IR 05000317/1987005
| ML20214U811 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/04/1987 |
| From: | Coe D, Collins S, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20214U768 | List: |
| References | |
| 50-317-87-05OL, 50-317-87-5OL, 50-318-87-05OL, 50-318-87-5OL, NUDOCS 8706110347 | |
| Download: ML20214U811 (41) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NOS. 87-05 (OL) and 87-05 (OL) FACILITY DOCKET NO at:d 50-318 FACILITY LICENSE NOS. DPR-53 and DPR-69 LICENSEE: Baltimore Gas and Electric C P.O. Box 1475 Baltimore, MD 21203 FACILITY: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 EXAMINATION DATES: April 21-22, 1987 CHIEF EXAMINER: , j . 27 7 D. H. Coe, Lead Reactor Engineer (Examiner) Date REVIEWED BY: ) R. M. Kell r, Chief, Projects Section 1C
[['/[f7 Date APPROVED BY: lb S. J. Collins, Deputy Director 6h Date Division of Reactor Projects SUMMARY: A written and operating retake examination was administered to one Reactor Operator (RO) candidate. A retake operating examination was administered to one other R0 candidate. Both candidates passed their examinations and were issued licenses.
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!, REPORT DETAILS TYPE OF EXAM: Replacement EXAM RESULTS: ..
l l R0 l l l Pass / Fail l I I I I Wditten Exam I 1/0 l h'_
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1 2/0 l l I I I I I I Simulator Exam 1 2/0 l , I I I I I I l Overall l 2/0 I I I I CHIEF EXAMINER AT SITE: D. Coe
~ OTHER EXAMINERS: N. Dudley .
F. Jaggar (EG&G) Personnel Present at Exit Intervies: NRC Personnel
, D.Coe,,ChiefExaminer D. Trimble, Resident Inspector Facility Personnel
! J. Lohr, Assistant to Vice President, Nuclear Operations R. Heibel, General Supervisor, Operations K. Nietmann, General Supervisor, Nuclear Training J. Lemons, Nnager, Nuclear Operations Departmen ~ i R. Douglass', Manager, QA and Staff Services i W. Birney, Supervisor, Procedural Development [ J. Yoe, Senior Operations Instructor l
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3 Summary of NRC Comments made at exit interview: No preliminary examination results were give During the examination, the NRC developed two concerns related to control room procedures as follows:
(a) No procedural guidance existed for boration with all Boric Acid Transfer Pumps (BATP) inoperabl (b) Precaution F to 0I-28 directed the operator to A0P-1C (Emergency Boration) which no longer exists thus raising concerns that when the A0P's were revised in April 1986, references to old A0P numbers were not removed from all other procedure . Summary of facility comments and commitments made at exit interview:
The facility representatives committed to a review of their procedures and incorporation of additional guidance where appropriate. Additions were subsequently made to 0I-28 (CVCS Operation), and A0P-9 (Alternate Safe Shutdown Procedure). A review of these changes has shown that they satisfy concern (a) of paragraph four of this repor In addition, similar changes are being made to A0P-1A (Inadvertant Boron Dilution) as part of a more extensive re-write of that procedur The licensee committed to conducting a procedure review of procedures which had not undergone a biennial review since the new A0P's were implemented and removed all improper references to old A0P numbers including revising Precaution F of 0I-28, thus satisfying concern (b) of paragraph four of this repor . For each subsequent operator examination at Calvert Cliffs Nuclear Power Plant, the licensee should provide as part of the r.ference material an up-to-date list of differences between Units 1 and 2 which are not identified by separate system descriptions and which the licensee determines is important knowledge for licensed operators. This list should be updated as plant modifications are made and should include those systems having generally high importance ratings (greater than 2.5) in NUREG 1122 Knowledges and Abilities Catalog. Thus, differences in the Gland Seal and Exhaust, Generator Cooling, and Reheat Steam systems, for example, would not be desire In addition, copies of system descriptions should be bound for future submittals of reference materia Finally, simulator initial condition options should include those with the Unit Two turbine on-line and at power.
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Attachments: Written Examination and Answer Key ( RO) 2 Facility Comments on Written Examinations Made After Exam Review - NRC Resolution of Facility Comments
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O. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _CALVERT CLIFFS REACTOR TYPE: PWR-GE DATE ADMINISTERED: 87/04/21 EXAMINER: JAGGA s ,,
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CANDIDATE:
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LMEIEUCTIONS TO CAND[DATE: Use separate paper for the answers. Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category up six (6) hours of and a final grade after at least 80%. Examination papers will be picked the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE _ TOTAL SCOBE VALUE CATEGORY 25.00 25.00 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW _25.00 25.00 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS _25.00 25.00 INSTRUMENTS AND CONTROLS 25.00 25.00 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 100.00 % Totals Final Grade All work dona on this examination is my ow I have neither given nor received ai Candidate's Signature
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- - - _ _ - .. . . . . . ', NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: - Cheating on the examination means an automatic denial of your application and could. result in more severe penaltie . Rastroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination-room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil onlr to facilitate legible reproduction . -Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . Consecutively number each answer sheet, write "End of Category __" a appropriate, start each category on a ngw page, write only on one side of the paper,-and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . 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 literatur . The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated. in the question or no .15. Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of
=the examiner onl . 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 complete .
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(~ l 18. When you complete your examination, you shall: f Assemble your examination as follows: i (1) Exam questions on to (2) Exam aids - figures, tables, et (3). Answer pages including figures which are part of the answe ~ Turn in your copy of the examination and all pages used to answer the examination question c. Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examine If after leaving, you are found in this-area while the examination is still in progress, your license may be denied or revoke . _ _ _ _ . _ _ _ _ _ _ _ _ _ _
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
'* . THERMODYNAMICS. HEAT TRANSEEH AND FLUID FLOW .
QUESTION 1.01 (2.50) The overall power ccefficient is a combination of three coefficient List those coefficients in order from the largest to the smallest contributo Assume beginning of cycle (BOC).
