ML20238D719
| ML20238D719 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/03/1987 |
| From: | Dudley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20238D709 | List: |
| References | |
| 50-282-OL-87-02, 50-282-OL-87-2, NUDOCS 8709110354 | |
| Download: ML20238D719 (82) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION III OPERATOR LICENSING REQUALIFICATION EXAMINATION REPORT l
I REQUALIFICATION ,
EXAMINATION REPORT NO.: 50-282/0LS87-02 l FACILITY DOCKET NOS.: 50-282 and 50-306 i FACILITY LICENSE NOS.: DPR 42 and 60 l
LICENSEE: Northern States Power Company l International Centre Building '
920 Second Avenue - South Minneapolis, Minnesota 55401 l
FACILITY: Prairie Island Units 1 and 2 l EXAMINATION DATES: June 16-25, 1987 CHIEF EXAMINER: Au .
Noel F. Dudley Audf ba -
01 9 f 2[B7 Date Lead Reactor Engineer APPROVED BY: [ [4 '/[J/6 )
Thomas M. Burdick, Chief Date Operating Licensing Section
SUMMARY
- hequalification written examinations and operating tests were administered to twelve senior reactor operators (SRO) and five reactor operators (RO). Four operators failed the operating test eight operators failed the written examination. The overall requalification program was evaluated as unsatisfactory per the criteria provided in the Licensing Examiner Standards, NUREG-1021, Chapter ES-601, Paragraph F.1.
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B709110354 PDR ADOCK h PDR h B2 V
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l DETAILS TYPE OF EXAMINATIONS: Requalification EXAMINATION RESULTS:
I_ RO l SR0 l l l Pass / Fail l Pass / Fail l EVALUATION l 1 I I I I I I I l j Written I 4/1 l 5/7 l Unsatisfactory i I I I 1 I I I I I I I Operating -l 4/1 l 9/3 l Marginal l i I I I I I I I i 1 l Overall l 4/1 l 4/8 l Unsatisfactory l l l l l l CHIEF EXAMINER AT SITE: N. Dudley, NRC R. Temps, NRC OTHER EXAMINERS: T. Guilfoil, Sonalysts F. Victor, Sonalysts I. Kingsley, Sonalysts B. Haagensen, Sonalysts RESULTS:
- 1. The following is a summary of generic strengths or deficiencies noted on the operating tests. This information is being provided to aid the licensee in upgrading license and requalification training programs.
STRENGTHS i
Uperators' use of procedures during normal and abnormal events.
Operators showed improvement in the response to tripping of bistables for i failed instrument channels. l k
DEFICIENCIES I 1
Operator knowledge and proficiency in areas outside their normally assigned responsibilities.
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L- Operator knowledge of the Reactor Vessel Level Indication System inputs, p expected indications and. effects of adverse containment on indications..
~ 0perator knowledge of the basis for the Safety Injection suction line
. recirculation pump. I Operator use of the turbine load limits to ensure loading rates'were not' exceeded.
Operator Anowledge of the requirement to frisk hand held material upon leaving tne Primary Auxiliary Building.
Operator ability to properly classify emergency events and perform re-quired notifications.
Operator ability to locate the charging; flow control valve in the facility.
~ Operator knowledge of local operations and leal tripping.of the Emergency Diesel Generators.
- 2. The following.is a summary of generic strengths or deficiencies noted from the grading of the written examinations. This information is' being .
provided to' aid the licensee in upgrading license and requalification
. training programs.
STRENGTHS Operator knowledge of switch positions required for starting Auxiliary Feedwater pumps.
'l Operator knowledge of the basis and signal processing for the Over- d temperature Delta-T protection circuit.
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Operator knowledge of the basis for the temperature downstream of the power operated relief valve during formation of a bubble in the pressurizer. ]j Operator knowledge of the effect of a Xenon transient, following a reactor
-trip, on the shutdown margin.
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Operator knowledge:of the effect of plant changes on the estimated critical position during a reactor start up. _
Operator knowledge of the steps required to initiate Emergency Boration. j
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DEFICIENCIES.
Operator knowledge of the basis for shutting the reactor vessel safety l injection isolation valves during power operations.
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Operator knowledge of conditions when the Reactor Coolant Pump trip criteria are not applicable in the Optimal Recovery Guidelines.
Operator knowledge of the accident conditions which are the design basis for the Emergency Core Cooling System.
Operator knowledge of the starting interlocks for the Reactor Coolant ,
Pumps.
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- 3. During the conduct of the simulator portion of these operating tests, the following performance or human factors discrepancies were observed:
A heater drain pump failed to start.
Lightning strikes interrupted two scenarios and resulted in the plant computer being inoperable for one scenario set.
Reactor Coolant Pumps tripped during fast transfer of the associated electrical bus.
The simulator model is unable to accurately simulate a solid water plant during accident conditions. The facility is aware of this problem but has no plans to correct the deficiency.
Turbine Driven Auxiliary Feedwater Pump steam supply valve failed in the closed position.
Boric acid initiation switch failed to operate properly.
- 4. The following problems were identified during the plant walkthroughs.
A tagout which was not active had not been properly cleared from the hold card log.
A tag hanging on the emergency diesel generator had been authorized to be cleared two days earlier.
Procedure C-28.1, Paragraph 7.9.c.(5) refers to a local indicator [18039],
however, the component in the plant is labeled [18035].
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4 0perators'were' not requiring hand l held materials to be frisked upon exiting the Primary Auxiliary Building.
Procedure C-17,.in.the table.of contents refers to-Page 37 for~ containment evacuation.section which actually begins on-Page 32.
.0ptima15 Recovery. Procedure-ES-1.1,. Post LOCA Cooldown and Depressurization,
- Step 7 is confusing and will be' reevaluated by the facility.
EXIT INTERVIEW:
- An exit meeting was held on June 25,1987!to discuss the ' preliminary results of the'requalification program evaluation.
Personnel'Present at Exit Interview:
NRC' Personnel R. Temps, Reactor Engineer (Examiner)
P. Sunderland, . Reactor. Engineer (Examiner)
M. Moser, Resident Inspector-
.I; Kingsley, Sonalysts B. Haagensen, Sonalysts Facility personne1' E. Watz1,-Plant Manager
.L. Eliason, General Manager Nuclear Plants
'T._Amundson, Superintendent of Training M. Sellman, General Superintendent of Operations D. Reynolds, Operations Training Supervisor Summary of NRC comments made at exit interview:
.The Chief Examiner reviewed.the number and types of examinations' administered during the evaluation period. The Chief Examiner noted.the fast and courteous treatment by the plant's security forces while obtaining visitor badges and commented on the cleanliness of the plant particularly in the Primary Auxiliary Building.
The Chief Examiner explained that areas of concern had been discussed in detail
.with-the Training Department and Resident Inspector prior to the meeting. It was' mentioned that although some problems were encountered with the simulator,
-most of the problems were of a transitory and nonrecurring nature and did not affect the. ability of the examiners to properly evaluate the operators' per-formance. The Training Department was able to correct most of the simulator problems during the evaluation period.
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- The Chi ^ef Examiner. explained.that the plant related problems identified during the plant'walkthroughs had been turned over to.the. Resident Inspector'for.fol-.
lowup,.
The. Chief Examiner explained that a list of generic program weaknesses had been provided to-the Training Department. The. Plant Manager was presented with the
, name of an individual who had failed'the operating examination and the-arcas'of weakness. identified during the examination.' The facility was~ requested to take appropriate action.in accordance with their requalification program based on the individual's failure of the operating examination.
' CHANGES TO THE WRITTEN EXAMINATION:
All facility comants'were considered during the grading of the examination even though some comments did not result in changes to the examination answer
- key. The~following changes were made to the examination.
Question Change Reason 3.06 Change " energized" to " actuate." Removes doubt as to whether solenoid energizes or deener-gizes to cause turbine trip.
4.06(c) Question deleted Question inferred an action had to be taken.
5.08- Question deleted Answer given in exam handout.
The question is compromised.
6.01 Question deleted The proper setpoints matched the incorrect setpoints to some extent, confusing the candidates.
8.04 Change "11 auxiliary feedwater 11 AFW pump does not have a pump" to "12 auxiliary feedwater motor..
pump."
2.01 Change 3. to "Leop A/B crossover Corrects for errors in valves A and B close (normally system description B35 closed)". Change 5. to " Containment fan coil return orifice bypass valves open." Add 6. "CRDM heat exchangersupplyandreturnsalves close, l.
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g Answer Change Reason
'2.02 AIdd " shutdown Auto" as selector Provides additional correct switch position, answer.
2.04.(c) Add "No~86 lockout'present." Provides additional correct
' answer.
2.08 Accept "95 psig and 100 psig" as Provides alternate correct setpoints. setpoints. ;
i 3.04(a.1); Add "or P10." Provides' alternate correct i answer.
L3.05(a.3)' Add"orpressurizerpressure." Provides alternate correct, answer.
3 05(c.2) Add "or rod stop." Provides alternate correct answer.
3.06 :1, 5, and 6 Delete "from train A." Includes trips from 20/AST1 Add 10. " Auto.stop header pressure and 20-ET solenoids.
less than 45 psig." Add.11. "HI-HI Solenoids 20-ET backup, level in low pressure feedwater
. 20-1-0PC and 20-2-0PC do not heater." cause turbine trips, 5 01 Partial credit for calculations Proper equation was not which do not use rho dot. 'provided.
5.02 Delete last sentence. Information not asked for by the question. l 5.03(b) Add "(24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after trip)." Corresponds to how informa-tion is taught.
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5.05(a) Delete "or Sm." Sm affect is offset by Pu 1 buildup. I J
5.07. Change "1077" to "1075" and "8.4 F" Corrects setpoints given in. -J to'"8.13 F." plant information summary book.
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'Nnswer Change Reason 6.03(c.1) Change " running" to " breaker closed." Clarifies answer for breaker i
. i. lockout signal. 1 I
j ;7.01(a)- Change. "2 ' minutes" to '!90 seconds." Provides proper delay time.
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7.03 Add "if.no SI pumps'are running and -Additional correct answer RCS pressure "> 1200:psig." from the lesson plan. .]
1 17.04 " <:60 psig" not' required for full Information not asked for.by 'l credit. the question. ;
8.03(a) ;Second R0fshould be shown in Unit 1.
Second RO is required on Unit that trips.
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'8.03(c) . Add "0SC'and HQEC." Both centers will be manned during an Alert.
8.04 Add:" secure card-log" to'part a. Cards will be attached to Add'" hold card log to part b. control room switches.
'8.06(b) Delete " tornado." Add "or Alert if Allows alternate tornado-is assumed to hit site." ' classification based on assumptions.
.8.06(c)' Add "or Alert based on LOCA >50 gpm, Allows alternate fuel failure and ECCS actuation." classification based on assumptions.
'8.07(a)- Change to " Axial flux out of band for Provides correct values for over I hour [1.5]'. . Reduce power._to axial flux readings provided.
< 50% [0.5] and high neutron setpoint
-< 55% [0.5]."
8.07(b) Change to "3:30.the next day." Provides correct values for axial flux readings provided.
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MASTER COPY fcf ;.
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION ,
1 FACILITY: PRAIRIE ISLAND 1&2 REACTOR TYPE: PWR-WEC2 l DATE ADMINISTERED: 87/06/16 EXAMINER: VICTOR, F. I CANDIDATE: J i
INSTRUCTIONS TO CANDIDATE:
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Read the attached instruction page carefully. This examination cepl aces the current cycle facility administered requalification exam nation. )
j Retraining requirements for failure of this examination are the same as j for failure of a requalification examination prepared and administered by j your- training staff. Points for each question are indicated in i parentheses after the question. The passing grade requires at least 70% '
in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25 4Z 15.00 25 4 910 1. PRINCIPLES OF NUCLEAR PJWER PLANT OPERATION, THERMf DYNAMICS, HEAT TRANSFER AND FLUI) FLOW 2 S.42 15.00 ,% GO9( 2. PLANT DESIGN INCLUDIFG SAFETY AND EtiERGENCY SYSTEM 3 25 4Z 15.00 ErGa#f_ 3. INSTRUMENTS AND C0f TROLS
- 4.00 a3.73
-- 15. 00 i#r ?" 00@ 4. PROCEDURES - NORM /.L. ABNORMAL, EMERGENCY AND RAfl0 LOGICAL CONTROL 5't .o o 60 nn #3 % Totals Final Grade 1
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature l
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS a '
' 'During the. administration' of this examination the following: rules apply:
- 1. ' Cheating Don thel examination means an automatic denial of your application and could result in more severe. penalties.
2.- Restroom trips are to be limited.and only one candidate at a. time may leave. You must avoid all contacts with anyone.outside the examination froom to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions. j
- 4. Print your name 'in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on'the cover sheet of the examination (if necessary).
- 6. Use only the ' paper provided. for answers.
7 Print your name.in the. upper right-hand corner of the first page of each section of the answer sheet.
'8. Consecutively number each answer sheet, write "End of Category. " as
' appropriate, start each category on a new page, write only on o_ne side {
i of the paper, and write "Last Page" on the last answer sheet.
'9 . Number each answer as to category and number, for example,1.4, 6.3.
10.. Skip at. least three _ lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face
'down on your desk or table.
- 12. 'Use abbreviations' only if they are commonly used in facility literature.
,13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth nf answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE 1 QUESTION AND 00 NOT LEAVE.ANY ANSWER BLANK.'
- 16. If parts of the examination are not clear as to. intent, ask questions of the . examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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- j8. -When you complete your examination, you shall:
- a. Assemble your . examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions, i
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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l l1.' PR,1NCIPLES'0F NUCLEAR-POWER PLANT OPERATION, ~PAGE 2 l- [g . HERM0 DYNAMICS, iiEAT TRANSFER AND FLUID FLOW 4 -> ...
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, QUESTION .1.01- -
.(2.00)'
.WHAT 'is the- adverse effect of'having a large negative DELTA-I and WHAT operator action'would be required? (Assume rod control stays in-
- automatic.).
. QUESTION 1.02: (3.00)
The relative worth of a control rod is dependent on the neutron flux reaching. it. ' LIST and, briefly EXPLAIN four (4) factors or conditions
'which affect the flux reaching a particular control rod. (Do not include power level .)
. QUESTION' 1.03 (2.50)
- a. . Where in the reactor core (Top, Bottort. or Center) is nucleate boiling most~ likely-to begin~ and state WHY it starts there rather than el sewhe re? .
.(1.5)
- b. -What "is the effect on heat transfer of entering a nucleate boiling condition from a non boiling condition? (1.0)
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-QUESTION 1.04 (1.50)
The heat output of the . reactor.can continue to cause the fuel to heat up following a reactor shutdown. WHAT is. the source of this thermal power,
. and WHY does. it NOT indicate on ~ the nuclear instrumentation?
-QUESTION. 1.05- -(1.60)
List the.four factors that must be present for natural circulation to
. occur.
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(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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11 ~. 4 ' PRINCIPLES 0F NUCLEAR POWER PLANT OPERATION, PAGE- 3 <
< Q. THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
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1 QUESTION: 1.06 ( .70) j Unit' ONE is prepared for startup after refueling. Keff = 0.95 and count {
rate is' 10 cps with all rods inserted. The operator pulls the shutdown -1 l
banks - fully out, adding + 3.5% dK/K of reactivity. Without further operator action, nuclear power will: (Choose the one correct response)- 1 A.. Continue' increasing until the fuel or moderator temperature increases.
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B. Increase to a new equilibrium count rate depending on Keff and source.
~ neutron' level .
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C. Increase until' the positive reactivity addition is offset by the 'l Isothermal Temperature Coefficient. l l
- D. Increase while rods.are moving but will decrease by an observable a amount as soon as rod motion stops. }
E. ' Increase while the rods are moving, but decrease back to 10 CPS j after rod motion stops. ~
QUESTION. 1.07 ( .70)
Which'one of the following statements concerning the _use of water as the moderator is correct?
L A. ' Water has a HIGH scattering cross-section, a LOW absorption cross-section,:and a SMALL energy decrement per collision.
B. ' Water has a LOW scattering cross-section, a HIGH absorption cross-section, and a LARGE energy decrement per collision.
C. Water has a HIGH scattering cross-section, a LOW ' absorption cross-section, and a LARGE energy decrement per collision.
D. Water has a. LOW scattering cross-section, a HIGH absorption cross section, and a- SMALL energy decrement per collision.
. QUESTION 1.08 (1.60)-
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Briefly explain how a calorimetric (heat balance) is calculated. List I
the basic heat transfer equation used and list all heat sources or heat sinks which are used in the calculation.
(***** CATEGORY 01 CONTlHUED ON NEXT PAGE *****)
L1 - PRINCIPLES OF' NUCLEAR P0'ER W PLANT--OPER TION, :PAGE .4~
Q F 4 fHEW 0 DYNAMICS, HEAT TRANSFER AND FLUID FLOW-1 L f,' , i~s QUEST 10N.'1.'09 .('.70) . '
< Which one of the following.will!cause plant efficiency to increase?
. , A.. i Tota 1LS/G blowdown is changed from 30 gpm to 40 gpm...
B. Steam' quality changes from 99.7% to 99.9%..
- C. Level increases to higher than normal
- 1evel in a feedwater heater.
'D. : Absolute condenser pressure changes ~ from 1.0 psia to 1.5 psia.
QUESTION 1.10- (' ' . 70 )
Concerning equilibrium Xenon-135 (Xe)L reactivity, which one of the c following ' statements is correct?
. A. 50% equilibrium Xe reactivity is about one-quarter of 100% equilibrium Xe reactivity.
B. 50%. equilibrium Xe reactivity'is.about one-hal f of 100% equilibrium
. 'Xe reactivity.
C. 50% equilibrium Xe' reactivity is about three-quarters of 100%
equilibrium Xe reactivity.
D. . 50% equilibrium Xe reactivity is about equal to'100% equilibrium Xe reactivity.
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(***** END OF CATEGORY 01 *****)
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2.- PLANT DESIGN'LINCLUDING' SAFETY AND EMERGENCY SYSTEMS PAGE 5
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' QUESTION: 2.01 (2.00)' l 1
O State FOUR automatic actions which occur within the Cooling Water. System upon receipt 'of' a safety injection signal- .
