ML20137K394
| ML20137K394 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/15/1986 |
| From: | Cooley R, Mccrory S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20137K373 | List: |
| References | |
| 50-382-OL-86-01, 50-382-OL-86-1, NUDOCS 8601240051 | |
| Download: ML20137K394 (95) | |
Text
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W3SES EXAMINATION REPORT Number: 50-382/0L-86-01 Docket No: 50-382 License No.: NPF-38 Licensee: Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Examinations administered at Waterford 3 Steam Electric Station f
Chief Examiner: i s / /f 5([
'S M VNcCrefn E'xaminer Bat (
/6/fb Approved by: '
r R. A. Cooley, SectOn Chief Date Sumary Examinations conducted on October 16, 1985.
Written and oral examinations were administered to ten (10) Senior Reactor Operators and twelve (12) Reactor Operators. Three (3) Senior Reactor Operators and six (6) Reactor Operators passed these examinations.
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W3SES EXAMINATION REPORT No. 50-382/0L-86-01 1
Report Details
- 1. Examination Results 4
SR0 Candidates R0 Candidates Total Pass Fail % Total Pass Fail %
10 3 7 30 12 6 6 50
- 2. Examiners l S.L. McCrory, Chief Examiner, NRC J. Pellet, NRC D. Graves, NRC a
J. Whittemore, NRC J. Upton, PNL
- 3. Examination Report l This Examination Report is composed of the sections listed below.
3 A. Examination Review Comment kesolution B. Exit Meeting Minutes !
C. Generic Comments D. W3SES Examination Key (SR0/R0 Questions and Answers)
Performance results for individual candidates are not included in this report because, as noted in the transmittal letter attached, examination reports are placed in NRC's Public Document Room as a matter of course.
A. Examination Review Meeting Comment Resolution In general, editorial comments or changes made during the examination, the examination review, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made as a result of the facility examination review. The modifications discussed below are included in the master examination key which is provided elsewhere in this report as are all other changes mentioned above but not discussed herein.
i
W3SES EXAMIGTION REPORT No. 50-382/0L-85-01 COMENTS (1) 1.3 B/ The answer key substitues a "t" for lamda bar in the 5.6 B reactor period equation found c, the equation sheet provided to the candidate. The equation on the equation sheet should be accepted as correct.
Resp. ACCEPT.
The actual value for 1* for W3SES is 3.048 x 10-5, A range of 10-5 to 10-4 should be acceptable.
Re *,p . ACCEPT.
(2) 1.4 D Accept alternate explanation if SUR is used cnd described correctly.
Resp. ACCEPT.
(3) 1.5 " Intrinsic source neutrons" should be accepted as an alterr. ate for spon'aneous t and cosmic fissions.
Resp. ACCEPT.
(4) 1.6 B Key should read " boron reduction over core age reduces competition for neutron flux and neutron flux increases slightly so XE-eq is higher".
Resp. ACCEPT.
(5) 1.7 B " Moderator Temperature Coefficient or Isothermal (Total) Temperature Coefficient" should be accepted in lieu of "heatup coefficient".
Resp. ACCEPT.
(6) 1.10/ Answer key should read: " Fuel should be loaded 5.7 toward the detector."
Resp. ACCEPT.
(7) 1.11/ C & D are misslabeled on The answer key.
5.4 Resp. ACCEPT.
(8) 1.12/ Alternate methods should be accepted, such as:
5.5 Q = M x dh Therefore dt = M x dh dt Q Resp. ACCEPT. For full credit the candidate trust indicate that he/she realizes the saturation value for h for 1120F water is a close approximation to the actual subcooled enthalpy.
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 (8) cont. The relation 3.41 x 106 BTU /hr = 1 MW from the equation sheet should be accepted as an alternate to assumption E.
Resp. ACCEPT.
A range of 0.1 to 1.0% rated thermal power should be accepted for the decay heat load, assumption B.
Resp. REJECT. This range is too large to be truly representative of actual conditions. Additionally, this value is part of the specific knowledge being tested. ,
(9) 2.1 A/ Separate " chemistry and boron concentration" into 6.2 A two possible reasons.
Resp. REJECT. Boron concentration is a chemical analysis and the one of principle concern in this situation.
Any reference to chemistry and/or boron concentration will be accepted as only one correct reason.
(10) 2.2 A/ Items A.5 and A.7 in the answer should read "EFAS-1 6.3 A and EFAS-2" respectively.
Resp. ACCEPT.
" Loss of Power" (Voltage) should also be added to the list of actuation signals.
Resp. ACCEPT.
The supplied list of individual systems should be accepted as an alternate correct answer because of the question wording.
Resp. REJECT. The candidates were clearly told during the examination to interpret the question as asking for actuation signals both verbally and written on the announcement board.
(11)2.3/ Accept "LT 15% turbine load" as an alternate for 6.4 "150-200 MWe".
Resp. ACCEPT.
Change "170 MWe" in the second sentence to "that power" to remove the double jeapordy condition.
Resp. ACCEPT.
(12) 2.4 D The key should be changed to " motor-operated" due to station modification DCN-MP-853.
Resp. ACCEPT.
4 i
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 2.4 E Answer should be changed to " fail-as-is" due to DCN-W -853.
Resp. ACEPT.
(13) 3.1 A/ The key should indicate both the descriptive name 6.6 A and the alpha-numeric designation of the panels as alternate correct answers. Designations provided.
Resp. ACEPT.
(14) 3.3 8 The panel listed is located on the CEDMCS local
, panels on the +21 foot elevation in the "B"
- switchgear room. This should be considered as an
, alternate correct answer.
Resp. ACEPT.
- Resp. ACEPT.
(16) 3.6 A The key s:.ould accept "No effect" if the candiaate goes on to explain that 2/4 CPC channels are required to get a pretrip and CWP.
2 Resp. ACCEPT.
(17)3.7
~
' RWST should read RWSP to be consistent with W3SES terminology.
j Resp. ACEPT.
(18) 3.8 B/ " Differential Protection (Current)" is also a 6.9 B correct answer.
Resp. ACEPT.
ll 4
1 (19)3.9A The key should accept Reed Switch or RSPT and Computer or Pulse Counter.
j Resp. ACEPT.
i i
B The actual setpoints are 100"/50" to ensure the 60" overlap required by T.S. is met. ,
j Resp. ACEPT. The key was changed to 100"/50".
(20) 4.4/ Item 10 should read "LE 1621 psia" vice "LT"
~
7.2 Item 16 should include " steam generator pressure is LE 764 psia" as an alternate input to MSIS.
Resp. ACEPT both items.
I (21)4.5/ Items 2, 4, and 5 should accept " Excess Steam 7.3 Demand" as an alternate to " Secondary Break".
Resp. ACEPT.
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 (22)4.7/ Since the question tests multiple concepts, partial 7.11 credit should be allowed for proper calculation if wrong radiation level is assumed.
Resp. ACCEPT. This standard policy.
(23)4.9/ Item 4 should accept Core Exit Thermocouples (CETs) 7.5 as well as " Core". Item S should read " Emergency" vice " Aux".
Resp. ACCEPT.
(24) 4.12/ Item C should be " Emergency" vice " Aux".
7.4 Resp. ACCEPT.
(25) 5.9 A The Key should accept calculations which express and explain the concept as an alternate method providing .
reasonable assumptions and calculations are made showing a slightly positive SUR.
Resp. ACCEPT.
B The power defect curve is not exactly linear over the entire range but can be considered so for a 10%
increment. The key should change "from 1-100%" to "with reactor power". -
Resp. ACEPT.
(26) 5.10 Add "7. Flux redistribution - as core ages, flux shifts to the outer regions of the core varying CEA worth."
Resp. ACCEPT.
(27) 8.6 Since the rod does not exceed the misalignment limits in the T.S. LCO, it should be considered OPERABLE.
Resp. ACCEPT.
(28) 8.7 Within the.last 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, the CEA tripped and was withdrawn to 130". There is no indication that it is "imovable as a result of excessive friction or mechanical interference or known to be untrippable."
Therefore, the correct T.S. should be 3.1.3.1.f.
, Resp. REJECT. The Senior Operator is being asked to make l a judgement based on partial information. Just
- I because the CEA tripped 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago does not rule out the possibility of mechanical fouling. When a judgement is required with less than complete information, the most conservative approach must be ,
taken until additional information is available. '
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 (29) 8.9 Item E should be N0 since the EAL requires S/G tube leakage above 10 gpm and an " Alert" level on the MS line monitor for an Alert classification.
Resp. ACCEPT.
(30) Gen. Questions 8.5 through 8.8 involved using Technical Specifications in varying situations of CEA malfunction. Nine of twerdy-two points were devoted to the knowledge and ability to interpret and apply one TS. This overemphasizes one specification knowledge area.
Resp. Not all of the point value was assigned to just TS usage and interpretation. Some questions asked for procedural information and others for system related information. The fact that the quastions related to only one basic TS is inconsequential since the candidates were given a copy of the TS necessary to fully answer the questions. Thus, the candidates were not required to demonstrate any amount of recall or memorization of TS requirements or limits.
The line of questioning was directed toward determining the evaluative and decision making skills of Senior Operators when forced to make a decision with incomplete information and then modifing that decision as more information became available. One or two simple questions is insufficient to make this kind of determination.
Reducing the point value and asking questions on more TS areas puts an unfair burden on the candidate when considering the time limits of the examination.
