ML20237L071
| ML20237L071 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/12/1987 |
| From: | Cooley R, Graves D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20237L063 | List: |
| References | |
| 50-445-OL-87-01, 50-445-OL-87-1, NUDOCS 8708200073 | |
| Download: ML20237L071 (109) | |
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COMANCHE PEAK EXAMINATION REPORT No. 50-445/0L-87-01 11 i Facility Licensee: TV Electric 4 400 North Olive, L. B. 81 l Dallas, TX 75201 Facility Docket No.: 50-445 l Operator Licensing examinations administered at Comanche Peak Steam Electric I Station Chief Examiner: U// s 1/I4/p > l David N. Graves Date . Approved By: k-RalphA. Cooley, Chief,Opergor
< P//d/ f7 Date '
I Licensing Section ! Summary: Examinations were administered to four Reactor Operator candidates and eight l Senior Reactor Operator candidates. Four Reactor Operator and seven Senior l l Reactor Operator candidates passed. l r l l l l 8708200073 870813 PDR ADOCK 05000445 V PDR \ _ _ _ _ - - -
1 o 2 l DETAILS
- 1. Examination Results i
Four Reactor Operator candidates and eight Senior Reactor Operator i candidates were administered written and operating examinations. Four i Reactor Operator candidates and seven Senior Reactor Operator candidates .. passed.
- 2. Examiners i l D. N. Graves, NRC Chief Examiner S. L. McCrory, NRC .
i J. L. Pellet, NRC ! J. E. Whittemore, NRC , i l 3. Examination Report l Performance results for individual candidates are not included in this report. This report is comprised of the sections listed below: I a. Written Examination Review Comment Resolution A copy of the facility's review comments is attached. Only comments
- not accepted and incorporated into the examination will be addressed j in this section. If a comment is not addressed, it was accepted.
l Comments containing clarifying or subjective requests will not be j addressed. Each item is listed by section question number. 1 l 2.05 a/6.06 a: The question specifically asks for the radiation monitors so no confusion should have arisen as to whether it was addressing hydrogen monitors or radiation monitors. 3.06 b/6.07 b: Component Cooling Water and Safety Chilled Water were not accepted as per Chapter II-7, Introduction to ESF, Figure . ICD-8, and Turbine Trip was removed from the answer key for the same I reason. l 3.12: Comment requests that the entire question be dropped from the l examination. Part a. will be retained for 0.5 points and the remainder of the question will be removed from the examination. ! Section 3 will contain 23 points instead of 25, but will still count ! for 25% of the final grade. 4.11/7.06: Iodine spiking was not accepted because the question stated that the reactor had already been at 100% power and a spike l due to the power increase would have already passed. I
,, 1 i ( 'a -
3 p" 5.16 b; Question; retained. -The intervals provided needlno l association'for determining.the rate of power increase. The formula- 1 was provided in the answer key for SUR determination. The chief i
- examiner believes'that-a minimally competent operator would-L" -
not be mislead or confused by " entering the~ heating range".vice
" reaching the,P0AH".
J
- 8.04 b'
- Shift Supervisor'or' Assistant' Shift Supervisor was~ accepted for one-half. credit.
8.10 a: Comment-not accepted. .It is conceivable that.the'TSC' . Managerfand the E0f: Manager may not be the Manager, Plant Operations' )
- . and Vice President, Nuclear Operations, respectively,-'during l emergency. conditions.-
- b. . Exit' Meeting Summary
.The exit meeting was held on July.17,:1987,. to conclude.the site 1 visit. The'following personnel were present: l 1
i l 'NRC Licensee D. N. Graves, Examiner L. G.'Barnes-W. F. Smith, OSP G. L.. Bell .. M. A. Neimeyer ? C. M. Rice d C. L. Turner 'l The following observations'were made' to the licensee; l i' (1) Escorted. access into and out 'of the 'fability was handled . smoothly. (2) The.following problems were noted on the simulator:.
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- a. The SSII panel would sometimes not allow the operator to j acknowledge and silence the alarm, which created a distraction'to the operators.
! b. The'RM-11 locks 'up periodically for no apparent reason.
- c. When both pressurizer spray valves fail open, the rate of primary pressure decrease appears extremely. slow.
- d. One of the-initial conditions (IC-10) initialized in an unstable plant condition and the operators are constantly.
'trying to stabilize the plant:from:the beginning of the scenario.
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t (3) The following operational concerns were noted: ,
- a. There does not appear to be a procedure for restoring site l power to a safeguards bus with the diestl generator j carrying the bus. ;
- b. Following a powers perturbation, each monitor on the RM-11 !
must be reset by the operator before proper indication can i be restored. Some of the operators were reluctant to take I the time to go through all the monitors to reset them, even when needed monitors were not useable due to not being reset,
- c. Attempts to maraally trip the reactor should be attempted from more than one location in the control room if one i attempt at one location does not' function.
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- d. The crew members appeared reluctant to pass along }
information on plant conditions and events to the other crew members, including the supervisor.' In several ! instances, this lack of communication allowed events to; ' i become more severe than they should have been. ] Facility personnel present at the exit stated that that they were left with the impression, from the last operator licensing exit meeting in October, 1986, that too much information passing between i the operators during the simulator examination would be grounds for failing the candidate (s). The chief examiner replied that that impression was wrong, and that the examination encourages an exchange of information during the simulator examination, with regard to keeping the crew members informed of all activities and events. If one or more candidate.g oppear to be "carryirig" other candidates, the examiners will take steps necessary to ensure that an evaluation of the other candidates' true abilities can be made. , The facility also stated that they believed the written examinations were performance-based and opemtionally-based and hoped that G ture examinations continue in that direction. Two items noted by the examiners and passed on to the Resident Inspectors were not mentioned at the exit meeting. Mr. Larry Barnes I of TU Electric was informed of these items via a telephone conversation with Mr. David Graves on August 5, 1987. They are listed below.
- a. There is no method of making offsite notifications from the Remote Shutdown Panel. Once control is established locally following a control room evacuation, cctside communications can not be conveniently made.
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- i. 4
- s. j 3 -]
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- 3. .;
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- b. The Emergency Diesel Generator start signal via a blackout j signalJuses the same logic as a normal start. )
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- c. Examination Master Copies Copies of the Reactor Operator and Senior Reactor Operator examinations and answer keys are attached.
l 1 1 l t 1 i 1 l i 1 1 i L______-___-___ _ _ . _ _ _ ___ _ _ _ _ _ _ _ _ _ _
r 1 ( ! ! i j l i I RO EXAM COMMENTS ) 1 Section 1
)
l Answer 1.03 c. Accept other answers based on motor theory ( (induction motors and Counter Electro Motive Force-CEMF) Answer 1.04 Accept any reasonable answer that discusses ! the Psat/Tsat-power density influence on DNB. Answer 1.07 Also accept NO CHANGE since in EOS-0.2, " Natural Circulation Cooldown", S/G levels are maintained 62% - 72% NR and with this much volume., the RCS wouldn't see a loss of AFW flow. i Section 2 l Answer 2.01 a. Also accept lo-lo level isolation valves l
- b. Also accept 15% RWST level
- c. Also accept MANUAL >
l Answer 2.02 If a wrong answer is given on the HOW - then a ' wrong answer will be given on the WHY. Accept a reasonable WHY ! for a given HOW. Answer 2.04 a.2 1 A1 and 1 A2 may be powered from UT if >15% ! power. 3 & 4 order may be reversed dependent upon time requirements, because the D/G will come on the bus <10 seconds and backfeeding the MT will take >8 hours. . l l Question and Answer 2.04 b Question is misleading in that it asks for "the only 6.9 KV breaker that does not open automatically when i ! another source is paralleled to it". This is misleading in that both l the preferred and the alternate breakers will not auto open if the diesel generator is synchronized to the bus, and the diesel generator breaker will not auto open if either the preferred or alternate source is paralleled to it. Since the question asked for the "only" breaker that had this feature, maximum grader discreation should be used. , 1 l l
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l l j L
l Answer 2.05 a. Containment Air Monitoring Systems do no!. have l any radiation monitors and CAMS has no control functions. CAMS is l l only a H2 monitoring system.
REFERENCE:
CP System Descriptions, Ill-18 of Post Accident Instrumentation System, Section 8.0 l Rev. 01-8410. Accept: NO Ouestion 2.05 e. S/G process radiation system has two subsystems; 1 the S/G blowdown. rad monitor and the S/G sample rad monitor Both of these rad monitors have automatic actions that are different. Blowdown isolates only blowdown but sample isolates sample and : blowdown. Maximum grader discretion required. Answer 2.06 Include valves 8801 A & B - open, S l Answer 2.07 If a wrong answer is given on the TYPE - then l a wrong answer will be given on the OPERATION. Accept a reasonable OPERATION for a given TYPE. Answer 2.08 Accept valve numbers for valve names.
- 1. RHR recirc sump suction valves or 8811
, 2. RHR/RWST suction valves or 8812
- 3. RHR to CVCS isolation (cross-connect) valves or 8804 Section 3 j Answer 3.03 b. OPN16 setpoint is a fixed value of 112%. The penalty for al exists but is zerced and will have no effect on actual !
setpoint. Answer: remain thn same. t
- c. OTN16 is based on To and not Tave. Grader l discretion required based on assumptions made by examinee j Answer 3.06 b. Tech Spec Table 3.3-5 lists the additional signals: j
- Auxiliary Feedwater I
- Station Service Water
- Component Cooling Water l
- Safety Chill Water !
- Emergency Diesel Generator i l
'l t
Answer 3.08 b. IR Permissive Defeat button is called SR Manual Reset.
REFERENCE:
CP SYS VOL 4 SEC lli-1 i Question and Answer 3.12 Request that this answer be dropped l from the examination for the following reasons:
- 1. The question requires the examinee to match the actual reactor trip breaker response to the trip initiator. NO response given in Column B reflects the actual response for b, c, or d. (See attached)
- 2. Initiator b is interlocked at CPSES to prevent occurence. (See attached)
- 3. Initiator e is not applicable at CPSES because there is no manual trip at the Remote Shutdown Panel. 1 l
- 4. Column B choices 1, 4, and 5 are identical in accordance with the I definitions given.
- 5. Terminology used throughout the question was unfamiliar and confusing (i.e. QMCB-A, QMCB-B, PSDA)
- 6. There was some confusion on the use of abbreviations in the question. "RTBs - reactor trip breakers", was apparently interpreted to mean all breakers (including bypass breakers )
by some, while it was interpreted to mean both RTBs (not
- bypasses) by others.
REFERENCES:
CP SYS VOL 4 SEC 111-10 : Drawing 7247D05 Sheet 2 Drawing 7247D05 Sheet 3 Drawing 7247D05 Sheet 8 Ariswer 3.14 PORV-455A will open due to Channel 455 failing high NOT due to the actuation signal of all four pzr pres channels (>2200). Also include all heaters OFF as acceptable answer. Accept final pressure band of 2185 psig to 2335 psig depending on candidates assumptions concerning one PORV relieving all the flow from both centrifugal charging pumps.
l I 4 Trn A/B Manuel Reactor Trip : O , y I Trn A/B Manuel Safety injection ',_/ tgg v> Trn A Auto Reactor Trip t Trn A Auto Safety injection O .
>< j V
Trn A/B Manuel Reactor Trip : D$ j Trn A/B Manuel Safety infection ;j in operate , 52H _ BYB --+ f 52a Closed
< I Sh Closed $$
BYA -+
$<c
" In Operate 5$ !
Trn B Auto Reactor Trip . Trn B Auto Safety injee. tion : G . Trn A/B Manuel Reactor Trip : V o>$ m Trn A/B Manuel Safety injection -
- cr Trn A/B Manuel Reactor Trip JG , tEy V
Trn A/B Manuel Safety injection - ! g ACTUAL RESPONSE FOR COLUMN A INITI ATORS COLUMN B CHOICES l RTA RTB BYA BYB RTA RTB BYA BYB SHTR UV SKTR UV SHTR UV SHTR UV SHTR UV SHTR UV sHTR UV SHTR UV
- e. X X X i. X X X X l
- b. X -OR- X 2. X X X
- c. X X X X X X X X 3. X X X ,
- d. X X X X X X X X 4. X X X X l
- e. N/A FOR CPSES 5. X -- X X X The only initiator whose actual response matches Column B is a. For initiators b, c, and d, no match exists.
@ As shown above, with both reactor trip bypass breakers racked in (in Operate),
two of the three conditions required for a shunt trip are satisfied. In this condition, the closing of either breeker completes the logic and sends a shunt trip to the other breaker. Therefore, initiator b is invalid. 4 i s
I Section 4 l l Answer 4.05 it is acceptable to enter the ERGS on a loss of all ! AC by going straight to ECA-0.0, Answer a or d 4
REFERENCE:
ECA-0.0 B. SYMPTOMS OR ENTRY CONDITIONS l Answer 4.08 Accept other substantiated answers such as l routine Control Rod Exercise required by OPTS l' Answer 4.11 Accept other reasonable answers such as lodine spiking or high background radiation levels ( Answer 4.12 b. Also accept other wording for the panels: ' Hot shutdown panel - Remote shutdown panel Switci, transfer panel - Shutdown transfer panel Answer 4.14 b. EOP-0.0 step 2 does not use control valves to verify turbine trip.
REFERENCE:
EOP-0.0 l l I l I
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l* SRO EXAM COMMENTS Section 5 l I Answer 5.01 See comments on RO exam Answer 1.03 Answer 5.07 (Concept) The question says briefly describe and the answer goes into lengthy detail of describing axial offset. A good brief description of Axial Flux Difference is found in Tech Specs. Also accept: Axial Flux Difference shall be the difference in normalized flux signals between the top and bottom halves of a four section excore . neutron detector. Answer 5.16 a. Also accept other plant responses to reaching the POAH.
- 1. S/G level swell and Hi Deviation Alarms ;
- 2. Pressurizer level deviation Hi Alarms
- 3. Power Range indication coming on scale j 4. Other reasonable plant responses l Question and Answer 5.16 b Request that this portion of the question be dropped from the examination for the following reasons:
- 1. Question refers to intervals and gives no reference as to what these invervals are associated.
- 2. Question is misleading in that it used terminology not used at at CPSES (heating range vs. POAH).
- 3. Answer key does not substantiate that interval two has decreased from a +13 DPM startup rate. ,
- 4. After calculating the SUR for the three intervals, interval 2 i was found to be different than the others. This by itself would not allow the operator to recognize that the reactor )
j had entered the heating range. J Question 5.17 The question is misleading by stating that more than one item in Column 2 may apply. This tends to lead the examinee to look for more than one answer. Maximum grader l discretion required such as answer f. can be answered by 1 or 4. ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ .b
J l l . I o j { l Section 6 Answer 6.01 See comments on RO exam Answer 2.01 Answer 6.02 See comments on RO exam Answer 2.02 Answer 6.05 See comments on RO exam Answer 2.04 i Answer 6.06 See comments of RO exam Answer 2.05 / Point value 6.06 e (2nd part) should be .25 Answer 6.07 See comments on RO exam Answer 3.06 Answer 6.10 See comments on RO exam Answer 3.03 Section 7 Answer 7.01 See comments on RO exam Answer 4.08 Answer 7.06 See comments on RO exam Answer 4.11 i Answer 7.07 See comments on RO exam Answer 4.12 Answer 7.09 b. The operator may proceed with the next step or substep g.t as directed by the RNO step in the ERG (ie. Go to Step ' whatever, which might not be the next step or substep). l Reference EOP-3.0 step 5.b RNO column. ' Answer 7.10 See comments on 90 exam Answer 4.05 Answer 7.11 See comments of RO exam Answer 4.14
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Section 8 'l Answer 8.02.a. Also accept Shift Supervisor's-(SS) office as 'this office is .in the Control Room and is where the key tockers are' ) located. Answer 8.04 b. Also accept Shift ' Supervisor or Assistant Shift I Supervisor, as CPSES' procedures specifically states by who. l Reference . owl-105 step 4.1.9. Answer 8.05 d. Clarification given by Proctor indicated that "RCP ; seal' flow" should be interpreted to, mean seal return floiv. This is l not how Tech Spec defines controlled leakage . Controlled leakage-is seal' flow to RCP seats (seal injection flow). Maximum grader discretion required. Answer 8.10 a. Also accept individual's title in the organization as i the question asked who by title. TSC manager - Manager, Plant Operations , EOF manager - Vice President,- Nuclear Operations l 1 i i
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQUANCHg_ PEAK _1_________ REACTOR TYPE: _ByB-WEQ4________________ DATE ADMINISTERED: _QZZQZZ10___.____________ EXAMINER: _MQQBQBY z _$z_____________ CANDIDATE: INSIBQQI]QN5_IQ_Q8NQ1Q61g1 Use separate paper for the answers. Staple question sheet on top of the answer Write answers on one side only. sheets. Points for each question are indicated in parentheses after the question. The p ass ing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
~ % OF CATEGORY % OF CANDIDATE'S CATEGORY
__VeLUE_ _IQIeL ___SQQ8E___ _yeLQE__ ______________QalgqQ8r_____________ _25tDQ__ _2520Q ___________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW _25200__ _251DQ ___________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS _22 00__ _251W1 ___________ ________ 3. INSTRUMENTS AND CONTROLS _2 5 2 0 0_ _ 2 5 AG1- ________ 4. PROCEDURES - NORNAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL _20&00__ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid. Candidate's S ignature
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I i t I L E . NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Ouring the administrate ion of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may i leave 4 You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil gely to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
S. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Jse only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of gggh section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a ogw page, write goly 90 gag sidg of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
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- 10. Skip at least thrgs lines between each answer.
t j ! 11. Separate answer sheets from pad and place finished answer sheets face ! l down on your desk or table. l
- 12. Use abbreviations only if they are commonly used in facility liigtgtung.