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' QUESTION 2.02 ' ( 2. 00 ) .
- a. List. the TWO control board switch positions and the THREE-plant l conditions that would cause the motor-driven' auxiliary feedwater
, pumps to start automatically. .
(1.5) l
.b.. What additional condition will automatically start' the turbine-driven (
' auxiliary feedwater pump?. (0.5) ')
l; QUESTION 2.03 (1.50)
TRUE or FALSE l
- a. The steam generator PORV fails closed on loss of air pressure, but fails ' 'l as is on. loss of power to the air supply solenoid.
- b. The steam, generator PORV can be controlled in either auto or manua'l from j)
.the control room or from the hot shutdown panel.
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- c. Each MSIV is equipped with two air accumulators which provide air ;
pressure to shut the MSIV when a trip signal is received. i 1
QUESTION 2 04 (2.70) i
.a.- Describe the design feature t' hat provides additional RCP radial bearing heat removal during plant startup and shutdown when RCS pressure is between 100 and 1000 psig. (0.5)
- b. . List TWO conditions- that could result in a low level alarm on a RCP standpipe?: Do not include leaking standpipe or loss of seal injection.
(1.0)
- c. List TWO interlock conditions that must exist for the RCP breaker to L
.close when the RCP control switch is placed in START. (1.2) i I
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
. 52. > ' PLANT DESIGN -lNCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE. 6 f, - .
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.-QUESTION 2.05 (1.80)'
' List the electrical bus which DIRECTLY supplies power to each'of'the
.-following ' components :
' Exampl e: Cooling water. pump #21 ---> 4160V bus 23 Ja'. . Residual-heat removal pump #11 b.1LCondensate pump #23
- c. Auxilfary'feedwater pump #21
'd . - Containment. spray pump #12'
- e. Feedwater pump #12
.f. Component Cooling pump #12 [0.3 for each answer]
QUESTION 2,06 (2.00)
. List the FOUR accident conditions that form the design bases of the ECCS.
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QUESTION 2,07 (1.50)
Answer the following statements TRUE or FALSE concerning the Fire t Protection System,
- a. With the #121 Fire ' Pump control switch in the PULLOUT position, the pump.will AUTO start on low fire header pressure unles: the pump circuit breaker is open. l (0.5)
- b. During MANUAL start of the Diesel Fire Pump, an ' interlock prevents i the operator from cranking the engine for longer than 30 seconds. (0,5) i
- c. If the.D.C. voltage for one of the Diesel Fire Pump Battery Banks drops j to 18 volts, that battery bank is blocked and will not be used in '
subsequent engine cranking cycles. (0.5)
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(***** CATEGORY 02 CONTINUED ON NEXT PAGE ****)
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2.. PLANT DESIGN I'NCLUDING SAFETY AND' EMERGENCY SYSTEMS PAGE~ 7
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QUESTIO.N 2.08 .(1.50)
LDescribe the~ automatic ' operation of Instrument Air Compressor #123 when
,its' control . board selector switch. is ,in the PREFERRED position. Include in^your; answer starting, stopping and loading sequence.
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' 3.' INSTRUMENTS AND CONTROLS PAGE 8
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QUESTION 3.01: (2.00)
For each of.'the following situations, indicate the initial direction of.
travel for the feedwater regulating valve FCV-466 (answer either OPEN, CLOSE'or NO CHANGE). Assume that the' plant is initially at steady state full power and that' FCV-466 is in AUT6. Consider each action independently,
- a. An' inadvertent SIS actuation.
- b. Controlling first stage pressure transmitter fails high.
c.: Controlling steam generator pressure transmitter fails low.
- d. Controlling feed flow transmitter. fails high.
- e. Steam generator level transmitter (LT-461) fails low.
QUESTION 3.02 (2.40)
' Refer to' figure 3-1 attached, " Intermediate Range N35 & N36".
On your answer sheet, label each arrow on the figure assigned a number
-(1-8). Include name, coincidence and setpoint (if applicable).
' QUESTION 3.03 (2.00)
- a. What feature of a pressurizer Power Operated Relief Valve (PORV) prevents inadvertent opening of the valve when a controlling pressure transmitter fails high? (1,0)
- b. During cold shutdown conditions, how is the RCS protected by the PORV from an Overpressure Accident? , (1.0)
QUESTION 3.04 .(2.00)
- a. List- the-TWO inputs to the P-7 permissive interlock including setpoints and coincidence,
- b. List the FOUR at power Reactor Trips blocked by P-7.
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(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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>3. > INSTRUMENTSLAND CONTROLS- PAGE' 9 s
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SQUESTION 3.05- -(2'10).
a'.1.ist the FOUR plant parameter input signals to.the Overtemperature Delta-T, Protection circuit. (0.8)
' b. What condition will the .0vertemperature' Delta-T Reactor Trip provide
. protection against? '
(0.5)
- c. What TWO protection or control' functions other than Reactor Trip does the Overtemperature Delta-T instrumentation. provide? (0.8) i
'QUESTIONi 3.06 (2.00)
'Oneof the main steam turbine protective tripping mechanisms is a solenoid trip devices List'FIVE signals that will :=;i::- the solenoid and thusi {
cause'a' turbine trip. A CTvMS '
' QUESTION 3.07- -(2.50)'
.a. Explain what effect the loop A control Thot RTD failing OPEN will have on the; Control Rod System. Include the signal processing logic. -
'(Assume rod control'in automatic.). .(2.0) 1
- b. Explain how a failed Thot channel can be eliminated from affecting Rod I Control. (0.5) l 1
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i 4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND l
PAGE 10 1
., . RADIOLOGICAL CONTROL l l ,
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QUESTION 4.01. (2.00)
List FIVE changes to the Safeguards Systems that must be accomplished to
. transition from Hot Shutdown to Cold Shutdown operations in accordance j uith procedure C1.6, " Shutdown Operations". (Only one unit at Cold Shut-l down.) '
QUESTION 4.02 (2.00)
According to procedure 1ES-0.5, " Natural Circulation Cooldown with Steam Void in Vessel (without RVILS)": i
- a. If a Reactor Coolant Pump (RCP) can be restarted, pressurize level should be greater. than 90%. Explain the reason for this high level requirement.
(1.0)
- b. If a RCP cannot be restarted, pressurizer icvel should be between 20% and 25%. Explain the reason for this low level requirement.
(1.0)
QUESTION 4.03 (2.00) j According to ' procedure 5AWI 3.10.1, " Method of Performing Independent Verification", describe the steps required for an operator to independently !
verify that a manual valve is in the correct position. Limit the explanation to OPEN and CLOSED positions.
J QUESTION 4.04 (1.50)
Answer the following questions regarding procedure C1.2, " Unit Startup Procedure":
- a. WHY does step 3.3A require oxygen to meet chemistry specifications prior to exceeding 180 degrees F? (0,5)
- b. 'WHY does the temperature downstream of the PORV increase to about 259 degrees F and stablize as a steam bubble begins to form in the pressurizer?
(1.0)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
i
-y, 4t ' PROCEDURES - NORMAL, ABNORMAL,-EMERGENCY'AND
~ PAGE 11-e . RAD,10LO61 CAL CONTROL
..y ,
LQ UESTION 4;05' l2.50) l
.r Emergency Procedure.1ECA-0.0, " Loss- of 'All AC Power", has a caution '
which states that the'.non-faulted Steam Generators should be depressurized' as' quickly as possible,'but in a' controlled manner. It also states, "Do. {
not: reduce RCS core: exit- TC temperature below 320 degrees- F."
- a. Why is the rapid 'depressurization of the SG performed? (1.0) b.' Why must this~ rapid depressurization be slowed or-: stopped if.
,". , . wide rangeL SG. level cannot be maintained above 60%?. (1.0) c."Why is the RCS temperature decrease stopped when core exit TC
. temperature reaches 320 degrees F? (0,5) 4.
P i
QUESTION 4i06.- (2.00) i l
- a.; Emergency Procedure 1FR-S.1, " Response to Nuclear Power Generation /ATWS" L step 4.'of. IMMEDI ATE ACTION requires initating Emergency Boration.
-Explain how Emergency Boration of the RCS is accomplished. (1.0)
'b, List TW0. methods l of rapidly borating the RCS other than by Emergency 1
' l Bo ra t ion. (0.5)
< WAT action. if rata' y is canoired to adjust the emeroencv hnr=tkr. n u,. N 1 (0.5)
QUESTION 4.07 (1.50)
According to procedure C1.8, " Shutdown From Outside The Control Room",
list the.. actions that should be taken by the Unit 1 PE&RO. Include those actions that would be taken in the event that conditions do not permit.'coropletion of Control Room actions, p ,
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) ,
l
(. .
in .' ", /- .
iyi, PR'0CEDURESi h
J4. NORMAt/, ABNORMAL, EMERGENCY AND PAGE 12:
. g ; RADIOLOGICAL CONTROL
- 1. ,
1; ..H c:.
.:.. r y
' QUESTION 4,08
'(1.50) .
With . Units '2_at.100%' power, indicate for each of the followin'g
? 1 separate situations whether Unit 2 should REMAIN AT POWER,-REDUCE o" POWER,; SHUTDOWN, or bel TRIPPED.
1
- a'. " Operational Basis Earthquake" annunciatorfis- received and j
- .
- confirmed by; thel graphic recorder.
-)
b
- b. .Two fulI 1ength control rods drop into the.c' ore.
- c. It is' established that a loss of containment integrity has l
.t, foccurred. i
!i j
l 4
/
l L
L.
(***** END OF CATEGORY 04 *****)
(************* END OF EXAMINATION ***************)
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70712220 TF 29906911 7417383837 1593704714 35711122 25689012 2344556677 8889900011 22222333 3333333333 3333344444 s . 5 s n 6 3 5 ei 850 9 r
Pg p 02500D60 00000000 0000000000 S O0015o45 0000000000 00000000 0000000000 0000000000 s/ t11 23456789 0123456189 01 23455189 b Lb 111111 1 111 2222222222 A
>E
r 397114 2362001483 t . e g 334680 3693715933 0754334456 8901 11 0690 557839322 aps 765433 2100998776 3727272727 2738388766 429501731 Sa 444444 4444333333 6554433221 1009987654 320986336 V 111111 1111111111 3333333333 3332222222 222111100 1111!11111 1111111111 111111111 y
p' .
e , 886827 0193264619 r p g 743357 1595174195 0307782617 5219863800 a 5320988776 6665555443 671151020 v s t 319753 2087643209
- n 887777 7766666665 8765321098 7654320864 074919680 E E 555555S544 4444444333 297428440 000000 0000000000 322221100 0000000000 0000000000
.d g 001388 691222 2179847874 21975307 41 0366652949 3702457891 000000000 976888412 ta iu s 346789 0112345567 8406284950 6172722223 345682151 S iq 666666 7777337777 7899001123 34455E7890 123457936 000000 7.373888888 3888888889 999999900
_ l 0000000000 0000000000 0000000000 000000011 t
.r o e 873788 a ph 3404790108 6283814566 6306035227 307883360 444321 0986421974 2075207418 Sa 000000 0999999888 5295280233 116 V 222222 111111 2111111111 1111111111 8877776665 1111111111 1111111111 5544433210 111111J111 329590'930 985532 000000999 111111I111 111111 y
lp p h
a abig 513092 8657049520 8645.444332 1862827308 6631343I0 v 753200 9999000123 3456789012 t
n E 654321 9876654321 0987654432 3345566664. 172548960 E 777777 6666666666 6555555555 1098764208 63135165 5544444443 3332221
.d g 359796 t i a u 9847761589 8638330245 5554318520 Siq h 790111 0986420741 8528518406 75371,805 346789 0012345567 7899011233 2840623579 14705145 l 444444 5555555555 5555666666 4456678901 34578027 6666E66677 77777888 -
r
.o g 927536 9621564835 6178191517 tap
- 767745 4909092574 5937110450 3128011236 804500238 171985 9830252002 5951976556 1657430737 619020567 Sa 324605 0630742086 4210870543 7802535210 01 345460 V 098776 6555444433 333.3222222 211098765411 22221111 3211 098755 e 100O00 0000000000 -
1111 00000 m 0000000000 0000000000 000000000 l
u o 473?15 0978467393 V p fg 288610 8096634651 6201425938 3081965367 925183110 a 271985 0257873547 6956968008 v v 102483 8819040880 8417520754 3728332111 2357928642 076757790 211110710 ic E 098766 2097654321 0987664321 f
100000 5554444333 3322222222 211!111111 098765310 ic 0000000000 0000000000 0000000000 100000000 e 000000000 p
S 454320 579135 9753197542 0987766778 0257155970 t.i u d g 999000 6502457913 0011!11122 5680246802 2223333344 5791461629 989428128 532362877 111222 2222222222 4445556677 890124640 a q v 000000 0000000000 2222222222 2222222222 223333345 Si 0000000000 0000000000 000000 0000000000 0000000000 000000009 L
0000000000 000000000 pr 814098 41 45983829 8227009753 209280 8229355281 2236206591 11 3623887 mha 3430725801 1085283481 e
t 676643 567890 0851840617 2727160493 7148252952 195923204 T F 444445 1123345566 7788990001 1222334456 839405055 5555555555 5555556666 6666666666 677899000 666666777 s
se n. i r
P g p 000000 900000000B 0000000000
- 000000 0000000000 000000002 S 505050 000000000G 0000000000 0000000000 s/ b 4!56;7 5050505050 505 0505050 0000J0008 i 7 18$9001 1 2 2334 4 55E57 5050500000 00000500C b L 1 1 1 1 1 1 11 1 1 111 11 7889901234 5578901 7*
A 1111 122222 22222333
>i o
a l e Table 3. Superheated Steam Abs hess ibl50 in 5at del I4*P4'8tW'
- 0'84'5 I4h4"i N' 641. Iempi Wattf Steam 208 250 300 330 400 858 $00 600 700 800 900 1000 1988 1200 98 26 44826 19876 248 76 298 Ph 348 26 398 76 493 76 598 26 698 16 198 26 898 78 998 76 (E8 ??
I101 74) = 0 01634 3336 397 h
5 4?? 4 AS? J 482 i SH 9 S41 7 571 5 6111 690 7 noJ 809 8 869 4 919 e 1sb 69 73 Il05 8 !!S02 1177 9 11957 3248 7 1748 8 12H I 1288 6 1316 1 1384 5 1497 le818 ISla t 1586 8 lir, '
s 0 1326 I Wil 2 0$D9 2 0841 2 1452 ! !445 2 1727 1 8983 22n7 2 2708 2 3144 23Mi f )t)4 2 fl96 2 4640 2 49' i So 5 , 37 16 8776 137 76 18776 237 76 ?V 71-8 337 76 43776 53? ?5 637 76 737 76 817 74 937 76 1037 ?6 1167 247 .b 0 0164l ?J U 78 14 84 il 90 14 96 ?S 40774 10873 114 21 116 IS Ut 08 h0 01 161 64 113 86 1678 19770 133 to ll31 a litt6 1171 7 3194 & I?lt 0 I?41 3 i?M 1 1788 P 1335 9 OM3 74116 1483 7 IS)4 7 15% 7 1639 6 s 0 D49 I 6443 1 sin l 90$4 89M9 I9%4 1 9943 20208 2 0460 2 0932 2 1369 2lH6 2 2159 2 2321 2IH6 2 Ji94 g, D UIIU e C ol639 38 47 38684 79 4193 56 19 4 % 4479988 e4
% 19 02706 79 54 Si c) M619 04 3%57790440679 606 79 606 79 706 19 806 M 906 79 1006 79 6303 49 00 Je fy 80 94 86 91 91 87 98 84 h
161?6 1143 ) 1146 6 11707 11917 1712 1 1740 6 1264 1 IP87 8 1335 6 43840 14134 1481 $ ISN 6 lu66 16396 s e 28% ! ?879 1 79/8 1 8273 18M3 1 8892 1 9473 1 9439 1 % 92 2 0166 2 0603 2 40!! 2 1394 2.lM1 2.2601 2 2430 Sh H H3 38 00 88 00 l18 to 188 to P18 0* 288 to J88 00 488 00 688 60 488 00 788 00 888 to 9N 00
- 0167 78 799 78 47 30 52 11 40 14 67 16 71 38 71 lil2 00s a 180 37 1150 $ 47 85 46 93 S1 00 95 06 $911 ti lt 6? M 5 Sllt ii%8 1864 1 78338 4808 is976111188459118;4) 17:1 1 9 9040 1763 l69263 !?87 4 13JS 7 11858 Hit? 1641 4 1634 3 h46 5 16144 4 $799 2 0177 7 9585 2 0969 2 IJ12 7 1676 22S3%
l $4
, 0?nfl 76 799 3697 86 97 IM 97 186 97 73ti 97 ?8697 386 97 46697 $86 97 61691 78697 886 97 946'll
@l'I H3I h 181 78 IISU 9 77837 29 899 31 919 33 M) Ji 9 ? ? 17 085 41986 45978 49 #64 $1946 57576 61 906 63 887 s 8 383? Ith? 1164 7 1191 6 til6 7 3D99 1263 6 1287 3 13n ? 11818 14332 4483 4 1634 5 IS86 3 M39 4 I 7839 I 8134 i 8437 l 87/0 1 8988 89242 1 9787 2 01$5 20%3 2 0946 2OW 7 1663 2 1982 pJI W 18 e 0 01681 70 047 22188 70 04 ??Put3%U1 ;) Mq00I??M 34,8H2 04 M4 372 64 4004 577 04 511M 77M4 871 64 971 0s n 196 77 11% ) 76 946 28 457 31 s&6 34 465 3i 458 40A47 43fM 46 470 49 40) t 0 33$8 4 1320 11676 1891 4 !?lle I?3e 7 17610 1786 9 13349 13835 1437 9 1481 2 1514 1 1963 un!
