ML20202E310
| ML20202E310 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/17/1986 |
| From: | Elin J, Obrien J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20202E275 | List: |
| References | |
| 50-361-OL-86-01, 50-361-OL-86-1, NUDOCS 8607140324 | |
| Download: ML20202E310 (175) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION REGION V Examination Report No. 50-361/0L-86-01 Facility Name: San Onofre Nuclear Generating Station Units 2 and 3 Docket Nos.: 50-361 and 50-362 Examinations Administered at: San Onofre NGS, San Clemente, California from April 29 to May 9, 1986 Chief Examiner: ./ b b J /. O'Brien, Operator Licensing Examiner Date Signed Approved by:
J
( hd V. Klin, Chief, Operations Section h [7/fb Da/eSigned' Su= mary:
Examinations on April 29 to May 9, 1986 Written and operating examinations were administered to seventeen initial candidates for R0 licenses. Written and operating examinations were administered to five initial candidates for SRO licenses. Written examination were administered to five reapplicants for a R0 license and one SRO reapplicant. Seventeen candidates passed the written examination for RO and six candidates passed the written examination for SRO. One SRO candidate _ failed the operating exam, and all other candidates passed their operating exams.
As a result of these exams, eighteen candidates for Reactor Operator and five candidates for Senior Reactor Operator were found to meet the minimum qualifications for licensing.
8607140324 860624 i PDR ADOCK 0500 V
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REPORT DETAILS
- 1. Examiners:
- J. P. O'Brien, RV ;
t G. W. Johnston, RV -
J. Upton, PNL
, J. D. Smith, PNL
, 2. Persons attending the Exit Meetings:
I *J. P. O'Brien, RV
- G. W. Johnston,.RV
- *T. Meadows, RV l' f*J. D. Smith, PNL f*J. Upton, PNL f*J. Wambolt, SCE d
f*D. Mette, SCE
< f*W. Kingsley, SCE f*M. Hyman, SCE-
- G. Swift, SCE
- Denotes Meeting on May 1, 1986
- Denotes Meeting on May 8, 1986
- 3. Written Exam and Facility Review:
The written exams were conducted on April 29, 1986 in the facilities-Training and Simulator Building. One large classroom and the portion
- of the hallway.to the dedicated washroom facilities was roped off for;
- the exclusive use of the candidates and exam team. This arrangement
} vorked out very well, and meets all the requirements requested and in accordance with NUREG-1021.
At the conclusion of the' written examination the facility staff was given an opportunity to review the exams, and to discuss any immediate questions with the authors of each exam. .Just prior to the first exit meeting, another opportunity was provided to discuss the facility l comments. Those comments not resolved and any further comments were i sent in writing to the Region V, and were resolved prior to grading the exams.- The comments and resolutions are addressed in the enclosed' j Attachment (1). Appropriate revisions to the master examinations were l performed prior to the examiners grading the exams.
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l 4. Operating Examinations:
4 Simulator exams and facility walkthroughs were conducted April 30 thru i May 1, 1986 and May 6 - 8, 1986. General weaknesses were noted in'the i candidates' abilities to describe the type of detector, construction, 4
and operation of the new type excore Nuclear Instrumentation. Further, the reference material provided to the examiners in this area needs updating.
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- 5. Exit Meetings:
On May 1, 1986 and May 8, 1986 the Examiners met with representatives of the plant staff to discuss the results of the exam. Those candidates who clearly passed the operating exam were identified. Also discussed was the proposed changes to 10 CFR Part 55, OLB policies concerning Simulator training vs. actual manipulations of the facility and Instructor Certification. Further discussed was the difficulties experienced by the examiners concerning site access and inadequacies of the reference materials provided by the facility, i
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ATTACHMENT 1 FACILITY COMMENTS AND RESOLUTIONS I
FACILITY COMMENTS RESOLUTION QUESTION 2.08 QUESTION 2.08 The examinees may have been The valves that control the initially confused about this venting are solenoid operated, question since it stated to use not motor operated, but "six motor operated valves", there are no other valves The valves' operators in reality that control the venting.
are solenoids. However, the The answer key figure facility believes that the drawing indicates the required that was intended to be derived response by showing the would still be drawn by the point count. There is no candidates. The answer key should change to the answer key.
be changed to reflect usage of motors or solenoids. Additionally, there was too much detail in the answer key drawing. We request the drawing be acceptable as attached.
QUESTION 2.09 OUESTION 2.09 The answer key provides no Answers of 55.2 1 5 gallons tolerances for the number of and 1.8 + 0.2 in, are the gallons per percent pressurizer acceptabTe ranges for level. grading.
Recommendation Accepting an answer with a tolerance of 55.2 gallons 15 gallons.
QUESTION 2.15 QUESTION 2.15 There are more alternate lineups The answer will be expanded c available than listed in the to include those paths not answer key. listed in the System Description.
Recommendation l
Expand the answer key to include the paths available by procedure S023-3-2.11, " Spent Fuel Pool Operations." This procedure was supplied as reference materials, with appropriate section attached for your reference.
FACILITY COMMENTS RESOLUTION QUESTION 2.17 OVESTION 2.17 The answer key limits the number Due to the use of the word of acceptable responses. We Auxiliary in the title for request the answer key be expanded the Auxiliary Feedwater to include the other auxiliary System, the Auxiliary uses of Main Steam as stated in Feedwater System is an section 2.1.2 of the referenced acceptable answer.
document for the question.
QUESTION 3.05 QUESTION 3.05 DCP's which have been installed Question 3.05 is deleted.
in the plant, but were not updated in the reference used for this question, have made the question non-applicable to San Onofre Units 2/3. Therefore, we request this question be deleted.
QUESTION 3.08a. and b. QUESTION 3.08 The reference used to develop Based on the fact that the answer key was an old System the old System Description Description. Since then, major is wrong, the answers modifications have been made and have been adjusted to the System Description is no longer read as follows:
correct.
- a. The cooldown rate is Recommendation controlled by throttling the SDC HX Outlet valves "S023-3-2.6 Shutdown Cooling which are upstream of System Operation" be used as the the SDH HXs common reference (this procedure was a output.
part of the exam material originally submitted). Hi-lited b. The total flow is portions of the appropriate maintained by adjusting sections are attached. Also see one of the SDC HX bypass P&ID's 40112b, 40112d and 40114b, valves which bypasses which schematically illustrates both SDC HX's taking these changes and are attached. the flow directly to (Also submitted as Reference the low-pressure header.
Material.)
FACILITY COMMENTS RESOLUTION -
1 QUESTION 3.08d. QUESTION 3.08d.
The old System Description was There is no change due to a used to develop the answer key loss of instrument air.
for this question. Major changes to the Shutdown Cooling System have occurred since its development. One being that the valves in this part of the system
- have been converted to motor operated valves.
Recommendation Change the answer key to indicate that nothing occurs on a loss of instrument air. P&ID's 40112b, 40112d and 40114b, which were originally submitted as exam material and are attached for your use, are the recommended references to support this change.
QUESTION 3.09b. QUESTION 3.09b.
Examinees may have been led astray Due to the incorrect reference because the question stated "Y01 to a B train source, either may receive power from a B train list of components will be
, MCC". Since Y01 only receives accepted as the answer for d
power from 2 A train MCC's we a total of 1.0 point instead request that the answer key accept of 2.0.
as the second source MCC BE or MCC BJ, or none at all. Referenced drawing attached.
QUESTION 3.10 j QlESTION 3.10 The reference used for the question This question is deleted.
contained invalid information.
DCP's installed in the plant make this question not applicable to San Onofre Units 2/3.
Therefore, we request deletion of this question.
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- FACILITY COMMENTS RESOLUTION 0VESTION 4.10 QUESTION 4.10 1 This question could be true or This question is deleted.
false, depending on the reference used. Since both references i were available for the exam we
! request this question be deleted.
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FACILITY COMMENTS RESOLUTION QUESTION 6.01 QUESTION 6.01 This question is inappropriate This question is deleted.
for SONGS 2/3 due to a CPC software modification (approx.1.5 years old) which removes CEAC penalty factors for inward rod deviation.
Under present software, given the situation stated in the question, the correct response would be:
One CPC would react to the dropped rod indication (assuming the CPC was reading signals from the reed switch stack in which the switch failed) to the failure by calculating a smaller margin to trip, possibly (depending on which group the dropped rod was in) developing DNBR/LPD trips in that channel.
QUESTION 6.13 QUESTION 6.13 There are more alternate lineups The answer will be expanded available than listed in the to include those paths not answer key. listed in the system description.
Recommendation Expand the answer key to include the paths available by procedt're 5023-3-2.11, " Spent Fuel Pool Operations." This procedure was supplied as reference material with appropriate sections attached for your reference.
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FACILITY COMMENTS RESOLUTION QUESTION 8.14 OUESTION 8.14 i We request that the equipment The answer key is changed to identification numbers for the accept either the radiation listed radiation monitors also monitor name or its equipment be accepted for credit as follows: identification number for the correct answer.
- containment airborne monitors, RE-7804 or RE-7607
- containment purge monitor, l RE-7828
- condenser air ejector wide range monitor, RE-7870
- plant vent stack airborne monitor, RE-7808
- containment purge or plant I
vent stack wide range monitor, RE-7865.
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FACILITY COMMENTS RESOLUTION QUESTION 6.15(b) QUESTION 6.15(b)
The information contained in the Added, " accomplished by a reference used for this question needle valve in the control is outdated. Plant modifications air supply line to the letdown on Unit 2 have bypassed the control valves," as an electronic lag circuit, and this alternate answer to Question function is now accomplished by 6.15(b). The original answer a needle valve in the control will be accepted if a air supply line to the letdown statement that it is the control valves. The answer key old way and no longer used is still representative of the is included with the answer.
configuration on Unit 3.
Therefore, we request the answer key be modified to accept either explanation for full credit.
QUESTION 7.05 QUESTION 7.05 This question could be true or This question is deleted.
false, depending on the reference used. Since both references were available for the exam we request this question be deleted.
QUESTION 7.13 QUESTION 7.13_
We request that the answer key Answer key changed to accept be modified to accept any two of any two of the following five the following five conditions, conditions:
which would require reinitiation of SI flow: a. less than one S/G operating
- a. less than one S/G operating b. pressurizer pressure not
- b. pressurizer pressure not greater than 200 psia greater than 200 psia c. pressurizer level not
- c. pressurizer level not greater than 30%
greater than 30% d. core exit saturation
- d. core exit saturation margin margin not greater than not greater than 20 F 20 F 1
- e. reactor vessel level not e. reactor vessel level not I greater than 82%. greater than 82%.
Refer to S023-12-3, Loss of Coolant Accident, page 29, which was supplied as a reference for exam preparation.
Ye UPTov U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: SONGS 2 and 3 (50-361/362)
Reactor Type: PWR-CE Date Administered: April 29,1986 Examiner: John Boegel, John Smith Candidate: Answer Key INSTRUCTIONS TO CANDIDATE:
Print your name on the line above marked " Candidate." The grade points available for each question are indicated within parentheses after each ques-tion. The passing grade is 70% in e'ich of the four (4) categories and is 80%
for the total grade. Use separate p.sper for your answers and write on only one (1) side of the paper, unless a (specific question instructs you otherwise.
Staple this question package to yout answer sheets. The examination questions and answers will be picked up six (ti) hours after the examination was started.
Read the statement at the bottom of this page. When you have finished this examination, affirm the statement b signing your name.
Category % of Candidate's '
% of Value Total Score M. Value Category 25 25 *
- 5. Theory of Nuclear Power T Plant Operation, Fluids and Thermodynamics 25 25 N 6. Plant System Design, Control, and Instrumen-tation 25 25 7. Prc9cedures - Normal, Abnoinnal, Emergency, and RaMiological Control 25 25 Administra tive Conditions, Procedures. *nd Limita-tions ,
100 TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received l aid. l l
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L FURTHER INSTRUCTIONS TO CANDIDATE
- 1. At the end of the written examination package is a copy of a portion of l the Operations Physics Summary for Unit 2 in Cycle 2. Use the tables and curves as appropriate.
- 2. At the end of the written examination package is a reference page containing equations, formulas, and constants. Use them as necessary.
- 3. Use the " Steam Tables" as necessary.
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Page 1 SONGS 2 and 3 April 29,1986 Points Available 5.0 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS AND THERMODYNAMICS (25.0)
QUESTIONS 5.01 and 5.03 are " multiple-choice" questions. For each question specify the letter designation for the phrase that provides the most correct statement.
QUESTION 5.01 As the effective number of full-power hours of operation of will change and, hence, the stable thecoreincreases,)8Ndresultfromthecorehavingasmall reactor period that w amount of positive reactivity will change; the changes are that (1.0)
(a.)),ff will increase and the reactor period will increase.
(b.) ),ff will increase and the reactor period will decrease.
(c.)),ff will decrease and the reactor period will increase.
(d.)),ff will decrease and the reactor period will decrease.
ANSWER 5.01 (d.) [+1.0]
Reference (s) 5.01
- 1. SONGS 2 and 3: Unit 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 154-157.
-Section 5.0 Continued on Next Page-
Page 2 SONGS 2 and 3 April 29,1986 Points Available OVESTION 5.02 After a reactor trip from full power level, the negative startup rate approaches the same value independent of the shutdown margin because (1.0)
(a.) the decay rate associated with the reduction of the temperature of the fuel determines the long-term decay rate for the neutron flux.
(b.) most of the neutrons are " prompt" and hence the prompt neutron diffusion time determines the long-term decay rate for the neutron flux.
(c.) the delayed neutron emitters with the shortest half-life determine the long-term decay rate for the neutron flux.
(d.) the delayed neutron emitters with the longest half-life determine the long-term decay rate for the neutron flux.
ANSWER 5.02 (d.) [+1.0]
Reference (s) 5.02
- 1. SONGS 2 and 3: Units 2 and 3 Operation:: Training, Reactor Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 148-151.
h -1. es vie r
/and Hgure 41.5.
- 3. GA: Syll bus'i/ Triga ra tifilig dianu si,],ReaQo rTikti cl" MTecpologifsInc.,~p.6-149 l
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-Section 5.0 Continued on Next Page-l
I Page 3 SONGS 2 and 3 April 29,1986 Points Available QUESTION 5.03 One of the characteristics of water is that it will hold gases dissolved in solution. Which of the following would DECREASE the concentration of dissolved gases in a quantity of water? (1.0)
(a.) increasing the pressure and/or lowering the temperature.
(b.) decreasing the pressure and/or lowering the temperature.
(c.) increasing the pressure and/or raising the temperature.
(d.) decreasing the pressure and/or raising the temperature.
ANSWER 5.03 (d.) [+1.0]
Reference (s) 5.03
- 1. SONGS 2 and 3: System Description, " Condensate System",
SD-5023-240, Revision 0, p. 5.
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-Section 5.0 Continued on Next Page-
Page 4 SONGS 2 and 3 April 29, 1986 i Points Available 00ESTION 5.04 Answer TRUE or FALSE to each statement given below concerning '
subcritical operation. grA,erve cHA"d5',
- a. If the reactor had been shutdown for 3 months, the 4ouse
.r.aage 6:tr =;ats would lose their ability to determine the level of the neutron flux because the flux level would be too low. (0.5)
- b. The neutron flux level is determined primarily by the neutrons produced by the intrinsic sources, the largest of which is due to a-particle absorption (0.5) g;pra ein Ots.
nau cc r
- c. If the indicated countrate by theccur : .enge intr =:nts doubled, the reactivity margin (to criticality) has been reduced by approximately one-half. (0.5)
- d. For each equal insertion (addition) of reactivity, it takes a longer amount of time for an equilibrium neutron-flux level to be reached as k,ff approaches unity. (0.5)
U d^'"ge eJfJ,q,MchesofCEAwithdrawalincreasedthecountrateby a
ypcurc;--enge
. instrument by 10 CPS, 20 inches of CEA withdrawal would have increased the countrate by 20 CPS. (0,5)
ANSWER 5.04
- a. FALSE [+0.5]
- b. FALSE [+0.5]
- c. TRUE [+0.5]
- d. TRUE [+0.5]
- e. FALSE [+0.5]
Reference (s) 5.04
- 1. SONGS 2 end 31 Nuclear-Erlergy Trbinpl. 3-hor Operati)ons Unit 12", p. 12.1-1.
Soccs 2 Axy " R f A O c of T H E e ITy " PR 8 3 4 ~ 203
f Page 5 SONGS 2 and 3 April 29,1986 Points Available OUESTION 5.05 A rupture of a Main Steam line is a more severe inc' dent (a more limiting condition) at E0C than at B0C. Briefly explain. (2.0)
ANSWER 5.05 The MTC is less negative at BOC than at EOC. [+0.67] This difference increases the severity of the incident at EOC because the incident provides a sudden cooling of the RCS [+0.67] which, via the MTC, causes the reactivity of the core to increase.
[+0.67]
I Reference (s) 5.05
- 1. Academic Seegram .for NucleHF/ PowerJlant Generic:)l,,
Personne Vplume IIf,.-Nucyr-Powerpent TOch logy, f l976,' Gener#V Physics Corp. , pp. 2-T27 132.
gopey zAA3 R5 actor T efa n ??. I G ~I "
-Section 5.0 Continued on Next Page-l l
Page 6 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 5.06 Figure 5.06 (0VESTION) shows the CEA Regulating Group Insertion Limits. Answer the following parts of this QUESTION with respect to that Figure.
- a. For continuous operation at 80% of full power for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with COLSS in-service, what is the acceptable range of CEA position for Group 67 (0.5)
- b. A W is there an unacceptable or prohibited region of operation? State two (2) reasons. (1.0)
ANSWER 5.06
- a. 150 to 120 inches withdrawn [+0.5]
- b. 1.1 ensure that core-design peaking factors are not exceeded OR 1.2 ensure that the fuel burnup is sufficiently uniform AND 2.1 ensure that there is sufficient rod worth to safely shutdown the reactor OR 2.2 ensure that there is sufficient rod worth to be within the calculational envelop for shutdown with an ejected rod
[+0.5 for 1. and 2.]
2.T foraxi r H Ar rin* n,y,usm r etu r oow a M AdLi d I$ M AnHTA,AlfC q, y fear rni ? TCur'Al < & *~rN o l~ A c EA 6Mc710" AectbfMT e2 L.t M
- 1 s*C >
- A ce Pv- Arts s or von. r
-Section 5.0 Continued on Next Page-
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Page 7 SONGS 2 and 3 April 29, 1986 Points Available 1.0 )De Gn.s 1 %
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4 Figure 5.06 (0VESTION)
Reference (s) 5.06
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operatina Characteristics Review Text, pp. 193-195.
- 2. SONGS 2 and 3: Technical Specification, San Onofre Nuclear Generation Station, Unit No. 2, Docket No. 50-361, Appendix "A" to License No. NPF-10, February 1982, Section 3.1.3.6, pp. 3/4 1-22, 3/4 1-24. A N P S A D r F a 4 L e o 3. l. 3. 6
-Section 5.0 Continued on Next Page-
Page 8 SONGS 2 and 3 April 29,1986 Points Available OUESTION 5.07 As the core ages, the delta-T from the fuel centerline to the coolant changes.
temperature at fullThis will subsequently power. Provide six (change the fuel 6) factors, that change over the life of the core which affect the heat transfer ability and subsequent full power centerline temperature. (3.0)
ANSWER 5.07 Roo 6 0 $v
- 1. fuel densification 9.
