ML20244D623
| ML20244D623 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/30/1989 |
| From: | Matlosz T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20244D595 | List: |
| References | |
| NUDOCS 8906190168 | |
| Download: ML20244D623 (229) | |
Text
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o o SOUTH CAROLINA ELECTRIC & GAS COMPANY vetersONc V.C.SUMME R NUCLEAR TRAINING CENTER (sun MS 1915 POST OFFICE SOM 88 JENKIN5VILLE,5. C. 29065 A44/d ENCLOSURE 3 March 30, 1989 f Mr. John Munro.
United States Nuclear Regulatory Commission Region II Suite 2900 101 Marietta, Street, N.W.
Atlanta, Georgia 30325.
Dear Mr. Munro:
Wo are. enclosing revisions to the -1989 Annual Licensed Operator Exams Answer Keys for Week 2. Included in the package are:
- Detailed justifications for questions OR-0032, OR-0045, SSO4-002, SSO4-019, and SS13-007.
- Revised answer keys for both R0 and SR0 Part B written exams.
- Revised answer keys for both R0 and SR0 Static Simulator 3 exam 5504. 1 i
Static Simulator exam SS13 did rot require changes to the answer i key but is included to maintain a consistent color: scheme. Per our telecon on 3-22-89, the comments section of . questions OR- 1 0032, OR-0045 and SSO4-005 have been revised. l If you have any further r,destions, please feel free to contact i me or Rusty Quick at your convenience. l
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Enclosures cc: K.W. Woodward i files 8906190168 890601 PDR ADOCK 05000395 ;
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EXAM KEY CHANGE REQUEST ;
EXAM NO., c re o / e o - 2 Pa < v G> QUESTION NO. O R - co's i
DATE: 3 / 3 c; / 99 REQUESTED BY: J. E C- c Ab n PROBLEM: 5ec A% Ae A n,,+ l l ,
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DELETION OF OR-0045 The number of problems associated with this exam item'far ,
outweigh its value to the examination. Questions concerning its open-endedness and validity were raised by both the examinees and the instructors administering the exam. Time constraints were also a problem as evidenced by interviews with examinees
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and analyzing their responses. Each of these problems will be .
addressed in more detail.
The validity of the question was compromised as a result of .q changes made during the exam review process. The original i intent of this question was to predict the impact on plant operations from de-energizing a bus (NUREG 1122 062000 A2.04).
A satisfactory response was that a reactor trip would result from losing two out of four power range channels. This met the intent of the K/A catalog reference and established the initial l validity of the question. Following the changes made during the review process, the question required outlining the sequence of bus de-energizations that led to the reactor trip. This '
sequence was weighted too heavily (150% of original point 4 value), and did not meet the intent of the orginal K/A catalog-reference. The importance to the health and safety of the public is based on predicting the reactor will trip if the bus is de-energized. Outlining the sequence of bus de-energizations that lead up to the trip is incidental, and not reflected in the K/A catalog reference. The examinee could completely meet the intent of the K/A catalog ability and still lose 60% ' credit on ,
the question.
Another problem with the question was that not all the required information was provided. Information as to the existing power j source to APN-5901 was inadvertently left out of the question.
This fact was crucial in answering the auestion correctly. ]
j The amount of time allotted for this question was inadequate. '
This fact was' verified through a number of different channels.
Six of the examinees-were_ interviewed after the exam, and all 6 ,
of them stated that this question was left until last. This was {
due to the complexity of the question and the confusion factor arising out of what was being asked. Our own operations 1 representative, when queried, responded titat he did not know j what the question was asking the first time he read it. One (
examinee's answer trailed off in mid-sentence. This was because the exam had come to an end and he was told to put down his pencil. This student scored the highest in last years exam.
The time constraints were further compounded by the fact that '
only two miscellaneous drawing books, required to answer the 1
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question, were available in the exam area. The examinees were instructed not to take these books back to their desk. This placed pressure on them not to spend much time looking at the drawing. As a result, they did not spend enough time analyzing the question. Questions asked of the proctor dealt with what could be assumed to have taken place up to this point, and what is the intent of this question. All of this evidence of time constraints is further supported by the fact that the original time allotted for the question was not increased when the question was changed, even though the complexity increased many-fold.
Another issue with this question was its problematic nature.
The examinee was required to determine an end result, and then outline the sequence of events leading up to that end result.
The fact is that there are multiple end results that can be chosen for this scenario. The choice of end results determines which sequence of events is outlined. Not only does this raise the issue of double-jeopardy, but also results in the sequence of events influencing which end result is chosen.
Some examples of end results that could be chosen are as follows:
o Evaluation of action statements for loss of onsite power distribution per T.S. 3.8.3.1 1
e Evaluation of action statements for loss of Diesel Generator per T.S. 3.8.1.1 e Evaluation of action statements for loss of DC sources per T.S. 3.8.2.1 l e Evaluation of Loss of Channel I Nuclear Instrumentation (Source Range and Intermediate Range) e Evaluation of Loss of Channel I Nuclear Instrumentation (Power Range) l Each of these end results could, and were, evaluated for the sequence of events that led to them. The proper end result had to be chosen from this analysis, and, consequently the selection of end result was influenced by the analysis of the sequence of events. A sequence of events that deals with Technical Specification interpretations may have been construed as more important than a sequence of bus de-energizations. The vagueness of the questica, coupled with the myriad of paths that could be taken, created a totally open-ended scenario.
For tnese reasons, the question has been deleted from the examination.
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i G v SS13-007 The original. setup of static simulator scenario 13 was intended '
to be a dropped control rod and incident fuel leakage coincident with a charging pump seal leak. The original setup page (copy ;
enclosed) identifies the malfunctions used. On closer inspection of the third line (Malf RMS1I), it can be seen that a malfunction in the original draft was erased and subsequently-replaced. The malfunction that was erased was " Letdown leck outside the RB". A malfunction to simulate charging pump seal leakage did not exist.
l When the static scenario was originally tested, the radiation monitor panel response was not as expected with high RCS activity. A decision was made to drop the letdown leak and use )
l radiation monitor panel malfunctions and overrides to simulate the leakage. As illustrated on the attached setup page, RMA3B j (Iodine) and RMA3C (Gas) were set to read the highest. Iodine 1 and gas radiation levels were emphasized to key the examinee '
into high RCS activity as the ultimate source of the high radiation levels. RMA5A & 5B (Aux Bldg Exh Plenurn) were also elevated to indicate a leak into the auxiliary building. These radiation levels were set to support question SS' 3-004, which ;
required examinees to choose the source of radiation leakage. I Specific values for charging pump seal leakage werg not chosen to calculate resulting radiation levels in the veny stack. It was felt that adequate information was not available from the i radiation mon!cors to determine a leak rate. Therefore, levels l were set high enough so that the students could be adequately !
keyed into RCS leakage outside the Reactor Building. j i
The radiation monitors that were set up during the examination j were different from those identified on the original setup page. '
This is because one of our instructors changed the radiation i monitor setup to include area monitors adjacent to chemical and !
volume control system piping. It was reasoned that the high RCS activity would also increase general radiation levels in the affected areas. RMA 3A, B, and C were inadvertently left off the revision. The subsequent review process failed to identify the error.
The examinees were asked to identify the source of radiation leakage as high RCS activity in question number SS13-004. Most of the radiation monitors in alarm were in the auxiliary building or plant vent stack. From these indications, it is relatively easy to see how they could respond to the question on RCS limiting conditions for operation with RCS leakage outside specifications.
1 LO D From their-analysis,'itiseemed the radiation monitor readings.
were leading them in that direction specifically.
For.these' reasons, it has been decided to accept."RCS Leakage" for full credit on._ question.SS13-007
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APPROVAL: W e dl '
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SSO4-002 The second sentence of the comments section was intended to be a j justification for the reason that 'c' is not a correct answer. '
The 'A' train-SI light was on; therefore, an 'A' train SI signal i
was generated. Hence, since an 'A'-train SI signal was- j generated, the 'A'-train ESF equipment would have started if--the '
loading sequencer had been properly activated. -)
-Answer 'a' -
is also acceptable because LOA EPL-136 was instated ;
on the simulator. This LOA removed power to ;he Emergency '
Safeguards Features Loading Sequencer (seeLattached drawing C-802-036). Since the ESFLS did not have power, it would'not have initiated its output functions which include:
- Output 1 -
Trip motor feeders on-NSR bus e Output 3 -
Align RBCU waterside to SW e Output 4 -
Auxiliary trips and lockouts e Output 7 -
Trip normal.and. emergency NSR bus supply breakers I The indications, or lack of indications, that would support these output functions led the examinees to believe that a failure of the sequencer occurred. In fact, it had occurred due )I to the LOA inserted on the simulator. l When the diesel generator breaker closes,-it initiates the Blackout Sequence Signal, which would cause the step functions of the ESFLS to occur. Because a malfunction was inserted to prevent the DG breaker from shutting, these step functions did not sequence; therefore, these indications lead some examinees to choose answer 'd'.
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- 1. Alternate answer #1 - Breaker racked out The question was written to solicit "possible" causes for the indications. It was not specifically stated to the examinees that the indications should be reasonable, taking into consideration the postulated conditions of the scenario. In six previous questions on this static exam, terminology on the order of "in this case" or "under these conditions" was used to key the examinee to use the entire set of simulator indications to formulate a response. For example; SSO4-001, SS04-003, SS04-005, SSO4-011, SSO4-015, SS04-017 all specify that the present conditions should be l applied. The briefing for the static simulator does not give this type of guidance. Furthermore; prior to the annual exams, a static exam was administered during the licensed operator requalification cycle. The examinees were informed at this time that questions may be included in a static scenario that do not require correlation to all conditions (i.e. some questions may stand alone).
ES-601, page 68 of 79, item e. states:
Questions may be used that do not relate to the transient but use the simulator as a frame of reference only, provided !
i the operators are aware of this lack of relationship to the transient.
This provides the precedent for "a stand alone" question and was the bases for the instructions to LOR classes concerning the applicability, or non-applicability, of a question to the given conditions.
Based on these arguments, " breaker racked out" is an acceptable answer.
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The attached drawings (B-208-020 CRO1 and CR01A) support the following alternate answers for the possible causes for the indication of RTB 'B'.- j
- 2. Alternate answer #2 - 52 contact failure ,
Failure (open) of the 52 'a' contact (on attached Westinghouse drawing 7022D93) for the reactor trip breaker- 1 would interrupt'the continuity through the red light and dropping resistor (on drawing B-208-020 CR01). The-Westinghouse diagram lists.this as an 'a' contact, but plant useage is per the IEEE device numbering (enclosed) which calls the contact a "52 a" or just "52" contact. j Generically, this type of device for a breaker is a 52 ;
device. This distinguishes the 52a contact from 33ao !
contacts which are used for valve position or breaker racked in, or out, status.
)
3 Alternate answer #3 - Breaker did not open fully 4
Partial opening of the breaker would also open the'52a !
contact as discussed in 2., above. In this case,-the main !
contactors may not move far enough to pick up the 52b -
contact to actuate the green light. A.similar set of circumstances occurred at McGuire and is detailed in IN 87-35 supplement 1: Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation From the i Control Room (see. attached page 3 of 4). J
- 4. Alternate answer #4 - Loss of DC to breakers Loss of 125 VDC from DPN-1HA1 de-energizes the entire control circuit including both red and green position indicating lights. (See highlighted portion of i B-208-020 CRO1).
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.: : O O l IN 87-35, Supplement 1 December 16, 1987 Pace 3 of 4 flattened ing and shape.
a mushroom laterally expanded the surface of the outer can segments. creat-rollerrelease spring (item latch
- 1) which holds the mechanism in readiness for release (item 161. o the stop roller. The extreme mushrooming impeded rotation of It is possible that sufficient mushrooming could totally prevent circuit operation breaker upon of the stop roller, which could prevent closure of the demand.
While not of safety concern for an RTS, this failure to requiring application close condition would energiration of the be of concern connected loads. for a breaker in a Class IE RT5 Position Indicatine Licht. At McGuire, red and green lights placed below each of the two xis spring-loaded manual control switches in the control room scrve to indicate whether the associated RTB is closed or open, respectively.
Operators are trained to operate both control switches simultaneously, one with each hand. and to interpret each set of lights as representing the actual status of each breaker.
of indicating continuity of the shunt trip circuit for each breaker.Howeve that the breaker has opened as intended or that the asso circuit has been interrupted.
from the red light behavior alone; ratherDetermining which is the case cannot be done interpreted in combination with the green, lithe red light behavior must be N ,
indications, such as rod position displays. ght behavior and other control room /3 3 Operators need to understand that associated shunt trip circuit is inoperable. tAdditionallyiit after release of ~ the spring-loaded manus 11 control'sw associated brookerihas failed to open in responsei that.immediate local? verification or trip action is'needed.~ At McGuire,to the pressing the manual trip plate at the RTS did not open the breaker, but manipu-lating the manual spring-charging handle did open it.
program for operators to ensure that they understand the various combinations of RTE indications and that they follow appropriate verification procedures for suspected " malfunctions" of these indications.
Trip Latch pivot Pin.
ber 1987, the Ifconsee reported that a Westinghouse 05-416 P to the trip latch (item 51 resulted in disengagement While not of of the i safety concern for an RTB. this failure to close condition would be of concern i for a breaker in a Class IE application requiring energiration of the connected loads. ;
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EXAM KEY CHANGE REQUEST EXAM NO. Y 80'2 bib QUESTION NO. dbd DATE: 3'b'83 REQUESTED BY: d5 " /c t-PROBLEM: b8d_ tt 4 tlMi RECOMMENDATION: ,Mu (;) (/buvt25tdv>Y d cv b RESOLUTION O DELETE FROM EXAM HANGE WORDING AS RECOMMENDED 0 LETSTAND ASIS APPROVAL: DATE: '!
S/N R lt!5TRUCTOR DEVELOPMENT I
TRANSMITTAL
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O SUPERVISOR, SIMULATOR AND TRAINING DEVELOPMENT O OPERATIONS REPRESENTATIVE NUCLEAR REGULATORY COMMISSION
t gs O1 OL OR-0032 !
' During a Safety Injection-actuation,,the annunciator "DG'B GEN:
TRBL" alarms. Which of the'following most correctly details the- H operator's response in'this situation?-
- a. Dispatch an operator:to locally identify the cause of the. . l i alarm and take action (s), as appropriate, in accordance-with ARP-004-XCX-5202.
'l
- b. Trip the diesel generator and carry- out' the . actions detailed '
in choice (a).above.
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- c. Depress GEN RELAYS RESET and' carry out the actions detailed in choice (a) above, f
- d. Depress ENG SD RESET _ and carry out the actions in choice -(a) above.
The revised answer key accepted either answer 'a':orL'c'. L0ur comments on the revised answer key were' j I
"This question has two equally plausible' choices.- The~ARP'for this annunciator says that'an immediate action;is to have an A0 respond similarly to choice 'a'.of this question. Precaution 3
[our revised answer key says Precaution 4] of SOP-306 has an operator perform actions'similar to choice 'c' of this' question.
Since, during an SI, the DG does not tie to the bus, the urgency of attempting to clear the trouble alarm is not as great.
Therefore, during an SI, either answer should be acceptable for j the criteria of "most correctly details".
The ARP for the annunciator "DG B GEN TRBL" lists 8 possible i causes (see attached sheet). The ARP for XCX-5202 outlines the 1 actions to take for each of the possible causes-of the MCB ;
satellite annunciator. Seven of the eight local ARPs are included in this justification. Three of the local ARPs (8-4, 8-2, 7-2) direct the operator to either reset,'or clear, the relay / flag. Two of the local ARPs_(7-3, 8-3) direct the ;
operator to prepare the DG for auto / manual start per SOP-306, !
which involves depressing the GEN RELAYS RESET.pushbutton. !
Refer to the attached drawing (1MS.32-084-8, SCHEMATIC DIAGRAM DG CONTROL PANEL) for this discussion. l i
- 1. Individual relays (51DG, 5'1VDG, 67DG, 46DG, 40DG) are powered through a contact PBX.
- 2. The relays are normally de-energized and are energized when !
they sense a condition in excess of their setpoint.
--.____.____.__.____-____m__~___m.--_ - _ . - - _ _ . _ _ _ - _ _ _ _ _ . _ _ _ . - - _ _ ___m___ __.- . _ _ . _ - . . . _ _ _ _ _ _ .._____._._______.--___m--__.__2_._.._,-.___-____m.4--..__.--- _
. s. ;o 9
- 3. In order to clear / reset the relay / flag, the RESET pushbutton (PB12, local OR S58/59. XCP-6117) must be pushed to energize, the PBX relay, opening the contact PBX, and-de-energizing the individual relay.
- 4. The reset pushbuttons are the GEN RELAYS RESET ~pushbuttons on the local panel (PB-12) and the MCB (S58/59).
Should the conditions have beenl involving a blackout, then.the "most correct" answer would have been' choice 'c'. In this' case, it would be imperative that.the MCB operator attempt to reset the cause of the relay -in a timely manner rather than dispatch an A0 to investigate locally.
l l
i
..; . m.
O ;goas s
i PANEL XCP-637' i ANNUNCIATOR POINT 3-4 .
l l
- DG B GEN See below FR2/1C; FR2/2D; TRBL ,
. FR3/1C; FR4/2A; FR3/2A; FR2/1B; XCX-5202 PROBABLE CAUSE:
l '. System ground. 6. Field failure.
- 2. Reverse power. 7. Overvoltage.
- 3. Negative phase sequence. 8. Overcurrent.=
4.- Generator stator hi temp.
- 5. Field ground.
AUTOMATIC ACTIONS: .
I 1. 'If diesel is running in test mode, trip will occur upon system ground, reverse power, negative phase sequence, field failure, and overcurrent.
MMEDIATE ACTIONS: - -
- 1. . ! Dispatch operator to diesel local panel to identify and attempt to correct cause of alarm. j u
SUPPLEMENTAL ACTIONS:
)
i
- 1. Refer to Technical Specification 3.8.1 for LCO requirements. l
- 2. Have maintenance investigate and repair as necessary. I
REFERENCES:
- 1. GAI DWG B804-637, Sh. 1.
- 2. GAI DWG B208-02_4, DG-13
- 3. Final System Design Description for Diesel Generator.
- 4. 1MS-32-08'4-4 ,5.
- 5. V. C. Summer Technical Specifications.
- - -- A Ammm M^^' .A man n m o n an
O O ARP-004 REVISION '3 PANEL XCX-5202 ANNUNCIATOR POINT 8-4:
SETPOINT: ORIGIN:
FIELD GROUND 64DG Variable 64DG Relay PROBABLE CAUSE:
- 1. This alarm is normal during every field flash (startup).
- 2. Ground on field or field power supply.
3 Relay failure.
AUTOMATIC ACTIONS:
l '
- 1. None.
IMMEDIATE ACTIONS:
- 1. h 1_empt to reset 64DG Rel
- 2. If it will not clear, contact Control Room and recommend shutting down the Diesel.
SUPPLEMENTAL ACTIONS:
- 1. Submit MWR if needed.
- 2. Notify Electrical Maintenance for further assistance.
