ML20205J084
| ML20205J084 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/21/1986 |
| From: | Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20205J078 | List: |
| References | |
| 50-206-0L-85-04, 50-206-L-85-4, NUDOCS 8601300095 | |
| Download: ML20205J084 (51) | |
Text
Examination Report No.
50-206/0L-85-04 Facility Name:
San Onofre Nuclear Generating Station' Unit 1 Docket No.
50-206 Examinations Administered at:
San Onofre NGS, San Clemente, California', from Decemb r 17-19, 1985 i
he
/ // [d Chief Examiner:
hns p, Operator License Date/igned G. (
Exam ep Approved By:
k
/ 2/ PG J.
- f. Elin, Chief Ddte Signed Op rations Section Summary:
Examinations on December 17-19, 1985 Written examinations were administered to seven Senior Reactor Operator candidates. Operating examinations were administered to all of those candidates.- All of the candidates passed the Operating examinations. Five of the candidates passed the written examination.
8601300095 860123 PDR ADOCK 05000206 0
1.
Persons Examined SRO Candidates Sev'en Senior Reactor Operator candidates were' examined.
2.
Examiners
- F. Jaggar, EG&G P. Isaksen, EG6G G. Johnston, RV
- Lead Examiner 3.
Persons Attending the Exit Meeting,
Southern California Edison:
A. J. Schramm, Act.ing Plant Superintendent J..J. Wambold, Training Manager R. J. Mette, Supervisor of Operations Training M. J. Kirby, Nuclear Training Administrator NRC.
F. Jaggar, EG6G P. Isaksen, EG&G P. Morrill, NRC:RV 4.
Written Examination and Facility Review'.
Written exams were administered as follows:
Seven written examinations to-SRO candidates.
At the conclusion of the exam the facility.staffJreviewed the examiand answer key. The facility staff comments;a're addressed in the' enclosed attachment (1). These-comments were. discussed with the facility. staff and appropriate revisions'to'the master examination key were made by the lead examiner prior to grading the candidates' responses.
5.
Operating' Examinations i
Facility walkthrough oral examinations were conducted December.18-19, 1985. No particular generic weaknesses.were identified by the examiners during the course of the examinations.
l
- 6. -
Exit Meeting i
I
. On 'December 19, 1985, the NRC representatives met with' licensee personnel. Those individua1' candidates who clearly passed _the oral.
examinations were identified..The NRC representatives discussed the overall performance of:the candidates.
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l Resolution'of Facility Comments 1.0 Facility Comment: Question 5.12
- i..
" Initial facility.provided reference did not address required NPSH for given condition'in question and the. required NPSH'does not change."
Resolution:
' Westinghouse. Thermal Science', Chapter 10, page 49 does address the condition given in the question and the answer is correct. This additional reference was available at the facility and added to the initial supplied reference sent by the facility.
No. change to answer key.
2.0 Facility Comment: Question 5.17 "AFW flow bypasses feedflow measuring-devices so lower _ mass flow indicated would also result in lower NI indication compared to actual."
Resolution:
Comment accepted as additional correct response. Answer key modified.
3.0 Facility Comment: Question 6.02
" System description appendices not required _information.' Reworded answer attached."
Resolution:
The answer suggested for 6.02 part "a" is essentially the'same as the answer key, therefore the key was left as is.
In part "b",
the facility wants partial credit if S/G temperature is plotted vs pressure.
In the satu' rated S/G, these would produce essentially the.same curve as temperature and pressure follow each other. The key'was left. unaltered.
4.0 Facility Comment: Question 6.03 a) and d) 4 j
"a)
Add ;immediately loads ESF (SI) equipment on busses.. delete-containment spray.
'De'ete containment spray."
d) l Resolution:
Both comments. accepted, answer was ch'anged.
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j 5.0 Facility Comment: Question.6,04 c)
~
"FCV 1112 does not close when overriden. _ Returns to normal operational control."
7 Resolution:
Comment' accepted, answer key was. changed.
6.0- Facility Comment: Question 6.06 c)
)
" Question asks for chemical (singular). Answer has two parts. Only one should be required."
i Resolution:
l Comment accepted,~ answer key was changed.
7.0 Facility Comment: Question 6.08 l
PI Setpoint.20% + or - 1 l
70- - 80%
106 '+ or - 1 j
P-3 Setpoint '... and 1/45.LVDTs on rod position. indication.
P P-7 should not be part of answer.
P-7 Delete-(five) under function.~ ^See references in answer key."-
Resolution:
Comments accepted, answer key changed a'ccordingly. In P-7, the.five was
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l not deleted but altered to four, j
8.0 Facility Comment: Question'6.10 a) 1
" Question is open ended add ' Exciter; Field) Breaker' and question is.not i
I clear that indirect answers are required."~
j Resolution:
Exciter Field' Breaker added to answer key. Grading of! question'will not' be based on candidate referring to.the trips'as' direct or indirect.
9.0 Facility. Comment: Question.6.10 b) t i
" Question should read ' Unit Differentia 1'.vice Generator Differential'.
l Generator Differential is electrically identical to Generator Loss of.
~
Field."
4 f-Resolution:
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I 1.
3 Question will be graded using the answers for parts I and 2 for each part.
10.0 Facility Comment: Question 7.01 a.2
" Replace answer with T.S. 3.5.2 A and B."
Resolution:
Comment accepted, answer key was changed.
11.0 Facility Comment: Question 7.02 c
" Add reverse ~ delta-T interlock and T.S. requirement for _10% power RCP restart."
Resolution:
The reverse delta-T interlock will be incorporated into the answer since supporting reference material provided supports the interlock which serves to minimize the differential toJperature between affected and inaffected loops. The T.S. requirement is not accepted. The requirement allows for continued operation with 1 or 2 loops in service for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, T.S. also allow I hour before Hot Standby with power above 10% and does not support an initial condition for the RCP restart.
12.0 Facility Comment: Question 7.03 b
" Add charging pump capacity increases and why only half credit for volume change versus temperature."
Resolution:
Partial credit will be given for both charging pump capacity and volume changes, however decreasing the leak rate with lower RCS pressure is more significant and required for full credit.
13.0 Facility Comment: Question 7.05 e and d
" Add T.S. references for parts e and d."
Resolution:
t Included additional reference for~part c.
Part d is adequately supported by the existing reference.
14.0 Facility Comment: Question 7.06 d and e "Part
'd' answer typo 150 vs 100 and part 'e' T.S. changes require j
additional RO prior to exceeding 200 deg. F (entering mode 4)."
l Resolution:
1
-Both comments accepted, answer key was changed.
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-4 15.0 Facility Comment: Questions 7.~07 and 7.08
" Subsequent action steps not required yet asked here."'
Resolution:
Comment noted. Candidates are expected to know system / system interrelationships and cce.cfons and limitations of procedures including the objectives and methc,ds used in ;.rocedures per NUREG-1021. ES 202 pages 2 and 3, and ES 402 page 3.
16.0 Facility comments: Questions for Section 8 8.01.c)
"Immediate~ reports required to Plant Superintendents and STA not V.P. & NARC Chairman."
8.02 "New T.S. adds also additionally NPE0 and additional RO."
8.06'b)
" Contact by phone also valid answer."
8.09
" Typo
' Controlled and any TCNS'.
8.12 a)
"During Mode 5 changes answer to 200 deg. F vice 350 deg. F."
Resolutions:
All comments accepted, answer key changed.'
17.0 Facility Comment: Question 8.07
" Entire procedure replaced, Q&A no longer valid. Request delete question.
Resolution:
Comment accepted, question 8.07 deleted from examination.
