ML20205A645
| ML20205A645 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/05/1986 |
| From: | Burdick T, Hanek J, Mary Spencer NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20205A625 | List: |
| References | |
| 50-237-OL-86-02, 50-237-OL-86-2, NUDOCS 8608110421 | |
| Download: ML20205A645 (91) | |
Text
.
U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-237/0L-86-02 Docket Nos. 50237; 50-249 License No. DPR-19/25 Licensee: Commonwealth Edison Company Post Office Box 767
- Chicago, Illinois 60690 Facility Name: Dresden Nuclear Power Station Examination Administered At: Dresden Nuclear Power Station, Morris, Illinois Examination Conducted: June 24-27, 1986 Examiners:
.$.kYby M. Spencer 8/r/gc D&te '
$~ $.Y $ f)G~/fC Da'te '
J. Hanek Approved By: . M. B dick, Chief [S I Operator Licensing Section Date Examination Summary Examination administered on June 24-27, 1986, (Report No. 50-237/0L-86-02)
Written and operating examinations were 6dministered to three Senior Reactor Operatcr (SROJ candidates and three Reactor Operator (RO) candidates. In addition, one simulator portion of the operating examination was administered to an R0 candidate.
Results: One SR0 and one R0 candidate passed these examinations. All others failed one portion of the examination.
t V
REPORT DETAILS
- 1. Examiners M. Spencer, INEL - Chief Examiner J. Hanek, INEL
- 2. Examination Review Meeting An examination review meeting is no longer conducted. Specific facility coirsr.ents concerning written examination questions, followed by the NRC response, are enumerated in Attachments 1 and 2.
- 3. Exit Meeting At the conclusion of the examinations, an exit meeting was held. The following personnel attended this exit meeting:
Facility Representatives R. Flessner J. Wujciua B. Zank S. Stiles NRC Representatives L. McGreger, Senior Resident Inspector, Dresden M. Spencer, Chief Operator Licensing Examiner, INEL The following observations and generic issues were discussed:
- a. A deficiency in the knowledge level understood by candidates concerning the fire protection systems and basic health physics principles was noted by the examiners,
- b. The insufficient use of and lackadaisical attitude toward procedures during the simulator examination were noted by examiners.
- c. Interruptions by personnel in the control room were disruptive to the oral examination process.
2
l ATTACHMENT 1 ;
DRESDEN STATION COMENTS R0 EXAM 6/24/86 Facility Comment:
1.06 b. Answer is incorrect, the correct answer is: The condition in which the reactor is not dependent on delayed neutrons.
Examiner Response:
1.06 b. Facility comment is valid. Answer key was changed for 1.06 b as follows: Prompt critical is the condition in which the reactor is not dependent on delayed neutrons.
Facility Comment:
1.07 b. See SR0 Exam comments 5.05 b.
Examiner Response:
1.07 b. There is no facility comment addressed against SR0 question 5.05.B.
Duplicate question concerning NPSH is 5.04.B answer key for 1.07 b was changed as follows:
NPSH is defined as the difference in pressure between the static pressure at the eye of a pump and saturation pressure.
Facility Comment:
2.01 Additional acceptable answers:
- 4. Isolation Condenser Drains
- 5. Isolation Condenser Loop Seals
- 6. Fuel Pool Cooling Heat Exchanger Drains
- 7. Fuel Pool Cooling Heat Exchanger Relief Valves
- 8. Shutdown Cooling Heat Exchanger Relief Valves and Drains
- 9. RBCCW Heat Exchanger Drains
- 10. RBCCW Heat Exchanger Relief Valves
- 12. RBCCW Pump Bed Drains
- 13. RBCCW Head Tank Drains i
- 14. Core Spray /LPCI Corner Room Sump Pumps
- 15. Isolation Condenser Condensate Header Drain l
- .-~ . - . - . _ _ . , - -
.. l
- 16. Shutdown Cooling-5 Valve Drains
- 18. HPCI Booster Pump Suction Relief Valve
- 20. HRSS Building Sump Pumps
- 21. Containment Cooling Service Water Head Exchanger Drains Examiner Response:
2.01 Facility comment is not valid. Question specifically asked for inputs other than from floor drains. Reference material, Dresden Student Text, Liquid Radwaste System, Book 4 Chapter 1 lists the three inputs given in the answer key and floor drains.
Facility Comment:
2.02 a. Additional acceptable answer: Afterfilter
- b. This question is inappropriate for a reactor operator written exam.
The location of pipe taps on a non-safety related system is out of the realm of required knowledge of a reactor operator. This question lends itself to the oral exam rather than a written exam.
Examiner Response:
! 2.02 a. Answer key was changed to include afterfilter as an acceptable i answer for 2.02 a. Point value breakdown was adjusted for the additional answer. Reference material was supplied by facility.
2.02 b. Facility comment is noted but not valid. This question is consistent with the requirements of ES-202 B.2 as follows:
"The candidate should be able to reproduce, from memory, sketches or descriptions of various hydraulic, pneumatic, or electrical distribution systems and mechanical components. Questions on design intent, construction, operation, and interrelationships of those systems most directly associated with normal nuclear power plant operation and reactor safety can also be included."
2
Facility Comment:
2.04 This is an inappropriate question for a Reactor Operator exam. This valve is under the control of a non-licensed operator and not the Reactor Operator.
Examiner Response:
2.04 Facility comment is not valid. This question is consistent with the requirements of ES-202 B.2. Furthermore, the non-licensed operator is under the direction of the licensed reactor operator.
Facility Comment:
2.07 a. Answer should also include: "0R"
- 1. Rx Water Level </=-59"
- 2. 8.5 minute timer timed out
- 3. Any core spray or LPCI pump running with >/=100 psig pressure.
Examiner Response:
2.07 a. Facility comment is valid. Reference material dated July, 1984 provided by the facility included the additional actuation signal of reactor water level less than -59 in. and 8.5 min. timer timed out and either core spray or any LPCI pump running with at least 100 psig discharge pressure. Answer key was changed to include these additional requirements. Point value breakdown was adjusted for the additional answers. Reference material was provided by the facility which was not included in the material supplied to the examiner.
l Facility Comunent:
j 2.10 c. See SR0 Exam comments 6.12 c.
Examiner Response:
2.10 c. This question is a practical application of a basic theory concept i and is consistent with ES-202 B.2. Answer key is correct with respect to Dresden Student Text, Standby Liquid Control, Book 3 Chapter 3 Page 11. It does not elaborate on the method utilized
! to prevent chugging.
3
9 "The minimum injection time is 50 minutes.
- 1) A too rapid insertion rate results in a lack of proper mixing and reactivity " chugging". The objective is to provide for a contro11ed' shutdown: Too fast a shutdown, with its accompanying power " chugging", could damage the Fuel."
Facility Comment:
4.i0 3. Answer is incorrect, correct answer is: Range 3 Examiner Response:
4.10 3. Facility comment is valid. Reference material was supplied to support the correct answer of Range 3 instead of Range 4 as described in Dresden Operating Procedure D0P 700-1.
Facility Comment:
4.13 b. Technical Specification bases are considered to be beyond the realm of knowledge of a Reactor Operator candidate. Therefore, this is an inappropriate question.
Examiner Response:
4.13 b. Facility comment is not valid. In addition to being a Tech Spec requirement, this procedure is identified in Dresden Operating Procedure D0P-300-7. This question is consistent with ES-202 B.2 which states the candidate should be able to explain reasons, cautions, and limitations of normal operating procedures.
i Additional Examiner Comnents:
1.04 b. Answer key 39.93 changed to 38.93 typographic error.
3.01 e. Answer key 20 seconds not required for full credit. Answer key changed to A time delay.
3.03.3 Answer key psia changed to psig.
3.04 c. Question clarified as flood-up during exam.
3.04 d. Question clarified as fuel zone during exam.
4.11 2. Answer key "not" was deleted typographic error.
4.18 b. Answer key VARIAC is an acceptable answer for EXC field VAR AC control.
I i
4
'. ATTACHMENT 2 DRESDEN STATION C009 TENTS SRO EKAN 6/24/86 Facility Comment:
5.04 B. Answer Key should be: "The difference in pressure between the static pressure at the eye of the pump and saturation pressure." The answer key currently defines " Required NPSH".
Examiner Response:
5.04 B. Answer Key was changed as follows: NPSH is defined as the difference in pressure between the static pressure at the eye of a pump and saturation pressure. Correct reference material was supplied by facility.
Facility Comment:
5.09 This question regards an obscure point and has been commented about on previous exams.
Examiner Response:
5.09 Comment noted. Question is consistent with ES-402.A.1 regarding fuel element characteristics.
Facility Comment:
6.06 b. The answer key is not correct. The answer key response describes the function for the Backup Scram Valves. The correct function is: "To supply instrument air to the SDV vent and drain valves to hold the valves opn."
Examiner Response:
6.06 b. Facility comment is not valid. Dresden Student Text, Control Rod l
l Drive Hydraulic System, Book 1 Chapter 6 Page 26 describes the function of the scram dump valves (20 A/B) and backup scram valves (19 A/B) as follows:
F. 5. n. 2) a) " LOW SCRAM AIR HEADER PRESSURE (less than 50 psig I
at PS-992 and B). This interlock anticipates control rods inserting l
i
O in a random pattern as their scram inlet / outlet valves. overcome spring pressure. To preclude random rod insertion patterns, the following valves are energized on low air header pressure: 19A, 20A, 20B.
This function is bypassed when the SDV Hi Hi Level Scram? Bypass Keylock switch is in " BYPASS".
Facility Comment:
6.12 c. This question is thought provoking and the information is not specifically mentioned in the lesson plan or the FSAR. Therefore, the specific response listed in the answer key should not be the only acceptable answer.
Examiner Response:
6.12 c. This question is a practical application of a basic theory concept and is consistent with ES-402A.2 concerning design intent. Answer key is correct with respect to Dresden Student Text, Standby Liquid Control, Book 3 Chapter 3 Page 11.
"The minimum injection time is 50 minutes.
- 1) A too rapid insertion rate results in a lack of proper mixing and reactivity " chugging". The objective is to provide for a l controlled shutdown: too fast a shutdown, with its accompanying ,
power " chugging", could damage the fuel ."
Facility Comment:
7.03 a. Answer should be:
Step 1: Start both CRD Pumps l
Step 2: Close charging water valve 2(3)-0301-25 Step 3: Rapidly insert all control rods using the Emergency l Rod-in Control Switch. "
l Examiner Response:
7.03 a. Facility comment is valid. Steps 1 and 3 of Facility Comment were added to answer key. Point value breakdown was adjusted for additional answers. Reference material was supplied by facility.
l l 2
Facility Comment:
7.03 c. " Cram Arrays" should also be acceptable.
Examiner Response:
7.03 c. Answer key was changed to include " Cram Array" or " Deep" rods for full credit. High worth was deleted from answer key, reference material was provided by facility.
Facility Comment:
7.09 b. Question was changed to read: A Type 1 RWP is' valid for
- 1. while a Type 2 RWP is valid for
- 2. .
Answer therefore are:
- 1. 1 year
- 2. Length of the Job Examiner Response:
7.09 b. Facility comment is valid. Dresden Radiation Protection Standards were changed in September, 1985 to incorporate Type 1 and Type 2 RWP's, Exam Reference Material was dated February 1982.
7.09 b. answar key was changed in accordance with the facility comment and revised Dresden Radiation Standards Pages 11-14.
Facility Comment:
7.10 b. Answer key should read:
l Less urgent action 100 REM Examiner Response:
7.10 b. Facility comment is valid, answer key 7.10 b. was changed to 100 REM for extremities dose during less urgent action conditions.
Answer key was a typographic error.
Facility Comment:
l 8.12 We do not expect license candidates to memorize tables in the Technical Specifications, especially in this case where the station manning always exceeds the reqrirements. We consider this question t
' to be inappropriate.
3
Examiner Response:
8.12 Facility comment is not valid ES-402-A.4. states that " Questions may also cover the requirements for certain personnel to be present at certain times" and questions pertaining to shift manning are consistent with this requirement.
Additional Examiner ' Comments:
5.01 B Answer key 39.93 changed to 38.93 - typographic error.
7.12 C Question collect changed to collet - typographic error.
6.04 C Question clarified as " flood-up" during exam.
6.04 0 Question clarified as " Fuel Zone" during exam.
4
U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE' EXAMINATION FACILITY: _DREgDEN_2tj3_____________
REACTOR TYPE: _EWR-GE3_________________
DATE ADMINISTERED: _@6fg6fg@__ ___________
EXAMINER: _H@NEKz_J.
APPLICANT: _________________________
IN@lBUCIlgNg_Ig_8EELIC@NIi Uzm separate-paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each qunstion are indicated in parentheses after the quection. The passing grcde requires at least 70% in each category and a final grade of at losst 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY
__Y86UE_ _Igl@( ___gCgBE___ _y@(UE__ ______________C8IEGQBY_____________
_22:gg__ _ggsgg ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS l
1 3 ________ 6. PLANT SYSTEMS DESIGN, CONTROL,
_2S 2E__ _2_:ZZ ___________
AND INSTRUMENTATION
________ 7. PROCEDURES - NORMAL, ABNORMAL,
_20:2E__ _23:2E ___________
EMERGENCY AND RADIOLOGICAL CONTROL i
________ 8. ADMINISTRATIVE PROCEDURES,
_22:99__ _26 SZ ___________
CONDITIONS, AND LIMITATIONS 192:99__ 199 99 ___________ ________ TOTALS FINAL GRADE _________________%
All work done on this examination is my own. I have neither givsn nor received aid.
APPLICANT'S SIGNATURE
i
, MRC RULES AM GUIDELINES FOR LICENSE EXAMINATIONS perier; t% e441stration of this Examinstion the fallowing ruin apply:
- 3. Cheating on the examination means an automatic dental of your appitcation 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 only 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 new page, write Jon1 og IsTde of the paper, and write "Last Page" on th7 east answer sheet.
- 9. Nueber each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and piv:e finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in factitty literature.
- 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 th.e examination are not clear as to intent, ask questions of the examiner 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 l been completed. ,
l
- 18. When you complete your examination, you shail:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a 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. t
z PAGE 2
$__mIMEQ8Y_QE_ NUCLE 88_EQWE8_E(8NI_QEEB811QN_ELUlpS_8NQ t IHE8MggyN9MICS QUESTION 5.01 (3.00)
Th2 reactor is shutdown and a plant cooldown is in progress.
Racetor pressure decreases from 450 psia to 300 psia in a 33 minute period. SHOW ALL WORK.
(1.5)
A. What is the cooldown rate?
B. How much reactivity has been inserted in the rector due to the moderator temperature coefficient (MTC)? (1.2)
C. With the above temperature change, has the MAGNITUDE of the MTC changed and if so, in what direction (more/less, (.5) positive / negative)?
QUESTION 5.02 (2.00)
R garding MCPR (Minimum Critical Power Ratio):
- a. What PHENOMENON could exist in a fuel fundle if it were operated at a MCPR LESS THAN ONE (< 1.0) and WHAT would (1.0) very likely be the CONSEQUENCE of the phenomenon?
