ML20137J610
| ML20137J610 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/06/1985 |
| From: | Guenther S, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20137J607 | List: |
| References | |
| 50-259-OL-85-02, 50-259-OL-85-2, NUDOCS 8508300434 | |
| Download: ML20137J610 (73) | |
Text
_ __
_4 ENCLOSURE 1 EXAMINATION REPORT 259/0L-85-02 Facility Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name: Browns Ferry Nuclear Plant Facility Docket Nos.: 50-259, 50-260, 50-296 Written examinations for the Browns Ferry Nuclear Plant were administered in the NRC, Region II offic 'n Atla ta, GA Chief Examiner: t- __,
W. x 5!s~ V S'gfriedGUgn Dath Signed Approved by: [
Bruce A y son, Sectip Chief Date Signed Summary:
Examinations on July 15, 1985 Written examinations were administered to two R0 candidates; neither candidate passed.
8508300434 850000 PDR G ADOCK 05000259 PDR
._ = _ _. -
REPORT DETAILS
- 1. Facility Employees Contacted A. R. Champion, Instructor, Browns Ferry Hot License Training Unit J. D. Johnson, Browns Ferry Requalification Unit Supervisor G. Moody, Browns Ferry Engineering Training Supervisor
- 2. Examiner S. Guenther, NRC, Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examination, the examiner met with A. R. Champion, J. D. Johnson, and G. Moody to review the written examina-tion and answer key. The following comments were made by the facility reviewers:
- a. Question 1.02.a Facility Comment: The pump curve figure is not the same one as in the book; this could lead to some confusion.
NRC Resolution: Figure 1.02 combines data found on three different transparencies (3-5) in the Browns Ferry reference material. If the candidate understands centrifugal pump characteristics, he should have no difficulty interpreting the figure.
- b. Question 1.21.a Facility Comment: The candidates may answer 0.1 to 1% power, mid range 7, P0AH (point of adding heat), or 0.7%
power.
NRC Resolution: The answer key was written to allow the grader latitude in marking the question. Any one of these answers is satisfactory for full credit.
- c. Question 1.22 Facility Comment: (a) is the best answer, although (d) might be considered true.
NRC Resolution: Oxygen will be generated in a post-LOCA containment due to the radiolytic decomposition of water. The resulting Hydrogen /0xygen mixture should be a significant concern to the operator. No change to the answer key is warranted.
Enclosure 1 2
- d. Question 1.23 Facility Comment: (b) or (c); although if you look at the figure, it does agree with the exam key.
NRC Resolution: With power in the intermediate range neutron flux will not be sufficient to cause a rapid Xenon burnout. (c) is the only correct answer.
- e. Question 2.23 Facility Comment: High Steam flow has a three second time delay so it may not trip. Thus (a) could be correct.
NRC Resolution: Browns Ferry procedure 01-73 indicates that the HPCI turbine WILL auto-isolate on high steam line flow, despite the 3-second time delay. If OI-73 is incorrect, then it should be changed to reflect the actual HPCI response,
- f. Question 3.11 Facility Comment: (d) could also have #3 as a correct answer since it is a yarway also.
NRC Resolution: Per Browns Ferry Lesson Plan #3, figures 2, 3, and 7, it appears that the Post-Accident Flooding Range instruments (LI-3-62/52) share the GEMAC A/B reference legs / condensing chambers. No change to the answer key is warranted.
- g. . Question 3.12 Facility Comment: (b), the flow-biased scram, is bypassed when not in RUN mode.
NRC Resolution: Browns Ferry Lesson Plan #22, figure 2, supports the facility's comment. The answer key has been changed accordingly.
- h. Question 3.16 Facility Comment: The candidates might list Rx zone and refueling zone as two different answers. .
NRC Resolution: This is a valid facility concern. The answer key has been modified to accept high ventilation exhaust radiation monitor readings in the refueling and reactor zones as two different signals.
4 Enclosure 1 3
- i. Question 3.17 Facility Comment: The question is not specific enough.
I NRC Resolution: The candidates should be aware of the rod movement controls and interlocks associated with various positions of the RSCS's Sequence Mode Selector and Rod Sequence Selector Switches. Any question regarding the clarity of the question should have been addressed to the examiner during the exam.
- j. Question 4.03 Facility Comment: The type of failure that has occurred should be addressed to allow the question to be analyzed instead of requiring memory of a list.
NRC Resolution: 0I-68 does not specify a failure mode within its symptoms, and no control room alarm exists which alerts the operator to the type of failure. No change to the question / answer is warranted.
- k. Question 4.09 Facility Comment: (b) or (c) could be correct. You must have the
, MSIVs closed in order to reset the Group 1 isola-l tion logic.
1 NRC Resolution: Although it is true that the MSIV handswitches must 1 be in the closed position to allow resetting the i isolation, it does not answer the question of why the precaution is necessary. No change to the
- answer key is warranted.
)
- 1. Question 4.10 4
Facility Comment: All the answers could be considered correct.
1, NRC Resolution: The premise of the question erroneously postulated
! an "undervoltage" vice an "overvoltage" condition and thereby made all the choices correct. The
- question has been deleted from the examination.
- m. Question 4.21
- Facility Comment: The candidates may state that the RFPT will go to
, the setting of the MSC and give a rapid increase in feedwater flow per the abnormal section of 0I-3.
t i
i i
- . -_ - ~ - - _ . - - - - - - - - - , _ - , - - , .
Enclosure 1 4 NRC Resolution: Since (per 01-3) the RFPT overspeed trip setting is above the high speed stop of the motor speed changer, an overspeed trip may not occur. The answer key has been changed to allow full credit for the alternate answer.
- n. Question 4.22 Facility Comment: The rod may not have stuck in the core so the LPRMs may change even if the rod is uncoupled, as long as it follows the drive out. "#2" of the answer key could be two parts of three.
NRC Resolution: It is true that the LPRMs may change even if a rod is uncoupled; however, as stated in 0I-85, it is still a method available to the operator for identifying an uncoupled control rod. No change to the answer key is warranted.
- 4. Exit Meeting The examinations were administered in the NRC, Region II offices. No site visit and no exit meeting were conducted.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
l l
l i
11 . S. NllCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: BROWNS FERRY 1, 213 REACTOR TYPE: BWR-GE4 DATE ADMINISTERED: 85/07/15 EXAMINER: GUENTHER,S APPLICANT _________________________
INSTRUCTIONS TO APPLICANT:
Una separate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at '
1 cast 80%. Examination papers will be picked up six (6) hours after tha examination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 30 B&res 1. PRINCIPLES OF NUCLEAR POWER -
___'50____ ______ ___________ ________
PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ZU c7 30 5 2579 PLANT DESIGN INCLUDING SAFETY
___1_0________'J _ ___________ ________ 7.
AND EMERGENCY SYSTEMS st-
'8.50 24.+5
_'_______ ______ ___________ ________ 3. INSTRUMENTS AND CONTROLS se 5 PROCEDURES - NORMAL, ABNORMAL,
_511_0___ _'}G" _ ___________ ________ 4. EMERGENCY AND RADIOLOGICAL CONTROL 7 11g 00 100.00 TOTALS FINAL GRADE _________________% All work done on this examination is my own. I have neither given nor received aid. l
~~~~~~~~~~~~~~
IPPL U UYI5~5EUUATURE
r- 1
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
--- isEER557sAsi5s- sEAi iEAssFEE As5 FE5i5 FE5s GllESTION 1.01 (1.00)
Which of the following statements correctly describes the behavior of the void coefficient of reactivity?
- o. It becomes more negative as the void fraction decreases.
- b. It becomes less negative as fuel temperature increases.
- c. It becomes less negative as core size increases.
- d. It becomes more negative as moderator temperature increases.
QUESTION 1.02 (1.00) The attached figure illustrates the ' Combined Head / Pressure Curves for Two Pumps'. Select from the figure the appropriate system operating point (numbered 1 through 6) for each of the following conditions.
- a. Pumps A and B running in SERIES with the pump discharse valve throttled shut from the initial condition.
- b. Pumps A and B running in PARALLEL with the pump discharge valve fully open.
QUESTION 1.03 (1.00) What is the process by which fission fragments and Beta particles transfer energy to reactor materials (fuel rods)?
- a. Direct Ionization
- b. Conduction
- c. Convection
- d. Radiation
(***** CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3
--- isEss559sisiEs- sEEi isissFEE Es5 FEUi5 FE5s QUESTION 1.04 (1.00) What are the units of neutron flux?
- o. neutrons / cm cubed
- b. neutrons / cm / second
- c. neutrons / cm squared - second
- d. neutrons / cm squared QUESTION 1.05 (1.00)
The rate of change of power in a nuclear reactor is governed by the average noutron seneration time (1-av). How does 1-av change as the core ases?
- a. 1-av INCREASES due to the DECREASE in the average delayed neutron fraction (B-bar) over core life.
- b. 1-av DECREASES due to the DECREASE in the averaSe delayed neutron fraction (B-bar) over core life.
- c. 1-av INCREASES due to the INCREASE in the averaSe delayed neutron ,
fraction (B-bar) over core life.
- d. 1-av DECREASES due to the INCREASE in the average delayed neutron fraction (8-bar) over core life.
QUESTION 1.06 (2.00) The attached figure represents a transient that could occur at a BWR. GIVEN: (1) A manual increase of the pressure setpoint to 1050 PSIG. (2) No other operator actions are taken. (3) Recorder speed: 1 division =1 minute EXPLAIN the cause(s) of the followins recorder indications:
- a. Core flow INCREASE at point #1
- b. Reactor pressure INCREASE at point #10
- c. Reactor level DECREASE at point #18
- d. Power INCREASE at point #22
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
i
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGC 4
--- isEER557sisiEs- sisi isiniFEE As5 FEUi5 FE5s QUESTION 1.07 (2.00)
The attached figure represents a transient that could occur at a BWR. GIVEN! (1) A closure of all MSIVs at 100% power. (2) No other operator actions are taken. (3) Recorder speed: 1 division =1 minute EXPLAIN the cause(s) of the following recorder indications!
- o. Core flow DECREASE at point #2
- b. NO power spike at point #15 due to the pressure spike at point #5
- c. Reactor vessel level INCREASE at point #13
- d. Total feedwater flow DECREASE at point #16 QUESTION 1.08 (1.00)
Which of the following radiation exposures would inflict the GREATEST biological damase to man?
- a. 1 Rem of GAMMA
- b. 1 Rem of ALPHA
- c. 1 Rem of NEUTRON
- d. NONE of the above; they are all equivalent HUESTION 1.09 (1.00)
Which of the following correctly describes the Maximum Fraction of Limitins Power Density (MFLPD)?
- a. LHGR-max / LHGR-LC0; must be maintained < 1
- b. LHGR-max / LHGR-LC0; must be maintained > 1
- c. LHGR-LCO / LHGR-max; must be maintained < 1
- d. LHGR-LCO / LHGR-max; must be maintained > 1
(***** CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATIONr PAGE 5
--- isEER55isARiEs- REAi fiAssFEE As5 FEUi5 FE5s QUESTION 1.10 (1.00) Which of the following correctly DEFINES ' void fraction'?
- a. steam volume in mixture / total volume of the mixture
- b. steam volume in mixture / liquid volume in mixture
- c. steam mass in mixture / total mass of the mixture
- d. steam mass in mixture / liquid mass in mixture QUESTION 1.11 (1.00)
When does a constant-speed centrifugal pump motor draw the LEAST current?
- a. at ' runout' conditions
- b. at its ' operating point'
- c. while 'cavitating'
- d. at ' shutoff head' conditions GUESTION 1.12 (1.00)
What is the QUALITY of a 540 degree F vapor-liquid mixture whose specific enthalpy is 1175 BTU /lbm?
- o. 0.559
- b. 0.816
- c. 0.964
- d. 0.971 l
1 (E**** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 6
--- iREER557sARICs- AEAi isissFER As5 FEUi5 FE5s QUESTION 1.13 (1.00)
Which of the following equations is used to perform a BWR reactor hoat balance? NOTEi c=CRD; f=Feedwateri s=Steami r=RWCU
- m. b-rx = (k3 x h.)+(d-amb)+(kc x he)-(ig xhp)-(d-pop)-(5cx Libr )
- b. b-rx = (i,x h,)+(E rx Libr)+( -amb)-(s,x hp)-(dtpap)-(se x h.)
- c. -rx = (s,x h,)+(d-pap)+(se x hc)-(k,x h )-(ke x Lihe)-( -amb)
- d. d-rx = (m,x h3)+(se x Lihe)+( -pap)-(5-amb)-(6,x h,)-(sex hc)
QUESTION 1.14 (2.00)
- c. DEFINE ' Critical Power'.
- b. Which one of the following conditions would tend to INCREASE the Critical Power level assuming all other variables remain unchanged?
- 1. Inlet subcoolins is DECREASED
- 2. Reactor pressure is DECREASED
- 3. The axial power peak is RAISED
- 4. Coolant flow rate is DECREASED QUESTION 1.15 (1.00) ;
1 Water, the primary coolant used in a BWR, can exist in three phases. Which l one of the following is correct concerning the phases of water? i 1
- a. The Latent Heat of Vaporization is the amount of heat required to l change one Ibn of water at 32F to one Ibn of steam at 212F. I
- b. It is impossible to raise the temperature of liquid water at atmos- I pheric pressure above 212F.
- c. The Latent Heat of Vapori=ation increases as system pressure is raised from atmospheric to normal operating pressure.