18.0 Facility Comment: Question 8.13 "All answers reversed. See Answer' Key."
Resolution:
Investigation of parts 'a' and
'b' sustained the answer key.. In part-
'a', permission most be granted by the SRO Operations Supervisor, not the.
Control Room Supervisor as' stated.
(Precaution 4.6 of SOI-14-17).
In
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part
'b', Kerotest Packless valves can be throttled for testing making the statement false (precaution'4.10, SOI-14-17)..Part 'c answer.was in error, answer key was changed.
A change to the resolution for part 'b'.was made by.a reviewer in Region.
V.
The question and answer were deemed by the reviewed to. represent a potentially misleading statement.and was determined to require recall for a precaution that had.been changed very recently. As this was a true or
5 false response for the candidates it was deemed appropriate to delete the question.
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NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Ey s m sco % y.-
FACILITY:
_gAN_QNQFRg-l____________
T - D G4 ssee (E)
REACTOR TYPE:
_ P WB --WE Q }_ _ ___ _ _ _ _ _ _ _ _ __ _
g, w p -... e DATE ADMINISTERED: _8_5__/_12__/_17_________________
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_I@AK@@N _P._____________
p EXAMINER:
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APPLICANT:
INgIBQQIlgNg_IQ_@BE61Q@ nil 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 least 80%.
Examination papers will be picked up six (6) hours after the examination starts.
X OF CATEGORY
% OF APPLICANT'S CATEGORY
__YBLUE_ _IQI@6
___SQQBE___
_y@6yE__ _
==
___Q@IgggBY__
_2Et99__ _2Ez99
________ 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_2Et99__ _2Ez99
________ 6.
PLANT SYSTEMS DESIGN, CONTROL,
_ _ _ _ _ = - -
AND INSTRUMENTATION
_2Ez99__ _2Et99
=
==-
___ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_2Ez99__ _2Et99
________ B.
ADMINISTRATIVE PROCEDURES,
= _ - _ =
CONDITIONS, AND LIMITATIONS 199190-199199
________ TOTALS FINAL GRADE _________________%
I All work done on this examination is my own. I have neither given nor received aid.
=__________________________
APPLICANT'S SIGNATURE
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 2
.TEERMODYNAMICS QUESTION 5.01 (2.50) a.
With the plant operating at 85% power and all systems in a normal / automatic configuration, the operator borates 100 PCM.
(1.0) 1.
Increases.
2.
Increases until rods move.
3.
Decreases.
4.
Decreases until rods move.
5.
Remains unchanged, whether or not rods move.
b.
State the THREE purposes for the Control Group' Insertion limits according to Technical Specifications.
(1.5) l i
QUESTION 5.02 (2.50)
Compare the CALCULATED Estimated Critical Position (ECP) for a startup to be performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power, to the ACTUAL control rod position (ACP), if the following events / conditions occurred.
Consider each independently. Limit your answer to ACP is HIGHER than, LOWER than, or SAME as the ECP.
- a. One reactor coolant pump is stopped two minutes prior to criticality.
(0.5)
- b. The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip.
(0.5)
- c. The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoint.
(0.5)
- d. Condenser vacuum is reduced by 4 inchos of Mercury.(24 to 20 in.) (0.5)
- e. All Steam Generator levels are being raised by 5% as the ACP (criticality) is reached.
(0.5)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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5.
THEORY OF NUC W AR POWER PLANT OPERATION. FLUIDS. AND PAGE 3
THERMODYNAMICS QUESTION 5.03 (2.00)
A.
Does-Beta bar effective Increase, Decrease, or Remain the Same, from BOL to EOL7 (Briefly explain your choice.)
(1.0)
B.
For equivalent positive reactivity additions to a critical reactor, will the SUR be the Same, Larger, or Smaller at EOL compared to BOL7 (no explanation necessary)
(1.0)
QUESTION 5.04 (1.00)
TRUE or FALSE 7 a.
At EOL, the Doppler Temperature Coefficient is more negative due to an increase in the quantity of Pu-240 in the fuel.
b.
With all rods out, and a constant boron concentration (ppm), the MTC becomes more negative as RCS-temperature (Tavg) increases.
QUESTION 5.05 (2.00) a.
Provide TWO reasons for Xenon contributing more negative reactivity at full power than Samarium.
(1.0) b.
Explain why you agree or disagree with the following statement:
" Equilibrium Samarium concentration at 50% power is approximately half its concentration at 100% power."
(1.0)
QUESTION 5.06 (1.00)
At BOL,-the components of the power defect in an INCREASING order of significance (reactivity value) are:
a.
Void, Doppler, MTC b.
Void, MTC, Doppler c.
MTC, Void, Doppler d.
MTC, Doppler, Void
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE 4
THERMODYNAMICS QUESTION 5.07 (1.00)
Which of the following statements concerning the power defect is correct?
a.
The power defect is the difference between the measured power coefficient and the predicted power coefficient, b.
The power defect increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.
c.
Because of the higher boron concentration, the power defect is more negative at beginning of core life.
d.
The power defect necessitates the use of a ramped Tava program to maintain an adequate Reactor Coolant System subcooling margin.
QUESTION 5.08 (1.00)
Daring fuel loading, which of the following will have NO effect on the shape of a 1/M plot?
a.
Location of the neutron source in the core.
b.
Strength of the neutron source in the core.
c.
Location of the neutron detectors'around the core.
d.
Order of placement of fuel assemblies in the core.
QUESTION 5.09 (1.00) l The reactor is critical at 10,000 cps when a S/G PORV fails open.
Assuming BOL conditions, no rod motion, and no reactor trip, choose the answer below that best describes the values of Tava and nuclear power for the resulting new steady state.
(POAH = point of adding heat) a.
Final Tava greater than initial Tavg, Final power above POAH.
b.
Final Tavg greater than initial Tavg, Final power at POAH.
c.
Final Tava less than initial Tava, Final power at POAH.
d.
Final 7ava less than initial Tavg.. Final power above POAH.
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(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 5
THERMODYNAMICS QUESTION 5.10 (1.00)
The Moderator Temperature Coefficient (MTC) varies with certain plant conditions. Concerning these variations, which of the following is correct?
The MTC becomes more negative as boron concentration is increased, a.
b.
The MTC causes axial flux distribution to be tilted towards the top of the core at BOL.
c.
The MTC varies as temperature changes because of the non-linear density changes of water as temperature changes, d.
The MTC is not permitted by Technical Specifications to be positive for any of the plant operating modes.
QUESTION 5.11 (2.50) a.
If steam goes through a throttling process, specifically as in a leak from the high pressure main steam header, indicate whether the follow-ing parameters will INCREASE, DECREASE, or REMAIN THE SAME.
(2.0)
- 1. Enthalpy
- 2. Pressure
- 3. Entropy
- 4. Temperature b.
Will the steam become subcooled, saturated or superheated as it leaks out?
(0.5)
QUESTION 5.12 (1.00)
From the choices below, select the one which best completes the sentence.
l When the flow rate through a centrifugal pump is increased by opening the i
discharge valve, the required NPSH and the available NPSH l
(a) increases; increases (b) increases; decreases (c) decreases; increases l
l (d) decreases; decreases
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 6
THIRMODYNAMICS QUESTION 5.13 (1.50)
TRUE or FALSE 7'
- a. The faster a centrifugal pump rotates, the greater the NPSH required to prevent cavitation.
(0.5)
- b. One of the pump laws for centrifugal pumps states that the volumetric flow rate is inversely proportional to the speed of the pump.
(0.5)
- c. Pump runout is the term used to describe the condition of a centrifugal pump running with no volumetric flow rate.
