ML20127H503
| ML20127H503 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/16/1985 |
| From: | Ferrell R, Hemming B, Higgins R, Jaggar F, Mcmillen J, Reidinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20127H470 | List: |
| References | |
| 50-282-OL-85-01, 50-282-OL-85-1, NUDOCS 8505210313 | |
| Download: ML20127H503 (118) | |
Text
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U.S. NUCLEAR REGULATORY COMISSION REGION III~
Report No.'-50-282/0L-85-01
-Docket No. 50-282/306'
.Licens'e Nos. DPR-42; DPR-60 Licensee:
Northern' States Power Company 414 Nicollet Mall 1'
Minninapolis, MN 55401 I
Facility Name:
Prairie Island Nuclear Power Plant
- Examination. Administered At: ' Prairie Island Nuclear Power Plant Examination Conducted: -March 26, 1985 Examiners:.
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.-Approved By:
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j perating Licensing Section Datg /
Examination Summary Examination Administered on March 26; 1985 (Report No. 50-282/85-01)
- The applicants. consisted of three instant senior reactor operators and two
. senior reactor operators (upgrade), one instructor certification and three
. reactor operators.
Results:
One instant senior reactor operator passed,'two upgrade senior reactor operators passed and two reactor operators passed.
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x REPORT DETAILS 1.-
Examiners-T.:D. Reiding'er*-
F.1Jaggar..
- R.cHiggins' R.' Ferrell
.8.: Hemming.
- Chief' Examiner 22.
Examination Review Meeting See Attachment Number 1.
3.
Exit Meeting-Facility representation from operations and plant management and the examiners met on March 29, 1985.
- The-list of attendees at the exit meeting:
Ted Amundson, Supt., Training, NSP Ed Watzl, Plant Manager, NSP Lee Finholm,. Nuclear Training Admin., NSP Bill Waldron,. Instructor Supervisor, NSP Mike Hall, Lead Simulator Instructor Mark Reddemann, Tech Support Training Supr., NSP
- .~
Wayne Bell, Operations / Simulator Instructor Max J. Balk, Supt., Operations Richard Lindsey, Plant Supt., Operations and Maintenance Ron Higgins,-NRC. Examiner Joseph Gonyeau, Hanager Production Training Tim Reidinger,. Chief Examiner Ralph Ferrell,-NP.C-Examiner i
. Paul.Hartmann, RI F
. Jim'Hard, SRI l
F The Chief Examiner indicated which candidates passed the~ oral and.
m simulator phase of the examinatiens.
The generic weakness noted was the difficulty in the interpretation of the bistable trip logics for nuclear L
instrumentation (i.e., loss of a nuclear power range instrument PRA would E '
entail tripping associated bistables).
Determining which bistables to be tripped by the logic diagrams proved difficult in many instances. The Chief Examiner made comment that-the system-descriptions were out of date L
-in several instances, i.e., the reactor protection chapter in the
- training material still has the pre-TMI Westinghouse logic for safety f
injection; low pressurizer pressure coincident with low pressurizer level vice the actual logic only of pressurizer pressure utilized for safety injection.
The training department has committed to sending revised training material along with individual lesson plans for future NRC L
examinations.-
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ATTACHMENT 1 Resolution of Comments for Prairie Island SR0 Examinations conducted on March 26, 1985.
SECTION 5 - Theory Of Nuclear Power QUESTION 5.05 - FACILITY COMMENT:
Choice "c" refers to an arbitrary convention (only recorded in one place that I know) rather than something of substance.
EXAMINER COMENT:
The "one place" this " arbitrary convention" is recorded is the literature which the facility provided the examiners.
The answer key will be modified to also accept choice "c" as a correct response.
QUESTION 5.09 FACILITY COMMENT:
No correct answer available from choices.
Delayed neutrons are born at
EXAMINER COMMENT:
Choice "b" should have included the phrase "of uranium 238." Choice "b" is the only choice which is not completely incorrect, so choice "b" will remain the only correct response.
QUESTION 5.11 FACILITY COMENT:
For an example, if Tavg is decreased below program level while maintaining power level,- both moderator and fuel temp decrease thus l-inserting positive reactivity in accordance with the Isothermal Temperature Coefficient.
EXAMINER COMMENT:
The definition of " isothermal temperature coefficient" could not be located in any of the literature provided by the facility.
A reference belonging to the NRC examiner stated that the " isothermal temperature coefficient" is the sum of the moderator temperature coefficient and fuel temperature coefficient when the core is at the hot, no power condition.
However, Exxon fuel utilizes the " isothermal temperature coefficient" at power.
Therefore, the answer key will be modified to also accept choice "c" as a correct response.
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QUESTION 5.16 FACILITY COMENT:
Answer b and c also correct statements (besides a).
See attachment 1 for (b) Boron is.a 1/V absorber.
See attachment 2 for (c) per a Westinghouse text.
EXAMINER COMENT:
Though choice "c" does.not agree with the reference the NRC examiner used, choice "c" will be accepted as a correct response because a different reference was provided by the facility to substantiate their comment.
The average neutron energy when the moderator temperature is 547*F is.0482 ev., while the average neutron energy when the moderator is 560*F is.0489 ev.
The difference in neutron energies, and thus the difference in the probability of absorption, is very slight.
This very slight difference in absorption does not begin to account for the, large difference in differential boron worth, so choice "b" will not be considered correct.
-QUESTION 5.18 This question concerns fuel element burnup limitations and is therefore considered by the examiners to be more relevant for a reactor engineer than for a senior reactor operator.
This question will therefore be deleted.
QUESTION 5.25 This quertion concerns the incore flux reading, a subject which is the responsibility of the reactor engineers, not the senior reactor operators.
This question will therefore be deleted.
QUESTION 5.28 FACILITY COMMENT:
= Disagree with the answer key.
See attachment 3 for details for General Physics " Mitigating Reactor Core Damage."
EXAMINER COMMENT: states that the predominste sources of tritium in the reactor coolant are two reactions of boron-10, which are not mentioned as choices, diffusion of tertiary-fission tritium through the clad, and the reaction of lithium 7 given as choices "a" and "c", respectively, so the an,wer key will be modified to accept either "a" or 'c" as correct.
QUESTION 5.30 FACILITY COMMENT:
Answers b and d are very similar.
See Attachment 4.
What is the difference between " radial" shape and " horizontal" shape? BOTH ANSWERS
-SHOULD BE CONSIDERED CORRECT.
It's "not necessarily directly related" 4
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.doesn't mean it's'not related at all.
The FAH refers to th'e-integral
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of.all:the horizontal power levels (for a coolant channel) including
- the one with the maximum heat flux.-
I-believe=this statement refers to the fact thatL'the fuel element with' the maximum F does not necessarily also have the maximum FAH.
q EXAMINER. COMMENT:
- Choice "d" was developed by, changing a statement in the Technical Specifications from "is not necessarily directly related to" to "is
~ directly related to."
This modification renders the statement false by' making it conflict with the statement-in the Technical
. Specifications.
The answer key will therefore not be' changed or modified.
QUESTION S.31 FACILITY COMMENT:
The answer key shows required values.while the question doesn't require them. ; NUMBERS SHOULD NOT BE REQUIRED.FOR FULL CREDIT.
EXAMINER COP 91ENT:
- The question asks for th'e three DNB-related parameter limits which must be maintained during power _ operation.
Limits implies numerical values,
. so numerical values will be required for full credit.
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'SECkION 6. Plant Systemi Desig~n!
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' QUESTION 6.5 FACILITY COMENT:
' Refer to Requal.'SRO Question 6.5.
' EXAMINER COMENT:
- Examiner lhas deleted'the question based on additional electrical 2 schematics provided'by the utility.
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- QUESTION 6.6 (a)~& (b) FACILITY COMMENT:
a)'
We have " ele'ctric" Main Feed Pumps.
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We'would not experience an overspeed trip - we could trip on low suction pressure if it were to drop to 200 psig for 5 seconds - if both main feed pumps are off the turb trips and so will the Rx if we are-above'10%.
At PI,-if the second condensate pump were not vented'at all, the physical layout would not produce' loss of suction for sufficient duration to cause the: trip-of the Main Feed pump.
If it could, I concur with the rest of your answer.'
b)-
Load; spike (MWt) prior to trip disagree with this answer for the reasons you=gave, for the PI plant.
This question may elicit numerous responses depending on various assumptions made.
It is
- almost impossible to predict-the exact response and therefore a
. great-deal of judgement must be used in grading.this question.
PI is'not'that big.
1 EXAMINERS RESPONSE'(a) & (b):
a)
Examiner notes.that the answer key-stated that the main feed pump could cavitate which will result in fluctuations in flow which will be reflected throughout the feedwater system.
This will result'in steam generator levels reaching'the 1ow. level' trip setpoint, the coincidence' steam flow / feed flow mismatch with S/G low level will r.
be made up andlcause reactor trip.
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b)
Examiner disagrees with utility comment thnt a load spike will not
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occur from extraction' steam being diverted to the turbine vice being
. condensed in the feedwater heaters.-
Prairie. Island simulator
- malfunction menu's list feedwater-malfunction and heater malfunctions-in which the following statement is made.. this will result in a
~
momen ary increase in generator output followed by a decrease in t
generator output reflecting the loss in enit efficiency.
Any assumptions made-by the candidates will be duly considered and
. graded accordingly.
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(ANSWER 6.9'(a) FACILITY COMENT:
1Stop valves Lo en - stop valve closed (right and left) alarm goes out -
indicating ifghts.~~-(on alarm annunciator panel).
EXAMINER COMENTi Examiner will.i.ccept' additional answer.,
QUESTION 6.11 = FACILITY COMENT:
LSee Requal. SRO Exam 6.6 comments.
EXAMINER COMENT:
Examiner notes that this facility comment has no bearing or relationship
-to requalification examination question 6.6.
Possibility of an utility typographical error.
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SECTION 7 --Procedures QUESTION 7.5 (a) & (b) FACILITY COMENT:
e La)- LThe following should be, acceptable answers:
1.
~ Pressurizer Power Operator Relieve Valves (PORVs)
!2.
' Reactor. Makeup Water (Primary Makeup Water) t3..
Pressurizer Relief Tank Drain-Valve
^ 4. '
Pressurizer Spray Valves-5.
Pressurizer Relief Tank (PRT) Vent Valve:Versus Relief Valve 6.
Reactor Vessel Flange Leakoff Isolation' Valve
-b): The reference of X-Hiaw-1-39 is incorrect.
It should be X-Hiaw-1-38 and.the following answers should be acceptable:
1.
Letdown Isolation or Loop Isolation Valves (letdown valves).
' 2.
Letdown Orifice-Isolation Valves (letdown isolation) 3.
-Excess Letdown Divert Valve (for Seal Injection Return
- Re11ef)-
4.
Charging Line Isolation 5.
Auxiliary Spray 6.
Excess Letdown Hx. Inlet P
- 7.-
Excess Letdown.Hx Outlet
- 8.~
.RCP #1 Seal Bypass 9.
RCP Seal Water Return Isolations Full credit should'be considered for answers given for multiple valves such as 11 RCP Seal Water Return and 12 RCP Seal Water Return.
EXAMINER COMENT:
. Examiner agrees that reference number was a typographical error. Will JacceptLthe identica1' answers provided by the utility and will accept.each
~ additional answer for part a) and part b) (answers). -No credit will be E
given for multiple valves in the same generic category-(i.e., 11 RCP seal
-return and 12 RCP: seal return.
QUESTION 7.2 FACILITY COMENT:
Full ~ credit should be oiven for the relative shape of the requested Exact duplicatlon should not be required for full credit.
curve.
EXAMINER COMENT:
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-Examiner agrees with utility and will mark accordingly.
' QUESTION 7.6.5-FACILITY COMENT:
' Answer.is incorrect - should read as follows:
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n "If due to_ low air pressure:
a.
Check for leaks.
b.
Ensure proper valve line up."
Also, your reference 47515:0308 is for Unit II - Unit I reference is 47015:0308 which states PORV valve Nos as 32195 and 32196.
Full credit should be given for 3 out of 5 responses.
EXAMINER COMMENT:
Utility comment is noted; however, has no material relationship to the answer key. Will accept 3 out of 5 response.
QUESTION 7.7 FACILITY COMMENT:
Relaxation of the snubbers should be an acceptable answer.
EXAMINER COMMENT:
Will accept utility abridged answer.
QUESTION 7.9 FACILITY COMMENT:
Typo in reference C/15 should be C1.5.
EXAMINER COMMENT:
Will amend the reference typographical error.
QUESTION 7.10 b) FACILITY COMMENT:
The answer of the Unit I Shift Supervisor would proceed to the Hot Shutdown area or room or panels should be given full credit because the Air Compressor-Auxiliary.Feedwater Pump. Room and the above mentioned area is one in the same.
EXAMINER COMMENT:
Will accept utility answer, although the system's description does not match the utility answer.
L QUESTION 7.12 FACILITY COMMENT:
Reference F3.19; 100 CPM with the frisker is the value used for the contamination limit.
EXAMINERS RESPONSE:
l The utility statement is taken out of context from reference F3.19.
However, will accept the inferred contamination limit of 100 CPM above background.
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QUESTION 7.15 FACILITY COMMENT:
The examinee may use the Reactor Coolant Loop A (11) and Reactor Coolant Loop 8 (12) as separate _ areas.
They should be acceptable answers.
EXAMINER COMMENT:
Will not accept reactor coolant loop A and B as separate areas.
This approach negates the purpose of identifying all radiation areas as prescribed in the plant reference material.
' QUESTION 7.16 FACILITY COMMENT:
Full credit should be given for an answer of 3 out of 15.
. EXAMINER COMENT:
Will accept 4 out of 5 answers for full credit.
The SRO should be cognizant of all his responsibilities not just selected responsibilities.
QUESTION 7.17 FACILITY COMENT:
' Full-credit should be given for 4 out of 7 answers.
The answer could include the following:
a.
Resume full responsibility for the operation of both units.
b.
Inform ~the Duty Engineer and the Shift Technical Advisor of the situation.
c.
Evaluate personnel, if necessary.
d.
Ensure Control Room manning is maintained.
e.
Refer to Fire Strategies.
f.
Refer to the Emergency Plan.
g.
Notify the Red Wing Fire Department of any fires requiring fire brigade action.
EXAMINER COMENT:
Will accept alternative answers relating to each SS responsibilities in addition to responsibilities noted in the answer key.
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SECTION 8 Administrative Procedures ANSWER 8.1: FACILITY CO M ENT:
' Credit should be given.for two (2) correct responses.if the response
-= " Safety Limits are exceeded" is given.
If specific events requiring.
- suspension of fuel han.dling (TS 3.8) are given, full credit should be
- given for each correct-response. ~TS Table 3.9-2 Part 2.a should be added to list of correct responses.
EXAMINER COMENT:
- Examiner.will accept the additional answers.
ANSWER 8.3 FACILITY COMENT:
The question asked.for. Tech Spec-limits.which if exceeded would require a responsive action within one (1) hour, but excluded QPTR and AFD. 'The.
- answer key included AFD limits.
Credit should be given for AFD responses or the required number of responses for full credit should be reduced to 4.
EXAMINER:ComENT:
- Examiner will accept the additional answers.
TQUESTION 8.8~
. FACILITY COMMENT:
The: answer given in the key is correct.
However, the candidates may assume'that (Red Tags) refers to Red Safeguards Hold Tags which must be removed during plant-heatup, cooldown and refueling operations.
In this case the response would be "true, equipment must be manipulated-
- during normal-operations."- Either response should receive full credit.
' EXAMINER COMENT:
1 Examiner will~ accept alternative answer from'the utility.provided the
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candidate stated that the assumption of Red' Tags does refer to Red Safeguards Hold Tags.
All candidates were informed verbatim from Standard ES-201 prior to the start of the examination that all
- assumptions should'be stated to obtain an answer... Paragraph L, ES-201.
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-If:so stated, all candidates will receive full credit.
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-fANSWER 8.14 FACILITYzCOMMENT:
.The answer key for. "a" lists all of the information to be included in f
the-annunciator out of service log.
The log has-headings on columns in
~which this information is to be' included in the log.
Full credit should-be given for annunciator Out of Service Log, along with the other two (2) required responses.
b EXAMINER COMMENT:
I The examiner will accept the facility comment.
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Resolution of Comments for Prairie Island
'R0 Exams Administered 3/26/85
'SECTION 1 - Principles Of Nuclear Power Plant Operations FACILITY COMMENT:
1.1 a)
The question r.ixed' reactivity and Kexcess.
An additional answer option is:
excess = K - 1 = Kexcess K
K c).
Wrong answer - It doesn't consider boron holddown.
EXAMINER COMMENT:
a)
Agree ~
- c)
Agree, answer is not complete.
EXAMINER RESOLUTION:
'a)
Options stated will be added to~ answer key.
c)
Will accept a description of how the three are related.
FACILITY COMMENT:
.1.3a)
How and why does Beta change over core life?
Answer included the effect (for 20% of the credit) of this change but the question didn't solicit it.
EXAMINER COMMENT:
Agree' EXAMINER RESOLUTION:
Final sentence in answer key will be placed in parenthesis.
FACILITY COMMENT:
1.7a)-
The answer key included the component parts of the power defect but the question didn't solicit them. Also they only included FTC and MTC (omitting VTC).
EXAMINER CIDMMENT:
Agree i.
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EXAMINER RESOLUTION:
Contents of Power Defect and' Power Coefficient will be placed in parenthesis and point value changed.
a l FACILITY COMMENT:
1.8 a)'
The change'in FTC with increasing fuel temp, was in the answer key but this. fact was not significant and should.not be required.
Lb)
- With DN8 these would also be void effects.
sEXAMINER COMMENT:
a) ' Agree
.b)-
Agree EXAMINER RESOLUTION:
a)
. Point value will be redistributed.
b)
Will add void to answer key but will notLrequire it.
FACILITY COMMENT:
1.9 b)
Question' asked for where in the core (axially) was the highest heat flux.
Key indicated between bottom and middle. Add between middle and top for BOL recycle core.
Full credit
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should be given for.either.
EXAMINER COMMENT:
Agree EXAMINER RESOLUTION:
Will accept d as possible answer.
FACILITY COMMENT:
1.10 c)~ Due to overdesign of feedwater heaters, the observed effect on efficiency of excessive condensate depression differ from the theoretical effect.
. EXAMINER COMMENT:
Agree in principle.
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EXAMINER RESOLUTIONi Answer remains as is. The theory-of condensate depression is what is being questioned.
' FACILITY COMMENT: (not provided but given during exam review) 1.12 c)'
Comment was made about the irrelevancy of the question.
EXAMINER COMMENT:
Dishgree. ~ Knowledge of T.S. Table 3.1-3 is required.
EXAMINER RESOLUTION:
- No change to_ answer key. -However, reference will be changed to T.S. Table 3.1-3.
FACILITY COMMENT:
1.15 d)
Affect of an incorrect steam flow signal on the calorimetric..
-Because it's not accurate enough.to use, it would have no effect but-the question is a thermo one not a procedure question.
I~think:they should also accept the thermo answer, (i.e.) for low steam flow'a lower calculated power.
EXAMINER COMMENT:
Agree-
. EXAMINER RESOLUTION:
Will accept either answer as correct.
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'SECTION 2"- Plant Design FACILITY COMMENT:
- 2.01 d)- Acceptable answer should be:
To ensure proper operation of #1 seal.
EXAMINER COMMENT:
Agree EXAMINER RESOLUTION:
Will accept either answer for full credit.
' Fu. " TTY COMENT:
2.02 c)
Answer key is incorrect.
2590 gallons is correct per T.S. 3.3.C(2).
EXAMINER COMENT:
Agree EXAMINER RESOLUTION:
Answer key changed to provide proper answer.
FACILITY. COMMENT:
2.'04 a)
The correct pressures for jockey pump operation, per logic diagram NF-40318 Sheet 1, are 108-113 psig (start /stop).
b)
On decreasing header pressure beyond jockey pumps capability, the' sequence is as follows:
Screenwash pump 105-110 psig (start /stop)
Motor Driven Fire pump-100 psig (start)
Diesel Fire pump 95 psig (start)
EXAMINER COMMENT:
a)
Agree b)
Agree EXAMINER RESOLUTION:
a)
Answer key changed to reflect proper values.
b)
Answer key modified to reflect proper answers.
Will allow f5 psig on setpoint values.
15 a.
FACILITY COMMENT:
L
~2.05 Question does not specify diesel generator.
Four of six should be adequate for full. credit.
This question could also be interpreted to mean pumps or motors supplied by the diesel generator.
EXAMINER COMMENT:
. Agree that question could have been worded differently.
Disagree with
-requirements for full credit.
6 components were asked for.
EXAMINER RESOLUTION:
Will change question to specify Emergency Diesel Engine.
' FACILITY COMMENT:
2.07 A recent design change and a new method of operating the station and instrument air systems may not elicit any of the original answer since the two systems are no longer normally cross connected.
However, due to the wording of the-question some operators may provide these answers and
-should not lose credit.
The correct answer for the case when the two systems are not' cross connected is:
- Preferred station air comp starts at 95 psig.
- Standby station air comp starts at 90 psig.
- Station air hdr pressure regulating valve open/ closed as necessary to maintain 88-psig.
- Condensate polishing header press reg valve opens / closes as necessary to maintain 82 psig.
EXAMINER COMMENT:
Agree EXAMINER RESOLUTION:
Will accept either set of answers for full credit.
. FACILITY COMMENT:
2.08 a)
Answer key does not specify reason for 210 psig interlock.
EXAMINER COMMENTS:
Agree L
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EXAMINER RESOLUTION:
Will add."and protects the low' pressure piping" to the answer key.
FACILITY CO MENT-2.10 a) _ According to Prairie Island FSAR Volume 2 Section 6.2 pp. 6.2-1 and 6.2-2, the four accidents designed for are.
