ML20133M218
| ML20133M218 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/02/1985 |
| From: | Dante Johnson, Keller R, Kister H, Ruscitto D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20133M216 | List: |
| References | |
| 50-423-OL-85-15, NUDOCS 8508130047 | |
| Download: ML20133M218 (100) | |
Text
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'Q U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N0. 85-15 (OL)
FACILITY DOCKET NO. 50-423 CONSTRUCTION PERMIT NO. CPPR-113 LICENSEE: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141 FACILITY: Millstone 3 EXAMINATION DATES: May 14-17, 1985 and May 21-23, 1985 CHIEF EXAMINER: , 6 D. Ruscitto, Examiner Date REVIEWED BY:
D. Johns 6n, Lead aminer 7/Ie/f[
Da'te REVIEWED BY: , f R. Keller, Chief, Project Section 1C 7 Date f(
APPROVED BY:
h CW b
/
H. Kiste/,\ Chief, Project Branch No. 1 8 Qate
SUMMARY
- Oral, written and simulator examinations were given to sixteen Senior Reactor Operator (SRO) and five Reactor Operator (RO) candidates. 2 R0 and 9 SRO candidates passed all portions of the examination and will be issued licenses. 3 R0 and 7 SRO candidates failed one or more portions of the exam-ination and their license applications were denied. Four candidates were identified as performing significantly above average on the oral / simulator portions of the examination.
G D f
REPORT DETAILS TYPE OF EXAMS: Initial EXAM RESULTS:
1 RO l SRO l l Pass / Fail l Pass / Fail l l l l l l l l l Written Exam I 3/2 l 16/0 l l l- 1 I I. I I I l Oral Exam l 4/1 l 15/1 l l l l l l l l l l Simulator Examl 3/2 I 9/7 l l l' I l l I I I 10verall I .2/3 1 9/7 l l l l l
- 1. CHIEF EXAMINER AT SITE: D. Ruscitto
'P. Isaksen, EG&G, Idaho R. Sailor, EG&G, Idaho
- 3.
SUMMARY
OF GENERIC DEFICIENCIES FROM ORAL AND SIMULATOR EXAMS Major deficiencies were noted in the following areas:
Ability to diagnose casualties Utilization of the radiation monitoring system Effective Utilization of Emergency Procedures Shift Crew Teamwork and Communications Minor deficiencies were noted in the use of portable radiation monitoring instruments t
i
r s
3
- 4.
SUMMARY
OF GENERIC DEFICIENCIES NOTED FROM WRITTEN EXAMS I R0 Exam (5 Candidates)
The following were areas of minor weakness:
RHR. Suction Valve Interlocks RCP Cooling Flow Paths Effect of EGLS LOP and SI Resets Power Range Instrument SR0 Exam (16 Candidates)
The following were areas of minor weakness:
Fuel. Temperature Coefficients Effects of an Impulse Pressure Channel Failure Station Bypass and Jumper Control Procedure
- 5. INTERFACE WITH PLANT STAFF DURING EXAM PERIOD Liaison with plant staff was good and the simulator instructors were helpful in scenario review and modifications during the course of several scenarios, which facilitated the examination process.
- 6. PERSONNEL PRESENT AT EXIT INTERVIEW NRC Personnel D. Johnson, Lead Reactor Engineer (Examiner)
D. Ruscitto, Reactor Engineer (Examiner)
T. Rebelowski, Senior Resident Inspector Facility Personnel R. Test, Director, Nuclear Training J. Black, Simulator Project Manager J. Crockett, Unit Superintendent W. Landon, Simulator Program Supervisor T. Harvey, Senior Instructor L. Allen, Simulator Instructor M. Hall, Operator Instructor
- 7.
SUMMARY
OF NRC COMMENTS AT EXIT INTERVIEW Gene-ic deficiencies during oral / simulator exams and interface with plant staff were summarized. Preliminary results of thirteen candidates clearly passing and eight candidates being marginal were presented. Four candi-dates were identified as being clearly above average on their performance on the oral and simulator portions of the examination.
4
- 8. EXAMINATION REVIEW L At the conclusion of ' the written examinations, the examiners met with the !
following licensee personnel to review the exam and answer keys to l identify any inappropriate questions relative-to plant specific design and to ensure that the questions will elicit the answers in the key and that they reflect the most current plant conditions.
T.~Harvey W. Mihalovits J. Crockett T. Mcdonald T. Hall W. Potter M. Levitan Attachments:
- 1. Written Examinations and Answer Keys (SR0/RO)
- 2. Comments on Written Examinations and Resolution I
5
ATTACHMENT 2 R0 Exam Comments and Resolution Question / Answer Comment 2.04a Key changed to read " Allows manual control of loads once SI is reset" since reset of SI cannot be assumed the way question is asked.
2.05a Reworded answer to include the concept of maintaining
-boron concentration low enough to prevent crystalliza-tion at room temperature.
2.07d Added additional correct answer per MCB.
2.08 Deleted "4 flow indicators with orifices" since these are local indications only and not used for normal control room operations.
-3.01 Two answers a're acceptable based on which reference is used. _ Training material is not consistent. Topic 8, Lesson 4, pages 45-46 states that the plant will trip. . Simulator transients indicate that it will not trip. Either will be accepted with an explanation.
3.05 The interlocks on RCS cold leg loop isolation valves have been removed from the system, however, the train-ing material has not been updated. This question was replaced with the question attached to the Master Exam.
4.01. Since these Tech Spec valves are not finalized, Part A is deleted 'and Part B graded according to answer given for Part A.
4.02 Expanded acceptable bands for assumed values to be more realistic in the calculation.
4.04 Comment that verbatim repeat of CAUTIONS from E0P should not be required is not accepted. Candidates are expected to know these and their bases per NUREG-1021. Added " Cooling head and starting RCPs" as an acceptable partial answer.
4.07 Comment that this is a memorized step is not accepted.
This knowledge is well within the level required of an R0.
Attachment 2 2 Question / Answer Comment 4.09b Comment that this is a memorization of a caution step is correct. This is within the scope of R0 knowledge.
4.09c Deleted due to possible confused wording.
SRO Exam Comments and Resolution Question / Answer Comment 5.01 Comment that one answer only is correct is not accepted. Question refers to fuel temperature. The effects of clad creep and fission gas buildup affect
~
fuel temperature.
5.04c' Comment that there are other answers is not accepted since the axial flux redistribution phenomenon is temperature related, not design, rod height or power dependent.
6.01c Comment that train dependance is not important is not accepted. This is an area where specific operator knowledge is required.
6.02 See comment for Question 3.05.
6.03a See comment for Question 6.01c.
6.04a Added additional correct answer based on reference supplied by DWG No. 12179-LSK-24-9.3J and 12179-LSK-24-9.20.
6.09c Correct answer is "To maintain proper pH in contain-ment sump" per T.S. Bases 3/4.6.2.3. Training mate-rial provided is not consistent with T.S. and should be modified. Either answer accepted.
7.01d Comments concerning memorization. is not accepted.
7.02d These are areas of knowledge with significant
.7.03c, e importance for an SRO.
7.04a Answer 7.04b Added . additional answers of " Core AT, S/G pressure /
temperature" as is good engineering practice.
i,
g'. .t
.Attachme'nt 2 3
- Ques 61on/ Answer- Comment 7.04d Added additional correct answer of RWLMS < 100%" per F-0.6.
7.04e- Au'xiliary spray flow must not be discussed for full' credit as it is implied by charging flow adjustment.
7.07b Deleted as too specific to HP work.
- 1 kASTlC:'Y U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _M1113IDHE 3 REACTOR TYPE: _EWR-WEC1 DATE ADMINISTERED:_ RELA 1L11 EXAM 1NER: _ HEMMING _W.
APPLICANT:
IN1IRUCI1ON1_IQ_AEELICANIl Uso separate paper for the answers. Write answers on one side only.
Stople 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 vaLUE_ _IQIAL SCOBE _YALME__ CAIEQQHY _
75.11
_21.2H__ _21.A2 -
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
- L C
_11.RR__ _11.aa 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 25.11
_11.aa__ _11.aa 3. INSTRUMENTS AND CONTROLS L A . T* : ) LL
_Eiraa__ _11.aa 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL laa.aa__ laa.Ra TOTALS FINAL GRADE %
All work done on this examination is my own. I have neither given nor received aid.
APPLICANT'S SIGNATURE
a
..-'~.
' ' .L.__ER1HC1ELEE_QE_NEQLEAR_EQWER_ELAHI_QEERAI1QE. PAGE 2 THERMQQ1 NAM 1QS EEAI_IRANEEER_ANQ_ ELE 1Q_ELQW QUESTION 1.01 (2.00)
After calculating an Estimated Critical Position for startup it is nocessary to dilute 200 ppm boron. Initially source range counts are 40 cps and 45 cps. After diluting 100 ppm boron, source range counts indicate 8S cps and 70 cps. Should you continue the dilution?
EXPLAIN. (2.0)
QUESTION 1.02 (3.00)
- a. Is the reactivity value of 100%.equp$librium Xenon double the reactivity value of 50% equ) librium Xenon. EXPLAIN. (1.S)
- b. Which of the below takes the reactor longer to achieve?
i
- 1. 2S% equplibrium xenon.
. OR
- 2. 50% equ/ librium Xenon.
EXPLAIN YOUR ANSWER. (1.5)
QUESTION 1.03 (3.00)
Hoc does control rod worth vary with each of the following?
EXPLAIN your answer.
- a. With its radial position in the core. (1.0)
- b. The RC system boron concentration is increased. (1.0)
- c. The moderator temperature increases. (1.0)
(***** CATECORY 01 CONTINUED ON NEXT PACE *****)
L
- 1.__ER1NQ1 ELE 1_QE_MEQLEAE_EQWER_ELAMI_QEERAI1QNm
,, PAOE 3 THERMQQ1 NAM 1QS _HEAI_IRAMEEER_ANQ_ ELE 1Q_ELQW QUESTION 1.04 (3.00)
During a startup the reactor is suberitical at 3000 CPS on the Source Range Instruments when a steam dump valve fails open.
- a. EXPLAIN what happens to reactor power and Tave. Continue your explanation until stable conditions are reached with no operator action. (Assume the reactor is undermoderated, at BOL and no reactor trip occurs.) (1.5)
- b. Assume the same transient as above occurs at EOL. EXPLAIN any differences in the power /Tave response and final stable conditions as a result of the increased burnup. (1.S)
QUESTION 1.0S (1.00)
The TOTAL POWER COEFFICIENT (pcm/% power) at BOL is LESS NEGATIVE THAN the total power coefficient at EOL. Briefly EXPLAIN why. (1.0)
QUESTION 1.06 (1.S0)
- e. Explain why fission product gas build-up in the gap between the fuel and clad causes Doppler (power only) Coefficient to become more negative over the life of the core. (1.0)
- b. Does the effect of " clad creep" cause the Doppler (power only)
Coefficient to become MORE or LESS negative, over the life of the core? (0.S)
QUESTION 1.07 (3.00)
- a. Of the coefficients that contribute to the power defect, which coefficient contributes most to the change of power defect over core life? EXPLAIN. (1.0)
- b. Explain why power defect is desireable for reactor operation at power. (1.0)
- c. Which of the reactivity coefficients that contribute to power defect act first to affect reactivity on a sudden power change due to rod movement? EXPLAIN WHY. (1.0)
(***** CATECORY 01 CONTINUED ON NEXT PAGE *****)
,.1. _'ERINQ1ELES_QE_NEQLEAE_EQWER_ELANI_QEERAI1QN. PAGE 4
. THERMQQY. NAM 1Q1 _HEAI_IRANEEER_AND_ ELE 1D_ELQW QUESTION 1.08 (2.S0)
- c. How and why does an INCREASE in CONDENSATE DEPRESSION effect plant efficiency? (1.5)
- b. How does an INCREASE in CONDENSATE DEPRESSION effect the NPSH for the condensate pumps? (1.0)
QUESTION 1.09 (2.50)
- a. During natural circulation, explain how it is possible to form a bubble in the reactor vessel head when indications show that the RCS is subcooled? ,
(1.5)
- b. How will pressurizer _ level respond, (INCREASE, DECREASE, or REMAIN THE SAME) if the backup neaters are energized with a bubble in the reactor vessel head? Assume normal pressurizer level and briefly EXPLAIN your answer. (1.0)
QUESTION 1.10 (2.50)
Indicate how'the following will affect Unit efficiency (increase, decrease, no change) at a steadf state power level: CConsider each case separately.)
- a. Absolute condenser pressure changes from i psi to 1.25 psi.
l
- b. Total S/G blowdown is changed from 35 gpm to 40 gpm.
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- c. Condenser hotwell temperature changes from 12S F to 130F.
- d. Steam quality. changes from 99.8% to 99.7%.
- e. Current being drawn by RCP's increases slightly along with a slight change in bus voltage. (2.5) l l
l i
l l
t
(***** CATECORY 01 CONTINUED ON NEXT PAGE *****)
- 1.__ER1HC1ELEE_QE_NECLEAE_EQWER_ELAMI_QEER&I1QN. PAGE S 5 IHERMQQINAMICE HEAI_IEANSEER_ANQ_ ELE 1D_ELQW QUESTION 1.11 (1.00)
Determine if the statement below is correct or incorrect.
Dofend your answer.
l
- , As the temperature difference between the fuel rod surface and the saturation temperature of the coolant (Twall-Tsat) increases, the heat flux across the fuel surface (BTU /hr sq. ft.) increases at a constant linear rate. (1.0) t l
l l
l l
l l
l r .
(***** END OF CATEGORY 01 *****)
PAGE 6
';A.__ELAHI_DEElGH_1HChun1HQ_E&EEII_ANQ_EMEEGENC1_E1EIEME QUESTION 2.01 (2.50)
- a. Is the flowrate through the RCP #1 seal constant for all i, plant conditions? EXPLAIN. 3 .
