ML20246M922

Exam Rept 50-382/OL-89-01 on 890515-19.Exam Results:Seven Operator Applicants Passed Complete Operator Licensing Exam & Three Senior Reactor Operator Applicants Passed Retake Exam

ML20246M922
Person / Time
Site:	Waterford
Issue date:	07/12/1989
From:	Graves D, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20246M913	List: ML20246M906 ML20246M922
References
50-382-OL-89-01, 50-382-OL-89-1, NUDOCS 8907190257
Download: ML20246M922 (182)

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APPENDIX- ^ 4 U.S. NUCLEAR REGULATORY COMMISSION < REGION IV Operator; Licensing Exam Report: 50-382/0L'89-01 Operating License: NPF-38 Dock'et:.50-382 O censee:'" Louisiana ~ Power and Light Company ATTN: J. G. Dewease, Senior Vice President' s Nuclear Operations 317 Baronne Street New Orleans, Louisiana 70160 ..g Facility Name: Waterford3SteamElectric. Station-(W-3). 4 o = Examinations Administered et: W-3

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7 l 2-9 ( Chief Examin ~ D.,N. Graves. Examiner - Date Operator Licensing Section Division.of. Reactor Safety i. Approved by: o J.'L. Pellet, Chief. Date Operator Licensing Section Division of Reactor. Safety Summary ~ NRC administered complete operator licensing' examinations to se"en reactor - operator applicants and retake written examinations-to three senior reactor - operator applicants. All ten candidates passed all portions of the examinations and have been issued the appropriate' licenses. i f: &7190257999734 Q ADOCK 05000382 PDC

v r y 1 p ! DETAILS. -1. Persons Examined SRO 3 Total Pass 3 7 10 Fail. 0 0' 0 2. Examiners- ~ D. N. Graves, Chief Examiner, I. Kingsley. G. Weale 3. , Examination Report Performance results for individual examinees are not included in this report as it will be placed in the NRC Public Document Room, and these results are not subject to public disclosure. 3.1 Examination Review Coment and Resolution In general -editorial.coments or changes made dufing the examination, or subsequent grading reviews are not addressed by this section. Coments regarding acceptance of concepts for credit and/or alternate methods of' . calculating answers are generally accepted with no change in the. answer key. The entire text of the coments and resolutions are included as. 3.2 Site Visit Summary 3.2.1 Following completics of the written exan.ination, the. facility licensee was provided a copy.of the examinations and answer. keys for the . purpose of comenting on the content validity of the examination. It was explained to the facility that comments were required within five q working days following the departure from site and that gradirg of 1 the examinations would not begin until the coments were received and resolved. 3.2.2-The examiners held an exit meeting with members of the licensee staff at the conclusion of the site visit. The following personnel were present: NRC Facility Licensee D. Graves J. O'Hern I. Kingsley D. Packer T. Staker W. Smith G. Weale C. Toth

t. The examiners provided the following comments during the exit meeting: 3.2.2.1 The facility's policy of not having control board indication of disabled annunciators may lead to a failure to recognize annunciators are disabled, especially during rapid transients when such information may be very important. A notebook (log) oi disabled annunciators is kept in the control room but no indication on the annunciator panel alerts the operators that an annunciator is disabled. Mr.. Packer stated that the present policy is currently under review. 3.2.2.2 Several candidates were questioned concerning the required actions to be taken if the operating shutdown cooling loop began cavitating due to low suction pressure while in half-loop operation and their responses indicated lack of familiarity with the loss of shutdown cooling procedure and would have probably resulted in the loss of both loops of shutdown cooling. 3.2.2.3 The apparent lack of initiative or willingness by the R0s to diagnose-problems and recommend solutions to the SR0 may result in degraded crew response to infrequent transients. They were very good at providing the SRO with data during the rimulator examinations but provided very little help when the SR0's diagnostic ability was curtailed by the examiners. 3.2.2.4 The SR0's use of the E0Ps during a situation that was not specifically covered by the E0Ps resulted in a discussion on E0P usage. The issue was whether the SRO should have initiated SI or continued with a controlled cooldown with an HPI pump running (RCS pressure was above the HPI injection pressure). The issue was resolved to the Chief Examiner's satisfaction with the facility (explanation that the action necessary to get back into the procedure SIinitiation)wouldcause a much more uncontrolled plant transient / condition than the controlled cooldown that the operators were currently performing. 3.2.2.5 The effects portion of the simulator cause/ effects manual was not sufficient to determine expected plant response to malfunctions. 3.2.2.6 Few of the provided Initial Conditions (ICs) were useable. Several of the ten provided were startup ICs. 3.2.2.7 Communication between crew members was excellent. 3.3 Master Examination and Answer Key A copy of the written examinations and answer keys with comments incorporated is attached (Enclosure 2). 3.4 Simulation Facility Fidelity Report All items on the attached Fidelity Report (Enclosure 4) have been brought to the attention of the facility.

r Recommended'NRC Resolutions for Licensee Recommendations on Waterford 3 Written Exams Reactor Operator Exam Question Recommended NRC Resolution 1.04 Licensee recommendation not accepted. Method C (as s proposed by the licensee) is already included in the-answer key (Method A with Submethod A2). No change to the answer' key is required. Houever, any method of calculation that correctly stated and used the applicable equations was accepted for full credit. { (Note - the answer key was revised to correct the value substitution errors in the second line of submethod A2.) 1.10 Licensee recommendation accepted. The answer key has been revised to include the alternate calculation method proposed by the licensee. However, any method of calculation that correctly stated and used the applicable equations was accepted for full credit. 2.01 Licensee recommendation not accepted. Part b of the question was invalidated because Figure 3.1-0 of the Technical Specifications was not provided to the candidates and no rods /CEAs were specified as being fully or partially withdrawn. Therefore, part b has been deleted from the exam. 2.02 Licensee recommen3ation not accepted. An adequate description of the correct concept is an acceptable alternati.? to a verbatim repeat of the answer key; no ch ar.g e to the answer key is required. 2.04 Licensee recommendscion accepted; the question has been deleted from the exam. 2.11 Licensee recommendation accepted. The answer key has been revised to indicate 0.5 gpm as an alternative to 720 gpd. 2.15 Licensee recommendation accepted. The answer key has been revised to include the alternate terminology and additional alternate answers. The licensee should consider incorporating the additional alternate answers in the Indications section of CP-901 038., Instrument Air System Malfunction. 2.18 Licensee recommendation not accepted. Correct alternate terminology is an acceptable alternative to a l verbatim repeat of the answer key; no change to the answer key is required. 2.19 Licensee recommendation accepted. The answer key has been revised to accommodate the exam proctor's clarification.

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3;01 Licensee recommendatiloni accepted; The answer key lia's 'been revised.to include'the additional alternate answers. However, it should be noted that the-terminology "autostop" is included in-the 'l Instrumentation, Controls & Interlocks section of I several Waterford 3~ lesson plans and refers to the 'l automatic cycling off of a pump or. compressor'when~some external control parameter is exceeded or some interlock condition is no longer satisfied. The lists of external control parameters and interlocks provided I in the lesson plan descriptions of autostops do'not include occurrences such as.overcurrent, undervoltage, shaft seizure, a sheared shaft, belt breakage, breaker malfunction,' power cabic severance,-etc. These occurrences will stop the pump or compressor even when 'the start switch / button is being held / pushed and.are not consideced autostops. 3.02 Licensee recommendation accepted. The answer. key has been revised to include the additional alternate answers. See 3.01 resolution for additional comments. 3.03 Licensee. recommendation not accepted. The question asks for THE four conditions / interlocks that must be satisfied to coune an EDG output breaker to close automatically. The answer key reference lists the conditions as four separate requirements and it is expected that learning objective 9 of lesson plan ZEDG-700-02 requires the listing of all four since all four are necessary. Furthermore, an inspection of the-EDG output breaker closing circuit on control wiring diagram LOU-1564-B-424 indicates there are indeed four contacts or sets of contacts that must,be closed for automatic closing of the diesel output breaker: a. 62BT contact (incorporates 3 Bus to 2 Bus tie open for >5 seconds), b. 27-1X, 27-2X, 27-3X contacts (incorporate UV or DV on 3 of 3 phases of 3 Bus), c. TX contact from breaker trip circuit (incorporates no trip or lockout signal), 1 l d. 52C2 or 52C3 contacts from Ready-to-Close L Generator Breaker Command Relays (incorporate rated conditions of output voltage and diesel speed). p Credit was given for a partial description of any one of the four requirements, but more than full credit was not awarded for multiple parts of meeting the same closing circuit requirement.

y; Y 43 q 7. O re A 3.04:

L i c e n s e e r e c o m m e n d a't i o n ' a c c e p t e d'.-

The'.' answer key has-been revised to. include the additional alternate 4 answers, :The-licenseeTshould considerrincluding-the s . additional alternate answers in the referenced 11esson pb.,g { plan. i "9- ?3.06 [ Licensee recommendation.not accepted...The : ques tion.. fg" ' asks 1for response 1of the B rFWp speed, not'the response of the. speed control system. However, candidate. j answers'that. indicated the'B MFWP speed wouldLrespond. R to the output to of the manual speed control.ler'were' given full'eredit. -3.14 Licensee recommendation accepted. The answer-key.has-been revised to include'the additional alternate m answers required by the exam 1 proctor's clarification.- 4 3.15 . Licensee ~ recommendation accepted . normal exam grading procedure. An adequate description'of the correct. concept is.an1 acceptable alternative to a verbatim repeat.of the-answer' hey; no change to the. answer key is-required.- 3.18. Licensee recommendation accepted. The answer key Terminology has been revised. .The. licensee:should consider correcting the referenced lesson plan.- 3.19' ' Licensee recommendation accepted.- Th caswer key- ~ H typographical error has been-corrected. n j3 3.20 Licensee recommendation :not_ accepted. -Correct-alternate terminology is an acceptable' alternative to a- .g verbatim repeat'of the answer key; no change to the answer. key is required. 3,26 Licensee recommendation accepted - normal' exam grading procedure. Correct alternate terminology is an acceptable alternative to a verbatim _ repeat of the answer' key; no ahange to'the. answer key-is required. 3.30 Licensee recommendation not accepted. Ensuring surveillance are current is not always a complete method of verifying the operability of a-safety-related pump. The. answer key has been left unchanged; adequate-descriptions of the concept of verifying the operability of the alternate MDEP.P were given full credit. ~3.34 Licensee recommendation accepted. The answer key'has been revised to include the elapsed times as acceptable alternate answers. l I ~ r

e L V ~ i l ' Resolution of Facility Comments j l 4.04 Concur. However, the equations provided in the facility comment are in one case identical .o and in the other case a derivative of the equation,s required by the answer key. Therefore, full credit will be.given for use of the proposed equations. In addition,-any. method of calculation that correctly uses'the proposed eWations will be accepted. Because there are likely to be other acceptable methods available, each will be evaluated on its ovn merits..TheLanswer key has been modified to reflect the above. 5.01 -Do not concur. Part b. did not specify that any full-length CEAs where stuck out of the core. Therefore, the candidates should have. assumed that all full-length CEAs were fully inserted, thereby requiring a 1% SDM as determined from Technical' Specification figure 3.1-0. However, figure 3.1-0 was.not provided to the cadidates. Therefore, part

b. has been' deleted.

5.02. Partially concur. No answer key change is required to part a. as the correct concept is always an acceptable alternative to verbatim adherence to the answer key. Part b. of the answer key has been mod.ified to incorporate facility comment. 5.03 Do not. concur.- The gestion clearly. indicated that an immediate action involving the Shutdown Cooling System was required. The premise and answer selections indicated an immediate controls manipulation was required-in the Shutdown Cooling System. In addition, each answer selection caused a change in the Shutdown Cooling System. There is l only one immediate action associated with the Shutdown Cooling System. Offnormal. procedure, Loss "... secure the LPSI of Shutdown Cooling, states, pump." ' 5 = 18 Do not concur. Both c. and d. can be interpreter 1 as the correct answer. Therefore, the question does not adequately test the desired knowledge / ability. l Consequently, the question has been deleted. i

3 i I i l 1 5.13 Partially concur. The K/A referenced in the facility comment (K/A 000076K305) is associated with part a. The part b. K/A is 000076A207 which specifically requires the tested knowledge / ability. 1 However, an operator will most likely have access to plant procedures containing the required information. Therefore, part b. has been deleted. 5.14 Concur. However, the additional answers should be incorporated into OP-901-038, Instrument Air System Malfunction, section 2.2, Indications. The answer key has been modified. 5.17 Concur. However, no answer key change is required as the correct concept is aways an acceptable alternative to verbatim adherence to the answer-key. 5.18 Concur. However, facility training material (LP-ZPLC-700-00, Pressurizer Level and Pressure Control, Figure 19) and RCS flow diagram (LOU-1564, G-172) refer to the pressurizer spray valves as RC-100E and RC-100F. Proctor clarification was required because the premise referred to RC-100F instead of RC-301A or RC-301B. In an attempt to clarify the question the proctor changed the valve number to RC-100A (which appeared to end confusion - apparently because candidates assumed valve was RC-301A). Valve RC-100F is dual identified as RC-301B on the referenced RCS flow diagram and is connected to RCS loop 1B. Valve RC-301A is connected to RCS loop 1A. Therefore, since the candidates assumed the_ valve number was RC-301A, RCP 1A must be stopped. The answer key has been modified. 5.22 Concur. However, the question requires LCO limits for S/G tube leakage. The facilty comment references the basis for the LCO which was not requested by the question. An answe. of.5 gpm is equivalent to 720 gpd and will be awa rded full credit. No answer key change is required. 6.02 Partially concur. The answer key has been modified to correct pump title (MDEFW vice MDAFW).

However, ensuring current surveillance may not always ensure operability of the pump.

For example, if the pump has been isolated for maintenance, it is not operable even though surveillance are current. j

D 1 i: l-l 6.07. Concur. The premise was. initially intended to refer Lto the spent fuel handling machine.

However, proctor clarification referred to the refueling machine.

The answer key-has been modified to accept any-three of nine possible answers. 6.10 Concur. The answer key has been modified.

However, irecommend incorporating terminology into facility otraining material.

6.12 Concur However, no answer key change is required as the correct concept is always'an acceptable alternative to verbatim adherence to the answer key. 6.15 Concur. However, no answer key change'is required as the correct concept is aways an acceptable alternative to verbatim adherence to the answer key. 6.26 Concur. The answer key has been modified. 6.30 Concur. Correct elapsed time will be given full credit. The answer key has been modified. i i____.-__._-.-.__._._-

t REACTOR OPERATOR EXAM COMMENT

1 COMMENT / RECOMMENDATION 1.04 L Add alternate method'c. to answer key as follows: . Method C using equations: CR ( 1 1 2 '2)

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~ ~ ~ ARho'= '2-1 ~ Keff '* K"ff 2 l Keff 1 1 = =.9756 y 1-o 1 -.025 g '~ 1~ 1 405 1 .9756 4 CR 1 ~ K*ff 135 1 - Keff 2 2 2 1 - Keff =.0081 => Kef f =.9919 2 2 ARho =.9919 .9756 = 1.68% .9919 *.9756

REFERENCE:

Standard Mathematical Practice

.'.;7.. -COMMENT / RESOLUTION 1.10 1. Add alternate Icethod to answer key.as follows: -Q = [MCpAT]nc "nc " 9 I )1007 nc nc -0 0 9 IM PAT]100% 9 0 100% 100% nc (3)(100)(60) = (100)(30) =- 6%

REFERENCE:

' Standard Mathematical Practice

QUESTION 2.01 (3.00) FILL IN THE BLANK Tha following conditions require emergency boration in accordance with OP-901-013, Emergency Boration. (0.5 each blank) c. The plant is operating at 50% power and shutdown margin is determined to be less than % delta-K/K. b. The plant is shutdown with Tavg equal to 180 degrees F and shutdown margin is determined to be less than % delta-K/K. c. An uncontrolled cooldown is in progress that is caused by excessive or excessive d. The reactor is being refueled and Keff increases to greater than or boron concentration decreases to less than opm. ANSWER 2.01 (3.00) c. 5.15 b. 2 c. feed flow, steam flow (may be transposed) d. 0.95, 1750 (0.50 each) REFERENCE LP, Selected Off-Normals at Power, LO-A.5 OP-901-013, p. 3 000024G011 ..(KA's) COMMENT / RECOMMENDATION 2.01 Change answer as follows a. 5.15 b. 231 c. 1eed Flow, Steam Flow (may be transposed) d. 0.95, 1720 NOTE: Question b. does not specify if any rods are stuck out.

REFERENCE:

OP-901-013 P. 3 Technical Specification Figure 3.1-0

(QUESTION, 2$ 0'. .(1.50)t 2 Th30follcwing cctien3 aro rcquired to bo, perform:d by th3 operators prior < toecxiting the control room whenLimplementing.OP-901-004, Evacuation of . Crntrol-Room and Subsequent-Plant' Shutdown. What:is the. reason / basis each cf.these actions is included in OP-901-004?. (0.75 each) a ic.. Verify Spray. Valve. selector switer. in the BOTH. position. { b.: Reset.khe Moisture' Separator Reheatar controls. _ ANSWER 2.02 (1.50) .si Facilitate depressurization (0.75) b. Prevent excessive RCS cooling (0.75) !. REFERENCE LP, Off-Normal Procedura - Evacuation'of Control Room and. Subsequent Plant Shutdown, LO-4 LP,-Off-Normal' Procedure --Evacuation of Control Room and Subsequent Plant. Shutdown, p. 8, 9 000068K318. ..(KA's) COMMENT / RECOMMENDATION 2.03 Change answer as follows: -a. Facilitate Depressurization-(Accept concept)- (0.75). b. . Prevent Excessive RCS Cooling (Accept concept) (0.75)

REFERENCE:

N/A

. fgn. - x n. , T. < 4, s w GV ~ ^ $ 5 UESTION ' J2.04 - il. 00)' Q ., 9 a i iTho plant'is in1 Mode 5 with. shutdown: cooling Train B in service /when#an. 1 b -Volcctrical fault.results in.a loss ofJinstrument bus'3MB-S. Whatimmediate. % c:ntrol switch action (NOT alarm acknowledgement or announcement) should ' 'tho. Primary Nuclear Operator take for the. loss-of:3MB-S? --ANSWER-2.04 (1.00) Trip LPSI pump B-g REFERENCE [OP-901-054, p. 18 -OP-901-046,:p. 7' .LP,; Selected Off-Normals whileLShutdown, LO-2.a. f 000057A219 000025G011 ~.00002 5G010 ...(KA's) COMMENT / RECOMMENDATION '2.04 Recommend deletion of question. Procedure OP-901-054 has NO operator Immediate Actions. 'The symptoms'for entry:into OP-901-046 do NOT include a Loss of Instruments Bus 3MB-S.' l This. question requires the operator.to recall from memory all' components lost on a. Loss of Instrument Bus.3MB-S. Operator entry into:OP-901-046' would'be initiated by. Control ~ Room annunciators, alarms and indications. L

REFERENCE:

OP-901-054 Pg. 16

.OP-901-046 Pg. 7 l l = _ - _ _ _ _ - - _ _ - _ _ - - _ _ - - . _ ~ _.

s :.- < 3. H QUESTION: 2.11 (1.00) Vh 1StSta the TWO (2). LCO' limits given' in Technical Specifications for~ stean .g^nerator' tube. leakage. Action statements.are NOT required., .(0.50 each). Q I; l i ANSWER l . 2.11-(1.00) '1.- 1..gpm total SGTL ( 0. 5)- 2.. -720 gpd SGTL in any S/G (0.5) REFERENCE Tcchnical Specifications, Definitions Tcchnical Specifications, LCO 3.5.2 000037G003 ..(KA's) . COMMENT / RECOMMENDATION -2.11 Change answer-(2.) as follows 2. 720 gpd SGTL in any S/G (0.5 gpm) -(0.5)

REFERENCE:

Techn'ical Specification Bases 3/4.4.5.2 .j e mm-.-_-----

Y i 9 . QUESTION'. J2.15; ( 1. 5 0 ).. LTh3 plant::is operating at steady state 100% power when an instrument air l-Jh22 der leak causes a sustained ~ decreasing' instrument. air system pressure. s. ' Assuming-no operator action'is.taken and the reactor does not_ trip, what are TWO-(2) valve actuations that will occur at. low instrument air pressure and willLreduce main feedwater pump suction pressures? .(0.50 each) b. FILL IN.THE BLANK-On decreasing instrument air pressure, OP-901-038, Instrument Air. Malfunction, requires the operator to trip the reactor when instrument. air header pressure reaches psig. (0.5) 1 ANSWER 2.15 (1.50)- 'l 1 '.a. 1. Condensate bypass to condenser valves open. (0. 5)- 2. Heater drains bypass to condenser valves open? (0.5)

b.-

65 psig.(+/ 5 psig)- (0.5)

REFERENCE OP-901-038, p.

7, 8 LP, Secondary System Off-Normals, LO-1.b 000065A206 000065K303 ..(KA's) COMMENT / RECOMMENDATION 2.15 Change answer (a.) as follows: a. Any two of the following (0.5 each) 1. Condensate bypass to condenser valves (short cycle recire valves) open 2. Heater drains bypass to condenser valves (alternate drain valves) open 3. Condensate pump recirc valves open 4. Heater drain pump recire valves open REFERENCEi Drawing LOU-1564-G153, Sht. 1-6 LOU-1564-G155, Sht. 3 _ _ - _ _ _ - _ = _ _ - _ - _ _ - _

QUESTION 2.18 (1.50) Th3 plant is operating steady state at 100% power when a valid automatic rc::ctor trip signal is actuated that does NOT result in a reactor trip. Lint-the THREE (3) contingency actions that must be performed in accordance with OP-902-000, Emergency Entry Procedure. (Assume that each contingency cction is NOT successful until all contingency actions have been completed.) ANSWER 2.18 (1.50) 1. Manually trip the reactor. (0.50) 2. Emergency borate. (0.50) 3. Open OST A32 and SST B32 breakers for 5 seconds and reclose. (0.50) REFERENCE OP-902-000, p. 2 LP, Introduction and Emergency Entry Procedure, LO-8 000029G010 g.(KA's) COMMENT / RECOMMENDATION 2.18 Change answer (3.) as follows: 3, Open SST A32 (feeder to A32 Bucs) and SST B32 (feeder to B32 Buss) breakers for 5 seconds and reclose (0.50)

REFERENCE:

Alternate Terminology J

7. )J n: MQUE ; TION T f2.19' (1.00) MULTIPLE CHOICE J(Select the correct answer. )-

Th2 plant is

1. c.- s 0 0 4 r.

? l failure'cause; operating steady steady at'100%Jpower when a controller s' pressurizer spray valve AG-teef to open fully.. 'The operators take the appropriate actions-in.accordance with OP-901-002,-RCS* 'PrCasure Control: Malfunction, which include. stopping which RCP?- ?!l si.. ~1A'

b.-

1B .. c. 2A o

d.-

2B. 5 UANSWER 2.19 (1.00); ~----b---- A s '. $ s u. .v*a.- . REFERENCE OP-901-002, p.:10

RCS: Flow Diagram - LOU-1564, G-172' 000027A215.