- d. The condenser removes sensible heat from the LP turbine exhaust in changing the saturated steam to saturated liquid.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) l l l i
I'
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 7
~ ~~~~TUER 66YU55E65I~U5IT TR5U5 FEE ~d 6" FLUED"FLUU QUESTION 1.16 (1.00)
Which of the following actions will INCREASE Browns Ferry's thermodynamic cycle efficiency?
- a. DECREASING power from 100% to 25% .
- b. LOWERING condenser vacuum from 29' to 25'.
- c. REMOVING a high pressure FW heater from service.
- d. DECREASING the amount of condensate depression.
QUESTION 1.17 (2.00) ANSWER THE-FOLLOWING TRUE OR FALSE:
- a. Shallow rods do NOT exhibit the reverse power response on rod with-drawal because the increase in voids is felt along a much greater length of the core.
- b. Withdrawing a shallow rod has a small effect on axial flux profile but a possible large effect on gross core poweri for this reason they are called power rods.
- c. The first rod withdrawn in a new 3roup has the highest worthi each succeeding rod in that group has a lower worth than the first.
- d. A control rod's worth varies directly with effective core size.
b (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
r
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 8
--- isEss559sAsiEs- sEAi isissFEE As5 FEUi5 FE5s QUESTION 1.18 (2.00)
MATCH each flow control line in COLUMN A with its correct descriptor(s) in COLUMN B AND its correct identification letter on the attached Power to Flow Operating Map. Multiple use of descriptors is possible. COLUMN A COLUMN B
- s. Minimum Power Line 1. Increases w/ power due to NC
- b. Minimum Expected Flow Control Line 2.Effect of rod insertion 9 power
- c. Minimum Pump Speed Line 3. Prevents recire pump cavitation
- d. Pump Constant Speed Line 4. Established at 50% rod pattern
- 5. Enforced by 20% FW flow intik 6.Recire pump dp remains constant GUESTION 1.19 (1.00)
Which of the following conditions will result in the largest (MOST nosative) Doppler /fvel temperature coefficient?
- a. 1000F fuel temperature with 10% voids
- b. 2000F fuel temperature with 10% voids
- c. 1000F fuel temperature with 30% voids
- d. 2000F fuel temperature with 30% voids
(***** CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 9
--- iAEss557sAsiEs- sisi isAssFEE As5 FEUi5 Fess QUESTION 1.20 (2.00) The attached fi3ure illustrates the ' Core Spray System Pipe Break Detect-ion Instrumentation'. Answer the followin3 9uestions by referring to and discussing, as necessary, the expected pressure relationships between the points labeled 1 through 7.
- a. What is the pressure relationship between points 6 and 7 while operating normally at power? JUSTIFY your answer. (1.0)
- b. BRIEFLY EXPLAIN HOW and WHY this dp will change if a core spray pipe break were to occur between the core shroud and the vessel nozzle. (1.0)
UUESTION 1.21 (2.50) The reactor is supercritical on a 60-second period in the source range at BOL. Assuming no further rod movements and the following initial conditions, STATE / CALCULATE the FINAL STABLE values of reactor power, temperature, and pressure. Show assumptions and calculations where necessary.
- a. Reactor power 2E +4 cps (0.5)
- b. Reactor temperature 281 F (1.5)
- c. Reactor pressure 35.3 psis (0.5)
GUESTION 1.22 (1.00) Si3nificant quantities of Hydrogen gas may be generated during, or sub-sequent to, a LOCA. This Hydrogen gas...
- a. is generated primarily by the zircaloy-water reaction if fuel clad temp-erature is allowed to exceed 2000 F.
- b. is generated pr_imarily by the radiolytic decomposition of water.
- c. could cause an-explosive hazard in the drywell if allowed to exceed the lower flammabi'lity limit of 1% in air.
- d. is of little concern since the containment is inerted and no oxygen should be present in the post-LOCA containment atmosphere.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 10
--- iAEss55isEsics- sEAi isAssFEs As5 FE5i5 FE5A QUESTION 1.23 (1.00) The reactor trips from full power, equilibrium xenon conditions. Twenty-four hours later the reactor is brought critical and power level is main-toined on range 5 of the IRMs for several hours. Which of the following statements is CORRECT concerning control rod motion?
- c. Rods will have to be withdrawn due to xenon build-in.
- b. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of xenon burnout.
- c. Rods will have to be inserted since xenon will closely follow its normal decay rate.
- d. Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.
(***** END OF CA EGORY 01 *****)
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 11 QUESTION 2.01 (1.00)
MOV-48 controls the RBCCW supply to the NON-ESSENTIAL loads. When will it automatically close?
- a. On a LOCA signal
- b. During a Loss of Offsite Power
- c. On low RBCCW pump discharge header pressure (609)
- d. On low Essential Header pressure (604)
QUESTION 2.02 (1.00) How would a loss of service air affect the operation of the Standby Liquid Control System (SBLC)?
- a. The SBLC tank level indication would be inoperable.
- b. The SBLC tank air sparser would be inoperable.
- c. The SBLC tank level indication and air sparser would be inoperable.
- d. It would have NO impact since the instrument air system supplies all SBLC needs.
QUESTION 2.03 (1.00) Which one of the following loads is powered from the 125 VDC Diesel Generator Battery System?
- a. The DG's DC air start compressor
- b. The associated Shutdown Board's control power
- c. The DG's motor driven fuel pump
- d. The DG's emergency lubricating oil pump (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
\
f
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 12
,-5 QUESTION 2.04 (1.00)
The following conditions are noted to exist. Which one will shut down the operating Steam Jet Air Ejector (SJAE)?
- a. Steam supply pressure / 210 psis
- b. Condenser vacuum / 10' Hg
- c. Off gas holdup volume temperature / 130 F
- d. NONE of the above 00ESTION 2.05 (1.00) l t
Which one of the followin3 EECW loads will be 'shed" automatically if EECW header pressure decreases to 50 psis?
- a. Control bay air conditioners
- b. RBCCW Hx
- c. Drywell Hydrogen and Oxygen analy=ers
- d. Control' air compressors QUESTION 2.06 (1.00)
The Recirculation MG Set Oil System is in its normal lineup for power
, cperation when the running AC oil pump trips.The DC oil pump auto starts f when the standby AC pump fails to restore oil pressure above 204. Which
) of the following correctly reflects the current equipment status? l
- a. The AC oil pump (s) AND the MG set drive motor have tripped.
- b. The AC oil pump (s) continue to run; the MG set drive motor has tripped.
- c. The AC oil pump (s) have tripped; the MG set drive motor continues to run.
- d. The AC oil pump _(s) and the MG set drive motor continue to run.
(***** CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx) b - -
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 13 OllESTION 2.07 (1.00)
An SRV actuates and the relief line vacuum breaker sticks OPEN. What censequences will this have during subsequent actuations of that SRV?
- c. It will have NO consequences since that is the normal position of the valve.
- b. Suppression chamber pressure will INCREASE since noncondensed steam would be vented above the torus water level.
- c. Water may be " pulled up' into the relief line and could result in over pressuri:ation of the line.
- d. Drywell pressure will INCREASE since noncondensed steam would be vented directly to its atmosphere.
QUESTION 2.08 (1.00) Which one of the following is NOT a function of the Standby Liquid Control (SBLC) injection pipin3 / vessel Penetration?
- a. Provide for measurement of above and below core plate pressure and hence core dp.
- b. Provide for measurement of above core plate pressure for use in jet pump flow measurement. j
- c. Provide a pressure reference to the CRD system for drive water dp.
- d. Provide a pressure reference for the Core Spray injection valve l logic.
QUESTION 2.09 (2.50) . MATCH each steam load in COLUMN A with ALL its possible sources of steam cupply listed in COLUMN B. COLUMN A COLUMN B
- a. HPCI .~ __ 1. Auxiliary Boiler
- b. RCIC 2. MSL A
- c. RFPT A 3. MSL B
- d. SJAE A 4. MSL C
- e. Off-Gas preheater 5. MSL D
- 6. MS equalizing header
- 7. MT cross-around header
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****) l l
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 14 L
QUESTION 2.10 (1.00) Which of the following is the only CLOSED valve in the RCIC steam supply flow path while in its normal standby lineup?
- o. Steam Supply Valve (FCV-71-8)
- b. Outboard Steam Isolation Valve (FCV-71-3)
- c. Trip Throttle Valve (FCV-71-9)
- d. Governor Valve (FCV-71-10)
HUESTION 2.11 (1.00) Which of the following correctly describes the interlocks associated with the RCIC pump suction valves?
- o. The suction source will automatically swap from the CST to the torus upon a high level in the torus.
- b. The CST suction valve will auto close when both torus suction valves are fully open.
- c. The CST suction valve will auto open (if closed) on initiation ONLY IF l BOTH torus suction valves are fully closed.
l
- d. The suction source will automatically swap from the CST to the torus I upon a low level in the CST.
l GUESTION 2.12 (1.00) The plant is operating normally at power when you receive a "Recire Loop A Control Seal Leak Abnormal' alarm and note a DECREASE in No.2 recire pump seal pre;;ure. Which of the following failures would cause this indication?
- a. Failure of No. 1 seal
- b. FailureofNo.((2 seal
- c. Plugging of the No. 1 internal restricting orifice
- d. Plugging of the No. 2 internal restricting orifice (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 15 QUESTION 2.13 (1.00)
Which one of the followins statements correctly describes the design /oper-ction of the ECCS Keep Fill System (PSC)?
- a. It can take its water from the pump suction of either Core Spray System I OR System II.
- b. The PSC pumps run continuously to maintain > 48 psis on system pipins.
- c. CST static head automatically supplies a backup pressure source in the event of PSC failure.
- d. The pump suction valves close on a PCIS Group 2 isolation signal.
QUESTION 2.14 (1.50) LIST six (6) DIFFERENT components supplied by the Drywell Control Air System. (e.g. RHR pumps A and B would be considered 1 component) GUESTION 2.15 (1.50) For each RHR system listed in COLUMN A, select from COLUMN B the RHR eystem(s), if any, with which it can be cross-connected. COLUMN A COLUMN B
- a. Unit 1, System 1 1. Unit 1, System 1
- b. Unit 1, System 2 2. Unit 1, System 2
- c. Unit 2, System 1 3. Unit 2, System 1
- d. Unit 2, System 2 4. Unit 2, System 2 ,
G. Unit 3, System 1 5. Unit 3, System i j
- f. Unit 3, System 2 6. Unit 3, System 2
- 7. Cannot be cross-connected GUESTION 2.16 (1.50)
LIST the three (3)[permissivesi3nals/setpoints required to allow simul-teneous openins of both the inboard and outboard RHR containment spray valves. i l (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx) 1
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 16 QUESTION 2.17 (2.00) 4KV Shutdown Board 3EA has a normal and three alternate power sources.
IDENTIFY the normal source and, IN THE ORDER OF PREFERENCE, the three e1 ternate sources of power for the Board. QUESTION 2.18 (1.00) Briefly EXPLAIN WHY the condenser circulating water system vacuum breaking system must be actuated if all the CW pumps trip. Include WHY it is neces-scry and the CONSEQUENCE of not doins it. QUESTION 2.19 (1.00) The Raw Service Water System is in a normal lineup with one pump running. LIST the automatic actions initiated in the RSW system upon starting any hish pressure fire pump. QUESTION 2.20 (1.00) LIST TWO (2) design features which prevent the secondary containment from beins overpressuri=ed. QUESTION 2.21 (2.00) LIST FOUR (4) signals which will result in a DIRECT trip of the RWCU racirculation pumps. (*****' CATEGORY 02 CONTINUED ON NEXT PAGE *****)
4
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 17 GUESTION 2.22 (1.00)
Which one of the following statements correctly describes the functioning of the ADS 120 second timer?
- a. The timer must be manually reset to prevent blowdown if the low water level signals clear during the timer run-out.
- b. The timer will auto reset if the high drywell pressure signal clears during the timer run-out.
- c. The timer can be manually reset to close the ADS valves once they have opened.
- d. The timer reset PB must be held in the depressed position to delay automatic blowdown beyond the 120-second timer run-out interval.
QUESTION 2.23 (1.00) In accordance with BF-0I-73, the HPCI auxiliary oil pump is left running for 15 minutes after the turbine is shut down. How will the HPCI system respond if an initiation signal is received durinS this 15-minute period?
- a. The system will start and inject normally.
- b. The system will auto-isolate on high steam line flow.
- c. The system will auto-isolate on mechanical overspeed.
- d. The system will fail to start.
QUESTION 2.24 (1.00) The Standby Gas Treatment System (SBGT) must be operated to remove non-condensables when the HPCI system is in operation. Where does it remove these noncondensables from?
- c. From the suppression chamber where they are vented by the HPCI gland exhauster. -
- b. Directly fromIt'he HPCI gland seal condenser.
- c. Directly from the discharge of the HPCI gland exhauster.
- d. From the HPCI pump room due to HPCI turbine shaft seal leakage.
(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
- 2. PLANT DESIGN INCLUDING SAFETY AND EHERGENCY SYSTEMS PAGE 18
, GUESTION 2.25 (1.50) Answer the following TRUE OR FALSE:
- a. The condensate heat exchanger flow balancing valve controls flow to ensure that the steam packing exhauster condenser has sufficient cooling flow.
- b. All nine full-flow condensate polishing filter /demineralizers must be in service for full power operation.
