calculated power (indicated power) to be lower than actual power.
et , e QUESTIONS - RO Requal 1.03 (1.00) RO License 1.04 (1.00) SRO Requal 5.03 (1.00) SRO License 5.03 (1.00) Attached Figure #219 shows a power history and four possible zenon traces (reactivity vs time). Select (a, b, c, or d) the curve that correctly displays the expected renon transient for the given power history. ANSWER C REFERENCE EIH: GPNT, Vol VII, Chapter 10.1-83-86 BSEP: L/P 02-2/3-A, pp 172 - 176; 02-0G-A, pp 57 - 60 Westinghouse Laulear Reactor Theory, pp. I-5.77 - 79 Turkey Point, Reactor Core Control, pp. 4 28 001/000-KS.13 (3.7/4.0) b is the correct answer Reference attached plot from
- XENON (PRIME computer program of Ienon at reactivity worth as a function of time) t
,.,--r-, . . , - - - - - - - . - - - ,
--,.--,---,-,.-,e,- , - , . , ,,n. ,, , - , , ,-,, --- --.m,- - - . . _ .,-m-,e , -,, y - - - - - - - ,,
i
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es , QUESTIONS - RO Requal 1.07 (1.00) R0 License 1.10 (1.00) SRO License 5.10 (1.00)
- a. Which power defect is the major contributor to the Total Power Defect at EOL7
- b. What is the major cause of the existence of a void defect?
ANSWER
- a. Doppler defect (+.5)
- b. Nucleate boiling REFERENCE Westinghouse Reactor Core Control, pp 3-38/42 001/000; KS.49(3.4/3.7)
Part a. Answer should be either Moderator and Doppler make roughly the same contribution at EOL or Moderator is major contributor. Cycle 4 data indicates that Moderator and Doppler make roughly the same contribution at EOL (Reference attached Requal lesson plan and design report curves). However, in previous cycles, moderator has always dominated at EOL. 9
1 QUESTIONS - R0 Requal 1.09 (1.00) RO License 1.14 (1.00) List the four most significant causes of Non-condensible gas formation in the RCS during the first hour following a LOCA. Assume the PZR empties after several minutes and forced convection flow is not available. Also, pressure does not drop to a level requiring any SI tank to inject and fuel rods have not ruptured. ANSWER
- 1) Dissolution of H2 (due to mass loss of pressure drop) (+.25 ea)
- 2) Radiolysis
- 3) PZR vapor space expansion
- 4) Zirc-water reaction REFERENCE SQN EGT 222.006, pp 23 EPE-009; EK3.11 (4.4/4.5)
" Gases from the pressurizer vapor space" should be accepted in lieu of
" Pressurizer Vapor Space Expansion" (Reference Requal Lesson Plan attached)
G G _.,e , _ _ _ , - . - . . , _ . - _ _ _ , _ _ . . _ _ _ . - . . _ . . _ . _ _ _ . , , ~ , . _ . . _ . . - . . . _ , - , . . . .--,-.,._-,-m._-_-,,-.._.m_ -
QUESTIONS - RO Requal 1.10 (1.50) RO License 1.11 (1.50) SRO Requal 5.08 (1.50) SRO License 5.11 (1.50) List the three main sources of fission neutrons in the core at each end of life and indicate their approximate contribution (in %) to power. ANSWER Pu-239 37% (+/-3) (+.3 for isotope, +.1 for %, + .1 for correct order) U-235 35.5% --thermal fission U-235 8% --fast fission REFERENCE SQN/WBN License Cert Teng, " Reactor Kinetics", pp 6 St Lucie Reactor Physics Section 7.6.7; SD 1, pp 33 Question did not solicit an order nor did it solicit seperating thermal and fast fission contributions. Candidates learned cycle 4 numbers. Therefore the following numbers should be accepted: (Reference attached Figure from
- Requal Lesson Plan)
, U-235 431 Pu-239 40% U-238 8%. W 4 6
. - - . - . _ . _ _ - _ _ _ _ . - _ _ _ _ . _ _ - ,-,.7- _ _ _ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ . _ _ , _ . - - - _ , _ _ _ _ - - _ _ . _ _ _ _ _ , . _ _ _ _ _ - . . . - . _ . _ _ _ ~ -
QUESTION - RO Requal 2.03 (1.00) Which of the following describes the basic flowpath through the Hydrogen Recombiners?
