IR 05000320/1985017
| ML20136D724 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/12/1985 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20136D689 | List: |
| References | |
| 50-320-85-17, NUDOCS 8511210354 | |
| Download: ML20136D724 (68) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 1 OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 50-320/85-17 (OL)
FACILITY DOCKET NO. 50-320 FACILITY LICENSE NO. DRP-73 LICENSEE: GPU Nuclear Corporation Post Office Box 480 Middletown, Pennsylvania 17057 FACILITY:
Three Mile Island Unit 2 EXAMINATION DATES: August 13 and 14, 1985 October 18, 21, and 22, 1985 CHIEF EXAMINER:
4.d b
//~ k-II Noel F. Dudley
Date Lead Reactor Engi er (Examiner)
REVIEWED BY:
k II/
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Robert M. Kel'er,~ Chief Date Projects Section 1C i
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APPROVED BY:
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Ha'rr7't.'/Kiyter, Chief
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Projects Bra'rtch No.1 SUMMARY: One Reactor Operator (RO) candidate and six limited Fuel Handling l
Senior Reactor Operator (FHSRO) candidates were examined. One R0 and five l
FHSRO licenses were issued. One FHSRO candidate failed the oral portion of l
his examination.
Significant problems were identified with the licensee l
approved defueling procedures with regards to the candidates' ability to perform evolutions in verbatim compliance with the existing procedures.
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.e REPORT DETAILS TYPE OF EXAMS:
Replacement X
EXAM RESULTS:
R0 l
Fuel Handler l
l Pass / Fail l
Pass / Fail l
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l Written Exam i 1/0 l
6/0 l
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i Oral Exam i
1/0 l
5/1 l
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1/0 l
5/1 (
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. CHIEF EXAMINER AT-SITE:
.N. Dudley
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Summary of generic strengths or deficiencies noted on oral exams:
FHSRO candidates were knowledgable of how to conduct defueling evolutions, but had difficulty following the procedures verbatim. All procedures were undergoing major revision prior to submittal to the NRC for final approval.
FHSRO candidates did not possess detailed knowledge of defueling system equipment, including type of motors, type and operation of motor breaks, and hydraulic and electrical control panels.
2.
Summary of generic strengths or deficiencies noted from grading of written exams:
FHSR0 candidates were unfamiliar with the Reactor Building Sump Recirculation System and the requirement for its used if the reactor vessel develope a major leak.
FHSRO candidates were unable to identify all signatures required for approval of a Unit Work Instruction (UWI).
3.
Personnel Present at Exit Interview:
Held August 14, 1985 NRC Personnel N. Dudley Lead Reactor Engineer (Examiner)
R. Cook Senior Resident Inspector Facility Personnel A. Miller Manager Plant Operations B. Leonard Operator Training Manager R. Maag Supervisor Licensed Operator Training R. Wells Licensing Engineer 4.
Summary of NRC Comments made at exit interview:
The oral portion of the R0 examination was a clear pass.
The oral portion of the FHSRO examinations will be administered after all FHSRO candidates have completed all on-the-job training requirements.
The NRC will maintain a continual involvement in the requalification program with respect to adequate coverage of defueling equipment and procedures.
5.
Personnel Present at Exit Interview held October 22, 1985.
NRC Personnel N. Dudley Lead Reactor Engineer (Examiner)
R. Cook Senior Resident Inspector
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Facility Personnel F. Perry Acting, Operator Training Manager R. Maag Supervisor Licensed Operator Training J. Auger Licensing Engineer 6.
Summary of NRC Comments made at Exit Interview:
The FHSRO candidates had problems with performing defueling evolutions in strict compliance with procedures. This may have been a result of the inadequacy of the procedures or the candidates' lack of dependance on the procedures during training evolutions.
The FHSR0 candidates did not exhibit the detailed knowledge of equipment that would be expected from SRO candidates at operating facilities.
FHSRO candidates, in general, understood and were able to explain the defueling administrative organiza-tion even though the organization is complex in terms of delegation of responsibility and authority.
It was noted that the housekeeping in the area of the fuel pool was unacceptable. Also, it was noted that some electrical lighting panels did not contain up-to-date controlled listingseof installed breakers and load,
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ANSWER NO.
CHANGE REASON 1.09 ADD "or yes with supporting Count rate would calculation."
theoretically increase by small amount.
1.10 a.2.
Change "133 kw" to "100 kw".
Corrects mathematical error.
2.06 Change answer to Four types of filters in
" Roll, Moveable Fiberglass; exhaust train from Reactor
.3 Micron Glass Fiber,
' Building.
Absolute Filter; Charcoal, Particulate;.3 Micron Glass Fiber, Absolute Filter."
4.03 Change to " Radiation area, Modified inaccordance l
5 mr/hr or 100 mr over five with facility procedures.
days (10 CFR 20) or 2.5 mr/hr (admin) RWP control; High Radiation Area, 100 mr/hr, RWP control and dose rate instrument; Locked High Radiation Area, 1000 mrem /hr, RWP control and Locked."
4.03 Ref.
Change to "9200-ADM-4110.01 Supplies facility reference, p.2, El-1; 9200-ADM-4110.06, p.2."
4.04 ADD, "3. Wait 10 minutes prior Incorporates additional to entries."
precaution for entering Halon filled room.
5.01 a Delete "well below 0.5" and The magnatude of the drop add "(resonance absorption is unknown. Provides increases)"
additional information.
5.07 a Change " lower" to " increased".
Provides correct change in gas pressure for higher flow rate.
5.07 b Add "or as is if assume air The bubbler tube does not is trapped or low if assume have an outlet valve.
obstruction is at regulator."
5.07 c Change to "no change since Corrects for actual response mass above bubbler tube would of level system to temper-remain constant."
ature change.
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-6-O ANSWER NO.
CHANGE REASON 5.09 d Add " covered by water".
Adds another condition which is used to prevent a pyrophoric reaction.
5.09 Ref.
Add "Phyrophoric, 12.2.01.170".
References lesson plan which deals directly with pyrophoric reactions.
7.01 a Add " Filter Canister AP."
Provides second means of preventing overloading a canister.
7.8 a Change to " Radiation dose from Specific limiting organ gaseous release (H3 Kr'') [0.9]" dose not required.
7.9 c Add "all shields installed".
Provides another require-ment for removal of canister from alternate part.
8.07 Add " authorized by SR0 and Recently issued temporary controlled as lifted leads change notice defined or jumpers",
procedure.
8.07 Ref.
Add "TCM to 4211-0PS-3252.1".
Provide recent TCM.
8.12 b Add "and responsible Supervisor is also supervisor".
responsible for signing UWI's for approval.
Attachments: Written Examination and Answer Key RO)
Written Examination and Answer Key SRO)
Facility Comments
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NUCL EAR REGUL ATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
THI-2
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REACTOR TYPE:
PHR-81W177
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DATE ADMINISTERE0! 05/08/13
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EXAMINERI DUDLEY
...............___._____
APPLICANT:
,__________ ______.....,
INSTRUCTIONS TO APPLICANT!
...... _ _ _. _. _ _. _ _.... _. _
Use separate paper for the anteers.
Write answers on one side only.
Staplo question shoot on top of the ansuer shoots.
Points for each question are indicated in parentheses after the question. The pcssing grade requires at least 70% in each catocory and a final grado of at Icast 80%.
Examination papers will be picked up six (6)
hours after the examination starts.
% OF CATEGORY
% OF APPLICANT'S CATEGORY VALUE TOTAL SCORF VALUE CATEGORY
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25.00 25.00 1.
PRINCIPL ES OF NUCL EAR POWER
.... _ _ _.. _. _
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llf AT 1RANSTER AND FL U3 D FLOW 25l00..__...I_0 25 0 2.
PLANT DESIGN INCLUDING SAFF1Y
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AND EMERGENCY SYSTEMS 25 00
. 2....
25 00
__....._ 3.
INSTRUMENTS AND CONTROLS
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4.
PROCEDURES - NORMALr ADNORMAL,
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EMERGENCY AND RADIOLOGICAL
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CONIROL 100.00 100.00 TOTALS
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FINAL GRADE _____.
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All work done on this examination is my own. I have neither giv0n nor received aid.
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
--- iREER559EARICs-sEAi isAnsFEs As5 FE0i5 FE6s
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QUESTION 1.01 (1.50)
Explain the basic operation of an eductor or jet pump.
QUESTION 1.02 (2.00)
a. List two causes of waterhammer.