, ,us ou Feooo cT r t o . #3 0 s t o v P e ,-
- 2. fuel pellet swelling
- 3. clad creep
- 4. clad corrosion
- 5. crud buildup
- 6. nature of the gas in the gap
- 7. concentration of the gas in the gap
- 8. thickness (size) of the gap Any six (6) [+0.5] each, +3.0 maximum Reference (s) 5.07
- 1. SONGS 2 and 3: Heat Transfer and Fluid Flow Fundamentals, Revision 1, February 1981, Part B, Chapter 4, pp. 235-241.
-Section 5.0 Continued on Next Page-t- 'Q t
i Page 9 SONGS 2 and 3 April 29,1986 Points Available The following statements apply to QUESTIONS 5.08 and 5.09.
The Unit 2 power plant has been operating continuously at a steady 100% of full power for 15 days. All control rods (CEAs) are fully withdrawn from the nuclear reactor core (AR0). All controlled parameters are equal to their respective programmed values or setpoints. The fuel-burnup status is that the core has reached 200 EFPD. The present boron concentration is 200 ppm. All systems are in AUTO control except for the CEAs which are in MANUAL SEQUENTIAL (MS).
QUESTION 5.08 If the regulating control rods (CEAs) were inserted while in the MANUAL SEQUENTIAL (MS) mode until Group 6 is at 108 inches withdrawn and if the boron concentration was adjusted to maintain the power level of 100%, what would be the new concentration of boron required for steady operation? Neglect any effect from changes in the xenon or samarium concentration. Assume the CEA worths do not change with core age. (1.5)
ANSWER 5.08 Using Table 4.1 or Figure 4.1, ,,,y n o,,f g a kg ap = 0.144 %Ak/k for BOC. [+0.Q Using Figure 3.1, PFd py',T F*K B4.8 To 67 2 inverse boron worth = 87 ppm /%Ak/k. [+0.Q Hence, l A ppm = (87)(0.144)
., = 12.5 ppm
! and neu boron concentration = 200 - 12.5
= 187.5 ppm [+0.5]
-Section 5.0 Continued on Next Page-i
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i Page 10 SONGS 2 and 3 April 29, 1986
. Points
- Available Reference (s) 5.08
- 1. SONGS 2 and 3: Operations Physics Sumary, " San Onofre Unit 2 Cycle 2", Revision 3, Figures 3.1, 4.1, and Table 4.1.
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Page 11 SONGS 2 and 3
. April 29,1986 Points Available QUESTION 5.09 The power plant is to be taken from 100% to 80% of full power.
- a. What would be the magnitude of the change in reactivity due to the temperature changes associated with this power change? Specify whether this change adds or removes reactivity from the core. Assume that the core burnup status does not affect this reactivity change. (1.0)
- b. If the core burnup status did affect this reactivity change, how would increasing the amount of burnup affect your answer to "a."? (0.5)
- c. If this maneuver from 100% to 80% of full power took 20 ninutes, make a sketch of xenon worth as a function of time. Show time beginning from the point-in-time of decreasing power and for the next 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. State the values of xenon worth for initial conditions, final conditions, and peaks or valleys. (1.5)
ANSWER 5.09
- a. Using Figure 5.1, m a o.24 ra o,78 % </g 27 power defect = 4r3 %ak/k. [+0.p Reactivity has been ADDED. [+0.5]
- b. Increasing the core burnup would result in more reactivity being added to the core for this 20% drop in power. [+0.5]
(og mots N;cpT**g C C A e ro v u ly & Cho vio)
-Section 5.0 Continued on Next Page-l 1
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Page 12 SONGS 2 and 3 April 29,1986 Points Available l
ANSWER 5.09 (contd)
- c. 3.2 2.8 -
f f 2.65
\
0 10 20 30 40 50
[+0.5 for initial equilibrium of 2.74 to 2.86]
[+0.5 for shape]
[+0.5 for final equilibrium of 2.59 to 2.71]
Reference (s) 5.09 1
- 1. SONGS 2 and 3: 02erations Physics Sumary, " San Onofre Unit 2 Cycle 2", Revision 3, Figure 5.1; Tables 6.1, 6.2, 6.3, and 6.4; T1gures 6.2 and 6.4.
, 2. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theon, Nuclear Physics and Core Operating Characteristics Review Text, pp.3204-207.
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-Section 5.0 Continued on Next Page-
l I Page 13 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 5.10 The turbine of the Auxiliary Feedwater (AFW) System is rated at 876 hp with steam supplied at a pressure of 1210 psia.
When the AFW turbine is being supplied with 500 psia main steam, how much work can be supplied by the turbine?
Assume thermodynamically ideal operation of the turbine.
Express the answer in Stu/lbm. (2.0) i
! ANSWER 5.10 I
hi = 1205 Btu /lbm [+0.5 for using saturated conditions]
isentropic expansion [+0.5]
h2 = 955 Btu /lbm [+0.5 for using atmospheric pressure]
j Ah = 250 Btu /lbm [+0.5 for 245 - 255 Btu /lbe]
l Reference (s) 5.10 4
- 1. SONGS 2 and 3: Units 2 and 3 Operations Yraining, Heat
! Transfer, Thermodynamics, and Fluid Flow Fundamentals, Revision 1, February 1981, Part A, Chapter 1, p.145-157.
l
- 2. SONGS 2 and 3: System Description, " Auxiliary Feedwater
- System", pp. 5, 30.
i 4
4
-Section 5.0 Continued on Next Page-
Page 14 SONGS 2 and 3 April 29,1986 Points Available QUESTION 5.11
(
- a. Sketch the thermodynamic performance of the following system on a T, S diagram. Label the key points on the diagram that correspond to the key points in the system. (1.0)
ILa f i ti c,.
/(3) l c,% ~
Gue rnict 1
%) '
F f ,
mp Cond' e n:e r ;
V Gsi)
I J b. Sketch the change in performance to the above system on i'
your I, S plot with the addition of a Moisture Separator ,
Reheater. Briefly explain w& the change in performance
- occurs. (1.5)
! c. Indicate clearly on your T, S plot the effect in performance to this system due to a reduction in condenser vacuum. (1.0)
Las ,',,e r e - s e a '
, ,e .rs u r e.
t I 1 i
i, I
-Section 5.0 Continued on Next Page- )
J i
(
Page 15 SONGS 2 and 3 April 29, 1986 Points Available ANSWER 5.11
/ %
T /
/9 M ~
g [+1.0]
b.
A f h13 A ll Z -
t
/y '7 0
[+0.75]
The average temperature at which heat is added is increased thus increasing the thermodynamic limit of the amount of heat that can be converted to work. [+0.75]
c.
Y Z j
, s'
- h $ .l.D brs e =
< p -: .i..i: m i-r e.,.r?
%?M .
. 'N -0
\
I
~
[+1.0]
(Amount of available work is decreased.
-Section 5.0 Continued on Next Page-1 J
. ._ - _ _ _ . - . ~ .. -_ _
1
, l Page 16 SONGS 2 and 3 April 29,1986 Points Available Reference (s) 5.11
- 1. Generic: Nuclear Energy Training, Vol. 4, " Plant Performance", NUS Training Corporation, Steam Power Cycle Chapter, pp.1.6-1 through 1.6-4.
I
- 2. Generic: Nuclear Energy Training, Vol. 4, " Plant Performance", NUS Training Corporation, Super and Reheat
. Cycle Chapter, pp. 4.3-1 through 4.3-4.
- 3. Generic: Nuclear Energy Training, Vol. 4, " Plant Performance", NUS Training Corporation, Condenser Operation Chapter, pp. 5.3-1 through 5.3-4.
i i
i i
d i
i i
i 1
-Section 5.0 Continued on Next Page-1 4
.------,-.-...------,,,,..-,,-,-c., - - - , - - - , - ~ ~ - - - . . - , . - , . - , , _ _ , , , - - . - , , ~ - - . . - - . . , . , . , . , . , - - - - , - . . . - - -.- ,- ----- , ..---c---.--,--r-
Page 17 SONGS 2 and 3 April 29,1986 Points i Available QUESTION 5.12 Feedwater enters the steam generators at 436 degrees F with a flow of 14 x los lb/hr. Saturated steam with 1% moisture content and a pressure of 735 psig is produced. How much thermal power is being transferred? (3.0)
ANSWER 5.12 6
flow = 14 x 10 lb/hr h=Mdeltah h in = h of FW, which is subcooled. From temperature table hp = h436 h p = 414.6 BTU /lb [+0.5]
- Steam out - saturated at 735 psig 735 psig + 15 psi atmos = 750 psia at 750 psia hF = 500.9 hFG = 699.8 hg = 1200.7 [+0.5]
4 h of actual steam = (0.99)(1200.7) + (0.01)(500.9) =
1193.7 BTU /LI OR h = 1200.7 - (0.01)(699.8) = 1193.7 BTU /lb [+1.0]
h=(14x106 lb/hr)(1193.7-414.6) BTU /hr 10 h=(14x106 lb/hr)(779.1 BTU /lb) = 1.09 x 10 BTU /hr [+1.0]
i Reference (s) 5.12
- 1. SONGS 2 and 3: Heat Transfer and Fluid Flow Fundamentals, Revision 1, February 1981, Part B, Chapter 2, pp.1/9.
i
-End of Section 5.0-i l __ . _ _ _ . . _ _ _ - - -
Page 18 SONGS 2 and 3 April 29,1986 Points Available 6.0 PLANT SYSTEM DESIGN, CONTROL AND INSTRUMENTATION (25.0)
QUESTION 6.01 is a " multiple-choice" questions Specify the letter designation for the phrase that provides the most correct statement.
QUESTION 6.01 b8N If, while operating in Mode 1 with all-rods-out AR0), one (1) of the Reed Svftch Position Transmitters (RSPTs fails for one (1) regulating CEA such that the failed RSPT,(ndicates that the rod is fully inserted, p
/ (1.0)
(a.) only one (1) CEAC would "see" the drohped rod and two (2) of the four (4) CPCs would generate / penalty factors (that are not equal to 1.0) for DNBR an fLPD.
(b.) two (2) CEACs would "see" the dropped rod and two (2) of the four (4) CPCs would generate penalty factors (that are not equal to 1.0) for DNBR and LPD.
/
(c.) only one (1) CEAC would "see" the dropped rod and all four (4) of the CPCs would' generate penalty factors (that are not equal to 1.0) for'DNBR and LPD.
/
(d.) two (2) CEACs would "see" the dropped rod and all four (4) of the CPCs would not equal to 1.0) for, generate DNBR and LPD. penalty factors (that are
/
/
ANSWER 6.01 j/
(c.) [+1.0] /
. /
Reference (s) 6.01 ,/
- 1. SONGS 2an!3:Training System Description, " Reactor Protection System and Core Protection Calculators", pp. 22, 23, Figure 34.
-Section 6.0 Continued on Next Page-
-- - .---..-,m -,-,,----,-r - - - - - - , , . - - - , -
Page 19 _. SONGS 2 and 3 April 29, 1986 Points Available QUESTION 6.02 Answer TRUE or FALSE. Condensate storage tanks T-120 and T-121 are used solely for providing water to the Auxiliary Feedwater System for plant cooldown. (0.5)
ANSWER 6.02 FALSE [+0.5] Only T-121 is seismic category I tank. T-120 is used for many things.
Reference (s) 6.02
- 1. SONGS 2 and 3: Trainina System Description, " Condensate Storage and Transfer System", Section I-A, p.1.
QUESTION 6.03 Describe the design features of the steam generator feed ring and connected piping that prevent the feed ring and connected piping from draining rapidly whenever the steam generator water level drops below the feed ring. (1.0)
ANSWER 6.03 The discharge nozzles are located on top of the feed ring [+0.5] , u _, y . n , ., . ;
and the connected piping is sloped away from the feed ring. /', ,. g
'~
[+0.5].
Reference (s) 6.03
- 1. SONGS 2 and 3: Training System Description, " Auxiliary Feedwater System", Section I-A, p. 3.
I i
-Section 6.0 Continued on Next Page-l i
I i
4
! Page 20 SONGS 2 and 3 April 29,1986 l
I Points i Available :
1 1
I
! QUESTION 6.04 j Operating and Bistable Trip Channel bypasses are used in the
! a. List two (2) of the three (3) Operating Bypasses and briefly j describe at least one (1) plant condition when you would expect to use each of these bypasses. (2.0) l 2
j b. How does placing one (1) bistable trip channel in bypass Tor maintenance affect the Reactor Protection System 2 l out of 4 logic? (0.5)
- c. What will automatically occur if an operator attempts to j bypass the same parameter in more than one (1) channel at the same time? (0.5) j ANSWER 6.04
- a. 1. Low pressurizer pressure bypass: system tests at
( low power or low temperature or heatup or cooldown of the RCS.
j 2. High log power level bypass: during reactor startup l or above 10-4% power.
a
! 3. DNBR/LPD trip bypass: at low power levels or below 1% power.
Any two (2) [+1.0] each, +2.0 maximum
)
- b. Converts RPS logic to 2 out of 3 logic. [+0.5]
c.
cyin pnt I The pr4 vests lopst/prioritf 4wo (hannels by) pass 2at the same the). [+0.5]will retgrn tpornya I
- p o TH e cMK OUT CP T f d' t' H e ***L (3Y b u i
} Reference (s) 6.04 !
! 1. SONGS 2 and 3: System Description, " Reactor Protection System and Core Protection Calculators", Section 4, Table 5, a p. 109.
- i j -Section 6.0 Continued on Next Page-I i
l
Page 21 SONGS 2 and 3 April 29, 1986 i
i Points Available QUESTION 6.05
- l What is the purpose of the CVCS letdown accumulator associated with the back pressure control valve? (1.0)
ANSWER 6.05 fif u~ t r u *t E The letdown accumulator is designed to limit the Sp ::ed-zetica
~ " '
rgting %= a backprescura - !ve fa!!!ng : : unt!'
opar.ator actier c2n tamtaate the eveni.. [+1.0]
sgc*LL4t*O "< < d 7Y/d
- N 7 k' w f s2i A roi L f TD' d ^' ' ' !
Reference (s) 6.05
- 1. SONGS 2 and 3: Trainina System Description, " Chemical and Volume Control System", Section I-C, p. 6.
QUESTION 6.06 List the five (5) components supplied by each critical loop of the Component Cooling Water System. (2.5) 3 ANSWER 6.06 1
1 2 Co NTA) "**4 27 f u rt 6r a ry co a t.o n g uxir Dcs.Q 7% LPSI pump
[+0.5] for r ,4 c e s e r,vr e if +& W W' T C* o 0 W eonr41umtar 5 7. containment spray pump [+0.5]
l
/ ,(, shutdown heat exchanger [+0.5]
7 E. standby HPSI [+0.5]
g, ( c u r,4 e c x os m y m r x.a ir s # y t u oi.e. c n D o. s-]
Reference (s) 6.06
^ '
- 1. SONGS 2 and 3: Training System Description, " Component i Cooling Water System", Section I-8, p. 3.
i
-Section 6.0 Continued on Next Page-i l
4
---I
4 Page 22 SONGS 2 and 3 3
April 29,1986
. Points
! Available
.l l QUESTION 6.07 ;
j A W must the Emergency Diesel Generator (D/G) lube oil circulating pump be run for a minimum of 30 minutes after
,1 shutting down a hot D/G7 (1.0)
ANSWER 6.07 l to dissipate heat [+0.5] from the turbocharger bearings [+0.5]
l To t 6 w r c e s n u gi cpnewc ro n r o nd ,7~ .7 9 o, e c]
) Reference (s) 6.07 h l.03 A A X
- 1. SONGS 2 and 3: System Description, " Emergency Diesel i Generator System", Section 185, p.10.
i l
i1 i
i t
I i
4 l
i l
l l
I l
-Section 6.0 Continued on Next Page-i
i f
i Page 23 SONGS 2 and 3 April 29,1986 Points Available QUESTION 6.08 i List the three (3) pretrips that will cause a CEA withdrawal prohibit. (1.5) l ANSWER 6.08 i
) 1. High local power density pretrip [+0.5]
- 2. High pressurizer pressure pretrip [+0.5]
- 3. DNBR pretrip [+0.5]
1 4
Reference (s) 6.08 j 1. SONGS 2 and 3: Training System Description, " Control Element
, Drive Mechanism Control System", Section II-B-20, p. 37.
i 1
i 2
l I
i i
-Section 6.0 Continued on Next Page- l 1 i l
1 i
j
i 4
Page 24 SONGS 2 and 3 April 29, 1986 I
, Points Available E
QUESTION 6.09
, List six (6) protective functions / devices that are provided to t
automatically shut the diesel generator down during non-emergency operating conditions. (3.0) i ANSWER 6.09
- 1. High-high vibration
- 2. Engine overspeed
- 3. Low lube oil pressure (2/3 logic)
- 4. High jacket water temperature (2/3 logic) i
- 5. Generator differential l 6. Over-excitation tripping relay l 7. Highcrankcasepressure(2/3 logic)
} 8. Loss of excitation 1
l 9. Voltage restrained overcurrent
- 10. Reverse power 4
- 11. Negative phase sequence ,
l
- 12. Stator ground i
j 13. Volts per cycle
- 14. Stator overtemperature
[+0.5each,+3.0 maximum]
Reference (s) 6.09
- 1. SONGS 2 and 3: Trainino System Description, " Emergency Diesel Generator System", Section II-B-2A, p. 29.
-Section 6.0 Continued on Next Page-1 i
J
Page 25 SONGS 2 and 3 l April 29,1986 Points Available QUESTION 6.10 What are the three (3) interlocks that trip and/or prevent a heater drain pump from running? (1.5)
ANSWER 6.10
- 1. Heater drain tank low level [+0.5]
- 2. Heater drain pump low flow [+0.5) i
- 3. Heater drain pump motor overcurrent [+0.5]
Reference (s) 6.10 4
J QUESTION 6.11 What is the purpose of the high-level override in the Feedwater Regulating System and why is it required? (1.0)
ANSWER 6.11 To aid in preventing a steam generator high level condition
@ l.o] {+0$} or moisture carryover into the main turbine OS.5]. [+1.03 PM V GwT Yu t Root D4nMr l'5 s.o]
Reference (s) 6.11 (II.c[1A4Ax
4 i
i I
-Section 6.0 Continued on Next Page-
, . _ , - - - - _ , - - , - _ ,-.-- v m . - - . . - - - - , . - - - - - - - - - - ,,----,,,,,.-m-~-%.-.- r-.--.r-. -- * ,---,+--wa. - - - - - - - - -=
- Page 26 SONGS 2 and 3 i April 29,1986 Points Available l
l QUESTION 6.12 l
List four (4) rooms that are isolated with fire barriers that i
are designed to National Mutual Limited ratings. If there are multiple rooms for the same purpose, use each only once in your answer. (2.0)
ANSWER 6.12
- 1. Lubrication oil storage room i
j 2. Control room
- 3. Cable spreading rooms j 4. Diesel generator rooms
- 5. ESF rooms
]
j Any four (4) [+0.5 each, +2.0 maximum]
]
4 Reference (s) 6.12 i
- 1. SONGS 2 and 3: Training System Description, " Fire Protection System", 5023-590, Section 2.2.1.1, p. 5.
