ML20137A895
| ML20137A895 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/08/1985 |
| From: | Morrill P, Obrien J, Pate R, Willett D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20137A885 | List: |
| References | |
| 50-528-OL-85-02, 50-528-OL-85-2, NUDOCS 8511260133 | |
| Download: ML20137A895 (135) | |
Text
{{#Wiki_filter:, -. . . . .-. , . .- = I . m Report No. 50-528/0L-85-02 ,. i . . Docket.No. 50-528/529
- i Licensee: Arizona Public Service' Company '
P. O. Box 21666
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j Phoenix, Arizona 85036 - Fac'ility Name: Palo Verde 1 and 2 , Examination at: Wintersburg, Arizona i-Examination conducted: September 24-27; October 1-3, 1985 ! f -
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Examiners: N M [OM /O"22 d5 D ~ J. Will 'tt, Chief Examiner Date Signed 1- t' 5 '
/d "22 ~h$
. P. O'Brien, Examiner Date Signed Y 4A Y NffkT P.~Mgfrill,Exapn6r Date signed I
Approved by: A7 / 1(. 'J V P' ate, Section Chief N [ [I. ' Date Signed 1 Summary: 3
, Examinations were conducted from September 24 to October 3, 1985. The , Written Exam was administered on September 24, 1985 to ten SRO and thirteen
, RO candidates. Operating exams were conducted from September 25 to October 3, 1985 to eleven SRO and ten RO candidates. Two of the SRO candidates failed the written exam and all eleven SRO's passed the operating exam. This results in nine SRO licenses being issued. All thirteen RO candidates passed the written exam, and nine of the ten RO candidates passed the operating exam. Of the fourteen RO candidates, the written examination was waived for one and the operating examination was waived for four. This results in thirteen R0 licenses being issued. 8511260133 851108 DR ADOCK 050 g 8 i
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- 1. Persons Examined -
RO Candidates: Thirteen candidates took the written examination. Ten candidates took the operating, examination (Simulator and Oral). SRO Candidates Ten candidates took the written examination. Eleven candidates took the operating examination (Simulator and Oral) .
- 2. Examiners:
*D. Willett, RV P. Morrill, RV J. O'Brien, RV G. Streier, EG&G J. Upton, PNL J. Smith, PNL
- Lead Examiner
- 3. Persons Attending the Exit Meetings APS:
+*J. Allen, Manager of Operations
+*W. F. Fernow, Manager Plant Services
+*F. E. Hicks, Training Manager
+*P. J. Wiley, Training Supervisor, Licensed Operators
+*R. J. Adney, Unit Superintendent
*L. Clyde, STA Supervisor
*R. Gouge, Unit 1 OPS S/S
+*J. Jarusi, Acting OPS Support Supervisor
+ J. Stavely, Computer Software
+ J. Schmadeke, Computer Maintenance NRC:
*D. Willett, Lead Examiner
*P. Morrill, Examiner
+ J. P. O'Brien, Examiner
*Present at Exit September 24, 1985
+Present at Exit October 3, 1985 s , - - -
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. 4. Written Examination and Facility' Review: '. .
4 g . i. ~ . Written' examinations were adminis'tered aslfollows: ,
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r l- 13'R0 Exams - September.24,31985' ,
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, = 10 SRO Exams - September?24; 1985 ' l m g.. L , i r-U' At the conclusion of'the written exam;;th'eldacility'stdff reviewed the exams. The comments made by;th'e staff at the donclus' ion of the review care included ~ in the attachmentf (1)r for th'e, SRO: exam and ' attachment (2) t
- for the RO exam.. These comments were dicuss'ed'with?the' staff'and
! Jappropriate changes were made to'the exams. prior to the grading of the exams. t ;4 ( x General weaknesses were-noted by the examiners in the accuracy of reference I- materials provided the examiners. 5- - -
- 5. Operating Examinations:
1 ir . Simulator _ and oral exams were conducted September 25-27, 1985; i j October = 1-3,.1985. ' p> General weaknesses were identified by the examiners in'the area of p b - Radiological procedures and release points, portable radiation monitor design,.use an,d operation.- i t.. ' 6. ' Difficulties With the' Simulator: r Numerous problems were encountered with the Simulator during the w Simulator examinationa. e Software and hardware problems wi%r a so dn evidence to a magnitude c where they could jeopardize f aa ran/. t of the examinations. Examples-of software problems were:
.. n- '(1)-Rea'ctor Water Makeup pump B - Flow indicated, but no discharge b pressure.
(2) Valve UV-514 could not be opened.wh n the VCT was isolated.
; i3)WhenSO4wasdeenergized,the'chargingpumpswerestillrunning and' flow was indicated.
- (4) NNI detector' failure RV-indication was erratic rather than low of voltage.
(5) Heater drain pump-pegged amp meter high on start. (6) Motor amps on two running cond. pumps did not decrease when 3rd pump starts. s JL (7) MFP'disch. valves HV-32, 31, lost indication on loss of Bus SO4.
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_. . -. . , .- ._ _ _ _ _ . _ _ _ _ ~ _ . _ _ .-.. . 3 I. - (8) Tref did not decrease when the turbine bypass to condenser was opened and turbine load was'. decreased.
'.(9) No alarm was received when the S/G safety valves lifted.
(10) MG synetoscope and frequency meter / RPM not working properly - , could not parallel main generator. . 7. . Exit Meetings On September'27, 1985 and October'3, 1985, exit meetings were conducted with licensee representatives. .Those individual candidates who clearly passed the operating exam were identified. The concerns expressed in-
- h. paragraph 5 and 6 except for written exam results were discussed at
. . length with those representatives. a 4 d 7- ] 4 4
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ATTACHMENT 1 FACILITY & NRC COMMENTS FOR PALO VERDE SRO EXAM OF SEPTEMBER 24,,1985
. Question 5.04 , l., , ,
(one point), Regarding Xenon half-life. Thefacilityanhchief, examiner agreed that the required.. level of; knowledge to answer . the question was inappropriate. -- i .- f s - > The question has been deleted. a ;, u
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Question 5.09 l -
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(one point), Regarding changes in neutron count rate with changes in temperature. The facility commented that temperature , m shadr, wing or downcommer. shadowing'of The detector was an appropriate response. The comment was accepted, and key was corrected. Question 5.13 (two points), Regarding calculation of criticality. The chief examiner changed the key to include (other than graphing the answer by 1 / M method) calculation of critical size by: Cr1A1 - Cr2A2 = 90(10) - 115(15) = 33 assemblies Cr1 - Cr2 90 - 115 Question 5.14 (one point), Regarding Xenon peaking. The key was changed to reflect that the time to peak Xenon after a trip from 100% reactor power is longer-than from 50% power, and that for purposes of burnout, power is synonymous with flux. The comments were accepted. Question 5.16 (one point), Regarding Doppler Power Coefficient. The key was changed to reflect that Doppler Power Cofficent becomes more negative over core life. Additionally, " closing the gap" was included in the key as an appropriate response for better heat transfer. The comments were accept'ed.
Question'6.02
- (one point), Regarding downcommer function. The facility commented that the downcommer valve is reopened at high flow rates to provide "10% full power flow" (present valve position of approximately 62%).
This comment-is accepted. Question 6.03' (one point), Regarding Automatic Withdrawal Prohibit (AWP) purpose. The facility commented that answer "B" is also correct if the Reactor Regulating System'is considered instead of the Steam Bypass Control System...
.The facility comment is accepted and the key has been changed to
-"A'and/or B" for: full credit.
. Question 6.05.
(two points), Regarding the SBCS. The facility commented that "No Load Tave"'was-the same as 564 F deg. The facility comment was accepted. ,
. Question 6.10 (1.5 points), Regarding Letdown Bypass Valve. The facility commented that their procedures have been changed to require letdown bypass flow when normal letdown #has been secured for greater than 22 minutes to warm up'the. downstream piping.
The facility comments were accepted. i
- Question 6.14 (one point), Regarding charging'line backpressure controller. The facility commented that auxiliary spray, in addition to,RCP' seal injection, receives its delta pressure from the charging line backpressure controller. , ,
The facility comment was accepted. - - (2.5 points), Regarding variable setpoint bistables. The facility-commented that, in addition to preventing unnecessary trips during startup and shutdown, variable setpoint bistables are used when a rate of change type of trip'is-desired. Additionally, the facility provided two more places that these bistables are used, in steam generator flow and variable overpower trip.
~ These facilityJcomments werc ' accepted.
Question 7.01
'(two points), Regarding EDG's. The facility commented that, while in the isochronous position, the diesel generator maintains 60 cycles and not rated voltage.
The facility comment is accepted. - Question 7.03 (2 points), Regarding independent' verification. Due to changes noted in the plant procedures, responses A and B were eliminated and the condition that the area was inaccessable (due to radiation area or locked) plus answers ~C and D for full credit OR full credit will be given if-candidate states that the procedure does not allow any exceptions.. Question 7.07 (2.5 points), Regarding precautions for starting a RCP. After the grader reviewed the procedure, he added a fourth additional possible precaution. Three of the four are required for full credit. Question 7.11 (two points), Regarding RCS activity. The facility commented that a fuel element failure would be detected initially by the Rubdium 88 detector in the CVCS. The facility commented that a " crude burst" would be distinguished from a fuel failure by the relationship between the letdown process monitor and the Rb-88 channel. On a crud burst the letdown monitor would increase but not the Rb-88 channel. Facility comments were accepted. Question 8.04 (one point), Regarding departure from Tech. Spec's. During the review of the key, with the lead examiner, by the grader it was agreed that there were two correct answers, A or B. Either will be acceptable for full credit. Question 8.14 (three points) Regarding Technical specification requirements. An announcement was made during the test to assume whether the out of commission diesel and motor driven auxiliary feedwater pump were in the same or opposite divisions. The Key was amended to reflect either assumption.
r ATTACHMENT 2 - FACILITY COMMENTS RO EXAM Question 1.02 Facility Comment: , 16 0 Additionally you might get a,8 and alpha reaction. NRC Resolution: This reaction was added to the key. Also the examiner added an Alpha-Boron reaction to the key. Question 1.05 Facility Comment: Student might answer with Fower Defect or FTC as opposed to Doppler. NRC Resolution: Examiner agrees these are equivalent and does not require a key change. Question 1.09b Facility Comment: Answer is. correct only if pump suction is decreased so much to cause cavitation otherwise discharge flow decreases due to less total head. NRC Resolution: Facility comment incorporated into the key. Question 1.13b Facility Comment: Student might say conduction thru steam due to film boiling. NRC Resolution: Conduction was included as an acceptable answer. Question 2.03a Facility Comment: In the control room the operator would see a "High Priority Trouble" alarm which may have been caused by the " Incomplete Sequence" indicated at the local panel. NRC Resolution: The high priority trouble alarm was added plus a SEAS alarm by the examiner.
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. , i Question 2.03b Facility Comment: ,
.Recentchanges'notincludedinreference$added./CSASonsame_ port
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as SIAS causing a diesel start on CSAS. ' NRC' Resolution: , CSAS diesel start added to the key. Question 2.05b
-Facility Comment:
New procedure changed time requirements to be 2-3 hours. NRC Resolution: Key changed to make time limits of a minimum of 2 hours and a maximum of 3 hours. Question 2.06c
. Facility Comment:
This mode is called the "thru filter mode". ' NRC Resolution: This terminology added to the key. Question'2.09a Facility Comment: The facility responded with several pages of possible answers 7 depending on the assumptions made by the candidate. NRC Resolution: The list was so extensive that verification of the added answers were not possible. Because the answer was so unmanageable the question was deleted.
' Question 3.04 Part 4 Facility Comment:
Answer is correct but is determined by Tave plus Pstm falling below a predetermined setpoint, or TLI y 60%.
*A.
NRC Resolution: <
' Answer given by the facility was understoo'dby the examiner when the question was written. The answer.did-not include 1this to - keep it simple. But the comment was included in the grading, process. ,
Question 3.06'(1)
-Facility Comment:
-8 to 2X10
-6 '9
-6 -
Overlap is equal to 2X10 vs.~2X10 to 2X10 NRC Resolution: Change was made to the key. Question 3.07 (3) Facility Comment:
"RRS Input Ch. Deviation" alarm no longer exists on the control boards.
NRC Resolution: Reference to this alarm was removed-from the key. Question 4.02b Facility Comment: 1 The T.S. on turbine overspeed was deleted. NRC Resolution: The key was changed to state no limit in the T.S. _ Question 4.03b Facility Comment: Is this the'most preferred? Why not maintain a path to the condenser. NRC Resolution: 1The examiner feels the given answer is the most preferred but there is-no procedural basis to require this answer. So the path to the condenser L answer was also accepted. Question 4.03c Facility Comment: Change subcooling requirement to > 28'F per the procedure. L
r-NRC Resolution: Subcooling requirement changed to ? 28"F. Question 4.05A(1) Facility Comment: Not required to report subcooling per the procedure. NRC Resolution: Answer #1 was removed from the key. Originally 4/5 answers were required, now 4/4 answers required. Question 4.07 Facility Comment: The procedure does not require a CIAS, only to isolate those CIAS valves that have auto actuation. This does not require you to check manual valves. NRC Resolution: Comment was accepted, but the candidate had to either specify a CIAS signal or list the valves that need to be actuated. 1 9
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EM 'n C> 'E ' " G k.. U. 5. NUCLEAR REGULATORY COMMISSION [U j . SENIOR REACTOR OPERATOR EXAMINATION Facility: PALO VERDE 1 & 2 Reactor Type: COMBUSTION ENG. b Date Administered: SEPT. 24, 1985 Examiner: D..J. WILLETT 1 Candidate: INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side oniv. Staple ouestion sheet on top of the answer sheet. Points for each question are indicated in parenthesis after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. Category % of - Candidate's % of l _Value Total Score Cat. Value Cateoory
.38 25 5. Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 25 25 ' 6. Plant Systems Design, Cdntrol
] and Instrumentation 75 ps 7. Procedures - Normal, Abnornal, Emergency and Radiological Control 2r N 1 8. Administrative Procedures, i Conditions, and Limitations i i 100 TOTALS Final Grade % all work done on this examination is my own; I have neither given nor receiveo l Aic. - 4 Cancicate's Signature I e % ,
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.I o' EQUATION SHEET f = ma v = s/t 2 EI w = ag a = v,t + 1at 5
Cycle efficiency = E = nC a = (vg - y, )/t KE = lsav v g=v A = AN A = A,e
+ at
- - PE = agh a = 8/t A = In 2/tg = 0.693/t.
U = VAP AE = 931Am t g(eff) = (tt. )(ts) - (t +t) 3 Q=kAT p I . I 4x Q = UAAT I.Ie -ux Pwr = Wg m I=I
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- o P=P 10 SUR(t) TVL = 1.3/u p.p .t/T HVL = 0.693/p o
SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg) IA *ff DI SUR = 26 CR = S/(1 - K,gg ) g,p
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T = '(t*/p ) +
, [(f 'p)/Aeff]p T = 1*/ (p - Q M = 1/(1 - K,gg) = CR g/CR0
"( ~ 0)! eff D M = (1 - K,gg)0 (I ~ eff)1 8 " ( eff-1)! eff = AK,ff/Keff SDM = (1 - K,gg)/K,gg
-5 p= [1*/TKygg -] + [B/(1 + A,ggT )] ,
1* = 1 x 10 seconds
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P = I$V/(3 x 1010) A,gg = 0.1 seconds I = No Idgg-Id22 WATER PARAMETERS Idg
=Id 2 2
1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters) I gal. ='3.78 liters R/hr = 6 CE/d (feet) 3 1 ft = 7.48 gal. MISCELLANEOUS CONVERSIONS , 3 10 Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps Density = 1 gm/cm 1 kg = 2.21 lba 3 Heat of vaiorization = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr , Heat of fusica = 144 Btu /lba 1 b = 3.41 x 106Btu /hr k 1 Atm = 14.7 psi = 29.9 in. Ig. 1 Btu = 778 ft-lbf I ft. H O 2
= 0.4335 lbf/in 2 1 inch = 2.54 cm F = 9/5 C + 32 C = 5/9 ( F - 32)
0 5.01 (1.0) the following is NOT a reason for rod sequencing and Which of ' overlap 7 A) To keep power peaking f actors within design limits E ' Optimize fuel burnup and energy generation C) Minimize effects of dropped rod on power distribution D) Ensure cycle to cycle fuel will aseet core lifetime engineering designs ANSWER : C REFERENCE : Palo Verde Tech. Spec. Bases 3/4.1.3 1
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I 5.02 (1.0) esill generate the i State sehether the situations listed beloos of the greatest tensile stress on a the inner OR outer esall' reactor vessel. Ah,Heatupatarateof90degreesF/ hour B) Cooldoesn at a rate of 50 degrees F / hour ANSWER = A) Outer B) Inner REFERENCE : Palo Verde, Teck. Spec Bases 3/4.4.8 2
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5.03 (1.0) as pipe diameter increases. Head loss due to friction __ _ ANSWER : Asecreases REFERENCE : Palo Verde Chapt. Cection II , page 18, Fluid flow - A. Pumps. 3
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t 5.04 (1.0) How enould the peak Xenon amplitude ch , after a Reactor trip, if the half-life of Iodine 135 was ger. AN.S.WER : will decrease.(The reason Xenon peaks is The peak amplitud because Iodine d y to Xenon is f aster than Xenon decay) REFERENCE : Palo V de (STD), Vol XI, Chapt. I, Sect. I, Reactor theory, Page 34. 6
e f t 5.05 (2.O) The reactor is determined to be shutdoesn by 5 % Delta K / K with indication in the source range of 30 counts per second. ' mat esill the source range indicate ashen Kef f in O.98 and 0.99 ? ANSWER : DELTA K
- --- = 0.05 K
1 -K
------- = 0.05 K
1 = K + 0.05(k) 1 = 1.05(k) K= 1 / 1.05 = 0.95 ( must be determined this way ) (0.5 points) 1 - K1 CR2 and 0.05 CR2
------ = --- - = ------ (0.5 points) 1 -
K2 CR1 0.02 CR1 (0.5 points) CR2 = (30), (2.5) = 75 cps Conversely CR3 0.05
---- = ----- (0.5 points) 30 0.01
= 150 cps (0.5 points)
CR3 = (30) (5) REFERENCE : Palo Verde Vol. XI, Chapter I, Section I l 5 l l
O e 5.06 (3.0) Figure 5 - 1 shows a closed loop system esith three (3)' identical parallel centrifical pumps. Initially all pumps are running.