(0.8)
b. Give two examples of how waterhammer can be minimized by the operator.
(1.2)
QUESTION 1.03 (2.00)
a.
How is heat being produced in the THI-2 reactor core ?
(1.5)
(Explain in detail)
b. What form of energy is the heat in the reactor core ?
(Choose the correct answer)
.1. Potential energy 2. Kinetic energy 3. Internal energy 4.
Mechanical work (0 5)
QUESTION 1.04 (2.50)
Due to a source range increase from 2 cps to 10 cps, the TMI-2 procedure ' Unanticipated Neutron Increase and/or Boron Dilution'
requires as follow up action a 1/m plot.
O.
Explain why 1/m is plotted instead of m.
(1.5)
b. What information is obtained from the 1/m plot ?
(1.0)
(mauxx CATEGORY 01 CONTINUED ON NEXT PAGE ummum)
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PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
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____________________________________________
GUESTION 1.05 (2.40)
Identify if the following conditions are subcooled, saturated, or cuperheated. (include the number of degrees if subcooled or superheated).
TEMP.
PRESS. (psia)
o.
540 1000 b.
560 1500 c.
665 2000 d.
640 2400 QUESTION 1.06 (3.00)
o.
What is " pump runout' and why is it an undesirable condition?
(1 5)
b.
What are two reasons a centrifu3al pump should be started with the discharse piping filled and the discharge valve shut.
(1.5)
QUESTION 1.07 (2.00)
If a reactor core has an initial count rate of 200 cps and a Keff of 0.8, what will be the expected count rate if 1% delta K/K of POSITIVE reactivity is added to the core?
Show your work.
QUESTION 1.08 (2.60)
Explain what THREE chemicals are added to the primary and the reason for addition of each.
QUESTION 1.09 (3.00)
o. Would the count rate on the source ranse detectors increase if the boron concentration in the primary was reduced to 3000 ppm?
Explain.
b. Would the count rate on the source range detectors increase if the primary coolant was removed from the core?
Explain.
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
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GUESTION 1 10 (4.00)
A pump has the following parameters:
speed (high):
8000 RPM Discharge head: 2200 PSIC Motor power:
800 Kw.
Flow:
600 CPM o. What would be the value of each parameter, if the pump is shifted to slow speed (4000 RPM) ?
(3.0)
b. How does the temperature of the fluid (water) being pumped affect the power required by the pump motor ?
(1.0)
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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
QUESTION 2.01 (2.00)
TMI-2 is required to have 2 chlorine detection systems operable.
Where do these systems measure or sense chlorine?
OUESTION 2.02 (2.00)
If a fire should start (and alarm) in the RB purse filter, how would the fire be extinguished ?
(2.0)
GUESTION 2.03 (4.00)
0 1. Explain the operation of a wet pipe sprinkler system.
(1.0)
2. List three areas protected by wet pipe systems.
(1.0)
b.1. Explain the operation of a deluse system (1.0)
2. List three areas protected by deluse systems.
(1.0)
GUESTION 2.04 (2.00)
When workinS on electrical equipment, ie racking breakers in and out, the potential for a flash and serious eye injury exists.
WHAT 'special'
equipment is now beins employed to protect a workers eyes and WHEN is it used?
QUESTION 2.05 (2.50)
The Emergency Diesels and Auxiliaries, Operating Procedure, 2104-6 2, precaution and limitations state "The diesel Generator shall NOT be cperated unloaded for extended periods of time...
Starting the enSine to warm it up or to verify operability must be followed by at leas.t 1/2 hour of operation at full load."
WHAT is the purpose of this precaution and explain why the problem cccurs?
(mmmmm CATEGORY 02 CONTINUED ON NEXT PAGE mammm)
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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
GUESTION 2 06 (2.00)
The reactor building purge exhaust system filters the air flow thru four filter banks. Briefly explain the types of filters used in each bank.
(4 9 0.5 ea.)
GUESTION 2.07 (1.50)
Briefly explain how (flow path) the SPC system may be used to increase reactor vessel water level per Proc. 2104.10.2, Primary Plant Operations in Drain Down Condition.
QUESTION 2.08 (2.00)
Match the tanks / sumps with their capacity!
o. Neutralizer Tank 1.
82,286 sals b. R.C.
Bleed Tank 2.
20,040 gals c. R.C. Drain Tank 3.
11,071 gals d.
Aux Building Sump 4.
9,646 gals o. Misc. Waste Holdup Tank 5. 7,240 Sals 6.
3,215 gals 7.
2,660 gals B.
359 gals (5 0 0.4 ea.)
GUESTION 2.09 (2.50)
Explain the differences in ion exchange methods for the two types o't resins used in the submerged domineralizer system.
QUESTION 2.10 (3.00)
What are FOUR of the five design basis for the Linear Recombiner cnd Vacuum Outgas System?
(mmmmm CATEGORY 02 CONTINUED ON NEXT PAGE mummm)
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PLANT DESIGN INCLUDING SAFETY AND ENERGENCY SYSTEMS PAGE
QUESTION 2.11 (1.50)
Name three (3) sources of electricity to the 230 KV substation et TMI.
(3 9 0.5 es.)
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INSTRUMENTS AND CONTROLS PAGE B
____________________________
GUESTION 3.01 (.60)
Which ONE of the followins statements is true ?
A. The DHCCW pumps will trip if suction pressure is less than 2 psis.
9. The DHR pumps will trip if DHCCW pressure is less than 29 psis.
C. The DHCCW pumps will trip if cooling water to the pump is lost.
D. The DHCCW pumps in a train will trip if the associated DHCCW sytem surge tank level is low.
QUESTION 3.02 (.60)
Which one of the followins sump pumps does not have a low suction pressure trip ?
A. WDL-P-4A/B (AUX BLDG SUMP)
B. WDL-P-6A/B (MISC WASTE TANK)
C. WOL-P-8A/B (NEUT TANK)
D. WDL-P-15A/B (CONTAM. DRAIN TANK)
GUESTION 3.03 (1.50)
State the alarms and action that would occur in the DHCCW cystem as the surse tank level decreases from 50' to 30'.
QUESTION 3.04 (1.00)
Why are the reactor building purse supply heaters secured ct least five minutes before terminating air flow ?
(1.0)
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INSTRUMENTS AND CONTROLS PAGE
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GUESTION 3.05 (2.00)
While performing a diesel generator load test procedure the cperator needs to ' synchronize" the Generator with the grid.
o. If the synchroscope is movin3 counter-clockwise, what parameter must the operator adjust (include increase or decrease) to correctly syncronize the diesel generator ?
(1.0)
b. The operator adjusts the diesel so the synchroscope is steady at the '12 o' clock' position. Explain why he SHOULD or SHOULD NOT close the diesel generator output breaker.
(1.0)
GUESTION 3.06 (2 50)
The reactor core temperature is measured by incore thermocouples.
Explain how a thermocouple works AND three places where the incore
thermocouples may be read for Unit II.
'
QUESTION 3.07 (2.00)
When and why would an operator use the disconnect switch in the Zone Detection Panels ?
GUESTION 3.08 (2.00)
What measurements or indications are used to assure each of the following conditions?
a. The leakage from the containment will be limited for off-site dose considerations.
b. Baron will remain in solution in the Reactor Coolant System.
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c. Th'e core will remain suberitical under all credible conditions l
which may exist during the long term cooling mode.
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INSTRUMENTS AND CONTROLS PAGE
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QUESTION 3.09 (3.00)
For each of the following parameters provide two types of detectors which can measure each parameter.
a.
Pressure b.
Flow c.
Level d.
Temperature e.
Neutron flux QUESTION 3.10 (3.40)
o. The manual bypass switch on the vital 120 VAC inverters have three positions. What is the input to each of the three positions ?
(3 0 0.8 ea.)
b. Which position of the manual bypass switch is desired (explain why) ?
(1.0)
DUESTION 3.11 (3.00)
Draw and explain the operation of the source range instrumentation t
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system.
(3.0)
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OUESTION 3.12 (3.40)
The prefilter and deminerali=ers in the EPICORE-II system use two tethods to measure water level. Enplain how each of the two systems l
functions.
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4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
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QUESTION 4.01 (.60)
,
A chronic whole-body radiation dose ist (Choose the correct answer)
A.
the acute dose multiplied times 2.5.
B. a dose received over a extended period of time.
C.
the acute dose multiplied times the appropriate quality factor.
D.
the T-eff of I-131.