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- 13. The point value for each question is indicated in parentheses after the l I question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the exgmingt only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given ass is t anc e in completing the examination. This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions. j
- c. TurnS in all scrap paper and the balance of the paper that you did-not use for answering the questions. ,
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- d. Leave the examination area, as defined by the examiner. If after ,
leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. 1 l I i
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f 12__EBIUCIELES_9E_UUCLE68_EQWEB_EkeUI_9EEBoIIQUt PAGE 2 ISEBdQQXU6dICSt_BEeI_IBeOSEEB_6dD_ELUID_EL9W l l QUESTION 1.01 ( .50) l Which of the following actions is most likely to cause water hammer ? ] (a) Starting a centrifugal pump with the discharge valve shut 1 (b) Feeding a steam generator with water colder than saturation (c) Placing vacuum breakers on the high peints of water systems (d) Draining a steam generator when it is above 212 F QUESTION 1.02 (1.50) The plant is operating at 100 % power with RCS Tave at 587 F and a steam pressure of 980 ps ig . What must TAVE be changed-to in order to maintain these conditions with 10 % of the tubes l in each steam generator plugged? SHOW ALL WORK, including any applicable formulas. QUESTION 1.03 (2.00) l a. Why does a single RCP pump running during hot shutdown draw more motor , amperage than one of four running at power? (0.5) I l
- b. Why does a RCP running at cold conditions draw more motor amperage than at hot conditions? (0,5)
- c. Why is RCP motor amperage higher when starting the pump than when running? (0,5)
- d. Why should operating a pump with too much flow and no discharge pressure be avoided? (0.5) l QUESTION 1.04 (1.00)
If DNB occurs in the core, WHERE is it most likely to occur, and WHY? (1.0) i (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1 I 11__EBIUCIELES_QE_N99LEeB_E9 WEB _EL6NI_9EEBoIIQNc PAGE 3 j 1 IUEBdQQXNedIGSt_BE61_IBeNSEEB_600_ELUID_ELOW i QUESTION 1.05 (1.50) How are each of the following parameters affected (INCREASE, DECREASE or NO CHANGE) if one main steam isolation valve closes with'the plant at 50% load. Assume all controls are in automatic and that.no trip occurs. 1
- 1. Affected loop steam generator level (INITIAL change only) j
- 2. Affected loop steam generator pressure !
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- 3. Affected loop cold leg temperature ]
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- 4. Unaffected loops steam generator pressure Unaffected loops cold leg temperature I 5.
i i l QUESTION 1.06 (1.50) i Indicate whether the following will cause-the power range instrument to be indicating HIGHER, LOWER or the SAME as actual power, if the instrument has been adj us t ed to 100% based on a calculated calorimetric,
- a. If the feedwater temperature-used in the calorimetric was higher than actual feedwater temperature,
- b. If the reactor coolant pump heat input used in the calorimetric is omitted,
- c. If the steam flow used in the calorimetric was lower'than actual.
QUESTION 1.07 (1.50)
- a. The RCS is des igned to allow and promote natural circulation. What RCS design feature (s). ensures that natural. circulation (NC) will occur?
(0,5)
- b. If, during stable NC cooldown, AFW flow is suddenly stopped, how will NC flow initially repond and why? (1.0) i
(***** CATEGORY'01. CONTINUED ON'NEXT PAGE.*****)
1 I iz__EBINCIELg3_QE_UggLgeB_E9 WEB _EL60I_9EEBoIIQN t PAGE 4 I IBEBb90IUedI93t_UEeI_IB6N$EE8_6NQ_ELVIQ_ELQW . I 1 1 I l QUESTION 't.08 (1.00) l J Explain how it is poss ible to have adequate subcooling indicotton with accurate pressurizer level indication and still form a steam bubble in the vessel head during natural circulation cooldown. (1.0) i t QUESTION 1.09 (1.25) Reactor power is steady at 1000 CPS when sufficient reactivity is added to instantaneously change Keff from 1.0 to 1.001. Describe WHEN (elapsed time) and HOW automatic protective action will occur if there is no subsequent operator action. (1.25) j QUESTION 1.10 (2.25) If reactor power is increased from 50% to 100%, how will DIFFERENTIAL rod worth change (increase, decrease, or remain the same) for the following conditions? Justify your answer. Consider each case separately,
- a. Rod posit ion and boron concentration are held constant, temperature is I allowed to decrease. l
- b. Boron is held constant, rods are withdrawn from 150 steps to maintain temperature constant.
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- c. Rod' position is constant, boron concentration is diluted to maintain i temperature constant, i 1
l 1 I l l I ( I 1 ! (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) I w___-____-___________-____ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _a
Iz__EBIUCIELES_9E_NygLg68_EQWE8_EL681_Q268611QN t PAGE 5 IUEBdQgIUedIG$t_SEoI_I860sEg8_ogg_ELgIg_EL9W QUESTION 1.11 (1.50) Assume the reactor is Xenon free. It then is taken to criticality and the power is raised to 50% at 5%/ min.. If a trip occurs as power reaches 50%, how will the Xenon concentration be trending in the following three situations? Use one of the choices (1-5) below to answer the three questions.
- 1. Increasing towards peak Xenon concentration.
- 2. Increasing towards 100% equilibrium.
- 3. Decreasing toward a dip.
4 Decreasing toward zero percent power equilibrium value.
- 5. At zero percent equilibrium value.
- a. One hour after the trip,
- b. 24 hours after the trip.
- c. If after 8 hours from the trip, the reactor was taken back to criticality and power returned to 50% at 1%/ min. What would be the trend as power reaches 50%?
QUESTION 1.12 ( .50) When performing a reactor S/U to full power that commenced five hours after a trip from full power equilibrium conditions, a 0.5%/ min ramp was used. How would the resulting xenon transient vary if instead a 2%/ min ramp was used?
- a. The Xenon dip for the 2%/ min ramp would occur sooner and the magnitude of the dip would be smaller,
- b. The Xenon dip for the 2%/ min ramp would occur later and the magnitude of the dip would be smaller,
- c. The Xenon dip for the 2%/ min ramp would occur sooner and the magnitude of the dip would be larger,
- d. The Xenon dip for the 2%/ min ramp would occur later and the magnitude of the dip would be larger.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
l I 1 li__EBIUCIELE2_9E_U99LEeB_E0 WEB _ELeUI_9EEBoIIQNi PAGE 6 .] ISEBdQQYN6dlQ$t_BE61_IB6NSEEB_eUQ_ELVIQ_EL9W H l l l l QUESTION 1.13 (1.00) l 1 Which-of the following-statements.concerning the power defect is cor' rect? J l
- a. The' power defect is the difference between the measured power )
coefficient and the predicted power coefficient. j
- b. .The power. defect increases the rod worth requirements necessary.
t'o maintain the desired shutdown margin following a reactor-trip.
- c. Because of the higher boron concentration, the-power defect is more negative at beginning of core life.
- d. The ' power defect necessitates the use'of a ramped Tavg program to maintain an adequate Reactor Coolant System subcooling margin.
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l QUESTION 1.14 ( .50) The reactor is critical at 10,000 cps when a Steam Generator PORV fails l open. Assuming BOL conditions, no rod motion, and no reactor trip, choose ! the answer below that best describes the values of'Tavg and nuclear j power for the resulting new steady state. (POAH = point of adding j heat). J a
- a. Final Tavg greater than initial Tavg, Final power above POAH.
l l b. Final Tavg greater than initial Tavg, Final power at P0AH.
- c. Final Tavg less than initial Tavs, Final power at POAH.
- d. Final Tavg less than initial'Tavg, Final power above POAH. l j
i QUESTION 1.15 (2.50) l For. the following, assume rod control is in manual. Describe the response-(direction of change AND reason) of power <and Tave after 2 minutes of Emergency Boration at: g a .100%. power (1.50)'
- b. 10E-8 Amps. (1.00)
Extend your answer to the restoration of stable conditions. (No numerical-values are required.) NOTE: If power and/or Tave do NOT change, so state = and explain why no change wil'1 occur. (***** CATEGORY U1 CONTINUE 0 ON NEXT PAGE'*****). t 3
r 4 1 I
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4 it__E81NCIELES_9E_UUCLE68_EQWE8_EL6UI_0EE8ellQUt PAGE 7 IUEBUQQ1N6DIC$t_dg61_lB663EgB_60Q_E(glQ_ELQW j l I I l QUESTION 1.16 (1.50) ; Unit 1 is at 90% power with control rods in MANUAL when the turbine is ramped down to 60%. Indicate whether the parameters below will increase, ; decrease or remain the same during both the initial response (first 30 ! seconds of the transient) and after turbine power has stabilized relative i l to the initial conditions. (Assume the following: No changes to boron / xenon j
)
Loop transport time is 10 seconds ! No operator actions) NOTE: No answer required where it is already filled in below. Initial Response Steady State
]
a) S/G Pressure NO ANSWER RQR0 b) Reactor Power NO ANSWER RQRD c) Teold d) Tavg l l QUESTION 1.17 (3.00) For the following situations, indicate whether the final stable power level will be HIGHER, LOWER, or THE SAME as the initial power level. EXPLAIN your answers. Assume the initial power level is at approximately 10 % following a normal reactor startup at the end of life. Consider each situation separately,
- a. Steam dump pressure setting is lowered by 20 psig while in Steam '
Pressure mode. (1.0)
- b. A small (1 %) main steam leak develops inside containment that is insufficient to initiate SI or Containment Spray. (1.0)
- c. RCS boron concentration is increased by 5 ppm. (1.0) l 1
(***** CATEGORY 01 CONTINUE 0 ON NEXT PAGE *****)
Iz__EBIUCIELES_9E_UUGLE68_E9 WEB _EL60I 9EE86IIQUt PAGE 8 IUEBd90106dIGSt_UE6I_IB6HSEEB_600_ELUIQ_ELOW i l i l i i l l i QUESTION 1.18 ( .50) l Choose the correct phrase to correctly complete the sentence. As the core ages, the ratio of PU239 atoms to U235 atoms increases. ! This changing ratio causes the...
- a. reactor period to decrease.
- b. Void Coefficient to become less negative.
l
- c. Moderator Temperature Coefficient to become less negative.
I
- d. delayed neutron fraction to increase. i
.I
{ l l I l l l l l l 1 l (***** END OF CATEGORY G1 *****)
l 21__ELeUI_9E3198_INCLyQIUQ_36EgIl_6UQ_gUgBQEU21_313 igm 3 PAGE 9 QUESTION 2.01 (2.50)
- a. During containment spray operation following receipt of a P signal, what prevents the N2 from the NaOH tank from entering the CSS pump suction? (1,0)
- b. Following CSS actuation, when is sys tem operation shifted from the injection phase to the recirculation phase? (0,5)
- c. What two (2) signals or actions will generate a P signal? (1.0)
QUESTION 2.02 (1.50) The air operator for HCV 182, Charging Flow Control Valve, develops a large air leak. HOW and WHY does the failure of this valve affect RCP seal injectton flow? (1.5) QUESTION 2.03 (3.00) What will te the position (OPEN or SHUT) of each of the valves circled (1 - 6) on the at tached F igur e MF-1 during: (3.0)
- a. Plant startup, reactor at 3%, 1 Main Feed Pump running
- b. Reactor operation at 60% power, both feed pumps operating QUESTION 2.04 (2.50)
- a. Describe the four (4) methods of powering the Safeguards AC Distribution System (leal and 1EA2). Indicate the paths if not direct l and order of preference of sources. (2.0)
, b. What is the only 6.9 KV bus breaker that does not open automatically I when another source is paralleled to it? (0.5) l l l (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
I l 2___ELoNI_gESIGN_IUCLygIgg_geEgIY_ogg_EUEB9ENCY_SYSIEd2 PAGE 10 QUESTION 2.0S (3.00) l For each of the process radiation monitors listed below, state the following: (3.0)
- 1. YES or NO as to whether it generates any automatic actions s when in the tripped condition, and
- 2. If YES in part I above, the automatic action (s) that take place,
- a. Containment Air Monitoring System
- b. Plant Ventilation Stack Monitors
- c. Condenser Off-Gas Monitor
- d. Component Cooling Water Monitor
- e. SG 81owdown Sample Monitor QUESTION 2.06 (3.00)
On figure CVCS-1, circle all components which respond to engineered safeguards actuat ion s ignals. For each, indicate the type of response (start or stop, open or close, etc.) AND the type of ESAS to which it i responds. Assume the CVCS is lined up for normal operation initially.C3.0) l I QUESTION 2.07 (3.00) l l For each of the areas of the plant listed below, describe the type of I permanently installed fire suppression system used in that area. Include i the principle type of fire detector used in the area and what sort of response activation of the detector causes. (3.0)
- a. Startup transformers
- b. Main control room
- c. Auxiliary building d Cable spreading area (excluding rooms 133 and 134) l l
QUESTION 2.08 (2.00) List 4 component interlocks or plant conditions that must be satisfied to l open either of the RHR/RCS suction valves (MOV-8710A/8). (2.0) I ($**** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
O l 21__ELeUI_QESIQU_INGL99189_SoEEIX_6NQ_EUEB9ENCY_3XHIEU$ PAGE 11 i l QUESTION 2.09 (2.00) State three RCP starting duty limitations / requirements. 00 NOT consider RCS conditions or the status of RCP support systems or components. (2.0) QUESTION 2.10 (l.S0) Answer the following TRUE or FALSE. 3
- a. The log ic cabinet controls bank current to the pulser for speed,
- b. The slave cycler generates current orders for its associated power cabinets.
- c. Selecting the individual control bank with the bank selector switch does not override the bank overlap program.
QUESTION 2.11 (1.00) Which one of the following fuel handling tools is pneumatically operated?
- a. New fuel assembly handling tool,
- b. Thimble plug handling tool,
- c. RCCA change fixture,
- d. Burnable Poison rod assembly handling tool.
(***** END OF CATEGORY 02 *****)
2___INSIBudEUIg_6NQ_CQUIBQL2 PAGE 12 i 1 i l 1 l QUESTION 3.01 (1.00) The reactor is in hot shutdown with RCS. pressure at 1775 psig. The reactor trip breakers have been reset and the shutdown banks are full out. I8C maintenance wants to perform a calibration on the Turbine Impulse pressure channels. Explain why this should not be done at t h is time, i l QUESTION 3.02 (1.50) Indicate whether the OTN16 AND OPN16 setpoints will INCREASE, DECREASE, or REMAIN THE SAME if the following parameter changes occur. Consider each change separately. (No explanation required.)
- a. Pressurizer pressure is increased by 100 psig (0,5)
- b. Power range N41 lower detector fails h ig h (0.5)
- c. Tavg is less than full load Tavg with reactor power at 100% (0.5) l QUESTION 3.03 (2.00) l Indicate whether the following situations will ARM ONLY, ARM AND ACTUATE, or HAVE NO EFFECT on the steam dump system. (Assume condenser interlock C-9 is met.) (2.0) 1
- a. Turbine trip, Tavg = 557 degrees F, steam dumps in Tavg mode,
- b. 80% power, 7.5%/ min. ramp decrease in turbine load for 3 minutes, l Tavg > Tref by 6 degrees F, steam dumps in Tavg mode of operation. l l
- c. Hot zero power, Tavg = 559 degrees F, steam dumps in STM PRESS mode l with 1092 psig set into the steam pressure controller. j
- d. 50% power, 9% step load increase, Tavg < Tref by 5 degrees F, steam dumps in Tavg mode of operation.
l l l I i l l (***** CATEGORY 03 CONTINUE 0 ON NEXT PAGE *****)
l 3t__INSIBudEUIS_600_998IBQLS PAGE 13 l l
. QUESTION 3.04 (2.50) l l
Find five (5) examples of improper plant or system response in the l following scenario: (2.5) The plant is operating at 75% power when an instrument technician mistakenly removes two (2) level transmitters on the same SG from service by isolating-the transmitters and opening the equalizing' valves. The ] resulting indicated low level in the steam generator causes a reactor trip, l Main Feedwater pumps trip, and all three (3) Auxiliary Feedwater pumps j start. The. turbine driven AFP receives.a low lube oil pressure alarm, then j trips on loss of lube oil. Motor driven AFP flow continues to the-affected SG until the MDAFPs trip on 2/4-high SG 1evel.
\ k QUESTION 3.05 (1.50)
List and briefly describe three different trip signals which could initiate a reactor protective function based on RCS flow conditions. Coincidence and setpoints are NOT required. ( 1. 5 )- l QUESTION 3,06 (2.00) L a. For EACH of the following two cases, state YES or NO as to whether.the reactor will trip in response to a simultaneous failure low of both IR channels. Justify each answer. (1.5)
- 1) Reactor startup in progress and at 5%-power l 2) The reactor is at 20% steady state power i
l b. Assume the reactor is at 100% power when one IR channel' fails high,
- followed immediately by a reactor trip (from other causes). What additional action will have to be taken during emergency procedures to ensure proper operation of the NI system? (0.5)
QUESTION 3.07 (1.00)
.l What components would be automatically operated if ONE'of the two 17%.
bistables in the Pressurizer Level Control circuit. failed low /off? IDENTICAL PARALLEL COMPONENTS COUNT AS ONLY ONE COMPONENT.
.i
(***** CATEGORY 03 CONTINUE 0 ON NEXT PAGE *****) I
l 32__INSIBUUEUIS_oNQ_G96IB0L3 PAGE 14 l i I l QUESTION 3.08 (1.00)
- a. During a normal rod withdrawal, you notice that only every other d ig it al rod position light is illuminating for ONE of the rods as it travels. What would cause this indication? (0.5)
State the accuracy of the affected rod's digital rod position ! b. indication system. (Either of the two poss ible accuracies constitutes a correct answer.) (0.5) i 3.09 ( .50) ! QUESTION i The THREE input s ig n a ls to the Steam Generator Feedwater Controller are: l
- a. Tavg, compensated feed flow, uncompensated steam flow,
- b. Feed flow, compensated steam flow, water level error.
- c. Compensated feed flow, water level, compensated steam flow, j
- d. Uncompensated feed flow, compensated steam flow, water level.