C.75) i b. What determines the differential pressure across #2 RCP seal?
i
- c. What is/are the flowpath(s) for the #1 RCP seal leakoff during a (.75) i phase A isolation?
QUESTION 2.02 (2.00)
( . 7 5)
- a. What are the functions of the Auxiliary Feedwater System.
- b. What is the performance criteria of the Auxiliary Feedwater System during a Station Blackout in order to prevent the (1.25)
RCS pressurizer from going solid.
QUESTION 2.03 (2.00)
List THREE support systems used to ensure that the emergency diesel generator will rapid start and load in the design time limit. DESCRIBE how each system accomplishes this task. (2.0)
(DO NOT include administrative or maintenance requirements.)
QUESTION 2.04 (3.00)
- a. A Safety injection (SI) with a Loss of Power (LOP) has occurred and the Emergency Generator Load Sequencers (EGLS) have cycled completely. All proper safeguard loads are running. Describe the effect depressing the ECLS LOP RESET has on the EGLS and the (1.5) operation of the safeguard' equipment.
- b. When will the EGLS respond to an initiating signal after the C.75)
EGLS LOP RESET is depressed? Be specific.
- c. What action (s) must an operator perform to restore the EGLS to (.7S) an armed condition, ready to auto initiate?
- )
(***** CATEGORY 02 CONTINUED ON NEXT PAGE
- .____s- - - _
' ..L _ELAMI_DE11GN_lHCLEQ1NG_EAEEILANQ_EMERGENCLEIEIEME PAGE 7 QUESTION 2.0S (2.00)
- a. What will cause the letdown orifice isolation valves (AV 8149 A.B.C) to close with no operator action? (control switch for all the valves ,
in the auto /open position). (1.0) l l
- b. What is the function and purpose of valve PCV 131 Cletdown pressure control valve) for each of the below. Be specific.
- 1. normal operations.
- 2. solid plant operations. (1.0)
QUESTION 2.06 (2.00)
- a. List THREE reasons for maintaining a minimum Pressurizer spray line flow during normal "at power" operations (1.0)
- b. What alarm (s) give indication to the operator that minimum spray flow is not being maintained? CO.S)
- c. Which RCS loops provide spray flow to the Pressurizer? (0.S) i QUESTION 2.07 (3.00)
- a. Describe the difference in flowpaths used for ALTERNATE DILUTE and DILUTE modes of operation in the Reactor Makeup System. C.75)
- b. Explain the purpose of designing two different dilution paths into the Reactor Makeup System. (.75)
- c. What is the major concern when dealing with fluid containing boric acid? What is done to alleviate this concern? (0.S)
- d. List ALL combinations that will cause the selected boric acid transfer pump to start. Include switch positions and input signals. (1.0)
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
s.
'A.__ELANI_DEElGN_1NGLEQ1NG_EAEETI_AND_EWERGENGl_11EIEME PAGE 8 QUESTION 2.08 (2.50) .
COMPLETE and LABEL the attached diagram of a basic RCP.
INDICATE all cooling flowpaths, major valves in the flowpaths, sources of cooling water, and all instrumentation associated cith the cooling flowpaths. (2.5)
QUESTION 2.09 (3.00)
- c. What THREE purposes does the bypass designed into the number 2 high pressure turbine stop valve perform? (1.0)
- b. State TWO reasons for using Moisture Seperator Reheaters after the High Pressure Turbine? (1.0) 1 . What is the purpose of the two atmospheric relief diaphrams on the top of the low pressure turbine. ( 1.,0 )
QUESTION 2.10 (3.00)
ESF systems are designed in accordance with the single failure
< criteria. This means that a fluid or electrical system is considered to be designed against a single failure if the failure is of any ACTIVE ccmponent Cassuming all passive components work properly) or a single failure of any PASSIVE component Cassuming all active components work properly).
Define ACTIVE and PASSIVE failure as it applies to the statement cbove. (3.0) s
(***** END OF CATEGORY 02 *****)
- ,1. IERIEUMERI1_ANQ_CQEIRQL1 PAGE 9 QUESTION 3.01 (2.50)
Dg The plant is at 100% power with the rod control system in automatic. Explain the response of the rod control system if the turbine impulse chamber pressure signal feeding rod control fails low. Carry your explantion to the point of no I
rod motion and assume no operator 1: _- ;- -
"__',- _ __) l- (2.5)
<- Mnon .
QUESTION 3.02 (2.00)
- o. List the source and signal inputs that program and actuate the Cold Overpressure Protection System (COPS). Be specific for EACH TRAIN. (1.0)
- b. What actions occur when Train A and Train B ARM / BLOCK switches are placed in the ARM position? (1.0)
QUESTION 3.03 (3.00) .
- a. List the signal (s) that are used by the Master Pressurizer Level Controller. (.75)
- b. What band is pressurizer level programmed to follow? (.7S)
- c. Define pressurizer level error. What is pressurizer level error used for? (1.5)
QUESTION 3.04 (2.00)
- c. Explain the purpose of the steam pressure input used in the developement of a steam flow signal for the S/G water level control system. (1.0)
- b. Explain how INDICATED steam flow would compare to ACTUAL steam flow if, during a power increase from 0-100%, the steam pressure signal stuck at it's 50% value. (1.0)
I I
(***** CATECORY 03 CONTINUED ON NEXT PAGE *****)
i3-,
IMEIEUMEHI1_ANQ_CQHIEQL1 PAGE 10 QUESTION 3.05 (2.00)
S tot e-t h e-5-i-n t e-r-1-oc k s-t-h a-t-mu s t b e--s a t-i-e f4ed-t o-o pen a n RC S-c o l d --l e g-l oo p i-s olaA4c a--valv e r (2.0)
(m l%)
QUESTION 3.06 (2.00)
- a. Define " Degree of Coincidence" as it applies to the solid state protection system CSSPS). (0.5)
- b. Explain why some protection curcuits are built with 3 detectors, 3 channels and a 2/3 coincidence while others use 4 detectors, 4 channels and a 2/4 coincidence. (1,S)
QUESTION 3.07 (3.00)
The plant is at 100% power and stable. A maintenance person incdvertantly trips the turbine but the reactor does not trip.
After 30 seconds the BOP operator de-energizes the Rod Drive M.G. sets. Describe the response of the steam dump system to this situation assuming no further operator action. Continue your discussion to the point where RCS temperature is stable the steam dumps close. Be specific. (3.0)
QUESTION 3.08 (3.00)
List ALL reactor trips that-are affected either manually or automatically by a PERMISSIVE. Include the name of the trip and the associated permissive (s). (3.0)
QUESTION 3.09 (3.S0)
- a. List all of the uses for INDIVIDUAL detector-signals from the power range instrument. (Signals tapped off prior to the summing amplifier.) (1.5)
- b. Explain the operation of the detector current comparator and the channel current comparator. Also state what each checks for, when they are.in service, and when they alarm. (2.0)
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
' ,3 -- 1 ERIE!JMERI1_AND._CQEIEQL1 PAGE 11 QUESTION 3.10 (2.00)
Rofer to the attached drawing. EN-2. On a your answer page, fill in the name of each region next to it's respective number.
Explain why there are two seperate lines labeled 1 and 2 on the grcph. (2.0) k%
(***** END OF CATEGORY 03 *****)
'4- ERQCEQUEEE - NQEMAL _AREQEMAL _EMERGENC1_ANQ PAGE 12
', RAQ1QLQQ1 CAL _CQEIRQL QUESTION 4.01 (2.00)
Monitoring the board citer assuming the watch as reactor operator, you see that all of the safety injection accumulators are out of the required Tech. Spec. band and indicate as follows:
pressure: 585 psig level: 60% (810 cu ft or 6060 gals)
- c. For each'perameter abcVe, STATE if the value is ABOVE, BELOW, or EQUAL TO the required Tech Spec value. (1.0)
- b. If the accumulators were left as found and a LOCA were to occur, would reactor safety be affected? EXPLAIN. (1.0)
QUESTION 4.02 (3.00)
The reactor is at 8% power with the turbine on the grid at 50 MW.
Tho unit is in Cycle One with boron concentration at 900 ppm. Rods are in manual with bank D at 160 steps. CALCULATE the dilution and dilution rate that will be required to escalate power to 80% at 1%/ min and have bank D rods at their rod stop limit. STATE all a s s ump t i o ris , show ALL work and show ALL values used with their proper units. (3.0)
QUESTION 4.03 (4.00)
According to the Reactor'Startup Procedure, OP 3202:
- c. What action (s) are required to be taken by the reactor operator if core boron concentration is changed by more than S0 ppm?
EXPLAIN. (1.S)
- b. How often must bank demand position be compared to digital position indication while starting up the reactor? WHY? (1.0)
- c. If criticality is not achieved by the time rods reach their maximum calculated position, what action is required? (1.5)
(Do not include any notifications)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
~ L _EEQQEQUEEE - HQRMAL&_&REQRMAL _EMERGEHQY._&EQ PAGE 13
'. Ran1QLQG1OAL_CQEIRQL ,
QUESTION 4.04 (2.00)
When using the procedure for cooldown, Cooldown Outside Control Room, EOP 3504, a caution warns the operator of the possibility of voiding in the RCS. List TWO ways that voiding can be overcome should it occur. Include All means that may be used to accomplish each. (2.0)
QUESTION 4.05 (3.00)
- a. State FIVE conditions that require immediate boration. (1.0)
- b. How long is immediate boration to be continued once started? (0.S)
- c. If the immediate boration flow is EXACTLY the minimum required by AOP 3S66, immediate Boration, how long must immediate boration flow be continued to insert 100 ppm into the RCS? Assume charging flow to be equal to or greater than boration flow. STATE all assumptions made and SHOW all work. (1.5)
QUESTION 4.06 (2.50) .
After working in an area for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, a worker discovers his pocket dosimeter is off scale and leaves the area. A subsequent survey reveals a hot area of 1200 mr/hr at 2 ft. from the " hot spot". The worker's activities were primarily at S ft. from the " hot spot".
- o. Determine the exposure the worker received. (1.25)
- b. If the worker's previous exposure was 900 mr. What LEGAL (10CFR20) exposure limits, if any, were exceeded?
State ALL assumptions. (1.25)
QUESTION 4.07 (3.50)
During the use of EOP 3S E-1, " Loss of Reactor or Secondary Coolant",
a steam generator found to be faulted is to be verified isolated by doing what 7 actions? (3.S)
(***** CATECORY 04 CONTINUED ON NEXT PAGE *****)
'.'L._EEQCEQUEEE - HQEMAL AREQRMAL _EMERGENCI_ANQ PAGE 14 R&Q1QLQG1 CAL _CQETEQL QUESTION 4.08 (3.50)
According to ES-1.1, St Termination, what are the five indications that are used to determine natural circulation flow. Include, where applicable, the desired status (stable, increasing, decreasing, soturation). Actual setpoints or values are not necessary. (3.5)
QUESTION 4.09 (1.50)
According to EOP-35 ECA-0.0, " Loss of All AC Power":
G. When can the Functional Response Procedures be implemented?
- b. What action is required if St is active or actuates while in EOP 3S, ECA-0.0? _
f a faulted steam generator is discovered, why must the steam generator pressure be reduced t less than 160 psig? (1.5)
F I
I 1
1
(***** END OF CATEGORY 04 *****) l
(************* END OF EXAMINATION ***************) I l
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I W BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Coolant Boron Concentration (PPM) 800 900 1000 400 800 800 700 0 100 200 300 I I I I I I I I I I I I I I I I I I I I I I 13.7 15.4 17.1 8.9 8.8 10.3 12.0 1.71 3.4 5.1 0.0 4 Percent Boric Acid Flow (GPM)
Coolant Boron Concentration (PPM) 1700 1800 1900 2000 1300 1400 1500 1800 1100 1200 i 1000 I I I I I 1 I 1 I I I I I-I I I I I I I I 29.1 30.9 32.8 34.3 22.3 24.0 25.7 27.4 17.1 18.9 20.6 4 Percent Boric Acid Flow (GPM) 4 PG-17
- o nW BORON ADDITION l
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I W l io im .o. imo .
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Il I I I I 500 100 10 PPM Boron 2500 2000 1500 1000 Concentration (C) dc 500X (7000-C) di M PPM /HR Boron 35 70 90 200 300 400 20 25 30 40 50 80 80 100 150 250 350 500 Addition l l l l llll l l l l l l Rate (dc/dt) l l l l l l l l llll l l l GPM 4 Percent Boric ' l l l ll 45 80 75 3 4 5 6 7 89 12 15 18 24 30
. Acid Flow (X) 21 27 eel T3943819 I o PG-19
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e
- ,si ' IE1NCIELEE_QE_NUCLEAE_EQWER_ELAHI_QEEEAllON.
. PAGE 15
. IREEMQQ1NAMICE._HEAI_IRAMEEER_ANQ_ ELE 1D_EkQW ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
MASTERCCPY ANSWER 1.01 (2.00)
NO, the dilution (and subsequent startup) should N }q be continued. [.51 Source range counts have doubled on one channe l f' thi s would infer that 1/2 of the amount of reactivity to go critical has been added.I.51 To dilute by an additional 100 ppm would probably 1d take the reactor eritical. t . 51 [s/sjphf/ 7 superceifical) 14 :-5")
REFERENCE Millstone Reactor Theory,Pp 10.2-10.6.
Reacuse rheory 7mst , 9. gr-8.8 axi9, E 9uadorns 84 and 6-Io .