QUESTION 4.02 (2.00)
10 CFR 20 has radiation limits fort A.
Whole body dose B.
Extremity dose C. Skin dose For each of the below, indicate which of the 10 CFR 20 limits would apply.
a. Beta radiation exposure to the eyes b. Gamma radiation exposure to the feet c. Neutron radiation exposure to the forearm d. Beta radiation exposure to the chest e.
Gamma radiation exposure to the less (5 9 0.4 ea.)
GUESTION 4.03 (2.10)
List and describe the three basic types of radiation areas.
Include' the access control measures and the long and short term dose limitations for each type.
QUESTION 4.04 (2.50)
What are the TWO requirements for entering a halon protected crea after the halon system has extiquished a fire?
Explain the reason for these requirements.
(mmmmm CATEGORY 04 CONTINUED ON NEXT PAGE mamma)
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4.
PROCEDUPES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
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QUESTION 4.05 (1.50)
l c. If the waste gas discharge flow rate is restricted to 50 scfe,
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where should the h13h flow trip setpoint pot be adjusted?
Figure 1 is provided.
b. If the waste gas discharge flow rate is not specified, where
should the high flow trip setpoint,'ot be adjusted?
l GUESTION 4.06 (2.00)
i If durinS defueling operations NI-1 causes an alarm on Panel 8e
'NI-1/NI-2 High Count', and has increased from 2 cps to 5 cps, what actions, if any, should be taken?
l QUESTION 4.07 (2.00)
c. If the containment purse system was in operation, how would containment pressure be equalized prior to opening both inner and outer air lock doors inorder to move the work platform into containment?
(1.2)
b. How could the control room operator determine how many people were in the containment?
(0.8)
GUESTION 4.08 (3.00)
What actions, if any, should an operator take prior to leavin3 the Main Control Room if he is ordered to evacuate by the Senior Reactor Operator due to heavy smoke.
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QUESTION 4 09 (2.80)
Provide FOUR routine evolutions or procedures which are conducted by operation's personnel to identify possible dilution of the ester in the reactor vessel.
(mmmmm CATEGORY 04 CONTINUED ON NEXT PAGE mammm)
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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
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GUESTION 4.10 (3.00)
The first immediate manual step for leakage in the SDS, Submerged Ion Exchanger System, is to stop the appropriate feed pump.
NNAT are the six (6) pumps that this step is refering to?
CName of the pump not the number.]
[6 9 0.5 ea]
(3.0)
QUESTION 4.11 (3.50)
The following questions apply to the Station Blackout Emergency Procedure when both diesels start, 2202-2.1:
o.
The first immediate manual action. step states " Verify the automatic action
'.
WHAT are these automatic action
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steps? CAn action step may have more than one action.3 (2.5)
b.
WHAT are the remaining immediate manual action steps?
[An action step may have more than one action.]
(1.0)
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
--- isERR55isisics-REAi isissFER AR5 FE5i5 FE5s
____________________________________________
ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 1.01 (1.50)
Driving flow at high velocity thru the nozzle developes a low pressure area in the ' throat' of the jet pump.[0.53 This low pressure causes suction water to enter the jet pump. The resultant mixture is at a ' medium velocity'.CO.53 The combined flow enters the diffuser which converts the velocity head back into pressure head.00.53 REFERENCE TMI-2 Nuclear Energy Training, Pumps and Fluid Flow, NET 4-6, sec. 6.3 ANSWER 1.02 (2.00)
o. Valve operation, opening or closing Pump starting or stopping Oscillation of auto control valves b. Slowly opening of valves between voided and full systems Proper venting of con.ponents Adequate level on tanks in systems where the tanks provide supply or surge function Proper use of steam traps and vents Proper sequencing of valves in pressurized systems
!
REFERENCE THI-2 Nuclear Energy Training, Thermodynamics, NET 4-2, ps. 2.1-4,5 i
'
ANSWER 1.03 (2.00)
o. As fission fragments decay by alpha, beta, and/or samma radioactive decay the fuel (and core internals) absorb the radiation and convert l
it to heat energy.
(1.5)
I b. 3. Internal energy (0.5)
i REFERENCE THI-2 Nuclear Energy Training, Shutdown Cooling Rerquirements, 3.14.3 TMI-2 Nuclear Energy Training, Thermodynamics, NET 4-2, pg. 2.1-2,2.2-1 l
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
---" FREER 559EARi E-sEAi iEAREFEE As5 FE0i5 FE5s C
...-----------------------------------------
ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 1.04 (2.50)
o. m = count rate / count rate initial. CO.53 is the symbol for soberitical multiplication and continues to m
increase toward infinity as criticality is approached. [0.53 1/m approaches zero and is easier to analyse on a graph. [0.53 b.
The time at which criticality will be reached. [1.03 (EOP requires 1/H to be plotted to time.)
REFERENCE E0P 2202-1.2, p 1 ANSWER 1.05 (2.40)
a.
subcooled,EO.33 4.6 F CO.33 b. subcooled,00.33 36 F
[0.33 c.
superheated,EO.33 29 F E0.33 d.
subcooled,[0.33 22 F
[0.33 REFERENCE Thermodynamics, Fluid flow, and Heat Transfer for Nuclear Power Plants ANSWER 1.06 (3.00)
a.
Increase in pump flow due to loss of backpressure [0.53.
The increased flow causes the motor to draw more current and possibly damage the motor winding [1.03.
(1.5)
b.
Water hammer [0.753 and excessive starting current E0.753 (1.5)
REFERENCE THI-2 NET 4-6 ps 6.4-5 & 6.4-6
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
--- isEER557sisiEs-sEAi iEARiFEE As5 FEUi5 FE5s
____________________________________________
ANSWERS -- THI-2 '
-85/08/13-DUDLEY ANSWER 1.07 (2.00)
p(1)= k(1) -1 / k(1)
'EO.33
= 0.8
- 1 / 0.8
[0.13
= -0.25 E0.13 p(2)= p(1) + 0.01 E0.23
= -0.25 + 0.01 E0.13
= -0.24
[0.13 k(2)= 1/ C1 - p(2)]4 E0.33
= 1/ E1 (-0.24)3'
E0.13
-
= 0.806 c(2)= c(1) [1-k(1)/1-k(2)3 E0.53
= 200 El-0.8/1-0.806]
E0.13
= 206 cps E0.13
, REFERENCE
'
L.P.
11.2.01.179 Subcritical Multiplication, p 11 ANSWER 1.08 (2.60)
Hydrazine EO.43 to control oxygen and oxidation of components. [0.463 Boron E0.43 for reactivity control. [0.463 NaOH E0.43 for PH control to reduce oxidation rates. [0.463 REFERENCE L.P.
12.2.01.088 Standby Pressure Control, p 23 ANSWER 1.09 (3.00)
c. No. [0.53 A reduction of boron from 5000 ppm to 3000 ppm would at sigriificantly increase the neutron leakage from the core. [1.03 or yrs s a, us w.e r... -.. u.,;rsc.v 0
b.
es. [0.53 As voids form the fast non-leakage probability decreases and more neutrons will reach the detectors.
E1.03 REFERENCE L.P.
11.2.01.124 Reactivity Coefficients, p 7,9
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
--- isEEs557aARiEs-sEAi iEAssFEE is5 FE6i5 FE5E
____________________________________________
ANSWERS -- TMI-2-85/08/13-DUDLEY ANSWER 1.10 (4.00)
0 1. Discharge head: 5p,0 PSIG (2200/(8000/4000)^2)
(1.0)
2. Motor Power:
1h Kw (800/(8000/4000)^3)
(1.0)
3. Flow:
300 GPM (600/(8000/4000))
(1.0)
b. As the temperature of the water decreases, fluid density increases [0.53 requiring pump motor power to increase.[0.53 (opposite is also true)
(1.0)
REFERENCE THI-2 Nuclear Energy Training, Pumps and Fluid Flow, NET 4-6, pg 6.2-1
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2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
ANSWERS -- TMI-2-85/08/13-DUDLEY ANSWER 2.01 (2.00)
.o.
Air intake tunnel (1.0)
-b.
Control room air supply duct.
(1.0)
REFERENCE THI-2 Recovery mode Tech Specs, pg. 3.3-7 i
ANSWER 2.02 (2.00)
By MPS (modified purge sys.) isolation (shutdown) and manual operation FS-V-422B or FS-V-423B (manual deluge isol. valves)
REFERENCE THI-2 Proc. 2104-4.91, 2-2.9 & 3.1.1.11
,
.