1.
Large LOCA.
2.
LOCA associated with ejected rod (small break).
~3.
Steam Generator Tube Rupture.
4.
Steam Line Break.
'This is consistent with B18b if you read the discussion which follows the acciaent listing.
The reactivity insertion due to an ejected rod is addressed by Rod Insertion Limits.
It is the small LOCA associated with the ejected rod accident that is addressed by ECCS.
Therefore, correct answer should be:
1.
Small break LOCA (associated with ejected rod).
2.
Large Break LOCA.
3.
SGTR.
4.
Steam Line Break.
b)
The B-section and FSAR are consistent here also.
The active injection mode includes high and. low head injection.
Please consider the following answer correct for modes of operation.
1.
Highheadinjection.
2.
Low head injection.
3.
Long-term recirculation.
EXAMINER COMMENT:
a)
Agree b.
. Agree EXAMINER RESOLUTION:
a)
Changed answer key to reflect proper answer.
b)
Added that "will accept High Head and Low Head injection."
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SECTION 3 - Instruments And Controls
. FACILITY-COMENT:
3.01 b)
A discussion concerning efficiency should not be mandatory.
All that should be required is a statement indicating FW inlet temperature decreased, thus causing RCS temperature to decrease, and therefore rods will step out.
EXAMINER COMENT:
Agree EXAMINER RESOLUTION:
Will put the first sentence in parenthesis.
FACILITY COMMENT:
3.03 a)
Should accept 0-10V signal for reference in addition to %
valve position, since the actual signal is 0-10V which is indicative of valve position.
Full credit should be given for either response, c)
The answer does not include all conditions which will cause 20/ET to actuate.
Per logic diagram NF-40777-1 these conditions are:
11A FW Ntr Hi Lv1 118 FW Htr Hi Lvl 12A FW Htr Hi Lv1
.128 FW Htr Hi Lvl 13A FW Htr Hi Lvl 138 FW Ntr Hi Lvl Reactor Trip
- 11 MSIV Closed
- 12 MSIV Closed 11 S/G Hi Hi Level 12 S/G Hi Hi Level
- Safety Infection
. Both FW pumps off
- 1GT (Generator Transformer) lockout IG (Main Generator) lockout Low auto stop oil pressure Also the question does not ask for setpoints, so they should not be required.
(i.e.) 45 psig on low auto stop oil pressure.
- Not in answer key.
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L LEXAMINER COMMENT:
. a)
Agree b)'
Agree
' EXAMINER RESOLUTION:
a)
Will accept 0-10V as a reference' signal.
~.' -Will add additional answers to key and will not require setpoints.
b
. FACILITY COMMENT:
3.04 b):
Previously all operators were taught that there were three conditions required to satisfy the condenser permissive.
They were the three listed. However, some operators may state that only two are required; 16" Hg vacuum in the condenser and either CW pump running (brkr closed).
This is. technically correct per logic diagram NF-40322-2 since the condenser permissive status light (47014-0205) is on when these two conditions are satisfied.
Either answer should be acceptable.
Also,'the setpoints were~recently changed to 16.5".
Either number should be acceptable. Actually 16" Hg i X" Hg should
'be acceptable where X is some small amount, possibly 1" to 2".
- EXAMINER COMMENT:
Disagree.three conditions were asked for.
Three required.
EXAMINER RESOLUTION:-
Will' accept 16" or.16.5".
FACILITY COMMENT:
13.05~(a) Inputs (plural) implies 2 signals are used for density compensation, but really the steam flow signal is compensated by steam pressure signal only.
Therefore, an acceptable answer should be steam pressure only.
However, since you ask for more than one, the original answerfshould be acceptable.
Ref. X-Hiaw-1-549 EXAMINER COMMENT:
Disagree - The steam flow signal that enters the density compensator
- (FM-464 (5)) is not the same signal that comes out.
Therefore, the
- 2. inputs are indeed separate.
EXAMINER RE 0LUTION:
No. change to answer.
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i FACILITY COMMENTS:
3.06
_This is an open ended question which does not ask for specific -
information.
Therefore,_it probably will not elicit the response about P7.
Also, the current answer is not complete and places too much emphasis on P7 related times (75% of total).
Recommended answer:
- Automatic rod control will maintain Tavg at approximately 560*F (Tref).
- Automatic S/G 1evel control will maintain S/G 1evels at 44%.
- P7 will net, block the low pressure reactor trip and therefore reactor will trip when the low pressure trip setpoint is reached.
- Tavg signal of 560*F into steam dump system would initially cause the equivalent steam dump demand of 13*F.
If the turbine were to trip while steam dump was in Tavg mode because trip controller compared auctioneered Tavg with 547*F not Tref.
Pzr level would be maintained at level equivalent to 560' Tavg (33%) by automatic pzr level control system since it uses auct Tavg.
Ref.
Logic NF-40322-2 Foxboro Logic X-Hiaw 1-547, 542, 548, 549, 550 Westinghouse Logic X-Hiaw 1-243, 244, 245, 246, 248 EXAMINER COMMENT:
Agree with parts 1, 2 and 5 above.
Agree with part 3 except only Rx trip breakers will not open.
Disagree with part 4.. Question did not specify turbine trip.
EXAMINER RESOLUTION:
Add requested answers to answer key with above comments.
FACILITY COMMENT:
3.07 a)
- Agree
- This is as stated in answer key EXAMINER RESOLUTION:
" Pressurizer heaters" will be accepted.
- No changes to answer key.
20 o
r t-
-FACILITY COMMENT:
3.09 a)
Due to high water content in containment atmosphere.
b)
Should accept:' All CFCUs shift / start in slow speed and discharge dampers fail to the dome.
c)
The following signals should be accepted:
sis Manual CI Manual CS
'Hi Radiation IR22 Hi Radiation 2R22 Hi Radiation IR11 Hi Radiation 2R11 Hi Radiation 2R12 Note:
SI is not required for containment vent isolation on High Rad level.
Ref.
Logic Diagram NF-40762 EXAMINER COMMENT:
a)
Agree.
b)
Agree c)
Agree EXAMINER RESOLUTION:
a)
Containment atmosphere added to answer key.
b)
Recommendation added to key, c)
Additional answers added to key and answer key corrected.
FACILITY COMMENT:
3.10 a)
Demand bank position is not used to calculate the rod insertion limit. Average T and auctioneered high Tavg are input to calculate the RIL.
However, the constant for Tavg is set to zero and therefore only average T is used to calculate the limit.
Ref.
X-Hiaw-1-547 EXAMINER COMMENT:
Agree EXAMINER RESOLUTION:
Will accept only Average T.
21 t
m t
- SECTION 4 - Procedures 4
FACILITY; COMMENT:
- 4.02 b).. 'Do:not reduce point score if assumption is not stated.
EXAMINER COMMENT:
Disagree.
The assumption must be stated so grader can be assured that knowledge of, Form-4 requirements _are demonstrated.
EXAMINER RESOLUTION:
1 No change.to answer key.
FACILITY COMMENT:
4.03 b)
Accept either ranking for full credit.
1.
Subcriticality-1.
Subcriticality 2.
Core Cooling 2.
Core Cooling 3.
-Heat Sink 3.
Integrity 4.
Integrity.
4.
Heat Sink 5.
Containment 5.
Containment 6.
Inventory 6.
Inventory Procedure (IF-0) is inconsistent with basis. A procedure change request has been submitted.
EXAMINER COMMENT:
Agree EXAMINER RESOLUTION:
, Answer key altered to reflect comment.
FACILITY COMMENT:
4.05 d)
Question ' improper - Nothina required for dilution.
Accept any answer related to heaters since candidate may interpret question to give listed response or accept "nothing required" as correct answers, f
EXAMINER COMMENT:
Agree
~
EXAMINER RESOLUTION:
'Will change answer key to reflect correct answer.
- Will. accept either answer.
. Question will be modified.
i 22 L
FACILITY COMMENT:
4.06 a)
Add as an acceptable answer assure the large motor monitor light is lit.
Full credit should be given for either response.
b)
Change acceptance criteria to 2/3 for full credit.
EXAMINER COMMENT:
a)
Disagree.
This is not part of General Precaution 2.3.19.
b.
Disagree.
This information~fs contained General Precaution 2.3.21 and is fully required knowledge.
EXAMINER RESOLUTION:
4.07 a)
The correct answer is "90 seconds after SI initiation." The candidates may realize that the question was looking for SI termination criteria and therefore give the response listed.
Full credit should be given for either response.
Ref.
ESO.2, Step 1.
c)
Answer should state "only if Fx trip breakers were cycled.
Closed is auto SI reinstated." Breakers will reopen if Rx trip signal is still present.
EXAMINER COMENT:
a)
Question indeed was asking for termination criteria.
Full credit given for term. criteria only, b)-
Agree EXAMINER RESOLUTION:
a)
No change to answer key.
b.
Change answer key to mention cycling trip breakers instead of closing.
FACILITY COMMENT:
4.08 a)
Change acceptance criteria to 6/8 for full credit.
b)
Add to answer a:
Class B AFFF (Foam)
Class C Water - also accept the deletion of CO 2 EXAMINER COMMENT:
a). Only six required on key, b)
Agree 9
23 k
.:n e
~
EXAMINER RESOLUTION:
a)
No change b.
Additions made to answer key.
Will accept water spray for
. Class C, deletion of CO not accepted.
2 FACILITY COMENT:
4.09 Change acceptance criteria to 2/3 for full credit.
EXAMINER COMENT:
Disagree. These items are found in Precautions section and are required knowledge.
EXAMINER RESOLUTION:
No change to answer key.
i-24 L-
[
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_11AIBIE 11LAdQ 112______
9 REACTOR TYPE 8
_EMR-MECZ______
SI R C'V DATE ADMINISTEREDt_A1423L26________________
EXAMINER:
_d&GSAta_Ea______________
APPLICANT:
IB11RUCI1QN1_IQ.ARELICAHIl Uso 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 af ter the question. The passing escde requires at least 701 in each category and a final grade of at locst 804.
Examination papers will be picked up six (6) hours after tho examination starts.
1 0F CATEGORY E OF APPLICANT'S CATEGORY
__MALUE_ _IGIAL
___1CQtE___
_MALUE__ ________ _____CAIESD11______
.11aQQ
_11400
___ 1.
PRINCIPLES OF NUCLEAR POWER
+
PLANT OPERATION, THERMODYNAMICSs HEAT TRANSFER AND FLUID FLOW
.22400__ _22aQQ
___ 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 1 _llcQQ__
22400
________ 3.
INSTRUMENTS AND CONTROLS j
.21cQQ 22a00
________ 4.
PROCEDURES - NORMALS ABNORMAL, EMERGENCY AND RADIOLOGICAL l
CONTROL l
i ASQaQQ _ 190a00
________ TOTALS FINAL GRADE ________
All cork done on this examination is my own. I have neither
! given nor received eld.
APPLICANT'S SIGNATURE
Ac__tBINC12LE3_DE_HuCLEA8.tDMER_ELAHI_DEERAIIDua PAGE 2
~~~
IDES 5DDXH&51C34_MEAI IBAMSEER_AND_ELUID ELDM QUESTION 1.01 (1 90)
- a. Define (or provide a formula for) Excess Reactivity (Kexcess).
(0.5)
- b. How is Kexcess controlled?
Provide 2 methods.
(0.*)
- c. Describe the relationship between the following terms.
1.
Kexcess 2.
Shutdown margin (SDM) 3.
Total rod worth (1 0)
QUESTION 1.02 (2.50) e a.
With an initial source count of 300 cps and a Kef f of.95, what is Kef f when the count rate is 1500 cps?
(0.5) b.
For equal reactivity addition during rod withdrawal on an approach to criticalitys determine if the following state-ments are TRUE or FALSE regarding subcritical multiplication.
1.
Each change in count rate INCRE ASES and each time to reach equilibrium DECREASES.
{
2.
Each change in count rate DECREASES and each time to reach equilibrium INCREASES.
l 3.
Each change in count rate is constant and each time to reach l
equilibrium remains constant.
j l
4.
Each change in count rate INCREASES and time to reach I
equilibr ium INCREASES.
(2.0) l l
GUESTION 1 03 (2.00) l l
ao HOW and WHY does Beff change as the core agost (1 0) l b.
Given the equations 8eff = 8 x IF Where IF is the Importance Factor.
Why is an IF required to define 8eff and what is the value of
,the IF st Pralrle Islandt (1 0) l l
Ic__2RINCIELE1_DE_HUCLEAR_2DMER_2LABI_DRERAIIDHa PAGE 3
IME850DXHA51C3a_MEAI_IRAHIEER_AND_ELUID_ELDE_.
QUESTION 1.04 (1 50)
TRUE OR FALSET o.
The production rate of Xenon from Iodine is FASTER than the decay rate of Xenon to Ceslum.
b.
During an increase in power f rom equilibrium Xenon conditions, Xenon concentration initially DECREASES.
c.
SLOWING the rate of a power decrease LOWERS the height of the resultant Xenon peak.
(1.5)
QUESTION 1 05 (1.50)
W:uld power range indications tend to indicate an INCREASES
! CREASE, or NO CHANGE for the following events?
Assume actual swer was unchanged at 75% (bef ore and af ter the event).
8rlefly EXPLAIN your answer. (Consider each separately.)
c.
Heatup of the reactor coolant b.
Core aging L.
Increase in boron concentration (1.5)
G JESTION 1.06 (1 00)
The Integral worths of 5 SEPARATE RCCA rod banks at BOL totals about 2.45 dk/ks yet the MEASURED TOTAL Integral worth of the same 5 RCC A banks is only about 1.74 dk/k.
Explain the difference.
(1 0) i i
l QUESTION 1.07 (2.00) l e.
Define Power Coef ficient and Power Defect.
Give the units of i
each.
(1.0) b.
How does 1. Power Coefficient and 2.
Power Defect change from BOL to EOLT (1.0) 4 l'
f
l I
La__tt18CIALE1_DE_MUCLE&t_tDMER_tLABI_DEERALIDKt PAGE 4
IDE850AINA51C34_HEAI_IRAH3EER_AND_ELUID_ELDM QUESTION 1 08 (1 60)
Explain how the following ef f ect the Power Coef ficient.
Assume that nuclear power remains constant.
a.
Crud builds up on the fuel.
b.
.ONS occurs.
(1 6)
QUESTION 1.09 (1.50) o.
For en INCRE ASE in each of the parameters below how does the critical heat flux (CHF) changet 1.
RCS Flow 2.
RCS Temperature 3.
RCS Pressure (0.75)
'b.
Match Column A to the respective core location in Column B.
(Choices from Column 5 MAY be used more than once).
A B
1.
Highest CHF a.
Bottom 2.
Minimum DNBR b.
Between bottom and middle 3.
Maximum actual heat flux c.
Middle d.
Between middle and top e.
Top (0.75)
QUESTION 1.10 (2 00) i Explain how each of the following aff ects plant ef ficiency.
s.
Water box air ejector b.
Air ejector loop seal o.
Circulating water temperature de Chierinator (2.0) 8
~ - - _ _., _ _ - - _
Ac__tt1NCIELES DE.NUCLEAE_20MER_2LABI_DEERAIIDHa PAGE 5
IMER500XMA51C 3a_HE AI_IRANSEER. AND_ELUID_ELOM 1
QUESTION 1.11 (1 50) c c.
Define condensate depression.
b.
What is the advantage of condensate depressient I
Determine the condensate depression in a condenser operating c.
at 4 inches of mercury with a condensate temper ature of 115 F.
(1 5)
QUESTION 1.12 (1 50) a.
What is the significance of RTNDTt (0.5) b.
Explain why the heatup and cooldown curves shif t to the right as the reactor vessel receives radiation exposure from neutron bombardment.
(0.5) c.
What is the main contributing chemical element that causes this shift?
(Choose one) 1.
Cu 2.
Fe 3.
Ni 4.
Sr (0 5)
QUESTION 1.13-(1.50)
Consider a cooldown of the RCS using Residual Heat Removal.
i.
Assuming a constant decay heat rates will RHR flow through the heat exchanger have to be adjusted to maintain a constant cocidown rate from 350 F to 150 F1 Explain your answer.
(1.5) f GUESTION 1.14 (1 00) a.
The reactor coolant pumps require about 304 more power to i
operate in cold shetdown <200 F than at 530 F (hot shutdown).
Why are the power requirements different for each condition?
(0.5) b.
If the VELOCITY of the fluid i s the SAME at 200 F and at 530 Fs will the MASS FLOW RATE also be constant at these two different conditionst Explain.
(0.5)
---,-----.-.-..,-----.-.-----....,,.n.
.-----_.-,,,,,n....,.--,n
,,n.,,, -, -,
n--
n.,
m-
-,-..e---_--
m Ic__tBIN CIELE3_DE_uMC L E AR_2DM E R_2L ABI_QEER&Il0Mt PAGE 6
IME850018&51C 3a_ME AI_IRANSEER_ AN D_ELUID_ELQM GUESTION 1 15 (2.00)
A MANUAL heat balance is run at full power. State whether CALCUL ATED power would be equal to, greater then, or less than ACTUAL power for the following conditions:
c.
Indicated feedwater temperature is 10 F HIGHER than ACTUAL temperature.
5 Heat output of the reactor coolant pumps was NEGLECTED in the' calculation.
o.
Tave is 1 degree less than Tref.
J.
Steam Flow Indication is lower than actual.
e.
Feed Flow indication is lower than actual.
(2.0) 9 t
l l
l 4
?
Ec__tL&MI_RE11S5_ INCLUDING _1&EEII_AHQ_E5ERGEHCI 111IE53 PAGE 7
i QUESTION 2.01 (3.50) c.
WHAT la the purpose of the No.1 seal bypass valve associated with the Reactor Coolant Pump and WHAT are the RCS minimum and maximum pressure requirements imposed f or opening the valvet (Specific values required).
(1.0) b.
The RCP No.1 seal water return flow to the CVCS is Isolated upon containment isolation.
WHAT provision is made for maintaining seal leekoff af ter the isolation valves closof (1 0) c.
If the leakage through No. 3 seal is greater than normals will the No. 2 seal standpipe level INCREASE or DECREASEt (0 5) d.
Esplain the reason for maintaining a minimum of 15 psig in the VCT in reference to the RCPs.
(1 0)
QUESTION 2.02 (2 50)
- a. State ALL the automat'ic actions that take place upon actuation of a "P" signal.
(1.0)
- b. State TWO reasons / bases for injection of caustic into the Containment Spray water.
(1.0)
- c. Technical Specifications require a minimum of _____ gallons in the Spray Additive Tanks. (Fill in the blank.
put your answer on your answer paper).
(0.5)
I QUESTION 2.03 (2 00)
Describe all of the Interlocks associated with the orifice isolation valves in the CVC System.
Include in your description the bases for the interlocks.
(2.0)
QUESTION 2.04 (3 00)
- c. What is the normal Fire Protection System water pressure AND how is that pressure maintained?
(1 0)
- b. During Fire Protection System operations describe how system pressure is maintained.
Include setpoints in your description.
(2.0) s i
...,,__-.-y.
.,,,_,_-._,_,_____.,_v._m___,__,___
Za__ELANI_Q111Sti_INCLUDINE_1&EEII AND_E5ERGEBC1_113IE51 PAGE 8
QUESTION 2 05 (1 25)
List 6 EXTERNAL components that are mechanically driven by the diesel engine.
(2.25) l QUESTION 2.06 (1.50)
- a. During normal handling of a spent fuel assembly,.Aat prevents '
the fuel assembly from being raised out of the water ?
(1.0) 6.
How close to the surf ace of the water can a spent fuel asss'bly be raisedt (0.5) l
'~
QUESTION 2.07 (2.00)
State ALL the automatic ' actions that would occur If the pressure in the Station Air Systems steadily decreased below the normal pressure of 100 psig.
(Include setpoints, do not include i
alarms or annunciators.)
(2.0) 0{ESTION 2 08 (3.00)
- a. Describe the Interlock (s) associated with the RHR supply to the SI pump Isolation valves (MV-32206 & MV-32207) AND the purpose l
of the interlock (s).
(1 0)
- b. Describe how AND when the interlocks in (a.) above are routinely defeated.
(1 0) 6.
State the interlock (s) associated with the SI test line to the RWST isolation valves AND the purpose of the Interlock (s).
(1.0)
QUESTION 2.09 (2.00) l Provide a brief sketch of the Component Cooling Water flow paths through a Reactor Coolant Pump.
Include the flow paths through the prep AND noter and show the approximate normal flow rates for each pa%5.
(2.0)
Zo_EL ABI_DESIG H_INCLUDIN G_1& EEIL ABD_E5EEGEN C1.SISIf 51 PAGE 9
k QUESTION 2.10 (3.25)
- a. List the 4 accidents that form the basis for ECCS performance.
(1 0)
- b. 10CFR50.46 lists five acceptance criteria that the ECCS must satisfy.
In order to meet this criteria, the ECCS must be capable of 3 phases of operation.
State the 3 phases of operation AND the purpose of each phase.
(2.25) k, e
4 s
I Y
=
6 l
e 2n_ 18118U5EMI1_AND_CDMIRDL1 PAGE 10 QUESTION 3.01 (3 00)
Unit 1 is oper ating at 45% power with all systems in automatic ocntrol.
For each of the following conditions, give the direction of initial red motion AND EXPLAIN why there is rod motion.
a.
A steam generator Atmospheric Power Relief Valve falls open.
(1 0) b.
A feeduster heater string becomes isolated.
(1.0) c.
The lower detector of the power range channel N-44 falls high.'
(1.0)
QUESTION 3.02 (2.00)
TRUE or FALSET l
The following concern the construction and operation of the POWER RANGE
, JCLE AR INSTRU MENT ATION. detector.
(No explanation is required.)
a.
Each upper and lower section provides inputs to a delta flux meters dette flux recorders and current comparator.
b.