..(KA's) COMMENT / RECOMMENDATION' 2.19 f

Change _ answer to (A)~

This-change is required due to proctors clarification. NOTE: - Proper Waterford-3 terminology for this valve is RC-301A.

REFERENCE:

l RCS Flow Diagram LOU-1564; G172

---

_~--------,_-x_--x--____--,,

p. w / l-

f. QUESTION:

43.'01-(2.00)'- 1 separate conditions / parameter trips that will-cause:an .Whstiare FOUR:l(4) cutostop of a running'-vaste. gas compresso?!?: Satpoints are NOT~ required. (0.50.each) .l!. . ANSWER. .' 3. 01 - .(2.00) -: 1. = High' discharge temperature (120 7!) -(0.50 each)'

2. -

' Low suction pressure'(1.5 psig), 3. Oil / gas leak detector activated (20 'psig) (1st or.2nd stage) ~ . 4 '. - Low oil evel (O. inches) REFERENCE ..LP ZGWM-700-00,.LO-6 & pg 8 071000A420 ..(KA's) -. n r . COMMENT / RECOMMENDATION .3.01 Change answer as follows: Accept any four (4) of the following (0.50 each)' 1. LHigh Discharge Temperature (120F) 2. Gas Surge Tank.(Low Suction Pressure) (1.5 PSIG) 3. 011/ Gas Leek Detector Activated (20 PSIG) (1st or 2nd Stage) 4. Low 011 Level (0 inches) 5. ~ Underveltage 6. Overcurrent

REFERENCE:

CWD - LOU 1564-B424, Sht. 682 & 681 o _s. a-.-

QUESTION; .3.02 -(2.00) .WSOta Condensate Pump B"is being used.to pump Waste Condensate Tank A to itha circulating water. system for discharge. a.. What'are THREE (3) separate conditions /paraineter trips that' will cause an,autostop of waste condensate pump B?' Setpoints are-NOT required. (0.50 each). b.. What other automatic component actuation (NOT an alarn orLannunciator) will' occur.in the liquid wasta management system when the.autostop of-waste condensate pump B occurs? (0.50) ANSWER. 3.02 (2.00)-

Q.

1. Wasta condensate tank A outlet valve not open (0.50 each)- Suction. cross-connect (WCT outlet X-connect) not open

2.. : Low level in waste condensate tank A 3.

~ b.. Liquid waste discharge valves-(LWM-441/442) close REFTP.ENCE LP ZLWM-700-00, LO-4~,5 & pg 13,14 068000A404 ..(KA's) COMMENT / RECOMMENDATION-3.02 Change answer (a.') as'follows: Accept any three (3) of the following (0.50 each) 1. Waste condensate tank A outlet valve'not open 2. Suction cross-connect (WCT outlet X-connect) not open 3. Low level in waste condensate tank A 4. Overcurrent 5. Undervoltage

REFERENCE:

CWD - LOU-1564-B424, Sht. 664 & 666 -__-_x__.

(QUESTION / '3~.03 (2. 00) l WhSt;are the FOUR'(4) required' conditions / interlocks.'needed to.be satisfied before=an Emergency Diesel Generator (EDG) output breaker will close automatically on a loss of'all off-site power? -(0.50-each) ~

ANSWER 3.03

( 2. 00)- 1.- -3 Bus to 2 Bus tie breaker open ( > 5 sec) 2. LUndervoltage or degraded voltage on 3 Bus (0.50 each)' 3. No lockout / trip. signal -4. EDG at rated conditions (speed / voltage). tREFERENCE .LP ZEDG-7000-00,,LO-9.& pg.56' 064000A302 ..(KA's) COMMENT / RECOMMENDATION 3.03 -Chane answer as follows: Accept any four (4) of the following:

1..

3 Bus to 2 Bus tie breaker open (> 5 sec) 2. Undervoltage on 3 Bus' '3. Degraded voltage on 3 Bus-4. No lockout / trip signal. 5. EDG at rated. speed 6. EDG at rated voltage NOTE: Although-lesson plan groups.some conditions together these are indeed separate conditions / interlocks.

REFERENCE:

LP. ZEDG-700-00 Pg. 55 and 56 e

Liu l, s ' QUESTION. 3W4 - (1150) 'l Wh t'are the THREE (3) different, unlike events / signals that will cause-the .. Emergency Mode F.2el Control Valves t on an Emergency _ Diesel Generator to ~ .Cctuate. (go operi or close) ? Setpoints are.NOT required. (O.50 each) ANSWER 3.04 (1.50)- 1.- SIAS start! .(0.50 each) 2. 3 Bus UV/DV start 3. Generator'(phase) differential'(87/DG) trip -REFERENCE LP'ZEDG-700-OO,.-LO-6 and pg 30 064000K402 ..(KA's) COMMENT / RECOMMENDATION 3.04 Change answer-as follows: Accept any three (3) of the following: l'. .SIAS start 2. 3 Bus UV/DV start ~ 3. . Generator (Phase) Differential (87/DG) Trip 4. Gene;ator Overspeed 5. Going to stop on SIAS but no loss of offsite power (i.e. Bus tie breaker closed) 6. Both EDG output breaker and bus tie breaker are closed (places diesel in test mode) 7. Normal test mode shutodwn (for cooldown cycle)

REFERENCE:

Emdrac LOU-15G4-2171 LOU-1564-2172 LOU-1564-2183 LOU-1564-1989 LOU-1564-1990

.(

QUESTIbN-3.06 ' - (1.' 5 0)

IzIf1theplantis.' stable'at90%-powarwithall' systems ~inautomatic,-howwill thy speed of the B main feedwater pump - (MFWP) respond.to each!of the fcllowing signals from/in~#2.feedwater control system-(FWCS)?. Consider each signal separately.- (0.50'aach). c. ' Reactor Trip Override 'b.- High' Level Override .c. Level Deviation- ' ANSWER 3.06' (1.50)- Goes to minimum 3900 rpm). (0.50 each) c. 'Goes to/ Remains a(t spted demanded.by #1 FWCS b.- Goes to/ Remains at speed demanded by B MFWP manual conto *11er c. REFERENCE LP ZFWC-700-00, pg 11,12,27 059000K405 ..(KA's) COMMENT / RECOMMENDATION 3.06 Change answer (c.) as follows: c. Goes to manual / remains at speed demanded by B MFWP. manual controller

REFERENCE:

LP ZFWC-700 (L124-024-01) Pg. 27 1 _____________________J

,n y l-(QUESTION? ,3'14- -(1.50) Wh t'THREE (3) fuel handling interlock conditions will automatically stop 'tha Traveling, Bridge with_ fuel; movement in progress?' Assume no operator- 'Cction.: (0.50 each)- 7eah)., if,, '/j, ?.,.,. s.ll. C /, K $ *

• W* h **~ * ^ *
• K "x. U. ; p..s.. ". g,,,, *, _

~,...... -. n.;.....J i f -

ANSWER 3.14' (1.50)

1..

, Bridge approaches wall-with trolley not.in gate' zone. ?2.1 Hoist' operating. 3. End of rail reached (limit switches). (0.5 each) 2 REFERENCE =LP, Fuel Handling and Storage Equipment, p. 15 'LP, Fue1~ Handling and Storage Equipment, LO-2.a 034000K402 ..(KA's) COMMENT / RECOMMENDATION 3.14 ' Add the following to answer. 98 Accept any three (3)'of the following: 1) Mast Bumper Contact 2) Grapple in or below Upper Grapple Operate Zone (UGOZ) 3). Holst being operated 4)' Spreader on fuel mas not retracted-5) Aligner on CEA mast not retracted 6) Fuel Hoise in " fuel only" region with fuel on .7) CEA Hoiset in "CEA only" region with CEA on. 8). One hoist not at Up Limit unless in Upender Area 9) In upender region with upender not vertical. NOTE: 'Due t'o proctor clarification during examination.

REFERENCE:

LP -ZFHS-700-00 Pg. 15 and 27

g. QUESTION' 3;15 (1.00) ) 1 A CEAC fails'and:will:not reset. What are the THREE (3) steps / functions I i.. .th'1 CPCs perform to determine'. valid penalty factors-for use when'only one CEAC is operable? (0.50 each) l 8 ANSWER 3.15 (1.50) 1.. . " Remember"' the last valid penalty factors received from the failed CEAC.(O.5) '2. Compare these factors with the penalty _ factors received from the operable CEAC.(0.5) 3. Select the largest-of the compared penalty factors for use..(0.5) REFERENCE LP, CPC, p. 18 LP, CPC, LO-5 012000K607 ..(KA's) COMMENT / RECOMMENDATION 3.15. Accept wording that reflectr> concept as long as all answer key components are present.

REFERENCE:

NONE l i l l' l

_ QUESTION ~3.18 (1.50) A2Cume that the Computer Room Halon Fire Suppression'aistem fails to .r i m e automatically when required, 'HOW and WHERE is the system manually released from the Control Room?. c.- (0.75) b. 'HOW and WHERE'is the system manually released from the local station? (0.75) ANSWER 3.18 (1.50) c.: Depress the (Emergency Manual Actuate) pushbutton on the Master Remote Control Pansl (0.75) E. Rer.ove lockpin and press button on top of the selected cylinder. (0.75) REFERENCE .LP, Fire Protection,and Detection, p. 22 LP, Fire Protection and Detection, LO-7 086000A406 ..(KA's) 4 COMMENT / RECOMMENDATION 3.18 Change Terminology.. Press button... in answer (b.) to... turn lever...

REFERENCE:

Actual Plant configuration, Lesson Plan in error

r-g fQUESTION. 3.19. (1.50)

C:r.c:rnNig. tho.dOcign of tho CVCS lotdtwn cyctom:

ia. 1 What'is the basis / reason-for-the MINIMUM flowrate permitted by the letdown ~ throttle valves when operating in automatic? .(0.50) -_ hat is the' basis / reason for the MAXIMUM flowrate permitted by'the W b.. -letdown throttle valves when operating in. automatic? (O.50) c. What-is the purpose of the lead / lag electrical unit located between the. pressurizer level controller-and the letdown throttle valve controller? (0.50) ANSWER 3.19 (1.50)

4..

Ensures adequate heat transfer (prevents thermal shock) across the residual heat exchanger. (0.5) -b. Based on maximum charging pump' capacity minus RCP CBO flow. (0.5)- 'c.

Slows the' speed oflthe letdown flow control valve stroke'(or prevents steam flashing / water hammer-instability in letdown system).

-(0.5) REFERENC:: LP, Pressurizer Level'and Pressure Control, p. 10, 17 LP, Pressurizer Level and Pressure Control, LO-2, 3 011000K604 004020A101 004000G010: ..(KA's) COMMENT / RECOMMENDATION 3.19 Change term residual to regenerative in. answer (a.) Typographical error

REFERENCE:

LP ZCVC-700-02 Pg. 10 l' u _j

g_..-... 7. ~- - r [ QUESTION.? 3.20; ' (1.50)-

1. LWhtnitheIECCS?is^ shifted:to recirculation-on'a Recirculation Actuation l'Signaly(RASF, what are:the: SIX- (6). valves that must. be closed by-the tcparator to prevent highly radioactive liquid from reaching-the-RWSP?-

-(0.25 each): INSWERT 3.20 (l'. 5 0) 'RWSP,~ outlet valves (SI-106A/B) m HPSI/LPSI pumps miniflow isolation. valves -(SI-120A/B)' ~ HPSI/LPSI' pumps minifins isolation backup valves (SI-121A/B) +- J(Valve' numbers acceptablei..but not.' required.) (0.25.each), REFERENCE

LP,-Containment Sprayr p..L29

--LP,' Containment Spray, LO-5 006020K401- ..(KA'r.) COMMENT / RECOMMENDATION. 3.20 . Add the following alternate terminology to answer: HPSI/LPSI,(Safeguards Pumps) Miniflow Isolation-Valves (Recirc Valves) Miniflow Isolation Backup Valves (Recirc Valves). . Accept: concept four'(4) recric valves close

REFERENCE:

LP ZSI-700-00 Pg. Il and 16 LOU-1564-016 /, Sht. 1 9

ryyr---- 4 ~ .i:- QUESTION 3.26-(1.50) Lict the! electrical buses that supply power to the motors of the following .EFW components / equipment. (0.50 each) a. Turbine-driven EFW pumpfsteam line shutoff valve.(MS-401A)_' - b. Motor-driven EFW pump A c. Motor-driven EFW pump B ANSWER' 3.26 (1". 5 0 ) 0,- 3AB-DC-S f-b. 3A3S (0.5 each) c. 3B3S - REFERENCE-LP, EFW System, LO-D SD, EFW System, p. 32 t)61000K202 ' 061000K201 ..(KA's) . COMMENT / RECOMMENDATION 3.26 Accept alternate terminolgy a. 3AB-DC-S (ABsDC-S),(AB DC Bus) b. '3A3s (A3S) (4160 Safety Bus A) c. 3B3S (B3S) (4160 Safety Bus'B)

REFERENCE:

N/A l J 'Ww--:--_= m

7. i!- jQUESTION.. 3.30- -(1.00)

During: a routine' surveillance run of the: B motor-driven: EFW pump, excessive

-motor vibration.is-noted.- In accordance with OP-100-001,.. Duties and. i? R~rponsibilities.of; operators on' Duty, whatfoperational. requirement must- -ba satisfied on'-A motor-driven EFW pump _.before maintenance.can be started. E j' cn B motor-driiren EFW pump?. r I f I ANSWER 1 3.30 (l. 00') (A MDETWP) operability. must be verified -REFERENCE ,,OP-l'00-001,.p. 33 .194001K102 ..(KA's)- ] ' COMMENT / RECOMMENDATION 3.30' Change answer as follows: (A MDEFWP) Operability must be verified (Ensure surveillance are current)

REFERENCE:

Technical' Specifications 4.03. l 4 h i ___._________.__n.__1____ J

g, <ib. R ' QUESTION! '3.34 , - (2.00). P-10-001,' section 8. 5, Power Increase to 100%, requires use of the Turbine jLoading Curve and the Turbine-Startup Curve to determine the maximum. -turbine::: loading rate during a? plant startup. The following data is.given: lts--Initial HP turbi'ne.first stage metal temperature was 100 degrees F. '"Currcct HP turbine first stage metal temperature.is 400 degrees F. . Initial. turbine steam admission time was-0600. Currcnt turbine fatigue index,.is 10000 cycles.

If the main turbine has just been: brought to 10% load at 1000,.use the

~ atttched. curves End the above data to determine FOR'EACH: CURVE the earliest timo that' turbine load.can reach 100%. c. ' Turbine Loading Curve (1.0) b. Ttrbine Startup Curve (1.0) n. ' WSWER. 3,34' (2.00) 4. 1150 (+/- 20. minutes) (1.0) b. 1220 (+/- 15 minutes) (1.0) REFERENCE OP-10-001, p. 73 OP-05-007, p. 30, 31 194001A108 ..(KA's) COMMENT / RECOMMENDATION 3.34 Accept elapsed time instead of clock time for answers.

REFERENCE:

OP-10-001 Pg, 69 OP-05-007 Pg. 30 and 31 1 2__:______________-_-_

o.- SENIOR REACTOR OPERATOR EXAM COMMENT

g-i COMMENT / RECOMMENDATION 4.04 Add alternate method c. to answer key as follows: u: Method C using equations: CR * (1 - Keff ) = CR * (l ~ K*ff ) y y 2 2 Aho = K*ff2 1 ~ K*f Keff

• K*ff 2

l .Keff =, 1 1 y =.9756 1 -_p 1- .025 g 'Keff CR y: l 405 1 .9756 CR 1 - Keff 135 1 - Keff y 2 2 1 - Keff =.0081 = Keff ~ *E

• 9 2

2 ARho =.9 19 6 = 1.68% delta-K/K (+/- 0.05%) } 6

REFERENCE:

Standard Mathematical Practice

?

h M !JQUESTIONL

'5.01 . '( 3. 0 0 ) FILLIN THE BLANK. i Thi foll'owing conditions, req'uire emergency boration in accordance.with 4- .OP-901-013, Emergency,Boration. (0.5.each blank) o.. The plant is, operating at 50% power and shutdowa margin is. determined ^ to be less than' b..

The plant is' shutdown with Tavg. equal'to-180 dagtses':F and shutdown.

~ .i margin is determined'to be less than c. 'An uncontrolled cooldown is in progress that is caused by' excessive, or-excessive d.

The-reactor is being refueled'and-Keff' increases to' greater'than or boron concentration decreases to less than opm.

-ANSWER 5.01 (3.00) 'O.' 5.15 .b. 2 c.. _ feed flow, steam flow (may be transposed) td. 0.95, 1750 '(0.50 each) REFERENCE LP, Selected.Off-Normals at Power, LO-A.5 OP-901-013, p. 3 3.9 .000024G011-000024G011 ..(KA'_s) COMMENT / RECOMMENDATION 5.01, Change answer as follows a. 5.15 b. 2 OR 1 fee Flow, Steam Flow (may be transposed) c. d. 0.95,'1720 NOTE: Question b. foes not specify if any rods are stuck out.

REFERENCE:

OP-901-013 P. 3 Technical Specification figure 3.1-0 t-a

E& 0" c.. QUESTION .5.02 -(3.00);

f' Yh..; State the' basis!for each of?the following~ actions performed prior to.

~ 33 ~ exiting the control room wher. implementing OP-901-004,; Evacuation of-ControlERoom:and SubsequentJPlant Shutdown. ~(0.75:each) 1.' ' Verify Spray Valve Selector switch.in the'BOTH position. 2. 'Resetjthe Moisture Separator. Reheater' controls.' Why does OP-901-004'(case II with fire) require the' availability _ b.. tof each of the following?' '(0.75'each) l '. Diesel' Generator B .2. CCW~ pump B-s - ANSWER 5.02' (3.00)

0. -

1.- Facilitate depressurization-(0.75) .2. Prevent excessive RCS cooling (0.75) b.- 1.' Diesel generator B'is needed_t'o supply power _to Safety Train.B controls which are used because B train cables run outside cable. spreading room (which could be the source of, or endangered by, the fire that has caused the CR evacuation).. (0.75)' 2.: CCW pump-B is needed.to provide cooling for DG B. .(0.75) -o REFERENCE LP, Off-Normal Procedure . Evacuation of Control Room and Subsequent; Plant ' Shutdown,. LO-4 LP, Off-Normal Procedure - Evacuation of Control Room and Subsequent Plant Shutdown, p. 8, 9 '4.5, 3.5 000068G007' 000068K318 000068G007 000068K318 ..(KA's) COMMENT / RECOMMENDATION 5.02 . Change answer es follows: a. -1. Facilitate'Depressurization (Accept concept)' (0.75) 2. Prevent Excessive RCS' Cooling (Accept concept) (0.75) b. 1. EDG B is needed to supply power to safe'.;y train B components, (NOTE) 2. CCW Pump B is needed to provide coolir-for DG B. NOTE: Reloainder of the original answer of b.1. was included in the lesson plan as clarifying information but was not solicited by the question.

REFERENCE:

LP' ZPPO-803-01 Pg. 6 r

/ .iQUESTIONi-5.03 (1.00)' i " MULTIPLE CHOICE (Select the. correct answer.) [Thi plant'isiin-Mode-5.with shutdown cooling Train B in service on.RCS: loop ) h ' 2 when an: electrical 1 fault: results in a: loss of instrument' bus 3MB-S. The I' CRS:should;immediately direct: [n; StartingcLPSI pump A. ib.. -Tripping LPSI pump B. I (c.. l Closing; shutdown cooling suction. isolation valve', SI-401B. d.. Closing. shutdown cooling' loop discharge isolation-valves,.SI-138B and-SI-1398.- p q \\ ANSWER 5.03 (1.00) I 1 <b. REFERENCE i OP-901-054,ep. 18 OP-901-046, p.~7, "LP,' Selected Off-Normals whil& Shutdown, LO-2.a '4.3, 3.9, 3.9 0000256011 0000256010 000057A219 0000256011 0000256010-

000057A219

..(KA's) I ~4 .. COMMENT / RECOMMENDATION-5.03 I L . Recommend-DELETION of question Procedure OP-901-054 has N_O operator Immediate Actions. The symptoms-for entry into OP-901-046 do NOT include a Loss of Instrument ' Bus-3MB-S.- 1j This question requires the operator to' recall from memory all components i lost on a Loss of Instrument Bus 3MB-S. Operator entry into OP-901-046 l would be initiated by Control Room annunciators, alarms and indications, j I i l

REFERENCE:

l OP-901-054 Pg. 16 CP-901-046 Pg. 7 I l \\ ?- j L- _a

7 QUESTION 5.08- -(la00) MULTIPLE CHOICE-(Select the correct answer.) The: plan': is operating steady. state at~60% power with VCT level at 44% and Reactor Makeup in Manual when a 30 gpm leak occurs in the charging line. Assuming letdown does not isolate, NO reactor trip, and NO operator cctions are'taken, VCT level-will: c. Increase and stabilize at'.a higher level. b; Increase, then decrease. c. Decrease, then increase. d. Decrease and stabilize at a lower level. ' ANSWER-5.08 (1.00)- c. REFERENCE LP, Selected Off-Normals at Power, LO-B.6 ?OP-901-014, p. 6 3.8 000022A201. -000022A201 ..(KAds) COMMENT / RECOMMENDATION 5.08 Accept either c. or d. as correct answers NOTE: When level restores to 8% charging pump section swaps back to VCT and cycles between 6 and 8%.

