ML20214R796
| ML20214R796 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/01/1987 |
| From: | Bjorgen J, Burdick T, Clark F, Hare E, Dave Hills, Lanksbury R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20214R790 | List: |
| References | |
| 50-373-OL-87-01, 50-373-OL-87-1, NUDOCS 8706080320 | |
| Download: ML20214R796 (72) | |
Text
- -
U.S. NUCLEAR PEGULATORY COMMISSION REGION III Report No. 50-373/0L-87-01 4
Docket Nos. 50-373; 50-374 Licenses No. NPF-11; NPF-18 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
LaSalle County Station j
Examination Administered At: Wilmington, IL and Marseilles, IL Examination Conducted: ' April 20-23, 1987 i
Examiners: Nb
[f/
/
E. D. Lanksbury 4 Daty Chief Examiner
~7n Dud &W LNn
).
E. Hills l
Ddte 3%
0
/h/
F. E. Clark D'att N
Y/k)
Y L
E. A. Hare i
D3td TTe /L4// kn udo J. C. Bjorgen 1
Dets 4
Approved By:
4 b
///P)
T. M. Burdick, Chief IIat'e Operator Licensing Section i
Examination Summary Examination Administered on April 20-23, 1987 (Report No. 50-373/0L-87-01)
Written, oral, and simulator examinations were administered to three Senior Reactor Operator (SR0) candidates and a simulator retake to one Senior l
Reactor Operator (SRO) candidate.
Results:
Three SR0 candidates passed the oral examination, one passed the simulator examination, and three passed the written examination.
A total of 4
one candidate passed overall.
8706080320 870602
~
PDR ADOCK 05000373 V
pon
.. ~..,, -. - -..
r REPORT DETAILS 1.
Examiners
- R. D. Lanksbury, Region III F. E. Clark, Region III D. E. Hills, Region III J. C. Bjorgen, Region III E. A. Hare, Region III
- Chief Examiner 2.
Examination Review Meeting Copies of the written examination and answer key were given to the facility personnel for review at the conclusion of the written examination.
Facility personnel provided their comments to the examiners on April 23, 1987.
Their comments as well as the resolution are enclosed as an attachment to this report.
3.
Exit Meeting On April 23, 1987, an Exit Meeting was held.
The following personnel were present at this meeting:
Commonwealth Edison Company S. Harmon, Operations Training R. Armitage, Operations Training Supervisor W. R. Huntington, Assistant Superintendent, Operations J. C. Renwick, Production Superintendent C. M. Allen, Nuclear Licensing Administrator S. L. Trubatch, Staff Attorney M. S. Turbak, Operating Plant Licensing Director G. J. Diederich, Station Manager NRC R. D. Lanksbury, Chief Examiner J. A. Malloy, Resident Inspector, LaSalle F. E. Clark, Examiner The following topics were discussed at the Exit Meeting:
a.
The examiners identified four generic deficiencies in the candidates' knowledge and abilities.
The first deficiency was that the candidates were very weak on their ability to utilize the emergency operating procedures.
The second deficiency was that the candidates were weak in their ability to locate and recognize proper keys needed for emergency operations. The third deficiency was the candidates' 2
ability to determine if equipment and components were safety related.
The fourth deficiency was the candidates' ability, while performing as Acting Station Director, to properly classify emergency events based on gaseous releases, b.
Two additional items of concern were identified.
The facility's Emergency Operating Procedure (E0P) format is not easy for the candidates to utilize during transient events.
The E0Ps require the candidates to use multiple procedures concurrently.
Since all procedures are contained in a single 8-1/2" x 11" binder, it is considered physically impossible to effectively use several procedures at once.
The E0Ps were in a format to be removed from the binder; however, when removed from the binder the loose pages from several procedures were mixed, which made them impossible to use.
The examiners also noted that the facility's Attachment (b) and (c) of LZP 1200-2, " Classification of Noble Gas Release", forms were cluttered with extra lines and information which made them easy to misread.
c.
During the Examination Review Meeting, which was held after the Exit Meeting, the Training Department committed to ensure that a March 1987 change to Procedure LOA-FW-01 was clarified.
See, Comment 7.11.b.
3
p ATTACHMENT 1 WRITTEN EXAMINATION COMMENTS AND RESPONSES SENIOR REACTOR OPERATOR EXAMINATION ADMINISTERED APRIL 20, 1987 Docket No. 50-373 Sheet 1 of 25 COMMENT:
5.01 a.
Point A shows the initial pressure spike caused by the turbine valves closing on the turbine trip.
This pressure spike is due to the turbine trip, the continuation of the curve at pressure in excess of 1100 psig could be related to bypass valve failure but should not be required to state " bypass valve failure" for full credit.
Reference the UFSAR, Chapter 15, Pages 15.2-8 and 9.
This sequence shows that even when bypass works properly pressure will spike to SRV lift setpoint.
So a bypass valve failure is not necessary to see a large pressure spike like this.
b.
LaSalle only has one recorder that indicates steam flow.
This steam flow indication is measured at the restricting orifices and would not show SRV lift.
(SRV's are upstream of orifices),
c.
Should also accept an answer that states "Recirc. pump downshift" for full credit.
(Need not state E0C-RPT downshift).
d.
Should not be required to state "... and water in the annulus pumped into the core" for 1/2 credit.
Full credit should be granted for saying the pressure spike causes void collapse which causes the indicated level
- decrease, e.
The slope of the graph at Point E shows a level increase of approximately five to six inches per minute.
The LaSalle Reactor vessel volume is approximately 200 gallons per inch which would mean level increased by approximately 1100 gpm.
Please reference the LaSalle CRD Hydraulics lesson plan, Page 15, which states that maximum CRD flow would be approximately 200 gpm (assuming the scram is not reset).
Therefore no credit should be taken off for stating the level increase could also be partially from feedwater input.
(LaSalle Feed Reg. valves are notorious for leaking past the seat).
9 i
2 l
I f.
Note the E0C-RPT is a downshift of the Recirc. pumps, so the pumps will still be running in slow speed. The forced flow is more significant than natural circulation, i
therefore natural circulation need not be mentioned. Full credit should be given for simply stating that jet pump flow may increase due to the SRV's opening (and reducing back pressure).
RESPONSE
a.
Coment accepted. Answer key changed to only require the turbine trip shutting the turbine stop and control valves, b.
Comment accepted. Question 5.01 Part b. is deleted.
Answer key changed.
7 l
c.
Coment accepted. The reason for the Recirc pump 1
downshift is not specifically asked for; therefore, will l
accept "Recirc flow decrease due to Recirc pump downshift."
i Will accept alternate wording for the E0C-RPT downshift.
+
d.
Comment accepted. Answer key changed to: Reactor water level decrease due to pressure spike collapsing the voids in the core."
e.
Comment accepted. Answer key changed to include level increase due to CRD pumps and feedwater flow, f.
Coment accepted. Answer key changed to indicate increased jet pump flow due to steam being drawn off by lif ting SRVs.
COM ENT: 5.04 a.
The assumed values of k and A should be any reasonable value given by the examinee and should not limited to the values given on the answer key. Note, the value given for A on the answer key (100 sec-1) does not agree with the value given on the equation sheet (0.1 sec-1).
(Answer key is wrong.)
c.
The initial drop in power is primarily due to prompt neutrons but not only due to prompt neutrons. Need not imply "only" for full credit.
RESPONSE
a.
Comment accepted. Will accept reasonable assumed values for y and d.
Answer key had the incorrect value for ii. Answer key changed.
b.
Coment accepted. Answer key changed to read " primary" vice "only".
i
.-n,---.-,
,-,-.-rr
--e-n
~,
3 COMMENT:
5.04 General Comment - The answer key shows a total of points allowed as 3.55 points instead of the 3.0 points specified.
The problem seems to be in the point values assigned to E (0.05 pt.) and (0.5 point).
RESPONSE
Comment accepted.
Typographical errors for point values removed from the answer key.
COMMENT:
5.05 c.
The answer key is wrong.
Increasing the speed of the Recirc. pumps will cause the required NPSH to increase.
This is one of the major reasons for having the Recirc.
pump downshifts from cavitation interlocks (i.e., less than 30% feed flow downshift).
Please reference Page 70 of Heat Transfer & Fluid Flow lesson plan.
Change answer key to state " Increase".
RESPONSE
c.
Comment accepted.
Answer key changed to " increase."
COMMENT:
5.06 Should also give credit as an acceptable answer the " cracking of the pellet" due to exposure.
See reference, Page 41 of the Core Thermal Lesson Plan.
Also the discussion on cladding creepdown should not be required.
This is not mentioned in the LaSalle Lesson Plan.
RESPONSE
Comment accepted.
Answer key changed to remove " clad creepdown" and add " cracking of the pellet."
COMMENT:
5.07 c.
The question is confusing in that it tries to tie the in critical power to the decreasing latent heat of vaporization and changing flux profile.
In reality the rise in pressure is not tied to the flux profile change.
It is true that the rising flux profile is not shifted because of increase in pressure.
These are independent of each other and are discussed as independent actions in the reference given for this answer.
Suggest dropping part "C" of this question and reducing the point value of the question by 0.5.
RESPONSE
Comment accepted.
Part c. of Question deleted. Answer key changed.
COMMENT:
5.08 a.
Full credit should be given for stating that reduced flow would cause increased voiding and an increase in indicated level.
The discussion on backpressure and decreased flow from the annulus should not be required for full credit.
b.
Should also accept a discussion on reduced core flow which causes reduced neutron moderation leading to reduced power.
4 c.
Jet pump flow decrease is due to the Recirc. pump trip.
This should be adequate for full credit.
The discussion on increased core voiding is not the cause for the reduction in flow and should be dropped from the answer key.
e.
If student assumes 3 element control on feedwater the answer is correct.
If student assumes single element control on feedwater then he only need mention the increase in level causes feed flow to decrease.
f.
The question asks why does steam flow drop at point F.
This is simply due to the drop in power which produces a drop in steam production.
This is adequate for full credit.
The discussion on EHC should be dropped from the answer key since this describes why steam flow recovers at some reduced level and is not what the question asks.
RESPONSE
a.
Comment partially accepted.
The portion of the answer pertaining to, " reduced recirc flow from the annulus,"
will be removed from the answer key.
The answer key will be changed to read, " Decreased recirc flow causes increased voiding in the core causing backpressure." The increased voiding causes a backpressure, which reduces the flow through the core and causes level in the annulus region to increase.
b.
Comment partially accepted.
Alternate wording for
" negative reactivity insertion," will be accepted.
c.
Comment accepted.
Answer key changed to accept "Recirc pump "B" tripped."
e.
Comment partially accepted.
If the e didate states the assumption that feedwater control is.n single element, will accept, "due to level increase."
f.
Comment not accepted.
The pressure change is due to the reactor pover decrease and the EHC system shutting the TCV's to control pressure.
If the EHC system did not throttle the TCV's, the pressure change would be a gradual drop as reactor power decreased.
Due-to the EHC system action, attempting to control pressure by shutting the TCV's throttle, the steam flow rate is rapidly reduced.
COMMENT:
5.09 d.
See reference, Page 252 of the Rx Physics Lesson Plan.
This discussion shows how rod worth follows the Keff curve over core age.
Should also accept an answer that discusses that rod worth initially decreases, then increases, then decreases again.
RESPONSE
Comment accepted. Will accept wording that indicates rod worth follows the Keff curve.
Answer key changed.
5 COMMENT:
5.11 This entire question should be deleted for the following reasons:
a.
This could be interpreted to mean as rods are withdrawn the Mod temp. would increase.
As mod. temp. increases the MTC becomes more negative.
See reference, page 252 of the.
Rx Physics Lesson Plan.
b.
This statement is False but the answer is given as True.
Fuel temperature would be the first thing to change on this transient and as. fuel temp increases this would add negative reactivity due to Doppler, again see reference, Page 252 of the Rx Physics Lesson Plan.
c.
Late in core life at a narrow temperature band MTC can be positive. See reference, Page 122 of Rx Physics Lesson Plan.
Therefore, if this was assumed to be the case, the answer would be True not False.
d.
This question.is misleading since normally, when discussing the void coefficient, it is during saturated conditions.
The facility feels that the wording on this question could intentionally lead the examinee into thinking voids only affect power during saturated conditions.
The facility lesson plans do not discuss-the negative reactivity addition of voids during subcooled nucleate boiling since the affect is minute compared to MTC.
RESPONSE
a.
Comment accepted.
Part a. of Question 5.11 is deleted.
Answer key changed.
b.
Comment partially accepted.
The statement in part b., as written, is false.
Answer key changed to false.
c.
Comment partially accepted.
If the candidate states the assumption that it is-late in core life and moderator temperature is between 150 - 200 F, then will accept true.
d.
Comment accepted.
The answer key has been changed from False to True.
COMMENT:
5.12 Should accept an answer that discusses a decreased margin to the MCPR limit for full credit.
RESPONSE
Comment partially accepted. Will accept a discussion that states the operating MCPR is established to allow sufficient margin to prevent the MCPR limit from being exceeded for the j
worst case.
See reference, Technical Specifications, Page B 3/4
'l 2-5 and LaSalle Lesson Plan, Thermal Hydraulics, Page 34.
6 COMMENT:
5.14 a.
If the affected jet pump is a fully instrumented pump, indicated flow could go up due to reverse flow through the pump.
(Flow is measured by ^P and doesn't matter which way flow is going.)
RESPONSE
Comment accepted. Will accept " increase" if the candidate states the assumption that the jet pump is fully instrumented.
COMMENT:
6.01 This question is not based on the learning objectives of the lesson plan.
Since this is not an objective, the answer should be limited to a more basic discussion on the design of the orifices.
See reference, Page 19, Chapter 21 of the lesson plans.
Should accept for full credit a discussion on restricting inventory loss during a MSL break outside the containment and limiting the ^P across the Reactor internals.
Discussion on level above the TAF before MSIV isolation should not be required for full credit.
RESPONSE
Comment partially accepted.
Answer key changed to " Limit Core D/P, Loss of level, or loss of coolant (0.5) following a steam line break outside of containment (0.5)."
COMMENT:
6.03 Also accept for max. time, " prevents release of fission products to the environment".
See reference, Page 20, Chapter 1
21 of the Lesson Plans.
RESPONSE
Comment partially accepted.
For minimum time, will also accept;
" slowly enough to assure Nuclear System Design limits are not exceeded (fuel vessel, etc...)
For maximum time, answer key changed to read " Limit release of reactor coolant during DBA assures the fuel barrier is protected against loss of cooling (0.25) and limit release of radioactivity to the environment (0.25).
See reference, Section 5.4.5 of the UFSAR.
COMMENT:
6.05 a.
Credit should be given for discussion on a recent LaSalle modification concerning a 9 minute timer which will bypass the high drywell pressure signal.
If you have all the other initiation signals except 1.69 psig, for 9 minutes, ADS will initiate without the 1.69 psig.
See reference, write up on the recent modification.
b.
Should also accept a discussion that states Operator actions are taken during this time to recover level.
(i.e., Time delay allows for operator to recover level to normal bands.)
7
RESPONSE
a.
Comment accepted.
If candidate stipulates recent modification does not require high drywell pressure, Will accept "9 min. time delay without high drywell pressure."
b.
Comment not accepted.
See reference, LaSalle Lesson Plan 37, Page 6, which states the ADS logical time delay is long enough to ensure HPCS has had enough time to operate, yet not so long that LPCI/LPCS Systems would be able to cool the core.
COMMENT:
6.08 This question is misleading for the following reasons:
(1) The local start pushbutton is only a normal start for the D/G, and if started using this P. B. (at the local D/G Panel) all D/G trips are still in effect.
(2) The control room start pistol grip switch is also a normal start and all D/G trips are in effect.
(3) The control room divisional start push button will start the D/G, but also starts all the ECCS pumps in that particular division.
If this push button is used then the only trips in effect are 3 listed on the answer key.
Note the engine start failure is also bypassed during ECCS conditions.
Please reference Chap. 47 of the lesson plans and the LOP-DG procedures you already have.
Based on this, all D/G trips should be accepted for full credit.
(Any 4) Reference LOP-DG-02, Page 4 and 5 for the following list:
Trips Never bypassed:
(1) Overspeed (2) Gen. diff. current (3) Emergency stop push button.
Trips bypassed during LOCA condition:
(1) Overcurrent (with voltage restraint)
(2) Gen. ground overvoltage.
(3) Underfrequency (4) Loss of excitation (5) Reverse Power (6) Failure to start (7) High cooling water temp (8) Low oil pressure RESPONSE: Comments accepted.
Question 6.08 deleted from the examination.
8 COMMENT:
6.12 Should also accept, for full credit, that pressure may increase.
If the. leak is large enough to cause the N2 back-up bottle banks to discharge then. primary containment pressure may go i
up.
See reference, Figure 68-8 of Chapter 68 of Lesson Plans.
RESPONSE
Comment accepted.
If candidate states the assumption that pressure drops to the N2 backup bottle discharge point; then,
" increase" will be accepted.
)
COMMENT:
6.14 Answer No. 1 should accept a discussion that says the mechanical vacuum pump only has a 1.75 min holdup volume.
See reference, Page 28, Chapter 32 of the Lesson Plans.
Answer No. 2 is incorrect; if the mechanical vacuum pump is started during normal operation, vacuum will not be lost.
The lesson plan only states that the mechanical vacuum pump will i
j only pull vacuum to 23" hg.