- a. Mixing chamber, preheater, recombination region
- b. Mixing chamber, recombination region, heater section
- c. Preheater, recombination region, mixing chamber
- d. Preheater, mixing chamber, recombination region
- e. Preheater, mixing chamber, heater section ANSWER C
REFERENCE Surry ND-88.4-LP-8, pp 8.6 Westinghouse Systems Manual cpp 4.5-20 028/000; K6.01(2.6/3.1) This is not even remotely related to safe operation of the plant. Delete the question. (Reference NUREG 1021) f r I
hO QUESTION - R0 Requal 2.04 i (2.00) a) For the following loads, indicate what combination of ERCW headers (1A. IB, 2A and/or 2B) is the NORMAL source of cooling water:
- 1) CCS Heat Exchanger "C"
- 2) EDG Heat Exchanger :2A-A
- 3) Containment Spray Heat Exchanger IB b) What 5 criteria / interlocks must be met for ERCW pump KA to auto start?
ANSWER a) (1) 2B (+.33 ea) (2) 1A (3) IB b) (1) SI from Train IA or 2A (+.2 ea.) (2) No blackout signal (3) Transfer switch on swgr in Normal (4) KA selected for operation (5) Purp RA not running REFERENCE SQN Requal 1986 week 1, day 4. "ERCW", pp 4-9 076/000; K1.01(3.4/3.3), K1.05(3.8/4.0), K1.19(3.6/3.7), K4.02(2.9/3.2) Should also accept the following:
- 1) Control Board Handswitch in Auto
- 2) No Lockout
- 3) Control Power Available (Reference SQN Drawing 45N765-15) 4 4
QUESTIONS - RO Requal 2.06 (1.00) RO License 2.14 (1.00) SRO License 6.11 (1.00) Provide the system pressures at which the following ECCS components will start to inject following a LOCA: (use criteria stated in E0Ps)
- a. SI Pumps
- b. RHR pumps
- c. Upper Head Injection ANSWER
- a. 1500 psig (+/- 25 psig) (+.33 ea)
- b. 180 psig
- c. 1250 psig REFERENCE SQN E-0, pp 3. Westinghouse Systems Manual, pp 4-1-33 EPE-Oll; EK3.12(4.4/4.6)
Should accept 1185 psig to 1285 psig for part c. (Reference SQN Tech Spec LCO 3.5.1.2) 1
- , ,=
QUESTIONS - RO Requal 2.09 (1.00) R0 License 2.17 (1.00) SRO License 6.13 (1.00) What 4 different ECCS related components are tagged out at low pressures to help prevent inadvertant over pressurization at low temperatures? ANSWER
-SI Pumps (+.25 ea)
-ONE Centrifugal Charging Pump
-UNI Gags
-Cold leg Accumulator Isolation Valves REFERENCE SQNP System Descrip. "RCS", pp 9 001/000; Kl.02 (3.9/4.1)
SQN GOI 3B only requires the SI pumps and Cold Leg Accumulator Isolation Valves to be tagged out. UHI gag motors are only required to have power removed and the one Centrifugal Charging Pump is only required to be pulled to lock. The UHI gag motors and the one Centrifugal Charging Pump can be tagged at the discretion of the Unit ASE, but are not required to be tagged. Therefore, the only 2 required responses to this question are SI pumps and Cold Les Accumulator Isolation Valves. (
-,-,-,-.,e- - - - - , , , , , - - . - . . , - - - - , - n-,,,- ,.-.,,--.c
on a. ,' QUESTIONS - RO Requal 2.11 (1.50) RO License 2.19 (1.50) SRO Requal 6.11 (1.50) SRO License 6.17 (1.50)
- a. Describe the order of processing elements in the Air Cleanup Units through which air is drawn by the Air Cleanup Subsystem.
- b. How are the processing elements in an INACTIVE air cleanup unit loaded with radioactive material kept cool?
ANSWER
- a. deminster>>> relative humidity heater >>>prefilter bank >>>HEPA filter bank >>> Carbon adsorber bank >>> electric heating element >>> carbon adsorber bank >>>HEPA filter bank (+.125 ea)
- b. Two cross over air flow ducts draw air from the active air cleanup unit
(+.5) REFERENC2 SQNP Sys Leccrip. 4.4, " Containment Air Purif and Cleanup System" pp 7-8 027/000; A2.01 (3.0/3.3) Part a should not require that the processing elements be listed in order. It is quite sufficient that the candidate know what the elements are, not necessarily what order they are in. Also, the electric heating element between the charcoal banks does not exist. (Reference SQN Drawing 47W866-1)
,. . _ . _ _ , - , _ . _ - , _ - - , _ _ - - , _ _ _ . , - - - . _ -m ,_ _ . - - - . - - - - , _ _ --,. -----w,,,--,_--- -
gp pu) 33V QUESTION - SRO License 6.06 (1.00) Which one of the graphs A-D in figure 603 correctly depicts the Pressurizer Pressure control system, Master controller output signal, based upon the demand signal shown? ANSWER d. REFERENCE SQN Requal 1986 Week 5/6, day 7. " Control System Theory" 202002 K4.08 3.3/3.4 5.03 2.4/2.4 None of the four answers is correct. The output of the pressurizer pressure controller is parabolic due to the fact that it is a proportional-integral (PI) controller. Delete question. (Reference attached output graph TI-41 scaling data sheet, and SQN Calibration Card).