[1.5] Explain how AND why each significant contributor to the Total Power Defect changes as the core age [1.0] QUESTION 1.02 (3.00) The ratio of the PU239 and PU240 atoms to U235 atoms increases over core lif Explain how AND why this increasing ratio changes the following: l- Delayed neutron fraction Reactor period Doppler Temperature Coefficient QUESTION 1.03 (3.00) A reactor startup and has just been completed and power is at the point of adding hea For the following situations, INDICATE WHERE final power level will be in reference to initial power level (HIGRER, LOWER, OR THE SAME). EXPLAIN your answe ' Include which coefficient causes the chang (Assume the core is at mid-life, no operator action and treat each situation separately). Steam dump pressure setting is raised by 20 psig, A 1%' steam leak develops outside of containment, c, An inadvertent 20 ppm boron addition is mad (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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.PAGE 3 PRINCIPLES OF NUCLEAR POWER PLANT OPERATIO IHEBMODYNAMICS. HEAT TRANSEEN AND FLUID FLOW .
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QUESTION 1.04 (1.00) Which one of the following best supports the reason why Xenon reactivity increases sharply after a trip following 1000 hr . i
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of operation at 100% power? ) Xenon decays less rapidly due to a reduction in the neutron flu . Iodine half-life is much shorter than Xenon half-lif Iodine production is greatly reduced and Xenon production is greatlyLincreased due to the reduction in neutron flu Due to reduced neutron absorption, Iodine concentration increases, and Xenon decays directly from Iodine, thus Xenon increases.
QUESTION 1.05 (2.00)
.The reactor is in the process of being started up. Power is at 10E-2%
with-CEA's in manual group control. A malfunctioning steam generator safety valve lifts, causing a steam flown increase to about 10% of total plant capacity. Assume no operator or reactor protective system action, and a negative MTC. Calculations are not necessar . For each of the following: Main steam pressure Primary Tave State HOW (increase, decrease, remain the same) and WHY each of the , parameters will INITIALLY chang . State HOW (higher, lower, remain the same) and WHY the final steady state value compares to the initial value prior to the transien (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) t .
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~1 .' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, . - - IHERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW < ' QUESTION 1.06 (1.50)
Anninstrument malfunction causes a spurious reactor rip from extended 100% power operatio Immediately followir.:, the trip, o pressurizer safety valve lifts and sticks ope Reactor Coolant Pumps are tripped according to procedure and RCS pressure drops to 1000 psi Answer each part independentl If natural' circulation flow could NOT be attained, what other means of core cooling exists AND will it be sufficient to cool the core? [1.0]
- Describe how auxiliary spray flow can be used to determine the presence of RCS voiding. [0.5)
QUESTION 1.07 (1.50) The heat output of the reactor can continue to cause the fuel to heatup following a reactor shutdow WHAT is(are) the source (s) of this thermal power, and WHY does it NOT indicate on the nuclear instrumentation? QUESTION 1.08 (2.00) The discharge valve of a running, motor operated, centrifugal pump is throttled (valve moved in the shut direction). Indicate whether each of the following will INCREASE, DECREASE, or REMAIN UNCHANGE Pump motor amp Pump discharge flo Pump discharge pressur Actual NPSH available at the pump (Assume fluid temperature remains constant).
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- PAGE 5 PRINCIPLES OF NUCLEAR POWER PLANT OPERATIONm THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW
. QUESTION 1.09 (1.00) Which statement BEST describes what happens to a fluid as it passes through a venturi? Pressure remains constant, and the velocity increases as the diameter of the venturi decrease Pressure increases and velocity decreases as the diameter of the venturi decrease Pressure increases and velocity remains constant as the diameter of the venturi increase Pressure increases, and the velocity decreases as the diameter of the venturi increase QUESTION 1.10 (1.00) Select the most correct statement from the followin a. If two centrifugal pumps are in parallel, the combined pump head will be approximately the sum of the individual pump head b. If two centrifugal pumps are in series, the combined power requirements will be approximately equal to the cube of the individual pump powe If two centrifugal pumps are in parallel, the combined flow will be approximately equal to the sum of the individual pump flow If two centrifugal pumps are in series, the flow from each pump will be approximately equal to the square of the individual pump spee QUESTION 1.11 (1.00) With all systems in manual and no operator action, what effect (INCREASE, DECREASE, or NO CHANGE) will decreasing the circulating water temperature have on each of the following? Condenser vacuu Condensate pump NPSH (Assume vacuum constant).
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* PAGE 6 1$ PRINCIPLES'OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW .
QUESTION 1.12 (1.00) Which one of the following will cause plant efficiency to increase? Total S/G blowdown is changed from 30 gpm to 40 gp Steam quality changes from 99.7% to 99.9%. Level increase to higher than normal in a feedwater heate Absolute condenser PRESSURE changes from 1.0 psi to 1.5 ps QUESTION 1.13 (1.00) Which statement best defines " Reactivity"? The ratio of the number of neutrons at some point in this generation to the number of neutrons at the same point in the previous generatio The fractional change in neutron population per generatio . The factor by which neutron population changes per genera-tio The rate of change of reactor power in neutrons per secon QUESTION 1.14 (1.00) Which one of the below requires the most-heat removal during condensation? (assume steam is of equal quality) one pound of steam at 0 psia.
, one pound of steam at 300 psi two pounds of steam at 600 psi two pounds of steam at 1200 psia.
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PAGE- 7 I~. l PRINCIPLES-OF: NUCLEAR POWER PLANT OPERATIO IHERMODYNAMIOS.' HEAT TRANSFER AND FLUID FLOW .
-QUESTION 1.15 (1.50)
List three reasons for establishing regulating group insertion limits?
-QUESTION 1.16 (1.00)
Explain why the pressure / temperature limit curves must be periodically redrawn to account for increased reactor vessel radiation exposur (***** END OF CATEGORY 01 *****)
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PAGE 8 I: PLANT DESIGN INCLUDING SAFETY'AND EMERGENCY SYSTEMS .