An acceptable answer is to prevent detonable H2 concentrations in the system, and should be accepted for full credit.
See reference, LGP 1-1, page 17.
RESPONSE
1.
Comment partially accepted.
Will accept; The MVP only has i
a 1.75 minute holdup volume and discharges directly to the stack.
(0,5) This could cause a release to the j
environment.
(0.5) 2.
Comment accepted.
Answer key changed to accept; "The MVP i
should not be operated to prevent the buildup of detonable H2 and 02 concentrations in the MVP (1.0),
i j
COMMENT:
7.02 a.
The knowledge of specific components affected in bottom head region are not operationally significant.
It is important that the operator understand in general, terms that bottom head components and recirc system components t
I are subject to thermal shock when a cold, idle recirc loop i
is started.
Credit should be granted for a general, r
conceptual explanation of the idle loop thermal shock i
phenomenon and not for the key words as indicated on the i
answer key.
t
RESPONSE
Comment not accepted.
Technical Specifications state the specific components for each limit.
See reference, l
1 Technical Specifications, Page B 3/4 4-1.
l COMMENT:
7.03 Also accept statement as ADS being one of the methods -
this is the same as saying SRV's.
j
RESPONSE
Comment accepted.
Answer key l
changed.
i.
-._-_- _ ~ _ _ _ _ _ _ _ _
9 COMMENT:
7.04 a.
Full credit should be given for saying less than or equal to 20% of rated power, mode switch position should not be weighted as half credit of this answer.
b.
The following answers should also be acceptable for full credit.
(As part of the 4)
(1) Also initial the Rod Sequence package.
See reference, LAP-100-13, Attachment A.
(2) Verify the rod motion announced by the NSO is correct.
See reference, LGP 1-1, Page 10.
(3) Any words that indicate the second verifier is present at the panel and double checking the rod motions.
RESPONSE
a.
Comment partially accepted.
The LaSalle Technical Specifications state that conditions 1 and 2 and power less than 20% of rated thermal power for the RWM to be operable.
Answer key changed to accept conditions "1 and 2" vice " mode switch in startup on run."
b.
Comment partially accepted.
Will add "Second verifier to initial the rod sequence package" for response 6.
Response
- 4 states, " verbally verify the rod motion with the unit operator prior to any rod motion" which is the same as,
" verify the rod motion announced by the NSO is correct."
Alternate wording will be accepted.
Answer key changed.
COMMENT:
7.07 b.
Should accept the first part of this answer for full credit.
The H2 dilution is the major concern since a loss of SJAE's will cause a loss of vacuum anyway (without any backflow occurring.)
RESPONSE
Comment not accepted.
LaSalle LOP-0G-07, Page 3, Precaution #4 specifically states the information in the answer key and the question references the LOP precaution.
COMMENT:
7.08 Full credit should be given for the discussion that states; rapid condensing of the steam in the drywell could cause the negative design pressure to be exceeded.
Mention of the vacuum breakers should not be required for partial credit as indicated.
RESPONSE
Comment not accepted.
The capacity of the suppression pool and drywell vacuum breakers is the bases for the development of the Drywell Spray Initiation Pressure Limit.
If the vacuum breakers were designed for a higher capacity, then this would not be a problem.
Reference; General Electric, Emergency Operating Procedure Fundamentals.
10 COMMENT:
7.09 There is no way for the operator to monitor 2200 F cladding temperature.
The LGA's are written such that adequate core cooling is assured by either maintaining level above TAF (LGA-01) or by having spray cooling via HPCS/LPCS or using steam cooling as determined by the number of SRV's open and Rx pressure (LGA-04).
Any discussion that deals with the concepts of maintaining Reactor level above the fuel (by any means) or use of core spray systems should be adequate for full credit.
Additionally, FSAR Accident analyses indicate that 2/3 core height will maintain adequate core cooling.
RESPONSE
Comment accepted. The following will be accepted as an alternate answer; (all three for full credit):
(1) Water level above fuel (minimum 2/3 core height)
(2) Spray cooling with HPCS/LPCS (3) Steam cooling with know flow (Rx pressure and SRV's open)
(First correct response (0.18) others at 0.16 each)
COMMENT:
7.10 b.
Should also accept health physicist.
See reference, LaSalle LRP-1000-1, Page 33.
RESPONSE
Comment accepted.
Answer key changed to accept " Rad Chem.
Supervisor" or " Health Physicist."
1 6
COMMENT:
7.11 a.
Answer should accept either the 45% stated or 49 x 10 lbs. feedwater flow - both are stated in LOA-FW-01.
Please reference your copy of this procedure, b.
The discussion on LOA-FW-01 mentions 2 concerns - a reactor scram or entering the core instability region (see reference, LOA-FW-01).
During the exam review this particular statement in the procedure was investigated.
This is a recent revision to the procedure (March of 87) and is not clear.
The intent of this change was to point out, that during single loop operation a scram could be caused by a rapid reduction in Recirculation flow.
This becomes a problem in single loop, since Technical Specifications require the flow biased scram setpoint to be reduced by 5.3% to (.66W + 45.7%) T.
(In two loop operation this is not a problem and should be clarified in the procedure.)
The Training Staff will follow up on this procedure change to make it more accurately indicate the problem.
Credit should thus be given for either of the answers given in the Key (scram) or for stating the limit is based on staying out of the " Instability region" as defined in Technical Specifications.
11 i
c.
Full credit should be given for discussion of the core instability region and what could occur with LPRM oscillations being out of phase so that the APRM's do not sense the power oscillations.
The question is not clear that it is asking for why reduced flow could cause a scram.
If the examinee starts into the train of thought on part b of this question, that the examiner is questioning the instability region of reduced flow aspect, then it is logical he would continue this thought on part c.
This would result in a discussion on what the instability region is and why it is a problem.
RESPONSE
a.
Comment accepted.
Answer key changed to also accept "49 x 106 lbm/hr feedwater flow."
b.
Comment accepted.
Answer key changed to accept either
" Reactor scram" or " Core Flow Instabilities."
l c.
Comment accepted.
Answer key changed to accept correct response to part b.
General Response:
The training department commitment to more accurately indicate the problem as stated in part b will be added to the examination report.
COMMENT:
7.13 Should also accept a discussion that states; when placing a controller in MANUAL, conditions should be stable and under control, or when continued operation would worsen plant conditions.
Action should be taken after review and approval of the SR0 immediately available.
Also, accept a discussion on when a system is withdrawn from operation continued surveillance of the relevant parameters must be maintained by a licensed R0... until it is no longer needed as prescribed by Technical Specifications or the system can be restored to normal.
All of these areas are discussed in LAP-1600-2.
See pages 5 and 6 of LAP-1600-2 and the comments and resolution to this same question asked on a previous NRC exam of 6-3-86.
Enclosed are the question and answer key from this previous exam.
RESPONSE
Comment accepted.
Answer key changed to accept alternate l
wording consistent with LAP-1600-2, pages 5 and 6.
I COMMENT:
7.15 b.
Specific breakers should not have to be mentioned.
Full credit should be given for stating that the bus trips and the D/G picks up on the bus.
RESPONSE
Comment partially accepted.
Will accept alternate wording that indicates normal and alternate breakers are open.
Answer key changed.
12 COMMENT:
8.02 c.
Also, accept " scram the reactor", this is the same as mode switch to S/D.
Should not be required to say operate one loop of pool cooling for full credit.
Pool cooling was alreadyinitiatedigparta.ofthisquestionwhenpool temp went above 100 F.
RESPONSE
Comment accepted.
Answer key changed to accept alternate wording that is consistent with answer key.
COMMENT:
8.06 This question has a couple of problems.
First, the surveillance schedule is not something that the SR0 would figure out.
The surveillance program is a computer based program that automatically calculates due dates and critical dates based on the last date the surveillance was done.
The surveillance coordinator (Tech Staff) is responsible for setting dates on Tech Spec related surveillances.
Second, major credit should be given if the examinee discusses that quarterly means 92 days and the Tech Specs define compliance as 1.25 times the time interval and 3.25 times 3 consecutive surveillances.
The examinee may miss the exact date due to c math error and should not docked failing credit for not having the exact date.
In reality, these surveillance schedules are checked by numerous people, the facility does not rely on one individual for setting critical dates.
RESPONSE
The surveillance due dates and critical dates ar erequired knowledge per the KA catalog, "NUREG-1123." Comment partially accepted.
Answer key changed to accept alternate answers that indicate the candidate has an understanding of the quarterly time frame (92 days) and the limits of extension, 1.25 times normal, not to exceed 3.25 times 3 consecutive surveillances.
COMMENT:
8.12 b.
Full credit should be given for stating the Shift Engineer or SR0 immediately aveilable.
It is not necessary Tor the examinee to state "if not sufficient time to locate the SE" as stated in the answer key.
In reality, during this type of event either the Shift Engineer, SCRE or Shift Foreman will be in the control room and will be immediately consulted when conditions of this level of urgency arise.
See reference, LAP-1600-2, Page 5.
RESPONSE
Comment not accepted.
LaSalle LAP-1600-2, page 5, paragraph 2 discusses deviations from Technical Specifications.
LAP-1600-2, Page 5, Paragraph 3, discusses withdrawing systems from operation, not deviating from Technical Specifications.
Deviations from i
13 j
Technical Specifications requires approval of the Station Shift Engineer, or if not available, the available SRO.
Withdrawing operating equipment from operation only requires the SR0 immediately available.
COMMENT:
8.13 This answer should be changed.
See reference, LAP-1600-2, Page 4.
The procedure states that in reactor conditions 4 or 5, the SE can authorize more than one surveillance or tests on the same system if the system is not required to be operable.
Since none 07 the qualifying conditions are given, the question should be answered true to make it correct.
4 i
RESPONSE
Comment accepted.
As stated, the question can be True or False.
Question deleted from the examination.
Answer key j
changed.
COMMENT: 8.16 (2) and (3) Should also accept for one of these, the NSO.
l Although not specified in the Tech Specs, the NS0's at LaSalle are not fire brigade trained or considered part of the fire brigade.
RESPONSE
Comment not accepted.
The Technical Specifications are very clear as to who is intended to be required, SCRE and Shift Supervisor (SS), the position of SCRE or SS cannot be filled with an NSO.
i I
l 1
1 l
l
f U.
S.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_LASALLE_1p2_____________
REACTOR TYPE:
_@WR-GEg_________________
DATE ADMINISTERED: _@Zf93f29________________
z_F _______________
EXAMINER:
, CLARK 3
CANDIDATE:
INgIRgCIJOUS_IQ_CQNDJD9IE1 Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY V_ A_ L_ U E_ _ _ T O T A L_ _ _S_ C_ O_R E_ _ - _ _V_ A_ L_U_ E_ _ _ - _ - _ _ - _ _ - _ _ - _ _C_ A_ T E_ G_ O_ R_ Y _ _ _ _ _ _ _ _ _ _ _ - -
(
_E E ; a _ _ _M
________ 5.
THEORY OF NUCLEAR POWER PLANT
^
OPERATION, FLUIDS, AND THERMODYNAMICS p
JEEass-- _?Er??~ ___________
________ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND IN.STRUMENTATION 7
_2Ez99 _ _2Ef7I
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 2.20 2 ql
_Ef_SO-_ _E@IE9
________ O.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS
- hl
_?tT99__
Totals Final Grade
'l I
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
(
['4 f"->.., *d [
- 7
.. / ka t
5 i
t,
- t. is.
b L.
- 4 %
h # k..
1
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Dusing the administration of this examination the f ollowing rules apply:
1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil gnly to facilitate legible reproductions.
4 Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
i l
7.
Print your name in the upper right-hand corner.of the first page of each section of the answer sheet.
B.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne si de of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least thtee lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly u' sed in facility l i t eta t u,te.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
I
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE i
OUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examinet only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be done after the examination has been completed.
f
. y c.
v:'. '
1 y
,.r..
.. 3 1..
3
/
l }' ( f.. $ %/ I es (,g i
n
f 18, When you complete your ex ami nati on, you shall
~
a.
Assemble your examination as follows:
(1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
(3)
Answer pages including figures which are part of the answer.
b.
Turn in your copy of the ex ami n a t i on and all pages used to answer the examination questions.
c.
Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
d.
Leave the examination area, as defined by the examiter.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
d h, a/ o. C : ' a r :
CO'i&>"Y,/
A i s.n i
.sur g4u 1
J i
s.
i 1
l
G __ISEggy_g[_ NUCLE @B_EgWEB_EL9NI_gEEB9IlgN _ELUlgS,9Ng PAGE 2
z 1
ISEBMggyNgMICS
- 2. 5" QUESTION 5.01 0.^^'
Attached Figure epresents a transient that could occur at a BWR.
GIVEN:
(ik The Turbine Generator tripped at T=30 seconds (2)
No other operator actions occur 30 seconds
= 1 di vi si on (3)
Recorder speed
=
EXPLAIN the cause(s) of the f ollowing recorder indications:
g/
a.
Reactor Pressure INCREASE (Point A) ga.
.g_
n --+--
e+mm-r-
7orer---
(point n-c.
Recirc Loop A and B Flow DECREASE (Point C) d.
Reactor Water Level DECREASE (Point D) e.
Reactor Water Level INCREASE (Point E) f.
Reactor Jet Pump Flow INCREASE (Point F)
DUESTION 5.02 (1.50)
MATCH the appropriate Thermal Limit (a-c), to each FAILURE MECHANISM (F1-F3)
AND to each LIMITING CONDITION (L1-L3) given below:
a.
Linear Heat Generation Rate (LHGR)
- b. Average Planar Linear Heat Generdtion Rate (APLHGR) c.
Minimum Critical Power Ratio (MCPR)
FAILURE MECHANISM LIMITING CONDITION F1.
Clad melting caused by L1.
Coolant transition decay heat & stored heat boiling following a LOCA F2, Clad cracking from the surface L2.
Clad plastic strain becoming vapor " blanketed" less than 1%
F3.
Clad cracking caused by L3.
Maximum clad temp-high stress from pellet erature of 2200 deg F s
expansion
?
% Y0 k y
,.,r~..--.e.~
y p;.' %
S,
~
A ', Na
[ hy 4 LJ l
e i g f.o 11 %
- -
- 4., rg s
D
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE
- )
9t__IHEgBy_gE_ NUCLE @B_EgyEB_EL9NI_gEEB@l}gN2_ELUlgS _@NQ PAGE 3
1 IHESDggyN@DICS QUESTION 5.03 (1.00)
STATE for which condition the reactivity coefficient contribution would be MORE NEGATIVE.
EXPLAIN your choice.
1.
Moderator void coefficient for a 1% INCREASE in void fraction at 10% void fraction in the core,
-OR-2.
Moderator void coefficient for a 1% INCREASE in void fraction at 70% void fraction in the core.
2 OUESTION 5.04 (3.00) a.
After notching out a rod with the reactor critical, you notice a 100 second period.
HOW MUCH reactivity was added by the rod notch?
(ASSUME BOL, SHOW ALL CALCULATIONS) b.
After a reactor scram from power the shortest STABLE period possi bl e is -80 seconds.
EXPLAIN this statement.
c.
Is the INITIAL period IMMEDIATELY following the scram shorter than -80 seconds? EXPLAIN.
QUESTION 5.05 (2.00) a.
Define Net Positive Suction Head (NPSH).
b.
Opening the Recirc System Flow Control Val ve (FCV) will cause the available NPSH f or the Recirc Pumps to INCREASE, DECREASE or REMAIN THE SAME?
c.
The required NPSH f or the Recirc Pumps INCREASES, DECREASES, or REMAINS THE SAME, when the Recirc Pumps are shifted from slow speed j
(15 Hz) to fast speed (60 Hz)?
QUESTION 5.06 (1.25)
The THRESHOLD power below which Pellet Clad Interaction (PCI) failures do not occur is known to DECREASE with fuel burnup. STATE three (3) of the four (4) reasons for this decrease in the PCI thr e shol d.
- 3., m7 COPY f t a C %.
.; ; g-z,,.,,
- e
- i:
p,
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE
- )
_ - - ~
"z__IHEQBy_g[_NUC6E96_EgWE6_E6@yI_gPE5@llgNt_ELUlDS _@ND PAGE 4
t IHERdODyN8DICS le b QUESTION 5.07 1-1. C G,
1 During power operations, core critical power will a._________
as reactor pressure increases.
Two reasons this occurs, are the b._______
latent heat of vaporization in the moderator and the corresponding c.________ of the flux profile in the core.
(SELECT THE APPROPRIATE RESPONSES) a.
(INCREASE, DECREASE or REMAINS THE SAME) b.
(INCREASED, DECREASED) dese./,2
=
- C:
.==m OUESTION 5.08 (3.00)
The attached Figure 5.08 represents a transient.that could occur-at a BWR.
Given:
(1) Recirc Pump B Trips (2) No operator actions occur 1 division = 30 seconds (3) Recorder Speed
=
EXPLAIN the cause(s) of the following recorder indications:
a.
Reactor Water Level INCREASE (Point A) b.
Reactor Power DECREASE (Point B) c.
Jet Pump Flow DECREASE (Point C) d.
Reactor Pressure DECREASE (Point D) e.
Reactor Feedwater Flow DECREASE (Point E)
. Point F) f.
Reactor Steam Flow DECREASE
(
GUESTION 5.09 (2.00)
State how each of the below listed conditions will affect control rod worth.