- c. The feedwater flow regulating valve fails open on a gradual loss of air pressure; however a handuheel is provided to force the diaphragm down and close the valve.
(***** END OF CATEGORY 02 *x***) M C
l i I r l l
- 3. INSTRUMENTS AND CONTROLS PAGE 19 GUESTION 3.01 (1.00)
The mode switch is in RUN and 14 of the 21 LPRMs assigned to APRM 'A' are operable. Which of the followins automatic actions will occur as a result of one of those 14 LPRM inputs failing downscale? (NO operator action.)
- o. A rod block
- b. A reactor half-scram
- c. A rod block and a reactor half-scram
- d. None of the above QUESTION 3.02 (1.00)
The Full-Core Display on the 9-5 panel has a BLUE scram light for each control rod. What is DIRECTLY indicated when this light is illuminated?
- a. That BOTH the inlet and outlet scram valves for that rod are open.
- b. That BOTH scram pilot air valves for that rod are deenergized.
- c. That BOTH scram pilot air valves for that rod are energized.
- d. That the beyond full-in overtravel reed switch for that rod is closed.
QUESTION 3.03 (1.00) Which of the following statements correctly describes the functioning of the Reactor Manual Control System (RMCS) auxiliary timer?
- a. It monitors the rod insert and withdraw cycles to prevent a faulty master timer from causing uncontrolled rod movement.
- b. It can be defeated by use of the CRD Notch Override Switch.
- c. It generates both a rod withdrawal and a rod insert block if and when it times out.
- d. It deselects the selected rod at the end of the automatic timer sequence for that movement cycle.
(***x* CATEGORY 03 CONTINUED ON NEXT PAGE *****) l l r l l l l
- 3. INSTRUMENTS AND CONTROLS PAGE 20 QUESTION 3.04 (1.00)
Which of the following indications / events will NOT occur when a Rod Block Monitor (RBM) system edge rod selected signal is generated?
- a. Both RBM channels will be automatically bypassed.
- b. Both RBM recorders will fail as is.
- c. The 4-rod display meters will continue to indicate any LPRM outputs which are present.
- d. All 4-rod display LPRM Detector Bypass lights will illuminate.
QUESTION 3.05 (1.00) An LPRM detector fails downscale and its function switch (S-1) on Fanel 9-14 is placed in the ' Bypass' position. Which set of indications (o through d) is correct for all the listed displays / panels? FULL-CORE DISPLAY FOUR-ROD DISPLAY PANEL 9-14
- a. white d/s light white bypass light white d/s light white bypass light
- b. no trips / lights white d/s li St h amber d/s light white bypass light
- c. no trips / lights white bypass light white d/s light white bypass light
- d. amber d/s light amber d/s light amber d/s light white bypass light (xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xx***)
- 3. INSTRUMENTS AND CONTROLS PAGE 21 QUESTION 3.06 (1.00)
Control room panel 9-5 contains two Primary Containment Isolation System roset switches (S32 and S33). Which PCIS stoup isolations are reset with these switches?
- o. Groups 1 through 8
- b. Groups 1,2,3,6,8
- c. Groups 1,2,4,5,7,8
- d. Groups 1,2,3,5,7 QUESTI0if 3.07 (1.00)
Which of the following signals / conditions is sensed to generate a reactor
'Recire. MG Set A/B Incomplete Startup Seq.' alarm?
- a. Failure of the voltage regulator to transfer from the startup source to the generator output.
- b. Failure of the pump discharge valve to start jossing open within three seconds.
- c. Failure of the generator to accelerate to 40% speed within fifteen seconds.
- d. Failure of the pump to develop a differential pressure of 5 pai within fifteen seconds.
QUESTION 3.08 (1.00) The main turbine has been reset in preparation for startup. Which of the followins sets of valve position changes / indications (a through d) would you expect to observe after selecting "Shell Warming'? TURBINE CONTROL TURBINE STOP INTERMEDIATE STOP INTERCEPT VALVES VALVES VALVES VALVES
- e. remain closed open fully remain closed remain open
- b. open fully close fully close fully open fully
- c. open fully remain closed close fully remain closed
- d. close fully open fully remain closed close fully (xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE *****)
- - - _ . _ mm.-
- 3. INSTRUMENTS AND CONTROLS PAGE 22 QUESTION 3.09 (1.00)
How would an SR'M* detector respond to a pin hole leak which caused a gradual decrease in Argon gas pressure?
- a. Gamma and neutron sensitivity would DECREASE.
- b. Gamma sensitivity would DECREASE but neutron sensitivity would REMAIN UNCHANGED.
- c. GAMMA sensitivity would REMAIN UNCHANGED but neutron sensitivity would DECREASE.
- d. Both samma and neutron sensitivity would REMAIN UNCHANGED.
QUESTION 3.10 (1.00) A reactor / plant startup is in progress with the node switch just having baen placed in RUN. APRM 'B' is bypassed due to a downscale failure.The IRMs have not yet been withdrawn when IRM channel 'H' fails upscale. What trip (s) will occur as a result of this failure?
- a. A rod block
- b. A reactor half-scram
- c. A rod block and a reactor half-scram
- d. None of the above UUESTION 3.11 (3.00)
MATCH each reactor vessel level indicator range in COLUMN A with ALL its applicable characteristics listed in COLUMN B. MULTIPLE matches are possible. COLUMN A COLUMN B
- a. Normal Control Range 1. Referenced to Inst. :ero
- b. Emergency System Range 2. Temperature compensated
- c. Shutdown Vessel Flooding Range 3. No elec. Power required
- d. Post-accident Flooding Range 4. No trips or alarms
- 5. Referenced to TAF
- 6. FWCS input
- 7. Only accurate with pumpr off
- 8. Calibrated cold
(**xxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx)
- 3. INSTRUMENTS AND CONTROLS PAGE 23 GUESTION 3.12 (2.00)
MATCH each UNIT 3 reactor scram signal listed in COLUMN A with ALL its sppropriate bypass conditions, IF ANY, listed in COLUMN B. MULTIPLE octches are possible. COLUMN A COLUMN B
- a. MSL High Rad (3 x NFLB) 1. RUN mode
- b. APRM HI HI 4.66W + 54) 2. STARTUP mode
- c. Scram DischarSe Volume (50 sal) 3. SHUTDOWN mode
- d. Condenser Low Vacuum (23' Hs) 4. REFUEL mode
- 5. Keylock switch
- 6. < 1055 psis reactor pressure
- 7. < 154 psig ist stage pressure
- 8. Never bypassed GUESTION 3.13 (1.50)
LIST the THREE (3) conditions and setpoints under which an APRM Flow Converter will produce a rod block. QUESTION 3.14 (1.00) A TIP trace is being run in the automatic modei the SCAN light is lit. A Group 2 PCIS isolation si3nal is received. DESCRIBE how the TIP system will respond. QUESTION 3.15 (1.00) Reactor power is at 33% of rated. What will happen when a rod is selected which is NOT contained in the currently latched group?
- a. a rod select error
- b. a rod withdrawal block
- e. a rod select error and a rod withdrawal block
- d. none of the above
(*x*** CATEGORY 03 CONTINUED ON NEXT PAGE ***x*)
- 3. INSTRUMENTS AND CONTROLS PAGE 24 QUESTION 3.16 (2.00)
What FOUR (4) signals, including setpoints, will automatically start the Control Room emersency pressurization unit? OUESTION 3.17 (1.50) A reactor startup is in pro 3ress and all A-12 and A-34 rods have been fully withdrawn $ the Sequence Mode Selector (SMS) and the Rod Sequence Selector (RSS) switches are placed in " NORMAL". This switch lineup... (COMPLETE THE FOLLOWING SENTENCES)
- a. allows...
- b. enables...
- c. bypasses...
QUESTION 3.18 (1.00) Answer the followin3 TRUE OR FALSE:
- e. The ' Mode Switch in Shutdown' scram signal is automatically bypassed after a two-second time delay thereby ensuring that all rods have completed their scram stroke,
- b. Closing a single Turbine Stop Valve may or may not, in and of itself, cause a reactor half-scram.
(***** CATEGORY 03 CONTINUED ON NEXT PAGE **xxx)
l l i i l l
- 3. INSTRUMENTS AND CONTROLS PAGE 25 l
QUESTION 3.19 (2.00) For each of the following situations (i and ii) select the correct Feed-water Control System / plant response from the list (a through e) which follows. An answer may be used more than once, and NO operator actions ! ere taken.
- a. Reactor water level decreases and stabilizes at a lower level.
- b. Reactor water level decreases and initiates a reactor scram.
- c. Reactor water level increases and stabilizes at a higher level.
- d. Reactor water level increases and initiates a turbine trip.
- e. None of the above.
- i. The plant is operating at 90% power in 3-element control when the HPCI l system inadvertently initiates and injects.
ii. The plant is operating at 100% power, in 3-element control, with "B" level detector selected when I & C Bus 'A' loses power. l l GUESTION 3.20 (1.00) t ! S21ected ARM sensor and converter units have installed ' bus' sources. These sources... l
- a. are normally shielded and are exposed only as required to test the j detector's operation.
( b. are only installed in those locations having a background reading ! above 0.1mr/hr.
- c. do not affect the ARM's indicated background radiation level in those areas monitored.
- d. aid in the detection of equipment malfunctions which cause downscale trips.
(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx)
4
- 3. INSTRUMENTS AND CONTROLS PAGE 26 QUESTION 3.21 (1.50)
Answer the following TRUE or FALSE:
- o. Four Backfeed switches, one for each 4160V Shutdown Board, are provided to allow feeding DG power back to the Unit Boards in order to start a CCW pump and establish the main condenser as a heat sink.
- b. The DG Emergency Stop feature shuts off the flow of fuel oil to the injectors; this could result in injector damage due to loss of cooling.
- c. Both banks of DG air start motors will be locked out if the engine fails to start on its third attempt.
QUESTION 3.22 (1.00) When synchronizing the generator to the gride the procedure directs the operator to adjust turbine speed to slowly rotate the synchroscope in the fast (clockwise) direction. Which of the following correctly gives the two parameters that the synchroscope is indicating?
- a. Current and voltage differences.
- b. Current and frequency differences.
- c. Voltage and phase differences.
- d. Frequency and phase differences.
(***** END OF CATEGORY 03 *****)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 27
~~~~RA5i5E55fCAC C5UTR5E------------------------ GUESTION 4.01 (1.00) OI-74, 'RHR System', cautions the operator NOT to start an RHR pump for Shutdown Cooling until after the recirculation pump for the associated loop is shutdown. Why is this precaution necessary?
- c. To prevent reverse flow through the RHR loop and heat exchanger.
- b. To prevent excessive jet pump vibration.
- c. To prevent exceeding the allowable RHR pump casing cooldown rate.
- d. To minimize thermal stratification in the RPV bottom head.
QUESTION 4.02 (1.00) Unit i has suffered a complete loss of RBCCW. Recovery efforts fail to restore drywell cooling within 10 minutesi drywell temperature is 185 F End rising. What operator actions are required per DI-70, 'RBCCW'?
- a. Immediately scram the reactor, trip the recirculation pumps, and initiate a reactor cooldown at 90 F/hr.
- b. Continue to monitor DW temperature; manually scram the reactor if DW temperature exceeds 200 F.
- c. Reduce recirculation flow to minimum; trip the recire pumps when seal cavity / cooling water temperatures alarm at 160 F.
- d. Immediately trip the recirevlation pumps; manually scram the reactor if DW temperature exceeds 200 F.
QUESTION 4.03 (1.00) Which of the followin3 is a symptom that you would expect to see as a result of a " Jet Pump Failure
- per OI-68?
- a. Decrease in indicated Core Flow
- b. Decrease in failed jet pump flow
- c. Increase in Core Differential Pressure
- d. Increase in Recirculation Flow in BOTH loops
(*xxxx CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 28
~~~~R 5656[66565L 66UTRUL'~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.04 (1.00) Unit 1 is operating at 100% power when the Off-Gas Post Treatment Radiation Manitor HI/HI/HI trip point is reached. Per DI-66, 'Off-Gas System *, which of the followins is NOT an appropriate operator action?
- e. Check the Off-Gas System isolated.
- b. With Supervisor's approval, reduce power to 60% with recirculation flow and then manually scram the reactor.
- c. Manually start the Standby Gas Treatment System.
- d. Stop the running stack dilution fans and start the standby dilution fan.
QUESTION 4.05 (1.00) Which of the following feed pump operating sequences is correct per DI-3,
'Feedwater System'?
- a. Place RFPT on turnins gearr start RFP seal injection water flow, admit RFPT sealing steam, pull condenser vacuum.
- b. Start RFP seal injection water flow, place RFPT on turnin3 Sear, admit RFPT sealing steam, pull condenser vacuum.
- c. Admit RFPT sealing steam, pull condenser vacuum, place RFPT on turning sear ~r start RFP seal injection water flow.
- d. Place RFPT on turning sear, admit RFPT sealinS steam, pull condenser vacuum, start RFP seal injection water flow.
QUESTION 4.06 (1.00) Per the ' Control Room Abandonment' procedurer what is the preferred method of scramming the reactor if you are UNABLE to do so prior to leaving the control room?
- a. Open the APRM feeder breakers to the RPS distribution panels.
- b. Alternately transfer both RPS buses to the alternate power supply,
- c. Locally isolate and vent the scram air header.
- d. Close the MSIVs at the Backup Control Panel.