ANSWER 2.03 (4.00)
,
!
a.1. In a wet pipe system the header is full of water and pressurized.
'
In the event of a fire the local sprinkler head breaks (melts)
,
- .
releasing water on the fire.
(1.0)
2.a. Diesel driven fire pump room (0.25)
b. Diesel generator rooms (2 systems)
(0.50)
c.
Turbine building (286/305 ele.)(2 systems)
(0.50)
b.1._In the deluge system, the header is dry, and has open no::les. The fire is detected by heat sensors, which send a signal to open the deluge valve and flood the area.
(1.0)
2.
There are 19 delu3e systems. Use list in 2104-6.1 rev 16, pg. 13 & 14.
(5 9 0.25 ea.)
REFERENCE
'
THI-2 Proc. 2104-6.1 rev. 16, pg 12, 13 & 14.
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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
ANSWERS -- TMI-2-85/08/13-DUDLEY ANSWER 2.04 (2.00)
Monogoggles [0.53 with ultraviolet inhibitor lenses [0.53 shall be worn when:
1. Racking 6900, 4160 and 480 volt breakers in and out [0.53 2. Openin3 or closing a circuit >/= 480 volts AC or 125 volts DC where the circuit opening device (contact switch blades, etc)
is visible. CO.53 REFERENCE THI Inter-Office Memorandum 2-84-5, May 17, 1984, Eye Protection ANSWER 2.05 (2.50)
To Prevent overheating of the exhaust system. [0.53 Unloaded operation causes carbon deposits and unburned lobe oil accumulation in the exhaust system [1.03 which leads to exhaust system overheating as the exarbon and lube oil burn off when loaded operation is resumed C1.03.
(2.5)
REFERENCE THI-2 Operating Procedure, Emergency Diesels and Auxiliaries 2104-6.2' P3 5 i
ANSWER 2.06 (2.00)
C;H-F-1-9 A/94 Roll, Moveable fiber 3 ags.,,,_.e e,,,
AH-F-20A/Be-
.3 mieren sless fiber, pa r t ic ul a t e, csetcott.
e AH-F=31A/ B4
.3 micron glass fiber, absolute filter.
(3 0 0.66 ea.)
REFERENCE THI-2 Lesson Plan Vol II, 12.2.01.045, R. B. Vent. and Purse, pg. 8 ANSWER 2.07 (1.50)
Water is pumped from SPC-T-4 with SPC-P-1A/1B thru system valves injectin3 into the RCS thru MUV-16A/B/C/D REFERENCE THI-2 Proc. 2104-10.2, Primary Plant OPS. in Drain Down Condition.
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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
_______________________________________________________
ANSWERS -- TMI-2-85/08/13-DUDLEY ANSWER 2 08 (2.00)
O.
4 (9,646)
b.
1 (82,286)
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d.
3 (11,071)
o. 2 (20:040)
(5 9 0.3 ea.)
REFERENCE THI-2 Lesson Plan Vol III 12.2.01.094, Radwaste Disposale Misc. Liquid, pg. 14 ANSWER 2.09 (2.50)
Organic resin E0.53 uses an ion exchange that removes ions which have hi3her affinity for sites on resin beads. [0.753 Inorganic resin CO.53 in addition to ion exchange uses uniform crystalline framework which acts like a sieve. CO.353 Resin will not degrade in high gamma flux. [0.43 REFERENCE L.P. SDS Overview and Chemistry, p 16, 19 ANSWER 2.10 (3.00)
1. Remove vessel water (enhance recombiner catalyst)
2.
Sample vessel atmosphere 3.
Inerting of vessel (154 of nitrogen or arson)
4. Add catalyst to SDS vessel vent 5. Provide sufficient catalyst to recombine REFERENCE L.P.
12.2.01.129 Linear Recombiner and Vacuum Outgas System, p5 ANSWER 2.11 (1.50)
1.
Unit i generator output.
2.
500 KV substation 3. Middletown Junction line 4. Jackson line (any 3 0 0.5 ea.)
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INSTRUMENTS AND CONTROLS PAGE
____________________________
ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 3.01 (.60)
CER Low coolins water flow to the DHCCW pump motor will trip the pump.
REFERENCE TMI-2 Lesson Plan Vol 1,
DHCCW, ps. 7.0 ANSWER 3.02 (.60)
C. Neut Tank, WDL-P-8A/B REFERENCE TMI-2 Lesson Plan, 12.2.01.094, Radwaste Disposal, Misc Liq, ps A-3 ANSWER 3.03 (1.50)
Makeup valve (DW-V54 A/B) opens (37')
[0.753 Low level alarm (setpoint: CAF)
[0.753 REFERENCE TMI-2 Lesson Plan Vol.
1, DHCCW ANSWER 3.04 (1.00)
To prevent trippins of the manual thermal cutouts located on the heaters.
(1.0)
REFERENCE TMI-2 Lesson Plan Vol II, 12.2.01.045, R.
B.. Vent & Purse sys Part of proc. 2104-4.01
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INSTRUMENTS AND CONTROLS PAGE
____________________________
ANSWERS -- TMI-2-85/08/13-DUDLEY ANSWER 3.05 (2.00)
o. The operator must INCREASE DIESEL GENERATOR FREQUENCY.
(1.0)
b.-The operator SHOULD NOT close the breaker because the frequency of the geneator and the grid are matched and the diesel would not pick up any load. It would be possible to trip the diesel on reverse power (or motor the generator)
(1.0)
REFERENCE THI-2 Question Bank & Proc. 2104-6.2 rev. 24, pg. 23, 4.3.7 ANSWER 3.06 (2.50)
Thermocouples are formed by the connecting of two different metals.
The ' Junction * of the metals will produce a small current flow proportional to the temperature of the metals. The amount of current flow is dependent upon the difference in temperature of the T/C to the reference T/C which is held at a constant temp.
(1.0)
Locations: cable room, Computer, Mimic panel (3 9 0.5 ea.)
REFERENCE NET 7-2, Instrumentation systems part 2, pg 2.1-4.
ANSWER 3.07 (2.00)
The disconnect switch is used to bypass interlocks and alarms [1.03 to allow restart of fans to clear smoke after the fire is out.[1.03 (2.0)
Or
,
When we.1 ding or water blasting is in progress in area. E1.03 Prevent inadvertant actuation due to smoke or suspended particals. E1.03 (2.0)
REFERENCE 4210-OPS-381'O.01 Fire Protection System, p 37
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INSTRUMENTS AND CONTROLS PAGE
____________________________
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ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 3.08 (2.00)
o. RB pressure (velometer at opening)
b. RB temperature (RCS maximum boron concentration)
c. RCS Boron concentration CO.66 each]
REFERENCE THI-2 Tech Spec Recovery Mode, p B 3/4 1-1, B 3/4 6-1 ANSWER 3.09 (3.00)
o. Bourdon tube, diaphragm, bellows b. D/P cell, venturi, rotometer, hot wire velometer c. D/P cell, float, gauge glass, bubbler d. T/C, RTD, Thermometer
,
e. Ion Chamber, GM tube, BF3 detector (Rem ball)
C10 0 0.3 each3 (Other instruments and detectors will be acceptable with plant ref.)
REFERENCE-TMI-2 Nuclear Energy Training, Instrumentation Systems Part 1, NET 7-1, PS 1.1-1 & sec. 1.3 and 1.4.
THI-2 Nuclear Energy Training, Instrumentation Systems Part 2, NET 7-2, pg 2.1-3, 2.1-4 ANSWER 3.10 (3.40)
0 1.
inverter output 2.
static transfer switch output (normally the inverter, Alt. ' alt. source')
3. Alternate source (120 VAC reg. transformer)
(3 0 0.8 ea.)
b.
static transfer switch output, aligns system for auto transfer to alt. source on batt/ inverter problem.
(1.0)
REFERENCE THI-2 Lesson Plans Vol.
2, Vital AC Dist, 12.2.01.022, pg 9 l
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3.