- - WW the f11ter in the common pump suction line A) If to the becomes partially clogged, what happens (1.0)
Delta P indication 7 B) If the discharge valve A - 3 is throttled closed partially, eshat happens to the flow in pump "B" (1.0) discharge line ? C) What happens to Delta P indication if discharge (1.0) valve A-3 is throttled closed partially ? ANSWER : A) Decreases B) Increases C) Decreases REFERENCE : Palo Verde Vol . XI, Chapt. 1 : Theory Section 2,Thermo., page 30 & 27. i 7
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A-1 N k4- n X , x Q %sveny B-2 B-3 D-1 M W - i a D4- i TANK T . C-2 C-3 ( water 1. _ .
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& S TfA M 54 fay FILTER 220.0 ;
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20.0 ' v s J O.0 0.0 40.0 80.0 120.0 160.0 200.0 240.0 280.0 System Capacity (GPM) Figure 5 -I i
5.07 (2.0) The reactor is at DO % poseer esith T hot 578 F deg. and T cold 542 F deg. Core floes is at 100 %, ashich is 90 million 1bs'/ hr. A after natural circulation is station blackout occurr. and, established, core Delta T = 30 f deg. A) If decay heat is aprox 2 % of full poseer , What is the mass floes rate ( % of full floes ) ? ANSWER : O = m cp d T (0.5 point) 2%= $ cp 30 f 80 % = 100 % cp 36 f
%/$ 30 f = cp = 80 % / 100 % 36 f (0.5 point) cp = 2 E=2% x 100 % 36 f / 30 f x 80 %
E = 7200 / 2400 m=3% (1.0 point) REFERENCE 's Palo verde, vol. IX, Sect. 4 078. & Vol XI, Chapt. I, Sect. 2, Page 16. i l l l 8 l
5.08 (1.0) mich condition enould equation G=edh NOT be applicable for 7 f A1 Across the reactor ( cold leg to hot leg ) B) , Across the steme generator (primary to secondary) C) Acr oss the steam generator (f eedesater to steme) D) Across a heat exchanger shall side (inlet to outlet) a ANSWER : B REFERENCE : 2, Palo Verde Vol. IX, Sect. 4, D 11. & Vol. XI, Chapt. 1 Sect. Page 16. 9 i
5.09 (1.0) As temperature decreases in the RCS coolant, density increases which increases the moderator to fuel ratio. Provide ' teso (2) reasons ashy nuclear instrumentation count rate will decrease as RCS temperature decreases 7 ( assume BOL, no control rod movement, and no boron dillution or addition in progress. ) ANSWER : A) Neutrons travel less distance, less leakage. (0.5) (TEAPERwatC Sp A caw s ky df THC OghzlK.) B) Higher baron density, more absorption by baron. (0.5) REFERENCE : Pal o verde Vol . XI tab 1 reactor theory,page 5.3 i 10
l 5.10 (1.0) hich statement below is correct if the power range instruments have been adjusted to 100 % based on a calculated calorimetric ? A) If feedwater temperature used was higher than actual, actual pot $er will be less than indicated. If RCP pump heat is ommitted from the calometric, B) actual power will be less than indicated. C) If steam floes used was lower than actual, actual power will be less than indicated. D) If steam pressure used was lower than actual. Actual poseer will be less than indicated. ANSWER : B REFERENCE : Palo Verde Vol XI Thermo hydraulics, page 16 l f l f l l 11 t
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5.11 (1.0) mat is the correct order of the boiling phases listed'below as HIGH they enould occur in a coolant channel with normal flow and heat flux 7
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- 1) Transition Boiling
- 2) Bulk Boiling
- 3) Film Boiling
- 4) Subcooled Nucleate Boiling ANSWER :
4, 2, 1, 3 REFERENCE : Palo Verde Vol XI, Chapt. I, Sect. 2, Page 34 & 35 l l l \ l I 12
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5.12 (1.0) A centrifical pump is operating at 1200 RPM, with a discharge fIow rate of 190 EPM at 300 psig. Initial pump poseer consumption is 50 KW. If the speed is changed so that the pump is using 400 set of the data below most closely reparements the KW, ashich constant efficency in an pump parameters 7 ( amma n== associated ideal pump) A) 2400 RPM, 600 PSIG, 720 GPM B) 2400 RPM, 1200 PSIG, 360 GPM C) 3600 RPM, 900 PSIG, 540 GPM D) 3600 RPM, 600 PSIS, 540 BPM ANSWER : B ! REFERENCE : STD pump law, Palo Verde Vol. XI, chapt. I, Secrt. 2, Page 20. 1 l l l i 13 l l l
5.13 (2.0) The folloosing data esas obtained during a core refueling. Number of assemblies loaded Neutron count rate O 40 cps 5 70 cps 10 90 cps 15 115 cps take to reach the The total number of assemblies it esill minimum critical size is assemblies. Use the attached graph paper if desired. (assume equal assembly esorth) . ANSWER : M = CR 1 / CR O = 70 / 40 = 1.75 33 assemblies 1 /M= 1 / 1.75 = .571 (From a linear plot 1 / 115/40 = .348
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R ERENCE : dS / #[ 2 - O 3 33 Cg, Cfz $0 - // 5 M Pal o Verde Vol . XI, Reactor Theory Page B14 & Fig. 8-12. 14
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1 5.14 (1.0) The time to peak Xenon conditions, after a Reactor trip from peak 100
% power and equilibrium Xenon is than the time to Xenon conditions following a reactor trip from 50 % kower and equilibrium Xenon because the equilibrium Xenon concentration at 50 % power is __ _ half of the Xenon concentration increases at 100 %
power, which physically is because increasing burnout as well as production. ANSWER : Gewrat. fjMB@, greater than, f lux (/vvid REFERENCE : Palo Verde Vol . XI, Chapt 1, Sect. 1, Page 35. I 15
5.15 (1.0) Beta, the fraction of delayed neutrons, _ over core life. ANSWER : D'ecreases REF'ERENCE : Palo Verde Vol. VOL XI, Chapt I, Section I,Page 15. T D 16
5.16 (1.0) The Doppler power coefficent tends to become ________ negative over core life because of better heat transfer due to '_________. !
/hadf M, clading creep.(CLOS /hG GM A)
REFERENCE : Palo Verde volume XI, Chapt. 1, sect. 1, page 23. I a 19
_ . . . __. . _ _ . . _ . _ _ _ _ . . . - _ _ _ . . _ . _ _ _ . = . _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ . _ . _ __ _ _ ._ __ - _ _ _ _ _ 5.17 (1.0) Delayed neutrons are _________ effective in sustaining the chain reaction in the core than an equal number of prompt neutrons j t ANSWER : LESS ., REFERENCE : I Palo Verde vol XI, Chapt. 1, Sect. 1, page 16 L 1 i .i 1 k L m l l 20
5.18 (1.0) Why are burnable poision rods designed into the reactor core rather than simply increasing the boric acid concentration in the reactor coolant 7
- ANSWER :
Burnable poi si on rods are used to reduce the soluble boe on concentration to ensure that the moderator temperature coefficent is negative for power operations. REFERENCE - Palo Verde vol. XI, chapt I, sect. 3, Page 42. e 21
5.19 (1.0) l l The control rod worth of all 76 CEA's moved together is _______ l the sum of each individual CEA worth. ANSWER : I less than REFERENCE : Palo Verde Vol. XI, Reactor theory, page 14.5. I f
5.20 (1.0) A penalty factor, which changes from BOL to EOL, is applied to the DNBR limit to accomidate the effects of __________,. ANSWER :
' Rod bow.
REFERENCE : Palo Verde Teck. Spec. Bases Page B 3 / 4 2-3, Spec 3/4.2.4 t-COLLS and CPC's. System. I e 23
6.01 (1.0) 16 seconds after a Reactor trip Steam Generator level i s 52 */. . Steam Generator level is being controled by ___________. A) Reactor Trip Overide (RTO) B) Single element C)- Economizer valve D) Modulating Feed Pump Speed ANSWER : B REFERENCE : Palo Verde Vol. III, Nucl ear Systems 9A, Feed Water Control,page NS-9A-5. i e e 1 i
6.02 (1.0) The downcommer valve is reopened at high steam t a ow rates to provide ________ to the steam generator downcommer annulus. This is necessary to alleviate the effects of ____ ___, thereby enhancing the Steam Generator circulation ratio and sta 111ty. ANSWER : subcooling steam carryunder lO lO fm foWA how ( MStr Vh ve- poskobu g y %) REFERENCC : Palo Verde Nuclear Systems 9A, Feedwater S y r.,t e m , Page NS-9A-13.
6.03 (1.0) The main ob.jective of the _ _ _ _ _ __ is to increase plant , availibility by avoiding unit trips due to Reactor Regulating ) System Failures. A) Automatic Withdrawl Prohibit (AWP) B) Automatic Motion Inhibit (AWI) C) Reactor Power Cutback System (RPCS) (D) Steam Bypass Control System (SBCS) ANSWER : A ANo/o< B REFERENCE : A, Palo Verde Vol III, Nuclear Systems, Steam Bypass 95,Page NS-7B-
- 8. F#q S 6 C,5 0- Foil R R s VOL'3 p, n cy s tv~ hS 4 c - ! G, r eota anen b..
3
~
6.04 (1.0) The AMI setpoint is 25 %, while Reactor and Turbine load are at 50 %, When the main Turbine trips on low condenser vacuum. Control Rods respond How ? ' A) Do not move, because turbine load index is less than 60 % B)- Insert till Reactor power is at AMI setpoint of 25 % C) Insert till 20 % Reactor power, because of RPCS lower limit D) Insert till 1G % Reactor power, because this is AMI limit. ANSWER : D REFERENCE : Palo Ver de Vol III, Nuclear Systems NS-9B, Steam Bypast Control System, Page NS-9B-9. 0 4
6.05 (2.0) The Steam Bypass Control System is designed to increase plant Availability. List all Initiating or combinations of initiating inputs that generate a " Quick - Opening - Block " Fdnction to the SBCS. ANSWER :
. . o A) Reactor trip and T ave less than or equal tc,{4Ijf9 AF)
( 1. :6
~
Ly cue : No lam 7'jfve B) A feed pump trip. (1.0) (This will generate a reactor p own-cutback with turbine setback.) PEFERENCE : Palo Verde Vol XI,\ tab 4, I 8, C , Sectior; 1f. Fage 13-2. s
. o 6.06 (1.0) Connections are provided on two of the main steam lines, upstream of the MSIV's, to Nitrogen gas. Why ? A) Prevent corrosion in S / G . B) Back seat MSIV's When shut down C). Pressure source for periodic Hyhro Testing D) . Assure no primary to secondary leakage during shut down ANSWER : A REFERENCE : Palo Verde Vol . IV, Power generating Systems PGS-1A, Fage F GE-1 A-5. 9 i 6 l
6.07 (1.0) There are 61 fixed incore neutron detector assemblies. How does a background detector differ from the other detectors within its assembly 7 ANSWER : A background detector is a signal cable without a rhodiuni detector. REFERENCE : Palo Verde Vol. III, Nuclear Systems, Fixed Incore Inst. -5A, Page NS-5A-6. c i e i 7
6.08 (1.0) Why is Undershoot " , by the Reactor Regulation System, necessary f.ollowing a greater than 10 % reduction in main turbine load 7 ANSWER : ' Necessary to remove the energyistored in the RCS REFERENCE : Palo Verde Vol. III,Nuc1 ear System 9C, Reactor regulation S/ttem, Page NC-9C-19. B
6.09 (1.5) The operational controls and indicators for the Excore safety channel include a " Trouble " lighted pushbutton with a memory function. List all information provided by the " Trouble " lighted pushbutton memory. ANSWER : A)- Indicates if detector voltage is or has been below a preset value. (0.5) B) Indicates if a interlocked circuit card is or has been removed. (0.5) C) Indicates if test or calibrate switch is or has been out of the normal or operate position. U . 5) REFERENCE : Palo Verde Vol.111, Nuclear Systems 4, E :cor e Nucle +r Inst.,Page NS-4-36. 9
/
6.10. (1.5) The letdown bypass valve, in the CVCS, is centro 11ed by an keylock switch. Full flow is Aproximately 0.5 GPM. When and why is this letdown bypass flow used 7 i ANSWER : (>n w- ) when at power and normal letdown is secure it is used before normal letdown is restored (0.75) to ' . ; .- i n c-Shor-mm l- t r ar c i an t s at the char gi r.g /l enn no r el . (0. 75) WA/M HP O fwe) C fic cAn e nP s*/ n & . REFERENCE : Falo Verde Vol. II, Nuclear Systen 2A, CVCS,Page NS-2A-40, 10
'6.11 (2.0) i l
l Each of the normal pressurizer spray valves has a manual bypass l valve. What are the reason (s) for these bypass valves ? ANSWER : ' A) Minimize thermal shoti. when spray val vet open.(1.0) B)-Maintain uniform chemistry and temperature in Pressuriner.(1.O) REFERENCE : Palo Verde 11, Nuclear Systems 1 B , Pr es s ur i z er , Page NS-10-7. 11
. . . - - _ _. .=.- .. -. .. __ . _ _ ._
6.12 (1.0) How is the reactor coolant pump seal injection temperature regulated ? ANSWER : e Temperature i s regulated by controlling the position of the condensate flow valve. REFERENCE : Pal o Verde Vol . II , Nuclear System 2A, CVCS, Page NS-2A-47. i S 9 i 12
+ - - - -.-- + - . - - r- .- ._ _ _ - . .
6.13 (2.0) Other than manual, what signals and their setpoint's will close the reactor coolant pump seal injection isolation valve 7 ANSWER : A) High-high seal injection heat exchanger out l et temperature, 150 F deg O/ . Q) . B) Low-low Heat exchanger outlet temperature, 70 F deg. O/.9) REFERENCE : rFalo Verde vol. II, Nuclear Syste s 2A, CVCS, Page NS-2A-47. 13
'6.14 (1.0)
What is the reason for the charging line backpressure controller in the CVCS 7 9 ANSWER : To maintain reactor coolant pump seel injection pressure- hi gher than reactor pressure. AsiD ot Plas'!Ac~ 11H$titM sf tyf af 6 MCM6/L Y/ FAN /Ubarbt f'tiCStf/W sfxAf REFERENCE : Palo Verde vol.II, Nuclear Systems 2A, CVCS,Page NS-2A-46. T 14 i
6.15 (1.0) Why are deborating Ion Exchangers used towards end of core cycle instead of feed and bleed deborating ? I ANSWER : Lowering baron concentration significantly at EDC low baron concentrations generates excessive waste water. REFERENCE : Palo Verde, Nuclear Systems 2A, CVCS,Page NS-2A-70. 4 1 16
6.16 (1.0) How does the design of the Chemical and Volume control System minimize the potential for thermal transients, to the pressurizer, when Auxilliary Spray is used 7 t ANSWER : Aux Spray flow is warmed by the regenerative heat exchanger. REFERENCE : ' Palo Verde Vol I, Nuclear System, CVCS, Page NS-2A-73. 17
1 6.17 (1.0) At , , , _ _ _ _____ Degree's F. RCS temperature the containment spray pumps are _ during the shutdown cooling. A) < 200 deg. F, secured B) < 200 deg. F, used C) > 200 deg. F, secured D) > 300 deg. F, used ANSWER : B REFERENCE : Palo Verde Vol. 1I, Nuc1 ear Systems 3A, Saiety i nj ecti on t.: Shutdown cooling, Page NS-34-21. 4 le
6.10 (1.5) Which Emergency Safety Feature Actuations are generated by signals sensed by radiation monitors 7 6.20 E Fuel Building Essential Ventilation Actuation (O.Ds
" ~ Signal (FBEVAS) ** Containment Purge Isolation Actuation Signal 10.5.
(CPIAS)
*** Control Room Essential Filtration Actuation Signal (0,5)
(CREFAS)
Reference:
PVNGS Training Artic1e NS-7B-15 3- 16, ESF AS 1/2 20
6.19 (2.5) The Reactor Protection System uses variable setpoint bistables for system parameters. (a) Why are " variable" setpoint bistables used in the (1.0) RPS ? (b) What are the three (3) RPS system parameters that (1.5) use this variable type of bistable ? 6.21 (a) to eliminate unnecessary trips duririg plant *O,5) startup and shutdown (b) Ic p cr - -!::r y c;_aca, ;wn m L ._ n o . u m ien ciur .i. ' 1. 5 1 preccurc- 2nd i s.. s t :c a.: gu, c r elu,- L. 2 g, c am e a
/\
Reference:
PVNGS Trai ni ng Ar ti cl e NS-tv-21, Reactor Protection System OR. (a) w uw arc ce cww rn er ce ra.o ,s ou;aco ( s ack A S BC P P n s,e swr- Silm cut oippsnc~ rk oan u,nn os3
-r? fichp b
(0) { C l+ 8"G** o, - na iu- t .~. eau o.s e-n o.a n, enac r l-) Low PMSSusare reesse srcm stuene r+z peessnac Ato, j
- 1) L n NO 2
- 3) Lsu $ far crE"m* M Pa und
- 4) swm c~ uro,n.o s) vuxaw ovatpou>cn rQ /
/ 21
PROCEDURES - NORMAL, ABNORMAL, EPERGENCY AND RADIOLOGICAL CONTROL 7.01 (2.0) For the below conditions, Briefly explain, why it is desirable for condition A) and not desirable for condition B)., to have the Emergency Diesel's SPEED MODE SELECTOR SWITCH in the ISOCFRONOUS position 6). h en it is carrying its respective Class IE bus (1.0) B) When paralleled to offsite. (1.0) ANSWER : a) in the Isochronous position, - if load changes occur, the diesel generator will strive to maintain 60 Hz r.d ^2t;d vu;;._g.(O.5) As load changes on the class IE bus the diesel will adjust and always return to the preset speed and verrtawe (0.5) b) It is undesirable for parallel operations because a frequency decrease on the incoming bus would result in the diesel striving to maintain the frequency at preset value (0.5). it
- . would pick up more and more load, overloading and possibly damaging the diesel (0.5)
OR
...If frequency increases on the incoming bus, this would cause the diesel to shed load (0.5) and eventually could go into a reverse power condition, damaging the diesel or trip the output breaker. (0.5)
References Lesson Plan NLC-23 and 410P - 1DG01 1
7.02 (1.0) kill in the Blanks in reference to the Emergency Diesel Generator procedure (410P - 1DG01): The Emergency Diesel is designed to supply KW continiously, but can supply KW for hours esi thin any hour period. ANSWER : A) 5500 (0.25) B) 6050 (0.25) C) 2 (0.25) D) 24 (0.25)
Reference:
410P - 1DGO1 l l l 1 2
7.03 (2.0) In reference to the Locked Valve and Breaker procedure (40AC - OZZO6): Identify two (2) circumstances for which independent verfication need not be performed by a second qualified operator, for systmas EMPORTANT TO SAFETY. ANSWER: ( any 2 of 4 below, 1.O each)
- a. Those po ions of as em within adiation ea ich will r uit in grea r than 10 mr whole b yd .