REFERENCES:
- 1. 1MS-032-084-4.
l 2. SS-200-903 l l
3 l
i t
I l
l
. Q.-
ARP-004
. REVISION 3 PANEL XCX-5202:
ANNUNCIATOR. POINT 8-2 SETPOINT: ORIGIN:
SYSTEM ND l"hg 60 Amps 51DG Relay PROBABLE CAUSE:
- 1. Generator grounded.
- 2. Relay failure.
AUTOMATIC ACTIONS:
- 1. Diesel trip if in Test' Start mode. ,
IMMEDIATE ACTIONS:
- 1. Determine cause of ground nd clear )
i
- 2. Whengroundisclear, pre p(are diesel for auto / manual start per 50P-306.
l SUPPLEMENTAL ACTIONS:
1
! 1. Submit MWR if needed.
- 2. Notify. Electrical Maintenance for further assistance.
REFERENCES:
- 1. 1MS-32-084-4.
l 2. SS-200-903 1
l l
I
1.
}ARP-004 REVISION 3 PANEL XCX-5202 ANNUNCIATOR POINT 7-2 OVERCURRENT SETPOINT: ORIGIN:
51VDG .
480 Amps 51VX Relay -
PROBABLE CAUSE:
- 1. High current due to excessive load or excessive circulating currents.
- 2. Relay failure.
AUTOMATIC ACTIONS:
NOTE:
Alarm only if in Emergency Start Mode.
- 1. If in Test Start Mode, Diesel Generator will trip.
IMMEDIATE ACTIONS:
l 1. If Diesel trips, prepare for auto / manual start per SOP-306.
- 2. If Diesel is still running:
- a. Reduce load to di 4250 KW.
- b. Adjust voltage to bring reactive load down. ;
I l NOTE Generator amps should always be less than one tenth of kilowatt' load. This keeps power factor between 1 and.
0.5.
- c. Take manual control of voltage regulator if it won't spRnd_in_auts
. Reset 51VDG Relay flag) j i
hbb$ kk b@ MM $$$2bbb b@NEOSb@
.y."
O o SOP-306' 1
1 REVISION 10 ,!
I '. PURPOSE-This procedure provides guidelines-and instructions for the 4 j
operation of the Emergency Diesel Generators.
- )
.i II. PRECAUTIONS I
- 1. When LOCAL / REMOTE / MAINTENANCE switch is in MAINTENANCE, the.
Diesel Generator is inoperable per Technical Specifications.
- 2. Before any engine cranking, ensure the following: ,
- a. Manual barring-device is removed.
- b. Turning motor is dis, engaged.
3 During an emergency start, if_ Generator Trouble alarm is-initiated, attempt _to reset by pushing GEN RELAYS RESET.
- 4. When a Diesel Generator is running, do not shift control ~
between local and remote, as governor droop control will be lost causing load cycling /possible engine trip and the test start' relay will drop'out, disabling the associated engine-and generator protective devices.
- 5. Never operate Diesel Generator with lube oil pressure less than 70 psig.
- 6. Whenever Diesel Generator is operated at less than 850 KW for greater than 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />, load to at least 2125 KW (50%
rated load) for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 7. Whenever Diesel Generator is operated at less than 850 KW for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, load to at least 2125 KW for at I
least 1/2 hour.
- 8. The Diesel Fuel Oil Transfer Pump suction strainers should be shifted and cleaned when the differential pressure.
exceeds 3 psid.
- 9. Diesel Generator load should not~ exceed the following ratings: _
- a. 4250 KW continuous,
- b. 4676 KW for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> out of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 1 year.
- c. 4676 KW for 7 days.
- d. 5100 KW for 30 minutes, but maximum rack stop is set at 112% (4760 KW) per Colt Industries recommendation via letter dated December 3, 1985.
PAGE 1 CF 20 GENERAL REVISION
o o
. '.~
ARP-004 _ \
REVISION 3 PANEL XCX-5202 ANNUNCIATOR POINT 7-3 ;
SETPOINT: ORIGIN:
REVERSE 103.68 KW 67DG Relay 67DG l
a I
. i PROBABLE CAUSE: J l
- 1. Not picking up enough load after paralleling to bus. )
- 2. Relay failure, j I
AUTOMATIC ACTIONS:
- 1. Trips Diesel when in Test Start Mode.
l IMMEDIATE ACTIONS:
- 1. pare Diesel for "te/== anni start'oe SOP-306.
- 2. Operate Diesel Generator as directed byTcini.rcl com.
SUPPLEMENTAL ACTIONS:
l
- 1. Notify Electrical. Maintenance for further assistance.
l 1
REFERENCES:
- 1. 1MS-32-084-4.
- 2. SS-200-903.
3 SOP-306.
l
.l I
f9AC& M ffhrf M9 82ffl&BAJL S&WFBVBM I
" . . - '. I '* O V .dr ARP-004 REVISION 3 PANEL XCX-5202 ANNUNCIATOR POINT 8-3 SETPOINT: ORIGIN:
NEGATIVE PHASE SE NCE 46DG Relay 484.5 Amps PROBABLE CAUSE:
- 1. Improper connections on Generator or breaker wiring after maintenance.
! 2. Generator unbalance fault.
AUTOMATIC ACTIONS: ,
- 1. Causes Diesel trip in Test Start mode. -
IMMEDIATE ACTIONS:
- 1. Notify Control Room.
- 2. Check direction of air flow on Diesel Generator cooling fan upstairs in the Diesel Building.
SUPPLEMENTAL ACTIONS:
- 1. Submit MWR to have wiring checked.
- 2. If (30'6._'~~
. Diesel
~ 'trippedfpFEpiiire
/WYALfoF VESau'tB5anual g e N p!f tA ysptart K E3 per SOP-6 7 w%tkut 3 Notify Electrical Maintenance for further assistahce. .J
REFERENCES:
- 1. 1MS-94B-084-4. !
- 2. SS-200-903.
3 SOP-306. -
I i
e I
BAra& M6 frh8 M2 (S&fM& BfMT B 27/9 2 Vf601
O O ARP-004 REVISION 3 PANEL XCX-5202 ANNUNCIATOR POINT 8-5 FIELD FAILURE SETPOINT: ORIGIN:
ODG Variable 40DG Relay PROBABLE CAUSE:
l 1. Failure of field to flash.
l 2. Fault in field circuitry.
- 3. Relay failure.
AUTOMATIC ACTIONS: ,
- 1. Trips DG output breaker in the Test Start mode. '
I l
IMMEDIATE ACTIONS:
- 1. Check Generator voltage and if no voltage is indicated 3 momentarily flash the field.
- 2. If generator voltage still is not present, perform the following:
- a. Depress Exciter Shutdown.
- b. Depress Exciter Reset.
- c. Turn Field Flash to flash for 10 seconds.
SUPPLEMENTAL ACTIONS:
- 1. Submit MWR to determine cause of field failure.
- 2. hotify Electrical Maintenance for further assistance.
REFERENCES:
- 1. 1MS-032-084-4.
- 2. SS-200-903.
QAGQ ho G RR Dn a G@NGR A G Q9T 99 9 Aa0
o O
~ ARP-004 REVISION 3 PANEL'XCX-5202 ANNUNCIATOR POINT 7-4 GENEFATOR- SETPOINT: ORIGIN:
8 hN 140*C ITY-15472B-TEMPERATURE l
PROBABLE CAUSE:
- 1. Sustained high current load.
2.- Loss of room cooling fan.
3 Instrument failure.
AUTOMATIC ACTIONS:
- 1. None.
IMMEDIATE ACTIONS:
- 1. Reduce circulating currents by adjusting voltage.
- 2. Reduce load if possible.
3 Check other temperature indicators.
- 4. Insure room cooling fan is running (HVAC panel behind Main Control Board).
SUPPLEMENTAL ACTIONS:
- 1. Submit MWR's if needed.
- 2. Notify Electrical Maintenance for further assistance.
l
REFERENCES:
- 1. 1MS-32-084-04.
- 2. SS-200-903 1
^
d o
9 j
, SOP-306 q REVISION l'O. 2 i
III. NORMAL OPERATIONS i
A. FB3PARATION FOR AUTOMATIC / MANUAL START 9
1.0 INITIAL CONDITIONS l I
1.1 Valve lineup is complete per Attachment IA (IB).
1.2 Electrical lineup is complete per Attachment IIA (IIB).
CAUTIbN 1.3 When LOCAL / REMOTE / MAINTENANCE switch is placed in MAINTENANCE, the Diesel Generator is inoperable.
13 Control Panel lineup is complete per Attachment IIIA '
(IIIB).
1.4 Service Water is operating and aligned to supply Diesel Generator per SOP-117.
1.5 Diesel Fuel Oil System is algined for operation per l SOP-307
]!
1.6 011 levels for Air Start Compressors are above' add mark.
I 1.7 Lube oil sump level is above add mark on sump dip stick. ]
1.8 Rocker arm lube oil reservoir sight glass level is at least 3/4 full.
1.9 Left and right air start distributor lubricator oil level is above dipstick's notch. j 1
1.10 The barring device engagement tool is completely removed.
1 1.11 Turning motor is disengaged. ;
1.12 Diesel Generator HVAC is aligned per SOP-503 i 1.13 All cylinder test cocks are closed.
1.14 Jacket water head tank is filled to greater than 3/4 full as indicated by gauge glass.
1.15 Injection nozzle cooling water sight glasses should be i i
full. If not, check for steady stream once engine starts, 4
PAGE 3 0F 20 GENERAL RFVISION
_________-___-_____w
l t.
O O .
SOP-306 REVISION 10 I
1.16 Diesel Generator governor settings are as follows:
- a. Load-Limit: Max Fuel b.- Speed Droop: 3.0
- c. Speed: DG-A, 14.12 D9-B,'16.06 f I
1.17 Diesel Generator turbocharger oil (sightglass marks) le' vel l is between the red and white marks. 8 1
2.0- INS *1RbCTIONS 2.1 -Manually open and close'er.ch drain valve on the air receivers to blow down any water:
- a. XVP-10083A(B)-DG, AIR START RECEIVER TANK 9A(9C) DRAIN VALVE.
- b. XVP-10984A(B)-DG, AIR START RECEIVER TANK 9B(9D) DRAIN VALVE.
2.2 Verify compressors recharge the receivers to 425 psig if pressure dropped-below 375 psig during the' blowdown
~
(LOCAL).
23 Place the LOCAL / REMOTE / MAINTENANCE switch in REMOTE.
2.4 Perform the following fr'om the Diesel Generator Local-Control Panel:
- a. Depress ENGINE SHUTDN RESET pushbutton._ i
- b. Depress EXCITER RESET pushbutton.-
Depress GEN EELAYS RESET pushbutto
- d. Verify READY,FOR AUTO START light illuminated.
2.5 Perform the following from the Main Control Board:
- a. Depress ENG SHUTDN RESET pushbutton.
- b. Rotate EXCITER switch to RESET position.
- c. Depress GEN RELAYS RESET pushbu
/ . i d.7erify D/G A (B) AttTO-START- NOi HEA_DY annunciator is ;
clear. j 1
PAGF 4 0F 20 GENERAL REVISION
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V. C. SUMMER REQUALIFICATION EXAM ,
Week of February.24, 1989 l
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O O
- V U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER REACTOR OPERATOR ANNUAL REQUALIFICATION EXAMINATION PART "A" SCENARIO #SS01 (ANSWER KEY)
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS POINTS A. Plant Operations 16.0 Submitted By: 1 %
/? 1
/ J-//-f'/
h /y' Date Approved:- -
/72 h/i V
' SupervisoE,Simu Training Develo nt And ' Dale 1
'f. ,
1987 - 1988 Annual Requalification Examination :
Part A (Answer Key) 1 QUESTION: SS01001 TIME: 5 MIN POINT VALUE:2.0 )
Determine whether any of the Critical Safety Functions are not fully satisfied, and if ' l any are less than fully satisfied, state the appropriate level of challenge (ie, solid, !
dashed, or dotted path). (2.0)
ANSWER:
1 Core cooling (.5) dotted path (.5) !
Heat sink (.5) dotted path (.5)
COMMENTS:
Requires use of EOP-12.0 i
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i 1987 - 1988 Annual Requalification Examination Part A (Answer Key) i QUESTION: SS01-005 TIME: 5. MIN POINT VALUE:la Which signal was the most likely cause of the Emergency Feedwater Pump "A" start? (1.0) !
l ANSWER:
Loss of all Main Feedwater Pumps (1.0)
COMMENTS:- !
i Requires knowledge of plant conditions and reference to Westinghouse logic sheet #14.
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1987 - 1988 Annual Requalification Examination- {
Part A (Answer Key) j QUESTION: ss01-006 TIME: 5 MIN POINT VALUE:L5_-
If SI termination criteria per EOP-1.0 were to be checked now, the criteria would: '(1.5) j j
- a. Not be met
- b. Be met for the existingconditions
- c. Be met when a S/G narrow range level exceeds 38% ,
- d. Be met when pressurizer level exceeds 39% -
ANSWER:
a (1.5)
COMMENTS:
Requires reference to EOP-1.0 and evaluate existing plant conditions to t determine if termination criteria exists. i 1
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. .O O o 1987 - 1988 Annual Requalification Examination Part A (Answer Key) t QUESTION: SS01-007 TIME: 3 MIN : POINT VALUE:1.0 What would be the proper action (s) for the Reactor Operator to take in order to i mitigate the accident. (1.0) l ANSWER:
Close MVG-8000A or (1.0)
-l' Close PCV-456A kb I COMMENTS: l Requires reference to EOP-1.0, Rev. 2 )
MVG-8000A is the isolation valve for PCV-455A l Requires evaluation of RCS pressure less than 2315 psig PI-402B failed complicates this evaluation l
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f O. O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: ss01-008 TIME: 4 MIN POINT VALUE:.75 Identify the major component that is collecting the number one seal leakoff from the Reactor Coolant Pumps. (.75)
ANSWER:
Pressurizer ReliefTank. (.75) l COMMENTS:
l Requires knowledge of seal leakofisystem and analyzinqreason for flow. Location of relief valve in relation to leakoff flow transmitter is veriaed on D-302-671 and D-302-673 l
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l 1987 - 1988 Annual Requalification Examination {
Part A (An'swer Key) j QUESTION: SS01-011 TIME: 4 MIN POINT VALUE:1.5 l The lack of any indicating light for WR loop 1 TH on subcooling monitor"A" indicates: (1.5)
- a. The input from that temperature detector is defeated or out of range,
- b. That temperature input is Not selected by the autioneer circuit. -
- c. That temperature input is the temperature selected by the auctioneer circuit.
- d. That particular input is not used on this subcooling monitor. i l
ANSWER:
I a (1.5) . '
COMMENTS:
Re uires reference to SOP-410 which says the green light will go out when the input is sabled. l j
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4 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: Ss01013 TIME: 6 MIN POINT VALUE:1.25-The Turbine Driven Emergency Feedwater Pump is not running at the present because: (1.25) a.The SI start signal was overridden
- b. The turbine driven pump started and then tripped on low oil pressure
- c. The turbine driven pump is not lined up for proper automatic operation
- d. There are no start signals at present ANSWER:
d (1.25)
COMMENTS:
Reguires referring to Westinghouse logic sheet 14 and' lack of annunciators indicating trip verification of proper lineup 1
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- l 1987- 1988 Annual Requalification Examination Part A (Answer Key) l
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QUESTION: SS01-014 TIME: 5 MIN . POINT VALUE:1j!
Determine whether or not a reactor vessel bead steam bubble is forming. Support your decision with at least two diverse indications. (1.5)
ANSWER:
A reactor vessel bubble is not forming (.5).
any two for(.5) points each
- 1) RV level normal and stable (.5)
- 2) Subcooling >0*F (.5)
- 3) Pressurizer level not rapidly increasing Accept alternate answers if applicable.
COMMENTS:
Requires reference to EOP.12.0 and knowledge of saturation conditions.
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1987 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: SS01-015 TIME: 3 MIN POINT VALUE:1.5 The core cooling indications, at the present time and for t.he most conservative value, indicates that: (1.5)
- a. The highest RCS temperature is 18 i 2 degrees F below saturation temperature as determined by lowest pressure,
- b. The lowest RCS temperature is 18 2 degrees F below saturation temperature as determined by highest pressure,
- c. The highest RCS temperature is 46 i 2 degrees F below saturation temperature as determined by lowest pressure.
I d. The lowest RCS temperature is 46 t 2 degrees F below saturation temperature as determined by highest pressure.
ANSWER:
a (1.5)
COMMENTS:
Requires knowledge ofinterpretation of subcooling monitor readings.
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.1987 - 1988 Annual Requalification Written Examination Part A Answer Key j QUESTION: SSG1-019 TIME: 10 MIN . POINT VALUE:4.0 i With respect to the Immediate Operator Action Steps of EOP-1.0, indicate what condition (s),if any, may not be consistent with theImmediate Action Steps. Address each step separately if a condition is not consistent with it. (4.0) i ANSWER:
(all at 0.4 points each)
RTB "A" Shut Turbine Stop Valve #2 Open Exciter field breaker not open SITrain "A"Not Actuated (Train "A" ESF loading sequencer lights not actuated)
FW Flow Control Bypass Valves Not All Shut SGBD PVG 503C open Train "A"RHR Pump Not Running Trair."A" SI/ Phase A Status Lights Not All Bright Only One RBCUIn Slow Speed Only One SWBP Running COMMENTS: d Requires analysing Main Control Board indications and verifying against EOP-1.0 Immediate Action Steps. Changes made to incorporate previously unaddressed {
correct answers and answers inadvertently left off key. Point values redefined appropriately.
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U. S. NUCLEAR REGULATORY COMMISSION t V.C. SUMMER SENIOR REACTOR OPERATOR ANNUAL REQUALIFICATION' EXAMINATION
. PART "A" SCENARIO #SS01 (ANSWER KEY) i l
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS POINTS A. Plant Operations 16.25 i
i Submitted By: / .
/ 3/7i')
/ , gy Date Approved: _/ / /r f
// '
Supervisor, S' lator And Training-Development DatI i
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O O i 1987 - 1988 Annual Requalification Examination {
Part A (Answer Key) i QUESTION: SS01001 TIME: 5 MIN
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POINT VALUE:2.0 !
Determine whether any of the Critical Safety Functions are not fully satisfied, and if !
any are less than fully satisfied, state the appropriate level ofchallenge (ie, solid, dashed, or dotted path). (2.0) l ANSWER:
Core cooling (.5) dotted path (.5)
Heat sink (.5) dotted path (.5)
COMMENTS:
l Requires use ofEOP-12.0 l
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O O 1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SS01-004 TIME: 5 MIN POINT VALUE:1.0 Determine the most conservative emergency action level that should be declared for the existing plant conditions assuming that this trend continues and all operator actions are unsuccessful to mitigate the accident. (1.0)
- a. NUE
- b. Alert .
- c. Site
- d. General ANSWER:
- e. (1.0)
NOTE: Accept answer b. if qualified that escalation to site area when PRT Rupture disc blows.
COMMENTS:
Requires applying plant conditions to Emergency Plan action levels and evaluating and extrapolating PRT conditions to assume rupture dise lifting and leakage to RB. Change made to allow selection of EAL for existing conditions if qualification made on when escalation to site area.