. ' QUESTION 2.01 (2.00) To which 4.16 kv unit buses may each of the three Emergency Diesel Generators.(EDG) be aligned? [1.25] ~ To which of the buses is each EDG NORMALLY lined up to supply? [0.75]
QUESTION 2.02 (1.50) The following pertain to the Emergency Diesel Generator (EDG) System: What minimum number of EDG starts can be provided by the two starting air. flasks associated with each diesel assuming they are initially full and are not recharged? How soon should the EDG be at rated speed and voltage following an auto start? QUESTION 2.03 (1.00) The following pertain to the design of the Engineered Safety Features System: The design purpose of the HPSI system is to (PREVENT / LIMIT) damage to fuel during a Main Steam Line Rupture event. Choose one. [0.5] In addition to core cooling and inventory maintenance, what other purpose does the HPSI system serve during a Main Steam Line Rupture? [0.5] QUESTION 2.04 (2.50) State the flow rate that will shut the Excess Flow Check Valve, 1.ocated downstream of the Regenerative Heat Exchanger. [0.5] How is the pressure equalized around the Excess Flow Check Valve so it may be reopened? NOTE: Include unit differences that may exist and maximum flow rate [2.0]
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PAGE 9 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
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QUESTION--2:.05 (2.50) State the-four purposes of the Auxiliary Feedwater Actuation System (AFAS). [1.0] State the normal, alternate, and emergency sources of water for the Auxiliary Feedwater System (AFW). [1.5] QUESTION 2.06 (2.00) Briefly describe the system that each unit uses to-protect the turbine-driven AFW pumps AND motor-driven AFW pumps against overheating during low load operatio Provide minimum flow rates for each type of pum [1.25] State the three devices that can actuate the tripping latch on the turbine-driven AFW pumps Trip and Throttle Valv [0.75] QUESTION 2.07 (1.75)
- State THREE reasons why th3 Pressurizer spray valve bypass valves supply a continuous spray flow. [0.75] What alarm (s) will indicate to the operator that proper Pressurizer spray flow is NOT being maintained? [0.5] . State the Pressurizer spray water maximum temperature differential as listed in Tech. Spec [0.5'
QUESTION 2.08 (3.00) State the actuation signal, coincidence (logic), and setpoint for . Containment Spray Actuation (CSAS). [0.4] ! When the CSAS setpoint is reached, what flow path does the fluid
take during the injection mode? [0.6] Ii the event of an undesired trip of the CSAS, does the fluid take the same flow path as listed in b. above? Explai [1.25] When the metals inside containment are in contact with boric acid, as during CS operation, what design feature protects against stress corrosion cracking?
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QUESTION 2.09 (1.25) F The' Salt Water air compressors start on an SIAS signal to supply a backup source of air to certain vital control valve Why is this beckup source of air required? QUESTION 2.10 (3.00) Briefly describe how an undetected leak in a Steam Generator i
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Blowdown Heat Exchanger can lead to exceeding rated thermal powe Assume unit is at 100% power.
, What automatic action occurs in the blowdown system if service water flow is lost to the blowdown heat exchanger? Why does this action occur?
~ QUESTION 2.11 (2.50) Describe the PREFERRED flow path used to establish a core flush
' during long-term core cooling following an LOCI. [1.5] The core flush is used to prevent the restriction of core flow due , to boron crystallizatio Ho.w does break location (hot leg vs.
- cold leg) affect the formation of boron crystals? [1.0] QUESTION 2.12 (2.00) , How are the following CVCS components protected from high temperature conditions? Include setpoint [0.5] j
- Ion Exchangers j - Boronometer and Process Radiation Monitor Briefly describe the Volume Control Tank (VCT) overpressure protectio Include setpoint [1.5]
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'3 ' . IN'STRUMENTS AND' CONTROLS . .
QUESTION 3.01 (3.00) The.following concern the control rod drive system, 7 Explain the effect a lift coil failure would have on rod withdrawa List five ways to determine whether a control rod is withdrawing properl QGESTION 3.02 (2.00) From the list below, choose the two radiation monitor channels that have automatic actions. Briefly describe the automatic actions for eac . Condenser Air Removal Discharge Monito Steam Generator Blowdown Recovery Radiation Monito Main Steam Effluent Radiation Monitor (any of three channels). Control Room Ventilation Supply Radiation Monito QUESTION 3.03 (2.00) When an SIAS is present, what four conditions will energiae the , Emergency Diesel Generator Shutdown Relay? QUESTION 3.04 (2.00) Decreasing reactor power activates the EXTENDED RANGE MODE in the NIS wide range log channels. State the automatic actions that occur when this happen [1.25] l State THREE automatic actions that are performed at 10-4% increasing reactor power when the level 2 bistable trips off?
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l . PAGE 12 INSTRUMENTS AND CONTPOLS . QUESTION 3.05 (1.50) Name the signal (s) used by the feedwater control system when the reactor power is LESS than 15%. [0.25] Name the signal (s) used by the feedwater control system when the reactor power is GREATER than 15%. [0.75] Which unit in the feedwater control system is specifically designed to compensate for transients within the steam generator such as shrink and swell. [0.5] QUESTION 3.06 (2.50) Match the action / signal in column A to the source of the signal in column B. NOTE: Column B responses may be used more than onc COLUMN A COLUMN B Reactor Regulating System CEA withdrawal Prohibit (CWP) Tavg - Tref AWP signal Reactor Protective System CEA Motion Inhibit bypass signals Plant Computer to CEA motion inhibit logic circuitry Digital Group CEA position CEDS control panel indication Reactor power (Qmet) input to metroscope QUESTION 3.07 (2.50) List the alarm signals generated by the CEA Motion Inhibit Circui Do not include the Out of Sequence signal. [1.0] What THREE conditions will cause a CWP interlock to activate?