- b. Th e portio of the syst in a ted Amirborne
+
h ' h)) h3 l Ollb (fL p p. If functional testing can be perf ormed without compromising safety, and it can prove all equipment, valves and switches involved are correctly alligned. 3[. If those portions are inaccessable, and safety instrumentation is available to verify position. grade
Reference:
40AC - OZZO6 Locked Valve and Breaker Control. 1 l 3
t 7.04 (2.0) In the procedure ~for Refueling Machine Operations, 41DP - 1F, the wet and dry seeight of a fuel assembly is "noted" several times.
- a. What are these weights? (1.0)
- b. Why are they "noted" ? (1.0)
Answer :
- a. 1451+/-25 lbs. DRY (0.5) 1261+/-25 lbs. WET (0.5)
- b. So that the operator of the refueling machine will recoginize when the fuel element has hung up (0.5) or is resting on something and full weight not being carried by the refueling machine. (0.5)
Reference : 41DP - 1F 4
t 7.05 (1,0) h en draining the Safety Injection Tanks, the water is stored in then
- a. Reactor Makeup Water Tank
- b. Refueling Water Tank
- c. Refueling Cavity
- d. Reactor Coolant Drain Tank ANSWER :
- b. (1.0)
Reference : 41DP - 1S103 & Lesson Plan NS - 2A - CVCS s 9 5 l
1 l
\
7.06 (3.0) h l During reactor startup, verification of proper overlap between Startup and Log Safety Nuclear Instrumentation Channels is required prior shifting the high voltage to the control channel.
- m. Over what range of each instrument should the overlap occur? (1.0) I b When is the High Voltage to the Startup channels shifted? (0.5)
- c. Why is the High Voltage Shifted? (0.5)
- d. How is the channel designed to minimize this problem if the High Voltage is inadvertantly not shifted 7 (1.0)
ANSWER :
- a. 20 to 2000 cps = 2 X 10-8 to 2 X 10-6 % power (1.0)
- b. When High CPS alarm is received ( approx.2OOO cps ) (0.5)
- c. To prolong the life of the startup channel. (0.5)
- d. The startup channel current will be limited to 1 milliamp by a resistor in the high voltage supply. (1.0)
Reference : 410P - 1ZZO3 and Lesson Plan NS-4 ( 6
f 7.07 (2.5)
, If during a reactor startup, RCP 1A trips, and you are the Control Room Supervisor (CRS) in r.harge of the estartups
- a. What Itirge procedural restrictions do you have for the first restart of a hot and / or cold RCP 7 (1.5)
- b. What are the restrictions for additional restarts of the RCP 7 (1.0)
ANSWER :
- a. 1. Allow motor to coast to a stop before attempting a restart. (O.5)
- 2. Do not attempt more than two consecutive starts with a pjjjj, i
cold motor (umbient temperature) (0.5)
'#l '
- 3. 'Do not attempt more than one start with a hot motor
[ ( greater ambi nt but less than 293 degrees F ) 4, /// WJ b. ())Jul ofofYjg' (An interval oO mt'.8hM inutes with the motor running or) 60 minutes with the motor stopped must elapse before attempting an addi tional start. (1.0) Reference : 410P - 1RCO1 and APS Exam Bank i i I e 7
I 7.08 (3.0) Indicate whether each of the following statements are TA&E or FALSE as they pertain to the Reactor Plant Startup Procedure:
- a. During the reactor startup, the shutdown CEA groups are fully withdrawn, the regulating CEA groups are withdrawn to their Estimated Critical position and then RCS baron concentration is diluted until criticality is achisved. True or False? (1.0)
- b. If the required Baron concentration change is greater than 50 PPM initiate Pressurizer Spray to equalize Pressurizer and RCS baron concentrations to within 10 PPM. True or False? (1.0)
- c. After criticality is achieved, increase reactor power to the point of adding heat (POAH) at approximately 5.0 DPM.True or False? (1.0)
ANSWER :
- a. False (1.0) s
- b. True (1.0)
- c. False (1.0)
Reference:
410P - 1ZZO3 8
7.09 (1.0) Fill in the blank for If you receive no ashole body radiation exposure for the first seven aseeks of a calendar quarter, then you may receive up to ___ eroe during the eighth essek esithout exceeding the normal eshole b'ody adminstrative exposure control limit.
- a. 100
- b. 300
- c. 500
- d. 800
- e. 1000 Answer a
- b. (300 mrem) (1.0)
Reference : 75AC - 9ZZO1 APPX A i 9 i
7.10 (2.0) List four separate conditions that require EPERGENCY BCRATION. State all your assumptions! ANSWER : (Any 4, 0.5 each)
- a. Failure of 2 or more CEA's to trip following a reactor trip.
- b. Shutdown Margin is less than 6.0% (modes 1 to 4)
- c. Shutdown Margin is less than 4.0% with Tave less than or equal to 210 degrees F.
- d. Reactor power not decreasing to source level fo116 wing a reactor trip.
- e. During refueling:
- Keff greater than O.95 Baron r.oncantration less than 2150 PPM.
Reference:
41AO - 12Z01 r l l l l l 10
7.11 (2.0) Concerning operation with a fuel element failure, with no primary to secondary leakage
- a. Describe how the operating personnel would detect a fuel elmeent fmilure? (1.0)
- b. What instrument would most likely provide the first indication 7 (0.5)
- c. Explain how they would be able to distinguish it from a Crud Burst. (0.5)
ANSWER : . TM coc5 R g - W DCraTK W4'O $Y'dRS*~ *
- E C'A*SS A CS AC h';' *'t OS:
- a. An unexplained increase in the RCS activity would be an indication of a fuel element leaking. (1.0)
- b. The Letdown Process radiation monitor in the CVCS would be the most likely first indication. (0.5)
- c. Have chemistry draw a sample and measure 1131/1133 ratio.
This will confirm the element failure. (0.5) 6 8 ', Osn.y s.Eroovs) PRoccc55 M oNir0R. G.RoSS Acnv.Ty* pin.h en W e4LQ j pCQQSE O A) A Cnao 11uRS T -thC R s - W CMkNct. wouto por f pcacnsi, 7*It*S R ELAnMsjim wwto se esr tuodark? ro OPipntv/2 of O2un Stes!~ k',reourcuoa.,xa psicee . - Reference : CVCS description and TS 3/4.4.7 and bases. 11
7.12 (2.5) Concerning the 41RO - 1ZZO6, The Steae Generator Tube Rupture procedure, answer the followings
- a. Briefly describe why the S/G 1evel in the affected S/G is maintained greater than 65% WR. (1.0)
- b. What is the prefered method to cooldown the RCS following a S/G tube rupture, if the MSIV for the affacted S/G is stuck open? (Assume you are less than 535 degrees F) (1.5)
ANSWER :
- a. Maintaining S/G 1evel greater than 65% for the affected 5/G ensures tube coverage (0.25), which will minimize radioactive r el ease if the ADV cycling is required. (0.75)
- b. Shut the uneffected S/G's MSIV (0.5), isolate Main Steam to the Aux Feed Pump from the affected S/G (0.5), and use the ADV on the uneffected S/G to cooldown the RCS. (0.5)
Reference : 41RO - 12Z06 i j i i 12
d
\
\
\
)
l 7.13 (1.0) According to 41AO - 1ZZ13, " Natural Circulation Cooldoesn", which of the following is NQT a proper indication of Natural Circulation?
- a. RCS cold leg temperature at maturation for S/G 4 pressure, and is controlable.
- b. Core exit thermocouples indication are stable and trending down.
- c. QSPDS indicates the RCS is becoming more subcooled.
- d. Core delta temperature (That - Tcold) is more than 57 degrees F. and is increasing.
ANSWER :
- d. (1.0)
Reference : 41AO - 1ZZ13 This is the end of Section 7 13
8.01 (2.0) In accordance with 10 CFR 20, " Standards f or Protection Against Radiation": (a) What is a RADIATION AREA 7 ' '
't.0)
(b) What is a HIGH RADIATION AREA 7 (1.0) 8.01 (a) An area (accessible to personnel) where a ma;or poriton of the body could receive (greater than): 5 Mrem in one hour (0.5, or 100 Mrem in five (consecutive) days. 'O.Un (b) An area (accescible to personnel) where a major portion of the body could receive (greater than): 100 Mrem in one hour. (1.0) Reference 10 CFR 20. 203 (b) (2) and (b ) (3) 1 1 l
8.02 (3.0) In accordance with 10 CFR 55, " Operators' Licenses": (a) As defined in 10 CFR 55, when is an individual (1.0) deemed to be operating the controls of a nucl ear, facility ? ib) What are the " controls" as defined in 10 CFR 55 7 (1.0)
"(c ) According to the " Exemptions from License" (1.0) provi si ons of 10 CFR 55 which individuals are allowed to operate the the reactor controls without a license 7 8.02 (a) An i ridi vi dual is deemed to operate the controls of ( 1, O r a nucleer facility it he directly manipulaten the controic or directs another to manipulate the controls.
(b) " Controls" means apparatus and mechanisms the '1.0) manipulation of which directly affect the reactivity or power level of the reactor. (c) An individual may manipulate the controls an a (1.0) part. of his training to qualify for are operatur license under the directi on and in the presence of a licensed operator or sensor operator.
Reference:
10 CFR 55.4(d) 8, (f) and 55.9(b) 2
8.03 (3.0) Refer to 10 CFR 50.72 and or 10 CFR 20.403 ( ATTACHMENT), which of the following events require immediate notification (within a period of one hour or sooner) to the NRC Operations Center via the Emergency Notification System 7 (0.5 each) * (a) Personnel exposure to an individuals hands of 200 Rems of radiation while performing steam generator tube repairs. (b) Personnel exposure to an individual's whole body of 30 Rem of radiation while working in a steam generator. (c) Declaration of an " Unusual Event" at PVNGS. (d) Taking the plant from mode 1 to mode 3 to comply with Technical Specification requirements. (e) Taking the plant from mode 3 to mode 5 to comply with Technical Specification requirements. (f) Discovery in mode 1 that two safety injection level instruments were improperly calibrated and that the levels have been above or below Technical Specification limits for two weeks. G.02
- D, C, li, and F requi re not i f i cat.icni wiLnin one hour. (0.5 each)
++ A end E do not require not i fi cat s ten wi t h2 n e n t?
hour. (0.5 each) i
Reference:
in CFR 20.403(a) and 50.72(a) (1)2 3: 50.72(b) 3
a cw %, su wr4 us.a t:-t-es t a sun} I tse tu noe my s.19e. as rawnded at 3s (d) Reports made by licensees in re- Nuclear Reguietory Commission Fit 1211.Jan I1.1973.48 FTt 33859 July 26. spond t3 the requirements of this sec-( A) In cn uninalyzed condition.thrt 19831 tion must be made as follows- under i 50.21(b) or 150.22 cf this part compromises plLnt (1) Ijeensees that have an installed hall notify the NRC Oper"_tions si;nificantly . t 2e.103 ho(ifications of incidents. Emergency Notification System shall Center via the Emergency Notification safety; " " (:) Immediate nottfacation. Each 11- make the reports required by para- System of; ' UI I" " C"" censee shall immediately report anF graphs (a) and (b) of this section to (i) The declaration of any of the design basis of the plant; or eserts insolving byproduct, source. or the NRC Operations Center in accord- Emergency Classes specified in the 11- (C) In a condition not covered by the special nucicar material possessed bY ance with 5 50.72 of this chapter. censee's approved Emer;:ency Plan;' plant's operating and emers ency pro-the licensee that may have caused or (2) All other licensees shall make the or cedures. threatens to cause: reports required by paragraphs (a) and (ill Of those non-Emergency events (iii) Any natural phenomenon or (1) Exposure of the whole body of (bl of this section by telephone and by specified in paragraph (b) of this sec- other external condition that poses an Eny individual to 25 rems or more of telegram. mallgram. or facsimile to the tion actual threat to the safety of_ the nu-radiation; exposure of the skin of the Administrator of the appropriate NRC (25 If the Emergency Notification clear power plant or significantly ham-chole body of any individual of 150 Regional Office listed in Appendix D System is inoperative, the lleensee pers site personnel in the performance remm or more or radiation; or exposure of this part. shall make the required notifications of duties necessary for the safe oper-a;f the feet, ankles. hands or forearms - via commercial telephone sarrice, ation of the plant. of any individual to 375 rems or more other dedicated telephone system, or (iv) Any event that results or should of radiation;or any other method which will ensure hate resulted in Emergency Core (2)The release of radioactive materi- that a report is made as soon as practi- Cooling System (ECCS) discharge into al in concentrations which. If averaged cat to the NRC Operations Center.' the reactor coolant system as a result oser o period of 24 hours, would (3) The licensee shall notify the of a valid signal. Exceed 5.000 times the limits specified NRC immediately after notification of (v) Any event that results in a major for such materials in Appendix B. the appropriate State or local agencies loss of emergency assessment capabil-Table II of this part; or and not later than one hour after the ity, of fsite response capability, or com-(3) A loss of one working week or time the licensee declares one of the munications capability (e g . signif t-more <f the operation of any facilities Emergency Classes. cant portion of control room indica-affected; or (4) When making a report under tion Emergency Notification System.
) Damage to property in excess of paragraph (aH3) of this section. the 11- or offsite notification system).
C) 7Nenty-four hour nott/lcation. #" (vi) Any event that poses an act al ( h erge ey Class declared; or o Each licensee shall within 24 hours of (til Either paragraph (bMI). "One. threat t,o the sa e discovery of the event, report any llour Report " or paragraph (bM2), power p event involving licensed material pos- ..Four-Ilour R'eport." as the paragraph duties site personnel necessaryinforthe theperformanc o safe opera on sessed by the licensee that may have of this section requiring notification of of the naclear power plant caused or threatens to cause'- Ev t (1) Exposure of the whole body of b crg ncy e en'fs-(l) One. fires, toxic gas releases, or radioacti e any individual to 5 rems or more of ra- hour reports. If not reported as a dec. releases. (2) Four-hour reports. If not report-diation; exposure cf the skin of the laration of an Emergency Class under ed under paragraphs (a) or (bMI) o whole body of any individual to 30 Eara raph (a) of this section. the li. this section, the licensee shall notify rems or more of radiation; or exposure cen shall notify the NRC as soon as the NRC as soon as practical and in all of the feet, ankles, hands, or forearms to 75 rems or more of radiation; or [ractical and in all cases within oneour of the occurrence of any of the cases, wi (2) The release of radloactive matert. rence of any of the following. I
- ti) Any event, found while the reac-al in concentrations which. lf averaged ( (A)i.he initiation of any nuclear over o period of 24 hours, would plant shutdown required by the torfound is shut down, while that, had the reactor uns it in been oper-cacced 500 times the limits specified Plant's Technical Specifications.
for such materials in Appendix B. (B) Any deviation from the plant's ation, would have resulted in the nu-Table II of this part; or Technical Specifications authorized clear power plant, including its princi-(3) A loss of one day or more of the ursuant to i 50.54(x) of this part. pal safety barriers.teing seriously de-operation of any facilities affected; or il Sa12 Imme<fiate notification require- glip Any event or condition during graded or being in an unanalyzed con-( Damage to property in excess of ments far operatine nuclear power re- operation that results in the condition dition that significantly compromises
* * "d" of the nuclear powerplant. Including plant safety, m! lon pu att his section ' e m ci sults i n an a o au mt a o 1
ni lea g tsy c rad d or res Its i be prepared so that names of individ- er e t r scens e licenml ar power plant being- of any Engineered Safety Feature uals who have received exposure to ra- ( ESF). Including the Reactor Protec-diation will be stated in a separate 'Other trquirements for immerfiate nor6h tion System ( R PS )- Ilowes er, act u-part of the report. catmn of the NitC by hcensret ofwraf mr nu 'These Fmerre icy Classes are addressed ation of an ESP. Including the ItPS.
%r smurr reactors are contamret risc 6n Appendo E of this part. that results from and is part of the 256 A d";.o $ ni'8%;.j"7 "' " " " ' a r- M ","3N*o'ns'fe'n",", % 2o"" N I-os'so preplanned sequence durinn testinc or
, 457
8.04 (1.0) 10 CFR 50.54(x) allows a licensee to take reasonable action that departs from a license condition or Technical Specification in an emergency when this action is immediatly needed to protect the public health and safety and no action consistent with license conditions and Technical Specifications that can provide adequate or equavilent protection is immediatly apparent. Licensee action permitted by this paragraph shall be approved, as a minimum, by ________ prior to taking the action. Which response best completes the above statement ? (a) the senior licensed operator present (b) a licensed senior operator (c) the plant licensed control operator (d) a licensed reactor operator Jk 01 G.04 (B) is tire correct answer. (1. o i I,
Reference:
10 CF R 50. 54 ( x and (y) , 4
e 8.05 (1.0) According to 10 CFR 50.36 and the PVNGS Technical Speci f i cati ons , exceeding a safety limit requires _________ . (a) placing the plant in hot standby within one hour and filing a Safety Limit Violation Report within 24 hours.
< (b) placing the plant in hot standby within six hours and notifying the NRC within one hour.
(c) placing the plant in hot standby within six hours and filing a Safety Limit Violation Report within 24 hours. (d) placing the plant in hot standby within one hour and notifying the NRC within one hour. B.05 (D) is the correct answer. i i . 0 .'
Reference:
Technical Specifications sections 2.1 and 6.7.1 10 CFR 50.36(c)(1)
r pSd*L ~ B.06 (1.0) 00
* ,/
Considering the Bases of the PVNGS Technic 41 Specification safety limits, which of the following statemenyj'is correct ? (a) The Local Power Density High trip is provided to, prevent the linear heat rate in the core from exceeding the fusel design limit in the event of a design basis anticipated operational occurance. (b) The Local Power Density High trip is provided to prevent the linear heat rate in the limiting fuel rod in the core from exceeding the fuel design limit in the event of a design basis accident. (c) The DNBR-Low trip is provided to to prevent the DNBR in the limiting coolant channel in the core from exceeding the fuel design limit in the event of a design basis anticipated operational occurance. (d) The DNBR-Low trip is provided to to prevent the DNBR in the limiting coolant channel in the core from exceeding the fuel design limit in the event of a design basis accident.