(Limit the answer to INCREASE, DECREASE, or REMAINS THE SAME.)
a.
increasing moderator temperature b.
increasing the percent voids i
c.
increasing the fuel temperature d.
increasing core age l
,rs..
t~n %
%l z
y
- f. j, p.\\ b.
- ?
i,'a - a
)
i;y y w ai m' l
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE
- )
.. _.. _ - -.. - ~
Dz__IHEQBy_QE_ NUCLE 98_BgyEB_P6@NI_gPEB8I]QN1_E6Ulpgi_9NQ PAGE 5
IHEBygpyN@dlC@
I l
OUESTION 5.10 (1.00)
Concerning control rod worths during a reactor startup from 100% PEAK XENON versus a startup under XENON-FREE conditions, which statement is MOST correct?
a.
BOTH central and peripheral control rod worth will be LOWER regardless of core XENON conditions, b.
CENTRAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.
c.
BOTH central and peripheral control rod worth will be the SAME regardless of core Xenon conditions, d.
PERIPHERAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.
/.5-QUESTION 5.11
'2^^"
A reactor startup is in progress with bulk coolant temperature less than saturation temperature.
Excessive rod withdrawal causes reactor power to increase on a short period.
Indicate if the following statements, concerning the above transient, are TRUE or FALSE.
n-
+s-
-mac n-n w+ + h ar m.
n thn -mMorator t emp er a tur e
.cse.. lent (MTC) is less 4eyoi..c
- -d co 121 'r
- L r ? 2 t
'I d'O
+i -; i. O stent.
d b.
Fuel Temperature coefficient will be the s.econd coefficient that affects the above transient because fuel temperature is the first to increase, c.
MTC adds positive reactivity during this transient because the fuel time constant d el ays the temperature increase of the moderator, d.
The void coefficient will not add negative reactivity to the reactor during this transient until the bulk coolant temperature increases above the saturation temperature.
QUESTION 5.12 (1.00)
Explain why the operating limit Minimum Critical Power Ratio (MCPR) must be modified when the plant operates at less than 100% rated flow.
N..p T mU~- COPY v
u 3 y :q
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE
- )
5 __IHEgBy_Q[_NgC6E98_EgyEB_ELgNI_gEEggIlgN _[(glgS _@Ng PAGE 6
g t
IHEBDggyN@MICS i
QUESTION 5.13 (1.50)
Heat transfer is primarily done by three methods:
a.
Name them.
b.
Heat transfer from the fuel cladding to the Reactor Coolant, during normal conditions, is primarily done by (1) _________;
whereas, the heat transfer from the fuel to the cladding is done by (2) _________.
QUESTION 5.14 (1.25)
INDICATE if the below listed parameters will INCREASE, DECREASE or REMAIN THE SAME, if the facility experiences a " Jet Pump Riser Failure":
e.
Failed Jet Pump Flow.
b.
Core Dif f erenti al Pressure.
4 c.
Reactor (APRM) Power.
d.
Indicated Core Flow.
e.
Actual Core Flow.
i i
t I
i o,& cm COPY
~
4
(***** END OF CATEGORY 05
- )
a
,r_..-_,,,,,,-.-r_.
,,...,,,_....,..-4
6 __EL@NI_SySIEdp_gESJgN3_CgNI69Li_@Ng_JNSI6gdENI@IJgy PAGE 7
QUESTION 6.01 (1.00)
The main steam line restrictors are designed to prevent what event end during what accident conditions?
DUESTION 6.02 (1.00)
TRUE of FALSE?
A loss of power to Reactor Protective System (RPS) Bus A will initiate a start of both trains of the Standby Gas Treatment System (SEGTS),
but a loss of power to RPS Bus B will initiate a start of only one train of the SBGTS.
QUESTION 6.03 (1.00)
What are the bases for the minimum and maximum closing time of the Main Steam Isolation Valves?
(Limit your answer to the nuclear fuel considerations.)
1 MASTER COPY
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE
- )
PAGE 8
bz__P6@N1_gygIEdp_gEglgN _CgNIBg61_@yg_lyglBU[ENI@llgy 1
1 QUESTION 6.04 (2.00) j Unit 2 is operating at 100% rated thermal power, with recirc in i
Master Manual (f l ux automatic). An operator inadvertently INCREASES the " pressure set" on EHC by 5 psig.
i ASSUME:
1.
No further operator actions.
2.
All other EHC control settings are normal.
l 3.
Starting parameters.
i o
TCV's 100% Steam flow position.
o BPV's 0% Steam flow position.
a o
Power 100% rated thermal power.
o Pressure 1005 psig.
T NOTE:
FIGURE 26-3 IS ATTACHED FOR REFERENCE.
i
[
Which of the following (a,
b, c,
or'd) most accurately describes both the INITIAL RESPONSE and FINAL STATUS of the different i
parameters and components?
INITIAL RESPONSE a
b c
d o
TCV's CLOSE
('83*/.)
CLOSE ('83%)
CLOSE ('83%)
NO CHANGE i
o BPV's NO CHANGE OPEN (*17%)
NO CHANGE OPEN ('25%)
L o
POWER INCREASE NO CHANGE INCREASE DECREASE l
1 o
PRESSURE INCREASE NO CHANGE INCREASE DECREASE i
i FINAL STATUS
~"?;:
~i?:';.
~'
I o
POWER
'100%
'100%
>100%
<100%
i o
PRESSURE
>1005 PSIG
<1005 PSIG t
I i
i t
DUESTION 6.C5 (2.00) 4 Answer the following concerning the Automatic Depressurization System
)
(ADS).
a.
LIST the four (4) ADS initiating signals. (setpoints not required) b.
STATE the BASES for the length of the' time delay for ADS automatic initiation.
~*
t
.x,eu<
e, i
8 f
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE
- )
1
_ _, _ _ _.... -. - -.. ~, - - _ - _ _ _ -
t bz__PL@NI_gy@IEDS_QEglGN _CQN189L _9NQ_INSIBUDENI@IlgN PAGE 9
2 i
1 i
i l
DUESTION 6.06 (2.25)
The APRM scram function actually consists of TWO separate setpoints:
a.
Fill in the Blanks: (Assume Two Recirc. Loop Operation) i Flow Biased Scram (1) x W+
(2) _______%
i Fixed Neutron Flux-High (3) __________%
b.
LIST the component (s) and the sensing point (s) of the sensor (s) i
)
which measure the variable "W".
l c.
While operating at 100% power, one MSlV fails shut resulting in a brief
(*1 second) flux spike to 121% power.
State which of the two scram setpoints mentioned above (one or both) should initiate a reactor scram?
JUSTIFY your answer.
)
QUESTION 6.07 (3.00) 1 With regard to the Unit 2 RCIC System:
I a.
Which of the following is the only normally CLOSED valve in the
)
RCIC steam supply flow path in the STAND-BY lineup?
1 (1)
Steam Supply Valve (F045) i (2)
Outboard Steam Isolation Valve (FOOB)
(3)
Trip Throttle Valve l
1 (4)
Governor Valve l
]
b.
For each of the situations listed below, STATE whether final RCIC j
injection into the reactor would CONTINUE AUTOMATICALLY, REINITIATE j
AUTOMATICALLY, require CONTROL ROOM Operator Action, or require LOCAL j
Operator action.
Assume that RCIC had automatically initiated prior i
to any of the following situations.
l
}
(1)
The Test Pypass Valve to the CST (FO22) FAILS OPEN.
l l
(2)
A 125% Overspeed Trip is received due to low control oil i
pressure.
Control oil pressure is then returned to normal.
(3)
After decreasing to 50 psig, RCIC Steam Line Pressure increases to 150 psig, j
(4)
After increasing to > +60 inches, Reactor Vessel Water Level decreases to < -60 inches.
l M, AEra COPY
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE
- )
e __P(9NI_@y@IEMS_DEgigN1_CQNIBQL1_9ND_lNSIBUMENI911gN PAGE 10 1
~
(
DUESTIO g-. -g L:CT t'*
four (4) Diesel Generator shutdown signals that remain OPERABLE if the Ulm_rL Ls_ started by using the local Emergency
~
Start Pushbutton-NOTE: CONSIDER DIESEL GENERATOR 2A QUESTION 6.09 (2.00)
The MINIMUM injection time for the Standby Liquid Control System (SDLC) is fifty (50) minutes and the MAXIMUM injection time is one hundred twenty five (125) minutes.
- e. STATE the BASES for the MINIMUM SBLC injection time.
b.
STATE the BASES for the MAXIMUM SBLC injection time.
QUESTION 6.10 (1.00)
Concerning Reactor Vessel Level, indicate if the following statements cre TRUE or FALSE:
a.
At Level 4 (31.5") the Recirculation cyctem Flow Control valves runback to minimum position with two (2) turbine driven feed pumps in operation, b.
Level 5 (55.5") trips the turbines and isolates High Pressure Core Spray (HPCS) and Reactor Core Isolation Cooling (RCIC) to prevent the reactor vessel.
damage to the turbines and prevent hydroing, QUESTION 6.11 (1.00)
Concerning the 250 volt battery:
4 List two (2) of the three (3) times when an equalizing charge is required.
1 QUESTION 6.12 (1.50)
The Drywell Instrument Air supply (IN) devel ops a line leak in the containment. Due to the leak, containment pressure will INCREASE, DECREASE, or REMAIN THE SAME?
EXPLAIN your answer.
~\\{
[.,. n.
- yn f. '.
%g A. p....
t t~..
r
.n%
7 j 'j i ?
%4 g imu 14 4wff 8
(*****
CATEGORY 00 CONTINUED ON NEXT PAGE
- )
6 __P69N1_@y@IEU@_DE@lGNt_CQUIBO(t_@ND_lN@l8UDENI@llgN PAGE 11 t
l 4
i i
OUESTION 6.13 (1.00)
TRUE or FALSE?
- a. During refueling operations a ROD BLOCK will exist if the mode 4
switch is in STARTUP and the Service Platform Holst is LOADED.
j
- b. During refueling operations a ROD BLOCK will NOT exist if the mode l
)
switch is in REFUEL and the Service Platform Hoist is LOADED 1
4 OUESTION 6.14 (2.00)
EXPLAIN why the Mechanical Vacuum Pump (MVP) is not run with the mode switch in RUN.
TWO (2) reasons required for full credit.
1 QUESTION 6.15
(.75)
TRUE or FALSE?
)
With an ECCS initiation signal present, the "O"
Diesel Generator j
local shutdown pushbutton on panel ODGO3J is depressed. The "O" Diesel Generator will stop and the output breaker will open.
r J
i
)
e D
I J
t i
i i
\\
V.
A cm.. y.,.
i.
.f, /.
t -
>/ [
A.r1 U
- \\
1.
s 4
,1 l
m o
i
.3
? N" ( Q 4
l
(*****
END OF CATEGORY 06 *****)
ii I
.,a
It__EBggEDUSE@_;_NQ80@bt_@@ygBU@(t_EDESQENgy_@ND PAGE 12 BBDig6g@lg@L_QgNIBQL QUESTION 7.01 (1.00)
LOP-RR-04, " Recirculation System Operatons",
.autions the operator NOT TO SHUT the Reactor Recirculation Pumps' discharge and suction valves prior to SHUTTING the seal purge isolation valve.
STATE the basis for this caution.
QUESTION 7.02 (2.00)
LOP-RR-04, "Startup of the Reactor Recirculation Pumps" has two Rocirculation pump starting limitations which are listed below.
Explain WHY each of the limitations is necessary.
c.
The pump in an idle recircul ation loop shall not be started unless the temperature of the coolant within.the idle and operating recirc loop are within 50 degrees F of each other.
b.
If the temperature, of the water, in the lower head is more than 145 degrees F below vessel saturation temperature, the recirculation pump shall not be started.
QUESTION 7.03 (2.00)
LIST six (6) systems which may be used RAPIDLY DEPRESSURIZE the Reactor Pressure Vessel during
_. restoration.
lel GUESTION 7.04 (2.00)
In accordance with LGP 1-1,
" Unit Startup to Hot Standby", and Technical Specifications.
- c. When must the Rod Worth Minimizer (RWM) be OPERADLE?
b.
Procedure LGP l-1,
" Unit Startup to Hot Standby". requires a second technically qualified operator when the RWM is INOPERADLE.
LIST four (4) of the five (5) specific duties that the second verifier must perform.
QUESTION 7.05 (3.00)
Procedure LOA-RX-Ol, " Control Room Evacuation", lists THIRTEEN (13) immediate operator actions that should be performed prior to leaving the control room.
LIST S;A (6) of the operator immediate actions performed in the control room prior to evacuation.
/\\({
U
- ~./y. l& f. *., T I
,\\
.s t. ;'
~
g e-07 D Oh T 1 NUE D Off td x Y" NGk * * * *
- h., ' < <'
4
(*****
CATEGORY
Z:__E59CEQUBEg_;_NQ80@(1_@@Nggd@61_EDE69ENCY_@Np PAGE 13 609196991C@t_CQNIBQL QUESTION 7.06 (1.00)
What FOUR items are required to be logged in the Unit log when the reactor is declared CRITICAL, per LGP l-1,
" Unit Startup to Hot Standby".
QUESTION 7.07 (2.00)
A CAUTION in Procedure LOP-OG-07, "Startup of the Off Gas System",
otates:
Process gas should not be introduced into the Off Gas system until the IN62-F3OO A and B (2N62-F3OO A and D) Off Gas suction control switches are placed to the AUTO position.
- c. WHAT function is enabled by the Auto position?
b.
WHAT is the BASES for this precaution?
QUESTION 7.08 (2.00)
A LOCA has occured and a high temperature steam environment exists in the drywell. EXPLAIN why the drywell sprays must NOT be initiated if conteinment conditions exist such that the UNSAFE region of figure LGA-G3, Drywell Spray Initiation Pressure Limit", is entered.
Figure LGA-G3, "Drywell Spray Initiation Pressure Limit," is attached.
QUESTION 7.09
(.50)
Dafine ADEOUATE CORE COOLING, as used in the Emergency Procedures.
DUCSTION 7.10 (2.00)
According to the LaSalle Radiation Procedure. LRP-!OOO-1, " Radiation Pr ot ec t i on Standard", what MANACEMENT POSITION is the minimum level of authority that may grant an individual permission to exceed the following occupational dose limits.
c.
50 mrem / day whole body but less than 100 meem/ day, b.
100 mrem / day whole body but lesb than 1250 mr em/qtr.
c.
1250 mr em/ qtr but less than 5000 mrem /yr.
d.
5000 mrem /yr but less than 7000 mrem /yr.
j g?* U ~1 & A p
-[
p
',7 J
<\\
's I
j V (t /' 4 5.r [ 'd $ n b $
4 h
(*****
CATEGORY 07 EONT !'NUED ON NEXT PAGE
- )
2:__ESggEggSEg_;_NO@d@6t_@gNgSU961_EDEBgENgy,@Ng PAGE 14 69919L991C9L_CgNI696 QUESTION 7.11 (2.50)
One immediate action for Procedure LOA-FW-01, " Loss of Feed Water Hea t er (s) ", requires core flow be decreased approximately 5 x 10 E6 lbm/hr for each 10 degrees F decrease in feed water temperature.
The immediate action also states a minimum core flow limit.
a.
LIST the minimum core flow limit per LOA-FW-01.
b.
STATE what is prevented by maintaining core above the limit.
c.
EXPLAIN the reason for the minimum core flow limit.
QUESTION 7.12 (1.50)
A condition arises that requires entry into a HIGH RADIATION AREA.
The operator will receive an estimated whole body dose of 50 mrem.
You have the following data available Candidate 1
2 3
Age 27 38 24 Exposure Week 15 mrem 35 mrem 5 mrem Quarter 2954 mrem 1207 mrem 16 mrem Life 18000 mrem 45720 mrem 29995 mrem Remarks:
NRC Form 4 on file YES YES NO Authorized 5000 mrem /yr 1250 mrem /qtr 100 mrem / day Each candidate is technically competent and physically capable of
~
performing the task.
Emergency limits do not apply and time constraints do not permit authorization for an administrative exposure limit increase.
EXPLAIN the reasons for accepting or rejecting each candidate.
QUCSTION 7.13 (1.00)
According to Procedure LOA-GP, " General Precautions" WHAT precautions must be taken PRIOR TO placing an ECCG system in manual?
,f.. g.k /t, f., T F4 n D
.,I u..
7 k
4 f *j ha 0
g q.
(*****
CATEGORY 07 CONTINUCD ON NEXT PAGE
- )
PAGE 15 Iz__EBgggpuggS_:_NQQd@(3_gBNQSdg(1_gd[BQgNQY_gNQ BBD196991GBL_QQNISQL e
QUESTION 7.14
(.50)
TRUE or FALSE 7 During accident conditions when Drywell Pressure is greater than 63 psig, operability of Safety Relief Valves (SRVs) and Containment Vent and Purge Dampers (VD) cannot be assured.
QUESTION 7.15 (2.00)
Power is being supplied from the normal. source and 4 Kv Bus 141Y ennunciator A 314 " Degraded Voltage" alarm is received.
a.
What are the immediate actions per LOA-AP-09, "4 Kv ESS Bus Degraded Voltage"7 b.-
If a Loss of Coolant Accident (LOCA) signal were present when the degraded voltage alarm were received, WHAT would happen to the Bus 141Y feeder breakers?