- - - . - - -, - , - ,- - . - - -- .,,,,- .- ---- - - ~_ , , _ _ . _ - . , - - . - . - - , - . - -
e',, QUESTIONS - R0 Requal 3.03 (1.25) R0 License 3.05 (1.25) Describe what happens to the coils associated with the CRDMs and what 2 alarms / indications actuate on an Urgent Failure of the rod control system. ANSWER The stationary and movable grippers energize and the lift coil deenergizes (+.75); ROD URGENT FAILURE Alarm and red lamp at power cabinet actuate (+.5) REFERENCE SQN " Rod Control System", pp 12 001/050; A2.01(3.7/3.9)
" Urgent Failure lamp on Logic Cabinet" should also be accepted.
(Reference Westinghouse Rod Control Training Manual attached) e 4
e ,, - QUESTIONS - R0 Requal 3.05 ( .50) RO License 3.07 ( .50) TRUE or FALSE: If the upper detector on a power range NI fails low while at' 75% power, the operation of the upper detector current comparator is defeated. ANSWER true (+.5) REFERENCE SQN "Excore NIs", pp 18 015/000; 6.04(3.2/3.4) Answer is False. All four detectors'below 50% power are required for auto defeat. A failed detector can be manually defeated on the NIS panel, but the question implies an auto defeat. Reference NRC Systems Manual Westinghouse NIS Training Manual f
- , e--.y, .-ym---,-----,------------.--------y,---.-,,. -- -- -- - - - - - - ,,
e'., QUESTIONS - RO Requal 3.07 (1.50) R0 License 3.11 (1.50) SRO Requal 6.06 (1.50) SRO License 6.12 (1.50) What 4 signals will automatically initiate the operation of the Auxiliary Building Gas Treatment System? ANSWER
-Phase A Containment Isolation signal from either Unit (+.375 ea)
-High Radiation signal from fuel handling bids area rad monitors
-High Radiation signal from aux Blds exhaust vent rad monitors
-High Temperature in Aux Bldg Supply Fan Suction REFERENCE SQNP Sys Desce. 4.4, " Cont Air Purif and Cleanup Sys" pp 15 EPE-060; PWG-10 (4.1/4.4)
High Radiation from RM-90-102 and RM-90-103 (Spent Fuel Pit Rad Monitors) are separate signals. RM-90-102 will only cause 'A' train ABGTS initiation and RM-90-103 will only cause 'B' train ABGTS initiation. Therefore, credit should be given for these two signals as seperate signals. (Reference Plant Drawing 45N630-4 attached)
( d fli) N QUESTIONS - SRO Requal 6.07 (1.50) SRO License 6.15 (1.50) - An SI signal was generated due to a transient caused by'an undervoltage +s ' condition on the 2A-A 6.9KV Bus. During this transient, the 2A CHG Pump breaker stayed closed causing an EDG lockout. (afl other loads were removed) ; ( What 5 actions must the operator take to load equipment on that bus using the >* 2A-A EDG?
,^ i L-4 ANSWER
- 1) Open CCW pump breaker (+.3 ea.)
- 2) Reset SI
- 3) Reset EDG lockout
- 4) Start EDG
- 5) Nanually load equipment REFERENCE o SQN ELEDST ,
EPE 055; EA2.06(3.7/4.1), PWG-11(4.3/4.4) Question implies that a D/G lockout occurred as a result of the transient. An undervoltage condition on the shutdown board er an SI signal will cause an emergency start of the D/G which will allow only Generator Differential or Engine Overspeed to trip the D/G. Also, the'overcurrent relay on the Diesel Breaker will not trip the breaker unless either the normal or alternate feeder breakers are closed. If the Diesel is tied to the board by itself, there is no overcurrent protection on the Diesel breaker. Delete the question due to confusion caused by implication that D/G will lockout if 2A-A Charging pump breaker does not load shed. Reference attached drawings 45N767-2 45N767-4 45N767-5 45N765-2 h
-, _ , _ - , - . . , - _ , _ _ , . ,y . ,m- , _ _ _ _ . . _ - _ . - _ _ _ . . _ . _ - . , - - -- - .--,
4
, QUESTIONS - RO Requal 4.05 (1.00)
R0 License 4.05 (1.00) SRO Requal 7.04 (1.00) SRO License 7.06 (1.00) The loss of which one of the;following 125 VDC Vital Battery Boards will cause a reactor trip and also number 2/4 S/G MSIVs and main feed regulation bypass valves to close?