Boron-triflouride (8F3) gas is in the outer volume of the detector but not in the inner volume of the detector.
o.
8F3 gas is in BOTH Inner and outer volumes of the detector.
d.
The detector uses no compensation circuitry to remove gamma caused current.
(2.0)
QUSSTION 3.03 (3.25)
- a. With the Main Turbine Control System (MTC) selected to OPERATOR AUTOS state the signals used for the reference AND feedback when in
- 1. IMP IM.
- 2. IMP OUT.
(1.0)
- b. List 3 conditions that will cause the MTC to switch to MANUAL.
(0.75)
- c. List 6 conditions that will actuate the 20/ET solenoid in the
' Emergency Trip control Block circuit in the MTC.
(1.5)
As._INSIRUEEBIS.480_CDHIRQL1 PAGE 11
/
i QUESTION 3.04 (3.00)
- a. What is the function of the bypass Interlock in the Steam Dump j
Systemt (1.0) i
- b. What 3 specific signals / conditions are required to satisfy the condenser permissivet (1.0)
How are the Steam Dumps " armed"?
(1 0)
Q UES TION 3.05 (1 50)
- a. State the inputs tb.? are used to develope the density compensation signal for Steam Generater Water Level Control.
(1 0) 3.
If the density compensation signal is steady at 1/2 of its normal 100% value, would the INDICATED steam flow be HIGHER, LOWER or the SAME AS the'value at 1% power.
(0 5)
QUESTION 3.06 (2.00)
A r amp from 100% power to remove the unit from the grid has begun.
sume that all systems remain in automatic.
Turbine Impulse assure transmitter PT-485 sticks and remains at its 100% output.
. scribe the ef f ects of this malfunction on plant operation, if it were to remain undetected, as the plant is ramped down and proceeds to cold shutdown condition.
(2.0)
QUESTION
'3.07 (3.00) l
- a. List all items controlled by the master pressurizer pressure controller.
(1 0)
- b. Pressure is decreasing and controller output is decreasing.
Is l
the controller functioning properly?
Explain.
(1 0) 1
- c. In par t "b"
above, you take MANUAL control.
Describe the l
controller operation required to raise pressurizer pressure.
(1.0)
I i
-.w-,
1 r.
31..'INSIEUNENIS_eND CONIROLS PACE 12 DUESTION 3.08 (2.50)
- o. ' List the four >1 ant parameter inrut signals that DIRECTLY feed the Overtemperaturw Delta-T (OTdT) protvetion circuit.
(1.0) 8.
Which of the following core parameters does the OTdT Protvetive circuit Provide Protvetion edginst exceeding?
1.
DNB 2.
Core Power Densitw.
(0,5)
C.
What two control functions other than reactor trie does the OPdT Protection channel provide?
(1 0)
DUESTION 3.09 (3.50)
A. Whw do the Reactor Conteinment Fen Coolers (RCFC) automatica11w
. shift (or start) to slow sewwd following an SIS signal?
(1.0) 4 B. How is RCFC affected on an SIS signal? (Include a description of the flow path.)
(0.9)'
C. List four signals that will ecuse Containment Ventiletion isolation.-).
(1.6)
DUESTION 3.10 (1.25)
Wha't ineut signals are sent to the couruter for use in calculating rod insertion limits?
(0.5) b.
What are the three design bases for the rod insertion limits?
(0.75) t
-.n
ia__EBOCEDUREn_=_NORuals_ABEDREALt_EBEEEEHCI_&MQ PAGE 13 RADIOLDGICAL_CQHIRDL QUESTION 4.01 (2 25)
- a. During a tour of the Auxiliary Building you discover en unconscious injured worker inside a contaminated controlled area.
What sre your specific responsibilitiest (0.75)
- b. Under what circumstances would the spread of contamination be of minor consequence when an injured person is in a known contaminated arest (0.75)
- c. What conditions would require the movement of an injured person in a contaminated area before proper medical help arrivest (0.75)
QUESTION 4.02 (2.50)
Af ter working in an area for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, a worker discovers his pccket dosimeter is of f scale and leaves the area.
A subsequent survey reveals a hot area of 1200 mr/hr at 2 f t. f rom the " hot spot".
The worker's activities were primarily at 5 ft. from the " hot spot".
- a. Determine the exposure the worker received.
(1.25)
- 6. If the worker's previous exposure was 900 mr.
What LEGAL (10CFR20) exposure limits, if any, were exceeded?
(1 25) 1
r is._ERDCEDURE3_= 80Rd&La_ABNORBALa_EBEEEENC1_AUQ~'
PAGE 14 ShD1DLDG1 CAL _CDUIEGL QUESTION 4 03 (2.50)
- a. State 2 purposes that the Critical Safety Function Status Trees are intended to serve.
(0.5)
- b. Listed below are the 6 categories of Status Trees.
Rank the categor ies accordi ng to pr iori ty as stated in IF-0.
Use 1 as the most important.
CONTAINMENT PRIMARY INTEGRITY SUSCRITICALITY REACTOR COOLANT INVENTORY CORE COOLING HEAT SINK (1.2)
.c.
The Status Trees contain paths of 4 different colors.
List the colors of the paths in order of severity (most to.least)
AND explain what general operator action is required for each color.
(0.8)
' QUESTION 4.04-(2 50) 7 ES-0.5 (Natural Circulation Cooldown With a Steam Vold in the
.l Vessel) notes that if the pressurizer is solids saturated conditions should be established-before reducing level.
What are the consequences of NOT ' er f orming this action before cooldown p
begins?
(1.0)
- o. During depressurization, the pressurizer level is checked following each procedure step.
If the level is 90% or greaters pressure must be raised by 100 psig and the preceding step redopt.
- 1. With normal system operations what could cause the level to increase during depressurization?
- 2. Why is pressure increased if level is >90%7
- 3. Why must level be maintained <90%7 (1.5) f
is._REDCEDURE1_=_NOR5&La_ABEDREALa_E5ERGENCI_ANQ PAGE 15
(-
RAQlDLDEICAL_EDRIRDL
-~
2 QUESTION 4 05 (3.00)
- a. Withdr awing the shutdown banks is administratively controlled in the startup procedure (C1.2).
State the two plant conditions, one of which must be mets that may exempt the shutdown banks from being withdrawn?
(1.0)
- b. What is the minimum shutdown margin that must be maintained i
with all shutdown and control banks inserted?
(0.5)
- c. What are the maximum allowable heatup rates for the RCS AND i
Pressurizert (1 0) a&&hos
- d. Prior to boron d!? t'cr. operations after the steam bubble is formed in the pressurizers what operator action should be taken to maintain RCS and pressurizer boron concentration equalizedt (0.5)
- i. '
b'iESTION 4.06 (2.50)
Es. State the 2 limits, one of which must be met, placed on the THIRD attempt to start a Reactor Coolant Pump as listed in
. Procedure C3.
(1 0)
l temp er atur e is GREATER than seal injection water temperature.
^
i List 3 diff erent actions that can be taken in order to prevent a cold water injection problem when the RCP is started.
(1.5)
QUESTION 4.07 (2.00)
- a. State the 5 requirements that must be met in order to reset SI.
Include all options, if any, i n accor dance wi th E-0.
(1 0)
- b. What 2 plant conditions, one of which must be met, require reinitiation of SIT (0.5)
- c. If SI reinitiation (after being reset) is required will it be automatic?
Explain.
(0.5) i 4
i
i Aa _ERDCEDURE1_=_HDR5&La_ABHDEBALa_EBERGENC1_AHQ PAGE 16 RADIOLDEICAL_CDNIRDL 1
QUESTION 4 08 (2.00)
- a. State the responsibilities of the Control Room operator af ter receiving a report of a fire as listed in procedure F5.
(1.4)
- b. Define class A, 8,
and C fires and what type of extinguishing agent may be used on each.
(0.6) i QUESTION 4.09 (1 75)
The following pertain to the Unit Shutdown procedure (C1 3).
- o. A precaution warns that poor circulation could cause a steam bubble to form in the reactor vessel head.
What action can be 4
taken to prevent this from happening?
(0.5) b.
If a steam bubble should f orm in the vessel head, what 3 actions can be taken to collapse the bubble?
(0.75) t
- c. If a steam bubble forms in the primary side of a S/G, what action can be taken to collapse the bubble?
(0.5) f QUESTION 4.10 (2.00)
The following pertain to Shutdown Outside the Control Room (C1 8).
- a. State the immediate duties of the Plant Equipment and Reactor Operator in an evacuation of the control room when conditions do not permit a reactor trip prior to leaving.
(1 0)
- b. As Xenon decays in the shutdown reactors Boron must be added to maintain shutdown margin.
State the basi c steps that must be taken to borate the plant f rom outside the control room.
(1 0) 4 k
4
r.
ta__E80CEDUSE1_=_BDREALa_ASHDRHALa_EBEREENC1_AHQ PAGE 17 SADIDLDEICAL_CONIRQL l
QUESTION 4.11 (2.00)
Match the Emergency Action Level in COLUMN A to the one correct i
description in COLUMN 8.
COLUMN A COLUMN B 3
Notification of Unusual a.
Provides ear ly and prompt notifi-Event cation of minor events which could develop into or be Indica-2.
Alert tive of more serious condi tions.
3.
Site Area Emergency b.
Declared when events are in prog-ress or have occurred which involv-4.
General Emergency ed actual or emminent core degrada-tion with potential for loss of containment integrity.
c.
Declared when events are in prog-ress or have occurred which involve actual or likely major failures of pl ant functions needed for protect-lon of the public.
d.
Declared when events.are'in prog-ress or have occurred which involve actual or potenti al de g r ed at i on of the level of plant safety.
(2.0) 4
.s
^
r Ic ERINCIELES_DE_HUCLEAE_EQWER_ELAHI DEERAIIDHt.___
PAGE 18 IHEREDDINA51G34_SEAI IBAH3EER_ABD_ELUID_ELDM ANSWERS -- PRAIRIE ISLAND 1E2
-85/03/26-JAGGAR, F.
\\
ANSWER 1.01 (1.90) h
} Ig a
- o. Kexcess = Kef f-1 willalao acc4/i 8ev:
k +<ces> o,, w,J gf Qm i\\'6^ *
(0 5) b.
With the use of:
- 1. C on t r o l rods
- 2. Burnable poison rod
- 3. Soluble boron
[2 required, 0.2 each]
(0.4) ml\\ ace pi a8 e.sc r pk s bD
. (1.0)
- c. Total th = Kexcess t SDM rod wor $4#~*
.t h t.
" ' t- ' d*A !k REFERENCE NUS NET MOD 3 pg 11.1-1, 11.' l-2, 11.1-3, 11.1-4 A SWER 1.02 (2.5,0) a.
CR1 1-Keff2 S
CR2 1-Keffl 300 1-Keff2
{
1500 1
.95 i
.99 = Keff2 (0.5) 1.
False 2.
False 3.
False
-4.
True
[0.5 ea)
(2.0) l l
REFERENCE NUS NET MOD.3 pg. 12 1-3, 12.4-1, 12.4-2 t
-7.
-,,.--e..
= - - - - - - -
w.- - - - - - - -
la__ERINCIELE1_DE_HWCLEAR_EDMER_ELAHI_QEER&IIDHg PAGE 19 IME85D DIB&51G 3t_ME AI_IE &HIEER_ A N D_ELUID_ELDE AsiSWERS -- PRAIRIE ISL AND 1E2
-85/03/26-JAGGARa F.
ANSWER 1.03 (2.00) g Co *3 C*3 a.
Bef f becomes smallerAas the core ages becaus3 of production of PU-239 which has a smaller B than U-235f(This change makes the reactor more sensitive to reactivity changes.)
(1.0) b.
Delayed neutrons are born at lower energies then prompt neutrons.
Therefore, they are less likely to leekout of the core. [0 253 Alsos they are less likely to cause fast fission.
[0.53 IF is the weighting of these two f actors.
The value of the IF at Pr airie Island i s 0.97. [0.253 (1.0)
REFERENCE Prairie Island Lesson Notes f or NET Mod.3 Tape 5.33 NUS. NET. MOD.3 pg 5.3-1s 5.3-2 ANSWER 1.04 (1 50) s.
True b.
True c.
True
[0.5 each)
(1.5)
R EF ERENCE l
NUS NET Mod.3 pg. 10.2-1s 10.2-2, 10.4-1 l
1 i
ANSWER 1.05 (1 50) a.
Increase - Temperature increases, density decreases, l e ak age increases.
i b.
Increase - As center fuel burns ups flux shifts to core entremities.
O.
Decrease - Boron ' concentration increasess absorption in downcomer increasess leakage decreases.'
[0.5 each)
(1 5)
REFERENCE NUS NET Mod.3 pg. 11.4-1
1 281HC12LES_DE_HUCLEAE_20MER_tLABLDEERAIIDNg_
PAGE 20 Id185DDINA51C3a_UEAI_IEANSEER_AND_ELUIQ_ELQM ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGAR, F.
ANSWER 1 06 (1.00)
The presence of other control rods causes.a signi ficant change in individual rod worth. [0.43 This reactivity worth difference is called control rod shadowing (effects). [0.43 This is only significant if
- he control rods are located adjacent to each other within the diffusion length of a neutron in the core. [0 23 (1 0)
TEFERENCE NUS NE T Mod. 3 pg. 7.5-1, 7.5-3, 9.4-1s 9.4-2 A1SWER 1 07 (2.00) a.
Power Coefficient [PCM/%powerl [0 253-Is the change in reactivity due to a change in r.eactor power.A Made up of the MTC and FTC.)
- .:: ?
Power Defect [PCM] [0.253-Is thegef fect of MTC and FTC on reactor control. [0.253 (ofd (1 0) b.
1.
Power Coefficient - More negative 2.
Power Defect - Increases (1.0)
(~FERENCE NUS NET. Mod.3 pg.
.1-1s 8.6-1; Lesson Notes on Tape-8 1 NSWER 1.08 (1.60) a.
As crud builds up it acts as an insulator between the fuel and coolant.
The temperature difference between the two must increase to maintain the same heat removal rate.[0.23 The i
l increased fuel temperature will cause an increase in power def ect due to the r aised dopp ler ef f ect.00.03"' The broadening rate of the resonant peaks in U238 decrease with an i nc r e as i n g temperatures [
] buts since there is a larger defect that must be divide y 100 percent power to give the coef ficients the Power Coefficient (PCM/ percent power) i s gr e at er. [D<f3 (0.8) 03 b.
Heat tr ansf er coef ficient decreasess [0 23 fuel temperature increasese [0.23 doppler defpct increags, [0.23 gower coeffIclent increases.[0.23 4ho u d e %+ mon). W ll occ-ph (0.8)
Onh tadd A t raf D p k J(,gt,,,
r REFERENCE NUS NET Mod.3 pg. 8.6-1s 8.6-2
la__tRINCIELE1_DE_HUCLEAR_fDMER_ELAHI DEERAIIDHa PAGE 21 IHEREDDINA51C3a_MEAI_IBANSEER_ABD_ELUIQ_ELDM At'SWERS -- PRAIRIE ISLAND 1E2
-85/03/26-JAGGAR, F.
ANSWER 1 09 (1.50) a.
1.
Increase-2.
decrease 3.
Increase
[0 25 each3 (0.75) b.
1.
a or b e"el( 00' "' O '" I 2.
d or c 3.
b
[0 25 each3 (0.75)
REFERENCE l'JS NET Mod.4 pg. 10 2-7, 10.2-8, 10.2-9 t
APtWER 1 10 (2.00)
'k,
Water box air ejecto'r Water box air ejector keeps condenser water boxes full ensuring all tubes are carrying circ. water to condense steam.
If tubes are not fulls less steam is condensed resul ting in hi gh cdsr.
pressure and reduced plant efficiency.
b.
Air ejector loop seal If air ejector loop seal is lost, interconderiser and main condenser vaccum equalize.
The higher main condenser pressure results in reduced plant ef ficiency.
c.
Circulating water temper ature If circulating temperature is increaseds condenser pressure will be higher and ef ficiency reduced.
If temperature is decreased, excessive condensate depression will reduce efficiency.
d.
Ch l or i nato r -
C hl or i nato r injects chlorine into cooling water system which kills algae and reduces fouling (of heat exchangers) resulting in better heat transfer.
Better heat transfer increases plant efficiency.
[0 5 each3 (2.0)
REFERENCE
- NUS NET Mod.4 pg. 7.3-2, 7.3-3s
- 7. 3-4
14__ERINCIELE1_DE_HWCLEAR_!DMEE_ELAHI_QEER&llQHz PAGE 22 IHER EDDIB &BIC34_UE AI_IRAd3 EER_ AND_ELUID_ELDM
~
ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGARs F.
ANSWER 1 11 (1.50) a.
The temper ature di f f erence between the saturation temperature for the existing condenser vacuum and the temper ature of the condensate.
(0.5) b.
Reduces cavitation in the condensate pumps.
(0.5) of mercurg =25 1.9632 ps i a c.
4" 1 9632 psia 1
F 125 F - 115 F = 10 F condensate depression (0.5)
REFERENCE NUS NET Mod.4 pg 5.3-2 ANSWER 1.12 (1.5'0) a.
The temperature above which a f ailure will be predominantly ductile. (Plus a safety factor.)
s (0.5)
(yc.rNJ*1 b.
The neutron bombardment causes an upward shif t41n the RTNDT.
(Since the heatup and cooldown cur ves are based on predicted RTNDTs the curve shifts to the right to allow for the increase in the RTNDT value).
(0.5) c.
Cu (0.5)
REFERENCE NUS NET Nod.4 pg. 10.1-2, 10.1-3* 7. S. ]r, b/g, 2, /-3 ANSWER 1.13 (1.50)
Yos.
As the RCS temperature drops, the temperature difference across the RHR heat exchanger also drops.
The cooldown rate will bo lower as a result.
The flow through the HX must be increased to maintain the same heat removal rate.
(1.5)
REFERENCE NUS NET Mod.4 Lesson Notes for Tape 5.4
(
Ic__ERINCIELES_DE_HUCLEAR_EDMER_ELAHI_DEERAIIDHL PAGE 23 IMER5DDId&51CSa_HEAI_IRAMSEER_ABD_ELUID_ELDK-~
ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGAR, F.
4 ANSWER 1.14 (1.00) a.
At 200 F density of water is greater; (more Ibm /ft3) therefores
-it takes more power to move each f t3 of water the same distance.
(0.5) t a at 200 F is greater than a at 530 F.
Examples a=
( v) (p) (3600/1hr) m/p at 200 F =
m/p at 530 F If p increases a i ncr e a s es.
If p decreases a decreases.
(0.5)
REFERENCE NUS NET Mod.4 pg. 2 3-4 ANSWER 1 15 (2.00) o.
Less than Greater than Equal to d.
Equal to ar 3
- Na 0.
Less than
[0.4 es]
(2.0)
REFERENCE NUS NET Mod.4 pg. 7.2-2s 7.2-33 Lesson Hotes Mod.4 Tape 7.2 l
1 A
-,..,,---,,..-----,.---a,..-w-
.,,a-,,,,, - -
--_-n----,-,,~e-
, - ~ _ - -. - - -, -
N 9
Ea__ELAHI DESIGN _ INCLUDING _1&EEII ABQ EBERGENCI_11SIE53 PAGE 24 ANSWERS -- PRAIRIE ISL AND 1&2
-85/03/26-JAGGAR, F.
l l
l ANSWER 2 01 (3.50) a.
Allows for additional seal injection water flow through the pump bearing for cooling purposes [0.53.
Primary system pressure mus t be > 100 psi g +-10 and < 1000 psig +-100 [0.53.
(1.0) b.
Relief valve directed to the PRT (1 0) c.
Decrease (0.5) d.- Ensymmye T.,~ _.. e,g y _,o.p,,se.i.
re-proper flow through No.
seal (1.0) e.1 ilFERENCE P.I. S ystem Descr ipt i on B-3 p.16-18; B-12 p.
51 Procedure C-3 p.10 AhSWER 2.02 (2.50)
's._ Start both Containment Spray Pumps.
[0.23 Open 2 Containment Spray Pump suction valves from the Spray Additive Tanks.
[0.43 t
Open 2 Containment Spray Pump Discharge valves.
[0.43 (1.0)
- b. Maintain pH of the water in the containment following a LOCA.
Enhance Iodine removal from the containment following a LOCA.
[0.5 es)
(1.0) 2590
- c. &990 gal.
(1950 gal. prior to modifications)
(0.5)
REFERENCE P. I. S ys t e m D e s cr i p t i o n 8-18 0 p.
10,11,16; T.S.
3.3 p.
3.3-3 r
f ~
Za__ELAHI_DESIGH_IBCLUDING_1&EEII_AND_EBERGEHC1_113IE51 PAGE 25 ANSWERS -- PRAIRIE ISLAND 162
-85/03/26-JAGGAR,.F.
ANSWER 2.03 (2.00)
The Letdown Grifice Isolation Valves will close if any of the following conditions exists
- 1. All charging pump breakers open.
- 2. A containment isolation signal is received.
- 3. A letdown line isolation valve closes.
[0.33 es.)
(1.0)
The bases for these interlocks is to limit the loss of coolant from the RCS in case of a rupture of the letdown piping and to insure ecoling water for the regenerative heat exchanger.
(1.0)
REFERENCE
-P.I. System Descriptions, B-12 p.
54, 55 ANSWER 2.04 (3.00)
/c@-//J
- a. A Jockey pump is used [0.53 to maintain pressure at W psig
[0.53.
(1 0)
- b. As pressure drops a motor driven pump [0.51startsatjb5psig
[0.53.
A diesel dr iven pump [0 53 s tar ts at JMPD ps i g [ 0.5 3.
(2.0)
.ce: w a p - p s % As/s4.gs Ar-tio psg
%~
pp.t untu n t CP3 '$
REFERENCE P.I. System Description B-31 p.