1 i
1 i
i l
l l
l MASTER COPY
(***** END OF CATEGORY 07
- )
.PAGE 16 Et__09MINISIB@llyE_66gC[QU6ES _CQNQlliQNS,9NQ,(lM11@llgN@
z t
i l
QUESTION B.01 (1.00)
What is the basis for a more restrictive chloride limit f or the l
reactor c ool ant system during a reactor startup?
i DUESTION B.02 (1.50)
For the suppression chamber average water temperatures listed below, WHAT ACTIONS are required by the Technical Specifications with the unit in operational condition 1 or 2?
a.
100 degrees F
- b. 107 degrees F during RCIC testing j
c.
114 degrees F l
i 1
l OUESTION 8.03 (2.00)
I i
STATE which Emergency Classification is appropriate for the following I
definitions.
j a.
Events are in progress or have occurred which involve actual.
or potential substantial degradation of the level of safety of l
the plant.
b.
Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
j c.
Events are in progress or have occurred which involve j
actual or imminent substantial core degradation or melting with the potential for loss of contai nment' i ntegri ty.
+
i d.
Events are in progrpss or have occurred which i nvol ve j
an actual or likely major failure of plant functions needed j
for protection of the public.
a i
3 QUESTION 0.04 (1.50) 4 Unit 1 Technical Specifications define SHUTDOWN MARGIN as...
(
l
" Shutdown Margin shall be the amount of reac t i vi ty pould be j
by which the reactor is subcritical. or j
subcritical assuming all control rods fu\\.ly inserted except...."
l LIST the three conditions which complete the definition of t
),
4
[.,. (.*., T z e
,r j,g' { ["' ' i, *s,.,5 f.
i.u,a 3.
%d W '
I 1
(*****
CATEGORY OO CONTINUED ON NEXT PAGE
- )
4 5
Oz__0901012ISOIlyE_E60CEpuSE@z_CgNp]IlgN@z_@Np_Lidll@llgNg PAGE 17 QUESTION 8.05 (1.00)
TRUE or FALSE a.
Equipment may be tested with the Master Out-of Service card still hung. Only the Personnel Protection Card and the Out-of Service Cards must be removed.
b.
Equipment Out-of Service Procedure, " LAP-900-4,"
is used to place equipment out of ser vi c e that is at the LaSalle Station but under the jurisdiction of the load dispatcher.
QUESTION 8.06 (2.00)
A Technical Specification Quarterly surveillance was performed on the Unit 1 High Pressure Core Spray system on January 1, 1987, and h " f'i d ed "; " h li d Apri1 16 1987.
$s eHecA W h b I, d67 eJ e ckys b e.+,c <c U.w I,e967 (A w e i986 nu+ o. leef y ecw )
a.
WHAT is the last MONTH and DAV the next quarterly surveillance can be performed on?
b.
What is the consequence of failing to perform a surveillance in the specified time interval?
1997 Calendar attached.
QUESTION 8.07 (1.50)
In accordance with Technical Specification, Se.c t i on 6.2, and LaSalle Administrative procedure, LAP-620-4, " Temporary Procedure Changes",
temporary changes to procedures can be made if THREE conditions are met.
WHAT are the THREE conditions?
QUESTION O.00 (1.00)
Unit 1 Technical Specifications state that, "!RRADIATED FUEL shall not be handled in or above the reactor prior to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reactor shutdown." The reason for this is thats (Choose the MOST correct answer) c.
The minimum time it takes to setup for fuel handling.
b.
The time required decay heat to be below the specified level, c.
Technical Specification bases for fuel handling accidents.
d.
Must allow Xenon to decay for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
/
4.J
,i
,,p
(: t.m o
,s
.i /
s.
f s su
(*****
CATEGORY 00 CONTINUED ON NEXT PAGE
- )
9___0901NigI69IlyE_E69CEpuSE@g_CQNQlligN@2_9Np_LidlI@IlgN@
PAGE 18 QUESTION 8.09 (1.00)
LAP-900-12, " Caution Card Procedure", specifies five (5) personnel who can authorize clearance of a caution card if the requestor of the CAUTION CARD cannot be located and the card no longer has a valid function.
List THREE of these personnel.
QUESTION B.10
(.50)
TRUE or FALSE?
Station Quality Assurance personnel DO NOT require the Shift Engineers permission to enter the Control Room during abnormal operations.
QUESTION B.11 (2.50)
- e. What THREE
" State and Federal" agencies are always notified when a GSEP classified event occurs?
b.
How often are updates provided to these agencies.
$W QUESTION 8.12
)'
gua v-g, C rot S oudd
,Under certain circumstances it is reco n that operation
/
outside the Technical Specificatic ay be required.
In accordance with LAP-1600-2
'onduct of Op,e r a t i on s " :
1
- a. WHAT three (3) ations permit you to violate Technical Specifica
..s ?
b.
WHO approve this operation?
a OUESTION 8.13 TRUE or FALSE?
The Shift Engine i authorize more than one surveillance or test on same system to be conducted si mul taneousl y.
QUEGTION 8.14 (1.50)
A TEMPORARY SYSTEM CHANGC is required to be implemented on a weekend, what THREE conditionc must be met to comply with the mm,ges"
%p requirements of LAP-240-6, em orgry e
l y '.. -a.'.
- h.,f
$a
/. - I '. L *** x.* ':
I v,
(*****
CATEGORY 08 CONTINUED ON NEXT PAGE
- )
i i
PAGE 19 Br__0001NISIgellyE_PQQCEQUBES _CgNQlligNSg_@NQ_ Lid 11911QNS t
i l'
3 OUESTION 8.15 (1.00)
LAP-100-13
" Control Rod Sequence Review and Implementation," requires J
1 Unit 1 rod 10-47 to be inserted and disarmed when reactor power is less than 20% of Rated Thermal Power.
i a.
WHAT is the malfunction with rod 10-47 which requires the disarming?
j b.
In accordance with the Technical Specification Bases, why must rod 10-47 be inserted and disarmed when reactor power is less than 20%
j of Rated Thermal Power?
1
.;~.'
GUESTION 8.16 (2.00) 1 7
(Fill in the blanks)
A site Fire Brigade of at least (1) members shall be maintained j
onsite at all times.
The Fire Brigade shall not include the (2) end (3) _________ and (4) ________ other members of the operating crew, i
l QUESTION 8.17 (1.50) l j
State whether each of the following statements is TRUE or FALSE:
a.
When lifting leads or removing fuses as part of an equipment l
outage in accordance with the Equipment Out of Service Procedure i
(LAP-900-4),
a " Temporary System Change" must also be processed.
l b.
If a "Tempor ary System Change" is a part of an approved j
procedure which returns the system to normal upon completion, it is sufficient to " log out" the device.
c.
Leads lifted to meet Technical Specification Action Requirements need only the concurrence of two individuals holding active l
SRO licenses.
I i
4 I
l 1
i I
i j
i i
i i
l i
.f..
h Y
i y y u w wh 6 %.+ 9 e
(*****
END OF CATEGORY 00
- )
1
(*************
END OF EXAMINATION ***************)
I i
D __IUEQS!_QE_NyCLE96_EQWEB_EL@N1_QCEQ@IlgN _ELylDS _@ND PAGE 20 t
t T_ H_ E_ R_ M_ O_ D_ Y_ N_ A_M_ _I C_ S_
ANSWERS -- LASALLE 162
-87/04/20-CLARK, F.
i
/
.D ANSWER 5.01
)
a.
Pressure increase due to the Turb'ne renerator trip shutting the n-d m"
h"'*=-
'1 2--
'n Turbine Stop and Control Valves
. -:- c ; r
.~
ww.u ng tu
,ml.m.c
- ::: c ;; -
.t.
La-m Lsmom I; m.-x,7 de.J[h dv y,m g;.Q f.
m ne,-+,e eccee.,en 7ECIRC PUMP 344C% (0.5) r"*'
c.
Recirc Flow decrease due to "'"
"P d.
Reactor Water Level decrease due to pressure spike collapsing the
- voids in the core (
1 and water 4"
t
.m onnulus p w. o r s. -. - t -
2.'
'O.227 e
em--
- e. Reactor Water Level increasq due to the CRD Pump inj ctingjnto he Reactor Vessel.
(QAT)[OnlT) w et.
[s.ed W A. W l6W LO* 2I T
- f. Reactor Jet Pump flow increase due to steam being drawn off by t e
' ' ' c n e n.
(0.5)
SRV's lifting em'-'n; a=+_-
- ,mm..t.;-
t' REFERENCE LaSalle Requal Lesson Plan, Thermodynamics LaSalle Requal Lesson Plan, Reactor Physics LaSalle Requal Lesson Plan, Heat Transfer and Fluid Flow LaSalle License System Descriptions, Reactor Protective System, Main Turbine and Auxiliaries, EHC Electrical, Rx Feedwater, and Main Steam LaSalle Requal Lesson Plan, Thermal Hydraulics +
LaSalle LO4-TG-06 241000K101 241000K102 241000K103 241000K123
...(KA'S)
ANSWER 5.02 (1.50)
F1.
b F2.
c F3.
a L1.
c L2.
a L3.
b (0.25 each)
REFERENCC i
LaSalle Requal Lesson Plan, Thermal Hydraulics, Page 40.
20!Oo9 ell 2 293OO9K107 293OO9V100 293OO9K119 293OO9K120
...tkA'S) 1 j rh S WPf
, {,,.# 4 -
[
(ke{.3 h b
- d
5 __ISE98Y_9E_NgGLE@S_EQWEB_E68NI_gEEQ@IlgN _E6y1Q@t_@NQ PAGE 21 t
g IbEBU99YN@dlGQ
'. ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 5.03 (1.00) 2.
70% void fraction in the core (0.5)
There is a larger % change in water volume for the same increase in voids (3.45% vs 1.1 */. )
(0.5)
-OR-The voids produced at 70% VF have a larger effect on core reactivity since they are in an area of higher neutron flux. (0.5)
REFERENCE LaSalle Requal Lesson Plan, Reactor Theory, Pages 136-146.
292OO4K111
...(KA*S)
ANSWER 5.04 (3.00)
- c. T=B-p/
p p = B / (T + 1)
.1 4G4 set '.5:
Assume B = 0.0072 (BOL);;.
7 and
=
p = 0. 0072/ [ ( 100) (0.1 ) + 13 = 6.545 X 10 E-4 DK/KCO.93 (1.0 pts) 0.693/55.6 = 0.0125 sec-1 b.
= Ln 2/t1/2
=
1 / -0.0125
-00 sec.
T =
1/-
=
=
After the initial prompt drop, power cannot, decrease faster than the longest lived delayed neutron appears.
(1.0 pts)
(Calculation not required for full credit.)
%$ FAN c.
Yes,[0.53 the initial drop in power will em45 be due to prompt neutrons.CO.53 (and could be calculated by T = 1* / p)
^ - t r)
REFERENCE LaSalle Requal Lessen Plan, Reactor Theory, Pages92-110.
292OO3K108
...(KA*S)
At45WER 5.05 (2.00) a.
NP5H, the difference between the suction pressure and the pressure at which boiling for the existing temperature of the fluid entering the pump. (1.0) b.
Decrease (0,5) 0.5) c.
uw,. -.
.Z~e C, e f.o. $(.
.[
[. b l.. A (, t.x'
~
f, '.+*.. **. ~ ' ' '
.Ut__IUEQ8y_gE_NyCLESB_EQWEE E(@N1_QEEQ@llgNg_E(Qlg@t_gNQ PAGE 22 IUEQUQQyN@dlQS l
- ANSWERS -- LASALLE 162
-87/04/20-CLARK, F.
REFERENCE LaSalle Requal Lesson, Heat Transfer and Fluid Flow, Pages 64-75.
293OO6K103 293OO6K110
...(KA'S)
ANSWER 5.06 (1.25) 1.
Neutron embrittlement of the cladding.
2.
Thermally induced pellet growth.
ep 8/44 risaatng
-! ! : <; ::;er d
g,4/bJ M A l
3, 1-2ra mn+5nn ns
+u
}
4.
Fission Product (Chemical) embrittlement of the l
cladding (from Cd/I).
(3 @ O.42 each) i REFERENCE LoSalle Requal Lesson Plan, Core Thermal Hydraulics, Pages 41 and 42.
GE BWR ACAD. SERIES, MATERIAL SCIENCE, Chapter 5, Pages 21 - 26.
293OO9K131 293OO9K132 293OO9K135
...(KA'S) o ANSWER 5.07
(
)
a
- a. decrease (0.5) 04 (OgEg b.
decreased (0.5)
_j j
. -._i,
- u.,;
^
REFERENCE LcSalle Requal Lesson Plan, Core Thermal Hydraulics, Pages 29 and 30.
l 293OO9K124 293OO9K126
...(KA'S) a i
l l
l k
1 LA a.)
f f,
,...**'a'*"'"
l
- . i./ Q ! L.
1 i
a
S __IUEQQY Q[,Nyg(EQB_EQWE6_E69NI_QEEQ811QNt_E(Q1QQt,8NQ PAGE 23 t
IbEQQQQyN9digQ
. ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 5.00 (3.00)
DAMSO
- =
anni>>e
.T"'
-4 increased a.
Decreased Rectre Flow "MS-(Ce d voiding in the core causing backpressure.
reas s core voidino b.
Decrease in Recire Flow (0.25) which (1,np/LL
%((g7[Njf7 [N W
(0.25) adding negative reactivit [y g'
..L.
Recirc Pump B Tripped (6 2 :.. ~. ; r-1 -- -
.-.m c.
d.
Decreasing Reactor Power (0.5)
FWCS response go Decreasino Steam Flow (0.25) and increasing o.
level (O*'*5) t p lu. A c c. U T-ht To (.tv g*t TNcAE M,c ipe s,su.m e r es ea
- F8 S i AK, t.K EcsA+ter.r C.e As7 L-J5
.5 7M 1
f.
Reactor power decreasing causes less steem to be pro uced; (0.25) therefore, the EHC controls Reactor Pressure (with TCV's) (0.25)*
REFERENCE LaSalle Requal Lesson Plan, Thermodynamics LaSalle Requal Lesson Plan, Reactor Physics LaSal1e Requal Lesson P1an, Heat Transfer and Fluid F1ow LeSalle Requal Lesson Plan, Thermal Hydraulics 202OO2K301 202OO2K302 202OO2K304 202OO2K305 202OO2K306 4
...(hA'S) 1 ANSWER 5.09 (2.00) a.
Increase b.
Decrease
- T~>/6*D E* Alt M AA U W
/
ROO WCW ycgMb/
Wg RcArts c.
Rematns the Same d.
Decrease og
~
(4 & O.5 each)
REFERENCF LaSalle Depual Lesson Plan, Reactor Theory, Pages 176, 200-202.
292OO5VIO9
...(KA'S)
I i
l ANSLER 5.1O (l.00) d.
REFCRCNCC LaSalle Requal Lesson Plan, Reactor Theory, Page 220.
292OODklO9 (KA'S) i e,
s
,e t
.. ~
', m. -
I
PAGE 24 Dz__ISEQBy_QE_UyGLEQQ EQWEQ_E(ONI_QEEQQIlgyt_E(ylpgt_QUp IdEQUgg!NQUlQg ANSWERS -- LASALLE 162
-87/04/20-CLARK, F.
/. S ANSWER 5.11 C. 'O P 84.fG/2/
c.
T_
- n cs b. 4. we /~4 t g ( 0. 5 )
- c. False (0.5) 7'AUI (O.5) d.
: : 11 RCFERENCE i
LaSall e Requal Lesson Plan, Reactor Theory, Page 200 LoSalle Requal Lesson Plan, Reactor Theory, Pages 120-176 292OO4H102 292OO4K100 292OO4K114
...(KA'S)
ANSWER 5.12 (1.00)
To protect the fuel (core) from an inadvertant core flow increase (0.5) such that the safety limit MCPR requirement is not exce ed. I'MSI me M habh 44 T I
w %'if 40 N
(0.5).
3p
-3 oc.c
,b*dk W IIE Pvt.
WC#A. M 6 a..m
- m e.
- M REFERENCE T' Y '#' "
- 4h
- * ~ ^
O '"'
LaSalle Technical Specifications, Page D 3/4 2-5.
LcSalle Requal Lesson Plan, Thermal Hydraulics, Pages 35-37.
l 29;OO9K127
...(KA'S)
ANSWER 5.13 (1.50) j c.
Conduction Convection Radiation j
(first correct answer O.34, others 0.33) b.
(1) Convection (0.25)
]
(2) Conduction (0.25)
REFERCNCE J
LaSalle Requal Lesson Pl<in, Heat Transfer and Fluid Flow, Pages 76-70.
293OO7N101
...(KA'G) j 1
1
- s.v o.) s u,. a u as w a
L.- IdE96Y-QE UWGLE06_E9 WEB _ELOUI'-QEEB0IlQUt_ELUIDSm._00Q PAGE 25 ISESD9910001GS
- ANSWERS -- LASALLE IL2
-87/04/20-CLARK, F.
ANSWER 5.14 (1.25) 6.
Decrease OA.3'AleAfht(Z5 C A Albf D M Yg? Sf*AM a NLLY D3% At4%,
. Tera 4,ees) e b.
Decrease c.
Decrease d.
Increase o.
Decrease (5 0 0.25 each) i REFERENCE l
LaSalle License System Description, Chapter 2.
20200!K301 202OO1K303 202OO1K601
...(KA'S) t 0
i t
i d
/ ',,
4 t,
As w.