't."'
8.06 (C) is t he ccrrect answer.
Reference:
PVNGS Technical Speci f icat 2 cns Dates pages 2-4 and 2-5 6
.3 CHECK 'M OR, "G" 0.07 (1.0) / If the reactor coolant system pressure exceeds 2750 PSI
[ mode 3, Technical Specifications require the pressure hen to in be reduced to less than _____ of design pressure ______. (a) 110 %, within 5 minutes. (b) 100 %, within 5 minutes. (c) 110 %, within 15 minutes. (d) 100 %, within 15 minutes. D.07 (A) is tiie c or r ec t answer. t1. > Referonce: PW4GL lechn1 Cal Speci f 1 C At i ones Ps.ragraph 2.1. i' 7
8.00 (1.0) In accordance with PVNGS station tagging and clearance requirements, which one of the f ollowing statements is inggeregt ? (a) More than one (red) danger tag may be attached to one device at the same time.
'( b ) More than one (blue) men at work tag may be attached to one device at the same time.
(c) A (yellow) caution tag and a (red) danger tag may be attached to one device at the same time. (d) A (blue) men at work tag may not hang on one device at the same time with a (red) danger tag. 8.08 (B) is the incorrect statement. (J.0) Referencer PVtJGS F rocedure 40AC-9ZZ15, Station Tagging and Clearance, cagt' 17 8
B.09 (1.0) According to PVNGS Station Tagging and Clearance procedures, temporary lifting of clearance tags for more than one shift is (a) not allowed.
~( b ) permissible with the concurrence of the acceptor
- - of the clearance.
(c) permissible with the concurrence of the responsible supervisor. (d) described on the Turnover sheet. 8.07 (D) is the correct answer. (i < > .
- Reference PVNGS Protecdur e 404C-92 215, Station Tagging and Clearance 9
B.10 (3.0) The PVNGS Technical Specification require that shutdown margin be greater than 6 % while in modes 1 through 4 and greater than 4 % while in mode 5. I (a) What is the definition of shutdown margin ?
'( b ) What are the most restrictive accident conditions (i e. Technical Specification Bases) which require the 6 */. SDM l i mi t ?
(c) What are the most restrictive accident conditions (ie. Technical Specification Bases) which require the 4 % SDM limit 7 8.10 (a) SDM is the amount of reactivity by which the (i.Q) reactor ts, or would be, subtriticci f ron. It-present condi ti on atsuming no change in part-length CEA position and all ot her CCAE are fullf inserted except the Eingle assembly of hi ghest war th which is +uily withdrawn. (b) Thr- 6 * ,. SDM limst is based on contro11ng the (1.0) reactivity transient associated with an uncontrolled RCS cocidown caused by a steem line breal at end of life and 1(c) et no load operatinu temperature. (c) The 4 % SDM limit is based on encursng that '1.0> reactivity transients resulting from a single CE4 withdrawl event are minimal.
Reference:
PVNGS Technical Specification, Definition 1.25, and bates 3/4.1.1 10
e 8.11 (2.0) Based on the PVNGS Technical Specifications, with regard to Minimum Temperature for Criticality, with the plant in mode 1: (a) What is the minimum operating loop temperaturd (1.0) CLCO for T(c)] 7
'( b ) In the event T(c) decreased below its LCO what (1.0) actions required by the Technical Specification Action statement (s) must be taken (including time limits) within one hour 7 8.11 (a) 552 F (i.es (b) Restore T(c) to meat the LCO in 15 minutes (v.5) or be in hot shutdown in the following 15 minut es. (0.61
Reference:
PVNGS Technical Specifications, 3.1.1.4 11
e . 0.12 (2.0) Complete tric .Ainimum shif t crew composition f or the modes listed below. (Do not consider health physics, chemistry or 18 C personnel . ) PERSONNEL MODE 4 (1.O) MODE 5 (1.O) SROs ______ ______ ROs _ = ______ Others(specify ______ ______ positions) 0.12 PERSONNEL MODE 4 ( 1. O ) MODE 5 ( 1. 6) SkOn 2 1 ROs 2 1
)
Others(spectfy 2AO, 1STA 1AQ positions)
Reference:
PVNGS Technical Specifications, 'lable 6.2-1 12
8.13 (2.O) e During the absence of the Shift Supervisor from the control room for modes 1 through 6, teho may be designated to assume the control room command function 7 8.13 ~
- When in modes, 1 through 4 an I n d i v i d tta l , other (1.0i than the STA, with a SRO license may assume the Control Room command function.
** While in modes 5 and 6 an individual with a RO or (4.Os SRO license may assume the Control Fcom command function.
Reference:
PVNGS Technical Specifications Table 6.2-1 13 _~ _ _ , _ _ - _ . _ - _ -. . . _ . . . _ _ _ _ _ __, _ . _ . _ __ . _ _ _ _ . .
8.14 (3.0) The plant has been operating at 90 % power for about three weeks. One motor driven auxiliary feed pump was placed out of service the previ ous day due to a bad bearing. While testing the GOO 1 Dieesel Generator the Diesel Governor iails to control ' f requency and the Diesel must be shutdown for repairs. The associated Technical Specifications are attached for your reference and the time of various events are listed below. 1100 14 November auxiliary feedpump placed out of service 1000 15 November diesel generator placed out of service 1015 15 November current time (a) Wh t surveillances or verifications must be (1.0) completed within the next two hours 7 (b) When must the plant be placed in hot standby if (1.0) neither the diesel nor the auxiliary feed pump can be returned to service 7 (c) If the steam driven auxiliary feedpump were found (1.0) inoperable at 1130 15 November when would the plant have to be in hot standby 7 G.14 (a) Each independent offstte power Supply must br t..'i chec6ed operable. The remaining diesel g erecr at or must be checlDd 3* operable. All required syst ems , subsystems, trains, t . ?'3 ; components, and devices that depend on the remoinino diesel generator ior power mu s, t be chected for operability. The E t e ans dr1ven auxi1iary feed pump mubt be ( . .' 5 .' operable. I (b) 1700 17 November ()R / POO /5'M00 (1 0) (c) 1730 15 November /7 30 15 400 (1 *' hhS"*E A SS aM G' Snthc b/w 00C 0Pfo$ ITE O/k OOC AS APP Fnw AM (.h : ow' is %"me,'a ~r
*y* A Foi PuoI ( % o. y p,*"hc) $
V6^ A FO poi t 'r3 rans k tzc UA f on ( ST@n A04 "grzaiL OC.)
Reference:
PVNGS Techn1 cal Specif2 cations, 3.7.1.2 and 3.8.1.1 14
pt,NT sysEOR.1NFORMATION'ONLY AUXILIARY FEEDWATER SYSTEM TO LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
. . a. Two feedwater pumps, each capable of being powered from separate 9 OPERABLE emergency busses, and
- b. One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:' MODES 1, 2, 3, and 4". . ACTION:
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
- b. With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. ~
,[ c. With three auxiliary feedwater pumps inoperable, immediately initiate
,( corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REOUIREMENTS 4.7.1.2 E.ach auxiliary. feedwater* pump shall be demonstrated OPERABLE: a.' At least once per 31 days on a STAGGERED TEST BASIS by:
- 1. Testing the turbine-driven pump and both motor-driven pumps pursuant to Specification 4.0.5. The provisions of Specifica-
- tion 4.0.4 are'not applicable for the turbine-driven pump for entry into MODE 3.
- 2. Verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, i.< in its correct position.
- 3. Verifying that all manual valves in the suction lines from the primary AFW supply tank (condensate storage tank CTE-T01) to ,
each essential AFW pump, and the manual discharge line valve of
- each AFW pump are locked, sealed or otherwise secured in the '
open position. T "Until the steam generators are no longer required for heat removal. PALO VERDE - UNIT 1 3/4 7-4 p a n e m so- a m a a a e s a n, e m e, . . w i ' ' '
~
FOR INFORMATION'ONLY
. . " PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) s
- b. At least once per 18 months during shutdown by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.
- 2. Verifying that each pump that starts automatically upon receipt -
, of an auxiliary feedwater actuation test signal will start
; automatically upon receipt of an auxiliary feedwater actuatio,n test signal.
- c. Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, by verifying on a STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 750 gpm at 1270 psia or eqpivalent.
- d. Th'e provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.
cc ( l l 'w .k ~ , PALO VERDE - UNIT 1 3/4 7-5 l Pa rs s k Icp% D A A A tit %I #'%Il V' '
3/4.8 EL 3/4.8.1 A.C. SOURCES OPERATING *-- LIMITING CONDITION FOR OPERATION '
- 3. 8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. Two physically independent circuits from the offsite transmission network to the switchyard and two physically independent circuits from the switchyard to the onsite Class 1E distribution system, and
- b. Two separate and independent diesel g,enerators, each with:
1. Separate day fuel tank with a minimum level of 2.75 feet
; (550 gallons of fuel), and .
. . . , _ 2. A separate fuel storage system with a minimum level of 80%
(71,500 gallons of fuel), and
- 3. A separate fuel transfer pump.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
, a. With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.la. and 4.8.1.1.2a.4 within 1 hour and at
'( .. _. least once per 8 hours thereafter; restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD 5,HUTDOWN within the following 30 hours.
- b. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance
_ , _ , laquicaments 4.8.1.1.la. and 4.8.-1:1.2a.4. within 1 hour and at least once per 8 hours thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hcurs from the time of initial loss or be in at least NOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- c. With one diesel generator inoperable in addition to ACTION a. or b.
above, verify that:
- 1. All required systems, subsystems, trains, components, and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are also OPERABLE, and
- 2. When i,n MODE 1, 2, 3, or 4*, the steam-driven auxiliary feed pump is OPERABLE.
~ ~~
If these conditions are not satisfied within 2 hours, be in at least ,( HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
"Until the steam generator is no longer required for heat removal.
PALO VERDE - UNIT 1 3/4 8-1 y= A rt s h i r' A M A A A T B A R O A h 00 GD -
r ELECTRICpLQfij$SEMSFORMATIONONLY
.o LIMITING CONDITION FOR OPERATION (Continued) . ..
ACTION (Continued)
- d. With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2a.4. within 1 hour and at least once per 8 hours thereafter, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours. With only one offsite source restored, restore at
' least two offsite circuits to.0PERABLE sta,'tus within 72 hours from time of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- e. With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.la. within 1 hour and at least once per 8 hours thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours or be in at least HOT STANDBY within the next 6 hours and,in COLD SHUTDOWN within the following 30 hours. Restore at least two diesel generators to OPERABLE status within 72 hours from time of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REOUIREMENTS
- 4. 8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:
- a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availablity, and b._ Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually) unit power supply from the normal circuit to the alternate circuit.
4.8.1.1.2 Each diesel generator shall be demonstrated OPERAELE:
- a. In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by: .
- 1. Verifying the fuel level in the day tank, .
- 2. Verifying the fuel level in the fuel storage tank,
, ( - '- 3. , Verify'ing the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, PALO VERDE - UNIT 1 3/4 8-2 ena m n n n c,o m o o m nno.
^
FOR'INEORMKBON ONIN . ' ELECTRICAL POWER SYSTEMS ; SURVEILLANCE REQUIREMENTS (Continued) C s . c) A flash point' equal to or greater than 125*F, and d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176-82.
- 2. By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975-81 are met when tested in accordance with ASTM D975-81 except that the analysis for sulfur may be performed in accordance with ASTM .
D1552-79 or ASTM D2622-82.
- d. At least once every 31 days by obtaining a sample of fuel oil from tne storage tanks in accordance with ASTM D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM D2276-78, Method A. -
e e 9 e L -
t 1 - .o d U. 5. nUCLEAn A r.G U L A TC R Y C OM P.15 51 dN RE ACICo LPthAlck LICP4SE 2XAdl.4Arish PAL;LIlf: _fdLU_1EE2t_2____________ c1 ACla d TY/t: _daE-Cadk________________ b e.T t A Dh 1 NI S T E R 50 : _E2LR3Ld2________________ L Aari' :- : _SIcLiEcz_Ga_____________ A F r L io' u.T: _________________________ 16 : 1t h.14)2 a _1 L_ cit.1.e Lil cst ;.gsr tt p.per r r .. r .n.vtrs. .rits an>>.rs cn one sice only, attric su. tion sneet us two or tn e ans.ar sheetse Pcints for each que.tico 11 e arcicatec is 5 . r t r t r. u 5> after the qut> tion. The passing ar ios r o us s r .s 60 least .., e r, : 3 cn category ano a f e r.a l grace of at l e i.t cv .. :n.ninacev.i . .e : r s nill Oc picked 'u p six (c) hours after int 4 m ai.i in e L a o f. s tor ca. . 2 Gi .AltbLsY 4 Gr AFPtitatil'. .slSGL3Y __kasks _laleL ___a..s2... _ kills _ ______________CaltGbil_____________ _s2aks _ _c2 sad ___________ ________ 1. Ps'I JC IPLL s GF hUCLEAR P0hER PLANT O P t K A T I L t. , TH EF MLOYh AhlC Ss HEAT InAN5Fik AND FLUID FLCh _s24kU__ _dio22 ___________ ________ d. PLANT CE543.5 INCLLDING SAftTY ANC s .*. 6 F G t N C f 5YSTEMS _22aLU__ .22s2a ___________ ________ 3. Itt 3 Te t r,e b i d A N ti CGNTWCL5 _Z2akw__ _22s92 ___________ ________ 4. PAJC_sLndL - NuRMAL, AbNCkPALs EMEEGeNCY AND RAvICLCGICAL C O N T d. L L AQuaky__ idda9Q ___________ _ _ _ _ _ _ _ _ T'JT A L S hhat 65 . ________________ C All *crh J Lt. a bn (nis ds. . . l c r. 15 *. y 3>n. I nove neither g i ve n s.cr rscaosc u;. APPticAhl'S SluNATURE
It__dh1BCiELdS_DE_duCLEAE_20htd_fL131_DEtlaIludz PAGe 2 IdcSdLdib&t1 cst _HdAI_lEAbStis_abH_ELuit_tLug QUthfiCN 1.01 (3.vt) H C's coJac tne actall critical roo position vary f r uia the estinatEo criticos ra; positson (tcP) for LACH of the following situations, inclwae a s4;EF (4psinatico nHY.
- d. AftLr a tr iW I r 'J at A L L '. voksrs an EC# is calculated using ZerG A.r.cn rc ctivity rcr s startur 6 5ours after tne trip.
(1.0) c . 'I r i a:Cual coran ccr cc,Lratica is 100 Jom lower (nan the value ossa rst t r. : tid. (1 0) c.v t rev 6A ds ao en t ri: '. P er.htsac of the a c t*a a l 200 dF PG. (1.0)
~
Qb tal tGN i.J2 (I. o.) a.o ns is Lae i n oi c s t i c.. or neutrars ( 5 0.9 ) important auring Lclo inutccan (aoJ.S aco)? (1.0) D. state fcur p a a .1 o t t awarces or reutrons in the core during L o l a a r. u t d o, n . (1.0) utthiluN 1.03 (3.ic) ce A l t hou gt tne J23d rescnance capture peaks cro.oen and flatten with increased tact t emper a tur e, tne area oncer tne peak remains tne same. kny th e n is there an increase in neutron capture as tne fuel temper atur e is i nc r ea se c ? (1.0)
- t. L0=5 the fuel t empe r a tu r e coef ficien t ( P C r. / F ) Decome MOPE CR O P. LESS NEGATIVE as fuel tenpe r a tur e is increased? (0 5)
- c. HL4 AND kHY co e s tr.t mo ct r a tor temperature coefficient (MTC) cna na e ( mor e or less ncsativel as temperature as increased at e L u'c l A N T aa u .tlN ts.s ciTRATIGNs in an ondermocerateo core? (1 0)
- c. Hun a.s u .nr 00:3 te. 'i t cnan;e as t or on concentration is incrtasec at a Gui. s . I T:r, Pts 4Towe, in en unoerroceratec core? (1.01 tAuka.Juh_3NETLR_f2Afd O O O O O f1
it. EhldCIELi1_QE_hdCLEaE_EGhth_fLASI_LEEdall3hz PAGE 3 IdsstG21UatlCit_dEAI Itab1Eid_ah2_EltIQ.ELGW c c t a i t v4 1.04 (1.50) en at er e tnret purposas t cr esintaining Roc insertson wirits? (1.5) G b t a l . '.'s 6 .v3 (J.vv)
- 2. we. a los. secrJa.; i rca 107, t o 3" ?. w i t t. rou con rof in manual
. r. ; to or.r:tcr ;; u . s . t , 12vt oecreases ano *isi cacse nucl e ar p;-cr ic e r a r s a i *. . .: et wi ll ca us e nucle ar ecrer to stop e r. .r . : i t. a s ri : 12,..i ;re e. i olansr posar? (1.5)
- o. +,r. 3 sw etrst roJ 2ree nii s l e at paw ars &ith rc: con tr ol in ranual aa, no ostrator a;tive, n u : l e ir power nill ramoin apprcxtrately L cns s.a t t v:si di t-1 er er..ertec L:A.
. wny will ncclear power rsm.in at t ri o- insta.1 fewar l av tl 1 (~1.5) w b t b l i s.1 1.Jc ( 4.i O )
icr saca c r 1r : roi log s fy c er gi t io ns, enich of t r. e two choices ac ui t t r.c 1.,i t V t J s A L (t itTurEntist or e ri tt J r a l as i n[i C a t e o ) rod acr:1. Du ar e eter ! 400 a o r t r. ouriteta.n Onoice 1 c r.o i c e 2
- 4. Inte,ral fas. 150-F 500-F (0.5)
- c. Ante Jr al ocr e late COL EOL. (0.5)
- c. t i r rcr en t ia l <cv <csiticn 40 incnes 130 inches (0.5)
- d. Differertial doe i n Gr ocp '; an inserted tne roc (0.5) ans:r is next rod witncrawn c . a vatle wi th m . s ?-
la_.BalusieLES_DE_duCLEAE_E0 HEE _ELASI_]EEEaII0tt PAGE 4 l bis cJu rbaBILit_ dE AI_lS ab 5 E E d _a Ea_ ELu lu _ EL L u l l l i Cu cL T ic:4 1.Ci (1.00) u r. i c n o ne et tne s t at sm an ts celcn would incicate tna t Natural Circulation n as seen amt stli sna c in t r.e oC5?
- 6. usite o eak er atar e scrca. tt:( ca re is increasing anc gr eater ttan iLil lanc ce l t a t a .e j. d r a t u r e .