INSTRUMENTS AND CONTROLS PAGE
____________________________
ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 3.11 (3.00)
Looking for good block diagram, may have to CAF REFERENCE TMI-2 NET Nuclear Inst., NET 7-3, sec 3, pg 3.3-1 ANSWER 3.12 (3.40)
o. BUBBLER SYSTEM CO.83 calibrated to indicate level based on 'back pressure' required to cause ' air bubble" flow. Indication is from 0 to 100%
E0.93 b. CONOUCTIVITY PROBE [0.83 Indicates water level due to the current (small) as water level covers probe. Indication is lights *
20%-amber, 40 to 60 % blue, 80% red. [0.93 REFERENCE THI-2 Lesson Plans 12.2.01.023, EPICORE II
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4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
~~~~
RA5i5L5GIEAE E5 TRUL
~~~~~~~~~~~~~~~~~~~~~~~~
____________________
CNSWERS -- THI-2-85/08/13-DUDLEY ANSWER 4.01 (.60)
Be& A dose received over an extended period of time.
REFERENCE l
THI-2 Nuclear Energy Training, Biological Effects of Radiation,
.
'
NET 5-1' PS 1.4-1 ANSWER 4.02 (2.00)
c.
A b.
B c.
B d.
C o.
A (5 9 0.4 ea.)
REFERENCE THI-2 Nuclear Energy Training, Radiation Units Guides and Limits, NET 5-2, pg. 2.2-1,2 ANSWER 4.03 (2.10)
c. Unrestrdeted area E0.33 uncontrolled access, < 2mr/hr, < 100mr/wk, < 500 mr/yr
[0.33 No contro b iethod required.
[0.13 b. Restricted ar e'a CO.33 s
Restricted access, radiation greater than above limits E0.33 Warning sign is p'osted.
[0.13 c.
Airborne area
[0.33 Radioactive material i the air exceeding (plus 25% of) 10 CFR 20 limits.
[0.33 Warning si3n is posted.
[0.13 REFERENCE TMI-2 Nuclear Energy Training, Radiation Qnits Guides and Limits, NET 5-2, pg 2.3-1 a, $ t) :?, n ~,.' AdM [C. ]]
[ 'j/ l; n Ill u,, m 1 2, (ts* (,'Gc)
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4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
~~~~
RA656E665CAE~66HT66L ~~~~~~~~~~~~~~~~~~~~~~~~
____________________
ANSWERS -- THI-2-85/08/13-DUDLEY ANSWER 4.04 (2.50)
Requirements:
1. " Suitable" breathing apparatus will be used
[0.753 2. The area has been cleared (vented) of all smoke and halon [0.753 3. s M r r. v..... n v.nu r: iWTA Y Reason: When halon is used to extinguish a fire it changes to a toxic state. [1.03 REFERENCE THI-2 Proc. 2104-6.1 rev. 16, pg.
7.0, 2.6.4 ANSWER 4.05 (1.50)
o. 2.4 [0.753 b. 6.4 (set point for flow rate of 100 scfm) [0.753 REFERENCE LP: 2104-4.3, Waste Gas Disposal System, p6 ANSWER 4.06 (2.00)
Confira detector reading. [0.43
Contact the Command Center and have all personnel evacuate the Reactor Building. [0.83 Secure IIF processing and restore RCS to steady state level control mode. [0. 8.7 REFERENCE E0P 2202-1.2 Unanticipated Neutron Increase and/or Boron Dilution, p 3
~
ANSWER 4.07 (2.00)
O. Shut off Reactor Building Purse Exhaust [0 63 Close supply dampers [0.63 b. Call the command center which maintians an access log. [0.83 REFERENCE 4210-OPS-3240.01 Reactor Building Entry, p 4,
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4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
~~~~
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____________________
C.NSWERS -- THI-2-85/08/13-DUDLEY ANSWER 4 08 (3.00)
Secure letdown C1.03 (by closing MU-V376)
Secure transfers involvins RCBT's [1.03 (Stop WDL-P-5A and B, close valves on panel 9 and place remote controls for WOL-V36A and B, and WDL-V167 in ' Local')
Notify SDS operator and verify DHCP-1 trips [1.03 REFERENCE 4210-EAP-1300.'05 Unit 2 Contol Room Evacuation ANSWER 4.09 (2 80)
Monitor reactor coolant level (hourly)
Monitor dilution sources (A0 checklist and low level alarms)
RCS mass balance (daily)
Equipment check list (daily)
[any 4 0 0.7 each3 REFERENCE Na:ards Analysis! Potential for Doron Dilution of RCS, Nov 1984, p 51-55 ANSWER 4.10 (3 00)
1. RB Jet Pump 2. RC Waste Transfer Pumps 3. IIF Processing Pumps 4. Misc Waste Transer Pumps 5. Neutrali:er Tank Pumps 6. Monitor Tank Pumps
[6 9 0 5 es]
(3.0)
REFERENCE THI-2 Emersency and Abnormal Procedure, 4210-EAP-3527.03, Leakage in the SDS Submersed Ion Exchan3er Sy5t'*, P9 3.0
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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
~~~~65656E665CAE"_66NTR6L'~~~~~~~~~~~~~~~~~~~~~~~
____________ _______
CNSWERS -- TMI-2-85/08/13-DUDLEY CMSWER 4.11 (3.50)
o. 1. Diesel Generators DF-X-1A and 1B start and energized the emergency buses.
2. NR-P-1A (18) and 1C (1D) will start.
3. NS-P-1A (1C) and 1B will start (if not in ' pull to lock')
4. Ventilation fans in the Control Room, Cable Room, Mechanical Equipment, River Water Pump House and Diesel Generator Buildin3 start.
5. If open/runnin3 for Processing, Dkt-P-1 and WDL-P-5A/B will stop and FCC-V-003 and WDL-V-40 will close.
[5 9 0.5 ea]
(2.5)
b.
1.
If reactor coolant processing weas in progress per 2104-10.2, then close MU-V-376, MU-V-10 and place WDL-P-5A/B in
' Pull to Lock'.
2. Restart the instrument air compressor per 2104-2.3.
[2 9 0.5 ea3 (1.0)
REFERENCE THI-2 Emergency Procedure, 2202-2 1, Station Blackout, pg i a 2
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5.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENGE EXAMINATION LIMITED TO FUEL HANDLING FACILITY!
THI-2
________________________.
REACTOR TYPEt PWR-B&W177
____________________.. _
DATE ADMINISTEREDI 05/08/13
.__..____________________
EXAMINER!
DUDLEY/RUSCITTO
_______________...__..__
APPLICANT!
_________________________
INSTRUCTIONS TO APPLICANT!
..... ________________...
Use separate paper for the answers.
Write answers on one side only.
Staple 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 the examination starts.
% OF CATEGORY
% OF APPLICANT'S CATEGORY VALUF TOTAL SCORE VALUE CATFGORY
__._____ _____.
......____.
________... ____.._________________........
20 00 25.00
________ 5.
THEORY OF NUCL EAR POWER PL ANT
.....___...._.
....____.._
OPERATION, FLUIDS, AND THERMODYNAMICS 20*00 25.00
.......
6.
PLANT SYSTEMS DESIGNe CONTROLe
....... ______
_________..
AND INSTRUMENTATION 20.00 25.00
..__...
7.
PROCEDURES - NORMALe ABNORMALe
________ ______
....... ___
EMERGENCY AND RADIOLOGICAL CONTROL
___I_0 25.00 20 0
..______ 8.
ADMINISTRATIVE PROCEDURESe
___ ______
___......_
CONDITIONS, AND LIMITATIONS 80.00 100.00 TOTALS
... ____...___
___________
_.._____
FINAL GRADE _________________%
All work done on this examination is my own. I have neither given nor received aid.
~~~~~~~~~~~~~~
5PPL5C55T 5~556U55URE I
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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
____
______..______.. ______________. ____
_....__
-___.
QUESTION 5.01 (2.00)
Answer the following concerning core reactivity!
a.
Briefly explain the effect of inadvertantly removing or displacing a major portion of the volume of water in the reactor vessel. C1.03 b.
What condition is ensured by maintaining a minimum boron concen-tration of 4350 PPM?
[1 03 GUESTION 5 02 (1.50)
Answer the following concerning hydrogen generation and control!
a.
How could hydrogen be generated inside a sealed fuel canister? CO.53 b.
Provide two reasons why hydrogen production inside a sealed canister is a concern. C1 03 OUESTION 5 03 (1.75)
Answer the following concerning the installed neutron sources!
a.
Identify by axial and radial location where the americium beryllium sources were located in the core. C1.03 b.
Why would their present location be of significance during defuelin3?
C H+3 0 15 QUESTION 5.04 (1.50)
Why are pressure switches used instead of level switches for measuring hydraulic control unit resevoir level?
QUESTION 5 05 (2.25)
What changer if any, would you notice in weight reading on an opene empty canister as it is lowered fully into the water.