- a. Unit 2. Board I
- b. Unit 1. Board II
- c. Unit 2, Board III
- d. Unit 1. Board IV ,
' ANSWER c
REFERENCE SQN AOI-21.7 pp 1 EPE-058; PWG-10(4.1/4.2) b and c are both correct answers. Loss of 125V Vital Battery Board II will cause a reactor trip on Unit 1 and 2/4 S/G MSIVs and main feed regulating 4 bypass valves to close. Reference SQN AOI 21.2 O
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~
QUESTION - 80 Requal 4.10 (.75) Aside from the on-shift SE (Shift Engineer), what other 3 personnel may authorize clearances at Sequoyah Nuclear Plant? ANSWER
- 1) ASE (+.25 ea)
- 2) Outage Coordinator
- 3) Other SEs assigned to the shift REFERENCE SQN AI-3, pp 2 PWG-14(3.6/4.0)
Chickamauga Load Dispatcher (CLD) should also be accepted P t a b
-- .--,y-, _ . . . _ - - - - -- -. ,y, ,,-, -. --
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. i l QUESTIONS - RO Requal 4.15 (1.00)
RO License 4.20 (1.00) SRO Requal 7.12 (1.00) SRO License 7.19 (1.00) E0P E-3. "SGTR", requires the operator to maintain AFW flow to the rupture S/G until natrow range level is established. Provide two reasons for this procedural requireseat. ANSWER
- 1) (Promote thermal stratification) so ruptured S/G doesn't depressurize during cooldown (+.5 ea)
- 2) Ensures S/G available as a heat sink if required REFERENCE
. Westinghouse ERG Background Document; (TPT QBNK 18) EPE-038; EK3.06(4.2/4.5) Iodine Scrubbing by the liquid portion of the S/G mass should be accepted as one of the two regired responses. AFW flow should be maintained until the tubes are covered to assure that the breat is not open to the steam space so that iodine can be retained in solution to prevent exceeding offsite dose limits Reference Westinghouse Steam Generator Tube Rupture Training Manual attached. e 4
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- - --7.,. - - - - - - ,- , -. , -,, , , .. -
..,g. ,
QUESTIONS - SRO Requal 5.05 (1.50) SRO License 5.07 (1.50) AN ECC is calculated for a startup following a reactor trip from 50% power equilibrium renon (BOL). Indicate if the actual critical rod position will be HIGHER, LOWER or the SAME from the calculated position for each of the following situations. Use attached curves as appropriate and treat each case individually,
- a. Zenon reactivity curve for trip from 100% is used to calculate conditions to startup 20 hours after the trip.
- b. Boron worth at EOL is used vice BOL worth. (Dilution is required to reach desired Boron concentration in both cases) c.
The EOL critical Boron Concentration is used instead of the BOL critical Boron concentration. ANSWER
- a. Lower (+ .5 ea)
- b. Lower
- c. Higher REFERENCE SI Lucie OP 0030126 and Plant Curves CNTO Reactor Core Control, Section 7 Part c cannot be answered. Critical Boron Concentration can vary greatly at BOL and EOL. There is no one BOL Critical Boron Concentration or EOL Critical Boron Concentration. Not enough information supplied to answer the question.
Delete the question. 1 I .