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QUESTION 3.08 (1.50)
'While operating at 85% power with pressuriser level transmitter LT-110x selected and HS-100-3 in the X+Y position. State the ,
expected automatic-system responses, in addition to receiving alarms, if LT 110x fails lo ' QUESTION 3.09 (3.00) The Reactor Program Unit Calculator (RPUC) in the Reactor Regulating System computes signals for four programs. List _
.the FOUR-program What TWO inputs does the RPUC use to calculate the four programs? ' QUESTION 3.10 (1.50) . State ALL the CONTROL FUNCTIONS provided by the Low Range Pressurizer Pressure channels. (PT-103, PT-103-1) Setpoints not require QUESTION 3.11 (1.50)
Concerning the Axial Power Distribution reactor trip; State the THREE inputs and their sources which are used to generate the APD signa Do not include RCP combination as an input signal What initiates an APD channel trip signal? QUESTION 3.12 (2.00) a; State the THREE events that occur in the EHC system when the Unit 1 master reset push-button is presse Which turbine trip signal DOES NOT need to be cleared to allow the turbine to be reset? [0.5]
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PAGE 14 d. ' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND
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BADIOLOGICAL CONTROL
. . QUESTION 4.01 (3.00)
10 CFR 20 provides federal regulations for radiation exposur Answer the following in accordance with 10 CFR 2 a. What is your QUARTERLY Whole Body exposure limit? [0.375] What THREE criteria must be satisfied to exceed this limit under NON-EMERGENCY conditions? [1.125] To ensure the above limits are not exceeded, Calvert Cliifs has instituted Administrative Dose Limit Fill in the blank The whole body dose to any individual shall not exceed per year or - per quarter without approval by the and th . [1.5] QUESTION 4.02 (2.50) As stated in procedure CCI-112G Safety Tagging, if any one of four conditions exist, independent verification may be waive List THREE of the four conditions. [1.5] State the NRC License requirements for the following personne . Senior Safety Tagger Safety Tagger [0.25 ea.] Who (by title) can perform tagout reviews? [0.5] ,
QUESTION 4.03 (2.00) According to GSO Standing Instruction #83-12, what actions are required in the event of a loss of-power to 11 DC BUS. Why are these actions required?
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PROCEDURES - NORMAL. ABNORMAL. EMEBGENCY AND . RADIOLOGICAL ~ CONTRO . P QUESTION 4.04 (2.50) The following pertain to AOP-2A, Excessive Reactor Coolant Leakage, Define the following: Major Leak Minor Leak [1.0] During the performance of AOP-2A, the reactor must be manually tripped if certain minimum parameter limits are exceede For the following parameters state the limit which would require a manual tri . Pressurizer Pressure Pressurizer Level Tavg [1.5] QUESTION 4.05 (1.50) State the TWO conditions, either one of which will require tripping the RCP's after a complete loss of component coolin [1.0] How long are the LP and HP Safety Injection pumps designed to operate with NO component cooling? [0.5] QUESTION 4.06 (1.50) During a natural circulation cooldown using AOP-3F Natural Circulation Cooldown, subcooling is maintained "near but not to exceed 200 F". State the TWO methods that can be used to INCREASE the subcooled margi [1.0) How is a DECREASE in subcooled margin accomplished? Be specifi [0.5]
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~PAGE 16 y4.' PROCEDURES -L NORMAL. ~ ABNORMAL. EMERGENCY AND-
. RADIOLOGICAL CONTROL
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~ QUESTION 4.07 (2.00)
The following pertain to information found in EOP- List the three steps used to ensure the reactor has trippe 'Do not include Alternate Actions. [1.0]
. Which three Radiation Monitors are checked to ensure normal radiation levels? [1.0)
QUESTION 4.08- (3.00) One of the Safety Functions checked periodically when using the emergency procedures is Vital Auxiliarie List FIVE of the Vital Auxiliaries that are checke List the remaining FIVE Safety Functions in order of priorit QUESTION 4.09 (3.00) For each condition below, apply RCP trip criteria as stated in-EOP-0 to answer-(YES or NO) if ALL RCP's need to be trippe Consider each condition separatel . RCS pressure decreases to 1725 psi . Positive LOCA indications exist and RCS pressure has decreased to 1500 psi . CIS has initiated, True or False? When EOP-8, Functional Recovery Procedure has been entered, the entirety of the procedure must be implemente . EOP-8 may be implemented anytime during the use of EOP-0 when multiple safety functions are not meeting their
acceptance criteri . If a subset of parameters for a single safety function are violated, EOP-6 need not be implemented if the Shift Supervisor determines that the recovery of the out of spec parameter (s) to within acceptance criteria is imminen (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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.. . QUESTION- 4.10 (1.00)
During.the performance of EOP-3, Total Loss-of:Feedwater, it is-dstormined that Auxiliary Feedwater and Main Feedwater are not available. . State the parameters that require isolating the first
.AND second S/ Setpoints not require ; QUESTION 4.11 (1.50)
The'following pertain to information contained in OP-2, Plant Startup from Hot Standby to Minimum Load, When taking the reactor critical what is the maximum sustained startup rate? What is the minimum RCS temperature that will be maintained withi minutes prior to achieving criticality? State the position the shutdown CEA's be must be withdrawn to prior to withdrawal of any regulating CEA' QUESTION 4.12 (1.50) State the flow path used during Fast Boration as lintea n OI-2B, CVCS Boration, Dilution and Makeup Operation [1.0] What~is the waiting period that should be observed-between repeated Fast Boration operations? [0.5]
(***** END OF CATEGORY 04 *****) (************* END OF EXAMINATION ***************)
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;L PRINCIPLES OF NUCLEAR POWER' PLANT OPERATION, ' THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW - ..
ANSWERS -- CALVERT CLIFFS ' -87/04/21-JAGGAR, < ANSWER 1.01 (2.50)
~ FTC [0.4]
MTC [0.4] Void coefficient [0.4]
[0.3] for proper order Mod. Temp. Defect increases'(becomes more negative). MTC becomes more negative. Due to a decreare in boron concentration [0.5]
Fuel Temperature defect decreases. Fyel temperatures decrease over core lif [0. 5] asd e cerpt fuel Te mf.De{ed days.-ibe un e of REFERENCE - dsscassten abovi offs.ttin5 efects af FTC.- as nurde Cal. Cliffs- RO-302-1-0 pp. 35-37,
~001000K529 001000K549 192004K113 ...(KA'S)
!-ANSWER 1.02 (3.00) Delayed neutron fraction decreases [0.5] because the beta ,
.is less for PU239.as compared to U235. [0.5] Shorter reactor period [0.5] because delayed neutron fraction decreases. [0.5]
4 Doppler Coefficient is more negative [0.5] because PU240 has a higher resonance cross section than U235. [0.5) i
- REFERENCE Cal. Cliffa LP. RO-302-2-0 p. 4-8, 15 RO-302-1-0 p. 33 192003K104 192003K106 192004K107 ...(KA'S)
J
. t
= _ . . . _ . _ _ . . _ . _ . _ . . _ - - _ _ _ . _ . , - . .
.