Briefly explain.
(mumum CATECORY 05 CONTINUED ON NEXT PAGE samma)
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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
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......_______.
QUESTION 5.06 (3.00)
List FOUR parameters or design features that must be considered to ensure that Keff of any canister will never exceed 0.95.
QUESTION 5.07 (3.00)
Explain how and why the following would effect the Reactor Vessel level indication!
a. Excessive air flow to detector b. Air outlet valve fully obstructed c. Decrease in RCS temperature by 10 F OUESTION 5.08 (2.00)
If a reactor core has an initial count rate of 200 cps and a Keff of 0.8, what will be the expected count rate if 1% delta K/K of POSITIVE reactivity is added to the core?
Show your work.
QUESTION 5 09 (3.00)
Answer the following concerning pyrophoric reactionst a.
What is a pyrophoric material? [0.73 b.
What pyrophoric material may exist in the core? E0.73 c.
During what TWO operations would the possibility of a pyrophoric reaction eHist? [0.83 l
d.
What actions are taken to prevent a pyrophoric reaction? C0.8]
i (amman END OF CATEGORY 05 samma)
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PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
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GUESTION 6.01 (2.25)
Answer the following concerning the Canister Positioning System!
a.
Why can't a fuel canister be loaded in the uppermost position while a knockout canister may? [1.253 b.
Why must full canisters be removed from only the canister removal port? [1.03 GUESTION 6.02 (2.50)
Provide three independant means of monitoring Reactor Coolant System (RCS)
level.
Do not include alarms.
Indicate where each indication may be read and identify any instruments which require power.
QUESTION 6.03 (2.00)
Answer the following concerning the Debris Vacuum System a.
How does the inline flow meter on the inlet line to the knockout canister measure flow? [1.0]
b.
What two conditions could cause a knockout canister high differential
'
pressure? [1.0]
QUESTION 6.04 (2.00)
Answer the following concerning the Canister Handling Tools a.
What effect would a loss of air have on the fuel canister grapple?
[1.03 b.
How could a canister be released if the air cylinder were to fail?
[1.03 (ammma CATEGORY 06 CONTINUED ON NEXT PAGE mamma)
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QUESTION 6.05 (2.00)
Describe how each of the following canister handling trolley limits are established (what mechanism) and how, if at all, they may be overridden.
a.
Travel zones b.
Maximum travel limits QUESTION 6 06 (3.00)
Answer the following concerning the In-Vessel Dewatering System!
a.
While dewatering a fuel canister, pressure increases to 12 PSIG.
What does this indicate and how could the problem be verified? [1 53 b.
What will occur if pressure continues to increase? [0.75; c.
How do you know if dewatering is complete? [0.753 QUESTION 6 07 (3 00)
a. Explain how workers are protected from fission product gases released during initiskt dewatering of canisters in the Reactor Vessel.
b. Explain how workers are protected from fission product gases released during final dewatering of canisters in the Fuel Handling Building.
QUESTION 6.08 (3.25)
Answer the following concerning the Hydraulic Control System!
a.
Why is there a one gallon leakage limit from the resevcir? [0.753 b.
What SIX conditions will activate an alarm on the hydraulic power unit?
No setpoints are required. [2.03 c.
What will trip the hydraulic pump? [0.53
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(mmmmm END OF CATEGORY 06 mamma)
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QUESTION 7.01 (1.50)
Answer the following concerning canister handling and transport!
a.
How are the knockout and filter canisters prevented from being overloaded? [0.753 b.
How will the buildup of hydrogen inside the canisters during transfer be minimized? [0.753 QUESTION 7 02 (1.50)
What actions must be taken (in order of priority) if the platform fails to stop after the speed set knob is returned to zero and the keylock is turned off?
[1.53 QUESTION 7.03 (1.00)
Due to a source range increase from 2 ces to 10 cps, the TMI-2 procedure ' Unanticipated Neutron Increase and/or Boron Dilution'
requires as follow up action a 1/m plot.
o. Explain why 1/m is plotted instead of m.
b. What information is obtained from the 1/m plot?
OUESTION 7.04 (2.00)
When attempting to pick up a loaded canister from the Canister Support with the Canister Handling Trolley it is found that the trolley must be moved 2 inches north.
The Canister Hoist has lowered the shield to within 1 foot of the canister.
What actionse if any, should be taken?
l (samas CATEGORY 07 CONTINUED ON NEXT PAGE anums)
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QUESTION 7.05 (2.00)
How many weeks a quarter would a radiation worker be able to work without exceeding any FEDERAL limits for whole body exposure given the following assumptions?
Show your work.
- Operators spend 2/3 of the time over open slot
- Operators make 2 entries per day
- All entries last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- Operators work 6 days a week
- Dose rates for whole body exposure are!
Transit to and from work platform 10 aren Platform dose 7 mrem /hr Slot dose 17 mrem /hr GUESTION 7.06 (2.50)
What are three methods of minimi=ing the spread of radioactive contamination while conducting defueling activities in the Reactor Building?
QUESTION 7.07 (2.50)
What actions, if any, should be taken if incore tubes begin to fail and reactor vessel level begins to decrease?
OUESTION 7 08 (3.00)
a.
If a filter canister dropped on the dry portion of the refueling canal and released 100% of its contentse what would be the major potential offsite radiation ha:ard and would it exceed any federal exposure limits?
(1.5)
b. What immediate actions, if any, should be taken in the event of dropping a filter canister on the dry portion of the refueling canal?
(1.5)
(manum CATEGORY 07 CONTINUED ON NEXT PAGE mamma)
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QUESTION 7.09 (4.00)
What actions, if any, should be taken by the FHSRO if the following events occur while fuel handling evolutions such as pick and place and canister transfers are under way in the Reactor Building.
Consider each situation seperately and justify your answers.
a. The control room reports that reactor vessel level as read ori RC-LI-100 is 130'.
b. After taking the watch on the second shift a low pressure system accompanied by heavy rains moves through the Middletown area.
The control room reports that the Spent Fuel Pool level has increased 1' over the last hour.
c. While in the normal defueling configuration of the work platform a canister transfer is to be undertaken through the alternate l
canister removal port.
d. During a normal canister transfer radiation levels on the work platform are reported as 150 mren/hr.
(smann END OF CATEGORY 07 sassa)
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OUESTION 8.01 (.60)
Which one of the following personnel has the authority to require l
the FHERO to terminate a defueling evolution?
A.
Defueling Task Leader 8.
Coordination Center Supervisor C.
Radiological Controls Representative D.
Auxiliary Operator GUESTION 8.02 (.60)
How can the FHSRO check whether a person conducting a defue11n3 Procedure has received proper training through a formal job briefing?
(Choose the most correct answer.)
A. Check forms attached to the controlling Unit Work Instruction B. Contact the trainih3 department to verify training record C. Check the Coordination Center attendance / activity los D. Have person provide certification of training GUESTION 8 03 (.60)
Which one of the of the following personnel determine whether a formal job briefing is required prior to conducting a defueling evolution?
A. Manager of Training for Licensed Operators B. FHSRO C. Plant Operations Manager D. Defueling Operations Task Leader GUESTION 8.04 (.60)
If difficulties arise in the completion of an activitye who aust the FHSRO advise on the means by which he plans to correct the situation?
Choose the most correct response.
A.
Shift Supervisor 8.
Fuel Handling Engineer C.
Coordination Center Supervisor D.
Defueling Operations Task Leader (assan CATEGORY 08 CONTINUED ON NEXT PACE sassa)
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ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
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QUESTION 8.05 (.60)
Under which one of the following situations is the FHSRO NOT required to evacuate the Reactor Building?
A.
When directed to evacuate by the Coordination Center Supervisor 8.
Fire in the Reactor Building C.
Total loss of Reactor Building lighting D.
Total loss of communications with the Coordination Center GUESTION O.06 (1.00)
Is the FH8R0 permitted to independently deviate from approved procedures in an emergency to protect public health and safety when other actions will not provide adequate or equivalent protection?
Explain your answer.
QUESTION 8.07 (1.50)
What requirements must be met for the FHSRO to authori=e the use of the key operated override switches on the canister handling trolley in the Reactor Building?
DUESTION 8.08 (1.50)
What is the difference between the words may, shall, and should when used in a procedure?
DUESTION 8.09 (2.00)
Describe which plant systems are under the direct cognizance or control of the FHSRO and provide FOUR examples.