B. Exit Meeting Summary At the conclusion of the examination period, examiners met with representatives of the plant staff to discuss the results of the examinations. The following personnel were present for the exit interviews:
First Week NRC UTILITY C McCrory D. Packer J. Pellet S. Alleman D. Graves C. Toth J. McGaha N. Carns D. Clark R. Ceddrek
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 NRC reported that all operating examinations were clear passes and that there were no generic areas of weakness observed during these examinations.
Second Week NRC UTILITY I[ Whittemore R. Barkhurst D. Packer C. Toth D. Clark NRC reported that all operating examinations were clear passed and that there were no significant generic areas of weakness observed during these examination.
C. Generic Ccmments There was a noticeable oecrease in written examination scores compared to the two previous examinations admininstered between January 1984 and January 1985. The table below shows a written examination performance breakdown for the last three examinations.
REACTOR OPERATORS Date No. Category Candidates 1 2 3 4 Total 01/24/84 5 87.04 84.46 89.44 80.72 85.42 10/16/85 12 73.26 75.77 76.75 93.86 79.91 (2) (2) (6)
SENIOR REACTOR OPERATORS Date No. Category Candidates 5 6 7 8 Total 01/24/84 8 87.58 84.25 81.73 87.18 85.16 (1) (1) 06/26/84 5 90.68 77.6 87.88 90.4 86.66 10/16/85 10 89.62 69.81 91.24 76.56 81.81 (5) (2) (7)
W3SES EXAMINATION REPORT No. 50-382/0L-86-01 The values shown are average scores for each category of the written examination and an average total score. The numbers in parentheses indicate the number of failures on a specific examination by category and overall. Where the overall number of failures is greater than the sum of the category failures it indicates that some candidates scored less than 80% overall but did not fail any one category.
While there has been a commendable increase in scores on Categories 4 and 7 (Plant Procedures), it has been more than off-set by the declining preformance for Senior Operators in Categories 6 and 8 (Plant Systems, Instrumentation and Control and Admin. Procedures, Conditions, and Limitations) and for Reactor Operators in Categories 1-3 (Reactor Theory, Plant Systems, Instrumentation and Control). A review of these three examinations did not find any of them*to be significantly ;
different in scope, content, or length. The Category 8 ;
questions 8.5 - 8.8 of this examination were the only departure fron previous question format. Senior Operator performance on those questions was generally good.
This information leads NRC to conclude that problems may exist in the W3SES training program. NRC suggests that the W3SES training program be closely evaluated by licensee staff personnel to identify the principle factors contributing to the decline in examination performance over the past year.
D. W3SES EXAMINATION KEY Date Administered: 10/16/85 -
i l
Exam Type: Senior Reactor Operator and Reactor Operator !
U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: WATERFORD 3 Reactor Type: CE - PWR Date Administered: 10/15/85 Examiner: S.L. McCrory Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side only. Staple question sheets on top of 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 Candidate's Category Value Total Score Value Category 25.0 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 25.0 25 2. Plant Design Including Safety and Emergency Systems 26.0 25 ,,_
- 3. Instruments and Controls 25.0 25 4. Procedures - Normal, Abnormal, Emergency, and Radiological Control 101 TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature l
I
, 1. THEORY OF NUCLEAR POWER PLANT OPERATIONS, FLUIDS, AND THERMODYNAMICS 1.1 TRUE or FALSE? No explanation required. (2.0)
A. As condenser vacuum is increased (absolute pressure decreased), more energy can be extracted from the steam.
B. The main condenser uses the conduction mode of heat transfer to reject heat to the circulating water system.
C. Increasing condensate depression (subcooling) will increase overall plant efficiency.
D. Decreasing condensate depression (subcooling) will decrease ,
condenser vacuum.
ANS:
A. TRUE B. TRUE C. FALSE D. FALSE KEY:
HTTRANS FLUID REF:
BASIC FLUID MECHANICS AND HEAT TRANSFER VAL:
0.5 pt each e
1.2 What is the difference in CAVITATION and GAS BINDING in a centrifugal pump? (2.0)
ANS:
Gas binding occurs when a pump is filled with a gas, such as air, so that the pump cannot pump the fluid desired.
2 Cavitation occurs when inadequate NPSH is available so voiding or boiling of the pumped fluid occurs in the pump suction.
KEY:
i FLUID 4
REF:
BASIC FLUID MECHANICS VAL:
i 1 pt each
]
4 I
4 I
1 I
- - - - - - . -, , r - - , - . p - -. - , , - , , -, - . - ., ,. ,, , , . - - . , .. , , , - . . - - .. . . - , - - . - -
1.3 A. What is the minimum reactivity that must be added to a critical reactor for it to be prompt critical? (1.0)
B. How much (by what factor) would power increase in one second at Waterford 3 if it were prompt critical? (2.0)
ANS:
A. p (reactivity) GE beta effective (beta value = 0.005-0.007)
- 8. T = 1*/p + (B-p)/tp (0.5)
So for prompt critical neglect the delayed term so that T = 1*/p (.25) 1* = 10 10-4 sec (.25) p = 0.005 - 0.007 (.25)
T = 1*/p = .0014 - 0.02 pec (.25)
P/Po = et/T - e(50 - 700)/1 sec (0.5)
KEY:
RXTH CORE 0PS REF:
BASIC REACTOR THEORY VAL:
1 pt for A, and as indicated for B.
1.4 A. True or False? After a reactor trip, the reactor will reach a stable negative startup rate of about 0.33 dpm (80 sec period). (0.5)
B. How does the change in Beta-effective over core life affect the STABLE reactor period after a reactor trip? (0.5)
C. How does Beta-effective change over core life? (0.5)
D. How does the change in Beta-effective over core life affect the TRANSIENT reactor period after a reactor trip (before reaching a stable period)? (0.5)
ANS:
A. TRUE B. NONE C. Betae ff gets smaller D. Transient period is shorter (due to faster response with a smaller Beta). Accept discussion of SUR if SUR is said to be larger at E0L.
KEY:
RXTH CORE 0PS REF:
BASIC REACTOR THE0RY VAL:
0.5 each 1
1.5 A. Explain how neutron production and indicated count rate l would change if the neutron sources were removed from the i reactor while it was subcritical (Keff less than 1). (2.0)
B. Explain how long it would take to reach a steady-state count rate when Keff is increased from 0.990 to 0.999 if it took one minute to achieve a steady-state count rate when Ke f was increased from 0.90 to 0.99. 1.0)
ANS:
A. The count rate would decrease to a small value since the 1
reaction is not self-sustaining (1.0). Neutron production would not go to zero since spontaneous and cosmis fissions still occur (intrinsic sources), but the indicated count rate could be 0 due to instrument limitations (1.0).
B. Longer (0.7) - 10 minutes OR 10 times as long (0.3).
KEY:
RXTH NEUT REF:
BASIC REACTOR THEORY -
VAL:
As indicated in the answer.
4 9
1.6 A. HOW does equilibrium Xenon reactivity (XE-eg) at hot full power change as a function of core age (EFPD)? (0.5)
- 8. WHY does Xe-eq change as a function of core age? (1.5)
ANS:
i A. Xe-eq gets larger as a function of core age.
B. Boron reduction over core age reduces competition for neutron flux (0.75) and flux increases as a function of core age (0.75).
4 KEY:
RXTH POISDNS REF:
BASIC REACTOR THEORY VAL:
As indicated. ,
c
1.7 A. True or False? The Waterford 3 reactor is ALWAYS operated with an undermoderated core. (0,5)
B. What observable plant behavior supports your answer to part A?
(1.0)
ANS:
A. TRUE B. The temperature coefficient is always negative (0.5) during any plant condition where operation is permitted which indicates that the core is always undermiderated (0.5).
ACCEPT CONCEPT.
KEY:
CORE 0PS NC REF:
W3SES PLANT DATA BOOK, TS 3.1.1.3 VAL:
As indicated l
l 3
1.8 How and why does moderator temperature coefficient change with core age? (1.5)
ANS:
MTC becomes more negative as the core ages (0.5) because with a lower boron concentration (0.5) an incremental change in temperature removes less boron from the core (0.5).
KEY:
NC RXTH POISONS REF:
BASIC REACTOR THEORY VAL:
As indicated.
1.9 Explain how and why overall plant efficiency changes as power is increased from 10% to 100% of rated power (Efficiency = net MW electric / gross MW thermal). (2.0)
ANS:
Overall efficiency increases with increased power because there is more feedwater heating and house loads do not increase linearly with increasing power output.
KEY:
HTTRANS REF:
BASIC HEAT TRANSFER AND THERMODYNAMIC THE0RY VAL:
0.5 pt for increcse, 0.75 pt ea for fw heat and house load l
l l
/ 4 T 1.10 When loading fuel into the core, should fuel be loaded toward the
- detector nr away from it? EXPLAIN (1.0)
- ,
, ANS:
Fuel should be loaded toward the detector (0.33) so that the 1/M plot conservatively predicts critic.ality (0.67).
i KEY: J.