(***** CATEGORY 03 CONTINUE 0 ON NEXT PAGE *****)
i l l 21__IUSIBudEUIS_AUQ_GQNIBQL3 PAGE 15
]
l l l l l QUFSTION 3.10 ( .50) j i Match the actual reactor trip breaker response of column 8 to the reactor I trip initiators in column A. Not all of column 8 answers will be used. Column 8 answers may be used more than once. (RT8s = reactor trip l breakers, RTA or RT8 = reactor trip breaker A or 8, BYA or BY8 = bypass reactor trip breaker A or 8). (0,5) Column A Column 8
- a. H1 pressurizer level train A 1. UV trip of all RT8s l Shunt trip of all RT8s b - e deleted
- 2. UV trip of RTA & BYB Shunt trip of RTA
- 3. UV trip of RTA Shunt trip of RTA & BYA l
- 4. UV trip of all RTBs j Shunt trip of RTA & RTB j l
S. UV trip of RTA & RT8 Shunt trip of all RT8s l QUESTION 3.11 (2.00) l I For each of the f ollowing s ituat ions determine whether the rod control interlocks should prevent outward rod motion. For those conditions where outward rod motion is prevented, explain what actions must be taken to reestablish outward rod motion. Assume rod control is in manual. Consider each case separately,
- a. An intermediate range nuclear instrument fails high during a plant startup with reactor power at 10%.
- b. A power range nuclear instrument fails high during a plant startup with reactor power at 60%.
- c. The turbine first stage impulse pressure transmitter fails low during a plant startup with reactor power at 20%.
- d. Simultaneously Loop 1 Th f ails high and Loop 1 Tc fails low while operating at 100% power,
(***** CATEGORY 03 CONTINUE 0 ON NEXT PAGE *****)
O 32__INSIBudENI$_60Q_CQUIBQL3 PAGE 16 QUESTION 3.12 (2.00) The reector is at 100% power with all control systems in automatic; and the controlling PRESSURIZER PRESSURE channel (Channel 455) fails.high. Describe the plant response to the new steady state condition (include any RPS/ESF signals that will be generated, and the final approximate RCS pressure). Setpoints are not required. Assume no operator action. (2.0) QUESTION 3.13 (3.00) What is the INITIAL response of the Rod Control System (RODS IN, ROOS OUT, or NO CHANGE) and BRIEFLY EXPLAIN why the change will or will not occur for the following instrument failures. Assume that the plant is at 50% load with all systems controlling in automatic,
- a. Loop 2 Cold Leg RTO fails LOW. (1.0)
- b. Turbine Impulse Pressure (PT-505) fails LOW. (1.0)
{'
- c. Power Range lower detector (NI-44) fails HIGH. (1.0) i QUESTION 3.14 (2.50)
- a. The CPSES Unit I reactor underwent SI actuation due to a spuricusly generated S signal. As a result of following the E0P's, SI has been reset, and the SI pumps have been stopped and placed in AUTO. At this point, will a valid S s ignal star t the SI pumps? Justify your l answer. (1.0)
- b. What are six s ig na ls (other than SI) generated by an S signal? (1.5)
(***** END OF CATEGORY 03 *****) - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ u
. i l
4t__BBQQEQUBES_:_UQBdebt_6000806Lt_EMEBGENQX_6UQ PAGE 17 BeQIQLQQIQ8L_QQUIBQL i i ! QUESTION 4.01 (2.00) , i I The plant is operating at 100% power with all control systems in automatic. Annunciator "RCP 2 UP BRG L/0 RSVR LVL Hi/Lo" alarms. According to ABN-101A, " Reactor Coolant Pump Trip / Malfunction," the first initial operator actions are to monitor RCP motor bearing temperatures on the j affected pump and notify the TUS00 Dispatcher. What are the other i required initial operator actions if the affected RCP bearing tempera- l tures exceed: (2.0) l
- a. 190 deg F
- b. 195 deg F l
1 QUESTION 4.02 (2.00) i List the six (6) Critical Safety Functions in order from highest to 1 l lowest priority. (2.0) I l QUESTION 4.03 (2.00) Briefly desc r ibe how each of the following valves are verified to be in their proper position per OWI-106, " Guideline on Component Position Verification."
- a. Normally open valves
- b. Normally closed valves
- c. Locked open valves
- d. Control valves (motor, air, solenoid, or hydraulicc11y operated)
(***** CATEGORY 04 CONTINUE 0 ON NEXT PAGE *****)
$1__EBQQEQUBg3_ _NQBd6Lt_6@UQBd6Lt_EdEBQEUQ1_6UQ PAGE 18.
S6019L99108L_G9BIBOL QUESTION 4.04 (2.50) In accordance with the IP0s for plant startup and operations, place the l items listed below in the proper sequence in which they occur during a l power ascent. (2.5) l
- a. Perform a secondary calorimetric, I
- b. Roll the main turbirc.
i
- c. Start a main feed pump'. l l
- d. Synchronize to the grid, s
)
- e. Place rod control in automatic.
l
- f. Place main feedwater control valtas to automatic. !
l
>/ \
l QUESTION 4.05 (1.00) , I l With the unit at 100% reactor power, a loss of offsite powe- occurs. l This transient trips the main turbine which in turn causes a reactor l trip. All emergency diesel genera: tors fail to start. (1.0) To what procedural point do you proceed first? ;
- a. ECA 0.0, Loss of all A/C power. 3
- b. ECA 0.1, Loss of All A/C power recovery without SI required,
- c. E0P-1.0, Loss of Reactor or Secondary Coolant,j ,
- d. E0P-0.0, Reactor Trip o r. Sa,fety s Inj ect ion. N ws u
% 0 QUESTION 4.06 (1.00) , 1' 's , ,
Why is there a precautionary note in ECA-0.0, Loss of All A/C Power, to MONITOR the CSF Status Trees for INFORMATION ONLY, but not'for purposes of implementation? , (1.0)
, l
! (***** CATEGORY 04CONTINUEDONNEXT[/ AGE *****) .
, g. ,
t 'd .
'st__EBQ' QEQUBES_:_NQBdeLi_6900BdeLt_EUEBQENQ1_6NQ- PAGE. 19 B6010LQQIQ8LiGQUIBQL.
I 1
. QUESTION 4.07 (3.00)
JA Econdition. arises which' requires entry into containment.while critical at j 40% power. The: operator entering.will receive a whole body dose of 40 ' mrem. Data _is.available on the following persons:- (3.0) _ Candidate 1 2 3 4 Sex male male- female male Age 27 38 24 20 l Wk/ exposure ~ 35: mrem 280 mrem. O mrem 30 mrem j Qtr/ exposure 1230 mrem 970 mrem '280 mrem 1120 mrem i Life exposure - 54730 mrem 5200 mrem 9770 mrem Remarks history -
'4 months -
H unavailable pregnant ) l Each candidate is technically competent and phys ically- capable of per f orm- i ing the task. Emergency. limits do not apply but time. constraints do not . permit obtaining authorization for an exposure limit increase. For'each l person indicate if that person could or could not be selected to perform ! the task based on exposure requirements only and j ustif y (explain) your response. QUESTION 4.08- (1.50) l Minimum control rod motion is desired when operating at constant high ' power conditions to minimize flux oscillations. What are three (3) ,
. purposes or times when routine control rod motion (non-emergency) should l be utilized? (1.5)
QUESTION 4.09 (1.00) Attachment'1, Surveillance Prior to Entering Mode 2, to IPO-002A, Plant Startup from Hot Standby to Minimum Load, is not required to be completed
-prior to startup if WHAT TWO (2) conditions are met?. (1.0) l QUESTION ~ 4.10 '(1.00)
A minimum of 2 RCPs should be running during plant cooldown. . Which-pump (s) should be operated during cool'down and why this (those) particular (1.0) pumps? L . .
*****)
.(***** CATEGORY 04.CONTINUEDo0N NEXT PAGE ,
I.
i
-. 1 l
l 41__BB00EQUBES_:_NQBd6Lt_6@NQBd6Lt_EUEBQEUQX_6NQ PAGE 20 i l 86019L991G6L_QQNIBQL l I I
)
l I QUESTION 4.11 (1.00) The reactor is operating at 100% power when a Gross Failed Fuel Monitor, 1RE-406 (FFL-260) ALERT alarm is received. A sample indicates that fuel failure has not occurred. What are two (2) other poss ible causes of the alarm (operational causes, not instrument malfunction). (1.0). 4 QUESTION 4.12 (2.00) Heavy smoke in the control room prompts the Shift Supervisor to order the j control room evacuated. (2.0) i
- a. What initial operator action (s) should be taken prior to evacuating i the control room? l
- b. Where do the Shift Supervisor, Reactor Operator, and Relief Reactor operator proceed to?
i I QUESTION 4.13 (2.50) Fuel Handling activities are in progress when the SRO in charge of fuel handling reports to the control room that a fuel bundle has been dropped l into the refueling canal in containment. What initial actions should be performed? (2.5) , 1 [ QUESTION 4.14 (1.50) List all of the immediate action substeps from E0P-0.0, Reactor Trip or i Safety I nj ec t io n, that allow you to accomplish the following immediate f action steps: (1.5) ! a. Verify reactor trip l b. Verify turbine trip
- c. Verify AFW flow and proper valve alignment l
l (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
-___-____-__w
Ss__880EEQU862_:_U98086t_8BU98d86t_EdgBQENCY_6NQ PAGE 21 ! 86019L99108L_CONIB9L
)
QUESTION 4.15 (1.00)- ! TRUE or FALSE, A Steam Generator with a ruptured' tube is classified as a faulted Steam Generator per the E0Ps. (1.0) I i i l i I I l l l l l l (***** 04 *****) END OF CATEGORY- - _ . _ _ _ _ _ _ _
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flRC LICENSE EXN11HATION HNiDOUT EQUATIONS, CO ISTANTS, NiD C0HVERSIONS 6 = m*Cp *deltaT 6=U*A*deltaT P = Po*10 sur*(t) P = P *et /T SUR = 26/T T = 1*/p + (p-p)/X p T=1/(p-p) T = (p-p)/X p p = (Keff-1)/Keff = deltaKeff/Keff p = 1+/TXeff + perf/(1+ AT) . 2, = in2/tg = 0.693/tg K = 0.1 seconds ~I
\
I = Io*e "* CR = S/(1-Keff) 2 l R/hr = 6*CE/d feet { l Water Parameters 1 gallon = 8.345 lbm = 3.87 liters I 1 ft3 = 7.48 gallons Density @ STP = 62.4 lbm /ft3 = 1 gm/cm3 Heat of vaporization = 970 Btu /lbm' Heat of fusion = 144 Btu /lbm
~
1 atmosphere = 14.7 psia = 29.9 inches Hg. Miscellaneous Conversions 1 curie = 3.7 x 10tv disintegrations per second 1 kilogram = 2.21 lbm l 1 horsepower = 2.54 x 103 Btu /hr
.1 mw = 3.41 x 106 Btu /hr 1 inch = 2.54 centimeters
' degrees F = 9/5 degrees C + 32 l degrees C = 5/9 (degrees F - 32) 1 Stu = 778 ft-lbf L
L -- >
11__EBIN01ELES_9E_UUGLE68_E99EB_EL6MI_9EEBoIIQUt PAGE 22 IBEBdQQXUedICSt_UE6I_IBeOSEEB_eUR_ELUIQ_EL9W ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCOR0RY, S. ANSWER 1.01 ( .50) (B) REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 193006 K1.04 3.4/3.6 193006K104 ...(KA'S) ANSWER 1.02 (1.50) S/G heat transfer = Q = UA(Tavg - Tstm) , Q,U, and Tstm remain constant; A1(Tavg1 - Tstm) = A2(Tavg2 - Tstm) (0.5) Given: A2 = 0.9 x Al From Steam Tables: Tsat for 995 psia = 544 F (0.5) A1(587 - 544) = 0.9A1(Tavg2 - 544) Tavg2 = 591.8 F (591 to 592.5 F acceptable) (0.5) REFERENCE CP Thermal-Hydraulic Principles, Chapter 12 - 8 Steam tables K/A 193005 K1.03 2.5/2.6 193005K103 ...(KA'S)
'e 1
11__EBIUCIELES_9E_ NUCLE 88_E99EB_EL68I_9EEB6IIQUt PAGE .23 , IBEBUQQXUedIC$t_UEoI_IB69SEEB_6NQ_ELQ1Q_ELQW j i
- l. ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S.
l l l f ANSWER 1.03 (2.00)
- a. A single pump running has a higher flow than when all 4 are operating (due to reduced discharge pressure) so more work is done and more amperage drawn. (ACCEPT CONCEPT FOR ALL PARTS) (0.5)
Also accept same reason as in part b.
- b. At cold conditions, fluid density is higher, so more mass is moved so more work is done and more emperage drawn. (0.5)
- c. It must accelerate more mass, which requires more work, and amps.(0.5) f
- d. Operating at runout may cause pump damage / trip on overcurrent. (0.5)
REFERENCE EQB WEC4 GENERIC R1 & HTFF K/A 191004 K1.07 2.9/2.9 K1.09 2.4/2.5 K1.12 2.5/2.7 191004K107 191004K109 191004K112 ...(KA'S) l i ANSWER 1.04 (1.00) DNB is most likely to occur where power density is high (0.25) and l temperature is approaching Tsat (0.25). This is most likely to occur in i I the upper half (6~9 feet up the core) &/OR center of the core (0.5). (1.0) y l REFERENCE EQB WEC4 GENERIC RT K/A 193008 K1.05 3.4/3.6 l 193008K105 ...(KA'S) I l I ANSWER 1.05 (1.50) l 1 l 1. Decrease
- 2. Increase l 3. Increase
- 4. Decrease
! 5. Decrease (0.30 each) J l REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 002000 K5.11 4.0/4.2 l l L-_--____-__-.-__-___--_-__--._-_.---.__-_______-__--___--__ _ - - - . . _ _ _ _ .J
t W 11__EBINQIELES_QE_ NUCLEAR POWEB_EL6NI_QEE86119Nt PAGE 24 IHEBdQQXUedIQSt _UgeI_IB6BSEEB_6ND.ELUlQ_ELQW- , 1 l
.' ANSWERS - ; COMANCHE PEAKT1 -87/07/13-MCCRORY, S.
002000K511 ...(KA'3) R 1
' ANSWER 1.06' (1.50)- H H
- a. Lower '(+.5 ea)-
.b. Higher i
- c. Lower REFERENCE ]
EQB.WEC4 GENERIC RT &.HTFF
'K/A 193007 K1.08'3.1/3.4 193007K108' ....(KA'S) d 1
1 ANSWER 1.07 (1.50)
- a. The heat sink must be at a higher elevation than the' heat' source.(0.5)
- b. Initially, NC flow will-be reduced'(0.2).due to less cold feed water entering the S/G causing less heat removal,(0.2) which causes higher. ,
RCS temperatures in the U-tubes-and reduces the thermal d r. iv ing - he ad (temperature difference between U-tubes and core) (0.6) REFERENCE EQB WEC4 GENERIC RT & HTFF j K/A 002000 K5.1~3 3.3/3.6 q K5.16 3.5/4.0 i K/A 193000 K1.21 3.9/4.2* ] K1.23 3.9/4.1 002000K513 002000K516 192008K121 193008K123 ...(KA'S) j 4 ANSWER 1.08 (1.00) Ouring nat. cire. cooldown, bypass flow . is minimal (0.25). Therefore,'the I water'in the upper head is decoupled frm the cooldown of'the'RCS (0.25).- z 1 When this occurs, water (& metal)-in the upper head may stay warm enough to flash to steam when the RCS'is depressurized, even.though the bulk ' j temperatures in the RCS are cool (0.5). (CONCEPT) '(1.0) .l REFERENCE EQB WEC4 GENERIC.RT & HTFF K/A 193008 K1.20 2.9/2.9' 193008K120 ...(KA'S) n
H It__EBIN91ELES_9E_UUGLE68_E0VEB_EL6NI_QEEB6IIQNt PAGE- 25 ISEBd90INedIGSt_UE6I_IB60SEEB_6NQ_ELUID_ELQW
-87/07/13-MCCRORY, S. I ANSWERS -- COMANCHE PEAK 1 l l
l l .1 ANSWER 1.09 (1.25) l Power is too low to meet requirements of P-6 (0.25), therefore the source i l range scram is in effect and will occur at 10 (ES) CPS. (0.5) l 1. Reactivity ~ change in keff or 1- Keff/Keff = .001/1.001 = 0.001 l l 2. Period = .007 - .001/0,1(0.001) = 60 seconds
- 1. Ln P/Po = t/T = Ln 100 =t/60 l
- 4. Time before trip occurs ~ 276 seconds (Accept any answer between 3 1/2 and 6 minutes if viable correct concept is used to evaluate j dnswer.) (0.5)
REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 012000 K4.02 3.9/4.3 K/A 192003 K1.09 2.3/2.3 012000K402 192003K109 ...(KA'S) ANSWER 1.10 (2.25)
- a. Decrease (0.25 for direction, 0.50 for justification)
Lower temperature increases the density thus reducing.the number of neutrons available for capture by the rods. I i
- b. Decrease f There is less flux available for interaction as the rods move towards )
the top of the core
- c. Increase Decrease boron concentration increases the number of neutrons available for interaction with the rods. ,
i REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 192005 K1.07 2.5/2.8 ; 192005K107 ...(KA'S) l i i I
l It__EBIUCIELES_DE_U9CLEoB_EQWEB_ELoNI_9EEBoIIQUt PAGE 26 IBEBd90YU6d10St_UE61_IB86SEEB_oGR_EL91R_EL9W 1 i ANSWERS -- COMANCHE. PEAK 1 -87/07/13-MCCRORY, S. - I l i l ANSWER 1.11 (1.50)
- a. (1) Increasing towards peak Xenon concentration, j
- b. (4) Decreasing toward zero percent power equilibrium value,
- c. (3) Decreasing toward a dip. (0.5 ea.)