1 ANSWER 2.05 (2.25)
Jacket coolant pump Lube oil pump Fuel supply pump Air start distributor Rotor of the generator Air-inlet blower
[0.375 ea.)
(2.25)
REFERENCE 1.I. System Description B-20.7 p.
6, 8, 13, 17, CAF
Za__tLAMI_DE11SH_IHCLUDING_1AEEII_AND_EBEREENCI_IIIIE51 PAGE 26 ANSWERS -- PRAIRIE ISLAND 1E2
-85/03/26-JAGGAR, F.
ANSWER 2.06 (1 50)
- a. The long handled tool used limits the height a fuel assembly can be raised by physically contacting the crane holst.
(1.0) b.
14 ft. below the surf ace.
(0.5)
REFERENCE P I. System Descriptions B-17 p.
4 ANSWER 2.07 (2.00)
/. At 95 psi g the pref erred compressor will start.
[0.53 J. At 90 psig the 1st standby compressor will start. [0.53
- 3. At 85 psi g the 2nd standby compressor will start (0 53 and the Sor wice Air supply valve (MV-32318) will close.
[0.53
- c. 3 (2.0) q, 2,.,. g b.b
~1. -bevs.n we eqt p-ess--4 erg.vst<c %%% s gtga $ Q C, D. Pehsk. gvss, rg Alt wM m asA m D PIM U O AMe. CawDsOMs N9 bm was b eM go 2 A ko Pr(@7 REFERENCE g
P.I. System Descriptions B-34 p.
14s 18 l
AhsdER 2 08 (3.00) j
- o. The associated RHR train discharge pressure must be less than I
210 psig AND the associated SI suction isolation valve closed.
[0.53.
This prevents RHR supply water to the SI system during recirculation from entering theRWSg0.53 g4 (1.0)
- b. After the RHR to SI supply valves are open, the SI pump suction valves can be re-opened. [0.53 This path is used when draining the refueling canal into the RWST. [0.53 (1.0)
-c.
The recirculation containment sump B valves (MV-32075s 76, 77 E78) will not open unless one of the two SI test line to RWST isolation valves are closed. [0.53 This prevents contaminated sump water'from entering the RWST. [0.53 (1 0)
REFERENCE i
P.I. System Description B-15 p.
14, 15 t
5
-n-- - - -
O c
REACTOR COOLAhT PUMP To Containment Upper Motor 8"""
Be.. ring oil cooler A
a E
A p<150 gpr
d l
i J.
c Lower Motor 5 gpm ~ ~ " " '. ' ' '.
Bearing oil J-Cooler
{}-----
l 6
A l}40gpmy'h......
E
b::s, s
= ~ ~ -. -
5 (T
Thermal
/
i l
re Barrier /lleat Disc,uar ge k/-
Exchanger n
[-
a Suction
-Compo cooling Water Supply & Return NOTE: Valve Numbers Assigned are for No. 11 R.C.P.
COMPONEhT COOLINO WATER FLOW THROUQi REACTOR C00LAh7 PLNPS L
FIGURE B3-11
1 Za__ELAMI_DE11SH_ INCLUDING 1&EEII_AND_EEERGENCI 111IE51 PAGE 27 ANSWERS -- PRAIRIE ISL AND 1&2
-85/03/26-JAGGAR,.F.
i ANSWER 2.09 (2.00)
Sce attached Figure 83-11 flow paths--33 0.2 es. [0.63 i
(solation valves--3 plus 1 check valve 3 0.2 es. [0.83 Approx. values--Upper Be aring-150 gpm Lower Bearing-5 ops There. Bar. HX.- 40 gpa 0.2 ea [0.63 (2.0)
REFERENCE P.I. System Descriptions B 3, Fig. 11 i
?
ANSWER Ley b+k LecA, smo b+{ loc A Si'a" Ime b ra(
2.10 (3 25 i
- a. 4444+ 0;d. 5 ';;;' e n, 1...
ef 3 = w viid u y Cvo;;at, S/G Tube Rupture.
[0.25 es.3 (1 0)
- b. Active In ectio ~[0.253 Insures initial cooling of the core
%'p ] Q g,
a erminates any reactivity increase.
Accumulator Injection [0.253 Rapidly reflood the core with 4
borated water following a l arge LDCA. [0.53 Rec i rcu l ati on [0.25 3---Provi des long term decay heat removal from the core following a LOCA. [0 53 (2.25)
REFERENCE P.I. System Descriptions 8-188, pp. 3-6 i
4
i la_ 1811RMBENIS_AND_CQHIRDL3 PAGE 28 ANSWERS -- PRAIRIE ISLAND 1E2
-85/03/26-JAGGAR, F.
4 i
ANSWER 3.01 (3.00) i (Steam flow increases. causing increased removal of heat from the s.
RCS, reducing Tave.) Tave - Tref deviation causes rod control circuit to withdraw rods to restore Tave.
(1 0) t (This causes reduced efficiency in the secondary plant cycle for the same turbine load output.J Tave will decrease because of greater heat removal.
Tave - Tref deviation causes rod contro'l circuit to withdraw rods to restore Tave.
(1.0) c.
This causes increased N-44 output which results in the power mismatch circuitry inser ting rods to match turbine power with indicated nuclear power.
(1.0)
REFERENCE P.I. System Description s B-7 p.
5-7
~+
ANSWER 3.02 (2 00) a.
True.
False.
False.
d.
True.
[0.5 each3 (2.0)
REFERENCE P.I. System Description, B-9 p.
9, 18-20
3h__IMSIEU5EMIS AMD.CDNIRDL3 PAGE 29 ANSWERS -- PRAIRIE ISLAND 162 85/03/26-JAGGAR, F.
ANSWER 3.03 (3.25) e.1. IMP IN-Ref erence--Percent of Load Feedback-Impulse Pressure
- 2. IMP OUT-Reference--Percent of valve position (0-ID V)
Feedback None
[0.25 es.3 (1.0)
- b. 1. Use Turbine Manual Pushbutton
- 2. Load reference channel failure
- 3. Speed reference is dif f erent from turbine speed by (10%)
- 4. Turn the Maintenance Test key f rom TEST to 0FF
[any 3 3 0.25 e s. 3 (0.75)
- c. 1. Generator lockout contacts (86) actuated
- 2. Both main feed pumps tr(<ip
- 3. Auto-stop Oil pressure 45 psig)
- 4. Reactor trip
- 5. High Level in the. Feed Water Hester 11s 12s or 13 6.
Hi-Hi Steam Generator water level
- 7. m v 'c h c(
[0.25 es.1 (1.5)
- t. s.'U.
4.
I(, T~ l0 JceE REFERENCE P.I. System Descriptions B-23 pp.
6, 7, 28 C
ANSWER 3.04 (3.00) l
- a. Bypasses the to-lo Tave block Inter lock and (allows steam dump to the condenser only below 540 F).
(1.0)
- b. 540 F Tave or interlock bypassed.
l
> 16" Hg vacuum in A & B condensers.
At least one circulating water pump running. (Breaker contacts shut)
[0.33 es.)
(1.0) i L
- c. Loss of Load-- 101 in < 2 min.
L Steam Pressure Mode Selected.
Co.5 es.1 (1.0) i l
l REFERENCE i
P.I. Ques tion Bank 3-28: 4-13 l
1 i
i
,.,n,,-.,---v,-
,.w--w
.---.m-mm. - - -,, - - - - - - - ~,, - -,, -, -, - - - - - - - - -,
la._IB1IRUBENIS_ADQ_CQUIRDL1 PAGE 30 ANSWERS -- PRAIRIE-ISLAND 162 85/03/26-JAGGARs F..
1 i
ANSWER 3.05 (1.50)
- a. Steam Flow dP and Steam Pressure (1.0)
.b.
Higher (0.5)
REFERENCE P.I. System Descriptions B-7s pp. 29-30 ANSWER 3.06 (2.00)
The falso high signal will not allow Tevo to program down with the ramp thus Tave will remain at 560 F. [0.53 P-7 will not actuate when power reaches 101 44,61*Wi thout P-7s the low pressure trip will remain active.
Whwn the RCS pressure reaches 1,900 psig 50.51 '
the trip breakers will open automatically. 00.;;"- % LewtCewb I (2.0)
$ kun3~ 5
- H Wo [pl). Pte.l. gut n 6.,.,g1 R fl})
REFERENCE P.I. System Description B-8 pp. 2 0-21; B-7 pp. 2-3, Fig. 87-5 ANSWER 3.07 (3.00)
- s. Propor tional heaters Back-up heaters Spray valves PORV
[0.25 es.3 (1.C)
- b. Yes, the output should follow the parameter direction.
(1.0)
- c. Controller output should decrease to raise pressure. 011 (1.0)
REFERENCE P.I. System Description B-7 pp. 18-20 p
mw,
.-+n,n, n
.,.,.,n.-
w-
--,-_n,.,,. -. - -
Ic__181IEU5ENIS_AND_CDMIRDL1 PAGE 31 ANSWERS -- PRAIRIE ISLAND IC2
-85/03/26-JAGGAR, F.
1 l
ANSWER 3.08 (2.50)
A.
1.
.Tave.
2.
dT.
3.
Pressure.
4.
dI.
[0.25 es.3 (1.0) 8.
DN8.
(0.5)
<C.
1.
Turbine runback.
[0.53 2.
Blocks automatic rod withdrawel.
[0.53 (1.0)
REFERENCE P.I. System Description, 8-8s pp. 9-13 ANSWER 3.09 (3.5.0)
A.
Prevent overloading motors due to the high water content (denser atmosphere) during a LOCA.
(1.0)
- 8. Shif ts to accident operations rerouting air flow through
.(the cooling coils, fan) the buttprfly vgly stotpg g
er containment. g p jf k Qd f.'
(
p
(
High Radiation.
Manual containment isolation.
Manual containment spray.
R-ils R-12, or R-22 +-Std*
[4 3 0.4 es.]
(1.6) i REFERENCE P.I. System Descriptions 8-18, pp. 18, 67, 82.
ANSWER 3.10 (1.25)
- a. Average Delta T.
0::: d i;.-% e..;sion.
(0.5)
- b. Insure adequte SDM.
Minimize severity of ejected rod accident. (and rod misali gnment)
Acceptable nuclear peaking factors (Fn delta H) 4CiFifLe (0.75)
REF8RENCE' F.I. Plant systems Lesson Plan Handouts, Plant information summar y.
~
is._ERDCEDURE1_=_HDRHALa_ABHDRBALa_EBERGENC1_AHQ PAGE 32 RADIDLDSICAL CQHIROL
'Al:SWERS -- PRAIRIE ISLAND IC2
-85/03/26-JAGGAR, F.
ANSWER 4.01 (2.25)
- c. Notify the shift supervisor of the location and apparent nature 1
of the injury.
(0.75)
- b. Where life or limb of the casualty appears to be endangered.
(0.75)
- c. When the victim is in a dangerously high radiation field.
(0 75)
REFERENCE P.I. Procedure F-4, pp. 8-9 ANSWER 4.02 (2.50)
. (1101)(I101) = (I2D2)(12D2)
[0.53 i
1200(2)(21/(5)(5)=192' ar/hr (192 mr/hr)(2 hr.)= 384 ares (0.753 (1 25)
- b. 900 arem + 384 area = 1284 ares
[0.253 Ne exceeded normal 10CFR20 whole body limit of 1250 mrem.
If assume that NRC FORM 4 is completes then limit of 3000 arem is not exceeded.
[1.03 NOTE: Answer to "b" is dependent on answer to "a" and graded accordingly.
(1 25)
REFERENCE P.I. Question Banks 5-16 l
4
r 1
&c__REDGEDURE3_=_NDRd&La_AADDRBALa_EEERGENC1_ARD PAGE 33 RADIDLDGICAL_CDHIRDL j
ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGAR, F.
ANSWER 4.03 (2.50) a.1. Gen er a l surve i l l ance under any condi tions.
- 2. Direct operator guidance. when outside the FRG's or EC A's.
4
[0.25 es.3 (0.51
- b. 5, 3, 1, 6,
2, 4
[0 2 es.3 (1 2)
- c. 1. RED--Immediately initiate indicated guidline.
- 2. ORANGE--Implement the associated FRG when all trees have been checked.
- 3. YELLOW--Implement FRG when practical.
- 4. Green-- No action required.
. [0.1 for order and 0 1 for ac t i o n 3 (0.8)
REFERENCE IF-0 Background information pp. 1-4 AHSWER 4.04 (2.50)
- a. A steam void will form above the lowering water and pressure will drop until saturation is reached.
The pressure drop alli not be controlled.
(1.0)
- b. 1. A void formation in the vessel head.
2.
To cause the void to lose saturation and collapse.
- 3. Allow room for expansion for potential volds without going solid.
[0.5 es.3 (1.5)
REFERENCE ES-0.5 and Background Information
(
m ha__EEDCEDULE1_=_BDidALa_AAMDEBALA_EBERGENC1_AMD PAGE 34 LADIDLDG1LAL CDUILDL ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGARs F.
ANSWER 4.05 (3.00) a.
RCS borated to at least the cold shutdown concentration (or i
greater) or borated to the hot xenon free concentration and is being maintained at no-load average temperature.
(1.0) b.
3%
(0.5)
I c.
RCS--60 F/hr) Pzr--100 F /hr (1.0) de By the use of heaters.
(0.5)
REFERENCE
.O.I.
Procedure C1.2 pp 5,6,7 ANSWER 4.06 (2.503
- a. The motor run for 20 minutes (prior to the third attempt) or it has been idle for 45 minutes.
(1 0)
- b. 1. Insure a steam bubble is formed in the pressurizer.
- 2. Cool the RCS below seal water temper ature.
l
- 3. Restrict seal injection flow to the RCP to <10 minutes prior to pump start.
(0.5 es.]
(1.5)
REFERENCE P.I. Procedure C3 p l
___,...x,
, - - -.. ~..
_._.,y_.__m___
h a__ tRDC ED URE1_=_ NDRB A La_ ABBDR BAL a _EBEREEN C1_ A12 PAGE 35 RADIELDGIEAL CDNIRDL i
A'45WERS -- PRAIRIE ISLAND 1E2
-85/03/26-JAGGAR, F.
i ANSWER 4 07 (2.00)
[0.23
)
l
- 2. Total feed flow to intact S/G's >200 opa Co.23 OR Wide range level in one S/G >60%. [0.23
- 3. RCS pressure >2000 psig and stable or increasing.
[0.23 4.
Presurizer level >10%. [0.23 (1.0) t, RCS subcooling (based on core exit TC's) <50 F.
[0.253 OR Pressurizer level cannot be maintained >5%.
[0.253 (0.5)
- c. No, the. Reactor Trip Breakers have not been cd'M I, thus, the i
automatic SI has not been reset (reinstated).
NOTE: MayanswerYES.ifassumeRTbreakersarec147 (0.5)
REFERENCE ES-0.2 p.
3; SI Logic diagram. ; Ei - o f 6 / c r
i
+
1 1
,.... ~..............,
r i
in__ERDCEQUEf1_=_HDRUAta_AadQRBALa_EBERGENC1_AND PAGE 36 EADIDLDEICAL_CDMIRQL ANSWERS -- PRAIRIE ISL AND 1&2
-85/03/26-JAGGAR,'F.'
i 1
j l
A NSW ER 4.08 (2 00)
.s a.1. Check Fire Detection Panels 'for af fected zone. [0.33
- 2. Contact BOP to check the zone. [0.23
- 3. Announce the fire over the page. [0.23 4.
Actuate the fire alarm. [0.33
- 5. Bypass the af f ected zone and reset the system. [0.23 (Report the fire to the, Red' Wing Fire Department if on a backshift).
6.
Insure the Fire Pumps have started proper ly. [0-23 (Notify guardhouse.if Red Wing Fire Dept. has been notified.)
(1.4)
- b. Class A--Drdinary combustibles such as paper, wood cloth, etc.
CO2, Water, Ha, Drysc hemi c a l.
Class B--Flammable liquids or cases CO2,. Ha, D r y che mi c a l, AFFF C4a m)
Class C--Energized electrical equipment CO2, Har D r y c he m i c a l, vaak-50 **
[0. :. e s. 3 (0.6)
REFERENCE P.I. Procedure Section F, F5 pp.
2-3, 6-7 ANSWER 4.09 (1.75)
(0 53 b.1. Increase RCS pressure.
- 2. Cool the head with CRDM cooling fans.
- 3. Vent the head to the pressurizer.
[0.25 es.)
(0.75)
- c. Add-cold water to the secondary side.
(0.5)
REFERENCE P.I. procedure C1.3 p.12
l ha__ERDCEDURE1_=_DDEBALa_ABHDEBALa_EBERGENCI_AND PAGE 37 SAQ1DLDGICAL_CDNIRDL ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-JAGGAR, F.
ANSWER 4.10 (2.00)
- a. 1. Pick up the radio.
- 2. Manually trip the reactor at the reactor trip breakers.
3.
Verify turbine trip at the pedestal.
- 4. Report to the remote S/D panel.
[0.25 es.]
(1 0) o.
1.
(Use last known boron concentration in calculation).
- 2. Place Boric Acid Pump in " local".
- 3. Close RMW & Emergency Boration Isolation to Chg. Pump Suc t ion va lve (VC-11-58 ).
l 4.
Open Emergency Bor,ation to Chg. Pump Suction MOV (MV-32086) manually.
- 5. Start pump.
- 6. Open VC-11-58 as necessary.
7.
(Observe ficw).
[0.2 es.3 (1.0) f REFERENCE P.I. Procedure C1.8, pp. 2s 5-6 ANSWER 4.11 (2.00)
- 1. - a
- 2. - d
- 3. - c
- 4. - b
[0 5 es.)
(2 0)
REFERENCE EPIP F3.2 pp. 1-2
e.
TEST CROSS REFERENCE PAGE 1
QUESTION VALUE REFERENCE s-m--
01 01 1.90 FSJ0000368 4
01 02 2.50 FSJ0000369 01 03 2.00 FSJ0000370
.01 04 1 50 FSJ0000371 01 05 1.50 FSJ0000372 01 06 1.00 FSJ0000373 01 07 2 00 FSJ0000376 01 08 1 60 FSJ0000375 01 09 1.50 FSJ0000376 01 10 2.00 FSJ0000377 01.11 1.50 FSJ0000378 01 12 1 50 FSJ0000379 01 13 1.50 FSJ0000380 01.14 1 00 FSJ0000381 01.15 2.00 FSJ0000382 25.00 02.01 3.50 FSJ0000383 02.02 2.50 FSJ0000384 o r.03 -
2.00 FSJ0000385 g 04 3.00
- FS J 00003.86
=0a.05 2.25 FSJ0000387 02.06 1.50 FSJ0000388 0'2 07 2 00 FSJ0000391 02.08 3.00 FSJ0000392
'02 09 2.00 FSJ0000393 02.10 3.25 FSJ0000404 25 00 03.01 3.00 FSJ0000389 03.02 2.00 FSJ0000390 03.03 3.25 FSJ0000394 03 0A 3.00 FSJ0000397 03 05 1 50 FSJ0000398 03.06 2.00 FSJ0000399 l
'03.07 3.00 FSJ0000402 03.08 2.50 FSJ0000403 03 09 3.50
-FSJ0000416 l
03 10 1.25 FSJ0000417 l
25.00 04.01 2 25 FSJ0000405 04.02 2.50 FSJ0000406 04 03 2.50 FSJ0000407 04.04 2.50 FSJ0000408 04.05 3.00 FSJ0000409 04.06
'2.50 FSJ0000410 4
f TEST CROSS REFERENCE PAGE 2
QUE STION VALUE REFERENCE
~
s - ---
04.07 2.00 FSJ0000411 04.08 2.00 FSJ0000412 04.09 1.75 FSJ0000413 04 10 2.00 FSJ0000414 04.11 2.00 FSJ0000415 25.00 100.00 I
o e
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3,0 U.S. NUCLEAR REGULATORY COMMISSION c
SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
Prairie Island REACTOR TYPE:
Westinghouse DATE ADMINISTERED:
March 26, 1985 EXAMINER:
T. D. Reidinger 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 in-dicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
% of
. Category
% of Applicant's Category Value Total Score Value Category 23 C
1Er 5.
Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics mL3
' -96 6.
Plant Systems Design, Control, and Instrumen-tation 25 7.
Procedures - Normal, Abnormal, Emergency, and Radiological Controls 25 8.
Administrative Procedures, Conditions, and Limitations V7 400 TOTALS FINAL GRADE All, work done on this exam is my own, I have neither given nor received aid.
Applicant's Signature a
I, a
l5.
THEORY OF NUCLEAR POWER-PLANT DPERATION, FLUIDS, AND PAGE 2
QUZSTION: 5 01
-(
.50)
-Choose the CORRECT' response.
The installed neutron source currently used at Prairie-Island:
-( e ) is needed to initiate the fission process.
(b) produces neutrons by the alpha decay of Antimony 123.
'(c)1 produces ~ neutrons by the spontaneous fission of Californium 252.
L(d) is a-type-of photo-neutron source.
OllESTION 5.02
(
.50)-
Ch'oose the CORRECT response.
The approximate value for 100% power
.aquilibrium. xenon' reactivity at Prairie Island is:
.(a) 1800'.pem
-(b) 2080 pcm (c) 2600 pcm.
(d)'3400 pcm 0UrSTION 5.03
(.50)
!Cacose^the CORRECT response.
To minimi:e radweste and boric acid changes,
'eparators will ' ride the' Xenon curve' by:
- y
-(a), increasing power by dilution, then borating to compensate for Xenon
~
'burnup, and then diluting again for Xenon buildup.
-(b) increasing power by dilution, then inserting control rods to compensate for Xenon'burnup, and then withdrawing control rods again for Yenon buildup.
-(c) increasing power by rod withdrawal, borating to compensate for Xenon burnupe'and then diluting to compensate for Xenon bJildup.