1747$ 17s0S 1 8141 18397 4 86H 1 8971 1 9397 1 98 )6 2 0?44 2 0678 2 0991 2 1336 21HS gg D
e 0 01691 16 101 99) 59 91 109 91 IS9 91 709 9'l PS993 35993 4 % 93 55991 6W 91 M9 97 8S491 95* 93 Q40 078 h t
7en v nm 0 JSJs 1 1141 16 gm% 8 pm7 17.A?9 W4% 19076 70pm107OfJ 71977$??UN 740 MIH4B) 77 Wi
% 7 29 W?% 41 17 148 14 714 17 t to 39 M4 Hath nH7 M7 Mw 1 1717 4 1s47 1 law I alas I a4n i A677 l 9149 4 9sna I Wil 7 0 vil 7 0144 ilon 7 soie D 4966 18 v 0 01701 11744 99 66 14%6 19%& N9H N94 449 H S49 M 64966 749 66 889 H 949 %
th0 341 a 218 9) la6e l 14 8:0 IS PS9 16 897 179H 18 9?9 Po ses ?? %I 74 9s? 76949 78 543 30 a m 3/ 4 'l 6 0 J682 66995 1889 0 17116 inis 1763 9 1744 0 0147 13410 14115 14478 Mid e bah l 1639 0 1 7334 ! !647 8 79J7 1 8/10 18467 1 8946 l 9386 1 9785 26179 2 0S43 1 0888 ? !787 gg $h gy gg, , 0 01708 11 896 40 71 90 71 140 11 190 71 240 73 NO 71 440 74 S40 FI 64071 740 14 840 71 940 79 6 278 03 (Mil I? 6W 13 %r 14 453 n JJ4 16 707 I? 939 19 66? Pt 379 23 092 24 803 M $12 78 ??0 s 0 3809 1 5872 H87 8 lil? 7 1237 8 1761 3 !?85 5 13139 138?8 1432 3 1481 1 1633 9 6860 1638 9 9 7152 1 7468 4 7768 1 8033 18M4 18??s 1 9214 1 9624 2 0009 7 0372 2 0117 71046 88 lh 37 JS 82 FS In M 18? M 737 75 337 75 43775 $32 M 632 M 732 76 83? M 912 FS
, 00016 10491 067 H1 6 236 14 If 69 8 1804 18818 12 674 13398 14165 15685 17 695 18699 20 199 71697 2J 194 74 689 8 0 3924 167bS 11 % 0 1211 7 1236 4 1260 8 !?83 0 13314 1382 5 14321 148? S 1513 7 n8S S 1614 8 1 6997 1 7312 1 7608 1 7883 1 8143 I P6N 1 9065 19476 1 9860 20??4 20%9 2 0899 49 $h G74 448 25 % M% 12$ % 17% 56 ??S 56 325 % 423 % 575 56 6?S % 725 % BIS % 9?S %
0 01721 9 399 9 til to 497 11 Pol al 892 0 $17 13 932 15 276 46 614 17 950 19 282 10 618 il 90 h' 743 49 1024 lis$ 4 !?lo 4 12M 7 1760 2 !?84 6 1333 3 1887 3 14)! 9 148? 3 IS33 6 IS8% 7 n)B 7 8 0 4021 i H18 8 6849 8 7173 1 1471 1774f i 8030 l 8492 8 8934 8 9345 1 9730 2 0093 2 04J9 2041 IE 5h 4281 02) 1998 68 98 I;S 98 168 98 718 98 318 98 419 93 S'8 98 618 98 718 98 814 98 91898 e 0 01721 8 384 8 769 9 424 40 06? 10 688 18 306 17629 43 741 14 94i 16 150 ! ? 3t0 18 549 19 846 h h0 71 lii41 IIBA l 1209 9 in49 !?S96 1788 1 13129 13A7 0 18317 148? 2 11114 IS85 6 16.15 6 8 0 4112 1 6586 16720 1 7048 !?N9 6 7628 1 7890 18J14 1 8816 1 9727 1 9683 1 9917 20J22 2 0612
$$ Sh 4287 011 , 0 01733 1793 6293 lif 9) 162 93 247 9) 312 91 412 93 $12 93 61793 787 9J 817 9) 982 Fl h 2 % 43 7 945 8 S46 9 IJO 9 102 10 767 il 381 17 48S 13 583 14 677 t$ 7ht M 859 17 948 t 0 4196 Il819 ID89 1234 7 17$91 1281 6 1312 6 13818 1411 $ 1487 0 ISU 3 nnS 1614 $
1 6608 8 6933 1 7237 I 7388 1 7788 8 82M 1 8740 1 9371 1 9S07 8 987 2 022 203 88 b 4292 113 e 00108 7174 7 79 5729 107 79 IS 7 29 20729 30729 40779 $07 79 60779 707 79 80729 90779 6 76? ?l (1776 ? ?S7 7 813 8 364 8 881 9 400 80473 11438 !! 446 13450 14452 M 412 16 450 8 0 4273 14440 1131 6 !?0ll e in)$ !?H S 1781 2 IU?3 1383 5 14313 1481 8 1333 2 1585 3 M36 4 16412 1 6829 1 7134 1 7417 1 7681 1 8168 1 8612 1 9024 1 9410 1 9774 2090 2 0450 h
88 e 0 01741 6 653 7 02 $77 195 0? 102 07 157 07 70702 307 0? 4070? 18202 60707 707 0? 80207 90701 U1# 881 h 6 67$ 7697 81% 8MF 9 615 10 % 7 1 t 41:4 17 417 u 317 64 251 n tel MI 61 1679 1 s 0 4344 56175 liso ) I?070 173? 1 IM79 178? ? 13119 1841 3 14111 1481 6 0330 68%7 1638 3 16J90 1 6736 1 7040 1 7374 8 1590 l 8077 l 8572 8 89M i 9321 1 9685 2 003l 2 0361 Sh 78 v 0 01148 6 705 4707 9707 14707 19107 297 07 39707 49707 $9707 49707 79707 89707 002 f 3) 6 %4 FD3 7 590 8 039 894 9 793 406M ll S?? 12.187 13 740 la no7 h 271 74 H A06 s 04418 16316 1206 0 H10 IMF) !?81 2 13316 D810 1410 9 1481 5 1512 9 1951 1618 7 4 % 40 len! 1 7237 I M04 1 7991 184J9 1 88S? 192J8 1 % 03 19949 2 0179
$n
,I e 0 01753 5 814 47 3g 97 3 las 39 89;39 29?19 392 39 497 39 592 19 691 M 79nt 997 19 1307 64) n 3 77 % libi 9 4 704 66e 7 074 7494 8 370 9in 9 943 10 750 11$$J 17 9 % la in
& 8 4434 1660 120s o ini7 I?% 7 1781 7 43313 0907 4430 7 1481 3 1617 7 IS45 0 % 18 1 46%4 16%8 4 7156 17a/4 1 7916 18361 1 8774 1 9161 1 95?6 1 9877 2 C/07
$h = Superhe81 f h = enthJipy, Blu per Ib v = Spetalic w0lume, tu il per lb s = entropy, Blu pel R per Ib B-3
t
? o Table 3. Superheated Steam-Co77tinuect Ans hess.
L td50 in *
$41 set Temper 81u'e - Degrees f eheenheit 1541 lem0) werev $leam 35g 480 458 500 550 600 700 800 900 1000 1100 1780 1300 saac SA 88 1312 04) 37 % 8796 13796 18796 23796 28796 38796 48796 $4796 68796 78796 88796 98796 v 0 01757 $471 5 801 6 718 6 672 7 018 7 408 7 794 8 560 9 319 10 075 10 879 ll S81 h ?&2 ti 18411 1704 0 1730 5 I?n t 1781 3 1306 ? 1330 9 1380 5 1430 5 14811 1131 6 the 0 4534 1 6708 1 6413 1 6790 1 7080 1 7349 1 7602 1 7842 18289 3819 1 9089 1 945 05 0 16 ?61 e 0 01762 S 167 % 3374 445 8374 133 74 183 74 23374 28374 38314 483 74 583 74 68374 78374 483 74 983 3
% 84 0 6 77) 6 $97 69M 7 330 8 057 8 768 9 480 10 190 to 898 il 604 !? 310 13 014 h 78652 il84 2 1703 0 12/9 7 175$ 5 1280 8 1305 8 1330 6 1380 7 1430 3 1481 0 l$3? 4 IS Shs 04590 1 6169 16396 16716 1 7008 1 7279 17$32 1 7777 48??0 1 8634 1 9028 13386 1.9 98 4320 28) h 7932 79 77 179 72 179 77 129 ?? 279 72 379 77 479 72 579 77 679 ?? 779 72 879 72 9 e 0 01766 4 895 6 !?8 $ 505 6 869 62?3 6 577 6 917 7 600 8 277 8 950 9 62 10 790 10 958 )1 ,
4 790 M 118S 3 1707 0 1278 9 1254 9 1780 3 1105 4 1330 ? 0800 14301 3480 8 !!)? 3 1584 6 Sh 0 4643 1 6113 1 6323 1 846 1 6940 t ill2 1 7467 1 1/07 1 81 % 88570 18967 1 9323 1 966 95 e 0 01770 4 651 ?%
4 84$87 75 87 5 70% $ %I174
$ 889 87617547
- 77) 6 548 ??5 787 2M 878477 37% 87 47% 87 $7587 67587 17587 875 47 97 07413) h 196 7818 9 133 9 747 10 380 11 012 il MI 4
294 70 1186 2 !?00 9 1778 1 I?%43 1279 4 130$ 0 1319 9 1379 7 6479 9 14R0 6 153? l !$8 Sh 0 4694 160h9 4 6253 16580 0 6876 1 7149 8 1404 1 7645 l 8094 4 8509 1 8897 8 9162 I 9 188 e 0 01774 d ell 27 4847718 !?2S18 172 186 772 716 61881327218 7 443 372 18 47?l8 $?? l8 67218 772 18 87218 97214 4 590 4327 871 8i 935 $ 766 S88 5 904 8 050 6 655 9 758 9 860 10 460 16 060
?18 $4 1887 2 1199 9 I??74 17S1 7 1779 3 1304 6 1379 6 1379 5 14?9 7 1480 4 1532 0 8 It's $ 4743 1 6027 16187 8 6$16 1 6814 1 7068 4 7344 3 7$86 1 8036 184$1 1 8839 8.9205 1 18% v 0 01778 a n?
h 18 63468 4 3$9 69061 11863 6 007 b lin 16861
$647 6 915214636 50e7687 046 63 368 62 465 63 56863 M863 76463 86863 96863 4338 37) 302 74 1144 0 1198 8 1726 6 1253 1 1278 8 13047 665 2 1329 8 741 0 816 9 389 9 961 10 532 7 1379 7 1479 4 1480 3 15318 IS8 ths 0 4790 8 5988.
h ?l 1 6127 (64% 467% I M31 1 7288 1 7530 1 7981 18396 8 8785 1 9164 1 9498 118 v 0 01787 eMA 0 34 791 h 4 649 li% 714 IM 4 468 777?) $ 16 E8 571 %7714SH7 716 76 70%% 76 6 7El36S ?] 4671 $6% 71 66% 21 76571 86% 21 96S 71 1 314 786 8 411 4 %l 9 %C7 10 tM J0% 80 0639 H97 7 Ima LM74 17m 3 iMil 137A 9 13 M O 147'17 1440 1 l$117 1584 1 16374 IHi Shs 04834 1 Stic I 6061 46396 i M98 1 6975 i FFJ) l 7416 4 1978 8 8344 3 8732 8 9099 8 9446 117 ill e 0 01785 3 881 319 974 26$
6197 111 97 161 97S211 1336 081 9$7 4 558 4 841 $ 119 M2 $91 917 til64M t? 36197 6 994 46192 56197 66197 76192 Sill? 96197 106l 7 $71 8 046 8 570 9 093 9 615 6 309 M 1189 6 11 % 7 121$ 6 1751 8 1277 9 13011 1324 6 Ilin 7 6479 0 1419 9 75316 1584 0(
a 0 4877 I Hl3 1 6001 16340 i M44 16912 4 7186 174h 4 7877 l 8194 88681 l 9049 I 9396 I 9727 2 Sh 178 8 73 58 73 158 73 M8 73 708 73 2%8 73 35873 M873 553 73 658 73 75813 858 73 958 73 1058 73 4341278 e 0 01789 3 ???5 3 7815 . 4 Or86 4 un0 4 6341 4 9009 9 M37 5 sal) 6 1978 67006 72060 7 1096 8?D9 8 7130 9 7134 6 312 58 1190 4 I195 6 1274 1 !?Sl 2 12774 1302 9 1328 2 5378 4 1478 8 14798 1331 4 IS83 9 1637 1 1696 3 17467 s 0494 3 6879 i $943 1 6286 8 659/ I 6872 1 7132 1 7376 8 78/9 1 8746 8 8635 I 9001 19349 I 9680 1 91 % 2 OJ00 Sh 130 167 5267 10767 157 67 20767 25267 35267 45267 H2 67 65767 752 67 85267 95? 67 1052 67 4347.33) he 0 01796 34544 3 4699 37489 4 0179 42672 4 415% d iS89 4 73A4 5 7118 6 18)& 664% tlH0 7981 8 0461 85033 9 318 96 1191 7 1193 4 1277 3 1249 9 1776 4 l'107 1 1327 $ 1377 9 14?8 4 84794 till t 1583 6 1636 9 1691 1 17461 0 4998 1 $813 4 5833 1 6182 1 6493 1 6!15 l 2037 1 7283 4.77J7 l 81% 18545 1 8911 182$9 1.8594 4 0961 2 0711 14 148 e 0 01803 37190 4696 %% 146 96 196 96 246 96 34E 96 446 % 546 96 646 % 746 96 846 96 94$ 96 1046 %
1353 041 6 374 96 1193 0 34%I 37643 3 952h 4 1844 4 4119 4 8388 % 299% $ 7364 6 !?09 6 60 % 7 0)e9 74652 7 4946 s 0 $078 157$7 i??o t 1748 7 3 ??S ) 1301 5 4376 8 13774 1448 0 1479 ) 1530 8 DIJ 4 1636 7 1690 9 17459 16@S 1 6400 19686 1 6949 4 7196 4.7652 1 8071 1 8461 1 8828 1 9176 1 9508 1 982) 2 0179
$A 118 v 0 01809 3 0119 4157 9157 14157 19157 24: 57 341 57 44157 S4157 641 57 74157 f4157 94157 (041 57 ';
058 438 t J300 1194 1 3 7208 345$$ 3 6799 1 8978 4 1112 . 4 5798 4 9421 6 3507 5 7568 6 6612 6 % 47 69%) 7 3 kin '
s 0 5748 lu95 7219 1 17474 177d 3 1300 $ 1376 1 1176 9 1427 6 14il 7 1530 S 1t83 I %n6 % 90 3 1 74s 7 1 % 993 16313 16602 16a67 1 7815 1 7573 1 7997 18183 1 8756 19099 1 9431 19748 2 0051
$h 188 v 9 01815 2814 16 45 86 44 13645 186 45 7364) 344$ 41645 5164% 6)645 7 % 45 7 % 45 916 45 10% 4$
0 63 %# h 336 0/ 189S 1 3 0060 3 2788 3 4413 36469 3 8480 4 7420 4 679$ 5 0132 5 3945 $ 7741 61$22 4 6793 6 90 % J s 0 5706 I Wel 1217 4 1246 0 1273 3 12996 1375 4 1U64 I4272 1478 4 1530 3 lit? 9 16h 3 seOS 1745 6 i
! 5906 16231 16522 3 6790 4 70J9 11489 8 7919 1 8310 1J678 8 9027 3 935t t 9676 8 9980 Sh ]
170 s 0 0182: 7 673t 31 58 fl $8 131 $8 19' $8 23158 331is 43158 $3158 631 M 73158 83158 931 58 1011 58 1 % 8 42) 6 )43 24 11 % 0 2 st67 3 0788 3 7396 34?% 36nt 39879 an% 4 71 % S 0749 5437) $ 7888 6 1440 6 4933 4 i
9 S b7M 1 5598 1715 6 1744 7 3277 2 1794 8 1374 7 3375 8 1476 8 1478 0 11300 l$816 1616 1 1690 4 17454 5 1 5813 16152 46447 16717 I6%8 4 H28 1 7850 1 8748 .l a bl0 18959 1 9791 1 9604 6 9913
$n l
let v 9 018?? ? 5312 16 93 4 97 I?n M 1492 27A 97 3M 97 4M 92 57697 GM 9? 7M 97 876 92 SM 97 10M 97 }
(373 081 6 34619 11 % 9 2 t 474 ? ss08 3 0413 ) 77R6 34093 3 1671 4 1094 44508 4 7907 $ 1789 3 46$7 6 8014 6 1363 j 8 0 5318 1 % 43 12:3 8 1743 4 1271 ? I!97 9 1314 0 13 FS I 1476 3 14777 1579 7 1587 4 1635 9 1690 2 1745 3 )
l b743 1 6074 1 6376 1 %4i 16900 I D62 1 7744 1 8176 1 8545 14894 1 9227 1.9546 1 9849 i Sh W ill
- 0 01813 7 40m 2247 72 47 17747 17247 ??!G7 3??47 41747 S2741 67747 71147 81247 91247 1012 47 '
H77 5 J7 h JiD 94 1197 6
- 4%1 2 HIS 2 87 % J os?) 3 7146 3 not 38889 42140 e slo 4 8577 $ 1766 5 M49 5 site s 0 4384 65496 1712 0 1/47 0 12708 lall ll1J 3 1374 8 len t 14774 IS/9 4 IM?l 16357 1690 0 47431 l5%7 4 6006 l 6307 16581 1 AB)$ l 7199 8 7722 18115 4 8484 I 8834 1.91H I 9484 1 9789 8
j '. 288 0 01819 2 nr3 44707sa5480 2398 70 168 7774720 ns 70 !!8 28u9 10 318 l oss3 703694) m al 418 704 9180e08to 4ilt3077 20 718 to 818 a u18 70 9t8 4 9:n 20 1018
$ 2191 20 S hrog i 13818G 6 3Mt lits )
4 0 5438 1 3454 Ulo n 4240 6 1490 12 % 7 n)/7 6 ! ) 74 3 14M 4 14770 1991 1581 9 16144 16M9 4 1745 0 luu 3 H38 16747 I Mit 8 6773 4 7239 17%) 18bi 8 6476 1 8776 5 5109 1 9427 1 9717 j
)
Sh = super 7icat I h = eenhalpy. 0tu w ab v = specsta eclume, cJ fl per lb 5 = entfocy, Blu pet T per (b I
l B -4
/ e j
'a '
l Table 3. Superhealed Steam-Continued Ab9 Pres 5 lbl50 in Sal 541 kmov8twe-Deteces f ahtenheit
($4t tempi Water Steam 400 450 500 550 400 700 800 800 1000 1100 !!00 1300 1400 1500 Sh 14 09 68 09 114 09 164 09 214 09 314 09 414 09 514 09 614 09 714 09 814 (* 914 09 1014 09 1114 09 118 e 0 0l444 2 18?2 7 7364 2 4181 2 5880 2 7504 2 9076 37137 3 5170 3 8080 43007 4 3915 4 6811 4 9695 5 7571 5 5440 ;
0 85 911 4 359 31 11910 !?08 02 1239 ? 1248 0 1795 3 1378 9 43737 1425 l 1476 7 1528 8 1581 6 1635 7 1689 6 1744 8 1800 8 s 0 5490 1 5413 1 5522 15872 3 6880 4 6458 8 6)lb I 71G7 1 7607 I 8001 18371 88778 1 9054 1 9372 1 9677 8 9970 j Sh to 17 6012 110 12 160 I? 210 17 310 12 48017 510 17 610 17 710 17 810 !? 910!? 1010 67 tilo 17 l fit v 0 011150 7 0R*3 7 1240 2 7999 7 4638 2 6199 2 7710 3 064? 3 3504 36377 3 91?5 4 8905 4 4678 4 74?6 5 0173 5 79f t l (389 886 h 36417 1199 6 1706 3 1237 8 12 % 9 1794 5 1371 2 1373 2 1474 7 1476 3 1528 5 1588 4 1635 0 1689 4 1744 7 1800 6 ,
s C.5540 1.5374 1 5453 45808 46120 1 6400 1 6658 1 7128 1755J l 7948 8 8348 1 8668 I 9002 1 9320 1 96?S I 9919 l Sh 6 30 56 30 los 30 15630 706 30 306 30 406 30 506 30 606 30 706 30 806 30 906 30 1006 30 1106 30 238 e 0 038 % 1 9985 7 0?!? 2 1919 / 3503 2 %0R 7 646) 2 9776 3 70?O 347?6 3 7406 4 0068 4 7737 4 53 % 4 1984 5 0606 1393 101 h 36828 1100 1 1204 4 1236 3 1765 7 t293 6 1320 4 1312 7 1474 2 1476 0 1528 7 1581 1 1634 8 1689 i 1744 5 1800 5 s 05588 1 5326 1 5385 3 5747 ,16067 1 6344 8 6604 1 7075 1 1502 1 7897 1 8268 8 86t8 8 8957 l 9770 1 9576 8.9869 54 7 61 57 61 '102 61 152 61 20? 61 30261 407 61 507 61 60261 70761 80261 90261 1002 61 1107 61 I F48 e 0 01860 1 9177 1 9764 7 0978 7 746? 2 3915 7 H16 2 8024 3 0661 3 3759 3 5831 3 8)P5 4 0476 4 3456 4 5977 4 8492 ,
1317 391 h 37727 3200 6 !?07 4 1234 9 I?64 6 1297 7 lIH F 1377 1 1423 8 1475 6 15?? 9 1580 9 1634 6 1689 1 1744 3 18U0 4 '
8 0 5634 1 5299 i 5320 1 5687 1 6006 1 6798 1 6552 1 7025 1 7457 8 7848 8 8219 18570 1 8904 19223 l 9528 1 9372 l Sh 4903 99 03 149 03 19901 29903 399 03 49903 $99 03 699 03 799 03 899 03 999 03 1099 03 1 750 v 0 01865 1 8437 2 0016 2 1504 ? ?999 24?67 2 6877 2 9410 31909 34382 3 6837 3 9778 4 1709 44111 4 6546 1400 971 h 8
376 14 1701 l 0 % 79 1 5764
!?3) 4 1763 5 1791 8 1319 0 13716 14234 1475 3 1577 6 15806 1634 4 1688 9 1744 2 1800 ?