(0.5)
QUESTION 5.14 (1.00)
In order to maintain a 200 F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately:
a.
245 psig b.
445 psig c.
645 psig d.
845 psig QUESTION 5.15 (1.00)
The reactor is operating at 30% power when one RCP trips.
Assuming NO reactor trip or turbine load changes occur, which one of the following parameters will DECREASE 7 a.
Flow in operating reactor coolant loops b.
Coro delta T c.
Reactor vessel delta P d.
Steam generator level in unaffected loop
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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5.
THEORY OF NUC M AR POWER PLANT OPERATION. FLUIDS. AND PAGE 7
THERMODYNAMICS QUESTION 5.16 (1.00)
Which one 6f the following requires the most heat energy to be removed by the main condenser?
n.
One pound of steam at 0 psia, b.
One pound of steam at 300 psia, c.
Two pounds of steam at 600 psia.
d.
Two pounds of steam at 1200 psia.
QUESTION 5.17 (2.00)
After a secondary calorimetric and adjustment of the power range inst-
- ruments, it is discovered that the Auxiliary Feedwater Pumps were operating.
HOW and WHY would this occurence affect ~the power range adjustment?
(2.0) l
(***** END OF CATEGORY 05 *****)
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 8
QUESTION 6.01 (1.00)
The Safety Injection System is designed to operate satisfactorily with second order mechanical equipment failures.
Describe what is meant by second order mechanical failures.
(1.0)
QUESTION 6.02 (3.00) a.
There are three possible alternatives to control Tavs while lacreasing reactor power from 0 to 100% power, they are programming Tavg over automatic controlled power range, maintain Tava constant at full power Tavg. and maintain Tava constant at no-load Tavg.
State which method is preferred, explain why it is preferred and why the others are not preferred.
b.
Sketch diagrams comparing the temperature and S/G pressure profile for all three.
QUESTION 6.03 (4.00)
The major automatic actions that are initiated by the Safeguard Load Sequencing System for each event below differ.
State the major automatic actions that occur for each.
a.
receipt of a Safety Injection System (SIS) Signal.
b.
loss of 4160 Volt Bus 1C or 2C (LOB) c.
loss of offsite power (LOP) d.
receipt of a SIS and a loss of offsite power together (4.0)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 9
QUESTION 6~04 (2.50) a.
Describe the timing and operation of the normal charging flow-control valve (FCV-1112) during a Safety Injection Signal event (SIS) and a SIS with Loss of Power (LOP).
Be specific.
(1.0) b.
Describe the timing and what occurs to an operating charging pump during a SIS / LOP signal.
Assume it is the pump that will start and all safeguards equipment will function normally.
Be specific.
(0,5) c.
Describe the provision available for overriding FCV-1112 and explain specifically what occurs to how the override is accomplished.
(1.0)
QUESTION 6.05 (2.00) a.
Why is the SONGS 1 125 VDC system ungrounded?
(1.0) b.
What indication does the operator have should a DC system ground develop?
(0.5) c.
Briefly describe how this ground can be located.
(0.5)
QUESTION 6.06 (2.50) a.
What components are operated by the Containment Spray Actuation system?
(0.75) b.
State 3 purposes for containment sphere spray !nitiation.
(0.75) c.
Aside from boron, what other chemical will be present in the Spray and Safety Injection recirculation Fluids?
Why?
(0.5) d.
What should the operator do if the charging pumps become inoperable during recirculation cooldown?
(0.5)
QUESTION 6.07 (1.50)
In the Steam Generator Level Control System, why do the steam and feed flow signals go through computers, AND why is the leve?. signal not directed through a computer?
(1.5)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 10 QUESTION 6.08 (2.00)
SONGS-1 incorporates 8 permissive circuits into the Reactor Protection System.
Choose 4 of the 8.
State it's number /name, setpoint, coincidence and function.
(2.0)
QUESTION 6.09 (3.50) a.
List the four (4) destinations of the output signals from the Loop T-ave computers.
(1.0) b.
Lis six (6) of the seven (7) outputs from the Average Tas e. Summing Computer.
(1.5) c.
What parameter signals are used to calculate:
1.
Rod insertion limits 2.
Variable Low Pressure Reactor Trip setpoint (1.0)
QUESTION 6.10 (3.00) a.
Describe the automatic actions that will occur due to a fault on the KV electrical bus.
(1.5) b.
Describe ALL of the electrical line-ups the operator could use to supply power to the Reactor Coolant pumps if the loss of bus was caused by the following devices?
I 1.
Generator differential (0.5) l 2.
Generator loss of field relay (1.0)
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(***** END OF CATEGORY 06 *****)
7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 11 RADIOLOGICAL CONTROL QUESTION 7.01 (2.50)
During' normal full power operation, there are 2 limits on Bank a.
2 control rod height. What are these limits and the purpose of each?
(1.5) b.
What action is necessary if the plant in to be operated above 90% power with both Continuous Axial Offset Monitoring System (CAOMS) channels out of service?
(1,0)
QUESTION 7.02 (2.50)
You are increasing plant power to full load with the reactor at 354 power when a Reactor Coolar.t Pump breaker is inadvertantly opened, a.
What is the operators immediate action?
(0,5) b.
What protection system trip setpoint(s) would be affected?
(0.75) c.
Why must reactor power be less than 10% to recover the idled loop?
(1.25)
QUESTION 7.03 (3.00) a.
For RCS cooldown and depressurization following a small LOCA within the capacity of the charging pumps (SOI-1.0-22),
the maximum cooldown rate limit is 100 F/Hr.
How or why may i
the cooldown rate limit be less?
(1.0) b.
Why may the allowable cooldown rate be increased to 100 F/Hr as RCS temperature decreases?
(1,0) c.
A caution note in this procedure states "If RCS pressure decreases to less than 300 pais above main steam pressure, j
trip operating RCP."
What is the reason / basis for this l
precaution?
(1,0) l l
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(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 12 RADIOLOGICAL CONTROL QUESTION 7.04 (2.00) a.
What TWO symptoms would indicate high activity in the RCS according to abnormal procedure 801-2.1-157 (1.0) b.
What is the TS bases for reducing Tava to less than 535-F (within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) if RCS activity is greater than 100/E bar microcuries per gram?
(1.0) 1 QUESTION 7.05 (3.00)
The following concern " control system malfunctions" Procedure SOI-2.3-1.
(Setpoints not required)
- a. What are 3 different reactor trips that could occur from contin-uous rod withdrawal at 90% power ?
(1.0) b.
If a reactor trip occurs as a result of a dropped rod, what protection signal would cause the reactor trip?
(0.5) l Why do procedures direct the operator to trip the reactor if c.
more than 1 rod drops ?
(1.0)
- d. What is the operators principal concern when he becomes aware that a control rod is untrippable from a withdrawn position ?
(0.5)
QUESTION 7.06 (4.50)
The following concern " Plant Starting from Hot Standby to Minimum Load" Procedure SOI-3-2.
a.
What is required of the Shift Superintendent prior to entering this procedure with other than normal hot standby conditions (1.0) present?
b.
What is required if this procedure is exited to commence shutdown?
(1.0) c.
What defines a cold start of the turbine?
(0.5) d.
What action is required if a S/G feedring becomes uncovered?
(1.0) e.
When is a second licensed operator required to be present in the Control Room?
(1.0)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
i
7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 13 RADIOLOGICAL CONTROL j
QUESTION 7.07 (3.00)
The following concern " Response to Nuclear Power Generation /ATWS" Procedure SOI-1.1-1, a.