ANSWER 1.02 (3.00) l*> - Q O. Nog Because the value of neutron flux appears in both the nfumerator and the denominator of the expression for Xenon, the eqdlibr um value will not change directly proportional with power level.'N Physically, this is because flux increases burnout~
as well as production. Therefore, doubling the power increases the equilibrium Xenon concentration because the denominator of Jhe fraction becomes smaller, but the value does not double.0 5) (1.5)
- b. 50% is reached faster.h.T quilibrium Xenon is dependent on flux level and in this case reaches it's equilibrium value sooner at the higher power level.[j,p] (1.5) l REFERENCE ,
Millstone Reactor Theory, RT-16. Pp 16.3-16.4, and figure 16-4.
,* % E11MC1ELEE_QE_HEQLEAE_EQWER_ELAMI_QEERAI1QN. PAGE 16
, I)LERMQQ1NAW1QE._HEAI_IRAMEEEE_ARQ_ ELE 1Q_ELQW ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
ANSWER 1.03 (3.00)
- o. Rod worth will in rease with neutron flux,t.51 therefore, rod worth increasi from the outside edge of the core to the middle of the core 51 omp f C.cmd drw.r phew $ i, i.h +o od .M<- pinecivoi d ( 1. 0 )
- b. As boron concentrat in increases, rod worth decreases t.51 because of the higher competition for neutrons. (.51 (1.0)
- c. As the moderator temperature increases, rod worth increases (.51 because the thermal diffusion length increases, thus more
. neutrons are in the epithermal range and available for rods to absorb. (.51 (1.0)
REFERENCE Millstone Reactor Theory, RT-14. Pp 2-5.
ANSWER 1.04 (3.00)
- c. The excess steam flow causes Tave to decrease and insert positive reactivity (0.51. Power increases. At the POAH, negative reactivity from FTC (0.51 and Tave decrease slows (0.21. Power rise and cooldown continues until reactor power equals steam demand (0.31. [Un#/ MTC and FTC balanca) (1.5)
- b. Power rise rate higher and time to reach POAH shorter (0.51 due to smaller beta-bar and more negative MTC (0.51. Final power is the same but temperature will be higher (still below no-load Tave) [0.51 (1.5)
REFERENCE Millstone Reactor Theory, RT-183 pge.l85 ANSWER 1.05 (1.00)
Total power coefficient is more negative at EOL than BOL primarily due to the large increase in the magnitude of MTC, due to boron dilution. (1.0)
- .*f _ ,PE1MQ1ELEE_QE_MEQLEAE_EQWER_EL&MI_QEER&I1QMu PAGE 17 THERMQQ1MAM1Q1 MEAI_IRAMEEER_AMQ ELE 1D_EkQW ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING. W. i REFERENCE Millstone Reactor Theory, RT-13, Pp 13.5 ANSWER 1.06 (1.50)
- c. The gases contaminate the gap which reduces the thermal conductivity of the helium gas which raises the temperature
! of the fuel. (1.0) l
- b. LESS negative. (0.5) l i REFERENCE G.P. Heat Transfer and Fluid Flow. Pp 235-240.
Millstone Reactor Theory. RT-13, p2.
ANSWER 1.07 (3.00)
- a. Moderator Temperature Coefficient (MTC) (0.51 due to an increase (more negative) in MTC as boron concentration is reduced over core life (0.5). (1.0)
- b. Power defect has a stabilising influence on reactor operation because it resists power changes. (As power increases, power defect adds negative reactivity and as power decreases, power defect adds positive reactivity). (1.0)
- c. Doppler (FTC) 10.51. Tuel temperature changes first [0.51. (1.0) i RETERENCE Millstone Reactor Theory, RT-13 Pp 6-7 and RT-12.
ANSWER 1.08 (2.50)
- c. As condensate depression increases it lowers plant efficiency because of the heat removed has to be replaced by the reactor with no usable work out or visa-versa. (1.5)
Increased
- b. By,d:I Q:::::
_; condensfte depression the NPSH is d::: : d on the condensate pumps (and visa-versa.) (1.0)
. d _'_E'E1NCIELE1_QE_MECLEAE_EQWER_ELAMI_QEEEAllQN. PAGE 18
. THERMQQ1NAMICE._HEAI_IRANSEER_ANQ_ELula_ELQial ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING. W.
REFERENCE 0.P. Heat Transfer and fluid Flow. P 182.
ANSWER 1.09 (2.50)
- c. Subcooling is based on core exit T/C or hot leg RTD readings.
During natural circulation the mass of metal in the head can retain heat and keep local temperatures above saturation. The temperature indicators would not reflect this local saturated condition. (1.5)
- b. Pressurizer level decreases because the pressurizer pressure increase will compress the vessel void and force water out of the pressurizer. (1.0)
REFERENCE G.P. Heat Transfer and fluid flow. Pp 355-358.
ANSWER 1.10 (2.50)
- c. Decrease
- b. Decrease
- c. ^ e e . ; : t MctTAL
- d. Decroase
- o. No Change (2.5)
REFERENCE C.P. Heat Transfer and Fluid riow, section B.1 ANSWER 1.11 (1.00)
Incorrect. As the delta T increases out of the natural convection region J cnd enters into the nucleate boiling region, the heat flux changes in a i nonlinear fashion up to the point of DNB. (1.0)
- s
.vf___PRINQ1ELER_QE_MHCLEAE_EQWEE_Ek&MI_QEEE&llQE.
- PAGE 19
. IRERMQQ1EAMLCE._HEAI_IEAREEER_AER_ ELE 1D_ELQW
-85/05/14-HEnO41NG, W.
4NSWERS -- MILLSTONE 3 REFERENCE Goneral Physics Heat Transfer, Thermodynamics, and Fluid Flow Fundamentals, p 125.
ist.__ELAMI_QE11GM_1MChuniMG_1&EEII_ANQ_EMERGENC1_111IEME PAGE 20
- ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING. W.
ANSWER 2.01 (2.50)
- c. No, as the plant' pressure changes so will the delta-p across the #1 seal thus changing the seal flowrate. (1.0)
- b. The #3 seal standpipe and the VCT pressure. (.75)
- c. Through #2 seal (to the CDTT) and the seal return line relief valve (to the PRT). C.75)
REFERENCE Millstone System Descriptions, topic 1. lesson 2, Pp 15 and figure RP 14 ANSWER 2.02 (2.00)
- o. Maintains water to the steam generators when the main feedwater system ir not operating for routine non-emergency conditions and is part of the Engineered Safeguards Systems where it functions to prevent core damage by maintaining water to the heat sink during emergency conditions (such as a small break LOCA). C.75)
- b. The Auxiliary Teodwater System must deliver at least 470 gpm to two (2) steam generators within 60 seconds to prevent a solid condition from developing. (1,25)
REFERENCE Millstone System Descriptions, topic 4, lesson 2, P 3.
+
..
- PAGE 21
. ~L EL&MLDE11GE_.1MGkHR1HG_1&EEIL&HQ EMERGENGL111IEME ,
ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING W.
t l
ANSWER 2.03 (2.00)
Jocket water cooling systems prewarming the system to insure engine up to temperature, reduce stress.
amfhe /**A'd'r'88#**'
Lube oil systemt prewarmingYansures the engine will be able to assume load immediately.
Air start system procharged to insure starting air is available immediately.
Tuol systems aux 11ary pump installed to insure immediate pressure to injectors.
CANY THREE) (2.0)
REFERENCE Millstone System Descriptions, diesel generator and support systems,
'Pp 5-7, 25-26, 32-33.
ANSWER 2.04 (3.00) /' )
g See. Clotwl'uCGkd N f " M /
- a. Stops EGLSg output signals Allows manual control of l o ad s onca. *I Ia 8Esch EGLS becomes inoperative of any new initiating signals. (1.5)
- b. For three seconds after the EGLS LOP reset is depressed the EGLS will respond to a new LOP signal. After three seconds it becomes inoperative. (.75)
- c. Depressing the Station LOP RESET after the EGLS LOP RESET is depressed will reset the EGLS to a fully armed and ready
. condition. (.75)
REFERENCE .
Millstone System Descriptions, D/G Sequencer. Pp5
s.
y ,- . *
. -L _._ELAMI_DE11GE_1ECLMQ1NG_1AEEII_ANQ_EMERGENC1_1111EME PAGE 22 ANSWERS -- MILLSTONE 3 -85/03/14-HEMd!NO, W.
ANSWER 2.05 (2.00)
- 0. Par. level ( 17%
-loss of power or air (1.0)
. closure or vales 459 or 460
- b. 1. controls pressure downstream of the letdown orifices to eliminate flashing and two phase flow.
REFERENCE Millstone System Descriptions, topic 2, lesson 1, Pp 9, 11-12 PtID EM-tO#A-18 ANSWER 2.06 (2.00)
- c. (1) Reduces thermal stress to the spray line and spray nottle.
(2) Reduces thermal stress to the surge line (3) Maintains pressurizer chemistry uniform with RCS (4) Promotes mixing in the pressurizer (any 3, .33 eal (1.0)
- b. Spray line or surgo line low temp alarms (0.5)
- c. Loop 1 and loop 2 (0.5)
REFERENCE Millstone System Descriptions, topic 1, lesson 4 Pp 6-8 and figure PR-2 E
l l
PAGE 23
. i.hEL&HLDEELGE 1HCLUQ1HG_E&EEILANQ EMEEGENGLE1EINE
-85/05/14-HE1441NG. W.
AN SWERS -- MILLSTONE 3 l
ANSWER 2.07 (3.00)
- a. Dilute mode travels only to the top of the VCT (spray nozzle).
Alternate Dilute travels to the top and bottom of the VCT. (.75)
(spray nossle and suction of the charging pumps)
- b. The Alternate Dilute path offers a fast method of dilution but used over a period of time will deplete the hydrogen in the RCS. A second path for routine dilution that does (.75) not affect hydrogen was designed into the system.
- c. Boric acid leaving solution (crystallization). [.25)
The temperature of any system containing boric acid is kept elevated to a temperature which is based on the concentration (0,5) of the boric acid. t . 2 5 ) (Or r%nking Bf concerrtrobon ota eno g h fo c//eviate Crysk//izehbn / . A.~ h 1 M F a / O Non' % )
- d. 1. Reactor Makeup Mode Selector in BORATE or MANUAL and the Reactor Makeup Control Switch in START.
- 2. Reactor Makeup Mode Selector in AUTO, the Reactor Makeup Control Switch in START, and VCT level at the low level (1.0) e makeup setpoint.
- 3. Pushbuttons on Mca h START REFERENCE Millstone System Descriptions, topic 2, lesson 2. Pp 14, 19, 29-31.
ANSWER 2.08 (2.50)
Figure RP-21 in Millstone S.D. topic 1, lesson 2.ccpf ald's"hd Drawing requirements: 4 labeled supply and return headers 4 labeled components cooled in RCP 4 cooling flowpat s 3
~
0 fIer i n d-i ee r't5 criicesf-C 3 relief valves spg 4 containment isolation valves (one is a check valve P Thermal barrier isolation valve (air)
CL- Thermal barrier supply side check valve
( . ilf e a l (2.S) ll&[Jwk Cy ?w [VCfCWA u s tuO d REFERENCE Millstone Systen Description, topic 1, lesson 2. drawing RP-21.
l l
PAGE 24 l, i "LEIL&HLQE11GE_1HCLU D 1 NG_E AEEIL&HQ_EMEEGENCLE1EIEME
'ANSW'ERS -- MILLSTONE 3 -85/05/14-HEAAdING. W.
ANSWER 2.09 (3.00)
(chesa
- a. SlowFwarming of the stop valves.
Pressurizing the stop valves for opening.
Pressurizing below the seat areas up to the CIV's for shell
' (1.0) warming.
- b. Increase thermal efficiency of the turbine.
Minimize erosion damage to the low pressure turbine. (1.0)
- c. They protect the exhaust hood and the condenser against (1.0) excessive steam pressure if circulating water is lost.
REFERENCE Millstone System Descriptions, topic BOP 2-3, Pp 5-11 ANSWER 2.10 (3.00)
An Active Failure is the failure of a powered component such as a piece of mechanical equipment, component of an electrical supply system, or instrumentation and control equipment A Passive railure is the structural failure of a static component which limits it's effectiveness in carrying out it's designed -
(3.0) function.
REFERENCE Millstone System Descriptions, topic 3, lesson 1, p 19.
l
PAGE 25 k _1.NEIRUMTEIE_&HQ_QQHIRQL1 ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
ANSWER 3.01 (2.50)
The low impulse pressure signal would cause rods to drive in at maximum speed. [.751 in a short period of time, the power mismatch input to the rod control system will fade. (0.51
.nd 'ha mi ~stch de?-'arad bet cen T. -
I. ..v. .i ii.c n; !::d 1:!ue,
- h;uld L. Leivn i l. . uv-;ead rs!ue for '1'="g.
.= a d T a '1 g .
will t=Va
=hi-k c"er sut; ed ye .;.cning. l 0 . ': : "cd; will n;; ;tey
(.
/
- q/
nara*==r" 'a --te.. Tavy iv uv-iv d T..I at ; ;yecd dete.m ..d
_by tw- t-_p.c=+u,- innut= r
'HT Mee_ ma sen b eta S 2.53 a eA do re s'n ec % to T).? ksw anel C- C w.l Q Cln d rt- ll c&mt
- 4. m &
o.vdaloG necw-lo roc! c&rol y A o h se,d herea.&
REFERENCE in lf)
Millstone System Dese ptions, topic 6, lesson 2. Pp 19-21 g c YC ANSWER 3.02 C2.00)
- a. Train A- auctioneered low wide range Thot wide range RCS pressure CPT405)
Train B- auctioneered low wide range Tcold wide range RCS pressure CPT403) L.25 eal (1.0)
- b. The respective PORV block valve will open if it's control switch is in automatic and the PORV's (1.0) lift setpoint source becomes the COPS programmer.