- , _ , _ _ _ _ _ _ _ . _ _ _ . , _ _ . _ . _ - . . . . - - . _ _ . _ . . _ _ _ _ _
_ - -
_ _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ ... PAGE 19 1 PRINCIPLES OF NUCLEAR POWER PLANT OPERATIO IHERMODYNAMICSi HEAT TRANSFER'AND FLUID FLOW ANSWERS -- CALVERT CLIFFS-87/04 /21-JAGGAR ,' ANSWER 1.03 (3.00) Lower [0.25]; the steam dump pressure setting increase causes an RCS temperature increase [0.25]. MTC [0.25] ands'- FTC-4 Doppler-)--EO,-26}-both' adds negative reactivity to lower reactor power.Co 24] Higher [0.3]; the increased flow will result in a lower RCS temperature (0.4]. MTC will add positive reactivity and power will rise [0.3]. Lower [0.4]; the negative reactivity inserted by the baron will cause power to decrease (0.6]. REFERENCE CE- Nuclear Physics, Reactor Theory and Core Operating Characteristics, p 162-166, 178 001000K515 004000K520 ...(KA'S) ANSWEh 1.04 (1.00) b (1.0) REFERENCE Reactor Theory Lesson RO-302-1-0 pp. 37-39, 3-34 to 3-40 192006K107 ...(KA'S)
.
ANSWER 1.05 (2.00) ' Steam pressure decreases [0.3] due to thermal energy removal from the S/G [0.3]. Final value lower due to delta T (Tave - Tstm) required to drive thermal energy across the S/G. [0.4] Primary Tave decreases [0.3] due to Tstm now less than Tave which drives thermal energy from primary to secondary [0.3]. Final value lower due to positive reactivity needed from MTC to offset negative reactivity added by FTC [0.4] REFERENCE Reactor Theory module 4, Learn. Obj. 4.7.12 and pg 4-35 035010K501 193005K103 (KA'S) I
.s
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ . _ _ _ _ - _ _ _ _
PAGE 20
[1.~ PRINCIPLES OF NUCLEAR POWER PLANT OPERATIO . THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ,
ANSWERS -- CALVERT CLIFFS-87/04/21-JAGGAR, ANSWER -1.06 (1.50) .Once through cooling [0.5] NO [0.5] Rapid increase in pressurizer level during Aux. spray [0.5]
. REFERENCE .a. .CEN-152'Rev 3 pg 5-31 and 5-34 EOP-5 Rev 0 pg 3 EOP-5 Rev 0 pg. 17-000056A218- 000056K302- ...(KA'S) *****]fAf3,23' o 0 0 o of Ep 2,37 ANSWER 1.07 (1.50)
This thermal power is from the decay of fission products (0.5) and consists mainly of alpha, beta, and gamma radiation which are not detected by the nuclear instrumentation (1.0).
REFERENCE Cal. Cliffs RO-302-2-0 i 000007A105 000007K105 ...(KA'S) , ' .? ANSWER 1.08 (2.00) decrease decrease increase increase [0.5 ea.] REFERENCE Thermodynamics, Fluid Flow and Heat Transfer for Nuclear Power Plants, ,
.
pgs 328-329 ' 191004K106 191004K114 ...(KA'S) ANSWER 1.09 (1.00) d REFERENCE GP HT&FF p. 313-314
191002K101 ...(KA'S)
s
.. . - .. -- . ._ - - . .-.
. . PRINCIPLES OF NUCLEAR POWER PLANT OPERATIO PAGE- 21
. . IljgBMODYN AMICS . HEAT TRANSFER AND FLUID FLOW ANSWERS -- CALVERT CLIFF /04/21-JAGGAR, ANSWER 1.10 '(1.00) REFERENCE GP HT&FF pp. 322-334 Appendix pg A-9 K109 191004K110 ...(KA'S)
ANSWER 1.11 (1.00) Increase b'. Increase [0.5 each] REFERENCE Cal. Cliffs RO-301-10-0 K511 039000A105 ...(KA'S) ANSWER 1.12 (1.00) '
.b . REFERENCE General Physics, Heat Transfer Thermodynamics and Fluid Flow,
' pp. 145 - 16 .002000K501 ...(KA'S) ANSWER 1.13 (1.00) ' b REFERENCE Cal. Cliffs RO-302-1-0 p.3-5 001000K556- ...(KA'S) ANSWER 1.14 (1.00) , C.
r- , , d
, , . ,- . - . - . . - . , , . - - - - - - - . - . . , . - , . , ., , , , - -, , , ,. -- ,w- w, ,, ,, , , , , - .
_ _ - . . .- . .. PRINCIPLES'OF NUCLEAR POWER PLANT OPERATION, PAGE '22
: .TilERMODYNAMICS . HEAT TRANSFER AND FLUID FLOW .. , ANSWERS -- CALVERT CLIFFS -87/04/21-JAGGAR, REFERENCE steem tables .
193003K125 ...(KA'S)
.
ANSWER 1.15 (1.50) Acceptable power peaking factors are maintaine . Maintain minimum available shutdown margi . Limit consequences of a CEA ejection acciden [0.5 ea.] REFERENCE B 3/4 1-3 ,
. Technical Specification B 3/4. K504 ...(KA'S) . ANSWER 1.16 '(1.00)
Fast neutron irradiation of the reactor vessel will raise its reference 1 transition temperatur [1.0] REFERENCE Technical Specification p.-B 3/4 4-6 193010K105 ...(KA'S) I
, . , , , . . _ . . . _ _ . - - , . . . _ _ . , , . _ , _ _ , , _ ~ . , _ . . . _,_ , . , _ - . ~ , , ,
PAGE 2:3 (*M.-PLANTDESIGNINCLUDINGSAFETY-ANDEMERGENCYSYSTEMS
.
-87/04/21-JAGGAR, .JANSWERS -- CALVERT CLIFFS
. ANSWER 2.01 (2.00) EDG 11--- bus 11, 21 [0.25 ea.]
EDG 21--- bus 14, 24 [0.25 ea.] . EDG 12--- bus 11, 14, 21, 24 [0.25] EDG 11--- bus 11 [0.25] EDG 21--- bus 24 [0.25] EDG 12--- bus 14 or 21 [0.25] REFERENCE Cal. Cliffs SD-52 p. 27 064000K101- ...(KA'S)
> . ANSWER 2.02 (1.50) four less than 10 sec [0.75 ea.]