What are the required control room operator actions when ensuring the reactor and turbine are tripped and they have failed to trip? (1.0) b.
When can emergency boration be stopped?
(1.0) c.
What is the basis for verifying AFW initiation?
(1.0)
QUESTION 7.08 (3.00)
The following concern "Overpressurization Hitigating System Actuation" Procedure, SOI-2.1-11.
a.
How is RCS pressure reduced if the PZR PORV's fail to function as required?
(1.0) b.
What is the basis / reason for allowing only one centrifugal charging pump to be operable when RCS pressure is less than 400 psig and PZR level is greater than 504?
(1.0) c.
How is the other charging pump made inoperable?
(1,0)
QUESTION 7.09 (1.50)
MATCHING:
A 25 year old radiation worker's total lifetime doce is 10 Rem and his NRC Form-4 is up to date.
His personnel monitoring devices are read for the first week of the quarter with the following results:
500 arem-whole body; 500 arem-skin;.3000 arem-extremities.
What are his dose limits for the remainder of the quarter for:
(Each of the values below may/may not be used more than once.)
a.
Whole body
- 1. 25 Rem b.
Skin 2.
15.75 Rem c.
Extremities
- 3. 7 Rem
- 4. 2.5 Rem i
i
(***** END OF CATEGORY 07 *****)
8.
ADMINISTRATIVE PROCEDUnrR. CONDITIONS. AND LIMITATIONS PAGE 14 QUESTION 8.01 (3.00)
During the. shift, the control operator reports that the plant is being operated in violation of a safety limit.
a.
What are the " Safety Limits" of concern?
(1.0) b.
Where could you obtain information on action to taken?
(1.0)
A A d m ag &4 w p_
c.A Who are Akindividuals or organizations you would make immediate reports to?
(1.0) i l
QUESTION. 8.02 (1.00)
From cold shutdown manning requirements, what extra personnel must be on duty prior to exceeding 200 F RCS temperature?
(1,0)
QUESTION 8.03 (2.00) l i
a.
What are 3 leak detection systems mentioned in the Unit 1 Technical Specifications bases that can detect a leak of 1
1 spa in a matter of hours?
(1.0) b.
What are the 3 Area Radiation Monitors addressed in the Radiation Monitoring Section (3.5.10) of SONGS-1 Technical Specifications?
(1.0)
QUESTION 8.04 (1.00)
Under what two conditions may containment integrity be relaxed when the Reactor Coolant system is not open?
(1.0) l I
I l
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 15 i
QUESTION 8.05 (2.00) a.
According to Operations Division Procedure SD123-0-14 " notification and reporting of significant events", in what time period must phone notification to the NRC operations center be made if a plant safety limit is exceeded?
(1.0) b.
Whose responsibility is it to ensure that proper notification is made and documented if the Compliance Division Duty Manager is unable to complete or make the required notification?
(1.0) j QUESTICS 8.06 (2.00) i a.
During modes 1-4, under what two conditions can the Shift i
Superintendent leave the protected area of the plant?
(1.0) b.
How does the Shift Superintendent contact the control room if he is outside the protected area.
(1.0) 1 1
b d e-0"".SJI O" 0.07 (1.00) t
" hr -t:t SMM+ne-le-the 4hif t-Superintendent-NOT-authorised-t<w cocovee-te M:h 2 fellow 4ng--e-reactor-trip?
(1A)
QUESTICN 8.08 (1.00) a.
What is the primary actione/ goal of the operations personnel if they find themselves in an emergency situation that is not covered by approved procedures?
(0.5) b.
Who may authorize departure from a license condition or Tech.
Spec. during an emergency condition when no action consistant with license conditions or Tech Specs can provide adequate protection?
(0,5)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
8.
ADMINISTRATIVE PROCEDURES. CONDITIONfi. AND LIMITATIONS PAGE 16 QUESTION 8.09 (1.00)
What must be done prior to using any uncontrolled (pink) procedure (operating or administrative) to perform work?
(1.0)
QUESTION. 8.10 (2.50) a.
According to SO1-VIII-1, " Recognition and Classification of EMERGENCIES", when is an emergency event not required to (0.5)
I be declared?
L b.
What TWO conditions would require the considering of a Precautionary Event Declaration?
(1,0) i c.
List the persons by job position / title who are to be contacted if there is a question concerning classification of an emergency?
(1,0)
QUESTION 8.11 (2.50)
What FIVE items require prior specific authorization of the Emergency Coordinator according to " Emergency Plan Implementing Procedure",
S0123 VIII - 20 (Emergency Planning Coordinator Duties)?
(2.5 i
QUESTION 8.12 (2.50)
Fill in the blanks for the following according to the PRICAUTIONS of SO1-3-1 " Plant Startup from cold shutdown to Hot Standby".
a.
During Mode 5:
The reactor shutdown margin shall not be reduced below 4 delta k/k with RCS temperature less than
__F.
(1.0) b.
General:
Positive reactivity changes shall not be made by rod drive motion whenever is not intact.
(0.5) c.
During Mode 5:
RCS pressure and temperature should not exceed psig and F when RHR is in service.
(1.0)
(***** CATEGORY 08 CONTINUID ON NEXT PAGE *****)
_...,.-y y
8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 17
~
QUESTION 8.13 (1.50)
TRUE or FALSE?
a.
The Control Room Supervisor can authorize the position checking of a manual valve by moving it in the open direction.
(0.5) l b.
Kero test packless valves shall not be used to throttle flow.
(0,5) c.
Manually seating a HOV in the Safety position may cause it to be unable to overcome the opening / closing torque and therefore is declared perable until operated electrically.
(0.5) 4 l
QUESTION 8.14 (2.00)
There are four manners in which work authorization can be given according to SO123-0-114 " Equipment Control Program".
When would the following authorizations be utilized?
(2.0) 1.
Permission 2.
Approval l
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
EQUATION SHEET d
f = ma y = s/t Cycle efficiency = (Net work out)/(Energy in) 2 w = mg s = V t + 1/2 at 3
E = mc
,gg KE = 1/2 mv a = (Vf - V )/t A = AN A=Ae a
c PE = agn Vf = Y, + at
- = e/t
.t=
tn2/t1/2.= 0.693/t1/2 1/2*ff
- EI*UII**)3 2
nD
[(g /2),(g y) j A=
1 b
- .E = 931 u m = V,yAo 7,g,-Ex O
Q = mCpat Q = UA A T I=Iec Pwr = W sh
.I = I 10** O f
o TYL = 1.3/u sur(t)
HVL = -0.693/u P = P 10 O
P = P e / *'
t o
SUR = 25.06/T SCR = 5/(1 - K,ff)
CR = 5/(1 - K,ffx) x CR (1 - K,ffj) = CR II ~ keff2)
SUR = 2So/t* + (a - o)T g
2 T = (t=/a) + ((s - oV Io]
M = 1/(1 - K,ff) = CR)/CR, T = 1/(o - s)
M = (1 - K,ffo)/(1 - K,ffj)
T = (a - o)/(Is)
SOM = ( -K,ff)/K,ff a = (K,ff-1)/K,ff = 4K,ff/K,ff t= = 10 seconds I = 0.1 seconds o = [(t*/(T K,ff)] + (i,ff (1 + IT)]
/
l j=Id I;d 2,2 2 l
l P = (taV)/(3 x 1010)
Id gd j
22 2
I = *N R/hr = (0.5 CE)/d (meters)
R/hr = 6 CE/d2 (feet)
Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem.
1 curie = 3.7 x 1010dos I ga]. = 3.78 liters 1 kg = 2.21 lba 3 Stu/nr 1 ft4 = 7.48 gal.