(d) increasing power slightly by' dilution, allowing Xenon.burnup to E
increase Tava, then increasing power to keep Tavs mak:Ded to Tref.
('-
u:
,=
A.
e c
I5.. THEORY'0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND-PAGE 3
7pgggggggggggg--------------------------------------
.GUESTION-5.04'
(.50)
Choose the CORRECT response concerning Samarium:
(ls The change in Samarium concentration following a reactor trip will diminish:the shutdown margin.
(b) Samarium is produced as a' result of the beta decay of promethium.
(c) The. equilibrium Samarium. concentration is directly proportional to reactor-power.
(d) Samarium beta' decays to Europium.
DuESTION 5.05
(.50)
Which of the "ollowing statements about reactivity is CORRECT?
h ); Retetivity is the ratio of the neutrons in the present generation divided by the neutrons in the preceding generation.
(b)fReactivity exactly equal to one means that the reactor is critical.
.(c)- Reactivity can be either added to or renoved from the core.
(d)-Reactivity is the fractional change-in neutron population per
~
generation.
'OL.STION 5.06
-(
.50)
Choose the CORRECT response.
Assume Prairie Island is suberitical with an zinitial count rate of-25' counts per second.
Rods are withdrawn to add 300 pea of-reactivity, resulting in a stable count rate of 40 counts per escond.. Which of'the following is closest to the value of Keff after.the rod. withdrawal (when the count rate is 40 counts per second)?
-(a).950
.(b).990 (c).995.
L(d).999.
m..
i f
ma.
m,
-l t-e 5.
'THEORYLOF NUCLEAR POWER PLANT' OPERATION, FLUIDS, AND PAGE 4
QUESTION 5.07
(
50)
Which of-the'following nuclides is NOT a fissile nuclide which contributes
- ficsions - during power 1 operation at Prairie Island?
. (c)-uranium 235
-(b) uranium 238
-(c)nplutonium 239'
-(d) plutonium 241 QUESTION 5.08
('.50)
~ Choose the CORRECT-response.
The major contributor to fast fission at Proirie' Island is:
-(d) plutonium 241-GUESTION 5.09-(.50)
Choose.the' CORRECT response.
The Importance Factor at Prairie Island is
,______ than one because delayed neutrons ________________.
-(e) lessi are less likely to leak from the core.
(b) lessi-do not cause-fast fission.
,( c ) greater; are less likely to leak from the core.
~(d) greateri do not cause fast fission.
(
i to
~ '5.
" THEORY OF NUCLEA'R POWER PLANT OPERATION, FLUIDS, AND' PAGE 5.
QUESTION 5.10
'C'.50)
JChoose the-CORRECT. response.
With a startup rate of.5 decades per minute, r9setor power will increase by a factor of 5 approximately every:-
(a) 60 seconds.
(6, 72 seconds.
-(c) 84-seconds.
(d) '96 seconds.
Ot!ESTION 5.11'
-(
.50)
Choose.the CORRECT response.
The isothermal temperature coeff icient is the sun of the-moderator temperature. coefficient and the (a) fuel temperature coefficient ~when power is below the point of adding heat.
(b) power coefficient when power'is below.the point of adding heat.
(c)-fuel temperature coefficient when power is above the point of adding heat.
-(d)' power coefficient when power is above the point of adding heat.
QUESTION-5.12
'(
.50)
Choose the CORRECT'recponse.
The void coefficient 't Prairie Island:
(c) is the same sign'(positive or negative) as the moderator temperature coeficient.
(b) is unaffected by changes in boron concentration.
(c)-is nonexistent unless there is bulk boiling.
(d) is.the same sign (positive or negative) as thefpressure coefficient.
e k
- 5.. THEORY OF; NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6
g g--------------------------------------
t s 0UESTION 5.13
(.50)
Ch:ose the CORRECT-response.
As fuel temperature increases, control rod
-w rth ______~iles the relative thermal neutron flux which the control rod Oxperiences; increases, control rod worth _______.
(c) increases; increases (b) increasesi decreases (c) decreasesi ~ increases
-(t) decreasesi. decreases
. 0UISTION. 5.14
. (.50)
Choose the CORRECT ~ response.
4ssuming a constant flux profile, control rod worth ~ increases as __________ increases.
-(c) boron concentiation (b) total. core flux
- (c) fission product concentration
.(d). moderator temperature
'UUfSTION-5.15
(.50)
- Choose the. CORRECT response.
Differential boron worth for a given Tavs
. (referfto Figure 5-1) is more negative at lower boron concentrations bacauset (a) of.the thermal flu:. redistribution at lower boron concentrations.
(b). fewer boron atoms'are available'to compete with each other.
(c) fewer fuel atoms are present, reducing the thermal utilization coefficient.
(d') of the harder neutron flux spectrum at lower boron concentrations.
t
5.
THEORY ~0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7
GUESTION' 5.16
(
.50)-
Choose the CORRECT response.
Di'ferential boron worth for a given boron concentration (refer to Figure 5-1) is more negative at 547 F than it is
-at 560 F because the:
(a) moderator density is less at. higher temperature.
(b) boron absorption cross section decreases at higher temperature.
.(c). neutron spectrum is harder at higher temperature.
.(d) neutron leakage is greater at higher temperature.
QUESTION 5.17
(
.50)-
C'qose the CDPRECT response.
' Shutdown Margin' as used in Technical-a,. 't c i f i c a t i o n - 3. 1 0 is the, amount by which t he reactor core would be sub-esitical at hot shutdown conditions if all control rods were tripped, cssuming:
'(e) normal hot channel factors are maintained, and assuming no changes in xenon or boron concentrations.
( b )- that the highest worth control rod assembly remained fully withdrawn, and assumin3 xenon-free conditions and no changes in boron concentrations.
(c) normal hot channel factors are maintained,-and assuming xenon-free conditions and no changes in boron concentration.
(d).that the highest worth control rod assembly remained fully withdrawn, and assuming no changes in xenon or boron concentration.
- 00EETIC;s 3.16
(.50; cM
(
Choose the CORRECT. response.' The ghuimum'Y4 1 element life allowed at Prairie Island is ______, which is based on _____ _________.
s (e) 44,000 MWD /MTU; fuel pellet swelling (b) 44,000 MWD /MTU; oDed deteriora tion
~
(c) 50,0 8'bHD/HTU; fuel pellet sh elling
--(d) 5,000 MWD /MTU; clad deteriorakion S-
~
FIGURE 5-1 MOD. TEMP.
' DIFFERENTIAL BORON WOR {H.
TAVG = 547
- VS.
- r-BORON CONCENTRATION
. T. A.V_G_.=. _5_6_0_*
UNIT 1 CYCLE 9 1700
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5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 8
QUESTION 5.19
(.50)
.Chcose the CORRECT response.
The procedures for the control of Axial Power D) :tribution are designed to:
(a) minimize the effects of xenon redistribution during load-follow.
-maneuvers.
(b) serve as backup protection against a dropped or misaligned control rod.
(c)~ ensure adequate control rod reactivity.
(d) limit potential reactivity insertions due to a control rod ejection accident.
'[
QUESTION 5.20
(.50)
C' oose the CORRECT response.
What action is required by Technical Specifi-c; tion 3.10 if' Delta I is'-12% when reactor power is 95%?
Refer to Figure 5-2.-
la) return Delta I to the target band within one hour or be in hot shutdown within the next four hours.
(b) reduce reactor power to less than 50% within one hour and reduce the high neutron _ flux setpoint to less than 55% within the next four hours.
reduce reactor power 1% for each 1% deviation from the_ target band within 15 minutes.
(d) return Delta I to the target band within 15 minutes or reduce power to less than 90%.
GUESTION 5.21
(.50)
Choose the CORRECT response.
What-action is required by Technical Specifi-cation _3.10 with Delta I at -20% and reactor power at 70%?
Refer to Figure
- 5-2.
(a) return Delta I to the target band within one hour or be in hot shutdown within the next four hours.
(b).redvee-reactor power to less than 50% and reduce the high neutron flux setpoint' to less than 55%.
(c) reduce reactor power 1% for each 1% deviation from the programmed band.
(d) return Delta I to the target band within 15 minutes or be in hot shut-down within the next hour.
4 0
a.-
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 9
'5.----
QUESTION 5.22
(.50)
Choose the CORRECT' response.
With reactor power at 10%, penalty deviation
-cutside the target band shall be accumulated on a~ time basis of __________.
Refer to Figure 5-2.
'(a) one minute penalty for each one minute ~outside of the target band.
(b) one half minute penalty for each one minute outside of the target band.
(c) one minute penalty for each one half minute outside of the target band.
(c zero minute penalty for time outside the target band.
GJESTION 5.23
-(
.50)
Choose the CORRECT response.
In which of the following situations will the further insertion of control rods cause Delta I to become more positive?
(a) Buildup of Xenon in the top of the core with rods fully withdrawn.
(b)' Positive MTC during a reactor startup.
-( c ) Bank D control rods inserted to the core midplane.
(d) Excessively negative HTC at EOL.
"GUESTION 5.24
(.50) jChoose the CORRECT response.
In order to permit immediate return to full power after a slow decrease from full power to 20% power, the operator should (a) allow Delta I to drift to within 2% of the lower end of the target band and keep it there throughout the power reduction.
(b) maintain Delta I in the middle of the target band throughout the power reduction.
(c) maintain all control rods withdrawn throughout the power reduction.
(d) allow Delta I to drift to within 2% of the upper end of the target band and keep it there throughout the power reduction.
es t
FIGl'RE 5-2
.f TARC.E" TLUX D!rTERENCE VS. PERCENT POW ER e
UNIT 2 Date: 04/07/82 30
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- 5.,
THEORY OF-NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 10 q
QUES
-(
.50) y-A 53M'.:
QS L T
1t 1.L.WL r:
NE3ATIliE A
Choose the C'ORRECT response.
.c tu 1
ncore Delta I always rea s wx _ _
\\g then excore Delta I because
'(c) loweri some neutrons f om the upper ore cross ver to the lower core and vice versa.
p
- (' b ) lowept incore.detee ors are l ess sensi ive than exco - detectors.
(c') h;fIher.;
some~neut7ons from th e lower cor cross over to e upper core nd vice versa.
/
/
-(d) higheri incore detectors are more sensitive than excore detector s.
('
QUESTION 5.26'
(.50)
Choose ' the CORRECT r esponse.
For a Ovadrant Power Tilt Ratio (GPTR) of 1.09-Technicc1LSpecification 3.10 requires that the operator (a) reduce reactor power to less-than 50%.
-(b)Lreduce reactor power to rated power less 2% for every percent that the OPTR exceeds 1.0.
(c) bring the reactor to hot shutdown.
-(f ) reduce reactor power to less than 85%.
QUESTION ~ 5.27 (1.50) fFme-three situaticns which could cause a Ovadrant Power Tilt.
QUESTION 5.28
(.50)
Choose.the CORRECT response.
The major source of tritium in the RCS is:
(0) diffusion through the clad of tritium produced.by ternary fission.
(b) reaction of lithium 7 with thernial neutrons.
(c) reaction of lithium 7 with fast nuetrons.
(d). deuferiusi activation.
I
4 5.
THEORY OF NUCLEAR POWER PLANT OPERATION,. FLUIDS, AND PAGE 11 g
. QUESTION 5.29 (2.00)
Tha hot channel factor limits will be met for normal operation provided four conditions are observed.
Name these four conditions.
QUESTION H5.30
(.50)
Choose:the CORRECT response concerning the Nuclear Enthalpy Rise Hot Channel Factor'Ffn.
~(c).The operator has direct control-over F[g through movement of rods.
(b) Abnormal perturbations in the radial power shape affect F[g (c) An error in the predictions for radial power shape can be conipensated-for-in Ffg by tighter axial control.
The horizontal power shape at the point of maximum heat flux is
- s directly related to F[g.
QUESTION 5.31 (1.50)
Technical Specifica' tion 3.10 lists three'DNB-related parameter limits which shs11 be maintained during power operation.
What are these three limits?
DUESTION 5.32
(.50)
Which of-the following conditions is NOT~necessary to cause brittle fracture?.
(a). pre-existing defects (b) load stress greater than yield stress (c) temperature below the nil ductility transition temperature (d) residual stresses i
r.
.. o
-- s
- 15. - THEORY OF ~ NUCLEAR POWER PLANT OPER ATION, FLUIDS, AND PAGE 12 00ESTION 5.33
(-
.50)
'Chaoseithe CORRECT response.
High energy neutron exposure increases the possibility of? brittle fracture of the reactor vessel by increasing the
_________________ of theEreactor vessel.
'(a)-niliductility transition temperature-(b) plastic deformation-
- (c) load stress (d)-yield stress OrESTION' 5.34 (2.00)
For; parts (a) and (b) of this question, refer to Figure 5-3.
-(0) What-is the basis for curve-A?
(1.0)
-(b) What is'the basis for. curve B?
(1.0) 100ESTION 5.35
(.50)
Choose-the CORRECT response.
With an RCS temperature of 220 F and a-steam bubble in the pressurizer, the maximum pressure at which pressurizer-spray il-allowed to-be used is _____.
(a) 1348 psis
.(b) 1148 psig
( i) 948 psis
-(d) 748.psis-L s
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Indicated RCS Te:rerature, *F FIGURE 5-3
F-9_
.5i : THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 13 QUESTION
<5.36-('
.50)
-Choose the CORRECTLresponse.
Innorder'to maintain a 200 F subcooling.
osrgin in'the RCS when reducing.RCS pressure to -1600 psis, steam-generator
.prossure must' be r educed to appro::imately'
.(a)~845 psig-
- ( b )' 6451psis
-( c ) 445 psig
. ( d' 245'psis UdESTION 5.37
(..50)
Choose the. CORRECT response.
When the flow rate through a centrifugal pun.p increases,Ethe required N,PSH _______, and the available NPSH _______.
(c). increases; increases
-(b)1 increases; decreases (c) decreases; increases
-(d) decreasesi decreases "OUESTION 5.38
(.50)
~
Which of the'following conditior.c is NOT indicative of peamp runout?
'(a) abnormally high discharge pressure (b). excessive current in the pump motor (c), failure of-the coupling between the pump shaft and the motor shaft
~
-(d) available NPSH less than required NPSH Y
.(
g g-
~
p p -.
5.: -THEORY OF NUCLEAR POWER-PLANT OPERATION, FLUIDS, AND PAGE 14 2
QUESTION t5.39
(-
.50)
-Choose the CORRECT-response.
' Assuming a11'other factors are identical, the cess flow rate _'of. fluid through a 10 inch diameter pipe will be approui-Octely._____ times:as great as the mass flow rate through a2 inch diameter pine.
(n)'2.5 (b) 5.0.
~(c) 12.5
'(d) 25.0 QUESTION: -5.40
(.50)
' Choose the CORRECT. response.
The circonium-water reaction:
-(a)~does not' occur'at normal clad temperature.
(b)' increases the concentration of dissolved oxygen in the RCS.
~
(c)~ contributes to clad hydriding.
(d) contributes-to clad densification.
'e L.-
v
.. ~
N y
EQUATIONS
-REACTOR THEORY RADIATION Ft.UIDS/TilERM0/ HEAT TRANSFER
=
x i
8 P = P,e
- = P,10 N=Ne k = Alptvt = A2p2V2 A = AN i=b+0 D
=0 D
Q = AtVi = A2V2 or t p
Ap Ap 7,7,-px = I 10 *!
L in " out + AEstored k-l k, - k f
p=
^
i k kg
= AR AT s = 0.693 E =,KE + PE + U + pV + Q + W k
2 R/hr @ d feet =
gZ 2
2 point source 8
cp I
Iidt
=1d2 2
I Ii t - 12d2 - line source "g
d
-=1-k C
H R/hr x time = R reduced for - turbine, SG pump, nozzle,
. cps Rad x QF = Rem ri ice, condenser, pipe, Rx M
cps flow a /dp
%o x % ad n
TI,gg = Th Bi R
f t y2 2
Onet " O Ddoppler + Dmod + Dvoid Bio +
'I ea ss = f r Imad loss a V Rad D 2g e head loss a Ap
+pXe
- DSm + DPu +
P=h
+pambient
=k F = pA E
Soron + prod + pfuel +
c p
AP2pu " api @ e x K Poisons) k = f(quality & Pressure)
O Pump laws speed u flow k2 =k t + 3k (speed)2a pressure 6k=k-1 MATil (speed)3a power Q = kAAT = hAAT = UAAT SUR = 26.06 a
9 ~ *
=b T
I?V log b = a Q = mah y
Q = cot p, 3.1 x 1010 e
log x = c log x All = m e. AT P
1gx-1gy U = en c AT E = No 1g
=
4 = nv 1 g xy = 1 g x + 1 g y H = U + pV AS = S Defect = Coeff x A Parameter T
pV = nRT ptVi, p2V2 Ti T2 C V1 + C2V2 = C (Vi + V2)
L cn Table 1.
Saturated Steam: Temperature Table ads Press 50ecihc Volume Entharpy Entropy Temp lb per
$at
$8t
$41 Sat.
$4t Sat fem 0 Fahr 50 in.
Li0w0 (v8p Vapor Leomd EvP0 Vapor Li0md Iv8p V8por Fahr t
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6,,
s, t
32 8 '
0 0asd9 0 016022 3304 )
3304 7
% 0179 1075 5 1075 5 0 0000 21873 21473 32 8 '
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40 0 0 12163 0 016019 2445 8 2445 8 8 027 l071 0 1079 0 00I62 21432 2 1594 48 0
~
42 0 0 13143 0 016019 22224 2272 4 10 035 0698
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,0676
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.us 4LWp n a aw my M le t 0 22183 0 0i6028 1383 6 13836 24 059 1061 9 1086 0 0 0478 2 0593 2 1070 na He 023643 001M31 1292 2 1292 2 26 060 1060 8 1066 9 0 0516 2 0491 2 1008 Ses le 8 0 25611 0 016033 12076 1207 6 28 060 1059 7 l087 7 0 0555 2 0391 2 0946 60 0 82 8 0 27494 0 016036 1829 2 1129 2 30 059 1058 5
'088 6 0 0593 2 0291 2 0885 62 0 84 0 0 29497 0 016039 1056 5 10 % 5 32 0$8 10574
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- I 68 0 0.33889 0 016046 926 5 916 5 36 054 10552. 091 2 0 0708 1 99 % 2 0704 60 0 r
70 0 0 36292 0 016050 868 3 468 4 38 052 1954 0 1092 1 0 0745 9900 2 0645 7e a 72 8 038u4 0 016054 814 3 814 3 40 019 1052 9 l093 0 0 0783 9834 2 0587 72 0 74 0 04!5%
0 016058 FM I 764 1 41 046 10S1 8 093 8 0 0021 9708 2 0;29 14 8 75 0 0 444?0 0 016063 717 4 717 4 44 043 10507 :1094 7 0 00S8 9614 2 0472 70 0 is t 0 47461 0 016067 673 8 673 9 46 040 1049 5,;095 6 0 0895, 9520 2 0415 18 0 80 0 0 50683 0 016072 633 3 633 3 48 031 1048 4 1096 4 0 0932 9426 2 0959 80 8 s28 0 54093 0 016077 S*55 595 5 50 033 10473
- 097 3 0 0969 9334 2 0303 82 8 84 0 0 57702 0 016082 560 3 560 3 52 029 04 6 l
.098 2 0 1006 9242 2 0248 34 0 ta l 0 61518 0 016087 227 5 5275
$4 026 045 0 : 099 0 01043
.9151 2 0193 Os s 08 0 0 65551 0 016093 496 8 4*i e 56 012
!043 9 1099 9 0 1079 1 9060 2 0139 et 0 98 9 0 69813 0 016099 468 1 468 1
$8 0:6 1042 7
'100 8 0 1115 89?0 2 0086 seI 92 8 0 74 ):3 0 016105 441 3 441 3 60 014 1041 6 101 6 0
152 8881 20c33 tt s to 0 0 79 % 7 0 016111 416 3 416 3 62 0:0 1040 $
102 5 0
108 SM? I 9980 to 8 MG 0 84072 00:fl67 392 8 392 9 64 006 1039 3 10'3 0
224 8704 1 9928 98 8 Se t 0 89356 0 016123 3709 3709 H OC3 1038 2 1304 2
- 0. 260. 8617 1 9876 Mt
. ~... - _ _.
190 8 0 98924 0 016130 350 4 350 4 67949 1037 I 1105 I O 1295 18530 l 9825 tes 8 187 0 100 7f 9 0066:37 333 3 331 1 69*95 1035 9
.105 9 01331
.8444
.9775 192 8 144 5 i Ot 9%
0 016144 313 1 313 1 71 992 10M 8 106 8 0 1366
.8358 9725 184 0 1H I 3 134' 0 016151 296 16 2% B8 73 99 1033 6
.107 6 0 1402 8273 94 75 las t 180 8 I2030 00161$8 28028 280 30 71 98 1032 6 ;108 5 01437 1 8188 ; M26 108.8 til t i2750 0 016165 26537 26539 77 98 031 4 l109 3 0.472 8105
.9577 lig t 112 0
,3505 0 0161'3 25137 251 30 76 96 030 2 1 02 0
50 7 8021
.9 20 112 0 114 9
,4299 0 016180 238 21 238 22 81 97 029 I I I0 0
S42 1918 9480 114 8 816 8 5133 0 016188 225 84 225 85 83 97 027 9
!! 19 0 l577 70 %
9433 lit t lis t 6909 0 016196 214 20 214 21 85 17 026 8
,122 0 611 ; 7774. 9346 118 8 4W.u E"'"MIWM?