4 i
i i
i l
l l
l
- -Section 6.0 Continued on Next Page-l i
Page 27 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 6.13 List three (3) alternate lineups for makeup for the Fuel Pool Cooling System other than the Refueling Water Tank (RWT) via the spent fuel pool makeup pump. (1.5)
ANSWER 6.13 s, gnr vsA 14 S f !* t* * *' # '
unr1 n. ra r1
& ~
- 2. v CT h AN=5 Iit Elo"Jo AYdi'it a t 'e A d N"c Ts4
- 2. P ri - 2 y a b r.t 6 inral LW ,,gc7 _ g,g 2 f M '*
I'n' % fffg(("
3.4.RWTviatheLPSMpumps e,
W]SAy+0.5
?. LC vrA Lf5If,r m yfe m denoHc Reference (s) 6.13 I' "
- O G # # " [+ /> d h d *' ^' M
- 1. SONGS 2 and 3: Training System Description, " Fuel Pool Cooling and Cleanup System", Section I-A, p. 6.
QUESTION 6.14 List the inputs to one (1) of the two (2) subcooled margin monitors. Include number of inputs if multiple inputs of the same parameters are used. (1.5)
ANSWER 6.14
- a. Two RCS cold leg temperature inputs [+0.5]
- b. One hot leg temperature input [+0.5]
- c. RCS pressurizer pressure input [+0.5]
~~ " "* '
- f,vonAinarooa e r Q : (" O S r
- Paov o* *r r A n c.: e w .r. e oz a: A e e cpyg o) reg rn; enw;f Reference (s) 6.14
- 1. SONGS 2 and 3: Training System Description, " Reactor Coolant System", Section II-A3, p. 14.
4
-Section 6.0 Continued on Next Page-i
Page 28 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 6.15
- a. What is the possible hydraulic effect and undesirable consequence of rapid closure of the CVCS letdown throttle va1ve? (1.0)
- b. How is this prevented? (1.0)
ANSWER 6.15
- a. Reduce pressure enough to fom a steam bubble in the letdown line [+0.5' and water hammer occurring when the bubble collapses ([+0.5]
- b. There is a lag unit between the level controller and the letdown throttle valve controller +1.0 pr oa /A u t w c., w.' n . a. s m[y w] .t e rnw * * ~ + d' " f, o xs twa u s ~ sr A e c c,= rio . ~ Tae~r e r' ic * ' ' ' "
- '~# "'"~#" #
- Reference (s) 6.15
- 1. SONGS 2 and 3: Trainino System Description, " Pressurizer and Pressure Control System", Section II-8, b, p. 16.
QUESTION 6.16 The motor-operated auxiliary spray valve (HV-9201) is provided to depressurize the RCS when nomal spray is not available.
How would you depressurize if this valve was also failed (nomal spray valve not available)? (1.0)
ANSWER 6.16 M U-l30 A manually operated auxiliary spray valve, i:CV4274, is available outside of containment to depressurize. [+1.0]
Reference (s) 6.16
fB10, p. 27.
-End of Section 6.0-
Page 29 SONGS 2 and 3 April 29,1986 Points Available
7.0 PROCEDURES
NORMAL, ABNORMAL, EMERGENCY, AND RADIOLOGICAL CONTROL (25.0)
OUESTION 7.01 Answer TRUE or FALSE. If conditions indicate that two (2) seals in one RCP have failed, then trip the reactor. (0.5)
ANSWER 7.01 FALSE [+0.5] initiate an orderly plant shutdown.
Reference (s) 7.01
- 1. SONGS 2 and 3: Abnormal Operating Instruction, 5023-13-6, Section 3.2.1, p. 2.
QUESTION 7.02 Answer TRUE or FALSE. If the grid frequency dropped, the Main Generator load would be decreased as system speed decreased to 59.7 hertz on Unit 2. (0.5)
ANSWER 7.02 FALSE [+0.5] increased Reference (s) 7.02
- 1. SONGS 2 and 3: Operating Instruction, " Turbine Startup and Normal Operations - Unit 2", S02-10-1, Section 6.3.3.1,
- p. 25.
-Section 7.0 Continued on Next Page-
m Page 30 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 7.03 Answer TRUE or FALSE. Placing a test or calibrate switch on an NI safety channel drawer in other than NORMAL or OPERATE will place the low DNBR and high LPD trips in the trip condition. (0.5)
ANSWER 7.03 TRUE. [+0.5]
Reference (s) 7.03
- 1. SONGS 2 and 3: Operating Instruction, " Reactor Protec-tion System Operation", 5023-3-2.12, Section 6.4 Caution,
- p. 6.
QUESTION 7.04 Answer TRUE or FALSE. If a seismic event rendered any portion of the Fire Detection System inoperable, then a fire watch must be established within a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (0.5)
ANSWER 7.04 FALSE. [+0.5] (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
Reference (s) 7.04
- 1. SONGS 2 and 3: Abnormal Operating Instruction, " Earth-quake", S023-13-3, Section 3.8.1, p. 3.
-Section 7.0 Continued on Next Page-
Page 31 SONGS 2 and 3 April 29,1986 Points Available 0VESTION 7.05 p Df The Emergency Coordinator elects to init'iate a natural circula-tion cooldown with the RCS in a saturated condition during a station blackout. Answer the following TRUE or FALSE. If the RCS Thot reaches 450'F and SIT discharge is not occurring due to RC5 pressure remaining abova 615 psia, then use the reactor head vent to the Quench Tank to lower RCS pressure. (0.5) i ANSWER 7.05 /
TRUE. [+0.5]
Reference (s) 7.05
- 1. SONGS 2 and 3: AbnohalOperatingInstruction,"Lossof Offsite Electrical Ppwer", 5023-13.1, Section 1.5.1.1,
- p. 17.
l
-Section 7.0 Continued on Next Page-
Page 32 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 7.06 List four (4) conditions that require immediate initiation of emergency boration into the Reactor Coolant System. (2.0)
ANSWER 7.06
- 1. Failure of two (2) or more CEAs to drop following a reactor trip
- 2. One or more regulatin groups below the Power Dependent Insertion Limit (PDIL
- 3. Shutdown Margin is determined to be ( 5.15% A k/k when T
avg is > 200'F.
- 4. Shutdown Margin is determined to be ( 3% A k/k when Tavg is ( 200*F.
- 5. Uncontrolled cooldown of the RCS (T 25'F below Tref) causedbyexcessivefeedwateradditioO>orexcessivesteam withdrawal
[+0.5 each, +2.0 maximum]
Reference (s) 7.06
- 1. SONGS 2 and 3: Abnormal Operating Instruction, " Emergency Boration of RCS", 5023-13-11, Section 1.1, p. 2.
-Section 7.0 Continued on Next Page-
Page 33 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 7.07 What might be the result of operating all three (3) charging pumps with flow only through the excess flow check valve via -
-1201MU1077 (l'.0)
ANSWER 7.07 May result in exceeding system design pressure. [+1.0]
Reference (s) 7.07
- 1. SONGS 2 and 3: Emergency Operating Instruction, S023-12-10, Revision 0, p. 5.
QUESTION 7.08 The plant has been operating normally for days. Suddenly, several alarms annunciate on the turbine generator electrical power panel (99A, B, C). The following conditions are observed:
high unit speed load reduction generator amps and volts swinging violently.
What abnormal operating instruction should be invoked? (1.0)
ANSWER 7.08 Operation during major system disturbances. [+1.0]
Reference (s) 7.08
- 1. SONGS 2 and 3: Operating Instruction, S023-13-4. l
-Section 7.0 Continued on Next Page- l l
Page 34 SONGS 2 and 3 April 29,1986 Points Available 00ESTION 7.09 During the Diesel Generator Surveillance Test, the procedure instructs the operator that if the Diesel Generator is operated at less than 20% generator load (940 kW) for 4-1/2 hours, the Diesel Generator should be run for 30 minutes at greater than 40% load (1880 kW). Explain why this is required. (1.0)
ANSWER 7.09 To clean out the exhaust stacks [+0.5] and remove possible glazing from the piston heads [+0.5].
Reference (s) 7.09
! 1. SONGS 2 and 3: Operating Surveillance Test, " Diesel Generator Monthly Test", 5023-3-3.23, Section 4.8, p. 5.
l
-Section 7.0 Continued on Next Page-l
Page 35 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 7.10 On Unit 2 the operator is instructed not to interrupt display of the six (6) key COLSS parameters for greater than 15 minutes when the COLSS backup computer is providing control room COLSS indication. List the six (6) key COLSS parameters. (3.0)
ANSWER 7.10
- 1. ASI [+0.5]
L'*'I
- 2. LPD limits [+0.5] o A (FD F o u/W O M A T' - d
- 3. Power limit margin [+0. 5] o i< doLII Po wM " ' d '( h # N'C
- 4. DNBR limit [+0.5] ee DNBA Po w,Tc 6 f'/'t + P 'd L' N ?
f4 # F# "" #-
~
- 5. Reactor power level [+0.5] c et
- 6. Azimuthal tilt [+0.5]
Reference (s) 7.10
- 1. SONGS 2 and 3: Operating Instruction, " Core Operating Limits Supervisor System", S023-3-2.21, Section 4.4, p. 4.
4
-Section 7.0 Continued on Next Page-
l Page 36 SONGS 2 and 3
- April 29,1986 Points Available OUESTION 7.11 The Service AirJststm cannot be removed from service if it is N
~
being used for certain purposes. List six (6) of these blf) uses. -(4.,Q.
ANSWER 7.11
. 1. Condenser and heat exchanger air and water wash in progress
- 2. Air being used in Auxiliary building (Radwaste)
- 3. Air being used in Unit 2 or 3 Turbine buildings
- 4. Air being used in Chlorinator or Unit 2 or 3 Circ. pump pit area
- 5. Air being used in Makeup demineralizer area
- 6. Air being used in Unit 2 or 3 Condensate or Refueling Water tank area
- 7. Air being used in Unit 2 or 3 Containment building
- 8. Air being used in Control and Auxiliary building area
- 9. Air being used in Unit 2 or 3 Fuel handling building or for refueling
[+9d each, +he maximum]
.s e, t s- r.5 Reference (s) 7.11
- 1. SONGS 2 and 3: Operating Instruction, " Instrument Air and Service Air System", 5023-1-1, Section 6.5, p. 10.
l
-Section 7.0 Continued on Next Page-
Page 37 SONGS 2 and 3 April 29,1986 Points Available QUESTION 7.12 List three (3) parameters / symptoms available in the control room that would alert an operator to a loss of boron concentration control /inadvertant dilution. (3.0)
. ANSWER 7.12 DLo]
- 1. Unexplained power level. end/or Tavg increase. [+1.0]
C+ r *7
- 3. Unexplained increase in count rate when reactor is shutdown.
[+1.0]
Any 3' [i 3.0] M A x'"
- Reference (s) 7.12
- 1. SONGS 2 and 3: Operating Instruction, S023-13-12.
QUESTION 7.13 Following a LOCA plant conditions appear under control, SI flow has been stopped, and SIAS has been reset.
What two (2) conditions would require re-initiation of full SI TTow? (1.0)
ANSWER 7.13 p c-r C MA-w r Ta a " z o ' J- 1. tiss T w I Te o f'r rd r -
"a.rf, u o r 4 u 47 a
- 1. subcooling isdest [+0.5] 4. P2 A u r u nrcs THAU 1* *~ THAa e co 6t ' d
- 2. pressurizer level is 3Jest [+0.5]
z ,g..cncran H ts is L e~dic wresearric run ez %
Reference (s) 7.13 4 ^' y t. C. o.r] (Ac H
- 1. SONGS 2 and 3: Emergency Operating Instruction, S023-12-1,
" Standard Post Trip Action," 5, p. 5.
-Section 7.0 Continued on Next Page-
Page 38 SONGS 2 and 3 April 29,1986 Points Available 00ESTION 7.14 What would be the sequence of events and the temperature at which they occur, if the CVCS letdown heat exchanger temperature controller failed low and went undetected /no operator action? (2.0) 4 ANSWER 7.14
(* c. s-3 [* A d 145'FAautomatically bypass the ion exchangers4and isolate flow to the boronometera and radiation monitor.
M,
- c. e. r]
~470*f7UtbmatT&lly Q c) 1solat~e ietdoW Reference (s) 7.14
- 1. SONGS Z and 3: Operatino Instruction, "CVCS Charging and Letdown", S023-3-2.1, Section 6.1.13 Notes 1, 2, and 3,
- p. 7.
QUESTION 7.15 Explain why instrument air should never be used to supply air to portable breathing apparatus. (1.0)
ANSWER 7.15 Because of potential nitrogen contamination [+0.5] from the nitrogen backup system [+0.5].
Reference (s) 7.15
- 1. SONGS 2 and 3: Operating Instruction, " Instrument Air and Service Air System", S023-1-1, section 4.6, p. 4.
-Section 7.0 Continued on Next Page-y - -,-
. . . - . -y. -. -,_qqm m -p4 , - -ga,y3-.~mn-m.-
Page 39 SONGS 2 and 3 April 29,1986 Points Available QUESTION 7.16 Explain why the main turbine shaft should not be brought to a standstill with steam on the turbine steam seal glands. (1,0)
ANSWER 7.16 To avoid creating hot spots in the turbine steam seal packing g1 ands, [+1.0] tox& w: r n M r' D4'"A G i Auo .rH A f r B '"^'C E'#3 p s. o] m A s s
- M Reference (s) 7.16
- 1. SONGS 2 and 3: Operation Instruction, " Establishing Condenser Vacuum", 5023-10-7, Section 4.1, p. 4.
QUESTION 7.17 Operating Instruction 5023-3-2.7, Safety Injection System Operation, instructs the operator not to operate the HPSI pumps longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at any one period of time with flow only through the minimum recirculation line. (Does not apply in a post-accident situation.) Explain the reason for this instruction. (1.0)
ANSWER 7.17 To preclude possible bearing damage. [+1.0]
pp am Pis.s k p ofe,e c w ac 04e A G i @ I. o]
Dl#3 * #"'"
- Reference (s) 7.17
- 1. SONGS 2 and 3: Operating Instruction, " Safety Injection System Operation", 5023-3-2.7, Section 4.3, p. 4.
-Section 7.0 Continued on Next Page-
Page 40 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 7.18 Below what temperature must the reactor coolant system be when hydrazine is added to the RCS? (0.5)
ANSWER 7.18 250*F + 10*F [+0.5]
Reference (s) 7.18
- 1. SONGS 2 and 3: Operating Instruction, "CVCS Chemical l Addition Tank Operation", S023-3-2.3, Section 4.3, p. 2.
QUESTION 7.19 In the functional recovery of RCS inventory, what might result from rapid operation of letdown flow control valves LV-0110A and B7 (1.0)
ANSWER 7.19 ,, g g, , e t o s o - c May result in exceeding the 650 psig setpoint of PSV-9206A [+1.0]
V A */ (c~fetr e J FLJruoat
- d L A f'* O o fis s a s o f I. V- o l'
- 4 [* l *]
Reference (s) 7.19 pg) m a x,4, v%
- 1. SONGS 2 and 3: Emergency Operating Instruction, 5023-12-10, p. 11.
-Section 7.0 Continued on Next Page-
Page 41 SONGS 2 and 3 April 29, 1986 4
Points Available QUESTION 7.20 i Explain why you should not operate the charging system with simultaneous alignment to both HPSI headers. (1.0)
ANSWER 7.20 Will violate train separation [+1.0]
Reference (s) 7.20 i 1. SONGS 2 and 3: . Emergency Operating Instruction, 2 S023-12-10, p. 4.
I
-End of Section 7.0-l 4
)
- I i
l
. - = - _ . _ . - . - - , , . . - - . -. .. . - - - _ - . - - - - . , - , , - __
s
. Page 42 SONGS 2 and 3 April 29,1986
' Points
,1 Available 8.0 ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (25.0)
! Complete QUESTIONS 8.01 through 8.05 by " filling-in the blanks".
i QUESTION 8.01 Unit 2 containment penetration valves are (color) labelled valves and require verification of their position when repositioned. (1.0)
]
ANSWER 8.01 I
red [+0.5]
independent g [+0.5]
980 tHien Reference (s) 8.01 j 1. SONGS 2 and 3: Operating Instruction S02-0-17,
{ Section 6.1.2.1, p. 4.
i I OVESTION 8.02 1
The Operating Instruction " Engineered Safety Features Actuation l System (ESFAS) Operation" covers the steps to verify the
!' operation of the ESFAS. This verification is necessary to meet a Technical Specification and hence, must be completed prior to entering mode from mode . To de-energize an 1 ESFAS auxiliary relay cabinet, an Form must j have been processed and approved per S023-0-13. (1.0)
- ANSWER 8.02 i
4 from 5 [+0.5]
Equipment Controln [+0.5] ;
i 1
or W AR Reference (s) 8.02 3 1. SONGS 2 and 3: Operating Instruction, " Engineered Safety Features Actuation System (ESFAS) Operation", S023-3-2.22, pp. 3-4.
4
-Section 8.0 Continued on Next Page-
)
i
{
-- _._ _ _ _ - - s_s, _ _ _ _ _ _ . , _ , , _ _ . . , , _ . _ . , _ _ , _ . . _ . . _ _ , . _ _ . , . _ _ _ _ , , , , _ - _ _ _ _ _ _ _ _ . _ _ _ , _ , _ . _ _ . _ _ _ _ . . . _ , ,
l l
l i
Page 43 SONGS 2 and 3 ;
- April 29, 1986 Points Available 00ESTION 8.03 In Mode 1 at Unit 2, the LCO for the Auxiliary Feedwater System requires that at least (how many) independent Steam-Generator Auxiliary Feedwater Pumps and associated flow paths shall be operable. The bases for this LCO is that the Auxiliary Feedwater System ensures that
. (1.5)
ANSWER 8.03 3 [+0.5]
the RCS can be cooled-down to less than 350*F from normal l operating power. [+ conditions in the event of a total loss of off-site 1.0]
Reference (s) 8.03
- 1. SONGS 2 and 3: SONGS Unit 2 Safety Technical Specifica-tion, Bases, Auxiliary Feedwater System, Section 3/4.7.1.2,
- p. 8 3/4 7-2.
i 1
-Section 8.0 Continued on Next Page-
Page 44 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 8.04
- a. At SONGS Unit 2, the Technical Specifications specify an allowable peak linear heat rate for operation in Mode 1.