,s
+,
)
tt__EL991_SYSIEdS_gEgight_CQNI69Lt_969_ldSlQydE@l@llQG PAGE 26 ANSWCRS -- LASALLC 1&2
-07/04/20-CLARK, I.
j ANSWER 6.01 (1.00) t_be mn+1no the* reactor veuel water level fenm 'nitinn h=1~
the 7g
- ;;;;; g gg tn-mt
+ne c r r r,
,;;,, ;, e ny igne r,
4 r.
t.'=
ne'er-ernt_.--;
- 0 ??, Mfgr th; c.-
s t e a m,
- 12.,a
.;simi an ul : ; cic c
.?':
4 Im s'h d oM D/p,foss op gg d4 and d so c4 A/T 3
))
/NVfN79 Aj/ (d.$) fell.cs.,I /A% /4 2 71r*AM : : 2 l/ W
\\
RCFCRCNCC 6stfM Curs spg demis+sa.s4fM7 (do$
LaSalle License System Description, Chapter.P; Page 19 28 239001M404
...(VA'S) i ANSWER 6.02 (1.00)
Falso t
REFERENCE LaSalle License System Description, Chapter 49.
I 261000K601
...(KA'S)
ANSWER 6.03 (1.00) ensures the pressure r i se wi thin the reactor will not cause Min
=
a significant increase in fuel cladding temperatures.
(Limit power increases due to pressure s tke.)
(0.5) e /f.
.It.c AJ #dou M 70.!"5 sty,eL4est.tV 7%CM
- 6 s !G d A th 4 u ot s' o e
Nor 6.wC Efed'a fucL YESS L L.s C TC~~)
is pro (tected against I ss o/ cooling assures the fuel barrier Max =
q if the M51V closure takes the man. time (i.e.,
the steaming rate greater than the feed rate and could uncover core). (0.5)
- gggy r' w e W y'v j, "* fe.t 5)
- a s
~ Dst /SM& Odd A*f do'mit /ttlust en AgM rs/t f~oo gw*~6mouss' A*Ss *M u,
- rorCo.er) sAMset isinerectro o
u,,,, s a-ne a.cs s e es n".ecoes e. **.r v nerencNCc l
LaSalle License Syt.tum Det.cr i p t i on. Chapter A Page 21 geffg yg.iklj gg 22900lr407
.. 0:A'S) 4 i
ANSWCn 6.04 (2.00)
I a
RErtntNCE LaSalle License System testription. Chapter 26, PAGCS 13-16 and i
r6we 26-7.
24 SOL.)OA39D 245000t100
...IkA'S)
.DV l
sv k
t p.; ; / 3.,,J: ; u,o t i
PAGE 27 bz__EL9NJ_Sy@Igdg_pESJGN _CQNI@g62,9NQ_JNSJ@gdgNI@IJQ@
1 ANSWCRS -- LASALLE 162
-87/04/20-CLARK, F.
ANSWER 6.05 (2.00)
O!b E
)
- a. Reactor Vessel low l evel (level 1,
-129")
High Drywel1 pressure (1.69 psig)
[ MOF MU Confirmatory low low vessel level (level 3,
12.5")
Low pressure core cooling pump di scharge pressur e (RHR 119 psig, LPCS 146 psig)
(4 & O.25 each)
- b. Time set long enough to ensure HPCS has had enough time to operate
( 0. 5 ) and not so long that the LPC1/LPCS would be unable to cool the core (0.5)
REFERCNCE LeSalle License System Description, Chapter 37 Page 6.
210000k403 210000K501
...(KA'S)
ANSWER 6.06 (2.25) c.
1.
0.66 (0.25) 2.
S M'.
(0.25) 3.
110%
(0.25) b.
Recirculation loop flow transmitters.
(0.5) c.
110% fixed scram (0.5).
This is because the flow biased scram incorporates a time delay into its actuation
('6 seconds) reprosentative of the fuel thermal time constant.
(0.5)
REFERCNCE LaSalle License System Description, Chapter 14, APRM, pgs.
5, 16, 53 215005E109 215005K402 215005k407
...(KA'S)
ANSWER 6.07 (3.00) a.
(1)
(1.0) b.
(1)
(Continue) AUTOMATICALLY (2)
LOCAL Operator Action (2)
CONTROL ROOM Oper ator A t;cn (4)
(Reinitiates AUlOMATICALLY (4 & O.5 cath)
REFERCUCE LaSalle Licenne System Description, Chapter 41 2170004701 217000A401 217000A407
...(KA'S)
,1*
g p.
. ~~ - m W
.,, /'
3 e
! l ;,,'
v(
L i.. b..
a.a f N.'..
k I-
6 __E6eNI_gy@lEDS_QEglgyt_CgglggLt,@Ng,1NgI59dEUISIlgN PAGE 20 t
1 ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
i
?
4 i
l ANSWER (1
j l
1)
Engine Overspeed i
2) rgency Sto ushbutton i
3)
Engi Failure 4)
D ren Current Lockout j
w 0.5 each) i j
REFERENCE i
LaSalle License System Description, Chapter 47.
j 264000K401 264000K407
...(KA'S) i i
i 4
ANSWER 6.09 (2.00) e.
Too rapid an injection results in improper mixing (0.5) and reactivity " chugging" (reactor power oscilliations). (0.5)
J b.
Fast enough to overcome the reactivi ty due to the cooldown following a xenon peak. (1.0) i j
REFERENCE LaSalle License System Description, Chapter 10, Page 10.
l 211000G010 211000K502 211000K503
...(KA'S) i l
ANSWER 6.10 (1.00) i i
a.
False (0.5) b.
True (0.5)
{
REFERENCE LaSalle License System Description, Chapter 3.
216000K104 216000h110 216000K113 216000K'16
...(KA'S)
ANSWER 6.11 (1.00)
,i 1.
Guarterly
~
2.
When the individual cell voltage is below its limit.
i 3.
When large discharges have been made.
fany 2 O O.5 each)
REFERENCE i
LaSalle License System Description, Chapter 43, Pages 7 and O.
263OOOA101 263OOOG010
...(KA'S)
_ ', a, !.
a e
..a -
% w. t s
b.__PL@UI_SYSIEUS_DEg1 gut _CQUlBg6t_@ND_lNglBydEgl@llOU PAGE 29 ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 6.12 (1.50)
Containment pressure will remain the same. (0.5)
The drywell instrument air systems suction is from the containment; (0.5) therefore, any leak from the system inside containment will not change containment pressure.
(0. 5) gg(, AC REFERENCE
/
8SM ME c"
fM LaSalle License System Description, Chapter 60, Page 21.
223OOlK118 (hA'S)
ANSWER 6.13 (1.00) 1 a.
True (0.5) b.
False (0,5)
REFERENCE LaSalle License System Description, Chapter 67, Page 25.
- g ha/d 201002K402 (KA'S)
(
h6 a I'
W AerpY.pWW.No(U-o s ~(% h Rf
(.o A, F ANSWER 6.14 (2.00)
No 1.
The MVP bypasses the off gas filters and discharges directly to the stack (0.5)
This could cause a release to the environment (0.5).
- . 5 :-
ML :
a,- - rnnHnnene
..,c iw can maintaan as L.,
i.,1 e-
. R v. a, 6 '- o(' gfg y $ D4 &, ck
.= :
.7 %nsor
.. saasu a
.w u'- -the M ve sk. dw not st gp # (D.53 % 4 (>MQs bia.id V of dd W Q (C b
REFERENCE LaSalle License Eystem Description, Chapter 32, Page 28 ggp had1 OMS 6
2 271000k101 271000K102 271000K110
...(KA'S)
- c. I hI* $. A
-LGf H g pWt* (o5 ANSWER 6.15
(.75)
False REFERENCE LaSal1o LOP-DG-09, Pages 4 and 5.
LaSalle License System Description, Chapter 47 264000E101 264000k402
...(KA'S) 0 1
J /. #,4b, {) l,Y* y p,"$ j Di[
t
-3
_4 c
m 2-
.-s..
PAGE 30 Zr__E599EggggS_;_UQBM8(g_8BNQ509Lg_EMESGgEgy,@Np 60919LQGig@L_gQN16g(
- ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
s i
i ANSWER 7.01 (1.00) 1 To prevent hydroing the Recirculation Pump and piping to CRD System pressure. (1.0)
REFERENCE LOP-RR-04, Page 3.
LaSalle License System Description, Chapter 5.
202000G001 202OO1K404 202OO1K405
...(KA'S) 1 ANSWER 7.02 (2.00) a.
Prevents undue stress on the vessel nozzles (0.34), bottom head 2
regi on (0.33) and recirc loops and pumps. (0.33)
- b. Limits undue stress on the vessel. (1.0)
REFERENCE Unit 1 Technical Specifications, Page B3/4 4-1.
202OO1K103 202OO1K117 202OO1K410
...(KA'S)
ANSWER 7.03 (2.00)
(Any six of the f ollowing, first 2 correct O. 3,4 each, others 0.33 each.)
1.
Main Turbine Bypass valves 2.
RCIC 3.
NHR (steam condensing mode)-
4.
Turbine Driven Reactor Feed Pumps 6.
Rad Waste Boiler 7.
Offgas preheaters B.
Gland Seal Steam Reboiler 9.
Main Condenser Deaerating Steam
- 10. Main Steam line drains
- 11. RPV head vent
- 12. SRVs ad. A05 REFERENCE LaSalle, LGA-04, Level Restoration Procedure.
295031E301 295031E302
.(KA'S) b.k
!I.
h'
Zs__BBOCEDUBES_;,0QSU@bz_@@N960@L't_EdgGGENC1_ANp PAGE 31
)
8891969GICe6_C9NIBQ6 ANSWERS -- LASALLE IL2
-87/04/20-CLARK, F.
ANSWER 7.04 (2.00) g I
- a. Whenever the reactor is in the b7ARTUP or RUN mode (0.25) and less than or equal to 20% of rated power (0.25).
b.
1.
Have no other duties 2.
Be present during all rod movement 3.
Check that the current sequence is correct prior to any further rod movement.
4 Verbally verify the rod motion with the unit operator prior to any rod motion.
5.
Must make a log entry into the unit operating log stating the rod pattern is verified.
(4 & O.375 each)
(
m g y gg Rop SteusessC ~PA LK Aff
[ NOM
- M8M REFERENCE LaSalle LGP 1-1 and Technical Specification, Page 3/4 1-6.
201000 GOO 1 201000 GOO 5
...(KA'S)
ANSWER 7.05 (3.00) 1.
Announce control room evacuation and why.
2.
Manually scram the reactor.
3.,
Place the mode switch in shutdown.
4.
Verify that power is decreasing and that all control rods are inserted.
5.
Start the Motor Suction and Turning Gear oil Pumps 6.
Trip the Main Turbine.
7.
Trip the retirc pumps.
8.
Stop reject of reactor cool ant if in progress.
9.
Confirm no LOCA indications.
- 10. Verify Bus 141Y (241Y) and 142Y (242Y) are energized.
- 12. Verify Bus 143 energized.
- 13. Place the HPCS diesel select switch in the local position.
(6 required at 0.5 each)
REFERENCE LaSalle Procedure LDA-RX-01.
295000G010
...(KA*S) fx P T [
W%
}gp.g e L,D 4pTC t
i E
j s\\
v %# t
?s__EBgCEggBES_;_Ng@d@(t_@@NQBd@(t_EDEB@ENCy_9NQ PAGE 32 BB9196991C@6_CgNIBg(
ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 7.06 (1.00) 1.
Time 2.
Rod Position 3.
Coolant temperature 4.
Reactor period (4 @ O.25 each)
(Will accept; time Rad / Chem notified -or person in Rad / Chem notified)
REFERENCE LcSalle LGP l-1, Page 14 201000G001 201000G010
...(KA'S)
ANSWER 7.07 (2.00) r a.
The auto position enables a trip of the suction valves on low second stage SJAE steam flow. (1.0) b.
This prevents hydrogen from entering the Off Gas system without i
adequate dilution flow (0.5) and prevents a loss of condenser vacuum from reverse flow, should the SJ AE be l ost. (0.5)
REFERENCE 4-LaSal l e LOP-OG-07, kSLje.
j 271000K301 271000K404
...(KA*S)
ANSWER 7.08 (2.00)
Spray initiation above this limit may result in a containment depressurization rate which exceeds the relief capacity of the suppression pool to drywell vacuum breakers.
(1.0) As a result, the containment negative design pressure may be exceeded, leading to containment failure. (1.0)
REFERENCE General Electric EPG - Emergency Operating Procedure Fundamentals.
205000 GOO!
275000 GOO 7
...(VA'S) i.Q t y%) q LA A p C **** 'L.e%.
f
~'"
A e-g
't a
i w
,v.
7 __P69gEgySES_;_Nggd@(z_@@Ng60@(t_EDEEGENCY_@Ng PAGE 33 6891969GIC86_CgNIBg6
. ANSWERS -- LAGALLE IL2
-87/04/20-CLARK, F.
b (egs.\\ AbestM (min 2/ d,<cSa.
3 gA A s e* q coot.q m % t Pe.s./ g pc.5 g g}.% a.or.3 e A k W ia Floc C A P u u ( S M dt* M
[ f.Itsr e.md <=sps< e.tg, o%ws, o.(L eacl)
ANSWER 7.09
(.50)
Heat removal from
+he rc; t e.
au i i s u i m,L Lv r estor e ana maintain the pri ' u r! M ;;m...g i-ew u tur e cetow avv vegr ees r W.DJ.
REFERENCE General Electric EPG - Emergency Operating Procedure Fundamentals.
295031K101
...(KA'S)
ANSWER 7.10 (2.00) a..The individual's supervisorNM 7h E[d #d /'Ip b.
Rad-Chem Supervisor 0 4-c.
Administrative and Support Services Asst. Superindendent (Administrative Superintendent) d.
Station Superintendent (P1 ant Manager)
REFERENCE LaSalle LRP-1000-1 294001K103
...(KA*S)
ANSWER 7.11 (2.50)
- 4. Ib w FO W
- a. Limit of 457. of rated core flow. [O.53 04 h
p
- b. The 457. of rated flow limit is to avoid a reactor scram. [O.53 4 gb.WI' c.
Rapid flow biased setpoint decreases and/or core flow instability (0.5) plus the APRM signal input to the thermal power monitor being time displayed, (0.5) reduces the margin to APRM scrams during core flow reductions.
(O.D)
REFERENCE LaSalle LOA-FW-01.
215005K407
...(KA'S) f 7
.t.,. i...g A P T- @
t h,$,.
a w
. A n,J 2
- .v u e y
^
7..__ESQCEQgBES_;_NOBd@(t_8BNO$d@(t_EDEBQENCy_@NQ PAGE 34 60919L991C66_CQNIBQ(
. ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 7.12 (1.50)
Candidate #1 - Reject, would exceed the 10 CFR 20 quarterly limit Candidate #2 - Rej ect, would exceed the admi ni str ati ve quarterly limit Candidate #3 - Accepted, even though 5(N-18) exceeded the limit only applies if going to 3000 mrem /qtr. Candidate will not exceed any admin or 10 CFR 20 limi ts.
REFERENCE LaSalle LRP-1000-1 10 CFR 20 294001K103
...(KA'S)
ANSWER 7.13 (1.00)
Do not secure or place an ECCS in manual mode unless, by at least two independent indications, (0.5) 1.
Mi sop er at i on in the AUTOMATIC Mode is confirmed.
(0.25) 2.
Adequate core cooling is assured.
(0.25)
$ g.~fgtf.Q T'E yJO(Lt>idCo. 0,b N$ s S76 AT* O W
- l. Y REFERENCE 401gg LGA-GP, page 2.
203OOOK1 209001K1 209002K1
...(KA'S)
ANSWER 7.14
(.50)
True.
REFERENCE LaSalle LOA-VP-03, Page 4 223OO1K10
...(KA*S) f)in%[
!. A / CTCO
!> i 3
i e.
=
. _. ~.
PAGE 35 Z __P6QQEQUBES_ _UQBd@6t_@@NQBd@bt_EdESQENQY_@ND 60919LQQ1G66_G901BQL ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 7.15 (2.00) a.
1.
Check system voltage not degraded [#A 2.
If degraded voltage not due to low system voltage, shed non-essential loads.
3.
If the degraded voltage condition cannot be corrected (within five minutes) refer to procedure for Loss of 4 Kv ESS Bus (LOA-AP-03).
(First correct response O.34, others O.33 each) b.
Bus 141Y Normal and Alternate feeder breakers immediately open (0.5) and the emergency diesel feeder breaker closes (0.5).
REFERENCE klQggg pg4 gg ggg LaSalle LOA-AP-09 N
262OOOGO10 262OO1K406
...(KA'S)
MC_
g. @ gg.6s1*E W E. T u gypkBLS-p i
M.cA.g# rFP COP h
~r v
..r
B:__09DINigIB@IlyE_PBgCEQUBEg2_CQNQlligNg2_@NQ_L]DlI@IlgN@
PAGE 36 ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER 8.01 (1.00)
The dissolved oxygen content of the reactor coolant may be higher than during normal power operations (0.5). This increases the influence of oxygen on potential chloride stress corrosion cracking (0.5).
REFERENCE LaSalle License System Description, Chapter 9,
Page 38.