RXTH CORE 0PS i 4
t, i REF: ,
BASIC REACTOR THEORY VAL: ,
As indicated, i
\
w
\
i 2
1.11 TRUE or FALSE? No explanation required. (2.0)
A. The operator can increase the heat removal reat from the RCS by reducing steam pressure.
B. A LOCA with no RCP's running can result in more inventory loss than a LOCA with RCP's running.
C. A total and prolonged loss of feedwater can lead to a loss of RCS liquid inventory.
D. The primary concern when fuel clad temperature reaches 14000F is the production of hydrogen.
ANS:
A. TRUE B. FALSE C. TRUE
- D. FALSE i
KEY:
- FLUID HTTRANS REAC i REF
f BASIC REACTOR THEORY VAL:
0.5 pt each i
]
I J
e 7 g , - , e ,- - ,=g
1.12 Calculate the time required for reactor vessel tulk water temperature to reach 2120F for the conditions below. STATE ALL f
ASSUMPTIONS AND SHOW ALL WORK FOR FULL CREDIT. (3.0)
A. Thereactorhasbeenshutdownfdr100hoursaftera250 day run at 1004.
B. ALL means of removing heat from the vessel are lost.
C. No circulation to the primary loops occurs.
D. Reactor vessel water is initially at ll20F and well mixed.
E. The reactor vessed head is de-tensioned but still sealed.
ANS:
ASSUMPTIONS ~
A. Vessel water volume = 3000 - 5000 cu. ft. (0.5 B. Decay heat load = 0.1 - 0.5% rated thermal power 0.5 C. Rated thermal power = 3350 - 3450 MW 0.5 D. Water density = 59.8 - 61.8 lbm/cu.ft. .25)
E. 57,000 Btu / min = 1 MW (3.41x106 Btu /hr) (.25)
F. 1 Btu will raise 1 lbm water 10F OR the enthalpy of subcooled water is approximately equal to that of saturated water at the same temperature. (.25)
SOLUTION G. Water Mass = AxD = 209,300 - 309,000 lbm (0.1)
H. Heat Load = BxCxE = 16 - 35 MW = 0.9 - 2x106 Btu / min (0.1)
- I. Heat Required = FxGx(dT=1000) = 21 - 31x106 Btu (0.1)
J. Time Required = I/H = 10 - 40 min = 1/6 - 2/3 hours (.45)
OR Time = Gx(dh=100) = 10 - 40 min = 1/6 - 2/3 hr (.55)
H KEY:
HTTRANS REF: :
BASIC CE REACTOR DESIGN, STEAM TABLES, BASIC HT&T VAL:
as indicated in the answer.
- If the' enthalpy method is used the point value of I is incorporated into the alternate J solution.
L
. END OF CATEGORY.1
+
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 2.1 A. What are two reasons for maintaining a small continuous flow through the pre'ssurizer spray lines? (1.0)
B. Where do the normal and auxiliary spray flows come from?
(1.0)
ANS:
A. Reduces thermal shock in the spray line.
Keeps the chemistry / boron concentration of the pressurizer close to that of the rest of the RCS.
B. Normal: The discharge of both loop 1 RCP's Auxiliary: Charging pump discharge KEY:
PZR PATH RCS REF:
A. 0.5 each '
B. 0.5 each l
l
2.2 A. What are the seven systems / subsystems actuated by the Engineered Safety Features Actuation System (ESFAS)? (1.5)
- 8. What are the only two hypasses applicable to the ESFAS?
Briefly describe what each bypass accomplishes. (2.0)
ANS: (ANY 7)
A. 1. SIAS
- 2. CIAS 4 3. CSAS
- 4. MSIS
- 5. RAS
- 6. EFAS-1
- 7. EFAS-2
- 8. Loss of Power (added after review)
B. Pressurizerpressurebypass(0.5): Disables pressurizer pressure reactor trip (0.25), CIAS (0.25), and SIAS (0.25)
Trip channel bypass (0.5): Allows only one channel for any type of trip to be bypassed at one time (0.25).
KEY:
J ESF CNTRL t-EF:
W3SES SD - PPS, pg 1, 2 & fig. 122 VAL:
A. 0.25 pt ea for 1-5, 0.125 pt ea for 6 & 7 B. as indicated Note: During the examination all candidates were told to interpret
" systems / subsystems" as " actuation signals".
i H
i
2.3 Describe how Stator Coil Water System (SCW) differential pressure (flow) and conductivity can affect main trubine automatic control and operation. Include parameter values as applicable. (1.5) j ANS:
Five seconds after loss of flow, a turbine runback is initiated to reduce power to less than 15% or 170 MWE (accept 150-200)
- (0.5). If that power is not reached within 45 seconds, the turbine trips (0.5). If loads are reduced !n time, the turbine will then trip if SCW conductivity reaches 1.5 umho/cm with a SCW Lo-Lo flow (0.5).
KEY:
+
MNTURB DESGN CNTRL MNGEN REF:
W3SES SD - SCW, pg 43a-19 VAL:
As indicated i
l i
I l
l l
2.4 A. What are the normal and emergency backup sources of water for the Emergency Feedwater System? (1.0)
B. Is the changeover from the normal to the backup source accomplished manually or automatically? (0.5)
C. The emergency Feedwater pump turbine is equipped with redundant overspeed trips. State whether the overspeed trips reset automatically or must be manually reset. (1.0)
D. What is the motive force for the Emergency Feedwater Pump
- turbine steam line shutoff valves (MS 401 A&B)? (0.5)
E. How do the above valves fail on loss of operating power?
(0.5)
ANS:
A. Normal - condensate storage pool Backup - ACCW wet tower basin B. Manually +
l C. Electrical overspeed - auto reset Mechanical overspeed - manual reset D. Motor-operated E. Fail as is (0.5) on loss of power KEY:
AFW PATH CNTRL REF:
W3SES SD - EFW, pgs 3, 5, 8 VAL:
0.5 each
__ _ __._4.-_.
, . - . , - _ . , , _y.,. _,., .-r_ y_
i l
2.5 Describe the flow path and function of each major in-line component in the Airborne Radioactivity Removal System (ARRS).
(2.0)
ANS:
Air is drawn from the containment atmosphere through a roughing filter or prefilter which removes the larger particles drawn through it (0.5). Air then passes through the HEPA filter which removes most of the remaining fine particles (0,5). Finally, the air passes through the HECA filters to remove Iodine (0.5). An exhaust fan then discharges the air back into the containment atmosphere (0.5).
KEY:
HVAC CNTMT PATH REF:
W3SES SD - CCVS, pg 17 17-6 VAL:
As indicated e
f
. , . -e , -~ - -- - -.e -
2.6 A. What are the 4 major components contained in a typical Static Uninterruptable Power Supply (SUPS)? (2.0)
B. Describe the major difference between a Safety and Non-Safety related SUPS. (1.0)
C. Describe the inputs available to a Safety Related Control and Instrumentation SUPS. (1.5)
ANS:
A. Rectifier Inverter Manual Bypass Switch OR Static Transfer Switch Power Distribution Panel B. A static transfer switch is provided on the Non-Safety SUPS which will auto transfer to the bypass supply when it detects abnormal inverter output.
C. 125 VDC to inverter 480 VAC to rectifier 120 VAC to manual bypass switch KEY:
ELEDST DESGN REF:
W3SES SD - 59, pgs 2 - 4, and fig. 59-3 VAL:
0.5 each in A & C 1 pt for B
~
l
2.7 A. In the event of a circulating water (CW) pipe rupture in the plant area, what DESIGN FEATURE prevents flow in the CW discharge piping from reversing and flowing from the river into the plant area and what activates this design feature?
(1.0)
B. Describe the sequence of events that occurs in the CW system automatically upon placing athe first CW pump switch to START. (1.0)
C. When can the second CW pump be started? (0.5)
ANS:
A. Vacuum breaker valves located on the CW return piping (0.5)
Manually operated (0.5)
B. The pump's discharge valve will open to 20% (0.5). Once the valve is at 20%, the CW pump breaker will close (0.5).
C. 100 seconds after the first CW pump's discharge valve is full open (0.5).
KEY:
CIRC DESGN CNTRL REF:
W3SES SD - CW, pgs 11, 12, 21 VAL:
As indicated
2.8 A. Describe the basic operation (flow path) of the control room HVAC for the High Radiation configuration. (1.5)
B. Where and why are gravity dampers used in the control room ventilation system? (1.0)
C. What are 5 of the 6 component parts that comprise a control room emergency filtration unit. Ignore dampers. (1.0)
ANS:
A. Normal outside air intake closes (0.5). The system shifts to full recirculation (0.5). Both emergency filtration unitsstart(0.5).
B. Usually on the discharge side of the fans to close and prevent reverse flow through idle fans.
C. (ANYFIVE)
- 1. Electric heating coil
- 2. Medium efficiency filter
- 3. HEPA pre-filter
- 4. Charcoal absorber
- 5. HEPA after filter
- 6. Centrifugal fan KEY:
HVAC PATH DESGN REF:
W3SES SD - 21, pgs 6, 7,14 VAL:
A. as indicated B. 0.5 ea for location and function C. 0.2 each
- 2. 9 Match each of the following areas (A-D) with the type of automatic fire suppression system present in that area. (2.0)
AREA SUPPRESSION SYSTEM A. Computer Room 1. Pre-action sprinkler B. Turbine generator 2. Deluge sprinkler bearings 3. Halon C. Fuel oil storage 4. Wet pipe sprinkler
- tanks (yard) 5. Multi-cycle sprinkler l D. RCP's 6. Foam water system
, ANS:
i A. 3 j B. 1 i C. 6 D. 5 KEY:
FIRE DESGN RET:
W3SES SD - FPS, pgs 65, 66 VAL:
0.5 each 6
END OF CATEGORY 2 i
i a
l
- 3. INSTRUMENTS AND CONTROLS 3.1 A. Where can the operator perform the setpoint reset function for the Low Pressurizer Pressure and Steam Generator Low Pressure reactor trips? (1.5)
B. Describe and explain what would occur if the operator repeatedly pushed the button to reset tne Low Pressurizer Pressure trip during normal operation. (2.0)
ANS:
A. Bistable control panel (or CP-10, PPS Panels)
Remote operator's module (or CP-7)
Remoteshutdownpanel(orLCP-43)
B. Nothing abnormal should occur (0.25). An interlock prohibits reset of the trip for 10 seconds after reset (0.5). The reset functions to lower the setpoint 400 psi below existing pressure (0.5). From a normal operating pressure of 2250 psi, the setpoint would be reduced to approximately 1850 psi, which is near the normal setpoint (0.25). Subsequent attempts to change setpoint will not cause a change unless plant pressure changes (0.5).