- b. WHY must the Technical Specification MCPR limit be modfied when core flow is LESS THAN RATED 7 (include in your answer (1.0) whether MCPR is increased or decreased.)
t I
QUESTION 5.03 (2.00)
- a. Which time in core life (BOL, Mid-of-life, or EOL) requires the least amount of positive reactivity addition to achieve prompt critical AND why?
- b. When is prompt critical achieved?
l i
l I
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
P Ez__INE98Y_9E_NUQ6E98_EQMEB_E69NI_gEEBBIlgN3_E691pS _@ND 3 PAGE 3 ISEBBggyN9d1Q@
QUESTION 5.04 (2.50)
A. What are THREE of the FIVE design or operational factors that insure adequate Net Positive Suction Head (NPSH) for the recirculation pumps? (1.5)
B. Explain what NPSH is. (1.0)
QUESTION 5.05 (1.50)
Give ONE undesirable result for each of the following.(Be more cpecific than " pump failure"):
A. Operating a centrifugal pump for extended periods of time with the discharge valve shut. (0.5)
B. Starting a centrifugal pump with the dischcrge valve full open. (0.5)
C. Operating a motor driven pump under " PUMP RUNOUT" conditions. (0.5)
QUESTION 5.06 (2.00)
DEFINE " Condensate Depression". (.5)
! A.
l l
B. WHY is it necessary for plants to operate with condensate depressien? (1.0)
C. HOW would CYCLE EFFICIENCY be effected if the amount of condensate depression is increased? (.5) l l
I l
. (***** CATEGORY 05 CONTINUED ON NEXT PAGE **$**)
Et__IMEQBY_QE_NUQLE98_EQWEB_EL9MI_QEEB811gN t_ELQ1QS _@NQ t PAGE 4 IdEBUQEYN6dlGE QUESTION 5.07 (1.50)
In a reactor fueled with U-235 and U-238:
A. Which nuclide(s) may fission upon absorbing a fast neutron? (.5)
B. What fissile nuclide can U-238 be converted into? (.5)
C. At the Middle of Core Life (MOL), which 2 nuclides will absorb a thermal neutron and fission? (.5)
DUESTION 5.08 (2.00)
For the following transients, indicate which COEFFICIENT of reactivity; alpha T, alpha D, or alpha V tends to change reactor power FIRST and in what DIRECTION.
A. Fast closure of one MSIV. (0.5)
B. Isolation of a feedwater heater string. (0.5)
C. A control rod drop. (0.5)
D. Relief valve lifting. (0.5) l QUESTION 5.09 (1.00) l The Ox8 fuel has a thermal time constant of appro::imately 5 to 6 l caconds. This means that in 5 to 6 seconds following a sudden l power increase: (choose ONE answer below) (1.0) l a. The fuel centerline temperature will reach its maximum (final) value.
l
- b. Clad surface temperature will reach its final value.
l
- c. Fuel centerline temperature will reach approximately 2/3 of its final value.
- d. Fuel centerline, clad and coolant temperature have reached their final values.
- e. Clad surface temperature will reach approximately 63*/. of its final value.
l l
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
l
-Ez__IME98Y_9E_Nyg6E98_EQWES_EL9NI_QEEB9IlgN2_E691pg2_8ND PAGE 5 ISEBd99%N9digg QUESTION 5.10 (2.00)
Indicate HOW each of the coefficients are effected EIncrease, Decrease or R main the same] by each of the three parameters listed? Consider each parameter separately.
- c. Rod Worth (delta K/K/ Bank) by:
- 1. Moderator temperature INCREASES
- 2. Voids DECREASE
- 3. Fuel temperature INCREASES E3 0 0.33 ea]
- b. Alpha Voids (delta K/K/ */. voids) by:
- 1. Fuel temperature INCREASES
- 2. Core age INCREASES
- 3. Control Rod Density INCREASES E3 0 0.33 eaJ DUESTION 5.11 (1.00)
In a subtritical reactor, Keff is increased from .880 to .965.
Which of the following is the amount of reactivity added to the core 7
- o. .085 delta k /k
- b. .100 delta k /k
- c. .125 delta k /k
- d. .220 delta k / k I
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) :
5.- THEOBy_gE_NUg6E86_EgWEB_E68NI_QEEB811gN3 _E6Ulpgz_8ND PAGE 6 IHE8DgpyN8digg QUESTION 5.12 (1.00)
The reactor trips f rom f ull power, equilibrium XENON conditions. Twenty-four hours later the reactor is brought critical and power level is main-tained on range 5 of the IRMs for several hours. Which of the following utstements is CORRECT concerning control rod motion?
- a. Rods will have to be withdrawn due to XENON build-in.
- b. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of XENON burnout.
- c. Rods will have to be inserted since XENON will closely follow its normal decay rate.
- d. Rods will approximately remain as is as the XENON estab-lishes its equilibrium value f or this power level.
QUESTION 5.13 (1.00)
Concerning contro) rod worths during a reactor startup from 100% PEAK XENON versus a startup under XENON-FREE conditions, which statement (1.0) is correct?
- a. BOTH control rod worths will be LOWER regardless of core XENON conditions,
- b. CENTRAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.
- c. BOTH control rod wortns will be the SAME regardless of core Xenon conditions.
l
- d. PERIPHERAL centrol rod worth will be HIGHER during the PEAK XENON l startup than during the XENON-FREE startup.
l l
l l
(***** CATEGORY 05 CONTINUED ON NEXT PAGE ****4)
- 5. THEORY _QF_NUQLEAR_PgWEB_ PLANT _gPgRAT1gN x _FLUlpgi_ANQ PAGE 7 IHgBMgpyNSMigg QUESTION 5.14 (2.00)
A significant amount of excess reactivity must be loaded into a core at BOL co that 100% power can be attained at the end of a fuel cycle. For each of the f ollowing, LIST the approximate value of K-excess which must be loaded to overcome that negative reactivity component at rated-equilibrium conditions,
- s. Moderator temp increase
- b. Void fraction increase
- c. Samarium buildup
- d. Xenon buildup OUESTION 5.15 (1.00)
STATE for which condition the reactivity coefficient contribution would be MORE NEGATIVE. EXPLAIN your choice.
Moderator Void Coefficient for a 1% INCREASE in void fraction at 10% void fraction in the core,
-UR-Moderator void coefficient for a 1% INCREASE in void fraction at 70% void fraction in the core.
(***** END OF CATEGORY 05 *****)
j
6- PLANT SYSTEMS DESIGN i_CQNTROL1_AND_INSTRUMENTATigN PAGE 8 QUESTION 6.01 (3.00)
Other than injection of sodium pentaborate, list FOUR f unctions of the atendby liquid control no::le penetration.
DUESTION 6.02 (2.00)
- c. Why are risers utilized on the jet pumps?
- b. What would be the detrimental effects of not utilizing risers?
DUESTION 6.03 (2.50)
Other than the Emergency Core Cooling Systems, list FIVE of the SIX systems or components that constitute the engineered safeguards at Dresden.
DUESTION 6.04 (3.00)
For each of the below listed vessel level indications, provide the following:
- 1. Range
- 2. Method of temperature compensation (if any)
- 3. Major control functions besides indication and alarm (if any) .
- a. Narrow Range GE/MAC i
- b. ATWS Level Transmitter ,
- c. Wide Range GE/MAC
- d. Wide Range Yarway, i
QUESTION 6.05 (1.00)
With respect to the Narrow Range Yarway instrument, what affect will the following have on indicated level?
l
- c. Increase in Drywell Temperature
- b. Increase in Reactor Building Temperature near the Instrument Rack.
l
(***** CATEGORY 06 CONTINUED ON NEXT PAGE * * ** * )
61__PL8NI_gygIgdg_gEgigNz_CgNIBg(z_@Np_INSIBydgNI@IIgN PAGE 9 QUESTION 6.06 (2.75)
With respect to the scram dump valves (20A and 20B), provide the following:
- a. Actuation signal (s) (setpoint not required) (1.0)
- b. Function (0.75)
- c. Power supply (0.5)
- d. When function is bypassed (0.5)
OUESTION 6.07 (1.75)
With respect to the RWM, what signal (s) are utilized to actuate and daactuate the LPSP and LPAP (include applicable setpoints and times) .
DUESTION 6.08 ( .75)
In the event of a failure of both recirc pump seals, the a._________
b._________ limits the total flow to c._________ gpm.
QUESTION 6.09 ( .50) f Following an auto initiation of HPCI, the low pressure sensing line f rom
i After this rupture, what will the HPCI turbine speed, assuming no operator cction?
I i
DUESTION 6.10 (1.25) l Hydrogen is added to the reactor coolant to reduce the a.______ in the coolant in an effort to reduce b.______. Oxygen is added to the offgas cystem to c.______ with the excess d.______ to reduce the potential of offgas e.______.
(***** CATEGORY 06 CONTINUED ON NEXT PAGE **$$$)
t - . - - -- _ - - . . _ _ ,
hz__ELONI_SygIggg_pgSIGN_ggNIBQL,_9NQ_lNSIBudENIgIlgN 3
PAGE 10 OUESTION 6.11 (2.75)
The Off-Gas HI-HI Radiation Trip logic will initiate on TWO conditions.
- a. What are these conditions? (1.0)
- b. List THREE auto actions that will result from a trip condition following timeout of the Timer. (1.5)
- c. What is the setting of the Timer? (0.25)
QUESTION 6.12 (2.00)
Concerning the Standby Liquid Control Pumps.
- a. What is the power supply (s) to the pump motors? (0.5)
- b. Briefly, what is the voltage supply and power to the squib valves? (0.5)
- c. Briefly, e:: plain why positive displacement pumps are utili:cd instead of centrifical pumps. (1.0)
OUESTION 6.13 (1.00)
Concerning the Halon 1301 fire suppression system.
- a. What areas are protected by this system? (0.5)
- b. True or False
- 1. Hal on 1301 relies on the displacement of c::ygen to er:tinguish fires. (0.25)
- 2. The system is suitable f or use in enclosed occupied spaces. (0.25)
(***** END OF CATEGORY 06 *****) ,
Zs__P80CEDUBEE_ _NOBd@bt_6ENgBd@bt_EDEBGENgy_QND PAGE 11 B091969GICeL_CQNIBg(
QUESTION 7.01 (2.75)
What are the FOUR entry conditions for the Reactor Control Procedure (DEOP 100)? Include applicable setpoints.
DUESTION 7.02 (1.50)
Irrespective of the entry condition, what other DEOP's are executed concurrently if DEOP 100 is entered.
QUESTION 7.03 (1.50)
- a. During an ATWS condition, what action must be taken to drive rods if the scram signal cannot be reset. (0.5)
- b. Why is this action necessary? (0.75)-
- c. What rods have the highest initial priority to insert? (0.25)
DUESTION 7.04 (2.00)
APRM AGAFS require adjustment if they are a.______ and reactor power is b.______. If reactor power is below c._______ the AGAF's are set at d.______.
QUESTION 7.05 (2.00)
- a. When may the vacuum breakers be utilized to slow the main turbine?
- b. How much vacuum decrease is recommended?
- c. What vacuum limitations are imposed on their use?
- d. Why is their use restricted?
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
- 7. PROCggURgg_ _NgRMAli_AgNgRMAla_gMgRggNgY_ANg PAGE 12 609196991996_GQNIBQL QUESTION 7.06 (2.50)
With regard to routine power changes DGP 3-1 requires radiation-chemistry shall be notified for at least three conditions regarding power changes.
- a. List these THREE conditions. (1.5)
- b. List TWO actions required if the Building Vent Noble Gas monitor is INOP. (1.0)
QUESTION 7.07 (2.50)
List FIVE automatic actions initiated by a main steam line High Radiation Alarm at 3 X normal.
QUESTION 7.08 (1.50)
Other than a f uel failure or instrument failure, list THREE possible cources of a main steam line High Radiation Signal.
QUESTICN 7.09 (1.50)
- a. What are FOUR reasons the shift engineer may terminate an RWP7 (1.0) l 7- "#eed A s,9=s I 7p't e Z RWP is valid for 1. ______ wh i l e an m .,
r.ded RWP i s l b.
valid for 2.______. (0.5) l l
l
\
1 l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) ,
PAGE 13 Zz_mEB99E996EE_2_NQBd@61_9ENQBd@L3_[d[B@gNQy_AND
. EC2196991C96_C9NISg6 QUESTION 7.10 (3.00)
Pcrsonnel exposures under emergency conditions ref erences dose limits f or life saving actions and less urgent actions.
What are the dose limits f or the f ollowing under those conditions?
- a. Whole body
- b. Extremities
- c. An acute whole body dose equivalent in excess of 1.______ rem shall be limited to 2.______.
QUESTION 7.11 (1.00)
List TWO conditions that must be met prior to placing the economic g2neration control system in operation with automatic flow control.
QUESTION 7.12 (1.50)
True or False
- o. Control rod drives which are fully inserted and electrically disarmed are considered inoperable.
- b. During reactor power operation, the number of inoperable control rods shall not exceed eight.
- c. Unlimited operation may continue with 3 inoperable control rods if it is determined the cause of failure is CRD colle t housing failure.
l l
I
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
1
PAGE 14 Zz__BBQGEDWBEE_:_NQBdeLi_8DNQBdBLi_EdEBGENCY_8ND
. B9D196991G96_99 NIB 96 QUESTION 7.13 (2.00)
While the pl ant is in shutdown cooling with the reactor recirculation pumps not running, surveillance of the vessel metal temperature recorder Stratification is indicated by is required at least once per a.1.______.
cn increasing a.2.______ temperature without a corresponding o.3.______ or a.4.______ change.
- a. List parameters a.1. through a.4.
- b. List FOUR suggested actions to minimize stratification if the RWCU system is not available and both recire pumps are off.
(***** END OF CATEGORY 07 *****)
.g __8951NISIBBIlME_BBQGEEMBEEz_EQNElligNgg_8Np_(IdlIBIlQNg PAGE 15 QUESTION 8.01 (1.00)
DAP 7-2 specifies a licensed operator or senior licensed operator chall be "at-the-controls" at all times.
What is the meaning of "at-the-controls"?
QUESTION 8.02 (3.50)
Concerning shift supervisor shift turnover.
- c. Where does it take place? (0.5)
- b. List SIX of the EIGHT items the oncoming shift supervisor shall review or preform. (3.0)
DUESTION 8.03 (1.50)
- a. If the engineering and safety evaluation checklist contains a discrepancy, what approval / actions are required to install a jumper (immediate installation needed) on a backshift? (1.C)
- b. What additional action is required if this jumper also reduces the margin of safety as defined in the basis for any Tech.
Spec 7 (0.5)
DUESTION 8.04 (1.50)
- c. 10 CFR-20 requires positive control over entry into High l Radiation areas. List TWO methods utilized at Dresden to establish this control. (1.0)
- b. List TWO personnel who can authorize entry to a High Radiation area in the Reactor Building at Dresden? (0.5) i l
(***** CATEGORY OO CONTINUED ON NEXT PAGE *****)
i
PAGE 16 Et__8Dd1NISIgellVE_EBQQEQUBE@t_QQNQlIlgN@t_QNQ_(ldlI@IlgNE QUESTION 8.05 (1.50)
Attachment A to DGP 1-1 gives special precautions to prevent a short period GvCnt.
After reaching a black and white pattern, what restrictions apply?