REFERENCE:

LP ZCVC-700-00 Pg. 18.and 19

y-r ~

i. QUESTION l 5 '.13; l ( 1. 75 ) '

. The plant; is: operating isteady state at'.804: power. - RCS gross activity'has

been trending higher'as. indicated by RCS. sample. analyses..The CRS=

, implements OP-901-021, High Activity in the'RCS. -102 Why does'.O'P-901-0216 direct the operator to start.'all available

charging pumps?1 (O.75) b.:

MULTIPLE. CHOICE (Select the. correct ' answer. ) CVCS purification: ion exchanger decontamination-factori(DF) has been - steadily decreasing.,.In'accordance with'OP-901-021,.the ion' exchanger, should-be isolated and flushed when its'DF first' reaches: (1.0) . 1.. 0.9-2. 0.7 . 3. O.5 4. 0.3 ANSWER 5.13 (l'. 7 5 ) a. To maximize purification flow. (0.75), 'b. 1 ( 1. 0 ) '. REFERENCE SOP-901-021,-p. 7.- 3.6, 2.7 000076A207 000076K305-000076A207' 000076K305 ..(KA's) COMMENT / RECOMMENDATION 5.13 Reconnend deletion of part B of question. This. action is a subsequent procedure action and is not.specifically. required knowledge in KA 000076K305. 4

REFERENCE:

OP-901-021 Pg. I KA 000076EK305 u-________-_______

n QUESTION 5.14' (2.25) The plant is operating at steady state 100% power when a header leak causes a sustained decreasing instrument air system pressure. The CRS implements OP-901-038, Instrument Air Malfunction. Assuming no operator action and the reactor does NOT trip, what are-a. TWO (2) reasons why feedwater flow to each S/G will decrease? (0.5 each) b. OP 901-038 directs the operator to control S/G levels by manually adjusting main feed pump turbine speed. Why can't feedwater flow be automatically controlled by the Steam Generator Level Control System? (0.75) c. FILL IN THE BLANK The operator is required to trip the reactor when instrument air header pressure first reaches psig. (0.5) ANSWER 5.14 (2.25) O. 1. Condensate bypass to condenser valves open. (0.5) 2. Heater drains bypass to condenser valves open. (0.5) b. Main feedwater control valves fail as is (without instrument air). (0.75) c.- 65 psig (+/- S psig) (0.5) REFERENCE OP-901-038, p. 7, 8 LP, Secondary System Off-Normals, LO-1.b 3.4, 4.2, 3.9 000065K308 000065A206 000065K303 000065K308 000065A206 000065K303 ..(KA's) COMMENT / RECOMMENDATION 5.14 Change answer (a.) as follows: a. Any two of the following (0.5 each) 1. Condensate bypass to condenser valves (short cycle recirc valves) open 2. Heater drains bypass to condenser valves (alternate drain valves) open 3. Condensate pump recirc valves open 4. Start up feed regulating valve closes 5. Feed pump recric valve opens 6. Heater drain pump recirc valve opens

REFERENCE:

Drawing LOU-1564-G153, Sht. 1-6 LOU-1564-G155, Sht. 3 LP ZFWC-700-00 Pg. 15 and 16

-QUESTION 5.17.' (1.50) The plant:is' operating steady state at 100% power when a valid automatic r actor trip' signal is actuated that does NOT Iesult in a reactor trip. List the THREE:(3) contingency actions that must be performed in accordance Evith OP-902-000, Emergency Entry Procedure. (Assume that each action fails until all contingency actions have been completed.) ANSWER '5.17 (1.50) l '. Manually trip the reactor (0.50). <2. Emergency borate. '(0.50) 2. Open both the following breakers for 5 seconds and reclose: '(0.25) a. SST A32 feeder (0.125) b. SST B32 feeder.(0.125) REFERENCE OP-902-000, p. 2 LP, Introduction and Emergency Entry Procedure, LO-8 4.5 000029G010 000029G010 ..(KA'w) COMMENT / RECOMMENDATION 5.17 Accept alternate terminology a. SST A32 Feeder (Feeder to A32 Buss) b. SST B32 Feeder'(Feeder to B32 Buss)

REFERENCE:

N/A

[ QUESTION 5.18. -(1,00) ,c ( MULTIPLE CHOICE:(Select the correct answer.). g.joog -TheplantIis'operatingsteadysteadyat-100%Ipowerwhenacontroller ifailure causes pressurizer spray valve "" ^^^" to fully open. The

operators take the' appropriate actions in accordance.wlth OP-901-002, RCS Pressure control-Malfunction, which includes stopping RCP:

.,X a.- '1A ,b.. '1B-c.= 2A -d. 2B l ANSWER -5.18 (1.00) b. h s.i e u :s. w < REFERENCE 9. 'OP-901-002, p. 10 i

RCS Flow Diagram - LOU-1564, G-172 4.0 000027A215

.000027A215 ..(KA's) l l COMMENT / RECOMMENDATION 5.18 Change answer to-(A) i This change is required due to proctor's clarification. l NOTE: Proper Waterford-3 terminology for.this valve is RC-301A. .,j

REFERENCE:

RCS Flow Diagram LOU-1564; G172 I I i i l l l 1 .1 l i

[.; a @:ii + p 5.22 -(1.00) p -QUESTION State the Two-'(2) appli' cable. Technical Specification LCO limits for"S/G tube leakage.- ~-(0.5 each). -ANSWER, 5.22 '(1.00) l'

1 gpm total SGTL.

'(0.5) 2.. = 720 gpd SGTL 'in ~ 2ny S/G ( O. 5 ).- REFERENCE Technical. Specifications, Definitions Technical Specifications, LCO 3.5.2 + 3.9,'4.1 000009G003. 000009G008 000009G003 ^000009G008 ..(KA's) COMMENT / RECOMMENDATION 5.22 Change answer (2.) as follows 2. 720 gpd (0.5 gpm) SGTL in any S/G (0.5)

REFERENCE:

Technical Specification Bases 3/4.4.5.2-1 l

SQUESTION

6.02 (1. 0 0 ) '

mo uva

During.'a routine' surveillance test of the-B MGM:W pump, excessive shaf t

'lcakage was noted. 'In accordance with OP-100-001, Duties.'and R:sponsibilities ot Operators on Duty, what administrative requirement must be satisfied regarding A MDAFW. prior to. initiating maintenance on B MDAFW pump?. ANSWER. '6.02 .(1.00) Varify operability (of A MDAFW pump)~ REFERENCE OP-100-001, p.-35 4.1 061000G011 061000G011 ..(KA's) COMMENT / RECOMMENDATION' 6.02 Change answer as follows: Verify operability (of a MDEFW pump) (ensure surveillance current)

REFERENCE:

Technical Specifications 4.03-S 1

---

_-_-__a

j; I QUESTION: 6.07 (1. 50)' h L.i

Wh'at-THREE (3) fuelLhandling interlock. conditions'willsautomaticallyEstop sthe Traveling Bridge with; fuel. movement:in progress?

Assume.no operator itction~. (0.5.each)

n.,

~' i. Q Ga $p. ' -, J..Au1y %'E*Om'J N k Y'/d>M*.dn'. T 4...:- o w - s n .~..A.Vp ANSWER.- '6.07 (1.50) 12

Bridge approaches wall with trolley not in gate zone.-

_2. . Hoist operating. 3. End of rail' reached (limit switches). .(0.5 each) REFERENCE LP, Fuel Handling and Storage Equipment, p. 15 LP, Fuel' Handling and. Storage Equipment, LO-2.a 3.3 034000K402 034000K402 ..(KA's) COMMENT / RECOMMENDATION .6.07 Add the following to answer. OR a Accept any three (3) of the following: 1). Mast' Bumper contact 2). Grapple-in or below Upper Grapple Operate Zone (UGOZ) 3) Holst being operated 4) , Spreader on fuel mas not retracted 5) Aligner on CEA mast not retracted 6) Fuel Hoise in " fuel only" region with fuel on 7) .CEA Hoiset in "CEA only" region with CEA on 8)- One hoist not at Up Limit unless in Upender Area 9) In upender region with upender not vertical. NOTE: Due to proctor clarification during examination.

REFERENCE:

LP ZFHS-700-00 Pg. 15 and 27 l j

{ l QUESTION-: t6.10' (1.50) L .If the' Computer Room Halon-Fire; Suppression System' fails to automatically l-r21 ease when(required,-how.is:it MANUALLY released? Include both LOCAL and-REMOTE operation. (0.75 each) l' ANSWER 6.10 .(1.50) R: mote'- depress the (Emergency Manual-Actuate) pushbutton on.the Master. R mote Control Fanel.(in.the Control Room). (0.75) Local - remove lockpin and press button on top of the selected' cylinder. (0.75) REFERENCE LP, Fire Protection and Detection, p. 22 LP, Fire Protection and Detection, LO-7 3.2 086000A406 086000A406 ..(KA's) COMMENT / RECOMMENDATION 6.10 Change Terminology... Press. button... in answer to... turn lever...

REFERENCE:

Actual Plant Configuration i \\

L l.. QUESTION. l6.12 ' (1.50)' On 'a1 RAS, what are the SIX (6) valves that must be closed by a control ' room operator to isolate potential leakage paths from the. SIS sump to.the RWSP? (valve' numbers are acceptable but.not required.) '(0.25 each)- ANSWER-6.12 (1.50) RWSP outlet valves (SI-106A/ B)' (0.25 each) LMiniflow valves from HPSI, LPSI, and CS pumps (SI-120A/B and SI-121A/B) (0.25 each) ' REFERENCE LP, Containment Spray, p. 29 LP, Containment Spray, LO-5 3.0 006020K401 006020K401 ..(KA's) COMMENT / RECOMMENDATION 6.12 Add the foll' wing alternate terminology to answer: o HPSI/LPSI (Safeguards Pumps) Miniflow Isolation Valves (Recirc Valves) Accept concept four (4) recire valves close

REFERENCE:

LP ZSI-700-00 Pg. 11 and 16 LOU-1564-G167, Sht. 1 ___._____.______.__.a.

4 ---QUESTION = [6'.15 L (1.50): cList-the buses that supply power to the motors of.the following EFW D 1 components / equipment. - .(0.5 each) l Oi Turbine-driven'.EFW pump steam-line shutoff valve-(MS-401A) -b. Motor-driven ETW pump-A c. . Motor-driven EFW pump B l., ANSWER 6.15 (1.50) a. 3AB-DC-S .b.- 3A3S (0.5 each)1 c. 3B35 -REFERENCE LP, EFW System, LO-D SD, EFW System, p. 32 3.3, 3.7 061000K201-061000K202 061000K201 061000K202 ..' ( KA ' s ) - COMMENT / RECOMMENDATION 6.15 . Accept alternate terminolgy a. 3AB-DC-S (AB-DC-S) (AB DC Bus) b. 3A3S (A3S) (4160V Safety Bus A) c. 3B3S.(B3S) (4160V. Safety Bur B)

REFERENCE:

N/A u

QUESTION 6226;, ( 1. 00 ) - cFILL IN THE BLANKS In.accordance.with Technical. Specifications and OP-100-001, Duties and R:sponsibilities of Operators on Duty, the Site Fire: Brigade shall consist

cf at.least members,.three (3) of which should be

~ (number) (0,5-each) (shift position) ANSWER 6~26' ' (1. 0 0) ' - c.- 5' (0.5) 'b. Aos (0.5):. ' REFERENCE .Tcchnical-Specifications, p. 6-2. OP-100-001,.p. 21-A 4.2 194001K116 194001K116 ..(KA's) -COMMENT / RECOMMENDATION 6.26 Change Answer (b~.) to b. NAos (0.5) NOTE:. Typographical. error REFERENCB: .N/A 4 u.--_

/ -QUESTION- .6.30 (2.00) The plcnt 10 st 10% p:wcr during a plcnt'etartup following c rofueling Ecutage. OP-10-001, section 8.5, Power Increase to 100%, states " Select the. ' Loading Curve or the Turbg the more restrictive of either the TurbineThe following data is giv caximum loading rate usin .no Startup Curve." ' Initial HP turbine first stage temperature was 100 degrees F. Current HP turbine first stacJe temperature is 400 degrees F. . Initial turbine steam admission occurred at 0600. . Current time is 1000. A2sume turbine fatigue limit is 10000 cycles. .U0ing the attached curves and the above data (as required), determine the ' EARLIEST time permitted for turbine load to reach 100% according to the: c. Turbine Loading Curves (1.0) b. Turbine Startup Curve (1.0) ANSWER 6.30 (2.00) c. 1150 (+/- 15 minutes) (1.0) b. 1220 (+/- 20 minutes) (1.0) REFERENCE OP-10-001, p. 73 OP-05-007, p. 30, 31 3.1 194001A108 194001A108 ..(KA's) COMMENT / RECOMMENDATION 6.30 Accept elapsed time as alternate response of clock time for answers.

REFERENCE:

OP-10-001 Pg. 69 ,OP-05-007 Pg. 30 and 31

f U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: WaterFord 3 REACTOR TYPE: PWR-CE DATE ADMINISTERED: 89/05/15 INSTRUCTIONS TO CANDIDATE: Uco separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each quastion are indicated in parentheses after the question. The passing grade requires at least 70% in each catecJory and a final grade of at -lenst 80%. Examination papers will be picked up six (6) hours after th2 examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 24.50 25.13 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 30.50 31.28 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) 42.50 43.59 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%) 97.50 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature

l i NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 'During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application end could result in more severe penalties. ] 2. Rsstroom trips are to be limited and only one candidate at a time may j leave. You must avoid all contacts with anyone outside the examination. { room to avoid even-the appearance or possibility of cheating. 3. Uue. black ink or dark pencil only to facilitate legible reproductions. 4.. Print your name in the blank provided on the cover sheet of the examination.

5.. Fill in the date on the cover sheet of the examination (if necessary).

6. Une only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each ocction of the answer sheet. 8.- Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. S3parate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The. point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions uned to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. 16, If parts of the exainination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed. i +

18. When you complete'your examination, you shall:

L. Assemble.your examination as follows: (1). Exam questions'en top. (2) Exam aids - figures, tables, etc. ~ (3) Answer pages including figures which are part of the answer. b. . Turn lin your copy of the examination and all pages used to answer the examination questions. Turn in all scrap paper and the balance of the paper that you did c. not use for answering the questions, d... Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examine. tion is still in progress, your license may be denied or revoked.

EQUATION SHEET f = ma v = s/t Cvcle efficiency = (Net work out)/(Energy in)- 2 w = mg s = V,t + 1/2 at 2 E = mc KE = 1/2 mv .a = (Vf - V,)/t A = AN - A=Aeg PE = ogn V7 = V, + at w = e/t 1 = sn2/t1/2 = 0.693/t1/2' 2 1/2*" "- 1M W = v 3P. nD A= [(t1/2)

• II ))

4 b t2 = 931 em m=V Ao -Ix l av I=IeO t. 0 = mCpat 1 6 = UA A T I = I,e "' I = I,10-*I M pwr = w ah f TVL = 1.3/u sbr (t) P = P 10 HYL = -0.693/u p=pe/I t o SUR = 26.06/T SCR = S/(1 - K,ff) CR = s/(1 - x,ffx) l x ~ CR (1 - K,ffj) = CR (I ~ Eeff2) ?UR = 26s/t* + (a - s)T j 2 T = (t*/o) + [(s - sy Io] M = 1/(1 - K,ff) = CR /CR, j T = 1/(o - 8) M = (1 - K,ff,)/(1 'K,ffj) T = (a - a)/(Io) SDM = 2, - K,ff)/K,ff ~ l a = (K,fe )/K,ff = AK,ff/K,ff 1* = 10 seconds I = 0.1 seconds ~I e = [(t*/(T K,ff)] + [a,ff (1 + IT)] / Ijj=1d d l 2,2 2 P = (reV)/(3 x 1010) Id gd j 22 2 I = eN R/hr'= (0.5 CE)/d (meters) R/hr = 6 CE/d2 (feet) l Water Parameters Miscellaneous Conversions I gal. = 8.345 lem. 1 curie = 3.7 x 1010dps 1 ga]. = 3.78 liters i kg = 2.21 lbm 1 ft4 = 7.48 gal. I hp = 2.54 x 103 Stu/hr Density = 62.4 lbm/ft3 1 mw = 3.41 x 106 5tu/hr Density = 1 gm/cm3 lin = 2.54 cm Heat of vaporization = 970 Stu/lom 'F = 9/5'C + 32 Heat of fusion = laa Stu/lem 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in. 2

4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 4 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) QUESTION 4.01 (1.00) MULTIPLE CHOICE (Select the correct answer) Prior to reaching criticality during a reactor startup, with the neutron (cps, a reactivity count rate initially stable at 100 counts per secondcauses the count rate to incr) ease and then cddition-(by CEA withdrawal) ottbilize at 200 cps. The CEAs are then withdrawn again, causing count rato to increase and then stabilize again at 400 cps. Nhich ONE of the following statements is CORRECT? a. The first reactivity addition was larger. o. The second reactivity addition was larger. c. The two reactivity additions were equal. d. The stabilization times are nonded to determine the relationship of the 1 reactivity additions. l QUESTION 4.02 (1.00) J MULTIPLE CHOICE (Select the correct answer) In cddition to the immediate/ direct effect of CEA positioning on Axial Shr:pe Index (ASI), CEA positioning / motion can also have a delayed / indirect j offcct on ASI because of: ( l c. Xenon oscillations b. Samarium redistribution ] c. Moderator displacement l d. Fuel pellet swelling (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) m_

s L4.

REACTOR ~ PRINCIPLES'(7%) THERMODYNAMICS Page. S' (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)

QUESTION 4.03 (1. 0 0 ).

MULTITLE' CHOICE (Select the correct answer) scume the reactor is operating at 100 percent power when an inadvertent rG2ctor trip occurs. If the reactor power decrease rate has stabilized (i.o., power decrease rate'is constant)' when power reaches l'E -2 percent .csvaral minutes after'the-trip, how many ADDITIONAL minutes will be 'rcquired for power to decrease to 1 E -4. percent?- 'a. 2 b.- 4 c. '6 d. '8: -QUESTION 4'.04 (2.00) Accume the reactor is subcritical by 2.5 percent delta-K/K and the neutron-csunt rate is stable at 135 cps. After some CEA withdrawal, count rate etcbilizes at 405 cps. How much positive reactivity has been added? STATE ASSUMPTIONS / EQUATIONS USED and SHOW ALL WORK. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

g____m --- i 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 6 4 f (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM 1 f QUESTION 4.05 (1.00) MULTIPLE CHOICE (Select the correct answer) Which one of the following describes the change in the absolute magnitude of the inverse boron worth (IBW) as RCS average temperature is INCREASED? c. IBW becomes LARGER because a greater concentration of boron is needed to keep the same total boron atoms in the core. b. IBW becomes SMALLER because more boron atoms are expelled from the core for an equal increase in moderator temperature. c. IBW becomes LARGER because boron is a 1/V absorber whose cross-section becomes rapidly smaller as moderator temperature is increased. d. IBW becomes SMALLER because less boron must be added to obtain an equal increase in boron concentration. QUESTION 4.06 (1.00) MULTIPLE CHOICE (Select the correct answer) AftOr being at 40% for several days, plant power is ramped to 80%, where racetor power, RCS boron, and Tavg are stabilized. If plant power and CEA position are then maintained constant, the operator will have to change RCS bor:n concentration to maintain Tavg matched with Tref. Which one of the fcllowing describes the RCS boron change required over the next one hour cnd the reason for this change? c. Dilute, because Xenon production from direct fission yield will temporarily exceed Xenon removal. b. Borate, because Xenon removal bf decay will temporarily exceed Xenon production. Dilute, because Xenon production from Iodine decay will temporarily c. exceed Xenon removal. 1 d. Borate, because Xenon removal by neutron absorption will temporarily exceed Xenon production. l (***** CATEGORY 4 CONTINUED OF NEXT PAGE *****) L_____

l s 4 t l 4. -REACTOR,'RINCIPLES (7%) THERMODYN'AMICS Page. 7 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 1 i QUESTION 4.07 (1.00) MULTIPLE CHOICE (Select the correct answer) Which.one of the following plant parameter changes will INCREASE the chutdown margin for a reactor that was shut down from high power operations-cbout 12 hours ago? Consider each separately. a.: RCS boron concentration is increased by 100 ppm. 'b. A.sh'utdown group CEA is fully withdrawn for a test. c. Xenon' concentration changes over the next 12 hours. d. The RCS is cooled down to 300 degrees F after-the shutdown. - QUESTION 4.08 (1.00) MULTIPLE CHOIL1 (Select the correct answer) With'the plant operating at power, which one of the following parameters rust DECREASE to cause the departure from nucleate boiling ratio (DNBR) to DECREASE (i.e., change from 2.2 to 2.1)? a. Nuclear power b. Reactor coolant flow

c.. Average. coolant temperature

.d.- Core delta-T (assume a constant T-cold) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) bo

4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page -3 (7%) AND COMPONENTS (10%) (FUNDAMENTALS' EXAM) QUESTION 4.09 (1.00) MULTIPLE CHOICE (Select the correct anse r) =After 10 years of reactor operation, th maximum allowable stress limit for tha reactor vessel inner wall is more restrictive than the ' stress limit for , tha rcactor vessel outer wall because of which one of the following? o. The inner wall has a smaller surface area than the outer wall. 'd b. The. inner-wall experiences more tensile stress than the outer wall. c. The inner wall experiences more neutron radiation'than the outer wall. d. The inner wall experiences a higher temperature than the outer wall. QUESTION 4.10 (1.00) MULTIPLE CHOICE (Select the correct answer) .Tha reactor is producing 100 percent rated thermal power with core delta-T st 60 degrees F and an RCS mass flow rate of 100 percent when a station ~bltekout occurs. After natural circulation stabilizes, decay heat g:n0 ration is equivalent to 3 percent rated power and core delta-T is 30 d:grees F. Natural circulation mass flow rate is:. o 0. 3% l b. 4.5% c. 6%- d. 9% I (***** CATEGORY 4 COhTINUED ON NEXT PAGE *****) 1

777c-- nt-r 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 9-y :(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) s j. 1 / QUESTION 4.11 - (1. 0 0). ~ MULTIPLE' CHOICE-(Select'the correct answer) ci Tha. reactor isL in hot standby producing negligible decay heat with two.: rasctor coolant 1 pumps running' .An-RCS cooldown and depressurization is to-b3 conducted while maintainin a 100 degree F subcooling margin in the RCS.- > "In order:to maintain the requ red subcooling, when RCS pressure reaches 11500. psia-steam generator pressure should be: Vek L373 psia ~ b. 435 psia c.; 556 psia ' d.. 658Lpsia QUESTION - 4.12 '- (1.00)

MULTIPLE CHOICE.(Select the correct answer)

JTho' plant'is in hot standby with the RCS pressure being maintained at 1000 psia by.a 100 percent quality steam bubble in the pressurizer. A proesurizer safety valve is leaking to the quench tank, where the pressure .ic being maintained at 5 psig. Whtch one of the following would be the .cxp;cted temperature in the-tailpipe downstream.of the safety valve? (Assume ambient heat losses'are negligible.) 0,-

260 dog F; b.

300-dog F c.

340.deg-F-d.- 1360 dog F (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) c_ -__1___________

l 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 10 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) QUESTION 4.13 (1.00) MULTIPLE CHOICE (Select the correct answer) Consider a single main feedwater pump running with the plant operating at 50 percent power and all condensate pumps / condensate booster pumps running. j Which of-the following parameter changes will INCREASE the available Nst Positive Suction Head (NPSH) for the main feedwater pump? c '. DECREASING the number of running condensate pumps by one b. INCREASING the feed pump feed flow rate c. DECRE?. SING the condensate temperature d. INCREASING the feed pump steam flow rate by 30 percent QUESTION 4.14 (1.50) A plant is originally operated at 100% power with RCS Tavg at 582 F, and a Cteam generator pressure of 900 psia. During a maintenance period, 4 parcent of the tubes in EACH steam generator are plugged. l ASSUME that RCS specific heat and mass flow rate through the SGs are { unchanged by the tube plugging (i.e., remain constant at the original 100% value). To maintain a steam pressure of 900 psia at 100% power with 96% of the SG tubes still available, Tavg must be changed to what new temperature? STATE ASSUMPTIONS / EQUATIONS USED and SHOW WORK. l ) ) { (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

Y ds 1 4. REACTOR PRINCIPLES (7%)~ THERMODYNAMICS Page 11- ~ l: (7%) AND COMPONENTS (10%)- (FUNDAMENTALS EXAM) p', . QUESTION. .4.15 ' (1. 00). ~ .k . MULTIPLE CHOICE'(Select the correct answer) ,If'en RCS cold leg resistance temperature detector.(RTD) develops an open circuitLin the sensing element, the associated temperature-indication Ewill:

12., : Indicate 1 higher than actual' temperature.

b. -Indicate lower than actual temperature. c.