KEY:
RPS PZR CNTRL REF:
W3SES SD - RPS, pgs 31-33 VAL:
A. 0.5 pt each B & C as indicated
3.2 Explain how the SBCS " Quick Opening" feature can be affected by a reactor trip. The explanation should include why the system reacts as it does, and parameters monitored that determine how the system reacts. (2.0) i ANS:
The " Quick Opening" feature can be blocked on a reactor trip (0.5). The block will occur at lower power (LT 58%) as measured by RCS Tave (0.5). Block signal generation is supplied by CEDMCS UV signals from the FWCS (0.5). Only 5 valves may quick open as valve #6 is always blocked on a reactor trip (0.5)
KEY:
STMDMP CNTRL REF:
W3SES SD - SBCS, pgs 5, 22, figs 2, 27 VAL:
As indicated 9
l 1
l l
l
3.3 A. How will the operator be made aware that an individual CEA timer has failed, and what is the impact of timer failure on normal CEA operation? Why? (1.0)
- 8. How will the operator determine the specific CEA(s) affected? Where is the indication obtained? (1.0)
ANS:
A. A timer failure alarm occurs when the primary CEA timing circuit fails (0.5). There is no impact on normal operation as there is a backup timing circuit available (0.5).
B. There are individual red alarm status lights that indicate failure of specific CEA's (0.5) on the CEA Disable and Timer Failure Lamp Panel (0.5) (Accept Local CEDMCS panels on the
+21 elevation in the "B" switchgear room).
KEY:
RODCNTRL IND REF:
W3SES SD - CEDMCS, pgs 10,11 VAL:
As indicated 1
l 3.4 Describe how an Engineered Safety Features Actuation Signal will affect the Essential Services Chilled Water System. Include a description of the normal line up in the answer. (2.5)
ANS:
Normal line up has 2 chillers supplying 2 safety and 1 non-safety loops with I chiller unit in standby (1.0). An SIAS will isolate the non-safety loop (0.5), split the safety loops (0.5), and align 1 chiller to each safety loop (0.5).
KEY:
REF:
. VAL:
As indicated
(
)
i i
i s
i n ..- - - . . - . - - - . . - , --n- - - - - ,. . --- .,,,,,-..,e.- .- ,-
, --- -~
L 3.5 A. Remote manual trip can be accomplished from either of two i locations in the control room. Describe how the reactor is '
I manually tripped from the control room, including the 4
locations of the manual push buttons. (1.5)
B. Describe how the trip circuit breakers are reset following a trip, including from where the reset is accomplished. (1.5) i ANS:
A. 2 pushbuttons on CP-2 2 pushbuttons on CP-8 Depressing both pushbuttons at either location will manually trip the reactor.
B. Go to " unlock" with the key lock switch below the row of !
resets. !
Depress the reset pushbutton.
Performed from the reset panel on the PPS cabinet (CP-10) front. ;
KEY: I RPS e
REF: (
0.5 pt each ;
l A
r >
r
)
i h
1 f
1 1
I i
3.6 A. What control action takes place when a Core Protection Calcualtor (CPC) pretrip setpoint is reached? (0.5)
B. What two reactor protection system trips are generated by the CPC's? (1.0)
C. A CEAC fails and will not reset. How are the penalty factors determined with only one operable CEAC7 (1.5)
ANS:
A. CEA withdrawal prohibit **
B. Low DNBR High local power density C. The CPC will keep the last valid penalty factors from the failed CEAC prior to its failure.
These factors are auctioneered against the operable CEAC penalty factors.
The larger of the two is selected for use by the CPC.
KEY:
COMPUT CPC CNTRL REF:
W3SES SD - CPC, pgs 66, 72 VAL:
0.5 pt each
- Note: Accept "no effect" for A. if the candidate explains that 2/4 logic is needed to get a CEA withdrawal prohibit. -
i l
1 3.7 The plant is operating at 100% power with all parameters within '
their normal bands. Automatic makeup to the VCT is not available. CVC-101, Letdown Isolation Valve, fails shut.
Describe the response in the CVCS system with no operator action.
All other systems respond normally. (2.0) i ANS:
VCT level decreases with no letdown flow (1.0). As VCT level decreased, the VCT outlet valve will shut (0.5) and the RWSP to charging pump suction valve will open (0.5).
KEY:
CVCS CNTRL REF:
As indicated 1
3.8 A. How will individual 6.9 KV motor feeder breakers react to loss of power to a 6.9 KV bus? (0.5)
B. What specific protection is afforded to RCP breakers, but not to other 6.9 KV motor feeder breakers? (0.5)
C. What are four problems or conditions that my exist when the control room indication for a 6.9 KV bus transformer feeder breaker has both lights extinguished? (1.0)
D. What conditions must be met to close a tie feeder breaker for the 3 ABS Bus? (1.0)
E. What alternative conditions must be met to close the auxiliary transformer feeder breaker to bus 2A or 28? (1.0)
ANS:
A. All breakers open on undervoltage.
B. Phase differential current (or Differential Protection)
C. Lamp burned out Breaker racked out Control power deenergized Trip circuit fuse blown D. Other tie breaker open 480 VAC feeder to 31 ABS open E. Bus deenergized OR Generator on line, bus and transformer voltage and frequency synchronized.
KEY:
ELEDST BKR CNTRL REF:
W3SES SD - 56b, pgs 4, 6 and 56c, pgs 11, 13 VAL:
A, B, D, & E - 0.5 pt each C - 0.25 pt each 1
- 3. 9 A. List the six methods or interlocks used in the CEDMCS to limit CEA travel at the top or bottom of the core. The list should include rods affected, method of position detection, and approximate setpoint. (2.0)
- 8. Describe how CEA's are sequenced in the Manual Sequential mode. (2.0)
ANS:
A. INTERLOCK R0D AFFECTED DETECTION
- SETPOINT Upr Elec Lmt ALL Reed Sw 152-153" Lwr Elec Lmt ALL Reed Sw 0.75" Upr Grp Stop Reg & SD Computer 145" Lwr Grp Stop Reg & SD Computer 6" Upr Cntrl Lmt PLCEA's Computer 145" Lwr Cntrl Lmt PLCEA's Computer 10" B. Withdrawal: When the group being withdrawn reaches 100",
the next group will start to withdraw.
Insertion: When the group being inserted reaches 50", the next group will start to insert.
! KEY:
RODCNTRL LMTS CNTRL REF:
W3SES SD - CEDMCS, pgs 28-30 VAL:
A. 0.33 each (0.0833 per element)
- B. 1 pt each
- Note: RSPT may be substitued for Reed Switch and Pulse Counter for Computer.
I END OF CATEGORY 3 p
, - ~ - - ,- - - - ---~ -------
, n-----
- 4. PROCEDURES, NORMAL, ABNORMAL, EMERGENCY i AND RADIOLOGICAL CONTROL l 4.1 The precautions of OP-10-001, General Plant Operations, require J
that RCS oxygen concentration be reduced to less than 0.10 ppm 1 before exceeding 2500F. (2.0)
A. What is used to reduce the oxygen concentration in this condition?
B. What is significant about the 2500F limit?
ANS:
l A. Hydrazine is used to remove 02 while subcritical below 2500F.
4 B. Above 2500F, hydrazine begins to breakdown and can no longer effectively remove oxygen.
KEY:
N0P RCS TS REF:
4 Generic CE operations VAL:
- 1 pt ea for A and B.
J I
4.2 The precautions of OP-10-001, General Plant Operations, state that a fourth Reactor Coolant Pump shall not be started until RCS temperature is above 5000F. Why is this restriction imposed?
(1.0)
ANS:
Below 5000F, the water in the RCS is dense enough that running all four RCPs will develop enough lift to cause the fuel modules to " float" in the core region.
KEY N0P CORE REF:
Generic CE core characteristics.
VAL:
1 pt, 0.5 each for water density and float or lift.
4 1
i l
1 l
l
i i
4.3 What conditions require that a spray cycle be recorded? Consider both normal and auxiliary. (1.0)
ANS:
i Normal - dT GT 1300F Auxiliary - dT GT 1400F i KEY:
NOP LMTS REF:
! W3SES OP-10-001, pg 10, Rev 4
! VAL:
O.5 pt each 4
l l
4.4 List 12 of the 16 imediate actions of OP-902-000, Emergency Entry Procedure. List only the principle statement for each action item. (Example: Check that Circulating Water flow is adequate.)
(4.0)
ANS: (ANY12)
- 1. Check for Reactor Trip
- 2. Check for Turbine Trip
- 3. Check for Generator Trip
- 4. Check Containment temp LT 1200F
- 5. Check that Train A Safety 4KV Bus is powered (energized)
- 6. Check that Train B Safety 4KV Bus is powered (energized)
- 7. RESET Moisture Separator Reheater controls, THEN check temperature control valves closed
- 8. Check Steam Bypass Control System is operating in auto.