1 5629 1 5951 1 6239 1 6502 16976 4 7405 1 7801 18173 1 8524 1 8858 1 9177 1 9487 1 9776
$h 45 % 95 56 14556 195 56 79556 395 56 495 56 595 56 69556 795 56 895 56 9 % 56 1995 56 248 e 0 01870 1 7147 1 9173 2 0619 2 1981 23?s9 2 5808 2 8?% J 0663 3 3044 3 5408 3 7758 4 0097 4 74?7 4 4150 14D4 44) lb 379 90 1701 5 1736 9 1267 4 1290 9 1318 7 137t l 1423 0 1474 9 1527 3 1580 4 1614 7 1688 7 1744 0 1800 1 s 0 5122 1 5230 1.5573 13899 1 6189 1 6453 1 6930 4 7359 1 77 % 1.8828 1 8480 8 8814 1 9133 1 9439 1 9732 4
I th 4220 92 70 14770 197 70 29220 39270 497 70 59?20 69?20 792 20 892 to 992 20 1097 20 778 v 0 01875 1 7101 1 8391 19799 2 1171 7 7388 74874 2 7186 7 9509 3 1806 34084 36349 38601 4 08a9 4 3087 1407 811 h 383 % 1701 9 1230 4 1761 2 1290 0 1317 5 1370 5 14?? 6 1474 6 1577 1 1580 1 143s 0 168A 5 17439 1800 0 s C 5764 8 5197 1 Mi$ i 5848 8 6140 1 6406 16V85 I 7315 1 7713 1 2085 I 8437 I 417I l 9090 l 9J96 8 9690 5t 18 93 8891 138 93 18893 288 93 38893 488 93 588 93 68893 18893 88893 988 93 1088 p 288 e 0 01840 1 6505 1 7663 19037 7 0377 21%I 2 3909 2 6594 2 8437 3 06 % 3 28 % 3 504? 3 7717 39384 4:543 1411 0 4 h 38717 12C2 3 1278 8 1260 0 1789 1 1316 8 1370 0 1422 1 1474 ? 1576 8 1579 9 1633 8 1688 4 1743 7 179s d 8 0 5805 1 5866 1.5464 1 5798 1 6093 i 6361 1 684I I 7273 1 1671 18043 1 839% 1 8730 1 9050 1 9356 1.9649 P 15 75 85 75 135 75 185 75 285 75 385 25 48575 585 75 685 75 785 75 88575 985 75 1085 75 298 e 0 01885 1 5948 1 6988 18127 1998 7 0712 2 3058 2 5769 77440 29585 3 1711 3 38?4 3 5926 3 8019 4 0106 14la W h 39060 1202 6 1727 3 1258 9 1288 1 1316 0 1369 5 1421 7 1473 9 1526 5 1579 6 1633 5 1688 2 17436 1799 7 s 0 5844 15 35 I A412 1 5750 1 6048 8 6317 16799 8 7232 8 7630 18003 18J56 88690 1 9010 1 9346 l 9610 56 32 65 8265 13265 18265 28265 38265 482 65 58265 68265 78265 88765 987 65 8082 65 384 v 0 01889 154?P 1 6356 4 7665 1 8883 2 0044 2 7263 2 4407 2 6509 78585 3 0643 3 2688 34724 3 6746 3 8164 1447 358 6 39199 1202 9 1225 7 !?S17 1287 7 1315 ? 1368 9 1471 ) 1473 6 1526 2 1579 4 1633 3 1688 0 1743 4 17996 i s 0.5882 !!!05 15hl 1 5703 16003 1 6274 1 6758 1 7192 1 7591 1 7964 16J17 1 8652 1 8972 1.9 24 1 9572 '
i Sh 29 64 79 64 ,29 f a 17964 279 64 379 64 4is 64 579 64 679 64 779 64 879 64 979 64 1079 64 i 318 e 0 01894 1 4919 1 5763 1 7044 :8?33 19163 21520 2 3600 2 % 38 2 7650 2 9644 31625 3 3594 3 55 % 3 7509 1420 361 h 39730 1203 7 4224 4 1756 5 i286 3 1314 5 1368 4 1470 9 64732 1525 9 1579 ? 1633 1 1687 8 1743 3 17994 s 0 5920 1 5076 1 5311 15657 i 5%0 1 6233 1 6719 1 1853 17%) l 7927 8 8280 4 8615 1 8935 l 9241 19Db Sh 26 69 7669 12669 174 69 276 69 376 69 476 69 576 69 676 69 77669 87669 97669 10?669 378 e 0 01899 1 4480 15707 1 6467 1 7673 1 87?S 7 0873 ? ?84 3 24876 26714 2 8708 3 0678 3 7538 3 4438 3 6332 1423 3tl n 40053 1203 4 12?? 5 12 % 7 1785 3 1313 7 1367 8 1420 5 1472 9 1525 6 1578 9 1632 9 1687 6 1743 1 1799 3 s 0 59 % 1 5048 I 5761 1 % 12 1 5918 1 6192 i % 80 l Fil6 1.7516 4 7890 1 8?43 1 8579 1 8899 8 9206 8 9500
$h 2387 73 823 82 673 Bf 2738? 37382 47382 $73 82 67382 773 87 873 82 $73 82 1373 82 338 e 0 01901 14048 1 4684 1 5915 1 7050 1 8125 2 0I68 ? ?t 32 74054 2 5950 2 7878 2 9697 3 l54 5 33389 3 5227 1426 881 6 403 70 1703 6 1220 9 1254 0 !?84 4 1313 0 13673 1420 0 14725 1575 3 15787 1632 7 16875 1747 9 1799 7 s 0 5991 1 50?! ! 5243 i M68 1 5876 3 6153 1 % 43 1 7019 8 7480 1 18 % 88708 1 8544 I 8864 I till I 9466 Sh 21 01 71 01 'l2101 17101 27401 371 01 ilfl 01 571 01 671 01 771 01 87101 97101 1071 01 (
$48 e 0 01908 1 %40 14191 1 5399 6518 I M61 19%7 28463 F H13 ?!!75 2 7000 78811 3 0611 3 2407 3 4186 14?B 991 ti 406 80 1203 8 'l 1219 7 1252 8 783 4 13 t? ? 1366 7 1419 6 14772 15?5 0 1578 4 163? S 1681 3 1742 8 1799 0 8 06026 14994 1 5165 1 H25 5836 1 6414 16606 17044 1 7445 1 7820 1 8874 1J510 1 8831 1 9838 1 9432 Sh 18 ?? 64 77 11477 16871 76877 36827 46827 56427 668 ?? 76427 86827 %B 77 1068 77 118 e 0 01912 1 37 % 1 3725 14913 1 6007 1 7078 I 8970 7 0832 2769 2 4445 2 6719 2 1980 2 9730 31471 3 3705 44317JI h 46983 I?os 0 1717 5 1251 5 !?82 4 1316 4 1366 2 1419 2 1471 1 1524 7 1578 2 1632 3 1687l 1747 6 17989 s 0 h059 1 4966 Ball 9 1 5483 15797 1 6077 16571 l.700J 1 7411 1.1787 label 1 4417 1 8798 1 9105 1 9400 Sh 15 59 6559 115 59 16559 765 59 36559 46 59 56559 66559 765 59 86559 965 59 10 % 59 388 e Oo1917 1 7891 13;n 14454 1 M75 165?5 1 84? 2 :237 ??ms 7 37 % 2 5482 2 7196 2 8898 30597 3 7779 (434 411 h 411 41 4;oa l 1715 8 1250 4 1781 5 1310 6 1365 6 1418 7 14715 1574 4 1577 9 163? 1 1686 9 1747 5 1798 8 8 0 6092 34943 150?J l 5444 1568 8 6040 16U6 8 6976 1 7379 1 7754 8 4109 18445 6 8766 I 907J l 9368 Sh 10 39 6019 110 39 160 39 160 39 360 39 460 39 560 39 % 0 39 760 39 860 79 960 39 1060 39 188 e C oli?S 1 7718 1 y472 1 3606 1 4635 1 M98 174ig 1 9139 2 0875 7 2484 2 4 t?4 2 5750 2 7366 28473 3 0577
[ 44.19 611 h 41859 17c4 4 1212 4 12477 1279 5 1309 0 1%45 1417 9 1470 8 IM18 15774 1631 6 16n6 5 4747 2 1794 g s 061% 4 4494 84982 4 5360 8 % 81 15%9 I 6470 1 6911 1 7315 47692 3 4047 18384 1 4705 I 9012 1 9307 ( Sh = Supe <Ficat, I v = Sg@ tic voiume, to it per Ib h - enthalpy Blu pe7 lb s a entropy. Blu per R per Ib B -5 il
8 i
+ 1
- l. .