(xxxxx CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 29
~~~~RA5i5E55fEAE C5WTR6[~~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.07 (1.00) Which of the following is a valid limitation applicable to Radiation Work Pormits for Routine Entry (RRWP)?
- c. An individual with a quarterly exposure limit of 250 mrem is NOT allowed to enter on an RRWP.
- b. The maximum allowed daily dose on any combination of RRWPs is 100 mrem.
- c. If both an RWP and an RRWP are in effect for an area, then EITHER permit may be used for entry.
- d. An RRWP will NOT be used for entry into areas with a dose rate in excess of 1 Rem /hr.
QUESTION 4.08 (1.00) A cold (185 F) reactor startup is in progress per GOI-100-1, 'Inte3 rated Plant Operations'. Select the proper sequence for performing the following steps from the heatup and pressurication section of the GOI.
- 1. Pull rods to raise power to mid-range 7 on the IRMs.
- 2. Reset HPCI low pressure isolation.
- 3. Place reactor feed pump in service.
- 4. Close reactor head vent (FCVs 3-98/99).
- 5. Raise pressure regulator setpoint to 920 psig.
- 6. Verify / open outboard MSIVs.
- 7. Reset RCIC isolation.
- 8. Switch SJAE to nuclear steam.
- a. 1,6,4,7,2,8,3,5
- b. 4,6,1,2,7,5,3,8
- c. 6,1,4,7,2,5,3,8
- d. 1,6,5,4,7,2,8,3
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) i l 1
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 30
- ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~R 656L66EddL C6 TR L QUESTION 4.09 (1.00)
OI-1, ' Main Steam System', cautions the operator to place the MSIV hand-owitches in the CLOSED position if the valves have closed automatically. Why is this precaution necessary?
- a. To seal in the close signal and prevent inadvertent valve opening.
- b. To permit resetting of the Group 1 isolation signal.
- c. To prevent the continued loss of control air pressure.
- d. To prevent valve actuator dama3e.
l QUESTION 4.10 (1.00) A 4160 V Shutdown Board A, B, C, D undervoltase alarm is received on Unit
- 1. Which of the following actions is CORRECT per DI-57, ' Auxiliary Electrical Systems *?
- a. Change the USST - B transformer taps.
- b. Contact the dispatcher to raise the system voltage.
- c. Place the capacitor banks in service.
- d. Raise the main senerator reactive power output.
QUESTION 4.11 (1.00) H:w is RPV temperature stratification prevented / minimized, per GOI-100-12, if RHR Shutdown Cooling is lost and cannot be restored?
- a. Raise RPV level to 60*; increase RWCU flow to maximumi reject water as necessary to keep moderator temperature < 200 F.
- b. Raise RPV level to the main steam lines; establish flow through the HSL drains to condenseri return flow to the RPV via condensate system.
- c. Maintain normal RPV level; maximize RWCU reject flow; return flow to the RPV via condensate system.
- d. Raise RPV level to the main steam linesi open 1 SRV to establish flow to the torusi return flow to the RPV via Core Spray system.
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 31
~
~~~~R d6I6[6656 L C6UTR6[~~~~~~~~~~~~~~~~~~~~~~~~ QUESTION 4.12 (1 00) Which of the following is a 10 CFR 20 exposure limit?
- a. 5 rem / year-whole body.
- b. 1 res/ quarter-whole body.
- c. 18.75 ren/ quarter-hands,
- d. 7 rea/ quarter-skin of whole body.
QUESTION 4.13 (1.00) Which of the following parameters is NOT required to verify RPV flooding without indication of RPV water level, per EDI-1?
- o. RPV pressure must be greater than suppression chamber pressure by at least 704.
- b. HPCI and RCIC are injecting into the RPV at rated flow.
- c. RPV pressure must be steady or increasing.
- d. At least three (3) MSRVs must be open.
QUESTION 4.14 (1.00) An MSRV has opened inadvertently and attempts are being made, per DI-1, to close the valve. How long can the valve remain open before a manual roactor scram MUST be initiated?
- a. 1 minute
- b. 2 minutes
- c. 5 minutes
- d. 10 minutes -
(xxxxx CATEGORY 04 CONTINUED ON NEXT PAGE ***xx) l 1
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 32
- -------------~~---------
~~~~RA555L55iEAL E5 TR5t QUESTION 4.15 (2.00) Unit 2 is operating at 100% power when a reactor scram occurs due to a Group 1 isolation. LIST ALL the required operator scram actions, per GOI-100-11, " Reactor Scram', with regard to the reactor NUCLEAR INSTRUMENTATION. QUESTION 4.16 (2.00) LIST ALL the times, per GOI-100-1, ' Integrated Plant Operations', when core thermal limits are required to be checked. QUESTION 4.17 (1.00) A Unit i startup is in progress with reactor power at 18%. What actions are required, per GOI-100-6, ' Rod North Minimi:er System', if the RWM becomes INOP while one of the two operators performing rod movement or verification of rod movement is out of the control room? QUESTION 4.18 (1.00) EDI-2, ' Containment Control', cautions the operator NOT to initiate drywell sprays unless torus water level is below 17ft 2*. BRIEFLY EXPLAIN WHY this precaution is necessary. QUESTION 4.19 (3.00) LIST ALL the immediate operator actions required by EDI-3, " Reactivity Control'. 00FSTION 4.20 (2.50) LIST the five (5) entry conditions for EDI-1, 'RPV Control'. , (xxxxx CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Rd6E6L 55EdL dUUTR6L QUESTION 4.21 (1.00) OI-3, "Feedwater System's cautions the operator NOT to energize the RFPT apeed jack until the MSC is in control. BRIEFLY EXPLAIN WHY this precaution is necessary. QUESTION 4.22 (1.50) LIST THREE (3) methods, per OI-85, " Control Rod Drive', of identifying an UNCOUPLED control rod. QUESTION 4.23 ( .50) TRUE OR FALSE: The turbine nameplate rating of 1098 MWe may be exceeded as long as the 3293 MWt reactor power limit and the gen-erator capability curve are enforced. (xxxxx END OF CATEGORY 04 xxxxx) (********xxxxx END OF EXAMINATION ****xxxxxxxxxxx)
. fvw v o svS 2
a a mg s a V,t
- 1/2 at
[ = mC* -
~kt A = la XE = 1/2 mv a = (Vf - /3 )/t A = A,e PE = mgn vf = V, + at w = e/t i = zn2/t1/2 = 0.693/t1/2 2
w . , .p nD 1/2'N
- UI1/~> N Id 3 A= 4 ((g/2 l I
- II D)I t.E = 931 mn -
m = V,yAo .tx Q.= m,ah I = I,e Q = mCpat 6 = UA4 T I = I,e~"* pwr = W ah I = I,10**/DL f WL = 1.3/u P = P 10 sur(t) HVL = -0.693/u t P = P,e /T SUR = 26.06/T SCR = S/(1 - K,g) CR, = S/(1 - K,ffx) SUR = 26o/t* + (a - o)T CRj (1 - K,gj) = CR2 (I ~ keU2) T = ( t*/o ) + [(s - o VIo] M = 1/(1 - K,g) = CR /CR j 3 T = 1/(o - s) M = (1 - K,ff,)/(1 - K,gj) T = (s - o)/(Io) SDM = ( - K,g)/K,g a = (K ,g-1)/K ,g = 4K,ff/K,g t* = 10 seconds ! I = 0.1 seconas-I I o = [(t*/(T K,g)] + [a,ff /(1 + IT)] I jd) = I d l P = (tov)/(3 x 1010) I jd) 2 ,27d 2 22
, I = eN R/hr = (0.5 CE)/d2 (,,g,73) '
2 R/hr = 6 CE/d gf,,g) Water Parameters Miscellaneous Conversions 1 1 gal. = 8.345 lem. I curie = 3.7 x 1010 aps
', 1 ga; . = 3.78 liters 1 kg = 2.21 lbm 1 ft' = 7.48 gal I hp = 2.54 x 103 Stu/nr .
Density = 62.4 1 /ft3 1 mw = 3.41 x 100 5tu/hr
. Density =-1 gm/c lin = 2.54 cm s Heat of vaporization = 970 Stu/lem 'F = 9/5'C + 32 Heat of fusion = 144 Stu/lbm ,
'C = 5/9 (*F-32) l 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf I 1 ft. H O = 0.4335 lbf/in, 2
e = 2.718 e -.
V.twn., C.'/lb Enth.lpy Sty /lb Ent,.py. Stellt a F
- 7' y,' m i., e, m- w.i.,
a, i, m a,
=t. , ._
, 8 *r
., , 4 a. , 5 l
0,01602 3305 3305 -0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 82 0.08859 0.01602 2948 2948 3.00 1073.8 1076.8 0.0061 2.1706 2.1767 35 35 0.09991 0 01602 2446 2445 8.03 1071.0 1079.0 0.0162 2.1432 2.1594 40 40 0.12163 0 0262 2.1164 2.1426 45 45 0.14744 0.01602 2037.7 2037.8 13.04 1068.1 1081.2 0.01602 1704.8 1704.8 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 50 80 0.17796 0.01603 1207.6 1207.6 28.06 1059.7 1087.7 0.0555 2.0391 2.0946 60 80 0.2561 0.01605 868.3 868.4 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 0.3629 70 1096.4 0.0932 1.9426 2.0359 80 0.5068 0.01607 633.3 633.3 48.04 1048.4 to i 468.1 468.1 58.02 1042.7 1100A 0.1115 13970 2.0086 90
- 90 0.081 0.01610 0.1295 1A530 1.9825 300 0.)492 0.01613 350.4 350.4 68.00 1037.1 1105.1 100 0.1472 1A105 1.9577 110 1.2750 0.01617 265.4 265.4 77.98 1031.4 1109.3 110 0.01620 203.25 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 120 1A927 0.01625 157.32 157.33 97.96 1019.8 1117A 0.1817 1.7295 1.9112 130 130 2.2230 2.8892 0.01629 122.98 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1A895 140 140 1.8686 0.01634 97.05 97.07 117.95 1008.2 1126.1 0.2150 1.6536 150 150 3.718 0.01640 77.27 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 160 4.741 5.993 0.01645 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1A295 170 170 0.2631 1.5480 1A111 180 180 7.512 0.01651 50.21 50.22 148.00 990.2 1138.2 0.01657 40.94 40.96 158.04 984.1 1142.1 0.2787 1.5148 1.7934 190
; 190 9.340 0.01664 33.62 33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200 l 1 200 11.526 210 14.123 0.01671 27A0 27.82 178.15 971.6 1149.7 0.3091 1.4509' 1.7600 210 0.01672 26.78 26.80 180.17 9703 1150.5 0.3121 1.4447 1.7568 212