REFERENCE EQB WEC4 GENERIC RT & HTFF l K/A 192006 K1.10 3.1/3.2 j 192006K110 ...(KA'S) ANSWER 1.12 ( .50) c
]
REFERENCE j EQB WEC4 GENERIC RT & HTFF ] K/A 192006 K1.10 3.1/3.2 l l 192006K110 ...(KA'S) ;
/
ANSWER 1.13 (1.00)
- 1 b
REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 192004 K1.08 3.1/3.1 192004K108 ...(KA'S) l ANSWER 1.14 ( .50) d. REFERENCE EQL WEC4 GENERIC RT & HTFF K/A 192008 K1.21 3.6/3.8 192008K121 ...(KA'S) l l
. i . 1 1
It__EBJNCIELES_9E_NUQLE68_EQWE8_EL6NI_QEE861]QN t PAGE 27 l IHEB000XNedICSt_BE6I_IB6NSEEB_oUD_EL91R_EL9W l l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. , ANSWER 1.15 (2.50) I
- a. Power decraases initially (0.25] due to the negative reactivity of the boron addition (0.25). The primary to secondary mismatch (0.25) causes Tave to decrease (0.25). The decrease in Tave inserts positive reactivity (0.25) and restores power to slighly lower than or the same as initial power (0.25).
- b. Tave is determined by the amount of pump heat and the steam dump pressure setting (0.25] thus it does not change (0.25). After the initial transient, power decreases (0.25] Cat a -1/3 OPM rate) to the i multiplied source level [0.25). i REFERENCE EQ8 WEC4 GENERIC RT & HTFF K/A 192008 K1.20 3.8/3.9 192008K120 ...(KA'S) l ANSWER 1.16 (1.50) a) increase; (no answer) (+.25 ea response) f b) (no ans); decrease l c) increase; increase l d) increase; increase j l
j REFERENCE EQB WEC4 GENERIC RT & HTFF K/A 002000 K5.11 4.0/4.2 l 002000K511 ...(KA'S) l 1 i l 1 i l i i l 1 1
i
, i l
1 lt__EBIUCIELE2_QE_NQQLg68_EQWEB_EL6NI_QEgB6110N t PAGE 28 IBEBdQQ1N6d193t_dg61_IB6N$Eg8_63Q_ELylQ_ELQW ! l l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. ] l \
)
i I ANSWER 1.17 (3.00)
- a. HIGHER (0.50) steam dump pressure setting decrease causes RCS temperature to decrease. MTC and FTC both add positive reactivity to increase power. (0.50)
- b. THE SAME (0.50) the steam dump system will compensate for steam leak by shutting valves to maintain demanded steam generator pressure. (0.50) (HIGHER if steam dumps initially closed)
- c. LOWER (0.50) the negative reactivity will cause power and TAVE to decrease. Steam dumps will reduce steam flow to maintain a constant steam pressure. MTC and FTC will add positive reactivity to offset .
boration. (0.50) (REMAIN THE SAME if steam dumps initially closed) I REFERENCE j CP Thermal-Hydraulic Principles, Chapter 12 - 27 j K/A 002000 K5,11 4.0/4.2 3 002000K511 ...(KA'S) j l
)i ANSWER 1.18 ( .50) 1 a.
REFERENCE , i EQB WEC4 GENERIC RT & HTFF l X/A 192003 K1.06 3.2/3.3 192003K106 ...(KA'S) l l 1
Ii L. I 2___EL6NI_DE2196_INCLUDIN9_S6EEIX_6ND_EUEB9ENCy_S11IENS PAGE 29 , 1 ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. f I l ANSWER 2.01 (2.50) ~j i
- a. The NaOH tank isolation valves shut on a NaOH tank low level (1.0)
- b. RWST EMPTY alarm (0.5) of 15%
- c. Hi 3 containment pressure (18.35 psig) (0.5) 2/2 pushbuttons on main control board (0.5) or manual. j
- REFERENCE Containment Spray System Description, II-10.13, 14 K/A 026000 K4.01 4.2/4.'3 0009 3.6/3.6 !
0260000009 026000K401 ...(KA'S) { a ANSWER 2.02 (1.50) l The large air leak will cause the valve to fail open (0,5). RCP seal l injection flow will decrease (0.5) due to the reduced backpressure from HCV-182 (0.5). REFERENCE i CVCS Description, II-2.19, 27 K/A 004000 K1.04 3.4/3.8 004000K104 ...(KA'S) ANSWER 2.03 (3.00)
- a. 1 - shut b. 1 - open i I
2 - open 2 - shut 3 - open 3 - shut l 4 - shut 4- open { 5 - shut 5 - shut j 6 - shut 6 - open (12 at 0.25 each) REFERENCE Main Feedwater System Description, VIII-7.23 l K/A 059000 K1.02 3.4*/3.4 061000 K1.02 3.4/3.7 059000K102 061000K102 ...(KA'S) I I l
l a ! l l PAGE 30 21__ELeUI_QESION_INCLUDIU9_SoEEIl_600_EUE80ENQ1_SYSIEUS l l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. t f i ANSWER 2.04 (2.50) }
}
- a. 1. 345 KV S/U transformer XST2 (0.25) :
- 2. 138 KV S/U transformer XST1 (0.25') via 1A1 and 1A2 (0.25) l
- 3. 345 KV main transformer (0.25) via aux UT (0.25) via 1A1 and i 1A2 (0.25)
- 4. 0/G (0.25)
Voltages and transformer numbers not required as long as grader can determine path. (0.25 for order) I b, diesel generator breaker (0.5) ! REFERENCE AC Distr ibution System Description, VII-1, Section 3.4 K/A 062000 K4.06 2.g*/3.3* , K1.02 4.1/4.4 062000K102 062000K406 ...(KA'S) l ANSWER 2.05 (3.00) ; 1
- a. YES (0.25). Containment ventilation isolation occurs (0.25). !
f i
- b. YES (0.25). Auto closure of gas release valve in waste gas processing j l system (0.25), Control room ventilation isolates (0.25). {
I
- c. NO (0.5)
- d. NO (0.5) j
- e. YES (0.25). Automatic closure of isolation valves in blowdown (0.25) i and sample lines (0.25).
REFERENCE ; Radiation Monitoring System Descriptions, XIII-18, section 4.1.a l K/A 073000 K4.01 4.0/4.3 l 073000K401 ...(KA'S) i 1
2 __EL6UI_DESIQU_INGLLJDIUD_S6EEIX_6UD_EdEBQEUGl_SISIEd$ PAGE 31 ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. ANSWER 2,06 (3.00) SEE FIGURE CVCS-1
- 1. 8160 - close, T (cont, iso, phase A) 10. 8511A - open, S
- 2. 8152 - close, T 11. 85118 - open, S
- 3. 1128 - close, S (safety inj ec t ion) 12. CCP01 - start, S j l 4. 1120 - close, S 13. CCP02 - start, S j
- 5. 1120 - open, S 14. 8105 -'close,.S
- 6. 112E - open, S 15. 8106 - close, S l 7. PDP - stop, S 16. 8100 - close, S
- 8. 8110 - close, S 17, 8112 - close, S
- 9. 8111 - close, S 18. 8801A - open, S
- 19. 88018 - open, S ;
(0.158 each numbered item) f REFERENCE CP NUC SYS CVCS, II-2 004000K404 004000K405 ...(KA'S) [ l
\
l k ! I l l l l l l l l t . _ _ _ _ _ _ _ _ - i
! *6 m,
&d 0-
. t:
- d. . )
*T*
g ...
=
--A-cs%_: - !a %. - Q2 ' )- . ci t
=
f; _ *j 'g -f
, !9 :) I 7
i 5 *~ m 4 A i, ! I 's l ~ E* ,X: ~ 5 l t. 4\ M i--- QX 4 , i ;p " b \g g. X X i o s r
;g-w w A =" -
.c ..
=
a 8 b 08 1 j i,3,r-$ >. ~ i - f' g o-
$- 4
!t m! ~ =+6
$-u $
-u =
- W .
L --- ,-e-5s ! g g I 3 lh. I g [h. h. , se =X 4 E9 +R 4>s
!4>4-xx a: >
se E g-c*.i+Ei
. i
! Eo s r- @#1 %Ts - i i, eW. a 2
=
b, d - 4: 4
; {
1 i m e
- } - -
5 : S, e 4 g gg E g e e 5 ) j N ( ~~~
--x -
4 i v" ! > _ EE j
'34 ~_ '
g a 1 [88 E- A' di l 2 " s I 3 g,_ {@ se = as - s e-
- Ild g #
8 4 9 s. ~ - j 1g--!i _ n a
. -3 l
d M3 Na dB w - i 1 1 t
._ _ v. .
- i WOX! 45 5 5 "$ 1 I s !
d8! i N x 2
$ 5
- : e' er a.d =
is r_ s= M 0 :l. l -7 l r ' a
- =,, 2 1
= e _ .s l 4_ d 2 $U -
2 + ' l i E-
= C g ;:: .
4 -l B a w m l , so. - 1
. m
~_ _ , ,
as a.es -- .> l
. sen e a <
l c
- l s Ldt__EL601_DE3100_INGL901NQ_S6EEll_600_EUEBDEUGl_312IEdS' PAGE 32 l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S.
I 1 I l y
- ANSWER 2.07 (3.00) j i .
0 ( a. Deluge water spray system (0.15) - dry piping'in the protected space 4 with open nozzles.CO.15) ' Water - is admitted to the piping through a ; deluge valve located outside the protected space and operated either ! manually _or automatically (0.15) Thermal. detectors are used in the space to detect the. fire. (0.15) The system is automatically initiated by the detector when a fire is sensed. (0.15) ;
- b. Preaction sprinkler system (0.15) - dry piping in the protected space having sprinkler nozzles with. fusible links.(0.15) Water is admitted through a deluge valve which only operated manually,(0.15) Thermal OR ionization detectors are used to sense the presence of fire.(0.15)
When a detector is activated, it generates an alarm only.(0.15) (The fusible links melt at preset temperatures.to admit water to affected areas of the protected space only.)
- c. Wet pipe sprinkler system (0.15) - wet (pressurized) piping system in the protected space with f us ible link (or liquid filled glass insert) sprinkler nozzles.(0.3) Water is admitted to the affected area in the space when the temperature reaches the melting point of the f us ible link (or the glass insert breaks).(0.15) The system uses a flow device to detect activation of a sprinkler nozzle and activate a remote alarm (0.15)
- d. Halon system (0.15) - dry piping system with open nozzles.CO.15) !
Halon gas is admitted through a block / isolation valve (located in the ; i dischar ge manif old) between the main and reserve' banks (a bank is four l l Halon bottles) and the distr ibution piping. (0.15) Ion detectors are ; used to sense fires (0.15) and will initiate remote alarms and aut omat ic a lly (delayed) initiate Halon discharge (0.15) into the ! affected space. Accepted explanation for preaction system for,this area. I REFERENCE l CP SYS VOL 3 SEC IX-11 086000K403 086000K604 ...(KA'S) 1 ANSWER 2,08 (2.00) ; 1
- 1. RHR recirc sump suction valves (8811) closed
- 2. RHR/RWST suction valves (8812) closed 1
- 3. RHR to CVCS isolation (cross connect) valve (8804) closed
- 4. RCS pressure <364 psig (on PT-405) ,
(0.5 each) jl l 1
I r I___EL6NI_DESIQU_IUCL901NQ_36EEIX_6NQ_ENE8QEUCX_1111EU$ PAGE 33 ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. l l l REFERENCE CP SYS VOL i SEC II-6.13 005000K407 ...(KA'S) l ANSWER 2.09 (2.00) l
- 1. Limited to 3 starts during 2 hour period with 30 min, idle period H before each restart. (0.667) l
- 2. If 3 starts (attempted starts) are made w/1 2 hours, the pump must be j allowed to idle for 1 hour before a fourth attempt is nade. (0.667) 1
- 3. Only one RCP is to be started at any one time. (0.666) !
(0.5 each) j l REFERENCE l CP ATTACHMENT 1 TO EOS-0.2 ! l 003000K614 ...(KA*S) f l l ANSWER 2.10 (1.50)
~
l
- a. TRUE (0.5 each)
! b. TRUE t c. FALSE REFERENCE CP SYS VOL 4 SEC III-3 001000K403 ...(KA'S) ANSWER 2,11 (1.00) c. REFERENCE l CP SYS VOL 3 SEC X-1 ( 034000K601 ...(KA'S) l l l
ht__IU$IBUUEUI$_AUQ_QQUIBQL$ PAGE 34 ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. ) I l I i { ANSWER 3.01 (1.00) Placing in test will deenergize the inter lock circuit P-13 which feeds P-7. (0,5) This will unblock the low pressurizer pressure trip function which will result in a reactor protection actuation. Shutdown rods will drop. (0,5) REFERENCE Instrument Failure Analysis, Table IFA-1 Solid State Reactor Protect 9n System Description, III-9.25, 27 K/A 012000 K4.01 3.7/4.0 012000K401 ...(KA'S) ANSWER 3.02 (1.50) OTN16 OPN16
- a. increase remain the same i b, decrease remain the same l c. increase remain the same (0.25 ea)
REFERENCE RCS Temperature and N16 Power System Description, III-5.4, 5, 6 K/A 010000 K1.01 3.9/4.1 K/A 012000 K4.03 2.3/2.7* l K/A 015000 K1.01 4.1/4.2 l 010000K101 012000K403 015000K101 ...(KA'S) ANSWER 3.03 (2.00)
- a. Arm only (0,5)
- b. Arm and Actuate (0.25 each)
- c. Arm and Actuate (0.25 each)
- d. No effect (0.5)
REFERENCE Steam Dump System Description, III-7.3, 4, 8, 9 K/A 041020 K4.17 3.7/3.9 041020 K4.11 2.8/3.1 041020 K4.14 2.5*/2.8* 041020K411 041020K414 041020K417 ...(KA'S)
i i
? #- q . t 5t__INSIB9dENI$_6NQ_ggNIBQL$ PAGE 35 ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. ,
l l ANSWER 3.04 (2.50)
- 1. indicated level would increase due to 0 dp j j
- 2. MFW pumps do not trip on low level l
- 3. TDAFWP doesn't start on low level in 1/4 SG
- 4. TOAFWP doesn't trip on low oil pressure {
- 5. MDAFPs don't trip on high SG level (0.5 each)
I REFERENCE Main FW System Description, VIII-7.13 l AFW System Description, VIII-8.10, 11, 14 K/A 061000 K4.07 3.1*/3.3* A3.01 4.2/4.2 590 OK4 06 b0 A3b 061000K407 ...(KA'S) j , i i i l ANSWER 3.05 (1.50) j
- 1. Low flow trip - generated from loop flow detectors (dp type)
- 2. RCP undervoltage trip - senses RCP bus voltage and initiates a trip singnal on low voltage. )
- 3. RCP Underfrequency trip - senses frequency on RCP buses and initiates a trip s ignal on low frequency.
(0.5 each) )
)
REFERENCE j CP SYS VOL 4 SEC III-9.16 012000K402 ...(KA'S) { i , i l i l l l l
I ) I bz__lUSIBgMEUIg_66Q_C9dI89LS PAGE 36 l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. ANSWER 3.06 (2.00)
- a. 1) YES. [0.25] P -6 drops out( because IR < 10 E-10 amps) (0.25) and SR NI reenergizes causing a level trip s ig na l (0.25)
- 2) NO , [0.25) P-10 is in effect (0.25) which will prevent the SR from reenergizing even though P-6 has dropped out.CO.25) 1 l
1
- b. Will need to depress the IR Permissive Defeat button (with power <10%)
to reactivate the SR high voltage and thus get Source Range indication. [0,50) REFERENCE CP SYS VOL 4 SEC III-1 K/A 015000 K3.01 3.9/4.3 015000K301 ...(KA'S) a i ANSWER 3.07 (1.00) i All pressurizer heaters (are deenergized).[.50) l One letdown isolation valvel.25] shuts l All orifice isolation valvesC.25) (shut). (1.0) l REFERENCE CP SYS VOL4 SEC III-6.7 t 011000K301 011000K302 '011000K303 ...(KA'S) { l I I l l l i l _____-______A
r 5t__INSIBudENIS_6UQ_CQNIBQLS PAGE 37 l ANSWERS - COMANCHE PEAK-1 -87/07/13-MCCRORY, S. , l 1 l
- ANSWER 3.08 (1.00) l i l a. Data A or 8 failure j l
or . Parity error in A or 8 data
- i or j Failure of A or 8 DRPI coils (or associated cabling). (0.5)- 1 l
- b. +10/-4 or +4/-10. (0.5)
REFERENCE CP SYS VOL4 SEC III-4 014000K601 ...(KA'S) 8 I ANSWER 3.09 ( .50) b. REFERENCE f CP SYS VOL4 SEC III.8 J K/A 035010 K4.01 3.6/3.8 035010K401 ...(KA'S) , j
-{
ANSWER 3.10 ( .50) ! I
- a. 2 (0.5) b-e deleted l l
REFERENCE : CP SYS VOL 4 SEC III-9 012000K103 012000K603 ...(KA'S) l l j 1 i 0
i
. l d
\
$___INSIBUDENIS_600_G08IBQLS PAGE 38 I 4
ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. 1 i q 1 l ANSWER 3.11 (2.00) { i
- c. Rod motion is prevented (0.50) 1 I
Block 01 signal (NOTE: acceptable No effect if C-1 blocked)
- b. Rod motion is prevented (0.50) !
Position Rod stop bypass switch or trip the PR bistables
- c. No effect (0.50)
- d. No effect (0.50) i l REFERENCE !