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1987- 1988 Annual Requalification Examination Part A (Answer Key) !
QUESTION: SS01-005 TIME: 5. MIN POINT VALUE:J,&
Which signal was the most likely cause of the Emergency Feedwater Pump "A"
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start?
(1.0) . d ANSWER: 1 Loss of all Main Feedwater Pumps (1.0)-
COMMENTS:
Requires knowledge of plant conditions and reference to Westinghouse logic .i sheet #14.
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O O 1 1987 - 1988 A~nnual Requalification Examination Part A (Answer Key) -)
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l QUESTION: SS01-006 TIME: 5 MIN POINT VALUE:ll i If SI termination criteria per EOP-1.0 were to be checked now, the criteria would:
(1.5)-
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- a. Not be met !
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- b. Be met for the existing conditions - '
i c. Be met when a S/G narrow range level exceeds 38%
- d. Be met when pressurizer level exceeds 39%
I l ANSWER: );
! a (1.5)
COMMENTS:
Requires reference to EOP-1.0 and evaluate existing plant conditions to
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determine if termination criteria exists.
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O O 1987 1988 Annual Requalification Examination i
f Part A (Answer Key) i
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QUESTION: SS01-007 TIME: 3 MIN . POINT VALUE:1_& l What would be the proper action (s) for the Reactor Operator to take in order to I mitigate the accident. (1.0) l ANSWER:
Close MVG-8000A or (1.0)
Close POV-COMMENTS:
Requires reference to EOP-1.0, Rev. 2 MVG-8000A is the isolation valve for PCV-455A Requires evaluation of RCS pressure less than 2315 psig PI-402B failed complicates t.iis evaluation
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1987 - 1988 Annual Requalification Examination l Part A (Answer Key) l 4
QUESTION: SS01-011 TIME: 1 MIN POINT VALUE:14 The lack of any indicating light for WR loop 1 TH on subcooling monitor "A"
. indicates: -(1.5) ;
- a. The input from that temperature detector is defeated or cut of range. .
- b. That temperature input is Not selected by the autioneer circuit. ,
- c. That temperature input is the temperature selected by the auctioneer circuit.
- d. That particular input is not used on this subcooling monitor.
ANSWER:
a (1.5) ..
COMMENTS:
Reguires reference to SOP 410 which says the green light will go out when the input is disabled.
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' 1 1987 - 1988 Annual Requalification Examination j Part A (Answer Key) l QUESTION: SS01-013 TIME: 6 MIN POINT VALUE:1.25 I The Turbine Driven Emergency Feedwater Pump is not running at the present l because: (1.25)
- a. The SIstart signal was overridden ;
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- b. The turbine driven pump started and then tripped on low oil pressure _ l
- c. The turbine driven pump is not lined up for proper automatic operation
- d. There are no start signals at present 1
1 ANSWER: -i d (1.25)
COMMENTS:
Reguires referring to Westinghouse logic sheet 14 and lack of annunciators indicating trip, verification of proper hneup.
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.o o 1 1987 - 1988 Annual'Requalification Examination i Part A (Answer Key)
QUESTION: SS01014 TIME: 5 MIN POINT VALUE:1_j! l Detennine whether or not a reactor vessel head steam bubble is forming. Support -j your decision with at least two diverse indications. (1.5) ]
ANSWER:
A reactor vessel bubble is not forming (.5). j any two for(.5) pointa each
- 1) RV level normal and stable (.5) {
- 2) Subcooling > 0*F (.5)
- 3) Pressurizer level not rapidly increasing Accept alternate answers if applicable.
l COMMENTS: .
Requires reference to EOP-12.0 and knowledge ofsaturation conditions. I l
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O O i 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: SS01-015 TIME: 1MINl POINT VALUE:11 '
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The core cooling indications, at the present time and for the most conservative value, _ I, indicates that:' (1.5)
- a. The highest RCS temperature is 18 t 2 degrees F below saturation 1
temperature as determined by lowest pressure.
- b. The lowest RCS temperature is 18 i 2 degrees F below saturation . s temperature as determined by highest pressure. .
- c. The highest RCS temperature is 46 i 2 degrees F below saturation temperature as determined by lowest pressure,
- d. The lowest RCS temperature is 46 i 2 degrees F below saturation temperature as determined by highest pressure.
ANSWER: '
a a (1.5) ]:
- 1 COMMENTS
- =l Requires knowledge ofinterpretation of subcooling monitor readings.
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t 1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SS01-019 TIME: 10 MIN POINT VALUE:4.0 With respect to the immediate Operator Action Steps of EOP-1.0, indicate what condition (s),if any, may not be consistent with the Immediate Action Steps. Address each step separately if a condition is not consistent with it. (4.0)
ANSWER:
(all at 0.4 points each)
RTB "A" Shut Turbine Stop Valve #2 Open Exciter field breaker not open SI Train "A" Not Actuated (Train "A" ESF loading sequencer lights not actuated)
FW Flow Control Bypass Valves Not All Shut SGBD PVG 503C open Train "A"RHR Pump Not Running Train"A"SI/ Phase A Status Lights Not All Bright Only One RBCUIn Slow Speed Only One SWBP Running COMMENTS:
Requires analysing Main Control Board indications and verifying against EOP-1.0 1 Immediate Action Steps. Cha,nges made to incorporate correct answers and answers inadvertently left ofikey. previously Pointvalues unaddressed redefined appropriately.
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- , O O U. S. NUCLEAR REGULATORY COMMISSION l V.C. SUMMER REACTOR OPERATOR ANNUAL .REQUALIFICATION EXAMINATION ,
PART "A" SCENARIO #SSO9 l (ANSWER KEY)
FACILITY: V.C. Summer j REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE: '
SECTION: TOTAL
)
CANDIDATE 'S POINTS POINTS A. Plant Operations 6,25 -
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Submitted By: 44 - / 3 ~~ I 7' ) 7 Approved:
[ /R 2
// ' Supervisor,St OTator And bate
/, Training))>velopment I
., . O .O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
L l QUESTION: SSO9-003 TIME: 4 MIN POINT VALUE:LO Have all of the required actions due to the Loop A control TH failure in regard to manipulations on the Main Control Board been completed properly? Justify your answer. (1.0)
ANSWER:
No (.5) Tavg defeat switch not selected (.5)
COMMENTS:-
Requires comparing AOP-401.1 required actions with control board switch configuration.
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. O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)-
. QUESTION: SS09-004 TIME: 6 MIN POINT VALUE:.75 If additional loads were placed on Bus IDA at this time, with no other operator .
actions, the bus IDA voltage would: (.75) .
- a. decrease
- b. increase
- c. remain the same
- d. go to zero due to D/G trip
' ANSWER:
a (.75)
COMMENTS:
Requires determination that DG is running in test start mode and that voltage droop is active.
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1987- 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: SSO9-005 TIME: 10 MIN ' POINT VALUE:15 What IDA?
major steps would be required to restore normal power supply to bus (1.5)
ANSWER:
- 1. Remove XTF-4 from service (.5)
- 2. Close XTF4-5 tie breaker (.5)
- 3. Parallel XTF-5 back snto Bus IDA (.5)
Also accept: Reset XTF-4 lockout for #1 COMMENTS:
Requires method analyzing ofrestonng plantpower.
normal conditions and, without procedural guidance, synthesize
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1987 - 1988 Annual Requalification Written Examination .l Part A Answer Key j QUESTION: SS09-006 TIME: 5 MIN POINT VALUE:.75 Identify which (may be more than one) of the following item (s) that would restore instrument air to the Reactor Building? (.75)
- a. Start A Instrument Air Compressor
- b. Restart RB Air compressor B
- c. Open XVB-2633 IA Backup Sys Isol Valve I
- d. Open XVG-2659 Inst Air to RB Air Serv ANSWER:
- d. (.75) l COMMENTS:
i Requires analyzing existing conditions and synthesizing a solution. Deleted because RB air compressor did not have enough time to trip during scenario setup. There i was no loss of RB instrument air. j j
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O O 1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SSO9-007 TIME: 6 MIN POINT VALUE:1.0 Would a Limiting Condition for Operation be met if the ESF bus IDA were to be placed on XTF-31? Justify your answer. (1.0)
ANSWER:
LCO would not be met (.5) because no indi pendence between offsite sources (.5).
NOTE: Accept the answer "YES" for full ( redit if thejustification for answer indicates the examinee is supporting a decisic.2 that the LCO would not be met.
COMMENTS:
Requires applying Tech Spec 3.8.1.1 to jven conditions. Change necessary because some examinees are interpreting "Wou .d LCO be met?" as "Would LCO be exceeded"?
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1987 - 1988 Annual Requalification Written Examination i Part A Answer Key .
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QUESTION: SS09-008 TIME: 4 MIN POINT VALUE:1.0 Determine the correct poten tiometer settings for FCV-113A and j FCV-168.' (l'.0) -l 1
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ANSWER: !
FCV-113A - 4.8 +/ .02 (.5) l FCV-168 - 7.50 (no tolerance)(.5)
COMMENTS:
I Requires using existing boron concentration, determining they are in auto makeup l mode, and determining values from curve book.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key l T L ,l QUESTION: SS09-009 TIME: 8 MIN POINT VALUE:1.0 -
Annunciators "CRB INSERT LMT LO-LO" and "CRB INSERT LMT LO" are most likelyin because:
(1.0) .
- a. Control rods are below the RIL
- b. Failure ofcontrolchannelloop AT
- c. Failure of control channel loop Tavg d.P/A converters are setimproperly ANSWER:
d (1.0)
COMMENTS: I Requires analyzing plant conditions to determine which is the cause of the referenced annunciators. Reference to PLS and T.S. Figure 3.1.1. Deleted because 1 RIL recorder indicated P/A converters were set properly (ie no correct answer). l l
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1987 -'1988 Annual Requalification Written Examination l Part A Answer Key 1 QUESTION: SS09-010 TIME: 4 MIN POINT VALUE:1.0 1 What temperature will RCS Tavg go to if the reactor tripped under these conditions?
Explain your answer. s u (1.0).
ANSWER: J 553*F (.5) Failed high Tavg cau'ses steam dumps to stay open until Lo-Lo Tavg I interlock closes valves (.5).
NOTE: If-examinee missed SS09-003 and did not identify properly that failed l
- .._ Tavg was not blocked, then, carry error forward and give full credit for
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, ,", - -557 (.5) restored by trip controller (.5)".'
COMMENTS:
l Requires recognizing that auctioneered high Tavg is failed high and not blocked. .,
Steam dump will close at Lo-Lo Tavg interlock. Chang ~e made to prevent double 1 jeopardy _with SSO9303., ~
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... ... O O U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER SENIOR REACTOR OPERATOR ANNUAL REQUALIFICATION EXAMINATION PART "A" SCENARIO #SSO9 (ANSWER KEY)
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS PO!NTS A. Plant Operations 7.25 Submitted By: // F <+ /
l /b \,' l Date
/z, , / ,r ,-
Approved: b '
e /$ 2
[
(, '
/ / j$up~erv* isor, Si lator And Training velopment Date .
O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: SSO9-001 TIME: 5 MIN POINT VALUE:1.'0 .
Determine if there are any conditions that would require immediate notification of the Management Duty Supervisor and if so, state them. (1.0)
ANSWER:
Loss ofnormal power to Bus IDA. (1.0)
[Also accept ESF actuation]
COMMENTS:
Requires comparing plant conditions to SAP-109.
Student may also refer to SAP.132 for ' specific MDS notifications i
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O o 1987 - 1988 Annual Requalification Examination '
Part A (Answer Key) i QUESTION: SSO9-003 TIME: 4 MIN POINT VALUE:1.0 !
Have all of the required actions due to the Loop A controlTH failure in regard to i manipulations on the Main Control Board been completed properly? Justify your J answer. (1.0)
ANSWER: .
No (.5) Tavg defeat switch not selected (.5) i COMMENTS: '
Requires comparing AOP-401.1 required actions with control board switch configuration. !
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O O 1987 1988 Annual Requalification Examination Part A (Answer Key) i QUESTION: SS09 004 TIME: 6 MIN J POINT VALUE:.1 If additional loads were placed on Bus IDA at this time, with no other operator:
actions, the bus IDA voltage would: (.75) -
- a. decrease ' !
- b. increase
- c. remain the same
- d. go to zero due to D/G trip ANSWER:
a (.75) j 1
COMMENTS:
Requires determination that DG is running in test start mode and that voltage droop, i is active. -
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O O l 1987 - 1988 Annual Requalification Examination Part A (Answer Key) 1 QUESTION: SSO9-005 TIME: 10, MIN POINT VALUE:1.5 What major steps would be required to restore normal power supply to bus IDA? (1.5)
ANSWER:
- 1. Remove XTF-4 from service (.5)
- 2. Close XTF4-5 tie breaker (.5)
- 3. Parallel XTF-5 back onto Bus IDA (.5)
Also accept: Reset XTF-4 lockout for #1 COMMENTS:
Requires analyzing plant conditions and, without procedural guidance, synthesize a.,
method of restonng normal power.
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l 1987 - 1988 Annual Requalification Written Examination l Part A Answer Key QUESTION: SS09-006 TIME: 5 MIN . POINTVALUE:.75 ~ !
l Identify which (may be more than one) of the following item (s) that would res' tore - !
instrument air to the Reactor Building? (.75) -I
- a. Start A Instrument Air Compressor
- b. Restart RB Air compressor B .
- c. Open XVB-2633 IA Backup Sys Isol Valve
- d. Open XVG-2659 Inst Air to RB Air Serv ANSWER: l j
- d. (.75)
COMMENTS:
Requires analyzing existing conditions and synthesizing a solution. Deleted because RB air compressor did not have enough time to trip during scenario setup. There was no loss of RB instrument air.
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. O O 1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SS09-007 TIME: 6 M!N POINT VALUE:1.0 Would a Limiting Condition for Operation be met if the ESF bus IDA were to be placed on XTF-31? Justify your answer. (1.0)
ANSWER:
LCO would not be met (.5) because no independence between offsite sources (.5).
NOTE: Accept the answer "YES" for full credit if thejustification for answer indicates the examinee is supporting a decision that the LCO would not be met.
COMMENTS:
Requires applying Tech Spec 3.8.1.1 to given conditions. Change necessary because some examinees are interpreting "Wou d LCO be met?" as "Would LCO be exceeded"?
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1987 - 1988 Annual Requalification Examination Part A (Answer Key) .
QUESTION: SSO9-008 TIME: 4 MIN POINT VALUE:1.0 "
Determine the correct potentiometer settings for FCV 113 A and FCV-168. (1.0)
ANSWER:-
FCV-113A - 4.8 +/ .02 (.5) -
FCV-168 - 7.50 (no tolerance)(.5)
COM.M~ENTS: j Requires using existing boron concentration, determining they are in auto makeup #
mode, and determimng values from curve book.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key I ;
L 4 QUESTION: SS09-009 TIME: 8 MIN POINT VALUE:1.0 Annunciators "CRB INSERT LMT LO-LO" and "CRB INSERT LMT LO" are most likelyin because:
(1.0)
- a. Control rods are below the RIL
- b. Failure of control channelloop AT
- c. Failure of cont rol channel loop Tavg
- d. P/A converters are setimproperly ANSWER:
d (1.0) l l
COMMENTS:
Requires analyzing plant conditions to determine which is the cause of the referenced annunciators. Reference to PLS and T.S. Figure 3.1.1. Deleted because RIL recorder indicated P/A converters were set properly (ie no correct answer).
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1987.- 1988 Annual Requalification Written Examination 2 Part A Answer Key QUESTION: SS09-010 TIME: 4 MIN POINT VALUE:1.0 What temperature will RCS Tavg go to if the reactor tripped under these conditions?
Explain your answer. (1.0)
ANSWER:
553*F (.5) Failed high Tavg causes steam dumps to stay open until Lo-Lo Tavg interlock closes valves (.5).
NOTE: If examinee missed SSO9-003 and did not identify properly that failed Tavg was not blocked, then, carry error forward and give full credit for:
"557 (.5) restored by trip controller (.5)".
COMMENTS:
Requires recognizing that auctioneered high Tavg is failed high and not blocked. '
Steam dump will close at Lo-Lo Tavg interlock. Change made to prevent double jeopardy with SS09-003, i
l I
sy . O O l U. S. NUCLEAR-REGULATORY COMMISSION V.C. SUMMER SENIOR REACTOR OPERATOR ANNUAL REQUALIFICATION-EXAMINATION- ;
PART "B" WRITTEN :
(ANSWER KEY) !
i FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE:
1 SECTION: TOTAL CANDIDATE 'S POINTS POINTS 1 B. Limits and Controls 21.25 l
l Submitted By: _.
/ 290'$ f I O Date Approved: c c / 70/t'7 l [' [ '. ' Supervisor ianulatorAnd Train' evelopment Date All work done on this examination is my own,I have neither stiven nor received aid.
Candidate's Signature
s .. O. O 1987 -;1988 Annual Requalification Examination Part A (Answer Key) - i QUESTION: OR-0005 TIME: 3 MIN . POINT VALUE:1.0 EOP-1.0 Step 16b. has the RO stop all Reactor Coolant Pumps. The basis for this -
stepis that:
- a. Reactor Building spray would cause shorting of motor.' i
- b. Pha' se B isolation signal has isolated cooling to motors. .
- c. Peak clad temperatures are calculated to be lower if pumps are tripped early.
- d. Inventory loss is higher if the pumps are left on.
ANSWER: '.
- b. (1.0)
COMMENTS:
None j
)
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- /
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1987 - 1988 Annual Requalification Examination ~.
Part A (Answer Key)
QUESTION: OR-0013 TIME: 8 MIN POINT VALUE:1.0 Source Range Channel N-32 is out of service for three weeks due to detector problems. Following a Reactor Trip it is noted that APN-5901 is faulted and de-
. energized. Electricians estimate 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore bus. What should be done to restore flux monitoring capabilities and when should it be done.
ANSWER:
Energize high voltage to N-33 at the Control Room Evacuation Panel (.5). This should not be done for at least 15 minutes (.5) -
following the reactor trip.
COMMENTS:
EOP-8.0 .
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1987 - 1988 Annual Requalification Examination'. '
Part A (Answer Key)
QUESTION: OR-0016 TIME: 8 MIN : POINT VALUE:0.75' i Following a reactor trip and safety injection due to a LOCA, a loss of 7.2 KV- l
- emergency bus IDA has occurred due to a bus fault. What operator action is necessary to respond to the challenged barrier between post-LOCA RB atmosphere ;
and the environment? Assume that ten minutes have elapsed since the LOCA and IDA hasjust failed.)
ANSWER: )
Close the RBCU return to SW pond (0.5) isolation valve for the SW booster pump D thatis off. (0.25)
COMMENTS: !
1
)
I 1
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. O Q j 1987 - 1988 Annual Requalification Examination I
- Part A (Answer Key) l i
1 QUESTION: OR-0123 TIME: 6 MIN. MIN . POINT VALUE:LO The plant has experienced a reactor trip due to a sustained loss of the service buses.