QUESTION 8.06 ( .50)
True or False The Shift Engineer and Station Nuclear Duty Officer can authorize plant rcstart following a scram if the root cause has been determined.
QUESTION 8.07 (2.00)
DOA 202-1, recirculation pump trip requires the operator to reduce the cpeed of the running recirc pump.
- a. What are the limits for each unit at Dresden?
- b. What is the bases for this differenco?
QUESTION 8.08 (3.00)
In accordance with operating order 5-86, there are specific periods the SCRE is responsible for ensuring an instrument mechanic is on siteWhat to perform APRM gain adjustments during plant startup and shutdown.
cre these periods? TWO required for each evolution.
QUESTION 8.09 (1.00) i What actions are required by the shift engineer or SCRE if the 4KV cross-tie between Dresden Units 2 and 3 becomes inoperable?
QUESTION 8.10 (3.25)
What are the safety limits at Dresden pertaining to fuel cladding integrity (include applicable plant conditions) .
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
PAGE 17 Ez__8Dd1NISIBSIlyE_P8QCEDUBEgg_QQND1IlgNgz_8ND_ Lid 1I811gN@
QUESTION B.11 (1.50)
If a Dresden safety limit is exceeded, what actions and reports are required? (Include applicable time limits. )
OUESTION B.12 (2.25)
- a. Answer the f ollowing with regard to minimum shif t manning (1.25) requirements.
No. of men in each position NON RAD Unit 1 cold shutdown and SRO STA RO LIC MEN second and third units above cold shutdown. a.1 a.2 a.3 a. 4 a.5
- b. What exceptions are allowed to the minimum manning requirements (1.0) by Tech Specs?
QUESTION 8.13 (2.50)
List THREE guidelines to be followed in accordance with Tech Specs to make o temporary change to an operating procedure (include all reviews and cpprovals required) .
QUESTION 8.14 (1.00)
- c. A fire brigade of at least a.______ members shall be maintained on-site at all times.
- b. Fire brigade training sessions shall be held at least b.______.
QUESTION 8.15 (1.00)
- c. What action is required if during normal operation APLHGR thermal limit is being exceeded as determined by normal surveillance.
- b. What time limit is allowed to restore APLHGR to within it's prescribed limits before proceeding to cold shutdown?
i f
I
(***** END OF CATEGORY 08 *****) t j (************* END OF EXAMINATION ***************)
i .
volume,0jen Emhelpy, strfin terapy,gi.finay i
tvep Steam Water tve, Sees. p f
, % Water e,
tver e.
84eem es Water a, a. a 4
- 4,, g i -0.02 1075.5 1075.5 OA000 2.1873 2.1473 32 0.08859 4A1602 3305 3305 32 3.00 10733 10762 0.0061 2.1706 2.1767 35 OA9991 0.01602 2948 2948 2.1432 2.1594 40 35 8 03 3071.0 1079.0 0.0162 0.12163 001602 2446 2446 2.1426 45 de 2037.8 13.04 1068.1 3081.2 0 0262 2.1164 45 0.14744 0.01602 2037.7 0.0361 2.0901 2.1262 to 3704.8 18A5 1065.3 1083.4 0.17796 0A1602 3704A 0.0M5 2.0391 2.0946 60 to 1207.6 28.06 1059.7 1087.7 80 0.2561 0A1603 1207A 38.05 3054.0 3092.1 0A745 1.9900 2.0645 70 0.3629 0.01605 868.3 868.4 80 30 48.04 1048.4 1096.4 0.0932 1.9426 2.0359 0.5068 0.01607 633.3 633.3 2.0086 90 58.02 3042.7 13002 0.1115 1A970 to 0A981 0.01610 468.1 468.1 100 to 350.4 48 00 1037.3 1105.1 0.1295 12530 1.9825 03492 OA1613 350.4 0.1472 1A105 1.9577 110 300 265.4 77.98 1031.4 1109.3 Sto 1.2750 0.01617 265.4 87.97 1025.6 1113.6 0.1646 1.7693 3.9339 120 1A927 OA1620 203.25 203.26 1.9112 130 320 97.96 3019A 1117A 0.1817 1.7295 2.2230 0A1625 157.32 157.33 140 130 107.95 3014.0 1122.0 0.1985 1.6910 1.8895 2.8492 0A1629 122.98 123.00 J
140 117.95 3006.2 1126.1 0.2150 1.6536 1.8686 150 3.718 0A1634 97.05 97.07 160 4
150 127.96 1002.2 1130.2 OJ313 1.6174 1.8447 4.741 0A1640 77J7 77.29 l 300 62.06 137.97 996.2 1134.2 0.2473 1.5822 1A295 17r 5.993 0.01645 62.04 1.5480 1A111 180 170 80.22 348.00 990.2 1138.2 0.2631 7.511 0A1651 90.21 1.7934 190 180 40.94 40.96 358.04 984.1 1142.1 0.2787 - 1.5148 190 9.340 OA1657 0.2940 1.4824 1.7764 300 33.62 33.64 168.09 977.9 1146.0 300 11.526 041664 0.3091 1.4500 1.7600 210 i 27.80 27.82 178.15 971.6 1149.7 230 14.183 0.01671 970.3 1150.5 '0.3121 1.4447 1.7568 III 0.01672 26.78 26.80 180.17 212 14.696 965.2 1153.4 0.3241 1.4201 1.7442 220 i 0.01678 23.13 23.15 188.23
- 220 17.186 958.7 1157.1 0.3388 1.3902 1.7290 130 0A1685 19.364 19.381 198.33
! 230 20.779 952.1 1160.6 0.3533 1.3609 1.7142 240 0.01693 16.304 16.321 208.45 240 24.968 945.4 1164.0 0.3677 1.3323 1.7000 250 l 0.01701 13.802 13.819 218.59 350 29 125 938.6 1167.4 0.3819 1.3043 1.6862 260 0.01709 11.745 11.762 228.76 270 i 240 35.427 931.7 1170.6 0.3960 1.2769 1.6729 41.856 0.01718 10.042 10 060 238.95 280 270 924.6 11732 0.4098 1.2501 1.6599 4
0.01726 8.627 8.644 249.17 290
! 280 49.200 917.4 1176.8 0.4236 1.2238 1.6473 0.01736 7.443 7.460 259.4 300 290 57.550 910.0 1179.7 0.4372 1.1979 1.6351 0.01745 6.448 6.466 269.7 300 67.005 902.5 1182.5 0.4506 1.1726 1.6232 310 0.01755 5.609 5.626 280.0 320 310 77.t 7 894.8 1185.2 0.4640 1.1477 1.6116 0.01766 4.896 4.914 290 4
! 320 89.64 878.8 1190.1 0.4902 1.0990 1.5892 340 0.01787 3.770 3.788 311.3 1,5678 360
' 340 117.99 862.1 1194.4 0.5161 1A517 0.01811 2.939 2.957 332.3 360 153.01 844.5 1198.0 0.5416 1.0057 1.5473 380 0.01836 2.317 2.335 353.6 340 195.73 375.1 225.9 1201.0 0.5667 0.9607 1.5274 400 l 400 247.26 0.01864 1.8444 1A630 0.9165 1.5080 420 i 1.4997 396.9 806.2 1203.1 0.5915 420 308.78 0.01894 1.4808 0.6161 02729 1.4890 440 1.2169 419.0 785.4 1204.4 440 381.54 0.01926 1.1976 0.6405 0.8299 1.4704 460 0.9942 441.5 763.2 1204.8 460 466.9 0.0196 0.9746 0.6648 0.7871 1.4516 480 0A172 464.5 739.6 1204.1 480 566.2 0.0200 0.7972 1202.2 0.6890 0.7443 1.4333 500 0.6545 0.6749 487.9 714.3 500 680.9 0.0204 512.0 687.0 3199.0 0.7133 0.7013 1.4146 520 812.5 0.0209 0.5386 0.5596 1.3954 540 520 536 8 657.5 1194.3 0.7378 0.6577 0.0215 0.4437 0.4651 1.3757 560 540 962.8 625.3 3187.7 0.7625 0.6132 0.3651 0.3871 562.4 560 1133.4 0.0221 589.1 589.9 1179.0 0.7876 0.5673 1.3550 580 0.0228 0.2994 0.3222 580 3326.2 550.6 1167.7 0.8134 0.5196 1.3330 'A0 0.2438 0.2675 617.1 Goo 1543.2 0.0236 646.9 506.3 1153.2 0.8403 0.46S9 1.3092 620 0 0247 0.1962 0.2208 1.2821 640 620 1786.9 679.1 454.6 1133.7 0.8666 0.4134 20599 0.0260 0.1543 0.1802 1.2498 660 640 714.9 392.1 1107.0 0.8995 0.3502 2165.7 0.0277 0.1166 0.1443 1.2086 680 660 758 5 310.1 1068.5 0.9365 0.2720 0 0304 0.0808 0.1112 660 2708.6 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 3034.3 0.0366 0.0386 0.0752 0 1.0612 705.5 700 0.0508 906.0 0 506.0 1.0612 705.5 3208 2 0.0508 0 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
" EQUATION SHEET Cycle efficiency = (Met wa v = s/t f = ma out)/(Energy in) 2 w = ng s = V3 t
- 1/2 at .
g = .x- 4 , gg,-At KE = 1/2 mv 2 , , (y , y o)jg 4 ,13 PE = agn
- = e/t x = sn2/t1/2 = 0.693/t1/2 vf= V, + at * "'
1/2" y,y j aD 2 ((c/2I
- I*ON A= , 1
-Dc ai = 931 ast m = V ,yAo ,
h = ECoat I = I,e "*
~
6 = UAaT I = I ,10** N '
Pwe = W7sh TV1. = 1.3/u sur(t) HVL = -0.693/u P = P010 t
P = Po e / *' SG = S/(1 - K,ff)
SUR = 25.06/7 G, = S/(1 - K,ff x)
G;(1 - K,ff3) = G2(I ~ "eff2)
SUR = 25s/t= + (s - o)T I
M = 1/(1 - K,ff) = G3 /G 3 T = (1*/s) + ((a - e VIo] M = (1 - K,ff,)/(1 - K,f,3)
T = V(a - a) SCM = ( - K ,ff)/K ,ff l
T = (a - o)/(Is) t' = 10 seconos a = (X,ff-1)/K,ff a *,f f/K,ff I = 0.1 seconds
- I e = ((t*/(T K,ff)] + (T,ff /(1 + IT)] Id Id l 1 *2 ,2 gd 2
Id j 22 P = (zsV)/(3 x 1010) R/hr = (0.5 C2)/c2 (,,g,73)
- = sN R/hr = 6 CE/d2 (f,,g) .
Miscellaneous Conversions Water Partneters 10 dos 1 curie = 3.7 x 10 1 gal. = 8.345 lem. 1 kg = 2.21 tem 1gaj.=3.78litars 1np=2.54x103*/.u/nr 1 f. = 7.48 gal. 1 m = 3.41 x 100 Beu/hr Density = 62.4 les/ft3 lin = 2.54 cm Oensity = 1 gm/c9 'F = 9/5'C + 32 Heat of vacorization = 970 Stu/lem 'C = 5/9 ('F-32)
Heat of fusion = 144 Stu/lem . 1 STU = 778 ft-1bf 1 Atm = 14.7 psi = 29.9 in. Hg.
1 ft. H 2O = 0.4335 It,f/in.
lEz__IMEQBy_QE_NQCLE@B_EQWEB_E68NI_QEEB@llgN_E(ylDS_@NDt t PAGE 18 ISEEdDDYNBdlGS
' ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 5.01 (3.00)
A. 300 psia = 417.35 F 450 psia = 456.28 F (f rom steam tables) (.5) 456.28 - 417.35 = 38.93 F for 30 minutes (.5) 38.93 X 2 = 77.86 F/HR cool down rate (.5) (1.5)
B. -38.93 F( -1X10-4 dk/k/F) =2 .&X 10-4 dk/k (1.0)
(For grading, answer is independant of part A.)
(.5)
C. Yes(.1) less negative (.4)
REFERENCE GE REACTOR PHYSICS REVIEW, pg 26 24 28 , STEAM TABLES DRESDEN - LESSON PLAN, BOOK 4, CHAPTER 12, PAGE 26.
ANSWER 5.02 (2.00)
Transition boiling may occur which can result in clad failure. (1.0) c.
- 6. To make the MCPR limit more conservative to account for the possibility of a sudden flow increase and a corresponding power increase. The MCPR is increased (or more conservative) (1.0)
("Recirc. pump runaway" acceptable f or " sudden flow increase")
j REFERENCE j NMP-1 Operations Technology, Mod.X, pg.X-34, Tech. Specs,pg.70-70a.
l l DRESDEN - Tech Spec 1.1, pg B 1/2.1-7, Se 3.5K, pg B 3/4.5-37 f
ANSWER 5.03 (2.00) l (0.5)
! c. EOL Because B eff is at its minimum value. (0.5)
- b. When added reactivity exceeds B eff, prompt criticality is achieved. (1.0)
REFERENCE Dresden Reactor Theory Lesson Plan, Book 4, Ch. 12, P. 22 l
i
THEORY _gF_ NUCLEAR _PgWER_ PLANT _gPERATigN x _FLUlpg,_AND PAGE 19 5.
IHE6dgpyN8dlCg ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 5.04 (2.50)
A. 1. They are located as f ar below the normal water line as possible '
to provide the greatest static head.
- 2. With feed flow less than 20% they are kept on minimum speed.
- 4. Low reactor Vessel water level trip, cavitation interlock.
- 5. Suction valve closed trip, cavitation interlock. (3 @ 0.5 ea)
L;.. ,mmt.on B. NIC;. .; the reanir=d g, mom .om im..g c and. u w. .e mi u.vi+=&4nn. (1.0) vi . ump t:.ut ai'l Nffk o defin 5 c..w u /rfe r .t -
sul
- oheeren c e ft!J) k f r $p/f m pf, S Il- ff!JJ"Y
- Al Ve ef/$ Dl L fm ed pQg= p REFERENCE Dresden Recire System Lesson Plan pg 16 & 18 ANSWER 5.05 (1.50)
A. The pump will eventually add a suf ficient amount of heat to the fluid to cause cavitation. (Will accept overheating of the pump.) (0.5)
B. Could cause excessively large starting currents or water hammer if the downstream piping was not filled. (0.5) i (0.5)
C. Causes excessive motor amps to be drawn.
REFERENCE DRESDEN - GE THERMO HT & FF pg 7-123, 124 ANSWER 5.06 (2.00)
A. The subcooling of condensate below the saturation temperature. (.5)
B. The condensate pumps would cavitate. (1.0) l
(.5)
C. Cycle efficiency would be decreased.
l REFERENCE DRESDEN - GE THERMO HT & FF, CHAP 6 1
Ez__INEQBY_9E_Nyg6g@B_EgWEB_EL8NI_QEgB811QN,_ELylpSz_8NQ PAGE 22 ISEBdggyN951CE
' ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 5.07 (1.50)
A. U-235 & U-23e ( . 25 each) (.5)
B. Pu-239 (.5)
C. U-235 & Pu-239 (.25 each) ( . 5)
REFERENCE DRESDEN - LESSON PLAN, BOOK FOUR, CHAPTER 12, PAGE 32 ANSWER 5.08 (2.00) 4 A. Alpha V increases power B. Alpha T increases power C. Alpha D decreases power D. Alpha V decreases power [8 9 0.25 each3 (2.E)
REFERENCE l_ DRESDEN - GE BWR Transient Analysis I
ANSWER 5.09 (1.00)
- o. (1.0)
I REFERENCE DRESDEN -GE THERMO HTX & FF, pg 9-102 ANSWER 5.10 (2.00) 0.1. increase o.2. increase l
o.3. remains the same
! b.1. increase b.2. decrease l b.3. increase [6 & 0.33 ea3 REFERENCE NMP1 Reactor Theory, Module 1, part 12, 13, & 14 DRESDEN - Lesson Plan Book 4, Ch 12, Rx Physics Review, pg 26-35
Es__IMEQBY_QE_NQQ6E88_EQWg6_ELQNI_QEg6811gN g _E(ylQSt_6NQ PAGE 21
.IHEBdggyN@dlGS
' ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 5.11 (1.00) b (1.0)
REFERENCE NUS: Vol 3, pp 6.1-3 BRUNSWICK 1 & 2, Student Study Guide, 02-2-A DRESDEN - LESSON PLAN BOOK FOUR, CHAPTER 12, PAGE 14.