REFERENCE S.D. 48, pg. 46-Tech Spec 4.8.1.1.1. A304 064000A306 ...(KA'S) i ANSWER 2.03 (1.00) l- PREVENT [0.5] b. To ensure adequate shutdown margin [0.5] REFERENCE S.D. 7 pg 58 S.D. 7 pg 1 006000K302 006050SG04 ...(KA'S) )
.
. - . - - . . . - - , - , , . ._. .-.
. . . . -
. . _ -.. _ . . - . . . . _ - _ . - - _ . - . _
4, 7
.PAGE 24_ [2 PLANT' DESIGN INCLUDING SAFETY AND' EMERGENCY SYSTEMS _ i.
, q . s-87/04/21-JAGGAR, ' . ANSWERS.- .CALVERT CLIFFS
.
<
i, ' sf
. ANSWER .2.04 (2.50) : +/- 20 gp [0.5]
c; ,. , . . - Unit .1 has F 'oypaEsiline [0.53,'with an orifice (0.5] around the check valve.' Maximum flow in bypass line is 10 gpm [0.5]:. Unit 2 has a'no16'in the disc of the' valve [0.5].
- -- ,
REFERENCE '
'
Cal. Cliffs, SD 6, PP. 12-13-004010A402 004020A108 . .(KA'S) .,
:. ;, i
.ej e i
.y ;,
ANSWER- 2.05 (2.50)
.,a-s .)
. -, , . Automatically-startupsthe AFW shs gem (upon low steam f.e'nerator leve <m 2
, Block AFW flow to a. ruptured steam generato e
:
-
d' jE'N . Provide ~high steam generator level ' alarm.? mi ,, c/ , Provide AFW flow to break alar (Warns operator of rupture .
- 'in AFW line to a steam generator). +
>
-[0.25.each =.1.0)
.
, -3 ,
i t As-t- t ' Normal - C'ST 12 "
% i . m. s .1# -Alternate - CST 11 p1 21 .
Emergency - FiremaIh (to AFW pump 13 (23)) [0 5 ea.]
,
REFERENCE Cal. Cliffs, SD 34, P. 4f ,
;
'-
013000K107 061000K401 ...(KA'S) d, (
.
i x
'. .?
4 x, u,
.
\_
, .
..A - , , - 1 e . w er .- ,,r , ,n-e---,--,-- - . , , ~ - . - , - - , , , - - - - -
. . - -. . .
_- PLANT DESIGN INCLUDING S?.FETY AND EMERGENCY SYSTEMS PAGE. 25-
-87/04/21-JAGGAR, .
. ANSWERS -- CALVERT CLIFFS-(2.00)
,
ANSWER- 2.06 Unit 1- TDAFW pump reciros back to CST 12 [0.25]. A flow orifice provides 80 gpm minimum flow. [0.25] MDAFWpumphasa[ Automatic'RecirculationValve F ARO-) ' that varies-reci.rcr-f-low-as-pump-discharge-pressure c-
. changes-[0. 25-3-with-a-1-50-gpm-minimum-flo# [0. 25] .
Pov*4u dd y Ha d ecf sy Unit 2- TDAFW pump is the same as unit 1.Ceaf) MDAFW pump Mls hhsfanfIR t it-has-been-altered-
. internal-ly-to provide-150-gpmg [0.25] . A local hand trip leve . Hand switch in the control room Turbine overspeed trip mechanis [0.25 each]
REFERENCE Cal. Cliffs, SD 34,.PP. 23, 25, 38 061000K407 061000K408 ...(KA'S) ,. ANSWER 2.07 (1.75) ' . Equalize boron concentration between RCS and pressurize . Reduce thermal stress to spray line and nozzl [0.25 each]
. Reduce thermal stress to surge lin Surge line and Spray line low temperature alar [0.5] F [0.5]
REFERENCE Cal. Cliffs, SD 5, P. 25 RCS Inst. Lesson Plan, PP. 43, 44 Tech. Specs., P.3/4 4-27 010000A108 010000K401 ...(KA'S)
.
%
y---- . - - - - - -
.e -- n -- - -~ - r--- , - , - , , - - - - , , - - ,
PAGE 26 PLANT DESIGN INCLUDING' SAFETY AND EMERGENCY SYSTEMS
'
- A'NSWERS -- CALVERT CLIFFS-
-87/04/21-JAGGAR, F.
ANSWER 2.08 (3.00) v.7 f /4 [0.1] high containment pressure [0.2] of 4'psig +/--r25-psig"-
[0.1]. RWT -> Spray pumps -> SDC heat exchanger -> Containment spray header -> Spray ring -> Containment sum [0.1 each] 'No'[0.5]. Spray water will go to the spray header isolation valves (0.25] which will open automatically only on an SIAS signal [0.25]. Water will recire. back to RWT [0.25]. Trisodium Phosphate (TSP) baskets [0.25] are installed near the containment floor. The TSP will dissolve as the water rises and change the pH'[0.25] of the spray water during recirculation mode [0.25].
REFERENCE Cal. Cliffs setpoint book; SD. 7, PP. 7, 53 013000K105 026000K101 026000.{402 ...(KA'S) ANSWER 2.09 (1.25) After an SIAS, service water is isolated to the turbine building causing the instrument air system compressors to be secure [1.25] REFERENCE cal. Cliffs, Salt Water System Description, K302 078000K403 ...(KA'S) ANSWER 2.10 (3.00) As the leak develops, the indicated flow rate will increase [0.25]. The operator will close the thr-ttle valve to maintain the required-indicated blowdown flow rate [u.75]. The error between indicated and actual flow rate is sent to the computer generated calorimetric power calculation resulting in a erroneous calorimetric [0.5]. Blowdown flow is automatically diverted around the ion exchangers on Hi temperature signal [1.0]. This protects the resin from over-temperature [0.5]. REFERENCE Cal. Cliffs,RSD 18, P. 45; NPE V. D. 278 7/8 A205 . .(KA'S)
, , , _ . . . ~ . , - , - , , . - . . - - _ _ . - .,-_.__.,_-3,-- . . , . _ . __s, , . . . . . , .
-- --_- __
PAGE 27 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS ANSWERS -- CALVERT CLIFFS -87/04/21-JAGGAR, F.