Bus IB3 is being' fed from Bus 1DB1 through the Bus 1B3 - 1DB1 TIE BKR. EOP-1.3 3 1
is being used to cooldown the RCS. In order to minimize the possibility of creating a j steam bubble in the reactor vessel hesd, what is the minimum amount of subcooling required? (1.0) l ANSWER:
130'F- (1.0)
COMMENTS:
EOP.1.3, step 3 requires determination of number of CRDM fans running. Bus 1B3 :
powers XFN-67B (SOP-114, Att. IIA) but at least 2 CRDM fans must be running to reduce subcooling requirements to 80 'F. .
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% ,G a 1987 - 1988 Annual Requalification Examination .
Part A (Answer Key) / !
QUESTION: OR-0028 TIME: 4 MIN POINT VALUE:1.0 - l During a response to safety injection, one diesel generator received an "DG ENG .' i START FAIL" annunciator. The IB Operator reported back that the cause was low.
air pressure but it is corrected and air pressure is adequate for another start signal.
The start failure relay now has to be reset by depressing the: !
1 i
- a. Engine Shutdown Reset pushbutton, j
)
- b. Emergency Start pushbutton. q
.l
- c. Generator Relays reset pushbutton.
- d. Emergency Start reset pushbutton. ..
ANSWER:
- a. (1.0)
COMMENTS:
Knowledge of reset functions from MCB.
J
.. . O '
b 1987 - 1988 Annual Requalification Examination -
.Part A (Answer Key) ~
. QUESTION: OR-0030. TIME: 3 MIN POINT VALUE:1.0 --
A steam generator tube ruptured and the the operating crew performed a rapid cooldown and depressurization per EOP-4.0, Steam Generator Tube Rupture.' Which of the following is TRUE concerning the subsequent operation of the RCPs? -
- a. The RCPs must be secured at 1380 psig.
~
- c. The RCPs must be left running under all conditions to assure core cooling,
- d. The RCPs raay be left running because it is an operator initiated .
cooldown.
ANSWER:
- d. (1.0)
COMMENTS:
Tests knowledge of bases of RCP trip criteria.
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O' O 1987 - 1988 Annual Requalification Examination-Part A (Answer Key)
QUESTION: OR-0038 TIME: 5 MIN POINT VALUE:2.0 For the leakage conditions shown below, indicate whether or not the leak exceeds the limiting condition for operation in Technical Specification. (within specified time requirements). Consider each condition separately. Assume no other concurrent leakage.
(a) 0.5 GPM loop drain valve bodyleak.
.(b) 1.2 GPM loop drain valve body to bonnet seal leak.
(c) 1.2 GPM unknown leakage.
(d) 3.0 GPM seat leakage from a pressurizer safety valve. .
ANSWER:
(a) exceeds (0.5) (pressure boundary) d (b) does not exceed (0.5) Identified Non-press bounde.ry I (c) exceeds (0.5)
(d) does not exceed (0.5)
COMMENTS:
Requires operator to determine what type ofleakage there is; then compare T.S. limits. j I
1 s
_ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ J
V
/"Y ' X-V 1987 - 1988 Annual Requalification Examination
.Part A (Answer Key).
QUESTION: OR-0041 TIME: 3 MIN POINT VALUE:1.0 The unit has tripped from 100% power due to large LOCA and a loss of offsite power has occurred. "A" emergency diesel ~ generator (DG) has started and loaded, but "B"
. DG has failed to start. While performing step 8a of EOP-1.0, the Reactor. Operator-notices that two charging pumps (A and C) are running on bus IDA.The "A" DG -
load is 5150 KW. The reactor operator should:
- a. Go on with EOP-1.0 as he has adequately verified step 8a'.
- b. Attempt to align 'C' pump to 'B' train injection using remotely .
controlled valves.
- c. Immediately trip one of the two charging pumps. .
q I
- d. Attempt to restore 'B' charging pump, and after restoration of'B', trip the 'C' pump. "
- ANSWER:
e (1.0)
COMMENTS:
Requires knowledge of ESFLS actions. Requires determination of overload .
conditions per SOP-306 .
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____________-_)
d O h .
1987 - 1988 Annual Requalification Examination I Part A.(Answer Key)
QUESTION: OR-0018 TIME: 5 MIN' POINT VALUE:1.0 Following a reactor trip with both motor' driven emergency feed pumps running, I
emergency feedwater flow is indicating 850 gpm on 'B' steam generator wide range flow indicator, the narrow range indicator is pegged high; and slightly low post trip - l values on the other loops. Assuming no further automatic actions occur (for at least i 2 minutes):
- b. .What actions should have occurred and why? a
('B' S/G LEVELIS NOT RECOVERING)
ANSWER:
. )
- a. Close B loop flow control valve (0.5) 1
COMMENTS: 1 l
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1987 -1988 Annual Requalification Examination .;
- Part A (Answer Key) l QUESTION: OR-0092 TIME: 6 MIN . ' POINT VALUE:1.5 - '{
In regard to ECCS, what is the required Technical Specification action for Train 'A'. l chiller inoperability, assuming that chiller 'C'is not available as the installed spare? -
(1.5)-
ANSWER:
Declare Train 'A' ECCS inoperable (1.0) and apply action 3.5.2a (.5) (with one ECCS -
system inoperable, restore the inoperable system to operable ::tatus within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Hot Shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.) -
(also accept: discussion of 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action to shutdown or restore "A" chiller.
COMMENTS:
Requires relating the inoperability of chilled water to the resultant inoperability of -
ECCS systems and a aplyin y appropriate Tech S
. T.S. definition of OP3RABLE-OPERABILITY. pec action. Requires applying the -
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'1987 - 1988 Annual Requalification Examination Part A (Answer Key).
QUESTION: OR-0077 TIME: 5 MIN. POINT VALUE:1.0 An emergency boration is required in Mode 5 solid plant operations due to miscalculation of shutdown margin. After the emergency boration, the operator is told to ensure proper mixing of boron between RCS and Pzr. At this point, to comply with the intent of the procedure, he should:(1.0)
- a. Cycle the Pressurizer PORVs
- b. Start a reactor coolant pump.
- c. Start a second RHR pump -
- d. Shift charging to the auxiliary spray valve.
ANSWER:
d (1.0) .
COMMENTS:
Requires referring to EOP-11.0 to determine intent of EOP step and then analyze -
choices to determine which one meets the intent.
I 1
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O L iJ 1987 - 1988 Annual Requalification Exaniination Part A (Answer Key) 1
-i
-QUESTION: OR-0110 TIME: 4 MINI POINT VALUE:4 i Following a safety injection actuation, Train 'A' service water flow to the RBCU's is in'dicated on the Main Control Board. Whatis the minimum flowrate that would be l considered acceptable for these conditions? (.5) ]
ANSWER: ,
2000 gpm (.5) ,
j
- COMMENTS: .
d Requires knowledge of recent mods to SW supply to RBCU's and Tech. Spec.
surveillance requirements.
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. O OL 1987 - 1988 Annual Requalification Examination Part A (Answer Key);
. QUESTION: OR-0015 TIME: 5 MIN ' POINT VALUE:1'.0 With the plant at 75% power "B" Diesel Generator receives an emergency start signal. After a few minutes the generator trips offdue to a faulty breaker. No STPs - 1 are in progress. q A. State two reporting requirements (either in-plant or out-of-plant).
(O.
5)!
B. Electrical Maintenance reports that it will require approximately 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />sto repair the breaker. .What,if any, technical specification -
limiting condition for operation is/are exceeded? If any are exceeded, then state the action statement that applies. (.5) .
ANSWER:
A. This event will require:
- 1. An ONO (.25)
- 2. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> telephone notification (0.25) !
- 3. Written follow-up to the NRC (0.25)
(Accept 2 of 3 for fullcredit) i B. T.S.3.8.1.1.a. (0.25) I T.S.3.8.1.1.c. (0.25) 1 I
i COMMENTS: l Interpretinoperable D/G htom mfd h M*q b b . Ams" LCD 3.8.l.l.b l.s Um O tk (0 M b
3.5 1.1. a l' d
g, g g ,1. c_- (a M d (0 U
. O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0017 TIME: 3 MIN. MIN POINT VALUE:1J During a response to reactor trip, the AB lower operator reports that the auxiliary feed lines are moving violently and making loud banging noises. The RO reports rapid flow oscillations and estimates total EFW flow is = 250 gpm.
The Shift Supervisor should:
A. Continue with the EOP in effect and wait for the EFW problem to correctitself.
B. Direct the AB lower operator to vent the EFW lines and pumps.
C. Shutdown all EFW pumps.
D. Switch the EFW suction over to service water.
ANSWER:
B.(1.0)
COMMENTS:
Indications of steam in EFW lines due to backleakage vent per SOP-211.
4 J.
1987 - 1988 Annual Requalification Examination
- Part A (Answer Key)'
QUESTION: OR-0019 TIME: 5 MIN POINT VALUE:1.0 Following a reactor trip after a trip of all Main Feed pumps, the plant has been stabilized in Mode 3. The 'A' motor driven emergency feed pump has been shutdown and the annunciator"MD EFP A AUTOSTART FAIL" has alarmed.
- a. Which of the 'A' MDEFP automatic starts are blocked? - (0.5)
- b. What action can the operator take to re-establish all of the automatic start features for the 'A' MDEFP pump? (0.5)
ANSWER:
- a. SI and low steam generator level. (.5)
- b. Reset one of the main feed pumps. (.5) .
COMMENTS:
Reference Special Instructions and Station Orders.
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-() . .) q 1987 - 1988 Annual Requalification Examination !
Part A (Answer Key) !
QUESTION: OR-0026. TIME: 6 MIN. MIN ' POINT VALUE:21 XVG-1037B,, EF SERVICE WATER HDR B XCONN ISOL VALVE, has been danger l
tagged shut to repair a broken valve stem on XVG-1001B. What system.
configuration and/or technical specification limitations resulted from the tagout? -
-(2. I 0)-
1 Address operability (or inoperability) of all EFW pumps in your answer including a -
justification foryour answers. -
ANSWER:
Shutting XVG-1037B renders B Train MDEFP inoperable (0.25) because it's backup source of water is isolated (0.25). The TDEFP . .
is still operable (0.25) because it still has a backup source from A - -
train service water (0. . The ATrain MDEFPis stilloperable(.25)because the backup source fro dlNdiloperable(.25) I Tech. Spec. 3.7.1.2, a 'on a applies. (0.5)~
ATu (Also accept: Must restore "B" MDEFP to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (.25) or) shutdown to Mode 4 (.25).
1 COMMENTS: 1
)
1 4
I
- - - - _ - _ - _ _ . - - _ _ b
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- . - O O !
1 l 1987.- 1988 Annual Requalification Examination
- l Part A (Answer Key) *!
a QUESTION: OR-0055 TIME: 3 MIN POINT VALUE:1'.0 1 The plant b as experienced a totalloss of AC power and the operating crew has ' .
reached step 15, of EOP-6.0 when "B" DG is started locally and bus 1DB is restored.
What action should the CRS take now?
ANSWER:
Proceed to step 26. (1.0) '
COMMENTS:
Requires student to apply continuing Caution 6, EOP-6.0 after he is past the step in the EOP.
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- 1987 - 1988 Annual Requalification Examination Part A (Answer Key) j QUESTION: OR-0170 TIME: 6 MIN POINT VALUE:1.5 j While preparing for heatup following a refueling outage, the pressurizer is being ' ,
taken solid and the nitrogen blanket is being removed per SOP-101 section F. While ')
performing step 2.5, an improperly calibrated level transmitter on the pressurizer l relief tank (PRT) causes the PRT to go solid. PRT pressure spiking results in l blowing the PRT rupture disk. Then ROATC immediately reduced FCV-122,
A. What other indications are available to verify RCS inventory? (.5) .
.I B. Should RCS inventory be considered stable. Explain why or why not? L '.
]
(1.0) j 1
J J
ANSWER:
A. RVLIS (.5)
B. No,(.5) since vent paths are isolated, the pressurizer is indicating a false l level due to vacuum (0.5).
COMMENTS:
i I
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..: O -(J 1 1987 - 1988 Annual Requalification Examination Part A (Answer Key) '
1 l
. QUESTION: OR-0050 TIME: 5 MIN POINT VALUE:1.0 While operating in Mode 5 with the RCS drained to the centerline of the hot legs, the d "RHR LOOP A FLO LO" annunciator begins alarming repeatedly. Observation of.
~
. the MCB indicators verifies the oscillations.
- a. Other than flow, what'two indications will'the Reactor Operator have to determine the status of the 'A' RHR pump? (0.5)
(0.5).
ANSWER:
- a. 1. Pump current will be oscillating (.25) .
.2. Pump discharge pressure will be oscillating (.25) ~ !
- b. Reduce RHR loop flow (0.5)
COMMENTS:
Requires analysis of symptoms that dictate entry into an AOP.
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s' T q O O U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER SENIOR REACTOR OPERATOR ANNUAL REQUALIFICATION EXAMINATION PART "B" WRITTEN (ANSWER KEY)
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 2/24/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS POINTS B. Limits and Controls 21.25 4
_._ / s Submitted By: _ MW / @I di Approved:
u -
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'1987 1988 Annual Requalification Examination i Part A (Answer Key)
QUESTION: OR-0005 TIME: 3 MIN POINT VALUE:LQ EOP-1.0 Step 16b. has the RO stop all Reactor Coolant Pumps. The basis for this step is that:
- a. Reactor Building spray would cause shorting of motor.
- b. Phase B isolation signal has isolated cooling to motors.
- c. Peak clad temperatures are calculated to be lower if pumps are ;
tripped early.
- d. Inventory loss is higher if the pumps are left on.
l ANSWER:
l
- b. (1.0) j l
COMMENTS:
None l
--.-_------------------n----------
O O 1987 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0013 TIME: 8 MIN POINT VALUE:1.0 Source Range Channel N-32 is out of service for three weeks due to detector problems. Following a Reactor Trip it is noted that APN-5901 is faulted and de-energized. Electricians estimate 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore bus. What should be done to restore flux monitoring capabilities and when should it be done.
l ANSWER:
Energize high voltage to N-33 at the Control Room Evacuation Panel (.5). This should not be done for at least 15 minutes (.5) following the reactor trip.
COMMENTS:
EOP-8.0 L
a s<
o o 1987 1988 Annual Requalification Examination Part A(AnswerKey)
QUESTION: OR-0016 TIME: 1 MIN POINT VALUE:0.75 Following a reactor trip and safety injection due to a LOCA, a loss of 7.2 KV emergency bus IDA has occurred due to a bus fault. What operator action is necessary to respond to the challenged barrier between post-LOCA RB atmosphere and the environment? Assume that ten minutes have elspeed since the LOCA and IDA hasjust failed.)
ANSWER:
Close the RBCU return to SW pond (0.5) isolation valve for the SW booster pump thatis oft. (0.25)
COMMENTS:
O O l
1987 - 1988 Annual Requalification Examination l
Part A (Answer Key) j i
I QUESTION: OR-0123 TIME: 6 MIN. MIN - POINT VALUE:1,.0 I The plant has experienced a reactor trip due to a sustained loss of the service buses.
Bus IB3 is being fed from Bus IDB1 through the Bus 1B3 - 1DB1 TIE BKR. EOP-1.3 is being used to cooldown the RCS. In order to minimize the possibility of creating a j steam bubble in the reactor vessel head, what is the minimum amount ofsubcooling ]
required? (1.0)
]
ANSWER: !
130 'F (1.0) i COMMENTS:
EOP-1.3, step 3 requires determination of number of CRDM fans running. Bus 1B3 3 powers XFN-67B (SOP-114, Att. IIA) but at least 2 CRDM fans must be running to l reduce subcooling requirements to 80 'F. . j 1
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1987 1988 Annual Requalification Examination l Part A (Answer Key) 1 QUESTION: OR-0028 TIME: 4 MIN POINT VALUE:1.0 l During a response to safety injection, one diesel generator received 'an "DG ENG 1 START FAIL" annunciator. The IB Operator reported back that the cause was low air pressure but it is corrected and air pressure is adequate for another start signal. '
The start failure relay now has to be reset by depressing the:
l
)
- a. Engine Shutdown Reset pushbutton. !
- b. Emergency Start pushbutton.-
- c. Generator Relays reset pushbutton.
j d. Emergency Start reset pushbutton. .
I ANSWER: ,
- a. (1.0)
COMMENTS: 3 Knowledge ofreset functions from MCB.
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1 O O 1 1987 - 1988 Annual Requalification Examination l
Part A (Answer Key)
QUESTION: OR-0030 TIME: 3_ MIN POINT VALUE:M A steam generator tube ruptured and the the operating crew performed a rapid cooldown and depressurization per EOP-4.0, Steam Generator Tube Rupture. Which of the following is TRUE concerning the subsequent operation of the RCPs?
l
- a. The RCPs must be secured at 1380 psig.
i 1
a
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- c. The RCPs must be left running under all conditions to assure core cooling.
- d. The RCPs may be left running because itis an operatorinitiated .
cooldown.
ANSWER: l
- d. (1.0)
\
COMMENTS:
Testa knowledge of bases of RCP trip criteria.
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o O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0038 TIME: 5 MIN POINT VALUE:2.0 For the leakage conditions shown below, indicate whether or not the leak exceeds the limiting condition for operation in Technical Specification. (within specified time requirements). Consider each condition separately. Assume no other concurrent leakage.
(a) 0.5 GPMloop drain valve body leak.
(b) 1.2 GPM loop drain valve body to bonnet seal leak.
(c) 1.2 GPM unknown leakage.
(d) 3.0 GPM seat leakage from a pressurizer safety valve. .
ANSWER:
(a) exceeds (0.5) (pressure boundary)
(b) does not exceed (0.5) Identified Non-press boundary .
(c) exceeds (0.5) l (d) does not exceed (0.5)
COMMENTS:
Requires operator to determine what type ofleakage there is; then compare T.S. limits.
1
O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0041 TIME: 3 MIN POINT VALUE:1&
The unit has tripped from 100% power due to large LOCA and a loss ofoffsite power has occurred. "A" emergency diesel generator (DG) has started a nd loaded, but "B" DG has failed to start. While performing step 8s of EOP-1.0, the Reactor Operator notices that two charging pumps (A and C) are running on bus 1DA. The "A" DG load is 5150 KW. The reactor operator should:
1
- a. Go on with EOP-1.0 as he has adequately verified step 8a.
! b. Attempt to align 'C' pump to 'B' train injection using remotely controlled valves.
- c. Immediately trip one of the two charging pumps. .
- d. Attempt to restore 'B' charging pump, ar.d after restoration of'B', trip the 'C' pump.
ANSWER:
c (1.0)
COMMENTS:
Requires knowledge of ESFLS actions. Requires determination of overload conditions per SOP-306 .
0 O 1 1987 - 1988 Annual Requalification Examination j Part A (Answer Key) R QUESTION: OR-0018 TIME: 5 MIN POINT VALUE:1.0 Following g reactor trip with both motor driven emergency feed pumps running, emergency feedwater flow is indicating 850 gpm on 'B' steam generator wide range -
flow indicator, the narrow range indicator is pegged high, and slightly low post trip values on the other loops. Assuming no further automatic actions occur (for at least !