Track actual' temperature, but with an offset.

-d. Fail as is. s ! QUESTION

4.16 (1.' 00)

MULTIPLE CHOICE (Select the correct answer) "If a rupture o: curs in a steam generator (SG). level detector reference leg,. .how will the associated SG level indication respond? -a. Indic' ate higher than' actual level. .b. Indichte lower than actual level.

c.. Indicate the same as actual level.

d. . Remain at the level existing prior to the rupture.

(*****

CATEGORY 4 CONTINUED ON NEXT PAGE *****) i p .i o

4 4. REACTOR PRINCIPLIS (7%) THERMODYNAMICS Page 12 ~ (7%) AND COMPONENTS-(10%) (FUNDAMENTALS EXAM) QUESTION 4.17 (1.00)- MULTIPLE CHOICE (Select the correct answer) A motor-operated valve (MOV) should NOT be manually opened and placed on its backseat (unless power to the_ motor operator has been lost) because of which one of the following?- .a. .The operator may not know how many turns of the handwheel are required to open the valv~s fully. Eb. Electrical power to the motor operator may be suddenly returned, causing possible operator injury. Manualoperation[increasesthelikelihoodofsubsequentleakagepast-c. the valve seat. d. The motor operator.may be unable to close the valve during subsequent-electrical operation. QUESTION 4.18 (1.00) MULTIPLE CHOICE (Select the correct answer) If'a fresh, unsaturated CVCS mixed bed demineralized resin is put in ccrvice without prior saturation treatment,-which one of the following d: cribes the expected response of RCS chemistry? 0. pH will INCREASE and borca concentration will DECREASE. b. -pH will' INCREASE and boron concentration will INCREASE. c. pH will DraREASE and boron concentration will DECREASE. d. pH will DECREASE and boron concentration will INCREASE. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) lE_ _

1 l-4; -REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 13 ^ (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) .c L QUESTION 4.19 (1.00) MULTIPLE CHOICE (Select the correct answer) If.the motor current for a running centrifugal pump suddenly-increases to c a value seteral times greater than running current and remains there until tha supply circuit breaker trips, which one of the follcwing malfunctions Dic' indicated? a. A, shut discharge' valve .b. A shut suction valve-

c. - A seized pump shaft-

.'. JA' sheared pump shaft d QUESTIONL 4.20 (1.00) I MULTIPLE CHOICE -(Select the correct answer) Which set of parameters describes RUNOUT conditior.s for a motor-driven- 'Emsrgency Feedwater pump? o. High discharge pressure, high flow, high motor current b. High discharge pressure, low flow, low motor current c.- Low discharge pressure, high flow, high motor current

d. -Low discharge pressure, low flow, low motor current-1

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) i 1

r >i w-- w. .j p.5 4. ' REACTOR' PRINCIPLES-(7%) THERMODYNAMICS Page 14 -(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) .; QUESTION '.4.21 (1.00) MU'LTIPLE CHOICE (Select the correct answer) r Whsn closint the first generator output breaker to connect the main ganarator ts the grid, the generator output frequency should be: a. Slightly lower than grid frequency. b.':Slightly higher than grid frequency. c '... Matched with gridffrequency. ' d. ; --Adjusted to - exactly 60 Hz. ~ -QUESTION-4.22 (1.00)- MULTIPLE CHOICE (Select.the correct answer) 'A motor-driven Emergency Feedwater pump is operating at low-flow conditione b:cause the downstream flow control valves are shut. Assume condensate ctorage pool level remains constant. If the flow control valves are opened, pump discharge pressure will and pump motor amps wi u O. Decrease; Increase b. Decrease;. Decrease .c. Increase; Increase d.- Increase; Decrease (*****. CATEGORY 4 CONTINUED ON NEXT PAGE *****) .j

E. j i, l l. l 1 l I 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 15-J74) AND COMPONENTS (10%) (FUNDAMENTALS' EXAM) a! . QUESTION. 4.23 (1.00) MULTIPLE CHOICE (Select the correct answer) A special.RCS chemistry analysis requires Tavg to'be REDUCED by 8 degrees F-Lwithout changing CEA position or plant. power (i.e., by changing RCS boron ' concentration ONLY). (Assume turbine power is kept constant.) Given the following initial parameters, what FINAL RCS boron concentration. 10' required to REDUCE Tavg by 8 degrees F? Initial RCS boren concentration = 550 ppm Total power coefficient = 0.020 percent delta-K/K/ percent power

Moderator temperature coefficient = - 0.015 percent. delta-K/K/ degree F Inverse boron woicth = - 100 ppm / percent delta-K/K 0L 538. ppm b.

544 ppm c. 556 ppm d. 562 ppm (***** END OF CATEGORY 4 *****) l -_r_-_._-__.--__-.-_._-

l l 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 16 (33%) QUESTIO!J 5.01 (2.50) FILL IN THE BLANK Tha following conditions re @ ire emergency boration in accordance with OP-901-013, Emergency Boration. (0.5 each blank) The plant is operating at 50% power and shutdown margin is determined Q. to be less than b. DELETED. An uncontrolled cooldown is in ' progress that is caused by excessive c. or excessive d. The reactor is being refueled and Keff increases to greater than or boron concentration decreases to less than ppm. QUESTION 5.02 (3.00) a. State the basis for each of the following actions performed prior to exiting the control room when implementing OP-901-004, Evacuation of Control Room and Subsequent Plant Shutdown. (0.75 each) 1. Verify Spray Valve Selector switch in the BOTH position. 2. Reset the Moisture Separator Reheater controls. b. Why does OP-901-004 (case II with fire) require the availability of each of the following? (0.75 each) 1. Diesel Generator B 2. CCW pump B (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

, %g, y. .1-5.' ' EMERGENCY:AND' ABNORMAL PLANT EVOLUTIONS' Page.17

(33%)

QUESTION 5.03 - (1. 00); ' MULTIPLE CHOICE.(Select the~ correct answer.)- !Thn plant is'in Mode 5 with shutdown cooling Train B in service on RCS loop 2cwhen anuelectrical fault results in a loss of instrument bus'3MB-S. The 'CRS~should immediately direct: La. Starting LPSI pump A. (b.. Tripping LPSI pump B. 0 c.; Closing shutdown cooling' suction isolation valve,'SI-401B. ~ iis. Closing shutdown cooling. loop discharge isolation valves, SI-138B and' SI-139B. L UESTION L5.04 (2.00) Q During a LOCA, OP-902-002, LOCA Recovery Procedure, directs the operator to., b! gin RCS' hot leg injection between two-and four hours after the' break-

cccurred.

10. What is the basis for the two-hour minimum delay? (1.0)- 'b.- What is-the basis for the four-hour maximum delay? (1. 0 ). QUESTION '5.05- '( 2. 5 0 ) ~For each of the following'immediate actions from OP-902-000, Emergency Entry Procedure, list the substeps required to perform that action. c. Check for. Reactor Trip. (0.75)

b. -

Check for Turbine Trip. (1.0) u> -c. Check for Generator. Trip. (0.75) (*****. CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5 -EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS Page 18 -(33%) QUESTION 5.06 (1.00) MULTIPLE CHOICE (Select the-correct answer.) A. rupture in the CCW nonessential loop has occurred and cannot be repaired. ~Iri 'cccordance with OP-901-010, RCP Malfunction,.the operator must trip the rc:ctor and al1~RCPs within: t' s. 3 seconds

b. -

30 seconds c. 3 minutes d.- 30 minutes -QUESTION 5.07 ,(1.50) Th2, plant is operating at 80%' power when a station blackout occurs. In .cccordance with OP-902-005, Degraded Electrical Distribution Recovery ~ Precedure, list SIX (6) parameters that are monitored to determine if cd;quate natural circulation exists. Setpoints are NOT required. (0.25 each) QUESTION 5.08 ~ DELETED. QUESTION 5.09 (1.50) Stcte the THREE (3) general conditions that require implementation of OP-902-008, Safety Function Recovery Procedure. (0.50 each) I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 19 (33%)_ ' QUESTION 5.10 (1.00) Tha plant is operating at steady state 100% power when a loss of gland c:aling steam results in lowering condenser vacuum. Number the following events in their order of occurrence if condenser vzcuum continues to decrease. Assume NO operator actions. c. Main turbine trips b. Standby vacuum pump starts c, SBCS valves interlocked closed d. Vacuum pumps shift to " Hogging Mode" o. Main feedwater pump turbines trip QUESTION 5.11 (1.00) MULTIPLE CHOICE (Select the correct answer.) Tha plant is operating steady state at 100% power with CEDMCS in Manual S:quential when a fully withdrawn regulating group CEA drops into the core. No operator action is taken and the reactor does NOT trip. After the plant Ct bilizes, with the CEA fully inserted, how will shutdown margin have ch::nged since before the CEA dropped? c. Increased, because the Tavg decrease results in less positive reactivity available upon a reactor trip. b. Decreased, because fewer CEAs are available for insertion resulting in less negative reactivity availab1'e upon a reactor trip. Remained the same, because the change in available negative reactivity c. has been exactly offset by the change in available positive reactivity upon a reactor. trip. d. Cannot be determined, because additional information is required to determine whether the available negative reactivity or the available positive reactivity has changed by the greatest amount. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

l' i 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 (33%) QUESTION 5.12 (1.50) A major steamline break has occurred requiring implementation of OP-902-004, Excess Steam Demand Recovery Procedure. In accordance with OP-902-004: 0.- What crf.teria requires stopping only TWO (2) RCPs (RCPs 1A and 2A) with 87as actuated? Setpoints are not required. (0.50) b.- What are the TWO (2) criteria that, if either is present, require stopping ALL RCPs? Setpoints are not required. (0.50 each) QUESTION. 5.13 (0.75) Tho plant is operating steady state at 80% power. RCS gross ectivity has. be3n trending higher as indicated by RCS sample analyses. The CRS implements OP-901-021, High Activity in the RCS. c. Why does OP-901-021 direct the operator to start all available chtrging pumps? (0.75) .b. DELETED. QUESTION 5.14 (2.25) The plant is operating at steady state 100% power when a header leak causes o custained decreasing instrument air system pressure. The CRS implements OP-901-038,- Instrument Air Malfunction. Assuming no operator action and the reactor does NOT trip, what are .o. 1N40 (2) reasons why feedwater flow to each S/G will-decrease?(0.5 each) b.- OP 901-038 directs the operator to control S/G levels by manually adjusting ma'n feed' pump turbine speed. Why can't feedwater flow be automatically controlled by the Steam Generator Level Control System? (0.75) c. FILL IN THE BLANK The operator is required to trip the reactor when instrument air header pressure first reaches psig. (0.5) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l I

5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21 (33%) QUESTION 5.15 (1.00) MULTIPLE CHOICE (Select the correct answer.) i Which ONE of the following indications is LEAST helpful in confirming which ctcam generator has experienced a 100 gpm tube leak in accordance with OP-902-007, SGTR Recovery Procedure? a. Radiation level on main steamline radiation monitors b. Radiation level on S/G blowdown radiation monitor j i c. Radiation level on condenser vacuum pump exhaust radiation monitor { d. Abnormal S/G level for existing feedwater flow and steam flow QUESTION 5.16 (1.00) MULTIPLE CHOICE (Select the correct answer.) -While performing a manual off-site dose assessment in accordance with the EPIPs, the CRS determines a dispersion factor (X/Q), which is a factor ] d;tormined by characteristics that is used to project 4 population exposure from a known radioisotope c. meteorological; release rate b. meteorological; concentration c. accident; release rate d. accident; concentration i 1 QUESTION 5.17 (1.60) Th3 plant is operating steady state at 100% power when a valid automatic rc:ctor trip signal is actuated that does NOT result in a reactor trip. Lict the THREE (3) contingency actions that must be performed in accordance with OP-902-000, Emergency Entry Procedure. (Assume that each action fails until all contingency actions have been completed.) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) L_-

5. ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 22 (33%) 4 QUESTION-5.18 -(1.00) MULTIPLE CHOICE (Select the correct answer.) The plant is operating steady steady at 100% power when a' controller ' failure causes. pressurizer spray valve RC-301A to fully cpen. The eparators take the appropriate actions in accordance with OP-901-002, RCS Prcosure Control' Malfunction, which includes stopping RCP: O. lA. b.- 1B -1 c. .2A~ d.' 2B QUESTION- '5.19 (1.00) 'NULTIPLE CHOICE (Select the correct answer.) Th31 plant is operating steady state at 70% power with pressurizer level control in Manual due to a controller malfunction.. Tavg is being 'Cointained on the program. From the attached graph from OP-901-001, Pressurizer Level control Malfunction, pressurizer level should be naintained at:

0..

44.5% b. 46.5% c. 48.5% l d. 50.5% (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l 1 l L

r PRESSURIZER LEVEL SETPOINT VS. T-AVERAGE 60 EEN 6 m g, ' ~ ~ ~~ - - = = = - - - , _ _7 33 l ~ \\ 30 ] l / LEVEL- -( - j 40 F e f ) s j 33 .I 30 ~ 4 - SSO $60 $70 sa0 sez . I T - AVERAGE (' u OP.-901-ool Revision 3.1 (1 of 1) { ( [_. a

s. L H l 5. L MERGENCY AND ABNORMAL PLANT ~ EVOLUTIONS Page 23 E (33%) . QUESTION 5.20 (1.50) FILL IN THE BLANK' r 'O. : 'In'accordance with Technical Specifications, during.CEA replacement -(no fuel. movement), at least-feet of water shall be maintained over the top of th,e .(0.5 each)

b. -

.The above requirement ensuresLthat in'the event'of'a ruptured, irradiated fuel assembly, at least 99% of the released radioisotope,. , wil1~be removed. -(0.5)

QUESTION 5.21

'(1. 00) 1 MULTIPLE CHOICE (Select the correct answer) Th2 plant is operating steady state at.100% power when it is determined Lthst-loop 1 steam generator has a 0.8 gpm tube leak. ,In accordance with Technical Specifications, this is: a. Controlled leakage b. Pressure boundary leakage c. . Identified leakage d. Unidentified leakage QUESTION 5.22 (1.00) State the TWO-(2) applicable Technical Specification LCO limits for S/G -tuba' leakage. (0.5.each) (***** END OF CATEGORY 5 *****) --_-_-__.m._____m ___m, _., _ _ _,,, _ _ _ _ _ _

n -6. PIANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 24' j RESPONSIBILITIES (13%) _ QUESTION 6.01 (1.50) A CEAC fails and will not-reset. How do the CPCs determine penalty factors with only one operable CEAC? " QUESTION 6.02 (1.00) During a routine-surveillance test of the B MDEFW pump, excessive shaft lo Kage was noted. In accordance with OP-100-001, Duties.and Re possibilities of Operators on Duty, what administrative requirement Curt be satisfied regarding JL MDEFW prior to initiating maintenance on B MDAFW pump? s .-QUESTION 6.03 (1.00) NULTIPLE CHOICE,(Select the correct answer. ) S31cct the minimum.DNBR required by Technical Specifications.to ensure cd:quate margin to DNB. c. 1.16 b. 1.26 l c. 1.36 1 d. 1.46 l 1. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

t 6. PLANT _ SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 25 j RESPONSIBILITIES (13%) i QUESTION 6.04 (1.00) MULTIPLE CHOICE (Select the correct answer.) Which one of the following sets of RCP seal pressures indicates total FAILURE of the MIDDLE SEAL? Assume RCS pressure is 2250 psia. Middle Seal Upper Seal Vapor Seal Pressure (psia) Pressure (psia) Pressure (psia) l c. 2250 1125 50 b. 2250 750 50 c. 1500 1500 50 d. 1500 750 750 QUESTION 6.05 (2.00) (MATCHING) M;tch each excore NIS detector in column A to the proper channels in which it is used in column B. (Items in column B may be used more than once.) (0.5 each) Column A Column B c. Fission chamber 1. Startup channel b. Uncompensated ion chamber 2. Control channel c. Compensated ion chamber 3. Safety channel d. Proportional counter (BF-3) 4. None/not used (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 26 RESPONSIBILITIES (13%) i QUESTION 6.06 (2.00) Th2 plant is operating at steady state 100% power with Channel X selected for input to the pressurizer LEVEL controller and Channel X + Y selected for input to the pressurizer heaters controller (for heater cutout). c. What THREE (3) different automatic equipment / component actuations will occur if Channel X fails low? Do not include alarms / annunciators. (0.5 each) b. What automatic equipment / component actuation will occur if ONLY Channel Y fails low? Do not include alarms / annunciators. (0.5) QUESTION 6.07 (1.,50 ) What THREE (3) fuel handling interlock conditions will automatically stop tha Refueling Machine Traveling Bridge with fuel movement in progress? A22ume no operator action. (0.5 each) 1 l l \\ (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

I l 1 6 -- PLANT SYST}:MS (30%) AND PLANT-WIDE GENERIC Page 27 RESPONSIBILITIES (13%) QUESTION 6.06 (2.50) (MATCHING) M2tch each CEDMCS control mode in column A to the phrase that describes it in column B. (0.5 each) Colunn A Lolumn B O. Auto Sequential 1. Allows novement of any 1 CEA group in high speed only, b. Manual Group 2. Allows movement of any 1 CEA group in high or low speed. c. Manual Individual 3. Allows movement of up to 2 regulating CEA groups at high speed only. d. Manual Sequential 4. Allows movement of up to 2 regulating CEA groups at high or low speed. o. Off 5. Allows movement of any 1 CEA in high speed only. 6. Allows movement of any 1 CEA in high or low speed. 7. Deenergizes all CEDMs resulting in rapid insertion of all CEAs, 8. Prohibits CEA motion except ot. reactor trip. QUESTION 6.09 (1.00) Upon receipt of a SIAS, what TWO (2) different " nonessential" heat loads continue to be cooled from the "A" CCW essential header? (0.5 each) QUESTION 6.10 (1.50) If the Computer Room Halon Fire Suppression System fails to automatically rolcase when required, how is it MANUALLY released? Include both LOCAL and REMOTE operation. (0.75 each) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I l !L__

E' J 1 'l i l 1 l '6. PLANT ~ SYSTEMS (30%) AND PLANT-WIDE GENERIC .Page 28 ) RESPONSIBILITIES (13%) QUESTION 6.11 (2.00) c. What is the basis for the MINIMUM flowrate permitted by the letdown throttle valves when operating in automatic? (0.5) b. What is the basis for the MAXIMUM flowrate permitted by the letdown throttle valves when operating in automatic? (0.5) What.is the purpose of the lead / lag unit located electrically.between c. the pressurizer level controller and the letdown throttle valve controller? (1.0) QUESTION 6.12 (1.50) On a RAS, what are the SIX (6) valves that must be closed by a' control room operator to isolate potential leakage paths from the SIS sump to the RWSP?- (valve numbers are acceptable but not required.) (0.25 each) QUESTION '6.13 (2.00) LA leak'in the Instrument Air System causes instrument air header pressure to decrease. List the equipment / component actuations that will occur in th3 Instrument. Air System at approximately each of the following instrument Gir header pressures.' (0.5 each) o. 112 psig b. 105 psig c. 100 psig d. 95 psig (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6 - PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC

'Page 29 RESPONSIBILITIES-(13%) -QUESTION 6.14 (1.00) MULTIPLE CHOICE'(Select the correct answer.) During an automatic source check of a radiation' monitor on RM-11, an alarm 10 received. If the source check had failed, an additional indication of tha failure will be: ~ c.

a. flashing.C/S pushbutton.

~b. a backlit red C/S pushbutton. c. a backlit amber C/S pushbutton. d. an extinguished C/S pushbutton. QUESTION. 6.15 .(1.50) Lict the buses that supply power to the motors of the following EFW components / equipment. (0.5 each) a. Turbine-driven EFW pump stcam line shutoff valve (MS-401A) b. Motor-driven EFW pump A c. Motor-driven EFW pump B . QUESTION 6.16 (1.00) MULTIPLE CHOICE (Select the correct answer.) In the Steam Bypass Control System (SBCS), the main channel steam header precsure setpoint is determined by a. select circuit and is compar-d.to a steam header pressure signal that is determined by a select circuit. ^ c. High, high b. Low, high c. High, low d.- Low, low (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l 1 i ) L _ -_ __ _ _ - _ _ _ _ _ _ _ _ _ _

w. + b $6 PLANT' SYSTEMS'(30%)'AND PLANT-WIDE GENERIC Page 30; . RESPONSIBILITIES - (13%) ' 'QUESTIONj .6.17-(1.00), . MULTIPLE: CHOICE (Select-the correct _ answer.) ltri the. Steam Bypass Control System (SBCS), the Automatic Motion Inhibit

(AMI)'permissivelsignal is developed using input from:-

c. Turbine first-stage pressure b.- Main steam flow c.; Main steam header pressure li.. Pressurizer pressure l QUESTION' 6.18' (1.00) MULTIPLE' CHOICE (Select the correct answer.) 'Tha Core Protection = Calculators (CPCs) correct the inputs from the.excore NIS detectors such that the inputs ~are proportional only to the flux inardiately adjacent to.the detectors. This correction is. called-the: ' c. - Shape annealing correction b.- CEA' shadowing' correction Ec. . Temperature' shadowing correction d. Flux, enhancement correction l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 31 j RESPONSIBILITIES (13%) { QUESTION 6.19' (1.50) '(MATCHING) Match the reactor. trip signals in column A to the. correct function in column B. (0.50 each) Column'A Column B c. High Linear Power 1. Prevent DNBR from exceeding design limits during anticipated b._ High' Logarithmic Power operational occurrences. c. High Local Power Density 2. Prevent linear heat rate from-exceeding limits during anticipated operational occurrences. s 3. Protect core from rapid reactivity-excursions (ejected CEA). 4. Protect integrity of fuel clad and RCS boundary in event of unplanned criticality. QUESTION 6.20 (1.00) MULTIPLE CHOICE (Select the correct answer.) Stoca generator low pressure trip channel B'has bee:i bypassed for maintenance. If the steam generator low pressure trip channel C Trip Chtnnel Bypass Switch is depressed, then: c. Both trip channels B and C will be bypassed. b. Only trip channel B will be bypassed. c. Only trip channel C will be bypassed. d. -No trip channels will be bypassed. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) c__- i

p b '6- -PLANT = SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 32 . RESPONSIBILITIES-(13%) QUESTION 6.21 (1.00) N MULTIPLE CHOICE (Select the correct answer.) i WhEn selecting a self-reading dosimeter (SRD), the maximum allowable . pro-existing reading is: c.. 25 mrem' ) b.: 50 mrem c. L75 mrem- -d. 100 mrem QUESTION 6.22 (1.00) MULTIPLE' CHOICE-(Select the correct answer.) Tha. maximum extended quarterly whole body exposure allowed by 10 CFR 20 for s 40-year old shift Supervisor is;

c..