. 212 14.696 ' 0.01678 23.13 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 220 17.186 03388 1.3902 1.7290 230 230 20.779 0.01685 19.364 19.381 198.33 958.7 1157.1 16304 16.321 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 240 24.968 0.01693 0.01701 13202 13.819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29A25 11.745 11.762 228.76 938.6 1167.4 0.3819 1.3043 1.6862 260 260 35.427 0.01709 41.856 0.01718 10.042 10.060 238.95 931.7 1170.6 03960 1.2769 1.6729 270 270 0.4098 1.2501 1.6599 280 49.200 0.01726 8.627 8.644 249.17 924.6 1173.8 280 0.4236 1.2238 1.6473 290 0.01736 7.443 7.460 259.4 917.4 1176.8 290 57.550 1.6351 300 i 0.01745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 300 67.005 5.609 5.626 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 310 77.67 0.01755 4.896 4.914 290.4 894.8 1185.2 0.4640 1.1477 1.6116 320 320 89.64 0.01766 3.770 3.788 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 340 117.99 0.01787 2.939 2.957 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 360 153.01 0.01811 2335 353.6 844.5 1198.0 0.5416 1.0057 1.5473 380 340 195.73 0.01836 2.317 1.8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 400 247.26 0.01864 1.8444 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 420 303.78 0.01894 14808 1.4997 1.2169 419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 440 381.54 0.01926 1.1976 0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 460 466.9 0.0196 0.9746 0.8172 464.5 739.6 1204.1 0.6648 0.7871 1.4516 480 480 566.2 0.0200 0.7972 0.6749 487.9 7143 1202.2 0.6890 0.7443 1.4333 500 500 6%.9 0.0204 0.6545 0.55 % 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520 s23 812.5 0.0209 0.5386 0.4437 0.4651 536.8 657.5 1194.3 0.7378 0.6577 13954 540 540 962.8 0.0215 560 0.3651 03871 562.4 625.3 1187.7 0.7625 0.6132 1.3757 l MO 1133.4 0.0221 580 0.2994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 1.3550 i 580 1326.2 0.0228 617.1 550.6 1167.7 0.8134 0.5196 1.3330 Goo 600 1543.2 0C236 0.2438 0.2675 646.9 506.3 1153.2 0.8403 0.46S9 1.3092 620 620 1785.9 0.0247 0.1962 0.2208 679.1 454.6 1133.7 0.8666 0.4134 1.2821 640 i 640 2059 9 0.0260 0.1513 0.1802
" 0.1443 714.9 392.1 1107.0 0.8995 U.3502 1.2498 660 l - 660 2365.7 0 0277 0.1166 0.1112 758.5 310.1 1068.5 0.9365 0.2720 1.2086 680 i G30 p708.6 0.0304 0.0808 0.0752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 j l 700 30943 0 0366 0.0386 ,
0.0508 906.0 0 906.0 1.0612 0 1.0612 705.5
- 705.5 3208 2 0.0508 0 l
l l TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE) ) l - A.3 l I
Enthelpy. Ste/lb tateepy. Steht a F tase8y. Blu/IB Unlume.D/lb Temp Color Esop Steam C:ler Evep Sesem tasse Gesem F***- P'ess. teser toep Steam F 9 ele 9 88*
't 'e 's "8 he A s e, e, g og .,
0.01602 3302A 3302.4 0.00 1975.5 1075.5 0 2.1872 2.1872 9 3021.3 E8886 0.0886 32.018 0.10 35.023 0A1602 2945.5 2945.5 3.03 10733 1076.8 0 006) 2.1705 2.1766 323 1022.3 &te 41.453 0.01602 2004.7 2004.7 13.50 1067.9 1081.4 0 0271 2.1140 2.1411 13.50 1025.7 0.15 0.15 0 0422 2.0778 2.1160 2122 1028.3 e.20 H.160 0.01603 1526.3 1526 3 21.22 1063.5 1084.7 a.20 64 444 0 01604 1039.7 1039.7 32.54 1057.1 1089 7 0 0641 2.0168 2.0809 37.54 1032.0 930 0.30 0.0799 1.9762 2.0 % 2 40.92 1034.7
&40 72369 0.01606 792.0 792.1 40.92 1052.4 10933 c.40 79.586 0 01607 641.5 641.5 47.62 1048.6 1096.3 0.0925 1.9446 2.0370 4742 1096.9 E5 0.5 0.1028 1.9186 22215 53.24 1038.7 S.6 85.218 0.01609 540.0 640.1 53.25 1045.5 1098.7 0.6 90 09 0.01610 466.93 466 94 58 10 1042 7 1100 8 0.3 1A966 2.0083 58.10 1040.3 0.7 9.7 0.1117 13775 1.9970 6239 1041.7 33 02 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 S.9 98.24 0.01612 368.41 368.43 66.24 1038.1 1104.3 0.1264 1A606 1.9870 0624 1042.9 E9 1.0 101.74 0.01614 333.59 333.60 69.73 1036.1 1105A 0.1326 13455 1.9781 99.73 1044.1 1A 2.0 126.07 0 41623 173.74 173.76 94A3 1022.1 1116.2 0.1750 1.7450 1.9200 94A3 1051A 2A 3.0 141.47 0.01630 118.71 118.73 109.42 1013.2 1122.6 0.2009 1.6854 1.8864 109.41 1056.7 3.0 0.01636 90 63 90 64 120.92 1006.4 1127J 0.2199 14428 1A626 120A0 1060.2 4.0 4.0 152.96 162.24 OA1641 73.515 73.53 130.20 1000.9 1131.1 0.2349 1.6094 1A443 130.18 1063.1 SA 5.0 S.O 170 05 0.01645 61.967 61.98 138.03 996.2 1134.2 0.2474 1.5820 1A294 1MA1 1065.4' SA 7A 176.84 0.01649 53 634 53.65 144.83 992.1 1136 9 0.2581 1.5587 13168 14421 1067.4 7A 3.0 142 86 0.01653 47.328 47.35 150.87 988.5 1139.3 0 2676 1.5384 1A060 15034 1069.2 S.0 9.0 188.27 0.01656 42.385 42.40 1%.30 985.1 1141.4 0.2760 1.5204 1.7964 15628 1070A 94 10 193.21 0.01659 38.404 38.42 161.26 982.1 1143.3 0.2836 1.5043 1.7879 161.23 10723 le 14.696 212.00 0.01672 26.782 26.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 180.12 1077.6 14.896 15 213.03 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1077.9 15 30 ??7.96 0.01683 20.070 20.087 196.27 960.1 11 %.3 03358 1.3962 1.7320 196.21 1082.0 to 30 250.34 0.01701 13.7266 13.744 218.9 945.2 1164.1 0.3682 1.3313 1A995 218 3 1087.9 30 40 267.25 0 01715 10.4794 10.497 236.1 933.6 1169A 03921 1.2844 1.6765 235.0 1092.1 40 to 281.02 0.01727 8.4967 S.514 250.2 923.9 117?.1 0.4112 1.2474 JAMS 250.1 10953 SO 80 292.71 0.01738 7.1 % 2 7.174 262.2 915.4 1177.5 0.4273 12167 1A440 262A 1088.0 80 70 302.93 0.01748 6.1875 6 205 272.7 907A 1180.6 0 4411 1.1905 1A316 272.9 1100.2 70 30 312.04 0.01757 5 4536 5 471 232.1 900.9 117.3.1 0.4534 1.1675 14208 241.9 1102.1 80 90 320.28 0.01766 4.8777 4.8 % 290.7 894.6 1185.3 0.4643 1.1470 1.0113 290.4 1103.7 90 100 327.82 0.01774 4.4133 4.431 298.5 088.6 1187.2 0.4743 1.12s4 1.6027 298.2 1105.2 100 320 341.27 0.01789 3 7097 3.728 312.6 S77A 11934 0.4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 0 01803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 324.5 1109.6 140 160 363 55 0.01815 2.8155 2.834 336.1 859.0 1195.1 0.5205 1.0435 1.%41 335.5 1111.2 150 380 373 08 0.01827 2.5129 2.531 345.2 850.7 1196.9 05328 1.0215 1.5543 345.6 1112.5 180 200 351.80 0 01839 2.2689 2.287 3*. 5.5 842.8 1198.3 0.5438 1.0016 1.5454 3542 1113.7 300 250 400 97 0.01865 1.8245 1.8432 376.1 825 0 1201.1 0.% 79 0 9585 1.5264 3753 11153 250 300 417 3h 0 01859 1.523B 1.5427 394.0 808.9 1202.9 0.5882 0.9223 1.5105 392.9 1117.2 300 350 421.73 0 01913 1.3064 1.3255 409.8 7942 1204 0 0 60M 08909 1.4968 408 6 1118.1 350 400 444 60 0.0193 1.14162 1.1610 424.2 7804 1204.6 0 6217 0 8630 1.4847 422.7 111E 7 400 8 450 456.28 0 0195 1.01224 1.0318 437.3 767.5 1204.8 0.6360 0.8378 1.4738 435.7 1118.9 450 500 467.01 0 0193 0 90787 0 9276 449.5 755.1 1204.7 0.6490 0.814S 1.4639 447.7 11183 500 550 476 94 0 0199 0 82183 0.8418 460.9 743.3 1204 3 0.6611 0.7936 1.4547 456.9 1118 6 550 400 48510 0 0201 0.74962 0.7698 471.7 732.0 1203 7 0.6723 0.7738 1.4461 469.5 111E.2 500 700 .503 08 0 0205 063505 06556 491.6 710.2 1201.8 0692R 07377 1.4304 488.9 1116.9 700 800 51821 0 0209 0.54809 0.5690 509.8 689 6 1199 4 0 7!11 0.7051 1.4163 506 7 1115.2 000 900 132 93 0 0212 0 47968 05009 526 7 669 7 11 % 4 07279 0.6753 1.4032 5232 1113.0 900 1000 544. 2 0.0216 0 42435 0 4460 542.6 f 50 4 1192.9 0 7434 0 6476 1.3910 530 6 1110.4 1000 1100 51E 24 0.0720 0.37863 04006 557.5 631.5 1169 1 0 757S 06216 1.3794 553i 1107.5 1100 ,
3200 M7.19 0 0223 034013 0.362h 571.9 613 0 1184 8 0 7714 0.5 % 9 1.3683 566 9 1104.3 1200 0 30722 0.3299 585.6 544.6 1180 2 0.7843 0.5733 1.3577 580.1 1100 9 1300 - 1300 577 42 00227 1400 557 07 0 0731 0 778/1 0 3018 5988 576 5 1175 3 0.7966 05507 1.3474 592.9 1037.1 1400 1500 5%20 0 0235 02h372 0.2772 611.7 558 4 1170 1 0.8035 0 '.283 1.3373 6052 1093.1 1500 2000 635 80 0.02 *a 7 01676f., 0.1883 672.1 466.2 113B.3 0 8625 0 4256 1.7881 662 6 IOGS 6 2000 2500 66d 11 0 0244 010209 01307 731 7 361.6 1093 3 0 9139 03206 1.2345 718.5 1032.9 250G 3000 695 33 0 0343 0 050/3 0 0850 8018 218 4 1070 3 0 9723 0.1891 1.1619 7823 973.1 3000 3298.2 0 0$08 0 0 050d 906 0 0 906 0 1 0612 O 1.0612 875.9 875.9 37082 70147 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE) A.4
I
! l i
Tempeestueo. F Abe preen. 300 400 000 000 700 000 900 1000 1100 2200 3200 1400 1900 l ) 100 200 ( v 0.0161 202 5 452.3 &11.9 871.5 631.1 400 7
! t 6 SS 00 1150 2 1195.7 1241.8 1208 6 1836.1 late 5 (101.74) a 0.1295 2.0609 2.1152 2.1722 2 2237 2270s tales I e 0.0161 73 I4 90.24 102.24 314.23 126 15 ISS 08 150.01 161.M 173 86 185 78 197.70 200 62 221.53 233 45
& 6 GS 01 1148.6 1144 8 1241.3 1288 2 1835 9 1964 3 1433 6 1483 7 15M.7 1586 7 1439.6 1893.3 1748.0 1301.5 (162.24) s 0.1295 1.8716 1.9369 13943 2040 2.0932 2.1369 2.1776 2 2159 2 2521 2.24E I.31M 2.3509 2.3811 2A101 l
I e 0 0161 38 84 44 93 51.03 57.04 63.03 69 00 74 98 80 M 86 91 92 87 98A4 104 to 110.76 11672 30 6 68 02 1146 6 11937 I?40 6 1287A 3335.5 1384 0 1433 4 14835 1534 6 1546 6 16395 1693.3 1747.9 1803 4 (197.21) s 0.1295 1.7928 1A593 1.9173 1.9692 2.0166 2.0603 2.1011 2.1394 2.1757 2.2101 2.2430 2.2744 2.3046 2.333 e 00161 0.0166 29 399 33.963 37.985 41.986 45378 49 964 53 946 57.926 61.905 65.882 59458 73A33 77307 is & 68.04 16l109 !!92 5 1239 9 1287.3 1335.2 13833 1433.2 1483 4 1534.5 1546 5 1639 4 1883.2 1747A 1803 4
, (21343) s 0.1295 0.2940 1.8134 1A720 1.9242 1.9717 2.0155 2.0563 2A946 2.1309 2.1653 2.1982 22297 2.2599 2JW90 a
! e 0 0161 0.0ln 22.356 25A28 28457 31.466 34.465 37.458 40 447 43 435 46 420 49 405 52.30B 55 370 98 352 i 30 6 68.05 16811 1191.4 1239.2 1286.9 1334.9 1383 5 1432.9 1483.2 1534.3 1546.3 1639.3 1803.1 17473 13133 (227.96) s 0.1295 0.2940 1.7005 1A397 12921 13397 1.9836 2.0244 2.0628 2A991 2.1336 2.1665 2.1979 22282 2J572 1 ) e 0.0161 0 0166 11 035 12.624 14.165 15 685 17.195 18 699 20 199 21.697 23.194 24 689 26.183 27A76 29.168l 40 6 48.10 168 15 1186 6 1236.4 1785.0 1333 6 1382.5 1432.1 1482.5 1533.7 1585.8 16388 1992.7 1747.5 1803 0j I (267.25) s 0.1295 0.2940 1.0992 1.760s 1A143 13624 1.9065 1.9476 1.9860 2.0224 2.0569 2.0899 2.1224 2.1516 2.1807 i e 0.0161 0.0156 7.257 8 354 9.400 10 425 11.438 12 446 13A50 14.452 15.452 16A50 17A44 18.445 19A41 to A 48.15 168 20 1181 6 1233.5 1283.2 1332.3 1381.5 14313 1481.8 1533.2 1505.3 1638.4 1682.4 1747.1 1802A (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1A148 1A612 1.9024 1.9410 1.9774 2.0120 2.0450 2A765 2.10E8 2.1300 e 0 4161 0.0166 0.0175' 6.218 7A18 7.794 S.560 9.319 10.075 10 829 11 581 12331 13AB1 13 229 14.577 '
! 30 6 64.21 168.24 269.74 1230.5 1281.3 1330.9 1300.5 1430.5 1481.1 1532 6 1554.9 1638.0 1692 4 1744A 1802.5 (312.04) s 0.1295 0.2939 0.4371 1.6790 1.7349 1.7542 1A289 1A702 1.9089 13454 1.9000 2.0131 EA446 2.0750 2.1041