LaSalle Technical Specifications, Section B 3/4 4.4, Page B 3/4 4-2 205000GOlO
...(KA*S)
ANSWER 8.02 (1.50) a.
Initiate suppression pool cooling or restore the average temperature to less than 100 degrees F (0.5) (If temperature cannot be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be in hot shutdown in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> - not required for full credit.)
b.
Stop RCIC testing (0.25) and initiate cooling or restore temperature to less than 100 degrees F.
(0.25).
c.
Place the mode switch in shutdown (0.25) and operate at least one RHR loop in the suppression pool cooling mode (0.25).
REFERENCE
[l-M A/J4 %
W 6fL) [vks- %(5-TEA 37 40 [M tMSN g Unit 1 Technical Specifications, Page 3/4 6-16.
MCT
/g%
223000G005
...(KA'5)
ANSWER B.03 (2.00) a.
Alert b.
(Notification of) Unusual Event c.
General Emergency d.
Site Area Emergency (4 0 0.5 each)
REFERENCE LaSalle L2P-12OO-1.
295000 GOO 2
...(K4'C) l h f." Yyf
- e m/'
k.\\
N f:- f
- [y e/. u, b u'
- '
o m. e e
-)
B___0901NIS16@llyE_PBQCEQUBES _CQhQlligNS _@NQ_(lg11911gNS PAGE 37 t
t
' ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER B.04 (1.50)
(1)
Highest worth rod (0.25) fully withdrawn (0.25)
(2)
Xenon free (0.5)
(3)
Cold (68 deg F)
(0.5)
REFERENCE LaSalle Unit 1 Technical Specifications, Page 1-6.
292OO2K110
...(KA'S)
ANSWER B.05 (1.00)
False (0.5)
False (0.5)
REFERENCE 1Ngg-LaSalle LAP-900-4 N
/*[//
294001K102
...(KA'5)
ANSWER B.06 (2.00) 4>
-7^ 'j U rli b j%
h [v9 a.
rtr + n s - -
I" (1.0) b.
Failure to meet the time interval for a surveillance constitutes g W
,j a failure to meet the operability requirement of the LCO. (1.0) kc[
r REFERENCE LaSalle Unit Technical Specifications, Page 3/4 0-2 206000 GOO 5
...(KA'S)
ANSWER B.07 (1.50) 1 - Intent of the original procedure is not changed. (0.5) 2 - One of the required SRO signatures must be the Shift Supervisor licensed on the affected unit.
(0.5) 3 - Must be reviewed by the Station Manager within 14 days (0,5)
REFERENCE LaSalle Technical Specifications, Section 6.2 LaSalle LAP-820-4 218000G001
...(KA'S) t h
f S
d Di
[ I;,
- y.. '
h r*ef Q
$ (#
kw b b 4
0 __090lNISIB@llyE_P69CEQUBE@t_CgNQlligN@i_@NQ,Ligi1@llgNS-PAGE 38 ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
ANSWER B.08 (1.00) a C.
REFERENCE LaSalle Technical Specifications, Page B 3/4 9-1 234000 GOO 1 234000 GOO 5
...(KA'S) i ANSWER B.09 (1.00)
Requestor's Immedi ate Supervi sor Requestor's Department Supervisor Shift Engineer 4
Operating Engineer Production Superintendent (Any three @.33 each)'
REFERENCE LaSalle LAP-900-12 294001K102
...(KA'S)
ANSWER 8.10
(.50)
TRUE REFERENCE LaSal l e LAP-1100-12 294001K105
...(KA'S)
ANSWER 8.11 (2.50) 4 a.
Illinois Emerg. Services and Disaster Agency (ESDA)
Illinois Dept. of Nuclear Safety (DNS)
Nuclear Regulatory Commi ssion 1
(3-0 0.5 each) b.
When conditions / classification of the. event change (0.5) i
.or at least every hour (0.5)
REFERENCE LaSal l e LZP-1110-1 295000G002
...(KA'S) e C' V'
- . i
., c ;,
g, i%
- 7. ( '.Q %gy y is. k
- ~
3 5 *-
1 i
->-,w Sz__eDd1N1QIB@IlyE_PBQQEQQBEQt_QQNQlligNQt_6NQ_LidlI@IlQNQ PAGE 39 ANSWERS -- LASALLE IL2
-87/04/20-CLARK, F.
ANSWER 8.12 (2.00) a.
1.
Prevent injury to the public or company personnel.
(0.5) 2.
Prevent releases off-site above tech spec limits.
(0.5) 3.
Prevent damage to equipment, (0.25) if damage could adversely effect public health and safety.
(0.25) b.
Station Shift Engineer (0.5)
(will accept SRO if candidate states that there is NOT sufficient time to locate the Station Shift Engineer)
REFERENCE LaSalle LAP-1600-2, Page 5 29400lK116
...(KA*S)
ANSWER f'.
007 h
re' __
s..;;-
REFERENCE LaSalle LAP-1600-2, Page 3 201000G001
...(KA*S)
ANSWER 8.14 (1.50) 1 - Safety evaluation completed and reviewed by two SRO's, (0.25) one of which must have an engineering degree or equivalent. (0.25) 2 - Change must be authorized by the Shift Engineer (0.5) 3 - Onsite review should be conducted promptly following the change. (normally the next day)
(0.5)
REFERENCE LaSalle LAP-240-6, Page 3 223OOOGOO1
...(KA'S) f.L,.. p\\/
A C J %.
i
' '# t ; ~
ve :. o y
---r
8:__e90161516611yE_PBQCEQUBE@t_CQNQlllQN@t_@NQ_Lldll@IlgNE PAGE 40 ANSWERS -- LASALLE 1&2
-87/04/20-CLARK, F.
i e
r ANSWER 8.15 (1.00) i a.
Rod 10-47 for Unit 1,
rod blade to drive coupling could not be proven by the surveillance.
(0.5) b.
To comply with the Technical Specification for a rod drop i
accident.
(0.5)
REFERENCE LAP-100-13, " Control Rod Sequence Review and Implementation" Technical Specification Bases 201003A202 201003K401 201003K402
..(KA'S)
ANSWER 8.16 (2.00) 1.
5 2.
Shift Supervisor 3.
Shift Control Room Engineer (SCRE) 4.
Two (2)
(4 at 0.5 pts each) 3 REFERENCE LaSalle Technical Speci f i cati ons
[
294001K116
...(KA'S)
ANSWER 8.17 (1.50) a.
False b.
True c.
True (3 @ O.5 pts each)
I REFERENCE LaSalle LAP-240-6 i
294001K102
...(KA'S) 1 f
a I
A i
3-c -- i,
7y
--r s-
-,.r--wr
,,wm-.
==
y----
--m--se, r
---,--w,-,w-+,-
,.l i' ' ;"i'
)
D t
n
.i j
~
o
)
I P
3 E
m
(
/
t n
io
_N P
(
/
'[
\\
r L
,).
r T
)
g
\\
\\
-;ig w
s 6e e
m s
a u
s s
a s
' (
s s
a n
u e
s
. / '-
m W;
m i11 s
u n
n a
e 7-F1 s
m u
T' 1
i w
m y,
i a
s.
r m_
=.
s e
s u.
..'e r
e e
m-L Y
m
~
.N
(%d
+
1
'w
(
p"
,h N/
g f '. /
s 4
s s
m n
u u
e n
a e
s nn n N'
)
e e
A f
pI s
sn a
W a
e t
j4 m
m n
Z io n
.e _
P
_- m --
=
=
=
r
=
=
. e r
=
=
s e
e
(
1 B
eg
=
a B
P A
V.
Ct 1
Fo 0
l
=F 5
Ae E
a v
R ss Vi U
e Cr
~
G s
FD s
I i
e n
F sa cc L
rr iicc ee
. - r 2
r 6
RR 1
l 1
- 1 1
j!;
- j ;
,lll11
- l1ij.
i
,i l;
,i j ; i$ j1;1!i j 1<
j,3
!!iii:i1
u a!*
ii,'
,f 1
,i[
- i
[;
l ill jt!ll, i,
)
C t
n.
ioP"
(
<, '}
2 e
.q.
g.
u s
M s
s e
o s
s
- f e
u s
s s
i e
n o
e e
a rv r
c e
l c
e s
a ss c
n d
a e
\\
c L1 c
s
, k s
a a
s g.
e
=
^
s e
s e
e g
r
_'e a
s a
a s
g
_ s
- .g s
r\\
)
- 7 F
m
/
f I
/j tn d' g T
i n
\\
o y y 9
P
)
['i
(
j was e
e c
sn n
a e
e r
s a
e aw a
e m
s s
w l\\
d a
e n
~
s m
an o-
. ~
. d:
. a r
4 n
n -
a a
~
1 %
1 3
1 3
r
~_
B I1 g'
g 7
\\
g1 g
1 2
tn e
.s a P g o J
P
(
r q
1 0
5 E
w R
a s
s L
e U
e T'
s ss s
G 6
a Il s
I e
e 6
n
~
e s
F s
s s
i a a
e-a s
n s
e sr ia r
r s
s a
a i1I'I' i:
1l
\\;I;l t!13\\.;
l;j 1;l
- (
)
I; il!
,Iil;ii lj;il,tl,<
LLL'
,,>r.
!1
- I oi;1s' j
l t,,r i.
4!!
.% g e.1 i
)
,N A
g.--)
t n
t-i p
i.C o
\\
P
,w t
(
g
('
i,<
t t
(
u i
t
<i w
t E
3 g
a L
s N
\\
E a
s T
m T
3, A
u t
(
u s
(
n s
\\
T e
i t
g It
.f g
, R s
lu t
s u.n
- U
^
=
l 4_m M7 i
m e
n e
e s
es m.
2 e
i s
s
^
t o.
t
- ,J e. %
.L
?.
.V
- . ~
.I
)
D 4
t n
i s s
g o.
n r
w g
u P
u s
E
(
s t
u t
i
/
p e
o r
t s
sn A
t e
\\
s i
f 1
u t
e S. -
e t
n e
g m
.s
=
~e
=
=
e6-t g
eB
=
=
i n
e e
a g
w p
i.
e.
-p 1
/
e g
a P
)
B 8
t 0
n i
5 o
P E
a
(
t R
[
a U
p I
r
/
EP G
/
m J
2
/.r f =
F 3
{
3 3
g t
- !-f\\
iii;1 f.
4 j
,J
,1j
,1<,
- \\
~ :; ; i 4
,3; i!,
- ,J441<
i 1I!iIs
l q"
r f
3 w)
.s
[:
.iI r m
fk s
ur y
O e
L p
P O
I t
T vi 4
t 6
s O
O P
A W
P C
O
'4 O
A L
C C
U AI
_~
t n
~ _
a C
C E
E l
M s
- ~
.I s
s b
s
~
t n
a_ q~m m
s s
e e
e a
e
-' e
=
G
=
P o
e i
s P
s i
s a
G i
s E
(N s k s
, d y'-
s'
\\'
)
,C W
U O
t L
.n ru F
O d
i a
L A
o f
.P-IE e
d l
p S
e
(
u E
P N
M I
E
-L p
\\
e J
k, a
1 u
T n
R t
s e
M-u e
=
e 4
s 1
s S
m s
3 0iL t
=
f L
a 1
- s i.
e -
h a
)
F t
2 n
i e o g P i.
(
a
)
P
.E f
t n
8 i.
0 i
o 5
j
- i P /
ru O
(
r L
u i
O E
f L
e R
t f
A I
0
/.
g\\y U
d L\\
S 4
y t
G 6
1 I
31 s
.1 a
A F
A m
t e4 e
4 e
=
e 8
=
9
^
=
^
8 u
=
0 0S.
=
L
^
s I.
8 e
e l
1
l q
j
\\ j,
(_
' ;~
p.:e,,; w iY J h L L x.
y g k'
~
STEAM LINE RESONANCE COMPENSATOR STEAM
+
THROTTLE t
~.
PRES 6URE n
l
'[
A Opsi o+
TURBINE TRIPPED BIAS IN,C l-PRESS I-
"O" CONTROL PRESSURE
-> MOT HVG e LVG, e
VALVE-SET p
x
% FLOW,b, N/
, DEMAND a
n DEC l-G AIN 1
UNIT
+
LOAD i
B LIMIT l
TURB TRIPPED.
+ IOpsi BIAS STEAM j
THROTTLE-i PRES,SURE
+
+
STEAM LINE RESONANCE COMPENSATOR
~
l FIGURE 26-3 PRESSURE CONTROL UNIT i
~
i
LGA-G3 (SIPL?
~
DRYWELL SPRAY INITIATION PRESSURE LIMIT gggggggggggggggggggggggggggggs 300
$5MMMM$$$$MMMMR$$$$$MMMMMB@MGM EMMMMM@MEMMMMBMGEMEMMMMMMMMMMR MMMMMMMMMMMMMG@MMMMMMMM@@ @ME*
MMMM@@@MMMMMMMMMMMMMMMM@@*
l Eg@@@@MMMMM@@@WMMMMMMMP I
88 MMMa@MMMMMBa@@MMMMMP ^
R@@@MMMMMMM@@MMMEP E
R$MGMMMMMB@MMMMP W*
RMMMMMMMMR$$NMr i
R$MMMMMMMa @MF E
EMMMMMMGGMW 5
GMMMMMM@@@7 MMMMER@@F E
MMMMR$$W 1
i MMM@Ma@7 MMMM$$$V
?
i 5
MRM@@@MT c
5 Mg@@@ M 5
[
100 MGMMME C
m MGMMMP MGMME'
?
HMM MMisF 8 MMM
.e.
f's, b
0 10 20 30 40 50 60 'T7 0
SUPPRESSION CHAMBER PRESSURE(psig)
[.[
!Uidas I$i!s i
I
M-
\\
11 l
l 1987i i
AANuAar reasuARY anAaCM Apen anAY JUNE satwvea satwtrs satwtea satwira satwtea satwtea 123 1234567 1234567 1334 13 123456 45678918 8 91811u1314 8 91811121314 5 6 7 8 Slett 3456789 7 8 910111313 18u1314155417 1516111819521 1814171819521 12131415161788 NIllfl31415N Hl5141788195 5 19 5 21 B B N 35M5555 35M5555 N EIIIIB M 5 171813 5 2131 5 IIII B M 5 5 5 555553831 53031 555538 35555530 555 SI 9
I AAY AUGUST SEWR OCf00ft MOVEAnten SOCIAasen j
z' satwtra satwtea satwtea satwtea satwtea satwves 1134 1
12345 123 1234567 18845 5 6 7 8 Stell I345678 8 7 8 91e1112 4 5 6 7 8 9N 8 91911121314 6 7 8 91911u IIl314tENIfl0 9101112131415 1314151417 1819 tilIl31415 NIT 9516171819 5 31 131415N171819 19 5 2tII B M 5 Mlfl819521It 521:25M55 1819 52 tit 5 M 55M5555 BIIIIBMBE ED553131 SM55!!55 N3538 5 5375 53031 35 B 5 5 3031 5 31 4
a
- o..e
.. s. m,
.R
!4. n r=, :-~ -.
f Y
.i. Q'
.l y
y j k\\,
\\
4
{
i
94 gleam /Temuseanadoersense 1 new toen abstranes tem L 42 aos 7eenspot eneth timestnlmesemeses ans pl8ptspartes e anse gespreisp4.1967, ty its Aserten soc
~
'4 f ] Tf
(
A j\\ (l > :
(a 4s t
l4 a
TSWe l'c + 3 7; r-p y,.s.