CP SYS VOL 4 SEC III-3
- 012000K610 ...(KA'S) l l
l l ANSWER 0.12 (2 00) j i 1 One PORV (PCV 455A) will open (0.30) When actual plant pres decreases towards setpoint (2200 psia), the functioning pzr press channels will.cause the PORV to close (0.30) l Both spray valves will modulate full open (0.30) l Reactor trip on low pressurizer pressure (0.30) l Pressure will continue to decrease until safety injection initiates (0.30) As SI continues, the pzr will eventually go solid and cause pressure I to raise to the PORV setpoint (0.25) Pressure steady state pressure would be slightly > 2200 psia (0.25) i REFERENCE CP SYS VOL 4 SEC IV-3 K/A 0160003.01 3.4*/3.6* l 016000K301 . .(KA'S) l i i r
nd
,. t o
~5t__IUSIBOMENIS_6ND_G9NIBQLS 1PAGE 139 j
~
ANSWERS.-- COMANCHE PEAK 1- -87/07/13-MCCR0RY, S.~ j j
'l ANSWER 3.13- (3.00)' !
i
~
- a. N0' CHANGE-(0.5). Results in a low loop Tavg, Rod Control utilizes <
a Auct ionee r e'd H igh. T avg . (0. 5 ) ..
- b. : RODS-IN'(0.5).
Pimp will generate a minimum. Tref, s-large-temperature error will cause rods to insert (0.25) Power rate. "1 mismatch will also cause-rods to' insert (0.25).
- c. RODS IN (0.5). Nuclear power > turbine power (mismatch), rods in to compensate for anticipated high Tavg ( 0,5 ) . -
REFERENCE
-Rod Control System' Description, III-3.11, 12 K/A 001000 K4.03 3.5/3.8 j 001000K403 ...(KA'S)
ANSWER 3.14 (2.50) 1
- a. No (0.25). The reset sequence blocks all automatic actuationTsignals until the P-4 signal has been reset by closing the. reactor' trip breakers (0.75). q i
l- b. - Feedwater isolation ! - Reactor trip i Auxiliary FW start I ! - Control Room emergency recirculation ]
- Phase A containment isolation j
- Containment ventilation isolation 1
- Station SW start
- Emergency diesels start 1 (6 at 0.25 each)
REFERENCE Introduction to ESF,.II-7.21, Table ESF-1, Figure 100-8 4 K/A 013000 K1.01 4.2/4.4 013000 K4.01 3.9/4.3 013000K101 013000K401 ...(KA'S) , Y 9 I
- I
( 4t__EBQQEDLJBES_:_NQBU6Lt_eBNQBdebt_EdE8QgNQX_68Q PAGE 40 l BoDIQLQQIQoL_QQUIBQL l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. l l-ANSWER 4.01 (2.00)
- a. - initiate load reduction to 45% (0.5) ,
- verify P-8 on (0.5) j
- b. - if > 48% power, manually trip reactor (0.5) )
- secure the affected RCP (0.5)
REFERENCE ABN 101A, RCP Trip / Malfunction, Rev 1, pg 4, 5 ; X/A 000015 G010 3.4/3.4 j 000015G010 ...(KA'S) i ANSWER 4.02 (2.00) i S- Suberiticality \ C- Core Cooling l H - Heat Sink P- Integrity Z - Containment I' l I - Inventory l (6 at 0.2 each, 0.16 for each manipulation to put in correct order) y REFERENCE J Westinghouse ERGS 1 l K/A 000029 0012 4.1*/4.2* j 000029G012 ...(KA'S) 'l J ANSWER 4.03 (2.00) 1 l l
- a. Move the valve a small amount in the closed direction, then reopen. l l
- b. Attempt to move the valve in the closed direction.
l
- c. Remove the lock ing device, move the valve a small amount in the l closed direction, then reopen.
- d. Visually inspect locally, or use remote position indication if local inspection is not available. Verify power to .the valve.
(0.5 each) l REFERENCE l OWI-106, Guideline on Component Pos it ion Ver if ic at ion, Rev.1, pg 6-7 l l K/A 194001 K1.01 3.6/3.6 , l l l l l l L
I l
. q l . i
- . t l 4. PROCEQURES - NQBU6Lt_A8NORMALc_EME80ENCY AND PAGE'941 l 86010LQGIGoL_QQN189L , j l i i
ANSWERS -- COMANCHE PEAK 1 -87/07/13-MC,CRORY, S. s 194001K101 ...(KA'S) i 1 i l , l' ANSWER 4.04 (2.50) i 1 t a
- 1. c l 2. b '
l 3. d x
- 4. e or f i
- 5. f or e . l b.5 or each manipulation required to put in correct order, 5 max)
REFERENCE l j IP0-002A, Plant Startup from Hot Standby to Minimum Load, Rev 2 IP0-003A, Power Operations, Rev 0 K/A 194001 Al-02 4.1*/3.9 3 194001A102 ...(KA'S) l I i d ! ANSWER 4.05 (1.00) t l L l d (1.0) also accepted a . i REFERENCE E0P-0.0, Reactor Trip or Safety Inj ect ion, Rev 2 1 K/A 194001 A1.02 4.1*/3.9 l 000007 G011 4.1*/4.3 . 000007G011 194001A102 . . . (K A 'S ) 1 ANSWER 4.06 (1.00) l Because none of the electrically powered safeguards equipment used to l restore Critical Safety Functions is operable (1.01 (none of the FRG's can be implemented) 4 REFERENCE Westinghouse User's Guide for ERG's, p. 17/18 ) s K/A 000055 EK3.02 4.3/4.6 ' 1 000055K302 ...(KA'S) , i l [
.i
[: l \ < , '. ____..._____w
*i D 'd.. ,
y
,, > . a t- o
+
h__EBQCEDUBg3 - NORMALi_e@Ng806L1, gdg8QgNQL6NQ n PAGE 42 86919LQ9196L GQNI30L- ' g
< .? n ANSWERS.-- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. A r-4o Y ."\
J 1.'
, }t
,s . f,s .
- ( 8 ]1 ANSWER 4.07 (3.00) 4 4
can'didate #1: rejected-(0.25) since he has no history on' file and will exceed 1.25 REM /QTR whole body exposure (0,5)- , candidate #2: rej ected -(0 .5) s i n c e l,h4 will e . ed-theweek1[11mitof 300 mr em who le body w i;t,, gout . Rad Pr ot ec t ion Su?e rv. iso r 's .i approval (0.5,) sy candidate #3: rejected (0.25) since she will exceed 300 mrem whole body during the term of her pregnancy (Od) t i
,.4 C candidate #4: accepted (0.25) since he will Mbt exceed the adminilimi't.of 300 mrem /wk(0.25) or the~whole body limit o f :1.'26 ' REM /Q TR
(.25) S REFERENCE i 'M Radiation Worker Training pg 11-12. K/A 194001 K1.03 2.8/3.4 '(w57, 194001K103 ...(KA'S) ,;
' I f ' -
.\T i l' 'y
,/ 4 ANSWER 4.08 (1.50)T ,
g f 3 -
..w
-l 4
- to force AFD to the t arget va lue d6r ing powe'r'.T.eh, D changes - (0. 5); .,.
, \ ' .'
- to maintain AFD at tho target value during r,edt.d.e dg . powe r op er' at ions ' ( 0. 5 ) .
a
- to dampen axial xenon oscillations.(0 7 5 ), , : %. 1- B ,
also accepterd r od e xce r c is ing pe r st.t vrr d lance' :s test ing;')
'l REFERENCE r 1 i',4 O ,
IP0-003A, Power Operations, RA)v 0, pg-3 K/A 001000 K5.06 3.8/4.1 l~ 001010 K5.34 3.2/4.1 ' 001000K506 001010K534 ...(KA'S) ,
't %
ANSWER 4.09 (1.00) ,
- Control Rod withdrawal is started within 24 hours of l as t i t'r ip ! ( 0. 5 )
\
.w
- RCS temperature has been > or = 551 F since-the trip (0,5).
( .,i
9
.51__EB99gDUBgS_:_UQBdekt_esNgBdett_gegBggugy_eNQ PAGE 43 f BeQI9L901 gel _CQUIB9L ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S.
REFERENCE IPO-002A. Plant Startup from Hot Standby to Minimum Load, Rev 2, Attach 1 K/A 19- A1.02 4.1*/3.9 194001A102 ...(KA'S) x, s ! P .. i
' ANSWER 4.10 (1.00)
'One of the 2 RCPs should be 1 or 4 (0.5) to provide pressurizer spray
'flou.(0.5).
REFERENCE IP9-005A, Plant Snu t<Jow n from Hot Standby to Cold Shutdown, Rev 2, pg 10 ! K/A 002000 K1.09 4.1/4.1 002000K109 ...(KA'S) l ANSWER 4.11 (1.00)
- CVCS vixed bed demineralized resin depletion (0,5) ,
l
- Crud burst (0,5) also accepted high background radiation RE F E 9t:NC E ABN-192A, High Reactor Coolant Activity, Rev 1, pg 3 ,
K/A 000076 EK1.06 2.1/2.6 i EA2.07 2.4*/2.7* 000076A207 000076K106 ...(KA'S) l l ANSWER 4.12 (2.00) a, trip the reactor (0,5)
- b. SS - Hot Shutdown Panel (0.5)
RO - Hot Shutdown Panel (0.5) RR0 - Switch Transfer Panel (0.5) REFERENCE : A3N 905A, Loss of Cont 31 Room Habitability, Rev 0, pg 2 K/A 000068 G010 4.1*/4.2* 000068G010 ...(KA'S)
]
, 1 l '
- I n
et__EBQGED9853 - NORMALt_ABN9Bd6Lt_EUEBQENQX_eNQ PAGE 44 86010L991066_G00189L l ANSWERS -- COMANCHE PEAK 1 -87/07/13-MCCRORY, S. I [ I i ANSWER 4.13 (2.50) 1
- Notify Rad Protection
- Actuate containment evacuation alarm
- Ensure containment purge and exhaust are isolated'
- Ensure containment preaccess filter units are in operation j
- Notify set ty to ensure no access is permitted into the affected area. l (5 at 0.5 e4 j 1
L REFERENCE A8N-908, Fuel Handling Accidents, Rev 0, pg 2, 3 l i K/A 000036 G010 3.7/3.8 l 000006G010 ...(KA'S) j l ! l i i ANSWER 4.14 (1.50)
- a. Rod bottom lights on Reactor trip breakers open Neutron flux decreasing
- b. All turbine stop valves closed
- c. AFW total flow > 470 gpm FW split flow bypass valve closed (6 at 0.25 each)
REFERENCE E0P-0.0, Reactor Trip or Safety Inj ec t ion, Rev 2, pg 4, 7 K/A 194001 A1.02 4.1*/3.9 194001A102 ...(KA'S) i t ANSWER 4.15 (1.00) i False (1.0) REFERENCE 3 E0P-0.0, Reactor Trip or Safety Inj ect ion, Rev 2, p-) 10- f K/A 000040 EA2.03 4.6/4.7 { 000040A203 000040G012 ...CKA'S) ! 1
'., i 8
4 I i U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQdeUQUE_EgeK_1_________ l REACTOR TYPE: _EW8:WEge________________ DATE ADMINISTERED: _HZZQZZ1G________________ EXAMINER: _QBAYES t _Q2______________ l CANDIDATE: _________________________ l ! IULIBUQIl0U5_IQ_QeUQ10eIEi Use separate paper for the answers. Write answers on one side only. l Staple question sheet on top of the answer sheets. Points for each ; question are indicated in parentheses after the question. The passing ! grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF ;
CATEGORY % OF CANDIDATE'S CATEGORY l __Ve6UE_ _IQIek ___LQQBE___ _VeLUE__ ______________QoIEGQBI_____________ 1 _252QQ__ _25200 ___________ ________ S. THEORY OF NUCLEAR POWER PLANT l CPERATION, FLUIDS, AND l THERMODYNAMICS . 1 1 _251QQ__ _251QQ ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, 1 AND INSTRUMENTATION _251Q0__ _2510Q ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL _25199__ _25199 ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS ADQt00__ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature
l
- i NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Ouring the administration of. this examination the following rules apply:
1
- 1. . Cheating on the examination means an automatic denial of.your application and could result in more severe penalties.
)
- 2. Restroom trips are to'be imited and only one candidate at a time may.
leave. .You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or. dark pencil gnly to. facilitate. legible reproductions.
- 4. Print ~your name in the blank provided on'the cover sheet of the examination.
(
- 5. Fill in the date on the cover sheet of the examination (if necessary). .I
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of gach section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as p
appropriate, start each category on a ogg page, write 2012 20 202 Eidg of the paper, and write "Last Page" on the last answer sheet. 1
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least iht gg lines between each answer. .
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility liigtgiung. l
- 13. The point value for each question is indicated in parentheses after the question and cen be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer j to mathematical problems whether indicated in the question or not. i
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the gxgm1Dgt only. .q
)
- 17. You must sign the statement on the cover sheet that' indicates that. the l work is your own and you have not received or been given assistance in ]
completing the examination. This must be done after the examination has -) been completed, j
i o j i I l l i ! 18. When you complete your examination, you shall:
- a. Assemble your examination as follows*
(1) Exam questions on top. ) (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer,
- b. Turn in your copy of the examination and all pages used to answer 1 the examination questions. l
- c. Turn in all sc r ap paper and the balance of the paper that you diu ,
not use for answering the questions. ! {
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. j
{.
)
l 1 i l l l l l 1 l l l . L__---__.--.-_.-------- - - . - - - - - - - _ - j
- (
$___IBE981_9E_NygLg68_EQWEB_EL6NI_QEgBellQNt_ELy1QSt_68Q PAGE 2 IBE~nd90106dICS QUESTION 5.01 (2.00)
- a. Why does a single RCP pump running during hot shutdown draw more motor amperage than one of four running at power? (0.5)
- b. Why does a RCP running at cold conditions draw more motor amperage than at hot conditions? (0.5)
- c. Why is RCP motor amperage higher when starting the pump than when running? (0,5) d, Why should operating a pump with too much flow and no discharge pressure be avoided? (0,5)
QUESTION 5.02 (1.50) Indicate whether the following will cause the power range instrument to be indicating HIGHER, LOWER or the SAME as actual power, if the instrument has been adj us ted to 100% based on a calculated calorimetric. (1.5)
- a. If the feedwater temper ure used in the calorimetric was higher than actual feedwater tempera.ure. ,
i
- b. If the reactor coolant pump heat input used in the calorimetric is omitted.
- c. If the feed flow used in the calorimetric was lower than' actual. j i
QUESTION 5.03 (1.00) Explain how it is possible to have adequate subcooling indication with accurate pressurizer level indication and still form a steam bubble in the vessel head during natural circulation cooldown. (1,0) l l l l i l i (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) i
l
'.* 1 5___IBE981_9E_NQQLg68_EQWE8_EL681_QEg8611QUt_ELQ10$t_6NQ PAGE 3 l
ISEBdQQ18601G2 l i QUESTION 5.04 (1.00) A temperature instrument with an out of date calibration sticker on it is reading 450 deg F. A recently calibrated pressure gage sensing in the same I area indicates 390 ps ig. Is the temperature instrument reading accurately (within + or - 2 deg F)? If not, how close is it reading to the actual temperature? Assume the system is under saturated conditions. SHOW ALL WORK. (1.0) l I QUESTION 5.05 (2.00) ! 1
\ /
FLOW ----> 1 2 3 1 ___________/ \___________ ; 1
- a. Describe the relationship (>, <, or =) between points 1, 2, and 3 on the above ventur.1 flow element for the following parameters (assume the *luid is inc omp r ess ib le, constant temperature, and no friction loss occurs): (1.5)
- 1. Mass flow rate ;
i l
- 2. Pressure
- 3. Fluid velocity
- b. How would the above change if fluid friction is considered (as in an actual system)? WHAT . HAPPENED to the energy (account for the energy change)? (0.5)
]
l l 1 l i (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) 1
~
5
$t__IBE981_9E_ NUCLE 68_E9 WEB _EL6NI 9EEB61196t_ELVIQ2A_6NQ PAGE 4 !
IBEBd90186dICS 1 5.06 I QUESTION (2.00) i Will the Departure from Nucleate Boiling Ratio (DNBR) INCREASE, DECREASE, I or REMAIN THE SAME if the following plant parameters INCREASE during power ! j operation? Consider each parameter independently.
- a. RCS pressure (0,5) j l '
- b. RCS temperature (0.5)
- c. RCS flow (0.5)
- d. Reactor power (0.5)
, l l l 1 l QUESTION 5.07 (2.00) I l What two (2) power distribution limits are used to ensure the power ! I distribution shape in the core is acceptable? BRIEFLY describe how each l is determined and in which direction (AXIALLY or RADIALLY) each ensures ) I acceptable power distr ibut ion. (2.0) QUESTION 5.08 (2.50) i 1 How are each of the following parameters affected (INCREASE, DECREASE i I or NO CHANGE) if cne main steam isolation valve closes with the plant at 50% load. Assume all controls are in automatic and that no trip l occurs. (2.5)
- 1. Affected loop steam generator level (INITIAL change only)
- 2. Affected loop steam generator pressure
- 3. Affected loop cold leg temperature
- 4. Unaffected loops steam generator pressure
- 5. Unaffected loops cold leg t empt.r at u r e
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
- 5. THEORY _QE_UQQLE68_EQWEB_EL6UI_QEE861190t_ELylgSt_6NQ PAGE 5 IBEBd901660193 l
i QUESTION 5.09 ( .50) During a reactor startup, an initial reactivity addition causes count rate to increase from 20 CPS to 40 CPG. A second reactivity addition causes the count rate to increase from 40 CPS to 80 CPS. Which of the following statements is correct? (0.5)
- a. The first reactivity addition was smaller,
- b. The second reactivity addition was smaller.
- c. The first and second reactivity additions were equal,
- d. There is insufficient data g iven to determine relationship of reactivity values.
QUESTION 5.10 (1.50) l Assume the reactor is Xenon free. It then is taken to criticality and the power is raised to 50% at 5%/ min.. If a trip occurs as power reaches 50%, how will the Xenon concentration be trending in the following three s it uat ions ? (1.5) Use one of the choices (1-5) below to answer the three questions.