( i j e 0.0161 0.0166 0 0175 4 935 5.588 6.216 6233 7.443 8050 8.655 9.258 9260 10A60 11A50 11A59 100 4 68.26 168.29 269 77 1227.4 1279.3 1329.6 1379.5 1429.7 1480 4 1532.0 1984.4 1637.6 1991.6 17M.5 1802.2 l 14516 1.7068 1.7586 13036 1A451 13839 1.9205 13552 13883 2A199 2.0502 2A794 (327A2) s 0.1295 0.2939 0.4371 i. e 0 0161 0.01 % 0 0175 4 0786 4A341 5.1637 5.6831 6.1923 6.7006 7.2060 7.7096 S.2119 S.7130 9.2134 9.7130 120 A 44.31 168 33 269 81 1224.1 1277.4 1328.1 1378 4 1428.8 1479A 1531.4 1583.9 1637.1 19D13 17M.2 1802A (341.27) s 0.1295 0.2939 0 4371 1.6286 1A872 1.7376 1.7829 12246 1A635 1.9001 1.9349 13600 13996 2.0300 2At92 l e 0.0161 0 0166 0.0175 3 4651 3 9526 4.4119 4 2585 5.2995 5.7364 6.1709 6.4036 7A349 7A652 72946 83233 140 t 48.37 168 38 269 85 1220 8 1275.3 1326.8 1377.4 1428 0 1479.1 1530 8 1583 4 1636.7 1990.9 1745.9 1301.7 l l (353 04) s 0.1295 0 2539 0 4370 1.6085 1.6686 1.71 % 1.7652 13071 13461 12828 1.9176 1.9508 1.9525 2Al29 2A421 f e 0.0161 0 0166 0 0175 3 0060 3.4413 3 8480 4.2420 4 6295 5.0132 5.3945 5.7741 6.1522 4 5293 "4.9055 7JS1
- 160 A 68 42 168 82 269.89 1217.4 1273 3 1325 4 1376 4 1427.2 1478 4 1530.3 15823 1636.3 1990.5 1745.6 1801.4
} (363 55) s 0.1294 0.2938 0 4370 1.5906 1.6522 1.7039 1.7499 1.7919 1A310 13678 13027 1.9359 1A576 1.9980 2A273 e 0 0161 0 0166 0 0174 26474 3 0433 3.4093 3.7621 4.1064 4.4505 4.7907 5.1289 5.4657 5A014 6.1363 6.4704 150 6 68 47 16847 269 9/ 1213 8 1271.2 1324.0 1375.3 1426.3 1477.7 1529 7 1582.4 1635.9 1990.2 17853 1801.2
- (173.C81 s C.1294 0.2938 04370 1.5743 14376 1.6900 1 7362 1.7784 1A176 1.8545 12894 13227 1 9545 1.9849 2A142
- e 0.0161 0 0165 0 0174 2 3598 2.7247 3.0583 3.3783 3 6915 4.0008 4.3077 4.6128 4.9165 52191 S.5209 5 221 200 > 6832 168 51 269 96 12101 1269.0 13221 1374.3 1825.5 1477.0 15291 1581 3 1635.4 16e9 8 1745D 1800.9 s
! (351 A0) a 0 1294 0 29311 0 43G9 1.5593 1.6242 1.6776 1.7239 1.7663 1A057 1.8426 1A776 1.9109 13427 13732 2A025 e OC161 0 0165 0 0174 0 0186 2.1504 24662 2.6872 2 9410 3 1909 3.4382 3 6837 3.9278 4.1709 4.4131 4 6546 68 66 168 63 270 05 3/5.10 1263.5 1319.0 1371.6 1423 4 1875 3 1527.6 1580.6 1634 4 1688.9 17442 1800.2 ! 250 6 (400 97) e C 1294 0.2937 0 4366 0.5567 1.5951 1.6502 1.6976 1.7405 1.7601 1.8173 1.8524 1.8858 1.9177 1.9482 1.9776 e 0 0161 0 01E5 0 3174 0 0186 1.7665 2.0044 2.2263 2.4407 2.6509 2 6585 3 0643 3.2688 3 4721 3.6746 3A764 l 300 4 68 79 IM 74 27u 14 375.15 1237 7 1315 2 1368 9 1421.3 1473 E 1526.2 1579.4 1633 3 1688 0 1743 4 1799.6 (417.35) s 0.1294 02937 04M7 C5%5 1.5703 1A274 1.6758 1.7192 1.7591 1.7964 12317 1A652 13972 1.9278 1 3572 e 0 0161 0 C165 0 0174 0 0186 I.4913 1.7028 1 2970 2.0332 21652 2 4445 2A219 2.7980 23730 3.1471 332C5 68 92 10385 270 74 375 21 1251.5 1311.4 1366 2 1419 2 14718 1524 7 1578.2 1632.3 1687.1 1742.6 1798 9 2
l 350 6 (431.73) e 01293 0 2936 0 43G7 0.5 % 4 1.5483 1.6077 14571 1.7009 1.7411 1.7787 1A141 13477 13795 1.9605 1.9400 e 0 0161 0 0166 0 0174 0 0162 12841 1.4763 1.6499 1.8151 1.9759 2.1339 2.2901 2.4450 2.5987 2.7515 2.9037 400 a 69 05 168 97 270 33 375 27 12451 1307 4 1363 4 1417.0 14701 1523 3 1576.9 1631.2 1656.2 1741.9 1795.2 l 1.5782 1.5901, 1 6406 1 6850 1.7255 1.7632 1.7988 13325 13647 1.8955 1.9250 (444.60) s 01293 0 2935 0 4365 0 56G3 e 0 0161 0 0166 0 0174 0 0186 0 9919 1.1584 1.3017 1.4397 1.5708 1 6932 1 A256 1.9507 2.0746 2.1977 2.3200 500 h 69 32 169 19 270 51 375 38 1231.2 1299.1 1357.7 1412 7 1866 6 1520 3 1574 4 16291 1684 4 1740 3 1796.9 (457.01) s 0 1292 02934 04364 0 5060 1 4971 1.5595 1.6'23 1 65/8 16990 1.7371 1.7730 1.8069 13393 1.8702 13998 f TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED
- WATER (TEMPERATURE AND PRESSURE)
A.5
Abe psees. Tempetetwee3F SD/s418-gese.esap6 300 300 300 400 SCO GOD 700 800 000 3000 1100 8800 3300 3400 3300
]
l e 0.0161 0 01 M 00174 0.0186 0 7944 0 94 % 10726 1.1892 1.3005 14093 1.5160 14711 3.7252 1.8284 3.0308 get 6 09.58 149 42 270 70 376 49 1215 9 1790 3 3351 A 1408 3 1430 351FA 1571.9 1627.0 1682 6 17383 179bA 4086JU) s 0.1292 02933 Sete OM57 8.4500 1.5329 1.5844 1.63bt 18769 3.71H 1.7517 l.7859 3A184 14494 13732 e 0.0161 00lu 00174 00196 00204 0.7928 0 9072 1.0102 1.1078 1.2023 1.2948 IJB58 1A757 1.5647 14530 yte t 69.84 169 65 270 49 375 61 487 93 1781 0 1345 6 1403 7 lebt 4 1514 4 1%94 1624.5 16bo 7 1737.2 179e.3 i
! 003.C8) s 01291 0.2932 04360 0 % 55 0 6889 1.5090 1.% 73 1 6154 14580 3.6970 17335 3.7679 1 80 % 18318 13617 e 0.0161 0 0lu 0 0174 0 0186 0 0704 0 6774 0 7873 0.8759 0 9631 1.0470 1.1289 12093 IJ885 1 M69 IA446 .
Soo 6 70.11 169 88 271.07 37573 48738 1271.1 1339.2 1399.1 1455 8 1511 4 IM69 IU21 1678 9 145.0 1792.9 1 018.2.) . 0.1290 0 2930 0 4358 0.% 52 0.6885 1.4869 1.5444 1.5940 1.6413 1 6807 1.7175 17522 3.7851 18164 13464 l l e 0.0161 0.01 % 0 0174 0 0186 0 0234 0 5869 0 6858 0.7713 0 8504 0.9262 0 9998 1.0720 1.1430 1.2131 1.2825 I l 308 6 70.37 170 10 213.26 37534 487A3 1260 6 13323 1394 4 1452.2 1508 5 1564 4 IM06 16U.1 17M.1 1791 6 i 5 31.95) s 0 1290 0.2929 0.4357 OM49 0 6881 1A659 1.5311 1.5822 3.6263 I M 62 13033 1.7382 IJ713 1.8028 18329 l d v 0.0161 0.01M 0.0174 00186 0 0204 0.5137 06080 06575 0.7603 0 8295 039H 0.9U2 1.07H 1.0901 1.1529 3800 6 70.63 170 33 271A4 375.96 487.79 12491 1325.9 1389 4 1444.5 1504.4 1 % I.9 1618.4 1675.3 1732.5 17903 (544.58) s 0.1289 0.2928 0.4355 0.5647 04476 1A457 1.5149 1.5677 1.6126 1.6530 1A905 1.7256 3.7589 1.7905 1A207
; e 0 0161 001M 0.0174 0.0185 0.0203 0 4531 0 5440 0 6188 06465 0 7505 03123 0 8723 0.9313 0 9894 IA460 '
l 1100 4 70 90 170.% 27143 376.08 48735 1237.3 1318 8 13841 14441 1502 4 1559.4 1616 3 1673.5 1731.0 1789.0 ; 4 OW.23) s 0.1269 0.2927 0.4353 0.5644 04472 1.4259 1.4996 1.5542 1.4000 1.6410 14787 IJ141 1J475 13793 1 3037 i i l i e 0 0161 0.0166 0.0174 0.0185 0 0203 0 4016 0 4905 0.5615 0 6250 0 6845 0 7418 0.7974 0 8519 0.9055 0.9584 [ ! 1300 6 71.16 170.78 271A2 376.20 487.72 1224.2 1311.5 13793 1440.9 1449 4 15M 9 1614.2 16714 17294 1787A ' ) 0 67.19) s 0.1288 0.2926 0.4351 0.5642 04868 1A061 1A851 1.5415 3.5883 1.6298 1 M 79 1.7035 1.7371 13691 1.7986 i e 0.01(I 0 0166 0 0174 0 0185 0.0203 0.3176 0 4059 0.4712 0 5282 0 5809 0.6311 067M 01272 0.U37 OA195 I 4 1400 6 71A8 171 24 272.19 376 44 487.65 1194.1 1296.1 1869.3 1433 2 1493 2 1551A 1609.9 1468 0 1726.3 1785.0 j 087.07)s 0.1287 0.2923 0.4348 0.5636 OM59 IJ652 1.4575 1.5182 1M70 1.6096 14484 14885 1.7185 1.7508 IJB15 , ! e 0.0161 0.0166 0.0173 0.0185 0.0202 0.0236 0.3415 0.4032 0 4555 0.5031 0.5482 0 5915 0.6336 0.6748 SJ153 ! i 1800 6 72.21 171.69 272.57 376 49 487.60 616.77 1279.4 1358.5 1425.2 1486.9 1546 6 1605.6 1464.3 1723.2 1782A
- (6G4.87)s 0.1286 0.2921 0.4 M 4 0. % 31 0.6851 0A129 1.4312 1.4965 1.5478 1.5916 1.6312 14678 8.7022 1.7344 1.7657 ;
e 0.0160 0.0165 0 0173 0.0185 0.0202 0 0235 0,2906 03500 03988 04426 0.4836 0.5229 0.5609 0.5940 06?f3 1800 a 72.73 172.15 272.95 376.93 487.% 615.58 1261.1 IM7.2 1417.1 1480.6 1541.1 1401.2 1660.7 1720.1 17791l '! % 2 1/12) s 0.1284 0.2918 0.4341 0 M26 0.6E3 OA109 1A054 1A768 1.5302 1.5753 1.6156 1.H28 1.6876 1.7204 1J516 ' i. { e 0 0160 0.0165 0.0173 0.0184 0.0201 0.0233 0.2488 0.3072 0.35M 0.3942 0.4320 0.4680 0.5027 0.5365 0.5695 4 3000 6 73.26 172.60 273.32 377.19 487.53 614 48 1240.9 1353.4 1408 7 1447.1 1536.2 1996.9 1657.0 1717.0 1777.1 l (635.00) s 0.1263 0.2916 0.4337 0 % 21 0 6434 0A091 1.3794 1.4578 1.5138 1.5603 1.6014 1.6391 1.6743 1J075 1J389 l e 0 0160 0.0165 0.0173 0 0184 0.0200 0.0230 0.1681 0.2293 0.2712 0.3068 0.3390 0 3692 0.3980 E4259 0 4529 j 3500 6 74.57 173 74 274.27 377 82 487.50 612.08 1176.7 1303.4 1386.7 1457.5 1522.9 1585.9 1647A 1709.2 1770.4
- . (668.11)s 0.1280 0.2910 0 4329 0.5609 0.6815 0 8048 1.3076 1A129 1.47M 1.5269 1.5703 1AOD4 1.6456' 1.6796 1.7136 e 0 0160 0 0165 0 0372 0 0183 0.0200 0.0228 0.0982 0 1759 0.2161 0.2484 0.2770 0 3033 0.3282 0.3522 0J753 '
t 3000 h 75 83 17t. 88 275.22 378 47 487.52 610.08 10t:0 5 1267.0 13632 1440.2 1503.4 1574A 1635 5 1701.4 1M1A j (695.33) s 0.1277 0.29c4 0.4320 0.5597 0.6796 0 8009 1.1966 1.3692 1.4429 1A976 1.5434 1.5641 34214 1.0161 14888 !! e 0.0160 0 0165 0.0172 0.0183 0.0199 0 0227 0.0335 0.1588 0 1987 0.2301 0.2576 02827 OJ065 0.3291 0.3510 l 3200 & 76.4 175.3 275 6 378.7 487.5 609.4 800.8 1250 9 1353.4 1433.1 1503.8 1570.3 16343 1698.3 1761.2 1 (705.C9) s 0 1276 0.2902 0.4317 0.5592 04788 03994 0.9708 1.3515 1.4300 1A866 1.5335 1.5749 14126 1.6477 1 A806 , e 0 0160 0 0164 0.0172 0.0183 0 0199 0.0225 0.0307 0.1364 0.1764 0.2066 0 2326 0.2563 0.2784 0 2995 OJ19P. i 3500 6 77.2 176 0 276.2 379 1 487.6 608.4 779 4 1224 6 1338.2 1422.2 1495.5 IM3J 1629.2 1693 6 17b7.2 e 0.1274 0.2899 0 4312 0 5585 0.6777 03973 0.9508 1.3242 1A112 1.4709 1.5194 1.M18 1.6002 1.6358 1.6691 .' e 0 0159 0.0164 0.0172 0.0182 0.0198 0.0223 0 0287 0 1052 0.1463 0.1752 01994 0.2210 0.2411 0.2601 02783 j; 4000 4 78.5 177J 277.1 3 79.8 4873 606.5 763.0 1174.3 1311.6 1403 G 1481.3 1552.2 1619.8 1685 7 17506 ll s 3.1271 0.2P93 0.4304 0.5573 0.6760 0 7940 0.9M3 1.2754 1.3807 1A461 1.497G 1.5417 1.5812 1.6177 14516 e 0 0159 0 0164 0 0171 0 0181 0.0196 0 0219 0 0268 0.0591 0.1038 0.1312 0 1529 0.1718 01S*0 0 2050 0J203 l! 5000 a 81 1 179 5 2791 381.2 488.1 604 6 7460 1042.9 1252.9 1304 6 1852.1 1529.1 16039 1670 0 1737.4 j e 0.1265 0.2861 0.4287 0.5550 0 6726 0J880 0.9153 1.1593 IJ207 IA001 IA582 1.5061 1.5481 1.5863 IA216 4 4 e 0 0159 0.0163 0 0170 0.0160 0 0195 0.0216 0.0256 0.0397 0.0757 0.1020 0.1221 0.1391 0.1544 0.!684 0.1817 jt ' 4000 h 83.7 181.7 281.0 362 1 AP8 6 602 9 7361 945.1 1188.8 1323 6 1422.3 1505 9 1M20 1654.2 1724.2 j s 0 1258 0 2670 0 4271 0 5528 0 M93 01826 ,0 9026 1.0176 1.2615 13574 1.4229 1.4745 1.5194 1.5593 1996.2 ( e 0.0158 0.0163 0 0170 0 0180 0 0193 0.0713 0 0248 0.03M 0 0573 0 031 A 0 1004 0.1160 0.1296 0 1424 0.1542 l 7000 & 86.2 104 4 283 0 384.2 489 3 601 3 729 3 901 A 1124.9 32813 1392 2 1482.6 1%31 16396 1711.1 l e 01252 0 2859 0 4256 0 5507 0 6G63 01/77 0 8926 1.0350 12055 1.31)I l.3904 1.44u6 14938 1.53'5 1.5735 l TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED) A.6 i
. .- - - . -.__ ~ - . - - _ - _
l N(fd , 1
/ 6 skem 1 '
I
/ cweve
/ / y Pump A / -
/ lp G' r !