I np = 2.54 x 10 Density = 62.4 lbe/ft3 1 nne = 3.41 x 106 5tu/hr censity = 1 gm/enr8 lin = 2.54 cm Heat of vaporization = 970 Stu/lom
- F = 9/5'C + 32 4
Heat of fusion = 144 Stu/lbm
'C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.
1 BTU = 778 ft-lbf i ft. H O = 0.4335 lbf/in.
2
.l
5.
THEORY OF NUCMAR POWER PLANT OPERATION. FLUIDS. AND-PAGE 18 THERMODYNAMICS ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
MASTERCOPY ANSWER 5.01 (2.50) a.
1 (Increases)
[1.0]
b.
1.
Acceptable core power' distribution.
2.
Limit the potential reactivity insertion (due to an ejected rod) 3.
To ensure core suberiticality after a reactor trip.(c/ 7A soM
[0.5 each]
(1.5)
REFERENCE SHNPP Technical Specifications 3.1.1.1; RT-LP-3.13, p 7-9.
SONGS TS 3.5.2; Lesson B-7, p 6-9.
ANSWER 5.02 (2.50)
- a. SAME
- b. 4?ICT! Md
- c. HIGHER
- d. SAME
- e. LOWER
[0.5 each]
(2.5)
REFERENCE SBNPP RT-LP-3.13, p 10-15 and RT-TP-262.
SONGS Lesson B-7, p 10-13,e.o w e s a 66ue4 A.: 3 ANSWER 5.03 (2.00) i-a.
Decreases [0.25]
Pu 239 concentration increases (while U 235 concentration decreases) [0.75].
(1.0) b.
Larger SUR.
(1.0)
REFERENCE SHNPP RT-LP-1.6, p 23,24.
SONGS Lesson A-7, p 10-14, 20-22.
5 l
l
5.
THEORY OF NUCMAR POWER PLANT OPERATION. FLUIDS. AND PAGE 19 THERMODYNAMICS ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 5504 (1.00) a.
True b.
True
[0,5 each]
REFERENCE SHNPP RT-LP-1.9, p 19; RT-LP-1.10, p 11-16,20-22.
SONGS Lesson B-1, p 45-49.
ANSWER 5.05 (2.00) a.
- 1. Higher fission yield.
- 2. Larger (thermal) absorbtion cross section (1.0) b.
Disagree [0.4] Equilibrium Sm concentration is not power dependent.[0.6]
(1.0)
REFERENCE SENPP RT-LP-1.11, p 9-21.
SONGS Lesson B-1, p 52-55.
ANSWER 5.06 (1.00) b REnxENCE Westinghouse Reactor Physics, pp. I-5.12, 25, and 27 SHNPP RT-LP-1.10, p 14,15.
SONGS Lesson B-1, p 38-51.
ANSWER 5.07 (1.00) b REFERENCE Westinghouse Reactor Physics, pp. I-5.26 & 27 SHNPP RT-LP-1.10, p 13-15.
SONGS Lesson B-1, p 38-51.
l l
5.
THEORY OF NUC M AR POWER PLANT OPERATION. FLUIDS. AND PAGE 20 THERMODYNAMICS ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 5'.08 (1.00) b REFERENCE Westinghouse Reactor Physics, pp. I-4.19 - 21.
SHNPP RT-LP-1.7.
SONGS Lesson A-8, p 15-18.
ANSWER 5.09 (1.00) d REFERENCE Westinghouse Reactor Physics, Section I-5, MTC and Power Defect SHNPP RT-LP-1.6, p 36-41.
SONGS Lesson A-7, Handouts on reactor transients; B-1, p 38-51.
ANSWER 5.10 (1.00) e REFERENCE Westinghouse Reactor Physics, pp. I-5.2 - 16 SHNPP RT-LP-1.10, p 0-12.
SONGS Lesson B-1, p 42-45.
ANSWER 5.11 (2.50) a.
- 1. REMAIN THE SAME
- 2. DECREASE
- 3. INCREASE
- 4. DECREASE b.
Superheated.
[0.5 each]
REFERENCE Steam Tables and Hollier Diagram.
SHNPP FF-LP-1.1, p 32-34.
~
1
5.
THEORY OF NUC MAR POWER PLANT OPERATION. FLUIDS..AND PAGE 21 THERMODYNAMICS ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 5512 (1.00)-
b REFERENCE SHNPP FF-LP-1.1, p 27-30.
~~", J SONGS-General Physics HTFF, p 319,320; W W '
~*
si :F" -'D, f. 44
=
ANSWER 5.13 (1.50)
- a. True
- b. False
- c. False
-[0.5 each]
REFERENCE Westinghouse Thermal Science, Chapter 10, Pp. 41-49 SHNPP FF-LP-1.1, p 21-23, 27-30.
SONGS-GP-HTFF, p 320-322.
ANSWER 5.14 (1.00) a.
REFERENCE SENPP Thermo-LP-1.1 and steam tables KA002/000,K5.01,3.1 Cook-Westinghouse Thermal Science, Chapter 2,Pp 63-70,79.
/020,K5.06,3.4 SONGS-GP-HTFF, p 83.
ANSWER 5.15 (1.00) c l
REFERENCE l
General Physics, HTFF - Fluid Flow Applications for Systems and Components.
l SHNPP T&AA-LP-1.19.
\\
5.
THEORY OF NUCWAR POWER PLANT OPERATION. FLUIDS. AND PAGE 22 THERMODYNAMICS 85/12/17-ISAKSEN, P.
ANSWERS -- SAN ONOFRE-1 ANSWER 5.16 (1.00) e REFERENCE Steam Tables ANSWER 5.17 (2.00)
~
l NI power would be adjusted to indicate a lower value than actual reactor Power [1.0].
This is caused by the lowering of the average feedwater temperature vs. the indicated feedwater temperature used in the (2.0) calculation-[1,07 4 ass p
- A
._j.
g.
& h -
x-:==
4W-A e =_4== %%_
~ J. = s_
1 M.
REFERENCE Steam Tables and Hollier chart I
)
m.,-- -
.,..,-,,-.--,.,,>n,
,,,,-,...-,-e
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 23 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
j
~.
ANSWER 6.01 (1.00)
The failure of any component to respond actively in the prescribed manner after the occurance of a first order condition.
REFERENCE SONGS I, SD-S01-580, page 6 m.e
-.m
-p--, -.-
y
~
~
b.__ELONI_gYgIgdS_QESl@h _QQNIBQ(x_8NQ_lN@lBQUENI@IlgN PAGE 24 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
2 ANSWER 6.02 (3.00)
Programming Tavg ove(r) automatic controlled power range a.
1.
i PREFERRED METHOD. l It utilizes higher steam pressure at full load for turbine efficiency and does not cause a change in reactor design conditions (Th) and S/G design (no-load steam pressure is at normal zero power level).h)
(0.5) 2.
Maintain Tavg constant at full power Tavg NOTPREFERRED.bh No load S/G pressure would be high creating a need for heavier S/G shell andpipingmaterials.(.4)
(0.5) 3.
Maintain T' avg constant at no-load Tavg NOTPREFERRED.(.h The full load steam pressure would be lower causing reduced turbine output.
The decrease in steam pressure would be steeper.
22==,s i t i -.= :::12 ;; ::t
- :; i;;ig
%.(.'O= 1:
to.5) 6.
FIGURE A FIGURE B FIGURE C I
e
/
\\
f d '
j s'
n T-T y
< r./
s s
\\
s N
i P\\
P N'
P PRESS.t TEMP.
0 POWER IdO5 160%
160%
(1.5)
Programmed Tavg.