QUESTION 8 10 (2 00)
a. List FOUR types of information which must be included in the chronological los maintained by the FHSRO.
b. What is the ninteum routine information which must be reported
-
by the FH8R0 to the Main Control room inorder for the Control
,
Room Operator to maintain his los?
(smama CATEGORY 08 CONTINUED ON NEXT PAGE maass)
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OUESTION 8.11 (2.00)
What evolutions require direct supervision by a FHSRO?
OUESTION 8 12 (3.50)
During defueling operations on a backshift when only minimum required staffing personnel are available the work crew which is in the Reactor tuilding identifies to the FHSRO the need to change the order of some steps in the Debris Bucket Handling Tool operating procedure.
The change is only needed for a one time evolution which is the next planned use of the handling tool.
is a. Who would initiate the Unit Work Intruction (UNI) to request the
,+
change?
(0.6)
b. How does the FHSRO know or verify that any UWI has been approved?
(0.6)
c. Should the FHSRO require the work crew to leave the Reactor Building during the processing of the UWI?
Justify your answer by indicating the persons required for concurrance or approval and how concurrance maybe obtained.
(2.3)
GUESTION 8.13 (3 50)
a. Under what conditionse if anye could a 2 ton missile shield be moved over the deep end of the fuel transfer canal using the polar crane?
(0.8)
.
b. What is the basis for restrictions on moving loads using the polar crane?
(1.5)
c. What type of notificationse if any, are required if the LimitinS Conditions for Operations for the polar crane are exceeded?
(1 2)
(asssa END OF CATECORY 08 mmann)
(massssassuman END OF EXAMINATION saamassamassass)
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ANSWER 5.01 (2.00)
a.
This will drop Keff ____ _____..
because of the removal of the moderator. C1 03 ( $tsoWANDE A850RPTEoM T NCREAs es)
b.
Ensures that Keff remains less than 0.99 for all postulated configurations. [1.03 REFERENCE TMI-2 FH/SRO Training Program (Penn State), Objective 45, p.8 i
TMI-2 Criticality Reporte p.11 l
l l
ANSWER 5.02 (1.50)
a.
Radiolytic decomposition of water under gamma flux. [0.53 b. Buildup of pressure in the canister. [0.53 Possible hydrogen combustion.
C0.53 REFERENCE SER For Early Defueling, p.
17,47 ANSWER 5.03 (1.75)
a.
In two peripheral assemblies (P4 and B12) [0.53 6 5 feet below the top of the upper end fitting.CO.53 b.
Because they may present a radiological neutron hazard. [0.753 REFERENCE Reactor Vessel Construction, 12 2.01 080 pp. 27, 28 ANSWER 5.04 (1.50)
As the fluid heats up the volume changes and the level increases C0.53 but the mass remains the same, therefore the indicated pressure remains the same. C0.53 This allows a very narrow level alarm band. [0.53 REFERENCE Control Systeme 12.2 01.159, p.12
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ANSWERS -- TMI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 5.05 (2.25)
It will show a continuous reduction in weight as it is lowered [0.753 until the open top reaches the water level and then the weight will continuously increase until the canister is filled.[0.75]
The reason for these changes is the buoyant force of the water. [0.753 REFERENCE Canister Handling Tools, 12.2 01.165e p.11 ANSWER 5.06 (3.00)
Fuel debris enrichment Fixed poison in canister ends Properties of moderator and reflectors Pool / storage ares Canister drop (design basis accident)
Canister shape / size
[any 4 0 0 75 each]
REFERENCE LP8 12.2 01.171 Defueling Canisters, p 23 ANSWER 5.07 (3.00)
a.
Indicated level will be higher than actual due to 1: :r Iv64cdsto gas pressure resulting from the higher flow rate.
b. Level fails high due to inability to establish air flow.
n As 1s 11 Assure su s a ru uco on Ltc or Ass arre owsesure n nr in-. serc<
c.
Indi::ted 1 ;:1 :ill ine erte der te kicke- 'er'r eeee-e:
We u us. e s us c Mris :, n nc e't 0 0c.c4 ragt wwa geogrsu' can'srnor'
REFERENCE LP! 12.2.01.049 Non-Nuclear Instruments TMI-2, p 73-76 s
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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 5.08 (2.00)
p(1)= k(1)
1 / k(1)
[0.33
-
= 0.8 1 / 0.8
[0 13
-
= -0.25
[0.13 p(2)= p(1) + 0.01 E0.23
= -0.25 + 0.01 E0.13
= -0.24 CO.13 k(2)= 1/ E1 p(2)3 CO.33
= 1/ [1 (-0.24)3
[0.13
-
= 0.806 c(2)= c(1) [1-k(1)/1-k(2)]
[0.53
= 200
[1-0.8/1-0.8063
[0.13
= 206 eps
[0.13 REFERENCE L.p.
11 2 01.179 Suberitical Multiplication, p 11
. ANSWER 5.09 (3.00)
a.
A material that will spontaneously (or by pilot) ignite when in the presence of oxygen. [0.73 b.
Zirconium hydride. [0.73 c.
During core boring.
Zr fines exposed during cutting operations.
Dewatering if cover gas is replaced by air.
[any 2 0 0.4 each]
d.
The core barrel and sample will be purged with argon as they are removed from the reactor. CO.43 Filled fuel canisters will have an argon cover gas applied durina dewaterina operations.CO.43 c h'enre or w a rig to.O REFERENCE SER For Early Defueling, p.49 Core Bore, 12.2.01.151, p.15 p ynon ctic, ot. t *' 170 1-
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PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
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ANSWERS -- THI-2-85/08/13-DVDLEY/RUSCITTO
,
ANSWER 6.01 (2.25)
l a.
A fuel canister requires a four foot shielding exclusion zone [0.53 while a knockout canister has a (4 inch) thick top which provides equivalent shielding. [0.753 b.
There is additional shielding hanging from the bottom of the shielded work platform. [1.03 i
REFERENCE
!
CPS 12.2.01.156, p.6 l
ANSWER 6.02 (2.50)
l
a.
RCS hot les pressure transmitter provides local readout (at 282' elev.
FHB) and a digital raadout in the control room. [1.03 The digital
readout only requires power. [0.53 b.
Bubbler system provides indication in the control room. [0.53 c.
Tyson tubing attached to RCS cold leg. [0.53 REFERENCE SER For Early Defueling, p.28
,
I ANSWER 6.03 (2.00)
l l
a.
The cooling effect of water flow on a heated wire changes the wire's I
resistance. [1.03
!
b.
The canister is either full [0.53 or the system is clogged. [0.53 REFERENCE Early Defueling Fines / Debris Vacuum System, 12.2.01.155, p.23
.
ANSWER 6.04 (2.00)
l a.
On a loss of air, the fail-safe spring automatically moves the activating rod downward causing the lifting pawls to engage. [1.03
!
b.
Lift up on the manual release lus CO.53 with the long handle hook
!
tool. [0.53 i
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PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO REFEREWCE Canister Handling Tools, 12.2.01.165, pp.7,9 ANSWER 6.05 (2.00)
a.
Programmable controller [0.53 which may be overridden by key switches
[0.53 b.
Limit switches E0.53 that may not be overridden. [0.53 REFERENCE Canister Handling Tro111ey, 12.2.01.160, p.12 ANSWER 6.06 (3.00)
a.
(1)
The drain screen is clogged. [0.753 (2)
Check for zero flow indication on the installed flowmeter.[0.753 b.
The pressure relief valve will lift. [0.753 c.
A steady stream of gas bubbles is visible. [0.753 REFERENCE In-Vessel Dewatering Systeo, 12.2.01.167, pp.5,6 ANSWER 6.07 (3.00)
a. Off gas system [0.53 creates an airflow through the work platform, into the IIF enclosure CO.53 and out to the reactor building atmosphere through filtration unit. [0.53 b. FHB DS vents to a holdup tank [0.53 which is vented to the SDS off gas filter. C1.03 REFERENCE SER for Early Defueling, p 31, 32
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PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
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ANSWERS -- THI-2-85/08/13-DVDLEY/RUSCITTO ANSWER 6.08 (3.25)
a.
To prevent a local criticality in case of a leak into the pool.[0.753 b.
(1)
High suction filter DP (2)
High pressure filter DP (3)
High return filter DP (4)
Pump suction valve closed (5)
High fluid temperature (6)
High fluid pressure (7)
High fluid level (8)
Low fluid level Cany 6 9 0.33 each3 c.