171 4 5 6927 0 016204 203 25 203 26 0797 10256 l i13 6 01646 I7693 19D9 110 0
~~
122 0 I ?891 0 016213 l92 94 192 95 09 %
1024 5 l,14 4 01680 17613 i l293 122 8 124 8 1 8901 0 016721 83 23 18324 91 96 1023 3 174 4 1 99S9 0 016229 3408 174 09 93 %
1022 2 15 3 01716 M33
.9247 124 0 178 8 2 !068 0 016238 6545 16547 95 96 1021 0
,17.0 0 1783. 7374 9157 12s s 16 8 03749 7453 9202 178 0 134 4 2 2230 0 016247 5732 15733 9796 1019 8 1117 8 01817 1 7295 9112 130 8 132 B 2 J44S 0 0162*6 49 64 149 %
99 95 l018 7 l110 6 0 1851 1 7217 9068 132 8 Hof 2 4717 0 01626%
4240 14241 101 95
'017 5 lit h 01884 1 7140 9024 134 0 135 0 2 6047 0 016274 35 55 135 57 103 95
.016 4
- 20 3 C1918 1 706]
8980 lat e 130 0 2 7438 0 016284 ;29 09 129 !!
10S 95 LC15 2 121 1 01951 16986 8937 13e 0 1at t 2 8892 0 016?97
- 2298 23 00 l07 95
- 014 0 1220 01985 l69:0 0895 las t 187 8 3 0411 0 0163C3 1721 1722 09 %
012 9 122 8 0 2018 16$)4 8852 182 9
..**i
- h..
184 4 3 1997 0 016)12 18 74 11 76 Ill5 011 7 123 6 0 7051 6759 8810 lat e z
las t 2 3653 0 016121
.l06 S8
,06 59 13 95
. 010 5 124 5 020n4 Mas
.8769 144 0 944 0 3 5J41 0 016332 10168 101 10 15 95 1009 3 !!25 3 0J117. M10 14727 140 0 190 4 37184 0016343 9705 9707
.17 95 1008 2
'126 1 0 2150
'6536 1 8686 190 0 Init 3 9U55 0 016M3 92 66 9268 19 %
5007 0 I?69 0 2183 6447 M46 fir e 1W 4 410M 0 016163 8850 ell?
FI M 1005 8 177 7 07216 6390 M06 194 0 154 0 4 3068 00161?4 84 %
44 57 23 95 1004 6
.128 6 02248 6318 8%6 tie s
==e>
864 8 4 5157 0 016384 80 42 80 83
,25 96 100J 4 il29 4 0 2283, 6245 14526 190 4 tes t 4 7414 0 016395 7727 7729 12796 1002 2
'll30 2 02313
- 6174 18487 198 4 14J 8 4 9722 0 016404 73 90 7392 IM 96 1001 0 1111 0 02MS 6103 1 8440 862 4 led 9 5 2124 0 016417 70 70 70 12 131 96 999 8 131 8 02377 M32 4 3409 tad I tes t 5 4673 0 016420 4767 6764 13397 990 6 132 6 0 2409 5961 1 8371 let e iH B S 7123 0 016440 64 18 64 00 13$ t7 9974 ll33 4 02441 5812 33333 186 0 199 9 1 9926 0 016454 6204 62 06 13797 996 2 1134 2 02473 15822 18295 170 0 172 8 6 2736 0 016443 6943 6945 lH 98 9M 0 1835 0 Onc$
l5753
.8258 1724 lis t 6 S6%
0 0lH14 56 9
$6 97 141 98 993 8 IIM 8 0 2537
' %84 8221 IMe 175 0 6 8640 00lus6 54 St 54 61 14399 992 6 lu66 02%8 5616 :.8184 1788 178 8
? ! 840 00lH98 52 JS 52 36 14S 99 991 4 !!17 4 0 1600 14S48 l 8147 178 0
% v m sw n 4v.a.
N y.% **B'.;> %,
e, 4 -
c.,,;ptW.,
C,- d t ' 1D **"S*Ci'Mi " H s*" 9O*
IO*b
~
~
co Tab 41. Saturated Steaml Temperature Table-Continued ads Press Specitec tolume EntPalpy (ntropy Temp to pe,
$at sat
$at
$at sat
$al fem 0 Iahr
$q in bquid Ivap Vapor b4Wid Iv80 Vapor b0uid Iv80 Vapor Iabr 8
0 V,
veg og h,
h eg h
5, seg sg i
g IN 8 75110 0 014510
$02)
$022 48 00 990 2 138 2 0 2631 Sato 8111 181 0 182 0 7 850 0 014S?? 44 172 18 109 50 01 989 0 131 0 0 2662 S413 8075 182 8 les t
$ 203 0 016534 46 232 46 249 S2 01 9976 139 8 0 2694 5346 8040 1MO tes 8 8 %8 0 016647 44 383 44 400
- lS4 02 986 S 140 5 0 2725 5279
.8004 tes 8 tes B 8 947 4 016559 42 621 42 638 156 03 985 3 141 3 027%
.5213 1 7969 Iat 8 190 8 9 340 0 016572 40 941 40 957 154 04 9841 l142 8 0 2787 1 6148 1 7934 198 8 192 8 9 742 0 016S85 39 337 39 3$4 160 05 982 8
,142 9 02818 5082 1 7900 192 0 IM8 10 168 0 016 % 8 37838 37 824 162 05 981 6 143 7 02848 5017 17865 the its t 10 605 0 016611 36 348 36 364 164 06 980 4 144 4 02879 4952 1 7831 19s Its 8 II 0$8 0 01 % 24 34 954 34 970 166 08 979 I
.145 2 61910
,4888 1 7798 19e B 2 ell 11 526 0 0.6637 33 622 33635 168 09 9779 186 0 0 2940 1 4474
.7764 telt Isa t 12 512 0 01 % 64 31 13S 31151 172 11 9754
.1475 0 3001 1 4697
.7698 tes t 2e8 8 13568 0 016f 91 28 862 28 8?8 17614 972 8
,1490 0 3061 1 4571 7632 228 8 fir e 14 69s 0 016719 26 78?
26 799 18017 970 3 l!50 5 0 3121 1 4447 7568 212 8 mmw=34lte@8tg 216 8 M 903 0 016747 24 878 24894 18420 967 8 1152 0 0 3183 1 4323 7505 216 8
~ yN * '
221 8 17184 0 016775 23 121 23 148 18823 965 2 1153 4 0 3241 14201
.7442 278 0 224 8 18 % 6 0 016805 2n $29 21 $45 19227 962 4 1154 9 03300 140al
.7380 224 0
!?I t 20 015 0 016834 20 0 %
20 073 196 31 960 0 1156 3 0 3359 I 3961 7320 228 8 222 8 21M7 0 016864 18 701 18 718 200 35 9574 IIS7 6 0 3417 1 3842 7260 232 8
);,
238 8 23 216 0 016895 17454 17471 20440 954 8 1159 2 0 3476 IJ725 7201 236 0
" 9 r.'
340 8 24 968 0 016926 15 304 16 321 K345 952 1 160 6 0 3533 13609 1 7142 248 0 344 8 26 826 0 016958 IS 243 IS 260 21250 949 5 162 0 0 JS91 1 3494 1 7085 244 8 248 8 28 796 0 016990 14 264 14 281 216 56 946 8 163 4 0 3649 1 3379 1 7028 248 0 212 0 30 843 0 017022 13 3$8 13 375 220 62 944 1 164 7 03706 1 3266 16972 212 8 2HI 33 051 0 017055 12 520 12538 22469 941 4
.lM I 0 3763 1.3154 1 6917 2M B 254 I 35 427 0 017089 11 745 11 762 22876 938 6 ::1874 03819 13043 16862 fla t 2W I 37 854 0 017123 11 025 11 042 23283 935 9
.168 7 0 38'6 12933 16808 264 8 268 0 40 500 0 017167 10 358 10 375 236 91 933 1
- 170 0 0 3932 12823 1 47 %
268 8 212 8 43249 0 017193 9 738 97M 240 99 930 3
.371 3 0 3987 12715 1 6702 272 8 278 8 46 147 0 017228 9 162 9 140 24508 927 5
,172 5 0 4043 12607 16650 278 0 298 9 49 200 0 017?64 8627 8 644 24917 924 4
- 173 8 0 4098 2501 GM9
!se 8 2HI S2 414 0 01730 81283 8 1453 2$3 3 923 7
.l ?$ 0 0 4154 2395 6548 264 8 ffl 4 55 795 0 01734 7 6634 76807 2574 lit t
.176 2 0 4?08
- 2290 6498 288 5 292 0
$9 M0 0 01738 723C1 7247S 2615 915 9
.}77 4 04263 2186 6449 192 8 fu 4 63 084 0 01741
- 6 4259 6 4433 26S 6 9130
,178 6 04317. 2082 6400 294 8 See t 67005 0 01745 6 4483 6 at$8 269 7 910 0
' 79 7 0 4372 : 19'9 6351 30s 8
~~
$t4 8 Fi l19 O E 749 6 09S5 61133 273 8 907 0 80 9 0 44?6 1877 6303 364 0 388 9 75 433 0 01753 5 7655 5 7830 278 0 9040
. 82 0 044'9
.1776
.6256 Mee 04S33
.3676 6209 812 0 sit e 19 953 0 01757 54%6 54742 282 1 901 0
,'I31 184 1 04586 1 1576
.,6162 318 8 318 0 84 688 0 01761 5 1673 51449 246 3 897 9 Stel 89 643 0 01766 4 8961 4 9138 290 4 IMO
,185 2 0 4640
- 1477
(!!6
!?t t 824 0 94 826 0 01770 4 6414 4 6595 294 6 8916 186 2 0 4692 1378 4071 324 8 i
321 0 100 245 0 01774 4 4030 4 4208 298 7 8845 187 2 0 4745
,1280 6025 328 8 4
332 0 105 907 0 01779 4 1784 4 1964 302 9 84S 3
.188 2 0 4798 3183 5981 332 8 338 8 111 820 0 01783 3 968 3 9859 307 1 882 1 1891 04850 11086
.5936 334 8 28I 117 992 001787 3 7699 3 7878 311 3 878 8 :190 1 04902 l 0990
- S492 348 8 240 124 430 0 01792 3 $434 3 6013 315 $
875 5
.191 0 04954
.0894 l 5849 344 8
.4bdM.7 LW 288 131143 0 01797 3 4078 342S8 319 7 872 2 191 1 0 6006
.0799 5806 288 352 8 138 138 0 01801 32423 3 7603 323 9 868 9 192 7 0 $0S8
,0705 5763 Ill e ass a 145 424 0 91806 30863 31044 328 1 865 5
,193 6 05110
,0611
.5721 354 8 360 0 153 010 0 01811 2 9392 1 9573 332 3 862 1
.194 4 0 5161 10Sl? 1 5678 3s8 e 3H e 160 903 0 01816 2 8302 2 8184
!s65 858 6
.195 2 0 5212 1 0424
$637 364 3 364 9 169 111 0 01821 2 6691 2 6873 340 I 8%!
.195 9 0 $263 10332
. M95 368 8 372 8 177644 0 01826 2 54SI 2 6633 345 0 851 6
.1% 7 0 5314 1 0240 5%4 372 0 375 0 186 517 0 91831 2 4279 2 4462 349 3 448 1
.1974 0 536S 1 0148
- S513 378 0 395 0 195 729 0 01834 23170 1 3353 3'36 644 5 198 0 0 5416 1 6057 l 5473 300 8 M48 20$ 294 0 01842 2 2120 2 2304 3579 840 0
.198 7 0 5466 0 9906 i S432 344 0 384 8 215 220 0 01847 2 1124 2 1311 362 2 437 2 199 3 O H16 0 98'6 15392 388 9
..J M20 225 516 0 01853 2 0184 2 0369 366 %
8334 1199 9 O n67 0 9786 u S352 392 8 396 8 236 193 0 01858 1 *291 1 9477 370 8 829 7 1200 4 0 %)7 0 96 % 1 5313 3ts t fi,(*]["
488 0 247 259 0 01864 8444 86 30 375 1 825 9 1201 0 0 5667 09607 5274 Set e
_7 404 0 258 ??S 0 01870
, 7640
.7827 379 4 822 0 1701 5 0 5717 0 9518
. 5234 404 0 400 0 270 600 0 01875 6877 7064 383 8 818 2 1201 9 0 57 % 0 9429
, $195 eas t 412 8 282 894 0 01881
.6152
. 6342 3881 814 2 1202 4 0 5816 09341
, S157 412 8 418 8 296 617 0 01887
. 5463 i MSI 392 5 810 2 1202 8 0 Sen 09253 iSal8 eis e 470 0 304 780 0 01894 8 4808 I4997 396 9 806 2 703 1 0 591S 0 9165 S080 428 8 424 0 327 391 0 01900 1 4184 I 4374 401 3 002 2 203 $
0 $904 0 9077
$042 474 0 428 8 336 463 0 01906 1 3591 1 3782 405 7 798 0 203 7 0 6014 01990
$004 428 0 432 8 351 00 001913 1302M 1 32179 410 1 793 9 204 0 0 6063 0 8903 49u 432 s 438 0 3H 03 0 01919 124887 3 2u06 414 6 789 7 i2042
, 0 6112 0 8816 1 4928 438 8 444 0 381 S4 0 01926
,19761 1 21687 419 0 7854 1264 4 0 6161 0 8729 4490 ode a 444 0 39754 0 01933 i l4874
,16406 4235 781 1 1204 6 0 6210 0 8643 44 9 444 e 448 0 414 09 0 01940 l 10212
,12 52 428 0 776 7 1204 7 0 6269 08%7
.4815 448 0 462 0 43114 0 01947 l 05764 07718 432 $
772 3 1204 8 0 6308 0 s471
,4778 452 s 488 4 444 73 0 01954 1 01518 193472 4370 7674 1204 8 0 63 % 08385
.4781 4M 8 4
.f.n
...~7.."~
~ '
- . v ':* ;,. q.
.2.
.. m.;
(
.C, L.'Ote.-
- rh u..
5 gy.h
.e j.2..
- g w...y c.
3 4
I E
Table 1. Saturated Steam: Tomswature Table-Contin 4 red A0s Press Specific volume Entnaipy
[ntropy Temp Lb pee
$4t Sat
$41 Sat St
$at lemo Fant 50en Lieu.d Evan Vapor LHluid leap Vapor t%ivio Evap Vapor Fahr i
p t,
oft
't he h og he S,
Sa f
400 0 4M 87 0 01 % 1 0 97463 0 99424 441 5 763 2
- ?04 8 0 6405 0 8299 1 4704 400 s 404 0 445 %
0 01969 0 93588 0 95557 446 1 758 6 1204 7 0 W54 0 8211 I4M7 op 8 404 0 504 83 0 01976 0 89885 0 91862 450 7 754 0 204 6 0 6502 0 8
1 4629 454 8 472 0 524 67 0 01984 0 86345 0 88329 4552 749 3
.204 5 IL6551 0:042 1 4592 472 8 475 4 545 II 0 01992 0 82958 0 84950 459 9 744 5
,204 3 0 6599 0 79 % 14555 478 0 400 0 SM 15 0 02000 0 79716 0 81717 464 5 739 6 12041 0 M48 07871 4518 400 0 end e 587 81 0 12009 0 7%Il 0 78622 469 1 734 7 1203 8 0 66 % 0 7785 44 ts 4e4 8 408 0 610 10 002017 0 7 %41 07%54 473 8 729 7 1203 5 0 6745 0 7700 4444 4s80 402 8 633 03 0 020/6 0 70794 0 72820 478 5 724 6 1203 1 0 6793 0 7614 4407 492 8 406 8 6M 61 0 02034 0 68065 0 70100 483 2 719 5 1202 7 0 6842 07528
.4370 4te t 300 0 680 86 002043 0 65444 0 67492 487 9 714 3 1202 2 06893 07443 4333 500 0 SM S 705 78 0 02053 0 62938 0 64991 492 7 709 0 1201 7 0 69 % 0 7357 4296 nu s 800 0 731 40 0 02062 0 60530 0 62592 4975 703 7 1701 1 0 6987 0 7271 4258 tes e 512 0 757 72 0 02072 0 58210 0 60289 502 3 6982 1200 5 0 7036 0 7185 4221 lit t 518 0 784 76 0 02081 0 55997 0 58079 5071 692 7 11918 0 7045 0 7099
.4183 816 0 M assimCOs j 520 8 812 53 0 02091 0 53864 0 559 %
$12 0 687 0 ' 199 0 0 7131 0 7013
.4146 120 0 124 0 841 04 0 02102 0 51814 0 53916 516 9 681 3 198 2 0 7182 06926 4108 524 0 usa..e v e. %4 528 0 870 31 0 02112 049843 0 51955 521 8 675 5 197 3 0 7231 06839 l 4070 520 8 632 8 900 34 0 02123 047947 0 50070 526 4 M96 1%4 0 7280 06752 t 4032 832 s
$35 0 931 17 0 02134 0 46123 0 48257 531 7 M36
.195 4 0 7329 06M5 13993 las t 640 9 962 79 0 02146 0 44367 0 46513 536 8 657 5 11943 0 7378 0 6577
.3954 let 0 544 0 995 22 0 02157 042677 0 44834 5418 651 3 L1931 0 7427 0 6409 3915 kat
,f,.
900 102849 0 02169 0 41048 0 41217 546 9 645 0 191 9 0 7476 0 6400
.3476 pts 552 0 1062 59 0 02182 0 39479 0 41 % 0 552 0 634 5 190 6 0 ?$25 0 6311
.3837 lif e H64 1097 55 0 02194 0 379 % 0 40100 5572 632 0
.189 2 0 7575 0 6222 1.3797 666 a 568 0 133 38 0 02207 0 36507 0 38714 M24 625 3 !!87 7 0 7625 0 6132 1 3757 048 0 564 0 17010 0 02221 0 35099 0 37320 M76 618 5 1186 1 0 7674 0 6041 1 3716 tes t M80 207 72 0 02235 0 33741 0 35975 572 9 till 1144 5 0 7725 0 5950 1 3675 068 0 572 0 l246 26 0 0:249 0 3?429 0 34670 578 3 604 5 1182 7 0 7775 05a59 1 3634 572 0 176 0 1285 74 0 02264 0 31162 0 33426 583 7 5972 1180 9 0 7825 0 57 % 1 3592 576 8 500 0 l32617 0 02279 0 29937 0 32216 589 1 589 9 1179 0 0 7876 0 5673 1 3550 540 8 Het
.3677 0 02295 028753 0 31048 5946 582 4 it ?6 9 0 7927 0 5583 l 3507 544 8 M89 4100 0 02311 0 27608 0 299:9 600 1 574 7 174 8 0 7978 0 5485 l 3464 Het
$til
.453 3 0 02320 0 26499 0 28827 605 7
%60
.l?? 6 0 8030 05M0
- 3420 H2O Het 64978 0 02345 025425 0 27770 611 4 558 4 l170 2 0 8082 0 5233
. 3375 906 8 698 8 543 2 0 02364 0 24384 0 26747 '
617 1 550 6 1167 7 0 8134 0 5196 1 3330 000 0 tes t
.5897 0 02382 0 3374 0 25757 622 9 542 2 1165 1 0 8107 050e 7 1 3284 eed e 608 9 637 3 00242 0 22394 0 247 %
628 8 533 6 1162 4 0 8240 0 49e 7 1 3230 tes t lif e
.666 1 0 02422 0 21442 0 23865 634 8 524 7 1159 5 0 8294 0 40 % 1 3190 812 0 sie s
,735 9 0 02444 0 20516 022960 640 8 515 6 !!%4 0 8348 0 4794 1.3141 814 0 678 0 1786 9 0 024 % Ol%M 0 22081 646 9 506 3 1153 2 0 8403 0 4689 1 3092 820 0 824 0 18390 0 024f t 0 18737 0 21226 653 1 496 6 1849 4 0 8458 04583 1 3041 824 0 674 8 1992 4 0 02514 0 17840 0 20394 659 5 4857 1146 1 0 8514 0 4474 1 2988 878 8 632 8 IW70 0 02539 0 17044 0 19583 H59 4764 1142 2 0 8571 0 4364 3 2934 832 0 638 0 2002 8 0 02566 0 16226 0 18792 672 4 465 7 1138 1 0 3628 0 4251 1.2479 834 5 640 0 2059 9 0 02!95 015427 0 18021 679 1 454 6 133 7 O SF06 0 4134 1 2921 848 8 844 0 2118 3 0 02625 0 14644 0 17269 6459 4431
!?t o 0 8746 040t$ 1 2761 tes t 848 8 2178 1 0 0?657 013876 0 16534 692 9 4313 124 0 0 8836 0 3893 1 2699 kal 837 8 2239 2 0 02691 0 13124 0 15816 700 0 410 7 03767 1 2634 es70
~ "
Die 2301 7 0 02728 0 12387 0 15115 7074 405 7 13637 12567 tes t I
Met 23657 0 02768 0 11643 0 14431 714 9 M21 1107 0 0 8995 0 3502 l 2498 Oss e 664 8
~4311 0 02811 0 10947 0 13757 722 9 3717
.100 6 0 9064 0 3361
,2425 Op 6 eas t 2498 1 0 02858 0 10229 0 13087 731 5 362 1 093 5 0 9137 0 3210 i 2347 est e 07:0 2556 6 0 02911 0 09514 0 12424 740 2 3457
,085 9 09:12 0J054 122M 872 0 l'il 26M 8 0 02970 0 04799 0 11769 749 2 328 5 (077 6 09287 02892 1 2119 Sit e 900 8 2708 6 0 03037 0 08080 0 11117 758 5 310 1 1064 5 OlH5 0 2720 2006 800 0 644 8 27821 00ble 0 07349 0 10463 768 2 290 2 1058 4 O W47 02537 1984 844 0 set t 28574 0 03204 0 06595 0 09799 778 0 2682 1047 0 0 9535 02337 1872 500 0 lef t 2934 5 0 03313 0 05797 0 09110 790 5 243 3 1033 6 0 9634 02110 1744 802 0 let t 3013 4 0 03455 0 04916 0 08371 004 4 212 8 1017 2 0 9749 01841
,1591 90s t
..~
700 0 30943 00M62 0 03857 0 07519 822 4 172 7 995 2 0 9901 0 1490 1 1390 700 0 702 0 3135 5 0 03824 00J173 0 06997 835 0 144 7 979 7
.0006 03746 1 1252 702 0 teo s 31772 0 0410s 9 02192 0 06300 454 2 102 0 9%2 0169 0 0876 1 1046 7e4 0 796 8 3198 3 0 04427 00 304 0 05730 873 0 614 9344
.0329 0 0527 1 08 %
791 0 700 47' 3208 2 0.05078 0 00000 0 05078 906 0 0.0 906 0 l 0612 0 0000 1 0612 7e5 47'
=
'Crilgal temperature
~
E
.2 s.