- 9. Check Feedwater Centrol in Reactor Trip Override
- 10. IF Pressureizer pressure is LE 1621 psia, THEN stop ALL RCPs
- 11. W Pressurizer is GT 1684 psia, THEN check the for auto
_ operation
- 12. IF Pressurizer pressure is LE 1684 psia on 2/4 channels OR T6ntainment pressure is GE 17.1 psia on 2/4 channels, THDi check for SIAS actuation.
- 13. Check Containment Area Radiation Monitors are normal
- 15. TFTor EITHER Steam Generator, level is LE 27.4% Narrow Tinge on 2/4 channels, THEN check for EFAS actuation.
- 16. IF Containment pressure is GE 17.1 psia on 2/4 channels, OR T/G pressure is LE 764 psia, THEN check for MSIS actuation.
KEY:
E0P REF:
W3SES OP-902-000, pgs 2-8, Rev 1 VAL:
0.33 each l'
e l'
f l
l
\
l
4.5 Using figure 7._ , identify the numbered blocks on a separate answer page. (2.0)
ANS:
- 1. Pressurizer pressure dropping rapidly and pressurizer level changing.
2.* Secondary Break
- 3. Primary Break 4.* Secondary break inside containment 5.* Secondary break outside containment
- 6. LOCA inside containment
- 7. Activity in Steam Plant
- 8. Steam Generator Tube rupture KEY:
E0P REF:
W3SES OP-902-000, Attachment 2, Rev 1 VAL:
0.25 each
- Note: " Excess steam demand" may be'substitued for " Secondary Break".
4.6 List four (4) ways that radioactive contaminants may enter the body and become an INTERNAL radiological health hazzard. (2.0)
I ANS: (ANY4)
- 1. Inhalation (breathingin)
- 2. Oral ingestion (swallowing)
- 3. Open wounds or skin abrasions
, 4. Through the skin pores
.! 5. Skin absorption (cellular osmosis)
(Will accept "through the skin" as a single correct answer)
KEY:
RADCON REF:
Std Rad Con Inforamation l VAL:
2 pts, 0.5 ea.
4 b
i
)
i I
)
l
i 4.7 What is the maximum exposure an operator could receive in an area posted " Caution-Radiation Area" if he remained there for 30 minutes? Explain your answer. (1.0)
.' ANS:
50 mr - A radiation area is anything up to 100 mr/hr. Therefore, in 30 minutes, a person could receive 100 mr/hr X 0.5hr = 50 mr.
KEY:
RADCON REF:
NUS Mod. 6.3 VAL:
1 pt, 0.5 for exposure, and 0.5 for explanation.
i
)
i i
i
}
4.8 Match one definition to each term. (2.0)
TERMS DEFINITIONS -
A. M R/qtr 1. Radiation effects that are transferred >
from parent to children. '
s.
B. 400 rems 2. The 10 CFR 20 MAXIMUM allowable annual dose not to exceed 5 (N-18) rems W -
form 4 on file) ,
e C. Chronic 3. One time limit for lifesaving.
} exposure D. 12 R 4. Small radiation dose received over a
- long period of time.
- 5. Median lethal dose (LD 50/30 ) for man.
- 6. The 10 CFR 20 dose limits for the whole body in a restricted area.
ANS:
A. 6 1. '
B. 5 2. D
, C. 4 OR 3.
1 D. 2 4. C
- 5. B
.; 6. A i
KEY:
RADCON i
REF:
FCS RAD MAN VII, & 10 CFR 20 .,)
l l VAL:
2 pts, 0.5 each.
~
9-j e' a
l \ ~
l
. t i
- -----___.7
. - - - - -- g 4,,_. _ ~ _ . . ~ . _ _ , . - - -
3 4.9 List the 6 conditions / criteria which are used to determine if natural circulation flow has been established. (3.0)
ANS:
- 1. Loop dT LT 640F
- 2. Tc constant OR dropping
- 3. Th constant OR dropping
- 4. Core exit thennocouples (CET) and Th dT LT 100F
- 5. Both SG wr levels GE 50% and steady or rising OR Both SG levels being restored by main or emerg feed
- 6. SG pressure approxomately equal to saturation pressure for existing Tc-KEY:
E0P REF:
W3SES OP-902-005, pg 8, Rev 1 VAL:
0.5 pt each.
x
'N 4.10 What is the procedural guidance for determining if aiding has
- occured in the RCS? (2.0)
ANS:
- 1. Pressurizer level rising suddenly while lowering Pressurieer pressure ,
- 2. Pressurizer level dropping suddenly while raising ;
Pressurizer pressure.
KEY:
E0P REF:
W3SES OP-902-005, pg 20, Rev 1 3
VAL:
1 pt each.
=
'f k g
! g.
1 3
a u 4
9 , ,.'
,1 (^ . - _ -- , , - . . . . _ , e. _ . , - - -- v ~
i 1 4.11 What are the immediate actions for condenser tube leakage? (2.0)
ANS:
- 1. Increase SG blowdown to maximum allowable rate (317 gpm) for
- each SG.
- 2. Open the Condensate Dump Valve (CD-145) to the waste pond as necessary to maintain Hotwell level near normal until the leak can be isolated.
KEY:
ADP REF: ,
W3SES OP-901-006, pg 5, Rev 3 VAL:
1 pt each.
I 1
1 e
4.12 If during a loss of offsite power, all Reactor Coolant Pumps are lost what is the restart criteria? (3.0)
ANS:
A. Pressurizer level GE 28% and constant or rising B. RCS Subcool Margin GE 280F C. Both SG levels GE 50% wide range and steady or rising OR Both SG levels are being restored by main or emerg fee 37 KEY:
E0P REF:
W3SES OP-902-005, pg 7, Rev 1 VAL:
1 pt each for A, B, and C l
END OF CATEGORY 4
.s_.- -
4 _. . _ -
f f
i U.S. NUCLEAR REGULATORY CCMMISSION.
SENIOR REACTOR OPERATOR LICENSE EXAMINATION !
Facility: WATERFORD 3 !
r Reactor Type: CE - PWR Date Administered: 10/15/85 l Examiner: S.L. McCrory !
f Candidate:
l INSTRUCTIONS TO CANDIDATE: l Use separate paper for the answers. Write answers on one side only. Staple f question sheets on top of answer sheets. Points for each question are '
i indicated in parentheses after the question. The passing grade requires at p 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. :
t
% of I J
Category % of Candidate's Category i Value Total Score Value Category {
25.0 25 5. Theory of Nuclear Power i Plant Operations, Fluids, e and Thermodynamics ;
i 2 25.0 25 6. Plant Systems Design, i Control and Instrumentation ;
i 25.0 25 7. Procedures - Normal, f Abnormal, Emergency, and !
Radiological Control .
I 22.0 25 8. Administrative Procedures !
- Conditions, and Limitations -
97 TOTALS
- Final Grade % i i
All work done on this examination is my own. I have neither given nor received aid. - '
Candidate's Signature -
! I I
9
- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONS, FLUIDS, AND THERMODYNAMICS 5.1 Explain how and why overall plant efficiency changes as power is increased from 10% to 100% of rated power (Efficiency = net MW electric / gross MW thermal). (2.0)
ANS:
Overall efficiency increases with increased power because there is more feedwater heating and house loccs do not increase linearly with increasing power output.
KEY:
HTTRANS REF:
BASIC HEAT TRANSFER AND THERMODYNAMIC THEORY VAL:
0.5 pt for increase, 0.75 pt ea for fw heat and house load l
l 1
5.2 TRUE or FALSE? No explanation required. (2.0)
A. As condenser vacuum is increased (absolute pressure decreased), more energy can be extracted from the steam.
B. The main condenser uses the conduction mode of heat transfer C. to reject heat Increasing to the circulating condensate (water depression system.will increase subcooling) overall plant efficiency.
D. Decreasing condensate depression (subcooling) will decrease condenser vacuum.
ANS:
A. TRUE B. TRUE C. FALSE D. FALSE KEY:
HTTRANS FLUID REF:
BASIC FLUID MECHANICS AND HEAT TRANSFER VAL:
0.5 pt each l
i
5.3 What is the diffe ence in CAVITATION and GAS BINDING in a centrifugal pump? (2.0)
ANS:
Gas binding occurs when a pump is filled with a gas, such as air, so that the pump cannot pump the fluid desired.
Cavitation occurs when inadequate NPSH is available so voiding or boiling of the pumped fluid occurs in the pump suction.
KEY:
FLUID REF:
BASIC FLUID MECHANICS VAL:
1 pt each i
i t
1 t _. . . - . -- ..
5.4 TRUE or FALSE? No explanation required. (2.0)
A. The operator can increase the heat removal reat from the RCS
. by reducing steam pressure.
B. A LOCA with no RCP's running can result in more inventory loss than a LOCA with RCP's running.
C. A total and prolonged loss of feedwater can lead to a loss of RCS liquid inventory.
t D. The primary concern when fuel clad temperature reaches 14000F is the production of hydrogen.
ANS:
A. TRUE B. FALSE C. TRUE D. FALSE KEY:
FLUID HTTRANS REAC REF:
BASIC REACTOR THEORY VAL:
0.5 pt each l
5.5 Calculate the time required for reactor vessel bulk water temperature to reach 2120F for the conditions below. STATE ALL ASSUMPTIONS AND SHOW ALL WORK FOR FULL CREDIT. (3.0)
A. The reactor has been shutdown for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after a 250 day run at 100%.
B. ALL means of removing heat from the vessel are lost.
C. No circulation to the primary loops occurs.
D. Reactor vessel water is initially at 1120F and well mixed.
E. The reactor vessed head is de-tensioned but still sealed. ,
ANS:
ASSUMPTIONS A. Vessel water volume = 3000 - 5000 cu. ft. .