REFERENCE Millstone System Descriptions, topic 6 lesson 6&7 Pp 15-16 C _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
T -
h
,/'
i ,
I M,cex f 3 $.0 &,/A -
[W
~
e M
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& Y ~
tl.ll' Y 'Ae d & A< A ftxdle Yf-VS d
... k$ SWA M nma JA
- i Y YY &
nwo m a
- 4 h A kMP j/
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/ / Q AA- b.
y -
/3 J ~ & :- J A m,,aaa4 -
l i
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i l
I I
I
PAGE 26
I __INEIEUMEEIE_AND_CQHIEQLE ,
ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
ANSWER 3.03 (3.00)
- n. Charging flowrate Actual pzr level Program level C.25 eal C.75) b.' .
25% at 557 F. to 61.5% at 587 T. dh- (.75)
- c. Level error is the difference between actual par. level and programmed level. (.751 Energizes backup heaters on a +/- 5% level deviation.
Energizes pzt. level deviation alm.
Provides input to control charging flowrate.
(.25 eal (1.5)
REFERENCE Llillstone System Descriptions, topic 6, lesson 6&7, Pp 25-26 ANSWER 3.04 (2.00)
- o. Steam pressure is used to compensate the steam flow signal for density variations in the steam as power increases. (1.0)
!Mgh
- c :: than actual. (1.0)
- b. Indicated steam flow will be REFERENCE Millstone System Descriptions, topic 6, lesson 9, p 18.
ANSWER 3.05 (2.00) 1 MW[
isolated hot leg wide range temperature must be/.112-within O2%b %f 5 Degr of auctioneered high wide range Thot.
- 2. Isolated cold leg wide range temperature must be within 5 Degr of auctioneered high wide range Tcold.
- 3. Hot leg isolation valve must be open.
- 4. Bypass isolation valve must be open.
- 5. Sufficient flow through the bypass / mixing line (200 gpm) (2.0)
,. a " -
. 1 3.0 f $~J.
fo 0.t j ._
- 0. . Ofttk "Std Mek assoce.hd u>dL 441 RMR sache>v vs.lveo ,
(87cin/a n 8702 n/a ). (dxtud q yp&uuo @) Q.sl
- h. 1 26S s i a. d*82. /j//dl 'da>td4.1c>v c.u<N/. % vs-.
' cvcs demL~4 A pop . O.>-M.A ep & _
do;ndiai>v 4Aa.c cuculd Au?DMA&A'tV__ &5p_ es '
- c. k 1h30 5 &R y ._
^ ^ _ _ . . _ _
- - ~ - ._
D A U S f fs op W ) / m t. u a r u i.a .$ a a. 4 L a J U25psef._
Q.. ~luiu nM & wk c.lu u ak 76QN ACS(loy air)p.
-luul a.u. ten.ohi 9 8804 , 68 t'L., , to 57 a gs 5g
~ lth LL yt a p & w.i m.a (I. s _
Oh L c.les.ul. E t -Q @ 0 75 u< L.3 (P2V-tsi) ( a.s
- b. L % D m 0 4 JeL<
' ~
C. Ru.U1~ p J 4.3fo y ) feu) AdC4. 4Z Q y (QA") ..
P
- 203 Wiru og @grues pap u.a. %
- L O. ( & SNC *rb ) .
[ 2P 0 5 uJ 3. h.s 7 - 10 AG2hhv 3 VMI , Tf.1, Less~ f. , (>+p
s,,.
PAGE 27
' L_1.NEIEl&lERIE_AND. CQHIRQLE
-85/05/14-HEMMING, W.
ANSWERS -- MILLSTONE 3 REFERENCE lesson 1. Pp 15-16.
Millstone System Descriptions, topic 1, ANSWER 3.06 (2.00)
- a. Degree of coincidence is the number of input channels required to intiate a protective action as compared to the total number (0.S) of input channels.
- b. Three detectors may be used and a 2/3 logic developed if NO control action occurs from a protection channel or a backup form of protection exsists.
For a safety grade system or if a channel is used for both protection and control purposes. 4 detectors and a 2/4 (1.5) coincidence is required.
REFERENCE lesson 1,2, and 3. Pp 8-11, 73 Millstone Systems Descriptions, topic 7, and topic 8, lesson 4, p 6.
ANSWER 3.07 (3.00)
Due to the lack of a P-4 signal, the Because steam dumps will arm using of the instant drop in the Loss of Load controller.l.75) impulse chamber pressure, the loss of load controller will see an instant-aneous 28 Degr deviation. This deviation will cause both the Hi-1 and Hi-2 bistables to trip which will trip open all three banks of steam dumps.l.75) The banks will remain open until temperature drops allowing the Hi-2 bistable to reset thus allowing bank 3 to cycle shut and then bank 2. When the Hi-1 bistable resets, bank 1 will cycle When all banks of steam dumps are closed, RCS temperature shut.l.75) will be 2 Degr above no-load Tavg due to the 2 Degr deadband in (3.0) the loss of load controller.C.75)
REFERENCE Milletone System Descriptions, topic 5. lesson 2, p 12 and figure SD 4 & 5.
, .* 28 PAGE
.#.12_IN11RUMENI1_ANQ_CQHIEQLi
-85/05/14-HEMMING, W.
ANSWERS -- MILLSTONE 3 l
ANSWER 3.08 (3.00) l PEmd!SSIVES TRIPS ___________________
- 1. P-6. P-10
- 1. S.R. HI flux
- 2. P-10
- 2. l.R. Hi flux
- 3. P-10
- 3. P.R. Hi flux to stpt P-13
- 4. P-7, P-10
- 4. Pzr. Iow pressure P-10, P-13
- 5. P-7
- 5. Pzr. hi level
- 6. P-8
- 6. Single loop LOT P-10, P-13
- 7. P-7,
- 7. Two loop LOT 8.4'H+
C. "0" :.- ;h_!! ;;;;d
- 9. P-7 P-10. P-13
- 9. RCP lo-lo shaft speed
- 10. P-9
- 10. Turbine / Reactor t.14 ea) (3.0)
REFERENCE lesson 1,2 and 3. Pp 65-70 and Millstone System Descriptions, topic 7.
Tcble 4.
ANSWER 3.09 (3.50)
- c. 1. OPdT and OTdt trip setpoint calculation curcuits. c,ure.d MiMkA NR-45 recorder 2.
- 3. NR 41-44 recorders g ( g,
- 4. Detector current comparator c/,rcuit
- 5. Plant computer
.6. Delta flux meters,dt. qhOtopd b N MM (1.5)
- b. The detector current comparator compares each upper (lower) detector to the average of all the upper (lower) detectors. (.251 It alarms when any detector output exceeds the average by 1.02 t.251 It monitors upper (lower) quadrant power tilts. (.25) and is active only when power exceeds 50%. (.251 The channel current comparator compares the output of a l l 4 : : : ^ -'
four power range summing amplifiers to each other. ( 251 It alarms when any two channels deviate from one another by 2%. (.251 Monitors for quadrant power distribution (.251 and is always (2.0) active. (.25) l l
l
.s',,' a
. . #1- iMEIREMENIE_AHE_CQEIEQLE PAGE 29 ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
REFERENCE Millstone System Descriptions, topic 6, lesson 4 Pp 20-21,26,28.
ANSWER 3.10 (2.00)
- o. I. recombination II. ionization 111. proportional IV. limited proportional V. gelger mueller VI. continuous discharge [.25 eal
- 1 curve is detector characteristics for gammas
- 2 curve is detector characteristics for alphas t.25 eal (2.0)
REFERENCE Millstone System Descriptions, topic 6 lesson 4 Pp 6-7 and figure EN-2.
l 'p., - ,
pAGE 30 L.__5EQCEQuREE_ ._NQEMAL._AENQEMAL._EMERGENCL.ANQ
. EAQLQLQGLC&k_CQNIRQL l .
W.
-85/05/14-HEMMING.
f AtiSWERS -- M1LLSTONE 3 ANSWER 4.01 (2.00) requi d ech c valu
.) o h pa m ers app BELOW 850 cu. and psi (
(T. alues . .
Reactor safety would be jeapordized because the accumulators b.
lack sufficient pressure and inventory for proper injection. (2.0)
Canswer will be graded accordingly if candidate responds that the indicated parameters are above T. S. limits) b M ecL 3 N aad M CmW A .g* h 6g no CA.a.d b go.mek o f' REFERENCE (.a n k m %+- P 3. Pp 55-56 Millstone Systems Descriptions, topic 3, lesson ANSWER 4.02 (3.00)
I Bonk D reactivity.. 170 pcm (+/- 5) A y 3(,- /1.% cag Power Defect 8%-80%;1500pcm(+/- 10) - 160pcm(+/- 10) 340pcm C+/- 20) [.91 Total reactivity.. 1340pcm(+/- 20) - 170pcm(+/- 5): 1170pcm C+/- 25) [. Kid
[.Y)
Diff. Boron Worth. .10.75 pcm/ ppm C+/- .1) SeceptID 'f- li pee /pp%
(.31 Dilution : 1170 pcm / 10.75 pcm/ ppm = 109 ppm (+/- 5) t.31 OcIlons from nomograph.. 8000 gallons (+/- 250)
.. 109 ppm over 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> : 91 ppm /hr (+/- 5) (.31 Dilution Time. .. ..
[.31 Dilution Rate nomograph. 112 gpm (+/- 5)
(3.0)
REFERENCE Millstone curve book.
ANSWER 4.03 (4.00)
- a. Par. heaters must be energized to induce spray flow. This insures proper mixing in the pzt. which equalises the boron (1.5) concentration between par. and RCS.
(1.0)
- b. Every 50 steps. This insures proper group alignment.
l 1
'p'. .
. 'i_E1LQCEauREE - HQEMAL._AREQEMAL._EMERGENCI._ANQ PAGE 31
. EAQ1QLQQ1 CAL _CQET.EQL ANSWERS -- MILLSTONE 3 -85/05/14-MEnedlNG. W.
REFERENCE Millstone Reactor Startup Procedure. OP 3202, Pp 8-10.
ANSWER 4.04 (2.00)
- 1. Increase RCS pressure by using pzr. heaters or increase charging if plant is solid.
- 2. Decrease RCS temperature by feeding and steaming S/G's, operation of core cooling equipment, or adjusting RHR flow.
3.(increasing RCS flow is listed in the procedure as a third choice, however no methods for achieving it are listed. Full credit will be be given, if this answer is chosen by the candidate , based on the information supplied by the facility ) (2.0) bM M i'i p h a.n c1 % b
- W5 b RETERENCE F Millstone Procedures.
EOP 3504, p 3 ANSWER 4.05 (3.00)
- a. 1. Control bank below the lo-lo insertion limit.
- 2. Failure of one or more RCCA's to fully insert on a trip.
- 3. Uncontrolled cooldown of the RCS on a trip or shutdown.
- 4. Uncontrolled or unexplained reactivity increase.
- 5. re clor make-up system. (1.0)
Failure of the SOfY\ 6 is.b b4h o f"
- b. Until entry condition is satisfied.(.L) (0.8)
- c. Required minimun flowrote per AOP 3566 = 35 gpm. tw gm o.ee9 Assume 10 al 4% boric acid = 1 pm given in AOP 3566) k m h mdtM 100 gb m m g.mergoney sik m s M k na Mme . gm 100 ppm x 10 gal / ppm = 1000 gallons boric acid.
1000 gallons / 35 gpm = approx. 30 minutes (+/- 5) (1.2)
RETERENCE Millstone Procedures, AOP 3566.
.../
. d.hiEQCEQUEER___MQEM&L _&REQEMAL EMEEGEMQ1_&MQ PACE 32
. RAQ1QLQG1 CAL _CQMIRQL ANSWERS -- MILLSTONE 3 -85/05/14-HEMMING, W.
ANSWER 4.08 (2.50)
- o. (11D1)(11D1) = (12D2)(12D2) 10.51 1200(2)(2)/C5)C5)=192 mr/hr (192 mr/hr)(2 hr.): 384 mrom [.751 (1.25)
- b. 900 arem + 384 area = 1284 mrom (0.253 He exceeded normal 10CTR20 whole body limit of 1250 mrom.
If assume that NRC FORM 4 is complete, then limit of 3000 mrom is not exceeded. [1.01 (1.25)
NOTE: Answer to "b" is dependent on answer to "a" and graded accordingly.
RETERENCE Millstone Procedures, HP 4902.
ANSWER 4.07 (3.50)
- 1. Main steam lines shut.
- 2. Main feed lines shut.
- 3. Blowdown lines shut.
- 4. Auxiliary feed lines shut.
- 5. Steam supply and warming valves to T/D ArW pump shut.
- 8. Mainsteam low point drains shut
- 7. 5/O atmospheric dump valves shut t.5 eal (3.5)
RETERENCE Millstone 3 Emergency Procedures. EOP E-1. P4
. ,: s
."TE_f.EQCEQUEER_._MQRMALm&RNQEMahm_EMERGENCI_&HQ PAGE 33
. RAQ1QLQG1 CAL _QQMIRQL
-85/05/14-HEMMING, W.
(NSWERS -- MILLSTONE 3 ANSWER 4.08 (3.50)
- 1. RCS subcooling based on core exit thermocouples. (0.5)
- 2. S/O pressurest.51- stable or decreasing.t.25) (.75)
- 3. RCS hot leg temperaturest.51- stable or decreasing.t.251 C.75)
- 4. Core exit TC'st.51- stable or decreasing.t.251 C.75)
- 5. RCS hot leg temperaturest.5)- at saturation temperature for S/C (.75) pressure.t.251 REFERENCE Millstone 3 Emergency Procedures. EOP-35 ES-1.1, attachment A.