ANSWER 5.12 (1.00) c (1.0)
REFERENCE BFNP: XENON & SAMARIUM LP, P.4,12 GGNS: LP OP-NP-514, p. 5-10 BRUNSWICK 1 L 2, Student Study Guide, 02-2-A.
DRESDEN - LESSON PLAN BOOK FOUR, CHAPTER 12, PAGE 45.
ANSWER 5.13 (1.00) d (1.0) l REFERENCE SSM BOOK 2, CH 2-A, SEC 13.7, PG 161 l
DRESDEN LESSON PLAN BOOK FOUR CHAPTER 12, PAGE 35
\
l ANSWER 5.14 (2.00)
- c. 4.77% (+- .48%)
- b. 3.8% (+- .38%)
- c. 1.0% (+- .10%)
- d. 3.0% (+- .30%) [4 0 0.5 each3 (2.0)
REFERENCE Dresden Reactor Physics Lesson Plan Book 4, Ch. 12, PP. 26-32, Figures 58-62 GGNS: OP-NP-513, OP-NP-514
1
- 5. THggRy_gF_NUGLEAR_EgWER_ PLANT _QPEBAllgN g _FLUlggt_ANg PAGE 22 IHEBdggyN6digg
' ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
EIH: L-RO-604; L-RD-605 ANSWER 5.15 (1.00) 70% void f raction in the core (0.5)
There is a larger % change in water volume for the same increase (3.45% vs 1,1%) [0.53
-OR-The voids produced at 70% VF have a larger effect on core reactivity since they are in an area of higher neutron flux [0.53. (0.5)
REFERENCE Dresden Reactor Physics Review Lesson Plan, Book 4, Ch. 12, P. 33 l
l l
1 l
l
6t__ELONI_gygIgdg_pggl@N _QQNIBQLg_@NQ_lNgIBydgNI911gN i
PAGE 23 ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 6.01 (3.00)
- o. Instrumentation tap for measurement of core DP.
- b. Pressure reference for measuring jet pump flow,
- c. Input to the core spray line break detection s'ystem.
- d. Input to CRD for cooling water and drive pressure DP.
[4 0 0.75 each3 (3.C)
REFERENCE Dresden Student Text #1, Book 1, P. 7 ANSWER 6.02 (2.00)
- o. The risers are provided to permit lowering the recirculation inlet no::les [0.53 to remove them out of the active core region [0.53. (1.C)
- b. So that they do not receive a significant fast neutron exposure
[0.53 which could change the mechar.ical properties of the materials [0.53. (1.C)
REFERENCE Dresden Student Text #1, Book 1, P. 13 ANSWER 6.03 (2.50)
- a. Standby coolant supply system
- b. Steam flow restricters
- c. CRD velocity limiters
- d. CRD housing supports
- o. Standby liquid control system Drywell nitrogen inerting [5 9 0.5 each3 (2.5) f.
REFERENCE Dresden Student Text #5, Book 1, P. 5
51__EL8NI_gygIgdg_QggigN _GQUIBQLs_8NQ_INgIBydgNIBI1QN z PAGE 24
. ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 6.04 (3.00)
- c. 1. O to +60 in (0.25)
- 2. Temperature compensated by a pressure signal (electrical compensation) (0.25)
- 3. Level input to feedwater control (0.25)
- b. 1. -60 to +60 in. (0.25)
- 2. Heat clamp between the reference and variable leg (0.25)
. 3. Recirc pump trips and ARI valve opening. (0.25:
- c. 1. -70 to +330 in. (0.25
- 2. None (0.25)
- 3. None (0. 25)
, d. 1. -340 to +60 in. (0.25:
- 2. None (0.25) l 3. LPCI/ containment spray interlock (0.25) j REFERENCE Dresden Student Tm:t #4, Book 1, PP. 3, 4, and 5 ANSWER 6.05 (1.00) l
- a. Increase (0.5)
- b. None (0.5) f REFERENCE Dresden Student Text.#4, Book 1, PP. 15 and 16 ANSWER 6.06 (2.75)
- 2. RPS subchannel A1, A2, A3, and B1, B2, B3 deenergized (0.5)
- b. Anticipates control rods inserting in a random pattern as their scram valves overcome spring pressure, precludes this by dumping the air at a preset pressure. ( 0. 75)
- c. RPS Bus A and B (0.5)
6t__ELONI_EYEIEdg_pggigN g_QgNIBg63_gNQ_lNEIBydENIBIIQN PAGE 25
- ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
REFERENCE Drcsden Student Text #6, Book 1, FP. 26 and 27 ANSWER 6.07 (1.75)
LPSP Actuate Total steam flow >/= 20% [0.253 AND [0.1253 feed flow >/= 10% for at least [0.253 60 seconds [0.1253 (0.75)
Deactuate (steam flow </= 20%) [0.253 OR (f eed flow </+ 10%)
[0.253 (0.5)
LPAP Actuate Total steam flow >/= 35% (0.25)
Deactuate total steam flow </= 35% (0.25)
REFERENCE Dresden Lesson Plan #8, Book 1, P.7 ANSWER 6.08 ( .75)
- o. breakdown
- b. bushing
- c. 60 E3 9 0.25 each3 (0.75)
REFERENCE Dresden Student Text #1, Book 2, P. 6 ANSWER 6.09 ( .50) 2000 RPM (0.5)
REFERENCE Dresden Student Text #10, Book 3, P. 35 l
l l :
y
6:__P66NI_EySI[d!_p[SIGUx_QQNIBg62_gND_lNSIBydENI6IlgN PAGE 26
- f.NSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 6.10 (1.25) t
- c. Oxygen
- b. IGSCC
- c. Recombine
- d. Hydrogen
- o. Explosions [5 9 0.25 each] (1.25)
REFERENCE Dresden Student Text #5,_ Book.2, PP. 2-5 4
ANSWER 6.11 (2.75) e
- a. One channel upscale [0.25] and one channel downsc al e [0.253, or both channels [0.25] upscale [0.253. (1.2)
- b. 1. Off-Gas chimney Isolation valve closes. (0.5)
- 2. Off-Gas drain valve closes. (0.5)
- 3. Of f-Gas pressurized drain tank is isolated f rom the i pressuri:ed drain pump..
(0.5)
- c. 15 minutes (0.25)
REFERENCE Dresden Student Text #1, Book 3, Page 8 l
ANSWER 6.12 (2.00)
- a. 1. Motor Pump A MCC 28-1 . (0.25)
- 2. Motor Pump B MCC 29-1 (0.25)
- c. To prevent chugging [0.253. As the reactor pressure decreased from the insertion of negative reactivity [0.25] the flow f rom a centrifical pump would increase [0.253, resulting in a rapid injection of boron [0.25]. (1.0)
REFERENCE Dresden Student Text #3, Book 3, PP. 5 and 11 l
l l
l I
bz__ELONI_gygIgdg_pggl@N_QQNIBQLg_9Np_lNSIB(idgNI9IlgN g PAGE 27 ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 6.13 (1.00)
- a. 1. Aux electric room (0.25)
- 2. Computer room (0.25)
- b. 1. False (0.25)
- 2. True (0.25)
REFERENCE Dresden Student Text 4t 5, Book 4, PP. 15 and 16 9
J .-
Z___PB99E99BES_:_NQBd@6t_@^NgBd@6t_gdgBggNgy_@NQ PAGE 28 58D196991G86_ggNIBQL ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 7.01 (2.75)
- 2. RPV pressure above 1060 psig. (0.5)
- 3. Drywell pressure above 2.0 psig (0.5)
- 4. A condition which requires reactor scram AND reactor power i s either:
- b. Cannot be determined (1.0)
REFERENCE Dresden DEOP 100, P. 1 ANSWER 7.02 (1.50)
- a. DEOP 100-1 (Reactor Level Control)
- 6. DEOP 100-2 (RPV Pressure Control)
[3 0 0.5 each3 (1.5)
- c. DEOP 100-3 (Reactor Power Control)
REFERENCE Dresden DEOP 100, P. 1 ANSWER 7.03 (1.50) 49-5+
a.1 Charging water valve 2(3)-03-1-25 must be closed.
(0.25)
- c. W. :rr% w " DEEP" rods. Qg REFERENCE Dresden DEOP 100-3, PP. 6 and 7 L9 a.$ .sh ci 40 ue ,s w r UId a3 spi /{y kne/ an ce4/ Mi a&j & fn rpey e reso - zo a 4/ so:M. +13) i t
a
PAGE 29 lZm__EBQGEDWBEE_:_NQBd@(S_ggNg8d@(g_gdE8GENgy_gNQ BBQlD69GIGBL_QQN18QL ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 7.04 (2.00)
- a. >/= 1.02
- b. > 20%
- c. </= 20% (2.0)
- d. .90 E4 9 0.5 each3 REFERENCE Dresden DGP 1-1, P. 18 ANSWER 7.05 (2.00)
- o. If excessive vibration is noted (> 15 mils) i b. Lower vacuum approximately 2 inches
- c. Do not lower vacuum below 25" (No greater than 5 inches of Hg back pressure.)
- d. It imposes excessive loads on the turbine last stage buckets. (2.C)
C4 0 0.5 each]
REFERENCE Dresden DGP 2-1, P. 11 ANSWER 7.06 (2.50)
- o. 1. Reactor startup l 2. Rx shutdown (all rods in) or scram (1.5)
- 3. A change of >/= 500 MWT in 1 hear [3 9 0.5 each]
- b. 1. Notify RAD-CHEM Department of increased sampling (0.5) requirements.
- 2. Make the required entry in the unit Log Book. (0.5)
REFERENCE Dresden DGP 3-1, PP. 1 and 2 l 9 t
It__BB9GEDWBEE_:_N9Bdebt_eRN9Bdebt_EdEBEENGY_eNQ PAGE 3D
, bed 1969ElGe6_GONIB96 l ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 7.07 (2.50)
- o. Reactor scram
- b. Group 1 isolation
- c. Chimney isolation valve closure
- d. Air ejector suction valve closure
- s. Mechanical vacuum pump trip [5 9 0.5 each] (2.5)
REFERENCE -
Dresden DGA 16, P. 1 ANSWER 7.08 (1.50)
- a. Crud burst
- b. Air intrusion
- c. Rosin intrusion [3 0 0.5 each] (1.5)
REFERENCE Dresden DGA 16, P. 3 ANSWER 7.09 (1.50)
- a. 1. Job completion
- 2. Conditions change
- 3. Cancellation
- 4. RWP expired [4 9 0.25 each] (1.0)
- b. 1. 24 ha.. . /jff"'
- 2. 7 J-7, j /d p/ f0I, [2 9 0.25 each3 (0.5) l
[ REFERENCE Dresden Radiation Protection Standards, PP. 11--EP/jV i
l l
Z___EB99E998gS_:_NgBd@bz_9BNgBd@(i_EdgBggNgy_@Ng PAGE 31
. 689196991986_99NIBg6 ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 7.10 (3.00)
- c. Whole Body
- Life saving 75 rem (0.5)
- Less urgent actions 2.5 rem (0.5)
- b. Extremities
- Life saving 200 rem fod (0.5)
- Less urgent actions FEE rem (0.5)
- c. 1. 25 rem (0.5)
- 2. Once in a lifetime (0.5)
REFERENCE Dresden Radiation Protection Standards, P. 26 ANSWER 7.11 (1.00)
- a. R:-: power > 20% (0.5)
- 6. 65-100% of rated core flow (0.5)
REFERENCE Dresden 2 Tech. Spec. 3.3.G ANSWER 7.12 (1.50) l
- a. False (0.5)
- b. True (0.5)
- c. False (0.5) i l
l REFERENCE I Dresden Tech. Specs. 3.3.B i
i i
i
Zz__gggggQyggS_:_NQBdebt_eENQBd@(g_EMEB@gNQX_@NQ PAGE 32 BOD 196991GBL_GQN1896 ANSWERS -- DRESDEN 2L3 -86/06/24-HANEK, J.
ANSWER 7.13 (2.00)
- c. 1. Hour f
- 2. Vessel metal we4er 8Y v4 7-*"
- 3. Water level or water temperature
- 4. Water temperature or water level [4 S 0.25 each3 (1.0)
- b. 1. Increase SDC flow
- 2. Start another SDC pump
- 3. Start CRD pumps
- 4. Flood the main steam lines while draining through the main steam line drains [4 S 0.25 each] (1.0)
REFERENCE Dresden DOP 1000-3, P. 3 0
- ,- -..e,-,- -,, -
mp --
'___8Dd1NIQI6811ME_PBQCEQySE@g_CQNQ111QN@t_@NQ_(ldlI@IlgNQ PAGE 33 B
. ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 8.01 (1.00)
"At-the-controls" means the unit operator is in line of sight of the unit front panels. (1.0)
REFERENCE Dresden DAP 7-2, P. 4 ANSWER 8.02 (3.50)
- a. Shift engineers office [0.253 or the control room [0.253 (0.5)
- b. 1. Review and initial the previous shift's emergency systeni s checklist.
- 2. Review previous shif ts daily surveillance sheets.
- 3. Review the unit and center desk logs from the last date on shift or preceeding four days whichever is less.
- 4. Review current daily orders.
- 5. Review the unit equipment out-of-service log.
- 6. Review and verify degraded equipment log is properly filled out.
- 7. Walk thru unit and center desk control panels.
- 8. Complete the on-coming section of the shift supervisor's turnover checklist. [6 required 9 0.5 each3 (3.0)
REFERENCE Dresden DAP 702, PP. 1 and 2 ANSWER 8.03 (1.50)
- a. 1. Safety evaluation checklist is completed and reviewed b-TWO SRO's one of whom shall be a S.E.P. (0.5)
- 2. Jumper is authorized by the shift engineer. (0.5)
- b. NRC approval is required prior to implementation. (0.5)
REFERENCE Dresden DAP 7-4, PP. 2 and 6
dm__endlu1SIseI1YE_e8gggnusgSm_coun111geSm_esD_Lin11eI1QuS PAGE 34
-86/06/24-HANEK, J.