Constant Tavg.
Constant Tavg.
9 Programmed 9 Programmed No Full Power Load Tavg.
REFERENCE SONGS, 80-60I-200, Appendix D i
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 25 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 6.03 (4.00) a.
Reactor trip and start of D/G's o breaker closure or auto loading 8' Also activationQo tainment Isolatiog.apshdAhe.daupto.4.nh aMsr) ypm ~
C:stsi7-t S,adsye. (ood.ng 7
b.
Start of D/G's.
Mobreakerclosureorautoloading.[
(0.5)
ReactorTripandstartofD/G's[nobreakerclosureorauto c.
loadingfr (0.75) d.
Reactor Trip, start of D/G's, closure of D/G breakers, sequential loading of emergency safeguards equipment on buses, actuation of Containment Isolation.srd Centei----t errer (1.5)
REFERENCE SONGS, Bd-SOI-590, page 4 ANSWER 6.04 (2.50) a.
FCV-1112 will open for an SIS event immediately [0.5] and after 11 sec during a SIS / LOP event [0.5].
(1.0) b.
The pump will trip off [0.25] will restart 21 seconds after power is restored [0.25].
(0.5) c.
There is a pushbutton override control on the unit console [0.75]
whf ch overides the solenoic causing the valv@b c.d.\\lec.
c cle : [0.25].
(1.0) do ce.ve,-t. 4.
as.nz c e b ll=1 h REFERENCE SONGS SC "1S, ; ::: I? :nd le :nd SOI 1.0-20 Sb - sol-SSD,
P, ed 14
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 26 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
I ANSWER 6.05 (2.00) i a.
If the system were normally grounded and another ground occurred on the opposite bus, malfunctions such as low bus voltage or false relay operations may occur.
(1.0) b.
Positive and negative system voltmeters to ground will show an imbalance [0.25] and a 10% ground will be annunciated [0.25).
(0.5) c.
Open main DC panel distribution switches to determine which circuit is affected [0.25].
Then each component is isolated, pinpointing the ground [0.25].
(0.5)
REFERENCE SONGS, SG #85, pages 7 and 8 ANSWER 6.06 (2.50) a.
1.
Refueling water pumps 2.
Hydrazine pumps and discharge valves 3.
Sphere spray valves
[0.25 each]
(0.75) b.
To washdown particulate matter, absorb airborne iodine and reduce sphere pressure.
[0.25 each]
(0.75)
Na3 PO4 to increase pH and minimize chloride stress corrosio ah ( *nc c.
of stainless steel components y hydrazine to absorb iodine g (0
d.
Open (MOV 880) refueling water pump crosstie to recirculation system.
(0.5)
REFERENCE SONGS, SG #17, pages 2, 6, 7, and 9 I
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 27 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 6.07 (1.50)
Feed flow is directly proportional to the square root of the differential pressure developed across the flow element, thus a square root must be extracted [0.5].
The same applies for steam flow plus density change must be inputted due to changing steam pressure [0.5].
Level change is a direct linear relationship with differential pressure change, so computers are not necessary
[0.5].
(1.5)
REFERENCE SONGS, SG #62, pages 2 and 3 I
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATIQH PAGE 28 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
O ANSWER 6.08 (2.00) h S t*.,'1S*. 2,'? RCP ' r er =+ 4 as Mtb,
0, d % b h f.
1.
P-1, Overpower Rod Stop a.
Setpoint :
b.
Coincidence = 1 channel of 4 PRNI increasing to setpoint c.
Function = prevents manual or auto rod withdrawal and blocks raise signal to the governor speed changer to halt power rise.
2.
P-2 Low Power Cutout of Automatic Rod Withdrawal.
a.
Setpoint = 15% of full load, b.
Coincidence = none c.
Function = prevents automatic rod withdrawal when MWe load (1st stage Press) is below preset value.
P-3, Rod Drop Rod Stop 3.
Setpoint = 5% decrease in power instantaneouslyer I f W W M U '* M -
a.
b.
Coincidence = 1 of 4 PRNIs having dropped rod indication.
c.
Function = prevent automatic rod withdrawal and initiate turbine load limit runback to 70% power.
4.
P-4, Steam Dump Automatic Mode Cutout a.
Setpoint : To unblock automatic steam dump a decrease
> or = 45 MWe within 10 sec. is required.
b.
Coincidence = none - PT417 c.
Function = Blocks automatic operation of the steam dumps when Tava-Tref setpoint deviations are reached unless the above decrease in HWe load has occured.
5.
P-5, Shutdown Margin Low Alarm (Minimum Insertion Alarm) a.
Setpoint = variable with delta T and Tavg.
b.
Coincidence = none - one for each control bank.
c.
Function = to warn operators of possibility of inadequate shutdown margin as determined by shutdown margin computers.
6.
P-6, Hi SUR Rod Stop a.
Setpoint = 2 dpm b.
Coincidence = 1 of 2 S.R. or I.R.
c.
Function = prevents manual and auto rod withdrawal while high startup rate condition existsinnd p: :r ir heler. 7 ';hich tieci; ";t ;;;;r trip:"'.
7.
P-7, At Power Reactor Trip Defeat a.
Setpoint = N.I.S. < or = 10% of full power.
Turb. 1st stage Press < or = 10% of full power.
b.
Coincidence = 3 of 4 Power Range N.I. Channels less than or equal to setpoint and turbine 1st stage pressure less than or equal to setpoint. L c.
Function = Defeat the (64*e) at power reactor trips and to activate or enable.the high startup rate trips.
8.
P-8, Single Pump Loss of Flow Reactor Trip Defeat a.
Setpoint = NI MWe (1st stage Press.) < or = 50% of full power / load b.
Coincidence = 3 of 4 PRNIs less than setpoint AND turbine 1st stage pressure less than or equal to setpoint.
c.
Function = Defeat the reactor trip from single loop low flow trip and single RC pump breaker open trip and alarms.
6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 29 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
o PEFERENCE SONGS, SG 12, pages 7 and 9 ANSWER 6.09 (3.50) a.
1.
Loop'T-ave recorder 2.
Loop variable low pressure trip 3.
Hi/Lo alarm 4.
Average T-ave computer
[0.25 each]
(1.0) b.
1.
Average Tave - Tref computer 2.
Control rod drive summing computer 3.
SDM computer 4.
Feedwater control valves 5.
Par. level setpoint 6.
Average Tave - T ref deviation alarm 1
7.
Ave T ave - T ref recorder
[any 6, 0.25 each]
(1.5) c.
1.
Average Tave and average Delta T (0.5) 2.
Loop Tave and loop Delta T (0.5)
REFERENCE SONGS SG 12, pp 2,3,7 ANSWER 6 10 (3.00) E,Ju-htd bred-e(~'%
a.
Turbine soleniod trips,dopening 220 KV breakers and aux.
transformer breakers [0.75).
This indirectly opens the exciter breaker, trips the RCP's and reactor (0.75).
(1.5) b.
1.
Energize 4160V busses 1A and 1B from the switchyard via "C" transformer.
(0.5) 2.
Pick up 1A and 1B transformers from switchyard via "C" transformer [0.5].
Open generator disconnect and close 220 KV breakers,-
reenergizer bus 1A and 1B via the "A" and "B" aux transformers.
[0.5]
(1.0)
REFERENCE SONGS SG #81, pages 1-3 f
I l
i
7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 30 RADIOLOGICAL CONTROL ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 7:01 (2.50)
(At least 21 steps)above RIL [037]r}o maintain a.
1.
aufficient SDM.[0.~575]
t= *cJ w 2. U = - y w-'y ~_> e ;- A & M 9o % u.Lud w 2.