2 minutes):
- b. What actions should have occurred and why?
l
('B'S/G LEVELIS NOT RECOVERING)
ANSWER:
- a. Close B loop flow controlvalve (0.5)
COMMENTS: :
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o i
0 ) '
O O 1 1987 - 1988 Annual Requalification Exarnination - i Part A (Answer Key) f 1
1 QUESTION: OR-0092 TIME: 6 MIN POINT VALUE:1.5 )
In regard to ECQS, what is the required Technical Specification action for Train 'A' .
chiller inoperability, assuming that chiller 'C' is not available as the installed spare?
(1.5) l q
ANSWER:
{
Declare Train 'A' ECCS inoperable (1.0) and apply action 3.5.2a (.5) (with one ECCS l
system inoperable, restore the inoperable system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Hot Shutdown within the {
following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.)
(also accept: discussion of 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action to shutdown or restore "A" chiller.
COMMENTS:
Requires relating the inoperability of chilled water to the resultant inoperability of '
ECCS systems and a lyin g appropriate Tech Spee action. Requires applying the T.S. definition of OP : E-OPERABILITY.
4
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1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0077 TIME: 5 MIN - POINT VALUE:1.0 An emergency boration is required in Mode 5 solid plant operations due to miscalculation ofshutdown margin. AAer the emergency boration, the operator is -
told to ensure proper mixing of boron between RCS and Pzr. At this point, to' comply with the intent of the procedure, he should:(1.0) 1
- a. Cycle the Pressurizer PORVs
- b. Start a reactor coolant pump.
- c. Start a second RHR pump -
- d. Shift charging to the auxiliary spray valve.
l ANSWER: 1 d (1.0) . )
COMMENTS:
Requires referring to EOP-11.0 to determine intent ofEOP step and then analyze l choices to deternune which one meets the intent.
)
I i
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o o i 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0110 TIME: 1 MIN POINT VALUE:1 Following a safety injection actuation, Train 'A' service water flow to the RBCU's is indicated on the Main Control Board. What is the minimum flowrate that would be considered acceptable for these conditions? (.5) -
ANSWER:
)
2000 gpm (.5)
COMMENTS: '
Requires knowledge of recent mods to SW supply to RBCU's and Tech. Spec.
surveillance requirements.
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1987 - 1988 Annual Requalification Written Examination Part B Answer Key QUESTION: OR-0015 TIME: 5 MIN POINT VALUE:1.0 With the plant at 75% power "B" Diesel Generator receives an emergency start signal. After a few minutes the generator trips offdue to a faulty breaker. No STPs are in progress.
A. State two reporting requirements (either in. plant or out-of-plant).
(O. E 5)
B. Electrical Maintenance reports that it will require approximately l 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />sto repair the breaker. What,if any, technical speciilcation limiting condition for operation is/are exceeded? If any are exceeded, then state the action statement that applies. (.5)
ANSWER:
A. This event will require:
- 1. An ONO l 2. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> telephone notification
- 3. Written follow-up to the NRC
- 4. Report per T.S. 4.8.1.1.3
- 5. Notification ofMDS (Accept 2 of 5 for full credit)
B. LCO 3.8.1.1.b is exceeded (0.1)
Action 3.8.1.1.a (0.2) and Action 3.8.1.1.c (0.2)
COMMENTS:
Interpret inoperable D!G. Changes incorporate previously unaddressed correct answers (Part A). Change to Part B because original key did not correctly answer question as worded.
'. O O 1 i
1987 - 1988 Annual Requalification Examination Part A (Answer Key) l QUESTION: OR-0017 TIME: 3 MIN. MIN POINT VALUE:la During a response to reactor trip, the AB lower operator reports that the auxiliary feed lines are moving violently and making loud banging noises. The RO reports rapid flow oscillations and estimates total EFW flow is = 250 gpm. .l
- The Shift Supervisor should:
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A. Continue with the EOP in effect and wait for the EFW problem j to correctitt elf. )i B. Direct the AB lower operator to vent the EFW lines and pumps.-
i C. Shutdown all EFW pumps.
D. Switch the EFW suction over to service water. !
.J ANSWER: I B. (1.0)
C0MMENTS:
Indications ofsteam in EFW lines due to backleakage vent per SOP-211.
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o o 1987 - 1988 Annual Requalification Written Examination Part B Answer Key l 1
i QUESTION: OR-0019 TIME: 5 MIN POINT VALUE:1.0 '
Following a reactor trip after a trip of all Main Feed pumps, the plant has been stabilized in Mode 3. The 'A' motor driven emergency feed pump has been shutdown and the annunciator"MD EFP A AUTOSTART FAIL" has alarmed. 1 l
- a. Which of the 'A' MDEFP automatic starts are blocked? (0.5) i i
- b. What action can the operator take to re-establish all of the' automatic start features for the 'A' MDEFP pump? (0.5)
ANSWER:
(1) SafetyInjection (0.125)
(2) Lo-Lo steam generator level (0.125)
(3) Trip of all main feed pumps (0.125)
(4) AMSAC (0.125)
NOTE: Minus 0.0625 for listing blackout in addition to the other four:
- b. Reset one of the main feed pumps. (.5)
COMMENTS:
Reference SpecialInstructions and Station Orders. Changes to Part A answer to incorporate previously unaddressed correct answers and redefine point values.
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1987 - 1988 Annual Requalification ' Written Examination Part B Answer Key _. i QUESTION: .OR-0026 TIME: 6 MIN. MIN' POINT VALUE:2.0 .
XVG-1037B, EF SERVICE WATER HDR B XCONN ISOL VALVE, has been danger tagged shut to repair a broken valve stem on XVG-1001B. What system configuration and/or technical specification limitations resulted from the tagout? q
.(2.
0)
Address operability (or inoperability) of all EFW pumps in your answer including a i justification for your answers. .
ANSWER:
Shutting XVG-1037B renders B Train MDEFP inoperable (0.25) f
{
because ivs backup source of water is isolated (0.25). The TDEFP is still operable (0.25) because it still has a backup source from A train service water (0.25). The A Train MDEFP is still operable (.25) because the backup source from A Train is still operable (.25) .
Tech. Spec. 3.7.1.2, action a applies. (0.5)
(Also accept: Must restore "B" MDEFP to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (.25) or) shutdown to Mode 4 (.25). Change made to correct typographical error.
COMMENTS:
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.1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0055 TIME: 3 MIN POINT VALUE:LQ, The plant has experienced a total loss of AC power and the operating crew has -4 reached step 15, of EOP 6.0 when "B" DG is started locally and bus 1DB is restored. ,
What action should the CRS take now?
ANSWER:
Proceed to step 26. (1.0)
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COMMENTS:
qgt s student to apply continuing Caution 6, EOP-6.0 after he is past the step in I
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O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: OR-0170 TIME: 6 MIN POINT VALUE:L1 l While preparing for heatup following a refueling outage, the pressurizer is being taken solid and the nitrogen blanket is being removed per SOP-101 section F. While performing step 2.5, an improperly calibrated level transmitter on the pressurizer relief tank (PRT) causes the PRT to go solid. PRT pressure spiking results in i blowing the PRT rupture disk. Then ROATC immediately reduced FCV-122, charging flow, to minimum and closed the pressurizer PORV. After responding to i the RB ventilation and radiation alarms, the pressurizer slowly drained and ;
eventually leveled off at 45% cold calibrated level.
A. What other indications are available to verify RCS inventory? (.5) !
B. Should RCS inventory be considered stable. Explain why or why not?, .
(1.0) I ANSWER: i A. RVLIS (.5)
B. No,(.5) since vent paths are isolated, the pressurizer is indicating a false level due to vacuum (0.5).
COMMENTS:
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i 1987 - 1988 Annual Requalification Examination L
Part A (Answer Key)- q
)
l - QUESTION: OR-0050 TIME: 5 MIN POINT VALUE:LO While operating in Mode 5 with the RCS drained to the centerline of the hot legs, the . )
"RHR LOOP A FLO LO" annunciator begins alarming repeatedly. Observation of the MCB indicators verifies the oscillations.
- a. Other than flow, what two indications will the Reactor. Operator have to':
i determine the status of the 'A' RHR pump? (0.5) 1
ANSWER: ,
- a. 1. Pump current will be oscillating (.25) , .
- 2. Pump discharge pressure will be oscillating (.25)
- b. Reduce RHRloop flow (0.5)
COMMENTS:
Requires analysis ofsymptoms that dictate entry into an AOP.
N -
A 7'y v .O V. C. SUMMER REQUALIFICATION EXAMINATION Week of March 2,- 1989 l
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,1-i U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER REACTOR OPERATOR ANNUAL REQUALIFICATION EXAMINATION PART "B" WRITTEN (ANSWER KEY)
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 3/2/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS POINTS B. Limits and Controls 20.5 1
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Submitted By: /, / / 3-30-Y1
- \ / Date Approved: s /5._3-67
[ [I Supervisor, Sifulator And Training development Date
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,. O O I
1987 1988 Annual Requalification Examination -
Part B (Answer Key)
QUESTION: OR-0002 TIME: 4 MIN POINT VALUE:LO In the event of a failure of the ESF stat.us lights following a trip, determine whether ~ 1 the Main Feedwater Flow Control Valve controller indication (0-100%) or . !
handswitch indication (green and red lights) is a more valid indication of feedwater isolation and address why for both light and controller.(1.0)
ANSWER:
Handswitch green and red lights (.5) are more valid because they are driven from valve position limit switches (0.25). The flow controllers indicate demand position to yalves(0.25).
COMMENTS: !
Requires determination of which is more valid indication of valve position in the .
event ESF statuslights are lost.
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1987 - 1988 Annual Requalification Examination -
Part B (Answer Key)
QUESTIONi OR-0003 TIME: ), MIN POINT VALUE:}.a
. The plant has just experienced a trip from 100% power coincident with a fault and subsequent loss of power to APN-5901. During the power decrease, N-36 reached -
approximately 5 x 10 3% power and then jumped up to'5 x 10-2% power when it swithhed from the campbelling mode to the pulse mode. Power is now decreasing ;-
again with Source range N32 reading 9 x 102 CPS and SUR equal to .33 DPM. N36 ~ l reads 5 x 10 6% power and .2 DPM. Which NIS channel would be more indicative of L 'I actual power and why. (1.0)
ANSWERi-Source Range N32 (0.5) would be more indicative of actual power. Channst N36 jumping up a decade during the transfer indicates that the discriminator voltage is
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set too low (0.5). (In lieu oidiscussion of discriminator voltage, also accept statement that normal S/D SUR should be -0.33 pm).
COMMENTS: 1 This is also sup mrted by SUR for N36 reading too low.
With APN-590: N-31 and N-35 would not be available.
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l 1987 - 1988 Annual Requalification Written Examination Part 8 Answer Key ,
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. QUESTION: OR.0007 . TIME: 1 MIN POINT VALUE:le l EOP-1.0 step 10 instructs the operator to " Ensure two RBCUs are in SLOW speed".
What should the NROATC do ifonly XFN-64A is running in slow speed following a safety injection and explain why this action should be done? (Assume both 7.2 KV -
ESF buses are available). - (1.0) .
ANSWER: H Start a RBCU in slow speed on train 'B'(.5). This will ensure that a RBCU in each train is runningin slow speed (.5).
COMMENTS:
Requires referring to EOP-1.0 and application of train related criteria. The second ,
part of the answer does not really address the "why" part of the question.' It is clear that if the examinee answers " Start one RBCU in SLOW in B train" that he is ensuring one RBCU is running in each train. For those that answered in this manner, t.be "why" part of the question should be a reasonable discussion of RB cooling and/or cleanup following an accident. -
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1987 - 1988 Annual Requalification Written Examination-' '
Part 8 Answer Key i
QUESTION: OR-0011 TIME: 4, MIN POINT VALUE:1.0 Following a loss of coolant accident and subsequent safety injection, the operating crew verifies that RB pressure is less than 12 psig per step 16 -
of EOP-1.0. While performing step 20 of EOP-1.0 it is noted that RB spray had actuated in the interim. (1.0) i i
The operating crew should:
- a. Immediately stop RB spray actuation by shutting offpumps and closing valves as necessary.
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- b. Go back to step 16 and verify proper RB spray, phase B isolation I
and trip all Reactor Coolant Pumps.
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- d. Re-enter EOP-1.0 at the beginning to rediagnose event. I I
i ANSWER:
- b. (1.0)
Also accept choice "d" with a qualifying statement on verification of Main Steam Isolation.
COMMENTS:
Application of EOP-1.0 Step 15 in that should he go back and complete step 15 after he has past that point, go on in procedure, or what. If"d"is selected and qualified with a discussion of venfication of Main Steam Isolation, then this is an acceptable i answer.
- . O O 1987 - 1988 Annual Requalification Written Examination Part B Answer Key QUESTION: OR-0032 TIME: 6 MIN POINT VALUE:1.0 During a Safety Injection actuation, the annunciator "DG B GEN TRBL" alarms.
Which of the following most correctly details the operator's response in this situation? (1.0)
- a. Dispatch an operator to locally identify the cause of the alarm and take action (s), as appropriate,in accordance with ARP-004-XCX-5202.
- b. Trip the diesel generator and carry out the actions detailed in choice (a) above,
- c. Depress GEN RELAYS RESET and carry out the actions detailed in choice (a) above.
- d. Depress ENG SD RESET and carry out the actions detailed in choice (a) above.
ANSWER:
if e (or a) (1.0)
COMMENTS:
Precautions in SOP-306. This question has two equally plausible choices. The ARP for this annunciator says that an immediate action is to have an AO respond similarly to choice "a"of this question. Precaution 4 of SOP-306 has an operator perform actions similar to choice "c" of this question. Since, during an SI, the DG does not tie to the bus, the urgency of attempting to' clear the trouble alarm is not as
- peat. Therefore, during an SI, either answer should be acceptable for the criteria of most correctly details".
j 1987 - 1988 Annual Requalification Examination 1
Part B (Answer Key) '
i QUESTION:'OR-0040 TIME: 5 MIN POINT VALUE:LA During turnover, the reactor operator is told that the DC input to the 5901 inverter ~ !
has failed due to circuit breaker failure. Which of the following actions most - i correctly describe the action that should be taken in this situation? : (1.0,
- a. Declare the vital bus inoperable and repair the breaker failure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be at least Hot Standby within the'next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> j
and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. Declare the vital bus inoperable and repair the breaker failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least Hot Standby within the next 6 I hours and in Cold Shutdown with the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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- c. Declare the vital bus inoperable and repair the breaker failure within 1 hourorbe in: 4 i
- 1. at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, j l
- 2. at least Hot Standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
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- 3. at least Cold Shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l
.}
- d. The vital bus is still considered operable 'nitiate corrective action to repair the breaker and return the system to its normal lineup as soon as possible. i ANSWER: i
- b. (1.0) '
COMMENTS:
Requiresinter Specification. preting a loss of vital bus and applying appropriate action ofTec !
,_ O. O 1987 - 1988 Annual Requalification Exarnination Part B (Answer Key) l QUESTION: OR-0044 TIME: 4 MIN POINT VALUE:L.0Q If a loss of AC power to vital bus 1DB is experienced, APN-5903 will: l (Assume normal alignment) (1.0) -
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- a. ~ Remain energized with power from APN-1FB.
- b. Remain energized with power from inverter XIT-5908
- c. Remain energized with power from battery XBA-1B.
- d. Remain energized with power from APN-4101 ANSWER:
- e. (1.0)
COMMENTS:
Requires knowledge of uninterruptible power sources and power supplies.
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1987 - 1988 Annual Requalification Written Examination -
Part R Answer Key 3
QUESTIONi OR-0045 TIME: . 10 MIN ~ POINT VALUE:2.5.
The unit is at 100% power, NI-43 (Channel III power range) and inverters XIT-5901 and 5907 are out of service for maintenance. (Applicable LCO's are being.
followed). Maintenance requests removing 7.2 KV/480V ESF transformer IDA1 from service. Explain why it would not be advisable to perform this manipulation.
Ensure your answer includes the end result 'and outlines the sequence of events that lead to that end result.
ANSWERi This would require de-energizin 1 k f.5) which would ultimately de-energize l APN-1FA (0.5) which would providing power to APN-5901(0.5). If }
de-energized, a 2/4 coinci igh PR Flux (0.5) would be met, and a reactor trip would result (0.5).
(
COMMENTS:
Re de energize quires knowledge of bus to clear IDA1. loads andthat Recommend using thisSOP-305 question to bedetermine which deleted from breakers to the exam.
The time frame alloted for this question is not nearly enough. It appears that the ].
examinees were addressing this question toward the end of the exam when time was running out. Ifsomeone in schedulin,g were to evaluate this request, they would take much more than 10 minutes to simply determine the end result. The answer involves the end result and a sequence of events. The question does not contain enough information to make an accurate evaluation in a reasonable time frame. A '
key item that should have been included in the body of the question is that APN-5901 is being supplied by APN-1FA. This would have cleared up most of the ..
questions that were asked during the exams. The examinees were confused over I what actions have already been taken & what was expected in response to the :
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O O 1987 - 1988 Annual Requalification Written Examination Part B Answer Key QUESTlON: OR-0049 TIME: 5 MIN POINT VALUE:1.0 A large LOCA has occurred and a transfer to cold leg recirculation is in progress per EOP-2.2. The Auxiliary Building Lower Operator reports flooding in the 'A' RHR pump room. To isolate the loop, the operating crew secures 'A' RHR pump and attempts to close MVG-8811 A or MVG-8812A but they won't close.
Why won't the valves close and what must the operator do to shut the valves from the MCB? (Power to the motors is available and the valves are not mechanically bound).
ANSWER:
. With 2/4 RWST levels less than 18% and an SI signal present, the valves will remain open (0.5) until the RO resets the SI LATCHED function by placing the NORMAL, RESET switch to RESET. (Will also accept reset the 647 relay)(0.5).
( Also accept discussion of reset SI for 0.25 pts in lieu of RESET on NORMAL, RESET switch).
COMMENTS:
)
Requires knowledge of what causes MVG-8811A and 8812A to open automatically and evaluation of the course of action to get it to shut. Information on EOP-2.2 is ,
included to tell examinee status of plant, i.e. SI has been reset by now and RWST is {
effectively empty. Since examinees did not have MCB layout drawings, they were l unable to accurately state the name of the NORMAL, RESET switch of the SI LATCHED" function. l J
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1 O O 1987 1988 Annual Requalification Examination
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Part B (Answer Key) '
1 QUESTION: OR-0051 TIME: 1 MIN POINT VALUE:1.0 !
The controlling pressurizer level channel fails low and subsequently the "RCP A SL l
INJ FLO LO" alarm annunciated. How are these two events related?
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ANSWER:
The failed low instrument causes charging flow to RCS to increase (0.5) to make up for the apparent level decrease. This large change in charging flow robs seal injection flow (0.5) from the RCP's resulting in the alarm. J COMMENTS: .
Requires student to analyze efTect that failure has on system and predict effect.