y 4
Preptf*l.** Of Saturat9d Steam end esturated Water Stiftperaturti Enthalpy, Stu/lb Entropy.Stuft a F Volume.9t /16 8
Wseer Evep tesem Water Evap Steam Water Esep Steam n
4 s,
6 s
s s
1 0
M 0A8859 ق 3305 3305
-022 10753 1075.5 OA000 2.1873 1.1873 32 I
as OA9991 tale 02 2948 2948 3.00 10n2 10762 0.0061 2.1706 2.1767 as 40 0.12163 021602 2446 2446 SD3 1073A 1079A 0.0162 2.1432 2.1594 40 l-f 45 0.14744 021602 2017.7 2037A 13.04 1068.1 1081.2 0.0262 2.1164 2.1426 45 to 0.17796 0D1602 17042 1704A 18 05 1065.3 1083.4 0.0361 2A901 2.1262 to 80 0.2561 0A1403 1207.6 1207.6 38.06 1059.7 1087.7 04555 2.0391 2.0946 80 TO 0J629 OA1605 368.3 868.4 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 80 03068 021607 633J 633J 48.04 10484 1096.4 0.0932 13426 2.0359 80 to 0.6981 0A1610 468.1 468.1 58 02 1042.7 1100.8 0.1115 1A970 2.0086 90 100 03492 0A1613 350.4 350.4 68.00 1037.1 1105.1 0.1295 1 3530 13825 100 110 12750 SA1617 265.4 265.4 77.98 1031.4 11093 0.1472 1A105 13577 110 120 1.9927 OA1620 20325 203.26 8737 1025.6 1113.6 0.1646 1.7893 13339 130 130 2.2230 0A1625 157.32 15733 9736 1019A 11172 0.1817 1.7295 13112 130 540 22892 021629 122.98 123.00 10735 1014.0 1122.0 0.1985 1AB10 13895 140 150 3.718 0A1634 97AS 97.07 11735 1006.2 1126.1 0.2150 1.8636 1A686 190 MO 4.741 SA1640 77.27 77.29 12736 1002.2 11302 0.2313 14174 1A487 180 170 5.993 0A1645 62A4 62.06 13737 996.2 1134.2 02473 1.5822 12295 170 l
180 7.511 ED1651 90.21 90.22 148.00 990.2 1138.2 0.2631 15480 1A111 180 l
190 9.340 SA1657 40.94 40.96 158.04 984.1 1142.1 0.2787 1.5148 1.7934 190 4
800 11.526 0A1664 33.62 33 64 148 09 977.9 1146.0 02940 1.4824 1.7764 300 210 14.123 041671 27AO 27A2 178.15 971.6 1149.7 0.3091 1A509 1.7600 210 l
212 14.696 0.01672 26.78 26.00 100.17 970.3 1150.5 0.3121 1.4447 1.7568 212 330 17.186 OA1678 23.13 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 320 ISO 20 779 851685 19364 19.381 198.33 958.7 1157.1 0.3388 1.3902 1.7290 330
?j 300 24368 SS1693 16304 16.321 208.45 952.1 1160.6 0.3533 13809 1.7142 340 J
350 29325 031701 13302 13A19 21839 945.4 1164.0 0.3677 13323 1.7000 350 MO 35.427 OA1709 11.745 11.762 228.76 938.6 1167.4 0.M19 1.3043 1.4462 360 270 41256 881718 10.042 10.060 2M.95 931.7 1170.6 0.3960 '9.2769 1.6729 270 l
30 49.200 SA1726 S.627 8.644 N9.17 924.6 11732 0.4098 12501 1A599 30 1
330 57.550 DD1736 7.443 7.440 259.4 917.4 11762 0.4236 12238 1.6473 290 300 67A05 SD1745 4.448 6.466 389.7 910.0 1179.7 0.4372 1.1979 1.6351 300 310 77.67 SD1755 5.609 5.426 2002 902.5 11823 0.4506 1.1726 1.6232 330 i
320 39.64 SA1766 4296 4.914 290.4 3943 1185.2 0.4640 1.1477 1.6116 320 f
j 340 117.99 BA1787 3.770 3.738 311 3 378.8 1190.1 OA902 3D990 13892 340 350 153.01 041811 2339 2.957 332.3 862.1 1194 4 03161 SD517 15678 360 MO 195.73 881836 2J17 2.335 353.6 844.5 1198.0 05416 1A057 1.5473 300 l
80 247.26 481064 13444 13630 375.1 825 3 1201.0 0.5667 0.9607 1.5274 400 480 308.75 SS1894 1A808 1A997 3963 306.2 1203.1 03915 03165 1.5000 420 l
400 M154 881926 1.1976 1.2169 419.0 785.4 1204.4 06161 R3729 1A890 440 l
480 4663 48196 0.9746 0.9942 441.5 763.2 1204.8 04405 02299 1.4704 400 i
i 80 366.2 Sa200 0.7972 OA172 4645 739.6 1204.1 asua &7871 1.4518 400 i
000 WO9 88204 0.4645 0.6749 487.9 714.3 1302.2 0m90 0.7443 1.4333 000 l
RIO 812.5 43209 0.5386 0.5596 512.0 487.0 1199.0
&7133 S.7013 1.4146 520 S40 9623 88215 0.4437 0.4651 636.8 467.5 1194.3 0.7378 E6577 IJD54 540 900 1133.4 03221 0.3651 0.3871 962.4 425J 1187.7 0.7625 E6132 1.3757 580 000 1326.2 km228 02994 0.3222 989.1 509 S 1179.0 0.7876 &S673 IJ550 See me 1943.2 SA2M 02438 0J675 617.1 560.6 1167.7 0A134 &$196 1.3330 800 880 17863 63247 0.1962 0.2208 686 3 906.3 1153.2 03403 SA689 1J092 820 G40 20593 88260 0.1543 0.1002 679.1 454.6 1133.7 03686 04134 12821 Sec 800 2365.7 48277 0.1166 0.1443 714 3 392.1-1107A DJ995 0.3502 12498 880 MD 2708.6 88304 OABOS 0.1112 768.5 310.1 1068 5 03365 82720 1.2006 000 see 3094.3 tats 4 E03e6 0.0752 a22.4 172.7 995.2 E9901 es1490 1.1390 tot ses.s anos2 Samos 0
CAmos e062 0
906.0 1As12 0
1A612 Tot.s '
_J
' f a4 k
b.Th[I fh.M[
6 ll Mi et 6.,4 attom and esturated water gwpesuto) i; l
saarep7.see aF sasen,.em./t snoeip7.ese 9.ha.eam g
l 7
57 wec s
en wenn s9 si seen s.ee si m menn ei 5
m, a.
a, 4,
s 5
i' <
asses 32Ais & Ale 02 3302A 3302 4 SCO tens 30n3 e
uan 2.un 0
1021.3 Esses tw 35m3 0 4:402 29453 2945 5 Sm nonA 10nA 0006i 2.n06 2.n96 Sm tenJ tie i
&1l 46 453 0A1602 2004.7 2004.7 1950 10673 131.4 0.0271 2.1140 2.1411 1830 1025.7 Ett f
tat
$3.140 SA1603 15MJ 1526.3 21.22 1063.5 1084.7 0.0422 2A738 2.1140 2122 8 tm
]
'I 630 W #4 Saltos 1039.7 1039.7 32.M 1057.1 139.7 00641 2A148 2209 N.54 1832.0 mm too 72 359 SA1406 732A 792.1 40.92 1052.4 1093J 04799 137M 2A562 40M 1034.7
&m l
El 79.586 0 01607 441.5 641.5 47.62 1048 6 1096.3 0.0925 13446 Im?C 47.62 10 45 l
46 35.218 Obl609 540 0 M0.1 53.25 1045.5 1098.7 0.1028 13186 2ml5 S3J4 1 46 E7 90 00 OA1610 466 93 466 94 98.10 1042.7 1100 0 OJ 18966 22083 98 10 1040.3 47 as MJB 001611 41147 411.69 62.39 1040.3 1102 6 0.1117 14775 13970 GJ9 10 68 1
ts W.24 001612 368 41 364 43 86.24 1038.1 3104J 0.1M4 13606 13570 G624 10423
&S l
3A 101.74 0A1614 333 S9 333 40 89 73 10M.1 11052 0.1326 1A455 13781 99 73 1044.1 1A RA 126 07 0 01623 173 74 173.76 94.03 1022.1 1116 2 0.1750 1.7450 13200 94 03 1051A SA SA 141.47 OA1630 118,71 118.73 109 42 1013.2 1122 6 0J009 1.4854 1564 109 4 SA 40 152 96 0.01636 90 63 90 M 12032 1006 4 1127J 0.2199 1A428 1AM6 120 9 4A E0 M2Je Obl641 73515 7353 130.20 1000.9 1131.1 SJ349 1AOD4 13443 130 SA
/
&O 170 05 0A1645 61.967 6138 135.03 996.2 11MJ OJ474 1.5820 13294 1M 01 Es TA 1M24 0.01649 E3 D4 53 65 144A3 992.1 1136 9 0.2581 1.H87 1AIGS 144Al 1067.4 7A
&O 18236 OA1653 47J28 47J5 150 27 988 5 1139J 0.2676 1.5384 13060 19024 1099.2 ta SA 1 5.27 0 016 %
42 m5 42 40 1M.30 M 5.1 1141A 0 2760 1.5204 1.7964 IMJS 1070A SA j
l 10 193.21 0.01659 38 404 38 42 161.26 982.1 1143.3 02836 1.9043 1.7879 16123 1072J 30 j
Stes 212A0 SA1672 M 782 M20 100.17 970.3 1150.5 0.3121 1A447 1.7568 180.12 10nA tems l
15 213 05 0 01673 M 274 MJ9 181.21 969.7 11503 03137 1A415 1.7552 181.16 1077.9 15 l
30 22736 0 01683 20 070 20 087 196.27 960.1 11 % 3 0.3358 13962 1.7320 196 21 1524 5
30 250.M 001701 13.7266 13.744 218 9 M5.2 1164.1 0.3682 1J313 1.9995 218 3 1 5 7.9 30 40 M7.25 0.01715 10 4794 10 497 236.1 933.6 1169 8 0.3921 1.2044 1A765 236.0 1092.1 4D go Mim 0.01727 84967 8.514 250.2 923.9 1174.1 0.4112 12474 JASS6 250.1 1095.3 30 2
80 392.71 SA1738 7.1562 7.174 262.2 915.4 1177A 04273 1J167 14440 362 0 1998 0 W
70 302 33 0A1748
&l475 6205 272.7 907A 11006 04411 1.1905 1.6316 272.5 1100.2 N j j
30 312.04 0A1757 S4536 S.471 282.1 900 9 1143.1 045M 1.1675 1A20B 513 1102.1 80 90 SIO m 001M6 44777 4395 290.7 394.6 11853 0 4643 1.1470 1A113 290 4 1103.7 90 300 327A2 001774 4A133 4A31 298 5 M B.6 1187.2 0.4743. 1.1294 1A027 298.2 11052 ISO I
R20 M127 0A1789 3.7097 3.728 312 6 877A 3190 4 0 4919 1ADEC 1AS79 312.2 1107.5 130 340 E3A4 001803 3J010 3J19 325 0 SES 0 1193.0 0.5071 14881 1A752 324 5 1109 6 340 180 36356 0A1815 22155 2434 336.1 059.0 1195.1 0.5206 1A435 13641 335 5 1111.2 35 330 573 5 001427 23129 2 531 346.2 SSO 7 1196 9 0.5328 1.0215 1.5543 345 6 1112.5 ISO 900 512 0.01839 IJES9 2J87 355.5 842A 3198 3 0.M3B 1A016 13454 3642 1113 Me i
350 8097 001865 1A245 13432 376 1 325 0 1201.1 0 5479 0 3585 1.5264 375 3 11152 350 300 417J5 001889 1A238 1.5427 394.0 GOB 9 1902 9 0.5M2 03223 1.5105 392 9 1117.2 300 NO G1.73 0 01913 1J064 1J255 409 8 794.2 1204A 0.0059 02909 1A968 408 6 1118.1 NO 400 444 EO O0193 1.14162 1.1610 424.2 700 4 12046 04217 03630 1.447 422 7 1118.7 40C 450 456JB 0.0195 IA1224 1 8818 437J M75 12042 04300 02378 1A738 435.7 1118 3 SC 900 467Al 00198 E90787 0 3276 449.5 755.1 1204.7 O M90 SA148 1A639 447.7 Ill8A Set SSO 4M94 0 0199 822183 03418 460 9 743.3 1204.3 0 4611 0.7936 1A547 458 9 11 Set 800 e620 0 0201 E74962
&M95 471.7 732 0 1203.7 04723 0.773B 1A461 4H.5 1118.2 Set 700 903 08 0.0205 E63505 0 65% 491.6 710.2 1201A 09928 0.7377 1A304 408 9 11163 79 800 518.21 0.0209 834809 S.5490 509A GB9 6 litt4 0.7111 &M51 1A143 506 7 1115.2 SD
)
900 83135 00212 447968 4 3000 SM7 459.7 11964 0.7279 E6753 1A032 523.2 11 90 1000 944.58 SM16 442436 E4440 542 6 480 4 litt9 0.7434 EM76 1JD10 138 6 111 l
1800 966m 0.0220 437863 0 4006 557.5 831.5 1889.1 0.7578 Eul6
- 1J794 55311107.5 lit 3300 967.19 00223 S34013 4 3625 5713 613.0 liteA E7714 Eten 1J 53 546 9 1104 j
same sn42 Om27 emna 6 2299 as54 Se4 6 Ita0.2 &7e43 esn3 Jan se0.1 11009 mar l
3400 B7A7 00231 8.27871 SJ018 998 8 SM S 1175.3 0.7966 0.9807 13474 Set t 8 1900 90630 00235 825372 62772 611.7 984 4 11701 OAM5 RS208 1.3373 805.2 3093.1 1 98 3000 635A0 60257
&l6M6 0.153 672.1 466.2 3138.3 02625 04256 3Jul e62 6 le N00 808 11 0.0286
&l0009 E1307 731.7 381 4 8083.3 03139 SJ206 12345 718 5 1 1
3000 mm 00343 42073 8250 Sola 218 4 150.4 0.972 &1991 1.1619 782A Sn.1 as asiaa =6A7 Emos 0
Emes tua e
mea uni 2 0
imi2 mA ent a l
{
1 34 Table 3.
W 2,
- l.,2 W.,
l W
W,2 TempersespeJ 3000 1500 3800 naso nano 1g00 test-temp) 300 ago 300 400 300 f.0008, 300 eop mpop pose. I l
he A p. 7 /
g 8
Ob/se in, b
l
$ *f
% Q [s/
~.
Sils $71A' Old WOJ 0 11902 8195 7 1841 A laa 4 35961 1854A ',
523 1I NES e 4016 letDe IF3M SS5M 19730 3362 32 Imos 3.11u 2.1722 Sm37 2270s 22144
)
3 4 50 11421 126 15 135 08 190 011384.3 3433 6 14833 1634.7 S l
001.74) s E1295 1986 7 7&14 9024 35 24 1338 2 1335.9 J521 11484 IIM A 94131A360 13043 *M 2AB32 2.1369 2.1776 2 e 0A141 92A7 MA4 30820 180 76 116.72 5
4 501 1303 4 44.tB SIA3 57.04 3 03 90.00 F4.98 SO M 86 91 1986 6 1839 5 3s833 1747.9 042.24) s a1295 12716 1443 5 llM61757 2.2101 12430 22M4 1 3133 7 U404 157A 1835.5 13Bd C 1443 e 00161 NA4 77307 30 6 502 1146 6 I5865 Ret 4 1532 1747 A 18034 09321) s 0.129511.732B 1
22890 l
161 SA146 r 29399 35963 37.955 41 A06 45978 14332 1443 4 1534 5 2A155 2 0543 2A946 2.1309 2.1463 2 1983 8 1335.2 e 0.0 3192.5 1239.9 1257J 8 56370 54352 1D717 31 A46 M 465 37.458 40 447 43 435 46 4 36 4 504 let 09 1 A1H 1A720 1A24 1747A 13033 4
1432 9 1443 2 15H 3 1986 3 14 Q13 03) s 0.1295 8 3 40 22 356 25 428 28 4571286 9 1334 9 13E3.5 I
e OA161 94166 G27.96) s 01295 02 M O 1J805 3A397 3A921 12397 12836 2A244 231M M EB9 36143 27.676 291 5 05 18811 1191 4 1239.2 15858 3638 3 19927 1747.5 18 30 6
18 699 20.199 21.497 2.1516 2.1007 14.165 15 485 17.195 1882 5 1533 7 2A549 2299 2.1224 1285 0 1333 6 1382 5 1432 113065 1.M7 e 00161 0 0146 11 26 12424 1196 6 1236 4 12624 0810 les 15 1992 1.760s 1 A143 12 446 33.450 14 452 1747.1 1802A 40 4
1533.2 19453 1638 4 30B2 4 9 67.25) s 0.1295 02 M O 7J57 8354 9A00 10 425 11 438 e OA161 64166,1181A 1233 5 1283 2 1832.3 1381.5 14313 34813 GB 15 14820 IJIM 1.M81 1 2168 18612 13024 13410 13774 13.5 1 13 229 14 577 12 331 343BD 3092A 17463 18023 11.581 80 6
0.1295 42929 114492 9J19 10275 10A291481.1 1532 6 1 6218 7A18 7394 8360 99211) s 1
1300 5 1430 5 0 0141 8 0166 0 01751230 5 1281 3 1930 9 1A790 1J349 13642 1A299 13702 1.90B9 1.M54 9200 30 400 11.060 11 A5 9
8821 34B24 369 74' 1 e
l 30 t 1746 3 18022 4 S35 S 388 6.216 4A33 7A43 8 050 8 665 92$8 0 1295 0 3 39 0 4371 le74 3891.6 0 12.04) s 2.0602 2A794 1227.4 1279.3 1329 6 1379 5 5429 7 1400 4 15 0.0161 RO1M 00175 1A036 3A451 1539 1A205 134 9 7130 926 14B29 369 77 14516 13084 1.7546 56831 41928 6700 e
1746 2 19020 300 t 01295 0 339 0 4371 1943 9 1637.1 14913 1A296 IA872 IJ376 13529 12246 1 027 A2) s 5 31 148 33 26931 1224.1 1277A 1328.1 1378 4 14288 1479A 1531.4 4 0786 4 6341 5.1637 i
0A161 E0166 00175 33 6.1709 E.0036 7549 FA652 7AM e
1943 4 3636 7 1830.9 17453 120 6 0.1295 8 3 39 0 4371 52995 51364 2A129 2A421 (34127)s 3 4461 3 3526 4.4119 4 2585 SA161 SA146 E0175 12203 12753 18263 1377.4 1425 0 5479.1 15303 131M 135m IAR25
(
13461 1528 5 37 ISE 20925 1AE86 1.7196 1.M62 13071 11 A295 BA132 53M5 57741 11532 e
1AGB5 1745 6 18014 i
14e 6
&1295 8 3 39 0.4370 3536J 3090.5 73 (353 04) s 3 0060 3 4413 3 2400 42420 43427.2 3478 412310 1A 1530 3 19823 IA350 336M 13930 18 48161 S AI46 0A175 13M 4 Sec & WC 54B 42 200391217A 12733 3325 413039 13499 1J919 4.1363 6 4704 e
44905 43907 S.1299 54E67 63014n (363 55) s &1294 R M 3B 04370 1.9906 1A622 3.0433 3 4093 3.M21 4.154 1A227 13545 13849 2A1 16293 Ita2 4 14MJ 80161 &0166 OA174 1324.0 13753 14MJ 2 6474 121M 18545 1594 180 6 S 47 35 47 209 32 1213 2 1271.2 1J784 52191 53209 5519 1A376 1A000 13362 e
3.0583 33783 3A515 4.0003 43077 44128 07305) s GL1294 R2935 04370 13743 1981 S SESS 4 3393 1745 13732 2A025 3GB 51 389.96 1210.1 12690 18224 1374.3 1425 4 7359B 23247 f.0161 S S184 8217 1A242 147M IJ239 1.M63 12057 B 4 4131 4Abe6 4
e A233B 04369113893 2 4662 2AS72 3D410 31909 343B2 3S ago e B 52 17442 1A002 1980 6 3654 4 leB 9155 i
08130) s 3.1294 3423 4 3475 3 1527.6 OAle6f21504 1A173 1A524 1263 5 1319.0 1371 41ADM 1.7405 13301 36M6 SAMs e &0141 8A166 42174 375.10 5 66 IS E3 270A5 13951 3A602
) s &l2te R2937 44314 0.5667 22263 2.4407 2450p 22585 BAS 43 S.3EER 34 6
3E33J IGABO 1743 4 17 300 i
1A278 1257 00186 13065 2A044 1421J 1473 6 19262 1579 41.79M 1 A (400 97 270 14 375.15 1257J 1315.2 1368 9 e 4A161 SDIM 90174 13703 1A274 1A750 1J192 1J591 3.1471 122C 5 79 35 74% 2937 & 4307 0 3665 1A970 2332 2J652 2A445 2A219 1390
[
300 6
1742 6 1795 1975 2 S S 2J 1 5 7.1 14105 33 I
(417J5) s 41294 i
6 5 92 35 25 27024 375.211251.5 1311.4 13s42 1419.2 1471 A 3824 1 04186 IA913 13038 13141 13477 12738 e 40161 AD1M E0174 IJ757 SJUDD IJ411 1A151 13799 2.1339 22401 SA E3M4 1.segl IA0U 1A671 l
1741.9 17tf
- 3) s 61293 asau e4367 330 1523.3 ISM 9 34312 34962 i
IJWEB 1A325 1 A547 139 1341 IAM3 1A499 (431.7 1417A 1470.3 e 68141 teles SA174 48162 1245.1 1307A 1365 4 l
1250 17255 1.M32 3 5 97 27033 37527 13282 1.9001 1A406 1A256 ISB07 2A746 2.19 e & S 05
- 80) e 41243 E2935 44306 R3463 3674 4 14291 2004 4 174 l
ag IA397 1.5798 1 Bet 2 13702 la 1J037 (444 1967 3 8412 1 1486 6 SS20.35478 1AB 0 2919 1.1984 e SA161 48144 4 AIM S4106 12312 1299 1 15 19 27051 375 3 1.9505 1A123
.01) e ;&l25t &2934 SA364 03040 i 1 A021 0 a 5 3t 33 (447
~~
~-~m
"-ww-y._
genen / Therme(ywndes af senom M
's Properties of superheated steam 6ed r.-W d water tiempera f, / Fable 3 f Y I " "
fft 5
ans poem.