- a. ccre outset t emp er 2 tus : is increason; and c reater than PCS satur tscr t s a.p e r a t u r . .
c . 3 te s .:. s e.it r a t or le.tl e, n r. c r u s i n j alth constant auxiliary TEconoter fica. c . a t . . aa generatur erts:.r2 is cic r e a si n; ano is ris a r, s a t u r a t i o n p r es sur e fcr toe (Lb i sn.p t r a t ur e . (1.0) C u t S I 16.4 A.Le (2.sU)
- a. esrine cavetstion (ex..icer p ex. p t only)? (1.0)
- c. = sis t tour inoic4ticn Leneses or outsice tric control roon) coula oe cacc ta . s t . r .1.i n e it a pJap is experiencing some u Sr .t or cavitaticnt (1.0)
GL E L i iui4 A-U9 (4.0L) . D esc r is e 40. ano edY ccntrarussi oLnp a i scn ar ge flow is offected (increases decr.3se or no chan;e) for ti.e following?
- b. suction pr es s ure increase (0 5)
D. suction pressure decrease (0.5)
- c. Inro tt l i ng conn tnc si cner;c valve. (0.5)
- o. An i nct e.s e i n p u a, ., .c. (0.5) fM WCTrif Pa(M *****)
e li_.Et4GL1 ELE 1_DE_ddLLLAE_EQhEd_fLAUI_QEEdal1Qut PAGE 5 IdidtuQ1 bat 1CSA_ddAI_IEabStLt_ibd_ELulu_ELCm Q L t.L T i SN 1.10 (1.00) L cruens ate aerreaston cc u la c e con si c er e to ce an AGVANTAGE for tcr conaunsate pona p .: r u t e c r. c u t 3 Did A0V A NT t.bE f or pl art therral ettscicacy. t A r c - A 's . (1.0) GL t d l !Q l.14 ( . . '. 8. ) iru. or < al se ?
- a. Irs .irrerontaal :. . c u r a t o r .: recessary to transfer heat is ir.. r r.I 3 pr cp3r to cr .6 tc tie a t tIuc. (0.5)
- c. r'wmo r ar. a o t la cne , *r, us ec to u scrite a centrifuw al p urr p
.. ri- a at i :. ,, o a p i o , c a n c. :. t c sn ut c i s cria r ; e valve. (t.5)
- c. i ne s a c e. n t ri c a t or v epor i ac t ion is anotner t e r ra for the latent n e st af c o nc es. . t i c o. (0.5)
- c. ons er une s u n.a imot T Gr cen tri t o].I putrs states that power recosicc by tna p -a n , r. v t S t is aire:tly p ro p or t a onal to the s c.c o r : cf int p a .s. '> ci:.a. (0.5) eu c h l itN .1. (1.i.)
ocuac u v on n av e ta supply mcre en er gy to procuce water at
> <> 4 e ur s teen at ios f? Explain. (Assume oressure of r eactcr ccol nt as 2235 psi a) (1.0)
QLtsfACN 1.A3 (i.Ct ) a t ats t ne noce of o r e s c i< i n a n t heat transfer fcr the following
. to.tecns
- a. c nter of tast geli. ..t to the pellet ed;e. (0.5)
- c. wiec .erface ta e. . < , oncur fsin ceilinJ ccnostions. (C.5) non i
Zi__BLamI_QE11Lb_idCLULibE_A&Eill_1NC_EdEdGEBC1_1131t51 PAGt 6 GLL5IldN 2 01 (1.00) ve2creue tna sy a te n Jsst.n ftetLre tn at en s ur e s the M5IV's can ce c ics ec f u l l o r sio a taas c r o f f-s it e pcWer and . sotsequent loss of i n s t r o.c t 1 L e r. c S c r v i c e sit s y s t e n.1 (1.0) ; ou t a l i .h . 02 (3..sJ
- a. 6 :sc ri t s t r.a r a s i t e c t i n ., er tne i t e 3.. ,enerator feeJuster e ,a lo t i n , 5olve ;v t< a c nnc cm c r Jurin; a powcr level increase i r o.t e.r tc 100. p),.t. ts r a asa tne r(asoning for each pnase of t r.i s <cive A r c , r ::. . (1.5)
- u. r c i l s ,, i n y a r e s: t)r ir e r I r o m 100 ?. oowers cescrice now tne feed pcaps onc~tetu r ,ul. tar., ve l ve s f unc ti on tc contrcl steam utnerotor voter I .(l? t u s s cree all s y s t e.m s are in automatic). (1.5)
Obetil;a 2.u3 t...cl C cncern er 3 t i. e e .te r ; e n e s cassel avstem:
- a. niiot incic.tions ; css t r, e eperator in the control room nave to incicute trat ta (n.r s tnc3 ciesel nas f ail eo te start on an e toracic s e *a n d i t (1.G) o . = r. i t aill cause tne s ... c r s e n c y cies=l to automatically start? (1 5) c . do. man y ruel oni stora,0 tanks ar : t h e r e s r.o enot is tneir c dacity b es e o o n! (txcluce tne day t ank ) (1.0)
QUtbiloh 2.04 (3.00)
- c. . nil e opergtin; st 3 .* ;. r o t.t r tr e outl et crain val ve for feeonater n eat er 6A fails clos-;. Give To r 2e centrol room indications at Inis esent. (1 5)
D. Assu'enJ n tre nast;r i t. (Enn rump *ailss H u 'n and WHY will the
.s uno f . c a v e t s r a m .. . . r, - c or i n ,
..i. event? (1.3)
I- Ro++os _.>1 .w 6 m MreaTr sa@A
. *****3
En__ELaSI_RE11EB_INCLUD1bG_laEEII_aba_E5Einijd1_alh1L51 PAGE 7 WU t 51 1Gtt 2.G5 (2.00)
- a. utrin, a $1 Abs Enrottlin; of t9e HPSI flo. con tr o l valves i s r esu a r e c to decr ees t pr essur e. Explain non tne HPSI flow control valves are intuttlec (valvc control oper a ti o n) from the c oret r c i r c L.c . (1.0) o . n r.a t ar e tre tene r c c o s t . .nsnts for initi at e ns simul taneous nct seu cclu lea i r s c t : o r. ! (T ,o r e q u i r e.1 ) (1.0)
Gu t h f isis i.vo (2.tv) b t, a t au tw ni o t i c r unc t s cri; ar c actuated by tne folicnin w upon e x ce t ai n, tnt er regn a c t p o i r. t ?
- a. 4 L u9 ( C en tr o l rvob sirtilatico nonitor)
- o. rc-37 trcutt occcas euts e aree F.onitor) c .
- L-141 ( w c rio e ns a r w o c u n. ptap nooitor)
- c. e,L-16s LFwel c a s i J 8 .~., v c n t i l a t i o n e x n a u s t monitor) (2.0) wut$11sl 4.Ci ( 2 . *, c )
utrang a coo l oown t o ce l J s n u t c o wn witn tne DLS 6t 260 F ano 350 p si o.
- a. nisat cooling loacs accid nor mal l y oe on tns Essential Cocling nater system under trLse cond it ion s ? (1.0)
- b. F. x p l a i n h o w t he Es.ential Cco li ng water system woulo r espond Ic a loss of offsite foner unce r tnes e conc i tions. (1.0) 4 Ji d l i).4 2.so (s.. 1
- a. ,nat iarce sisten., , uesn tr cv s uc fcr ccmcustiole gas contrcl i n c c.) L r.r. .: n t ? (1.ai
- o. t c l i J.i n. 6 w as t a l 2. . mutAs nvcrojen gas m ay accumulate niinin toe contain -
.. a r es ul t of an at 3 processes? (1.b)
.00000n
Z e._ _2 L eb l_2 E11Gu _ IN C Ld Q1f.f h _l e E LIl_a t:2_E5sEGEB;I_1151sti PAGE 8
%U t h T a uis ..G4 ( 3 . t. G i Trw seecI3t ec)tlatiaw I i s t s a. i s p l a c e :' in TEs1 at 307, power.
A s s t. ra t n3 cytritor b a t a c r. . nrtt is t r. c e'f9ct on the followinG8
- e. Pre .urster Isvel ccntrus s y s te s' . (1.5) o.
itto. L , r u . .:, c 3:n Li c I O t u rr . (1 5)
" t h a l' 4 W 2 . i t. ( 2. a J Our iI , r o r :n . I 100'. ( O n :. t i 3 ; s c ; i ch , e i or je vacaun 3rtaktr valve 15 ' l r. a d v e r 1 :. r. E l y 00cnso.
- a. n c , ,,9 u s e tec ,s a x e t i . r .- r - e cw i.t t r s y s t:., respenc to this
= ven t? (1 0 )
- u. 1 ti.s s e. v a s t a corrt., 1 : a. i. un c o u s l y ith a S/d tube r utur , rich ressec, ts tr t poclic rasith enc safety, WHAT rs 3 or cciscerns ont ,. 6 f t (1.5) 1
'- N W f
PAGE 9
'Aa__ibSItudEhll_ add _GublEDL3 WL t i f iu, 3.Cl (4.30)
I wc planc pr otse to an s3s tem tr spSe High Lccal I' o n e r Censity and Low w at s, are gener atec if tn: Lcr e protect ion Calculators.
- c. neat i. the p urp ose ct socr of theae trips? (1.5)
- c. Last v inputs ta r. g. e ccre prctaction calcul. tor anich are uscc sa , e r.c r o c a t e.t a r trets. (1.8)
- c. rat ccntrci a c t i J f. (cFeb pldCS ch9n thf pre-trip setpcint5 cre r:4cnet? (1.0)
Cuth)Awa 3.02 (d.1U)
~
1 r. e plant 4. at 4)' -e-.r en ;ttoay state conc i ticns, except a xe rson veastootica, resultini I r3 m a previous penar transient, 45 I I. p r J 6 r e 5 5. a.Al t a.: wLSa 12 sacreracle, w r,a t inaications woule alert the cherstor tc tne p r e t e r. c s of t r.e xenon oscill3tsen? (0.75)
- c. nl at in3 acy nt s ,e s ,culc tric C CL 5 5 prov id a if it nas o p = r s t i n .,1 (1.0) c . w h at _c t i e r.s shoulo t- tanso if ASI varies by nore than v.J> . nits f r can L3.? (0.75)
Qvtbl1GN 3.v3 (A.;0) Gescrine what nappens er tne Feeuweter Control System upcn r e ce i vi n, . reactor trippec over ri o2 (RTU) si;nal. incluae any a coi t to nal control s i ., r a l s t t' e system r ei::e i v e s . (1 5 @
- n .
yyu
1s._lbilauSEhlS abo _CQUIBDL1 PAGE 10 Outaf.u.< 3.0* (3.20) 9619 Verce u r. s t 1 is op5.ratina at EC per cen t poner anen c E dr iny oil Fressure is itst on feedd3ter pump turoine A. On the httd panal t r. c ALIJ 3LL .I l e ,r.t is illurinatec, cut the AUTO ALI1bAlt.svi LF 5d4vit. 14.nt is NLT illuminatec. Jescribe what control ,yaten actsvatise ei ll occ ur . Assume nc operator action ant - r ac.o r cce2 not tri t. tvisroesro effsets to tne Steam Generator attea l eve a ccntral) (3.2) Get>T2ui 3.s a t2. LJ 1sscr:0c own tot J .) ; s , . t . it ac:cun ts rer r a ci a l, axial anc n cn.yre :tr s c a l power . . t r e t ut i on effects of CEA position on line cr esc e . censity. (3.0) LOta A u'8 3 60 - ( J . s i. ) LuriO4 a r *. a c L J r 5 C dr ius , v s r 41 Ca t i o n of proets overlap ostn-en startup ona ... :ctut3 t'cc l e a r Instrumentation Channels is rs,aint. rsscr to ..ittin, the ni;n volta]e to tne control CnsdHtle
- 1. u ver . 6, u t i . r'. r. ,r s o c ri instronent shoule tne overlap occur? (1.0)
- c. c os - is te c c i is < l'...
. sni f ted ? (1.0)
- 3. tisa 1 cne c ri ana : t tssianeu to .rininize tnis proclam if the ai,n voltewe is inaevertently n et snitte ? (1.0)
L u c s T A v.4 4.07 (2.ub) a s s u it e stont cecrstiaru at o c t, po=cr dith CE0 mci in the AS scdc. u c 3p la ic i t. a t t u.v a n t t ita open a na Tave is selected to average. Lsacres, cna errecc; 0' s. contraI ano Pressurizar level. Assume ro aisratus sctica. (2.0) n***** CA R u-T MM NGNTR'4M@N G 74 TAT PAGE *****)
i 2a__AS3IeundaI5_AND_C0dIELL5 PAGE 11 but3 flu 4 3.de (4.id) C cr.c e r n i n ; tre C or a Pro t ectico cal cul atcrs (CPC's): as . c e n tae t et 's or otect t r. e e l ;nt from exceeding Ott o R if the Ftr ater ucca .4 J i .. .s e r. t u i r. tne C'49* l imi t? Explain your o r. 3 a c r . (1.5) D. t ne or t il e s r. .a a t a sc : . src caIciastors is nettron power. nnat in ct c a r r cc t e a.i . oce2 t r. i s p .. e r signal uncargo? (1 5) c.t at .r: I H- t c a r i. _un ;uxi l i a r y trips gener atec ty t he C PC. (1.5) West 1 4 -J.v9 t....) ar ; carec i t s cra -s i l wamuc in: a pr es Caemic al Aasitson pump to t r ip .sa t:14 t s ca l l y ? (t.. r . ,L a r e s) . (1.0)
.. t 3 6 ' ? + _ *. % .id C A T C G O R Y _ 0 3 *****)
3 PAGE 12 ic__EssucuudES_:_dQa5AL2_adduEtekt_EdEd3EUC1_AbL saklukQG1 CAL _CQSIdGL Go t S T iai4 4.v1 ( i . -) c ) 1
- c. .i es .I kAOS of signos beta sn d Jame.a were in,cated by 3watscaings wnicn ocul; cause t he he; hest uose? txPLAIN. (1 0)
D. w nico a t tre aua sa evols fresent th? .ir e a t e s t iXTh%NAL r .Ji at i o n case? c A r u - , '. . (You are r e o ri re; pracective e e v t ni a 4 cr; safet) .le_ac3 orly). (1.0) wu t i l iu.4 4.02 (i.?C)
.ir.uicate o h s t iie r 34cn et t t. : fclicw199 stcTs outs ur ODES 60T h w ed 2n assc(sateJ iaus.ricci 3reci f i cat i or s limit. (Nc explanation rtccare;).
- 4. rs t a c t a r a. c mulatin; ds.tcr
- c. I Lr a in:: utne r at a r ov e r ageec Tr i p S y s te, c . a ts aia Generator jarets valves
- o. n ain recJ P a ro p
- e. rars de sec ticn a y e t i. 4 (2.5)
's u c a l l uri 4.03 L3.Lu)
- e. L ur e n; 3 bb tua! r.wr t u r is why must tne not le, temperature o s i es s than 371 F pl s or to iso latin; tne ofrecta1 S a? (0.5)
L. ay what a.e tn c os is tre AL5 cool eo dJwr fJllCHing a SG cuoe ruptura if t .1 e .'. 5 1 V fcr tn e afrecteo SG tseis to at.ut? (Assume Delow $3 t- ) (1.0)
- c. uuren, a SG tuoa ruptures ncw s hou l d tne affected SG water l e ve l oe controlleas if tne affecte1 SG is isolateo, the nicoccon system is uravailable, and tne followin, indications ere prusents (1.5)
FZh gr ess ur . = 1300 psia nud net ,
. .,_rature = 545 F Artecteo Lo .. . .u r c = 9 00 psia
--- .. - o0000n
is _.E h 0C tku dis _:_ hQd ba kt_ a h 6 L t de k t_ E dElG E UC1_a b u PAGE 13 heuisLOGICAL_C03IdQL L L e , r 2 &i *.v4 tu.ic) in tne Poeificatioa 3 t. r arc:tcure, "Placin; a puritication a on t acion ,c r- in : 2r<ic+", there is a s e n te nc e enat states:
"Instroet t r. c n. ci t n S, r_tcr Lc Opea 2 turns the son exchanser cotect vsivt." nos fi v v e .: tre ntclear av er o tor cper tne cLtl&L vo l v L3 i. a . i se ;esn e0:ti0n? (2.1)
L Ut sl a s.1 4.vb ( c . '- s 1 AGCuiuin, tc tot v. 467_-rJ, ci st si COS linJnos t ic Procedur e (%let-12 UA), .+ t e a t rv,t i.. 'sel tr . TCll.7 pen; OpcfatorS maK6 L c *.r,e Lvit i r c i r. ;J a ase statacr LC#h)?
- 2. s r s a cr f t, s r a tor ( r . .. r . . e, w a r .. : ) (i.2)
Le L (CGf air y L - C- r J: Jr 6: * .s rt iLirt;) (1.2) 6b t JI s uf. 4.ws (c... #
'a. a l. s t , ar e r. y , 4: t i o '. . f.:a tc at taste if tne reactor coolant
+ u 1 ,. .uai- e.. a s c i s s e .s.tse is I 7st e r 1 c an e. c t ce restoreo? (1.0) oe c a ,21 i s t' t ii t 4 0. ; t i i . s C O ., L t. r n eff Ctf of d loss Cf thC wcator. t , c t. s ce41 in s: .icn sjstem. (1.0)
QutSIAuN 4.v7 6e.s.) vLring a s tat iso ol .;n c u ts (per 41Fu-12209) *sthoci re Jarcs to r e s t c r i ri, el uctr a:a l ro,er, waat acticns shocia Le taken to stabilize tre osaa p l en t? (3.0) 4ctalam4 4.we te.