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1987 - 1988 Annual Requalification Examination Part B (Answer Key)
I QUESTION: OR-0057 TIME: 4 MIN POINT VALUE:Lg ,
The most severe consequence of racking CCW pump 'C' onto the IDB bus after '
CCW pump 'B' was stopped for high bearing temperature and prior to its being racked down would be: ,
4
- c. The active CCW train (A) would have no standby pump l available.
- d. RHR pump 'B' seal cooler would not be receiving flow during this evolution.
i ANSWER: J
- b. (1.0)
COMMENTS:
Requires knowledge of start interlocks and Precaution 4 in SOP-118.
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1987 - 1988 Annual Requalification Written Examination Part B Answer Key I
QUESTION: OR-0059 TIME: 4 MIN POINT VALUE:2& l What two annunciators associated with the Component Cooling Water system could l
be indicative of a Reactor Coolant Pump #1 seal failure? Justify your answer.
I ANSWER: i l
rest t cf hot RCS water flow past thermal barrier (0.5).
flow which heats up CCW exiWg seal water HX (0.5). i
- 4. RCP THERMAL BARRIER HIGH TEMPERATURE (Moduflash alarm) (0.5) i due to heatup ofCCW(0.5).
t COMMENTS:
Knowledge of Annunciator Recponse Procedure, AFP-001, Panel XCP-603, Rev. 3 Answer Key did not list two annunciators tha*. ven also correct. Some examinees are misreading the question to be asking for any 9 arm functions that may be indicative of a # 1 seal failure. This is the intent of the question; therefore, accept alternate answer #4.
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1987- 1988 Annual Requalification Written Examination Part 8 Answer Key i
QUESTION: OR 0085 TIME: .1,Q MIN l POINT VALUE:2.a ,
Calculate and compare the startup rates following a 5 step rod withdrawal at 10% l power, BOL with bank D at 48 steps compared to the same 5 step rod withdrawal ,
with bank D at 213 stepr, Use No Xenon. j Beff = .0068 and A = 0.1 (2.0) )
l ANSWER:
{
SUR= 26.06 dpm (Aeffe / Beff-e )
SUR@48 = 26.06 dpmI(0.1)(44)/(680-44)] 26.06 dpm = 0.178 dpm i .02 dpm (0.25 pts for value of 44 +/-1,0.25 pts for SUR)
SUR@213 = [(0.1)(8.3)/(680-8.3)) 26.06 dpm =
l 0.032 dpm i .003 dpm (0.25 pts for value of 8.3 +/-1,0.25 pts for SUR) ' !
I SUR for pull at 48 steps is (accept 4 -6) times as large as at 213 steps (1.0)
(Also accept higher in lieu of"(accept 4-6) times" or a line by line comparison of the SUR calculations for the two rod pulls that quantitatively illustrates the required !
comparison. <
COMMENTS:
Requires use ofcurve book Figure 11-4.3 to determine rod worths.- Error bands allow for use of differential rod worth at start of pull (5 x DRW) or integral rod worth over 1/3 of 15 step interval (IRW + 3). Must provide a formula sheet. ,
Question does not specifically solicit a quantitative comparison; therefore, accept reasonable discussion in terms of hi her than/ lower than or line by line comparison of SUR calculations for two rod pull that quantitatively illustrate the comparison.
O O 1987 - 1988 Annual Requalification Written Examination -
Part 8 Answer Key QUESTlON: OR-0091 TIME: 1 MIN POINT VALUE:14 State the response (in regard to time frames) of the ESF HVAC chillers to'each of '
the following scenarios and explain why:
(1.
5)
- a. Immediately following blackout when both' systems were running normally for two weeks.
b.- Immediately following blackout assuming both systems had been started immediately before the time of blackout.'
- c. If abr the start in scenario b, the DG tripped and was restarted again.
ANSWER:
- a. - Restart immediately upon ESFLS step. (0.5)
- b. Available 5 minutes after previous start. - (0.25) Anti-recycle shortened to .
5 min.on ESFLS(0.25)
- c. Available 20 minutes aner previous start. (0.25) Anti-recycle back to 20 min. (0.25)
COMMENTS:
i Requires knowledp of anti-recycle lockout and application to various scenarios, Also relates to basis of Precaution 5 of SOP-501 and various Cautions in the body of the procedure. There really is no "why" for art "a"if the system is running l
normally. In this case, there is no need to a the Anti-Recycle feature because l
it ran out 2 weeks prior to the ' xotulated conditions. The question should have clearly solicited a discussion of the Anti-Recycle features for each scenario.
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- . O O 1987 1988 Annual Requalification Examination Part B (Answer Key)
QUESTION: OR-0093 TIME: 5 MIN POINT VALUE:13 With the Train 'C' chiller already operating on bus IDA1 due to chiller 'A' being inoperable for maintenance, the Train 'B' chilled water pump is found to be inoperable due to impeller damage. The required action would be to: (1.0)
- a. Place the Train "C" chilled water pump on IDB.
- b. Declare Train "B" ECCS inoperable.
- c. Valve the Train A chilled water pump to chiller "B".
- d. Follow Technical Specification 3.0.3.
ANSWER:
b (1.0)
COMMENTS:
Requires determining inoperability of Train 'B' chilled water and relatin inoperability of ECCS systems. Application oft.S. definition ofoperable operability.g it to -
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. I 1987 - 1988 Annual Requalification Examination Part B (Answer Key) j QUESTION: OR-0096 TIME: 5 MIN POINT VALUE:la L
During a reactor startup, the following N-45 trace is obtained. N-31 is being used for the 1/M plot. What is the most conservative assumption regarding the reactivity ;
condition of the reactor and the operability of N-31 and N-32? (1.0)
- a. N-32 has failed high. The core is suberitical.
- b. The core is suberitical by the 1/M plot.
- c. The core isjust suberitical. N-32 has responded quicker due to the proximity of '
group D to the source.
- d. The core isjust critical. N-31 has failed low.
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ANSWER: i
- d. (1.0) !
COMMENTS: }
N-32 failure ruled out by No N-31 response to shim (should respond even if I suberitical) Distractor "C" based on note in REP-109.002. Both channels should still l see increase.
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.. I 1987 - 1988 Annual Requalification Examination Part B (Answer Key) j i
QUESTION: OR-0122 TIME: 7 MIN MIN POINT VALUE:}.a During a post-trip review following a severe transient the following sets of conditions were noted. Specify during which set (s),if any, a safety limit was violated.
A. Tavg = 610' O. Tavg = 632' RCS PRESS. = 2025 psig RCS PRESS = 2235 psig ,
REACTORPOWER = 70% REACTOR POWER = 65%
B. Tavg = 637' D. TAVG = 615' !
RCS PRESS. = 2250 psig RCS PRESS = 1990 psig REACTOR POWER = 33% REACTORPOWER = 50% i ANSWER: l C (1.0)
COMMENTS:
Requires interpreting Figure 2.1-1.
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1987 - 1988 Annual Requalification Examination Part B (Answer Key)
}
QUESTION: OR-0148 TIME: 3 MIN POINT VALUE:la The Reactor is in mode 3, shutdown banks cocked, and STP-102.003 (I.R. Analog Channel Operability Test) hasjust been completed.~ A review of the STP indicates ;
the "AS LEFT" setting for N36 high flux trip is equivalent to 32% power. Which of .
the following describes the proper actions for this situation? (1.0)
-('
A. Correct the setpoint to the current equivalent to 25% RTP prior to increasing power above P-6.
B. Correct the setpoint to the current equivalent to 25% RTP prior to i entering mode 2.
C. Place N36 in the tripped condition within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and proceed with the startup.
]
D. Place N36 in the tripped condition prior to entering mode 2. .
1 ANSWER: 1
- b. (1.0)
)
COMMENTS: i 1
T/S 3.3.1 does not state an exception to 3.0.4 for this event.
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1987 1988 Annual Requalification Examination Part B (Answer Key)
QUESTION: OR-0173 TIME: 3 MIN POINT VALUE:1.0 Given that a VCS Technical Specification LCO Action Statement which, requires
" suspension of all core alterations"has been entered, which of the following MAY proceed?
- a. Allowance for the removal of any neutron sources from the reactor core area.
- b. Allowance for the use of the refueling bridge - provided that the bridge " low load limit" is bypassed (or "jumpered").
- c. Allowance for " shuffling" of the control rods and burnable poison assemblies -
provided that Keffis < or = to .95.
- d. Allowance for the completion of a component " movement" to a " safe"(i.e.;
" conservative") position within the reactor pressure vessel.
ANSWER:
- d. (1.0)
COMMENTS:
In accordance with VCS Technical Specification Definition 1.9 CORE ALTERATION:
" Suspension ofCORE ALTERATION shall not preclude completion ofmovement of a component to a safe conservative position".
I
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~o. EQUATIONSHEy p
. I fa .
f = ma v = s/t Cycle efficiency = (Net work out)/(Energy in) 4
, = og 2 s = %,t + 1/2 at i e me- '
KE = 1/2 mv a = (Vf - V,)/t A = AN A = Ag e *I PE = agn V7 = V, + a t w = e/t A = an2/t1/2 = 0.693/t1/2 !
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- IID I) d = 931 an -
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-gx Q = aCpat Q = UA A T I
- I g e~""
Pwr = Wfah I = I,10*"/ M M = 1.3/s P = P 10 sur(t) HVL = -0.693/u ur
. . P:e '
SUR = 26.06/T SCR = 5/(1 - Kgf) !
CR, a S/(1 - Kgf,)
SUR = 26e/s* + (a - s)T CRj (1 - K gfg) = CR2 II ~ " df2)
J T = ( t*/s) + [(s - s )/ fe] M = 1/(1 - Kg f) = CR j/CR, I T = s/(s - s) M = (1 - Kgf,)/(1 - K,ffj)
T = (s - s)/(Is) SOM = (1 - Kgf)/KWf a = (Kgf-1)/Kg f = aK gf /Kgf t' = 10 secones ;
I = 0.1 secones-I .
s = [( L*/(T Kgf)] + CIgf(1+IT)]
/
-I d 18 P = (saV)/(3 x 1010) Id j j =2 ,2 2 g8 jj 22 I = eN 2 R/hr = (0.5 CE)/6 (meters)
R/hr = 6 CE/d2~(feet)
Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lee. 1 curia = 3.7 x 1010 dos 1 ga;. = 3.78 liters I kg = 2.21 les 1 fte = 7.48 gal. 1 np = 2.54 x 103 8tu/nr Density = 62.4 Ituli/ft3 1 nr =.3.41 x 106 8tu/hr Density = 1 ge/cW lin = 2.54 cm Heat of vaporization = 970 5tu/lem *F = 9/5=C + 32 dest of fusion = 144 5tu/les 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-1bf D on ms o nnm hona_
.. O O i l' U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER SENIOR REACTOR OPERATOR <
ANNUAL REQUALIFICATION EXAMINATION '
PART "A" SCENARIO #SSO4 (ANSWER KEY) !
.1 FACILITY: V.C. Summer i REACTOR TYPE: .PWR .l DATE ADMINISTERED: 3/2/89 CANDIDATE: I l
SECTION: TOTAL CANDIDATE 'S POINTS POINTS I A. Plant Operations 15.5 i
i Submitted By: (e / 3~IO~YI Date Approved: .
. m /J5047,
- [ Supervisor imulator And Date '
Trai
- Development
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s 1987 - 1988 Annual Requalification Examination !
Part A (Answer Key) i QUESTION: 8804-001 TIME: 3 MIN POINT VALUE:Lg, ;
, Which is the best procedure to implement in this case? (1.5) l A. EOP-1.0 J
D.EOP-6.2 1 ANSWER:
b.(1.5) ;
COMMENTS: '
Req ufres evaluation ofplant status andjudsoment o EO. P-6.0 should be entered directly on loss oTpower. fmost applicable ; procedu
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. 1 1987 - 1988 Annual Requalification Written Examination -
Part A Answer Key QUESTION: SSO4-002 TIME: EMIN POINTVALUE:1&
Which of the followingis the initiating event that explains the status of - _.
"A" train ESF equipment?
(1.0)
- a. The "A" train sequencer failed to operate.
- b. All"A" train equipment was manually stopped.
)
- c. An "A" train SI signal was not generated. '
- d. The "A" D/G output breaker failed to shut.
ANSWER: '
d (1.0) -
)
(Also accept answer'a') 3 j
}, 1 i
COMMENTS:
Failure of *A" train sequencer to operate would not have prevented closure of the D/G output breaker. "A" train SI hght is on, which would have prevented "A" train loads from being off with switches in AUTO (unlabeled midposition). Due to LOA EPS-136, loss of power to 'A' Sequencer, the output functicas of the ESFLS (realign ,
RBCUs, trip normal and emergency NSR Bus Supply breakers) were not completed. !
because of this,'r and 'd' are correct the way the question is worded.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SSO4-003 TIME: A MIN POINT VALUE:1&-
How would you align the Steam Dump System for this condition? Include all MCB operator actions. (1.0)
ANSWER:
Arm the atmospheric steam dumps and steam generator power reliefs by placing the j train "B" STM DUMP INTERLOCK switch to the unlabeled midposition or to BYP - 1 INTLK. (1.0)
- 1. Transfer POWR RELIEF setpoint controllers to manual & close valves. )
- 2. Set steamline power relief valves to PWR RLF. - -
l
- 3. A(just PWR Relief setpoint controllers as necessary, 2
~
]{r COMMENTS: ^
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Requires knowledge ofnormal lineup and recognition th'at dumps are not -
armed due to train"B"STM D INTERLOCK being mispositioned in OFF.
Examinees were under the impression (from dynamic simulator Scenarios) that MCB switches would not be masaliped to enhance scenarios. Additionally ~, they recognised that entry conditions omsted for EOP-6.0, which had' switch 9 manipulations for the Steam Dump System. Therefere; an alternate answer is acceptable.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SSO4-005 TIME: 4 MIN POINT VALUE:1.0 Identify two automatic actions that have not occurred as concisely as possible.
Assume present conditions he.ve existed for twenty minutes. Disregard sequenced equipment. (1.0)
ANSWER:
- 1. Failure of"A"D/G output breaker
- 2. Failure of"B" D/G to start
- 3. Failure ofTD EFW Pump
- 4. Failure of normal steam release to atmosphere -
- 5. RTB 'A'did not open as required a y '
n !
COMMENTS: '
~ 3 I .,
No credit given for failure ofD/G 'A' output breaker to ire.ventdouble l "B" Train equipment is listed individually, then credit for failure of"B{eopardy. D/G to start If should notbe Ipven. The s receive credit nor answer 2.pecific identification of"B" D/G to start must be stated to
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1987 - 1988 Annual Requalification Examination 1 Part A (Answer Key) !
QUESTION: 8804 008 TIME: 1 MIN POINT VALUE:31 :
Determine whether any of the critical safety functions .are not fully satisRed, and if.
any are less than fully satinRed, state the appropriate level of challenge (i.e. solid, dashed or dotted path). i (2.5)
ANSWER: '
Heat sink (.5) solid path (.5) Core cooling (.5) dashed path (.5) inventory L.25) dotted (.25)
COMMENTS:
May also note that CSF are being monitored forinformation only. Requires comparing conditions to EOP-12.0.
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4 1987 -'1988 Annual Requalification Examination Part A(AnswerKey) i QUESTION: 8804-011 TIME: (MIN POINT VALUE:LR- !
Outline the progression ofEmergency Action Levels that would occur honn the - i present plant conditions and continuing for several hours. Assume that these ).
conditions have existed for 20 minutes. (1.0) 1 ANSWER:
A progression to Site Area Emergency would be made aner 15 minutes on loss of all A.C. (0.5) A progression to general emergency would be made after several hours withoutemergency feedwater. (0.5)
COMMENTS:
Thisclassification requires aj t call that"A" DG is inoperable due to an inability to useit to powerloads. not use 8804-011 with 88H-010 i 4 b l 1
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- O O 1. E r. ' l 1987 1988 Annual Requalification Examination Part A (Answer Key) i QUESTION: 8804 013 TIME: 1 MIN POINT VALUE:Lg,
. Evaluate the consequences for the core if the present RCP seal conditions were to l continue forseveral hours. (1,0) .
ANSWER:
The loss of RCS inventory through the seals could not be replaced, because no ECCS !
flowis available. i i
I This loss ofinventory would eventually result in an uncovered oore and damage.
(1.0)
COMMENTS:
Requires analysis ofECCS and RCP status, knowledge .
r of gen 1
extended loss of all A.C. scenarios. Starting the dinession at"an uneovered alwe" i implies knowledge ofinventory loss Do not use 81504 -018 with 8804 012 -
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1987 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: 8804-015 TIME: AMIN POINT VALUE:LD, What is the fastest way to isject the ECCS accumulator in this condition? (1.0)
- b. Reduce RCS pressure using auxi1Lry spray.
- c. Increase seemnulator pressure by adding Nitrogen
- d. Depressurising all SG's to 250 psig ANSWER:
d(1.0)
COMMENTSc i PZR PORV's will be ineffective because RC8 temperature is above saturation i temperature for accumulator pressure. Requires resemnee to ROP-6.0. ;
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vg==. eg 157 - 1988 Annual Requalification Written Examination Part A Answer Key sr 9r QUESTION: S804-016 TIME: (MIN. POINTVALUE:LQ The reactor coolant pump (RCP) breakers have tripped open in response to either one of two trip signals. What are these two trip signals and what is the bases for each?
(2.0)-
we +b.s framW - 3W ANSWER:
,,,,,,m,.e,, .h.%i.- *+ * .
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Underfrequency (.75 -prevents RCS flow ham degrading faster than flywheel effect ,25).._
)
Undervoltage (.75) - prevents re-energising 7.2 KV bus with BCP breaken closed
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- and starting pumps with no interlock protection (.25);
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COMMENTS:9 m ' - . -
Requires anal
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annunciators and 108D837 logies'to detersnine trip signals. If motorove listed as a trip signal, then assept overeurrent protection on motor and RB penetration asbasesfor terpretin
' to asking ser the bases se theactortripinseesd re trip, Most . gtity.w:gquestion as -
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key 1
I QUESTION:- SSc4-017 TIME: 1 MIN . POINT VALUE:1,1 !
Explain whether or not the Excore NuclearInstrumentation Intermediate Range -
1 meters on the Main Control Board are exhibiting a normal response to current j plant conditions.
(1.5) i 1
ANSWER:
The SUR meters (0.75) are exceeding .33 DPM (0.'75) which is not normal thislong after a trip.
M" 4
COMMENTS:
gi.
Requires analysing control board indications and counparing them to expected post trip values. Since nuestion does not addiese time aAer trip, credit for addressing time anertri erroneous indications. p should'be redistributed toPidenti8 cation ofmeters and .
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1 l 1987 - 1988 Annual Requalification Exannination
- i Part A(Answer Key)
QUESTION: 8804-018 TIME: 1 MIN ' POINT VALUE:Lg,
. With respect to Rosetor Trip Breaker indications, what operator action, if any, is - I required?
(1.0)
ANSWER:
Inunediate local veri 8eation of trip action. (1.0)
COMMENTS:
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157 - 1988 Annual Requalification Written Examination Part A Answer Key i QUESTION: SSO4-019. TIME: i MIN POINTVALUE:Lg, Other than burned out IIght bulbs, state the possible causes for the indication of RTB j
'B'.