Sc :=her belew 305 ste tv yrovider uvrai,s ul ei " Life" r
=ha"1d action become7ecessaiy.[G.5] '-
(1.5)'
& ys$g
~_ y '- - C
- vb +. p, _ _ :_.+ m '= = A q,.A. Mn b.
Perrodically 'da c' a e axial offset using values from NIS detector currents C.uW 2-
_ _ ef s e !==. --4= % ak,)
(1.0) l REFERENCE SONGS SOI-3-3 p.
12, 13, and T.S.
3.11, 3. -C. 2 ANSWER 7.02 (2.50) a.
Put control rods in manual.
(0.5) b.
Loop variable low pressure trip.
(0.75) a z
,y ar _ w '= 4.
JL/a c.
To4 minim ze differential temperature between affected and unaffected loops [0.5],so a large temperature change will not be seen by the core on RCP restart (0.5) resulting in a power excursion.[0.25]
(1.25)
REFERENCE SONGS SOI-2.1-1, p 2,3 ANSWER 7.03 (3.00) a.
The cooldown rate will be limited by the ability of the charging system to maintain pressurizer level.
(1.0) b.
Leak rate will decrease as RCS pressure decreases.
'Will u.
' ---Mef seellei-RGB-vplae. vhangs at--
1;Les u y=_3,i c=yerature for 1/2-oredit-),(,
- - A e4=p p.---gJ,y y.(.1.0) i,
~>p>~
-a y n v,e _+ a 4 -s y s
. r.s) c.
Concern for possible RCP damage when operating under conditions of inadequate subcooling.
(1.0)
7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PATE 31 RADIOLOGICAL CONTRQL ANSWERS -- sad ONOFRE-1
-85/12/17-ISAKSEN, P.
REFERENCE 2f SONGS SOI-1.0-22, pp. 3,6, and BKG. p 8' ANSWER 7.04 (2.00) a.
1.
Sample shows an increase by a factor of 10.
2.
Containment Sphere high rad. alarm (R-1232).
[0.5 each)
(1.0) b.
Prevents the release of activity in the event of a SGTR, since sat uration pressure is less than the lif t pressure of an atmosph-eric relief valve. [1.0)
(1.0)
REFERENCE SHNPP AOP-032, p 3; TS bases 3/4.4.8.
1 SONGS SOI-2.1-15, p 2; TS 3.1.1 ANSWER 7.05 (3.00) a.
- 1. Overpower 1
- 2. Variable low pressure
- 3. High pressurizer pressure
- 4. High pressurizer level
[any 3, 0.33 each)
(1.0)
- b. Variable low pressure trip (0.5) l
- c. Severe flux tilt (0.4] could cause fuel overheating and damage in high flux areas of the core. [0.4]
(1.0)
- d. Adequate shutdown margin (0.5)
REFERENCE SONGS SOI-2.3-1, Pp. 8,10,12; ys 3.s.s g 3 33 I
I
7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 32 RADIOLOGICAL CONTROL
+
ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
1 ANSWER 7.'06 (4.50) a.
Reviews all steps and determines whether.they need to be Performed based on plant conditions.
Complete abnormal alignment / evolution checklist listing steps required (according to SOI-14-43).
(1.0) b.
Comments made for each step not performed, close out procedure (and filed).
(1.0) c.
Initial impulse chamber metal temperature below 200F.
(0.5) d.
Feedwater flow reduced to (or maintained) less than 100"gpm until level above feedring (264).
(1.0)
/5D s
hring r;;:t^
st er+'& pt Af y p-m g (gy)
(1.0) e.
REFERENCE SONGS SOI-3-2, pages 2-7 ; TT p 4-7.
ANSWER 7.07 (3.00) a.
Insert control rods AND runback turbine load limit.
(1.0) b.
When the reactor is shutdown AND any uncontrolled cooldown is stopped.
(1.0) c.
To remove excess heat generation in the core (capable of running l
heat 10 minutes after a loss of feedwater with ATWS) by ensuring steam generator feed is available.
(1.0) j REFERENCE SONGS SOI-1.1-1, pages 3, 13, 23
7.
PROCEDURES - NORMAh. ABNORMAL. EMERGENCY AND PACE 33 RADIOLOGICAL CONTROL, ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
i ANSWER 7:08 (3.00) a.
By using RCS vent valves.
(1.0) b.
The mass addition pressure transient can be relieved by the required operable overpressure protection system (s).
(1.0) i i
c.
The motor breaker is racked out and caution tagged.
(1.0)
REFERENCE SONGS SOI-2.1-11, page 3 ANSWER 7.09 (1.50)
- a. 4 (2.5)
- b. 3 (7)
- c. 2 (15.75)
(0.5 each]
REFERENCE SHNPP RP-LP-1.3, p 10.
SONGS HP SO123-VII-4.0, pages 6 and 10; 10 CFR 20 i
8._
ADMINISTRATIVE PROCEDURES. CONDITIONS _AND LIMIIATIONS PAGE 34 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
4 ANSWER 8.,01 (3.00) o.
1.
Reactor Coolant System pressure (2735).
(0.5) 2.
Improper combinations of Reactor Coolant System temperature and pressure as well as nucleer power.
(0.5) b.
Technical Specifications or 10 CFR10.(36)n s o ia.s - = -49 (1.0)
Plet bjer-mbded-c.
1.
Vic: S:: id::t S Sit: "r
- rr (0
2.
NARG-e eeeeen STA (0
-3.
"" O "__ --
' O. 30F 60 43 o g )l4 REFERENCE SONGS T.S. 2.0, 6. 7 '3 ANSWER 8.02 (1.00) 1.
'/. AN'*"*l 0
4AH
'O.5) 2.
Control Foom Supervisor
[. Ai soc.C (J.o) 3.
AMaenoA oPco REFERENCE SONGS T.S. 6.2.2.2 and SOI-1-3 p.
5 ANSWER 8.03 (2.00) a.
1.
Sump level 2.
Radiation monitoring 3.
Humidity indication (0.33 each]
(1.0) b.
1.
Control room 2.
Spent fuel pool area 3.
Containment radiation-high range (0.33 each]
(1.0)
REFERENCE SONGS Tech. Specs. 3.1.4, 3.5.10 and 3.6.1 l
)
)
8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONE PAGE 35 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 8.04 (1.00) 1.
Pressure less than 500 psig (0,5) 2.
SDM greater than 14 delta k/k (0,5)
REFERENCE-SONGS Tech. Specs. 3.1.4, 3.b.10 und 3.6.1 ANSWER 8.05 (2.00) a.
I hour (1.0) b.
Shift Superintendent (1.0)
REFERENCE SONGS 1 SD 123-0-14 ANSWER 8.06 (2.00) a.
1.
Fire or other emergency occuring on-site but outside the protected area requiring assessment of impact on continued operation by the Shift Superintendent.
(0,5) 2.
Brief visit to AWS building for conduct of business.
(0.5) y\\ anEL b.
TWO-WAY radio or t
(1.0)
REFERENCE SONGS SD123-0-30, page 5 f."CT:".
".07 (1.00)
If CA""! Of th: trip 1: "MPETERMIFE9 [0.5) AMD 211 eignifieret
- ::t: O f = TRANSIENT-eee-NOT-wet,1,-UNDERSTOOD - [ 0. 5 ) ;
-( 1. 0 )
REFEREN05-60NGG-GOl-14-27, p:;;; 3
8.
AMINISTRATIVE PROM nun n. CONDITIONS. AND LIMITATIONS PAGE 36 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 8.08 (1.00) a.