ANSWER 4.09 (1.50)
- a. When at least one AC Emergency Bus is energized, t.51
- b. SI should be reset (to permit manual loading of the equipment). t.51 c To prevent injection of accumulator nitro en into the RCS, ~
I l 1.51 (1. )
L /. o
~
REFERENCE Millstone 3 Emergency Procedures, EOP 35 ECA-0.0, Pp 3.5,&9.
~
h COOLING WATER TO THE REACTOR -
- )
W COOLANT PUMP a
'O Water 1.
CCW g g Loads n _ __ ,,
ig
- _ _ - -g
,_ h E m
--lig!-&--- :'/E -
l l@T=,. 4 3g51 ?= a ,,:
Oh Other
~ ~
\ /
I.n Reactor Coolant Pump RP-21 k
O S
- U. S. NUCLEAR REGULATOPY CO MM I S SI ON SENIOR REACTOR OPERATOR LICENSE E X AM IN ATIO N FACILITY: _dlL LS IDbE _1______ _ _ _____
REACTOR TYPE _EW3-MECH ________________
D AT E A DM I NI S T E RE D _H 24 01/li_ _______________
EXAMINERS _1S&EigNz_E,_____________
RCOPY APPLICANT _________________________
IH1IEUCI1QHS ID_&EELICAMll Use separate paper for the answers. Wr ite answers o n on e side only.
Staple question sheet on top of the answer s heets. Points for each question are indicated in par entheses af ter t he que st ion. The passing grade requires at least 70% in each category and a final gr ade of at least 801. Examination papers will be picked up si x (6) hours after the examination starts.
% OF CATEGORY % OF APPLICANT 8S CATEGORY
__X&Lut. _IDIAL ___1CDRE___ _MALUE__ ______________CAIEGQR1_____________
_25aQQ _22sDD ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, F L U10 5, AND THER MODYNA MI C S
________ 6. PL ANT SYST EMS DE SIGN, CONTROL,
_22402__ .2faQD ___________
AND INSTRJMENT ATION
________ 7. PROC EDURES - NOR M AL, ABNORMAL,
.22sD9__ _224DD ___________
EMER GE NCY AND RADICLOGIC AL CONT ROL
________ 8. ADMINISTRA TIVE PROCEDURES,
_22s00__ 22AQQ ___________
COND IT IO NS , AND LIMITATIONS lQQaQQ__ 10DaQD _ _ _ _ _ _ _ _ _ _____ T OT A L S FINAL GRADE _________________t All work done on this examination is my own. I have n ei ther given nor received ald.
~~~~~~~~~~~~~~
SPPLiC5N TI~ S SIGN 5YUEE WSERCPY t
=
PAGE 2 53__IHkDEI_DE_HUCLEAE_EDWER_ELABI_DEERAIIDBa_ELUIDia_AHD
. IHEEDDDINADICS
- L l
QUESTION 5 01 (2.00)
List the TWO f actors which interact to resul t in t he Dop pl er Fuel Temperature coefficent (FTC) being more nega tive a t EOL AND briefly explain how each f actor af fects the value of FTC. .
(2.0)
QUESTION 5.02 (1.50)
According to Technical Spec i fi cat ion bases 3 /4.1.3, ther e are l THREE reasons for the contr ol rod i nsertion limits. NAME THE ;
THREE REASONS. (1.5) i 1
l QUESTION 5.03 (3 00) l i
Unit 3 calculated Shutdown Margin is 10% delta k/k assuming the most reacti ve control rod worth i s 1000 PC M. The Source Range count r ate is 50 cps. Show all work and state any assumptions made f or the following;
- s. Determine the final count r ate af ter the shutdown ba nks are fully withdrawn, assume the shutdown bank rod worth is 5600 PCM. (1 5)
- b. Determine the final count rate af ter 100 ppa d llution of the RCS FOLLOWING as above. (1 5)
QUESTION 5.04 (3.00)
- a. Explain the ef f ect of rod position on the Moder stor T emperature Coe f ficient (MTC). Consider only rods inserted or withdrawn at power and disregar d any effects of change s in bor on concentrat-lon. (1.0)
- b. Explain how and why the magnitude of MTC will v ary wi tn RCS temperature. (1.0)
- c. What are two 12) ef fects that cause the Axlal F lux Re distri-tion reactivity effect? (1 0)
(***** C ATEGORY 05 CONTINUED 01 NEXT PAGE *****)
w- ,--------____m__m__ . -
'Sa__IBEDEI_DE_duCLEAE_EDWEE.ELAWI_DEERAIIDut_ELUIDit_ASQ PAGE 3
, ' IHEE50DISA51CS QUESTION 5.05 (2.50)
- a. Provide the full power equilibrium PCM values for tne following poisons:
- 1. Xenon 10 25)
- 2. S amar i um (0.25)
- b. Provide TWO reasons f or Xenon con tributi ng mor e nega ti ve reactivity at full power than does Samar ium. (2.0)
QUESTION 5 06 (3.00)
- a. Explain the response of reactor power and Tave after 2 minutes of Emergency Boration at 100% power. Assane r od contr o f is in manual. (1.5)
- b. Explain the response of reactor power and Tave after 2 minutes of Emergency Boration at 10 -8 amps and no l o ad Tave. (1.5)
QUESTION 5.07 (2 50)
Assume one RCP trips at 304 power without a reactor protection system actuation or a change in turbine load. Bri ef ly d iscuss how each of the following parameters will ch an ge .
- a. Flow in the operating Reactor Coolant Systems loops. (0 5)
- b. The ratio of core flow compared to the total loop fl ow. (0 5)
(Core flow / Total loop flow)
- c. Reactor vessel delta-P. (0.5)
- d. Actual Core delta-T. (0.5)
- e. An (RCS) operating loop steam generator temper sture. (0.5)
(**ee* C ATEGORY 05 CONTINUED 09 NEXT PACC *****)
in__IMEDRI.QE_HUCLEAR_EDWER EL&HI_DEEE&IIDBa_ELUIQit_AdQ PAGE 4
, IBEEEDDISABICS QUESTION 5 08 (2.00)
- a. What is the advantage of condensate depr ession ? (0.5)
- b. What is the disadvantage of condensate depress lon? (0 5)
- c. Determine the condensate depression if the condenser is operating at 4" Hg absolute and the cond en s a te temperature is 115-F. (1.0)
QUESTION 5.09 (2 00)
- a. Wny is the limit for the over temperature Delta T trip based on not r eaching s atur ati on condi t ions 11 the hot legs? (1.0)
- b. Refer to figure 5-1 attachea.
Operation wi thin the limits of the 2000 psis curve f rom "984 power- ~607-F Tave to "120% power- 575-F Teve will prevent ex ceeding what specific alnimum p lant th er mal cr iter la? (1.0)
QUESTION 5 10 (2.50)
A reactor operates at 100% power with RCS Tave at 570 de gr e e s an d a steam pressure of 770 psig. How much will Tave change if 25% of
> the Steam Generator tubes are plugged and 100% pow er ano 770 psi g steam pressure are maintained ? (2 5)
QUESTION 5.11 (1 00)
Why is the allowable RCS PRESSURE for a cool down sor e li mi t ing than for a hastupt (1.01
(***** END OF CATEGORY 05 **" *)
m 60__E L A NI_ SIS IE 51_D ESIGN a_GDHIROLa_ AND _ IN SIRU BE NI &I lQ H PAGE 5 QUESTION 6.01 (3 00)
For each case below EXPLAIN the resul ting me thod o f reac tor cool ant system temperature control AND Indica te the approx imate final RCS Tave. Assume all sys tems normal except as s tated, no op er ator actions AND consider each case separately.
- a. The normal steam pressure setpoint is re duced by 92 psi while in Hot Standby awaiting reactor startup. (1.0)
- b. The train A steam dump selector switch i s plac ed in 'off' while at 54 reactor power awaiting turbine startup. (1 0)
- c. Tr ain 8 reactor trip br e ak e r f al l s to op en u po n a tr i p from 784 power. NOTE: Train A br eaker opens . (1.0)
GUESTION 6.02 (3.00) p g]
- a. State the 5 Interlocks hat must be sati sfied to open an RCS cold leg loop Iso ation valve. (2 0)
- b. What are the reas s/ bases for the Inter locks in as above? (1.0)
QUESTION 6.03 (3.00) e, Assume the plant is shutdown at 500 F and 2003 p s i g. Will the Cold Overpressure Protection System (CDPS) act to re duce plant
! pressure immediately if a loop Tcold i ns tr umen t f all s LOW 7 l
SRIEFLY EXPLAIN your answers INCLUDING Which train i s af f ected, what action takes place, and any applicable setpoints. (2 0) i
- b. What is the purpose of the PORV i nterlock? (1.0) i QUESTION 6.04 (2.10)
- a. What TWO Diesel Generator alarms will al ways s top the diesel 4 engine? (1 0)
, b. What will cause a Start Fallure (SFR)? Se spec i f ic. (0.6) l c. What action is required (as a sinimum) Def ore anothe r st ar ti ng i attempt can be madet (0.5)
( ***** C ATEGORY 06 CONTINUE 0 09 NE X T P AGE * ** * * )
i i
t
(3 o r c.~.t (0.o%)
$ o.. Jkte 7um slecku auscatut. war 1r Rite sac.Liou advea (87ain/e n 8702 A/e). f'dJud a.y cytes4., &) (/.s)
- b. % 2CS & L. o. cold /JsGd eordd ou wh4. chn>wp v&.
cecs dui k q .o J. yo y . u>-L&.A e w ww idLL 3 kd k e d 4 Res p ? -
(o.s)
- c. s,.%lt Thio C o dictbv 4Aar wowW /?u7wd&At V &i,o n-N
- PW
$v>
O a.-W W na ef.h.i m lu.a- kt'S(6*p un) pia >>w ia .hu .d.a a 425 psQ
- WiU auto &9 c. low sk 760pQ ACS((op tot)p .
~k)W w< p u J.u w & 860V , 6212 , 8!57 M E858 tlh L chsed . [ 2 .ta 9 a.7 s u<.L '1 (i.s)
CA 4 M = ^ + A* ^^ f'e, a='
= =,+ ' x = " ^ & 6-" ~ ^ ^ 'D b, Ltldtwh N MM 0& 0h (W-15I ) (o.5)
- c. Rux r J.u d (< % y ) feu) & 4: y (w (car) h -
'O "{} W
- M A rv p & fa y L.,O, Rd fe (L{yM LD. S&.- ( fouuu 34 c n L .)
cg2e c . s u.a. : # c, Ah w a a W .c.,z , r p .1 , Lew.a 6 , psp 7- ic Aldin k ? Ll 0 I ,' fop 0, 2 ,l.ru e> t , pop /: a~a I
PAGE 6
'$ s__EL & HI_111IE Bi_D ESI G Br_CQHIRQ L t _ ABQ _IH1IEl dE bl &I l0 B i
QUESTION 6.05 (2 50)
The plant is operating at 30% power when the f i r st stage impulse pressure transmitter PT 505 falls HIGH. Exp lain t he effects of this f ailure and the sequence of events (con tr ol a nd pro tection) that lead to a reactor trip. Assume BOL, no oper ator a ction and initial (Setpoints plant conditions are in a normal / automatic c onf igu r ati on. (2 5) not required).
QUESTION 6.06 (2 40)
The pl ant is operating at 80% power when a T hot Rf D f ail s high.
EXPLAIN how this failure will affect the f ol lowing. Consider each item independently. Assume no operator acti on and all c ontrol systems are in automatic.
(0 6)
- a. Rod insertion limit setpoint (0 6)
- b. Ch ar ging flow (initially)
=
(0 6)
- c. Control rod bank position (0.6)
- d. Steam dump control system QUESTION 6 07 (3.00)
List the sequence of events (control and pro tec tio n) that leads to a reactor trip when the contr olling P r ess ur i zer LEVEL channel (459) falls HIGH.
ASSUME- No oper ator action and initial plant condi tions ar e in a normal / automatic conf igur ation at 50% load. (Setp oi nts of contr ol (3 0) and protective events are not required.)
(***** C ATEGORY 06 CONT 1 HUED 01 NE X T P A GE * * * * * )
PAGE 7 (s__EL&dI_1XiIE51_DE11EHt_CONIRQLt_ANQ_INSIEUBENIALIQB QUESTION 6.08 (3.00)
Indicate whether the following statements ar e TRUE for OT Delta-T, OP Delta-T, or BOTH, ( OT De l t a-T an d OP D el t a-T )
protection instruments.
- 1. Backup for the high neutron flux trip. (1 0)
- 2. Circuitry dynamically compensates for pi ping d el ays to the loop temperature detectors. (1 0)
- 3. Requires RCS pressure within the high and low reactor trip setpoints in order to be val id. (1.0)
QUESTION 6 09 (3.00)
- a. What automatic actions affecting the Que nch Sp ray System occur on decreasi ng RWST level, other th an alarms? Include both the action and the associated l e v el when they o ccur, (Numerical values not required). (1.0)
- h. How is Sodium Hydroxide (NaOH) added to the OJ ench Spray System upon COA 7 Please be specif ic. (1.0)
- c. Why is NaOH added to the Quench Spray System? (0.5)~
- d. What is the effect of pressing the CDA r eset pushbut tons too scont(0 5) l l
l l
l l
1
(***** END OF C AT EGORY 0 6 * * ** * )
PAGE 8 lo__ERQCEDUREi_=_MDR5Att_ARNDRd&La_E5ERGENC1_AND
. ' EADIDLDEICAL_CDUIEDL l
)
1
. 1
. i QUESTION 7.01 (3.50) l The following concern " Reactor Startup", pro cedure OP 3202.