1.25 rem b. 3.0 rem c. 5.0 rem d.- 8.75 rem i QUESTION 6.23 (1.00) Und r what'TWO (2) conditions may an unlicensed operator operate the C ntrol Element Drive Mechanism Control System (CEDMCS) during a reactor -ctartup in accordance with OP-100-001, Duties and Responsibilities of ( Operators on Duty? (0.5 each) 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *=**e) ) 1

T I~ 1: 6.- PLANT SYSTEMS (30%) AND PLANT-WIDE GENERJS Page 33 RESPONSIBILITIES (13%) QUESTION 6.24 (1.00) MULTIPLE" CHOICE. (Select the correct answer. ) During a plant tour, the Shift Supervisor must not engage in any activities that would prevent him/her from contacting the control room within'a maximum of minutes. 0.' 5 -b. 10 c.L 15 d. 20 s QUESTION 6.25 (1.00) MULTIPLE CHOICE (Select the correct answer.) During independent verification of a valve lineup, a locked throttle valve chtuld be verified by: c, . Unlocking the valve and closing the valve while counting the number of turns. The valve should then be reopened the same number of turns and locked. b. Unlocking the valve and opening the valve while counting the number of ' turns. The valve should then be reclosed the same number of turns and locked. Observing the valve stem, position indication, or flow c. instrumentation. The valve locking device should not be removed.

d.

Attempting to open end close the valve to ensure movement is not possible. The valve locking device should not be removed. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1

6-PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 34 RESPONSIBILITIES (13%) 1 -QUESTION 6.26 (1.00) FILL IN THE BLANKS In cccordance with Technical Specifications and OP-100-001, Duties and R possibilities of Operatort, on Duty. the Site Fire Brigade shall consist of ct least _ members, three (3) of which should be. (number) (0.5 each) (shift position) QUESTION 6.27 (1.00) Number the following in the proper order to be accomplished for isolating a HPSI pump for impeller inspection in accordance with UNT-5-003, Clearance R: quests, Approval, and Release. 2. Tag boundary valves closed b. Remove and tag breaker fuses c. Vent and drain the pump-d. Tag control switches in OFF o. Rack out circuit breaker QUESTION 6.28 (2.00) FILL IN THE BLANK Tha plant is operating at 50% steady state conditions. The Technical Specification limit for oxygen in the RCS is ppm. c. b. The Technical Specificati^n limit for Chloride in the RCS is ppm. The Technical Specification limit for Fluoride in the RCS is ppm. i c. d. The Technical Specification limit for Dose Equivalent Iodine-131 in the RCS is uci/gm. (0.5 each) (***** CATEGORY 6 CONTINUEO ON NEXT PAGE *****) i )

r___ h 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 35 RESPONSIBILITIES (13%) . QUESTION 6.29 (1.00) MULTIPLE CHOICE (Select the correct answer.) Shift turreover has just been completed except for the STA. The oncoming -j STA cannot report to work for several hours. The offgoing STA: May go home prior to being relieved 2 hours after receiving c. authorization from the onshift Shift Supervisor. b. May go home prior to being relieved after receiving authorization from the onshift Shift Supervisor because the STA position will be filled within 2 hours. c. Must remain on shift until relieved by a qualified STA because the 2-hour time limit for shift manning does not apply to this situation. d. Must remain on shift for at least 2 hours, and then he may go home after receiving authorization from the onshift Shift Supervisor. QUESTION 6.30 (2.00) Tha plant is at 10% power during a plant startup following a refueling ) cutige. OP-10-001, section 8.5, Power Increa'se to 100%, states "Selact the maximum loading rate using the more restrictive of either the Turbinc Londing curve or the Turbine Startup Curve." The following data is given: Initial HP turbine first stage temperature was 100 degrees F. Current HP turbine first stage temperature is 400 degrees F. Initial turbine steam admission occurred at 0600. Current time is 1000. Accume turbine fatigue limi? is 10000 cycles. Using the attached curves and the above data (as required), determine the EARLIEST time permitted for turbine load to reach 100% according to the: C. Turbine Loading Curves (1.0) b. Turbine Startup Curve (1.0) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) /

w x , y_ ; ?i: PLANT DATA BOOK . SECT 10tb3.2.5REV.c 7yg3yy i START UP RECOMMENDATIONS [U

FOR HP BB 296 NUCLEAR STEAM SYSTEM UNITS I-APPLY' INITIAL LCADo 5*'.

'lo % M=- to % d I f i ; y INCR'EA 3 LDAD I \\ l (Exatei.Est ' \\ 1 1 K E D a ~ .y 5% LOAD )\\ g m n W 5' 1p \\ j ACCELE L o 9 70SYNCSPC l - 3 _ A. '5__ _ _ JENAMPLE23 _1 3 L_..__ 0 ( 0 10 0 200 300' 400 500} OtGREES F INITIAL MP TUROINE FIRST* STAGE METAL TEMPERATURE EXAMPLE 1 (shown on Chart) Determine the time to roll from ti.rning par to reted speed. synchronies and load to 100% load with the HP turbes firststage metal temperstwe being 1000F prior to toiling.- . PROCE*)URE Enter the chart at 1000F initial HP turbine first stage metal temperature and project to the roJIing lire. The intersection indicates that the unit should accelerate to synchronous sosed at a uniform rete it I hour or lonpr. The acceleration rete is 1800 rpm /80 min = 30 rps/ min. Continue the prcjestion tp the 5% load line. Determing from the chart that 5% load should be held for e minimum of 57 mnvisa in order to heat soak the turbine rotor l before increasing load. To determine the time to increase had from 5% to 100%, project to the 100% toad line. The cumulative time from turning gear to 100% Iced is 4 hours 35 minutes. The time to incream load from 5% to 100% is 2 hours 38 minutes (4 hours 35 minutes I hour 57 minutes) usme a load changing rete of 95%/158 min = 0.8%/mn. EXAWPLE 2 (shown on Chert) Determine the time to roll from turning gear to rated seevd. synchronize and load to 50% 3 sad with the HP tur-bine firstisage metal temperature being 4000F prior to rolling. l PROCEDURE Enter et 400'F initial HP turbine fira stay metal temperature end project to the rolling line. The interaction indientes that the unit should be accelerated to synchronous speed within 10 minutes, synchronized.or. loaded initially to 20% (as indisted by entering the initialloed scele located abow the chart et the 400ef metal temper-I sture) to avoid cooling the estor. Continue projection of the line to the 50% Ioed line end determine the curcula-time time of 40 minutes from twning gear to 50% Iosd or 30 anutes (4010 min) from 20% to 50% load. The lead shenging rats is 30%/30 min = 1.0%/ min. [j d i CT 23814 8 t s m mm _ =

A6 o R LOAD CHANGING RECOMMENDATIONS l; FOR HP BB 296 NUCLEAR STEAM SYSTEM UNITS FIGURE 1 400 l - - i $ 200 7__ s /l7 5 140*F $ 200 E / 5 r_ _ g y l -l ~

• 10 0

/ i 'O O 13 40 60 80 10 0 PERCENT MATED LOAD = ~ FIGURE 2 s, 400 300 OF e / e >/s// / s J 200 / = v v en w 10 0 E Inao'r 1n 'O ,i 2 3 4 5 TlWE TO CHANGE LCAD-HOURS EXAMPLE (Shown on Charts) Determine the time required sad Isad changing rate to increase load from 25% to 100%. Auume a 10,000 cycle fatigue indes h being used. PROCEDURE Enter Figure 1 at 25% Iosd and 1C0% Icad and determine from curve the first stage temperature change from 0 to 25% load to be 1558F and from 0 to 100% Ioad to be 2958F. By subtracting the 0 25% temperature change from the 0100% chante, tb first stage temperature change that occurs in intracting Icac from 25% to 100% !s 2S58-1558 = 1408F. Enter Figure 2 with the 1408F first stage steam temperature change and project to the isletted 10,000 cycle fatigue indes curve. It is determined that load should be increa.H f.rsm 2I% to 100% load at a uniform ra:e ever 0.2 hour (12 minutes). The load changing rate is 75%/12 min. = iNm.n. / CT.23813.A

j].- lf.

r v {i1 ' .Y o I' 1y' i 6 '. -PLANT SYSTEMS (30%)' AND PLANT-WIDE GENERIC 'Page 36 RESPONSIBILITIES ( 13'E ) QUESTION 6.31 (1.00) ~Liot'the MINIMUM Protective Action Recommendations (PARS) for a General Emargency involving an'offsite radiological release. -QUESTION 6.32 (1.00) MULTIPLE CHOICE (Select the correct answer.) If.a General Emergency is declared at 0800, by what time (the absolute latast) must the local offsite government agencies be issued Protective Action Recommendations (PARS)? c. 0805 b.' 0815 c. 0830 d. 0900 (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) l

r L g 4 i s s n .,s ' 4 -- REACTOR PRINCIPLES'(7%) THERMODYNAMICS-Page - (7%) AND COMPONENTS (10%) - (FUNDAMENTALS EXAM) p,; e ANSWER / 4.01-( l'. 00 ) ...f... REFERENCE PLANT SPECIFIC REACTOR THEORY & OPERATIONAL ASPECTS.- (PSRTOA), FIG 2. 4-8 [ 3.8,-3.9 192008K105-192008K104-- 192008K305 192008K104 (KA's)' ANSWER 4~.02 (1.00)'

---

n ----

' REFERENCE L PSRTOA, pg 3.2 3.5, 3.4 192005K114 192006K106 -192005K114 192006K106 (KA's) r . ANSWER. 4.03 (1.00). ---c--- . REFERENCE' g PSRTOA, pg 2.3-15 j

3.1-192008K123 192008K123

..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) i 1.j s =- _...l___._'___________________, _[___,_

g. 7,, z-- [ p .I "41 REACTOR PRINCIPLES-(7%) THERMODYNAMICS 'Page 38 -(74) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) .] i i

ANSWER l

'4.04 (2. 0 0). '.Applidable equations: CR1 * (1-Keff1) = CR2 * (1-Keff2) (0.50) Rho = (Keff-1)/Keff (0.50) METHOD A By rearrangement, Keffl = 1/ (1-rhol) Since Rhol = .02500, Keff1; = 1/(1-[.035)) =.9756 (+/ .001) (0.25) C.d; siince' CR1/CR2' = (1-Keff2)//1-Keff1) .135/405 =.1/3 = (1-Keff2)/1.9756) Keff2 =.9918 (+/ .001) (0.25) y SUBMETHOD A1 Since Rho 2 = 1-1/Keff2 Rho 2 '~=.1-(1/.9918) n .0083 or -0.83% delta-K/K (+/-'.05%). .(0.25) R3cctivity added =.Rhc2 - Rhol R22ctivity added = .83 -(-2.50) e 1. 67% delta-K/K (+/ . 05%) - (0.25) SUBMETHOD A2

Since~ reactivity added.=. delta-rho = (Keff2-Keff1)/Keff2

• Keffl (0.25)
• .9756 =.0162/.9676 Re:ctivity added = (.9918

.9756/.9918 R20ctivity added =.0167 or 1.67% delta-K/K-(+/ .05%). . ( 0. 2 5.) METHOD B- . Combining the applicable equations, CR2 *. rho 2/(A-rho 2) = Cal * ' rhol/ (1-rhol) (0.50) 135

• rhol * (1-rho 2)

,er 405 *' rho 2 * (1-rhol) =

Since rhol =

.025, rho 2 = .0082 or -0.82% delta-K/K (+/ .05%) (0.25) R$0ctivity'added = Rho 2 - Rhol - Red:tivity added; = .82 -(-2. 50) = 1.68% delta-K/K (+/ .05%) (0.25) (Other'. correct methods may be accepted.) .(***** CATEGORY-4 CONTINUED ON NEXT PAGE *****) ) ?-

m..$

i '44 REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 39 -(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) Il 1 i-j 'IREFERENCE ~ PSRTOA pg 2.3-2,3

3. 8 ^

192008K104 192008K104 ..(KA's) W n.. }mic(ANSWER 4.05: (1.00) .;\\___.'a REFERENCE y PSRTOA pg 3.3-13 2.9 192004K110 ..(KA's) 192004K110 y ANSWER 4.06 (1.00) }lih----6---- -t Y RIlFERENCE PSRTOA', pg 3.2-8 '3.4 y192006K106' 192006K106- ..(KA's) ,, p' JANSWER 4.07 (1.00)

---

a----

REFERENCE. l?SRTOA, pg 4.'l-9,10 h 3.9 192002K114L 192002K114 ..(KA's) l . ANSWER 4.08-(1.00) ____ d ____ (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) [ q .. a

1 A 8 I I i: '4. - -- REACTOR PRINCIPLES - (7%) - THERMODYNAMICS ~ Page 40 ( 7 % ) AND COMPONENTS - (10 % ) (FUNDAMENTALS EXAM) .' REFERENCE W3SES LP L310-031-52 pg 7,8-3.6' 19300GK105 193008K105- ..(KA's) 0 ANSWER .4.09 (1.' 00) c - -- - ~' REFERENCE' W3SES LP ZMSC-703-00,'pg 6 3;0

193010K105 193010K105

..(KA's) ANSWER 4.10: (1.00) c. REFERENCE W3SES LP L110-704-01, pg 3 -4.2 193008K122 193008K122 ..(KA's) -ANSWER' -'4 11 (1.00) d. . REFERENCE CE Steam-Tables 3.4,:2.7, 3.8 193003K125 193001K101 193008K115 193QO3K125 193001K101 I --193008K115 ..(KA's) '; ANSWER 4.12 (1.00) . __ d ____ j 1 l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) 1: o a I __1_ _____1.__

t: 4s-REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 41 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) REFERENCE StOCm Tables 'TMI Accident Records 3.' 4 193003K125 193003K125 ..(KA's) j ANSWT,R ' 4.13 (1.00)

---

c ----

RJ;FERENCE W3SES LP L310-031-22, PG 11 3.3, 2.8 4 191004K106 19J004K115 191004K106 191004K115 ..(KA's) cANSWER. 4.14 (1.50) Applicable equation: Q = UA(Tavg - Tstm) (,0. 5 0) Since Q, U, and Tstm remain constant, Al o (Tavg1 - Tstm) = A2 * (Tavg2 - Tstm) Giv0n: A2 = 0.96

• Al From Steam Tables; Tstm = Tsat for 900 psia = 532 F (0.50)

A1. 0 (582 - 532) = 0.96Al * (Tavg2 - 532) (delta-T2 = 52.1 F) Tcvg2 = 584.1 F (583.6 to 584.6 F acceptable) (0.50) l REFERENCE W3SES LP L110-704-01 pg 5 2.9 191006K113 191006K113 ..(KA's) 1 f ~ ANSWER 4.15 (1.00) { l ... n (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) { I i i 1 t, dis _

2 Y f ' &f e t' J ? i c. q Los REACTOR" PRINCIPLES (7%) THERMODYNAMICS _ . Page.42 (74).AND' COMPONENTS (10%) (FUNDAMENTALS EXAM) i r-1 REFERENCES ~RTD Circuit' Analysis E2,9-(KA's) j 191002K114: '191002K114' ' AESWER. 4.16 (1.00) --- a ---. i ' REFERENCE.' ~W3SES LP ZIC-705-00, pg'5 j '3.0 .191002K109' (KA's) i 191002K109.. i l -: ANSWER 4.17 . (1. 00). ---d--- j 1 i .REPERENCE W2.tT.S 1P ZLTV-2'00'-00 pg 25 l i

3.7 191001K106 (KA's) j 391001K106 i

ANSWL'R. 4.36 (1.00)

... - at REFERENCF,

!3 CVCS SD pg 1.4,15. 3.; 1. !:191007K103 191007X10b (KA's) 3 . ANSWER 4,29 (1.00) l.. ~~~-c---- .(**'*** CATEGORY-4 CONTINUED ON NEXT PAGE *****) Q _ _ = _ _._ _ _ _ _ _ - _ _ _ _

./ Cy '., r

4-~

REACTOR' PRINCIPLES'(7%) THERMODYNAMICS Page 43 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)

REFERENCE:

'Sisulator malfunctions RCO3, RC04 3.1 '191005K101 19100'5K101 ..(KA's) ANSWER 4.20 (1. 0 0). ____c____ REFERENCE r. 'W3SES LP ZTYH-803-00,lpg 16-2.7 191004K112 191004K112 ..(KA's) ANSWER-4.21 (1.00) ] ___g___ . REFERENCE' CP-10-001, pg 72 '.3.5 191008K108 19100BK108 ..(KA's) ANSWER 4.22 (1.00)

---

a----

REFERENCE -W3SES LP ZTYH-803-00, pg 16 2.9^ 191004K107 191004K107 ..(KA's) -' ANSWER 4.23 (1.00) L---d--- (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

t 1 4 L4. = REACTOR PRINCIPLES (7%) THERMODYNAMICS. Page 44 (7%) AND-COMPONENTS (10%) 'f11NDAMENTALS EXAM) . REFERENCE.'. PSRTOA, pg 3.3-13 _. .. REACTOR OPER STUDY GUIDE, PART/2, PG 3-22 004000A404 004000A404 ..(KA's) ' V -: );). { i. A ( ..t 3 i (***** END OF CATEGORY 4 *****) uli____________________-______________ ____y

CT .. i w p 1 .r 5. EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS Page 45 (33%) ..\\ ' . ANSWER. 5.01 .(2.50) . d.- ' 5.l'5 ~ b. DELETED. c. feed' flow, steam flow (may be transposed) d. 0.95, 1720 .(0.50 each) ' REFERENCE ~LP, Selected off-Normals at Power, LO-A.5 OP-901-013, p. 3 ?3.9000024G011 ..(KA's) -ANSWER 5.02 ( 3.'00) c. 1. Facilitate.depressurization (0.75). 2. -Prevent excessive RCS cooling (0.75) Diesel generator B is needed to supply power to Safety Train B b.

l..

controls-(which.are used because B train cables run outside cable spreading room which could be the source of, or endangered by, the fire that has caused the CR evacuation). (0.75) 2. CCW pump B is needed to provide cooling for DG B. (0.75) REFERENCE LP, Off-Normal Procedure - Evacuation of-Control Room and Subsequent Plant Shutdown, LO-4 lLP, Off-Normal Procedure - Evacuation of Control Room and Subsequent Plant Shutdown, p. 8, 9 4~.5, 3.5 000068G007 000068K318 000068G007 000068K318 ..(KA's) I 5 ANSWER 5.03 (1. 00) j b. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) }

i l 5; EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 46 (33%) REFERENCE 1 OP-901-054, p. 18 OP-901-046, p. 7 LP, Selected Off-Normals while Shutdown, LO-2.a 4.3, 3.9, 3.9 0000256011 0000256010 000057A219 0000256011 0000256010 000057A219 ..(KA's) . ANSWER 5.04 (2.00) c. Ensures that injection water reaches the core (by ensuring decay heat is 1,ow enough so that core steam flow does not entrain injection water, thereby prevent ing it from reaching the core). (1.0) b. Ensures boron does not precipitate in core. (1.0) REFERENCE OP-902-002, Pg. 4 LP, SI and SDC, p. 32, 33 4.6 000011K312 000011K312 ..(KA's) ANSWER 5.05 (2.50) i O. 1. All CEAs fully inserted 2. Reactor power dropping 3. SUR negative (0.25 each) b. 1. Governor valves clos.ed 2. Throttle valves closud 3. Reheat valves closed 4. Intercept valves closed (0.25 each) c. 1. Exciter field breaker tripped 2. Generator breaker "A" tripped 3. Generator breaker "B" tripped (0.25 each) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 47 (33%) REFERENCE OP-902-000, p. 2 LP, Intro and Emergency Entry Procedure, LO-7 4.5, 4.3 000007A107 000007A106 000007A107 000007A106 ..(KA's) F ANSWER 5.06 (1.00) c. REFERENCE OP-901-010, p. 11 3.7 000015A210 000015A210 ..(KA's) ANSWER 5.07 (1.50) 1. T-hot 2. T-cold 3. Core temperature 4. S/G level j 5. Main feedwater flow 6. Emergency feedwater flow 7. S/G pressure (any 6 0 0.25 each) REFERENCE OP-902-005, p. 8 LP, Degraded Electrical Dist. Recovery Proc., LO-D.3 4.6 000055A205 000055A205 ..(KA's) ANSWER 5.08 DELETED. ANSWER 5.09 (1.50) 1. An event cannot be diagnosed (0.50) 2. Multiple events are occurring (0.50) 3. An event is in progress for which the appropriate optimal Recovery Procedure is not maintaining safety function criteria. (0.50) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l-l 1 i L

5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 48 (33%) REFERENCE OP-902-008, p. 1 LP, Safety Function Recovery Procedure, LO-1 4.6, 4.4 000074G011 000074G012 000074G011 000074G012 ..(KA's) ANSWER 5.10 (1.00) 0.- 3 b. 1 c. 5 (1.0 for correct sequence, .25 for each out of sequence) d. 2 o. 4 REFERENCE LP, Secondary System Off-Normals, LO-1.g OP-901-036, p. 6 3.1, 2.9 000051G011 000051K301 000051G011 000051K301 ..(KA's) ANSWER 5.11 (1.00) c. REFERENCE Technical Specifications, Definitions 3.9 000003K107 000003K107 ..(KA's) ANSWER 5.12 (1.50) O. Low pressurizer pressure (< or = 1621 psia). (0.50) j b. 1. CSAS actuated. (0.50) l 2. Loss of CCW to RCPs (for > or = 3 minutes). (0.50) J (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) i

V a .? 't { v. K '51 ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 49 i!. (33%) L . REFERENCE LP,'I'xcess Steam Demand, LO-D.1 j LP," Excess Steam Demand, p. 7 ~OP-902-004, p. 5 ll 3.6 000040G007 000067A108 000067A108 ..(KA's) ANSWER-5.13. (0.75) 'no-. -To maximize purification flow. (0.75) b.t DELETED. m REFERENCE' .OP-901-021, p. 7 3.6, 2.7 000076A207 000076K305 ..(KA's) ANSWER 5.14 (2.25) c. Any two of.the following at-0.50 each 1. Condensate bypass to condenser valves (short cycle recire valves) open 2. Heater drains bypass to condenser valves (alternate drain valves) 1, oPen + 3. Condensate pump:recirc valves open 4. Startup feed regulating valve closes 5. Feed pump recirc valve opens 6.- Heater drain pump recirc valve opens

b.

Main 'feedwater control valves fail as is (without instrument air).(0.75) c. 65 psig (+/- 5 psig) (0.5) REFERENCE CP-901-038, p. 7, 8 LP, Secondary System Of f-Normals, LO-1.b 3.4, 4.2, 3.9 000065K308 000065A206 000065K303 000065K300 000065A206 000065K303 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 3

l S. FMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 50 (33%)

ANSWER 5.15 (1.00) c..

REFERENCE OP-902-007, p. 5 4.6 000038A203 000038A203 ..(KA's)

ANSWER 5.16 (1.00) c.