(1)
Low fluid level (2)
Pump suction valve shut E0.25 each3 REFERENCE Control System, 12.2.01.159, p.12
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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 7.01 (1.50)
h i
[0.753 Canister wei rutcn snmerck +k$s continuously monitored during loading.
a.
ru.
b.
The canisters are dewatered to expose 50% of the recombiner es5eyst within an inert cover gas. [0.753 REFERENCE SER For Early Defueling, pp 15,17 ANSWER 7.02-(1.50)
1.
Push emergency stop pushbutton [0.753 (on the control console.)
2.
Open the platform drive disconnect switch C0.753 (on the electrical power distribution center.)
REFERENCE
-
Control System, 12.2.01.159, p.9 ANSWER 7.03 (1.00)
0, 2 a. m = count rate / count rate initial. [9v93 m is the symbol for suberitical multiplication and conti u s to increase toward infinity as criticality is approached. C
.
1/m approaches zero and is easier to analyse on a graph. [9v53
b.
The time at which criticality will be reached. [+ve]
ANSWER 7.04 (2.00)
Override the bridge Operation Sequencial Limit using the
' Bridge / Trolley Move Override' key switch and position trolley. C2.03 or Raise the shield. Position trolley. Lower shield. C2.03 REFERENCE LP! 12.2.01.160 Canister Handling Trolley, p 23, 24
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 7.05 (2.00)
er/uk = 6 day /wk x 2 entries / day {10er/ entry + 3hr(2/3x17 +1/3x7)mr/hr> CO.83
= 612 mr/uk E0.33 week /qt allowed = 3 Rem /qt [0.43 /.612 ar/wk E0.43
= 4.9 weeks
[0.13 REFERENCE 10 CFR 20 Defueling System Review, Jan 13, 1985, Bradbury; Attachment 8, Defueling Crews ANSWER 7.06 (2.50)
Wash down tools and handling equipment as they are removed from the Reactor Vessel.
[0.833 Bassing the potentially contaminated portions of tools and handling equipment.
[0.833 Segregated storage of potentially contaminated tools and handling equipment.
[0.833 REFERENCE 4210-OPS-3255.16, Operation of In-Vessel Dewatering System, p7 ANSWER 7.07 (2.50)
Makeup from the BWST CO.83 Recirculate and sample reactor building sump to ensure boron > 4350 ppm.
[0.83 Setup and initiate Reactor Building Sump Recirculation System. [0.93 REFERENCE SD: 3510-012, Reactor Building Sump Recirculation System, p 4.
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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 7.08 (3.00)
8s enen 6wca n'WW [H3N]
s a. Radiation dose t; th: ben:-
'2.7 REhr tw11w.vd-L 7 ww.=
io why..id? [0.93 No limits would be exceeded. [0.63 b. Notify Control Room and Radeon.
[0.53 Evacuate personnel from refueling canal.
[0, 53 Isolate Reactor Building.
[0.53 REFERENCE SER: Early Defueling of THI-2 Reactor Vessel, p 4c 4210-EAP-3252.01, Loaded Canister Drop, p2 ANSWER 7.09 (4.00)
a. Suspend core alterations CO.53 due to unexplained loss of level in the RCS. [0.53 b. No action. [0.43 expected raise in SFP due to drop in atmospheric pressure. [0.63 c. Limit access to the entire canal area and canal walkway area as required by Radeon personnel [0.53 to prevent personnel exposure. [0.53 Atc 5tnet 02 I W> r&Ltc d. Continue transfer and assess situation with SS/SF and Radeon. [0.53 Normal radiation levels are between 20-100 mrem /hr and evacuation is required at 200 mrem /hr. [0.53 REFERENCE 4200-OPS-3255.01, p 3, 4,
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ANSWERS -- TMI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 8.01 (.60)
C St Radiological Controls Representative REFERENCE 4000-ADM-1000.02, p2 4000 ~ MM ~ 3310. 01, p7
-
ANSWER 8.02 ( 460)
A. Check forms attached to the controlling UWI REFERENCE 4000-ADM-2600.01, p5 ANSWER 8.03 (.60)
B. FHSRO (Job supervisor of department having lead responsibility)
REFERENCE 4000-ADM-2600.1, p4 ANSWER B.04 (.60)
A,@ Shift Supervisor REFERENCE 4000-ADM-3240.01, p9 ANSWER 8.05 (.60)
B.
Fire REFERENCE 4000-ADM-3240.01, p6
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ANSWERS -- THI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 8.06 (1.00)
No. [0.33 Must receive approval from licensed SRO prior to taking the action. [0.73 REFERENCE 4000-ADM-1218.01, p 11
.
ANSWER 8.07 (1.50)
Under controlled conditions. [0.753 Operator must have a specific movement plan. [0.753 n urncaz z rc or s&C REFERENCE turncan M 1.rrtre s.enos Ake 7urstrks L.P.
12.2.01.160, Canister Handling Trolley, p 13 TCW TC YLit - OfS -]X til. 01 ANSWER 8.08 (1.50)
Shall is a requirement.
[0.53 Should is a recommendation.
[0.53 May denotes permission but is neither a requirement nor a recommendation. [0.53 REFERENCE 4000-ADM-1218.01, p2 ANSWER 8.09 (2.00)
All inplant systems directly provided for reactor vessel fuel removal are controlled by FHSRO. [1.23 Examples:
Canisters and canister handling and support systems Transfer systems Long handles tools
[any 4 0 0.2 each]
REFERENCE 4200-0PS-3255.01, p8
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ANSWERS -- TMI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 8.10 (2.00)
a. Stationing or securing watch Starting or stopping major defueling equipment Removing or returning to service major defueling equipment Canister movements and addresses Off-mormal or out of specification conditions Operations in progress when assuming watch Other information determined important Cany 4 0 0 3 each]
b. Canister movements and locations
[0.83 REFERENCE 4200-OPS-3255.01, p7 ANSWER 8 11 (2.00)
I Handling / loading of fuel ranisters
[0.73 from the start of the evolution, which places fuel canisters into the Reactor Vessel E0.63 until the fuel canisters are teansferred and positioned in the
'A'
spent fuel pool. [0.73 REFERENCE 4210-ADM-1000.01, p5 ANSWER 8.12 (3.50)
a.
FHSRO E0.63 b. Implementing approval signature by the Div/Dep or Section Head CO.63
c. Wait in Reactor Building [0.33 d uc ee i a0%
('][Q[j[,f[,,
FHSRO may act as document coordinator. [0.63 Only two members of unit management staff one of whom is SRO licesed are require to concur. [0.73 The Duty Superintendent may approve via telcon. [0.73 REFERENCE 4000-ADM-1218.2 p 11 l
4000-ADM-3000 1 p 11, 13
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8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
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ANSWERS -- TMI-2-85/08/13-DUDLEY/RUSCITTO ANSWER 8.13 (3.50)
a. A docketed Safety Evaluation for the activity is approved by the NRC.
[0.83 b. Reconfiguration of or damage to the core. [0.753 Damage causing unisolable leak from reactor vessel. [0.753 c. 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification [0.63 Special Report or LER (within 30 days) [0.63 REFERENCE T.S.
3 10-1, B3/4 10-1, 6-13, 6-14
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JUN 2 61985 NRC EXAMINERS:
N. Dudley, D. Ruscitto REQUEST FOR ADMINISTRATION OF WRITTEN AND OPERATING EXAMINATION FOR OPERATOR LICENSING Please make arrangements to administer written and operating examinations to the following candidates:
CANDIDATE l
DOCKET NO.
l EXAMINATION TYPE I
I Michael L. Benson l 55-60647 l LSRO Dean D. Hollmann l 55-60646 l LSRO
' ~ ~
Thomas R. Osterhoudt i 55-60645 l LSR0 John J. Pfadenhauer l 55-60644 l LSR0 James W. Quinnette l 55-60643 l LSR0 Ronald E. Walker l 55-60642 l LSR0 Facility and Location: Three Mile Island Nuclear Station, Middletown, PA (Unit 2)
Facility Contact: B. Leonard, 717-948-8046 Chief Examiner: N. Dudley Written Examination to be Prepared by SRO: N. Dudley, D. Ruscitto Dates of Examinations: August 12, 1985 - August 16, 1985 Robert M. Keller, Chief
'
Projects Section IC Division of Reactor Projects cc:
Senior Resident Inspector DRP Section Chief
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Chief, OLB, DHFS, NRR
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