(1.0) i
,I ANSWER: l
,i RTB 'B' shunt trip circuit is inoperable (loss ofcontinuity of the RTB 'B' shunt trip l circuit). (1.0)
(Also accept anyof the following):
4
- 1. Breakerracked out i
- 2. 52 contactfailure- #' ~
S. :",..s.kar.didnotopeatdly '"i j
- 4. LossorDC tobreaker i
I COMMENTS: cm=- =
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. O O U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER REACTOR OPERATOR '
ANNUAL REQUALIFICATION EXAMINATION PART "A" SCENARIO #SSO4 (ANSWER KEY) l l
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 3/2/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S POINTS POINTS A. Plant Operations 14.75 1
Submitted By: I /3D+f 0 Date Approved: [x
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(( Supervi r, Simulator And TrHniing Development Date
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1987 - 1988 Annual Requalification Examination Part A (Answer Key) .
QUESTION: 8804 001 TIME: 1 MIN POINT VALUE:14 Which is the best procedure to implement in this case? (1.5)
A. EOP-1.0 -
l B. EOP-6.0 i
! ANSWER:
- b.(1.5)
COMMENTS:
Roc uires evaluation of plant status andjudsoment ofmost applicable procedure.
EO. P-6.0 abould be entered directly on loss oTpower.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SS04-002 TIME: 1 MIN POINTVALUE:}A Which of the followingis the initiating event that explains the status of "A" train ESF equipment? (1.0)
- a. The "A" train sequeneer failed to operate.
- b. All"A" train equipment was manually stopped.
- c. An "A" train SI signal was not generated.
- d. The "A" D/G output breaker failed to shu t.
ANSWER:
d (1.0)
(Also accept answer'a')
f
{o COMMENTS:
Failure of"A" train sequencer to operate would not have prevented closure of the D/G output breaker. "A" train SI hght is on, which would have prevented "A" train loads from being off with switches in AUTO (unlabeled midposition). Due to LOA '
EPS-136, loss of power to 'A' Sequencer, the output functions of the ESFLS (realign RBCUs, trip normal and emergency NSR Bus Supply breakers) were not completed.
because of this, 'n' and 'd' are correct the way the question is worded.
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key ,
QUESTION: SS04-003 TIME: 4 MIN POINT VALUE:1.0 l How would you align the Steam Dump System for this condition? Include all MCB l
operator actions. (1.0) l ANSWER: '
Arm the atmospheric steam dumps and steam generator power reliefs by placing the train "B" STM DUMP INTERLOCK switch to the unlabeled midposition or to BYP INTLK. (1.0)
- 1. Transfer POWR RELIEF setpoint controllers to manual & close valves.
- 2. Set steamline power relief valves to PWR RLF.
- 3. Adjust PWR Relief setpoint controllers as necessary. g 3 I
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COMMENTS:
{
Requires knowledge of normal system lineup and recognition that dumps are not I armed due to train "B" STM DUMP INTERLOCK being mispositioned in OFF.
Examinees were under the impression (from dynamic simulator Scenarios) that MCB switches would not be misaligned to enhance scenarios. Additionally, they recognized that entry conditions existed for EOP-6.0, which had switch -
manipulations for the Steam Dump System. Therefore, an alternate answer is acceptable.
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~ 1 1987 - 1988 Annual Requalification Written Examination !
Part A Answer Key QUESTION: SSO4-005 TIME: 4 MIN
- POINTVALUE:M ,
Identify two automatic actions that have not occurred as concisely as possible. :
Assume present conditions have existed for twenty minutes. Disregard sequenced equipment. (1.0) i
.i i
ANSWER:
- 1. Failure of"A" D/G output breaker
- 2. Failure of"B" D/G to start
- 3. Failure ofTD EFW Pump
- 4. Failure of normal steam release to atmosphere 1
- 5. RTB 'A'did not open as required I i
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COMMENTS:
No credit given for failure of D/G 'A' output breaker to prevent double ppardy. If
{ .
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1 1987 1988 Annual Requalification Examination 1 Part A (Answer Key)-
QUESTION: 8804 008 TIME: 1 MIN POINT VALUE:3&
Determine whehr any of the critical safety functions .are not fully sans8ed, and if q any are less than fully satisSed, state the appropriate Isvel of challenge (i.e. solid, 'I dashed or dotted path).
(2.5) -
i ANSWER:
Heat sink (.5) solid path (.5) Core cooling (.5) dashed path (.5) Inventory (.25) dotted (.25) .
1 COMMENTS:
May also note that CSF are being monitored for infonnation only. Requires {
comparingconditions to EOP-12.0.
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1987 1988 Annual Requalification Examination .
Part A (Answer Key)
QUESTION: ss04-012 TIME: g, MIN POINT VALUE:LH Which of the following statements is INCORRECT concerning the RCP seals?
- a. The #1 seals are being signi8cantly degraded.
- b. Seal leakoff temperature is high due to loss of seal injection and CCW to the thermalbarrier heat exchanger.
- c. Seal condition should remain stable because #1 seal AP is acceptable,
- d. RCS #2 seal degradation may be expected due to high leakoff temperature ,
ANSWER:
Do not use 8804-012 with 8804-013.
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1987 - 1988 Annual Requalification Examination Part A (Answer Key)
QUESTION: s804-015 TIME: 1 MIN- POINT VALUE:L9, Whatis the fastest way to idect the ECCS accumulator in this condition? (1.0) '
- b. Reduce RCS pressure using auxiliary spray.
- c. Increase accumulator pressure by adding Nitrogen
- d. Depressurising all S/G's to 250 psig ANSWER:
d(1.0)
COMMENTS: -
PER PORV's will be ineffective becauss RCS temperature is above naturstion'.
temperature for accumulator pressure. Requires reference to EOP-6.0. .
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1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SSO4-016 TIME: 1 MIN POINT VALUE:2,9, ,
The reactor coolant pump (RCP) breakers have tripped open in response to either one of two trip signals. What are these two trip signals and what is the bases for each? (2.0)
ANSWER:
Underfrequency (.75) -pmvents RCS flow firam degrading faster than flywheel .
effect.25) ,
j Undervoltage (.75)- prevents re-energising 7.2 KV bus with BCP bmakers closed I and starting pumps with no_ interlock protection (.25) - i e s .
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to asking for the bases 9mr the reactor tdy instand,erthe, A
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I i 1987 - 1988 Annual Requalification Written Examination Part A Answer Key 4 QUESTION: SSO4-017 TIME: 1 MON POINTVALUE:Lg, - ) Erplain whether or not the Excore Nuclear Instrumentation Intermediate Range meters on the Main Control Board are exhibiting a normal response to current plant conditions. (1.5) ANSWER: The SUR meters (0.75) are exceeding .33 DPM (0.75) which is'not normal thislong aAer a trip.. . .
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COMMENTS:. - - -
- 5a Requires analysing control board indications and " theun to .
es post trip values. Since question does not aAer trip, credit for
'ag;thne aAertdp abould be redistributed to 14=tiSention ohneters and erroneous indications.~ x -
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. .= w 1987 1988 Annual Requalification Emannination
, Part A (Answer Key)- I l,
QUESTION: 8804-01s TIME: 1 MIN POINT VALUE:L9, With respect to Beactor Tdy Breaker indications, what operator actiset,1f any, is
)
mguired? (1.0) i 1 i ANSWER: l I Inunediate local veri 8 cation of trip action. (1.0) l COMMENTS:
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.- Part A Answer Key QUESTION: SSO&O19 TIME: 1 MIN POINTVALUE:la 1 Other than burned out light bulbs, state the possible causes for the indication of RTB
*B'.
(1.0) 1 ANSWER: RTB 'B' shunt trip circuit is inoperable (loss ofcontinuity of the RTB 'B' shunt trip circuit). (1.0) 1 (Also accept any ofthe following): . i 4
- 1. Breakerracked out ; ;
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1987 - 1988 Annual Requalification Examination Part A (Answer Key) QUESTION: S813 002 TIME: iMIN POINT VALUE:LQ
. Determine whether any conditions exist that fall to meet the Limiting Condition for Operations ofTechnical Specifications for Power Distribution Limits. (Verified by direct control board indications). (1.0)
ANSWER: DNB Parameters (0.5) QuadrantPowerTiltRatio (0.5) COhfMENTS: Requires comparing plant conditions with LCO's to determine failures. This question should normally follow S813-001.
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O O 1987 - 1988 Annual Requalification Examination Part A (Answer Key) 1 QUESTION: SS13 004 TIME: 1 MIN POINT VALUE:3 .! The ultimate source of radioactive contamination indicated by the present conditions is probably: (.75) .
- a. Gas Decay Tank rupture ,
l
- b. Liquid Waste evaporator explosion
- c. Steam GeneratorTube Rupture
- d. High RCS cetivity due to failed fuel. 1 i
ANSWER:
- d. (.75)
COMMENTS: i Requires analysing radiation monitor panel to deterndne soures. Secondary Red levels being nonnel ethnizata "c". High Iodine levels olhainate all the rest but"d". i pu, ". j,la ~
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Part A Answer Key i
'I QUESTION: SS13-005 TIME: (MIN POINTVALUf:LQ !
Other than the Emergency Plan, determine what is the most limiting time frame that exists which requires notification ofoffsite authorities. - (1.0) ANSWER:
- 1. hour notification to NRC (1.0) I I NRC not required only the time frame) !
1
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Requires comparing plant conditions to SAP-132 requirements. I hour notification per I-8 of SAP-132 , Question does not solicit to whom notification is to be made, . ) i i l l l l l f
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l 9 o 1987 1988 Annual Requalification Examination Part A (Answer Key) QUESTION: S813-006 TIME: (MIN POINT VALUE:la Determine if any additional surveillance activities are required per existing annunciators in alarm. (1.0) ANSWER: Rod Position Indication (0.5) QuadrantPowerTilt Ratio (0.5) [ Shutdown Margin) COMMENTS: Compare existing annunciators to ARP' to determine additional surveillance perGTP-702. Shutdownmarginnotreg
- for full credit to avoid double jeopardy.
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1987 - 1988 Annual Requalification Written Examination l. Part A Answer Key ) QUESTION: SS13-007 TIME: 1 MIN POINT VALUE:.75,' 1 Determine whether, any conditions exist that fail to meet the Limiting Condition for i Operations ofTechnical Specifications for the Reactor Coolant System.(.75) ! ANSWER: l
' High RCS Activity (.75) i (Alsoaccept: RCSLeakage) doe 4M i
COMMENTS: Requires comparing >Iant conditions with LCO's to determine failures. Convert 4 CPM to Monitor 1 per RYL 1 curve HPP-904 A++aeh=*at 5; Page 28 of 31 in Radiation ( int Book. High radiation conditions outside containment and in the : 1 plantvent1 examinees to believe that RCS water is leaking out. ! I i t ! l l:p, .
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l, f. ffb._- .' f;^ 7 g. 1 1987 - 1988 Annual Requalification Written Examination ' Part A Answer Key l i QUESTION: SS13-008 TIME: 1 MIN POINTVALUE:LQ { Ifconditions exist which require entry into an EOP or AOP, then identify the specific I procedure (s) which would be entered. (1.0)
)
ANSWER: EOP-9.0 (0.5) AOP-403.6 (0.5) (Accept EOP-10 for AOP-403.6) COMMENTS: 2-Requires cornparing plant conditions to en requirements ofEOP's and AOP's. Due to confusion resulting from recent pr ure changes some examinees are y, stating entry conditions exist for EOP-10 (which has been changed to AOP-403). If an examinee went to EOP-10.0, he would find en SAP-139 Attachment that would direct him to AOP-403.
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1 QUESTION: 8813 010 TIME: istIN POINT VALUE:Lg, ! Assuming that boron concentration has not changed fhun its value nt 1005 power prior to the transient, choose the moet correct answer in regards to the reactivity efects from Tavg changing during the transient. (1,0)
- a. N not erset was negative due to initial Tavg.
- b. N not efect was positive due to initial Tavg.
- c. N net efect was negative and would be at any power level.
- d. N not efect was posithe and would be at any power level.
ANSWER: b (1.0) _ n - u < COMMENTS: h1 i p powerleveland rod tiesto assumptions made on. b I 1 b..
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(' 1987 - 1988 Annual Requalificadon Examinadon 1 Part A(Answer Key) l QUESTION: 8813-012 TIME: 1 MIN POINT VALUE:M Using available radiation monitoring systesa panel alarins, indica % W . l controls, determine whether the control roomt environment is adequualy protected at the present time and explain why. (1.5) ANSWER: It is not adequately protected (.75) because the RMA 1 Train A and Train B Interlock > bypass switches arein bypass (.75). COMMENTS: Requires anal red monitor panel to determdne itceneret moosa isolation capableof properfhaetion. 3 d b[ t
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M o o 1 U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER REACTOR OPERATOR ) ANNUAL REQUALIFIC ATION EXAMINATION l PART "A" SCENARIO #SS13 ; (ANSWER KEY) l i
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FACILITY: V.C. Summer i REACTOR TYPE: PWR DATE ADMINISTERED: 3/3/89 j CANDIDATE:
.SECTION: TOTAL CANDIDATE 'S l POINTS POINTS A. Plant Operations 12.0 Submitted By: i '- - / I-30Yf I
Date - Approved: /3-h'8[ [ Superv' or, Simulator And r ing Development Date I
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;;& Q!MCiNRR$.9@V8 am 9 , 9 n 1987 - 1988 Annual Requalification Written Examination Part A Answer Key 1
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- wy j 1987 - 1988 Annual Requalification Examination Part A (Answer Key) !
QUESTION: SS13 002 TIME: 1 MIN POINT VALUE:LQ, ! Determine whether any conditions exist that fail to meet the Limiting Condition for Operations of Technical Specifications for Power Distribution Limits. (Verined by f direct control board indications). (1.0) l ANSWER: DNB Parameters (0.5) ) Quadrant PowerTilt Ratio (0.5) -I COMMENTS: i Requires comparing plant conditions with LCO's to determine failures. This question should normally follow SS13-001. 1 s ' 1, g ( t, ra e i Ydl , y .
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- l 1987 - 1988 Annual Requalification Examination I Part A (AnswerKey) j QUESTION: 8813 003 TIME: 1 MIN POINT VALUE:Q, Determine the amount of dme that operation may condnue based on AFD with !
i respect to Technical Specifications, assuming base load operation. Jusdfy your ; answer. (1.0) i ANSWER: Indefinite (0.5) Only 1/4 outside band (0.5) COMMENTS: Requires determining if AFD is outside its limits and ifso, determining action. i 4 ! s 1<c 1
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Q+,qW Q.i?%gr. + ';27~U"?,. w?TM 9 z %yf W. i?-WO@@%%,$n$$a$wp$ Q c.- : e~.<+; ...,,,w 1987 - 1988 Annual Requalification Examination Part A (Answer Key) QUESTION: 8813 006 TIME: g MIN POINT VALUE:LQ' , Determine if any additional surveillance activities are required per existing . annunciators in alarm. (1,0) 1 I ANSWER: . l Rod Position Indication (0.5) Quadrant PowerTilt Ratio (0.5) i 1 [ Shutdown Margin] ! COMMENTS: Compare existing annunciators to ARP to determine additional surveillance per GTP-702. Shutdown margin not req for full credit to avoid doublejeopardy. . s.4 il,; lR
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-~1 wm , x x.<t w v. m j 1987 - 1988 Annual Requalification Written Examination Part A Answer Key QUESTION: SS13-007 TIME: 4 MIN POINT VALUE:.7),
Determine whether, any conditions exist that fall to meet the Limiting Condition for Operations ofTechnical Specifications for the Reactor Coolant System.(.75) ANSWER: . High RCS Activity (.75) (Also accept: RCS Leakage)(,25) COMMENTS: Requires comparing CPM to pc/ml r RE slant conditions with LCO's to determine failures. Convert . Monitor Se L-1 curve HPP-904 At*mehmant 5; Page 28 of 31 in Radiationi plant venti at Book. High radiation conditions outside containment and in the examinees to believe that RCS wateris leaking out.
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i 1987 - 1988 Annual Requalification Written Examination Part A Answer Key 1
-i QUESTION: SS13-008 TIME: 1 MIN POINTVALUE:LQ, Ifconditions exist which require entry into an EOP or AOP, then identify the specific ,
procedure (s) which would be entered. (1,0) l ANSWER: EOP-9.0 (0.5) j AOP-403.6 (0.5) f (Accept EOP-10 for AOP-403.6) COMMENTS: A , 1 1 Requires comparing plant conditions to en mquirements ofEOP's and AOP's. k Due to confusion resulting from recent ure changes some examinees are " stating entry conditions exist for EOP- 0 (which has been changed to AOP-403). If an examinee went to E0P-10.0, he would find an SAP-139 Attachment that would direct him to AOP-403. y :, . J , I k. I ix;k4 3.A. r I e,p
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QUESTION: SS13-009 TIME: (MBI POINTVALUE:LI. : A calorimetric hasjust been performed that showed thermal power at 2560 MWT. Using the existing NI indications and assuming that everything else is normal, what'
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actions are required? ! (1.5) ANSWER: ' A4ust gain on N-44 (0.5) to within i2% (0.5) of the calorhnstric power (0.5) - (Also accept discussion at N-44 out of tolerance but with no ree4ustment due to - 4 dropped rod). .
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- r. t 9e 1987 1988 Annual Requalification Exanaination ~
Part A (Answer Key) QUESTION:' S813 010 TIME: 1 MIN POINT VALUEQ $ ~ Assuml4 that boron concentration has not changed firent its value at 1005 power , prior to the transient, choose the most correct answer in regards to the reactivity : effects from Tavg changing during the transient. (1.0)
- a. The not effect was negative due to initial Tavg.
- b. The net effect was positive due to initial Tavg. . ,
- 1. :
- c. The not effect was negative and would be at any' power level.
- d. The not offeet was positive and would be 'at any power level.
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1987 1988 Annual Requalification Examination ..
, Part A (Answer Key)
- x. ;
QUESTION: S813-011 TIME: 1 MIN . POINT VALUE:J),
State whether shutdown margin, as denned by Technical Speci5eations, did or did not change during the transient thatjust took place and explain why. (Note: Boron i concentration did notchange).
(.75)
ANSWER: I 1
Shutdown Margin would not change (0.5) since all rods are assumed inserted. (0.25)
COMMENTS: .
Requires comparingchang !
References Technical Speca,e Scation deAnition in rod position forSDE' to 'esset on SDE 1
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9 1987 - 1988 Annual Requalification Examination Part A(Answer Key) l QUESTION: 8813-012 TIME: 1 MIN POINT VALUE:14 Using available radiation monitoring system panel alarms,(adications, and controls, determine whether the control room environment is adequately pr*W at the present time and explain why. (1.5)
ANSWER:
It is not adequately protected (.75) because the RMA-1 Train A and Train B interlock bypass switches are in bypass (.75). -
COMMENTS:
- Requires anal n rad monitor panel to determine if Control Boom isolation capable ofpe ngproperfunction. -
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U. S. NUCLEAR REGULATORY COMMISSION V.C. SUMMER SENIOR REACTOR OPERATOR ANNUAL REQUALIFICATION EXAMINATION !