REFERENCE EP-2-050, p. 10 3.7 000060K104 000060K104 ..(KA's) ' ANSWER 5.17 (1.50) 1. Manually trip the reactor (0.50)

2. -

Emergency borate. (0.50) 3. Open both the following breakers for 5 seconds and reclose: (0.25) a. SST A32 feeder (0.125) b. SST.B32 feeder (0.125) REFERENCE OP-902-000, p. 2 LP, Introduction and Emergency Entry Procedure, 74-8 4.5 000029G010 000029G010 ..(KA's) ANSWER 5.18 (1.00) c. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l I i )

Mi l { .Si " EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page

(33%)

REFERENCE 'OP-901-002, p. 10 s

RCS Flow Diegram - LOU-1564, G-172 4.0' 000027A215 000027A215

..(KA's) ANSWER. 5.19 (1.00) b. REFERENCE OP-901-001, p. 10 3.8 000028A205 000028A205 ..(KA's) ' ANSWER ~ 5.20 (1.50) c. 23, fuel (0.5 each) b. ' Iodine (0.5) REFEREFCE T;chnical Specifications, LCO 3.9.10.2 -T chnical Specifications, Bases . 3. 8 ', 3.8 000036G004 000036G003 000036G004 000036G003 ..(KA's) ANSWER. 5.21 (1.00) c. REFERENCE 'Tschnical Specifications, Definitions

T;chnical' Specifications, LCO 3.5.2 3.9,-4.1.

l 000009G003 000009G008 000009G003 000009G008 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) )

.h ! g

~ Y f d - i 5 EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS' Page 52 (33%) l-ANSWER 5.22 "(1.00) . 1 '.- '1.gpm total SGTL. -(0.5) 2.- '720 gpd SGTL in any S/G (0.5) REFERENCE. 'T;chnical Specifications, Definitions l .Tcchnical Specifications,. LCO 3.5.2 3.9, 4.1 .000009G003 000009G008 000009G003 000009G008 ..(KA's) l 1 i J (***** END OF CATEGORY 5 *****) L___=_---__-_

r I '6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 53 RESPONSIBILITIES (13%)

ANSWFri 6.01 (1.50)

Tha CPCs will." remember"<the last valid penalty' factors from the failed CEAC (0.5). These factors are compared with the operable CEAC penalty factors (0.5). The' largest of the penalty factors is selected for use. (0.5) REFERENCE LP,'CPC, p. 18 LP, CPC, LO-5 32 012000K607 012000K607 ..(KA's) s ANSWER 6.02 (1.00) Varify operability (of A MDEFW pump) REFERENCE OP-100-001, p. 35- '4.1 -061000G011 061000G011 ..(KA's) ANSWER 6.03 (1.00) b. REFERENCE TCchnical Speci'fications, Bases - Safety Limits 3.8 002000G006 002000G006 ..(KA's) ANSWER 6.04 (1.00) c. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l ]

f 6 '.-- PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (13%) REFERENCE -LP, RCP,.p. 10, 11 -OP-1-002, p. 5, 10 3.9 003000A201 003000A201 ..(KA's) 4 ANSWER. 6.05 (2.00) c. 3. b. 2. -c. 4. (0.5 each) d. 1. ' REFERENCE 'LP, Excore ".4IS, p. 6 -110 LP,1Excore NIS, LO-2 3.2 015000K601 015000K601 ,.(KA's) ' ANSWER .6.06 (2.00) c.- 1. Both backup charging pumps start (0.5 each) 2. Letdown throttle valves to minimum 3. .All-pressurizer heaters deenergize (tripped or blocked) b. .The pressurizer heaters will deenergize. (0.5) i REFERENCE-1 -LP, Pressurizer Level and Pressure Control, figure 48 LP, Pressurizer Level and Pressure Control, LO-4 3.6-011000A211 011000A211 ..(KA's) j (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L______-_-______ l

6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page-55 RESPONSIBILITIES (13%) . ANSWER 6.07 (1.50) Acespt any three (3) of the following at 0.50 each: 1. Hoist operating 2. Mast bumper. contact 3.. Grapple in or below upper grapple operate zone (UGOZ) 4. Spreader on fuel mast not retracted 5. Aligner on CEA mast not-retracted -6. Fuel hoist in " fuel only" region with fuel on 17. CEA hoist in."CEA only" region with CEA on 8. One-hoist not at UP limit'unless in upender area 9.. In upender region with upender not vertical REFERENCE LP, Fuel Handling and Storage. Equipment, p. 15 LP, Fuel Handling and Storage Equipment, LO-2.a 3.3 034000K402 034000K402 ..(KA's) ANSWER .6.08 -(2.50) .c. 4. b. 1. c. 5. d. 3. O. 8. REFERENCE LP, CEDMCS, p. 19 - 21 LP,~CEDMCS, LO-E 3.8 001000K401 001000K401 ..(KA's) . ANSWER 6.09 (1.00) 1. RCPs (0.5) 2. CEDM coolers (0.5) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****,

i i l 6; PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 56 RESPONSIBILITIES (13%) j l } REFERENCE { LP, CCW, p. 4 LP, CCW, LO-6.a 3.4 008000K102 008000K102 ..(KA's) ANSWER 6.10 (1.50) R2;cte - depress the (Emergency Manual Actuate) pushbutton on the Master R: mote Control Panel (in the Control Room). (0.75) Local - remove lockpin and turn lever on top of the selected cylinder. (0.75) REFERENCE LP, Fire Protection and Detection, p. 22 LP, Fire Protection and Detection, LO-7 3.2 086000A406 086000A406 ..(KA's) ANSWER 6.11 (2.00) O. Minimum - ensures adequate heat transfer (prevents thermal shock) across the RHXer. (0.5) b. Maximum - based on maximum charging pump capacity minus RCP CBO flow. (0.5) c. It slows the speed of the letdown flow control valve stroke. (1.0) REFERENCE LP, Pressurizer Level and Pressure Control, p. 10, 17 LP, Pressurizer Level and Pressure Control, LO-2, 3 3.4, 3.1, 3.1 004000G010 004020A101 011000K604 004000G010 004020A101 011000K604 ..(KA's) (***** CATEGOPY 6 CONTINUED ON NEXT PAGE *****) 1

6f. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 57 -RESPONSIBILITIES (13%) ANSWER 6.12-(1.50) RWSP outlet valves (SI-106A/B)' (0.25 each) Miniflow valves from HPSI,.LPSI, and CS pumps (SI-120A/B and SI-121A/B) (0.25 each) REFERENCE -LP,-Conta1 ament Spray, p. 29 LP, Containment Spray, LO-5 3.0 006020K401. 006020K401 ..(KA's) ANSWER 6.13 (2.00) a. -Running air compressor loads b. Standby air compressor starts c. SAS crosstie opens (SA-125) (0.5 each) d. Bypass around inst. air dryer opens (IA-123) REFERENCE CP-901-038, p. 5 LP, Instrument Air System, p. 7 LP, Instrument Air System, LO-3 and 7 3.5, 3.2 078000K402 078000A301 078000K402 078000A301 ..(KA's) ANSWER 6.14 (1.00) o. REFERENCE ELP, Radiation Monitoring System, p. 30 LP,-Radiation Monitoring System, LO-10 3.1 g 072000A406 072000A406 ..(KA's) i I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L- _ - - _.

L 3. PLANT SYSTEMS'(38%)'AND' PLANT-WIDE GENER M Page 58 --RESPONSIBILITIES (10%)

3. -

1 $ ANSWER, 3.22l ' (1. 50). No lockout (no 86G1/86G2' signal) (At-least).one generator OCB closed (0.5 each). '2.. Generator in synch 3.- ' REFERENCE SD.ZMT-700-00, p. 28 & LO-4 062000A401 ..(KA's) 1 ANSWER 3.23 (2.00) a. Running lairLcompressor loads up b.- ~ Standby air compressor starts Ec, SAS:Orosstie opens (SA-125) (0.5 each). d. Bypass around.IAS air dryer opens (IA-123) REFERENCE' 10P-901-038,.p. 5 LP, Instrument Air, System, p. 7 LP, Instrument Air System, LO-3 and.7 -078000A301. 078000K402 ..(KA's.)- ANSWER 3.24 '(1.00) ____e____ REFERENCE-LP,- Plant Protection System, p. 12, figure 82 LP, Plant Protection-System, LO-10.d 013000K404 ..(KA's) 1 L 1 ANSWER. 3.25 (1.00)

---

a----

l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l l.......

-3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 59 RESPONSIBILITIES (10%) REFERENCE LP, Radiation Monitoring System, p. 30 LP, Radiation Monitoring System, LO-10 072000A403 ..(KA's) ANSWER 3.26 (1.50) a. 3AB-DC-S b.. 3A3S. (0.5 each) c. 3B3S REFERENCE LP, EFW System, LO-D-SD, EFW System, p. 32 061000K202 061000K201 ..(KA's) ANSWER 3.27 (1.00)

---

d----

. REFERENCE HP-1-109, p. 12 194001K103 ..(KA's) ANSWER 3.28 (1.00) ____3____ REFERENCE 10 CFR 20 ll' 194001K103 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) w__--__-__-_---_-______-_____-__-____

,j' n; e \\ 3 e C PLANT SYSTEMS- (38%)- AND ' PLANT-WIDE-GENERIC - Page.60 7 RESPONSIBILITIES-(10%). f s. [ ANSWER i3.29 ( l'. 0 0 ) - < 1. '- Must be for purpose ofitraining~ . (0,5)'

2;

.Must be supervised by a~. licensed operator: (0,5); 1 X; REFERENCE OP-100-001,-'p. 34 c194001A111 ..(KA's)- ANSWER 3,30 -(1.00): f(A"MDEFWP); operability must be-verified ' REFERENCE. ~OP-100-001, p. 35 ~194001K102: ..(KA's)' ~ ANSWER 3.31' (1.00) ____e____ IREFERENCE-- OI-010-000, p._13 194000K101 ..(KA's) ANSWER? 3.32 (1.00) 'a.- 5 (0.5)

b.1 3

(0.5) w '(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) )

3. -PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 61 RESPONSIBILITIES (10%) REFERENCE T chnical Specifications, p. 6-2 OP-100-001, p. 21-A 194001K116. ..(KA's) ANSWER' 3.33 (1.00) n. 4 b. 2 c. 5 (1.0 for correct order, .25 for each out of sequence) 4. 1-c. 3 REFERENCE UNT-5-003, p. 12 194001K102 ..(KA's) ANSWER 3.34 (2.00) c. 1150 (or 110 minutes) (+/- 20 minutes) (1.0) b. 1220 (or 140 minutes) (+/- 15 minutes) (1.0) l REFERENCE i OP-10-001, p. 73 l OP-05-007, p. 30, 31 194001A108 ..(KA's) l 1 l l i i ) (***** END OF CATEGORY 3 *****) { (********** END OF EXAMINATION **********) i L-. .- ____-----__________ ____ _ d

-m= f-s. 9 r i; s L-SIMULATION FACILITY FIDELITY REPORT

,p, g

r Facility Licensee:" Louisiana Power and Light Company Facility Docket Number: 50-382 Facility License' Number:. NPF-38 oU Ope. rating Tests Administered at: IWaterford 3 Operating; Tests. Administered: May 16-18, 1989 a. During~ the c6nduct of the. simulat'or portion'of the operating' tests identified above, the:fc11owing apparent performance and/or human factors discrepancies were observed: ~ 1. A " Cry Wolf." annunciator malfunction was4 inserted to alarm but did.not. The simulator supervisor stated that any malfunction inserted into the sixth malfunction slot does not function. 2. Malfunction EG16A.: Load. Sequencing Failure, did not perform as expected. 3. A steam generator level transmitter was programmed to: fail on a two ' minute ramp. When the malfunction was inserted, the indication .immediately went to 0.. 4.1 When, inserting.a malfunction for a ramped failure of an instrument, the initial value must be inserted as well.as the final value.- This is . difficult to perform when the present value (premalfunction) is not known. -The simulator operator, on several occasions, had to use a best-guess initial value for the malfunction's initial;value. This may cause a step jump. in the parameter if the inserted initial value is not close to the actual valua, P ' ___.:.__2.-_

.7 a.

6; > PLANT' SYSTEMS (30%) AND/ PLANT-WIDE' GENERIC Page'58- . RESPONSIBILITIES (13%): c 3 ..t ? ANSWER" 6.15.- '(1. 50) 4. 3AB-DC-S' b. 3A3SL (0.5 each) c. ,3B3S' . REFERENCE LP,.EFW' System,;.LO-D ..SD, EFW System, p. 32' -3.3, 3e7 061000K201 061000K202 -061000K201. 061000K202 ..(KA's). ANSWER 6.16_ (1.00) c. REFERENCE-JSD,.'SBCS, p. 7 2.9 '041020K606. 041020K606 ..(KA's) ANSWER 6.17' (1.00) . a'. - REFERENCE' SD, SBCS, p. 24 3.8 001000K407 001000K407 ..(KA's) -ANSWER 6.18 (1.00) a. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) z__

n i 1 P} 9 6c PLANT' SYSTEMS(30M.AND PLAN'T-WIDE GENERIC .Page 59 RESPONSIBILITIES-Y D%) d REFERENCE. .LP,.CPC and.CEAC,~p. 25, 32 LP,1CPC and CEAC, LO-3 3.2-012000K607 012000K607 ..(KA's) ' ANSWER .6.19 (1.50)- c. 3. b. 4.- (0.5 each) c. 2. REFERENCE LP, Plant Protection System, p. 8 LP,. Plant Protection System, LO-1 -. 4. 3 012000K402 012000K402 ..(KA's) LANSWER 6.20' (1.00) d. REFERENCE LP, Plant Protection System,_p. 12, figure 82 LP, Plant Protection System, LO-10.d SD, Plant Protection System, p. 66, 67 '4.5 013000K404 013000K404 ..(KA's) ' ANSWER 6.21 (1.00) ~b. (****+ CATEGORY 6 CONTINUED ON NEXT PAGE *****) l

'r:1 p; g -~ c'

L;

,;..~ ,.r i 16. PIANT SYSTEMS-(30%) 'AND PIANT-WIDE-GENERIC Page 60 RESPONSIBILITIES (13%) l.i ~ REFERENCE' HP-1-109,--p. 12 3.5 7-L 194001K104 194001K104' ..(KA's). ANSWER 6.22l - (1. 00) ' .b.

- REFERENCE '

10 CFR'20 3.4 '194001K106 194001K106 ..(KA's) ANSWER' 6.23 (1.00) 1. (Only) for purpose of training, and (0.5) 2. -(Only) when_ supervised by a licensed. operator. (0.5) REFERENCE OP-100-001, p. 34 4.1.. '194001A111' 194001A111 ..(KA's) LANSWER 6.24 (1.00) b. -REFERENCE. OP-100-001, p. 39 3.4 194001A101 194001A101 ..(KA's) ANSWER 6.25 (1.00) 'c. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

[.g ^

6.

PIANT SYSTEMS'(30%) AND PLANT-WIDE GENERIg Page-6L RESPONSIBILITIES (13%) ~ R' EFERENCE - [; OI-010-000,:' p. 13. .3.7-194000K101 -194000K1011 ..(KA's) .,' ANSWER 6.26' (1. 00 ). o.. 5 ' ( 0. 5 ).' b.' "NAos (0.5)'

' REFERENCE-Tcchnical. Specifications, p. 6-2 OP-100-001',.p. 21-A-4.2' 194001K116L 194001K116

..(KA's) ANSWER' 6.27~ (1.00) a.. 4s .h. 2 c.' 5-(1.0.for correct order, .25'for.each.out of. sequence) d. 1 c. 3 REFERENCE 'UNT-5-003, p. 12 4.1- '194001K102 194001K102 ..(KA's) ANSWER 6.28 (2.00) n. 0.1 b. 0.15 c. 0.1 'd. '1.0 (0.5 each) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l i

m l i i 1 4 I .6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 62 RESPONSIBILITIES (13%) ' REFERENCE Tcchnical Specifications, 3.4.6, 3.4.7 -2.9 194001A114 194001A114 ..(KA's) ANSWER 6.29 (1.00) c. REFERENCE T chnical Specifications, p. 6-5 3.9 194001A111 194001A111 ..(KA's) ANSWER 6.30 (2.00) a. 1150 or 110 minutes (+/- 15 minutes) (1.0) b. 1220 or 140 minutes (+/- 20 minutes) (1.0) REFERENCE OP-10-001, p. 73 OP-05-007, p. 30, 31 '3.1 194001A108 194001A108 ..(KA's) ANSWER 6.31 (1.00) 1. Shelter the 2 mile radius. (0.5) 2. Shelter the 2 - 5 mile downwind sectors. (0.5) REFERENCE EPIP, General Emergency, p. 4 EPIP, Protective Action Guidelines, p. 5 4.4 194001A116 194001A116 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

r_ i ,..: e i;(

p..

s 1 [F l' 6. PLANT SYSTEMS-(30%) AND PLANT-WIDE GENERIC' Page'63 1 RESPONSIBILITIES (13%) = ANSWER '6.32 (1.00)-

bi-.

TREFERENCE V EPIP, General Emergency, p. 4 EPIP,: Protective Action Guidelines, p. 5 4. '4 -

194001A116

-194001A116. ..(KA's) o (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********)

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: WaterFord 3 REACTOR TYPE: PWR-CE 2 i DATE ADMINISTERED: 89/05/15 I INSTRUCTIONS TO CANDIDATE: I Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing j grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. 1 % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.38 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) 25.50 25.89 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) 48.00 48.73 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%) 93.50 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature l i l

p. NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS "TDuring'the administration of this examination the'following rules. apply:- .l. : Cheating on.the examination means an automatic denial of your application icnd could result in more severe. penalties. 2. Restroom trips are to'be limitedfand_only one candidate at.a time may leave. You must avoid.all. contacts with anyone outside theLexamination room to avoid even the appearance mr possibility of: cheating.

3.. Use-black ink or~ dark pencil only to facilitate-legible reproductions.

4..

Print your name in the blank provided on the cover sheet of the examination. '. ' Fill in the'date on the cover sheet of the examination (if necessary). 5 6. Use only the paper provided for answers, 7. ' Print your name in the upper right-hand corner of the first page of.cach s section of the answer sheet. 8.g consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side -of the paper, and write "Last Page" on the last answer sheet. 9.- Number each answer.as to category and number, for example, 1.4, 6.3. 10.: Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on.your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value~for each question is indicated in. parentheses after the-question and can be used as a guide for the depth of answer required.

] ' 14..Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not. '15.' Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION ~AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the

-work-is your own and you'have not received or been given assistance in completing the examination. This must be done after the examination has -been completed. _ _ = _ _ _ _

18.-When you complete your examination, you shall: a. Assemble your examination as follows: (1) Exam questions on top. -(2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer. b. Turn in your co.py of the examination and all pages used to answer the examination questions, c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions. d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. i i

-g EQUATf0N SHEET f ='ma .v = s/t Cycle efficiency = (Net work out)/(Energy in) 2 w = mg s = V t + 1/2 at o 2 E'= mc KE = 1/2 my a = (Vf - V,)/t A = IN A=Ae' n PE = mgn Vf = V, + a t w = e/t i = En2/t-1/2 = 0.693/t1/2 / 1/2*"

• U t M t @

2 t w. y ap. n0 A= [(t1/2)

• It )3 4

b aE = 931 am m = V,yAo -Ix o Q = mCpat 6 = UAa T-I = I e "* o I = I,10'*/ M Pwr = W ah f TVL = 1.3/u sur(t) P = P 10 HYL = -0.693/u P = P,e*/ .SUR = 26.06/T SCR = S/(1 - K,ff) CR = S/(1 - K,ffx) x SUR = 26p/t* + (8 - p)T CR)(1 - K,ffj) = CR2L I*beff2) T = (t*/o) + [(a - o V Io] M = 1/(1 - K,ff) = CR /CR, j T = s/(o - s) M = (1 - K,ffa)/(1 'K,ffj) T = (s - o)/(To) SDM = { - K,ff)/K,ff a = (K,ff-1)/K,ff = 4K,ff/K t* = 10 seconds eff I = 0.1 seconds o = [(t=/(T K,ff)] + [a,ff (1 + IT)] / I)dj = I d 2,2 2 P = (I4V)/(3 x 1010) Id gd j 22 2 I = cN R/hr'= (0.5 CE)/d (meters) R/hr = 6 CE/d2 (feet) Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 x 1010dps 1 ga]. = 3.78 liters i kg = 2.21 lbm = 7.48 gal. I hp = 2,54 x 103 1 ft4 Stu/nr Density = 62.4 lb"t/ft3 1.w = 3.41 x 100 Stu/hr Density = 1 gm/c., lin = 2.54 cm Heat of vacarization = 970 Stu/lom 'F = 9/5'C + 32 tient of fusion = iaa Stu/ltm 'C = 5/9 ("F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in. 2

L { l 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 4 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAMl 1 QUESTION 1.01 (1.00) MULTIPLE CHOICE (Select the correct answer) Prior to reaching criticality during a reactor startup, with the neutron count rate initially stable at 100 counts per second (cps), a reactivity cddition (by CEA withdrawal) causes the count rate to increase and then stabilize at 200 cps. The CEAs are then withdrawn again, causing count rate to increase and then stabilize again at 400 cps. Which one of the following statements is CORRECT? a. The first reactivity addition was larger. b. The second reactivity addition wan larger. c. The two reactivity additions were equal. d. The stabilization times are needed to determine the relationship of the reactivity additions. QUESTION 1.02 (1.00) MULTIPLE CHOICE (Select the correct answer) in addition to the immediate/ direct effect of CEA positioning on Axial Shape Index (ASI), CEA positioning / motion can also have a delayed / indirect offect on ASI because of which one of the following? a. Xenon oscillations b. Water gap peaking c. Moderator displacement d. Fuel shadowing (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

'1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 5 (7%) AND COMPONENTS (11%)- (FUNDAMENTALS EXAM) I, l QUESTION' 1.03 (1.00) l-MULTIPLE CHO1CE (Select the correct answer) 'Ameume the reactor is. operating at 100 percent power when an inadvertent reactor-trip occurs. If the reactor power. decrease rate has stabilized .(i.e., power decrease rate-is constant) when power reaches 1 E -2 percent-soveral minutes after the trip,.how many ADDITIONAL' minutes will be required for power to decrease to 1 E -4 percent?- a. 2 b.- 4 c. 6 ' d.' 8 . QUESTION 1.04 (2.00) Assume the reactor is subcritical by 2.5 percent delta-K/K and the neutron count. rate is stable at 135 cps. Atter some CEA withdrawal, count rate stabilizes at 405 cps. How much positive reactivity'has been added? STATE ASSUMPTIONS / EQUATIONS USED and SHOW ALL WORK. l 1' l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) 1