- a. What operator actions are required i f cr it ical ity is NOT achieved when control rods reach the MAXIMUM r od pos ition on the ECPT (1.0)
- b. What additional operator action i s requi red when dil uting the RCS boron concentration more than 50 ppi? (0.5)
- c. Ar e you permi tted to adjust boron concen tr ation whil e withdr awing the shutdown banks? Briefly EXPLAIN. (0 5)
- d. How is proper group alignment and bank o ve r l ap d eter mi ned during rod withdrawal for criticality? Be spacific. (1.0)
-8
- e. While recording data at 10 amps, loop D Tavg i s 53 5-F.
What action is required if you have determined that loop D Tavg has been < 551-F for the last 15 minutes. Inc lude any applicable time llaltations. (0.5)
QUESTION 7 02 (3.00) l The following concern " Response to Nuclear P ower Generat ion /
ATWS" procedure E 0 P F R-S . I .
How is a reactor trip verifled? (1 0) a.
i b. What operator action is required if the reacto r f all s to tr ip manually? (1.0) i
{ How is a tur bine trip verified? (0.5) c.
- d. What condition must be met before bor ati on c an be (0.5) terminated?
l l
(***** C ATEGORY 07 CONTINUED 01 NEXT PAGE *****)
PAGE 9 2,s _ERQCEDURE1_=_SQR5 Alt ABBDEdalt EdERGENCI_AdQ
' BA01DLQGICAL_CDMIEDL QUESTION 7.03 (3.50)
The following concern " Reactor Coolant Pump Op e r at io n" procedure OP 3301D precautions.
- o. Why should the RCP seal leakof f i sol atio n valv e be closed when (1.0) l RCS pressure is below 100 psla?
- b. How long can RCP operation continue if t he sea l leak of f isolation valve was shut due to il seat leakof f exce ed ing (0.5) the limit for saf e oper ation?
(1.0)
- c. List the RCP starting duty r equir ements.
(0.5)
- d. Why are these starting duty requi rements neces sary?
- e. When are you required to stop the RCP's if Reactor P lant (0.5) component cooling water flow to the RCP's is l ost?
QUESTION 7.04 (3 50)
The following co ncer n "Natur al C ircul ati on C ooldow n" pro ccoure EOP 35 ES-0.2.
- a. What is the priority / order f or attempting to r estart (1 0)
RCP's? Why?
What specific indications are used f or sonitor ing RC S cooldown. (1.0) b.
- c. How is RCS depressurization performed if normal l e td ow n is (0.5)
NOT in service?
- d. What would e your primary indication of steam v oi di ng in (0.5) the reactor vesself
- e. If auxiliary spray flow is requir ed, H0d i s auxili ar y spray (0 5) flow maintained / adjusted?
(***** CATEGORY 07 CONTINUED 01 NEXT PAGE *****)
PAGE 10 Ia__EEQCEDURES_:_HORBALa_ASHOEd&La_E5EEGENCh_ASQ
, ~ EA21DLOGICAL_CONIEDL t
I i
QUESTION 7.05 (3.00)
The following concern " Steam Gener ator Tube Ruptur e" procedure E0P 35 E-3.
a.
What is the criteria for determining if RCP's should be (1 0) stopped?
(1.0)
- b. List FOUR ways the ruptured S/G can be i dentif led.
- c. If a PZR PORV is used f or RCS depressuri zations the PRT may What rupture and result in adver se containmen t cond it ions . (1.0) is the definition of adver se containment condi ti ons?
QUESTION 7 06 (3 00)
- a. List FOUR conditions that require Immedi at e Bo r ation (2.0) as stated in ADP 3566.
b.
What operator actions are required to Immediate Bora tes (1 0) according to AOP 35667 QUESTION 7 07 (3 00)
The follow;ng concern " Radiation Work Permit Compl etion and Flow Control", procedure SHP 4912.
- a. What are the Tuo conditions which allow contin uous HP personnel (1 0) coverage to be substituted for a RWP7
D e te_,;w o
,o
- c. What is indicated / implied by your s i gn at ur e as SS/SCO ( )
on a RWP?
(***** CATEGORY 07 CONTINUED 01 NE XT P AGE * ** * * )
PAGE 11 Za__EEDGEDUEES :_HQEBAlt &&tiDEdALt_E5ERGENEL ABQ
- EAQIDLDGICAL_CDUIEDL
\
f QUESTION 7.08 (2.50)
The following concern " Refueling Oper ations" proce dure OP 32108.
l f
I a. Driefly expl ain the exception to maintai ning r esidual heat removal flow during core a l ter ati ons, include any ap p l i c able (1.0) ti me limitations.
f
- b. What is the basis / reason f or maintaining 10 5 f e et o f water above the top of each fuel assembly du ri ng all h andl in g (0.5)
{ operations.
- c. Whos by job position / title can approve /authori ze loads gr eater than that of a fuel assembly and RCC to trav el (0.5) over Irr adiated f uel in the vessel with the ne ad remov ed?
- d. What count r ate indication r equir es susp ension of fuel (0 5) handling operations?
l l ***** END OF C AT EGORY 0 7 *****)
Bo__AQ51HISIRAIIVE EEDCEDURESt_CDdQlILDUSt_A'3D_LIdlIAIIDUS
)
QUESTION 8.01 (3.50) f The following concer n " Removing Equipment from Ser vice f or Maintenance, procedure GP 3250.
hig h temperature? (10)
- a. When is a system considered high pressur e,
- b. What is the required order of iso lation of a h igh pr essure (1.0) system pump suction and discharge v alves ?
(0 5) c.
Can a discharge check valve act as a pre ssure barr ie r?
The
- d. Maintenance is to be performed on a hydr ogen s ys tem.
af f ected portion has been pur ged with si x system volumes, isolated, vented and tagged. What addit ional action is (1 0) required before allowing the work to be per f or med?
QUESTION 8.02 (3.00) a.
What are the TWO conditions which allow the " operator at the controls" to leave the Surveillance Area of the Control Room during Mode 1 operation, according t o AO P 6. 01, Control (2.0)
Room Procedure?
b.
Which personnel, by job position / title c an aut horize taking (1 0) the reactor critical?
(***** C ATEGORY 08 CONTINUE D ON NEXT P A GE * * * * * )
~
c PAGE 13 (Ro__A.051HI11RAIIME_EEDGEDUBESt C0bQ111DBSt_ASu_ lib 11AllDUS I *.
QUEST 10h 8.03 (3.50)
- a. What is the MINIMUM number of operable excore channe is indicating AFD outside the target band befor e AFD i s cons id er ed outside its target band by Technical Spec i f i cati on s ? (0.5)
- b. Arsume the plant is operating at full power an d the Axial Flux Difference (AFD) has been ou tside the tar ge t band for the last 5 minutes. What are the TWO ac tions specif ied which you may choose between to meet the Technical (1.0)
Specification requirements? Include time l imi t a ti on s.
- c. Assume that it is 0310 on 05/13/85 and the plant is pr esently at 45% power. Considering the AFD penal ty his tory b elows at what date and time may power be i ncr ease d above 50%7 EXPLAIN.
(Show all work.) Assume no devia tion ou ts ide the ba nd after 0310 on 05/13/85.
TIME WENT GUT TIME BACK DATE OF BAND IN BAND POWER 05/12/85 0310 0318 85 %
05/12/85 1557 1637 65 %
0310 45 % (2 0) 05/13/85 0148 QUESTION 8.04 (2 50)
The following concern Department Instruction No. 3-OPS-3.07 on Valve Operation.
- a. Wnat are THREE r equirements regar ding aa nual s eating ihandwheel closure) of motor operated valves? (1.0)
- b. Explain how manual valves should be checked cl os ed A ND open (1 0) during performance of a valve lineup.
- c. What action uust be perf ormed prior to p lant cooldown f or a backseated valve, WHY is this action necess ary ? (0.5)
(***** C ATEGORY 08 CONTINUED 09 N E X T P A GE * * * * * )
PAGE 14 lid &IAIIDSS
'Ao__ADBIBISIE&IIYE_EEDCEDUEESt_CDSQIIIQUSz_AND_
f e
QUESTION 8.05 (3 00)
- a. List FIVE of the six actions that only the Dir ector of S ta ti on Emergency Operations (DSEO) or the Actin g DSED can authorize, (2.5) as stated in EPIP 40108.
(0.5)
- b. Wher e ar e the call back recorders lo cate d?
QUESTION 8.06 (1 50)
If specific activity of the RCS is >10 uCl/ gr am d ose equi valent I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one cont ir.uous time interval, the plant must be placed in at least hot standby w ith RC S T avg
<500 F. What is the basis f or reducing the RCS te mper atur e to (1.5) less than 500 F7 QUESTION 8.07 (2.003 r
List FOUR of the five Technical Speci fication base s/ reas ons for (2.0) the MINIMUM temper ature f or criticality l i mi t a t i on . \
QUESTION 8.08 (2 50)
The f ollowing concern " Station Bypass / Jumper C ontr of " pr oc edure, ACP-QA-2.068.
- a. If a technical specification change is r equire d and an unreviewed safety question is found to exist, bef or e the instal lation of a jumper can be authorizeds approval from _______ must be (0.5) obtained. (Fill in the blank on your an swer s heet)
- b. t' hat conditi on al lows the Shif t S upervisor to grant exception (0.5)
- o per forming a s econd ver ificati on of a jumpe r inst al l ation?
- c. Who by job position / title must complete and si gn the Assessment (1.0)
Section of the Jumper-lifted l e ad-b y p a ss controf sheet?
- d. Under what conditions can a jumpe r be installed WITHOUT using (0.5) procedure ACP-QA-2 06B?
1
- )
'(***** C ATEGORY 08 CONTINUED ON NEXT PAGE l
PAGE 15 ja__AD518111RAIIME ERDCEDUEElt_CONDIIIDHSt ASD_L15&IAIIQ35 l
QUESTION 8.09 (1.50) l The concentration of the boric acid sclution in th e Refu el ing Wa ter Storage Tank (RWST) shall be verified The once cheper mi 7stds sys amplin edaccordance the RWST with Technical Specification (All 3.5.4. samp les tan en at 1200 hours.)
on the following schedule.
April 1 - - April 8 --- A p r i l 16 --- A p r i l 24 --- April 31
- a. EXPLAIN why or why not surveillance time i nter va l re qu i r ements (0.75) were exceeded on April 16.
- b. EXPLAIN why or why not surveillance time i nter va l re qu i r em en ts (0 75) were exceeded on April 24.
QUESTION 8.10 (2.00)
What action (s) (BOTH operational AND adminis tr at iv e) mus t be taken i f the RCS-PRES SURE-S af ety L imi t is exceeded, in accordance with TS? Consider ALL Modes AND include app licabl e time limits (2.0) in your answer.
(***** END OF CATEGORY 38 *****)
(************* END OF EXA MIN ATION ***************)
ECUATICN SHEET
' Cycle efficiency = (Net work f = :na v = s/t cut)/(Energy in) 2
, = mg s = V,t + 1/2 at
[ = CC A = 14 A=Ae' n KE = 1/2 mv a = (Vf - 13 )/t PE = agn
- = e/t i = en2/tjjg = 0.693/t1/2 Vf = V, + at t1/2"
- U *1/?
n0 2 y,y g As 4 [(t1/2) * (*b)3 aE = 931 sn m=V uAo ,
-!:x Q = mCp at I = I g e~"*
6 = UA A T I=I o 10-*/ M Fwe = Wyah TV1. = 1.3/u sur(t) HVI. = -0.593/u P = Po10 P = Poe*/ '
SCR = S/(1 - K,ff)
SUR = 25.06/T CR x = S/(1 - K ,ffx)
SUR = 25a/t* + (a - o)T CR)(1 - K ,ff)) = CR 2 (I ~ eff2)
T = ( t*/o ) + [(a - o V io] M = 1/(1 - K,ff) = CR)/CR 3 7 = 1/(o - a) M = (1 - K,ff,)/(1 - K,ff))
T = (a - o)/(Io) SDM = ( - K ,ff)/K ,ff t' = 10 secones a = (K,ff-1) A,ff = *eff/K,ff I = 0.1 seconds-I e = [(t*/(T K,ff)] + [i,ff (1 / + IT)]
d Ij ) = I d2gd,2 2 P = (rov)/(3 x 1010) I)dj 22 2 I=N R/hr = (0.5 CE)/d (meters)
R/hr = 6 CE/d2 (feet) ,
Miscellaneous Conversions Water Parmeters 1 gal. = 8.345 lem. I curie = 3.7 x 10 10 eg, 1 kg = 2.21 lbm 1 gja .==7.48 3.78gal.
liters I hp = 2.54 x 10 3 Stu/hr 1 f. i mw = 3.?1 x 100 5tu/hr Density = 62.4 lbqt/ft3 lin = 2.54 ::3 Oensity = 1 gm/c9 *F = 9/5'C + 32 Heat of vaporization = 970 Stu/lem
- C = 5/9 (*F-32)
Heat of fusion = 144 Stu/lem 1 BTU = 778 ft-lbf 1 Atm = 14.7 psi = 29.9 in. Hg.
1 ft. H 2O = 0.4335 lbf/in. 1
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520 - 1.0 1.2 0.2 0.4 0.6 0.8 0.0 FR ACTION O F R ATED THERM AL POWE R (FIG UR E 2.1 1)
REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN l
Mll.L5 TONE 3 ftG5-1
%'_:,INEQR1_QE_HUCLE AE_EQMER_ELABI_ DEER AIIDBa_ ELU1Di z_ AUD PAGE 16
.'.. IHEE50Q1HABICS ANSWERS - MILLSTONE 3 -8 5 /0 5/14-I SA KS E Ns P.
MASTERCOPY ANSWER 5.01 (2.00)
- 1. BUILDUP OF PU240 [0.53 -- Causes an incr ease i n the resonant absorption resulting in a MORE negative react.
per degree temperatur e chan ge [0.53. (1.0)
- 2. CLAD CREEP / PELLET SWELL [0.53 -- Causes an increase in gap conductivity and wi th increasing power t he pel le t ed ge remains cooler at EOL r esul ting in a LESS negativ e FTC [0 53. (1.0)
~3. Fassaou && go. coup _ pe,cwy _
m .