Table 3. Superheated Steam-Continued Abt Pres 8 - llu$0 in Set $al Tempe:8twe Degeres f ahrenheit ($4t lemon Water Steam 850 $90 Sie 800 $50 700 800 900 1000 1800 1283 1300 1400 15C0 Sh 498 S40 M 40 10540 1440 20540 25540 35540 8 % 40 55540 65540 7 % 40 855 40 9 % 40 10 % 40 1444 60) he 0 01934 (1610 11738 1 2843 1 3836 1 4763 4 % 46 1 6499 1 8158 19759 21339 2 2908 24450 2 5987 2 7516 2 424 17 12046 8208 8 1245 1 12775 1307 4 1335 9 1363 4 1417 0 1470 1 15233 3576 9 1631 2 1686 2 1781 9 Sh s 0 6217 14847 14894 1 5282 4 5618 1 5901 1 6163 1 6406 16850 1 7255 4 7632 8 7988 1 8326 186d 7 18955 1 479 60 5060 800 60 15060 200 60 25060 35060 45060 $$060 650 60 750 60 85060 950 60 10% f 3 1449 401 e 0 01942 11057 8 1071 12148 1 3113 14007 I a8% i % 76 a 1758 I 8195 2 0304 2179$ 2 3273 24139 2 6146 2 h 8 429 $6 1204 7 1735 2 1242 4 12754 130s 8 1334 s in?3 1416 2 1469 4 IS?2 7 1576 4 1610 8 168) 8 1741 6 37 Sh 06276 14802 34808 1.5206 i $542 1 5836 8 6100 16345 16791 1 7197 8 1575 1 7932 1 8269 8 3598 I 88 e C Gi950 10M4 4597 9597 14597 446 1 t517 5 2454 1 3319 9597 24597 345 97 44597 $8597 645 97 74597 84597 94597 1045 97
" 54 038 6 434 77 8204 8 4138 14926 1 644) 1 7918 1 9363 2 0790 2 2203 2 3605 24998 26)l4 s 0 6332 14759 1239 7 12734 1304 2 If!32 1 6474 1 5772 . 313 2 1368 4 14 th 3 18b8 7 li?? I 1575 9 1610 4 1685 5 1741 2 37977 6040 1 6286 16734 1 7142 1 7521 1 7878 1 8216 18SJ8 18847 1 9143 th 488 e 0 01959 1 0097 41 60 9850 14l 50 19150 241 50 34150 44150 541 50 64150 74150 84150 941 50 104113 6458 501 6 43983 1204 8 1 0939 1 1852 l 2691 1 3482 14242 1 $703 I 7117 1 8s04 1 9872 2 I??6 2 2669 21903 2 6233 s 06387 44718 12M 9 427L 3 1307 5 1331 8 1360 0 leid e 1468 0 IS716 1575 4 1629 9 1685 1 1740 9 179 ' d th 4 5060 1 5409 I 6784 i $982 162J0 I u8b i 7089 1 7449 8 1826 I 816S I 8488 18797 1 9093 488 3718 ~ 8718 3718 o 0 01967 0 9668 1 0409 1 1300 2115 18718 23718 33718 43718 $3718 63788 73718 83718 93718 1033 14 6462 82) h 444 75 !?Si 8 1234 4 1269 5 300 8 1788) 13615 I S623 16384 1 7716 1 9030 2 0130 2 1619 2 2900 2 4173 8 06439 I 4612 14990 t $346 L $662 . 330 $ that 14136 1467 A IS?0 9 1574 9 1629 5 1684 7 1740 6 179* 2
. $926 ii176 4 6622 I 7014 3 7419 i)?77 I 8116 8 8439 18748 1904$
lh 32 99 8799 13299 880 e 0 01975 0 9276 0 9919 1 079l i n84 8799 23299 332 99 43299 $32 99 61799 732 99 83299 93299 1032 49 6467.01) h 449 $2 1208 7 2327 1 3037 14397 IS708 1 6992 8 8256 1 9507 2 0746 2 1977 2320 1238 2 17670 12991 s 0 6490 14639 14921 1.5284 1559$ l 329 1 1157 7 1817 7 1866 6 1570 3 1$74 4 1629 1 1684 d 1740 3 1795 9 Sh 5874 1 6123 1 6578 1 6990 17J71 1 7730 1 8069 3 8J93 18702 1 8955 5?9 e 0 01982 0 8914 8893 7891 12893 h 0 9466 1932l l 1994 78 93 122893 1816 32893i Song not 1 3819 42893 S2893 I 6323 62893 1 1542 77893 62891 928 91 1028 93 18746 4471 071 454 18 1204 5 1278 3 f ?64 8 17974 9940 2 1175 2 2302 0 0 6$40 1 4608 377 7 IM65 1411 8 len t l$19 7 1573 9 1628 7 4840 1740 0 17% 7 44853 15221 0 $$39 h 5818 8 6072 a 65)0 16943 1 7325 1 7684 8 8024 I 8348 1(47 I8%4 Sh Se8 e 0 01990 0 8577 24 99 74 99 124 99 I74 99 224 99 3?4 99 424 99 514 99 624 99 f24 99 824 69 928 99 1024 '9 ti?$ 08) h 458 71 4204 4 0 904% 0 9884 1 9640 16347 17010 1 3284 1 4508 1 5704 1 6890 1 8042 4093 20136 2 14?) s 0 6587 14%5 1725 3 1262 5 1295 7 1326 3 13 % 3 Ia10 9 1465 6 1519 8 1673 4 1678 2 1683 6 1739 7 1796 4 14786 1.5164 1 5485 3 5767 1 6023 16481 4 6897 1 7280 t 7640 1 7981 18J05 1 8615 1 8911 Sh Sll e 0 01998 0 8?64 21 16 71 16 121 16 til n 22116 321 16 421 16 $2416 621 16 12116 821 16 928 16 8024 14 1878 841 h d6314 12042 08u3 0 9479 1 0217 1 0902 31%2 17787 1 3977 8 5129 1 6266 1 7388 1 8500 19603 2 05A9 s 0 % 34 14S?9 4222 2 1260 3 1291 9 5324 9 Ina2 1410 0 14644 I)18 6 1572 9 n27 6 n83 3 1094 1Mi 84720 t $106 8 5431 15717 1 5915 1 6418 4 68$3 1 7237 4 1598 .) 1939 1 8261 1 8573 4 8870
$h 188 e 0 02006 0 7971 1743 6743 11743 16743 21741 31743 41743 $l743 61743 11743 81783 91743 101743 4482.$71 h 46747 1201 9 08287 0 9100 0 9824 1 0497 1 1125 4 2324 1 3473 14%) 66H3 l 6780 47DS 1 8921 19W3 s 0 6679 8 4495 1219 8 1758 0 1292 1 1323 a 1353 0 1409 2 1463 7 4518 0 1572 4 16?? 4 1682 9 17J91 17959 14654 1 5049 1 5380 16%8 8 $929 i 6J94 1 6811 1 7196 1 7556 1 7898 8 8223 1 8513 3 8831 sh let e 0 02011 0 7697 1380 6380 11380 163 80 21380 3I180 41380 51380 613 80 76180 81380 913 80 1013 t0 4486 20) h all 70 1203 7 0 7944 0 8746 0 94 % 10 09 10726 1 1892 8 3008 . 3 4093 inno 1 6711 17M2 18:84 191e9 8 0 672J l 4461 121% 9 1255 6 3290 3 1322 0 IMI8 14083 1863 0 8517 4 1671 9 16270 1682 6 17M 8 17956 i AS90 1499J l $329 I 5628 i S884 4 6JSI i 6769 1 1855 6 7617 1 7859 8 8184 1 8494 4 8792 Sh 638 e 0 02032 0 7084 $46 %$16 10% ll 1 % 11 20511 30% ll 4051% S05 11 60% Il 70% Il 866 11 tos ta 100s li 1s94 891 6 48189 1702 8 0 7871 0 7954 0 8614 0 9?54 0 9835 1 0979 31%9 1 2979 13%9 i 4 444 15909 i 6n64 1 7813 8 4 6824 14381 1707 6 1749 6 178% 7 1318 3 1348 7 1406 0 1861 2 tili9 1570 7 4749 n8t 6 6735 0 17N 9 144J0 8 48$8 3 5207 1 $$0? I $77$ 1 6249 i M11 1 70S9 4 1422 1 7765 I 8092 4 8403 4 8708 Sh 108 e 0 02050 06%6 46 92 96 92 146 92 196 92 79692 396 92 496 92 $96 92 696 97 796 92 896 97 996 92 00J 081 h 49I60 1701 0 0 1271 0 79?8 0 8$20 0 9072 1 0102 8 1078 12023 1 7948 I J858 14767 1 %si 1 6530 a 0 6928 I 8304 1743 4 1781 0 1314 6 13e 6 3403 7 14594 8614 4 1%94 n24 8 n80 7 1737 2 37943 14726 1 $090 1 5399 I 5673 4 6154 1 6560 4 6910 1 7335 6 7679 4 8006 3 8318 8 8617
$h 750 e 0 07069 0 6095 39 16 89 16 139 16 78916 289 16 389 16 48916 $8916 689 16 789 16 889 16 989 16 61084) 6 600 89 1200 7 0 6676 0 7341 0 7887 0 8409 0 9386 1 0306 11196 8 2063 1 2916 131$9 1 4592 1 5419 6 0 7022 34232 6236 9 12761 1310 7 1342 6 1401 5 44S7 6 1512 9 IS68 2 n23 8 4798 17 % 4 17936 I oss i 4977 iSn6 1 5577 1 6065 l 6494 56886 1 1252 1 7598 1 1926 8 8239 185J8 Sh 888 31 79 e 0 07087 0 % 40 al 79 t 3179 181 79 281 79 381 79 481 79 581 79 68 79 789 79 881 79 981 79 61824) h 509 84 (199 4 0 6151 06714 0 7373 9 7878 0 8759 090) 19470 l l289 82093 I ?8M 1 3669 4 44A6 s 0 Flit Ian3 6730 1 1271 1 8306 8 1339 3 l399 1 64 % 8 IS19 4 1%69 1622 7 1678 9 873% 7 87979 1 4472 34869 i Sits iS484 i S980 8 6413 3 6807 I 7175 1 7622 1 7851 1Bnd I 8464 Sh 24 76 818 e 0 02105 0 5310 74 76 124 76 174 76 274 76 374 76 474 76 $74 76 674 76 274 76 814 16 974 76 1526 24) h S1840 1198 0 0 5683 0 6796 0 6829 0 7315 0 8205 0 9034 0 9830 1 0606 1 1366 8 2ll$ 1 2851 I M89 6 07197 14096 1723 0 170 9 !)02 8 1340 13 % 8 les4 0 nl0 0 t%$7 n26 6 1678 0 1734 9 17923 14347 14763 1 5102 153 % 1 5899 163J6 4 673J 1 7102 1 7450 1 7760 1 8;/34 1 8395 th 888 18 05 6805 }l8 05 168 0t 26805 368 0% 468 05 % 8 05 668 05 768 05 86805 968 05 i
e 0 0?l23 0 5009 0 31 951 h S?6 70 41 % 4 0 5763 O Sat 9 0 6388 018$8 0 7713 0 8s04 0 9262 0 9998 1 0720 1 1430 1 7131 8 282) 5 0 7211 14032 tilt S 4260 6 )?98 6 1132 7 1M44 14V 2 n08 $ 1%44 1670 6 -16771 1734 1 17916 3 4223 1 4659 iSolo 16314 1 $822 1 6263 I6%7 1 7033 3 7382 Jill ! 8078 I tilt Sh = 6upe7 heat. f h = enthaloy. Btu cer Ib V = 8pcCallC Volume. Cu il per Ib 8 == entF0py, Stu pel I per Ib i . B-6
l-1 ,
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Table 3. Superhealed Steam-Continued l Aos Press I ltdo in - Set $41 h*Dt'aluee - De8'ees Isheen%I 'l (Sal. Iempi Walel $leam 550 600 650 700 150 800 150 900 1000 1100 1200 1300 1400 1501
$n 8s8 1i 61 61 6l til6l l6t 61 til6l 261 6) SI)f t 361 61 46161 56181 66161 76168 86161 961 81 1538 39) he 0 0?l41 04711 04883 0 548$ 0 5993 0 6449 06811 07??2 0 76 % 0 8030 0 8753 0 9455 1 0847 1 0817 1 1484 12:43 s $14 74 1144 7 12676 lini 4794 4 1329 3 1361 5 1397 0 1421 6 I430 1 1070 l%31 1619 5 1676 2 1733 3 1791 0 0.7358 1 3970 14098 84%7 4 4911 1 5278 1 300 1 5748 i $977 1 6193 1 6395 16961 1 7317 1 7649 87965 1 8"67
$h 1800 542 M 42 10547 1%4? 20$ 47 7 % 47 30447 3 % 42 4% 4? 5 % 42 6 % 47 7 % 42 8 % 42 955 4?
(544 b8) he 0 02159 0 4460 04535 0 5137 0 5636 0 6640 0 64n9 0 687) 07245 0 7603 0 8795 0 8966 0 96?? 1 0?66 1 0908 1 15?9
$47 % 1197 9 1199 3 1749 3 1790 I i3h 9 1158 7 1189 6 44 l'l 4 1848 5 ho$ 4 l%l9 1618 4 16PS 3 1332 6 IN3 s 0 7434 i 3910 13913 1 4457 4 4833 1 5849 1 $426 i % 77 66908 16126 1 6530 16905 1 1256 17$89 8 1905 1 8?07 Sh tant e 0 07177 04??? 4947 9947 18947 19947 749 47 79947 34947 44947 54947 64947 74947 44947 94947 4%0 $3) n $$015 l1910 048h 05317 0 574) 0 614? O DIS 0 6877 07?l6 0 7881 0 8$14 0 9166 09767 1 0373 IF3 s 0 7$07 $ 3851 1243 4 I?85 7 13?? 4 13 % 8 4387 2 1817 3 1446 6 1503 9 1%07 1647 4 1674 4 1731 8 l?** 6 14358 14748 t hor? 15h4 1 % 06 I S842 1 6062 16469 16845 1 7897 1 7531 1 7848 1 8.51 5 54 1888 e 0 07195 0 4006 4377 93 72 18377 19377 24172 29172 14377 44177 S4177 64177 14377 843 97 U) ?2 {
($% 28) h $$75$ lisil 0 4531 0 5011 0 5440 0 5826 0 6188 0 633 0 6865 0 1S05 0 4121 08i23 0 9313 0 ?894 1048 0 7578 1 3?94 17373 1281 2 1318 8 93$19 l354 3 1415 7 1444 7 ISd? 4 l%94 1616 3 1673 5 1731 0 lif 9 0 l' 34759 1 8664 18996 1 6784 16547 1 5779 1 6000 1 6410 16181 1 7141 1 7475 1 7793 1 8;67 j Sh 1110 e 00??l4 0 3807 39 it 89 18 139 18 189 18 23918 2A918 339 18 439 18 139 l8 639 18 7J9 48 839 18 979 Il ' IS61821 h %d it litio 0 4763 04146 0 $l62 0 % 38 0 $889 0 6723 0 6$44 0 7161 0 ??54 0 8332 0 8899 G e4% im7 s 0 7667 1 3738 1230 9 1276 6 1315 7 1349 9 1382 7 34130 3447 8 )$00 9 IS% I 16l4 2 6612 6 1730 2 1:59 3 1 4160 14581 1492) 4 5716 1 5474 15711 45941 1 6353 1 673? I 7087 1 74?? I 7741 18x5 Sh l!88 e 0 0??37 0 3674 3?88 87 8I 132 81 187 81 237 81 787 81 337 81 432 81 S32 88 612 81 FW 81 817 81 91? 91 1567 191 6 $7185 1184 8 04016 04497 04905 O S??) 0 %I5 05939 0 6250 06845 0 7418 0 7974 0 8519 0 9055 0 9' M s 0 File 1 3683 1274 ? 1771 8 1311 $ 1346 9 1379 7 1410 8 1440 9 14994 1556 9 1614 7 1671 6 1779 4 1 77
- 9 1 4061 14$0i 14851 4 6160 l SelS I % 58 1 5883 1 6798 1 6619 I 2035 1 1371 1 7691 1 7916 Sh 1308 e 0 0??69 0 3799 ??$8 7?l8 I??S8 17758 727 58 777 $8 3?? S8 42758 5?? $8 622 58 ???SB 8?? $8 9?* !8 .
(577 421 h 585 % 1l89 7 OM10 04052 0 4441 04404 0 5179 0 5436 0 5779 0 6787 068?? 0 7341 0 1847 0 834% bHM 5 0 7843 l J577 1709 9 I?61 9 1303 9 1340 8 1374 6 1406 4 14171 14 % 3 1%4) 16t2 0 1%98 1727 9 17 4 ) 4 3860 14340 14711 1 $0?? I $796 1 6544 3 6773 1 6194 14578 1 6937 4 ??75 4 7596 1 7907 Sh 1439 e 0 9730i 0 3018 1793 6791 ll? 93 If0 93 Pl? 93 76793 31293 41293 $17 93 617 93 71291 84291 917 9) h 0 1175 03%7 040sq 04400 047t ? 0 $u04 0 6707 0 5809 06311 06798 0 F??? 0 7737 0 8:75 08707) $98 83 ll FS 3 s 07%6 1 3474 8194 1 175l 4 1796 1 1334 $ 1369 3 1407 0 14332 6493 2 1%IB 1609 9 1%80 1776 3 171$ 0 1 3652 34181 14515 14900 I $182 1 6436 8 6670 1 6096 1 6484 168JS 1.1185 17$08 i Fils sh 1508 e 0 07346 0 7772 3 80 $380 10380 l%)80 70380 25380 30180 40380 503 80 60380 70380 80180 9M+3 1596 201 h 611 68 1l 70 1 0 2870~ 0 3328 0 3/17 04019 04350 046?9 0 4894 0 5394 0 % 69 06327 0 6773 0 7210 0 '! N s 0 8085 1 3373 II)6 3 !?40 ? 1787 9 1328 0 1364 0 1397 4 1429 7 14901 1549 ? 1607 7 1666 2 1774 8 1713
- 1 3431 1 4022 14443 4418? 15073 15J33 4 5672 1 6004 1 6395 16759 1 7101 1 7475 l i?ia Sh 1648 e 0 07387 OMM 4%ll 9%l3 14% I) 1%I1 ?4513 ?% I3 3% I) s1S l3 5 % 11 6% Il 7% ll 8% !)
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- 08199 1 3774 I??83 I?ti 4 1321 4 8358 $ 139? 8 leh ? lea 6 9 8546 6 1604 6 1%43 177I ? 1 Jr !
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.T li .' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION,. PAGE 13 L* . THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
'[ - '
- p. . . : ANSWERS -- PRAIRIE ISLAND 182 -87/06/16-VICTOR, F.
ANSWER 1.01 -(2.00)- Too much power .is being produced in the lower half of the core which may result in exceeding hot channel factors and/or cause xenon
.~ oscillations.(1.0) Operator should borate (0.5) which moves'the control rods outward. and shif ts flux upward (0,5)
REFERENCE CNTO Reactor Core Control pp8-32 192005K110 ...(KA'S) { . ANSWER 1.02 (3.00).
- 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 poison concentration increased fewer neutrons. reach the rods. 4 Rod shadowing -' When adjacent rods are inserted, the existing 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 to which it is exposed. j 7 Core age - As the core ages, boron is reduced which causes rod worth - to increase.
- 8. Anti-shadowing - An inserted rod suppresses the nearby flux but i causes a : flux peak further out. A rod inserted into this peak I will have a higner worth.
(4 required at 0.25 for each factor / condition and 0.5 for each explanation)
.q J
REFERENCE-CNTO Reactor Core Control pp6-14 to 6-26 001000K511 001010K504 ...(KA'S)
- 1. ' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 14 1 s . THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
- h. -ANSWERS -- PRAIRIE ISLAND 1&2- -87/06/16-VICTOR, F.
i J ANSWER 1.03. (2.50) a,- ' Nucleate boiling is most likely to' start at the top of the' core or ' j fuel assembly.(0.5) because this is the hottest part of the core and 1 (1.5) i ( Cfurff.r.earer therefore 'd Csg6 cAc fnA9d conditions. saturation Wnw (1.0)#f/2o9FAnod) l b.; At the onset of nucleate boiling the heat transfer rate increases (due to the removal of the heat of vaporization and the break up of the laminar layer at the clad rurface). (1.0) REFERENCE Westinghouse _ T-H Principles pp3-75 CNTO Reactor Core Control pp8-19 L 002000K509 ...(KA'S) 1 i l ANSWER 1.04- (1.50) f
' Decay of fission products (0.5). !
It consists main'y of gamina radiation which are not indicated on Source or Intermediate nuclear _ instrumentation (1.0). f REFERENCE l Westinghouse'e Fundamentals of Nuclear Reactor Physics pp3-31 & 3-41 'i 192008K126' ...(KA'S) ]
' ANSWER 1.05 (1.60) l 1
- heat source
- heat sink
- elevation difference between source and sink {
thermal driving head between source and sink (dT or density difference) (0.4 each) REFERENCE Westinghouse T-H Principles pp14-16 000074K103 193008K121 ...(KA'S) l l I l 1 l
. .J
1 ' PRINCIPLES OF '10 CLEAR POWER PLANT OPERATION, PAGE 15
., T_HER fDYNAMICS, HEAT TRANSFER AND FLUID FLOW . ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-VICTOR, F.
ANSWER 1.06 ( .70) B. Increase to a new equilibrium count rate. ! REFERENCE Westinghouse Fundamentals of Nuclear Reactor Physics pp8-14 001010K508 192008K104 ...(KA'S) l ANSWER 1.07 ( .70) C. High scattering cross-section, Low sbsorption, Large decrement REFERENCE-f Westinghouse Fundamentals of Nuclear Reactor Physics, pp4-77 j 192001K105 ...(KA'S) ! l ANSWER 1.08 (1.60) 2 j The heat removed by the Steam Generators is calculated from feedwater ] flow times the difference between steam enthalpy and feedwater enthalpy. ! Qd(h-stmminush-fw) (0.7) Subtract blowdown losses (0.3) i Subtract RCP heat (0.3) I Add letdown losses (0.3) ! REFERENCE Westinghouse T-H Principles ppl3-40 to 13-43; P.I. Exam Bank 015000K504 ...(KA'S) l ANSWER 1.09 ( .70)
--B.--
REFERENCE , Westinghouse T-H Principles pp7-67 l 193005K103 193005K104 ...(KA'S)
- 2. -PLANT DESIGN INCLUDING SAFETY'AND EMERGENCY SYSTEMS PAGE 17 A'NSW'ERS' '- PRAIRIE ISLAND 1&2 -87/06/16-VICTOR F.
ANSWER 2.01 (2.00) l
.1. ~ System isolates into two headers with the vertical motor driven I pump lined up to supply the unit that initiated the SI.