- 1. Increasing towards peak Xenon concentration. ;
- 2. Inc r eas ing towards 100% equilibrium.
- 3. Decreasing toward a dip.
- 4. Decreasing toward zero . percent power equilibrium value.
- 5. At zero percent equilibrium value,
- a. One hour after the trip,
- b. 24 hours after the trip.
- c. If after 8 hours from the trip, the reactor was taken back to c r it ic a lity and power returned to 50% at 1%/ min. What would be the trend as power reaches 50%? ,
)
I 1 I
)
1 (***** CATEGORY 05 CONTINUE 0 ON NEXT PAGE *****)
a.
- l 51__IME981_DE_U99 leo 8_E9WE8_EbeNI_QEE8611QN t_ELQ1QS t_6NQ PAGE 6 i
IHEBdQQ1N6dIQ3 , i I l l QUESTION 5.11 ( .50) I When performing a reactor S/U to full power that commenced five hours I after a trip from full power equilibrium conditions, a 0.5%/ min ramp i was used. How would the resulting xenon trans ient vary if instead a f 2%/ min ramp was used? (0.5) l l
- a. The Xenon dip for the 2%/ min ramp would occur sooner and l the magnitude of the dip would be smaller, l
l b. The Xenon dip for the 2%/ min ramp would occur later and the magnitude of the dip would be smaller. 4 i
- c. The Xenon dip for the 2%/ min ramp would occur sooner and the magnitude of the dip would be larger, l
- d. The Xenon dip for the 2%/ min ramp would occur later and the magnitude of the dip would be larger.
QUESTION 5.12 ( .50) l The reactor is cr itical at 10,000 cps when a Steam Generator PORV fails i open. Assuming 80L conditions, no rod 1otion, and no reactor trip, choose ) the answer below that best describes the values of Tavg and nuclear power for the resulting new steady state. (P0AH = point of adding heat). ; J
- a. Final Tavg greater than initial Tavg, Final power above POAH, b, Final Tavg greater than initial Tavg, Final power at POAH.
- c. Final Tavg less than initial Tavg, Final power at P0AH.
- d. Final Tavg less than initial Tavg, Final power above POAH.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
l
'51__IBE9BX_QE_NygLg68_EQWg8_EL6NI_QEg86119Nt_ELVIQ$t_6NQ PAGE 7 l ISE800RXUedICS :
l l I l 1 l QUESTION 5.13 (2.50) For the following, assume rod control is in manual. Describe the response (direction of change AND reason) of power and Tave j after 2 minutes of Emergency Boration at. i
- a. 100% power (1.5)
- b. 10E-8 Amps (1.0) l' Extend your answer to the restoration of stable conditions. (No numerical values are required.) NOTE: If power and/or Tave do NOT change, so state and explain why no change will occur.
i QUESTION 5.14 (1.50) Unit 1 is at 90% power with control rods in MANUAL when the turbine is ramped down to 60%. Indicate whether the parameters below will increase, decrease or remain the same during both the initial response (first 30 seconds of'the tr ans ient) and after turbine power has stabilized relative to the initial conditions. (Assume the following: No changes to boron / xenon Loop transport time is 10 seconds No operator actions) NOTE: No answer required where it is stready filled in below. In.itial Response Steady State a) S/G Pressure NO ANSWER RQR0 t b) Reactor Power NO ANSWER RQR0 c) Teold i d) Tavg I 1 I I ($**** CATEGORY 05 CONTINUE 0 ON NEXT.PAGE *****) , i
PAGE 8 32__IDE981_9E_U99LEoB_20 WEB _EL6NI_QEE861198t_EL91Q$t_600 IBEBdQDYUedIG3 l 1 QUESTION 5.15 ( .50) 1 Choose the phrase to correctly complete the sentence. As the core ages, the ratio of PU239 atoms to U235 atoms increases. (0,5) This changing ratio causes the...
- a. reactor SUR to increase for a given +ok change
- b. Void Coef f ic ient to become less negative. l
- c. Moderator Temperature Coefficient to become less negative.
- d. delayed neutron fraction to increase.
QUESTION 5.16 (1.50) The reactor is taken CRITICAL and a +1/3 DPM SUR is established.
- a. From control room nuclear instrumentation, how can the operator tell when the heating range has been reached (2 required)?
(Rod position and boron concentration are held constant) (0.5) 4
- b. In which of the following intervals was the heating range entered? (1.03 (1) Interval 1 - reactor power increased by a factor of 6 in 143.3 seconds (2) Interval 2 - teactor power increased by a factor of 3 in 99.0 seconds (3) Interval 3 - reactor power increased by a factor of 5 in 128.8 seconds.
1 l i l l l l , (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) 1 _ _ _ . --_a
l .'
'5___IBE98Y_9E_UUGLEoB_E9 WEB _EL6UI_9EEBoI196t_ELU192t_8NQ PAGE 9 IUEBdQ91N6diQ$
1 i I i l QUESTION 5.17 (2.00) Match each of the items in column 1 to the short definitions in column 2? More than one item in Column 2 may apply. (2.0) COLUMN 1 COLUMN 2 ; l a. fast neutrons 1. high energy neutrons (>l.0 MeV) l
- b. activity 2. always occur indirectly from fission through f iss io n
- c. delayed neutrons (average) fragment daughter decay
- d. reactivity 3. fractional change in neutron
! population per generation l e, slow neutrons
- 4. always occur directly from
- f. prompt neutrons the fission reaction
- 5. low energy neutrons (<0.63 cV)
- 6. number of disintegrations per ,
unit time of a radioisotope i 1 1 i (***** END OF CATEGORY 05 *****) l 1
. , 1 PAGE 10 l
61__ELo81_SYSIEMS_DESIQut_CONIBQLt_o89_INSIBUSEUIoIJQN 1 I QUESTION 6.01. (2.50)
- a. During containment spray. operation following receipt of a P s ignal, what' prevents the N2 from.the NaOH1 tank from entering the CSS pump suction? (1. 0 3 -
- b. Following CSS actuation, when is system operation shif ted from the ,
injection. phase to the rec irculation phase? _(0,5) l
- c. What two (2) signals or actions w il'. gene r ate a P signal? (1.0) i l
I QUESTION 6.02 (1.50) l The air operator for. HCV 182, Charging Flow Control Valve, develops a large 4 air leak. HOW and WHY.does the failure of this valve affect RCP seal l l inj ect ion flow? (1.5) j l J i I QUESTION 6.03 (3.00) What w.ill be the position (OPEN or SHUT) of each of the valves circled (1 - 6) on the att ached Figure MF-1 dur ing: (3.0)
\
l I
~
a, Plant startup, reactor at 3%, 1 Matn Feed Pump running-
- b. Reactor operation at 60% power, both feed pumps operating QUESTION 6.04 (2.50)
Find five (5) examples of improper plant or system response in the following scenario: (2.5)
-The plant is operating at 75% power when an instrument technician mistakenly removes two'(2) level transmitters on the same-SG from; service by isolating the transmitters.and' opening the equalizing' valves, zThe
.resulting indicated low level in the-steam generator causes a reactor. trip, Main Feedwater pumps trip, and all three (3). Auxiliary Feedwater pumps start, The turbine driven AFP receives a low lube oil pressure! alarm, then trips on. loss'of lube oil. Motor driven AFP flow continues to the affected-SG until the MOAFPs trip on 2/4 high SG 1evel. ,
l 4 l (***** CATEGORY 06 CONTINUED ON NEXTLPAGE *****)
6 1 l 8 1 2
/ -
g F - _ r 9 b 4 5C 2 _ T E O Y 1 E 2 T E N _ R V- O A F N
.; DPM y D
.D P. A HM NLE OPT C MS EAY SSS /,
Wp@ wV g g [i s E _ H 3 C V8 O E1 P2 F - V F q~ D _ / D - A N C . - O L m M I T W N E G
- I H
_ O A L S AA
- R C E T S
R . I O SM P. IH F - R A H OY E E P R L D C F N _ N N O _ F A I F _ E I O O C O H R I I _ T L O S E TG - A A S LL AO U W V S O L O* _ N O g E WF wT C ISR _ A L R T F
- M
- O N A 2 _ B C 1 [I _ R E S S A S 1 E S N G I T V L E T A E P Y B A P Y B O T N A A H B E , - L U V N E R P W O L N O T O N G E O R F I T R I T E T A I D A T L L E L A E P O E O WV S S A _ B S L I _ F. I DA DE D T O EV T V D E E E E S E FS F N _ 1 R E ,S ,E F F E F E _ S / V VA VV8L V,V SP E VL V S A L - T O RA FV F I PY SA FB FV FV I
- _ N . . . . .
1 2 3 4 5
l ht__ELeUI_3X$IEUS_QESIQUt_99 BIB 9Lt_669_INSIBubEUI6IIQU PAGE 11 i i l QUESTION 6.05 (2.50)
- a. Describe the four (4) methods of powering the Safeguards AC Distribution System (1EA1 and 1EA2). Indicate the paths if not direct ;
and order of preference of sources. (2.0)
- b. What is the only 6.9 KV bus breaker that does not open automatically when another source is paralleled to it? (0,5) l l
l QUESTION 6.06 (2.50) , i For each of the process radiation monitors listed below, state the f o i l.ow ing : (2.5) l 1. YES or NO as to whether it generates any automatic actions when in the tripped condition, and l
- 2. If YES in part 1 above, the automatic action (s) that take place.
- s. Containment Air Monitoring System
- b. Plant Ventilation Stack Monitors
- c. Condenser Off-Gas Monitcr
- d. Component Cooling Water Monitor
- e. SG Blowdown Sample Monitor QUESTION 6.07 (2,50)
- a. The CPSES Unit i reactor underwent SI actuation due to a spuriously j generated S signal. As a result of following the E0P's, SI has been l reset, and the SI pumps have been stopped and placed in AUTO. At this peint, will a valid S signal start the SI pumps? Justify your !
answer. (1,0) l
- b. What are six signals (other than SI) generated by an S signal? (1.5) !
l I l i l l l l (***** CATEGORY 06 CONTINUE 0 ON NEXT PAGE *****) '
1 6t__PL6UI_312IEd3_QE3108t_CQUIBQLt_6NQ_10$IBLJUEUI61198 PAGE 12 QUESTION 6.08 (3.00) l What is the INITIAL response of the Rod Control System (RODS IN, ROOS OUT ! I or NO CHANGE) and BRIEFLY EXPLAIN why the change will or will not occur for the following instrument failures. Assume that the' plant is at 50% load with all systems controlling in automatic, I
- a. Loop 2 Cold Leg RTD fails LOW. (1.0)
- b. Turbine Impulse Pressure (PT-505) fails LOW. (1.0) )
1
- c. Power Range lower detector (NI-44) fails HIGH. ( 1. 0 ')
l i i QUESTION 6.09 (1.50) _ The reactor is in hot shutdown with RCS pressure at 1775 psig. The reactor trip breakers have been reset and the shutdown banks are full out. You are the SRO and I & C maintenance wants to perform a calibration on the Turbine Impulse pressure c ha nne ls . Explain why you would allow /not allow him to do this. QUESTION 6.10 (1-.50) Indicate whether the OTN16 AND OPN16 setpoints will INCREASE, DECREASE, 1 or REMAIN THE SAME if the following parameter changes occur. Consider ) each change separately. (No explanation required.)
- a. Pressurizer pressure is increased by 100 psig (0.5) i
- b. ,
Power range N41 lower detector fails high (0,5)
- c. Tavg is less than full load Tavg with reactor power at 100% (0,5)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) l l
d Sz__EL6NI_313 Igd 3_QE31QN_QQNIBQLt_66Q_IU$1800gNI6119N t PAGE 13 I ; 4 QUESTION 6.11 (2.00) Indicate whether the following situations will ARM ONLY, ARM AND ACTUATE, or HAVE NO EFFECT on the steam dump system. (Assume condenser interlock. _C-9 is met . ) (2.0)
- a. Turbine trip, Tavs = 557 degrees F, steam dumps in Tavg mode.
l L b.. 80% power, 7.5%/ min. ramp decrease in turbine load for 3 minutes, Tavg > Tref by 6 degrees F, steam dumps in Tavg mode of operation. t l c. Hot zero power, Tavg = 559 degrees F, steam dumps in STM PRESS mode with 1092 psig set into the steam pressure controller. i
- d. 50% power, 9% step load increase, Tavg < Tref by 5 degrees F, steam dumps in Tavg mode of operation.
i l l l I 4 1 i i i i (***** END OF CATEGORY 06 *****) u_____-_-_. _ _ _ _ _ _ _ _ _ -
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4 Z1__EB99EQUBES_:_U9Bdelt_6BUQBdeLt_EdEBGEUGX_600 PAGE 14 1 B6010L90106L_00UI80L l l l l QUESTION 7.01 (1.50) Minimum control rod motion is desired when operating at constant high power conditions to minimize flux oscillations. What are three (3) purposes or times when routine control rod motion (non-emergency) should be utilized? (1.5) 1 I i QUESTION 7.02 (2.00) During reactor startup and operation, Engineering Support should be i notified if any of several reactivity anomalies occur. List four- (4) (2.0) I i ! QUESTION 7.03 (1.00) Attachment 1, Surveillance Prior to Entering Mode 2, to IP0-002A, Plant ] Startup from Hot Standby to Minimum Load, is not required to be completed j prior to startup if WHAT TWO (2) conditions are met? (1.0) i l l QUESTION 7.04 (1.00) ] 1 A minimum of 2 RCPs should be running during plant cooldown. Which pump (s) ] should be operated during cooldown and why this (those) particular (1.0) pumps? l l l j f I l l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
., l
'Z2_ _ E B 00 E Q U B E S _: _ N Q B U6 L t _6 @ N Q B U6 L t _ E U E B Q E N G Y _6 U Q PAGE 15 B6DIQL99106L_G9dIB9L QUESTION 7.05 (2.50)
In accordance with the IP0s for plant startup and operations, place the j items listed below in the proper sequence in which they occur during a i power ascent. (2.5) l I a. Perform a secondary calorimetric. i
- b. Roll the main turbine.
- c. Start a main feed pump.
, o
- d. Synchronize to the grid. ;
l l [ l e. Place rod control in automatic. !
- f. Place main feedwater control valves to automatic.
QUESTION 7.06 (1.00) The reactor is operating at 100% power when a Gross Failed Fuel Monitor, 1PE-406 (FFL-260) ALERT alarm is received. A sample indicates that fuel i failure has not occurred. What are two (2) other possible causes of the alarm (operational causes, not instrument malfunction). (1.0) I QUESTION 7.07 (2.00) Heavy smoke in the control room prompts the Shift Supervisor to order the control room evacuated. (2.0)
- a. What initial operator action (s) should be taken prior to evacuating the control room?
- b. Where do the Shift Supervisor, Reactor Operator, and Relief Reactor op.erator proceed to?
i QUESTION 7.08 (2.50) l Fuel Handling activities are in progress when the SR0 in charge of fuel handling reports to the control room that a fuel bundle has been dropped into the refueling canal in containment. What initial actions should be performed? (2.5) 4 I (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) l t
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- __EB99E99BES_:_N9BdoL4_oBN9BdoLt_ EMERGENCY AND PAGE 16 4 l
86019L99196L_99.UIB9L t l 1 [ QUESTION 7.09 (2.00) l l a .' In accordance with the rules of usage for the EOP's, when is it required to start monLtoring status trees? (1.0) i
- b. What actions should an operator perform if AFTER referring to a Response Not Obtained (RNO) action step, the expected RNO cannot be satisfied? (1.0)
QUESTION 7.10 (1.00) ! i. With the unit et 100% reactor power, a loss of offsite. power occurs, j This transient trips the main turbine which in turn causes a reactor trip. All emergency diesel generators fail to start. (1.0) i To what procedural point do you proceed first?
- a. ECA 0.0, Loss of all A/C power. ,
1
- b. ECA 0.1, Loss of All A/C power recovery without SI required.
- c. E0P-0.0, Reactor Trip or Safety Inj ect ion ,
j d. E0P-1.0, Loss of Reactor or Secondary Coolant. QUESTION 7.11 (1.50) F List all of the immediate action substeps from E0P-0.0, Reactor Trip or ] Safety Inj ec t ion, that allow you to accomplish the following immediate l action steps: (1.5) j 1
- a. Verify reactor trip l k
i
- b. Verify turbine trip )
)
- c. Verify AFW flow and proper valve alignment 1
I QUESTION 7.12 C .50) TRUE or FALSE. A Steam Generator with a ruptured tube is class if ied as a faulted Steam Generator.per the E0Ps. (0.5) I l (***** CATEGORY 07 CONTINUE 0 ON NEXT PAGE *****)
l ? ) ZA__BB9CE99BE3_:_UQBd6Lt_6@UQBd6Lt_EdEBQEUGl_6NQ PAGE 17 86919699106L_C93IB9L i QUESTION 7.13 (2.50) What are five (5) conditions that indicate Natural Circulation Flow is occurring? Assume containment conditions are normal. (2.5) i QUESTION 7.14 (1.00) i Why is there a precautionary note in ECA-0.0, Loss of All A/C Power, to MONITOR the CSF Status Trees for INFORMATION ONLY, but not for purposes of implementation? (1.0) l i QUESTION 7.15 (3.00) While functioning as shift supervisor, a condition arises which requires entry into containment while critical at 40% power. The operator entering util receive a whole body dose of 40 mrem. You have the following data available to you: (3.0) Candidate 1 2 3 4 Sex male male female male Age 27 38 24 20 Wk/ exposure 35 mrem 280 mrem 0 mrem 30 mrem Qtr/ exposure 1230 mrem 970 mrem 280 mrem 1120 mrem Life exposure - 54730 mrem 5200 mrem 9770 mrem Remarks history - 4 months - unavailable pregnant Each candidate is technically competent and physically capable of perform- l ing the task. Emergency limits do not apply and time constraints do not : permit obtaining authorization for en exposure limit increase. Give your reasons for accepting or rejecting each candidate for the job. I i i i l i 1 l r**t** END OF CATEGORY 07 *****) l 2
b 82__6DdINISIBoIIVE_EB9CEDUBESt_QQNQ111gN$t_60g_LIdlI611QUQ PAGE 18 i QUESTION 8.01 (3.00) i
- a. Any person performing an activity who cannot, or believes he/she should not, follow a procedure as written, shall perform WHAT TWO (2) ]
actions immediately? (1.0) l
- b. What are two (2) methods that may be utilized by the Shift Supervisor to resolve apparent procedural discrepancies? (2.0)
QUESTION 8.02 (2.50) I
- a. Where, in the control room, are the two duplicate sets of security related keys maintained? (1.0) [
- b. Who, by title (2 required), has access (keys) to the lockers containing the above security keys? (0.5) l c. Which two (2) of the three key lockers in the control room MUST remain locked at all times? (1.0) l QUESTION 8.03 (3.00) ,
l During a tour of the plant, you observe valves locked in each of the i manners described below. Indicate whether each is acceptable or not. (3.0) l
- a. A carbon steel valve handwheel is chained to a pipe,
- b. A stainless steel valve operator is secured to a pipe with chain,
- c. A carbon steel valve operator is secured to its valve yoke with a steel cable.