REFERENCE ED */ 3 Millstone RTOC chapter 13s p. RT-13.3 ANSWER 5.02 (1.50)
- 1. Maintain adequate shutdown margin.
- 2. Limit worth of ejected control rod.
- 3. Ensure acceptable core power distributions. [0 5 each] (1.5)
REFERENCE Millstone Technical Specification bases 3/4 1 3.
MASTERCC?Y
1'a__ INEGRI_DE_SUGLEAE_EDMER_ELABI_ DEER AIIDHt_ELU1QS t_ABQ PAGE 17
/* ' 'IMEREODXHABICS ANSWERS -- MILLSTONE 3 -8 5 / 05/14-I S A KS EN, P.
ANSWER 5.03 (3 00)
- n. CR(f) = CR(I) C(1 - KI)/ (1 - Kf)J Reactivity in core (1)= -10s 000 p cm + (-1000 p cm ) = -11s000 pcm Reactivity in core (f)= -11,000 p cm + 56 00 pen = -54 00 pcm SDM = (1 - Kaff)/Keff OR p = (Kef f - 1)/Keff ) Keff =l/(1 p)
Ki = 1/(1 + 0 11) Ki = 0.9009 Kf = 1/(1 + 0 054) Kf = 0.9488 CR(f) = 50 cps (1-0.9009) = 96.7 cps (1.5)
(1-0.9488)
- b. Assume Boron worth = 10 pcm/ ppm K(i) = 0 9489 CR(i) = 96 7 cps Reactivity in core (I) = -5400 pcm + (13 0 p p m x 10 p cm/ ppm)
= -5400 pcm + 1000 pcm = -4400 pcm
= = 0.9579
__ K(f) 1/(1+0.f4)
CR(f) = 96.7 x (1-0.9488) = 96.7 x 1.216 = 117.6 cps (1.5)
(1-0.9579) _ a. 5 M A,',. ' f ^ -4
_..s p --^- & ;L REFERENCE Millstone RTOC, Chapter es pp RT-8.5-ll
S'nJ IMEDRI_DE MUCLEAE_EDMER_ELAtil_DEERAIIDUA hLUIDSz_AHQ PAGE 18
." 'IMEREDRIHABICS ANSWERS -- MILLSTONE 3 -85 / 05/14-I S A KS EN s P.
ANSWER 5.04 (3.00)
- a. Withdrawing control rods tends to make th e coef fi ci en t more pos-itive. [0.5) Withdrawing rods eff ectivel y incr eases core size and less neutron leakage occurs. With less l eak ag e an y tempera-ture change will result in a small er reactivity chang e. C O.5 3 Will accept opposite aff ect if exp lanation of r od i ns er ti on. (1.0)
- b. At higher temperatures the rate of density chan ge bec omes largers increasing the magni tude o f MTCf as e="# - e'---^r -
(1 0)
- c. 1. The change in value of MTC with respec t to t empera ture. (0.5)
- 2. The axial flux shift resulting from better iederation at cooler core inlet temperatures. (Resul t ing i n non-un i f orm fuel burnup). (0.5)
REFERENCE Millstone 3 RTOC, chapter 12s pp RT-12.2-4 ANSWER 5.05 (2.50)
- a. 1. 2750 to 2850 pcm (0.25]
42C Lee
- 2. 4&fLto 9&d'pcm (0.253 ,
(0.5)
- b. 1. Higher fission yleid of Xenon precursor [1.03
- 2. Higher (thermal) absorption cross section f or Xen on C1 03 (2 0)
REFERENCE Millstone 3 RTOCs chapter 16, p. RT-16.2 Curve books Sim form 3209-5 C6
?
Ia_ IMEDRY_QE_SUCLEAE_EDMER_ELABI_DEERAIIDBa_ELUIESz_AUQ
_ PAGE 19
." 'IMEE50QINABICS ANSWERS -- MILLSTONE 3 -8 5 /0 5/14-ISA KS EN, P.
ANSWER 5.06 (3 00)
- a. Power decreases initially due to the boron addi ti on CO.53 the primary to secondary mismatch causes Tave to de cr ease CO.53 ,
the decrease in Tave inserts positive reactivity and restores ;
reactor power to a slightly lower than or the s ame as i n i t i al power CO.53 (possible low pressure trips lo-lo Tave implies low pressure) (1 5)
- b. Tave is determined by the amount o f pump heat C O.53 and the steam dump setting thus it does no t chang e CO.5 J Af te r the initial transient, power decreases at a -1/3 DPM rate to the multiplied source level CO.53 (1 5) 1 REFERENCE WNTC Transient and Accident Analysis, chap te r 3, p . 3.16 ANSWER 5.07 (2.50)
- a. Increase - due to reduction in back pressure f rom other loops.
- b. Decrease - due the backflow in th e 4 th l oop.
- c. Decrease - due to less flow resistance across the co re.
- d. Increase - less flow = less heat removal and n igher ex it temperature.
- e. Decrease - Increased delta T means lower Tc and since S/G temp.
is always slightly < Tc, S/G temper ature is less.
CO.25 for each r espons e; I,0 and Explan.] (2.5)
REFERENCE Transient Analysis, chapter 4, p. 4 17 ANSWER 5.08 (2 00)
- a. Increases NPSH (cavitation) (0.5)
- b. Reduced efficiency (0.5)
- c. 4" Hg = 1.9632 ps l aCO.25 3 Tsat = 125-FC O. 5 3 (-0.25 if table 2 vs table 1 is used) 125-115 = 10-F condensate depress ion C o.2 53 (1.0)
sa._; IEDR1_QE_buCLE AE_ EDMER_ELAtil_QEER AIIh_ ELUIQ1 t_ AdQ PAGE 20
' I R R50015ABICS ANSWERS -- MILLSTONE 3 -8 5 /05/14-I S A KS EN s P.
REFER E NC E GP HT&FF Sect II, Part Bs p. 155-159, 182-133; Sec t. III Part Bs p. 319-320 ANSWER 5.09 (2 00)
- a. OT Delta T uses Thot and Tcold inputs to measure the delta T across the core. Once the core exit reaches saturati on the enthalpy rise can no longer be equated to the delta T across the core and therefore the OT Del ta T tr ip no longer provides adequate protection. (partial credit for discJssion of disadvan-tages of saturation conditions) (1 0)
- b. Prevents exceeding the DNBR limit (0.753 of 1.3 C0.253. (1.0)
REFERENCE Tochni cal Speci fications p. A-8 & 9; and B as es B 2-1.
Fig. 2.1-1 ANSWER 5.10 (2.50)
S team Gener ator Heat Tr ansf er = Q=UA(Tave-Ts tm) C0.51 Q, Us and Tstm remain constants therefore CO.53 Al(Tavel - Tstm) = A2(Tavez - Tstm) [0.53 Givent A2 = 0.75 Al From steam tables: Tsat f or 785 psig =516 de gr e es (0.5 )
Al(570 - 516) = .75Al(Tave2 - 516)
Tave2 = 587.8 (accept 587-588) Co.5) (2.5)
REFERENCE I
GP HTFFs Sec. II, par t 8, chapter 2.
l l
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l
,16IMEORX_QE_SUCLEAE_P.QMER_ELAtil_ DEER AIIDSa. ELul014._AdQ PAGE 21
. IMEREDQXHABICS ANSWERS - MILLSTONE 3 -8 5 / 05/14-IS A KS EN s P.
ANSWER 5.11 (1.00)
Bocause during a C/D the inner wall of the Reactor Vessel experiences a tensile stress [0 53 which inc reases the total stress en the inner wali C0 5]. h ce" N >il'-- Aw =
- e (1.0)
& h ="9 4 p_=w '
A n ;- ? -t m m 2 _'__L ~1 u 1ao*F REFERENCE Tochnical Specifications 3/4.4.9 and Bases.
6a__RL&dI_S11IENS_DESInda CDHIRQLt_AdQ IBSIRudESIAIIDH PAGE 22 ANSWERS -- MILLSTONE 3 -85 /05/14-IS A KS EN s P.
ANSWER 6.01 (3 00)
- a. The normal steam pressure setpoint of 1092 psi g main tains Tavg at ~557 Fs a decrease in the setpoint to 1000 psig would cause the dumps to open and cool Tave to ~550 F wher e the P-12 interlock would close all steam dumps (1ote 0.25 credit given for correct conversion to Tsat ~547 F) (1.0)
- b. Secondary pressure would rise to the setpoint of the secondary atmospheric relief valves [0.53 which wo uld maintain pressure at 1125 psig C0 25] and primary temperature 560 +/-1 F C0.25].- (1.0)
- c. A signal by the Load Rejection controller to.5 3 woul d control primary temperature at "No Load" Tref +2 F devlation (dead band) (559 F) [0 53. (1.0)
REFERENCE Millstone 3 SD Topic 5s Lesson 2, Steam Dump p. 11 -1 9.
ANSWER 6.02 (3.00) %
- a. 1. Isolated hot leg wide r ge temperature mu st be wi thin 5 Deg-F of auctioneered high w de ran ge Thot.
- 2. Isolated cold legylde range tempera ture iust be within 5 Deg-F
, of auctioneered f gh wide range Tcol d.
- 3. Hot leg isol lon valve must be open.
- 4. Bypass i lation valve must be open..
- 5. Suff cient flow through the bypass / sixing line (200 gpm) (2.0)
- b. To event reactivity additions f rom either co ld and/or dilute ter injected into the RCS and thermal shock considerations. (1.0)
REFERENCE Millstone 3, Vol is Topic 1, Lesson is p. 15 -16.
I l
L
, da,__EL&BI.311IE51_DE11 Eda. CQHIRQLa._ANQ_INSIMdEHIALIQH PAGE 23 ANSWERS -- MILLSTONE 3 -85 / 0 5/14-ISA KS E N s P.
ANSWER 6.03 (3.00)
- a. - NO PRESSURE REDUCTION; The Train A PORV only opens on auctioneered Thot that it provides. [0.5]
- Auctioneered Tcold inputs to Tr ain B. [0.jb]
- If the COPS is ARMED the PORV (456) wi l l open OR i f assumed not ARMED then no pressure reduction occur s[1.03 WERf (2 0)
- b. It prevents depressurization of the RCS past the i nt er l ock setpoint (2200 psla) If a pressur e channel sel ected to a PORV falls high. (1.0)
REFERENCE Millstone 3 Vol 4, Topic 6, Lesson 667s p. 12,14-16,pp-8,35spp-9.
ANSWER 6.04 (2.10)
- a. 1. Low lube oil pressure.
r m ' '
i 1" L"' A*/'a" A - a.. cm. m -
- b. The cranking time Ilmit relays time out (7 secs) bef or e the low speed contacts energize the low speed re lay. (0 6)
- c. Operation of the engine shutdown reset. (0.5)
REFERENCE Millstone 3, Vol is Diesel Gene p. 42s50,51.
g+ w 0 sag rua. e a n -l9 LSac -AM hato .3 r Tand +MSupGsc por-Qt SH'vs't.'s.b.
tems s ANSWER 6.05 (2 50)
Centrol rods will automatically move outward [ 0. 51 due to temper ature error and power mismatch adding posit ive reactivit y [0.5 J. With a soall MTCs reactor power will rise rapidly [0.51 c ausing a (C-2) overpower rod stop [0.51 and power overshoot resul ts in a high noutron flux trip [0.51. (2.5)
REFERENCE Millstone 3, Vol. 5, Topic 8, Lesson 4, ICC f ailur e anal ys iss Page 43.
1 f 5
,, 6a#LAMI_111IEBi_D131Gua_GQHIRQLa_&tia_IN SIEu BENIAIIQd PAGE 24
^
ANSWERS -- MILLSTONE 3 -85 /0 5/14-IS A KS EN s P. .
ANSWER 6 06 (2 40)
- a. Raises the limit, because high dT indica tes a higher power. (0 6)
- b. Increases to raise pressurizer level to 100% programs because of the higher Tave. (0.6)
- c. Rods move ins because of the Auct. Tave/ Tref alsmatch. (0.6)
- d. No effects the demand signal i s present (Tave/ Tr ef) but there is no arming signal. (0.6)
REFERENCE Milstone 3, Vol. 4s Topic 6, Lesson 7, Pages 25, 26s Losson 2s Pages 46, 47s RS-3,5s i Lesson 3s Pages 26s 27s RI-21s Vol. 3s Topic 5, Lesson 2s Page 12 ANSWER 6.07 (3.00)
- 1. Backup heaters energize CO.43
- 2. Charging flow to minimum (FCV 121 mi n. o pen po si tion ) (0.63
- 3. Pressurizer level decreases and letdown isolat ion (LCV-460 and orifice valves) [0.73
- 4. Backup and control heaters cutout (0.43
- 5. Reactor trip on high pressurizer level C0 93 (3.0)
REFERENCE Millstone 3, Vol. 5s Topic 8, Lesson 4s Page s 61, 62.
ANSWER 6.08 (3 00) l
- 1. OP Delta-T
- 2. BOTH
- 3. OT Delta-T C1.0 each) (3.0)
,--------,w--------,y---. - . -,- ---y ..--. .----+--.--m--
r-- ----c-r-.r~~--v-- m -%, , , , , , , - , _ _ _ _ m ,,
6a,J ELANI_11SIE51_QE11GL._CQHIRQLa._ANQ_INSIEu2ESI&llQU PAGE 25 ANSWERS -- MILLSTONE 3 -8 5 /0 5/14-IS A K S EN s P.
REFERENCE Mllistone 3, Vol. 3, Topic 6s Lesson 8, Pa ge s 7-14.