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QUESTIONS - RO License 1.20 (l.C0) SRO Requal 5.11 l (1.00) The attached figure shows the change in pressure across a pressurizer PORY and its associated upstream and downstream piping for various valve positions. EXPLAIN why the major pressure drop occurs in piping segment Pl-P2 when the valve is slightly open, whereas the major pressure drop occurs in piping segment P2-P4 by the time the valve is fully open. ANSWER When slightly open, the pressure drop is across the valve itself as there is 1senthalpic expansion (+.5). As the valve is fully opened, head losses in the piping become more significant (+.5) REFERENCE Westinghouse Thermal / Hydraulic Principles, pp 10-71/73 010/000; KS.02(2.6/3.0) Some credit should be given for a discussion of increased frictional losses through a throttled valve causing a larger pressure drop just downstream of the valve. Alpo, it is doubtful that any candidate will usa the term "isenthalpic expansion" in their discussion. Answers that include discussions of unrecovered head loss due to high velocity steam passing through the throttled valve should also be considered. e
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f on d o, ' QUESTIONS - SRO Requal 6.04 (1.50) SRO License 6.10 (1.50) Fill in the blanks in the statement below concerning the Containment Air Return System: Both fans are actuated upon an actuation signal but are delayed starting for minutes. They continuously draw air from the dome of the containment vessel and from the following pocketed spaces , , ,and a ANSWER Containment Hi-Hi pressure; 10; S/G enclosures; PZR enclosure; accumulator spaces; instrument room (+.25 ea) REFERENCE Westinghouse PWR Systems Manual, sect 4.5, pp 14 022/000; PWG-4 (3.5/3.8) Eithee Containment Hi-Hi Pressure or Phase B are acceptable answers. Containment Hi-Hi Pressure generates a Containment Isolation Phase B signal which starts the Air Return Fan Timers. (Reference SQN Drawing 45N779-5)
,--,-4-,.-.,,-.,,-------n-,. - - - , , .- , , - - - , - , -,,- ,--w. ,,,- - , , ,, m.,- , - - - . > ,,,,_,,,*
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- QUESTIONS - SRO Requal 7.08 (1.50)
SRO License 7.13 (1.50) AOI-29, " Dropped or Damaged Fuel Assembly", discusses the " Worst Case" event of a dropped and damaged fuel assembly. What are the 3 criteria, that if met, could result in a radioactive release high enough to require implementation of the REP? (ie. the worst case) ANSWER
- 1. < 100 hours after shutdown (+.5 ea)
- 2. Assembly from the highest core power region
- 3. All fuel rods damaged REFERENCE SQN AOI-29, pp 5, 8 EPE-036; EK3.03(3.7/4.1)
Tech Spec LCO 3.9.3 does not allow movement of irradiated fuel in the reactor vessel unless the reactor has been suberitical at least 100 hours. Therefore, the less than 100 hours after shutdown criteria should not be required as part of the answer. I
. .dk , o QilESTION - SRO Requal 7.13 (1.50)
SRO License 7.20 (1.50) The Response Not Obtained for step 1 of FR-H.1. " Response to Loss of Secondary Heat Sint" states: If ALL S/G Wide Range levels < 25%, then STOP ALL RCPs and immediately initiate feed and bleed per steps 11 to 13. Why are the RCPs tripped prior to initiating-feed and bleed, aside from the fact that heat input from the pumps will be removed? ANSWER RCPs will keep 2 phase flow mixture (+.75) and the PORVs will not be able to I release as much steam (energy) (+.75) REFERENCES Westinghouse background document EPE-074; EK3.08(4.1/4.2) There is nothing in the Westinghouse background document that supports this answer. All of the reasons for tripping the pumps in the background document are related to RCP heat input. Delete the question. 6 e i
l
- l. . %dI'.,
- QUESTIONS - SRO Requal 8.03 (1.00)
SRO License 8.05 (1.00) True or False
- a. Rad Tumbler Sets are installed on doors leading directly to high radiation areas but not exceeding 1000 mr/hr.
- b. The Plant Health Physicist controls the keys to the Rad Security Locks ANSWER
- a. false
- b. false REFERENCE SQNP Requal Trng. Inst. Notes Part b. is true. The Plant Health Physicist and the Shift Engineer control Keys to the Rad Security Locks.
' ENCLOSURE 4 REQUALIFICATION PROGRAM EVALUATION REPORT Facility: Sequoyah Nuclear Plant Examiner: W. Dean, D. Nelson, L. Lawyer, C. Shiraki, J. Whittemore Date(s) of Evaluation: December 15-18, 1986 Areas Evaluated: X Written Oral X Simulator Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M or U) Written Examination 1/3 7/1- 8/4 M Operating Examination . Oral N/A N/A N/A N/A Simulator 4/0 8/0 12/0 S 1 . Evalcation of facility written exw6 nation grading N/A Overall Program Evaluation Satisfactory Marginal X Unsatisfactory (List major deficiency areas with brief descrip-tive comments) Operator performance on the simulator phase of the examination was good, with effective use of emergency procedures and crew interaction particularly note-worthy. More concerted use of annunciator response procedures should be
- emphasized in future requalification training on the simulator. A major deficiency was reactor operator (RO) performance on the written examination.
One R0 was evaluated as substandard in 3 of the 4 examined areas. Generic weaknesses were noted in section 4 of the written examination, particularly knowledge of the guidelines for usage of Emergency Operating Procedures (E0Ps) and the bases for performing key steps in E0Ps. Submitted: Forwarded: Approved: W. M. Dean J. F. Munro C. A. Julian
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