.r. r.tersnc. to tra . ar'.s crececure (410P-1ZZ03) it tr. .se.. e r. v ; .r. ..;' rcacaer-
, the tCPs onat actico sccais t.. t .p tr o tar ; (3.0) m -
ha__dduthcuhdS_:_DD&5&Lt_AdhDEdsLt_L3EdGiUCI_ab6 PAGE 14 saQiLLuGICAL_CDNIROL ot t 31 1;.4 4.09 te.vo) ary uo .6 not aant to rseLce sc5 pressure below c t.e pressure in t r. c rup tur es s te en ,encr;ter cu r in g a steam gener ator tube r L p t o r e 't (2.0) QO t:1 Ava 4.ic ( 3. L L ) A - . o r t . s e r. n t ser n a s t s t i r. n ., a . n il C2AS i s r e:eivea. An e v al u.t ico c r c l oa t ; u r . i t e s n. c us t L2 rac3 tc cetermine if the t s aa ac tu a t ic n e ss i n s e s . r c r. t or is a valid ac tuation. In accordonwe asin Fr J ce Jut : *let-luZ30s now is tnas cone? f3.0) O
(cocco0Co***00 LNU UF EXAMINATION *0000**0*000*o0) la__dticlC1ELt1_GE_ddLLiad_EChEi_fLah1_QdiEall2bt PAGE 15 Idit h lbatiCit_ dial _IdaiiSEEd_ add _ELula_ELdh Ab se tas -- P A LG VER 02 2 -85/04/25-STkdIEW, G. ANS's:n 1.01 (J.;w) 6 A ctu al c r i ti c al pa z i t s cri all o c ni Jner dua to Xenon peak after t r. c tr i c. (1.0)
- o. ctu;.I c r i te w al pa si t iun will at lawer ..ito less coron in the cs t t; u s c r.t r o s .c o . sai n -: e u tc De inserte.d to co.npensate for i ns terut icectsviti si tne usren. (1 0)
- u. . .. t a .. . cr s tic al c.i ien asil >. hi.; Par Ne to less excess rsucsi<1L3 r s ir s i n i n ., i, t i . .: cor c at 200 E r- P u . (1.0) 6 LF t wie s .
P.sv Jer.e .u c i v o r I r. : c . . .
.. d s :. r 1.uz -
( i: . . . ) t r.o r e is no instrument inaication.
~
- a. ( itrioat a c.n c n a wsi ve.
.:nct i n s ; r o .. : i '. :.casaticr., you oc not nnow core reactivity a ta: a ., os erctaar t .' . L'.stus is c h 3 r. ; i n 3 . ) Sc neotrons are n u a : .* tc essure ti... er c r e act iv i ty sta tus of the reactor is n r.w, n ine tne 1 s;r w 4 '. r. t e t s o n i n c, i c a t i J n is avella01e to
,was e. m ; '. r e t [ r s :., <. s e r. . (1 0)
- u. L. s i.c o t a n t a u s r e . i -:, n e r f u e l
- 4. u. c L . r s t ar : 9 acurces J. 's a., t o i r. e r =Jarce
,. Pouct neutran scorces (1.0)
- 5. Aipha- bron ca.. ken
(. , A.lgw. e84 %dron e t r c - ci16: F clo Verce 'J u es t i o n o c c h i
It__EsluCIELE1_UE 32CLf aS_EC'aES_f kaGI_DEEEaIl]3t PAGE 16 lechrudIhacisSt_dkal_IEadStiE_abd_ELt12_ELas AAdots) -- PALO VcR DE 2 -8 5 /09 /2 >-5T kt le R, G. A s. S at e. l.J3 (J.20)
- 4. Tr2 neuttcr. .ees a :,nericant increase in assorption cross s c s s .,n a v or a a utr ran.c cf anergies (decreasa in the fcel asif . cat a c i r. , ) . (1.0)
- c. ... i.c..tive
. ismore .; ). (C.5)
- c. J i ', : 2LtT.es wor = n...Li.t LQ.;} t?cius; tne censity cnan;e per r as ,r a s t er oc ..a....s s es e c r at or c a [0.ij. (1/2 Oredit wiven t or a..ca231:n at ts: _raien/reecvit of i anc moc. .s temp. inc.) (1.0)
J. Plc t e c c .: ss less nr... sv. (cecr*ases) LU.5J cecause tne nunter u r c or e r. a to rs ( pe l . .r ) a r. c r. e core u acr ea ses mcr e per P c n in ,; ht 1.igner ocrc1 c e r. c e n t r a t i m s . [0.2] (Also accert r '. s e v a t uescusis;t (r trsrmal utaliza: son) (1.0) kLrtst.ivt . Pitc vur;e titary 4 ic A( a ut . 1.C4 (4.;;)
- 1. t o. .. e inut oce:ptacis rower oistrication finats e ra mainteinec.
- c. ens a. u t re a t L 1 a m a n e.v. u m 3cr is maintainec.
- 4. t a r. i t tne pctantial effects ct ra: c a s a l i ,naient un tne Esscciatec
, .cc Jen t .n a l y s es. (roc ea sc ti on ) [u.3 eact] (1.5) I i
.4 t P t h c.4 4 3 Peso Verau'T.d. 83/4.1.3 i
Ah d ad e 1.05 (J..e)
- s. -s au-tr i ncr e ss t. '
. .' f. : perature inctcasts LC.75J tisis a 16 3c c ne,a ti y e r i v i ty to turn rower via doppler [0.75]. (1.b) i r
- c. lae pseoc w i .. .11' ri r. e , & t o w : reactiwits aut positive r t ac ts . s t y aill a- . ac az e cf tne Ic aer rue i t c.r t e r a tu r e tvsp;iar) tv. /a; ., n .r rsu retar cmper ature (MTC) [C.753. (1.5)
La _ _E hluLIE Lt3_QE_du CL t as_EQh E d_ f La bl_C EEdillG u t PAGE 17 IdisdQulh&BICSA_dEAI_IEAULLEs_abk_ELu12_EL0d Ah5ats$ -- PALO VERCc 2 -85/07/23-$1 f.clERs G. ALFtrittuc C-E he 4cto r Ineory p;s. 170,174 L 211 Ah. hts 1.co (2.J0)
- a. (0.5)
- o. e (0.5) c 1 (0.5)
- o. 2 (0.5) 4 AtFEFLaCt -
Cc ecacier l hec r y p,s. 161-193 AH5a:- t.07 (i.Cv)
- d. (1 0) ketchcaC Generel eny tcs,Hast Tr :nsf er anc Fluid eles p95. 355-356 Ad5'tk c 1 00 (2.J0)
- 4. Ine form 3 tion of DuoDits (steau) in the eye of the imptlitr or a pump oue to oper ati on with insufficient sucticn pressure.
L O.2 5] . The odoblas collapse alon; the impclier vanes. [0.753 (1 0) be v t or ati on, noise, lover or f l uc tu a t i n g e .np e r a g e / f l o w / d i sch ar g e pr es sor e. (1.0) ktFcocNud G ene r al enysics Heat Ir.o.fer anc Fluid Flow p;s. 310-320
la. _f si3 J1E L E1_U E_du f tr.a E_EDh EE_ f La SI_ J EtlaI1064 PAGE 18 lbit dJu r b atICSt_ di AI_IE Au5EE E _a ba_ ELult_ ell h A N b o t .- 5 -- PALJ VERud 2 -85/04/25-STAEIEd., G. A N 5 n t e. 1 09 (u.0v)
- a. ! 10- incr: ele; Ju. to rurf e c rx reieirenents cecrease (0.9)
- v. P u .t .- r l v. ...s11ats: r. . ce fd s h a/proen 35 Iero anc as tre J un e ..w (otca rav- .*ii ,C t. O 2 = r J . ".74 c a. wll. 47.% is n.4 ymd A (0.5) d uca.y i.t. .s 4. c re 2. .
O. t loc u. Asaca 2= 6 7, . . , , t _m t e si s tance increases. (0.5)
- d. Pl] s :a c t u .a : L a6es., ,4 u ' , FcSJ increiS$5j PJFP ldes. (0.5) e L t c . e e . '. .
b snc t si n ; s i ca ric 4 L Irsi ,ftr ens Elaid rio* ;,s. 32J-322
- 4:4 3 mi * ..Lu l i .1 )
a u v o l e l .. ..
- $ r' O r : 15=; '~;o tvr con da n i t t e p 'JT p (ceCreases Chance cf F .1d .aeeisL:G7) EG.5}.
v i s a ; v a . . '. 4e a te 4m u:. . .c refust concensate ccula ce usea for p r a a uc t i e r. of electricity (neat reaectec froni c ea s esi. . e is to t to tne cycle) LO.23. (1.0)
. t i t . ..
o c r.c r a i enysee, He 6 ir sns t er o ric FILia . luw g; 2>3 ANs<ts 1 11 (m.LJ)
- 4. r els e J. r eise
- c. T r ue /
- c. i als. CC.5 eacnj (3.0) s c h . c +. .
0.nr e l . i. , ; i c a neac ir .. cru Fiull Flo*
la__EhlbCIELE1_QE_ddCLEAE EQmEE_ELAUI_QEEEaIICGt PAGE 19 Ibik cu2Ibad1CS1_UE AI_ IR& dst Ee_a b2_E Lu i2_ EL a m Ah54td5 -- PALO VER0c 2 -db/09/25-$1REIcRs G. AN$e:E. 1.12 (1.00) Mcre an er 3 y i s reau arc; te p r oc uce steam at 564 F. Both require tnc 5 ani s t in o u n t of sensici: r.c o t to raise tte aubcoalec water Lc saturatico cemaerature, cut tne latent aeat of vaporizaticn must we ausc to so e l it. (1 0) dtrt uNw: P hia tera. ..ucsti29 aann A h 5 s:t. m A.13 (A. s '. ) a . (. u n J u o L i o n
- o. r oca eti on LO.b eacnj (1.0) d e t t e c..u utneral ee n y t i cs Heat ir 1 r er anc Flusa Fiod 6
Za. dLah1_QE11kJ 13CLuk1bG_laELIX_kUQ_idEtGE3 1_315Iid1 PAGt 20 A N 5 a in S -- PALO VERDE 2 -85/09/29-STrEIEF, G. Asi i n c r. 2.C1 Li.LCJ lov oir ruservesr, ar e i t c v s tec as a bacxue centrol air supply L C .* J f ar rcastionia; ;i. : s.s c r .u li c flaic control v61ves LG.3]. to ollJe /. c c u r u l a t J. r pr s:si t tc sct on the 931V L0.3] (1.0) (t/g ev.&*.4 4.< im u h ouis*. % A s ee.
- t b .)
s t r e v.in: Mien ate.n .)at+2 Jaa.i i y '. i c r. t s . 1$ Ah a ne r J.u2 (J...)
- a. Frca . /. tc 104 .nu n ,. r. . c r e r Fa;V ramps osan to preneat to; ts: ,ater in s i e. t r sc p r e v'a n t trertsi snock. trom 157 to 507 In3 us ncJi.or Fans it inot to incra ese the efficiency cf the -
ste3n cy le. F r ra c. n. - to 100. tr.e co ncamer F.RV ramps open to IC% tu cil.vlite tna htitcts er s te am c a r r y'a n c e r , anc enhancing tre rscir; latsoa r2t.o. (1.5)
- c. 6Tas r.ictwr tr i ppt c 5r r ice s i nal snuts the econcmizer
-<alvs), r2ro a tas r. . i r- f cecrate r pumps to cinicum speec,[0.753 ana
> va s tio ns tne treJabiti ra,ulating Velves to minimum or maximLK.
r esi tian c ep e na i n s er an- tac t Tave is less than or greater than na-losc la.a. (1.5) retc n .: A c 3 S y; t;- 9 Jez ription p;;. 23-24 E ss ;a at er . C on tr a l S y s t .. r. ca s cr i pti on p as. 2-3 ANSoc- 2.03 ( 3. sc ) e.4 ) i nc o.n p l ( t e saqaence alarm.
- 2) c ack of wG r u nn i r. , alstr.
s) L 3rd ct v0ittas cr steeo i r.a i c a t i o n . (1.0) ( w it Act. p* ats. - ut pior;.ty hw ater .')bbo SEM dae=)
- o. il S arc ty enJection .c tu aticn s ignal (SIAS).
JJ Ausillory resa s. tctuttian s i gn al (afAS). 3s Lisa o r v c I t a .;c . iis res6ective bus !LUP). (1.5) ( w;.t .4 c., ,+ .t s. - cS A 5 ') c) o va- on s tcr csa 's . eaiscaty i: r ueo on providing
. u r r a e a : ri t ater4,- . . e 5 :-e I tael cil for 7 Joys continuous speretion - (rlu. .. .r in tcr t e s t e r. . . ) (1.0)
Za ELeul_uE1153_ISCLug1LQ_aattII_eS0_itiiGEUC1_h1LIidi PAGE 21 AhJacR$ -- PALO VERDE i -6 5 /09 / 2 $-5T RElcF , G. n L F c r i r. '. c C a rs el i r s t i ti- cescripti:n A t4 S ec t 2.u4 ( 3.d ) a . 1. ri s . n itvaI .s l a r .T icr i t e. c n s.t e r 7esttr ua
- c. L r a a p e r. . I t v .; 4 e r, .% reLtcr orsin tann
- 3. s. ;uu s, e c t i c tror tas r s st ar cr ai n curp (1.5)
- o. ran : .: i a.ter .;r u s r , o r. I: I a ll as 1:s; r10 eil ce insertec a r te :.h e m e i n te.4-et: t t r a. o r. w h i c 7 c1usas a scwer inlet
; r es .us e to t .1 = .d r i irt I c ..t r ir1et eressure ni1i recuce outlet I t o r. s re'teran, toe ,tr .c :. p t : c u r ir r?spcnse ta a lower
- ., / i lavei to .ti s i n t s i r ./L i e vcl . ('1 5 )
slec-nh. Pale Ver.-; J c' t 4 C l o n . a rir Ab b ec a 2.0; (i . st i
- a. Inc v lvas ar e c a r v '. i i v.; L: seiccter, sverrict (0.2 9 ), tnis is aor.e ay se lec ts 1; "Jc. cren" po s i t i on an ] crnn the "Jca close" A us i il ole ( (.i . ,7 3 ) . (1.0)
C 3, L. i.c :,coner t n a n ,l' .l o o r ana no later tr'en I ricor 5 folio,ing a . ucca. (1.0) k t i c r.c N u Serety ina ec t eun s ys ter. c.es c r i p t io n p ;s . 39 r. 92
'.'l 4 0 121.o 7 g g 15 A rt h s:6k 2.06 (d.vC)
- n. Actu ate s the control e s c .7 essen ti a l tiltration nits [C.51.
L, . 4 sol te s - t f.e contae4 i. c t w i i o n n e, pur o. suppiy anc exhaust eucts (JPAAS). t o. . .
- c. A.LJicalio t i i tr a ;i t .c c er ', o r s3c. 07p/ 1and 3 seal e x t. a t s t .
L v . J J (Tkru- C M v m o s c
- t. . isalates t r. c n a r 't . . . ia.ico an 1 a c t s v .i t I n g the essentiel v en t a l .s t i e n s y s t .r .. .- ass L t . 's ] . (2.0)
r PAGE 22 E __etAUI_Qdi1LN_1bCLuQ1bG_1AthIl_Abd_idEEGEUC1_SihIEDS
~ mtw$ dins -- PALO VER02 2 -95/03/25 aTRELEF, G.
ktFEF:NC: Reciation .1 c n s t o r i a 3 s2atem cescri pt i on pgs. 3,*s7t4 Ahs>L F J.J7 (2.wv)
- a. A. 3.mtccsr coatan s r.c a t e x c n ans er
- 2. t a;en t s si ciin l i s r (l.C) o . e c.S 2 ma wili trig anc L e r est ir te1 witr tne E5F load st;uuncer. (1.0) keres:iit:
P alc verme questaun conn
~
A fi c a c h. 4.dt ( . . is ) a.A. H y s r u e n r e c a .no i r . r s y s t e n.
- 2. H yJr o Je re /cr g e sy; tem J. Lcnt a s tr co t 3 t30 p f ur e .ntn it or i qq system [C.5 each] (1.5)
L. 1. I sac cec cnpos e to ca ct viter Dy raosolysis.
- d. 4 met.1 w e t ar rsaticr D e t ne ee n the clac ano cociant.
- 3. C or r c 2 s (n cr ti. *ttais o i tn in tnc containment. [G.5 each) (1.5)
F t F c nc.4s: Lcntainn.unt N>arogen L vri t r o l sys te r Gesc r ip ti on pgs. 3-4 Ah h oc k 2.09 (3.vC)
- a. e LJJ nill raise level setpoint to (.nax program level) cue to tuli scale Tava. inpct from kk5, (tot tnere will oe no effect cn pressur izer l ev e l cecause to take RR$ to test you must oc in loca l automa ci c cr manuel control on PLCS.) (1 5)
- b. Ar. the event of a > : c to r trip there will not ce a quick open U104K Jue LJ Idve (L . cec 3ust 39C3 will recelte a full Schle i 2ve > ;nal tron se.., (1.5) r: t r e r. cia te e aic Ve r :e w (2 Lean u.
E s _ _ d Lid I_ Q E11EM _ IS C Lu kih E _ h A L EIl _ a ha _ E5 E RG E U C 1_.t1S IL d 5 PAGE 23 ANd t<5 -- PALu VERDd 2 -8 5 / 09 / 2 s -5 T xd I t Rs G. 4 - aiws tn 2.lu (2.tv) s.s. .... ;; ;;...r tr. t-!? c a -: cr - ';. : ! '- ':::!3 t r.e aux i l i Er > raecoct:r .> ster *ill autcmatically provice aater is tre 5/J. (1.0) o.tn i cs s er < . c u a r.- tn- 2, . s 5alvcs to tne concenser are esteces. r 6 4c a r i na cs s i.. c as o i t ti e i '. n e r S t r. o s p r u r i c cunp or a 2Cs 4te(senere valv.2, the use of a t 7 c s o ri s r i c uomps cr aECS
. . r.c s o n e r e valves ri ti te in un c o m. t r c l i e c rausation rclease tc tn- c e ca r .):r e .r, te s r ucis e. (1.5) hLrte:ns; e s lu .' e r 2 susstian cenk O
l I l I I i i l l
la _1b11hJdEbli_ ADD CQblEGL3 PAGE 24 Ah5btn3 -- PALO VEADE 2 -8 5 /04 /2 5-ST RcIER, G. A h S 4L e. J.Ol (4.30)
- 4. .91GH Ltu leip--to e r e v c:. t linear t' e s t rates in limiting tLel pin tror a e ce s e e ri,. t v e l cesi;n limit in t rie event of an e nticio atc c oper at e cr E s cc cur re nc e .
Lea L cn lkiP--La r r e s us, t thed in l i .m i t i n ; cool 6nt cnannel trca ,aenw celoa ruei . - s i , r. ti?st in the event of an b re t t c a p a t e u Operaticisl w ccwt re nc e. (1.5) L. 4 c x-c 3 r e tsaaton s .c a.L r r a L. Cc< FGast Ons
- i. I ft
- 4. TC
- s. Prtr pressura
- o. n(/ LFte; Tram .'.
- 7. Cea centity fccitra (0.3 e a c t.) (1.6) c.C.A is snits.te; to s c u t'.c h (1.0) h L t t e 6.4 L ;
r elo Ve rw J wb ti t ion a h nh V Ol b' 11 1 s sect. is p;. i4 Ab s hc n J.ui (2.20)
- 4. 451 reacings fram inc Lore Protection C alculators (CPL) ci f f er i n w fron 531.