At BOL, this limit is (12,14,or
- 16) kW/ft, while at EOL it is (12,14, or 16) kW/ft. (1.0)
- b. One method of determining that this limit is being met requires verification that the ASI is within its limits.
'If ASI was 0.0, then operation at a maximum of %
of rated thermal power would be allowed. (0.5)
ANSWER 8.04 o f- 11, '1
- a. 14 A ^+0. 5' 14 A l+0.5l
- b. 100% [+0.5]
I Reference (s) 8.04
- 1. 50NGS 2 and 3: SONGS Unit 2 Safety Technical Specifica-1 tions, Power Distribution Limits, Section 1.2.1.4. 2,r,/
1
-Section 8.0 Continued on Next Page-t
Page 45 SONGS 2 and 3 April 29,1986 J
Points Available QUESTION 8.05 The three (3) characters of the Event Code (e.g., Al-1, D2-4, etc.) designate the , the ,
and the , respectively. (1.5)
ANSWER 8.05
- 1. Event category [+0.5]
- 2. Emergency action level [+0.5]
- 3. Initiating condition [+0.5]
l Reference (s) 8.05
- 1. Songs 2 and 3: EPIP S023-V111-1, p. 3.
4 1
-Section 8.0 Continued on Next Page- )
l
Page 46 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 8.06 Provide the Unit 2 Technical Specification definition of shutdown margin. (2.0)
ANSWER 8.06 1 1
Shutdown margin shall be the instantaneous amount of reactivity
[+0.5j by which the reactor is subcritical or would be subcritical from its present condition [+0.5] assuming 1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn [+0.5],
and 2) no change in part length control element assembly position
[+0.5]
Reference (s) 8.06
- 1. SONGS 2 and 3: Unit 2 Technical Specification, Definition
" Shutdown Margin", p. 1-5.
-Section 8.0 Continued on Next Page-
i l
f Page 47 SONGS 2 and 3 April 29, 1986 Points Available 1
i QUESTION 8.07 Complete the following table. (3.0)
Mode Reactivity, K,ff % Power T,yg
- 1. Power Operation 2 0.99 )5 2 350'F l 2. Startup
- 3. Hot Standby
- 4. Hot Shutdown 0
- 5. Cold Shutdown 0
- 6. Refueling 0 ANSWER 8.07
- Mode Reactivity, K,ff % Power T,yg
- 1. Power Operation 2 0.99 )5 2 350'F
- 2. Startup 2 0.99 55 2 350'F l 3. Hot Standby ( 0.99 0 2 350*F
- 4. Hot Shutdown ( 0.99 0 350*F)T,yg>200'F
- 5. Cold Shutdown ( 0.99 0 s 200'F j 6. Refueling ** 5 0.95 0 s 140'F
[+0.25] each Reference (s) 8.07
! 1. SONGS 2 and 3: Station Order 5023-0-3, p.1.
- l
-Section 8.0 Continued on Next Page-
Page 48 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 8.08 If there is an area within Unit 2 which is accessible to person-nei, in which the radiation level is such that a person could receive to a major portion of the body in one hour a dose greater than 1000 mrem, and in which no enclosure exists (or could
! reasonably be constructed) to deny access by locks, then i special provisions'are required according to the Technical Specifications. List four (4) of these requirements. (1.0)
ANSWER 8.08
- 1. rope-off or barricade the area
- 2. post the area in a conspicuous manner j 3. provide a flashing light
- 4. entrance shall be controlled by a RWP
- 5. continuous surveillance Any four (4) [+0.25 each, +1.0 maximum]
! Reference (s) 8.08
-Section 8.0 Continued on Next Page-
Page 49 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 8.09 The Technical Specifications for Unit 2 place a lower limit on T of 520'F. What are the four (4) considerations in the basiYCfor this LC07 (2.0) i ANSWER 8.09 This limitation is required to ensure:
i 1. the moderator temperature coefficient is within its analyzed I temperature range 1 2. the protective instrumentation is within its normal operating range
- 3. the pressurizer is capable of being in an OPERABLE status j with a steam bubble
- 4. the reactor pressure vessel is above its minimum RT NDT temperature.
[+0.5each]
Reference (s) 8.09
- 1. SONGS 2 and 3: SONGS Unit 2 Technical Specification, Section 4.1.1.4, p. 3/4 1-2.
i 4
f
_,,.._..,,_,.-.n, -- - - _ . - . - - . - - - . , - , , .,
I Page 50 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 8.10 i
Assume a Safety Limit Violation has occurred at Unit 2. Accord-ing to the Unit 2 Technical Specifications four (4) actions must be taken. List two (2). (2.0)
ANSWER 8.10
- 1. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Manager of Nuclear Operations and the NSG Chairman shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the OSRG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- 3. The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuclear Operations and the NSG within 14 days of the violation.
, l
- 4. Critical operation of the unit shall not be resumed until authorized by the Commission.
Any two (2) [+1.0 each, +2.0 maximum]
Reference (s) 8.10
- 1. SONGS 2 and 3: SONGS Unit 2 Technical Specifications, Section 6.7, p. 6-13.
-Section 8.0 Continued on Next Page-
Page 51 SONGS 2 and 3 April 29,1986 Points Available OVESTION 8.11 Define IDENTIFIED LEAKAGE by listing the three (3) types. (3.0)
ANSWER 8.11
- 1. Leakage (except CONTROLLED LEAKAGE) into closed systems from pump seals or valve packing that are captured and conducted to a sump or collecting tank [+1.0]
- 2. Leakage into containment atmosphere from specifically known sources but not PRESSURE BOUNDARY LEAKAGE [+1.0]
- 3. RCS leakage through a steam generator to the secondary system [+1.0]
Reference (s) 8.11
-Section 8.0 Continued on Next Page-
. ~ . . -_-
Page 52
- SONGS 2 and 3 April 29, 1986 Points Available
! QUESTION 8.12 i
l Unit 2 Technical Specification 3.7.2.1 requires that the tempera-ture of both the primary and secondary coolants be greater than 70*F when the pressure of either coolant in the Steam Generator is greater than 200 psig. What is the basis for this specification? (1.0) 1 ANSWER 8.12 l
1 Conditions that could produce brittle fracture must be prevented
! [+1.0]
Reference (s) 8.12 I 1. SONGS 2 and 3: SONGS Unit 1 Technical Specification, Section 3/4.7.2, p. 3/4 7-13.
- p. 3/4 7-3.
i l
I 1
4 d
-Section 8.0 Continued on Next Page-
Page 53 SONGS 2 and 3 April 29,1986 Points Available t
QUESTION 8.13 I According to Unit 2 Technical Specifications, two (2) separate and independent D/G sets are required. Each D/G syr' m must meet three (3) requirements relating to the availability of fuel. List two (2). (1.0)
ANSWER 8.13
- 1. engine-mounted fuel tanks [+0.3] containing 2 325 (250 to 400) gallons of fuel [+0.2]
- 2. fuel-storage system [+0.31 containing 2 47,000 (30,000 to 60,000) gallons of fuel [+0.2]
- 3. operable fuel-transfer pump [+0.5]
Any two (2) [+1.0 maximum]
Reference (s) 8.13
! 1. SONGS 2 and 3: SONGS Unit 2 Technical Specifications, Section 3/4 8.1, p. 3/4 8-1.
l l
-Section 8.0 Continued on Next Page-1
. _ . . _ . . _ _ , , _ _ . . _ , . . _ - _ - ..m._,, _ _ _ _ _ . . . _ _ -
Page 54 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 8.14
'I For Modes 1 through 6 any radioactive gaseous effluent release which results in a whole body dose at the exclusion area boundary greater than 2.0 mrem for the duration of the release is classified as an ALERT. Name three (3) radiation monitors that could provide indications of the release. (1.5)
ANSWER 8.14
- 1. Containment Airborne Monitor 4 0-7##Y "
- 2. Containment Purge Monitor st s - M
- f ,
- 3. Plant Vent Stack Airborne Monitor /i-7808
- 4. Condenser Air Ejector Wide Range Monitor 44 7 6 > *
- 5. Containment Purge or Plant Vent Stack Wide Range Monitor M-28'#
Any three (3) [+0.5 each, +1.5 maximum]
)ec.cp , e o mecog,- up a , a c ga, m ra r 7, y, ,gs, f. - F-n C AfAO Reference (s) 8.14
- 1. SONGS 2 and 3: S023-V111-1, pp.11-12 of 46.
-Section 8.0 Continued on Next Page-l
h Page 55 SONGS 2 and 3 April 29,1986 Points
- Available l
OVESTION 8.15 pf_y .5 .g., s
- M /-
Complete the following table, he , N ~6' (2.0)
Unit 2 Minimum Shift Crew Composition Position Number of Individuals Required to Fill Position Modes 1, 2, 3, and 4 Modes 5 and 6 SS 1 1 SRO R0 A0 STA Ah5WER 8.15 Modes 1, 2, 3, and 4 Modes 5 and 6 SS 1 1 SRO 1 None R0 2 1 A0 2 1 j STA 1 None
[+0.25 each, +2.0 maximum]
Reference (s) 8.15 i 1. SONGS 2 and 3: Unit 2 Technical Specification, 6.2.2, Table 6.2-1, p. 6-4.
-End of Section 8.0-
-End of Exam-1 l
, s 1 .
1 s
1 i.
EQUATION FORMULA AND PARAMETER SHEET
___________________________________7 :._______________________________..____
Where mi = m2
- (density)i(velocity)t(area)t = (density)2(velocity)2(area)2 i s KE="{2 PE = mgh PEl + KE y+P Vg y = PE,+KE - 2+P Y22 where V = specific volume P = pressure Q = mcp(Tout -Tin) Q = UA (T,y,-Tstm) Q = m(ht-h2) 4 P = Pg10(SUR)(t) P = Po et /T SUR = 26.06 T = (# - p) - i T p Q = p(# - p)
X,ff delta K = (K,ff-1) CR 3 (1-Keff1) = CR 2 (I-Keff2) CR=S/(1-K,ff)
(1-Keffi) '
f (1-K,ff) x 100%
SDM =
M = (1- A,eff2) K t
eft i
1 decay constant = in (2) = 0.693 A g = Ag e-(decay constant)x(t) t 1/2 1/2 Water Parameters Miscellan g f, Conversions 1 gallon = 8.345 lbs 1 Cr4 3. . x 10 10 dps
- I gallon = 3.78 liters 1kJs (R' bs 1 ft = 7.48 gallons I hp = 2.54 x 10 3Btu /hr 3 6 Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr 4 Density = 1 gm/cm 1 Btu = 778 ft-lbf i
Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 1 ft H 2O = 0.4335 lbf/in.2 X,ff = 0.08 sec w -, om,. m..- r- - ,,e m e - w-e-m -p. ~
Rev.1 i
1 OPERATIONS PHYSICS
SUMMARY
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FIGURE 3.3 HIP INVERSE BORON WORTH vs. BURNUP (CBC, 545'F1
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kc.V 3 TABLE 4.1 ROD WITHDRAVALS FROM POIL AT HFP Reactivity * (% AK/KO Inches Withdrawn BOC Bank 6 108.0 .14445 112.5 .13011 120.0 .10255 1
- 127.5 .07167
.04080 135.0
.01436 142.5 0 150.0
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ROD WITHDRAWAL AT HIP FRO *. IP0ll VITH HZP XENON Reactivity" (% AK/KO
- Inches Withdrawn BOC Bant 6 Bank 5
$ (OTPD) i 60.0 .5547E+00 E 0.0 .5467E+00 O.0 67.5 75.0 .5330E+00 2 0.0 .5203E+00 0.0 82.5 90.0 .5055E+00 0.0 4906E+00 0.0 97.5 T 4.5 105.0 4742E+00 1 .4502E+00
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19.5 J
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'l 42.0 150.0 .2866E+00 49.5
.2653E+00
( 60.0 67.5 150.0 150.0 .2505E+00 l
.d 75.0 150.0 .2357E+00 9 82.5 150.0 .2208E+00 150.0 .2060E+00
- 90.0 150.0 .1887E+00
_' 97.5 R;c cp, ,, ,
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- 105.0 .1487E-00 112.5 150.0 150.0 .1224E-00 3[p]y .-
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ROD WITHORAWALS FROM PDIL AT HFP
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Rev. 2 TABLE 6.1 FRACTIONAL EQUILIBRIUM XENON WORTH VS. POWER Power (%) Fractional Xe Worth 100 1.000 80
.946 60
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. TABLE 6.2 HFP EQUILIBRILH XENON WORTH (CBC. 583*F)
Burnup EFFD Xe Worth (% AK/K) 2.713 13.19 2.717 26.43 2.727 52.90 2.767 232.31 3 2.845 264.67 a =
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HFP EQUILIBRIUM XENON WORTH vs. CORE-AVERAGE x, Worth C5 &K/KI Temperature .Burnup 1 ppm 500 >PM 2100 PP5 (oF) (EFPD) 2.8036 2.5810 264.67 2.8826 545 2.9516 2.7037 264.67 3.0415 400 3.0226 2.7588 264.67 3 1198 260 3.0194 2.7555 264.67 3.1188 f 68 1
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4 TABLE 6.3 HFP EQUILIBRIUM XENON WORTH AT 545'F Xe Worth (% AK/K) 500 PPM 2100 PPM Burnup EFPD 1 PPM 2.8507 2.7744 2.5536 13.19 2.8513 2.7750 2.5540 26.43 t .
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Rev 3 TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP FROM 200%
TABLE 6.t NOTE: Prior to the trip, equilibrium conditions were assumed to be present.
HOURS BURNUP WINDOW IN WHICH TRIP OCCURRED AFTER (EFPD)
>100-165 >165-230 >230-EOC TRIP 0-35 >35-100 2.73 2.77 2.81 2.85 0 2.71 3.55 z 1 3.32 3.36 3.40 3.48 -
4.01 4,11 2 3.81 3.85 3.91 4.23 4.31 4.43 4.55 3 4.19 4.89 i-
- 4 4.47 4.52 4.60 4.74 4.67 4.73 4.82 4.97 5.13 5
4.81 4.87 4.96 5.13 5.29 6
4.89 4.95 5.04 5.22 5.39 7
- 4.91 4.98 5.08 5.25 5.44
- 8 4.90 4.97 5.07 5.25 5.43 9
4.86 4.92 5.02 5.20 5.39
.:- 10 4.78 4.84 4.95 5.13 5.31 11 4.69 4.75 4.85 5.03 5.21 12
( 13 4.57 4.64 4.73 4.91 5.09
- / 4.44 4.51 4.60 4.77 4.95 14 4.30 4.36 4.45 4.62 4.79
- 15 4.15 4.21 4.30 4.46- 4.63 16 ji 17 4.00 4.06 4.14 4.30 4.46 3.84 3.90 3.98 4.13 4.29 18 3.68 3.73 3.81 3.96 4.11 19 3.52 3.57 3.65 3.79 3.93 20 3.36 3.41 3.48 3.62 3.75 21 3.20 3.25 3.32 3.45 3.58
-- 22 3.05 3.09 3.16 3.28 3.41 23 2.94 3.00 3.12 3.24 24 2.90 2.75 2.79 2.85 2.96 3.07 y 25 2.64 2.70 2.81 2.92 26 2.61 2.47 2.50 2.56 2.66 2.76
- 27 2.33 2.37 2.42 2.51 2.61 28 2.20 2.24 2.28 2.37 2.47 29 2,33 30 2.08 2.11 2.16 2.24 31 1.96 1.99 2.03 2.11 2.20 1.88 1.92 1.99 2,07
- 32 1.85 33 1.74 1,77 1.81 1.88 1.95 34 1.64 1.66 1.70 1.77 1.84 1.60 1.66 1,73 35 1.54 1.56 36 1.45 1.47 1.50 1.56 1.62 37 1.36 1.38 1.41 1.47 1.53 i
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pev 2 TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP FROM TABLE 6.f' NOTE:
Prior to the trip, equilibrium conditions were assumed to be present.
HOURS BURNUP WINDOW IN WHICH TRIP OCCURRED (EFPD)
AFTER >165-230 >230-EOC
>35-200 >100-165 TRIP 0-35
] 1.32 1.38 1.43 38 1.28 1.30 1.29 1.34 d 39 1.20 1.22 1.24 1.26 1.17 1.21 40 1.12 1.05 1.14 1.07 1.09 1.14 1.18 1.11
- 41 1.02 1.06
- 42 0.99 1.00 1.00 1.04 0.92 0.94 0.96 0.97 43 0.90 0.93 44 0.87 0.88 0.87 0.91 0.81 0.82 0.84 0.85 45 0.82
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- 47 0.71 0.71 0.74 0.66 0.67 0.69 0.69 48 0.67 0.63 0.64 i D 49 0.62 0.58 0.59 0.60 0.62 0.65 0.61 1
(Y 50 51 52 0.54 0.50 0.47 0.55 0.51 0.48 0.56 0.52 0.49 0.58 0.54 0.51 0.57 0.53 0.49 j 53 0.47
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0.44 0.45 0.46 0.46 L 54 0.44 0.41 0.42 0.42 0.43 55 0.41 0.38 0.39 0.40 0.40 56 0.38 0.36 0.36 0.37 0.37 57 0.36 0.33 0.34 0.34 0.35 58 0.33 0.31 0.31 0.32 0.32 59 0.31 0.29 0.29 0.30 0.30 60 0.29 0.27 0.27 0.28 0.28
- 61 0.27 0.25 0.25 0.26 0.26 62 0.25 i .
0.23 0.24 0.24 0.24 4..4 63 0.23 0.23 64 0.22 0.22 0.22 0.23 0.20 0.20 0.21
~ ,; 65 0.20 0.20 0.21 66 0.19 0.19 0.19 0.20 0.18 0.18 0.18 0.18 67 0.17 0.18 68 0.16 0.17 0.16 0.17 i 0.15 0.15 0.16 0.16 69 0.15 0.14 0.14 0.15 0.15 70 0.14 0.14 71 0.13 0.13 0.13 0.14 0.12 0.12 0.13 72 0.12 0.12 0.'13 73 0.11 0.12 0.11 0.12 0.11 0.11 74 0.11 0.11 0.11 0.10 0.10 0.10 75 OD f
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CY 3 TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP TABLE 6.4 NOTE:
Prior to the trip, equilibrium conditions were assumed to be present.
BURNUP WINDOW IN WHICH TRIP OCCURRED HOURS (EFPD)
>165-230 >230-EOC AFTER >100-165 TRIP 0-35 >35-100 0.10 0.10 0.09 0.09 0.10 76 0.09 0.09 0.09 0.08 0.09 0.09 0.09 77 0.08 0.08 0.08 0.08 0.08 78 0.08 0,07 0.07 0.07 0.08 79 0.07 0.07 0.07 0.06 0.07 80 0.07 0.06 0.06 0.06 0.07 81 0.06 0.06 0.06 0.06 0.06 82 0.06 0.05 0.06 0.05 0.06 83 0.05 0.05 0.05 0.05 . 0.05 84 0.05 0.05 0.05 0.05 0.05 85 0.05 0.04 0.04 0.04 0.05
- 86 0.04
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ops pag y NCOBpage]-/8 W
Joe- uPToW U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: SONGS 2 and 3 (50-361/362)
Reactor Type: PWR-CE Date Administered: April 29, 1986 Examiner: Joe Upton, John Smith Candidate: Answer Key INSTRUCTIONS TO CANDIDATE:
Print your name on the line above marked " Candidate." The grade points available for each question are indicated within parentheses after each ques-tion. The passing grade is 70% in each of the four (4) categories and is 80%
for the total grade. . Use separate paper for your answers and write on only one (1) side of the paper, unless a specific question instructs you otherwise.