l I 6 / \
,I
, /
/ \
Pun,) B l
/
, . + '
/ '
i , l 7 .
/ 3 l
/
/
- l
. / 5 '
/
, .. /
/.& % Pump A
///
s/F
. l y (gpm) , l g
e
- Combined Head / Tressure Curve for Two Pumps .
l e, m3 - ..) l
\ .o2.
s A , e
,
- g,ey
. i l * - '
itA EVENT prESSUCE SETPCl",7 INDCEASE POWER. 1005
/
'. y ' -
l l G I I 5 h. I ur' G
=~_. sr g
a- 6 g ll I [ ll ll d' O 20 4'O EO il0 100 120 i 8 0 12 1' S CORE FLOW TOTAL STEAM FLOW ( X 1 MILLION lbs/hr) ~(X 1 MILLION lbsthr) I a t
------"~~~~~
e ....--- 6 ,, g4 - -
~"~ ~
t j ,, ,, ,
~
950 970 990 1010 1030 1050 0 C 0 12 18 P.E ACTOR PRESSURE TURBINE STE AM FLOW i . . (PSIG) ( X 1 MILLION Ibs/hr)
--- - ..~~~~A ; . w: . - . , . . . . . -
183 gygCT PRESSMAR arf 70lMTIMcREAsa PODER 1004 ),[... , 5 4 f - 1
/
\
n j g _5, 21
--...-~ -
I 20 1 h e-- . _ f E-i s = 18 '
, - "a--- ....,
" " 18 19 "
[ v- i,ll l 0 800 SOO 900 1200 1500 0 10 20 30 40 30 e6' [ (-, RE ACTOR PRES 8URE RE ACTOR VESSEL LEVEL
-l*
O (P8IG) (IN C H E S) 'I 1 6 ' i_ Q 3 l 2 2 I h a u .. . -
--....,'~~. -..,,,, ,'
*)
_,,....-~~~....
) 27
-i
) ;
pw--- -
=
A tl 4 y 23 ~' ' *- p- 28
.> f j e [4 . -
.. - - d F r - --,
g 22 26 % ' t [. i
' 34
>{. .
d d 11 O 26 SO ys 100 125 0 4 3 'I t 16 , APRM TOTAL FW FLOW (% POWER) ( X 1 MILLION Ibs/hr)
. . . - - . . e- . ~~ ,
m
1A tytNT MEIV MOEUEE Powen 1005
\
I ( w
' *~ < n '
~1 T)
J' o 20 40 to so too tao o 4 s la is - I CORE FLOW TdTAL STEAM FLOW s o ,
- -J In to'ths/he) (a to m e ethen D
r i I O7 %
, 8 g J -
- d
.p m
\. ,
950 970 990 1010 1040 1050 o 4 3 13 14 REACTOR PRESSURE TURetNE STEAM FLOW fpstel (a 10s m.fe,y
, =
,, . g.., , .. - so **I ^ ~ .- * * *__* ~ - ~..
_ Mm M
15 evass? Magy en ameame __ pewsq 1805
. t 5 . -. i
- I I
l I l i I i i {
/
..............-- m g ===mmun..........
's.. .,
3. 14 t 18 ,- e g
\ gg to
, i i D o soo soo soo isoo isoo o io ao so ao so J' ao f- [ REACTOR PRESSURE REACTOR VESSEL LEVEL l f (Petel (seeCMas)
't 5 o
.J P
,1 if lt l. li i !? lf l5 19
, d
,, is --
", , . qp .
mu = t h 13
- n . - . m s . . . ..... . . . , , g
- , u g , *
) ' gg
\ ..
o as so rs too its o 4 8 ta is
- I* APRed TOTAL FW FLOW tt Powsal fa 1o sgn ,,,,,
r em g = w. w -M'- _ ,
Page 42 of 44 08/13 F PECCENT QATED THERMAL FOWER, Lesten Plan 8 e s W W 8 $ 5 3 8 8 8 s 3 I I I ll 1i I i I i i i l I I
. I :: .
s - l - l l
.l 1 >
g l l I l I 1 l 8 \ l.! o - 5. 1 0 ~
",'.Ql$-M. .
m
+sg u-n - .
5 m .[ - o- ". z g o , -
> e n
0 m 3 -- Sk'. i.' .
,i e-A ,. _ s '. - O
~~ g y - l.+
a i- . . o - i-t) , r .. 1.
. g..
~
E , . W
.# 9"'
8 - H - In
\ - .
1 p y - l v . , . - 1r W - j -
, I i 1 1 I I I I I I I .
FIGURE 6' REACTOR POWER VERSUS CORE FLOW OPERATING MAP _ b 3% t . I t' -
. . . .:.: 4
_.,~,.. . _ _ __ , _ _
Pas 2 18 of 18 06/19/84 Lessen Plcn 45 o . W L DRYWELL STEAM DRYER WATER LEVEL f EE
.E C'
[Md NI DM N O O O. - - - - - - - -- - W dh, l
. s, a
ABOVE CORE
;[ PLATE dpA H
;; PRESSURE se
,, @ h '
N N / U l
- STANDBY LIQUID CONTROL
~
FIGURE l.2c CORE SPRAY SYSTEM PIPE BREAK DETECTION INSTRUMENTATION l l 4
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 34
--- iREss559sisiEs- REsi isissFEE As5 FEGi5 FE5s ANSWERS - BROWNS FERRY 1, 283 -85/07/15-GUENTHERrS ANSWER 1.01 (1.00) c REFERENCE BFNP REACTIVITY COEFFICIENTS LPrP.3 ANSWER 1.02 (1.00) -
- c. 1 b4 REFERENCE BFNP PUMP CHARACTERISTICSrPUMP HEADrPUMP LAWS LPrP.4 ANSWER 1.03 (1.00) a REFEREt:CE BFNP ATOMIC AND NUCLEAR PHYSICS LPrP. 20 ANSWER 1.04 (1.00) c l REFERENCE .
BFNP NUCLEAR REACTIONS LPrP. 7 ANSWER 1.05 (1.00) b REFERENCE BFNP NEUTRON SLOWING DOWN AND DIFFUSION LPrP.6-8
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 35 l
--- isiss557nAsiCE- sEAi fEAsiFEE As5 FE0i5 FE5E l ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHER,S , 1 ANSWER 1.06 (2.00)
- c. Due to the chans,e in two phase flow resistance.
- b. Due to the decay heat input.
- c. Due to the void collapse on the pressure increase.
- d. Due to the pressure increase.
REFERENCE BFNP TRANSIENT 4 18 ANSWER 1.07 (2.00)
- c. Due to the recire pump trip at 1120 psis.
- b. Due to the anticipatory MSIV closure scram.
- c. Due to MSRV opening causing a level spike.
- d. Due to the FWCS cutting back to follow steam flow.
REFERENCE BFNP TRANSIENTS #1 ANSWER 1.08 (1.00) d REFERENCE , BFNP MCD BWR LP,P.4 ANSWER 1.09 (1.00) a REFERENCE BFNP LHGR AND BASES LP,P.8-9
-. = - - -
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 36
~~~ isERR559sisiEs- sEAi isissFEE As5 FEUi5 FE5s ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHERrS ANSWER 1.10 (1.00) a REFERENCE BFNP THERMAL HYDRAULICS LPrP.6 ANSWER 1.11 (1.00) d REFERENCE BFNP PUMPS LPrP.5-6 ANSWER 1.12 (1.00) d REFERENCE RFNP STEAM TABLES LPrP.8 ANSWER 1.13 (1.00) b REFERENCE ;
BFNP REACTOR HEAT BALANCE LPrP.5 1 ANSWER 1.14 (2.00) l l
\
l a. The assembly power which would cause the onset of transition boilin3 { at some point in the assembly. !
- b. 2 REFERENCE BFNP TRANSITION BOILING & ATLAS TESTING LPrP.5-6 l GEXL CORRELATION & CRITICAL POWER LPrP.3 4
4 r - - -.- - , , _ - . - . - - - - - , . . - -
- m. --..- . .
-...e .- - .. .... . , . , -__- _ .- . _ - _ . . . - . , . _
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATIONr -
PAGE 37
--- iREER567 sari 5i- AEEi iEEWiFEE AR5 FEUi5 FE6s ANSWERS -- BROWNS FERRY in 2&3 -85/07/15-GUENTHERrS i
ANSWER 1.15 (1.00) b REFERENCE BFNP PHASES OF MATTER LP STEAM TABLES ANSWER 1.16 (1.00) d REFERENCE BFNP RANKINE CYCLE LPrP.517-8 ANSWER 1.17 (2.00)
- a. false
- b. false
- c. true
- d. false REFERENCE BFNP CONTROL ROD WORTH LPrP.5-8 ANSWER 1.18 (2.00)
- a. 3 r 5 r K
- b. 4 , I
- c. 1 r 6 r G (or H)
- d. 2 , 6 r E ,
1
. REFERENCE BFNP LP48,P.25-29 ANSWER 1.19 (1.00)
C l l l i l I 1 1
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 38
--- iAERR559sARIEE- AEsi iEAnsFEE Es5 FEDi5 FE5s ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHERrS REFERENCE BFNP REACTIVITY COEFFICIENTS LPrP.8,15 ANSWER 1.20 (2.00)
- a. p-7 = p-3 + the heiSht of cooler water in the sensing line.
Therefore p-7 > p-6 even though p-3 < p-2.
- b. p-6 remains unchanged but p-7 now senses p-5 which is ~7 psid
< p-3 due to the pressure drop across the steam dryers.