. ANSWERS -- DRESDEN 2&3 ANSWER B.04 (1.50)
- a. 1. Locking the area except when access is required.
- 2. Use of an access control monitor to restrict entry.
[2 9 0.5 each] (1.0)
- b. 1. Shift Engineer Shift Foreman [2 9 0.25 each] (0.5) 2.
REFERENCE Dresden DAP 12-4, PP. 1 and 5 ANSWER B.05 (1.50)
The notch override switch shall (0.5) not be used between positions 00 and 24 [0.53 until the first bypass valve is open E0.253, or the unit (1.5) is on the line [0.253.
REFERENCE Drssden DGP 1-4, P. 32 ANSWER 8.06 ( .50)
(0.5)
False REFERENCE Dresden DGP 2-3, P. 7 ANSWER 8.07 (2.00)
- a. Unit 3 60%
Unit 2 43% E2 9 0.5 each] (1.0)
- 6. Inadequate jet pump riser in Unit 2 which causes large jet pump vibrations during single loop operation. (1.0)
REFERENCE Dresden DOA 202-1, PP. 1 and 4
~.
l
)
ht__eDdlNISIBellVE_EB9GEQWBE5t_G9NQlliQN@g_@NQ_(ldll@IlQNS PAGE 35
- ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER B.08 (3.00)
- c. Unit startup.
- 1. During the time period just prior to placing the reactor mode switch in the run position until the beginning of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> xenon soak. (0.75)
- 2. During the time period between the end of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> xenon soak and the placement of the unit on the 5 MWe/hr ramp rate. (0.75)
- b. Unit shutdown
- 1. From the initial load drop with recirculation flow to placing the reactor mode switch to startup. (0.75)
- 2. Any anticipated power change (increase or decrease of greater than 150 MWe within an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> time period. (0.75)
REFERENCE Dresden Operating Order #5-86 ANSWER 8.09 (1.00)
- 1. Notify the operating engineer on duty supervisor. (0.5)
- 2. Notify NRC Region III (0.5)
REFERENCE Dresden Operating Order #25-86 l
ANSWER 8.10 (3.25)
- c. MCPR < 1.06 GE 8x8R or 1.05 ENC and GE 8x8 fuel With Rx pressure > 800 psig and core flow > 10% of rated. (1.0)
- b. Core thermal power shall not exceed 25% of rated when reactor pressure is less than 800 psig or core flow
< 10% of rated. (0.75)
- c. Neutron flux shall not exceed the scram setting for longer l than 1.5 seconds as indicated by the process computer. (0.75)
- d. With irradiated f uel in the reactor, the water level shall not be less than 12 inches above the top of the active fuel. (0.75) l REFERENCE Dresden Tech Specs 1.1 A thru D
s._._eDdlNig16@llyE_PBgCEDyBE@t_CQNDillgNSt _6NQ_LidlI611gNE PAGE 36 ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 8.11 (1.50)
Rmactor shall be shutdown immediately and shall not be resumed until cuthorized by the NRC [0.53 report's, hall be promptly made to the Division V-P Nuclear Stations [0.53 and the N operations center as soon as (1.5) possible within one hour E0.5].
REFERENCE Dresden Tech Specs 6.4, P. 6-16 ANSWER 8.12 (2.25)
- a. 1. 2
- 2. 1
- 3. 3
- 4. 5
[5 9 0.25 each] (1.25)
- 5. 1
- b. Shift crew composition may be less than the minimum requirements for a period of time not exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to cccommodate unexpected absence provided immediate action is taken to restore the composition to within the minimum requirements. (1.0)
REFERENCE Dresden Tech. Specs. Table 6.11, P. 6.5 ANSWER 8.13 (2.50)
The intent of the original procedure is not altered. (0.5) a.
- b. The change is approved by two members of the plant management staff at least one of whem holds an SRO license on the (1.0) unit affected.
- c. The change is documented, reviewed by the onsite review and invesitgative function and approval by the station (1.0) superintendent within 14 days of implementation.
REFERENCE Dresden Tech Spec's 6.0D, P. 6-16
5___0Dd1NISIBQIlyE_EBgCEQQ$ES 3 ._CQNQlligNL,_@NQ_(ldlI@llgNS PAGE 37
' ANSWERS -- DRESDEN 2L3 -86/06/24-HANEK, J.
ANSWER 8.14 (1.00)
- c. 5 (0.5)
- b. Quarterly (0.5)
REFERENCE Dresden Tech Spec's 6.1E, P. 6.1 ANSWER 8.15 (1.00)
- a. Take action to restore it within 15 minutes. (0.5)
(0.5)
- b. Two hours REFERENCE DRESDEN - TECHNICAL SPECIFICATIONS, 3.5I, page 3/4.5-15 l
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _DRESDEN_2ty3_____________
REACTOR TYPE: _BWR-GE3_________ _______
DATE ADMINISTERED: _@6f@bf2d________________
T C0PY EXAMINER: _HANEK i _J._______________
APPLICANT: _________________________
INSIBUCI1ONS_IQ_8EE61C8NIi Uste separate paper f or the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. 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 six (6) hours after the examination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY
__YOLUE_ _IDIBL ___ECOBE___ _yGLUE__ ______________C@lEGOBy_____________
_2pagg__ _23 Zs ___________ ________
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
_ 2_ _4 _ _7 _5 _ _ _ _2 _4 _. _0 _3 ___________ ____-___ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS l_2b:2E__ _2E 22 ___________ ________ 3. INSTRUMENTS AND CONTROLS
_26z99__ _2Ez24 ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL l CONTROL 1
'1g3:99__ 1g9 99 ___________ ________ TOTALS l
l l
l FINAL GRADE _________________%
- All work done on this examination is my own. I have neither I giv
- n nor received aid.
l l
l EPPLiCd5TI5~5555dTUR5~~~~~~~~~~~~~~
l l
l
NRC RULES A W GUIDELINEL FOR LICENSE EXANINATIONS During the ad=1:.1:tration of thi: exa=inetton the fellowing rule: apply:
- 1. Cheating on the examination seens an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be Ilmited 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 gly 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 categor{ on a new page, write Jon1 one sTde of the paper, and write "Last Page on th 7 east answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 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 literature.
- 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 00 NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of th.e examination are not clear as to intent, ask questions of the examiner 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 examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
l (2) Exam aids - figures, tables, etc.
l (3) Answer pages including figures which are a 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. :
l 1 -- . - . -
Iz__ESINCIE(ES_QE_ NUCLE @S_EQWEB_E6@NI_QEE8@IlgN t PAGE 2 IUEEdQQyN@dlC@t_dE@l_lB@NSEEB_8NQ_E(Ulp_E6QM QUESTION 1.01 (1.00)
In a subtritical reactor, Keff is increased f rom .880 to .965.
Which of the following is the amount of reactivity added to the core?
- a. .085 delta k / k
- b. .100 delta k / k
- c. .125 delta k/k
- d. .220 delta k / k QUESTION 1.02 (1.00)
The reactor trips f rom f ull power, equilibrium XENON conditions. Twenty-four hours later the reactor is brought critical and power level is main-tained on range 5 of the IRMs for several hours. Which of the following statements is CORRECT concerning control rod motion?
- a. Rods will have to be withdrawn due to XENON build-in.
- b. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of XENON burnout.
- c. Rods will have to be inserted since XENON will closely follow its normal decay rate.
- d. Rods will appro::imately remain as is as the XENON estab-lishes its equilibrium value for this power level.
l i
l l
I l
l (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
i 1
It__EBINQlELES_QE_NQQ(E68_EQWEB_E(@NI_QEgB@IlgNt PAGE 3 16EBdQQYU@dlG@t_6E@l_IB88@EEB_8NQ_ELylQ_ELQW QUESTION 1.03 (1.00)
Concerning control rod worths during a reactor startup from 100% PEAK XENON versus a startup under XENON-FREE conditions, which statement is correct? (1.C)
- c. BOTH control rod worths will be LOWER regardless of core XENON conditions.
- b. CENTRAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.
- c. BOTH control rod worths will be the SAME regardless of core Xenon conditions.
- d. PERIPHERAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.
QUESTION 1.04 (3.00)
The reactor is shutdown and a plant cooldown is in progress.
Rwactor pressure decreases from 450 psia to 300 psia in a 30 minute period. SHOW ALL WORK.
A. What is the cooldown rate? (1.5:
1 B. How much reactivity has been inserted in the rector due to the moderator temperature coefficient (MTC)? (1.C; i
C. With the above temperature change, has the MAGNITUDE of the MTC changed and if so, in what direction (more/less, positive / negative)? (.Si OUESTION 1.05 (2.00)
Rzgarding MCPR (Minimum Critical Power Ratio):
- a. What PHENOMENON could exist in a fuel fundle if it were operated at a MCPR LESS THAN ONE (< 1.0) and WHAT would l very likely be the CONSEQUENCE of the phenomenon? ( 1. C :-
- b. When core flow is LESS THAN RATED, is MCPR increased or decreased. (1.C;
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
I
1_ __EBINQ1 ELE Q,QE _NQQ(E@B_EQWE B_E(@NI_QEgB@llgN u PAGE 4 ISEE590XN Bd lGE u_SEBl_ISBNEEEE _6MD _ELWlD _E6QW QUESTION 1.06 (2.00)
- a. Which time in core life (BOL, Mid-of-life, or EOL) requires the least amount of positive reactivity addition to achieve prompt critical AND why?
- b. What is the definition of prompt critical?
QUESTION 1.07 (2.50)
A. What are THREE of the FIVE design or operational factors that insure adequate Net Positive Suction Head (NPSH) for the recirculation pumps? (1.5)
B. Briefly, explain what NPSH is. (1.0)
DUESTION 1.08 (1.50)
Give ONE undesirable result f or each of the following.(Be more cpecific than " pump failure"):
A. Operating a centrifugal pump for extended periods of time with the discharge valve shut. (0.5)
B. Starting a centrifugal pump with the discharge valve f ull open. (0.5)
C. Operating a motor driven pump under " PUMP RUNOUT" conditions. (0.5)
QUESTION 1.09 (2.00)
A. DEFINE " Condensate Depression". (.5)
B. WHY is it necessary for plants to operate with condensate depression? (1.0)
C. HOW would CYCLE EFFICIENCY be effected if the amount of condensate depression is increased? (.5)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE ***38)
'lu__EBING1 ELE @_QE_NyGLE88_EQWEB_EL@NI_QEEB8IlQNm PAGE 5 ISEBdgDYU8dlGEt_SE@l_IB8MSEEB_@NQ_ELylD_ELQW QUESTION 1.10 (1.50)
In a reactor fueled with U-235 and U-238:
A. Which nuclide(s) may fission.upon absorbing a fast neutron? (.5)
B. What fissile nuclide can U-238 be converted into? (.5)
C. At the Middle of Core Life (MOL), which 2 nuclides will absorb a thermal neutron and fission? (.5)
QUESTION 1.11 (2.00)
For the f ollowi ng transients, indicate which COEFFICIENT of reactivity; alpha T, alpha D, or alpha V tends to change reactor power FIRST and in what DIRECTION.
A. Fast closure of one MSIV. (0.5)
E. Isolation of a feedwater heater string. (0,5)
C. A control rod drop. (e,5)
D. Relief valve lifting. (0.5)
QUESTION 1.12 (2.00)
A significant amount of excess reactivity must be loaded into a core at BOL so that 100% power can be attained at the end of a fuel cycle. For each of the f ollowing, LIST the approximate value of K-excess which must be loaded to overcome that negative reactivity component at rated-equilibrium conditions.
- a. Moderator temp increase
- b. Void fraction increase
- c. Samarium buildup
- d. Xenon buildup
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1- PRINCIPLEg_gF_NUQLEBR_PQWgR_PL@NT_QPgRATigNi PAGE 6
,' ISEgdggyN9diggi_dE91_IBBNgEE8_8Np_E6Ulp_ELgW DUESTION 1.13 (1.00)
STATE for which condition the reactivity coefficient contribution would be MORE NEGATIVE. EXPLAIN your choice.
Moderator Void Coefficient for a 1% INCREASE in void fraction at 10% void fraction in the core,
-OR-Moderator void coefficient for a 1% INCREASE in void fraction at 70% void fraction in the core.
QUESTION 1.14 (1.00)
Th2 Ox8 fuel has a thermal time constant of approximately 5 to 6 seconds. This means that in 5 to 6 seconds following a sudden power increase: (choose ONE answer below) (1.0)
- a. The fuel centerline temperature will reach its maximum (final) value.
- b. Clad surf ace temperature will reach its final value.
- c. Fuel centerline temperature will reach approximately 2/3 of its final value.
- d. Fuel centerline, clad and coolant temperature have reached their final values.
- e. Clad surface temperature will reach approximately 63% of its final value.
DUESTION 1.15 (2.00)
Indicate HOW each of the coefficients are effected [ Increase, Decrease or Rimain the same] by each of the three parameters listed? Consider each pcrameter separately.
- c. Rod Worth (delta K/K/ Bank) by:
- 1. Moderator temperature INCREASES
- 2. Voids DECREASE
- 3. Fuel temperature INCREASES [3 0 0.33 ea]
- b. Alpha Voids (delta K/K/ % voids) by:
- 1. Fuel temperature INCREASES
- 2. Core age INCREASES
, 3. Control Rod Density INCREASES [3 0 0.33 ea]
l l
l (***** END OF CATEGORY 01 *****) ,
1 I
s__Eb@N1_QE @l@N_lyC(UQ1N@ _EQEElY _@MQ _EUER @E NC Y _@Y@lE d@ PAGE 7 QUESTION 2.01 (1.50)
Other than floor drains, list THREE inputs to the reactor building floor drain sump.
QUESTION 2.02 (3.00)
- a. Other than the Instrument Air Dryers, list FOUR components where moisture is removed from the Instrument Air System. (2.0)
- b. Where do the service air and Unit 3 cross-ties tap into the Unit 2 Instrument Air System. (Upstream or downstream of a major component required as a reference.) (1.0)
DUESTION 2.03 ( .50)
A downscale trip on an area radiation monitor could be an indication of which of the following: (CHOOSE ONE ONLY)
- a. Low background in the area of the detector.
- b. Instrument failure.
- c. A saturated G-M tube from a very high radiation level.
QUESTION 2.04 (2.00)
Concerning the fuel pool cooling filter demin bypass valve (1901-40), list TWO purposes of this valve that require it to be open.
QUESTION 2.05 (1.50)
List THREE functions provided by the RWCU system taking a suction on the reactor vessel lower head.
l l
(***** CATEGORY 02 CONTINUED ON NEXT PAGE ***?*)
2___E68SI_pEgl@N_ING69pidg_S$EEIy_8NQ_EdEBGENCy_Sy@Igdg PAGE B QUESTION 2.06 (2.75)
- a. List THREE signals that will cause a HPCI (Group IV) isolation.