Staple this question package to your answer sheets. The examination questions and answers will be picked up six (6) hours after the examination was started.
Read the statement at the bottom of this page. When you have finished this examination, affirm the statement by signing your name.
Category % of Candidate's % of Value Total Score Cat. Value Category 25 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 25 25 2. Plant Design Including Safety and Emergency Systems 25 25 3. Instruments and Controls 25 25 4. Procedures - Normal, Abnormal, Emergency and Radiological Control 100 TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature I
t '
FURTHER INSTRUCTIONS TO CANDIDATE
- 1. At the end of the written examination package is a copy of a portion of the Operations Physics Summary for Unit 2 in Cycle 2. Use the tables and curves as appropriate.
- 2. At the end of the written examination package is a reference page containing equations, formulas, and constants. Use them as necessary.
- 3. Use the " Steam Tables" as necessary.
\,\ !
t Page 1 SONGS 2 and 3 1 April 29, 1986 Points Available
[
i 1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW (25.0)
QUESTIONS 1.01 through 1.07 are " multiple-choice" questions. For each question specify the letter designation for the phrase that provides the most correct statement.
QUESTION 1.01
> If the temperature of the metal casing of the Main Turbine, when
! measured in degrees Celsius, increased by 20*C, the metal-casing temperature, when measured in degrees Farenheit, would increase j by (1.0)
- (a.) 68'F.
(b.) 36'F.
! (c.) 18'F.
(d.) 11'F.
i f ANSWER 1.01 (b.) [+1.0]
i j Reference (s) 1.01 i SONGS 2 and 3: Units 2 and 3 Operations Training, Heat i 1.
j Transfer, Thermodynamics, and Fluid Flow Fundamentals,
! Revision 1, February 1981, Part A, Chapter 1, pp.15-17.
i 4
1 1
3 i
i I.
! -Section 1.0 Continued on Next Page-I i
L
j i i
j
}.
! Page 2 SONGS 2 and 3 April 29, 1986 ,
i Points Available 4
I QUESTION 1.02 If a tank contained 5 lbm of wet vapor of 96% quality, the l mass of water in the tank would be (1.0) !:
1 i
j (a.) 0.1 lbm.
i j (b.) 0.2 lbm.
i j (c.) 4.8 lbm.
i (d.) 4.94 lbm.
i
! ANSWER 1.02 I
i (b.) [+1.0) i Reference (s) 1.02 1 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Heat Transfer, Thermodynamics, and Fluid Flow Fundamentals, Revision 1, February 1981, Part A, Chapter 1, pp. 38-43.
b l
I i
i 1
I i
l l
j -Section 1.0 Continued on Next Page-i i
I l
t
i i Page 3 SONGS 2 and 3 April 29,1986 ,
Points Available i
QUESTION 1.03 Delayed neutrons are emitted through the radioactive-decay
, chain of (1.0) >
(a.) various fission-fragment nuclei and comprise less than 1%
of the total number of neutrons released in the fission s
process.
j (b.) various fission-fragment nuclei and appear, on the average, with more energy than the average energy associated with the neutrons produced immediately in the fission process.
(c.) various fission-fragment nuclei that have been produced f after a reactor shutdown from at-power conditions and 4 appear, on the average, with less energy than the average energy associated with the neutrons produced immediately
- in the fission process.
1 (d.) various f 3sion-fragment nuclei that are " neutron rich"
+ and that are in an excited state following the fissioning event and compose between 6 and 7% of the total number of neutrons released in the fission process.
ANSWER 1.03 j (a.) [+1.0]
Reference (s) 1.03
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor i Theory, Nuclear Physics and Core Operatino Characteristics Review Text, pp. 71-78.
I j 2. Palo Verde 1 and 2: Palo Verde Licensed Operator Training, j Reactor Theory, Pre-License Review Course NLC55, pp. 4.6, j 5.2, and Figure 4.12.
1
- 3. St. Lucie 1 and 2
- Reactor Physics Trainino Manual, j " Reactor Physics", pp. 7.2 7.2-8.
l l
-Section 1.0 Continued on Next Page-j i
l
3 .
1 i
Page 4 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 1.04 After a reactor trip from full power level, the negative startup
- l. rate approaches the same value independent of the shutdown margin I because (1.0) 1 I (a.) the decay rate associated with the reduction of the temperature of the fuel determines the long-term decay rate for the neutron flux.
I. (b.) most of the neutrons are " prompt" and hence the prompt i neutron diffusion time determines the long-term decay I rate for the neutron flux.
'l l (c.) the delayed neutron emitters with the shortest half-life determine the long-term decay rate for the neutron flux.
j j (d.) the delayed neutron emitters with the longest half-life determine the long-term decay rate for the neutron flux.
t j ANSWER 1.04 I
(d.) [+1.0]
I
! Reference (s) 1.04
- 1. SONGS 2 an.d 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operatina Characteristics Review Text, pp. 148-151.
I
- 2. Palo Verde 1 and 2: Palo Verde Licensed Operator Training, Reactor Theory, Pre-License Review Course NLC55, p.11.5
- and Figure 11.5.
- 3. GA: Syllabus & Trica Trainina Manual, " Reactor Kinetics",
GA Technologies Inc., p. 6-14.
J
! -Section 1.0 Continued on Next Page-
.i I
a l
I
Page 5 SONGS 2 and 3
. April 29,1986 I
Points I Available
. QUESTION 1.05 As the effective number of full-power hours of operation of will change and, hence, the stable the coreperiod reactor increases, that w )b'did result from the core having a small amount of positive reactivity will change; the changes are that (1.0) j
- i (a.) ),,, will increase and the reactor period will increase.
j (b.) ),,, will increase and the reactor period will decrease.
l (c.) ),,, will decrease and the reactor period will increase.
, (d.) ),,, will decrease and the reactor period will decrease.
z i j ANSWER 1.05 j (d.) [+1.0]
j Reference (s) 1.05 l 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operatina Characteristics Review Text, pp. 154-157.
1 1
i i
i I
- -Section 1.0 Continued on Next Page-l i
ri .
4 SONGS 2 and 3 Page 6 4
April 29, 1986 ,
Points Available
. QUESTION 1.06 Enthalpy, h, of a substance is a measure of (1.0) i (a.) the energy possessed by the substance due to its phase change from liquid to gas.
(b.) the energy possessed by the substance due to its temperature, pressure, and volume.
1 (c.) the internal energy of the substance.
i (d.) the amount of work energy applied to a substance to change J its pressure and volume from some reference values.
j ANSWER 1.06 I (b.) [+1.0]
i
- Reference (s) 1.06 I
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Heat j Transfer, Thermodynamics, and Fluid Flow Fundamentals,
' Revision 1, February 1981, Part A, Chapter 1, pp. 35-36.
4
(
i l
l
-Section 1.0 Continued on Next Page-l i
---,m.-, .,- , . - , - - ---i.-.-_-~----- - - - - - - - - . = , - + . - - - . - . - , ---ry ..._ ,,,,.y - , ,. ,.- .,_m- ., , , - 2 ---w-,--- . . . , - , -vo - - , - - -,.,
Page 7 SONGS 2 and 3 '
April 29, 1986 Points Available OVESTION 1.07 One of the characteristics of water is that it will hold gases dissolved in solution. Which of the following would DECREASE the concentration of dissolved gases in a quantity of water? (1.0)
(a.) increasing the pressure and/or lowering the temperature.
(b.) decreasing the pressure and/or lowering the temperature.
(c.) increasing the pressure and/or raising the temperature.
(d.) decreasing the pressure and/or raising the' temperature.
ANSWER 1.07 (d.) [+1.0]
Reference (s) 1.07
- 1. SONGS 2 and 3: System Description, " Condensate System",
SD-5023-240, Reviston 0, p. 5.
-Section 1.0 Continued on Next Page- l
i .
e Page 8 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 1.08 Consider that Steam Generator (S/G) No. 1 is clean and new and S/G No. 2 has heavy mineral deposits of the outer surfaces of the tubes. The power plant is at 100% of full power and all I levels and pressures are at the programmed values.
- a. Which loop has the higher T,yg? (0.5)
- b. Which S/G has the higher heat-transfer coefficient from the RCS to the secondary fluid? (0.5)
- c. Which S/G has the higher steam flowrate? (0.5)
- d. Which S/G has the higher thermal conductivity for the S/G tubes? (0.5)
ANSWER 1.08
- a. Loop 2 [+0.5]
- b. S/G #1 [+0.5]
- c. S/G #1 [+0.5]
- d. S/G #1 [+0.5]
Reference (s) 1.08
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Heat Transfer, Thermodynamics, and Fluid Flow Fundamentals, Revision 1, February 1981, Part A, Chapter 3, pp.104-118.
t I
-Section 1.0 Continued on Next Page-L _
Page 9 SONGS 2 and 3 April 29,1986 Points Available OUESTION 1.09 The turbine of the Auxiliary Feedwater (AFW) System is rated at 876 hp with steam supplied at a pressure of 1210 psia,
- a. When the AFW turbine is being supplied with 500 psia main steam, how much work can be supplied by the turbine? Assume thermodynamically ideal operation of the turbine. Express the answer in Btu /lbm. (2.0)
- b. If the turbine was receiving 260 Btu /lbm and was driving the AFW pump with a power of 600 hp, what would be the steam flowrate through the turbine? (1.0)
ANSWER 1.09
- a. h1 = 1205 Btu /lbm [+0.5 for using saturated conditions]
isentropic expansion [+0.5]
h2 = 955 Btu /lbm [+0.5 for using atmospheric pressure]
Ah = 250 Btu /lbm [+0.5 for 245 - 255 Btu /lbm]
- b. 600 hp x 2545 Bt hr = 1.53 M Btu /hr [+0.5 for conversion]
1 MBu r = 5,873 lbm/hr [+0.5 for 5,800 - 5,950 lbm/hr]
-Section 1.0 Continued on Next Page-
Page 10 SONGS 2 and 3 April 29,1986 Points Available Reference (s) 1.09
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Heat Transfer, Thermodynamics, and Fluid Flow Fundamentals, Revision 1, February 1981, Part A, Chapter 1, p.145-157.
- 2. SONGS 2 and 3: System Description, " Auxiliary Feedwater System", pp. 5, 30. '
)
-Section 1.0 Continued on Next Page-l
s Page 11 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 1.10 Figure 1.10 (00ESTION) shows the CEA Regulating Group Insertion Limits. Answer the following parts of this QUESTION with respect to that Figure.
- a. For continuous operation at 80% of full power for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with COLSS in-service, what is the acceptable range of CEA position for Group 67 (0.5)
- b. h is there an unacceptable or prohibited region of operation? State two (2) reasons. (1.0)
ANSWER 1.10
- a. 150 to 120 inches withdrawn [+0.5]
- b. 1.1 ensure that core-design peaking factors are not exceeded OR 1.2 ensure that the fuel burnup is sufficiently uniform AND 2.1 ensure that there is sufficient rod worth to safely shutdown the reactor OR 2.2 ensure that there is sufficient rod worth to be within the calculational envelop for shutdown with an ejected rod
[+0.5 for 1. and 2.]
- 2. s -
hn ass Y AtpC Afh W h
S ?
-Section 1.0 Continued on Next Page-
s ,
Page 12 SONGS 2 and 3 April 29,1986
, Points
. Available 1.0 joecR.s g _ _ -- --
u __ _ _l _ _
s _ _ ._ ._ -
_ _ _ly5 -
_ _ _A_ _ _ _ _ _ _
e.s _ l; _ _h _ _ _ _ _ _ __
g _ _
_go \ _ _ __ _ -
lv g _ _
_y .
4 g o.s -
gl" --- l; \
g 4 _,,Q \ _ _ _ TRANSIENT _
> INSERTION g es _ __lU;; ; _ __
_'N umii l!
- ~ ~ ~ - ~ -
$ 3 3 e.4 _ 2 h !, _
B 15 _ _ g z .- \ _ --
io l l" C E \ i
.i j g \
_l'!"
- u
= - -
\ """~
- \. ,
no on.'e - __
\.0 on.. __ _ _ _
e.i _ __ _ _ _ _ _ _ _ _ _ _ _ __
j - - . 80" GR. 6
- . /l i I l Gn. 5 Gn.4 e i e e 3 g l g g 150 120 90 60 30 0 150 120 90 l i
150 120 99 60 30 0 CE A WITil0R AWAL . INCllES i l
Figure 1.10 (0UESTION) !
Reference (s) 1.10
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 193-195.
- 2. SONGS 2 and 3: Technical Specifications, San Onofre Nuclear Generation Station, Unit No. 2, Docket No. 50-361, Appendix "A" to License No. NPF-10, February 1982, Section 3.1.3.6, pp. 3/4 1-22, 3/4 1-24.
-Section 1.0 Continued on ex Page-
, 3. s e n di.r 2 d .5 ' b /** O'"
A n,r fin ~ u.r n. .e Jh W'~f-&
g ., .. , pf_ '92, .ivrr-i6 64y.i'%
Ba f " ' ' ' ' -
. . - - , _ . . ,.---9 . -% , . - - . - w.,.i , .,
e Page 13 SONGS 2 and 3 April 29, 1986 Points Available The following statements apply to QUESTIONS 1.11, 1.12, 1.13, and 1.14.
The Unit 2 power plant has been operating continuously at a steady 100% of full power for 15 days. All control rods (CEAs) are fully withdrawn from the nuclear reactor core (AR0). All controlled parameters are equal to their respective programmed values or setpoints. The fuel-burnup status is that the core has reached 200 EFPD. The present boron concentration is 200 ppm. All systems are in AUTO control except for the CEAs which are in MANUAL SEQUENTIAL (MS).
QUESTION 1.11
- a. What is the expected value for the AT across the core? (0.5)
- b. At this point in the life of the core, the neutron flux might have an axial profile as shown below.
Why is there a peak in the top half of the core? Why is there a peak in the bottom half of the core? (1.5)
- c. If the shape and magnitude of the neutron flux was the same in the top half of the core as in the bottom half, what would be the ASI? (0.5)
- d. If some CEAs were partially inserted into the top half of the core, would ASI increase or decrease? h Iaf (0.5)
- e. What is the expected value for the Equilibrium _ Shape dex? (0.5)
' ~
( rf s.1" ,j) f an py&
a xM 9' 1 l
-Section 1.0 Continued on Next Page-I I
o Page 14 SONGS 2 and 3 April 29, 1986 Points Available ANSWER 1.11
- a. AT = TH-TC = 611 - 553 = 58'F [+0.5 for 55 - 61*F]
- b. With a fuel-burnup status of 200 EFPD, the core is near EOC (End-of-Cycle). At EOC, the U23s fuel has been dispropor-tionately burned-up in the bottom half of the core. This shift in the relative fuel concentration to the top half of the core is responsible for the peak in the top half of the core. [+0.75] At full power, the moderator density decreases with core height. The higher moderator density in the bottom half of the core is responsible for the thermal neutron-flux peak in the bottom half of the core.
[+0.75 for explanation of each peak.]
- c. zero [+0.5]
- d. increase [+0.5]
- e. Using Figure 7.1, ESI = +0.008 [+0.5]
Reference (s) 1.11
- 1. SONGS 2 and 3: System Description, " Reactor Coolant System," Figure 28.
- 2. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 194-203.
- 3. SONGS 2 and 3: Operations Physics Summary, " San Onofre Unit 2 Cycle 2", Revision 3, Figure 7.1.
-Section 1.0 Continued on Next Page-
Page 15 SONGS 2 and 3 April 29,1986 Points Available OVESTION 1.12
- a. If the flowrate of the primary coolant through the core was reduced, explain the effect that this would have on the AT across the core. (1.0)
- b. If the flowrate of the primary coolant through the core was reduced, explain the effect this would have on the axial neutron-flux shape. (1.0)
ANSWER 1.12
- a. If the flowrate was reduced, more heat would be added to the primary coolant as it passes through the core. This will raise the AT across the core. [+1.0] (An increase in the temperatures in the core will cause the power produced in the core to try to decrease. However, if the electrical output was to remain the same, the secondary system would adjust and an increase in the AT across the core would remain to offset the decrease in the flowrate of the primary coolant.)
- b. If the flowrate of the primary coolant was reduced, the temperatures in the core would rise. The increase in temperature would be greater in the top half of the core than in the bottom half. This would cause the neutron flux distribution to shjft to the bottom of the. core. [+1.0]
t a. nst ske .4 en + &W Reference (s) 1.12
- 1. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor ,
Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 194-203.
- 2. SONGS 2 and 3: Units 2 and 3 Operations Training, Heat Transfer, Thermodynamics, and Fluid Flow Fundamentals, Revision 1, February 1981, Part B, Chapter 3, pp.189-203/+'-
-Section 1.0 Continued on Next Page-
Page 16 SONGS 2 and 3 i
April 29,1986 Points Available 1
OUESTION 1.13 If the regulating control rods (CEAs) were inserted while in
^
the MANUAL SEQUENTIAL (MS) mode until Group 6 is at 108 inches
- withdrawn and if the boron concentration was adjusted to maintain the power level of 100%, what would be the new concentration
]
of boron required for steady operation? Neglect any effect from changes in the xenon or samarium concentration. Assume
! the CEA worths do not change with core age. (1.5)
ANSWER 1.13 Using Table 4.1 or Figure 4.1, f ,, f g./I go [/[ ,
! Ap = 0.144 %Ak/k for BOC.
[+0.5)
Using Figure 3.1, e4 .e // 97. 2 inverse boron worth = 87 ppm /%Ak/k. [+0.5]
Hence, 1
A ppm = (87)(0.144)
= 12.5 ppm
)
and 1 new boron' concentration = 200 - 12.5
= 187.5 ppm [+0.5]
< Reference (s) 1.13
- 1. SONGS 2 and 3: Operations Physics Summary, " San Onofre Unit 2 Cycle 2", Revision 3, Figures 3.1, 4.1, and Table 4.1.
i
-Section 1.0 Continued on Next Page-4 1
l
l i
Page 17 SONGS 2 and 3 April 29,1986 Points Available QUESTION 1.14 The power plant is to be taken from 100% to 80% of full power.