ANSWER 2.11 (2.50) HPSI pumps [0.3] take a suction on the containment sump [0.3] and discharge into the charging header [0.3] to the auxiliary spray line into the pressurizer [0.6]. There is minimal flushing flow through the core for a cold leg break, and boric acid concentration can increase [1.0]. REFERENCE Cal. Cliffs, SD 7, P. 67; LP 201-5-0 p.10; EOP 5 p. 2 A111 . (KA'S) ANSWER 2.12 (2.00) (TE-224) will close a bypass valve for the IX columns and an isolation valve for the Boronometer and PRM at 145 F +/- 10 [0.5] Gas and liquid relief valves are provide [0.5] The gas relief is set at 70 psig +/- 5 psi [0.5] The liquid relief is set at 80 psig +/- 5 psi [0.5] REFERENCE Cal. Cliffs, SD, PP. 15, 23 004000A340 004000K403 . (KA'S)
- _ _ _ _ _ _ _ _ . _ _-________ _ _.. _ _ _ _ _ _ ._ _
' PAGE 28 INSTRUMENTS AND CONTROLS . ANSWERS -- CALVERT CLIFFS -87/04/21-JAGGAR, ANSWER 3.01 (3.00) f Rod zill not move up [0.Al because the lift coil is used to raise the upper gripper [0.f5), rod-won'-t-fal-1-or -insert-00:4f d u e_t o_acti o n- o f-l owe r- g r-i ppe r-00 J 51A . Metrascope RPI Computer indication Group deviation Metrascope digital CEA motion inhibit 4 ' Pulse counter Rod bottom lights [5 G Oy3'each] , REFERENCE SD 60, CEDS; p 9, 25-29 001000K408 001000K503 ...(KA'S) ANSWER 3.02 (2.00) Shuts B/D recovery discharge valves and diverts B/D flow to the Miscellaneous Waste Processing System [1.0] Outside dampers shut [0.4] post LOCI fans start [0.2] post LOCI filter dampers open [0.2] kitchen and toilet fans stop [0.2] REFERENCE S.D. 15 pp 46, 53, 63, 60 073000K401 073000SG04 . .(KA'S) ANSWER 3.03 (2.00) Engine overspeed [0.5] Lube oil low pressure switches trip [0.5] Crankcase high pressure switches trip [0.5] Cranking time control relay (start failure relay) time out [0.5] REFERENCE S.D. 48 pg 109 064000K402 (KA*S) ___-__ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ ._ _ _
'
PAGE 29 INSTRUMENTS AND CONTROLS
. . ANSWERS -- CALVERT CLIFFS-87/04/21-JAGGAR, ANSWER 3.04 (2.00) The dual section proportional counter is energized to provide additional neutron detecting sensitivity [0.75]. Also the indication changes from percent power to counts per second [0.5]. . Enables the high SUR trip Enables the SUR and TM/LP pretrip inputs to the CWP circuit Energizes a level 2 status lamp Enables PDIL function of the metroscope [3 @ 0.25 ea.]
REFERENCE Nuclear Inst. system description pgs. 20-21,23-24 and 25 015000A303 01500,0K604 .. (KA'S) ANSWER 3.05 (1.50) Steam Generator leve [0.25] Steam Generator level Steam flo Feedwater flo' [0.25 ea.] Feedwater lead / lag unit. 3- [0.5] '
,,
t*ff,, REFERENCE Downce men le=J/Ing enol (les'el) Mc \\ also necef g,,g' g,, ;,f, gn,p",jpgw wen g,I,,l Cal. Cliffs SD 32 p. 17-20; R C -#3-1-0 Pg./D 059000A307 059000A410 059000K107 .(KA'S) i ANSWER 3.06 (2.50) B A D C B [0.5 each] REFERENCE L.P. RO-60-3-0 pgs. 5-6 001000K401 001000K407 (KA'S)
.
- - - _ _ . - _ _ _ _ _ _ _ , __
-a . . PAGE :30
. ' INSTRUMENTS AfD , CONTROLS ~
e
'* ANSWERS o-- CALVERT: CLIFFS
-
-87/04/21-JAGGAR, ANSWER L3.07 ' ( 2. 50 ) -
. cr. ' PDIL-Deviation MISH MIRG [0.25 ea.]
b. - ' High power level;pretrip High SUR pretrip TM/LP.pretrip [0.5 each]
' REFERENCE Cal. Cliffs SD 60 p. 36-37 001000K407 001000K408 ...(KA'S)
ANSWER 3.08- (1.50)
- Starts all backup charging pumps - Letdown signal to minimum Lo-Lo level heater cutout [0.5 each]
REFERENCE L.P. RO-62-1-1 pg. 23 011000A203 011000K513 ...(KA'S) ANSWER 3.09 (3.00) . Pressurizer level
-- 2 . Steam dump positioning. signal Tref Tave - Traf [0.5 each] . Tave- Turbine first stage pressure (PTFS) [0.5 ea.]
REFERENCE-L.P. RO-58-1-2 pg. 14 001000K102 001000K104 .. (KA'S)
.
-__- - _ _ _ _ _ _ - _ _ _ .. . .. .
u :.;. PAGE 31 ' 3; INSTRUMENTS AND CONTROLS
.
1* ANSWERS --:CALVERT CLIFFS-87/04/21-JAGGAR, ANSWE .-10 (1.50) Open SI tank isolation valve . Shut shutdown cooling return valve . Provide logic circuitry inputs to arm, open, and shut the PORV' [0.5 each] REFERENCE Cal. Cliffs, SD. 62, PP. 28-30 010000A403 010000K103 010000K301 010000K403- ...(KA'S) ANSWER 3.11 (1.50)
? .t;v ,1 6.drv< Lia$ (ye..J WS . -Reactor-power-[0.25]-generated by the TM/LP calculator [0.25]. - ASI [0.25]-from the nuclear instruments [0.25]. CEA Function [0.25]-fixed input from the safety analysis [0.25]. A channel trip occurs if the axial shape index (YI) exceeds a positive or negative limiting value [0.25] of the power-dependent insertion limit's (YP or YN) [0.25]. w,n n ecept _ ", It asy efece.g3 %,
h m.b 6,14e 3 on "te ae cue <. ~ . co. 25,3
.