4.+,Q.. g,1.'7. '.'...,
. - D*,
L, MW,'8-y
- -7,2.
,*.p.... ;..
.,, w.g-s g.f,,
.g
,4,,..i ;b;
3 Table 2: Satu?sted Steam: Pressu?e Table C
Abs Press.
Temp
$at.
$at
$at
$st
$at Sat.
Abs Press 2/10 in.
fa7tr Ligw0 leap Vapor bowd Ev8p Vapor liquio
[vap Vapor 2/Sq in p
t og v,g v
he h,g h
8, 8,g 8
p g
g g
8 00063 32 018 0 016022 3302 4 33024 0 0003 l075 5 075 5 0 0000 21872 21872 8 elan 9 25 59 373 0 016032 12355 1235 5 27382 060 1 0074 0 0542 2 0425 2 0967 8 25 GH 79 586 0 016071 641 5 641 5 47623 0486 0% 3 0 0925 944 %
2 0370 SH 18 101 34 0 0161 %
33359 333 60 6973 036 1 05 8 0 1326 8455 9781 10 SS 162 24 0 016407 73 515
?3 532 30 20 000 9 31 1 0 2349 6094 8443 le
=
18 8 19321 0 016592 38 404 8420 6126 9a21 50 5 0 3121 4447 7%8 14 40s 43 3 0 28 %
5043 7879 1s t id eel 212 00 0 016719 26 782 6 799 80 37 970 3 13.8 213 03 0 016726 26274 "5 290 8121 969 7 50 9 0 3137 1 4415 1 7552 ta s 26 8 227 %
0 016434 20 070 20 087 19627 960 I
.156 3 0 3358 13 % 2 1 7320 28 8 34 8 25034 0 017009 13 72 % 13 7436 218 9 945 2 164 1 0 3642
'3311 L 69%
34 e se t 26725 0 017151 10 4794 104%5 236 1 933 6 169 8 0 3921 2844 6765 48 0 Be t 281 02 0 017274 44967 4 5;40 250 2 923 9
.374 1 0 4112 2474 6584 Se e 64 8 292 2r 0 017383 71%2 7 1736 2(e 2 915 4 1776 0 4273 2167 6440 et t
.ma,Q.
te 8 302 93 0 017402 6 1875 6 2050 272 7 9078 180 6 0 4411 1905
- 6316 1s t pgsLet44148 80 8 312 04 0 017573 5 45 %
54711 282 1 9u0 9 183 1 0 4534 11675 16208 Os t 18 8 32028 0 037659 4 8779 44953 290 7 894 6 185 3 0 4643 1 1470 1 6113 se t les e 327 82 0 017740 4 4133 4 4310 298 5 sSS 6 1187 2 0 4743 1 1284 1 6027 fee 8 110 8 334 79 0 01782 4 0306 4 0484 305 8 8831
- 188 9 04834 1 1115 1 59 %
118 5 128 8 34127 0 01789 3 7097 3 7275 3 26 8778
.190 4 0 4919 1 0960 1 5879 129 6
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4 Section.6 - Plant Systems Design, Control, and Instrumentation f6.1 List five (5) conditions that would initiate a Main Feed Pump Trip.
(1.0) 7.2. Match.the most appropriate plant / load limit corresponding 6
s to.the plant condition.
(answers can be used more than once)
Plant Conditions 1.
1 condensate and 1 feedwater pump in service.
(0.2).
J 2.-
I heater drain, 2 feedwater pumps, 2 condensate pumps in service.
(0.2) l 1
3.
3 adjacent low pressure heaters removed from service, high pressure heaters remain in service.
(0.2) 4.
1 feedwater pump and 2 condensate pumps operating.
(0.2) 5.
Swapping running feedwater pump with the second (0.2) feedwater pump.
Plant / Load Limit a.
Turbine load must be reduced by 20%
b.
100% power c.
62% - 65% power d.
200 MW e.
< 100% power 6.3 The reactor is in hot shutdown and primary pressure is 1850 psig.
You are the SRO.
Mr. Goodwrench (I&C) wishes to conduct maintenance on the turbine first stage pressure j
instrument. Would you authorize him to do the maintenance?
Defend your answer.
(2.0) l 6.4 Unit 1 is at 10% power, operators are switching from the feedwater bypass valves to the main feed regulation valve, The S/Gs are overfed momentarily and RCS average temperature s'
"* drops.
The reactor operator now withdraws control rods in response to the temperature decrease in the primary.
Describe the plant response due to the RO withdrawing the rods to raise i
RCS temperature.
(1.25) 4 i
s l
6.5 Prairie Island, Unit 1, is operating at 68% power and a reactor trip and..i.., 'rj::ti;a occurs from the loss of instrument bus IV.
Explain how this reactor trip could occur.
(1.25) 6.6 Recently a Midwest Westinghouse plant experienced a reactor trip from 100% power.
Shortly before the reactor trip, the plant experienced a 110 MW spike in the electric load.
Reactor power remained constant during the spike.
Rods and turbine were in manual.
The condition that led to the reactor trip began with air entering the condensate system from the standby condensate pump.
a.
Explain how Prairie Island could experience a reactor /
turbine trip with the same conditions (include automatic trip setpoints and coincidcnces).
(1.25) b.
Explain how Prairie Island would possibly experience the load increase on the turbine before the trip.
(1.25) 6.7 Place the following in the order of largest to smallest r
current draw on the pump motor.
(1.0) a.
Operating one RCP in hot shutdown.
b.
Operating two RCPs at power.
c.
Operating one RCP in cold shutdown.
d.
Starting one RCP in hot shutdown.
6.8 According to Prairie Island Technical Specifications, the
{
Power Range Nuclear Instrumentation is only required in power operations.
In spite of this fact, no more than one channel can ever be removed from service during shutdown modes.
Explain why.
(1.75) 6.9 a.
What plant parameters would you use to indicate that the turbine is " Latched"? List three indications.
(1.25) b.
What supplies the operating oil to the turbine governor during startup to " latch" the turbine?
(1.25) 6.10 The RCP must be stopped when the upper or lower bearing water temperature has increased to 185*F, the high
,, temperature alarm. True/ False (0.5) 6.11 Prairie Island procedure precaution on the normal operation of Pressurizer Relief Tanks states, "Do not allow the pressure in the PRT to exceed 6 psig during normal operation." The alarm is set at 8 psig and the PRT is designed for 100#. What is the basis for maintaining pressure in the PRT below 6 psig t
during normal operation?
(1.5) i i
i 2
i r,, _. _ _ _ _. _ _,. _ _ _- _.. _ _ _. _
6.12 a.
What signals are required to enter the emergency makeup 4
mode of operation for the Volume Coatrol Tank during normal power operations and describe what action takes place once these signals are received?
(1.0) b.
When the Volume Control Tank reaches its normal level, all valves will automatically revert to the normal mode of operation.
True/ False (0.5) 6.13 What automatic start signal (s) for the motor driven auxiliary feedwater puap is/are lost when the control room manual selector switch is positioned from auto to shutdown auto position?
(2.0)
'6.14 How would rod motion be affected for an " Urgent Failure" alarm in the:
a.
Logic cabinet (0.75) b.
Power cabinet (0.75) 6.15 On the output of the main generator, two potential trans-formers exist per 'hase.
Explain the affect on the main p
generator power operation if-.
I Regulating potential trar sformer (voltage regulator) a.
is inadvertently racked out.
(0.25) b.
Metering potential transformer (phase relay) is inadvertently racked out.
(0.25) 6.16 Describe the difference on the Main,feedwater system, on a Safety Injection and a Reactor Trip with low T,y,.
(1.25) 6.17 The design spring of the relief valve located on the RHR l
suction piping from the lodp hot leg is based on the g
maximum water generated due to expansions as a result of
'u',
'51 loss of decay heat removal capability while operating the RCS in a solid water condition.
True/ False (0.75)
Explain and defend your answer.
6.18 List in the proper order, starting from a stationary position, an out motion sequence for a full-length control rod drive mechanism.
(i.e., 1, 2, 3, and etc.)
(0.75)
"* a.
Energize Lift Coil w
b.
De-energize Movable Gripper s '
s s
N g
3 e
v
=
c.
Energize Stationary Gripper d.
De energize Lift Coil j
e.
Stationary Gripper is energized f.
Energize Movable Gripper g.
. De-energize Stationary Gripper 6.19 Explain the operational differences between Train A and Train B of the auxiliary building special ventilation system when stopping both trains.
(0.5)
I a
4
- )
6 4
(
4 m.
Section 7 - Procedures, Normal, Abnormal, Emergency and Radiological Control 7.1 In the Steam Generator Tube Rupture procedure (IE-3) step 3 notes that feed flow should be maintained to the ruptured S/G and its wide range level be maintained between 60% and 75%.
Explain the basis for this step.
(2.0) 7.2 Prairie Island procedure on dampening Delta I oscillations on a large axial xenon transient is to react to the Delta I swing with rod movement.
(1.25)
Plot on Part B the general trace you would expect on the C panel strip recorder when rods are moved by procedure to dampen the Delta I oscillations.
(See Figure 7.2) 7.3 In the loss of reactor / secondary coolant procedure, it states "within 30 minutes cf SI actuation Stop All Turbine Building Roof Exhausters." What is the basis for this step?
(1.25) 7.4 What are the immediate manual actions for the " lost of one train of DC" per procedure C20.9?
(1.25)
- 7. 5 In the SI termination procedure (IES-0.2) step 3 states
" Reestablish Instrument Air to Containment."
In the following systems, list the valves which were affected (either failed open/ failed closed) by the loss of instru-ment air to components inside reactor containment.
a.
Reactor coolant system (list 3 valves)
(1.25) r b.
CVC System (list 5 valves)
(1.25) 7.6 List the immediate actions upon receiving an "Over Pressure Protection System Improper" alarm per Prairie Island re-sponse instructions.
(1.0) 7.7 In the Unit Shutdown Procedure, a precaution states, "when the S/G power-operated relief valves are being
-used for cooldown, the operator should stop the flow thru valves for a period of 5 minutes at every 25*
temperature interval.
Explain the basis of step.
(1.25)
In Prairie Isla~d Power Operations procedure C1.4, a
. 7. 8 n
precaution states, "at steady state or changing load
- bove 90%, the control should be in Auto, Imp out."
a What is the basis for this precaution?
(1.25) t
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7.9 What are your specific responsibilities as a SRO upon the loss of the computer alarm system?
(1.5) 7.10 The control room had to be evacuated due to heavy smoke from an electrical fire behind a panel in Unit 2.
Unit 1 is at 100% power and Unit 2 is at 92% power.
a.
Which unit shift supervisor will make the decision to evacuate the control room?
(0.75) b.
Where do the respective shift supervisors proceed upon leaving the control room and what are their duties now?
(1.0) c.
If Unit I was tripped and Unit 2 has not been tripped when control room was evacuated, what could you do as SS of Unit 2 to trip the reactor?
(1.0) 7.11 Match the following plant limit / loads corresponding to the failed valve (s).
Unit 1 is at 100% power and the following valves fail to the indicated position without operator action:
(answers may be used more than once) 1.
a single reheat stop close.
(0.25) 2.
2 reheat stop valves close that feed one of the 2 LP turbines.
(0.25) 3.
2 intercept valves close on the same side of the turbine.
(0.25) 4.
2 intercept valves close feeding one of the two LP turbines.
(0.25) 5.
1 control valve opens all the way.
(0.25)
Load / Plant Limits a.
Trip the turbine b.
Initiate unloading the turbine to 50% load
-.c.
Unload turbine to 25% icad d.
Maintain turbine load e.
Place controller in manual and change valve position to the desired location 2
t
n 7.12 When frisking yourself, when are you considered contaminated?
Provide the frisker reading if background reading is 125 CPM.
(0.75) j 7.13 Equipment used in a controlled area may be unconditionally released to the clean area if it has a white tag affixed to it.
True/ False.
Defend your answer.
(1.0) 7.14 Frisking should be used if an individual suspects bodily contamination.
Provide the correct order for using the frisker when exiting a controlled area.
(1.25) a.
Remove the glove liner inside out and place in clothing cart.
b.
Slowly move both hands close to frisking probe and check hands not contaminated.
c.
Frisk the exposed areas of the body and areas which rubbed against surfaces.
d.
Remove both booties and place in clothing cart.
e.
Frisk the dosimeter and TLD.
7.15 Prairie Island has v,ery high radiation areas that are extremely dangerous.
List 4 of the 5 areas of very high radiation.
(2.0)
't.16 Generally outline the immediate actions of a shift supervisor upon notification of serious injuries or casualties to plant personnel.
(1.5)
(
7.17 List the duties / responsibilities per F-5 (Fire Fighting) of each unit shift supervisors upon notification of a major fire in the plant.
(1.25) f 3
r o
Section 8 - Administrative Procedures, Conditions and Limitations
(
8.1 List five Technical Specifications which, if exceeded, would require immediate responsive action.
(BE SPECIFIC)
(2.0) 8.2 List the shift supervisor responsibilities delineated in Prairie Island section work instruction (SW 1-0-9, Rev. 2) containment entry instructions.
(1.25) 8.3 List five Technical Specifications which, if exceeded, would require a responsive action (hot standby, restorative action, etc.) within one hour.
(BE SPECIFIC)
(EXCLUDE QTPR AND AFD)
(2.0) 8.4 List all the requirements listed in Prairie Island (5 ACD 1.5) needed to authorize a procedure deviation.
(2.0) 8.5 Checklists can be used in an emergency to alter the status of a piece of equipment.
True/ False (0.25)
Defend your answer.
(0.5) 8.6 Physical independent verification on the removal of the cards and the return to service of equipment is not mandatory under what 4 conditions?
(2.0) 8.7 Match the following:
1.
Hold Card (0.25) 2.
Bypass Tags (0.25) 3.
Special Mechanical Bypass (0.25) 4.
Secure Card (0.25) 5.
Unsafe Cards (0.25) a.
To maintain service or to safeguard equipment b.
Blocks a component out of service or prevents it from performing its intended function c.
Required if a device is definitely hazardous for use
_, d.
Used for marking lifted wires, special electrical jumpers
-e.
Used only to protect and prevent injury to human life f.
Alerts operators that a change in position of a device which is tagged could invalidate test results L
r 8.8 Plant controlled keys (red tags) can be checked out to.
individuals under normal operating conditions.
True/ False (0.25)
Defend your answer.
(0.5) 8.9 List the 2 responsibilities the shift supervisor has concerning liquid and gaseous radioactive releases.
(2.0) 8.10 a.
What is the maximum whole body radiation exposure limit you as Emergency Director would authorize to allow an individual into a high radiation area to account for missing persons or to secure and/or operate vital equipment.
(0.75) b.
What is lifesaving operation limit for whole body.
(0.75) c.
Can you as Emergency Director authorize the limits in part a and b verbally?
(0.5) 8.11 a.
If the SRO is now serving as the Emergency Director what duty (s) cannot be delegated?
(1.0) b.
If you are the Emergency Director what individuals can relieve you of,those duties?
(1.0) c.
What emergency classification (s) requires an Emergency (1.0)
Director?
8.12 On your shift a monthly surveillance item is discovered overdue.
Required due date was the 25th of the month, assume today is the 31st, and the performance of the SP l
has begun.
All previous surveillances were completed on time as scheduled. Which of the statements below is correct about the surveillance (SP)?
(1.0) a.
The SP has been missed and the system must be declared inoperable until the SP is completed satisfactorily.
b.
The system is operable as the Technical Specification allows a monthly SP to be waived 1 month out of 3.
c.
The system is operable because the Technical Specifi-cation allows a time extension and the extension has not been exceeded.
- d.
The system is operable because the 3.25 time interval for 3 consecutive SP was not met.
m
(
2 L
8.13 A precaution in procedure C1.3 Unit Shutdown Procedure states, "The shutdown banks must be at the fully withdrawn position whenever reactivity is being inserted by boron and xenon changes." There are 3 exceptions to this precaution.
Name two (2) of those exceptions.
(2.0) 8.14 a.
What are the administrative controls for removing spurious Control Room annunciators / alarms from service?
(1.0) b.
Who can authorize the initiation of these adminis-trative controls?
(0.5) i 8.15 a.
List the general responsibilities of a Shift Supervisor to ensure the correct, complete and necessary infor-mation is placed on the main control board.
(0.5) b.
When shall the control board notes be reviewed on a weekly basis by the Shift Supervisor?
(0.5) c.
Who can authorize the permanent information to be placed on the control board?
(0.5)
O 5
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U.S. NUCLEAR REGULATORY COMMISSION i
SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
Prairie Island REACTOR TYPE:
Westinghouse DATE ADMINISTERED:
March 26, 1985 EXAMINER:
T. D. Reidinger 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 in-dicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
% of Category
% of Applicant's Category Value Total Score Value Category 24 dMP 5.
Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 23 4Mt 6.
Plant Systems Design, Control, and Instrumen-tation 25 7.
Procedures - Normal, Abnormal, Emergency, and Radiological Controls 25 8.
Administrative Procedures, Conditions, and Limitations 17 te@
TOTALS FINAL GRADE All work done on this exam is my own, I have neither given nor received aid.
Applicant's Signature t
4-5.
4 5..
THEORY OF NUCLEAR POWER PLANT OPERATION,-FLUIDS, AND PAGE -15 ANSWERS -- PRAIRIE ISLAND.182
-85/03/26-HIGGINS, R.
ANSWER 5.01
(.50)
(d) i REFERENCE Lesson Notes for NUS NET Series, p 17 and 42
' System Description B2-25 Wsstinshouse Reactor' Theory Review Text, p I-4.4
" ANSWER 5.02
-(
.50)
.(c)
REFERENCE' Figure lC1.
-ANSWER
'5.03
(
.50)-
(d)
REFERENCE
.Losson Notes for NUS NET Series, p 39 AN',WER 5.04
(.50)
(b)
REFERENCE Leeson Notes for NUS NET Seriest p 39 NUS NET section 10.5 ANSWER 5.05
(.50)
(d) n (c)
[h-REFERENCE Wastinghouse;Reator Theory Review Text, p I-3.2
.Leeson Notes for NUS NET-Series, p 28
V
Je s
5.
' THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 16
. --- 7p g g g g g g g g g g g g --------------------------------- -----
- ANSWERS--- PRAIRIE ISLAND 1&2
-85/03/26-HIGGINS, R.
ANSWER
' 5.06
(.50)
(c)
REFERENCE
~
_L;e son Notess for NUS NET Series, p 42 ANSWER 5.07
(.50)
(b)
REFERENCE ~
V3sson: Notes for NUS NET Series, p 18
-ANSWER 5.08
(.50)
(e)-
REFERENCE.
Lesson Notes for NUS NET Series, p 22 ANSPER.
5.09
(.50)
--({}
R'EFERENCE-Lesson Notes for NUS NET Series, p 26 AnbWER 5.10
(
.50).
(c)
REFERENCE
- Losson Notes for NUS NET. Series, p 28 rANSWER 5.11
(.50)
- (0) o'(c) Mh
-t
g-N' 5.
. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,-AND PAGE 17 ANSWERS -- PRAIRIE-ISLAND 1&2
-85/03/26-HIGGINS, R.
-REFERENCE
'Wastinghouse Reactor Theory Review Text, p I-5.22 ANSWER 5.12
(.50)
(c)'
REFERENCE Lesson Notes for NUS NET Series, p 35
- ANSWER 5.13
(.50)
(c)
ErtEREACE ison Notes for NUS NET, Series, p 33 and 37 A
.At!SWER 5.14
(.50)
-(d)
REFERENCE Lesson Notes for NUS NET Series, p 33 and 37
-W2.stinshouse Reactor Theory Review Text, p I-5.42 ANSWER 5.15
(.50)
(b)
REFERENCE 1HestinShouse Reac+,or Theory Review Text, p I-5.31 ANSWER 5.16
(.50)
(O) 71 (C)
[
. REFERENCE Wastinghouse Reactor Theory Review Text, p I-5.31 n
5 u.
5.
THEORY'0F NUCLEAR POWER PLANT OPERATION, FLUIDS,-AND PAGE ----
ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-HIGGINS, R.
~
ANSWER 5.17.
(.50)
(d)
' REFERENCE-TS 3.10-1
- NC" R 5.10 s.avi (d)
REFERE
[L2sson Notes S NET Se ies, p 26 ANSWER 5.19
(
.50,)
(a)
REFERENCE' TS 3 10-11 ANSWER 5.20
-(
.50)
(d)
REFERENCE TS 3.~10-3
' ANSWER.
5.21
(.50)
(b)
REFERENCE
-TS 3.10-3 ANSWER' 5.22
(.50)
-(d)
['
b
r 5.
. THEORY OF NUCLEAR PUWER PLANT OPERATION, FLUIDS, AND PAGE 19 ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-HIGGINS, R.