- a. What would be the magnitude of the change in reactivity due to the temperature changes associated with this power change? Specify whether this change adds or removes reactivity from the core. Assume that the core burnup status does not affect this reactivity change. (1.0)
- b. If the core burnup status did affect this reactivity change, how would increasing the amount of burnup affect your answer to "a."? (0.5)
- c. If this maneuver from 100% to 80% of full power took 20 minutes, make a sketch of xenon worth as a function of time. Show time beginning from the point-in-time of decreasing power and for the next 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. State the values of xenon worth for initial conditions, final conditions, and peaks or valleys. (Use Core Data Book sheets provided.) (1.5)
ANSWER 1.14
- a. Using Figure 5.1, 9/ ,2f p 4 3%[ tl(([
5 power defect = fi//%Ak/k
[+0.5)
Reactivity has been ADDED. [+0.5]
- b. Increasing the core burnup would result in more reactivity
[+0.5]
beigdded to the core for this 20% drop ligpower.
( sp L medish o m )
-Section 1.0 Continued on Next Page-
Page 18 SONGS 2 and 3 April 29, 1986 ,
Points Available
- c. 3.2 2.8 ,
' - 2.65 0 10 20 30 40 50
[+0.5 for initial equilibrium of 2.74 to 2.86]
[+0.5 for shape]
[+0.5 for final equilibrium of 2.59 to 2.71]
Reference (s) 1.14
- 1. SONGS 2 and 3: Operations Physics Summary, " San Onofre Unit 2 Cycle 2", Revision 3, Figure 5.1; Tables 6.1, 6.2, 6.3, and 6.4; Figures 6.2 and 6.4.
- 2. SONGS 2 and 3: Units 2 and 3 Operations Training, Reactor Theory, Nuclear Physics and Core Operating Characteristics Review Text, pp. 204-207.
A 1790 , 173 */ Y'Y ,
-Section 1.0 Continued on Next Page-l l
Page 19 SONGS 2 and 3 April 29,1986 Points Available OVESTION 1.15 Figure 1.15 (00ESTION) shows the design specifications for an Auxiliary Feedwater Pump. How many gpm can one such pump supply if the steam generator pressure is at the pressure setpoint of the second lowest main steam safety valve. (1.5)
ANSWER 1.15
- h&
pump head =
4 ft H 2O [+0.5 for 1107 psia)
= 2550 ft H20 [+0.5 for 2535 to 2565]
From Figure 1.15 (QUESTION),
2550 ft H 2O -> 1100 gpm [+0.5 for 1050 to 1150]
Reference (s) 1.15 SONGS 2 and 3: System Descriptions, " Auxiliary Feedwater 1.
System", p. 2 and Figure 6.
- 2. SONGS 2 and 3: System Descriptions, " Main and Reheat Steam System", p. 15.
-Section 1.0 Continued on Next Page-i i _- - ..
i l i
Page 20 SONGS 2 and 3 l April 29,1986 Points Available
/
Nose: Dem o clu g 1 con us 40 2
- a. g
, ress aequir.4 J 3, j i !
0
[30 i
3200 -
i . ._ .J.Pusan Efficiency amo --
1 -
I'2s00--- . .
He_ad_ Capacity,_, j .o ,t 3
2 .00--
30{
3 V 2400-- - - .. __ . . . . _ _ . . _ _ _ 40 i E
2200-- - - - -
. - . _ . . _ . . . _ . _ _ . 1200 30 j sur e sp.eme crmer 1.m s00 20-t 400 10 l
l' l .
I O O O 200 400 s00 300 1000 1200 Gdeas Per Minute Figure 1.15 (0UESTION) ;
1
-End of Section 1.0-
Page 21 SONGS 2 and 3 April 29, 1986 Points Available 2.0 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (25.0)
QUESTIONS 2.01 and 2.02 are " multiple-choice questions. For each question specify the letter designation for the phrase that provides
- the most correct statement.
QUESTION 2.01 During Mode 1 operation with all systems / components operable and aligned in the normal manner, the four (4) motor-operated isolation valves for the Safety Injection Tanks (SITS) are (1.0)
(a.) CLOSED to isolate the SITS from the RCS but receive an OPEN signal on a SIAS.
jd>dC' ,
(b.) interlocked with Pressurizer pressure such that, if the ; ,3- gr RCS pressure is 1 500 psig at Unit 3, the valves would be "*"
automatically CLOSED.
(c.) interlocked with Pressurizer pressure such that, if the RCS pressure is ( 650 psig at Unit 3, the valves would be automatically CLOSED.
(d.) provided with position indications which would provide an alarm in the control room if the valves are not fully OPEN when RCS pressure is 2 500 psig.
ANSWER 2.01 (d.) [+1.0]
Reference (s) 2.01
- 1. SONGS 2 and 3: System Descriptions, " Safety Injection and Shutdown Cooling System", pp. 15, 45, 47.
-Section 2.0 Continued on Next Page-1
Page 22 SONGS 2 and 3 April 29, 1986 Points Available 00ESTION 2.02 The Safety Injection System consists of three (3) HPSI pumps; pump No. 1 (P017), pump No. 2 (P019) and pump No. 3 (P018),
and the necessary piping and valves such that, upon an SIAS (1.0)
(a.) pump No. I would normally be aligned for injection only into Loops 2A and IB and pump No. 2 would be aligned for injection only into Loops IA and 28.
(b.) pump No. 3 is provided as an installed spare and could be aligned to either or both high-pressure headers.
(c.) pumps No I and No. 2 each feed a high-pressura header and Loops 1A, IB, 2A, and 2B each receive flow from both headers.
(d.) pump No. I could readily be aligned for hot-leg injection into RC Loop 1 only and pump No. 2 for RC Loop 2 only.
ANSWER 2.02 (c.) [+1.0]
Reference (s) 2.02
- 1. SONGS 2 and 3: System Descriptions, " Safety Injection and Shutdo'wn Cooling System", p. 4.
- 2. SONGS 2 and 3: P&I Diagram, " Safety Injection System, System No. 1204", No. 40112A-6 and 40112C-3.
-Section 2.0 Continued on Next Page-
Page 23 SONGS 2 and 3 April 29, 1986 Points Available 00ESTION 2.03 Answer TRUE or FALSE. Each Main Feedwater Pump is designed such that its capacity alone would allow continued full power operation of the power plant following the loss of one (1) of the Heater Drain Pumps. (0.5)
ANSWER 2.03 FALsc IRUE [+0.5]
Reference (s) 2.03
- 1. SONGS 2 and 3: System Description, " Main Feed Pump, Turbine and Turbine Controls", SD-S023-260, Section 1.2.2, p. 3.
QUESTION 2.04 Answer TRUE or FALSE. Condensate storage tanks T-120 and T-121 are used solely for providing water to the Auxiliary Feedwater System for plant cooldown. (0.5)
ANSWER 2.04 FALSE [+0.5] Only T-121 seismic category I tank. T-120 is used for many things.
Reference (s) 2.04
- 1. SONGS 2 and 3: System Description, " Condensate Storage and Transfer System", Section I-A, p. 1.
-Section 2.0 Continued on Next Page-
Page 24 SONGS 2 and 3 April 29, 1986
.?. d >~ e. . a-,.d 4. +
MaI. #/ 4* ~f Av a le e dar { A pus g wd TsAjeM OUESTION 2.05 g ,A ,, 4 g _ [ % d Answer the following parts of this QUESTION that refer to the
" Turbine Gland Sealing System".
a/ To where is the high-pressure leak-off from the HP-turbine
/ throttle and stop valves directed? (0.5)
[ To where is the high-pressure leak-off from the LP-turbine (0,5) throttle and stop valves directed?
- c. To where is the excess sealing steam in the low-pressure glands of the HP-turbine throttle valves, LP-turbine stop and throttle valves, HP-turbine and LP-turbine directed? (0.5)
- d. Why are the Main-Turbine stop and governor valves designed to be sealed with steam instead of packing? (0.5)
ANSWER 2.05
- c. to the gland-steam condenser [+0.5]
- d. to allow for ease of movement of the valve stem [+0.5]
(This design allows the valves to be quick acting, with less chance of " hanging-up" and, in the case of the throttle valves, allows for finer control.)
Reference (s) 2.05
- 1. SONGS 2 and 3: System Description, " Turbine Gland Sealing l System", Section I-A, pp. 1-2.
l 1
-Section 2.0 Continued on Ne'xt Page-
Page 25 SONGS 2 and 3 April 29,1986 Points Available QUESTION 2.06 What three (3) valves automatically OPEN upon a start signal to the Salt Water Cooling Pump System? (1.5)
ANSWER 2.06
- a. bearing seal water supply control valve [+0.5]
- b. pump discharge valve [+0.5]
- c. CCW heat exchanger salt water cooling outlet valve to the circulating water box culvert [+0.5]
Reference (s) 2.06
- 1. SONGS 2 and 3: System Description, " Salt Water Cooling -
System", SD-5023-410, Section 2.3, p. 13.
QUESTION 2.07 A connection is provided from the discharge side of the CVCS charging pumps to the HPSI header. What is the primary purpose of this connection, and in what condition must the RCS be in to carry out the purpose? (1.0)
ANSWER 2.07 i
x to allow testing of the operability of the safety injection check valves upstream of the RCS injection nozzles [+0.5] when
- the RCS is pressurized [+0.5]
lf , p$ N k lW bl Reference (s) 2.07 [ #
PFs A > ^ W# -
- 1. SONGS 2 and 3: System Description, " Safety Injection and Shutdown Cooling System", Section III-A2, p. 40.
-Section 2.0 Continued on Next Page-
Page 26 SONGS 2 and 3 April 29,1986 Points i
Available QUESTION 2.08 Shown in Figure 2.08 (0UESTION) is a one-line diagram of RCS.
Draw on this figure the Reactor Coolant Gas Vent System (RCGVS).
Show the connections to the gas spaces of the RCS, the ,,/,,,; ,/
connections for releasing the gases, and show six (6) motor-operated valves that control the flow from the gas spaces to the release points. (2.0) i ANSWER 2.08 See Figure 2.08 (ANSWER). [+2.0]
Reference (s) 2.08
- 1. SONGS 2 and 3: System Description, " Pressurizer and Pressurizer Control System", Section I-CS, pp. 5-6 and Figure 3.
1
-Section 2.0 Continued on Next Page-t
Page 27 SONGS 2 and 3 April 29,1986 u
" fI Points Available I
I II 1'jst
!n,! . !. .;):
I 3:u.
- - n t; f I
- r.I i l C. 1
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50 asi alj I-3
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- tg=.
g :t -
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- 5
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t.
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5
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- t
-Section 2.0 Continued on Next Page-
Page 28 SONGS 2 and 3 April 29,1986 1 4 Points f
h
, .I,
~ @$i,Z.g:
{}
f Available i .. .. i. r-l! "i .. ;; Fit' 53
- ')E si- E! :l:ij 3 ,
- c; a ;
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.=
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g ,a 33* y ,3 m d a I g,t :* *. !:
- I& 3 c.:~.=
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= H.
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.- y
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!: ef .gf
- r
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- is t!! i, 11! En
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e a 3 -
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o . r.--o-i .b q I ,
n : ,, '
5
- I 5 f
c -
36 m n I m' t' O C:
y
.4 l S. i -
" 2
- - .g
(,
s "II "l%v$2"i .I I
az . Ea
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r
- c. ., te
=- -
- " +
Loc.- i:.
- z! cc t.@ ';;' +. j o
(v . :: m -
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c.r ' i .2to* *45 ij !!s. W
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t.' -1; - i::: e.rI: y 6 0- ,. :. -
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-Section 2.0 Continued on Next Page-
Page 29 SONGS 2 and 3 April 29,1986 Points Available QUESTION 2.09 A change of 1% in the Pressurizer level is equivalent to how many gallons? Assuming an inside diameter of 94.5 in., what is the approximate change in level for this volume? (1.0)
^
ANSWER 2.09 ff g ,a - 7d 55.2 gallons [+0.g 4 , ig-dp ((
3 Outside diameter = 106.5 in. 4, ,f-Approximately 6 in. wall = c,fgr.t'9)
Inside diameter = 94.5 in. -= //R 7
. 7013.8 in.3/in. = 30.36 gallons /in.
, f. g g SA k.
2 3 3 = ~ 1.8 in. [+0.5 7,7
= Pbpiesb
-vr(W # 5)2fix' = GW [b Reference (s) 2.09
+.s/
- 1. SONGS 2 and 3: Training System Description, " Pressurizer and Pressurizer Control System", Figure 1.
- 2. SONGS 2 and 3: Operator Surveillance Test, S023-3-3.37, "RCS Inventory Balance", Attachment 9.6, p. 2.
CD ,ci. g-
- n, :: o l . >
I , . . . . 7 .1 I '77C 7'
_~ ~
L. - , .99 7 > -" , . =
pr!(r' -;
/,,y:* - 7. C -? j~
-Section 2.0 Continued on Next Page-
Page 30 SONGS 2 and 3 April 29,1986 Points Available OUESTION 2.10 List six (6) of the valve types that should automatically CLOSE on the initiation of a main steam isolation signal (MSIS). Do not include the MSIVs in the list. (By value type it is meant that you should NOT list as more than one item valves that have the same function; i.e., MSIV HV-8204 and HV-8205 would be one valve type). (3.0)
ANSWER 2.10
- 1. S/G feedwater isolation valve E A /
- 2. S/G blowdown isolation valve foWM V '
- 3. S/G water-sample isolation valve y ,b- f.eeh N
- 4. MSIV bypass-valve isolation valve fm " *D
- 5. Main-steam drain isolation valve (fb v
W *
- 6. Atmospheric-dump valve o f"
& Y) $" y g
- 7. Auxiliary feedwater pump turbine steam-supply valves
[+0.5 each, +3.0 max.]
Reference (s) 2.10
- 1. SONGS 2 and 3: System Description, " Main and Reheat Steam System", SD-5023-160, Section 2.3.2, p. 36 j f F.
l l
l
-Section 2.0 Continued on Next Page-
Page 31 SONGS 2 and 3 April 29,1986 Points Available OUESTION 2.11 Answer the following parts of this QUESTION which refer to the Main and Reheat Steam System,
- a. Specify the number of safety valves associated with Steam Generator E088 and the range (minimum and maximum) of the setpoints. (1.0)
- b. Draw the one-line diagram for S/G E088 showing the main-steam line connections for the safety valves. Indicate the location of containment penetration and the MSIV. (1.0)
- c. Indicate on the one-line diagram the point at which steam is fed to the auxiliary feedwater pump turbine. What would be the position (OPEN, CLOSED) of the isolation valve between the main steam line and the auxiliary feedwater pump turbine under the conditions of an EFAS? (1.0)
ANSWER 2.11
- a. 9 [+0.5]
1100 to 1155 psia [+0.5]
- b. I (+0.25)
I I I I-$tN""
Aux Feed l lII _ Pump Turbine
(+0.25) (+0.5)
N M
(+0.25) gy,j3)
L ;
\ oS7, V -Section 2.0 Continued on Next Page-
9 Page 32 SONGS 2 and 3 April 29,1986 Points Available
- c. See Figure 2.11 (Answer) (b.) above [+0.5]
Upon an EFAS, the isolation valve should OPEN [+0.5].
Reference (s) 2.11
- 1. SONGS 2 and 3: System Description, " Main and Reheat Steam System", SD-5023-160, Revision 0, pp. 14-16.
- 2. SONGS 2 and 3: P&I Diaaram, " Main Steam System", System No. 1301, 40141C-9.
t i
i l
-Section 2.0 Continued on Next Page-l 1
1
-. ,. , - _ _ . _ . _ _ _ _ . .__ - .-_-. _ _ , _ _ _ - , . _1
I Page 33 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 2.12 Describe the two (2) design modifications of the steam generator feed ring and connected piping that prevent the feed ring and connected piping from draining rapidly whenever the steam generator water level drops below the feed ring. (1.0)
ANSWER 2.12 The discharge nozzles are located on top of the feed ring [+0.5]
and the connected piping is sloped away from the feed ring
[+0.5].
Reference (s) 2.12
- 1. SONGS 2 and 3: System Description, " Auxiliary Feedwater System", Section I-A, p. 3.
-Section 2.0 Continued on Next Page-- l
Page 34 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 2.13 Answer the following QUESTION which refers to the Main Turbine System.
When shuting-down the Main Turbine as prescribed by procedure, at approximately what power level (% power) are the turbine drain valves opened and at approximately what power level are the unit auxiliaries transferred? (1.0)
ANSWER 2.13 20% 1 5% [+0.5]
10% 1 5% [+0.5]
Reference (s) 2.13
- 1. SONGS 2 and 3: System Description, " Main Turbine System",
SD-S023-180, Revision 0, p. 77.
QUESTION 2.14 What provides the closing force for the main feedwater block valve? (0.5)
ANSWER 2.14 Nitrogen gas pressure [+0.5]
Reference (s) 2.14
5D-S023-250, Section 2.2.8.3, p. 16.
1
-Section 2.0 Continued on Next Page-I
Page 35 SONGS 2 and 3 April 29,1986 Points Available OUESTION 2.15 List three (3) alternate lineups for makeup for the Fuel Pool Cooling System other than the Refueling Water Tank (RWT) via the spent fuel pool makeup pump. (1.5)
ANSWER 2.15
- a. Nuc service water +0.5]
. Primary pla emineralized wat ,
- c. via the LPSI .
[+0.5]
Reference (s) 2.15 A
4' y, c au suoca WATGR H o f e~ f .
- e. wrr v c~r ~
f
$ es '"ga/&94 47 aL.
- a. n,x A 3 " " T ""*- N ' '" P P"'* M
$, B ws '7" p~ d~fwt ]py //p s2 pp g : :7 n z. p .sIf Y~ C f grd.; ea k e i.r' ~ ~ 2
/. soH6 S Q d2 : Cg9 I ""# ,
"?
() p) g &
se2.3 ?. // , f&2.a< ^ s}
21, /7 W , p./.
-Section 2.0 Continued on Next Page-l l
l f
Page 36 SONGS 2 and 3 April 29, 1986 Points Available OUESTION 2.16 List the five (5) components that are connected to each of the critical loops of the Component Cooling Water System. (2.5)
ANSWER 2.16
- a. HPSI pump % f. $ Ymlwf"f 7-
- b. standby HPSI g .g p
- c. LPSI pump 7
- d. Containment spray pump
- e. Shutdown heat exchanger M 7 f - >
E + d.1~ em # + A m )
Reference (s) 2.16
- 1. SONGS 2 and 3: System Description, " Component Cooling Water System", Section I-B, p. 3.
-Section 2.0 Continued on Next Page-
Page 37 SONGS 2 and 3 April 29,1986 Points Available OVESTION 2.17 List the four (4) auxiliary systems that are supplied steam from the main steam lines. (2.0)
ANSWER 2.17
- a. Gland steam system [+0.5]
- b. Turbine flange heating system [+0.5]
- c. Auxiliary steam system [+0.5]
- d. Steam air ejector system [+0.5]
Q. &
Reference (s) 2.17 fUWL+44 a ^# $7 E' '
- 1. SONGS 2 and 3: System Description, " Main and Reheat Steam System", S0-5023-160, Section 2.1.2.3, p. 6.
-End of Section 2.0-
I Page 38 SONGS 2 and 3 April 29,1986 Points Available 3.0 INSTRUMENTS AND CONTROLS (25.0)
QUESTIONS 3.01 through 3.05 are " multiple-choice" questions. For each question specify the letter designation for the phrase that provides the most correct statement.