Desaperets% F l
sh/se in.
testtesse) 100 300 300 400 900 000 700 800 900 3000 '1100 1300 1300 1400 1300 j
e 00161 OmlM e0174 a0le6 07344 0.9456 1 An6 1.le92 1.s00s 1 4093 13160 1Artl 1.n52 1 32s4 1 3 :09 30 6 08.54 109 42 270 70 375 49 1215.9 1290 3 33512 1400 3 3463 0 1917.4 1571.9 1627A 1882 6 17382 1795 6 (40620) s 0.1292 0333 0 4M2 03657 1AHO 1.5329 1.5444 1 A351 1 A769 1.7155 1.7517 1.7959 13144 134M 13792 e
0.0161 041M OD174 E0186 0204 0 7328 0 9072 1A102 1.1078 12023 12948 IJB54 1A757 13647 1530 7ec e 9934 15 65 270A9 37561 487.93 12SIA 1 M S.6 1403.7 1459 4 1514 4 1969 4 16243 Im07 1737.2 17943 1
(503.05) s 0.1291 0 3 32 0 4360 03655 06889 1.5000 1.5473 1A154 1 AS40 1 A970 1.7335 1.M79 13006 1A318 1A617 l
l e
0.0161 OAIM 00174 E0186 00204 0.6774 0 7328 0 5759 0.M 31 1A470 1.1299 12003 IJEB5 1J669 1A446 000 6 70.11 3803B 271.07 375.73 487AS 1271.1 1339.2 1999.1 1455 3 1511.4 1566 9 3622.7 1675 9 1735.0 1792.9 (51821) s 0.1290 CJ930 0.4354 0 5652 0 6885 1A469 15444 1.5900 1A413 1A807 1.7175 1.7522 1.7851 1A164 13464 e
00161 0D166 00174 02186 Q M 04 0 5469 0 6858 0.7713 0 3504 0 9262 0 9998 1A720 1.1430 12131 1J825 900 6 70 37 170 10 27126 37534 48733 12606 1332.7 1394 4 1452.2 1508 5 1564 4 1620 6 16U.1 1D41 17916 (531.95) e 0.1290 0 3 29 0 4357 0.M49 0 6881 1A659 15311 1.5422 1A263 1A662 1.7033 1.7382 1.U13 13028 13329 e
CD161 02166 0.0174 0 0186 0 0204 0 5137 06080 06475 0.M03 03295 02966 0.9622 1m66 1.0901 1.1529 1800 6 70 63 170 33 27144 375 96 487.79 1249.3 1325 9 1389 6 1448.5 1504 4 1M1.9 1618 4 1675 3 1732 5 17903 (544 58) s 0 1289 02928 0 4355 05647 06876 1.4457 1.5149 1.M77 1.6126 3A530 14905 1.72 % 1.7589 1.7905 1 3207 1
e 0.0161 CD166 0 0174 0 0185 0 0203 0 4531 0.5440 0 6108 0 6465 0 7505 0 3121 0 3723 0.9313 0 9094 1A468 l
1100 6 70 90 170 % 27113 376 08 487.75 12373 13183 1384 7 1444 7 1502 4 1559 4 1616.3 1673 3 17310 1799D (5 % 25) s 0.1289 0327 0.4353 03644 06472 1A259 1A996 15542 1A000 14410 1.6787 1.7141 1.7475 1.7793 13097 e
00161 02166 0 0174 0.0185 0 0203 0 4016 0.4905 0 5615 0 6250 0 GH5 0 7418 0 7974 03519 0 9055 0 9544 1300 6 71.16 170.75 27122 37620 487.72 1224.2 13115 1379 7 1440.9 1449 4 15M 9 1614 2 16714 1729 4 1757A (567.19) s 01298 02t26 0 4351 0.5642 04868 1A061 1A851 1.5415 1.54E3 1A298 14679 1.7035 1.7371 1.7691 1.7996 e
0 0161 02166 0 0174 0.0105 0.0203 03176 0 4059 0 4712 0 5282 0.5809 0 6311 06798 0.7272 0.M37 03195 1400 4 71 68 171.24 272 19 376 44 487.65 11H 1 1296 1 13693 14332 14932 1551A 1609.9 1668 0 1726.3 1755 0 (587A7) s 01287 0323 0 4348 0.506 0 6459 13652 1A575 1.5182 1.5670 1.6096 1A444 14845 1.7185 1.7508 1.7515 e
00161 0D166 0 0173 0 0185 0 0202 0 0236 0 3415 0 4012 0 4555 0 5031 0 5482 0 5915 0 63M 0.6748 07153 1400 4 7221 171 69 272 57 376 69 487 60 616 77 1279 4 13585 14252 1486 9 1546 6 1605 6 1M4.3 17232 1782.3 (604 A7) s 01296 02921 0 4344 0 % 31 0 6851 0A129 1.4312 1.4968 15478 13916 1.6312 1.M 78 1.7022 1.7344 1.M57 e
0.0160 OD165 0 0173 0.0185 0.0202 0 0235 0.2906 0 3500 0 3988 0 4426 0 4836 0 3229 0 5609 0 5980 0.0 43 3000 6 72 73 17215 272.95 37693 487.M 615 58 1261.1 1347.2 1417.1 1400 6 1541.1 1601.2 1660 7 1720 1 1U9.7 4621m) s 0.1284 0 3 18 0 4341 03626 06843 03109 1A054 1A768 15302 13753 141 % 1A528 1AS76 1.7204 1.7516 e
0 0160 4 0165 0 0173 0A184 0 0201 0 0233 02488 03072 03534 03942 04320 OA680 (L5027 05M5 03695 3 00 6 7326.172A0 273J2 377.19 487.53 614 48 1240 9 1353 4 1408 7 1447.1 1536.2 1596 9 1657A 1717.0 1777.1 53530)s 01283 02916 0 4337 0.5621 0.6834 OA091 13794 1A578 15138 1.5603 1A014 11391 14743 1.7075 1.73B9 e
R0160 02165 0.0173 00184 0 0200 0 4230 0 1681 02293 02712 03068 03390 0 3692 03900 0 4259 0 4529 2500 6 74 57 173 74 274.27 377A2 487.50 612.08 1176 7 1303 4 1386 7 1457.5 1522.9 1545.9 1647A 1709.2 In0.4 466Lil) s 0 1280 62910 0 4329 0.5609 0.6815 0 3048 IJ076 1.4129 1A766 15269 13703 1AOM 1A456 14796 1.7116 e
0.0160 E0165 0 0172 0 0183 0.0200 0.0228 0.0982 0.1759 0.?!61 02464 0.2U0 0J033 EL3282 0.3522 03753 1
3000 6 7538 174AE 27522 378 47 4B752 610 05 1060 5 1267.0 1M32 1440.2 1509 4 15742 163B5 1701.4 1Mla 1995 33) s 0.1277 02904 04320 (L5597 06796 03009 1.1966 1.3692 1A429 1A976 15434 1.5441 1A214 1.6561 1Ame8 e
0.0160 RD165 0 0172 0.0183 0.0199 0.0227 0.0335 0 1588 0.1987 0.2301 02576 R2827 0J065 03291 03510 3000 6 M4 175 3 275 6 3787 487.5 609 4 000 8 1250 9 1353 4 3433.1 19033 15703 16MA 1698 3 1M1.2 (705.0s) s 0.1276 02902 0 4317 E5592 0.6738 0.7994 0.9708 1.3515 14300 1Ae66 15335 13749 1A126 14477 1AB06 i
e 04160 03164 0.0172 0A113 00199 00225 OA307 E1364 0 1764 02066 0 2326 0.2563 02784 0R95 03190 3000 t D.2 IM O 2762 379.1 487.6 608 4 779 4 1224 6 1338 2 1422.2 1495.5 1%3.3 16292 1693 6 1757.2 e 0.1274 R399 04312 05585 OA7U 0.7973 09508 13242 1A112 14709 131M 13618 1A002 1A358 1A691 e
00159 0A164 02172 60142 0.019e 0.0223 0 0287 0.1052 01M3 01752 0.19H &2210 02411 02601 0.2753 i
4000 e 78 5 in.2 2U.1 379A 487.7 606 9 M30 1174 3 1311 6 1403 6 1481J 1552.2 16192 1685 7 17506 e
0.1271 4 353 04304 03573 0.6760 0.7940 OJM3 12754 IJB07 1A461 1A976 13417 13812 1AIN 1A616 i
l e
02159 ED164 02171 E0181 SA196 0.0219 EON 8 0.0H1 0.1038 E1312 01529 0.1718 01890 02050 02203 9000 6 81.1 179 3 279 1 EB12 488.1 404 6 746 0 1042 9 12529 1364 6 1452.1 1529.1 1400 9 1670 0 1737.4 e
0.1265 SJeB1 04287 E5550 0.6726 0.7sso 09153 1.1H3 12207 1A001 1AS42 1.5061 15481 1.5463 1A216 e 021H SD163 00170 E0100 02195 04216 40256 02397 OA757 0.1020 0.1221 0 1391 0 1544 01844 61817 0000 6 83.7 381.7 381.0 382 7 des 6 402 9 7361 9451 Il0B 8 1323 6 1422.3 15059 1542 0 1654 2 1724 2 e 0.1254 43S70 0.4271 0 5528 te693 0.7826 0.9026 1A176 12615 1.3574 1A229 1A748 1.51M 13H3 1596 2
- 04158 83163 E0170 E0100 00193 02213 02248 023M 0.0673 60B16 0.1004 0.1140 E1298 01424 61542 3000 6 as2 384 4 M30 M42 439.3 401.7 729.3 9013 1124 9 1281.7 1M2J 1482 6 15631 1638 6 1711.1 e 01252 Easte 042% SS507 Ee463 E7777 0A926 12350 12055 13171 13904 1A446 1At3B 1A355 1.5735
r N
e j
. ee vbN. ; *
=
M/Ab m
\\
~
g
(
L~
\\
- =
i u
e<
x Thmm
\\
u n
(
v m
X r
m S
5Nt@ MW; i
W WQ><<%
j W%
><%9L
>=c Q <%5
- $M9,;
I w
\\ $
i
=
I x > < QM) s, h
h m
2 I
v w4 s
a
%-l
%3(
s W
~
7
~
2==%h h':
i q
N h<
)
Q
-===
s== m se l
l
""'"4 Mq
-==um=:q W
h
~ ~ ~
N N A Q N 6 Q l
M 7 Z;=-se f
ll x===# -= _,
~
~
N %
mm e:===
~ ' *
~"""
A l
l es 1
D 5 C ~~~~~~"5
'""""."~.Q Er6 C
4IgW 9510'0 I_I_I
~ ~.--
Elm iI _I I
I I
I l_l I
t j
}
c~2
^
~
wm
(,g.... >.
g h. b. p: T t il t
YY, jb u
u u
u'u gle l l
A,/,A/ F U/,/',
n n
l
-l l
l A,llA 1FJ N, il M, nr n
-l l
l 8SDbxA / M# /%,
l y
J
} g i iP L I.
l eac i L
Ml l
l
/d MSA / N // /3V,
\\
f h
i I N(
l ad '
\\
- l l
l
[8MAf
/ M ///V 1 t
kj ii
+1 1
in-ml l
l NykWN,) N, n/!,IW
]
gy l Rf)M9 'U k T1 3 ll l JDfA7sh&b71 L 7t 1
l ' l1 l
i lfMH40WaVNJ 71 l:
~
lWMHE 7>MM 4 3 lIsa u &v n/
.I w
lIBMWMW//Y
~l\\HM
~
NMH%(HY
~
~1 hWX'UR5WY :~
~
"VMXM7x M
~
"U7M % M
~
TWMM M 2,.,
l
,c teuanon ww.i..
spcte efficienq o (metmort
~ [f. en o o s/t evt)/(Enner sa,
' a. se, s.st+5atg e
E. act A. 9 -At IE = 5 avt a.(vf-v.1/t
. y
' A = ha
,l t
(x,y r
~
,..n2/g = e.m/s
,,,,,n
. m./t v,. v. e.s ts ff
[(tg) (t il e
b W. -f I(4) + (gH
_J y, gc,.tx 4
i aE,931 as
,j i=aCpat 4
! = 108 er h = llAA
- t. u f
Pwr = N ah g..,\\
I = 1,10-m/TR f
TVL = 1.Sh
%. :..W'
\\
MtL = -0.693A P = P,10sur(t) i P = P et/T o
SCR = 5/(1 - II,ff) l SUR = 26.06/T CRx = $/(1 - Keffa) i CR (1 - Reff ) = CR (1
- kef(2) 2 SUR = 25pfs* + ( e - p )T M = 1/(1 - Eeff) = CRt/CRo T = (**/,) + [(s - p)/ip)
M = (1 - Ir ffo)/(1 - Keffi) e
' T = s/(p - s) 50M = (1 - E,ff)/K,gy l
l
. T = (s - p)/(Ap)
A* = 10-5 seconds e * (Keff-1)/Keff = AKeff/Keff I
e.1 seconds-1 4
p = [(* /(T s ffD + Is ff/(1 + ITD e
e
' Igd) = 1 d32 2
f F = (tov)/(3 x 1010)
Ildt 2elyd2 2
R/hr = (0.5 CE)/d (meters) r l
3 =.N R/hr = 6 CE/o (f.et)
Miscellaneous Conversions Water Parameters 10 1 curie = 3.7 a 10 dps i
l 1 gal.
8.345 lim.
1 kg = 2.21 Its 3 l
1 as). = 3.78 liters 1 Inp = 2.54 x 10 stu/hr 6
1 ft3 = 7.48 galt -
1 er = 3.41 a 10 stu/hr Density = 62.4 lbs/ft 1 in = 2.54 cm tensity = 1 en/cm3
'T = 9/5*C + 32 Itest of vaporization = 970 Stu/lba
- C = 5/9 (*F-32)
Heat of fusion = 144 Stu/lba 1 STU = 778 ft-1bf 1 Ata = 14.7 psi = 29.9 in. Ng.
1 ft H O = 0.433 lbf/in?
2
.. -. - - -..... J
-.