Stablize the plant (0.5) b.
Shift Superintendent (0.5)
REFERENCE SONGS SO1-14-42, page 3-A ANSWER 8.09 (1.00)
Verify that it is current (0.5] by checking it against a controlled copy d any TCN's (0.5].
(1.0) and REFERENCE SONGS Procedures prerequisite (ALL)
ANSWER 8.10 (2.50) a.
If conditions are corrected within 15 minutes of recognition.
(0.5) b.
1.
Events which constitute a significant trend leading to t
degradation of safety.
(0.5) 2.
Trends indicating an imminent mode change which would activate an EAL.
(0.5) c.
Unit Superintendent AND Emeriancy Planning Coordinator.
(1.0) j
[0.5 each]
REFERENCE SONGS EPIP SD1-VIII-1
8.
ADMINISTRATIVE PROCEDUMR. CONDITIONS. AND LIMITATIONS PACE 37 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
ANSWER 8.11 (2.50) 1.
Emergency Event Declaration 2.
Notification of offsite agencies 3.
Precautionary plant / site evacuation 4.
Offsite protective action recommendation 5.
Exceeding 10 CFR 20 exposure limits REFERENCE SONGS EPIP SO123 - VIII - 20, p 2
[0.5 each)
(2.5)
ANSWER 8.12 (2.50) a.
5, 4M.1oo (1.0) b.
Containment integrity (0.5) c.
400, 400 (1.0)
REFERENCE SONGS, SO1-3-1, pages 3 and 7 ANSWER 8.13 (1.50) a.
F (0.5) b.
F (0,5) c.
Jf (0.5)
REFERENCE SONGS, S01-14-17, pages 2, 3 and 4
A.
ADMINISTRATIVE PROmnUpra. CONDITIONS. AND LIMITATIONS PAGE 38 ANSWERS -- SAN ONOFRE-1
-85/12/17-ISAKSEN, P.
e ANSWER 8.14 (2.00) 1.
To work on a piece of equipment only when the equipment cannot be fully de-activated for issuance of a clearance.
2.
To work on a system or a piece of operating equipment for which a clearance cannot be issued AND should be of short duration.
(1.0 each)
(2.0)
REFERENCE SONGS, 50123-0-114, page 6 I
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l Y RESOLUTION OF FACILITY COMMENTS FOR SONGS-1 GRO EXAM Section5 5.12 Facility Comment:
Initial facility provided reference did not address required NPSH for given condition in question and the required NPSH does not change.
NRC Resolution:
Westinghouse Thermal Science, Chapter 10, Page 49 does address the condition given in question l
and the answer is correct.
This additional re-forence was available at the facility and added to the initial supplied reference sent by the facility.
No change to answer.
5.17 l
Facility Comment:
AFW flow bypasses feedflow measuring devices so lower mass flow indicated would also result in lower NI indication compared to actual.
NRC Resolution:
Comment accepted as additional correct response answer key modified.
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SECTION 6 Facility Comment:
6.02 System description appendicles not required information.
Reworded answer attached.
NRC Resolution:
The answer suggested for 6.02 part "a" is essentially l
the same as the answer key. therefore the key was j
left as is.
In part "b",
the facility wants partial credit if S/G temperature is plotted vs pressure.
In the saturated S/G, these would produce essen-tially the same curve as temperature and pressure follow each other. The key was left unaltered.
Facility Comment:
6.03 a)
Add - immediately loads ESF (SI) equipment on buses, delete containment spray.
(
6.03 d)
Delete containment spray.
NRC Resolution:
Comments for both "a" and "b"
- accepted, Answer Key changed accordingly.
Facility Comment:
6.04 c)
FCV 1112 does not close when overridden.
Returns to normal operational control.
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NRC Resolution:
Comment accepted, Answer Key changed accordingly.
Facility Comment:
6.06 c)
Question aaks for chemical (Singular).
Answer has two parts.
Only one should be required.
NRC Resolution Comment accepted, Answer Key changed accordingly.
Facility Comment:
6.08 PI Setpoint 20% i 1 70-801 106 i i 1
P-3 Setpoint...And 1/45 LVDT's on rod position indication P P-7 should not be part of answer P-7 Delete ( five) under function See References in Answer Key NRC Resolutions Comments accepted, Answer Key changed accordingly.
I In P-7, the five was not deleted but altered to four.
l Facility Comment:
6.10 a) Question is open ended add " Exciter i
Field Breaker" and question is not clear that indirect answers are required.
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NRC Resolution:
Exciter Field Breaker added to Answer Key.
Grading of question was not based on candidate referring to the trips as direct or indirect.
Grading was done solely on the statement of the actions occurring.
Facility Comment:
6.10 b)
Question sho'uld read " Unit Differential" vice " Generator Differential" Generator differential is electrically identical to Generator Loss of Field.
NRC Resolution:
Question was graded using the answers for parts 1 and 2 for each part.
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7.01a.2 Facility Comment:
Replace answer with TS 3.5.2 A and B.
NRC Resolution:
Comment accepted, answar and reference modified.
7.02C Facility Comment:
Add reverse delta-T interlock and TS requirement for <10% power RCP restart.
NRC Resolution:
The reverse delta-T interlock will be incorporated into the answer since supporting reference material provided supports the interlock which serves to minimize the differential temperature between affected and inaffected loops.
The TS require-ment is not accepted.
The requirement allows for continued operation with 1 or 2 loops in service for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. TS also allow I hour beforo Hot Standby with power above 104 and does not support an initial condition for the RCP restart.
7.03b Facility Comment:
Add charging pump capacity increases and why only half credit for volume change versus temperature.
NRC Resolution:
Partial credit will be given for both charging pump capacity and volume changes however de-creasing the leak rate with lower RCS pressure is more significant and required for full credit.
7.05c and d Facility Comment:
Add TS references for parts e and d.
NRC Resolution:
Included additional reference for part c.
Part d is adequately supported by existing reference page 12 and therefore not included.
7.06 d and e Facility Comment:
Part d answer ' typo
- 150 vs 100 and part e TS changes require additional RO prior to exceeding 200-F (entering mode 4)
NRC Resolution:
Both comments accepted and answers and reference modified.
7.07 and 7.08 Facility Comment:
Subsequent action steps not required yet asked here.
NRC Resolution:
Comment noted.
Candidates are expected to know system / system interrelationships and cautions and limitations of procedures including the objectives and methods used in procedures per NUREG-1021, ES 202 page 2 and 3, 402 page 3.
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O SECTION 8 Facility Comment:
8.01 c)
Immediate reports required to Plant Superintendents and STA not V.P. &
NARC Chairman.
8.02 New T.S. adds also additionally NPE0 and additional R.O.
8.06 b)
Contact by phone also valid answer 8.09 Typo
" Controlled and any TCNS" 8.12 a)
During Mode 5 changes answer to 200"F vice 350*F NRC Resolution:
All above comments accepted, Answer Key changed accordingly.
Facility Comment:
8.07 Entire procedure replaced Q&A no longer I
valid.
Request delete question.
NRC Resolution:
Comment accepted, Question 8.07 deleted.
Facility Comment:
8.13 All answers reversed.
See Answer Key.
NRC Resolution:
Investigation of parts "a' and "b' sustained j*
the Answer Key.
In part "a",
permission must be granted by the SRO Operations Supervisor, not the Control Room Supervisor as stated.
j (Precaution 4.6 of SOI-14-17).
In part "b",
Kerotest Packless valves can be throttled for testing making the test statement false i
(precaution 4.10, 501-14-17).
Part "c" answer was in error, Answer Key was changed.
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