Include applicable setpoints. (1.5) b, If the HPCI turbine is running when the Group IV signal is received, what actions will occur. (1.25)
QUESTION 2.07 (3.25)
- a. What conditions are required f or automatic ADS initiation (include setpoints). (2.25)
- b. What signal (s) will actuate the solenoids f or the electromatic relief valves if the control switch is the f ollowing positions. (1.0)
- 1. Off
- 2. Manual
- 3. Automatic OUESTION 2.08 (2.75)
- a. The isolation condenser will actuate at a.l._____ psig after a
- a. 2. _____ ti me del ay. (1.0)
- b. What is the function of the time delay and what would be the effects if it were not used? (1.0)
- c. List THREE sources of shell side makeup water (primary and backup). (0.75) l QUESTION 2.09 (2.00)
- a. Why are risers utilized on the jet pumps?
- b. What would be the detrimental effects of not utilizing risers?
l l
l l (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
(
i f
2___P(@N1_pgSIGN_lNQ(UDIN@_S@Egly_QUp_gdEB@ENCy_gy@ led @ PAGE 9 QUESTION 2.10 (2.00)
Concerning the Standby Liquid Control Pumps.
- c. What is the power supply (s) to the pump motors? (0.5)
- b. What is the power voltage and supply to the squib valves? (0.5)
- c. Briefly, explain why positive displacement pumps are utilized instead of centrifical pumps. (1.0)
QUESTION 2.11 (1.00)
There are TWO sets of vacuum breakers associated with the containment cystem. Provide the following information on each set.
- a. Setpoint
- b. Normal position DURING a LOCA
- c. Safety actuation flow path QUESTION 2.12 (2.50)
Other than the Emergency Core Cooling Systems, list FIVE of the SIX systems
- or components that constitute the engineered safeguards at Dresden.
l l
l l
(***** END OF CATEGORY 02 *****) ,
PAGE 10 3___INDIBudENIS_9dD_G9 NIB 962 QUESTION 3.01 (2.75)
- a. The retirc pump speed control mismatch circuitry prevents exceeding a ___a.___ speed mismatch between the two recirc (0.25) pumps.
- b. W' hat is the primary and secondary reason speed mismatch (1.0) is limited?
- c. What protective function occurs if the mismatch exceeds the (0.5) limits established in a. above?
Under what conditions will the circuit trip a recirc pump? (0.5) d.
- c. What function (associated with mismatch) allows restart of an idle (0.5) recirc pump?
DUESTION 3.02 (2.50)
- a. If the plant is operating with one main steam line i sol at ed ,
thy is the main st -sm line rad monitor for that line considered (0.75) operable?
- b. What type of detectors are the main steam line rad monitors? (0.5)
- c. What is the main source of the background reading when at power? (0.5)
- d. Why is the background reading different for Unit 2 and 3? (0.5)
- e. Is the downscale alarm a valid indication of instrument (0.25) failure when at very low power levels (not in run)?
l l
l QUESTION 3.03 (2.50)
List FIVE of the SIX conditions that must be met for an auto start of a ctandby feed pump. (include applicable setpoints.)
l l
f t
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
)___1gSIBUMENIS_AND_CONIBOb6 PAGE 11 QUESTION 3.04 (3.00)
For each of the below listed vessel level indications, provide the following
- 1. Range
- 2. Method of temperature compensation (if any)
- 3. Major control functions besides indication at,1d alarm (i f any).
- a. Narrow Range GE/MAC
- b. ATWS Level Transmitter
/ 1
- c. Wide Range GE/MAC l k##
- d. Wide Range Yarway c/ 7,g QUESTION 3.05 (1.75)
With respect to the RWM, what signal (s) are uti; ired to actuate and deactuate the LFSP and LPAP (include applicable setpoints and times).
4 QUESTION 3.06 (2.75)
The Off-Gas HI-HI Radiation Trip logic will initiate on TWO conditions.
a .- What are these conditions? (1.0)
- b. List THREE auto actions that will result from a trip condition f ollowing timeout of the Timer. (1.5)
- c. What is the setting of the Timer? (0.25)
QUESTION 3.07 ( .50)
Following an auto initiation of HPCI, the low pressure sensing line from the HFCI flow element (FE-2-2356) ruptures. (Assume 1000 psi g R>:
pressure.)
l l
After rupture, what would be the HPCI turbine speed assuming no operator action?
l l
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
i
PAGE 12 3___INSIBUdENIg_9dD_C9 NIB 96@
QUESTION 3.08 (1.00)
With respect to the Narrow Range Yarway instrument, what affect will the f ollowing have on indicated level
- a. Increase in Drywell Temperature
- b. Increase in Reactor Building Temperature near the Instrument Rack.
QUESTION 3.09 (2.00)
Briefly, explain how the f eedwater regulating bypass valve " Runout" control functions. Refer to attached Figure 1.
QUESTION 3.10 (2.00)
Explain how each of the f ollowing components in the f eedwater regulating valve control circuit function if a lockout signal is received.
Rmfer to attached Figure 2.
- a. Pressure switch
- b. Solenied operated pilot valve
- c. Air dump valve
- d. Air lock valves QUESTION 3.11 (2.00)
[
List FOUR events / signals which occur (in order) as EHC oil pressure dscreases from 1600 psig to 500 psig. (Setpoints not required.)
l QUESTION 3.12 (2.00)
- c. While operating at 100% power a " Stator Cooling Pumps Auto Trip" What automatic action will occur as a annunciator is received. (Confine result of this alarm? your answer to the tur bine af f ects only.)
l
- b. What action is required to restart the stator cooling pumps?
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
PAGE 13 ht__1MEIBQUEMI5_98Q_GQUIBQLS QUESTION 3.13 (2.00)
A 4kv breaker has neither red or blue lights illuminated, the control ewitch is not in. pull to lock and the bulbs checkout good. List TWO probable causes of this condition and the results, i
i i
i I
l i
l i
l l
(***** END OF CATEGORY 03 *****) ;
.w
- k. PROCEDUREg_ _NQRMAl t_ABNgRMAL _EMERgENC,V_AND u PAGE 14 88D196991C66_CgN16g6 QUESTION 4.01 ( .50)
Loss of cooling water to a recirculation pump requires pump shutdown within
___1.___ to avoid pump ___2.___ damage.
QUESTION 4.02 (2.50)
List FIVE automatic actions initiated by a main steam line High Radiation Alarm at 3 X normal. .
QUESTION 4.03 (2.00)
While the plant is in shutdown cooling with the reactor recirculation pumps not running surveillance of the vessel meta 1' temperature recorder is required at least once per a.1.______. Stratification is indicated by an increasing a.2.______ temperature without a corresponding a.3.______ or a.4.______ change.
- a. List parameters a.1. through a.4.
- b. If the RWCU system is not available and both recirc pumps are off, list FOUR suggested actions to minimize stratification.
QUESTION 4.04 (2.00)
DOA 202-1, recirculation pump trip requires the operator to reduce the epeed of the running recirc pump.
- c. What are the limits f or each unit at Dresden?
- b. .What is the reason for this difference?
OUESTION 4.05 (1.50)
Attachment A to DGP 1-1 gives special precautions to prevent a short period ovent.
After reaching a black and white pattern, what restrictions apply?
i e
f
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
jg__PBQQEQQ8E@_ _NQBd@bg_6ENQBd@(g_Edg8@[NQY_6NQ PAGE 15 E8DlQLQGIG86_QQNIBQL QUESTION 4.06 (1.00)
DAP 7-2 specifies that a licensed operator or senior licensed operator chn11 be "at-the-controls" at all times.
What is the meaning of "at-the-controls"?
QUESTION 4.07 (1.00)
List TWO conditions that must be met prior to placing the economic gIneration control system in operation with automatic flow control.
QUESTION 4.0B ( .50)
When may seal purge flew be established during a recirc system startup pur DO 202-1?
QUESTION 4.09 (1.00)
A coupling check is perf ormed when withdrawing control rods to position 48.
- a. EXPLAIN HOW this coupling check is performed. (0.5)
- b. WHAT indication would tel) the operator the rod was uncoupled? (0.5)
OUESTION 4.10 ( .75)
While perf orming a reactor startup, the SRM's are withdrawn to maintain greater than ___1.___ cps and less than ___2.___ cps until the IRM's are on range ___3.___ or above. Failure to maintain these limits will result in a rod block.
QUESTION 4.11 (2.50)
Other than a decreesing neutron flux, list FIVE other check's the operator can ',ke to assure Standby Liquid Control is injecting.
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
- 4. PROCEDURES _ _NgRDAli _ABNQRdAl i_gdgRGENgy_@Up PAGE 16
, R_A_D_IO_LO__G_IC_A_L_C_ONTR_OL_
)
DUESTION 4.12 (1.25)
- c. In reference to the Dresden II Tech.. Specs. for the primary containment, the suppression pool water temperature shall not exceed ___a.1.___ during normal power operation. During testing which adds heat to'the suppression pool, the pool temperature shall not exceed ___a.2.___ and must be obsLrved and logged every (0.75)
___a.3.___ minutes until the heat addition is terminated.
- b. What is the maximum suppression pool temperature allowed during reactor operation? e (0.25)
- c. What action is taken if it exceeds this maximum temperature during operation? (0.25)
DUESTION 4.13 (2.00)
Tech. Specs. discuss that the pref erred method utilized to disarm a CRD is electrically.
- a. How is this action performed? ,"
- b. List TWO reasons why this is the preferred method?
DUESTION 4.14 (1.00)
What would be the expected whole body dose rate f or each of the following areas at Dresden?
- a. Radiation Area
- b. High Radiation Area l
l OUESTION 4.15 (1.50)
What are the quarterly exposure limits established by the NRC for the
! f ollowing: (Assume NRC-Form 4 completed.)
l l
- a. Whole body l
- 6. Skin of whole body f c. Hands, forearms, feet, and ankles I
(44*** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
l _
I t__EEQQ[QUEg@_ _NQEd@(g_@@@ qed @(g_EMEE@[NQY_@NQ PAGE 17 l E89196991GOL_G9NIEQL OUESTION 4.16 (1.00)
Anawer the following TRUE or FALSE.
- c. At least one IRM must be in service in the core quadrant where refueling is taking place.
- b. An SRM detector is considered inoperable if it has less than 3 cps under any conditions.
QUESTION 4.17 (2.50)
When paralleling electrical sources, the synchroscope should be rotating
- 1. in the ___2.___ direction and ___3.___ voltage should be slightly
___4. ___ t h an t h e ___5. ___ vol t ag e.
QUESTION 4.18 (1.50)
Whil e i ncreari r.g load on the main generator, what controls are used to adjust the f ollowing:
- a. Main Generator VARS
- b. Amplidyne AVR Balance
(***** END OF CATEGORY 04 *****) ,
(************* END OF EXAMINATION ***************)
O M k
=
I a-C El
.s5
< Ji g 3
N s
t h
- 9981 ' '%
E '
\
IWWl:
8
.5 3' .
it i 5.!s wt
^'
E!!_
lia sw" W
"w o 77 --
, gg-3 I
g i
= 3 x a D-e s= .-
s e!
.4. i : i{ u$ *g g, .
s .
lgi ~
==
~
t ^ -I 1
, t L Er.
s u I t
g tt n. wa
=
=
. ~ 55ag g,3 1 g ~
tt , ,
l
- g - ,,,,
T -
- g 1 , ,
[sa -
=5
" ,;, ; o w
hw 3
= ,
$s
. e 5.>
a E 1
=
=ts;5 IE
S 8
g4
(~N.,9 a*
< .t U i V ll 1:
i t 90 h
? T q s l
i; W
=
j,d %
W [ D "3 - 4 h
4g E8><
(s I t
. - --- = ,;'
w>
s8>i
<a ), ' '
7
,A t
5 l l o gi:
J k
$ l l =
62 '
HE u +
- -. e t i 1
- :- g g f r i g, A/ t ,
- A
.. rr
- 96
- - u ,
,u 4
< 3 E J e
b ., s .h . .h:
-- . s lb -y -E
&W h 0= .A r 523 : .
821 eo 8
<g>< %
f g8a $
a u M k e
== -
- 4
- I t
a - - I r -
- 2 -
2 -
- l -
1 I .
F l **$
[D5 2
[S dS I
l
.I _
bd I I EW cs' t t
.. .. .. ., 28 -
I ,, ,, .. ,, I gg I
=
= I ef l
E.m l
53
' .a.> I as I 83< l G.
8 I i L_ __ _. _._ _ _ __. _ _ ___ __. _ _ _ _ __ _i
( -
~ + == * - . . .- -- . . . . . .