- iso L f,S r. a r.d LPG margin meters f l uc taa ti n g (0.75)
- a. 'i. c ar l i er ce tec ti on et transient.
- 2. Less limiting ccrsrol b.ncs. (1.0) c . H l f -c y c l e campi ng cr Fower sniping t e c t.n i s ue s (0.75) d6 tlc:Hwc Ctc sesson p l an 41CF-14Z05 6pp. d.
la__1balidedul5_AdQ_C0hlgDLA PAGE 25
. Ah an cas -- P ALO VER DE 2 -85/09/29-STFdittac r. rial .crsne S i ana l ( RF - ) [0.3J which .
as , c n s r a c .a c ts 349xin. I.v. altn the Tava ta setscint se,n 1 La.b). ( 1 5 ) -9P a t t c ..c . t . r c Sc c st si cRD tr o i 2351. ?Lss ps. 23 Vcicr. v$11 s ec t ion c r... ;c *1 ai5 ace 3.v* (a.c0)
~
A. L c., or .taran, asI c s:s teeJr.at2r pwnp trip. (G.8)
- 2. nrC) . u t c a. e c a c actuativo in *Ltc 3 ele:t will c;us a scme roo crops 3 >. o v s 79 per c ent $c ,r (0.6)
- d. 1 rcsne 'eteac4
. L-. 20 r ur cen t av er (0.6)
*. Turaans runcsc< at tus;ine pow 3r ;reater tran reactor power (C.8) n t r t o -. :l s stac6ar ec-cr w6Lasc< L 3 ; t . r. cescr ip t ion A '. : v 6 e 3.00 (3.00) sEcici: c a c ri C P C d o c , a t.tle l oo k u p the tacle is entereu with tne CcA srcups which are in eacn of 20 axial core slices. (1.0)
Aaios: Aan 6acore lowege midult and uppsr rtacir.ss correcteo for snepe annealin, enc r oc sn aJowi ng effects Dy acoressable co n s t aa t s :o ,er:rutt exial power profila. (1.0)
- i. o nt y toi e t r a c a l: A2 a ruir 2 s cwe r t il t adcressable constant
.;t ecv s ati cn a ;r e n a suegroup issi;nec a penalty rector oy Jc,,' . (1.0)
B e r : r. c t L c C FL i s s L :.a utscristier. . . r 4 H.a 1.2.1, 1. J . 2
a __lbSIdudiblS_AdQ_CQhIEQLi PAGE 26 AN5hce'5 -- PALd VEADE 2 -8 5 / Co /2 5 -S T e t ; E r. s G. ANhatk J.sb L3.00) 6 1 2 v-2 v/) cps = 2 4 i v ,P' ; c d x 1 C-6 oercent power (1.0)
- 2. Tv prosvi.s tne Iers ci tns s tor tup cnann el (1 0)
- 3. f r.e st;rtc, cnaint 6%rr.nt -seI t. 9 limit =c to one(1) oille.no :) a r e t a u t .' r ir tr.e n e r.n v c i t a Je supply. (The life of toe ina tr ukca t 4: 16 .- ., c s ts re c. ) (1.0) ntthe-ctce 41uP-ictJ3 r..o cacora *A
. .y a te n jescre,Lica 6,. LS A tl a w c r 3.J7 (c...)
- 1. i r a t r o..s e n t fhils :r s . : eso;st. ar s ,i c a r e n t si e sn Tc.
- i. ns;n I v,-irar arrcis a s a r er. ;ru a ?.
3 . 4 ;. . . . . . . -,.....;- _!_- _' . i.r:1.
- 9. rrcasosi;cr ,l e v e e t i l so to va simum level. (2.C)
> t F e w Eill.
Polu Verus GLestion vank J r -w-- - ,. - -y - y- -- ,,,
4 3s__1h1Ihudsh1S_AND CUBIEDL1 PAGE 27
- A h5h t45 -- P ALO VERDE 2 -85/09/25-SThEIERs G.
ANhnts 3.Jb (4 50)
- a. Nc [C.)], tae ./C8 s are set to trip passa on a transient with c er t ai n s y s t e .n t s ai e celays. If tne oper ator operatec outsice tie L.0 t a f.G C Ene ters r. 0 L i c ce tos shnrt for tne LPC's ~
to r esc t cefort exceewin, Iust linits C1.01. (1.5) i' O. 1 s o.: p e crneoiina d . 4 0. ali? C O a sil)
- 4. T et.s e r a tu r c a n, u a - i n , (J.a eacnj (1.5)
- c. 1. Ccre c e r.a s t i o ns outssce the ane t yzea rar amer ter space 6 L es = t r. a n 2 ACP'a r 2 ri n e n ,
- 4. A3=Imuc nct I cu L24;trature creater t,sn toe sattration teak st atur e r Jr tot ere::urizer rreasure.
*. laternal prJce scr laults Lan) 3 9 0.5 each3 (1.5) h e r c h.c i t.
Crw ss i tem ucscrsatsun 9,0. 9s ic-IS Ahbacn J.J9 (1.LJ)
- 1. t l eC tr i c a l f 4 Ji C
- 2. L O-L a s p r a ) C ae n 10 s l s tar s,e ta nk !? vel (C.5 edCn3 (1.0)
VtrtPL4Lc s C o r.t o i n nen t S pr a y ano Iccine Ren:csal system aescription pg. 19
da_ _ddLiteudi1_: bGiddLt_&SbOE3att.EdE3GES'ar_aGG PAGE 28 daw 1LLdG1LAL_GQdidLL Arissen3 -- PALU Vc A Dti 2 -85/09/25-SiksIER, G. An'sud e 4.LJ (2 00) .
- m. A l pie o:. : L % . a j --i .ic t t r a n . t. o e s t .' n i J r' ionizin, power L v . :: J id: ( r . r. . ) = soss (r 4 Js ) x ;r] (1.0)
's . uaa.a;_: 6v.;J--a . rs i ci c t r t i v.7 po-er anila a l e . r 3 :. and tet,3 ar c :. 7 . r t r 4 r. ac o r. ) :asiiy sb: alcec t0.5]. (1.0) 4 :a s.. . e w.s: (L.au) se sGa n i, E Oc/t 4 1laes O. L' O 'a a.Pdild v c e 4 i Ta l ;
ce sila ,i a v e c I l-a l t
- c. .-cra nat r. c v .: a li g s t e . s c:2 .64,4 e linet t..> .: a c t ) (2.5)
'httu a
. It; P olc werst Icon. SJCCa.
Al. $ n t N ,.oh (3.s>i
- e. Ic pr v ent e a rts n; au sot;ty v4Ivas. (0.5)
De a r.u ; att e r f c0 c e.: au . 21V L C . 2 J a r. J Jst atmo s prit r i c currp valve t c c c010o w r'. tU.>J an..4,e g..g b c.na.E,.m u==54..b d 5/6 (l.01 SS
- c. coutco n t r. t etC 3 to ci tsin ;, r e a t e r t h en Je F suococling. [0 75]
u ;pr ess ur i ze AC$ until aC5 pres:ura is ;Ii antly jreater th&n $G p r ca sur e LO.73J. (1.5) A c F ti s t1C.:
*isu-144co p w. ,
ha__En2CikuRES_:_SQ&d&Lt_eauCadAlt_Edi&GE3C1_ahQ PAGE 29 nesikwuGICAL CDMIdDL Ah5etw$ -- PALJ VERDE 2 -85/09/25-aTktItks G. Ari s n e s 9.04 't2 1v) P osi tiv e or r eJ a ti v e r i sct i v i t; ch an ges can occur wncn placing an On.dxetien cr in 5Lt.acc. F ar ti di flG= 3nould te estaDiished tc aswaliga t rie 60.1 excrin,cr avrc r concentration prior to e s ta tli si. ns tull flor t s.4 ; v, h t rie icn excnan,cr. (2.1) Aft: Ab4C: rato Verst wuestian s e. .'e n AN5 eta s.05 (2 4v)
~
Le 1. i t ..L ; t _ ... s : r . c u i ia .: t o te - vi ieas U i . .- Ed ;;;.;;- T
. 1.
4 .' II .c0 Fr easa re I. l 's tn an 2100 psiJ J. I f xua prcs4;r. e_ ,r vale r t nan 23 )0 pseJ 4 at cure airfarcnteas L(nperature is greater t n a r, 57 aegre s r. O. any a f s t e h a o n c r .r a l : L i e t or tranJs. [4 e 0.3 e ac n] (1.2)
- b. 1. 1r nare t n an one sia :s not fully ins er t ec.
- 2. Po=er nct oecreasin a to sour ce level.
- s. -nf safety ss;nal actuatec.
- 4. A n3 system annorrelities cr trends. (1.2) n E F c e.c N cc 41tp-1Z401 pgs. 3-11
hi_.BiQCtQQREi_:_bdddakt_adudddatt_ESEEGLEC1_aEQ PAGE 30 haul 0L'J G1L AL_LQ3IdGL A NS W :k 5 -- PALO VEROE 2 -85/09/2t-5 Tid 1Er, G. Ah 5 cc e 9.V6 (J.LL1 de li c c e t s o n = rt ive r t e. (1.0)
- b. $ e. 41 4 7 sec is cia ia wJ'- to F r c v9 nt intrusion of contaminatts into tne s t. 4 f t a c. l
.;6 . .P d ii s c h will rsGdce tne life of the aucia. (1.0) n t r a s ; . . '. ;
41Gr 4C n)o AN h au m $.0/ (a.uci
- 1. *ll CtA's 99rofic; fully I r. z e r t e c . .
- i. conuc4Iy a ni C i at e . .. . . r. . . . a 4 3 / an d - '
aw&. a .4ud* 4 c es usM .
- 3. iLLi ste 3LP Di3eJJtt t3 riT.
4 4 s a n t.i n steat j ea t r : L vr tres.wra 1179-1223 F5so using the i t 'r.u a F h u i 4 s Jung v.lv.a. (.u
. n ct c o o l c G'an sCL).
- p. r osn tai n s t e . ... isne. tcr level n i t .7 a tu rbi nc driven Ath pump.
- o. Vereti r. s t c r .1 c i r ( w a s t o c ri . (3.0) i L F C r L'e L.
91su Ali)Q pas. 4-> Ar,14tr 4.Je (3.svi 4i the r6 actor is not critscal upon riacnin; the LCP, the over .Lo r w ill teil out a crior t u s < an in tre orocecure enc will
*ILnura* re v ulating gruces sr. 100 P C 'i inct e men ta until the
- r e ac tcr is cr sti cal or :tP + 300 PCM is r e a co t c. r5 rods > lJr",p w,+. e.Js (3.0)
# #* P
- J;luk /cor
- and p i4 it n,J 3 apu n t F t r :a Le 41Ct-14ZJ3 Ftra rap 6 * . . . ' i . 1-- E
- - - . .. . ~ . -. -. _ _ - . - _ __ . _ - ~.
is._EtGCiQudt1_:_BQ1daLA_AabGidALL_EdidGESC1_AUC PAGE 31 eAwiukdG1LAL_sadItLL AA5 Le$ -- PALU VERDE 2 -85/07/22-STReicRs G. An d e:n 4.v9 ( 2.LC ) Nansn; swa gr(asari r; i , r. s r
- r it a t c a r.. gener 3 tor pressure ensures mL) calutocr uc t i .1 J t ccc ars trsraLy compratisin. SnutGCnr margir. (2.0) i-nitLr "_.s b '
,1 s u . L . -
ANhb:- 4 40 (a.os) by . I s a r. i n , et concanntsnt v r : 5. d ie on indi c ato r : i r.c c 0 re t a s n.: c r. t cr e sast : ..i r'ccr2er (to ce tarit anc ;r e ssur e a ustz ie r 6 , s 'c JaAi acesati.nJ. I sie cs, rat;r car, actartine from t r. e 2;o .; incic tiana ir v.. ;(tpoint ,a; e <c e ece c. L3.0)
' n c r e a. ;R c 41AL Alias ,s.a 4
s k 4
-e- - - . +
(*000000****00 LND OF EXAMINATION *000***0*000000) / la__e t1EC1E Lii_Gt_d d LL ie t _ EQ h E E_ f La SI_ D EE E&Il0 b g PAGE 15 IdEhowlb&t1C5t_ dial IBali3EEE_AM_ELula_ELdk , AhSdER5 --~PALU VERDc 2 -85/09/25-STkEIERs G. . ANSken 1.01 (3.00)
- a. A ctu al cr a tical position well De ni gher due to Xenon peak after the tr i p. (1.0)
D. A ctu al c r i ti c al position will be lower with less ooron in the RLd the C cntr ol Roos will need to be ins er t ed to compensate for t he lower r ea cti vi ty of the bor on. (1.0)
- c. A ctu al critical position will be higher due to less excess r eac ti v i ty r emai ning i n the cor e a t 200 EFPD. (1.0)
R E F E Rt.N L E Polo Verde Nucl e ar Theor) AN$btf 1.02 (2.00)
- c. ( w i t hou t some ne ucr ons there is no i nst r ume nt indication.
hitnout instrument incication, you do not know core reactivity s tat us or >hether tne status is changing.) So neutrons are needed to assure that the r e act iv i ty status of the reactor is known and the i n str urient at i on i no i ca t ion is avail abl e to r,uiu e o p e r at o r a ct i on. (1.0)
- b. 1. S pon taneous f i ss i on o f fuel
- 2. R eac tor start-up sources
- 3. S us t a i n er sources
- 4. Phocc neutron sources (1.0)
- 5. Alph=- h en e== kaa
(. . kir* e4 vms4** R EFE RtN Cd P elo Ve rde Question Dank
Lt _EB1BLIELEh_Ut_32CLEAE_ELMEE_ftaSI_QEEEallDUt PAGE 16 lbtitdelhaalLSt_diAI_IEaBSLEh_ASQ_ELU12_ELQs A N Sn En d -- PALO VdR DE 2 -85/09/25-STREIER, G. AN S al k 1.03 (3.50)
- e. The neu tr on s ees a significant increase in absorption cross section o v er a wider range of energies (decrease lie the fuel sel f sn a t i cing). (1.0)
- b. Less negative (i nc r eas es ) . (0.5)
- c. MTC Decomes more negative [0.b] because the density change per F as 9r eater at ni ghe r t empe r at ur es (0.5]. (1/2 credit given f or discussion o f ex p ans i c n / r em ov a l of B ano mod. as temp. inc.) (1 0) de NiC becomes less negative (decr eas es ) [0.5] because the number o f Doron atoms (poison) in the core cecr eases mor e per F change at hi gher oor en concentr ations. [0.5] (Also accept r ele van t discussson of thermal utilization) (1.0) klFEktNCL Palo Verae theory # 12 AN S WE R 1.04 (1.50)
- 1. Ens ur e thet acc ep tabl e power d is tr i buti on limits are maintained.
- 2. Ens ur e t h at tne minimum SDM is maintained.
- 3. Limit the potential ef f ects of rod misa li gnment on the associateo acc i jen t sna lys es. (rod eJ ecti on ) [0.5 eachJ (1.5)
REFEkEdCb Palo Verde T.S. b 3 / 4.1. 3 ANSW6k 1.05 (3.00)
- e. As p owe r increases fuel temperature increases [0.75] this will aod n ea a ti v e reactivity to turn power via Doppler [0.75). (1.5)
- b. The [pppeoCEA will inser t nega tI Ve r eacti Vi t) but positive r eac tiv i ty will be acdea be c aus t of tho lower fuel temper atur e (Doppler) [0.75J ano lower mooerator temper ature (MTC) [0.75]. (1.5)
1:,_.EL1hLiELti_QE_ddLLtAE_E0kkd_fkabl_DEEE&IlQdz PAGE 17
-IdihDJarbat1LSt_ddel_IEadhEEE_Abk_ELul0_ELOM Ah5wLkS -- PALO VERDc 2 -85/09/23-SlkEIER, G.
R LFL h LNut C-E he act o r ' T rieo ry pas. 170,174 E 211 AN S WE R 1.06 (2.00)
- a. 2 (0.5)
D. 2 (0.5) c 1 (0.5)
- d. 2 (0.5) kEFEktNCE C-E k ea ct o r Thecry pas. 181-193 ANSWtk 1.07 (1.00)
- d. (1.0)
RtFtRENCE G ene r al Physi cs Hea t Tr ansf er and Flu id Flo w pgs. 355-358 ANSktR 1.08 (2.00)
- a. Ine format ion of buobles (steam) in the eye of the impeller of a pump oue to oper ati on with insuf fic ient suction pressure.
L O.2 5] . Ibc buooles collapse al ong the impeller vanes. [0 75] (1.0)
- b. V or ati ons noises lower or fluc tuating amper age / flow /di schar ge pr es sar e. (1 0)
RLFEhENCE G ene r al Physi cs Hea t Tr ansf er ano Fluid Flo w pgs. 319-320
la__Ehl.!s1ELLE_DE_NdLLcaE_EDhEh_fL&SI_DEERallQbt PAGE 18 l b Ei bu k 1 b Atic St_ dt al _lE6B L E EE _i ha_ ELula_ ELQ h ANbotnS -- PALU VERuE 2 -85/00s25-STREIER, G. ANSutx 1.09 (2.00)
- e. Flow increases due to pump work requirements decrease (0.9)
D. P ump flom osc ill ates ano as NPSH approches zero and as the pump cavitates flon will i, o t o z e r o. 74 ce.vtl. 47.% u n.+ rat (0.5) dt w k y .~'.a 4.ccc u s,
- c. F low dect eases as the sy ster re si stance increases. (0.5)
- d. Flow incr eases s ince pump speed increases; pump laws. (0.5)
REFEktNCE G ene r al Pnysics Heat Transfer and Fluid Flow pgs. 320-322 ANSnEk 1.10 (1.00) Aovantawe - Incr eas es NP5H for con densate pump (decreases chance of pump cavitation) [0.53. D isadvanta we - S team used to reheat condensate could be useo for production of electricity (heat rejected from conuensate is lost to the cycle) [0.5]. (1.0) REFERENCE General Pn ys i cs Heat Tr anster ano Fluid Flow pg 153 ANSwth 1 11 (2.00)
- a. F als e
- b. False
- c. True
- d. F als e [0.5 each] ( 0)
R EFE ktNCt Genr al Pny s i cs Heat Transfer and Fluid Flow
In__EhlhclELih QL_ddLLEAE_EQmEh_ELaul_QELEAIIQBt PAGE 19 I bs h tu21 ba tlc ht_diel_ l h& Ult Et _a b2_E Lulu _ EL D h Ah5wLd3 -- PALO VEK0c 2 -85/09/25-STREIER, G. ANSudR 1.12 (1.00) More en er 9 y is reauirec to procuce steam ae 564 F. Both require the same amount of sensible neat to r aise the subcooled water to s aturat icn temperatur es out the latent heat of vaporization cust De adoeo to 0o: 1 it. (1 0) REFEnENCE P alo Verde question Dann ANStEk 1.13 (1.00)
- a. Conduction LO.S each) (1.0) c . R ac i at i o n -(cceds e t o )
R E Ft k tlitd G ene r al en y s i cs Heat Transfer and Fluid Flow l
- Z a _ _ E L ab l_ Q L 11 kd _ IS C Lu k 1b E _ h A E L II _k U Q _ E dE RG E S;1_1111E d1 PAGt 20 ANSwEnS -- pALD VddOE 2 -85/09/25-ST9EIEFs G.