L [ 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 6 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l l QUESTION 1.05 (1. 00) MULTIPLE CHOICE (Select the correct answer)' Which one of the following describes the change in the absolute magnitude of the inverse boron worth (IBW) as RCS average temperature is INCREASED? Q. IBW becomes LARGER because a greater concentration of boron is needed to keep the same total boron atoms in the core. b. IBW becomes SMALLER because less boron must be added to obtain an equal increase in boron concentration. c. IBW becomes LARGER because boron is a 1/V absorber whose cross-section becomes rapidly smaller as moderator temperature is increased. d. IBW becomes SMALLER because more boron atoms are expelled from the core for an equal increase in moderator temperature. QUESTION 1.06 (1.00) MULTIPLE CHOICE (Select the correct answer) After being at 40% for several days, plant power is ramped to 80%, where renctor power, RCS boron concentration, and Tavg are quickly stabilized. If plant power and CEA position are then maintained constant, the operator will have to change RCS boron concentration frequently over the next hour to keep Tavg matched with Tref. Which one of the following describes the boron change required over the next hour and the reason for this change? .a. Dilute, because Xenon production from direct fission yield will temporarily exceed Xenon removal, b. Borate, because Xenon removal by decay will temporarily exceed Xenon production. Dilute, because Xenon production from Iodine decay will temporarily c. exceed Xenon removal. d. ' Borate, because Xenon removal by neutron absorption will temporarily exceed Xenon production. I j (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l \\

g.- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 7 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) s QUESTION 1.07 (1.00) MULTIPLE CHOICE (Select the correct answer) Which one of the following plant parameter changes will INCREASE the chutdown margin for a reactor that was shut down from high power operations cbout 12 hours ago? (Consider each change separately.) n. Increasing RCS boron concentration by 100 ppm b. Full withdrawal of a shutdown group CEA for a test c. The Xenon change over the next 12 hours d. A cooldown of the RCS to 300 F QUESTION 1.08 (1.00) MULTIPLE CHOICE (Select the correct answer) With the plant operating at power, which one of the following parameters must DECREASE to cause the departure from nucleate boiling ratio (DNBR) to DECREASE (i.e., change from 2.2 to 2.1)? a. Nuclear power b. Reactor coolant flow c. Average coolant temperature d. Core delta-T (assume constant T-cold) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

l 1, REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 8 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l QUESTION 1.09 (1.00) MULTIPLE CHOICE (Select the correct answer) After 10 years of reactor operation, the maximum allowable stress limit for 'the reactor-vessel inner wall is more restrictive than the stress limit for tha reactor vessel outer wall because of which one of the following? a. The inner wall has a smaller surface area than the outer wall. b, The inner wall experiences more tensile stress than the outer wall. c. The' inner. wall experiences more neutron radiation than the outer wall. d. The inner wall experiences a higher temperature than the outer wall. QUESTION 1.10 (1.50) The reactor is producing 100% rated thermal power with core delta-T at 60 F and an RCS mass flow rate of 100% when a reactor trip occurs because power is lost to all RCP buses. After natural circulation flow stabilizes with a d cay heat generation rate of 3% rated power, core delta-T is 30 F. Assume that RCS specific heat capacity remains constant through this event. What is the natural circulation mass flow rate (in percent)? STATE ASSUMPTIONS / EQUATIONS USED and SHOW ALL WORK. l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l

' 1 '. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page. 9 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) -QUESTION ~ 1.11 (1.00) MULTIPLE CHOICE (Select the correct answer) The reactor'is in hot-standby < producing negligible decay heat with two lesctor coolant pumps running. An RCS cooldown and depressurization are to' be conducted while maintaining a 100 F subcooling margin in the RCS. To ha<e the required subcooling when RCS pressure is reduced to 1500 psia, steam generator pressure must be concurren?.ly reduced to which of the following? n; 373 psia. b.. 435 psia c. 556 psia d. 658 psia QUESTION 1.12 (1.00) MULTIPLE CHOICE (Select the correct answer) The~ plant is in hot tandby with the RCS pressure being maintained at 1000 psia by a 100 percent quality steam bubble in the pressurizer. A pressurizer safety valve is leaking to the quench tank, where the pressure is being maintained at 5 psig. Which one of the following would be the expected temperature in the tailpipe downstream of the safety valve? (Assume ambient heat losses are negligible.) a. 220 deg F 'b. 260 deg F c. 300 deg F d. 340 deg F l i (***** CATEGORY L CONTINUED ON NEXT PAGE *****) 1 i C_________________ }

l '1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 10 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l ' QUESTION 1.13 (1.00) MULTIPLE CHOICE (Select the correct answer) l Consider a single main feedwater pump running with the plant operating at ~50 percent power and all condensate pumps / condensate booster pumps running. H Which one of the following parameter changes will INCREASE the available Not Positive Suction Head (NPSH) for the main feedwater pump? c. DECREASING the number of running condensate pumps by one b. -INCREASING the feed pump feed flow rate c. DECREASING the condensate temperature d. INCREASING the feed pump steam flow rate by 30 percent QUESTION 1.14 (1.50) A plant is originally operated at 100% power with RCS Tavg at 582 F, and a steam generator pressure of 900 psia. During a maintenance period, 4% of the tubes in EACH steam generator are plugged. Assume that RCS specific heat capacity and mass flow rates through the SGs are unchanged by having 4% of the total SG tubes plugged (i.e., remain constant et the original 100% value). To maintain a steam pressure of 900 psia at 100% power with 4% of.the total SG tubes plugged, Tavg must be changed to what new temperature? STATE ASSUMPTIONS / EQUATIONS USED and SHOW WORK. (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1.. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)

L l QUESTION 1~15-(1.00) MULTIPLE CHOICE (Select the correct answer) If the sensing element-of a cold leg resistance temperature detector (RTD) dsvelops an open circuit, how will-the associated temperature indication respond? c.- ' Fail 1as is. b. Track actual temperature, but with an offset. c. Indicate higher than actual temperature. d. Indicate lower than actual temperature. -QUESTION 1.16 (1.00) MULTIPLE CHOICE - (Select the correct answer) If a rupture occurs'in a steam generator (SG) level detector reference leg,- how will the associated SG level indication respond? a. Indicate higher than actual level. ~ b. Inc~'.cate lower th n actual level. l c. Indicate the same as actual level. d. Remain at the level existing prior to the rupture. l .i I i l 1 i l (***** CATEGORY l CONTINUED ON NEXT PAGE *****) j i L izz ________ ___ _ _. _. _ _ j

'1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 12 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) QUESTION 1.17 (1.00) MULTIPLE CHOICE' (Select the correct answer) A motor-operated valve (MOV) should NOT be manually opened and placed on its backseat (unless power to the motor operator has been lost) because of which one of the~following? a. The operator may not know how many turns of the handwheel are required to open the valve fully, b. Electrical power to the motor operator may be suddenly returned, causing possible operator injury. c. Manual operation. increases the likelihood of subsequent leakage past the valve seat. d. The motor operator may be unable to close the valve during. subsequent electrical operation. -QUESTION 1.18 (1.00) MULTIPLE CHOICE (Select the correct answer) If a fresh, unsaturated CVCS mixed bed demineralized resin is put in service without prior saturation treatment, which one of the following describes the expected response of RCS chemistry? a. pH will DECREASE and boron concentration will DECREASE. b. pH will DECREASE and boron concentration will INCREASE. pH will INCREASE and boron concentration will DECREASE. c. d. pH will INCREASE and boron concentration will INCREASE. l l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) 1

I.,. l'. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 13 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM), QUESTION. 1.19 (1.00) MULTIPLE CHOICE'(Select the correct answer) EIf the motor current for a running centrifugal pump. suddenly increases to. "a value several times greater than running. current and_ remains there.until

ths' supply circuit breaker trips, which one of the following malfunctions is indicated?

a..

A. shut discharge valve b. A shut suction valve

c.. A seized pump shaft d.

A sheared pump shaft QUESTION 1.20 (1.00) MULTIPLE CHOICE (Select the correct answer) Which set of parameters describes RUNOUT conditions for a motor-driven Emergency Feedwater pump? a. High discharge pressure, high flow, high motor current b. High. discharge pressure, low flow, low motor current c. Low discharge pressure, high flow, high motor current ~d. Low discharge pressure, low flow, low motor currant l-l l p (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l _mm_m.mw__m___ _ _ _ - _ _ _ _ _ _, _ _ _ _ _ _ _ _.. _ _ _ _.. _ _ _ _ _ _ _. _ _ _ _ _ _ _ _

h1 REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 14 h '( 7 % ) AND COMPONENTS'(11%)- (FUNDAMENTALS EXAM)_ l- -QUESTION 1.21 (1.00) 'MdLTIPLE' CHOICE l Select the correct answer)' l

Whrn closing the.first generator output breaker to connect the1 main-

~g:nerator to the grid, the generator output frequency should be: a. Slightly lower than grid frequency.

b.

Slightly _ higher than grid frequency. c.. Matched with grid frequency. d.- Adjusted to exactly 60 Hz. QUESTION 1.22 (1.00) MULTIPLE CHOICE (Select the correct answer) A motor-driven Emergency Feedwater pump is operating at low-flow conditions ibscause the downstream flow control valves are shut. If the flow' control . valves are opened,-EFW pump discharge pressure will and EFW pump ' motor current will -a.~ Decrease, Increase 'b._ Decrease, Decrease c. Increase, Increase - d. Increase, Decrease (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

p.. ~1. -REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 15 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) QUESTION 1.23 (l'00) MULTIPLE' CHOICE (Select the correct answer). A'cpecial.RCS chemistry. analysis requires Tavy to.be REDUCED by 8 degrees'F without changing CEA. position or. plant power (i.e., by changing RCS boron- ' concentration ONLY). (Assume turbine power is kept constant.) 'Given the following initial parameters, what' FINAL RCS boron concentration must be.obtained to REDUCE Tavg by 8 degrees F ? Initial RCS boron concentration = 550 ppm Total power coefficient = - 0.020 percent delta-K/K/ percent power Moderator temperature coefficient = - 0.015 percent delta-K/K/ degree F i Inverse boron worth'= - 100 ppm / percent delta-K/K .l o. 538 ppm 'b;. 544 ppm .c.. 556 ppm, d. 562 ppm l l. l i i l 1 (***** END OF CATEGORY 1 *****) Il L _ _ __ _ i

j 2; EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 16 (27%) -QUESTION 2.01 (2.50) . FILL IN'THE BLANK

Thn'following conditions require emergency boration in accordance with

'OP-901-013, Emergency Boration. (0.5 each blank) The plant is operating at 50% power and shutdown margin is determined a. to be less than. % delta-K/K. b. Deleted c. -An uncontrolled cooldown is in progress that is caused by excessive or excessive d. .The reactor is being. refueled and Keff i.ncreases to greater than or boron concentration decreases to less than ppm. QUESTION' 2.02 (1.50) Tha following actions.are required to be performed by the operators prior to exiting the control room when implementing OP-901-004, Evacuatton of Control. Room and Subsequent Plant Shutdown. What is the reason /'; asis each of these actions is included in OP-901-004? (P.75 each) Verify Spray Valve selector switch in the BOTH position, a. b. Reset the Moisture Separator Reheater controls. QUESTION 2.03 (1.50) Case II of OP-901-004, Control Room Evacuation With Fire, has an initial caution that requires Emergency Diesel Generator B and CCW Pump B to be 'available.during use of the procedure. For each of these components, what is the reason / basis it is included in the availability caution? (0.75 each) La. Diesel Generator B b. CCW pump B (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l h----________mm-_2._ __m

21 ' EMERGENCY'AND' ABNORMAL PLANT EVOLUTIONS Page 17 (27%) QUESTION.' '2.04: (O.00) Deleted-QUESTION 2.05 (2.00) OP-902-002, LOCA Recovery Procedure, directs the operator to begin ECCS hot leg. injection between two and.four hours after an RCS rupture occurs. -a. What is the' reason /basie for the two-hour minimum delay? (1.00) b.. What is the reason / basis.for the four-hour maximum delay? (. 00) . QUESTION 2.06 (2.50) For each of the following immediateLactions from OP-902-000, Emergency Entry Procedure, list the substeps required to perform that action. a'- Check for: Reactor. Trip. (0.75) b.- Check for Turbine Trip. (1.0) c. ' Check for Generator Trip. (0.75) QUESTION 2.07 (1.00) MULTIPLE CHOICE (Select the correct answer.) With the plant operating at 100% power, a rupture in the CCW non-essential loop has required immediate isolation of the non-essential loop. In cccordance with OP-901-010, RCP Malfunction, the operator must trip the reactor and all RCPs within how long after the CCW isolation? a. 30 seconds b. 60 seconds c. 3 minutes d. 5 minutes (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i l l 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 18 (27%) QUESTION 2.08 (1.50) The plant is operating at 80% power when a station blackout occurs. In cecordance with OP-902-005, Degraded Electrical Distribution Recovery, lint SIX (6) parameters that are monitored to determine if adequate natural circulation exists. Setpoints are NOT required. (0.25 each) QUESTION 2.09 (1.50) State the THREE (3) emergency conditions that require implementation of OP-902-008, Safety Function Recovery Procedure. (0.50 each) QUESTION 2.10 (1.00) MULTIPLE CHOICE (Select the correct answer.) The plant is operating steady state at 100% power when it is determined that loop 1 steam generator has a 0.8 gpm tube leak. In accordance with Technical Specifications, this leakage is defined as: a. Controlled leakage b. Pressure boundary leakage c. Identified leakage d. Unidentified leakage QUESTION 2.11 (1.00) State the TWO (2) LCO limits given in Technical Specifications for steam gcnerator tube leakage. Action statements are NOT required. (0.50 each) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2. EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Page 19 -(27%) QUESTION 2.12 (1.00) Thn plant is operating at steady state 100% power when a loss of gland c aling steam results in decreasing condenser vacuum. Number the following Ovnnts in their order of occurrence if condenser vacuum continues to d: crease. Assume NO operator actions are taken. n. Main turbine trips b. Standby vacuum pump starts c. SBCS valves interlocked closed d. Vacuum pumps shift to " Hogging Mode" o. Main feedwater pump turbines trip QUESTION 2.13 (1.00) MULTIPLE CHOICE (Select the correct answer.) The plant is operating steady state at 80% power with CEDMCS in Manual Sequential when a fully withdrawn rdgulating group CEA drops into the core. No operator action is taken and no reactor trip or cutback occurs. After the plant stabilizes, with the CEA fully inserted, how will shutdown margin have changed since before the CEA dropped? n. Increased, because the Tavg decrease results in less positive ' reactivity available upon a reactor trip. b. Decreased, bacause fewer CEAs are available for insertion resulting in less negative reactivity available upon a reactor trip. c. Remained the same, because the change in available negative reactivity has been exactly offset by the change in available positive reactivity upon a reactor trip. d. Cannot be determined, because additional information is required to determine whether the available negative reactivity or the available positive reactivity has changed by the greatest amount. (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1

2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 (27%) QUESTION 2.14 (0.75) Tha plant has been operating steady state at 80% power, but RCS gross activity has been trending higher as indicated by RCS sample analyses. The CRS implements OP-901-021, High Activity in the RCS. Why does OP-901-021 direct the operator to start all available charging pumps? QUESTION 2.15 (1.50) Tha plant is operating at steady state 100% power when an instrument air header leak causes a sustained decreasing instrument air system pressure. a. Assuming no operator action is taken and the reactor does not trip, what are TWO (2) valve actuations that will occur at low instrument air pressure and will reduce main feedwater pump suction pressures? (0.50 each) b. FILL IN THE BLANK On decreasing instrument air pressure, OP-901-038, Instrument Air Malfunction, requires the operator to trip the reactor when instrument air header pressure reaches psig. (0.5) QUESTION 2.16 (0.75) For a sustained decreasing instrument air system pressure, OP 901-038, Instrument Air Malfunction, directs the operator to control S/G levels by manually adjusting main feed pump turbine speed. What is the reason the Feedwater Control System cannot automatically control the S/G levels on decreasing instrument air pressure? I l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21 (27%) l Q6ESTION 2.17 (1.00) MULTIPLE CHOICE (Select the correct answer.) In accordance with OP-902-007, SGTR Recovery Procedure, which ONE of the 1 following indications is LEAST helpful in confirming which steam generator l 1 has experienced a 100 gpm tube leak? a. Radiation level on main steamline radiation monitors b. Radiation level on S/G blowdown radiation monitor c. Radiation level on condenser vacuum pump exhaust radiation monitor d. Abnormal S/G level for existing feedwater flow and steam flow l QUESTION 2.18 (1.50) The plant is operating steady state at 100% power when a valid automatic rsactor trip signal is actuated that does NOT result in a reactor trip. List the THREE (3) contingency actions that must be performed in accordance l with OP-902-000, Emergency Entry Procedure. (Assume that each contingency I action is NOT successful until all contingency actions have been completed.) ) QUESTION 2.19 (1.00) MULTIPLE CHOICE (Select the correct answer.) 1 The plant is operating steady steady at 100% power when a controller failure causes pressurizer spray valve RC-100A to open fully. The operators take the appropriate actions in accordance with OP-901-002, RCS Pressure Control Malfunction, which include stopping which RCP? a. 1A 4 1 b. 1B c. 2A I d. 2B (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1

[ - 2. - EMERGENCY AND ABNORMAL PLANT EVOLUTIONS. 'Page 22-(; (27%) 1' l- _ UESTION ~2'.20 (1.00) Q FILL IN THE BLANK In accordance with Technical Specifications, during a CEA replacement in ttha' reactor vessel WITHOUT fuel movement, at-least (a) feet.of water

chall'be maintained over the top of the _ (b)

(0.50.each) (***** END OF CATEGORY 2 *****) I

1 '3.- ' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC-Page 23 ' RESPONSIBILITIES (10%) QUESTION: 3.01 (2.00) What are FOUR (4)-separate. conditions / parameter trips that will cause an autostop of a running. waste gas compressor? Setpoints are NOT required. (0.50 each) QUESTION 3.02' (2.00) Waste Condensate Pump B is being used to pump Waste Condensate. Tank A to the circulating water system for discharge. a.. What are THREE (3) separate conditions / parameter trips that will cause an-autostop of waste condensate pump B?' Setpoints are NOT required.- (0.50 each) b. . What other automatic component actuation (NOT an alarm or annunciator) will occur in'the liquid waste management system when the autostop of -waste condensate pump B occurs? (0.50) . QUESTION .J.03 (2.00). .What are the.FOUR (4) required conditions / interlocks needed to be satisfied bnfore an Emergency Diesel Generator (EDG) output breaker will close automatically on a loss of all off-site power? (0.50 each) QUESTION 3.04 .(1.50) What are.the THREE (3) different, unlike events / signals that will cause the Emsrgency Mode Fuel Control Valves on an Emergency Diesel Generator to actuate (go'open'or close)? Setpoints are NOT required. (0.50 each) QUESTION 3.05 (1.00) What are the TWO (2) design bases / reasons that, on a SIAS, the LPSI cold l leg. injection flow control valves (SI-138A/B, SI-139A/B) open to a L throttled position instead of full open? (0.50 each) l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l

3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERI-, Page 24 RESPONSIBILITIES (10%) QUESTION. 3.06 (1.50) LIf the plant is stable at 90% power with all systems in automatic, how will the speed of the B main feedwater pump (MFWP) respond to each of the following signals from/in #2 feedwater control system (FWCS)? Consider each signal separately. (0.50 each) a. Reactor Trip Override b. High Level Override c. Level Deviation QUESTION 3.07 (1.50) MATCHING For each type of reactor trip in column A, pick the matching primary function of the trip from column B. (0.50 each) Column A Column B (choices) a. High Linear Power 1. Prevents DNBR from exceeding. design limits during anticipated b. High Logarithmic Power operational occurrences. c. High Local Power Density 2. Prevents linear heat rate from exceeding limits during anticipated operational occurrences. 3. Protects core from rapid reactivity excursions (ejected CEA). 4. Protects integrity of fuel clad and RCS boundary in event of an unplanned criticality. l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l 1

3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 25 RESPONSIBILITIES (10%) QUESTION 3.08 (1.00) MULTIPLE CHOICE (Select the correct answer.) In'the Steam Bypass Control System (SBCS), the " main" demand channel dsvalops the steam header pressure setpoint using a -select circuit, and compares the setpoint to a steam header pressure signal that is dcveloped by a -select circuit. a. High, High b. Lma, High c. High, Low d. Low, Low QUESTION 3.09 (1.00) MULTIPLE CHOICE (Select the correct answer.) In the Steam' Bypass Control System (SBCS), the Automatic Motion Inhibit (AMI) permissive signal is developed using input from: a. Turbine first-stage pressure b. Main steam flow c. Main steam header pressure d. Pressurizer pressure (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) L _- _ _ - _..- _

'3 PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page 26 RESPONSIBILITIES (10%) QUESTION 3.10 (1.00) MULTIPLE CHOICE (Select the correct answer.) .Which one of the following sets of RCP seal pressures indicates total FAILURE of the MIDDLE SEAL? Assume RCS pressure is 2250 psia. Middle Seal Upper Seal Vapor Seal Pressure (psia) Pressure (psia) Pressure (psia) a. 2250 1125 50 b. 2250 750 50 c. 1500 1500 50 d. 1500 750 750 QUESTION 3.11 (1.00) MULTIPLE CHOICE (Select the correct answer.) Tha Core Protection Calculators (CPCs) correct the input from each excore NIS detector such that the value used by the CPC is proportional to the flux immediately adjacent to the detector. This correction is called the: c. Shape annealing correction b. CEA shadowing correction c. Temperature siadowing correction d. Flux enhancement correction (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ( l L__________-_.

r '31 PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page 27. E . RESPONSIBILITIES (10%) . QUESTION 3.12-(2.00) . MATCHING For'each neutron detector in column A, pick the excore NIS channel in which " cit'is used from' column B. (Column B choices:may be,used more than once.) C s (0.50 each) Column A Column B (choices) 'a. Fission-chamber '1. Startup channel ~b. Uncompensated; ion' chamber 2. Safety channel c. ' Compensated' ion chamber 3. Control channel -d. Proportional counter (BF-3) 4. None/not used QUESTION 3.13 (2.00) 'The plant is operating at steady state 100% power with the Level-Measurement Channel Selector Switch (HS-110) selected to X and the Heater Cutout Selector Switch (HS-100-3) selected to X + Y. 'n. What THREE (3) different automatic equipment / component actuations will occur if level measurement channel X fails low? Do not include alarms / annunciators. (0.5 each) b. What' automatic equipment / component actuation will occur if ONLY level measurement-channel Y fails low? Do not include alarms / annunciators. (0.5) 1 i QUESTION 3.14 (1.50) What-THREE (3) fuel handling interlock conditions will automatically stop tha Refueling Machine with fuel movement in progress? Assume no operator action. (0.50 each) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 28 RESPONSIBILITIES (10%) QUESTION 3.15 (1.50) A CEAC fails and will not reset. What are the THREE (3) steps / functions tha CPCs perform to determine valid penalty factors for use when only one CEAC is operable? (0.50 each) i l QUESTION 3.16 (2.50) MATCHING For each CEDMCS control mode in column A, pick the applicable descriptive phrase from column B. (0.5 each) Column A Column B (choices) a. Auto Sequential 1. Allows movement of a single CEA group in high speed only. b. Manual Group 2. Allows movement of a single CEA group in high or low speed. c. Manual Individual 3. Allows movement of up to two regulating CEA groups at high speed only. d. Manual Sequential 4. Allows movement of up to two regulating CEA groups at high or low speed. ) c. Off 5. Allows movement of a single CEA in high speed only. 6. Allows movement of a single OEA in high or low speed. 7. Deenergizes all CEDMs resulting in rapid insertion of all CEAs. 8 Prohibits CEA motion except on reactor I trip. J I i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l I l _____-_-O

3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 29 RESPONSIBILITIES (10%) QUESTION 3.17 (1.00) Upon receipt of a SIAS, what TWO (2) different " nonessential" heat loads continue to be cooled from the "A" essential header of Component Cooling ' Water? (0.50 each) QUESTION 3.18 (1.50) Assume that the Computer Room Halon Fire Suppression System fails to release automatically when required. a. HOW and WHERE is the system manually released from the Control Room? (0.75) b. HOW and WHERE is the system manually released from the local station? (0.75) QUESTION 3.19 (1.50) Concerning the design of the CVCS letdown system: a. What is the basis / reason for the MINIMUM flowrate permitted by the letdown throttle valves when operating in automatic? (0.50) b. What is the basis / reason for the MAXIMUM flowrate permitted by the letdown throttle valves when operating in automatic? (0.50) c. What is the purpose of the lead / lag electrical unit located between the pressurizer level controller and the letdown throttle valve controller? (0.50) QUESTION 3.20 (1.50) When the ECCS is shifted to recirculation on a Recirculation Actuatien Signal (RAS), what are the SIX (6) valves that must be closed by the operator to prevent highly radioactive liquid from reaching the RWSP? (0.25 each) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) I

7-__. t 1:f 3. PLANT SYSTEMS - (38%) AND PLANT-WIDE GENERIC Page 30 RESPONSIBILITIES-(10%) QUESTION 3.21 (1.50) What are the THREE (3) signals / interlock conditions required for a Startup . Transformer feeder breaker to close automatically? (0 50 each) ' QUESTION 3.22 (1.50)

If the Startup Transformers are supplying the 6.9 KV'and 4 KV buses, what cra the THREE (3) required signals / interlock conditions, BESIDES the breaker control switch signal, needed for a Unit Auxiliary Transformer foeder breaker to close when the breaker control switch is moved to CLOSE.