9
P EMh.I,y GW/Ib EM,epy, Otufte a F Wolu .ft'/lb 9
- *y- . . , c, 8 w.i., e, . , .,
- 7
., a, a. a. 4, .,
-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 0.08455 0.01602 3305 3305 22 3.00 10733 1076A 0.006) 2.1706 2.1767 35 0.09991 0.01602 2948 2948 2.1432 2.1594 40 35 8.03 1071.0 1079.0 0.0162 0.12163 0.01602 2446 2446 2.1^26 45 40 2037.8 13.04 1068.1 1081.2 0 0262 2.1164 45 0.14744 0.01602 2037.7 0.0361 2.0901 2.1262 50 1704.8 18.05 1065.3 1083.4 to 0.17795 0.01602 1704A 0.0555 2.0391 2.0946 60 1207.6 28.06 1059.7 1087.7 80 0.2561 0.01603 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 0.3629 0.01605 868.3 868 4 2.0359 TO 48.04 1048.4 1096.4 0.0932 1.9426 to 0.5068 0.01607 633.3 633.3 90 to 58.02 1042.7 1100A 0.1115 14970 2.0086 0.01610 468.1 468.1 100 30 0.6981 68 00 1037.1 1105.1 0.1295 12530 1.9825 0.9492 0.01613 350.4 350.4 110 100 77.98 1031.4 1109.3 0.1472 1A105 1.9577 12750 0.01617 265.4 265.4 110 120 1025.6 1113.6 0.1646 1.7693 1.9339 0.01620 203.25 203.26 87.97 120 1A927 97.96 1019 3 11172 0.1817 1.7295 1.9112 130 2.2230 0.01625 157.32 157J3 1.6910 1.8895 140 330 123.00 107.95 1014.0 1122.0 0.1985 140 2.8892 0.01629 122.98 0.2150 1.6536 1.8686 150 97.05 97.07 117.95 1008.2 1126.1 150 3.718 0.01634 0.2313 14174 1A487 140 77J7 77.29 127.96 1002.2 1130.2 240 4.741 0.01640 137.97 996.2 1134.2 0.2473 1.5822 1A295 170' 5.993 0.01645 62.04 62.06 1A111 180 170 148.00 990.2 1138.2 0.2631 1.5480 7.511 0.01651 50.21 50.22 0.2787 ., 1.5148 1.7934 ago 180 40.96 158.04 984.1 1142.1 9.340 0.01657 40.94 1.7764 200 190 33.64 168.09 977.9 1146.0 02940 1.4824 200 11.526 0.01664 33.62 1.4509 1.7600 210 27A2 178.15 971.6 1149.7 0.3091 210 14.123 0.01671 27A0 9703 1150.5 D.3121 1.4447 1.7568 212 0.01672 26.78 26.80 180.17 212 14.696 965.2 1153.4 0.3241 1.4201 1.7442 220 0.01678 23.13 23.15 188.23 220 17.186 958.7 1157.1 0.3388 1.3902 1.7290 230 0.01685 19.364 19.381 19833 240 230 20.779 952.1 1160.6 0.3533 1.3609 1.7142 0.01693 16.304 16.321 208.45 240 24.% 8 1164.0 0.3677 1.3323 1.7000 250 13.802 13.810 218.59 945.4 250 29A25 0.01701 1167.4 0.3819 1.3043 1.6862 260 11.745 11.762 228.76 938.6 260 35.427 0.01709 1170.6 0.3960 1.2769 1.6729 270 10.042 10.060 238.95 931.7 270 41.856 0.01718 1173A 0.4098 1.2501 1.6599 280 8.627 8.644 249.17 924.6 280 49.200 0.01726 1176.8 0.4236 1.2238 1.6473 290 7.443 7.460 259.4 917.4 290 57.550 0.01736 1179.7 0.4372 1.1979 1.6351 300 6.448 6.466 269.7 910.0 300 67.005 0.01745 1182.5 0.4506 1.1716 1.6232 310
(;.01755 5.609 5.626 280.0 902.5 810 77.67 1185.2 0.4640 1.1477 1.6116 320 4.896 4.914 290.4 894.8 320 89.64 0.01766 1190.1 0.4902 1.0990 1.5892 340 3.770 3.788 3113 878.8 340 117.99 0.01787 1194.4 0.5161 1.0517 1.5678 360 2.939 2.957 332.3 862.1 860 153.01 0.01811 1198.0 0.5416 1.0057 1.5473 380 2.317 2335 353.6 844.5 340 195.73 0.01836 1201.0 0.5667 0.9607 1.5274 400 1.8444 1A630 375.1 825.9
- 400 247.26 0.01864 1203.1 0.5915 0.9165 1.5080 420 1.4808 1.4997 396.9 806.2 420 30s.78 0.01694 0.6161 0.8729 1.4890 440 1.2169 419.0 785.4 1204.4 440 381.54 0.01926 1.1976 0.6405 0.8299 1.4704 460 0.9942 441.5 763.2 1204.8 460 466.9 0.0196 0.9746 0.6648 0.7871 1.4516 480 0.8172 464.5 739.6 1204.1 480 566.2 0.0200 0.7972 0.6890 0.7443 1.4333 500 0.6545 0.6749 487.9 714J 1202.2 500 680.9 0.0204 687.0 1199.0 0.7133 0.7013 1.4146 520 0.0209 0.5386 0.5596 512.0 1J954 540 520 812.5 657.5 11943 0.7378 0.6577 0.0215 0.4437 0.4651 5368 1.3757 560 540 962.8 625.3 1187.7 0.7625 0.6132 0.0221 03651 0.3871 562.4 1J550 580 SEO 1133.4 0.3222 589.1 589.9 1179.0 0.7876 0.5673 580 1326.2 0.0228 0.2994 550.6 1167.7 03134 0.5196 1.3330 500 0.0236 02438 0.2675 617.1 13092 620 600 1543.2 5063 1153.2 0.8403 0.46S9 C.1962 0.2208 646.9 1.2821 640 620 1786.9 0.0247 454.6 1133.7 03666 0.4134 0.1543 0.1802 679.1 1.2458 660 640 20599 0.0260 392.1 1107.0 02995 0.3502 0.0277 0.1166 0.1443 714.9 1.2025 680 660 2365.7 310.1 1068.5 0.9365 0.2720 0 0304 0.0808 0.1112 758 5 640 2708.6 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 0.0366 0.0386 0.0752 0 1.0612 705.5 700 30943 0.0508 906.0 0 906.0 1.0612 3203 2 0.0508 0 705.5 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
EQUATTON SHEET Cycle efficiency = (Met work f = ma v = s/t out)/(Energy in) 2 w = a; s = V ,t + 1/2 at 5=x- A = 13 A = A,e XE = 1/2 mv a = (Vf - 1,}/t PE = agn
- = e/t x = sn2/t1/2 = 0.693/t1/2 Vf = V, + at t II**}3 2
y=,p A"
n0 4
1/2*" "(t((I* 1/ZI W
- IIDI)
- .gx aE = 931 .m m = V,yAo ,
o
~
Q = mCoat I = I e "*
d = UAa7 I = I ,10** E Pwe = Wfah TVL = 1.3/u sur(t) HVL = -0.693/u P = P,10 P = Pa e*/' , SG = S/(1 - K,g)
SUR = 25.06/T Gx= S/(1 - K,ffx)
G;(1 - K,ff)) = G25I ~ eff2)
SUR = 2So/1' + (s - o)T M = 1/(1 - K,g) = CRj /G 3 T = (1*/s ) + ((a - o V Io] x = (1 . X ,gg}/(1 . K ,g))
7 = 1/(a - a) SCM = (1 - K ,g)/K ,g 7 = (a - o)/(Ta) t' = 10# seconos o = (X,ff-1)/K,g = *,ff/K,ff I = 0.1 seconds
- I o = [(1*/(T K,g)] + [a,g/(1 + IT)]
Idll"Idgd I d; 2 ,222 2 P = (t4V)/(3 x 1010) 2 R/hr = (0.5 C2)/d ( ,, ,73)
Z = *N R/hr = 6 CE/d2 (feet)
Miscellaneous Conversions Water Partneters I curie = 3.7 x 10 10dos 1 gal. = 8.345 lem. 1 kg = 2.21 10m Igaj.=3.7811 tars 1 np = 2.54 x 10 3 Stu/nr 1 f. = 7.48 gal. 1 m = 3.41 x 100 5tu/hr Density = 62.4 lem/ft3 lin = 2.54 cm Density = 1 gm/cm3 *F = 9/5'C + 32 Heat of vaoorization = 970 Stu/lom 'C = 5/9 (*F-32)
Heat of fusion = 144 Stu/lem - 1 STU = 778 ft-lbf 1 Atm = 14.7 psi = 29.9 in. Hg.
1 ft. H 2O = 0.4335 inf/in.
__,__.,_,----m. ,- _. - - , - , , . - . , - - - - . . _ . . , - - -_- , - _
1___EBINCIE(ES_gE_ NUCLE @B_EQWEB_E(@NI_QEEB@IlgNt PAGE 1E
, ISE8dggIN@d1CS _ME@l_IB@NSEEB_@NQ_E(Ulp_E(QW t
ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 1.01 (1.00) b (1.c; REFERENCE NUS: Vol 3, pp 6.1-3 BRUNSWICK 1 & 2, Student Study Guide, 02-2-A DRESDEN - LESSON PLAN BOOK FOUR, CHAPTER 12, PAGE 14.
ANSWER 1.02 (1.00) c (1.C)
REFERENCE BFNP: XENON & SAMARIUM LP, P.4,12 GGNS: LP OP-NP-514, p. 5-10 BRUNSWICK 1 L 2, Student Study Guide, 02-2-A.
DRESDEN - LESSON PLAN BOOK FOUR, CHAPTER 12, PAGE 45.
ANSWER 1.03 (~ ha) d (1.C)
REFERENCE SSM BOOK 2, CH 2-A, SEC 13.7, PG 161 DRESDEN LESSON PLAN BOOK FOUR CHAPTER 12, PAGE 35 i
l i
1 l
It__EBINQlELES_QE_UQQLE68_EQWEB_E(@NI_QEE8@llgNt PAGE 19 ISEEdQDYN@d1CSt _ME@l,,lE6NSEEE_6NQ_E(Qlp_E6QW ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 1.04 (3.00)
A. 300 psi a = 417.35 F 450 psia = 456.28 F (f rom steam tables) (.5) 456.28 - 4',7.35 = 38.93 F for 30 minutes (.5) 38.93 X 2 = 77.86 F/HR cool down rate (.5) (1.5)
B. -38.93 F( -1X10-4 dk/k/F) = C X 10-4 dk/k (1.0)
(For grading, answer is independant of part A.)
C. Yes(.1) less negative (.4) ( . 5)
REFERENCE GE REACTOR PHYSICS REVIEW, pg 26 & 28 , STEAM TABLES DRESDEN - LESSON PLAN, BOOK 4, CHAPTER 12, PAGE 26.
ANSWER 1.05 (2.00)
- a. Transition boiling may occur which can result in clad failure. (1.C)
- 6. The MCPR is. increased (or more conservative). (1.0)
("Recire. pump runaway" acceptable for " sudden flow increase")
REFERENCE NMP-1 Operations Technology, Mod.X, pg.X-34, Tech. Specs,pg.70-70a.
DRESDEN - Tech Spec 1.1, pg B 1/2.1-7, & 3.5K, pg B 3/4.5-37 ANSWER 1.06 (2.00)
- a. EOL (0.5)
Because B eff is at its minimum value. (0.5)
- b. Whcr addcd rrect...uy exceeou ; c f f,, rompt critical v4y is
" ===*- de or,ft/n su ud;d y b r m k r /3 ,, ,f ' c' REFERENCE der * <deJ *~ AArd nN/"t DRESDEN REACTOR THEORY LESSON PLAN BOOK 4 CHAPT. 12 PAGE 22.
1- P R I N CIE6 E g_ gE_ NgCLE 88_E gWE B_EL 8NI_QEE BBIlgN1 PAGE 20 IHEgdggyN8dlCS _HE81_IB8NSEEB_8Ng_E691g_E69W 1
ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 1.07 (2.50)
A. 1. They are located as far below the normal water line as possible (to provide the greatest static head).
- 2. With f eed flow less than 20% they are kept on minimum speed.
- 4. Low reactor Vessel water level trip, cavitation interlock.
- 5. Suction valve closed trip, cavitation interlock. (3 @ 0.5 ea)
B. N": l i: +he m qi ti c d 5r :: :nd L-me wonai Li m,.; t th: suctic-cf ; wmg tnet not reggLt in c&vit ti on. (1.0)
N/ Il d![*
- t 4;.J & ),'((tr 1e Le /a /WJJ Wf fq&gg f[g REFERENCE N#A".
Dresden Recirc System Lesson Plan pg 16 & 18 ANSWER 1.08 (1.50)
A. The pump will eventually add a sufficient amount of heat to the fluid to cause cavitation (will accept overheating of the pump). (0.5)
B. Could cause excessively large starting currents OR water hammer if the downstream piping was not filled. (0.5)
(0.5)
C. Causes excessive motor amps to be drawn.
REFERENCE
) GE THERMO HT & FF pg 7-123, 124 DRESDEN T.H.T.F.F. LESSON PLAN PAGE 8.
ANSWER 1.09 (2.00)
A. The subcooling of condensate below the saturation temperature. (.5)
Without CD, the condensate pumps would cavitate. (1.0)
B.
(0.5)
C. Cycle efficiency would be decreased.
REFERENCE l
GE THERMO HT L FF, CHAP 6 DRESDEN T.H.T.F.F. LESSON PLAN PAGE 8.
l l
t t
- 1. PRINCIPLES _QE_NyGLEAR_PQWER_ PLANT _QPERATigNt PAGE 21 ISEBdOQYN@dlCS t_dE@l_IB@NSEEB_@ND_E6MID_E69W ANSWERS -- DRESDEN 2L3 -86/06/24-HANEK, J.
ANSWER 1.10 (1.50)
A. U-235, U-238 (.25 each) (.5)
B. Pu-239 (.5)
C. U-235, Pu-239 (.25 each) (.5)
REFERENCE RX PHYSICS REVIEW, pg 32 DRESDEN REACTOR THEORY BOOK 4 CHAPT.12 PAGE 32.
ANSWER 1.11 (2.00)
A. Alpha V increases power B. Alpha T increases power C. Alpha D decreases power
.D. Alpha V decreases power (4 9 0.5 ea)
REFERENCE DRESDEN - GE BWR Transient Analysis ANSWER 1.12 (2.00)
- a. 4.77% (+- .48%)
- b. 3.8% (+- .38%)
- c. 1.0% (+- .10%)
- d. 3.0% (+- .30%) [4 3 0.5 each3 (2.0)
REFERENCE Dresden Reactor Physics Lesson Plan Book 4, Ch. 12, PP. 26-32, Figures 58-62 GGNS: OP-NP-513, OP-NP-514 EIH: L-RO-604; L-RD-605 1
it._EBINCIELES_QE_Nyg(g68_EQWEB_E(@NI_QEEB811gN u PAGE 22 ISEBM QDYN@ mig @ t _BE@I_IB@N @EE B _8NQ _E(Q1p_E(g W ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 1.13 (1.00) 707. void fraction in the core (0.5)
Thsre is a larger % change in water volume for the same increase (3.45% vs 1.1%) [0.53
-OR-Th2 voids produced at 70% VF have a larger ef f ect on core reactivity since thsy are in an area of higher neutron flux [0.53. (0.5)
REFERENCE Dresden Reactor Physics Review Lesson Plan, Book 4, Ch. 12, P. 33 ANSWER 1.14 (1.00)
- a. (1.0)
REFERENCE GE THERMD HTX & FF, pg 9-102 ANSWER 1.15 (2.00) 0.1. increase a.2. increase a.3. remains the same b.1. increase b.2. decrease b.3. increase [6 @ 0.33 ea]
REFERENCE NMP1 Reactor Theory, Module 1, part 12, 13, & 14 DRESDEN - Lesson Plan Book 4, Ch 12, Rx Physics Review, pg 26-35 J
l
'2___P(@NI_DESl@N_lNC(yDIN@_S@EEIY_@ND_EDEBGENCY_SYSIEd@ PAGE 23
. ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 2.01 (1.50)
- c. Rx building equipment drain tank overflow
- b. Non-regenerative heat exchanger drains
- c. Shutdown heat exchanger drains [3 0 0.5 each3 (1.5)
REFERENCE Dresden Student Text #1, Book 4, Table 5 ANSWER 2.02 (3.00)
- a. 1. Moisture separators pfff #(lfff
- 2. Local instrument air receivers
- 3. Prefilters g-
- 4. Main instrument air receiverp l Dr 9[# y) each] . (2.C) g
- b. 1. Service air between the 2A instrument air receiver and prefilters. (0.5)
- 2. Unit 3: on the main header downstream of main instrument air receiver. (0.5)
REFERENCE Dresden Student Text #3, PP. O and 9, Figure 1 ANSWER 2.03 ( .50)
- b. (0.5)
REFERENCE Dresden Student Text #2, Book 3, Page 11 ANSWER 2.04 (2.00)
- a. To provide a flow path around the filter and demineralizer during backwashing, precoating and resin replacement. (1.0) l b. Provide a flow path f or the additional system flow generated when both pumps and heat e:: changers are used. (1.0)
REFERENCE Dresden 2tudent Text #5, Book 3, P. 14 l
l
h__P6@NI_Dggl@$_INC69 DING _g@ggly_9ND_EdgR@gNCy_gygIgdg PAGE 24
- ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 2.05 (1.50)
- a. Crud removal from bottom of reactor
- b. Prevent temperature stagnation in bottom head
- c. Measurement of bottom head water temperature C3 O 0.5 each] ( 1.y5 )
REFERENCE Dresden Student Text #5, Book 3, P. 2
[
ANSWER 2.06 (2.75)
- a. 1. Low reactor pressure at 80 psig (0.5)
- 2. High HPCI area temperature at 200 F (0.5)
- 3. High steam line flow at 300% (0.5)
- b. 1. Isolation valves 2301-4, 5, 35, and 36 close (0.5)
- 2. The aux oil pump is interlocked against an auto start. (0.25)
- 3. Decreasing loss of oil pressure starts closing stop and control valves. (0.25)
- 4. Emergency oil pump starts. (0.25)
REFERENCE Dresden Student Text #10, Book 3, P. 30 ANSWER 2.07 (3.25) a)Y
- a. 1. DW pressure >/= +2 psig ..