ANShtn 2.01 (1.00) T uo air rese r vo o rs are pr ov i cec as a backup control air supply [0.9 3 f or pos it i oni ng the nyorauli c fluid control valves [0.3]. to allow accumul ato r pressur e to act on the MSIV [0.33 (1.0) (yg cw.M&l t,.c 's sa Awwn'.% h a u. + .t. 9 .) REFtRENCE Main Stean system descraption ry. 13 AN5tEr 2.02 (3.00)
- a. From ut to 15% tne ocwncomer FnRV ramps open to preheat the feeowater in oroer to prevent thermal shock. From 15% to 50%
the downcomer FWRV is shut to i ncrease the efficiency of the s tear cyc l e. From 507 tc 100% the downcomer FWRV ramps open to IC% to allevi ate tne affects of ste am carryunders and enhancing the r eci rcu l at ion ratio. (1.5) D. (Tne r e ac t or trippeo over r ide s ignal shu ts the economizer v alv e), ramps the main f eedwater pumps to minimum speeds [0.753 and p osi ti o ns tne f eedwater r egulat ing valves to minimum or maximum posi tion cepenai ng on whetner T ave is less than or greater than no-loao Tave. (1.5) R EF E REN CE RCS Sys tem descr ipt ion pgs. 23-24 Feedwater Contr ol S ys ten. de s cr i p ti on p gs. 2-3 ANScER 2.03 (3.b0) a.1) I nc omp l et e sequence alarm.
- 2) L ack of DG running al arr.
- 3) L ack o f vo lta ge or speea inoication. (1.0)
( wi s Acc p+ ats. - 41 f,sor;4y T=1.te tam.b% sgAs at. ) o.1) S are ty injection actuation s ignal (SIAS).
- 2) A ux i l i a r y feedWbter actuation signal (AfAS).
- 3) Loss of vo ltage to c,g as.- CJ As ) i t s resFective bus (LOP). (1.5)
( ;.t c) T no-one for.each diesel capacity is based on providing suff sci ent storage or tne diesel fuel oil for 7 days continuous oper at i on - ( plu s 194 margin fo r testing.) (1.0)
' Za__ELadI_uEllLb_IUCLualbh_aattll_ASQ_EdEEGEBC1_s151Edi PAGE 21 AhSW tRS -- P ALD VER DE 2 -85/09/25-STRE1ER, G.
k E Ft k E tile D i es e l Sys tcm cescr ipt ion AN5tER 2 04 (3.00)
- a. 1. Hagh level al arm for f eedwat er heatcr 6A
- 2. Dropping level in the he s t er drain tank
- 3. keouced flow f r.om the heater dr ain pump (1.5)
D. w hen th e heater dr ain pump f ail s, less flon will be insertec i nto the main f eeawater train which causes a lower inlet p r essur e tc the MFP, the lower inlet pressure will reduce outlet f lons r equ ir i ng tne NFP to spee dup in response to a lower S/G level to mai nta in $/G l evel . (1.5) REFERENCt Palo Verde Quest ion bank AN5 ten 2.05 (2.00)
- a. T he val v es ar e throttled by sel ecting override LO .2 5 3, this is cone by selecting "Jos open" po si t ion and thtn the " Jog close" position LO.7b]. (1.0)
& 3
- b. Nc sooner th a n Jf n o u r ano no later than 2' hours following a LbCA. (1.0)
REFtKENCE S efe ty Injection system cescr iption pas. 39 6 42
'll SO 121 e] w f 'AS AN5tER 2.06 (2.00)
- a. Actuate s the control room e ss en ti a l filtration units IO.53.
- b. 1 sol ste s the con ta i nn ent bulloing pur ge supply anc exhaust aucts ( cpl AS ) . LO.bj
- c. Automatic fil tra tion of concens er vac. p ump / b land seat exhaust.
L O.5 3 (,Thru-Chr maat) de lholates the no r ma l ventilation and activating the essential v ent il a t i on syst em (FSEVA5) L0.5). (2.0) i
Zs__Etab1_kchIsd_luLLuulbE_hattIl_AUQ_EBEEGENC1_SXhIEdh P/GE 22 ANSwLnS -- PALO VEKDE 2 -85/00/25-5TREIEF., G. REFEEtNCE Roon ation Mon sto ring system cescri ption pgs. 3,4,7E9 AN ShE h 2.07 (2.00)
- 8. 1. S hut dow n coo l in g heat ex ch an ger
- 2. Essenti al cniller (1.0)
D. E C nS pump will trip and be rest ar ted with the ESF load s t qu en c e r . (1.0) REftAENCE P alo Verde question Dank ANSetx 2.0E- (3.0v) a .1. Hyar o ge n r ecomo i ne r system
- 2. Hydr ogen pur ge system
- 3. C ont a i nn.e n t a tmospher e mon it or i ng system [0.5 each] (1.5)
- b. 1. T ne cec c.nposi ti on o f water by radaolysis.
- 2. A metal water r eac tion betwe een the c lad and coolant.
- 3. C or r cs cn of tnc me tals wi tn in the contai nment. [0.5 each) (1.5)
REFERENCE C ont ai n men t Hydrogen Control syste m Descr ip tion pgs. 3-4 ANScEh 2.09 (3 00)
- a. PtC; raise level setpoint tn im=v nrnorme lewasi c;; *w
';:l .w.ic !.,s. ..+,i i . v ., k kS , 'but t r, e t ; "! te "O O f f e ct
_cr rie. sus .ier ;;;;l escow s iv iaku RR: to test 70; :::t
-us .n i ou i a u t u .a . 6 i u er in er u e: ; nticl vn r i.C S . F gg),4,d 4+r+4-be in the event of a kesc tor trip there will not be a quick open block Jue to lave ( Laha o e c au s e SB C s w i l l receive a full scale lave signal from Kh5.) (1.5)
REFEkcNCc P alo Verde Qucstson bank
Es__dLadl_CL11L3_130LuklbG_iAELIl_AhE_E5ERGEUC1_11SIEd5 PAGE 23 ANSW LR5 -- P ALu VER DE 2 -85/09/25-STREIERs G. ANSeth 2.10 (2.tu)
- a. L., e..; ;; ..;.. t r. . ' .' ? ! t-!; and on ; tu i!C !:;;!;
t i.e aux i l i ar y feedwster systen will automatically provide water to the S/G. (1.0)
- o. On l oss et vacuum the 5cCS valves to the concenser are oeteateo r equ iri ng coo lcown with e ither atmospheric dump cr
$6CS 4tmosphere valves; the use of atmospheric oumps or SBCS atmospn er e valves wi ll be an uncontrolled radiation release to tne atr cs p ner e anc the publi c. (1.5)
REFEkENCt t Palo Verce question bank I l
. s aa__1b51hJuibl5_abD.CQhlLULL PAGE 24 AN$kEKS -- PALG VERDE 2 -85/09/25-SlRtIERs G.
A h 5 ut s. 3 01 (4.30)
- a. HIGH LPD lh1P--to prevent l i nea r heat rates in limiting fuel pin f rom ex ce eding fuel oesign limit in the event of an anticip ate o oper ationa l occur re nce .
lum DNBA 1 RIP--to prevent DNbR in limiting coolant channel from 40eng De low fuel cesign li mi t in the event of an anticipatea oper at ional oc cur re nc e . (1.b) L. 1. E x-c or e f i ss i on chambers
- 2. CEA positions
- 3. Th
- 4. Tc
- b. Przr pr ess ur e
- 6. KCP speed from CPC
- 7. CEA penalty factors (0.3 each) (1 6)
- c. C WP is inittate3 to CEUMC5 (1.0)
REFERENCE P alo Verde question bank Vol VIII, sect. is pg. 24 AN5hER 3 02 (2.50) D. ASI readi ngs from the Core Protection Calculators (CPC) ol f f er i ng f r o m E 51. Also DNBk and LPD margin meters f l uc tua t i n g (0.75) D. 1. E ar l i e r de tec t i on o f transient.
- 2. Less l i mi t ing control banos. (1.0) c . H a l f -c y c l e campi ng or power snaping techniques (0.75)
REFLkENCL CPC lesson plan 410P-il205 app. 8.
s 1.__1hkliudtu15_AUD_CubitDis PAGE 25 ANSnexS -- PALO VE K DE 2 -85/09/25-STREIER, G. ANScEn 3.03 (1.50) Ine ATU nail bl o cn any s i gn a l to the econimizer valve except tnrougn the transfer switch, wh i ch is a zero signal anc closes the econ 6mizer valve [0.53 anc the downcomer water level will ba control led oy tne b ef i ll Lemand Signal ( RF D ) [0.53 which is generated by summing Tavg witn the Tavg NL setpoint signal [0.53 ( 1. 5 ) -@> REFEheNCb F e eo wat er con tr o l systen hSSS pg. 23 Vo lute VIII section 6 pas. 39-42 ANSbEh 3.04 (3.20)
- 1. L oss of b e ar i ng oil causes f eedhater pump trip. (0.8)
- 2. R PCS automatic actuation in Aut o Select wi l l cause some rod drops a Dov e 75 per cent powe r (0.8)
- 3. T urb ine s e to a cn to 60 per cent power (0.8)
- 4. Turonne runbacn if tur oine power greater than reactor powe r (0.8)
( 74W.+ f9rM 4 f." [ n W 40M kEFtRENCE Re ac tor Power Cutback s) stem oe scr ipt ion ANSbEA 3.05 (3.00) R aci al E ach CPC does a table l oo k up the table is entereo with the CEA groups which are in each of 20 axial core slices. (1.0) Axlett Aan eacore lowels micale and upper readings corrected for snape annealing anc roc shadowing effects by accressable const ants t o gener stc axia l power prof ile. (1.0) Nons ymmetr i ca ll Azimuthal power t ilt addressable constant CEA c ev i ati on within a s ub g r o up assigned a penalty ta ctor by C EAC's. (1.0) REFEhENCc C PC sys tem aescription para 6raphs 1.2.1, 1.3.2
aa__lbildudtbil_Au2.CQblEUL5 PAGE 26 Ah5k tR$ -- P ALU VERDE 2 -85/09/25-SinEIEK, G. AN$hEk 3.u6 (3.00)
- 1. 20-20J3 cFs = 2 x 10,'to 2 x 10-6 percent rower (1.0)
- 2. To prolong the l it t of the s tar tup ch ann el (1 0)
- 3. Ine startup cnannct current wil l be limited to one(1) m il l i am p by a resistor in the h igh voltage supply. (The life of the instru' ment will De s hor tene d. ) (1.0)
REFEkENCt 4109-1Z203 pg. 6 E xco r e hl s y s te m de sc r ip t ion pg.18 AN5cEF 3.07 (2.00)
- 1. I nst rume n t f a l l s n i g t. causing a n apparen t high Tc.
- 2. High Tavg-1 ret errors al arm and awp.
3 . -C r, e . . . . s ; es .;e;!c^ :!:r" sad AMI .
- 4. P ressur i zer leveI will go to ma ximum level. (2.0) ,
kEFEkENCC P alo Verdt Question oanh
3s__lb11huuthlh_AbQ_GuhlLLLS PAGE 27 A NSh bRS -- P A LO VE40E 2 -85/09/25-5TkEIERs G. AN$ntR 3.J6 (4.50)
- c. No CC.5]s tne CPC's are set to trip b as e d on a transient with c er t ai n system tomo celays. If the operator operated outside the LLO r ange tne t i n.e mould te too short ior the CPC's to r tact oef ore exceecing fuel l im i ts [1.0 3. (1.5)
- b. 1. S nap e anne ali ng
- 2. Rod shacowing
- 3. Temp er a tur e sna cowing [0.5 each) _ (1.5) c .1. C or e cono s tions outside the analyzed paramerter space
- 2. L ess than 2 RCp's running 3 . M a x a m u ir. h o t leg temperature greater than tne saturation temper atur e f or the pressurizer pressure.
- 4. I nt e r n a l processor faults [any 3 a C.5 each) (1.5)
R t FE LU4 CL CPC sys tem oescispticn pgs. 9, 16-18 AN$cck 3.09 (1 00)
- 1. E l ec tr i c a l fault
- 2. Lo-Lo spray chemical stor age tank level [0.5 eacn3 (1.0)
REFEktNLt C ont a innen t Spray ana Iodine Reroval system description pg. 19
. s ia_.28kCLkudch_:_bQid&Lt_AabOEs<_EdE3GEb;1_abQ PAGE 28 dak1LLQG1LAL_LQ31dLL AhSwekS -- PALO VERDc 2 -85/09/25-STREIER, G.
AN$tEo 4.03 (2.00)
- e. A lpnas L u. 5 J--s no r t r anged wit h nign ionizing power LO.D] [dE (rems) = cose (r ads ) x QF ] (1.0)
- b. G ammas C O . a ]--m or e p e n e t r a t i on power while alphas and betas ar e shor t r ange and easily shieloed [0.53. (1.0)
ANibEt 4.02 (2.50)
- a. Does no t have a limit
- b. Doe [* nave a lim 6 t
- c. Does nave a i smi t
- o. Does no t h av e a limit
- o. Does nave a l imi t [0.5 each) (2.5)
REFtkEnte Palo Veroe Tech. Specs. ANShek 4 03 (3.00)
- a. To prevent !sitsng SG safety va lves. (0.5)
- b. Shut an af f ected SG M51V [0.53 and use atmospheric dump valve to coo 1oown. [0. 5 ) an. * *= # ag.*. g b c= ae C .- u=54* *b A S/c (1.0)
SS
- c. C ool oonn the RCS to obtain greater t h an JHr F s u bc o o l i n g . [0.75)
Ocpr essuri ze RCS until RC5 pressure is s lightly greater than $G pressur e [0.75J. (1.5) kEFERENCc 91KU-12Z00 PS. *
/
. t ha _Eh2GLLuddh_:_Udadalt_AduCBdAlt_E5ERGE3CY_AdQ PAGE 29 hiGiLauG1L4L_Gd31EDL Ah5wtR$ -- PALJ VERDE 2 -85/09/25-STkelER, G.
ANShEh 4.04 (2.10) P osi tive o r negativ e r eactivi ty changes can occur when pl acing an ion exchanser in scrvice. Par ti al flow should be established tc equalize the son exchanger boron concentration prior to establishink full flow through the ion exchanger. (2.1) REttkENCE Pelo Verde question Dank AN5cdk 4 0b (2.40)
- a. 1. +t-RCL t e .u p e i . t u . c is wr s a te r us iess '
s ;. .n 23 S grecs F r . . . . . . nn le d_
- 2. 11 RL5 pressure es less t h an 2100 psig
- 3. IfRCS pressare is gr eater than 2300 psig
- 4. It core offferentsat temperature is greater than 57 degr ees F.
- b. Any system aOnormalities or trends. [4 3 0.3 each] (1.2)
- b. 1. 11 more than one CEA is not fully ins er t ed.
- 2. Power not decreasin's to sour ce level.
- 3. A ny safety signal actuatec.
- 4. Ans system abnorralities cr trends. (1.2)
REFtkENCc 41 E P-1Z Z01 pgs. 3-11
, t I . \
ha__EtuCLuuhEh_:_bddd&Lt_AdudBDAtt_EBEEGEBC1_adQ PAGE 30 EAR 1DLuG1LAL_GQSIdDL A h5 d Eks -- P A LU VERDE 2 -85/09/25-STFEIER, G. Ah5dtk 4.06 (2.0C)
- e. No action as req ui r ec. (1.0)
- b. Seal in Jec tion i s usec to prevent intrusion of contaminates s nto the shaf t s eal syst em which will reduce the life of the seats. (1.0)
REFERENCE 410P-1C HJB AN $ dE k 4.07 (3.00)
- 1. All CEA's verafled full) i nse rt ed. .
- 2. Manu as i y ini t iat e C ';; r. ; M S 15 /'an d - ' '2-
- u. 4u44 msu h .
- 3. Isol ate ALP bleedof f to ADT.
- 4. M ain tai n steam gener ator pressure 1175-1225 psia using the a tmo spher i c oump valves (co not coolcown RCS).
- 5. Main tai n ste am gener ator level with a turbi ne driven AFW pump.
- 6. Verify na tur a l circulation. (3.0)
R E F E KEN CE 41kO-1ZZ39 pgs. 4-2 ' ANScLK 4 06 (3.00) if the reactor is not critical upon reaching the ECPs the oper ator will fall out a char t g iv en in the procecure and will uitnoraw r ewulating groups in 100 PCM i ncr e men ts until the reactcr is cr stical or ELP + 900 PCM is r ea cn e d. IS r.Js > s3r",,h,& ech (3.0) d ; lu k /co r'*
- wd p u it r.J 3 ap #" M ^
RLFEkENCt 41CF-12ZO3 paragrapn 4.3 10.1-2 l
e- , i ia__Et0ChuddLi_:_h01dakt_4abDhdakt_EdiEGLUC1_abQ PAGE 31 EAw1DLOG1LAL_kdSIELL AN5htxS -- PALO VERDE 2 -85/09/25-STRE1ERs G. Ah5tch 4.09 (2.00) M aki ng RC) pr es s ur e nigner than steam gener ator pressure ensures RC S o s l ut i on oces not occurs t he re by compromisinw snutoown margin. (2.0) R EFL EENCE 41kO-1ZZUb AN 5 ht s 4.10 (3.00) by looking at containment pressure on indicators ano contai nment pressure on recorder (to determine pressure JLst pr ior to CS AS ac tuat i on) . Ihe operator can determine from the 400ve i no ic a ti o ns at the setpo int was e xce eceo. (3.0) R EFL kENCE 41AU-12Z30 pg. 3}}