2 Both diesel driven cooling water pumps start. 4.r.
- 3. :. Tu L . ..c bu il d i .iu l,en ' . l5el init h tcd thc M. fkTLod $e'ien p :chw .el art
.i cl 4escaVaws enAwo thc Buni camt that(Nsxmsay carro) 4 All _ cooling water inlet and outlet isolation valves on the containment fan coils open for the unit initiating the SI.
.e ,---a ..,s - - - .. - - . . s u ...u .u u sus,sa su e, NY 5 b5?r5NfN$ h c5ll SruN 5/k/52 Y SSE YWON E ti. C ADM MfAr ffrpAH6R wm' An tltim/ [4 required 0 0.5 ea.]
VAutS C L otf. REFERENCE P.I. 50 B-35pp34j 076000K101 DVG Nf-i'03tS/j M2 ydt(sf-pgjj y/f.g[,gg,y 076000K402 ...(KA'S) ANSWER 2.02 .(2.00)
- a. Selector switch ( Auto-Manual-Shutdown Auto switch) in AUT0A og 5'//vrAnw Avro
~
4 Control switch (Start-Hormal-Stop switch) in NORMAL.
. A low-low level in either SG for the associated unit.
A safety injection (SI) signal from the associated ESF train.
' Loss of both main feedwater pumps for associated unit (breakers open).
(0.3 for each) b.For the TDAFW pump, an undervoltage condition on both Bus 11 & 12. (0,5) REFERENCE P.I. 50 B-288 pp7 and 11j D V6 NF- 903/2 - / 061000K402 ...(KA'S) n ANSWER 2.03 (1.50)
- a. . Fal se L.. . b. - Fal se l' c. False REFERENCE P.I. SO B-27 pp5,6 and 9 039000K601 ...(KA'S)'
= _ _ ,
[ '. I2h PLAND DESIGN' INCLUDING ~ SAFETY AND EMERGENCY SYSTEMS PAGE- 18
<. */A'NSWTRS'--: PRAIRIE: ISLAND 182 .
-87/06/16-VICTOR, F.
'(, .
P
, ANSWER' 2.04- ._ ( 2. 7 0 ) --
- a. : Flow' past. the the~ radial. bearing is increased (0.25) by providing a
' bypass line around #1 seal.(0.25) b.: 1.. Lack of leakage' t_hrough #2 seal [0.5]
- 2. Excessive leakage. through. #3 seal -[0.51 c.: 1. Associated oil. lift pump running.[0.6]
2.; 011L lift pump pressure greater than. 350 psig.[0.6] . i
- REFEREEE '
5,' y'0 f 8G Lectrav r REcSpr; (genu)nt 4,vNdA RTOA)
'P.I.- SD B-3 pp12 to 15; pp 21 003000K403. i...(KA'S)
ANSWER 2.05 .(1.80)
'a.- 4160V bus 15- .
- b. 4160V bus 24
- c. 4160V bus 26
- d. 4160V' bus 16-
- e. 4160V. bus.12'
- f. 4160V bus 16L [0.3 each]
. REFERENCE a.- P.I. SD B-15 pp7'
- b. P.I..SD.B-28A pp7
- c. P.I. SD~B-28B pp6 j d.^P.I. SD B-18D pp6 '1
- e. . P.'I. SD B-28A pp11
- f. P.I. SD B-14 pp6 062000K201 ...(KA'S)
- a
~
ANSWER' 2.06 (2.00) -
- 1. Loss-of-coolant accident. 1 '
2.L Rod ejection accident. 3..; Loss of secondary coolant. i.4. Steam generator tube rupture. (0.5 each) ] 1 REFERENCE-P.I.SD B-188 pp4 006050K004- ...(KA's) i l l J
'2. PLANT DESIGN-INCLUDING' SAFETY AND EMERGENCY SYSTEMS.- PAGE' 19
~
' d A'NSWERS'-- PRAIRIE. ISLAND'1&2 -87/06/16-VICTOR, F.
- a . ,
ANSWER 2,07 -(1.50)
.a. True
- b Fal se c'. False
-' . REFERENCE-LP.I. SD B-31A pp12, 15, & 52.
'086000A302 086000K402 ...(KA's)
ANSWER 2.08 (1.50) Automatically starts' at 97 psig in .its associated receiver (0.5). LAfter 10 seconds the compressor loads and remains loaded until its associated receiver exceeds 102 psig(0,5). If the compressor runs un)oaded for 10 minutes it automatically stops.(0.5)
'(Sirhwr 95 us f g u o jo e p s; (, g ugp rgs
-REFERENCE P.I..SD Bi34'pp9,10 078000K401 ...(KA'S) l 1
a i i l l.
~!
m_ _ . - - -
q . , - i L 3 '. INSTRUMENTS ' AND ' CONTROLS : PAGE .:20' g . ANSWERS'-- PRAIRIE ISLAND 1&2-
-87/06/16-VICTOR, F.
H:q,. :.
.] 1 LANSWER .: 3.01 (2.00)-
.a. CLOSE . (0. 4 ) ..
b.N0 CHANGE (0.4) )
- c. CLOSE. (0.4) "
-d.-CLOSE (0.4) !
- e. OPEN: (0.4) U REFERENCE. -
P.I. SD B-7 pp38 to 42 j 059000K010 ...(KA'S) 4 i ANSWER- 3.02 (2.40)- ; i
.1.-Re' actor Trip 1/2 25% Power Equivalent
.2.'. Rod Stop' 1/2 20% Power Equivalent
- 3. P6 Premissive 1/2 >10 minus 10 Amps
.. (1. through 3-interchangeable)-- !
- 4. Startup Rate indication (
- 5. Computer i
- 6. Remote indication (Control Board or N45) -j (4 through' 6 interchangeable)
- 7. Loss 'of Compensating Volatge. l i
- 8. Loss of Detector Voltage. ~ (0.3 each)
'{
REFERENCE P.I. 50 B-9 pp11 and 12, figure B9-9 ~f 1 1015000K402 015000K405 015000K407 015000K601 ...(KA'S) j i
. ANSWER 3.03- (2.00)
, a..The power operated relief valve requires TWO channels (0,5) above 2335 psig to open and remain open.(0.5) (1.0) j; l
i.
-b. When the Overpressure Protection System is ENABLED (0.5) the operating setpoint for the PORVs is . lowered to 500 psig. (0,5) (1.0)
REFERENCE l P.I. SD B-7 pp32 and 33 k L 010000K403- ...(KA'S) N_-__ __ _ ____ _
nY - . t.3i 7 INSTRUMENTS AND CONTROLS 'PAGE 21" ,j I AYANSWERS--PRAIRIEISLAND.'l&2 .-87/06/16-VICTOR, F. ! x.- i. L I i
- ANSWER' 3.04 :(2.00) g <
- a. 1. Power Range NI,(0.2) 2/4(0.1) above 10% nuclear-power (0.1) .
.2. 1st stage turbine pressure,(0.2) 1/2(0.1). >.10% turbine power (0.1)-
']
, .b. Il Two loop low flow and RCP; trips. U '
- 2. Low. Pressurizer Pressure. .
3.;High Pressurizer Level.
- 4. 4160 VAC undervoltage on RCP buses.
(0.3 each)- 1 REFERENCE l
, - P. I. SD B-8 Tabl e B-8-2.ppl of .1 i 012000K406 012000K610 ...(KA'S) l l ANSWER 3.05- (2.10)-
a . 1. L Ta'v'9
- 2. DELTA-T 4E/t ggp6
. 3. RCS Pressure d4 y ys4 '
'3 4.70 ELTA-I (flux) (0.2 for each)
'b. Prevents exceeding'DNB..(0,5)
- c. 1. Turbine. runback J2. Blocks automatic and manual rod withdrawals j (0.4 each) <
. ok R00 ST0f: i REFERENCE j P.I.'SD B-8.pp7 and 16 001000K407 ...(KA'S).
ANSWER 3.06 (2.00)
- 1. - Reactor' trip 'r; t ra ;r, A.
l, 1.2.. Manual pushbutton on the operator's console. ,. . 3. . Trip of both main feedwater pumps.
- 4. = Generator . lockout, E , 5. .High-high SG 1evel (6 ^rlgs -
!6.cAnySIfce;trair,A.p)frrtra'r,A 3- -;
7.. Either Main Steam Isolation valve closed. 4 8 Main transformer lockout.
- 9. Backup overspeed trip.(111.5%) ( Any 5 at 0.4 each) l
'/0. Av70 JTef filADErl l'GNvAC 16ts By qf j> fig
'II; Hi-Hi LGvEL W Lew Minve; FW ttorn
'i3 .INSTRUMENTSiAND CONTROLS, PAGE j; -,-jANSWERSi- PRAIRIE ISLAND 1&2. -87/06/16-VICTOR,F.~
l'". [ ( .. l- ' REFERENCE P. I. SD -B-22A- pp34 and 35 ; 3 9 6-2 3 y 9-h 045000K411 ...(KA'S)
'0 ANSWER 3.07; (2.50)
, a. Loop,A Tavg will indicate high.(0.5) l Loop A Tavg becomes autioneered high input to temperature' mismatch channel (0.5) .
~ Tref minus Tavg signal will go negative.(0.5)
.' Rods IN command.is produced.(0.5)
"b. Place the Tavg CHANNEL 0EFEAT. switch for the failed channel to the i
'" DEFEAT" position.(0.5)
REFERENCE'
-P.I. SD B-7'pp9 to 11; Figure b7-1, B7-2 4 001000A101 :001000K602 ...(KA'S) i l
l 1 I I Y J
- 4. '. PROCEDURES'- NORMAL', ABNORMAL, EMERGENCY AND- PAGE -23
-RADIOLOGICAL CONTROL, ANSWERS -- PRAIRIE ISLANDJ1&2-
-87/06/16-VICTOR, F.
I ANSWER ~4.01 (2.00)
- 1. 51 Pump control switches in Pullout-Stop.
- 2. CS Pur.p control switches in Pullout-Stop.
- 3. Accumulator isolation valves closed (valve breakers locked and tagged 0FF).
'4. BA~ to .Sl Pump Suction valve closed (valve. breakers locked and tagged 0FF). ..
- 5. Caustic' Addition valve to CS Pump closed.
6.:SI to Cold Leg Isolation valve closed. 7 SI to Reactor Vessel Isolation valve closed. (Any FIVE at 0.4 each) (2.0) REFERENCE P.I. Ptocedure C1.6 pp3' 013000K012 ...(KA'S) ANSWER 4.02 (2.00)
- a. As' a RCP is started, reflood of the vessel upper head with cool water will collapse the steam bubble (0.5) and pressurizer level will decrease.
rapidly as pressurizer water fills the void.(0.5) -(1,0)
- b. If'a 'RCP-cannot be started and a rapid cooldown is initiated, the void l in the upper head grows larger (0.5) which-'causes an insurge into the pressurizer. The lower level' prevents taking the pressurizer water solid.(0.5) (1,0)
(Similar wo'r ding acceptable.) REFERENCE P.I. Procedure IES-0.5 Background Information ppl 000027A201 l
...(KA'S) '
i {> i
- _ =_
mJ4b PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND -PAGE 24
- RADIOLOGICALsCONTROL F 'ANSWfRS -- PRAIRIE ISLAND 1&2 -87/06/16-VICTOR, F.
ANSWER, .4.03 (2.00) The operator 1should: _
,' (a.' Read the required position from the procedure. !
')
~ (b. Read - the valve label. {
- c. Check the valve CLOSED, by attempting to turn the valve handwheel i in the clockwise (closed) direction. ..
- d. Check the valve OPEN by either closing the valve about 2 turns and reopening or attempting to open the valve.by. turning in the counter- 1 clockwise direction. (Only one method required.)
.(0.5 for each answer) (2.0)' !
, REFERENCE
( P.I. Procedure 5AWI 3.10.1 pp4 & 5 j 191001K108 l s
...(KA'S) '
~ ANSWER' 4.04 (1.50)
- a. Hydrazine, which is added to the coolant to scavenge oxygen, decomposes
'above 180' degrees-F.(0.5). q l
~ b. _With the PORVs open during ~ Pressurizer bubble formation,- Prest,urizer 1 pressure equals PRT pressure which is 20 psig.(0,5) The saturation j
' temperature for 20 psig is 259 degrees F.(0.5) j REFERENCE-P.I. SD B-4A pp33; Procedure C1.2 pp3 & 8 j 002000A403^ ...(KA'S)
ANSWER 4.05 (2.50) a Depressurizing the SG will cooldown the RCS(0.25) and reduce RCS i pressure and temperature.(0.25) At lower RCS pressure, inventory l loss through RCP seals is reduced (0.25) and SI accumulators can inject.(0.25) (1.0) { b .'.At 60% to.65% wide range, the SG level is maintained above the U-tubes !
.(0.25) which ensures sufficient heat removal capability (0.25) during l i
natural circulation (0.25) or reflux boiling.(0.25) (1.0) I
- c. To prevent the reactor core returning to criticality due to moderator
- temperature effect.
(0.5) p ) i l l 4 i L L ! Y _ _ - - --_ _
. q.
[4.: cPROCEDURES- iNORMAL, ABNORMAL, EMERGENCY AND PAGE 25-
-RADIOLOGICAL CONTROL:
ANSWERS.--- PRAIRIE ISLAND'1&2 -87/06/16-VICTOR, F.
'.,1 .-.
' . I REFERENCE'
' P.I'.; Emergency Procedure '1ECA-0.0 pp7; Background Information pp2, 3 000055K302 :...(KA'S)
ANSWER 4.06- (2.00)
- a. To. Emergency Borate:
- 1. Shift the running BATP to FAST speed and open the in-service BAST recirculation valve 50%.(0.5)
- 2. 0 pen Emergency Boration valve (MV-32086).(0.5)
, b. Normal boration with maximum boric acid flow (0.25) and Safety' Injection.(0.25)
M u H e r r:w i .W.-{ C. 5 ) GF6 REFEREN'E C P.I.. Emergency Procedure 1FR-S.1 pp3; Procedure C12 pp88 & TM-86-60 pp2 000024K011- ...(KA'S) ANSWER 4.07 _(1.50) The. PE&R0. trips the reactor,(0.25) picks up a radio if available and leaves the Control Room.(0.25) . (0.5) If. conditions do' not permit the above action, the PE&R0 proceeds to Unit 1
' Rod Drive Control Room (0.25) and manually trips the reactor at the breakers.(0.25) ..
(0.5) The PE&R0 verifies turbine trip (front standard)(0.25) and proceeds to the remote shutdown panel area.(0.25) (0.5) REFERENCE i P.I. Procedure C1.8 pp3 ;
'000007K006 ...(KA'S)
ANSWER. 4.08 (1.50)
- a. Shutdown
- b. Trip i c. . Shutdown..
L [0.5 each]
' REFERENCE AB-3'rev.'1, p 3 C5 rev. 7, p 14 !
1 b L l
pgy r :33--- *; \ tf ' '4e .PROCEDORES - NORMAL,-ABNORMAL,. EMERGENCY AND I.- ' RADIOLOGICAL CONTROL PAGE e y f?' ANSWERS 4- ^' PRAIRIE ISLAND.1&2 .
-87/06/16-VICTOR, F.
1 r -i b ( ;, . ;. C19.7 rev. 3, p 1 000003G010' 000069G01 l'. , , , (gg.3) - . I l 1 E I i r ', j) e e ; ,
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U. S. NUCLEAR REGULATORY' COMMISSION f SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: PRAIRIE ISLAND 1&2 REACTOR TYPE: PWR-WEC2 ._ DATE ADMINISTERED: 87/06/16 EXAMINER: TEMPS- _ CANDIDATE: INSTRUCTIONS TO CANDIDATE 1 Rond the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Rstraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be' picked up four (4) hours after the examination starts.
% OF CATEGORY- % OF CANDIDATE'S CATEGORY
~VALUE TOTAL SCORE VALUE CATEGORY 13.50 2 3. 13 A S . 00 '#r 'C 5. 004 5. THEORY-OF NUCLEAR POWER PLANT !
OPERATION, FLUIDS, AND i THERMODYNAMICS
/3.%3 23.55 - 15 . 0GGN - 2 5 . 0 ^Kb 6. PLANT SYSTEMS DESIGN, CONTROL, ,
AND INSTRUMENTATION i
'E.%
15.00 .25.00gp 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
.15.00 -4%4g 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 56AO 00.00-- % Totals Final Grade All work done on this examination is my own. I have neither given l nor received aid.
p Candidate's Signature i A i [
3 k s .
*, ., NRC RU65S AND GUIDELINES FOR LICENGE EXtNINATIONS During the administration of this o :amina*; ion the fol l.owing' rtles apply: ,
- 1. Cheating on the edsmination means an automatih de.nial of /ber application end could result iic more severe penalties.
- 2. Restroom trips are to be limited and only one 'candidtto as a tims'rtar leave. You must avoid all contacta with anyone cutside the examination room to avoid even the appearance or poselbility of cheat'ing.
- 3. Use black ink or dark pencil only to facilitatt > legible 'reprc-ductio.uc.
)
- 4. Print your name in the blank provided on the cotter sleet of the examination. ,
- 6. Fill in the date on the cover sheet c0 the examination (if necessary).
- 6. Use only the par.er provided for answers.s .
7. J Print your name in the upper right-hand corner of the first page of each scetion of the answer sheet.
- 8. Consecutively number each answer sheet, writo 'End of Category:__." as appropriate, start each categsry on a new pare, write oniz'an Rug side of the paper, and write "Last Page" cn.the last answer sheet.
- 9. Number each answer as tu category and number, for exampla, 1.4s G.3.
4
- 10. Skip at least thren lines betuten each answer.
- 11. Separate answer sheets from pad and place finish 5d answe.e sheets fece down on your desk or table.
- 12. Une abbreviations only if they are commonly used in facility li%gra.ture.
- 13. The point value for each question in indicated in parentheses af ter the question and can be nned as a guide for:the depth -f' answer required.
- 14. Show all calculations, me.thods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or tot.