B. Decay heat load = 0.1 - 0.5% rated thermal power .
C. Rated thermal power = 3350 - 3450 MW .
D. Water density = 59.8 - 61.8 lbm/cu.ft. (.25)
E. 57,000 Btu / min = 1 MW (3.41x106 Btu /hr) (.25)
F. 1 Btu will raise 1 lbm water loF OR the enthalpy of subcooled water is approximately equal to that of saturated water at the same temperature. (.25)
SOLUTION G. Water Mass = AxD = 209,300 - 309,000 lbm (0.1)
H. Heat Load = 8xCxE = 16 - 35 MW = 0.9 - 2x106 Btu / min (0.1)
- I. Heat Required = FxGx(dT=1000) = 21 - 31x106 Btu (0.1)
J. Time Required = I/H = 10 - 40 min = 1/6 - 2/3 hours (.45)
OR Time = Gx(dh=100) = 10 - 40 min = 1/6 - 2/3 hr (.55)
H KEY:
HTTRANS REF:
BASIC CE REACTOR DESIGN, STEAM TABLES, BASIC HT&T VAL:
as indicated in the answer.
- If the enthalpy method is used the point value of I is incorporated into the alternate J solution.
l l
l
5.6 A. What is the minimum reactivity that must be added to a critical reactor for it to be prompt critical? (1.0)
- 8. How much (by what factor) would power increase in one second at Waterford 3 if it were prompt critical? (2.0)
ANS:
A. p (reactivity) GE beta effective (beta value = 0.005-0.007)
B. T = 1*/p + (B-p)/tp (0.5)
So for prompt critical neglect the delayed term so that T = 1*/p (.25) 1* = 10 10-4 sec (.25) p = 0.005 - 0.007 (.25)
.0014 - 0.02 sec (.25)
T = 1*/p P/Po = et =/T = e(50 - 700)/1 sec (0.5)
KEY:
RXTH CORE 0PS REF:
BASIC REACTOR THEORY VAL:
1 pt for A, and as indicated for B.
[
l e
l l
5.7 When loading fuel into the core, should fuel be loaded toward the detector or away from it? EXPLAIN (1.0)
ANS:
Fuel should be loaded toward the detector (0.33) so that the 1/M plot conservatively predicts criticality (0.67).
KEY:
RXTH CORE 0PS REF:
BASIC REACTOR THEORY VAL:
As indicated.
1 i
i I
l l
l l
l
, .. 4 , , . . , ,. _. , ._-
5.8 The plant has been at 60% power for several days with all rods out. A single rod drops into the core but does not produce a reactor trip. (3.0)
A. Explain how and why the dropped rod will affect the ma.rimum (peak) linear power in the core.
B. How and why will the maximum linear power change over the next 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if the rod is not recovered?
ANS:
A. When the rod drops, total power does not change. Therefore the maximum linear power will increase because power around the rod will drop, causing power to gu up in the rest of the Core.
B. For the first few hours Xe will build up in the vicinity of the rod due to reduced burnout ratt. This will further suppress power generation in this area and cause the maximum-linear power to increase more.
KEY:
POIS0NS RXTH REF:
STD RX THE0RY VAL:
3 pts, 1.5 each for A and B.
l l
l
5.9 A. The reactor is subcritical with a count rate of 20 cps.
Reactivity is added to increase the count rate to 40 cps.
What would be the effect of adding the same amount of reactivity again? Explain your answer. (1.5)
B. With an initial power of 10%, reactivity is added to increase power to 20%. What would be the effect of adding the same amount of reactivity again? Explain your answer.
(1.5)
ANS:
A. The reactor would be critical or slightly supercritical.
When subcritical, if the count rate is doubled, then of the reactivity needed for Keff to equal I has been added.
Adding the same amount of reactivity again will cause Keff to equal 1 (actually it is slightly higher than 1).
Calculations demonstrating this concept are also acceptable.
B. The reactor power will increase to about 30% because the total power defect is approximately linear with reactor power.
KEY:
RXTH NC REF:
A. STD RX THE0RY B. W3SES TDB 1.2.1, Rev 0 VAL:
3 pts, 1.5 each for A and B.
l N___ _ _ _ _ .
5.10 The relative worth of a CEA is dependent on the neutron flux reaching it. List and explain four (4) factors or conditions which affect the flux reaching a particular CEA. (3.0)
ANS: (ANY4)
- 1. Temperature-- Neutrons travel longer distance at higher temperature, therefore, higher probability of capture.
- 2. Boron concentration-- As concentration goes up fewer neutrons reach the rods.
- 3. Fission product poisons-- as poision concentration increases fewer neutrons reach the rods.
- 4. Rod shadowing-- when adjacent rods are inserted, the exist-ing rod sees a lower flux.
- 5. Radial position-- rods near the center of the core see higher flux than peripheral rods.
- 6. Axial position-- the farther a rod is inserted into the core the greater the flux it is exposed to.
- 7. Core Age-- as the core ages, flux shifts toward the outer edges of the core.
KEY:
RXTH NEUT REF:
Std reactor theory and core characteristics VAL:
3 pts, 0.25 for factor / condition, and 0.5 for explanation i
l
, 5.11 Briefly explain why you agree or disagree with the following statement. (1.0)
A 100 heatup with a +.3 delta K/K MTC will cause power to change as much, but in the opposite direction, as a 100 cooldown with a
.3 delta K/K MTC.
ANS:
Disagree. Power will increase in both cases, but will not increase as much dering heatup because Doppler effects will aid in turning power.
KEY:
NC RXTH COREOPS REF:
STD CE CORE CHAR.
VAL:
1 pt, 0.3 for disagree, and 0.7 for explaination.
END OF CATEGORY 5 i
, _ _ _ . , , , . . - _ , . . - , , , , , _ ..,m- , , . . .- , , . ~ _ , . , - . - , - - - - -
- 6. PLANT SYSTEMS DESIGN, CONTROL AND INSTRUMENTATION 6.1 A. In the event of a circulating water (CW) pipe rupture in the plant area, what DESIGN FEATURE prevents flow in the CW discharge piping from reversing and flowing from the river into the plant area and what activates this de:ign feature?
(1.0)
- 8. Describe the sequence of events that occurs in the CW system automatically upon placing athe first CW pump switch to START. (1.0)
C. When can the second CW pump be started? (0.5)
ANS:
A. Vacuum breaker valves located on the CW return piping (0.5)
Manually operated (0.5)
B. The pump's discharge valve will open to 20% (0.5). Once the valve is at 20%, the CW pump breaker will close (0.5).
C. 100 seconds after the first CW pump's discharge valve is full open (0.5).
KEY: -
CIRC DESGN CNTRL REF:
W3SES SD - CW, pgs 11, 12, 21 VAL:
As indicated f
6.2 A. What are two reasons for maintaining a small continuous flow through the pressurizer spray lines? (1.0)
B. Where do the normal and auxiliary spray flows come from?
(1.0)
ANS:
A. Reduces thermal shock in the spray line.
Keeps the chemistry / boron concentration of the pressurizer close to that of the rest of the RCS.
B. Normal: The discharge of both loop 1 RCP's Auxiliary: Charging pump discharge KEY:
PZR PATH RCS REF:
i A. 0.5 each B. 0.5 each i
d
- , . , ,. , , - * - - - . . - - - - - , - , , -----,--y.yw- -w--- - ---+,y--- --
e- -,
6.3 A. What are the seven systems / subsystems actuated by the Engineered Safety Features Actuation System (ESFAS)? (1.5)
B. What are the only two bypasses applicable to the ESFAS?
Briefly describe what each bypass accomplishes. (2.0)
ANS: (ANY7)
A. 1. SIAS
- 2. CIAS
- 3. CSAS
- 4. MSIS
- 5. RAS
- 6. EFAS-1
- 7. EFAS-2
- 8. Loss of Power (added after review)
B. Pressurizer pressure bypass (0.5): Disables pressurizer pressure reactor trip (0.25), CIAS (0.25), and SIAS (0.25)
Trip channel bypass (0.5): Allows only one channel for any type of trip to be bypassed at one time (0.25).
KEY:
ESF CNTRL REF:
W3SES SD - PPS, pg 1, 2 & fig. 122 VAL:
A. 0.25 pt ea for 1-5, 0.125 pt ea for 6 & 7 B. as indicated Note: During the examination all candidates were told to interpret
" systems / subsystems" as " actuation signals".
l l
l
6.4 Describe how Stator Coil Water System (SCW) differential pressure (flow) and conductivity can affect main trubine automatic control and operation. Include parameter values as applicable. (1.5)
ANS:
Five seconds after loss of flow, a turbine runback is initiated to reduce power to less than 15% or170 MWE (accept 150-200)
(0.5). If that power is not reached within 45 seconds, the turbine trips (0.5). If loads are reduced in time, the turbine will then trip if SCW conductivity reaches 1.5 umho/cm with a SCW Lo-Lo flow (0.5).
KEY:
MNTURB DESGN CNTRL MNGEN REF:
W3SES SD - SCW, pg 43a-19 VAL:
As indicated i
l l
l I
L
l What are the 4 major components contained in a typical 6.5 A.