QUESTION 3.01 If, during Mode 1 operation at Unit 2, channel A of the Reactor Protection System (RPS) for lo Pressurizer pressure has alarmed, a potential cause would be that (1.0)
(a.) the wide-range pressure sensor for channel A had failed to a pressure indication lower than the adjustable bistable setpoint.
(b.) the narrow-range pressure sensor for channel A had failed to a pressure indication lower than the fixed setpoint which is an addressable constant in the Core Protection Calculators (CPCs).
(c.) the wide-range pressure sensor for channel A had failed to a pressure indication lower than the fixed setpoint which is an addressable constant in the Core Protection Calculators (CPCs).
(d.) the narrow-range pressure sensor for channel A had failed to a pressure indication lower than 1806 psia.
ANSWER 3.01 ;
eu (c3 '
(a . ), [+1.0]
Reference (s) 3.01
- 1. SONGS 2 and 3: System Description, " Reactor Protection System and Core Protection Calculators", p. 29 and Figure 31.
-Section 3.0 Continued on Next Page-
Page 39 SONGS 2 and 3 April 29, 1986 Points Available 00ESTION 3.02 If, for CPC channel A, one (1) of the cold-leg temperature (Tc) sensors fails LO (provides a signal indicating a lower temperature) an immediate effect would be for (1.0)
(a.) the calibrated neutron-flux power, pcal, to increase.
(b.) the T signal c used to calculate DNBR to decrease.
(c.) the " calculated AT power" to increase.
(d.) the calculated LPD setpoint to decrease.
ANSWER 3.02 (a.) [+1.C]
Reference (s) 3.02
- 1. SONGS 2 and 3: System Description, " Reactor Protection System and Core Protection Calculators", Figure 31.
I 1
-Section 3.0 Continued on Next Page-i 1
l
e Page 40 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 3.03 The reactor vessel flange 0-ring seals have a leak detection system that consists of two taps coming off of the (1.0)
^
(a.) annulus between the C-rings that feed a line to the quench tank that contains a flowrate transmitter which provides an alarm on CR50.
(b.) interior of each hollow 0-ring that feed a line to the quench tank that contains a flowrate transmitter which provides an alarm on CR50.
(c.) interior of each hollow 0-ring that feed a line to the reactor drain tank that contains a pressure transmitter which provides an alarm on CR50.
(d.) annulus between the 0-rings that feed a line to the reactor drain tank that contains a pressure transmitter which provides an alarm on CR50.
ANSWER 3.03 (d.) [+1.0]
Reference (s) 3.03
- 1. SONGS 2 an'd 3: System Description, " Reactor Vessel and Internals," p. 18 and Figure 34.
i i
I
-Section 3.0 Continued on Next Page-
, _ _ y_ .. _
_..__v_. .,, - _ _ _ .- ,._. __ __,._ . , _ -._ , _ _ _ . , , - ,_,, , , . . __. , , . ,
Page 41 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 3.04 The Pressurizer level control system utilizes two (2) level transmitters 110X and 110Y such that (1.0)
(a.) transmitter 110X sends a signal to a meter on the CR50, to a meter on the evacuation shutdown panel L-42, and to a bistable that could cut off all IE heaters.
(b.) transmitter 110X sends a signal to a meter on the CR50, to a meter on the evacuation shutdown panel L-42, to a recorder on the recorder panel, and to a bistable that could cut off one (1) and only one (1) IE heater bank.
(c.) transmitter 110Y sends a signal to a meter on the CR50, to a meter on the evacuation shutdown panel L-42, and to a bistable that would cut off one (1) and only one (1) NON-IE heater bank.
(d.) transmitter 110Y sends a signal to a meter on the CR50, to a meter on the evacuation shutdown panel L-42, and to a recorder on the recorder panel, and to a bistable that could cut off all NON-IE heaters (with selector switch in X-AND-Y position).
ANSWER 3.04 (b.) [+1.0]
- Reference (s) 3.04
- 1. SONGS 2 and 3: System Descriptions, " Pressurizer and Pressurizer Control System", p.15 and Figure 19.
-Section 3.0 Continued on Next Page-
Page 42 SONGS 2 and 3 April 29,1986 Points Available QUESTION 3.05
/
There is a lag unit in the Pressurizer level control system that is positioned (1.0)
(a.) between the 1 vel controller and the letdown throttle valve contro ler and may prevent the formation of a bubble in the letd wn line due to a rapid closure of the letdown throttle v lve.
(b.) after t letdown throttle valve controller and may prevent the li ing of the relief valve upstream of the backpressure regul ing valve due to rapid opening of the letdown thro le valve.
(c.) be een the level controller and the letdown throttle v ve controller and may prevent the lifting of the relief v lve upstream of the backpressure regulating valve due o rapid closure of the letdown throttle valve.
(d. after the letdown throttle valve controller and may prevent the formation of a bubble in the letdown line due to rapid opening of the letdown throttle valve.
ANSW 3.05 (a.) [+1.0] ,
R ference(s) 3.05
- 1. SONGS 2 and 3: System Descriptions, " Pressurizer and Pressurizer Control System", p. 16.
-Section 3.0 Continued on Next Page-
l l
I Page 43 SONGS 2 and 3 April 29,1986 Points Available OVESTION 3.06
- a. Draw a one-line diagrara showing the two (2) motor-generator (MG) sets that provide power to the CEAs and the nine (9) trip circuit breakers connecting the MG sets to the CEAs that are controlled by the Reactor Protection System (RPS). (1.5)
- b. If one (1) of the four (4) initiating relays of the RPS was tripped, K-1, K-2, K-3 or K-4 (choose only one (1)),
which (if any) of the trip circuit breakers would be opened? (1.0)
ANSWER 3.06
- a. See Figure 3.06 (ANSWER) [+1.5]
- b. I and 5, 2 and 6, 3 and 7, or 4 and 8 [+1.0]
The circuit-breaker numbers correspond to those shown in Figure 3.06 (ANSWER).
Reference (s) 3.06
- 1. SONGS 2 and 3: System Description, " Reactor Protection System and Core Protection Calculators", pp. 17-18 and Figure 24.
-Section 3.0 Continued on Next Page-
r Page 44 SONGS 2 and 3 April 29, 1986 Points Available MG 1 MG 2 MOTOR MOTOR GEN. GEN.
CROSS TIE
( m (i 9
K- 2 ------------ 2 )--) s -)3--)7---------------K-3 K-1-------------l-)--)s -) s -- - -- - - -- -- -- - - K- 4 L
/
I CE,u I I CEAs l NOTE: ( ALL BREAKERS ARE CLOSED IN NORMAL OPERATION )
Figure 3.06 (ANSWER)
-Section 3.0 Continued on Next Page-
Page 45 SONGS 2 and 3 April 29,1986 Points Available OVESTION 3.07 Given the following plant conditions, list the actuation signals (if any) of the Engineered Safety Features Actuation System that should have been triggered. (3.5)
- a. Pressurizer pressure = 1700 psia AND containment radiation = 970 mr/hr AND all other parameters are normal
- b. Pressurizer pressure = 1700 psia AND containment pressure = 14.5 psig AND RWST level = 22.5% AND all other parameters are normal
- c. Pressurizer pressure = 1900 psia AND Steam Generator 88 pressure = 750 psia AND Steam Generator 88 level = 30% AND all other parameters are normal ANSWER 3.07
.. . i. 4 s. , czA r, assu~~y cenr
- a. SIAS, CCAS, CPIS [+0.5 each,^ 0.5 :::5 'er eth--e, +1.5 max.]
- b. SIAS, CCAS, CIAS [+0.5each,3-0.5 :::5 f:r :thert, +1.5 max.]
e o n e-
- c. EFAS [+0.5, -G.5 eadi Tv.- eth:r ]
Reference (s) 3.07
- 1. SONGS 2 and 3: System Descriptions, " Engineered Safety Features Actuation System", Table 12.
-Section 3.0 Continued on Next Page-
l l
Page 46 SONGS 2 and 3 April 29,1986 Points Available QUESTION 3.08 The following parts of this QUESTION refer to the Shutdown Cooling System (SDCS).
- a. Under normal shutdown-cooling lineup and operation, how is the cooldown rate controlled? Specify the location in the lineup of the components that accomplish the control? (1.0)
- b. Under normal shutdown-cooling lineup and operation, how is the shutdown-cooling flowrate to the RCS controlled?
Specify the location in the lineup of the components that accomplish the control. (1.0)
- c. From where in the RCS is suction taken for normal shutdown cooling? What interlocks or automatic features do the suction isolation valves have? (1.0)
- d. For post-LOCA SDCS operation, a loss of compressed air is assumed for these control valves. Under the loss-of-air condition, how is the shutdown cooling process controlled? (0.5)
ANSWER 3.08 s The ennl rinwn rato is ccnticllcd b) i;r" inn the nosition o[tha gneyv #1cr ennteni valva (HV-Q316)~[+0.51.which i(duniisiideaofthe^"*""t fenm the KnrHXt and unstream of' the sucHAs oypass iivw 11 ra-[+0.5] .
- b. The iviel flow is autemeticelly centiviied by the-SDCHXs Mc: fisw ceritrol volvc utilizing ; fioncetc ignal fenm 2 conene in the line leadino tn the RCS. I+1.0]
^* N &
4CK f c> c ev oaf A n v /e:.~ f M r> c ex%
w nPf-
-Section 3.0 Continued on Next Page-b.
fhfb <mme'fSl A $ f "~ f xw g
a e, + me b oc a-.
Page 47 SONGS 2 and 3 April 29,1986 Points Available
- c. -Loop 2 hot leg [+0.33]
Pressurizer pressure interlock prevents opening unless pressure s 361 psig [+0.33] >
RCS pressure > 500 psig -> auto CLOSE [+0.33]
- d. contrn1 inc211y 2"d ""211; th; SO::X fisw cc,itre; valve (NV0'M) 3"d the S""X bypass .'la uv,,i.cl vel,o y','0'00) 9D ggnten1 dic i s cas Ing3y 33 [3 P2"21!e! valve gjqgg])J , eted bG['ap 7[J
-vc.S : , m , .,sary 6 -{ k Mu . c ' '~ )
Reference (s) 3.08
- 1. SONOS 2 eiid 3. 3,atam Oc;cript!cnc, " Safety !njection afd G'2tdc':: Ccclir.; Sy';tc=", p. 21 er.d figur S.
Somas R e / .5 : c:pp a. fm YC , Y p hOpa Wf M S O.t3 A. G , g . 13, ,p ,
- 2. C oHG s- t ed 3 fQ m/ fm(m8$
%r~ ) '
JT & T n "/
- w. x y n .2 a , 4 4 /s.z p n d 44 !!+ D .
-Section 3.0 Continued on Next Page-
Page 48 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 3.09 Answer the following parts of this QUESTION which pertain to the Class 1E - Electrical System,
- a. List the four (4) possible sources of electrical power for bus 3A06 (for example, but not necessarily correct -
Unit 2 Main Generator via a loadcenter transformer) (2.0)
- b. Y01 is the designation for the A-train 120 V AC vital dis-tribution panel. This panel may receive its power from an A-train 480 V AC Motor Control Center (MCC) er # e 2 S tr;i "00. List the components in g path from a MCC s.4 to Y01. naf (2:0)
- c. List one (1) load that is designed to be tied to either bus 2A04 or 3A04 and list one (1) load that is designed to be tied to either bus 2804 or 3B04. (1.0) l
-Section 3.0 Continued on Next Page-1
f Page 49 SONGS 2 and 3 April 29, 1986 Points 4 Available AJSWER 3.09
- a.
- Unit 3 Main Generator via a unit auxiliary transfomer.
- from bus 2A06 v'fa cross tie.
- 220 kV offsite power via a reserve auxiliary transformer.
- emergency D/G 3G003.
[+0.5] each
- b. A-train MCC (BY) battery charger [+0.25]
l A-train 125 V DC dist. swbd. [+0.25] l inverter [+0.25] switch [+0.25] Y01 og i B-train MCC (BJ) 480/120 transformer [+0.25] voltage regulator [+0.25] 120 V AC panel [+0.25] kirk-key interlock [+0.25] switch ! Y01
- c. 2A04 or 3A04 ) auxiliary building emergency chiller
[+0.5] 2B04 or 3804 ) control room emergency AC unit OR swing MCC [+0.5 each, +0.5 maximum] Reference (s) 3.09
- 1. SONGS 2 and 3: System Descriptions, " Class IE Electrical System," Figures 1, 2, and 3.
-Section 3.0 Continued on Next Page-
L a Page 50 SONGS 2 and 3 April 29,1986 Points Available lo[/ Y QUESTION 3.10 The channels of the Excore eutron Flux Monitoring System all
~
indicated 10 7% power and en one (1) safety channel failed high. Explain any impa s that this malfunction would have on the startup channels. (1.0) ANSWER 3.10 The 10-6% sour 8/S on the safety channel would have triggered. This would re ve the high voltage power supply to both, one i or neither the startup channels. [+1.0] Reference (s) .10
- 1. NGS 2 and 3: System Descriptions, "Excore Neutron Monitoring System," pp. 8, 24 and Figures la, 7, 9 and 14.
i t
-Section 3.0 Continued on Next Page-l l
Page 51 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 3.11 Answer the following parts of the QUESTION with' respect to the safety channels of the Excore Neutron Flux Monitoring System,
- a. Specify whether the 10-4% bistable (8/S) receives its neutron flux level signal from the center detector or from the summer. (0.5)
- b. As the power level is increased from below to above 10-4%
power, specify whether the 10-4% B/S is energized or de-energized and specify what this circuit action would permit and what this action should accomplish 4 automatically. (1.5) ANSWER 3.11
- a. from the center detector [+0.5]
- b.
- above 10-'% B/S is energized [+0.5]
(/) permits manual bypassing (above 10-4%, auto removed below 10-4%) of the 0.89% High Log Power trip and pretrip [+0d] [+ p'. 29 [ + d. 2 E~3
) automatically removes any DNBR/LPD bypass [*Od]
Reference (s) 3.11
- 1. SONGS 2 and 3: System Descriptions, "Excore Neutron Flux Monitoring System," p. 24 and Figure 9.
(& S/61 l~ - f" $h Sy f h " p$ Jn if * % [ 4 A 'O Q), cm p 4, aw We k' b* O f[+42h
-Section 3.0 Continued on Next Page-
Page 52 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 3.12 Answer the parts of the QUESTION which refer to the Incore Neutron Flux Monitoring System.
- a. How many fixed incore detector assemblies are in the core? (0.5)
- b. How many neutron detectors are in each assembly? (0.5)
- c. Where are the thermocouples in the fixed incore detector assemblies located axially? (Examples, that are not necessarily correct, but indicate the type of answer:
near the active-core midplane, about 135 in above the bottom of the active core, near the elevation of the instrument nozzles, etc.). (0.5) ANSWER 3.12 l
- a. 56 [+0.5]
- b. 5 [+0.5]
- c. about 16 inches above the top of the active-fuel region
[+0.5] Reference (s) 3.12 '
- 1. SONGS 2 an'd 3: System Descriptions, "Incore Flux Monitoring System," pp. 4-6.
-Section 3.0 Continued on Next Page-i
r . 1 Page 53 SONGS 2 and 3 April 29,1986 Points Available OVESTION 3.13 Answer the parts of this QUESTION which refer to Feedwater Regulating System and the high-level override (HLO) control function.
- a. Answer TRUE or FALSE. If the level sensor selector switch for S/G 088 was set on "Both" and if one (1) and only one of the level sensors reached 170 inches, the HLO signal be sent to the Feedwater Control System (FWCS)? (0.5)
- b. If a HLO signal was sent to the FWCS, what would be the resultant valve position for the FWRV bypass valve? (0.5)
ANSWER 3.13 rnacc
- a. IAOf [+0.5]
- b. 0 (zero flow demand) [+0.5]
Reference (s) 3.13 , 1. SONGS 2 and 3: System Descriptions, "Feedwater Regulating System," p. 8 and Figure 10.
-End of Section 3.0-i 1
t
o Page 54 SONGS 2 and 3 April 29, 1986 1 Points Available l 4.0 PROCEDURES: NORMAL, ABNORMAL, EMERGENCY, AND RADIOLOGICAL CONTROL (25.0) OVESTION 4.01 Answer TRUE or FALSE. Placing a test or calibrate switch on an NI safety channel drawer in other than NORML or OPERATE will place the low DNBR and high lpg trips in the trip condition. (0.5) P ANSWER 4.01 ] TRUE [+0.5] ! Reference (s) 4.01
- 1. SONGS 2 and 3
- Operating Instruction, " Reactor Protection System Operation", SD-5023-3-2.12, Section 6.4 Caution,
- p. 6.
QUESTION 4.02 One of the "Immediate Actions" in Errergency Operating Procedure 4 S023-12-1, " Standard Post Trip Actions", is to " VERIFY RCS , Inventory Control Criteria Are Satisfied." Specify the criteria that must be satisfied. (1.0) i ANSWER 4.02 3
- Verify PZR level - CONTROLLED BETWEEN 10% and 70% [+0.5]
- Verify RCS saturation margin - GREATER THAN 20'F [+0.5]
Reference (s) 4.02
- 1. SONGS 2 and 3: Emergency Operating Procedure, " Standard Post Trip Actions", 4.yS023-12-1, Revision 0, p. 5.
I -Section 4.0 Continued on Next Page-
Page 55 SONGS 2 and 3 April 29, 1986 Points Available 1 l OVESTION 4.03 List the three (3) symptoms associated with mitigating an event that would result in the use of the FUNCTIONAL RECOVERY portion of the Emergency Operating Instructions. (1.5) ANSWER 4.03
- Diagnosis is not achieved. [+0.5]
l
- Symptoms do not correspond to any one Optimal Recovery Instruction (multiple malfunctions). [+0.5]
- Actions are not satisfying the Safety Function Status i Check for Optimal Recovery Instruction. (An optimal recover plant.)y instruction [+0.5] is not adequately recovering the Reference (s) 4.03
- 1. SONGS 2 and 3: Emergency Operating Instruction, " Functional Recovery", 96kS023-12-8, p.1.
I i
-Section 4.0 Continued on Next Page-
Page 56 SONGS 2 and 3 April 29,1986 Points Available OUESTION 4.04 TheattachedfigureshowstheUnit2 pressure /temberh't'ure optimum cooldown curve. Match the appropriate alphabetical letter from the curve with the numerically listed functions. NOTE: Three (3) events at "A" and two (2) events at (3.0)
~
"J".