- 2. Rx water level </= 59" Mhd.)
- 3. 120 second timer timed out N&H5-) ,J 7
- 4. Any core spray or LPCI pump running with >/= 100 psig
- pressure (A-W5-)b'/h
- b. 1. Off - Auto-blowdown only (0.25)
- 2. Manual - Always energized (0.25)
- 3. Automatic - Auto blowdown signal and relief signal (0.5)
REFERENCE Dresden Student Text #1h Bookj , PP. 3, 5 and 6 ftAtr NA tl 0
~
N0 lA b'Y ho /2./ 4/4 tr lfdelhlhl A$ f, f po og<c on .r/r%pr ay /pu pm r"@@!)
viA' d kJ /e psy Adwp pewre. (.it I *
. hz__EL9NI_pggigN_1Ng(yp1Ng_g6Egly_8ND_gMg8@gNgy_SyEIgMS PAGE 25
- ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 2.08 (2.75)
- c. 1. 1070 psig (0.5)
- 2. 15 second (0.5)
- b. Allow for the decay of the pressure spike which occurs because of the MSIV or main stop valve closure to prevent spurious or frequent initiation of the system during anticipated turbine trips. (1.E)
- c. 1. Clean demineralized water (primary)
- 2. Condensate transfer (backup)
- 3. Service water "OR" fire protection (backup)
[3 0 0.25 each] (0.75)
REFERENCE Drasden Student Te::t #12, Book 3, PP. 7 and 10 l
ANSWER 2.09 (2.00)
- m. The risers are provided to permit lowering the recirculation inlet no: les [0.53 to remove them out of the active core region [0.53. (1.C)
- b. So that they do not receive a significant fast neutron exposure
[0.53 which could change the mechanical properties of the materials [0.53. (1.C)
REFERENCE DrGsden Student Text #1, Book 1, P. 13 ANSWER 2.10 (2.00)
- c. 1. Motor Pump A MCC 28-1 (0.25)
- 2. Motor Pump B MCC 29-1 (0.25)
- c. To prevent chugging [0.253. As the reactor pressure decreased,
[0.253 the flow from a centrifical pump would INCREASE [0.253 resulting in a rapid injection of boron [0.253. (1.0)
REFERENCE Dresden Student Text #3, Book 3, PP. 5 and 11 2
l
2___E69NI_DEg1Gy_INC(yp1Ng_E9 Eely _9Np_EdEB@gNCy_gygIEd@ PAGE 26
, ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 2.11 (1.00)
- a. 0.5 psid (0.25)
- b. Closed (0.25)
- c. Rx building to torus and torus to drywell (0.5)
REFERENCE Drssden Student Text #15, Book 3, PP. 15 and 16
~
ANSWER 2.12 (2.50)
- c. Standby coolant supply system
- b. Steam flow restricters
- c. CRD velocity limiters
- d. CRD housing supports G. Standby liquid control system
- f. Drywell nitrogen inerting C5 3 0.5 each] (2.5)
REFERENCE Drasden Student Text # 5, Book 1, P. 5 a
w-, - ,,, ,-_v-.,.-.,._._m- -
_ . , _ , - . . - - , , - . . , . , , , , . , ,._..-.,,,.-,..,3. . , - . - _ y .- , . - - . - . - . . - - - - - - - - - -
3___INgIBUMENIg_AND_CONIBO(S PAGE 27
' ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 3.01 (2.75)
- c. 10% (0.25)
- b. Primary: to avoid confusing the LPCI loop select logic (0.5)
Secondary: To prevent flow-induced vibration in the jet pumps (0.5)
- c. Prevents the high speed pump from increasing and the low speed pump from decreasing. (0.5)
- d. If the mismatch exceeds 10% and the discharge valve on the low speed pump is closed. (0.5)
- a. A ?n - ; oe time delay. (0.5)
REFERENCE Drssden Student Text #2, Book 2, PP. 12-14 ANSWER 3.02 (2.50)
- a. The detectors are geometrically arranged so the system is capable of detecting any significant increase in radiation level for any number of lines in operation. (0.75)
- b. Gamma sensitive Ion chamber. (0.5)
- c. N 16 gamma (0.5)
- d. Because the hydrogen addition to Unit 2 causes an increase in the N 16 levels. (0.5)
- o. No (0.25)
REFERENCE Dresden Student Text #1, Book 3, PP. 1 and 3 ANSWER 3.03 (2.50)
- 1. Supply breaker trip on a running feed pump.
- 2. A standby RFP is selected. o jJ,j
- 3. Suction pressure above the trip setpoint of 120 Feve.
- 4. At least one ventilation fan is operating.
- 5. Oil pressure is greater than 20 psig
- 6. Rx water level less than 55" [5 required 0 0.5 each] (2.5)
REFERENCE Dresden Student Text #4, Book 2, PP. 23 and 24
b___INSIBydgNIg_gNQ_QQNIBg6g PAGE 20
- ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 3.04 (3.00)
- c. 1. O to +60 in (0.25)
- 2. Temperature compensated by a pressure signal (electrical compensation) (0.25)
- 3. Level input to feedwater control (0.25)
- b. 1. -60 to +60 in. (0.25)
- 2. Heat clamp between the reference and variable leg (0.25)
- 3. Recirc pump trips and ARI valve opening (0.25)
- c. 1. -70 to +330 in. (0.25)
- 2. None (0.25)
- 3. None (0.25)
- d. 1. -340 to +60 in. (0.25)
- 2. None (0.25)
- 3. LPCI/ containment spray interlock (0.25)
REFERENCE Dresden Student Text #4, Book 1, PP. 3, 4, and 5 ANSWER 3.05 (1.75)
LPSP Actuate Total steam flow >/= 20% AND feed flow >/= 10% for at least 60 seconds (0.75)
Deactuate steam flow </= 20% OR feed flow </+ 10% (0.5)
LPAP Actuate Total steam flow >/= 35% (0.25)
Deactuate total steam flow </= 35% (0.25)
REFERENCE Dresden Lesson Plan #8, Book 1, P.7
h___INSIBydENIS_9NE_gDNIB06S PAGE 29 9 ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 3.06 (2.75)
- c. One channel upscale and one channel downstale, or both channels upscale. (1.0)
- b. 1. Off-Gas chimney Isolation valve closes. (0.5)
- 2. Off-Gas drain valve closes. (0.5)
- 3. Off-Gas pressurized drain tank is isolated f rom the pressurized drain pump. (0.5)
- c. 15 minutes (0.25)
REFERENCE Dresden Student Text #1, Book 3, Page 8 ANSWER 3.07 ( .50) 2000 RPM (0.5)
REFERENCE Dresden Student Te::t #10, Book 3, P. 35 ANSWER 3.08 (1.00)
- o. Increase (0.5)
- b. None (0.5)
REFERENCE Dresden Student Text #4, Book 1, PP. 15 and 16 ANSWER 3.09 (2.00)
The RFP runout relay energi=es a soleniod valve which blocks the supply from the positioner output and places full 100 psig instrument air on top of the valve diaphragm. (2.0)
REFERENCE Dresden Student Text #6, Book 2, P. 6
_ -. ___ _y r _ _ -_ y. _ _ . - . _ , , . . . _ ,
I It__INgIBQdgNIg_AND_QQNIBQLg PAGE 30 ANSWERS -- DRESDEN 28<3 -86/06/24-HANEK, J.
ANSWER 3.10 (2.00)
- c. Senses low air pressure and deenergizes the solenoid cperated pilot valve.
- b. Isolates and bleeds off the air supply to the air dump valve.
- c. Air dump valves exhaust air from the air lock valves.
- d. Air lock valves reposition to interrupt any air signal from the positioner and lock the air in the valve operator.
[4 9 0.5 each] (2.C)
REFERENCE Dresden Student Text # 6, Book 2, P. 2 ANSWER 3.11 (2.00)
- c. Auto start of standby EHC pump.
- b. Turbine trip on low FAS oil pressure (indirect reactor scram) .
- c. Direct reactor scram.
- d. Lock in master trip relay and all valves closed signal to EHC preusure control logic, t0.4 each + 0.1 each for correct order] (2.C.
REFERENCE Drcsden Student Text MB, Book 2, P. 18 ANSWER 3.12 (2.00)
- a. A loss of stator cooling will cause a turbine runback to 25%
of rated load in 3 minutes. (1.C;
- b. Reset the generator lockout relay. (1.C)
REFERENCE Dresden Lesson Plan #11, Book 2, PP. B-10 ANSWER 3.13 (2.00)
- 1. A loss of control power preventing breaker operation. (1.C)
- 2. Loss of trip circuit continuity which would prevent the breaker from being tripped from the centrol room. (1.C)
L
N
$,.__INgIBWg!$1@_QNp_QQNIB96E PAGE 31 rANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
r d
REFERENCE Drssden Lesson Plcn #12, Book 2, PP. 11-12 J
4 u
4 t
b i
s 4
a f
4 i
l
r o
A. PROgggURgg_ _NgRM962_AgNgRM8(i_gMgBggNCY_ANg PAGE 32 o
Be9196991Ce6_CgNIBg6 1
ANSWERS -- DRESDEN 263 -86/06/24-HANEK, J.
ANSWER 4.01 ( .50)
- 1. One minute
- 2. Seal E2 O O.25 each3 (0.5)
REFERENCE Drcsden, DOP 202-1, P. 2 ANSWER 4.02 (2.50)
- a. Reactor scram
- b. Group 1 isolation
- c. Chimney isolation valve closure
- d. Air ejector suction valve closure
- s. Mechanical vacuum pump trip C5 9 0.5 each] (2.5)
REFERENCE Dresden DGA 16, P. 1 ANSWER 4.03 (2.00)
- a. 1. Hour
- 2. Vessel metal
- 3. Water level or water temperature
- 4. Water temperature or water level E4 9 0.25 each] (1.C)
- b. 1. Increase SDC flow
- 2. Start another SDC pump
- 3. Start CRD pumps:
- 4. Flood the main steam lines while draining through the main steam line drains E4 0 0.25 each] (1.C)
REFERENCE Dresden DOP 1000-3, P. 3 i
l
$t__E8QQEQg8E@_;_NQBd8(t_d@NO8d8(s_EME8@ENQY_ANQ PAGE 33 6091969G1G86_GQNIBQL
-o f ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 4.04 (2.00)
- c. Unit 3 60%
Unit 2 43% [2 0 0.5 each3 (1.0)
- b. Inadequate jet pump riser in Unit 2 which causes large jet pump vibrations during single loop operation. (1.0)
REFERENCE Drasden DOA 202-1, PP. 1 and 4 ANSWER 4.05 (1.50)
Th2 notch override switch shall [0.53, not be used between positions 00 and 24 [0.53 until the first bypass valve is open [0.253, or the unit i s on the line [0.253. (1.5)
REFERENCE Dresden DGP 1-4, P. 32 ANSWER 4.06 (1.00)
" At-the-control s" means the unit operator is in line of sight of the unit front panels. (1.0)
REFERENCE Drcsden DAP 7-2, P. 4 ANSWER 4.07 (1.00)
- o. Rx power > 20% (0.5)
- b. 65-100% of rated core flow (0.5)
REFERENCE Drosden 2 Tech. Spec. 3.3.G I,
O
T-ht__EBQGEDWBgS_:_NQBd@Lt_9ENQBd@Lg_Ed[BGENQY_9NQ PAGE 34 R_A_D__IO_LO_G__IC_A_L__C_O_N_T_R_O_L_
7 ANSWERS -- DRESDEN 2L3 -86/06/24-HANEK, J.
ANSWER 4.08 ( .50)
Only after the pump suction and discharge valves are open.
REFERENCE Dresden, DOP 202-1, P. 3 ANSWER 4.09 (1.00)
- a. By attempting to withdraw the rod past position 48. (0.5)
- b. Rod overtravel alarm. (0.5)
REFERENCE Dresden, DOP 400-1, P4 DOP 400-2 ANSWER 4.10 ( .75)
- 1. 100 cps
- 2. 1 x 10 E+5 cps
- 3. -&- j(4oj, y [3 0 0.25 ea3 (.75)
REFERENCE Dresden, DOP 700-1, P. 3 ANSWER 4.11 (2.50) l 1. Amber light of squib firing centinuity circuit not lit.
- 2. Flow indicating pilot light net lit.
- 3. R:: water cleanup system isolation.
- 4. Decreasing level of Standby Liquid Storage Tank.
- 5. Standby liquid squib valve circuit f ail annunciator light lit.
[5 9 0.5 each] (2.5)
REFERENCE Dresden, DOP 1100-2, P. 3
I a
it _889GEDW8EE_:_N98586t_8BN98deLu_EME8EENGY_eNQ PAGE 35 0 8021969W1GBL_G9NIBQL ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 4.12 (1.25)
- c. 1. 95 F
- 2. 105 F
- 3. 5 minutes [3 9 0.25 each] (0.75)
- b. 110 F (0.25)
- c. Scram the reactor (0.25)
REFERENCE Dresden, Tech. Specs. 3.7.A.1 ANSWER 4.13 (2.00)
- e. By removing the amphenol type plug connectors from the drive insert and withdrawal solenoids. (1.C)
- b. This is pref erred as it continues cooling water flow and minimites crud accumulation in the drive. (1.C' REFERENCE Dresden, Tech. Spec., Bases 3.3.A.2, P. B/34.3-15 ANSWER 4.14 (1.00)
- a. greater than 5 millirem / hour (0.5)
- b. Greater than 100 millirem / hour (0.5)
REFERENCE Dresden, Radiation Protection Standards, P. 3 r
l l
ANSWER 4.15 (1.50) l l a. 3.0 rem /qtr l b. 7.5 rem /qtr
- c. 18.75 rem /qtr [3 0 0.5 each] (1.5) l l REFERENCE Dresden, Radiation Protection Standards, P. 24
34__P6pqEQQBE@_;_NQBd@61_9@NQBd@Li_gdgB@ENQy_ANQ PAGE 36 RADIOLOGICAL CONTROL 4
ANSWERS -- DRESDEN 2&3 -86/06/24-HANEK, J.
ANSWER 4.16 (1.00)
- c. TRUE (0.5)
- b. FALSE (0.5)
REFERENCE Drasden, DFP 900-1, P. 4 ANSWER 4.17 (2.50)
- 1. Slow
- 2. Fast (clockwise)
- 3. Incoming
- 4. Higher
- 5. Running [5 9 0.5 each3 (2.5)
REFERENCE Dresden, DGP 1-1, PP. ~25 and 26 ANSWER 4.18 (1.50)
- a. Voltage adjust
- b. EXC field VAR AC control C/ ' /[/ 9/(jf/7 0 [2 9 0.75 each] (1.5)
REFERENCE Drasden, DGP 1-1, P. 26
, _ _ _ . _ _ , . _ _ _ _ . _ _ . _ . _ _ . _ . . - . . _ _ _ . _ . . _ _ . . _ . . _ _ _ _ . _ _ _ _ _ _ __ . _ _ ._ _. _