PART "B" WRITTEN- '
(ANSWER KEY)
FACILITY: V.C. Summer REACTOR TYPE: PWR DATE ADMINISTERED: 3/2/89 CANDIDATE:
SECTION: TOTAL CANDIDATE 'S ;
POINTS POINTS B. Limits and Controls 23.0 ;
Submitted By:
A /bb
/ Date Approved: .f, ,/jg::V) .
/7 .7/ M dupervisor, 'mulator And Date Trai g evelopment l
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1987 - 1988 Annual Requalification Examination
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Part B (Answer Key) ;
QUESTION: OR-0002 TIME: AMIN POINT VALUE:14 In the event of a failure of the ESF status lights following a trip, determine whether i the Main Feedwater Flow Control Valve controller indication (0400%) or handswitch indication (green and red lights) is a more valid indication of feedwater isolation and address why for both light and controller.(1.0)
ANSWER:
Handswitch green and red lights (.5) are more valid.
l because they are driven from valve position limit j switches (0.25). The flow controllers indicate demand position to valves (0.25).
COMMENTS: j I
Requires determination of which is more valid indication of valve position in e j event ESF statuslights are lost.
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l 1987 1988 Annual Requalification Examination '
Part B (Answer Key)
QUESTION: OR-0003 TIME: 1 MIN POINT VALUE:L,Q The plant hasjust experienced a trip from 100% power coincident with a fault and -
subeequent loss of power to APN-5901. During the power decrease, N-36 reached
; approximately 5 x 10-3% power and thenjumped up to 5 x 10-2% power when it -
.l switched from the campbelling mode to the pulse mode. Power is now decreasing ;
again with Source range N32 reading 9 x 102 CPS sud SUR equal to .33 DPM. N36, reads 5 x 10 6% power and .2 DPM. Which NIS channel would be more indicative of .
actual power and why. .
{
(1.0) '
ANSWER:
Source Range N32 (0.5) would be more indicative'of actual power. ' Channel N36 jiunping up a decade during the transfer indicates that the discriminator volt 4ge is a
set too low (0.5). (In lieu of discussion of discriminator voltage, also accept statement that normal S/D SUR should be -0.33 pm). #
COMMENTS: ~
This is also supported by SUR for N36 reading too low.
With APN-5901 N-31 and N-3G would not be available.
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i 1987.- 1988 Annual Requalification Written Examination Part 8 Answer Key-1 I
QUESTlON: OR-0007 TIME: . E MIN - POINT VALUE:}A
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EOP 1.0 step 10 instructs the operator to
- Ensure two RBCUs are in SLOW speed".
What should the NROATC do ifonly XFN-64A is running in slow speed following a safety injection and explain why this action should be done? (Assume both 7.2 KV ESF buses are available).' (1.0) i l
ta bU in slow speed on train 'B'(.5). This will ensure that a RBCU in train is runningin slow speed (.5).
COMMENTS:
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Requires referring to EOP-1.0 and application of train relatasi criteria.L The secon;d part of the answer does not really address the "wh of the question. Itisclear that if the examinee answers " Start one RBCU in in B train"that heis ensuring one RBCU is running in each train. For thoes that answered in this manner, the "why" part of the question should be a -=Ma discussion of RB cooling and/or cleanup following an accident. -
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- o 0 2H l 1987 - 1988 Annual Requalification Written Examination - i Part 8 Answer Key j j
QUESTION: OR-0011 TIME: iMIN POINT VALUE:LQ Following a loss of coolant accident and subsequent safety injection, l the operating crew verifles that RB pressure is less than 12 psig per step 16 of EOP-1.0. While performing step 20 of EOP-1.0 it is noted that RB spray had i actuated in the interim. (1.0) !
I The operatingcrew should:
- a. Immediately stop RB spray actuation by shutting offpumps and closing valves as necessary. j.
- b. ,
Go back to step 16 and verify proper RB spray, phase B Isolation
- 4 l
and trip sll Reactor Coolant Pumps.
- c. Verify RB pressure is still less than 12 peig and then secure RB spray.
'd. Re-enter EOP-1.0 at the beginning to rediagnose event. !
ANSWER: ,fm.,.
- b. (1.0) yi x
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Also accepigbesos "d" with'a qualifying statement on veri 5 cation of Main Steam Isolation. ;;pQ.+g Mdf "J 5['"I ( ;,n_,,
COMMENTS: -
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Application of EOP-1.0 Step 15 in that should he go back and complete stop 15 aAer he has that point, so on in procedure, or what. If"d"is h and quali5ed with a 'on of verl5 cation of Main Steam Isolation, them this is am soceptable answer.
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1987 - 1988 Annual Requalification Examination I t
Part B (Answer Key) i QUESTION: OR-0031 TIME: 1 MIN POINT VALUE:}a l Given the following status ofcritical safety functions (CSF) while in EOP-2.0, Loss of Reactor orSecondary Coolant:
i (1.0) ,
- 1. Core Cooling- Dashed Path
- 2. Suberiticality- Dotted Path .
- 3. Integrity- Dashed Path j
- 4. Heat Sink- Solid Path
- a. In what order should the above conditions be addressed? (0.5)
- b. Ten minutes later, while progressing through EOP-15.0, Ia the above conditions still exist except that Core Cooling :..
is now on a Solid Path. What actions should be taken and why? (0.5)
ANSWER:
- a. 4,1, 3, 2 (.5 - minus 0.125 for each one that is out oforder .Give ;
full credit for other answers if subsequent sequencing is correct) )
I
- b. The Core Cooling Solid Path should be immediately c . . s..;
addressed (0.25) bosom,os '
it is a higher priority than the Heat Sink Solid PatE"(0.38). -
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i Requires ofuseage rules for EOP-12.0.
Requires ofgiven conditions to priorities.
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1987 - 1988 Annual Requalification Written Examination Part B Answer Key l QUESTION: OR-0032 TIME: 6 MIN POINT VALUE:1.0 During a Safety Injection actuation, the annunciator "DG B GEN TRBL" alarms.
Which of the following most correctly details the operator's response in this situation? (1.0)
- a. Dispatch an operator to locally identify the cause of the alarm and take action (s), as appropriate,in accordance with ARP4004-XCX-5202.
l
- b. Trip the diesel generator and carry out the actions detailed in choice (a) above. I 1
- c. Depress GEN RELAYS RESET and carry out the' actions detailed in j choice (a) above. }
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- d. Depress ENG SD RESET and carry out the actions detailed in choice (a) above.
ANSWER:
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(1.0) I COMMENTS:
Precautions in SOP-306[TidAquestion has two equally plausible choices. The ARP for this annunciator says that an immediate action is to have an AO respond similarly to choice "a" oftids c ;uestion. Precaution 4 of SOP-306 has an operator perform ac shnilar to cho.ce "c" of this question. Since, during an SI, the DG '
does not tie bus, the urgency of attempting to clear the trouble alarm is not as great. The 'during an SI, either answer should be acceptable for the criteria of most correed) Is".; ,
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1987 - 1988 Annual Requalification Written Examination :l Part B Answer Key )
QUESTION: OR-0037 TIME: 4 MIN POINT VALUE:1.5 l
. Surveillance is due on the 'A' diesel generator but the test start circuitry is '
inoperable. A recommendation has been made to start the diesel using emergency j start and run the diesel surveillance in that mode. Name four reasons why j (administrative and/or technical) this would not be acceptable.
ANSWER: '
- 1) Speed droop would not be operable
- 2) Voltage droop would not be operable (Also accept droop circuitry would be inoperable for items # 1 & #2 j
- 3) Normal trips would be bypassed 1 4)In violation of procedure 5)In violation of FSAR-
- 6) Would not be able to parallel with grid
- 7) Would be inoperable per T.S., therefore would not be able to perform STP. (Accept similar wording).
Accept any 4 for full credit. (.375 each).
COMMENTS:
Requires the knowledge that speed and voltage droop and nonnal trips are activated by test start and that they are required for parallel operation. Other correct choices were not included on answer. ,
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1987 - 1988 Annual Requalification Examination Part B (Answer Key) 1 I
QUESTION: OR-0040 TIME: 1 MIN POINT VALUE:LQ-During turnover, the reactor operator is told that the DC input to the 59011averter ;
has failed due to circuit breaker failure. Which of the following actions most '
correctly describe the action that should be taken in this situation? .(1.0)-
- a. Declare the vital bus inoperable and repair the breaker failure i within 2 hours or be at least Hot Standby within the next 6 hours .
and in Cold Shutdown within the following 24 hours. .
- b. Declare b vital bus inoperable and repair the breaker failure within 24 hours or be in at least Hot Standby within the next 6 hours and in Cold Shutdown with the following 30 hours.'
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- c. Declare the vital bus inoperable'and repair the breaker failurk 3
l within I hourorbe in:
- 1. at least Hot Standby within the next 6 hours,
- 2. at least Hot Standby within the following 6 hours, and i
- 3. at least Cold Shutdown within the subsequent 24 hours. )
- d. The vital bus is still considered operable. Initiate corrective action to l repair the breaker and return the system to its normal lineup as !
soon aspossible.
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- b. (1.0)
COMMENTS:
Requires inter Specification. preting a less of vital bus and applying appropriate action ofTe
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1987 - 1988 Annual Requalification Examination- I Part B (Answer Key)
QUESTION: OR-0044 TIME: 1 MIN . POINT VALUE:L9, If a loss of AC power to vital bus IDS is experienced. APN-5903 will:
)
.(Assume normal alignment) (1.0) a.' Remain energized with power from APN-1FB.
i
- b. Remain energized with power from inverter X1T-5908 i
- c. Remain energized with power from battery XBA-1B.
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- d. Remain energized with powerfrom APN-4101 j
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1 i ANSWER: 1
- c. (1.0)
COMMENTS: 1 Requires knowledge of uninterruptible power sources and power supplies.
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1987 - 1988 Annual Requalification Written Examination Part B Answer Key QUESTION: OR-0045 TIME: 10 MIN POINT VALUE:2.5 The unit is at 100% power, NI-43 (Channel III power range) and inverters XIT-5901 and 5907 are out of service for maintenance. (Applicable LCO's are being followed). Maintenance requests removing 7.2 KV/480V ESF transformer IDA1 from service. Explain why it would not be advisable to perform this manipulation.
Ensure your answer includes the end result and outlines the sequence ofevents that lead to that end result.
ANSWER:
This would require de-energizing i '
hich would ultimately de-energize APN-1FA (0:51which would hav viding power to[APN-5901(0.5).'If 4 de-energized,)a 2/4 coincidene PR Flux (0.5) wotild be met, and a reactor {
trip would result (0:5). ,
/5 COMMENTS:
Re de energize quires knowledge of bus loads and using SOP-305 to determine which breakers to to clear IDA1. Recommend that this question be deleted from the exam.
The time frame alloted for this question is not nearly enough. It appears that the l examinees were addressing this question toward the end of the exam when time was !
running out. Ifsomeone in scheduling were to evaluate this request, they would !
take much more than 10 minutes to simply determine the end result. The answer !
involves the end result and k sequence of events. The question does not contain 1 enough information to make an accurate evaluation in a reasonable time frame. A i key item tha t should have been included in the body of the question is that APN- '
5901 is being supplied by APN-1FA. This would have cleared up most of the questions that were asked during the exams. The examinees were confused over what actions have already been taken & what was expected in response to the information given. "
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I 1987 - 1988 Annual Requalification Written Examination Part B Answer Key ;
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QUESTION: OR-0049 TIMEi 1 MIN POINT VALUE:li I A large LOCA has occurred and a transfer to cold leg recirculation is in progress per EOP-2.2. The Auxiliary Building Lower Operator reports flooding in the 'A' RHR j pump room. To isolate the loop, the operating crew secures 'A' RER pump and attempts to close MVG-8811 A or MVO-8812A but they won't close.'.
Why won't the valves close and what must the operator do to shut the valves from the MCB? (Power to the motors is available and the valves are not mechanically bound).
w ANSWER:
With 2/4 RWST levels less than 18% and an SI signal present, the valves will remain -
f.
I open (0.5) until the RO meets the SI LATCHED fhaction by placing the NORMAL, RESET switch to RESET. (Will also accept reset the 647 relay)(0.5).
( Also accept discussion of reset SI for 0.25 pts in lieu'of RESET on NORMAL, RESET switch). wof A t( e i n B-COMMENTS: I Requires knowl of what causes MVG-8811A and 8812A to open automatically and evaluation of eenres of action to get it to shot. Information on EOP-2.2 is ,
included to tell ====i=== states of plant, i.e. SI has been reest by now and RWST is effectively . Since sumaninees did not have MCB layout drawings, they were i unable to state the name of the NORMAL, REBETswitch of the "SI LATCHE 9:n~.7 -
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1987 - 1988 Annual Requalification Examination Part B (Answer Key)
QUESTION: OR 0051 TIME: AMIN- POINT VALUE:1.0 The controlling pressurizer level channel fails low and subsequently the "RCP A SL INJ FLO LO" alarm annunciated. How are these two events related?
ANSWER:
The failed low instrument causes charging now to RCS to increase (0.5) to make up for the apparent level decrease. This large change in charging now robs seal injection ilow (0.5) from the RCP's resulting in the alarm.
COMMENTS:
Requires student to analyze effect that failure has on system and predict effect.
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j 1987 1988 Annual Requ:.lification Examination i Part B (Answer Key) I QUESTION: OR-0057 TIME: A MIN POINT VALUE:LQ The most severe consequence of racking CCW pump 'C'onto the IDB bus after j
CCW pump 'B' was stopped for high bearing temperature and prior to its ]
being racked down would be:
l
- a. Neither RHR Hx would receive flow on a SI signal. I i
- b. Neither Train 'B' CCW pump would start on a SI signal.
c.
l The active CCW train (A) would have no standby pump l available. i a
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- d. RHR pump 'B' seal cooler would not be receiving flow during ~ !!
s this evolution. '
ANSWER:
- b. (1.0)
COMMENTS: '
Requires knowledge of start interlocks and Precaution 4 in SOP-118.
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1987 - 1988 Annual Requalification Written Examination l Part 8 Answer Key QUESTION: OR-0059 TIME: 4_, MIN - POINT VALUE:2.0 What two annunciators asweinted with the Component Cooling Water system could be indicative of a Reactor Coolant Pump #1 seal failure? Justify your answer.
i ANSWER: l 1
- 1. RCP(A,B,C,) THERMAL B AR FLO HI alarm (0.5) due to flashing CCW as a j result of hot RCS water flow past thermal barrier (0.5). I
- 2. RCP (A,B,C) CCW TEMP HI alarm (0.5) due to hot RCS water flow past ;
thermal barrier. (0.5) l
- 3. LTDN/SL WTR,HX FLO LO TEMP HI alarm (0.5) due to increase seal' return; !
flow which heats up CCW exiting seal water HX (0.5).
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- 4. RCP THERMAL BARRIER HIGH TEMPERATURE (M 4 due to beatup of CCW(0.5).
COMMENTS:
Knowledge of Annunciator Response Procedure, ARP-001, Panel XCP-603, Rev. 3 -
Answer Key did not list two annunciators that were also correct. Some examinees i are misreading the question to be asking for any alann functions that may be indicative of a # 1 seal failure.' This is the intent of the queMon; therefore, accept alternate answer #4 MT ; , -
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1987 - 1988 Annual Requalification Written Examination Part B Answer Key QUESTION: OR-0085 TIME: IQMIN POINTVALUE:LQ, Calculate and compare the startup rates following a 5 step rod withdrawal at 10%
power, BOL with bank D at 48 steps compared to the same 5 step rod withdrawal with bank D at 213 steps. Use No Xenon.
Beff = .0068 and A = 0.1 (2.0)
ANSWER:
SUR= 26.06 dpm(Aeffe / Befr-e )
SUR@48 = 26.06 dpm[(0.1)(44)/(680-44)] 26.06 dpm = 0.178 dpm i .02 dpm (0.25 pts for value of 44 +/-1,0.25 pts for SUR)
SUR@213 = [(0.1)(8.3)/(680-8.3)] 26.06 dpm =
j 0.032 dpm i .003 dpm (0.25 pts for value of 8.3 +/-1,0.25 pts for SUR) '
SUR for pull at 48 steps is (accept 4 -6) times as large as at 213 steps (1.0)
(Also accept higher in lieu of"(accept 4-6) times" or a line by line comparison of the ~
SUR calculations for the two rod pulls that quantitatively filustrates the required comparison.
COMMENTS: ;n Requires use ofcurve book F1 for use ofdifferentialred II-4.3 to determine rod worths. Error bands allow at start of pull (5 x DRW) or integral rod worth over 1/3 of15 stepinterval(IEW + 3). Must provide a formula sheet.
MY.
Question reasonable ly solicit a quantitative comparison; therefore, accept ofSUR ra in terms of higher than/ lower than or line by line compannon for two rod pulls that quantitatively illustrate the companson.
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i 1987 - 1988 Annual Requalification Examination i 1
Part B (Answer Key) !
QUESTION: OR-0096 TIME: 1 MIN. POINT VALUE:L9, During a reactor startup, the following N-45 trace is obtained. N-31 is being used for .
the 1/M plot. What is the most conservative assumption regarding the reactivity condition of the reactor and the operability of N-31 and N-32?. (1.0)
- a. N-32 has failed high. The core is suberitical,
- b. The core is suberitical by the 1/M plot. ,
- c. The core isjust suberitical. N-32 has responded quicker due to the proximity of.
group D to the source.
- d. The core is just critical. N-31 has failed low.
1 ANSWER: "
i
- d. (1.0) l' COMMENTS:
N.32 failure ruled out by No N-31 response to shim (should respond sven if- l suberitical) Distractor "C" based on note in REP-100.002. Both channels should still -j see increams. i l
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i 1987 - 1988 Annual Requalification Examination-Part B (Answer Key) ;
QUESTION: OR-0172 TIME: 4_ MIN POINT VALUE:}&
During shift turn-over and a review of station logs, it is noted, by the CRS, that; :
- 1) the Integr' ated Fire Computer System (IFCS) was removed from service;
- 2) a fire watch patrol has been established as per appropriate VCS station procedures :
and 3) Attachment VIII of SOP-509 is now being used to document / log fire watch patrol activities.
During subsequent review of AO logs, it is noted that fire door PA-201 - Hre door of an area normally monitored by the above IPCS - cannot be fully shut due to extension cords running under the door during on-going cable tray modification / repair. The CRS also notes that the MWR for the cable trayjob DOES 1 NOTcall for a fire watch. I*
A I
The most appropriate course of action, by the CRS, is to now: (1.d) a) Suspend modi 5eation activities, have the extension cords removed, and have the AO fully shut the Are door.-
b) Allow continuanEEofmodi5 cation activities and continue conducting, HOURLY reviews of the AO and fire watch logs.
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c) Station the AO.ater near the open fire door whenever the AO IS NOT-performing neridal" log-taking" duties and allow continuance of modification activities.
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' MI n l d) SuspiiilMhadan activities (and leave extension cords in place) until a ,
continuously roving See watch can be stationed. l
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ANSWER:
- a. (1.0)
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COMMENTS: '
Requires applying Tech. Spee. required actions.
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