J
- 15. Partial credit may be giv9n. Tnorefore, ANSWER ALL PARTS ~OF THE QUESTION AND DO NOT LEAVP, ANY ANSWER BLANK. ' '
- 16. If parts of the examination are not clear as ta ittent, ask questions at the examiner only.
i
- 17. You must sign the statement on the cover sheet that' indicates ' that; the work is your own and yoa have nct received or been givea nasistance in completing the examination.
been completed. This must be done after the examination has l l
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ila.' %en'fdu compleie your exenination..'you shall: \ ils % ., .. . _ y ): . Ul'lin cAssemble your examination as follows: .
@. g h ' .\ {t). Exam questions on top.
.. e . ..
o , r. 2'7(2) :1 Exam aids - figures, tables,ietc. m . (3.)
. Answer pages including figures which'are part of the answer.
,a.
lbdiTurn in'y6urJcopy of the: examination and all pages used to answer
- d 'se ,-
1 tha - , examination questions. n. V' c. - idrn-in all scrap paper.and the balance of the paper that you did-not -,,_ use for answering the. questions. v-e .d. Leave the examination area, as defined by the examiner. If after N 16aving, . you Are found in this area while the examination.is still
+
. in progress, your license may be denied or revoked.
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- 5. THEORY OF NUQLEAR POWER PLANT OPERATION FLUIDS. AND PAGE 2 THERMODYNAMICS 4
4, QUESTION 5.01 (2.00) . Unit 1 is operating at 60% power, steady state conditions, BOL when rod withdrawal is manually initiated.
- a. Calculate the Startup Rate (SUR) which would be achieved IMMEDIATELY after commencement of rod withdrawal. Assume a differential rod worth of 7.5 pcm/ step, a rod speed of 40 steps / min, effective delayed neutron fraction of 0.00596 and a delayed neutron precursor avg. decay constant of 0.0767. Show all equations used and calculations made. (1.25)
- b. How would the SUR at EOL compare with the SUR at BOL for the same reactivity addition, if all other factors were held constant?
Justify your answer. (0.75) QUESTION 5.02 (2.00) Assume that. control rod bank CBD is initally at 180 steps and power is 70%. If rods are withdrawn several steps and turbine load is maintained constant, the coolant Tavg will increase due to the primary to secondary power mismatch which occurs. Explain the mechanism by which the moderator temperature coefficient and the fuel temperature coefficient will EACH act to limit the increase in coolant Tavg which occurs. 1 (
-QUESTION 5.03 (2.25) I l
The plant has been operating at 100% power for the last ten days when it
~
trips. State HOW (GREATER THAN, LESS THAN or SAME AS the SDM at time of trip) and WHY the shutdown margin will be affected by Xenon for each of the following times. Consider each case separately and assume all other i E fcctors are constant.
- a. 8 hours after the trip j
1
- b. 26 hours after the trip !
! c. 80 hours after the trip 1 1. l~ l l l 1 i (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) I
~
p T[- ~ ~ l - 5. ' THEORY OF'NUCMAR~ POWER PLANT OPERATION. FLUIDS. AND PAGE 3 THERMODYNAMICS
-t 1=
QUESTION 5.04 (2.25) j l If reactor power is increased from 75 to 100%, HOW (INCREASE, DECREASE or REMAIN THE SAME) will differential rod worth change for each of the l
'following onditions. Consider each separately and justify each response j
L with a brief explanation. i
- a. Rod position and boron concentration are held constant, Tavg is allowed "I to decrease
, b. Rod position held constant, boron concentration diluted to maintain l: Tavg constant c.! Boron concentration is held constant, rods are withdrawn towards their upper limit to maintain Tavg constant
'l QUESTION 5.05 (1.50) I Prior to a' shutdown Unit 2 had operated at 100% for three months. HOW and WHY would the actual critical rod position (ACP) vary from the estimated critical rod position (ECP) for each of the following situations. Consider occh case separately,
- a. 50 hours is assumed in the ECP form from shutdown to startup rather than the actual. ten hours it takes to startup the reactor.
{
- b. Actual boron concentration is 100 ppm lower than the desired boron concentration used in the-ECP calculation. I l
4 j (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
.5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 4
, THERMODYNAMICS QUESTION '5.06' (2.40)
Rsfer to Figure 5.1. Two Condensate Pumps (centrifugal) are in parallel taking a suction on.the hotwell. Each pump has a discharge check valve
'endLits pressure and flow are measured between the pump and the check velve., For each situation below, complete the table provided on Figure 5.1 to indicate the expected change in the Flow Rate, Discharge Pressure, and Pump Current. Use arrows to indicate how the parameters should change for the running pump or pumps-
- a. Pumps 1 & 2 are running, Pump 1 shaft binds and RPM decreases by 50%.
- b. fump 1 is running, Pump 2'is started.
- c. Pumps l'& 2 are running. Pump 1 shaft shears at the coupling between the pump and the motor.
- d. Pump 1 running, Pipe rupture occurs downstream of the check valves.
- e. Pumps 1 & 2 running, Pump 2 check valve disk becomes loose and creates significant blockage at the check valve.
QUESTION 5.07 (1.10) Unit 1 is in hot shutdown with Tavg at 547 F. How much will Tavg have to INCREASE to cause the SG SAFETY with the lowest setpoint to lift? Assume steam dumps do not operate. Show all work and state any additional assumptions, s QUESTION 5.08 (1.50)
'What~are the FOUR (4) conditions identified in the Technical Specifica-tions that must be met to preserve the validity of the core Hot Channel factors that are required to be periodically calculated?
i
- 4. y
, , ,p >W' v
l (***** END OF CATEGORY 05 *****)
4 6 Asws/ ;, , ( . n. .
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i
- 6. PLANT SYSTEMS DESIGN CONTROL. AND INSTRUMEN_IAIlQH PAGE 5
\
l QUESTION 6.01 (1.60) On a decreasing pressure in the Fire Protection System state what events occur at the following pressures?
- a. 120 psig M. M
- b. 105 psic .
c.
- d. 90 psig 95 psig Y'.j'# {)7'%
O # " QUESTION 6.02 (2.00) State FOUR automatic actions which occur within the Cooling Water System upon receipt of a safety injection signal. ; l QUESTION 6.03 (2.70) l
- a. Describe the design feature that provides additional RCP radial bearing heat removal during plant startup and shutdown when reactor coolant pressure is between 100 and 1000 psig. (0.5)
- b. List TWO conditions that could result in a low level alarm on a RCP standpipe? Do not include leaking standpipe or loss of seal )'
injection. (1.0) c. List TWO interlock conditions that must exist for the RCP breaker to close when the RCP control switch is placed in START. (1.2) QUESTION 6.04 (2.00) For each of the following. situations, indicate the initial direction of travel for the feedwater regulating valve FCV-466 (answer either OPEN, ! CLOSE or NO CHANGE). Assume that the plant is initially at steady state l full power and that FCV-466 in in AUTO Consider each action independently. l
- a. An inadvertent SIS actuation. i
- b. Controlling first stage pressure transmitter fails high. I
- c. Controlling steam generator pressure transmitter fails low.
- d. Controlling feed flow transmitter fails high. ;
l
- e. Steam generator level transmitter (LT-461) fails low.
l l l 1 (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) I
- 6. PLANT SYSTEMS ~ DESIGN. ~ CONTROL. AND INjiTRUMEHIATlDH PAGE 6 i
, *4 :
. QUESTION 6.05 (2.00) a.:What design feature of a pressurizer Power Operated Relief Valve (PORV)
. prevents inadvertent opening of-the valve when a controlling pressure transmitter fails high?
- b. During cold shutdown conditions, how is the RCS protected by the PORV from an Overpressure Accident? ;
QUESTION 6.06 (2.50) a.-Explain what affect the Loop A control Thot RTD failing open will have on the Rod Control' system? Include the signal processing logic. (2.0)
- b. Explain how a failed Thot channel input signel can be prevented from affecting the Rod Control System. (0.5)
QUESTION 6.07 (2.20)
- a. Why are the high head SI to reactor vessel nozzle supply valves (MV-32069 and MV-32067) closed when the SI system is aligned for ECCS operat$on?
- b. Why are.the high head GI to reactor vessel isolation valve (MV-32074) and.the high~ head to cold leg isolation valves (MV-32070 and MV-32068) !
closed during cold shutdown? l l l l l { J I l l (***** END OF CATEGORY 06 *****) 1
~
A,
- 5- ~s e ., ,a
- 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 7 B@lgLQQ1 GAL CONTROL'
- i. j .
QUESTION 7.01 (1.80) In accordance with the' Optimal Recovery Procedures: 0; What action, if any, is' required to be taken in order to re-instate automatic Safety Injection (SI) protection after a SI acteuation and SI' termination have been completed?' - (0.6)
- b. What TWO parameters should be monitored to. determine the need for-re-inttiating Safety Injection-(SI) protection following SI termination?
(1.2) QUESTION 7.02 (1370) What steps must be taken to initiate Emergency Boration which is required as an immediate action for 1FR-S.1, Response to Nuclear Power Generation / cATWAS? QUESTION'7.03 '(2.40) In accordance with the Optimal Recovery Procedures, state FOUR conditions when the Reactor Coolant Pump trip criteria is not applicable. QUESTION' 7.04 (2.00) If the following alarms are received simultaneously indicate what the probable cause of the alarms is and what actions should be taken. Unit 1 Instrument Header pressure low
. Unit luInstrument Air flow high Unit 1 and 2 Screenhouse IA pressure low Unit 1 Auxiliary Building IA pressure low Unit 1 Containment IA pressure low
- . ~ _ - - - - - - - .
- 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 8 RADIOLOGICAL CONTROL QUESTION 7.05 (2.00')
'With Units 2.at 100% power, indicate for each of the following scparate situations whether Unit 2 should RI: MAIN AT POWER, REDUCE POWER, SHUTDOWN, or be TRIPPED. Assume no trip occurs.
- a. " Operational Basis Earthquake" annunciator is received and confirmed by the graphic recorder.
- b. Two full length control rods drop into the core.
- c. The Daily Leak Rate Surveillance has just been completed and indicates an increase in Reactor Coolant leakage to 7.0 gpm identified and controlled leakage and 2.0 gpm unidentified.
- d. Flow is lost in the Component Cooling System and cannot be immediately restored. No high temperature alarms are received for the-first 5 minutes.
- o. It is established.that a loss of containment integrity has occurred.
QUESTION 7.06 (1.50) , Answer the following questions regarding procedure C1.2, " Unit Startup Procedure":
.n. Why does step 3.3A require oxygen to be within required chemistry !
specifications prior to exceeding 180 F7 (0.5) b-. Why does the temperature downstream of the PORV increase to about ! 259 F and stabilize immediately after the formation of a steam bubble ' in the pressurizer? (1.0) QUESTION 7.07 (2.00) i ' According to procedure 1ES-0.5, " Natural Circulation Cooldown with Steam Void in Vessel (without RVILS)":
- a. If a Reactor Coolant Pump (RCP) can be restarted, pressurizer level should be greater than 90%. Explain the reason for this high level requirement.
- b. If a RCP cannot be restarted, pressurizer level should be between 20% and 25%. Explain the reason for this low level requirement.
_ _ ~ - - - - - - - - .
}
4
' ' 7. PROCEDUREM - NORMAL. ABNORMAL. EMERGENCY AND- PAGE 9 RADIOLOGICAL CONTROL 3
l
. QUESTION 7.08 (1.60)
- c. What is the maximum whole body dose a volunteer may receive under emergency' conditions for life saving activities?
(0.6) b..What TWO individuals, by title, may authorize. exposures in excess of 5 Rem in one year? (1.0) (***** END OF CATEGORY 07 *****)
1
' ' ' 8 .' ADMINISTRATIVE PROCEDURES. CONDITIONS.'AND LIMITATIONS PAGE 10 QUESTION 8.01 (1.00) a _Whose~ approval is required for release of liquid or gaseous radio-active waste?
- b. Whose approval is required for bypassing interlocks on the fuel handling equipment?
QUESTION 8.02 (1.20) In accordance with the bases of the Technical Specifications, state the purpose of the overtemperature delta T reactor trip. Include the two constraints that must be met to assure the trip provides adequate protection. QUESTION 8.03 (2.60)
' Assume a plant trip has occurred on Unit 1 and Unit 2 is at 100% power.
Answer the following questions assuming only the minimum number of licensed operators are available at the facility.
- a. Using the enclosed figure show where each licensed individual should be located. Include the type of license held. (1.0)
- b. Which individual shall be responsible for supervising activities affecting operations of the plant as a whole.
(0.6) c.'What support organizations will be established, in accordance with the Emergency Plan if.an Alert is declared? (1.0) i QUESTION 8.04 (2.40)
- a. Which two logs would be required to be updated for the performance of an electrical plant switching request from the Power System Operator. The request is for maintenance work to be performed on a transformer off of the 345 KV ring bus. The Units are at 100%
l power. (0.8)
- b. Which four logs maintained by licensed operators would be required to be updated for a maintenance job to replace the impeller in the 111+ Auxiliary Feedwater pump. The suction and discharge valves will be shut and the pump motor will be pulled. The Units are at 100%
power. (1.6) _ ~ _ _ _ _ I
9
/.
J
] North
.N
/ s m 1 Z
\ =
5 C O a
- C k U m
Z k
/
. m
=
/ \
/ i i
I a
~
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o 8.
' ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 11 l
QUESTION 8.05 (2.40)
-a. During Unit 1 power operations, Safety Injection Pump #12 is declared Jinoperable.
According to the Technical Specifications what action is required prior to initiating repairs to SI pump #127 (0.8)
- b. Twenty four-(24) hours later SI Pump #12 is still inoperable. Repair parts for the SI' Pump are not expected on site for another 15 hours.
Following the guidance of Section Work Instruction-0-22, " TECH SPECS RELATED. SHUTDOWN REQUIREMENTS', state the actions that must be taken, including any time limitations which are imposed. (1.6) QUESTION- 8.06 (2.40) Classify each of the following events using the Emergency Conditions provided. Consider each situation separately and provide all the applicable bases for the classification.
~
- a. SG #1 is faulted inside the containment. SG #2 is ruptured and SI has initiated. Containment pressure is 3 psig. All other systems are functioning normally.
- b. The Units were at 100% power when a tornado in the area caused a loss of offsite power. During the confusion a worker in a contam-inated area tripped and hit his head. He is unconscious and requires hospitalization. His clothing is contaminated to 11,000 dpm/100sqcm.
- c. A 200 gpm primary leak causes a reactor trip and SI actuation.
Coolant activity is 400 uCi/cc and containment pressure raises to 15 psig. i l
b v .- ... n* 8 '. ' ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS-PAGE '12 1 QUESTION 8.07 (3.00) Given that the Power. Distribution readings noted below existed in the
. questions.
Unit l' core'after a. power increase to 90%, answer the following i The' power increase was completed.at 01:00. TS 3.10-1 is provided, 1
- a. What actions, if any, should have been taken at 04:007 Justify your your answer by referencing applicable' paragraphs from the TS. (2.5) 3
.{
- b. How sooniafter 04:30 may.a power increase to 100% 1 i
_______________________________________________________'be initiated?'._(0.5) { 02:00 04:00 04:30 Nuclear Enthalpy Hot Rise 1.5 1.54 1.54 Channel Factor [FNdeltaH]
-Engineering Heat Flux Hot 2 1.8 2.0 1.8 Channel Factor [FNQ] '6' 2.0 2.3 2.0 10' 2.0 2.3 2.0 FNQ (equil) 2' 1.6 1.8 1.8 6' 1.7 2.0 2.0 10' 1.8 2.0 2.0 Quadrant power tilt 1% 3% 2% . Axial flux reading -3 -6 -2 Axial flux target is +3 1
- 1 i
- j 1
l l d (00000 MB Cd6 f%@F* Paw (E ^^^^^S
- 5. TE ORY OF NUCLFAR POWER' PLANT OPERATION. FLUIDS. AND PAGE 13 THERH0 DYNAMICS ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS 4
ANSWER 5.01 (2.00)
- s. Lambda = 0.0767 [0.125]
Beta eff =. 0.00596 [0.125] rho dot = (7.5 pcm/ step) X (40 steps / min) X (1 min /60 sec)
= 5 pcm/sec [0.25]
SUR =rho (26= X0 [(rho sincedot) + (lambda at steady stateXconditions, rho)] / (beta eff - rho) therefore SUR = ( 26 X rho dot ) / beta eff [0.50] SUR~= (26 X 0.00005) / 0.00596 = 0.218 DPM [0.25,] htok Gert:r Gucy pcx cu c u sn mes wazw D e ccr use e,,
- b. SUR will be higher [0.25] because beta eff is smaller at EOL [0.5]
REFERENCE F of NRP, page 7-38 and 7-72 P8188L-001 Reactor Physics #20 KA importance 3.4 001000K547 ...(KA'S) ANSWER 5.02. (2.00) Fuel temperature will increase [0.25] v. g-neutrons travel further into the fuel and doppler broadening occurs EOT25*3e i resonance escape probability is decreased [0.25] !
- c. >-
moderator becomes less dense [Ov36-]r neutrons can. travel further [0.25] more neutrons reach control rods and are absorbed [0.25] W en the negative reactivity of the two terms above balances the positive ,
.-Tcvg-levele react 4xity-added ont by the rods, e power mismatch "ill no lenger-exis-te-and s
[n sin] __7 REFERENCE i F of NRP, pages 6-39 and 6-48 P8188L-001 Coefficients and Defects #1 i KA importance 4.1 3.7 3.9 ( '001000K510 001000K515 001000K529 ..(KA'S) L 4 l 1 l
-1 I
( . _ _ _ _ - . _ . _ _ _ _ _ _ . _ _ - - -- - - ~ -
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE 14 THEMMODYNAMIGS ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS ANSWER 5.03 (2.25)
,a. Greater than [0.25]
Xenon reactivity peaks about 8 hours after a trip [0.5]
- b. Same as [0.25]
Xenon reactivity is approximately equal to the value immediately after the trip [0.5] (2y #cs3 nerrt TtT/),
- c. Less than [0.25]
Xenon reactivity is virtually gone [0.5] REFERENCE Westinghouse " Reactor Core Control" Chpt 7, pgs 13-23 Operations, CIA, Section 4 and 6, Figure C1-6 P8188L-001 Xe Effects # 1 and Reactivity Balances # 4 KA importance 4.1 3.7 ' 001000K538 001010K526 ...(KA'S) ANSWER 5.04 (2.25)
- a. DRW decreases. [0.25] As Tavg decreases , " sphere of influence " of control rods decreases due to increase in moderator density. [0.50]
- b. DRW increases. [0.25] As boron conc. decreases, more neutrons can reach the control rods .