- d. A stainless steel valve operator is secured to a two inch conduit with ,
a stainless steel cable. j j
- e. A stainless steel valve operator is secured to a structural steel beam !
with a stainless steel cable. l f. A carbon steel valve handwheel is secured to a cable tray with chain. , i t
)
l l l 1 (***** CATEGORY 08 CONTINUE 0 ON NEXT PAGE *****) !
1 1 52__89dINISIBoIIVE_BB9CE99BE3t_Q969(IIQN$t_80Q_(IdlI6119Nj PAGE 19 ) I l QUESTION 8.04 (2.50) l
- a. An operator may take reasonable action that departs from a license I condition or technic al spec if icat ion under what conditions? (2.0) i
! b. Who, as a minimum, must approve the above departure from license J conditions prior to taking the action? CO.5) j I QUESTION 8.05 (2.00) l Indicate wh?ther each of the following is Controlled, Identified, Pressure , Boundary, or Unidentified Leakage, or not considered leakage at all. (2.0)
- a. S/G tube leakage into the secondary system l
- b. Leak at the weld connecting one pressurizer code safety line to the pressurizer,
- c. Code safety leakage inte the PRT (as indicated by level increase and l high safety valve discharge line temperature. 4
- d. RCP seal flow QUESTION 8.06 (2.00) i
- a. What person on shift is NORMALLY designated as the Fire Brigade leader? (0.5)
- b. In the event the above individual is not brigade qua li f ie d, who can fulfill the position of B r ig ade Leader? (0.5)
- c. Other than the Brigade Leader, who make up the Fire Brigade (include the number of individual required and from what departments)? (1.0) l QUESTION 8.07 (2.50) f i
- a. When is a third approval required for approval of a temporary procedure change? (1.0) l I
! b. Who are the three (3) persons that must approve a temporary change, I assuming that three are required? Include any requirements the ' individuals must meet. (1.5) ] t d ! 4 l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) l
'D 2_ _6001NI SI B 611 y g _ E B Q Q g g U B E $ t _ Q Q U Q 111 Q N g t _80 Q _ L id 11611 g N 3 PAGE 20 i !
! l l QUESTION 8.08 (2.00) What are four (4) categories of persons that may act as Independent j, Verifiers for a temporary modif icat ion? (2.0) QUESTION 8.09 (2.00) Answer the following with regard to Clearance and Safety Tagging:
- a. What qualifications must an independent verifier meet for clearance purposes? (0,5) l
- b. Who may waive the Independent Verification requirement, and for what reason? (1.0)
- c. A breaker has several clearance tags on it requiring it to be locked, but has only one lock attached. Is this acceptable? (0,5)
QUESTION 8.10 (2.50)
- a. What three individuals are designated to assume the duties of Emergency Coordinator? (1.0)
- b. What three decision-making or approval authorities may NOT be delegated by the Emergency Coordinator? (1.5)
QUESTION 8.11 (1.00) What authority does Comanche Peak (Texas Utilities) personnel have with regard to imposing protective actions on the Comanche Peak site or the surrounding area? (1.0) (***** END OF CATEGCRY 08
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'flRC LICENSE EXN41t(ATION HMD0 LIT EQUATIONS,,00 ISTANTS, MD CONVERSIONS Q = [n*Cp *deltaT Q = U*A*deltaT-P=Po*10sur*(t) P = P *et/T- SUR = 26/T.
I T = 1*/p + (p-p)/X p T=1/(p-p)- T =-(p-p)/X p P = (Keff-1)/Keff = deltaKeff/Keff p=1/TKeff+feff/(1+I.T) . q A = In2/tg = 0.693/tg PC = 0.1 seconds-1 i
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I = Io*e "* l J CR = S/(1-Keff) 2 i R/hr = 6*CE/d feet 1 l l Water Parameters -l
. 1 gallon = 8.345 lbm = 3.87 liters .i i ft3 7,48 gallons !
Density @ STP = 62.4 lbm /ft3 = 1 gm/cm3 ) Heat of vaporization = 970 Btu /lbm Heat of fusion = 144 8tu/lbm 1 atmosphere = 14.7 psia = 29.9 inches Hg. Miscellaneous Conversions :) I curie = _3.7 x 10iv disintegrations per second i i 1 kilogram = 2.21 1 horsepower = 2.54lbm x- '103 Btu /hr i 1 mw = 3.41 x 106 Btu /hr' i 1 inch = 2.54 centimeters ? degrees F = 9/5 degrees C + 32 degrees C = 5/9. (degrees F - 32)
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- 5. THE981_9E'U996E68_E9 WEB _ELoNI 9EEB61190t_EL91QSt_6NQ PAGE 21 ISEBd9910edigS )!
ANSWFRS -- COMANCHE PEAK 1 -87/07/13-ORAVES, D. j l
' I ANSWER 5.01 (2.00) ,
'n
- a. A single pump running has a higher flow than when all 4 are operating (due to reduced discharge. pressure) so more work is done and more amperage drawn. (ACCEPT CONCEPT FOR ALL PARTS) (0.5) Also accept {
same reason as.in part b. q l
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- b. At cold conditions, fluid density is higher, so more mass is moved so more work is done and more amperage drawn (0,5). 1 l c. It must accelerate more mess,.which requires more work, and amps (0.5) i
- d. Operating at runout may cause pump d am ug e\
/ trip on overcurrent (0.5).
?
l
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l REFERENCE Westinghouse Thermal Hydraulle P r inc ip les and Applications to PUR, pg 10-43,44,47 K/A 191004 K1.07 2.9/2.9 K1.09 2.4/2.5 , 4 K1.12 2.5/2.7 l 191004K107 191004K109 191004K112 ...(KA'S) ) I l i J ANSWER 5.02 (1.50) ( ' 4
]
- a. Lower l
- b. Higher l
- c. Lower ]
(0.5 each) l REFERENCE , Westinghouse Thermal Hydraulic Prinviples and Applications to PWR, pg 13-41 i K/A 193007 K1.06 3.1/3.3 193007K106 ...(KA'S) i i i l [ l l l l
ie PAGE 22 b2__INE981_DE_U996EeB_E9 WEB _ELeUI_9EEBoIIQN_ELQJQ3t_8NQ t IUEEdQRXU6 DIGS ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. ANSWER 5.03 (1.00) During nat. cire, cooldown, bypass flow is minimal (0.25). Therefore, the i water in the upper head is decoupled from the cooldown of the RCS (0.25). When this occurs, water (a metal) in the upper head may stay hot enough to flash to steam when the RCS is depressurized, even though the bulk temperatures in the RCS are cool (0.5). (CONCEPT) j REFERENCE E10 WEC4 GENERIC RT & HTFF K/A 193008 K1.20 2.9/2.9 l 193008K120 ...(KA'S) l l ANSWER 5.04 (1.00) l 390 ps ig + 14.7 psig = 404.7 psia (0.25) Saturation temperature for 404.7 psia: (456.28 deg F - 444.6 deg F)(4.7/50) + 444.6 deg F = 445.7 deg F (0.5) The temperature instrument is reading 4.3 deg too high (0.25) ; REFERENCE Steam Tables K/A 193003 K1.25 3.3/3.4 193003K125 ...(KA's) ANSWER 5.05 (2.00)
- a. 1. 1 = 2= 3 (0,5)
I 2. 1 >2< 3 (0.5)
- 3. 1< 2 > 3 (0,5)
- b. The pressure at 3< 1 (0.25). The difference in pressure is accounted for by the generation of heat (0.25) due to fluid friction.
REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, pg 11-22,23 l K/A 191002 K1.01 2.2*/2.4 I K/A 193006 K1.13 2.2/2.3 191002K101 193006K113 ...(KA'S) 1
. J d'
51__IBE9BX_9E_UU9LE68_E9 WEB _EL6UI_9EEBoII90t_EL9102t_66Q PAGE. 23 IUEBdQQ1uodICS , ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. r , ANSWER 5.06 (2.00) f i
- a. increase l b. decrease f
- c. increase 6
- d. decrease f (4 at 0.5 each) 1 REFERENCE l Westinghouse Thermal Hydraulic' Principles and Applications to PWR, pg 13-23,24 K/A 193000 K1.05 3.4/3.6 ,
l 193008K105 ...(KA'S) l L I l l ! ANSWER 5.07 (2.00) ! l Axial Flux Difference (0.25) determines axial distribution (0.25) and is determined by' subtracting calibrated I from the bottom detectors from the calibrated I from the top detectors and dividing by the 100% power j calibrated I (0.5). j i i Quadrant Power Tilt Ratio (0.25) determines the radial flux shape (0.25) and is determined by ratioing the maximum upper half excore' detector I to ! the average upper excore detector I (also applies to lower detectors)C0,5).
] !
REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, t pg 13 13-50 l K/A l'93009 Kl.01 2.3/2.8 K1.02 2.3/2.8 l 193009K101 193009K102 ...(KA'S) i i I
's l
2 l
4 5 __IBE981_9E_UV9LE68_E0 WEB _ELoNI_DEE86I199t_ELu1Q3t_6NQ. PAGE 24 1UE80001U6d192 l i ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. l
,l l l
! ANSWER 5.08 (2.50)
- 1. Decrease
- 2. Increase
- 3. Increase
- 4. Decrease
- 5. Decrease q l [0.5 eachl i' REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, pg 12 12-47 '
K/A 192008 K1.21 3.6/3.8 192008K121 ...(KA'S) l j 1 ANSWER 5.09 ( .50) b (0.5) (The second reactivity addition was-smaller) REFERENCE , Westinghouse Fundamentals of Nuclear Reactor P hys ic s , pg 8-54 K/A 192008 K1.03 3.9/4.0 192008K103 ...(KA'S) ANSWER 5.10 (1.50) t
- a. (1) Increasing towards peak Xenon concentration.
- b. (4) Decreasing toward zero pe:' cent power equilibrium value,
- c. (3) Decreasing toward a dip. [0.5 ea.)
REFERENCE EQB'WL04 GENERIC RT & HTFF K/A 192006 K1.06 3.4/3.4 K1.07 3.4/3.4 192006K106 192006K107 ...(KA'S) a
6
'S t _ _ I B E 0 Bl _9 E _ U U C L E 68_ E 9 WE B _ E L 6 SI _9 E E B oII Q U t _ E L U I D 3 t _6 N Q ' PAGE 25 18E800010601G1 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D.
I {- ANSWER 5.11 ( .50) l c (0,5) REFERENCE EQB WEC4 GENERIC RT & HTFF l K/A 192006 K1.06 3.4/3.4 l l 192006K106 ...(KA'S) { ANSWER 5.12 C .50) d (0.5) i l REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, pg 12 12-43 K/A 192008 K1.18 3.6/3.5 K1.21 3.6/3.8 r K/A 035010 A2.01 4.5/4.6 035010A201 192008K118 192008K121 ...[KA'S) k ' ANSWER 5.13 (2.50)
- a. Power decreases initially [0.25] due to the negative reactivity of the boron addition (0.25). The primary to secondary mismatch [0.25]
causes Tave to decrease (0.25). The decrease in Tave inserts positive reactivity [0.251 and restores power to slightly lower than or the same as initial oower [0.25]. i
- b. Tave is determined by the amount of pump heat and the' steam dump i pressure setting [0.25] thus it does not change [0.25]. After the initial transient, power decreases [0.25] (at a -1/3 DPM rate) to the multipiled source level [0.25).
REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, ' Chapter 12 l K/A 192008 K1.17 3.3/3.4 K1.20 3.8/3.9 192008K117 192008K120 ...(KA's) l
]
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1 . l 5t__IBE9BX_9E_UU9LE68_E9WE8_EbeUI_DEEBoIIQUt_EL91QSt_6UQ PAGE 26 I6EB0901060193 i i ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. ) l 1 i i: ANSWER 5.14 (1.50) l l a) increase; (no answer) (+.25 ea response) ) b) (no ans); decrease c) increase; increase l d) increase; increase ! i REFERENCE , Westinghouse Thermal Hydraulic Principles and Applications to PWR, pg 12 12-54 1 K/A 035010 K1.09 3.8/4.0 035010K109 ...(KA'S) j
- 1 1
1 ANSWER 5.15 ( .50) ], a (0,5) l l I REFERENCE Westinghouse Fundamentals of Nuclear Reactor Physics, pg 7-38 i K/A 192003 K1.06 3.2/3.3 j 192003K106 ...(KA'S) ANSWER 5.16 (1.50)
- a. - Operator can notice that SUR has decreased
- Power change on IR is leveling off
- RCS temperature increases (2 required at 0.25 each)
- b. 2 (1.00) (From P = Po10ECSUR X t) the SUR in Interval 2 has decreased from +13 DPM. The other intervals have +1/3 DPM SUR)
REFERENCE Westinghouse Thermal Hydraulic Principles and Applications to PWR, pg 12-32 K/A 192008 K1.15 3.4/3.4 K1.17 3.3/3.4 192008K115 192008K117 ...(KA'S) f _____...___________w
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d 51__INE9Bi_9E_UUCLE68_E9 WEB _EL6NI_9EEBoII9Nt_ELUIR$t_oWQ PAGE 27. j IBEBdD01060192 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D.
) 1 I
I i I l K ANSWER 5.17 (2.00)
- a. 1 allowed 4, but must have 1
- b. 6 f v
- c. 2
- d. 3 l
- e. 5 i
- f. 4 allowed 1, but must have 4 l l Ca -f et 0.33 each) l l REFERENCE
! Basic Reactor Theory K/A 192001 K1.01 1,9*/2.0 K1.02 2.4/2.5 ' l K/A 192002 K1.11 2.9/3.0 l 192001K101 192001K102 192002K111 ...(KA'S)
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6t__EL6NT SY3 TEM $_Qg3IQN _CQNTRQLt_ANQ_ t INSTRUMENTATION PAGE 28 j i ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. ) l ) l l l ANSWER 6.01 (2.50) I l
.1
.a. The NaOH tank iso lat ion valves shut on a NaOH tank low level (1,0) ]
f
- b. RWST EMPTY alarm (0.5) or 15%
- c. Hi 3 containment pressure (18. 35 ps ig) (0.5) 2/2 pushbuttons on main control board (0,5) or manually q l
REFERENCE j Containment Spray System Description, II-10.13, 14 ! X/A 026000 K4.01 4.2/4.3 j G009 3.6/3.6 . ! 026000G009 026000K401 ...(KA'S) l l I ANSWER 6 02 (1.50) ( The large air leak will cause the valve to fail open (0,5). RCP seal l inj ec t ion flow will decrease (0,5) due to the reduced backpressure from j HCV-182 (0,5).
, REFERENCE CVCS Description, II-2.19, 27 K/A 004000 K1.04 3.4/3.8 004000K104 ...(KA'S) l ANSWER 6.03 (3.00)
- a. 1 - shut b. 1 - open 2 - open 2 - shut 3 - open 3 - shut 4 - shut 4 - open 5 - shut 5 - shut l 6 - shut 6- open l
l (12 at 0.25 each) REFERENCE Main Feedwater System Description, VIII-7.23 K/A 059000 K1.02 3.4*/3.4 061000 K1.02 3.4/3.7 059000K102 061000K102 ...(KA'S) i
ht__PL681_3ISIgd3_QE3196t_CQUIBQLt_60Q_lU$189dEUI61190 PAGE. 29' 1 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. i 1 4 i 5 1 ANSWER 6.04 (2.50) 1 l l
- 1. indicated level would increase due to O dp
- 2. MFW pumps do not trip on low level
- 3. TOAFWP doesn't start on low level in 1/4 SG
- 4. TOAFWP doesn't trip on low oil pressure
! 5. MDAFPs don't trip on high SG 1evel l (0.5 each) REFERENCE Main FW System Description, VIII-7.13 ! AFW System Description, VIII-8.10, 11, 14 K/A 061000 K4.07 3.1*/3.3* f A3.01 4.2/4.2 l K/A 059000 K4.16 3.1*/3.2* l 059000K416 061000A301 061000K407 ...(KA'S) i J I i ( ANSWER 6.05 (2.50)
- a. 1. 345 KV S/U transformer XST2 (0.25)
- 2. 138 KV S/U transformer XST1 (0.25) via 1A1 and 1A2 (0.25)
- 3. 345 KV main transformer (0.?S) via aux UT (0.25) via 1A1 and 1A2 (0.25) l
- 4. 0/G (0.25)
Voltages and transformer numbers not required as long as grader can determine path. (0.25 for order) b, diesel generator breaker (0.5) REFERENCE AC Distribution System Description, VII-1, Section 3.4 K/A 062000 K4.06 2.9*/3.3* K1.02 4.1/4.4 062000K102 062000K406 ...(KA'S)
6t__EL6HI HYSIEMS_DESIGNt_GQNIBQLt_680 INilBudENI8IIQN _PAGE 30 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. 1 I ANSWER 6.06 (2.50)
- n. YES (0.25). Containment ventilati-on isolation occurs (0.25). 1 I'
- b. YES (0.25). Auto-closure of gas release valve in waste gas processing system (0.125), Control room ventilation isolates (0.125).