Static Uninterruptable Power Supply (SUPS)? (2.0)
B. Describe the major difference between a Safety and Non-Safety related SUPS. (1.0)
ANS:
A. Rectifier Inverter Manual Bypass Switch OR Static Transfer Switch Power Distribution Panel B. A static transfer switch is provided on the Non-Safety SUPS j which will auto transfer to the bypass supply when it detects abnormal inverter output.
KEY:
ELEDST DESGN
, REF:
W3SES SD - 59, pgs 2 - 4, and fig. 59-3 VAL:
0.5 each in A 1 pt for B l
l l
6.6 A. Where can the operator perform the setpoint reset function for the Low Pressurizer Pressure and Steam Generator Low Pressure reactor trips? (1.5)
B. Describe and explain what would occur if the operator repeatedly pushed the button to reset the Low Pressurizer Pressure trip during normal operation. (2.0)
ANS:
A. Bistable control panel (or CP-10, PPS Panels)
Remote operator's module (or CP-7)
Remote shutdown panel (or LCP-43)
B. Nothing abnormal should occur (0.25). An interlock prohibits reset of the trip for 10 seconds after reset (0.5). The reset functions to lower the setpoint 400 psi belowexistingpressure(0.5). From a normal operating pressure of 2250 psi, the setpoint would be reduced to approximately 1850 psi, which is near the normal setpoint (0.25). Subsequent attempts to change setpoint will not cause a change unless plant pressure changes (0.5).
KEY:
RPS PZR CNTRL REF:
W3SES SD - RPS, pgs 31-33 VAL:
A. 0.5 pt each B as indicated l
l l
6.7 Explain how the SBCS Modulating Mode permissive / actuating setpoints are varied with changing plant conditions. The explanation should indicate how the setpoint varies as well as parameter inputs used to generate the signal. (1.5)
ANS:
The system setpoints will decrease as power is increased (0.5),
by biasing the signal to maintain setpoint (approx. 40 psi) above steam pressure (0.5). The setpoints are generated from a steam flow signal that receives a positive bias from pressurizer pressure (0.5).
KEY:
STMDMP CNTRL REF:
W3SES SD - SBCS, pgs 5, 22, figs 2, 27
, VAL:
As indicated l
I l
l l
t
6.8 A. The penalty factors calculated by the CEAC's.will ramp up l for to account for ___,. (Fill in blanks) (1.0) l B. Other than time, what are two other factors that the magnitude of the penalty factors are dependent upon? (1.0) 1 ANS:
A. one hour Xenon redistribution B. (ANY TWO)
Magnitude of the CEA deviation Direction of the CEA deviation CEA configuration The subgroup with the deviating CEA KEY:
RODCNTRL LMTS TS RPS REF:
0.5 pt each i
i I
h
6.9 A. How will individual 6.9 KV motor feeder breakers react to loss of power to a 6.9 KV bus? (0.5)
B. What specific protection is afforded to RCP breakers, but not to other 6.9 KV motor feeder breakers? (0.5)
C. What are four problems or conditions that mjy( exist when the control room indication for a 6.9 KV bus transformer feeder breaker has both lights extinguished? (1.0)
D. What conditions must be met to close a tie feeder breaker for the 3 ABS Bus? (1.0)
E. What alternative conditions must be met to close the i
auxiliary transformer feeder breaker to bus 2A or 2B7 (1.0)
ANS:
A. All breakers open on undervoltage.
B. Phase differential current (or Differential Protection)
C. Lamp burned out i Breaker racked out Control power deenergized Trip circuit fuse blown D. Other tie breaker open 480 VAC feeder to 31 ABS open E. Bus deenergized OR Generator on line, bus and transformer voltage and frequency synchronized.
4 KEY:
ELEDST BKR CNTRL REF:
W3SES SD - 56b, pgs 4, 6 and 56c, pgs 11, 13 VAL:
A, B, D, & E - 0.5 pt each C - 0.25 pt each i
l l
I
6.10 A CEAC fails and will not reset. How are the penalty factors determir.ed with only one operable CEAC? (1.5)
ANS:
The CPC will keep the last valid penalty factors from the failed CEAC prior to its failure.
These factors are auctioneered against the operable CEAC penalty factors.
The larger of the two is selected for use by the CPC.
KEY:
COMPUT CPC CNTRL REF:
W3SES SD - CPC, pgs 66, 72 VAL:
0.5 pt each END OF CATEGORY 6 l
l l
[
- 7. PROCEDURES, NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 7.1 The precautions of OP-10-001, General Plant Operations, require that RCS oxygen concentration be reduced to less than 0.10 ppm before exceeding 2500F. (2.0)
A. What is used to reduce the oxygen concentration in this condition?
B. What is significant about the 2500F limit?
ANS:
A. Hydrazine is used to remove 02 while subcritical below 2500F.
B. Above 2500F, hydrazine begins to breakdown and can no longer effectively remove oxygen.
KEY:
N0P RCS TS REF:
Generic CE operations VAL:
1 pt ea for A and B.
l 1
4 i
(
l
s s l l
7.2 List 12 of the 16 imediate actions of OP-902-000, Emergency Entry Procedure. List only the principlerstatement for each 1 action item. (Example: Check that Circulating Water flow is adequate.)
ANS: s Check for Reactor Trip 1.
- 2. Check for Turbine Trip
- 3. Check for Generator Trip '
- 4. Check Containment temp LT 1200F
- 5. Check that Train A Safety 4KV Bus is powered (energized)
- 6. Check that Train B Safety 4KV Bus is powered (energized) 7 .- RESET Moisture Separator Reheater controls, THEN check temperature control valves closed ,
- 8. Check Steam Bypass Control System is operating in auto.
- 9. Check Feedwater Control in Reactor Trip Override
- 10. IF Pressureizer pressure is LE 1621 psia, THEN stop ALL RCPs
- 11. TF Pressurizer is GT 1684 psia, THEN check the for auto '
operation
- 12. IF Pressurizer pressure is LE 1684 psia on 2/4 channels OR T6ntainment pressure is GE 17.1 psia on 2/4 channels, THER check for SIAS actuation.
- 13. Check Containment Area Radiation Monitors are normal
- 15. TF Tor EITHER Steam Generator, level is LE 27.4% Narrow Range on 2/4 channels, THEN check for EFAS actuation.
- 16. IF Containment pressure is GE 17.1 psia on 2/4 channels, or 37G pressure is LE 764 psia, THEN check for MSIS actuation.
KEY:
E0P REF:
W3SES OP-902-000, pgs 2-8, Rev 1 VAL:
0.33 each
\ l'
7.3 Using figure 4.5, identify the numbered blocks on a separate answer page. (2.0)
ANS:
- 1. Pressurizer pressure dropping rapidly and pressurizer level changing.
2.* Secondary Break
- 3. Primary Break 4.* Secondary break inside containment 5.* . Secondary break outside containrent
- 6. LOCA inside containment
- 7. Activity in Steam Plant
- 8. Steam Generator Tube rupture KEY:
E0P REF:
W3SES OP-902-000, Attachment 2, Rev 1 VAL:
0.25 each
- Note: " Excess steam demand" may be' substituted for " Secondary Break".
i l
[
l 1
- _. . _ . - -, . - - _ _ _ _ _ . . . _ _ . . - _ _ . _ - ~ - . . _ _ - _ - _
t j, "' -
i
~.
(
~,4 ,
f
' 7.4 If during a loss of offsite power, all Reactor Coolant Pumps are lost what is the restart criteria?(3.0)
ANS:
1 A. Pressurizer level GE 28% and constant or rising L'
- B. RCS Subcool Margin GE 280F' C. Both SG Tevels GE 50% wide range and steady or rising OR Both SG levels are being restored by main or emerg feeE KEY:
E0P.
~
REF:
j W3SES OP-932-005, pg 7, Rev 1 VAL: .
1 pt each for xA, B, and C 1
k I'
\,
es)
~
i i
'a l
h .
- m. _ . .
7.5 List the 6 conditions / criteria which are used to determine if natural circulation flow has been established.(3.0)
ANS:
- 1. Loop dT LT 640F
- 2. Tc constant OR dropping
- 3. Th constant OR dropping
- 4. Core exit thermocouples (CET) and Th dT LT 100F
- 5. Both SG wr levels GE 50% and steady or rising OR Both SG levels being restored by main or emerg feed
- 6. SG pressure approxomately equal to saturation pressure for existing Tc-KEY:
E0P REF:
W3SES OP-902-005, pg 8, Rev 1 VAL:
0.5 pt each.
i v
l l
7.6 What is the procedural guidance for determining if voiding has '
occured in the RCS? (1.5)
ANS:
- 1. Pressurizer level rising suddenly while lowering Pressurizer pressure
- 2. Pressurizer level dropping suddenly while raising Pressurizer pressure.
KEY:
E0P REF:
W3SES OP-902-005, pg 20, Rev 1 VAL:
0.75 pt each.
r s.__ , _ m - - -,.w... - ,y - w - -
l l
l 7.7 List the 3 conditions which define COLSS as out-of-service.(1.5) j ANS:
- 1. Plant Computer out of service
- 2. Failure of redundant sensors of variables that are used in COLSS calculations.
- 3. COLSS in the unscheduled mode (shutdown)
., KEY:
N0P REF:
W3SES OP-4-005, pg 3, Rev 6.
VAL:
0.5 pt each
- l l
I
7.8 List the imediate actions for a Toxic Chemical Release. (1.5)
ANS:
- 1. Ensure Control Room ventilation system isolation.