REFERENCE ~ Cal. Cliffs, SD 59, PP. 19-20 012000K606 012000K611 ...(KA'S) ANSWER 3.12 (2.00) . Mechanical trip valve resets Master trip solenoid. valve resets Emergency trip pressure solenoids are deenergized which removes the hydraulic lock in signa [0.5 each] Vacuum trip [0.5] REFERENCE Cal. Cliffs, SD 23-1, PP. 38-39 045000A402 045000K402 045050SG04 ...(KA'S) I t
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ . _ _ _ _ _ . _ _ _ _ _ . _
- ~ -
PAGE' 32 4 PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND'
-
RADIOLOGICAL CONTROL
, .
ANSWERS - -CALVERT CLIFFS -87/04/21-JAGGAR, AliSWER 4.01- (3.00) .25 Rem /Qt [0.375] Three (3) REM /Qtr is not exceeded Total accumulated lifetime dose does not exceed 5(N-18) Accumulated ~ Exposure on record (NRC-4). [0.375 ea.] REM, 2 REM, General supervisor, General. Supervisor-Radiation Safet [0.375 ea.] REFERENCE 10 CFR 20.101 (a) (b) (1), (2), & (3) Cal. Cliffs CCI-800B p. 10 194001K103 ...(KA'S) ANSWER 4.02 (2,50) . Emergency conditions exis . Entry into a High Radiation or Hazardour area is require . An operational test is used to verify operability and the component is not a locked valv . The component that is being restored is not Safety Related or affects plant reliabilit [3 of 4 0.5 each = 1.5] . RO or SRO license on both unit . No license requirement [0.5] Only Senior Safety Tagger [0.5]
, < .w .+ < , ,wa n , , ,, :. .,, c .- , , REFERENCE Cal. Cliffs, CCI-112G, P , 6 194001K102 ...(KA'S)
t
'% , . -
'PAGE 3 ' PROCEDURE 5 - NORMAL. ABNORMAL. EMERGENCY AHD
- RADIOLOGICAL CONTROL
..
ANSWERS -- CALVERT CLIFFS-
-87/04/21-JAGGAR, ANSWER 4.03 (2.00)
Immediately station an operator at the Unit 2 turbine front standard
[0.25]
to in direct manually tripcommunication with the control the turbine if necessary [0.5].room (0.25]because Required in order the remote.and automatic electrical trip functions are lost [1.O]. REFERENCE Cal. Cliffs, GSO Standing Instructions, 83-12 045000K412 063000K302 ...(KA'5) ANSWER 4.04 - (2.50) . One charging pump is unable to maintain pressurizer level with minimum letdown flow. fe..s] One charging pump is able to maintain pressurizer level with minimum letdown flow but leakage is greater than Tech. Spec Co as3 . TM/LP pretrip valu . 101 inches F Ce.$ c ] REFERENCE Cal. Cliffs, AOP-2A, P , 3, 4 002020SG10 ...(KA'S) ANSWER 4.05 (1.50) . Ten minutes Thrust bearing temperature reaches 195 [0.5 each] hours [0.5] REFERENCE Cal. Cliffs, AOP-7C, PP. 2, 7 000026A206 003000K404 .(KA'S)
,
.. PROCEDURES --NORMAL. ABNORMAL. EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL .,.
ANSWERS -- CALVERT CLIFF /04/21-JAGGAR, F.
-ANSWER 4.06 (1.50)
. . Ir. crease the cooldown rat . Raise pressure.using pressurizer heater [0.5 each] Reduce pressure using auxiliary spra [0.5]
REFERENC Cal. Cliffs, AOP-3F, P. 5-000056K103 ...(KA'S) ANSWER 4.07 (2.00) . Depress one set of reactor trip button . Verify all-CEA's fully inserte . Verify prompt drop in NI powe . Main plant ven . Condenser off-ga . Steam Generator Blowdow , c,,,% ,, mt ,,,,,, d c t 3 4,y REFERENCE Cal. Cliffs, EOP-0, PP. 5, 8 194001A102 ...(KA'S)
,
. . .
PAGE 35 PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND -- : RADIOLOGICAL CONTROL
.
ANSWERS -- CALVERT CLIFFS -87/04/21-JAGGAR, ANSWER 4.08 (3.00) Any FIVE of the following: 4kv Vital Buses 125v DC Buses 120 Vac Buses Instrument Air Pressure Component Cooling Pumps Service Water Pumps Saltwater Pumps Condenser vacuum 6 -[5 0 0.3 each] Reactivity Control Pressure and Inventory 4 RCS and Core Heat Removal ,,,.<a Containment Jeolation fod'" [5 0 0.2 each] D d ' ^ - ' ' - ' ty Cent reb [0.5 for priority] j{.2,6en. \ cv<ls ede<n nits c.nb. ment REFERENCE Cal. Cliffs, EOP's 194001A102 ...(KA'S) ANSWER 4.09 (3.00) . No, (only one pump in each loop should be tripped). No, (pressure decrease to 1300 psia). Yes [0.5 each] . FALSE FALSE FALSE [0.5 each] REFERENCE Cal. Cliffs, EOP-0, P. 6; EOP-8, pp. 4-5 003000SG07 ...(KA'S) ANSWER 4.10 (1.00) /T S - Steam Generator Level A"$CETTemperature [0.5 each] ew nas hi(mmh (qtan.AfCVth
. -- - . . , , ,, ._
. .-
. . PROCEDURES'-' NORMAL. ABNORMAL, EMERGENCY AND PAGE 14.
- RADIOLOGICAL CONTROL
.., . ANSWERS -- CALVERT CLIFFS -87/04/21-JAGGAR, . REFERENCE ' Col. Cliffs, EOP-3, p. 13 194001A102 ...(KA'S)
ANSWER 4.11 (1.50) '1DPM pW inches 0.5 each] REFERENCE Cal.-Cliffs, OP-2, P. 5 001050SG,* ...(KA'S) ANSWER 4.12 (1.50) BAST -> Boric Acid Pump -> CVC-514 (Boric acid pumps to Chg. pump suction) -> Chg. pump suctio [1.0) . Approx. 5 mi [0.5)
~ REFERENCE Cal. Cliffs, OI-2B, PP. 21-22 000024AP01 000024SG07 ...(KA'S)
s S }}