[0.50] c. DRW decreases. [0.25] As rods are withdrawn from the core, they see less flux; as rod worth is proportional to flux, rod worth decreases as rods are withdrawn into a lower flux region. [0.50] REFERENCE F of NRP, Chapter 6, pages 6-32 P8188L-001 Rod Worth #3 KA importance 3.6 2.8 001000K511 001010K504 ...(KA'S)
- 0) ,
72 5 'TMORY OF NUCrRAR POWER PLANT OPERATION; FLUIDS. AND PAGE 15 THERH0 DYNAMICS
' ANSWERS'-- PRAIRIE: ISLAND 1&2 -87/06/16-TEMPS' l ANSWER ' 5' . 0 5 '(1.50)
- a. ACP will be higher. [0.25] Due to Xe and S:t reactivity being greater-thanMthe values used in the ECP calculations [0.5]
- b. ACPiwill be lower. [0.25]'This compensates for the' lower amount of q
- reactivity associated with the lower boron concentration. [0.50] ;
REFERENCE i RCC,. Chapter:7, pages 3-12 and 24-32 s P8188L-001. Reactivity Balances # 1, Form C1A-2 { q KA importance 4.'2
- 001010A207. ...(KA*S)
I; ANSWER 5.06 (2.40) ll Pump 1 ll Pump 2 [0.10 each] Situation'!! Flow ! Pressure l Current !! Flow ! __________;;______;__________;_________;;______;_' Pressure l Current a !! v l v l
^
ll
^
-l 'y c ^
__________;;______;__.________;_________;;______;__________;i _______. j b ll- v l
^
! v !!XXXXXXlXXXXXXXXXX 1
__________;;______;__________;_________;;______;__________.lXXXXXXXX ________ c j !. v l v. l v l l'
^
l v ^ __________;;______;__________;_________;;______;__________;l ________
- d. l! ^ l v l
^
!!XXXXXXlXxxxxxxXXX
__________;;______;__________;_________;;______;__________;lxxxxxxXX ________
,- e. ll- ^ l v !
^
ll v l
^
! v ;
.v =; Decrease ^ = Increase > = No Change i REFERENCE Woctinghouse " Thermal Hydraulic Principles, Vol II" Chpt 10, pgs 32-48 .i K&A Appendix A-Components: Pumps-Centrifugal #7 I .
I 1 _ _ _ _ . _ _ _ . _ _ _ _ _ _ .u___-- _-_--_-- -a
't
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,' j
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' : 5 .~
THEORY OF NUcr.r4R POWER PLANT OPERATION. FLUIDS. AND ~PAGE 16 THERMODYNAMICS
' ANSWERS --' PRAIRIE: ISLAND 1&2 ' -87/06/16-TEMPS t -
f ANSWER '5;O7 ~(1.10) Low set'. safety'=' psig = 1092. PSIA-[0.30]
,'PcatEof: 1092 psia =.Tsat of 555.4 F'[0.40]
. Increase in Tavs = 555.4'- 547.0 = 8.4 F [0 40]
. REFERENCE-(6DF)#
.THP, Chapter 2,,pages 71 through 78 Steam Tables Components A-18 3.2-KA:importance-4.0 035010K109- ...(KA'S) s.{f.g ' -
[}d ' p ANSWER' 5.08 (1.50) / [* J u l 1)LControl rods in a single bank move togeth'r e with no individual rod insertion differing.by more.than 15" fr'om bank demand position -
- 2) Control rod banks are sequenced with overlapping. banks
~
3)' Control bank insertion limits are not violated !' 4)-Axia'l power distribution control procedures are observed ' [ FOUR @ 0.375:each ] REFERENCE TS's,:page3.10-10'f' F8188L-001: Peakirfg Factors # 7 KA-importance ! .- , 001000K546,/, . .. 3'.
. ( KA6' S )
. ,/'
./.
7..
/
1
- l. n
}- 6. PLANT SYSTEMS' DESIGN. CONTROL'. AND INSTRUMENTATION PAGE 17 ANSWERS ---PRAIRIE ISLAND 1&2 -87/06/16-TEMPS -! l
. ANSWER 6.01 (1.60) ,gp' y
- c. jockey pump starts -
( 'i
- Og,s N I
- b. screen wash pump starts
- c. motor driven fire p mp' /
starts s
\
p '
,[
- d. diesel ~ driven fire ump starts j REFERENCE
./ [0.4 each] 1 Fire prote tion p3 086000A1,01 ...(KA'S) .
4 ANSWER 6.02 (2.00)
- 1. System' isolates into two headers with the vertical motor driven pump lined up to supply the unit that initiated the SI.
- 2. Both diesel driv.3n cooling water pumps start. !
- 3. TurMne-building--header--14clation-valve closes en the Unit theta l 4.
knitiatesc ths CT.] tc0f A/B tt:55ccre ML VES Ana A N8b'..Misr (w>u); ' All cooling-water inlet and outlet isolation valves on the containment fan coils open for the unit initiating the SI.
- 5. Ccaponente-Goel-le pump sterta en the unit which-delti-atad +h RI p
- 45. Leerme,v,rr FO' ceu Trum ottrzcc BrHss VAL /r C'"
s &. CROM If EAT kt citwt.c g Sa/Ar Act (CTa/W [4 yequ$ red 9 0,5 eg,3 v A t ecs c oo>c REFERENCE P. I,. SD B-35pp34; 0 4d- # ' 9C I'#' D #3 P81716L-003 Cooling Water System: N'e' # '1M ' D EO 4.b 076000K101 076000K402 ...(KA'S)
. ANSWER 6.03 (2.70)
- a. Flow past the the radial bearing is increased-[0.25] by providing a bypass line around #1 seal. [0.25]
- b. 1. Lack of leakage through #2 seal [0.5]
e 2.' Excessive leakage through #3 seal [0.5] y Straert ac>ct L c. 1. Associated oil lift pump runningf[0.6] I
- 2. Oil lift pump pressure greater than 350 psig.[0.6]
REFERENCE ! P.I. SD B-3 pp12 to 15; pp 21 P81710L-002 RCP: EO 7, 6 KA importance 3.1, 2.5 L
V p .
- 6. . PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 18 ANSWERS -- PRAIRIE-ISLAND.'1&2 -87/06/16-TEMPS i :003000K113-L .
003000K404 003000K602 ...(KA'S) i=
. ANSWER.' 6.04. (2.00)
- a. CLOSE [0.4]
- b. NO CHANGE .[0.4]
- c. CLOSE [0.4]'
d..CLOSE [0.4]
.e. OPEN '
[0.4].
. REFERENCE
<P.I.-SD B-7 pp38 to-42 L 059000A408
...(KA'S)'
ANSWER 6.05 (2.00) l
- a. The. power operated relief valve requires TWO channels [0.5] above 2335 psig to open.and remain open.[0.5]
i
- b. )Rien the Overpressure Protection System is ENABLED [0.5] the operating !
setpoint for the PORVs is lowered to 500 psig. [0.5] REFERENCE I P.I. SD B-7 pp32 and 33 ! 010000K403 ...(KA'S) l ANSWER 6.06 (2.50) l
.a. Indicated high loop A Tavg [0.5] :
Loop Tavg signal is auctioneered high [0.5] ' Tref - Tavg signal becomes negative (0.5] !
-Rod IN command produced [0.5] l
- b. Place the Tavg CHANNEL DEFEAT switch for the failed channel to the
" DEFEAT" position. [0. 5] .
REFERENCE P.I. SD B-7 pp9 to 11; Figure b7-1, B7-2 001000A101 001000K602 ...(KA'S) t
nc= . L i p-
'68' '
I
- 6. PLANT' SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 19 ANSWERS -- PRAIRIE ISLAND'1&2 ' -87/06/16-TEMPS ANSWER :6.07 (2.20)-
la. Prevent thermal shock'to the reactor vessel [0.8].in the event of , a spurious SI. actuation. [0.3]
, ., g g gy gg,, p .
- b. Prevent overpressurization of the RCS [0.8]hurihi filling' $f the -@ ;
-accumulators -(\,f [0. 3] !
' REFERENCE B-18A p 21, 29; para 4.4 KA'importance 3.8, 3.9 006020K104' 006030K601 ...(KA'S) l 1
4 1 l f - __ __ _ - - _ i
? V-
' . ' . ..- l
- 7. PROCEDURES '- HQBtML. ABNORMAL. EMERGENCY AND PAGE 20 RADIOLOGICAL CONTROL
. ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS "
i 1 ANSWER 7.01 (1.80) 10 scwuns Reset reactor trip breakers [0.6] a.' (and wait E-minutes 4 \ q
.b. Subcooling [0.4] based on core exit TCs [0.2]
'PZR level [0.6] l I
- REFERENCE-1ES-0.2 rev. 2, p 3,; Fold out page )
j P8180L-006 rev. O, Engineered Safeguards: EO-3 KA importance 4.9, 4.2, 4.5 1 000074A201 ! 000074A205 000074K305 ...(KA'S) 1 ANSWER 7.02 (1.70) Shift running BATP to fast (0.6] Open BAST recire valve to 50% [0.5] Opcn: Emergency Boration valve (MV-32086) [0.6] REFERENCE TM-86-60 of'C12.8.4 Emergency Boration of the RCS EO: SWI-0-10 rev. 7, p 1
.KA importance 4.0 000024G010 ...(KA'S)
ANSWER 7.03 (2.40) Following SI initiated from cold SD, HSB, or startup conditions [0.6] During recovery operations following-initiation of operator controlled cooldown. [0.6] Following " RCP restart specified in ERG recovery instructions. [0.6]
, REFERENCE W sr?$akh' $$$N'1b NS'o Pc?'hds*iu9e > ius,m (isar p w c wJ Ea 0 Background Information for Westinghouse Owners group ERG, Generic Isrue RCP trip / restart, HP/LP-Rev. 1, Sep. 1983, p 58.
P8197L-012, E-1/E-2 Review: EO-7 KA'importance 4.2, 4.2 000011K314 000074K308 ...(KA'S) p.mou ps.W P9197L ~Gi2 , Quarwe Sc ,p G V
r .. o.' o 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND' PAGE 21 RADIOLOGICAL CONTROL
' ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS ANSWER .7,04 (2.00) t Air' leak'in Unit 1 IA line [0.4]
Start all additional compressors [0.4] (121,122,123,124,125) ) l
-Vorify System Air not cross connected upstream of air dryers [0.4]
Verify System Air cross connected downstream of air dryers [0.4] ] ShutdownUnit1ifheaderpressure(<60psig)[0.4] REFERENCE caaw r or w rer o v Gg C-34'rev. 4, p 23, 24 B-34, p 22 4 P878L-005 rev. O, IA and Station Air; EO-5 KA'importance 3.9, 4.1 000065G010- 000065G011 ...(KA'S) H 1 I ANSWER 7.05 (2.00)
- a. Shutdown
- b. Trip.
- c. Remain at power
- d. Trip
- o. Shutdown
[5 @ 0.4 each] REFERENCE AB-3 rev. 1, p 3 C5 rev. 7, p 14
-TS 3.1.9. '
C4 rev. 6, p 7 C14-rev. 4, p 13 C19.7 rev. 3, p 1 KA importance 3.8, 3.8, 3.5, 4.2
- 000003G010 000009A233 000026G010 000069G011 ...(KA'S)
I l ' ANSWER 7.08 (1.50) n.. Hydrazine, which is added to the coolant to scavenge oxygen, decomposes above 180 degrees F. [0.S]
- b. With the PORVs open during Pressurizer bubble formation, Pressurizer pressure equals PRT pressure which is 20 psig.[0.5] The saturation temperature for 20 psig is 259 degrees F.[0.5]
l i l. L. - - --
p
- , ,.y m ;7, PROCEDUMA - ' NORMAL. ABNORMAL. ~ EleMENCY AND 'PAGE '22 RADIOLOGICAL CONTROL
'ANSWERSL-- ' PRAIRIE ISLAND 1&2 -87/06/16-TEMPS REFERENCE P.I. SD'B-4A pp33; Procedure C1.2 pp3 & 8
- 002000A403
..._(KA'S)
" ANSWER -7.07- (2.00)
'a.-As a RCP is' started, reflood of theLvessel upper head with cool water will collapse the steam bubble (0.5) and pressurizer level will decrease rapidly as pressurizer water' fills the void.(0.5) b..If a.RCP cannot be started and a rapid cooldown is initiated,- the void in.the upper head grows-larger (0.5) which causes an'insurge into the
. pres surizer..
The lower level prevents taking the pressurizer R solid.(0.5) REFERENCE P.I. Procedure 1ES-0.5 Background Information ppi 000027A201. ...(KA'S) 1
,I ANSWER .7,0 8 - '(1.60) i
- a. 75 Rem.[0.6] f
- b. Superintendent of Radiation Protection [0.5] l
- Emergency Director [0.5]
d i
- REFERENCE-Emergency Plan Implementing Procedures Number F3-12 rev. 3, p2 ~ i F2 rev. 4, p 12 194000A116 194000K104 194999K103 ...(KA'S) h u
, 1 l -: ' .
.- - - _ _ _ - _ - _ . _- - - - - - - - - - - - - - - - - - ^'
- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 23 E
/
ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS
/f, b
l l - ANSWER 8.01 (1.00)
- a. Superintendent Radiation Protection [0.5]
- b. Two SROs [0.5]
REFERENCE ', SACD 10.1 p. 2 ! Operations Manual C 17, rev. 9, p 2 P 8182L-033 rev. O, Fuel Handling: EO-4 n 0 P 9145L-001, ACDs abd Operations SWIs: EO-4 035000G001 ( 059000G001 068000G001 ...(KA'S) ANSWER 8.02 (1.20) Provides core protection against DNB [0.6] provided
- 1. Slow transient [0.3]
- 2. Pressure within range of trip values [0.3]
REFERENCE TS p 2.3-4, rev. 32 P 8184L-033, rev 0, Rx Process Instrumentation: EO-6 KA Importance 3.8 012000K501 ...(KA'S) ANSWER 8.03 (2.60) 0.l
- a. [0xf$> each for proper license
[4--f@ each for proper location
- o. I
- b. Unit i SRO [0.6]
- c. TSC [0 25:, OSC [0 25];
jjg f'c [0,'),5] EOF [025; REFERENCE SWI-0-2, rev. 13, p 2, 3 P 9145L-001, ACDs'and Operations SWIs: EO-04 KA importance 3.9, 3.4 194001A103 194001A109 ...(KA'S) 1 5
\,. /; '
,..e '2
%f'e y' .; it A _ ADMINISTRATIVE _P[tkQiFDURES, CONDITIONS. ANIi LIMITATIONS PAGE t
2d p.'m -ANSWERS - p 1WJRIE ISLAND 1&2 -
-87/06/16-TEMPS
'f r.
,Q 'l
,I
-p ' ANSWER 8.04 (2.40)
- a. Substation hold card log. [0.4] '. ,
i Plant substation electrical log. [0. 41,
.-src uk LMC LCG [faQy yi ' '
,A
- b. Unit 1 secure card log [0.4] f
- Component blocking and locking les; [0.4)
, Operating log [0.4] U Unit 1 Reactor log [0.4] / 4t.:t T 1 ITCLl? C ARD LOV CO 9]' *S
/ REFERENCE SWI-0-6 rev. 3, Hold and Secure Cards SADC 3.10.6 SWI-0-3 Safeguard hold card and component blocking / locking SWI-0-20 Outage completion '
P 9145L-001 ACDs and Opeyations EWIs- EO-4 KA.importance 3.4, 4 .1 - 194001A106 194001K102 ...(KA'S) ANSWER 8.05 '2.40) '
- a. SI Pump #11 must.be tested to demonstrate operability.[0.8)
- b. Shutdown initiated wfithin one hour [0.8)
Unit placed in hot shutdown within six hours after shut'down nau initiated [0.8] , REFERENCE P.I. Tech Specs 3.3-1A; SW1-0-22 ppi ' 006000G011 006000G015 ...(KA'S) f f ANSWER 8.06 (2.40) ^
- a. Alert [0.5] due to SGTR p 4-12 [0.3]
- b. Unusual Event [0.5] due to loss of offsite power p 4 -28 [ 0.15]e !
l
-toenado--; F 4 4-{0.1] u '
,4 transport injured man p 4-39 [0.19y D Atcar J r cu re .4 0c nri.s rt c.t Site ou A L c,t r en> c c ou A'rea Emg. [0.5] due to need for maritoring t.eams p 4-46 [0.2],
REFERENCE Lr un. ec t1 r>eFc G
.< y' 4'c Emergency Plan rev. 6, Chap 4.0 KA importance 4.4 tw s W taa ruv 194001A116 ...(KA'S) ,
o l , . .'
' 8 '.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 25 ANSWERS -- PRAIRIE ISLAND 1&2 -87/06/16-TEMPS ANSWER 8.07 (3.00)
- a. All parameters in spec with exception of FNQ at 10' [0.7]
using K(10') of 0.95 have 2.487 is not < 2.427 2.487-2 427 / 2.427 = 2.5% s Reduce power [0.5) to 87.5 % [0.3] Reduce flux trip setpoint by 2.5% [0.5] , Monitor rod position [0.2] ' Initiate in-core mapping [0.3]
- b. 05:00 [0.5] (30 minute pennity for FNQ) d REFERENCE r TS 3.10-1 P 8171L-033-J : EO 5, 6, 8 and Terminal Objective 001000G010 001000G011 ...(KA'S)
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