- 2. Start both diesel generators
- 3. Stop both RAB Normal Supply Fans (HVR-0002A and HVR-0002B)
KEY:
A0P REF:
W3SES OP-901-047 VAL:
0.5 pt each 1
i i
i l
{
I 1
l
7.9 What are the imediate actions for condenser tube leakage? (2.0)
ANS:
- 2. Open the Condensate Dump Valve (CD-145) to the waste pond as necessary to maintain Hotwell level near normal until the leak can be isolated.
KEY:
A0P REF:
W3SES OP-901-006, pg 5, Rev 3 VAL:
1 pt each.
1 i
i l
1
i l
l i
l l
7.10 List four (4) ways that radioactive contaminants may enter the body and become an INTERNAL radiological health hazzard. (2.0)
ANS: (ANY4)
- 1. Inhalation (breathing in)
- 2. Oral ingestion (swallowing)
- 3. Open wounds or skin abrasions
- 4. Through the skin pores
- 5. Skin absorption (cellular osmosis)
(Will accept "through the skin" as a single correct answer)
KEY:
RADCON REF:
Std Rad Con Inforamation VAL:
2 pts, 0.5 ea.
I i
i y yy,,m --y- .r w%w---- ~%v --- e-- , - g w t vi-- -- - --+y *--g * --- -we-s i- y w-- i-gw
7.11 What is the maximum exposure an operator could receive in an area posted " Caution-Radiation Area" if he remained there for 30 minutes? Explain your answer. (1.0) !
ANS:
50 mr - A radiation area is anything up to 100 mr/hr. Therefore, in 30 minutes, a person could receive 100 mr/hr X 0.5hr = 50 mr.
KEY:
RADCON REF:
NUS Mod. 6.3 VAL:
1 pt, 0.5 for exposure, and 0.5 for explanation.
4 l
[
l
i 7.12 Match one effect to each dose. (1.5)
DOSE (rems) EFFECT A. 25 1. LD50/no treatment B. 100 2. LD100/with treatment C. 200 3. LD100/no treatment D. 400 4. Nausea in 50% exposed individuals E. 600 5. Lower white blood cell count F. 800 6. Threshold for death ANS:
A. - 5 1. - D B. - 4 2. - F C. - 6 OR 3. - E D. - 1 4. - B i E. - 3 5. - A F. - 2 6. - C KEY:
RADCON REF:
Fundamental Radiaton Effects VAL:
1.5 pts, 0.25 each l
1 l
4 e
END OF CATEGORY 7 4
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS.
8.1 Procedure UNT-5-002, Condition Identification and Work Authorization, lists 11 general maintenance / repair activities which require that the SS/CRS be informed prior to accomplishment -
but do not necessarily require a CIWA. Give 7 of them. (3.5)
ANS: (ANY7)
- 1. Greasing and lubricating
- 2. Adjusting valve or pump packing, (except for valves and pumps in the section XI testing program and the pump and valve test program).
- 3. Replacing gauge glass
- 4. Blowing out or cleaning drain, supply and sensing lines.
- 5. Tightening or replacing (nonsafety-related) loose or damaged i
screws and connections which do not require specific torque requirements.
- 6. Replacing light bulbs, lenses and caps
- 7. Replacing fuses that do not require environmental qualification
- 8. General housekeeping, cleaning and inspection which do not require opening a system.
- 9. Replacing and cleaning non-radioactive filters
- 10. Replacement of consumable materials such as ink, pens, paper, reagents, etc.
- 11. Work on accessory parts that perform no operational function, such as nameplates, tags, cover plates, inspection plates, etc.
KEY:
J08 ADMN REF:
W3SES ADMN PROC UNT-5-002, pgs 8,9, Rev 4 VAL:
3.5 pts, at 0.5 each
8.2 True or False. The granting of a clearance means only that all switches and valves through which the equipment could be energized have been opened and tagged or closed and tagged but does not mean that the equipment has been tested to prove that it is de-energized, grounded, or depressurized.(0.5)
ANS:
TRUE KEY:
JOB TAG REF:
W3SES ADM PROC UNT-5-003, pg 9, Rev 4.
., VAL:
0.5 pts.
l I
8.3 Aside from the shift review of active clearances, what are the other periodic review / verification requirements?(2.0)
ANS:
- 1. Every 30 days - compare index to outstanding clearance sheets.
- 2. Quarterly - visually verify the placement of tags on a
, representive cross-section sample of active clearances.
KEY:
TAG JOB REF:
W3SES ADM PROC UNT-5-003, pg 22, Rev 4 VAL:
2 pts, 1 pt each, 0.5 each for period and requirement 4
4
_ ..., _.. 4, _
, , . . , ._ m .- _,. ,. , _w - - 44 9-.m_
8.4 Either the Shift Supervisor or the Control Room Supervisor has
- specific authority to order power reduction or shutdown if continued operation of the unit will result in . List the four general conditions / situations which apply to this authority.
(3.0)
ANS:
- 1. Imediate equipment damage
- 2. Danger to station personnel or a threat to the health and safety of the public.
- 3. Violation of the operating license or Technical Specification requirements.
- 4. An unnecessary automatic trip.
KEY:
JOB REF:
W3SES ADM PROC OP-100-001, pg 12, Rev 3
! VAL:
3 pts, 0.75 each.
I
, . _ , _ _ , . ,,. . ~ . . - , _ _ . , _ . , , _ _ . _ ,
~
The following scenerio applies to questions 8.5 through 8.8.
The reactor has been operating for more than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at 100% power with all rods out. The core age is 100 EFPD. Operator error results in
, an inadvertant reactor trip with no actuation of ESF systems. Four 3
hours after the trip reactor recovery has proceeded to the point that group 6 rods are at 134" when a minor CEA deviation alarm is received and the reactor operator notices that one of the group 6 rods is still at 130".
8.5 What innediate action is required of the operator? (1.5)
ANS:
- 1. Stop all CEA movement
- 2. Place the CEDMCS mode switch in "off".
KEY:
{ AOP RODCNTRL
- REF
1 W3SES OP-901-009, pg 12, Rev 3 VAL:
1.5 pts, 0.75 each I
l l
}
i i
i
_ _. ~ , . _ . . _ . _ _ _ . . . _ _ _ _ . _,_ . . _ , _ , _ _ _ _ . . _ _ _ , ,
2 8.6 What is the status of the affected rod per Technical Specifications? (0.5) j ANS:
I The rod is OPERABLE. (Minor misalignment alone is insufficient to
, declare the rod INOPERABLE.)
- KEY
TS REF:
W3SES TS 3.1.3.1 VAL:
- 0.5 pt 4
4 t
i i
4 i
i i
i l
1 i
8.7 Attempts to move the affected rod individually are unsuccessful and the rest of the group 6 rods are positioned at 130".
- Reference the Technical Specification which applies to the known
, condition at this time. Justify your selection. (To get credit, the reference must be given to the smallest subparagraph division (Ex: 3.4.1.2.a.2.b)). (2.0)
ANS:
TS 3.1.3.1.a At this time nothing is known about the rod except that it will not respond to in/out signals from the control panel. For safety consideration until the problem with the rod can be identified, it must be assumed to be mechanically bound or untrippable.
KEY:
) TS RODCNTRL REF:
TS 3.1.3.1 and NRC precedent VAL:
2 pts, 1 pt for TS and 1 pt for justification.
1 l
i i
i I
8.8 The fault is an open in the lift coils for the affected rod.
A. What, if any, alarms or annunciators would have been activated in the control room which are specific to the fault? (1.0)
B. With this information, what is the least restrictive appropriate Technical Specification statement? Justify your selection. (2.0)
C. With this condition, is the plant permitted by Technical Specifications to be operated at full power for an unspecified period of time? Explain. (2.0)
ANS:
A. None. There no alarms or annunciators which would specifically indicate an open in the lift coil of a rod.
(This can only be determined by measurin a shunt in the power line to each coil.)g the current across B. 3.1.3.1.f - Since an electrical fault has been identified which would not have resulted from mechanical binding nor would interfere with tripping the rod, and alignment and insertion are in limits, this is the appropriate TS.
C. Yes, since the rod is not mechanically bound or untrippable, is above the long term insertion limit and shutdown margin is met, operation may proceed for an unspecified time.
KEY:
TS RODCNTRL IND REF:
W3SES NSSS VOL 2, pg 969(82H6)/ds-25, 42, 43, Rev 0 W3SES TS 3.1.3.1 and bases VAL:
A. - 1 pt B. - 2 pts, 1 pt for TS and 1 pt for justify C. - 2 pts, 0.5 ea for YES, rod condition, insertion limit, and shutdown margin.
8.9 Which of the following conditions or events would result in an Emergency Action Level classification of " ALERT" or higher?
Indicate yes or no for each one. (4.0)
A. Site experiencing winds greater than 75 mph.
B. Evacuation of the control room anticipated with control of shutdown systems established from local stations.
C. RCS leakage greater than 44 gpm but less than 100 gpm.
D. Area Radiation Monitor reading on the RM-ll console trending upward by a factor of 103 with no explanation.
E. Steam line fault with 12 gpm primary to so ondary leakage.
F. Dose equivalent I-131 of the RCS.is 350 uCi/ml, not due to spiking.
G. Loss of all onsite DC power.
H. Loss of both shutdown cooling trains with anticipation of recovering at 72ast one train in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ANS:
Except for "E." ALL OF THE AB0VE ARE ALERT OR HIGHER.
KEY:
EPLAN REF:
W3SES EP-1-001, Attachment 7, Rev 5 VAL:
4 pts, 0.5 each END OF CATEGORY 8 l
1 i
( *
-_ __ , _ . . _ .