Function
- 1. Collapse Pressurizer bubble
- 2. Align shutdown cooling and provide LTOP
- 3. Bypass Pressurizer Low Pressure Trip
- 4. Depressurize safety injection tanks
- 5. Degas RCS and purve VCT E. Remove one HPSI pump from service
- 7. Close RCP controlled bleed header isolation valve to isolate RCP seals from VCT pressure
- 8. Secure last operable HPSI
- 9. Unlock and close SITS outlet valve breakers and place control switches to close
- 10. Stop last operating RCP
- 11. Borate to cold shutdown
- 12. Stop 2 RCPs
-Section 4.0 Continued on Next Page-
I 1 1 Page 57 SONGS 2 and 3 April 29,1986 1 Points l Available 1
+ '71 OP(AAflNG IN11RUCfl0N $Q2)*$*l.$
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son. . muhulca_'] ; _tattEC:3.7.gi,g"'"T.. 2LW5 f . 1;J" - R.LA ..WERAIDLcurtyLJ nyt T 4.g.g, w i ca i " m/ nc: if: __-2 MM styp L,txP8bj d .k -[. hl j
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0- , . . 0 800 200 300 400 SCO 600 700 RCS ituPtnatuRC ten AttA0 m(NT I # ACE I 0F l Figure 4.04 (0UESTION) ] i -Section 4.0 Continued on Next Page-i i
- - . - - , - - . . - .- . - ~ - , - - - - - - --- - . - - - - - - - - - . - - . -
J , Page 58 SONGS 2 and 3 April 29, 1986 ] Points
~
Available .i l ANSWER 4.04
- 1. J
- 2. H , f, 6
- 3. F,$#
- 4. D
- 5. A
- 6. G , N , l'
- 7. L
- 8. J
- 9. E
- 10. K
- 11. A
- 12. A
--@0.25 ::ch} {+ o.33] is4N 3.O ^ ^>' " "
Reference (s) 4.04
- 1. SONGS 2 and 3: Operating Instruction, " Plant Shutdown-Hot Standby to Cold Shutdown", S wS023-5-1.5, Attachment 2/3, pp. 37-38.
1 i
-Section 4.0 Continued on Next Page-i
Page 59 SONGS 2 and 3 itpril 29, 1986 Points Available OVESTION 4.05 List three (3) conditions of the control room that will render operation from the control room impossible. (1.5) ANSWER 4.05 1 ne nse m ke ;7 ;7,;gc,t,vi; W i;,e
- 2. wigh eirborne act!';ity or radiati^" dese ratas 3 .- Toxic or fh=21e ; :es 1
4 ._ Damaae to control cablac or wiring leadir.g to the car,trc 1 ennm [+0.5 each +1.5 maximum] Reference (s) 4.05
- 1. SONGS 2 and 3: Abnormal Operating Instruction, " Shutdown from Outside the Control Room", 8DfS023-13-2, Section 1.1,
- p. 2.
I. D+ m e
.2 .
Vfe. w ? b l f tE -
- s. y + af g ff d&G S r k- f .
- a. d'fA W 3 wW A - "; Mr 2
/pJfae g # #
-Section 4.0 Continued on Next Page-
Page 60 SONGS 2 and 3 April 29,1986 Points Available OUESTION 4.06 List four (4) conditions that require immediate initiation of emergency boration of the Reactor Coolant System. (2.0) ANSWER 4.06
- 1. Failure of two (2) or more CEAs to drop following a reactor trip
- 2. One or more regulating groups below the Power Dependent Insertion Limit (PDIL)
- 3. Shutdown Margin is determined to be ( 5.15% A k/k when T avg is > 200*F.
- 4. Shutdown Margin is determined to be ( 3% A k/k when Tavg is ( 200'F.
- 5. Uncontrolled cooldown of the RCS (T 25'F caused by excessive feedwater additiM o >r below Tref) steem excessive withdrawal
- 6. During refueling with keff greater than 0.95 or boron concentration less than 1720 ppm
[+0.5 each, +2.0 maximum] Reference (s) 4.06
- 1. SONGS 2 and 3: Abnormal Operating Instruction, " Emergency Boration of RCS", 8kS023-13-11, Section 1.1, p. 2.
-Section 4.0 Continued on Next Page-
t Page 61 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 4.07 During a station blackout after 30 minutes of no offsite power and/or no power to the 4 KV ESF bu A04 or A06 Fe rertcc-dj
/, af fc /(xplain VCT. how you would stop the RCP controlled bleedoff to theJews 1 ANSWER 4.07 Make a containment entry [+0.5] and manually close [+0.5]
HV-9216; pro eaatrelled bleedef' te th: "CT [+0.5} Reference (s) 4.07 i
- 1. SONGS 2 and 3: Abnormal Operating Instruction, " Loss of Offsite Electrical Power", WSO+S023-13-1, Section 1.2.3.1,
- p. 14.
l l l 1
-Section 4.0 Continued on Next Page- 1 l __
i Page 62 SONGS 2 and 3 April 29,1986 Points Available QUESTION 4.08 Operating Instruction S023-3-2.16, Movable Incore Instrumentation, cautions the operator not to allow the movable detector to remain in the core for extended periods of time. Why is this required. (1.0) ANSWER 4.08 Detector burnout may occur [+1.0] Reference (s) 4.08
- 1. SONGS 2 and 3: Operating Instruction, " Movable Incore Instrumentation", 895S023-3-2.16, Section 6.2.3 Caution,
- p. 3.
QUESTION 4.09 During a diesel generator (D/G) surveillance test, the D/G had been run for 5 hours at 15% generator load. What must now be done to clean out the exhaust stacks and remove possible glazing from the piston heads? (1.0) ANSWER 4.09 The D/G should be run for 30 minutes [+0.5] at greater than 40% load (1880 kW) [+0.5]. Reference (s) 4.09
- 1. SONGS 2 and 3: Operating Surveillance Test, " Diesel Generator Monthly Test", 9B4S023-3-3.23, Section 4.8, p.
5.
-Section 4.0 Continued on Next Page-
Page 63 SONGS 2 and 3 April 29,1986 Points ( Available OVESTION 4.10 The Emergency Coordinato elects to initiate a natural circulation cooldown w h the RCS in a saturated condition during a station blac ut. Answer the following TRUE or FALSE. If the RCS Thot reac es 450'F and SIT discharge is not occurring due to RCS pressur remaining above 615 psia, then use the reactor head vent o the Quench Tank to lower RCS pressure. (0.5) ANSWER 4.10 TRUE [+0.5 Reference (s) .10
- 1. NGS 2 and 3: Abnormal Operating Instruction, " Loss of ffsite Electrical Power", 88>=S023-13.1, Section 1.5.1.1,
- p. 17.
QUESTION 4.11 Operating Instruction 5023-3-2.18, " Steam Bypass System Operation", states that the steam bypass valve should not normally be operated with the master controller (PIC-8431) in remote and the valve permissive switch in manual. Explain the reason for this instruction. (1.0) ANSWER 4.11
.* t f This defeats the single-failure proofness [fAcS] of the system, allowing certain single failures in the main channels to open one or more of the valves operating in this manner [30:5].
g , i. 4 m a Q ' W Reference (s) 4.11
- 1. SONGS 2 and 3: Operating Instruction, " Steam Bypass System Operation", S6*S023-3-2.18, Section 4.3, p. 3.
-Section 4.0 Continued on Next Page-a.
l Page 64 SONGS 2 and 3 April 29, 1986 i l Points } Available i 1 OVESTION 4.12 j How long is each nitrogen accumulator capable of operating its associated steam dump valve upon loss of instrument air? (0.5) 1 ANSWER 4.12 j 15 hours + 2 hours [+0.5] I Reference (s) 4.12 1 { 1. SONGS 2 and 3: Operatina Instruction, " Atmospheric Steam c
- Dump Operation", 5022-3-2.18.1, Section 6.4.1, p. 6.
) ! i
- i i
1 i i I 4 t 1 I l 4 .i
-Section 4.0 Continued on Next Page-
Page 65 SONGS 2 and 3 April 29, 1986 Points Available QUESTION 4.13 On Unit 2 the operator is instructed not to interrupt display of the six (6) key COLSS parameters for greater than 15 minutes when the COLSS backup computer is providing control room COLSS indication. List the six (6) key COLSS parameters. (3.0) l ANSWER 4.13
- 1. ASI [+0.5]
- 2. LPD limits [+0.5] A 49p pp ya
- 3. Power limit margin [+0.5] e- C04 S # F 2- #M "b
- 4. DNBR limit [+0.5] e P N # ^~ MF
- 5. Reactor power level [+0.5] A ((P
- 6. Azimuthal tilt [+0.5]
Reference (s) 4.13
- 1. SONGS 2 and 3: Operating Instruction, " Core Operating Limits Suvervisor System", 49pS023-3-2.21, Section 4.4,
- p. 4.
-Section 4.0 Continued on Next Page-
Page 66 SONGS 2 and 3 April 29,1986 Points Available OVESTION 4.14 Why should Unit 2 heat treating outages of the circulating water system be programmed to coincide with high tides? (1.0) ANSWER 4.14 To increase circulating water pump NPSH [+0.5] and maximize
+ fhfgabSeN Fthe EYk k5 * ! $o'h?Sa?. 'e r
- H (red f"#'
e se INet/A's A'M *! '~ h *'I '7'" N ' ' M' "fd ' TAIA ^ M Reference (s) 4.14
, 1. SONGS 2 and 3: Operating Instruction, " Heat Treating the Circulating Water System - Unit 2", S023-5-1,1, Section 6.1.1, Note 2, p. 5.
QUESTION 4.15 What are the 10 CFR 20 quarterly dose limits for:
- a. Whole body (0.5)
- b. Hands, forearm, feet, and ankles (0.5)
- c. Skin (0.5)
ANSWER 4.15
- a. 1.25 rem [+0.5]
- b. 18.75 rem [+0.5]
- c. 7.5 rem [+0.5]
Reference (s) 4.15
- 1. SONGS 2 and 3: Health Physics Procedure, " Personnel Monitoring Program",,89pS0123-VII-4.0, Section 6.5.1, p. 5.
-Section 4.0 Continued on Next Page-
Page 67 SONGS 2 and 3 April 29,1986 Points Available OUESTION 4.16 h is it not desirable to operate an RCP in a loop with a ruptured S/G tube? (1.0) ANSWER 4.16 May increase RCS to S/G leakrate [+1.0] Reference (s) 4.16
- 1. SONGS 2 and 3: Emergency Operating Instruction, M S023-12-10, p. 20.
Jt. .rvua S 4aa/#' If***J 6 "
/
ge.za-!*-V , p. af. Rev. l,
)
1
-Section 4.0 Continued on Next Page-
Page 68 SONGS 2 and 3 April 29, 1986 Points Available OVESTION 4.17 List the six (6) highest priority safety functions in the order of their priority, highest first, lowest last, in the functional recovery procedure. (1.5) ANSWER 4.17
- 1. reactivity [+0.2] priority [+0.05]
2 v at. / - - a u , a ,-t e s s 2. RCS inventory [+0.2] priority [+0.05] f y& RCS pressure [+0.2] priority [+0.05] (#. heat removal [+0.2] priority [+0.05] (,-{ containment isolation [+0.2] priority [+0.05] 6= ceat2 4 a= ant t: ; ratur; an b ic=>ure [+v.z] priori ty 0 0.05] Reference (s) 4.17
- 1. SONGS 2 and 3: Emergency Operating Instruction, " Functional Recovery", $S023-12-8, Section 6A, p. 4.
A fe vi s,b n I
-Section 4.0 Continued on Next Page-
Page 69 SONGS 2 and 3 April 29,1986 Points Available QUESTION 4.18 Define a High Radiation Area. (1.0) ANSWER 4.18 High Radiation Area. Each accessible area having radiation
'"--+4"^d "-
levels of 100 mrem /hr or greater Hi-gh Sdiatf or anea and shal' be cearpie"a'_'rb s3tud niih a ciga er rigar bearing tha radiatina c a'2tt e r :y d c k [+1.0] Reference (s) 4.18
- 1. SONGS 2 and 3: Health Physics Procedure, " Posting and Access Control", @950123-VII-7.4, Section 6.1.2.2, p. 4.
A- Gen e ri e- : O c6. / [ dE d Ae d $ ' if e M 7$ QUESTION [. 9 b8); /E9 / #f# Why should you not operate the charging system with simultaneous alignment to both HPSI headers? (1.0) ANSWER 4.19 would violate train separation [+1.0] Reference (s) 4.19
- 1. SONGS 2 and 3: Emergency Operating Instruction, SMS023-10-10, p. 4.
-End of Section 4.0-
-End of Exam-
EQUATION FORMULA AND PARAMETER SHEET Where mi = m2 (density)t(velocity)i(area)1 = (density)2(velocity)2(area)2 KE="{2 PE = mgh PEg + KEg +PgVg = PE +KE +P Y22 2 2 where V = specific volume P = pressure Q = mcp(Tout -Tin) Q = UA (Tave -Tstm) 0 " "(b l-h2) P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (# - p) E
= (# - p)
T p m pXeff delta K = (K,ff-1) CR1 (1-K,ffg) = CR2 (1-Keff2) CR = S/(1-K,ff) (1-K,ffy) (1-K,ff) x 100% SDM = M = (1-Keff2) K eff decay constant = in (2) = 0.693 A1 = Ao e-(decay constant)x(t) t t 1/2 1/2 Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 3 1 ft = 7.48 gallons I hp = 2.54 x 10 Btu /hr 3 6 Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 2 1 ft H 2O = 0.4335 lbf/in.2 A,ff = 0.08 sec
Rev.3_ i I OPERATIONS PHYSICS
SUMMARY
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kc.V 3 TABLE 4.1 ROD WITHDRAWALS FROM PDIL AT HFP Reactivity * (% AK/KO Inches Withdrawn 0 Bank 6 30C 108.0 .14445 112.5 .23011 120.0 .10255 I .07167
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ROD WITH0RAWAL AT HIP FROM 2PDIL VITH HIP XENON Reactivity" (% AK/KO
- Inches Withdrawn BOC Bant 6 Bank 5
! ' (O T PD) i 60.0 .5547E+00 G 0.0 .5467E+00 O.0 67.5 75.0 .5330E+00 2 0.0 .5203E+00 0.0 82.5 90.0 .5055E+00 0.0 4906E+00 0.0 97.5 105.0 4742E+00 i 4.5 .4502E+00 12.0 112.5 120.0 .4181E+00 .
s 19.5 .3793E+00 27.0 127.5 E .3404E+00 34.5 135.0 j S 42.0 142.5 .3072E+00 - 'i .2866E+00 49.5 150.0
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TABLE 6.2 HFP EQUILIBRIUM XENON WORTH (CBC, 583*F) Burnup EFPD I' NO# 13.19 26.43 52.90 g 132.31
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TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP FROM 100% TABLE 6.t I NOTE: Prior to the trip, equilibrium conditions were assumed to be present. HOURS BURNUP WINDOW IN WHICH TRIP OCCURREO AFTER (EFPD) 0-35 >35-100 >100-165 >165-230 >230-EOC TRIP g
; O 2.71 2.73 2.77 2.81 2.85 9 1 3.32 3.36 3.40 3.48 3.55 2 3.81 3.85 3.91 4.01 4.11
- 3 4.19 4.23 4.31 4.43 4.55 4 4.47 4.52 4.60 4.74 4.89 5 4.67 4.73 4.82 4.97 5.13 6 4.81 4.87 4.96 5.13 5.29 7 4.89 4.95 5.04 5.22
- 5.39 l 8 4.91 4.98 5.08 5.25 5.44 9 4.90 4.97 5.07 5.25 5.43 4.86 4.92 5.02 5.20 5.39 i- 10 4.95 5.13 5.31 11 4.78 4.84 4.69 4.75 4.85 5.03 5.21
( + 12 13 4.57 4.64 4.73 4.91 5.09 i 14 4.44 4.51 4.60 4.77 4.95
- ; 15 4.30 4.36 4.45 4.62 4.79 16 4.15 4.21 4.30 4.46- 4.63
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. 17 4.00 4.06 4.14 18 3.84 3.90 3.98 4.13 4.29 19 3.68 3.73 3.81 3.96 4.11 20 3.52 3.57 3.65 3.79 3.93 21 3.36 3.41 3.48 3.62 3.75 22 3.20 3.25 3.32 3.45 3.58 23 3.05 3.09 3.16 3.28 3.41 24 2.90 2.94 3.00 3.12 3.24 2.75 2.79 2.85 2.96 3.07 y 25 2.81 2.92 26 2.61 2.64 2.70 27 2.47 2.50 2.56 2.66 2.76 28 2.33 2.37 2.42 2.51 2.61 29 2.20 2.24 2.28 2.37 2.47 30 2.08 2.11 2.16 2.24 2.33 31 1.96 1.99 2.03 2.11 2.20 32 1.85 1.88 1.92 1.99 2,07 33 1.74 1.77 1.81 1.88 1.95 34 1.64 1.66 1.70 1,77 1.84 35 1.54 1.56 1.60 1.66 1.73 36 1.45 1.47 1.50 1.56 1.62 37 1.36 1.38 1.41 1.47 1.53 RECE!.';D C M.* l I
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Rev .2 TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP FRO TABLE 6.f' NOTE: Prior to the trip, equilibrium conditions w re assumed to be present. HOURS BURNUP WINDOW IN WHICH TRIP OCCURRED (EFPD) AFTER >165-230 >230-EOC 0-35 >35-100 >100-165 TRIP y 1.43 1.32 1.38
-j 38 1.28 1.30 1.29 1.34 1.22 1.24 39 1.20 1.17 1.21 1.26
.' - 40 1.12 1.05 1.14 1.07 1.09 1.14 1.18 1.11 41 1.06 1.02 42 0.99 1.00 1.00 1.04 0.92 0.94 0.96 0.97 43 0.93 0.87 0.88 0.90 0.91 44 0.87 0.81 0.82 0.84
- 45 0.79 0.82 0.85 46 0.76 0.77 O.79 0.72 0.73 0.76'
- 47 0.71 0.71 0.74 0.66 0.67 0.69 0.69
- 48 0.67 0.62 0.63 0.64 0.C5 i
O 49 0.59 0.60 0.62 0.58 0.61 1 (Y 50 51 52 53 0.54 0.50 0.47 0.55 0.51 0.48 0.56 0.52 0.49 0.58 0.54 0.51 0.57 0.53 0.49
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fcY 3 TRANSIENT XENON REACTIVITIES FOLLOWING A TRIP FROM 1 TABLE 6.'t NOTE: Prior to the trip, equilibrium conditions were assumed to } be present. HOURS BURNUP WINDOW IN WHICH TRIP OCCURRED (EFPO) >230-EOC AFTER >100-165 >165-230 TRIP 0-35 >35-100 0.10 0.10 0.09 0.09 0.10 76 0.09 0.09 0.09 77 0.08 0.09 0.09 0.09 0.08 0.08 0.08 78 0.08 0.08 0.08 79 0.07 0.07 0.07 0.08 0.07 0.07 0.07 80 0.07 0.07 0.06 81 0.06 0.06 0.06 0.07 0.06 0.06 0.06 82 0.06 0.06 0.06 83 0.05 0.06 0.05 0.06 0.05 0.05 0.05 84 0.05 0.05 0.05 85 0.05 0.05 0.05 0.05 0.05 ) * . 86 0.04 0.04 0.04 0.04 0.04 0.05 0.04 87 0.04 0.04 0.04 0.04 0.04 0.04 88 0.04 0.04
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