REFERENCE BFNP LP445,P.13-14 ANSWER 1.21 (2 50)
- s. Reactor power will stabilize at the POAH (range 7) (0.5)
- b. Assume: B=0.007 lambda =0.1/see alpha M=-1E -4 delta k/k/F C.253 Usin3: T = B - p / lambda x p E.253 p = B / lambda x T + 1 p = 0.007 / (0.1)(60) + 1 p = 0.007 / 7 = 0.001 delta k/k E0.53 (0.001dk/k) / (-1E -4dk/k/F) = 10 F temperature rise and a final temperature of 291 F E0.53 (1.5)
- c. Indicated reactor pressure = ~43.5 psis (0.5)
REFERENCE BFNP REACTIVITY COEFF. LP REACTOR POWER & REACTOR PERIOD LP ANSWER 1.22 (1.00) a REFERENCE BFNP MCD LP,P.6.6-6.10,6.32 i l
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 39
--- isERR559REsi5s- AEEi iEisiFEE An5 FEUi5 FE5s ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHER,S ANSWER 1.23 (1.00) c REFERENCE BFNP XENON & SAMARIUM LP, P.4,12
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 40 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHER,S ANSWER 2.01 (1.00)
, c REFERENCE BFNP LP947,P.7 ANSWER 2.02 (1.00) b REFERENCE BFNP LP439,P.18 ANSWER 2.03 (1.00) c
--REFERENCE BFNP LP938,P.5,7 ANSWER 2.04 (1.00) d REFERENCE BFNP LP930,P.7 ANSWER 2.05 (1.00) d REFERENCE BFNP LP451,P.9 ANSWER 2.06 (1.00)
D l
-. ---- - l
- 7. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 41 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHERrS REFERENCE BFNP LPt7,P.16 ANSWER 2.07 (1.00) d REFERENCE OFNP LP49,P.8 ANSWER 2.08 (1.00) b REFERENCE BFNP LP42,P.25 ANSWER 2.09 (2.50)
- c. 1.3
- b. 1,4
- c. 6r7
- d. 1,4
- e. 1,6 REFERENCE BFNP LP6 30rP.5r12 LP4 9,P.29 tPt 11,P.22-23 LPt 42rP.8 FOI-41rP.2 ANSWER 2.10 (1.00) a REFERENCE ~
BFNP LP440rP.10 d
. , ~ . _._m - - ___... - , . . . - , . .
- 7. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 42 ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHER,S ANSWER 2.11 (1.00) b REFERENCE BFNP LP940,P. 15i0I-71,p.7 ANSWER 2.12 (1.00)
C REFERENCE BFNP LP47,P. 28 AN3WER 2.13 (1.00) d REFERENCE BFNP LP645,P.7-8 ANSWER 2.14 (1.50)
- 1. Inboard MSIVs 20 SRVs
- 3. RBCCW to DW air coolers
- 4. Containment / torus vacuum breakers
- 5. LPCI testable check valves
- 6. CS testable check valves
- 7. DWE/FD to RW valves
- 8. Rx head vent drain valve
- 9. Rx seal cavity drain valve (60.25ea/1.5) ic.
N <.u.vm.c t ..i<- An .n r^ N$FEREkdE'"' BFNP LPtS4,P.14 tt-uA g 3 i
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 43 ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHERrS ANSWER 2.15 (1.50)
- c. 7
- b. 3
- c. 2
- d. 5
- e. 4
- f. 7 REFERENCE BFNP LPt44rP.39 ANSWER 2.16 (1.50)
- 1. LPCI initiation signal present
- 7. DW pressure >= 1.96 psis.
- 3. Rx water level > 2/3 core coverage (312+5/16')
REFERENCE BFNP LPt44rP.23 ANSWER 2.17 (2.00) Normal: 4KV Unit Bd 3A Alt.61: Bus Tie Bd Alt.62: DG 3EA Alt.93: Shutdown Bd A REFERENCE BFNP OI-57,P.108 ANSWER 2.18 (1.00) If all three CW pumps are tripped the discharge valve for the last CW pump tripped remains open E0.53 resulting in backflow of warm water from the tower warm water channel through the plant to the pumping station forebay (polluting the EECW supply) [0.53. REFERENCE BFNP LP450rP.9,12
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 44 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHERrS ANSWER 2.19 (1.00)
- 1. The running RSW pump will trip.
- 2. The RSW storage tank isolation valves (FCV-25-70/32) will auto close.
REFERENCE BFNP RHS LP ANSWER 2.20 (1.00)
- 1. MS relief panels
- 7. Zone relief panels
- 3. Exterior siding relief panels
- 4. HPCI flow limiter (200.5ea/1.0)
REFERENCE BFNP LPt16,P.39 ANSWER 2.21 (2.00)
- 1. Inlet inboard isolation valve (69-1) not fully open.
- 2. Inlet outboard isolation valve (69-2) not fully open.
30 Reactor return isolation valve (69-12) fully closed. 40 Pump flow <= 90 spm for 7 seconds.
- 5. Pump cooling water (RBCCW) outlet temp. high (140F) (400.5ea/2.0)
REFERENCE BFNP LP913rP.10 ANSWER 2.22 (1.00) e REFERENCE BFNP LPt43rP.6-7,12
Po PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 45 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHER,S ANSWER 2.23 (1.00) b REFERENCE BFNP LP442,P.25;BF-0I-73,P.4 ANSWER 2.24 (1.00) c REFERENCE BFNP LP442rP.11-12 ANSWER 2.25 (1.50)
- a. True
- b. False
- c. False REFERENCE BFNP LP911,P.10,12,38
- 3. INSTRUMENTS AND CONTROLS PAGE 46 ANSWERS -- BROWNS FERRY 1r 2&3 -85/07/15-GUENTHERrS ANSWER 3.01 (1.00) d REFERENCE RFNP LP922rP.16 ANSWER 3.02 (1.00)
D REFERENCE BFNP LP429,P.6 ANSWER 3.03 (1.00) b REFERENCE BFNP LPt29,P.11 ANSWER 3.04 (1.00) b REFERENCE BFNP LP635,P.8 ANSWER 3.05 (1.00) c REFERENCE DFNP LP921rP.10,12-13 ANSWER 3.06 (1.00) b 1
- 3. INSTRUMENTS AND CONTROLS PAGE 47 ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHER,S REFERENCE BFNP LP417,P.20 ANSWER 3.07 (1.00) d REFERENCE BFNP LP48,P.30 ANSWER 3.08 (1.00) c REFERENCE BFNP LP914;0I-47,P.17-18 ANSWER 3.09 (1.00) a REFERENCE BFNP LPt19,P.5-6 ANSWER 3.10 (1.00)
-b REFERENCE BFNP LP920,P.16 ANSWER 3.11 (3.00)
- a. 1,2,6
- b. 1,2,3
- c. 1,4,8
- d. 5,7,8 REFERENCE BFNP LPt3,P.5-6,16
- 3. INSTRUMENTS AND CONTROLS PAGE 48 ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHER,S ANSWER 3.12 (2.00)
- o. 8
- b. g2.5,4
- c. 3,4,5
- d. 2,3,4 REFERENCE BFNP LP428,P.17-19 Lc alt P.2v ANSWER 3.13 (1.50)
- 1. Flow mismatch E.43 / 10% E.153
- 7. Upscale high E.43 / 115% [.153
- 3. Mode switch not in operate E.43 REFERENCE BFNP LPt22,P.16 ANSWER 3.14 (1.00)
- 1. The TIP will auto transfer to the manual reverse mode.
- 7. The ball valve will close E.253 when the in-shield limit switch is closed C.253.
REFERENCE BFNP LPt23,P.21-22 ANSWER 3.15 (1.00) d REFERENCE ! I BFNP LP924,P.10,13 1 1 l 1
- 3. INSTRUMENTS AND CONTROLS PAGE 49 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHERrS ANSWER 3.16 (2.00)
- 1. 270 epa C.153 &bove background on the CR rad monitor E.353
- 2. +11" E.153 Rx water level C.353
- 3. 2.45 psig E.153 drywell pressure C.353
- 4. 100 mr/hr E.15] refuel 'cr C.. ) :one vent exhaust rad monitor E.353 no v .nr a- L .. d c ,3g (qg,g ,4
~
- s. As z- .. .. .. ..
REFERENC BFNP LP433rP.19 ANSWER 3.17 (1.50)
- o. selection of any 'B' sequence rod.
- b. group notch control logic.
- c. the continuous withdraw mode of RHC.
REFERENCE BFNP LP425,P.24,26 ANSWER 3.18 (1.00)
- a. False
- b. False REFERENCE BFNP LP928,P.15,7 ANSWER 3.19 (2.00)
- i. e ii. d REFERENCE BFNP LP912rP.24; TRANSIENT 420;0I-57,P.53 ANSWER 3.20 (1.00) d l
l -- i
- 3. INSTRUMENTS AND CONTROLS PAGE 50 ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHERrS REFERENCE BFNP LP(34rP.4 ANSWER 3.21 (1.50)
- s. False
- b. True
- c. True REFERENCE BFNP LP938,P.16,17,21 ANSWER 3.22 (1.00) d REFERENCE BFNP OI-47,P.24 J
l t J
, .--e.-_--,_, -- , _ , ._ ...,,,r_ _
,x .,m, r . . , _ _ _ . _ _
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 51
~~~~R56 6LU5505E~5U TR6E-~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHERrS ANSWER 4.01 (1.00) b REFERENCE BFNP OI-74rP.2;0I-68,P.3 ANSWER 4.02 (1.00) S REFERENCE BFNP OI-70rP.12-13 ANSWER 4.03 (1.00) d REFERENCE BFNP OI-68,P.28-29 ANSWER 4.04 (1.00) c REFERENCE BFNP OI-66,P.39-39A ANSWER 4.05 (1.00) b REFERENCE , BFNP OI-3rP.2
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 52
- ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~RA5iBL55iEAL E5NTR5L ANSWERS -- BROWNS FERRY 1r 2&3 -85/07/15-GUENTHERrS ANSWER 4.06 (1.00) d REFERENCE BFNP ' CONTROL ROOM ABANDONMENT"rP.2 ANSWER 4.07 (1.00) e REFERENCE BFNP RCI-9,P.11-12 ANSWER 4.08 (1.00) c REFERENCE BFNP GOI-100-1rP.14-16 ANSWER 4.09 (1.00) c REFERENCE BFNP OI-irP.3 ANSWER 41 (1.00) M u rs ownT.ca D REFER E BFNP I-57,P.2
1 l l
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 53
~~~~RA5i6E55iEAL 55aTRUL'~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- BROWNS FERRY 1r 2&3 -85/07/15-GUENTHER,S ANSWER 4.11 (1.00) B REFERENCE BFNP GOI-100-12,P.13 I ANSWER 4.12 (1.00) c REFERENCE 10 CFR 20.101 ) ANSWER 4.13 (1.00) b REFERENCE BFNP EPG-X,P.104;E0I-1,P.26 ANSWER 4.14 (1.00) d REFERENCE BFNP OI-1,P.9 ANSWER 4.15 (2.00)
- 1. Observe NIs to ensure Rx power has decreased to < 3%.
- 2. Drive in all operable IRMs and SRMs.
- 3. Transfer APRM/RBM recorders to IRMs; turn SRM recorders on.
- 4. Down-range IRMs as needed to follow power down.
REFERENCE BFNP GOI-100-11,P.4-5
40 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 54
~~~~ - ~~~~~~~~~~~~~~~~~~~~~~~~
RE5iBL55iEAL E5nTR5L ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHER,S ANSWER 4.16 (2.00)
- 1. At the beginning of each shift.
- 2. At the middle of each shift.
- 3. Following any power change of >= 40 MWT.
- 4. Following any unexpected power change.
REFERENCE BFNP GOI-100-1,P.20;0SIL 632 ANSWER 4.17 (1.00)
- 1. A third licensed operator must be in the CR within 5 minutes (to verify that no rod movement has been performed and the sequence adhered to)
OR 20 The reactor must be manually scrammed. REFERENCE BFNP GOI-100-6,P.23 ANSWER 4.18 (1.00) If water is present on either side of the suppression chamber-to-DW vacuum breakers they may not return sufficient nitrogen to the DW to preclude exceedin3 its design negative pressure. REFERENCE BFNP EDI-2,P.27;EPG-X,P.194 i t
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 55
~~~~RA5iBE55iEEE ESATRUE~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- BROWNS FERRY 1, 283 -85/07/15-GUENTHER,S ANSWER 4.19 (3.00)
- 1. If the Rx fails to scram when setpoint reached, then manually scram.
- 2. Verify existing conditions by multiple indications.
- 3. Verify all auto actions have occurred; if not, place controls in manual and make corrective manipulations.
40 Trip the recirculation pumps.
- 5. Place mode switch in SD. Place SDV high water level bypass switch to bypass.
- 6. Reset Rx scram (verify SDV vents and drains open) and manually scram the reactor, reset and repeat if rod motion is observed until all CR are fully inserted. (Continuously monitor flux until all rods full-in.)
REFERENCE BFNP EDI-3,P.5 ANSWER 4.20 (2.50)
- 1. Rx water level cannot be maintained above +11'.
- 2. Rx water level cannot be determined.
- 3. DW pressure > 2.45 psis.
40 A condition exists which requires an MSIV auto isolation.
- 5. Rx pressure cannot be maintained < 1055 psis.
l REFERENCE BFNP E0I-1,P.3 ANSWER 4.21 (1.00) i l The MGU will run to its HSS and the turbine will trip on overspeed. ( 9%. , a tk mw ,,.4 .wu ,a e.w .3 4 h o.> .;wt. % } REFERENCE
- BFNP OI-3,P.2,p+
l ANSWER 4.22 (1.50)
- 1. Annunciation of rod overtravel when the rod is withdrawn full-out.
- 2. No digital readout and no backlighting on the full-core display.
- 3. L PRM readings surrounding that rod will not change.
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 56
~~~~R I6 [66 EIL"5 UiR6E-~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- BROWNS FERRY 1, 2&3 -85/07/15-GUENTHER,S
' I REFERENCE BFNP OI-85,P.30 ANSWER '4.23 ( .50)
TRUE. i REFERENCE BFNP OSIL #20 i , l i
! l l
_ _ _ _ _ _}}