ANSWER 6 09 (3 00)
- c. 1. Quench spray pump discharge valve cl oses - RWST low-low-low level.
- 2. Pumps auto stop - RWST empty level. (1.0)
- b. The CAT isolation valves open on CDA C O. 51 a ll ow i ng gravity flow to the suction lines of each pump [ 0. 51. (1.0)
- c. ho aid in the removal
- .-_; c. and g.e-r2 5$ 4(05) g w.ns , a es tw en
=m tieon; z.o,f (e o=d:.-
i neD
- }-M^F^I &; *=:-_ ^ #-'A jn W9
, _.m de Resets and blocks the CDA signal (block signal c lear s when high-3 pressure signal cl ear s s <10 ps i g). (0.5)
REFERENCE Millstone 3 svol 3, Topic 3s Lesson 5s p. 8,10 s 11, 20,23, 2'+j TM=" A E =V;' % " 3 N . L.1. 3
PAGE 26
- .Ia ;EEQCEQuRE1_
- _BDEBALt_ASHQEHALA_EdEEGENC1_AMQ
. RAQ1DLDGICAL_CQUIRDL
-8 5 /0 5/14-IS A KS ens P.
ANSWERS -- MILLSTONE 3 ANSWER 7.01 (3 50)
- a. 1. Terminate the startup by full y inser ting a ll control rods. (1.0)
(0 5)
- b. Energize PZR heaters (to induce spray fl ow).
- c. No, wi th the reactor in the source r ange posit ive re ac tivi ty must not be changed by more than one controlle d me th o d at a time. (0.5)
- d. Rod motion is stopped (every 50 s teps) a nd bank demand position (1.0) is compared to di gital pos ition i ndicati on.
(0.5) in Hot Standby within the next 15 minutes. CpW eM4
- e. Be
- :-f AM&
6 w rv ; % % [C V-)
w- %--
q1-n -
_a _
REFERENCE OP 3202, Pages 4, 7-10.
ANSWER 7.02 (3 00)
- a. 1. Rod bottom lights lit.
- 2. Reactor trip and bypass break ers ope n.
- 3. Olgital rod position indicato rs at zero. (1.0)
- 4. Neutron flux decreasing.
(10)
- b. Trip Bus 32B and 32H load center supply breaksrs.
(0.5)
- c. All turbine stop valves closed.
- d. Af ter adequate shutdown margin is obtained (dJring (0.5) subsequent actions).
REFERENCE E0P 35 FR-S.1, Pages 3, 6.
l
IclERDCEDURE1_=_HQEBAL4_ AANDRd&La_EHERGENGL AND PAGE 27
. 'RADIDLOGICAL_CQUIROL ANSWERS -- MILLSTONE 3 -85 /05/14-IS A KS ens P.
e ANSWER 7.03 (3.50)
- a. To prevent contaminants from the RCP sea l leak of f li ne from being forced back into the RCP seal chamoer. (1.0)
- b. 30 minutes (0 5) c . (1. Only one RCP started at a time) ro.G
- 2. Two successive starts are permitted,provid ed the RCP coasts to a stop between starks.C* 0
- 3. A third start is permi tted af tePTta nd ing idle f or 45 minutes v or af ter running f or 20 iiinutes .I..Q (1.0)
C*.O
- d. To prevent damage to the RCP motor windi ngs. (0 5)
- o. Before RCP (upper or lower) bearing temp er atur es exc ee d 190-F. (0.5)
REFERENCE OP 33010 Page 5.
ANSWER 7 04 (3.50)
- a. 2, 1 then 3 or 4s to provide normal PZR spray. (1.0)
- b. 1. Core exlt TC's (A " v"O
- 2. RCS hot Iea temperatures - W' fw. _f-P *- F # **
(1.0)
- c. Use one PZR PORV. (0.5)
- d. Unexpected I ar ge var I ati ons in PZR Ievel f v2. R.ULMS / I oo7e (0 5)
O. (Auxillarysprayflow is maintained and)c hargin g flow is throttled as necessary.Cr"cvIMI *
(0.5)
REFERENCE EOP 35s ES-0 2 f F-o.L.
i 1
. ~ . - . _ . - - - . . - - - - - , _ - _ - - _ - . . _ - - . ~ - - - - - . - - _ . - - - , _ . _ - - - - - . _ . _ . - - .. .----- -
Z* 810CEDu1ES_=_HQEBA La._AaBQE5 Ata _EBERGEHCL ASQ PAGE 28
.' '--'RAQ1DLDEICAL_CQHIRQL ANSWERS -- MILLSTONE 3 -8 5 /0 5/14-ISA KS EN s P.
ANSWER 7.05 (3 00)
- c. 1. At least one charging or SI pump r un n i n g .
- 2. RCS pressure < 1410 psia (1738 f or a dverse containment). (1.0)
- b. 1. Unexpected increase in S/G narrow range level. j
- 2. High S/G sample radiation.
- 3. High S/G steamline radiation.
- 4. High S/G blowdown line radiation. (1.0)
- c. Containment prassure(> b psia)4 r adi at i on >1000 R/ hr . (1 0)
REFERENCE E0P 35 E-3, Pages 3,4,13; F-0 5p A c s e ic. Ips're. . o ou l v P . 2. t .
Ia_' EEQCEQUEll_=_HQEBALa ASHORBALa._EBERGENCL AHQ PAGE 29'
.' 'RAQ1DLDSICAL_CQHIRDL ANSWERS -- MILLSTONE 3 -8 5 /0 5/14-I S A KS EN, P.
ANSWER 7.06 (3 00)
- a. 1. Control rod bank height below the ro d bank tow-low limit alarm setpoint (with the reactor cri tical) .
- 2. Failure of one or more control rod c luster s to f ully insert following a reactor tr ip or s hutdow n (Ind ic ated by digital rod position indi c ation s ystem.
- 3. Uncontrolled cooldown of the reactor coolant foi lowing a reactor trip or shutdown (T ave dec reasin g in an uncontrolled manner as indicated by two of the l oops low-low Tavg status lights).
- 4. Uncontrolled or unexplained r eactivi ty inc re ase (indicated by abnormal control rod bank inser ti ons in cr easi ng Tave or increasing nuclear power).
- 5. Failure of the Reactor Makeup Cont ro l S yst em to the extent that the makeup system must be bypassed to accomplish boration of the Reactor Coolant Syst em.
[Four required 0.5 each3 (2.0)
- b. 1. START a boric acid transfer pump.
- 2. OPEN the Emergency Soration Supply to char gi ng pump suction.
3.
- Ro.C Veri f y Emergency Boration flow of 35 opm go r grea ter.
([. Increase letdown and charging flow as nece ssary ) (1.0)
REFERENCE AOP 3566, Pages 2 and 3.
ERQCEDURES.=_HDRHAL4_AAMDR5&LA_EBERGEBCI ASD PAGE 30 l' Zag _RAQ1DLOGICAL CDMIRDL ANSWERS -- MILLSTONE 3 -85 / 05/14-IS A KS ens P.
ANSWER 7.07 (3 00)
- a. 1. Very short duration tasks (i.e. exan instio n of a work areas retrieve tools, etc).
- 2. An emergency which threatens personn el or pl ant saf ety. (1 0)
- b. On the ly ter record form (I nc i denta l exposure sh . SM/4--
- c. 1. Approval of the RWP.
- 2. No plant evolutions are planned which cout d chan ge the radiological conditions in the area.
- 3. The plant is not Jeopardized by work indic ated on the RWP.
- 4. To noti f y HP whenever an evol uti ons pl anne d/ taken pl ace p,o that would change radiological condi tions. Li<S4 REFERENCE SHP 4912s Pages 3 and 7.
ANSWER 7.08 (2.50)
- a. Flow may be suspended for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during performance of core alterations i n the vicini ty of the vessel hot legs. (1.0)
- b. To ensure the gamma dose rate at the wat er sur f ace i s within limits (2 5 arem/hr). (0.5)
- o. Shift Supervisor. (0.5)
- d. Excessive or unanticipated count rate mu ltipli cation (i.e. doubling). (0 5)
REFERENCE OP 32108, Pages 5-7.
,, ahAAD51HI11RAIIME_ERDCEDUREst CDHDIIIDH3a._AtID_LIBIIAI1ONS PAGE 31 ANSWERS -- MILLSTONE 3 -85 /05/14-IS A KS EN s P.
4 ANSWER 8 01 (3.50)
- a. > 500 psigs 200-F (1.0)
- b. Olscharge first then suction. (1.0)
- c. No (0.5) de Chemistry samples the immediate area and insid e clos ed volumes for explosive concentrati on of hydrogen. (1.0)
REFERENCE OP 3250, Pages 4-6.
ANSWER 8.02 (3.00)
- a. 1. To verify the receipt of an annunciator al arm.
- 2. To initiate corrective actions resul ting f rom an emergency. (2.0)
- b. Station Superintandent, Unit Superintend ent an d Oper ations
, Supervisor. (1 0)
REFERENCE ACP 6 01s Pages 3, 6s 7J OP 3202 4
, ah__AndlH111RAI1XE_ERDCEDuREla_COBQIIIQHSz_A3D_LidII&IIDMS PAGE 32 :
ANSWERS -- MILLSTONE 3 -85 / 0 5/14-I S A KS E N s P.
ANSWER 8 03 (3.50)
- 2 c o.s)
- b. Within 15 (or next 10) minutes CO.23 eit her.
- 1. Restore the indicated AFD to within the ta rget cand CO.4]s or
- 2. Reduce the thermal power to <90% of r ated th er ma l power. CO.43 (1 0)
- c. Accumulated penal ty over the past 24 hou rs is 89 min ut es . C1.0)
The penalty will be reduced to 60 minute s at 1618 mi nu tes on 05/13/85 and then power may be increased. C 1.0 3 (2.0) 85% 0318-0310 = 8 C O.25 3 65% 1637-1557 = 40 C o.25 J 45% 0310-0148 -
82/2 = 41 CO.5]
89 min.i total penalty 05/13/85, from 1557; 81 min l e f t 21 m i n -> 1618 05/13/85 REFERENCE TS; 3.2 1 ANSWER 8 04 (2.50)
- a. 1. Shif t Supervi sor approval.
- 2. Notification to Operations Superviso r/ Duty O f f ic er
- 3. Identification on Shif t Turnover Sheet.
- 4. Cheater bars must not be used. C3 requir eds 0.33 each] (1.0)
- b. Closed - by going to close until seated. C o.43 Opened - by parti ally closings opening until seated then closing one-quarter turn. CO.63 (1.0)
- c. Va lve taken of f i ts backseat to prevent undue stress es '
to the valve. (0.5)
REFERENCE DI-3-OPS-3.07, Pages 3s 4s 6.
Aa;;A051HISIR AIIM E_ EEQ CEDURES4_CDNQIIID NS t_ AN D_LIMIIAIIDM S PAGE 33 ANSWERS -- MILLSTONE 3
-85 /05/14-ISA KS EN s P.
ANSWER 8.05 (3.00)
- a. 1. Changing incident classification and postu re cod e level.
- 2. Recommending protective actions f or of f sit e author ities.
- 3. Ordering assembly or evacuation.
- 4. Authorizing emergency reentry into r adiolo gi cal areas for repairs or . search and rescue. j
- 5. Authorizing r adiological exposures i n exce ss of NNECo or 10 CFR 20 exposure limits.
- 6. Authorizing contaminated personnel to leave the station. (5 requireds 0.5 eachJ (2.5)
- b. Unit 1 Control Room. (0.5)
j ANSWER 8.06 (1 50) c ,.s3 If a tube rupture were to occursga release will be p r e ve n t e d -! ^. " ;"
since the S/G atmospheric relief setpoint will be above the
- ocrresponding saturation pressure for 500 F..C1.03 (1.5) f REFERENCE Toch. Spec. 3/4.4.8 and Bases.
ANSWER 8.07 (2.00)
- 1. MTC in analyzed r ange.
- 2. Protective instrumentation within normal opera ting r ange.
- 3. P-12 Interlock above its setpoint.
! 4. PZR is capable of operable status with a steam bubbl e.
- 5. Reactor vessel above minimum RT t empe r a ture .
NDT ,
[4 requireds 0.5 each] (2.0) l REFERENCE Toch. Spec., Pages 8 3/4 1-2.
--r-, ---- ,--,.-,,,-,n -
, - , , - -,,--,,_,_,,,,,,.,----v, --
,-----,,-,,.,-~_-,,,.--m ,-- .e, -e n- me ---------.,,-,--ny -
,,$4_*.AD51HIIIRAIIEE_EBOCEDURElt_CDDEIIIDHSz_A1DLIdII&IIQH1 PAGE 34 o
ANSWERS -- MILLSTONE 3 -85 / 05/14-IS A KS ens P.
ANSWER' 8 08 (2.50)
- c. NRC (0.5)
- b. If the second verification would result in signi ficant radiation exposure. (0.5) ,
- d. If identified and controlled in another approved procedure. (0 5)
REFERENCE ACP-QA-2.06Bs Pages 6, 8, los 12.
ANSWER 8.09 (1.50)
- a. Interval requirement not exceeded CO.253. Eight days does not exceed 1.25 times the specified interval C O. 51. (0.75)
- b. Interval requirement exceeded Co.253. The las t 3 consecutive intervals exceed 3.25 times the specified i n te rv al C O. 51. (0.75)
REFERENCE Toch. Spec.s Page 3/4 0-2.
ANSWER 8.10 (2.00)
Modes 162-- Be in HSB with pressure within limits in one hour. (0 6)
Modes 3,4,5-- Reduce pressure to within l imi t in 5 minutes. (0 9) i All Modes-- Notify the NRC Operations Center i mmed i a tely (within !
one hour). (0.5) j l
REFERENCE Toch. Spec., Pages 2-1s 6-16.
i l
l l