- c. NO (0,5)
- d. NO (0.5) l
- e. YES (0.25). Automatic closure of isolation valves in blowdown and sample lines (0.25).
REFERENCE Radiation Monitoring System Descriptions, XIII-18, section 4.1.a K/A 073000 K4.01 4.0/4.3 073000K401 ...(KA'S) I ANSWER 6.07 (2.50) I
- a. No (0.25). The reset sequence blocks all automatic actuation signals ,
until the P-4 signal has been reset by closing the reactor trip ! breakers (0.75). l b. - Feedwater isolation l' - Reactor trip !
- Auxiliary FW start
- Control Room emergency recirculation i Phase A containment isolation
- Containment ventilation isolation
- Station SW start
- Emergency Diesel Generators start j (6 at 0.25 each)
REFERENCE Introduction to ESF, 11-7.21, Table ESF-1 ! K/A 013000 K1.01 4.2/4.4 ! 013000 K4.01 3.9/4.3 3 013000K101 013000K401 ...(KA'S) {
g
. i 6t__EkedI_313IEUS_D6319Nt_CQNIBQLt_6NQ_1U$1BydEUI611QN PAGE 31 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. j i
i l ANSWER 6.08 (3.00)
- a. NO CHANGE (0,5). Results in a low loop Tavg, Rod Control utilizes !
I a Auctioneered High Tavg (0,5).
- b. RODS IN [0.5). Pimp will generate a minimum Tref, a large temperature error will cause rods to insert (0.25). Power rate mismatch will also cause rods to insert (0.25). !
- c. RODS IN (0.5). Nuclear power > turbine power (mismatch), rods in to compensate for ant ic ipated high Tavg (0.5).
REFERENCE Rod Control System Description, III-3.11, 12 K/A 001000 K4.03 3.5/3.8 001000K403 ...(KA'S) i ANSWER 6.09 (1.50) Will not allow the test (0 5). Placing in test will deenergize the interlock circuit P-13 which feeds P-7. This will unblock the low j pressurizer pressure trip function which will result in a. reactor protection actuation. Shutdown rods will drop. (1,0) i REFERENCE Instrument Failure Analysis, Table IFA-1 Solid State Reactor Protection System Description, III-9.25, 27 K/A 012000 K4.01 3.7/4.0 012000K401 ...(KA'S) I I l ANSWER 6.10 (1.50) { l { OTN16 OPN16 '
- a. increase remain the same
- b. decrease remain the same
- c. increase remain the same (0.25 ea) i REFERENCE !
RCS Temperature and N16 Power System Description, III-5.4, 5, 6 { K/A 010000 K1.01 3.9/4.1 , K/A 012000 K4.03 2.3/2.7* f K/A 015000 K1.01 4.1/4.2 010000K101 012000K403 015000K101 ...(KA'S)
l 1
., 1 l .
- l 6t__EL6UI_SYSIEUS_DESIQN t_QQUlBQLt_AUQ_IN31BydEN1611QN PAGE 32 l
ANSWERS'-- COMANCHE PEAK 1 -87/07/13-GRAVES, 0, l 1 1 ANSWER 6.11 (2.00) i'
- a. Arm only (0.5).
l.
- b. Arm and Actuate (0.25 each)
[ c. Arm and Actuate (0.25 each)
- d. No effect (0,5) ,
I l REFERENCE l Steam Dump System Description, III-7.3, 4, 8, 9 K/A 041020 K4,17 3.7/3.9 , f l 041020 K4.11 2.8/3.1 041020 K4.14 2.5*/2.8* 041020K411 041020K414 041020K417 ...(KA'S) i J l l l l 1 i l I l l l I l t ? l l
.I
'a ft__PBQQEQUBES_:_U9806Lt_6@UQBdekt_EDEBQEUQ1_600 PAGE 33 B6019L99196L_G90IB9L ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D.
i ANSWER 7.01 (1.50) j
- to force AFD to the target value during power level changes (0.5)
- to maintain AFD at the target value during reduced power operations (0.5)
- to dampen axial xenon oscillations (0.5) i Also accepted control rod excercise per surveillance, i REFERENCE IPO-003A, Power Operations, Rev 0, pg 3 K/A 001000 K5.06 3.8/4.1 001010 K5.34 3.2/4.1 001000K506 001010K5.3 ...(KA'S)
ANSWER 7.02 (2.00)
- Source Range increases by a factor of 2 while changing boron concentration and the reason cannot be determined.
- disagreement with predicted value of reactivity balance by > or =-1% dk
- calculated SDM < technical specification value
- dk addition corresponding to a period < 5 seconds i
- unp lanned c r it icality :
l i (4 required at 0.5 each) REFERENCE IP0-002A, Plant Startup from Hot Standby to Minimum Load, Rev 2, pg 4, 5 l K/A 001000 G002 3.2/3.9 j 001000G002 ...(KA'S) I i ANSWER 7.03 (1.00) j
- Control Rod withdrawal is started within 24 hours of last trip (0.5)
- RCS temperature has been > or = 551 F since the trip (0.5) l l
REFERENCE l IPO-002A, Plant Startup from Hot Standby to Minimum Load, Rev 2, Attach 1 K/A 194001 A1.02 4.1*/3.9 i
}
l r.; , z__BB00EDUBES_:_U9Bd.ekt_oBUQBdekt_EUEB9EUQ1_oug PAGE 34 B6019L99196L_99UIB9L ANSWERS -- COMANCHE PEAK 1 -87/07/13-GAAVES, D. 1 l 1 194001A102 ...(KA'S) l 1 [ ANSWC.R 7.04 (1.00) I One of the 2 RCPs should be 1 or 4 (0,5) to provide pressurizer spray l flow (0,5). , REFERENCE l IPO-005A, Plant Shutdown from Hot Standby to Cold Shutdown, Rev 2, pg 10 K/A 002000 K1.09 4.1/4.1 { 002000K109 ...(KA'S) ? d ANSWER 7.05 (2.50)
- 1. c )
- 2. b l
- 3. d
- 4. e or f
- 5. f or e
- 6. a l (0.5 for each manipulation required to put in correct order, 5 max)
REFERENCE IPO-002A, Plant Startup from Hot Standby to Minimum Load, Rev 2 IPO-003A, Power Operations, Rev 0 K/A 194001 A1.02 4.1*/3.9 194001A102 ...(KA'S) q ANSWER 7.06 (1.00)
- CVCS mixed bed domineralizer resin depletion (0,5)
- Crud burst (0.5) Alse accept high background radiation.
REFERENCE ABN-102A, High Reactor Coolant Activity, Rev 1, pg 3 K/A 000076 EK1.06 2.1/2.6 EA2.07 2.4*/2.7* 000076A207 000076K106 ...(KA'S) l a
._-._____._________w
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- 6.
kt__PBQQEQUBg3:_UQ806Lt_68NQBd6Lt_EdEBQgNQX_6NQ' PAGE 35 B6DIQL99196L_990189L l l ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. l l i l l ! ANSWER 7.07 (2.00) i
- a. trip the r e a c't o r. (0,5) j
! b. SS - Hot Shutdown Panel (0,5) RO - Hot Shutdown Panel (0.5) RRO - Switch Transfer Panel (0,5) i REFERENCE ABN 905A, Loss of Control Room Habitability, Rev 0, pg 2 K/A 000068 G010 4.1*/4.2* 000068G010 ...(KA's) l i ANSWER 7.08 (2.50)
- Notify Rad Protection
- Actuate containment evacuation alarm
- Ensure containment purge and exhaust are isolated l
- Ensure containment pre-access filter units are in operation
- Notify security to ensure no access is permitted into the affected area.
(5 at 0.5 each) REFERENCE ABN-908, Fuel Handling Accidents, Rev 0, pg 2, 3 K/A 000036 G010 3.7/3.8 ! 000036G010 ...(KA'S) i i ANSWER 7.09 (2.00) j 1
- a. - on transition out of E0P-0.0 (0.5) ;
- when instructed to start monitoring in E0P-0.0 (0,5)
.l
- b. - the operator proceeds with the next step or substep in the left c hand column of the procedure (0.5) !
- while continuing to try and satisfy the action step [0.5)
REFERENCE Westinghouse ERG User's Guide ( K/A 000007 G012 3.8*/3.9* 000007G012 ...(KA'S) l 4
80GEQUBES_:_NQBd6Lt_6QUQ80$Lt_EUE8QEUQ1_6UQ DAGE 36 6010LQQIC6L_GQUIBQL lERS -- COMANCHE PEAK 1 j -87/07/13-GRAVES, D. R 7.10 (1.00) l l.0) or 1
- a. Either acceptable 1
!RENCE l0. 0, Reactor Trip or safety Injection, Rev 2 l194001 A1.02 4.1*/3.9 l000007 G011 4.1*/4.3 .07G011 194001A102 ...(KA*S) l t .R 7.11 (1.50) Rod bottom lights on Reactor trip breakers open Neutron flux decreasing All turbine stop valves closed AFW total flow > 470 gpm FW split flow bypsss valve closed t 0.25 each) RENCE 0.0, Reactor Trip or Safety Inj ec t ion, Rev 2, pg 4, 7 194001 A1.02 4.1*/3.9 01A102 ...(KA'S) R 7.12 ( .50) e (0.5) RENCE 0.0, Reactor Trip or Safety Injection, Rev 2, pg 10 000040 EA2.03 4.6/4.7 G 012 3.8*/4.1* 40A203 0000400012 ...(KA'S) ' s
1
?
ki__EB9CEDUBES_:_U9Bd6Lt_6BU9Bd6Lt_EdEBGEUGl_8U9 PAGE 37 . BBRIQL99198L_G99IB9L i ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. i i ANSWER 7.13 (2.50) { i
- 1. Core exit TCs (.25) - stable or decreasing (.25) l
- 2. RCS Subcooling (.25) - greater than 15 F (.25)
- 3. SG pressure (.25) - stable or decreasing C.25)
- 4. RCS hot leg temperature (.25) - stable or decreasing (.25)
- 5. RCS cold leg temperature (.25) - at approx. saturation temp for SG -
pressure (.25) REFERENCE l EOS 0.1, Reactor Trip Response, Rev 2, pg 15 ; K/A 002020 KS.10 3.8/4.1 00202 50 00 bOkb4 ...(KA'S) ANSWER 7.14 (1.00) Because none of the electrically powered safeguards equipment used to restore Critical Safety Functions is operable (1.0) (none of the FRG's can be implemented) , REFERENCE Westinghouse User's Guide for ERG's, p. 17/18 j K/A 000055 EK3.02 4.3/4.6 000055K302 ...(KA'S) i ANSWER 7.15 (3.00) candidate #1: r ej ected (0.25) since he has no history on file and will , exceed 1.25 REM /QTR whole body exposure (0.5) ] l candidate #2: rejected (0.25) since he will exceed the weekly limit of f 300 mrem whole body without Rad Protection Supervisor's l approval (0.5) i l I candidate #3: rejected (0.25) since she will exceed 300 mrem whole body during the term of her pregnancy (0,5) candidate #4: accepted (0.25) since he will not exceed the admin limit of 300 mrem /wk (0.25) or the whole body limit of 1.25 REM /QTR : (.25) l l 1 s
g...
-Zz__EB99E99BES_:_N9Bd86t_oBU9Bd6Lt_EUEB9EN91_60Q PAGE 38 ;
i BeQ19L99196L_99 BIB 9L ANSWERG -- COMANCHE PEAK't -87/07/13-GRAVES, D. REFERENCE Radiation Worker Training pg 11-12 K/A 194001 K1.03 2,8/3.4 l 194001K103 ...(KA'S) ! i
.1 l
h i l l 1 l 1 l l l l
.1 l
1 b _
[ - l l 2 l t' 1
, i at__oDdINISIBoIIVE_EBOCEDUBESt_C9901I1903t 660_L101I611991 PAGE 30 ]
l ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. l u i i 1 ANSWER 8.01 (3.00) 1 1
- a. Place the system or component in a safe / stable condition (0.5) and !
notify the Shift Supervisor (0,5). , l l b. - Determine a method by which the activity can be performed with the i procedure as written.
~
- Initiate temporary procedure change (if intent not altered). !
i
- Initiate preparation and approval of a temporary procedure.
- Initiate r evis ion to existing procedure.
(2 at 1.0 each) REFERENCE OWI-105 Guidelines on Use of Procedures, Rev 1, og 2,3 K/A 194001 A1.11 2.8/4.1* A1.12 3.1/4.1* . 194001A111 194001A112 ...(KA'S) ; 4 ANSWER 8.02 (2.50)
- a. " Security Keys" key locker (0.5) j
" Controlled Keys" key locker (0.5) !
1
- b. Shift Supervisor (0.25)
Assistant Shift Supervisor (0.25) I
- c. Security Keys locker (0,5)
Controlled Keys locker (0,5) ! l l REFERENCE OWI-102, Operations Department Key Control, Rev 1, pg 1, 4 K/A 194001 K1.05 3.1/3.4* 194001K105 . .(KA'S) ANSWER 8.03 (3.00) acceptable a, c, e (0.5 each) not acceptable: b, d, f (0.5 each) l _ - _ _ _ . __-_ _ ___- D
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. 'a t _ _6901NI S IB 611 y g _ B B Q Q E Q Q B E $ t _ Q Q N QII1 Q N$ t _6NQ _ L IMII6 Il 0 N2 PAGE 40
-87/07/13-ORAVES, D.
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ANSWERS -- COMANCHE PEAK 1 REFERENCE OWI-103, Operations Department Locked Valve Control, Rev 3, pg 3 K/A 194001 K1.01 3.6/3.7 '! 194001K101 ...(KA'S) l I l l l ANSWER 8.04 (2.50) J I
- a. When this action is immediately needed to protect the public health l and safety (1,0) and no action consistent with license conditions and I technical specifications that can provide adequate or equivalent protection is immediately apparent (1.0). Two concepts required.
Wording may vary significantly. j
- b. a licensed SRO (0,5) Accepted SS or Asst. SS for 0.25 pts.
REFERENCE 10CFR50.54(x) 10CFR50.54(y) K/A 194001 A1.02 4.1*/3.9 1 194001A102 ...(KA'S) i i ANSWER 8.05 (2,00)
- a. identified (0,5) b, pressure boundary (0.5) i
- c. identified (0.5)
- d. controlled (0,5)
REFERENCE Technical Specification Definitions f 4 K/A 002000G005 3.6/4.1 0020000005 ...(KA'S) f l i i l 1 i l I
I
; i
. a
. bt__AQUINISIB6IIVE_ERQQgQQBE$t_CQUQillDU$t_60Q_LidlI6119N$ PAGE 41 1 \
l ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. 1 l ANSWER 8.06 (2.00) i j a. Ass is t ant Shift Supervisor (0,5)
- b. Auxiliary Operator (0,5) certified in all areas of the plant,
- c. 2 Auxiliary operators (0,5) !
2 Security personnel (0.5) REFERENCE FIR-104, Fire Brigade, Rev 5, pg 5 . K/A 194001 Kl.16 3.5/4.2* l 194001K116 ...(KA'S) l i i ANSWER 8.07 (2.50) i i
- a. Changes that affect the operational status of station equipment (1.0).
l
- b. 2 members of plant management staff (0.5),-one of whom must be SRO licensed (0.5) and either the Shift Supervisor or the Assistant Shift Supervisor (either for 0.5). ,
REFERENCE l STA-205, Temporary Changes to Procedures, Rev 8, pg 3 K/A 194001 A1.03 2.5/3.4 l 194001A103 ...(KA'S) { i ANSWER 8.08 (2.00)
- one of equivalent training to the person installing the modification
- insta11er's/ remover's supervisor l l
- anyone in an engineering position
- member of operations department as determined by the SS (4 at 0.5 each)
REFERENCE i STA-602, Temporary Modifications, Rev 3, pg 3 K/A 194001 K1.02 3.7/4.1 y 194001K102 ...(KA'S) l l I i J l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ . _ _ _ _ _ . _ _ _ _ _ . . d
1 f l
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> i . a t _ _e Dd.INISIBollyE _BBQC E QUB E $ t_G QUQIIIQ U$ t _6N Q_ LIdII6IIQU$ PAGE 42 ANSWERS -- COMANCHE PEAK 1 -87/07/13-GRAVES, D. i ANSWER 8.09 (2.00)
- a. R0 (0,5) or SR0
- b. SS (0,5) in cases of significant radiation exposure (0,5)
- c. yes (0.5) j l
REFERENCE STA-605, Clearance and Safety Tagging, Rev 5, pg 6, 8 K/A 194001 Kl.02 3.7/4.1 194001K102 ...(KA'S) ANSWER 8.10 (2.50)
- a. on duty SS TSC manager EOF manager (0.33 each)
- b. - Emergency classification and E-Plan implementation (0.5)
- Communication with off-site authorities (0,5)
- Protective action recommendations to state and county officials (0.5)
REFERENCE EPP-109, Duties of the Emergency Coordinator, Rev 5, pg 3, 4 K/A 194001 A1.16 3.1/4.4* 194001A116 ...(KA'S) i ANSWER 8.11 (1.00) Texas Utilities has no authority with respect to impos ing protective l response actions beyond the boundaries of its site (1.0). REFERENCE EPP-304, Protective Action Guide, Rev 8, pg 4 K/A 194001 A1.16 3.1/4.4* 194001A116 ...(KA'S) I _____ _}}