REFERENCE TS 3.10-5 if A N S.'IE R 5.23
-(
.50)
^(c)
. REFERENCE-
-Losson Notes for NUS NET Series, P-SOE-78-11 ANSWER 5.24
(.50)
-('d)
REFERENCE
-Lasson Notes forfNUS NET, Series, P-SOE-78-11
^ N C ',' E n 5.23 L
.av>
c
-(c' REFERENCE-clon Notes for NUS NET A ries, p 108
.A ER 5.26
(.50)
(c)'
REFERENCE-TS 3.10-5 ANSWER 5.27 (1.50) rod misali3nment or dropped rod
(.5) inlet-temperature mismatch 1
(.5) unbalanced core flow
(.5)
< improper fuel load
(.5)
Any thrFl'of the preceding five will receive full credit.
REFERENCE TS 3.10-13
~
- ;- +
r-
,a
'5.
. THEORY ~OF NUCLEAR. POWER PLANT OPERATION, FLUIDS, AND PAGE 20 7pgggggggggggg--------------------------------------
ANSWERS -- PRAIRIE ISLAND 1&2
-85/03/26-HIGGINS, R.
ANSWER 5.28
(
.50')
( a )' en (c) _
-REFERENCE t.
"Lasson Notes for NUS NET Series, p 102
' ANSWER 5.29 (2.00) et1 trol rods.in~a single bank move together (.25) with no individual rod insortion dif f ering by niore than 15 inches from the bank demand position.(.25) control rods are sequenced with overlapping banks (.5)'
contro11 bank insertion li,mits are not violated (.5)
La::ial power distribution -control limits are observed (.5)
REFERENCE
'TS 3.10-10 ANSWER 5.30
(.50) 9.(b)
- REFERENCE TS 3.10-10
' ANSWER 5.31' (1.50) 1RCS Tavs (.25)-less than or equal to 564 F (.25)
.Proesurizer pressure (.25) greater than or equal to 2220 psia (.25)
Rocctor coolant flow (.25) greater than or equal to 178,000 spm (.25)
REFERENCE TS 3.10-8 ANSWER
,,5.32
(.50)
(b).
?
L
p a
5.
THEORY'0F NUCL' EAR' POWER PLANT OPERATION, FLUIDS, AND PAGE. 21 ANSWERS -- PRAIRIE. ISLAND 1&2
-85/03/26-HIGGINS, R.
. REFERENCE
~ Thermal-Hydraulic Principles and Applications to'the-PWR II, p 13-60 ANSWER 5.33.
(.50)
(a)-
REFERENCE
, Thermal-Hydraulic Principles end Applications to the PWR II, p 13 l ANSWER' 5.34
- ( 12. 00 )
(a) Low steam generator pressure SI.
(1.0)
(b)-Pressurizer' spray effectiveness or 50 F subcooling.
(1.0)
_ REFERENCE Lesson Notes for NUS NET Series, p 82 ANSWER 5.35
(.50)
(c)
REFERENCE
'TS'3.1-4.
Sieam Tables
-ANSWER.
5.36
_(
.50)
.(d)
REFERENCE Steam T'bles a
2 ANSWER 5.37
(.50)
(b)-
REFERENCE' Lasson Notes.for NUS NET Series, p 79 M
=
,y.wg n
T-t-t
I:
- .. -. THEORY OF NUCLEAR POWER PLANT OPERATION,-FLUIDS, AND PAGE 22
^
ANSWERS ~- -PRAIRIE ISLAND-12,2
-85/03/26-HIGGINS, R.
ANSWER-5.38
(.50)
-- ( e )
REFERENCE
'1h7tmal-Hydraulic Principles and Applications to the PWR II, p 10-43 ANSWER 5.39~
(
50)
(d)
REFERENCE Thirmal-Hydraulic Principles and Applications to the PWR II, p 8-15
' ANSWER.
5.40-(.50[)
<ct REFERENCE
- Losson Notes for NUS. NET. Series, p 84a k'
L WW*
I l
t l
- b.,
m; o
Answers Section 6 - Plant System Design, Control and Instrumentation 6.1 Ref. B 28-51, Table B28-1 1.
Lube oil pressure 1 6 psi s
2.
Loss of all condensate pumps 3.
Suction pressure 1200 psi for > 5 second running pump 4.
Undervoltage 5.
Hi-hi S/G water level 6.
SI 7.
Turbine trip if both feed pumps are running 8.
Loss of 2/3 condensate pumps in that unit when 2 feedpumps are running 9.
Overcurrent 10.
Low voltage 11.
Out of phase fault 6.2 Ref. E-28, B28 1.
C 2.
E 3.
A 4.
C 5.
D 6.3 Ref. B8-14 (2.1.1.3.2), Table B8-2, SH6-5652020 No. Prairie Island low pressurizer pressure trip is 1900 psig.
If the turbine first stage pressure is placed in test for
,, maintenance purposes, it will de-energize interlock circuit P-7.
This will unblock the low pressurizer pressure trip function and result in a reactor protection actuation.
i L _.
^
6.4 LER 84-001-Prairie Island a.
RCS temperature will drop in response to the overfeeding M - ] $. $5 ct%.,.u.-z $~
K).< m.dE.w, cm LryQ"-t.cE btepfr%:.
of the S/G's a
.M wxb cen.-
u y-b.
The reactor Jrip4 on overpower (the fow fange setpoint) due to the RO withdrawing the rods.
Ref. Chapter B20.8-9, B8-7, Drawing 5652020 6.5 The reactor-f.r.ip_ occurred due to indication of low RCS flow with reactor power greatirW'CDbop-B bte_aker (52/12 RCP) auxiliary
-w he P-8 setpoint.
There are 3 channels per reactor coolant loop.
R
[NM contact will stay closed but RPS actuation'Etreutt_wijl sense a
" loss" of the closed RCP breaker, it will make up with (P"8)-and' actuate a trip.
6.6 Ref. B-28 a.
The standby condensate pump was not vented properly and this air entered the suction header of the running condensate flow caused the main feed pumps to trip (overspeed) or cavitate and cause a stop of extraction flow from the LP heaters.
The loss of FW caused a steam flow /FW flow mismatch and when the falling S/G 1evels reached the low level trio setooint-the coincidence steam flow / feed flow mismatch with S/G low level was made up and caused a reactor / turbine trip.
b.
The loss of FW heaters extraction steam flow caused a 110 MW spike in electric load because the extraction steam was diverted to use in the turbine.
No level problem in heater drains so no effect on spill over valves or check valve closino.
The extraction steam is no lonaer beina condensed in the heaters so the back Dressure from the heaters force extraction steam to the turbine.
The turbine increases electric load.
(Loss of turbine feed pump could cause 30 MW spike) 6.7 1.
d 2.
c 3.
a 4.
b 6.8,If.more than one PRNI channel is de-energi_ed, P10 will block source range high voltage causing a loss of source range.
Source range is required in shutdown modes.
(
2 e
- 7. -.
\\
6.9 Ref. B22 4
a.
'1.'
Turbine is latched - throttle (stops) shut, reheat stops open, interceptor valves open, governor valves shut (shown by indicating lamps) 2.
Latch light is illuminated 3.
The unit trip monitor lamp goes off 4.'
Control /stop/rcheat/ interceptor valve position indicators b.
1.
Seal oil backup pump provides auto stop oil 6.10 Ref. C3, paragraph 2.3.8 False - 200*F 6.11 Ref. NF 40780-8, C/13, step 51 PRT logic - 10 psig turns off and gate which turns off air to vent valve which then closes to protect waste gas header from over pressurization.
This causes PRT - Auto vent isolation.
6.12 Ref. B12-88, Figure.612-26 a.
A low level signal from both volume control tank level channels (112/141) will close a motor operated valve on the discharge of the volume control tank and open a motor operated valve from the refueling water storage tank.
b.
False - Valves must be changed by operator action.
6.13 Ref. NF40767-1, C28, p. 15, paragraphs 5, 6 The automatic start of auxiliary feed pump from " loss of both main feed pumps" is lost when selector switch CS 46785 is placed in other than auto position.
6.14 Ref. B5-1-29, paragraph 1.7.2.2 a.
All rod motion would be inhibited except for an " Urgent Failure" in the shutdown banks A, B, which would inhibit motion cn shut-down banks A, B.
,,b.
The motion of all rods in the affected power cabinet would be
-inhibited; 3
i k
6.15 Ref. 822-83, paragraph 2.4.7, figure B22-36 a.
If the regulating potential transformer is opened, the feedback signal to the voltage regulator will be lost and voltage control will be switched to manual and controlled by the use of the base adjuster.
b.
Ref. B22-42, paragraphs 1.3.3.7, 1.5.2.2, ANN 47506-0407 If the metering PT is opened on one phase, the relays which are supplied to the metering PT will sense a generator fault due to a loss of phase and trip the generator.
This " sensed" flow of unbalanced currents would initiate a generator trip and lockout scheme #86, trip main generator breaker, generator field breaker,.
and the turbine.
6.16 Ref. B28-64 On a safety injection the main feed pumps are tripped automatically along with a feedwater isolation.
A reactor trip with low T the main feed pumps are not tripped (gone on recirc.), but a fee 8#0a,ter isolation also occurs.
e // p 'r'/? p g 6.17 Ref. W False. The relief valve is designed to accommodate the output on all charging pumps at relief pressure.
6.18 Ref. Rod Control A-4, B-6, C-5, D-7, E-1, F-2, G-3 6.19 Ref. C19.2 Upon stopping Train A, the components that were automatically shutdown remain shutdown, where as upon stopping Train B -11 normal equipment that was operating restarts automatically.
4 u
s
n s
,o Answers Section 7 - Procedures, Normal, Abnormal, Emergency and Radiological Control 7.1 Ref. IE-3
,,Q, N d u ye< < e w /p;' ph[
Zr).4~t'+
It is also important to maintain the water level in the ruptured steam generator above the top of the U-tubes.
When the primary system is cooled in subs 2quent steps, the steam generator tubes in the ruptured steam generator will approach the temperature of the reactor coolant, particularly if reactor coolant pumps continue to run.
If the steam space in the ruotured. steam aenerator exoands_lo contact thgig._ colder tubes. condensation will occur which would decrease the ruptured steam
~'
generator pressure.
This would reduce the reactor coolant _subdo~ ling o
_ margin and/or increase _primarv-to-secondarv leqKage, possibly delaying SI termination or causing SI reinitiation.
Conseq_uently, the water level must be maintained above the top of the tubes to insulate the i ~ -
steam space.
In addition to insulating the steam space, this ensures a secondary side heat sink in the event that no intact steam annerator is availahlo and also providoc nrntaction aQainst misdiagnosis of the.
ruptured steam nonerator due to an imbalance of FW flow.
7.2 Ref. 060 7.3 Ref. 1E-1 The auxiliary building must be maintained at a lower pressure than turbine building to ensure that any potential airborne contamination in the auxiliary building will be passed through the special ventilation filters.
7.4 Ref. C20.9 1.
Inspect the reactor trip 2.
Verify the reactor trip breakers open 3.
Verify that all full length control rods and shutdown rods are properly inserted by inspecting the rod position indications 4.
Verify the turbine generator tripped 5.
Verify the generator has tripped by verifying BKRS 8H16 and 8H17 (8H13 and 8H14) are open 6.
Verify no fire alarms received for the zone containing the battery room
- 7. 5 Ref. X-H1AW1-7 a.
RCS System - Flange, leakoff detection isolation valve 1.
PORVs pressurizer g, 'hw%.[
h9
.W&r.,s4 4
2.
Primary makeup valve to PRT 3.
Spray valves to P2R 4.'
PRT drain valve 7) p f ",w J-L '
5.
PRT gas tem Ff 31320 Ref. X-H1AW-1-M 3T b.
CVCS - (2) letdown valves - 31226, 31225
- (3) letdown isolation valves
- - (2) excess letdown HX (inlet / outlet) isolation valves
/
- (1) seal injection relief valve to VCT or RCDT
- (1) RCP. bypass leakoff isolation
- (2) RCP seal #1 (31335/6) returns
- (2) Primary water makeup valves to standpipes
__ - (1) Charging line isolation valves to loop f
- (1) Auxiliary spray isolation valves to pressure 7.6 Ref. 47515-0308 1.
Determine initiating conditions 2.
Ensure power operated relief isolation valves MV-32197 and l
MV-32198 fully open l
3.
If pressure high a) reduce pressure to clear alarm b) If heatup > 275*F, place control switch to " disable" 4.
If temp. < 275*F and pressure < 500#, place control switch
~~
to " enable" 5.
Check for leaks and valve lineup l
l l
(
2 i
7.7 Ref. C1.3 f
To allow the stroke of the snubbers under the discharge elbows to equalize with the steam expansion movements.
7.8 Ref. W CAF
~
1%
This is to prevent grid freq ncy perturbations causing an increase in turbine power which could result in exceeding turbine load limits.
7.9 Ref. 6/4e c I. 5' 1.
SS contact computer engineer or computer I&C tech and initiate g-[
~
work request.
SS shall assure 2 qualified operators are assigned specifically 2.
tomonitortheprimaryandsecondarysystemsoftheaffectedunit(,h at all times.
3.
SS contact load dispatcher and request any load follow programs {
for the affected unit be suspended.
7.10 Ref. C1.8, paragraph A
'a.
Unit 1 p
g b.
Unit 1 (SS) will proceed to the air compressor - auxiliary feedwater pump room and establish communications.
Unit 2 (SS) will report to the hot shutdown panel provide supervision and assistance.
c.
Direct the Unit 2 PE and RO to proceed to Unit 2 rod drive control room and manuall{/ M C -
trip the reactor at the breakers.
Mw /16 c -r.3%d..
7.11 Ref. C/11 /
//
1.
D 2.
A 3.
A 4.
A
,5.
E 7.12 Ref. Radiation Safety plant Usually 100 CPM above background so it would be 225 cpm.
3 L
7.13 Ref. F2 - Chapter 7 2
False.
It would be a green tag.
7.14 Ref. F2 D,A,B,C,E 7.15 Ref.'F2 1.
Incore thimble head chase area when thimbles are withdrawn 2.
Reactor head during high power operation 3.
Reactor coolant loop areas during high power operation 4.
Spent resin tank room 5.
Primary system demineralizers if sand shielding were removed 7.16 Ref. F4
/f1.
Dispatch a team with wire stretcher and first aid kit, fi~
f
.q 2.
Call Red Wing Ambulance Service.35F 3.
Call.St. John's hospital
, 3 6~
- 4..' Proceed to emergency scene with a portable radio 3
(Coordinatetheactivitiesatthescene,)
5.
7.17 Ref. F5 Unit 1 (SS) shall assume responsibility for operation of both units and coordination of fire fighting activities.
He shall inform duty engineer and the STA of the situation and evacuate personnel (if necessary).
Unit 2 (SS) is the Fire Brigade Chief.
He shall don protective clothing, obtain a radio and report to the scene of the fire immediately.
He shall direct excess CR personnel to access control for. equipment and then to the scene of the fire.
}
4 L-
Answers Section 8 - Administrative Procedures, Conditions and Limitations 8.1 a.
Immediate response 1.
T/S 3.1-14 E Maximum RC oxygen, chlorides, fluorides concentrations exceed limits.
T/S 2.1 Safety limits - thermal power level, coolant pressure and coolant temperature total combination.
1 T/S 2.2 Safety limit - Rx coolant system pressure shall not exceed 2735 psig with fuel assemblies installed in the reactor vessel.
T/S 3.1-9 Paragraph 5 - if total leakage other than controlled leakage exceeds 10 gpm, reactor hot shutdown shall be initiat immediately.
T/S M-Y SI, ITHf', Rwf W,W
.s &&.,,e Y}W2.
T/S 3.3-5 D-2 a-1 If one diesel fooling water p mp oos, th'e other diesel water pump and associated diesel are to be immediately tested.
b-1 If one motor driven cooling water pump oos, then both diesel driven cooling pumps shall be demonstrated to be operable.
T/s 3.3-5 0 c-1
... check operability of the diesel driven pump and the diesel if one cooling water header is operable.
T/S 3.9-5 g
... radioactive material in gas storage exceeds limit.
T/S 3.9-7 E B-radioactive liquid effluent monitoring instrumentation channel alarm / trip set-points less conservative.
F b gaseous effluent...same as above.
T/S 3.10-3 para:6-1 AFD outside envelope; reduce power to
_50% and setpoints to _55%.
T/S 3.4-2 3c Actuation logic (for one train steam exclusion...other train is tested and found operable prior to beginning repair of oos channel.
e
r.
r /5 3./D-T/5 3.7 T/S 3.7-2 para B-2 Diesel generator oos, operability of other diesel shall be tested immediately.
T/S 3.8-1 Refueling and fuel handling Part A and Part B - LCO's T/S 3.9-1 A-1-b Liquid effluent - exceeds limits, restore concentrations immediately.
T/S B Gaseous effluent - same.as A above.
T/S 3.9-5E.
Oxygen concentration at outlet of oper-ating recombiner _4% by volume-suspend all additions of waste gas to system.
j 8.2 Ref. SW1-0-9, Revision 2 1.
The Shift Supervisor is responsible for insuring thct. the containment entry log is maintained.
2.
He shall not permit containment occupancy during approaches to criticality.__ w e u.u p e d h '
8.3 One hour response j $
3, l u
T/S3.10-3paragrapb6 Afd_+/-5% target band _1 hour _24 hours and it does not exceed envelope.
T/S 3.10-4 paragraph 9 Afd alarms oos-log AFD for each operable excore channel.
T/S 3.14-1-A Inoperable fire detection instrumentation systems a
B Spray and sprinkle systems C
Carbon Dioxide system D
Fire hose station i
F Yard Hydrant hose house G
Penetration fire barrier T/S 3.1-2 paragraph 4 pzr
...with one or more PORVs inoperable-within one hour either restore or close block valves or if block.
T/S 3.3-2 paragraph e One accumulator may be inoperable for up to one hour when every pzr pressure _1000 psig.
4s 3. I e
l 2
L
l.
l e
s g
.m T/S 3.5-4 table 3.5-6 1.
Degraded voltage place inoperable channel in tripped condition within one hour.
x 2.
Loss of voltage - 4 KB Safeguards (90%)
(Same as part one above) s.
3.
Loss of voltage - 4 KB Safeguards (50%)
(Same as part one above)
T/S 3.9-5.e Reduce concentration of oxygen to _2% if 02 concentration _4% volume at' outlet of recombiner.
8.4 Ref. 5 ACP 1.5 1.
Clearly not change the intent of approved procedure and
[.$)
2.
Be approved by the on duty Shift Supervisor and another licensed /. }-
senior. reactor operator _to verify that the change is appropriate (*b/
and within the intent of the procedure', and 3.
Individuals approving the deviation shall, amend the affected
[ ~2) procedure and initial and date the procedurs prior to implementing the deviation, and 4.
Complete Section A of the procedure deviation / chang 9 proposal (
documenting the reason (s) for the deviation.
.N.
8.5 Ref. SW 1-0-10
\\
~
No.
Checklist shall be used to confirm not alter the status of equipment.
8.6 Ref. 5 ACD 3.2 a.
Indirect indication (status light, annunciator, etc.) clearly depicts the proper operating alignment of the system / component.
b.
A significant amount of radiation exposure would be received.
c.
Post-work functional testing can be performed, without compromising plant safety, which clearly verifies that all equipment (valves, switches, etc.) involved in the activity is correct Q aligned.
NOTE:
When testing does not verify that portions of the involved equipment are correctly aligned; or the testing itself positions equipment in a non-routine
~
operating status, that equipment SHALL be individually verified to be in the correct operating status.
7 3
L
r d.
A pre-start checklist (i.e., for outage related work) which adequately verifies correct system alignment is completed prior to the time the equipment is required to be operable.
OPTIONAL e.
If any of the methods a through d above or a combination thereof is used, the method used, the checklist number, test number, etc.,
SHALL be documented in Section II of the I and R by the Shift Supervisor (initial and date).
8.7 Ref. 5 ACD 3.9, 3.10 1.
E 2.
D 3.
B 4.
A 5.
C 8.8 Ref. 5 ACD 5.3 False. Only under emergency situations.
8.9 Ref. 5 ACD 10.1 1.
Verification that the proper release instructions for each planned batch release of liquid and gaseous radioactivity are used.
k 2.
Verification of the operability of the effluent monitor in the release path.
8.10 Ref. EP, p 6-31 a.
25 rem b.
75 rem c.
Yes (F-3-12) 8.11 Ref. EP, p 5-7, paragraph 7
~~
A.
Authorizing offsite protective action recommendations t
4
v.
i
.B.
1.
Plant Manager 4
2.
Plant Superintendent Engineer and Rad Protection 3.
Plant Superintendent-Operations and Maintenance 4.
Superintendent Rad Protection C.
Alert, site area and general emergency 8.12 Ref.'C 8.13 Ref. C1.3, paragraph 3.2 a.
The reactor coolant has been borated to at least the cold shutdownconcentyation.
.6ede,E4 w 2mo*?<$tl*<N.Q, /6./O & y p 7 e
b.
The reactor coolant has been borated to at least the hot xenon -
free boron concentration and is being maintained at~no-load average. temperature.
.%- f 2-ef-
~
CD tbewithdrawn,!thereactorcoolantmust c.
If th banks ca be borated as conditions require and the boron concentrations conformed by sampling.
i
-C 8.14 Ref. SW1-0-14 a.
1.
An entry shall be made in the Annunciator Out-of-Service Log, listing date, time, annunciator name and number and a7 signed by the authorizing Shift Supervisor.
7E <$u M J m v.e w h < T 2.
Entry shall made on Unit's status board Y
0 m.4 (Awork'requestshouldbe1[itiatedwhenappropriate.]
3.
b.
Shift Supervisor 8.15 Ref. SW-0-19.
a.
Any note to be placed on CB must be reviewed by duty SS, initialed and date note if he concurs.
b.
Review outstanding notes each Sunday on midnight shift.
Those deemed still necessary shall be initialed and dated by duty SS.
_c.
Superintendent of Operations.
Y
_