(0.50 each) QUESTION 3.23 (2.00) 'A leak in the Instrument Air System (IAS) causes instrument air header-pressure to' decrease. What IAS equipment / component-actuation will occur at each~of the following instrument air header pressures? (0.50 each) (Do NOT include alarms / annunciators.) a. 112 psig b. 105 psig c. 100 psig d. 95 psig l (***** CATEGORY 3 CONTINUZD ON NEXT PAGE *****)

'31 PLANT' SYSTEMS'(38%)'AND PLANT-WIDE GENERIC Page 31_ RESPONSIBILITIES (10%) QUESTION: 3.24 (1.00) MULTIPLE CHOICE. (Select the correct answer.) Steam generat'or low pressure trip channel B has been bypassed for . maintenance.. If the steam generator low pressure trip channel C Alternate-Action'Latchdown Switch is~ depressed, then: La.- Both trip. channels'B and C.will be bypassed. 'b'. Only. trip channel B will be bypassed. c.- Only trip channel.C.will be, bypassed. .d. No trip channels will be' bypassed. QUESTION 3.25. (1.00) MULTIPLE CHOICE -(Select the correct answer.) During'an automatic source check of a. radiation monitor on RM-11, an alarm. Gio. received. :If the source check has failed, what additional indication of the failure will be present? a. A flashing C/S pushbutton. b. A backlit red C/S pushbutton. c.- A backlit amber C/S pushbutton. d. An extinguished C/S pushbutton. QUESTION -3.26 (1.50) List the electrical' buses that supply power to the motors of the following I EFW components / equipment. (0.50 each) 'a. Turbine-driven EFW pump steam line shutoff valve (MS-401A) -b.. ~ Motor-driven EFW pump A c. Motor-driven EFW pump B (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l

.1 1!- 1 3L PLANT-SYSTEMS ~(38%)-AND PLANT-WIDE GENERIC Page 32

RESPONSIBILITIES (10%)

I QUESTION 3.27-(1.00)

MULTIPLE CHOICE (Select.the correct answer.)

Whnn selecting a self-reading dosimeter '(SRD) for.use, the maximum allowed 1 pro-existing reading is

a. 10 mrem b. '20 mrem c. 25 mrem .d.- 50 mrem QUESTION. ,3.28 (1.00) . MULTIPLE CHOICE (Select the correct answer.) .Ths maximum extended quarterly whole body exposure allowed.by 10 CFR 20'for ce40-year old radiation worker is: a.' 1.25.. rem b. 3.0 rem ic. 5.0 rem d. 7.5 rem . QUESTION 3.29 (1.00) In accordance with OP-100-001, Duties and Responsibilities of. Operators on -Duty, what are the TWO (2) conditions required for.an. unlicensed operator to operate the. Control Element Drive Mechanism Control System (CEDMCS) 'during a reactor startup? L (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) i

3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 33 RESPONSIBILITIES (10%) QUESTION 3.30 (1.00) During a routine surveillance run of the B motor-driven EFW pump, excessive motor vibration is noted.. In accordance with OP-100-001, Duties and R:sponsibilities.of Operators on Duty, what operational requirement must b3 satisfied on A motor-driven EFW pump before maintenance can be started on B motor-driven EFW pump? QUESTION 3.31 (1.00) MULTIPLE CHOICE (Select the correct answer.) During a valve lineup verification, a locked throttle valve should be verified by: a. Unlocking the valve and closing the valve fully while counting the number of turns required. The valve should then be reopened the same number of turns and relocked. b. Unlocking the valve and opening the valve fully while counting the number of turns required. The valve should then be reclosed the same number of turns and relocked. c. Observing the valve stem, position indication, or flow instrumentation. The valve locking device should not be removed, d. Attempting to open and close the valve slightly to ensure movement is possible. The valve locking device rhould not be removed. QUESTION 3.32 (1.00) FILL IN THE BLANK In accordance with Technical Specifications and OP-100-001, Duties and. Responsibilities of Operators on Duty, the Site Fire Brigade shall consist of at least __(a)__ members, of which __(b)__ shall be Level A qualified. l (number) (number) (0.5 each) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

1 4 '3. PLANT' SYSTEMS (38%) AND-' PLANT-WIDE-GENERIC Page 34 RESPONSIBILITIES (10%) s ' QUESTION: 3.33 . (1.00) In.accordance with UNT-5-003, Clearance Requests, Approval, and Release, -j number the'following steps in the proper order to be accomplished for l .prsparing.a HPSI.pumpifor mechanical seal maintenance. a. Tag boundary valves closed

b.,

~ Remove pump breaker fuses c. ' Vent and drain the pump j i d. Tag' control switch in OFF .] a. Rack out' circuit breaker .I

\\

-QUESTION 3.34 (2.00) P-10-001, section:8.5, Power' Increase to 100%, requires use of the Turbine Londing Curve and the Turbine Startup Curve to determine the. maximum turbine' loading rate during a. plant startup. The following data is given: 1 l Initial HP turbine first stage metal temperature was 100 degrees F.. ) Current HP turbine first stage metal temperature is 400 degrees F. l Initial turbine steam admission time was 0600. l Current turbine fatigue index is 10000 cycles. I I If the main turbine has just been brought to 10% load at 1000, use the l attached curves and the-above data to determine FOR EACH CURVE the earliest l time that turbine load can reach 100%. l a, Turbine Loading Curve (1.0) b. Turbine Startup Curve (1.0l l (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) _o

PLANT DATA BOOK SECTION 3.2.5 REV. c ruasar START UP RECOMMENDATIONS [k FOR HP BB 296 NUCLEAR STEAM SYSTEM UNITS I-APPLY INITIAL LOAD: St. - ' 10% E 20 % d I t 1 s 4 i \\ INCREA l 3 WD I ( \\ l I o' (ExAMPt.Ett * \\ T Y K I' 4\\ \\ \\ C' %(\\ N N~ g g HOLD t i, a: Q S% LOAD g' \\ n \\. s rs \\ u T 1 ACCELER w o 9 TOSYNCS s, JEXAWPLE2! lgs_ \\ _1 I O ( OEGREES F O 10 0 200 300 400 S00} INITJAL MP TURBINE FIRST STAGE AeETAL TEMPERATURE EXAMPLE 1 (Shown on Chart) Determine the tirne to roll from turning gear to rated speed, synchronize and load to 100% load with the HP turbine first4tage metal temperature being 1000F prior to rolling. PROCEDURE Enter the chart at 1000F initial HP turbine first stage metal temperature and project to the rolling line. The intersection indicates that the unit should accelerate to synchronous soeed at a uniform rate in I hour or longer, The acceleration rate in 1800 rpm /60 rnin = 30 rpm / min. Continue the protection tp the 5% iced line. Determme from the chart that 5% load should be held for a minimum of 57 minutes in order to heat soak the turoine rotor before increasing load. To determme the tirne to increase load from 5% to 100%, project to the 100% load line. The cumulative time from turning gear to 100% Icad is 4 hours 35 minutes. The tirne to increese load from 5% to 100% is 2 hours 38 minutes (4 hours 35 rninutes.1 hour $7 minute. ) usmo a lead shanging rate of 95%/158 min = 0.6%/ min. EXAMPLE 2 (Shown on Chart) Determine the tirne to roll from turning gear to rated speed, rynchronite end load to 50% load with the HP tur. bine f;rst stage tnetal temperature being 4000F prior to rolling. PROCEDURE 8 f Enter at 400 F :nitial HP turbine first stage metal temperature and project to the rolling line. The intersection indicates that the unit should be accelerated to synchronous speed within 10 minutes, synchronized, and loaded initisily to 20% (en indicated by entering the initial load sesis located aboss the chart at the 4000F metal temper-sture) to avoid cooling the rotor. Contmue projection of the line to the 50% Icad line and drtermme the cumula-tive time of 40 rninutes from turning gest to 50% load or 30 mmutes (4010 min) from 20% to 50% !ced. The load changing rate is 30%/30 min = 1.0%/ min. CT.23814-B l

Qg Q--{x &N Od.G C% ' ' * " ~ 7 Ac o LOAD CHANGING RECOMMENDATIONS FOR HP BB 296 NUCLEAR STEAM SYSTEM ' UNITS FIGURE 1 Ljsoc g__ 5 / l E 14o*r 7 3 $ 200 ? Y / 5 r__../. ~ { -l

• li 10 0 /e

[ i 0 0 20 40 60 so 10 0 PERCENT RATED LOAD = FIGURE 2 w 400 / 330 / / / m B ///' / / 200 g// 5 W/ // y' 5 Vp:::V g y 100 r, 140*F j O 'O I 2 3 4 S TIME TO CHANGE LCAD-HOURS EXAMP8.E (Shown on Charts) Determine the time required and load changing rate to increase load from 25% to 100%. Assume a 10,000 cycle fatigue index is being used. PROCEDURE I Enter Figure 1 at 25% Ioad and *00% Icad and determine from curw tbs first stags temperature change from 0 to 25% load to be 1550F and from 0 to 100% load to be 2950F. By subtracting the 0 25% temperature change from the 0100% change, the first stage temperature change that occurs in increasing load from 25% to 100% is 2950-1550 1400F. Enter Figure 2 with the 14C0F first stage steam temperature change and project to the selected 10.000 cycle fatigue index curve. It is determined that load should be increased from 25% to 100% toad at a uniform rate over 0.2 hour (17 minutest The Icad changing rate is 75%/12 min. = 6%/ min. CT-23%

4 "E 12 ' REACTOR PRINCIPLES' (7%) ' THERMODYNAMICS .Page 35 -(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) LANSWER: 1'.~ 01 l L(1. 00). ---a--- REFERENCE l 1 PLANT SPECIFIC REACTOR-THEORY & OPERATIONAL' ASPECTS (PSRTOA),. FIG 2.4-8 192008K104 192008K105-' ..(KA's). ' ANSWER-1.02- -(1.00)

---

a ----

. REFERENCE = PSRTOA, pg.3.2-17 '192006K106 192005K114 ..(KA's) -ANSWER' 1.03 (1.00) ---c--- REFERENCE

PSRTOA, : pg.'2. 3-15

<192008K123 ..(KA's) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

c (1,' REACTOR ~ PRINCIPLES'(7%) THERMODYNAMICS Page.36 (7%)~AND COMPONENTS (11%) (FUNDI.MENTALS EXAM) L ANSWER 1 1.04 ( 2..' 0 0, LApplicable, equations: CR1 * (1-Keff1) = CR2 * (1-Keff2) -(0;50) l Rho = (Keff-1)/Keff (0.50) METHOD:A By, rearrangement, Keffl = 1/ (1-rhol) ,Since.Rhol = .02500, Keffl = 1/(1-[.025])'=.9756 (+/-J.001) ' ( 0. 2 5) ~ And since CR1/CR2 = - (1-Keff2)/ (1-Keff1) g 135/405 ='1/3 = (1-Keff2)/1.97F6) Keff2 =.9918 (+/-.001). (0.25)- TSUBMETHOD A1 -, Since Rho 2 =L1-3/Keff2 MicM! '=.1-(1/.9918) = .0083 or -0.83%. delta-K/K (+/ .05%) (0.25)- R: activity added = Rho 2 - Rhol Rocctivity added = .83 -(-2.50) = 1.67% delta-K/K (+/ .05%) (0.25) 'SUBMETHOD A2 .Since reactivity added a delta-rho = (Keff2-Keff1)/Keff2'

• Keffi (0.25)-

Rocctivity added = (.9918.-.9756)/.9918 *.9756 =. 0162/.9676

Recctivity added =.0167 or 1.67% delta-K/K (+/

.05%) (0.25) METHOD B Combining the applicable' equations, CR2'* rho 2/(1-rho 2) = CR1'

• rhol/ (1-rhol)

(0.50% or 405

• rho 2 * (1-rhol) = 135
• rhol * (1-rho 2)

'Since rhol = .02S, rho 2 = .0082 or -0.82% de'ta-K/K (+/-.05%) (0.25) Ranctivity added = Rho 2 - Rhol R activity added = .82 -(-2.50) = 1.68% delta-K/K (+/ .05%) (0.25) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) LL_

.c k 11;- REACTOR PRINCIPLES;(7%) THERMODYNAMICS Page 37 '(7%)-AND COMPONENTS-(11%) (FUNDAMENTALS EXAM) y " REFERENCE-l-PSRTOA pg 2.3-2,3; [1 '192008K104. ...(KA's)- i. ' ANSWER 1.05 . (1.00)- ~ a'---- 6- : REFERENCE PSRTOA pg-3.3-13 ..(KA's) 192004K110 .. ANSWER. .1. 0 6. (1.00) L

---

d ----

-REFERENCE .PSRTOA, pg 3.2-8. 192006K106 ..(KA's) [ ANSWER.: .. 07' (1.00) [ .----a---- -REFERENCE .PSRTOA, pg 4.1-9,10 192002K114 ..(KA's) ANSWER 1.08 (1.00) y ---- (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) J:-___---_________

q g- ,q y .; l -l 1 1 REACTOR-PRINCIPLES (7%) THERMODYNAMICS. Page 381 .i c 3 3..

(7%) AND COMPONENTS'(11%) (FUNDAMENTALS" EXAM)-

~ s

R5FERENCE tW3SES LP L310-031-52fpg_7,8 193008K105'

..(KA's) 1 { .s ' ANSWER 1.09: (1.00);

---

c ----

' REFERENCE t' ~ W3SES LP ZMSC-703-00,.pg 6 193010K105 ..(KA's) h (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l l. L._-___ _____________x_____---_-__

I, -1? REACTOR PRINCIPLES (7%) THERMODYNAMICS ' Page 39-(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) ANSWER- '1.10 (1.50) , Applicable: equation: Q = b cp delta-T (in NC and forced. circulation)_ (0.50) .Thar'efore,Lat 100% 100 = 100

• cp
• 60 or cp =-

100 (0.25). 100

• 60

.While at 3%, 3 = m

• cp
• 30 or cp =

3 (0.25) m

• 30 Since cp is equal before and.after the event, 3

100 (0.25) u m

• 30 100
• 60 6% (+/

.5%) (0.25). Thsrefore, m= 3 100

• 60

= 30 100 Alternate calculation method:

Qnc.

-(M

• cp
• delta-T)nc Qrtp' (M
• cp'* delta-T)rtp Qnc * (M
• delta-T)rtp Mnc.

=- Qrtp * (delta-T)nc 3

• 100
• 60

= 6% Mnt = 100

• 30 REFERENCE W3SES LP L110-704-01, pg 3 193008K122

..(KA's) ANSWER 1.11 (1.00)

---

d----

I l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) ( ) I

}. 1- ' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 40-(7%)-AND COMPONENTS (11%) (FUNDAMENTALS EXAM) REFERENCE CE Steam Tables 193008K115 193001K101 193003V125 ..(KA's) ANSWER 1.12 (1.00) ____ c ____ REFERENCE Stram Tables TMI Accident Records 193003K125 ..(KA's) ANSWER 1.13 (1.00)

---

c ----

REFERENCE W3SES LP L310-031-22, PG 11 191s04K115 191004K106 ..(KA's) ANSWER 1.14 (1.50) ' Applicable equation: Q = UA(Tavg - Tstm) (0.50) (Tavg2 - Tstm) Since Q and U remain constant, A1 * (Tavg1 - Tstm) = A2 * (0.25) 4 And A2 = (1.00 -.04)

• A1 = 0.96
• A1 (0.25) j From Steam Tables; Tstm = Tsat for 900 psia = 532 F (+/-.5 F)

(0.25) (Tcyg2 - 532) (delta-T2 = 52.1 F) A1 * (582 - 532) = 0.96Al * .T;vg2 = 584.1 F (+/ .6 F) (0.25) i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) I i

1 !ik ? REACTOR' PRINCIPLES ~ ~ ( 7 %) " THERMODYNAMICS Page.41-

(7%) AND COMPONENTS-(11%) (FUNDAMENTALS' EXAM)-

" REFERENCE ':W3SES LP:L110-704-01 pg.5 191006K113- ..(KA's) d; ANSWER.. -1.15 (1.00)

____ c ____

' REFERENCE RTD CircuiteAnalysis-191002K114 ..(KA's)- fANSWER '1.16 (1.00)'

--- a ----

REFERENCE o

W3SF.S LP.ZIC-705-00, pg 5 191002K109

..(KA's)

ANSWER.

1.' 17 ' (1.00) ---d--- -REFERENCE -W3SES LP ZLTV-200-00'pg 25 191001K106 ..(KA's) ANSWER. 1.18 (1.00) _.c (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) w _____

1. REACTOR' PRINCIPLES ~ (7%) ? TH?rMODYNAMICS Page 42' -(7%)-AND-COMPONENTS (11%) ;T17NDAMENTALS EXAM)- REFERENCE CVCS SD pg'.14,15 19't007K108 ..(KA's) ANSWER 1.19 '(1.00) .____c____

REFERENCE-Simulator malfunctions RCO3, RC04 191005K101

..(KA's) ANSWER'

1. 2 0..

' (1. 0 0) -

---

c----

'. REFERENCE - W3SES LP ZTYH'-803-00, pg 16 191004K112- ..(KA's)- ANSWER 1.21 . (1. 00) ---b--- REFERENCE-1 ' O P-10-0 01', pg 72 j 191008K108 ..(KA's) l -ANSWER 1.22 (3.00) .----a---- (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) i 1

r R 3'. 3 1< REACTOR PRINCIPLES (7%)-THERMODYNAMICS. .Page 43 -(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM). [ REFERENCE W3SES'LP ZTYH-803-00, pg 16 191004K107- ...(KA's) '. ANSWER 1.23 (1.00) ---d--- 'CREFERENCE PSRTOA, pg 3.3 - REACTOR OPER STUDY. GUIDE,

• PAR't. 2, PG.3 004000A404

..(KA's) l

(***** END OF CATEGORY 1 *****) lu-

u-2.' EMERGENCY AND' ABNORMAL' PLANT EVOLUTIONS' Pagef44.

(27%)

<? ANSWER-2.01-(2.50) a;-- 5.15 L' b. Deleted c.

feed' flow, steam flow (may be transposed)'

_d.. 'O.95,:1720 .(0.50 each) REFERENCE LP, Selected Off-Normals'at-Power,-LO-A.5 OP-901-013, p. 3 '000024G011 ..(KA's) LANSWERL 2.02_ (1.50)- -c. Facilitate depressurization '(0.75) b. Prevent excessive RCS cooling (0.75) REFERENCE"

LP, Off-Normal'~ Procedure - Evacuation of Control Room and Subsequent Plant Shutdown, -ID-4 ELP, Off-Normal Procedure - Evacuation of Control Room and Subsequent Plant Shutdown, p.

8, 9 000068K318 ..(KA's) ' ANSWER 2.03 (1.50) i o. EDG B is needed to supply power to Safety' Train B controls which are j used because B train cables run outside cable ~ spreading room:(which .j could be the source of or endangered by fire that has caused the CR I evacuation). (0.75). b. CCWP B is needed to provide cooling water'for EDG B. (0.75) REFERENCE ll LP ZPPO-803-01, pg 6 j '000068G007 ..(KA's) 1 h (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 4 l f I L___==-_____

t '2. EMERGENCY AND' ABNORMAL' PLANT' EVOLUTIONS Page 45 p _(27%)- j i l l ANSWER 2.04 .(0.00) ,' Deleted' -REFERENCE 000025G010 000025G011 090057A219 ..(KA's) .. ANSWER- .2.05-(2.00) 'a. Ensures injection water reaches core (by ensuring decay heat / core steam flow;are low enough so that injection water is not entrained out 'through-break ); (1.0)

b.

. Ensures boron-does not precipitate / plate out in the core. (1.0) REFERENCE OP-902-002,-Pg. 4 LP,fSI and SDC, p. 32, 33 000011K312 ..(KA's) ANSWER 2.06 (2.50) c.- '1. All CEAs fully inserted )' 2. Reactor power dropping 3' SUR negative (0.25 each)

b. -

1. Governor valves closed 12. . Throttle valves closed 3. Reheat valves closed 4. Intercept. valves closed -(0.25 each) c.

1.

' Exciter field breaker tripped .R 2. . Generator breaker "A" tripped 3. Generator breaker "B" tripped (0.25 each) j REFERENCE I } OP-902-000, p. 2 LP,- Intro and Emergency Entry Procedure, LO-7 000007A107 000007A106 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) I j )

I f ( 2d EMERGENCY AND-ABNORMAL PLANT EVOLUTIONS-Page.46 (27%)- '.AN'SWER- ' 2.07 (1.00) ____c____ ~ LREFERENCE LOP-901-010, p.;11 000015A210 ..(KA8s) ' ANSWER" ' 2.08-(1.50). ^ I' ' .T-hot 2. T-cold-3.; LCore-temperature 4. S/G level 5..- . Main feedwater flow 6.- Emergencycfeedwater flow 7. LS/G pressure (any 6 @ 0.25 each) REFERENCE. t. -902-005, p. 8 LP. Degraded, Electrical'Dist. Recovery Proc., LO-D.3

000055A202

..(KA's) ' ANSWER 2.09 (1.50) 1.1 'An event cannot be diagnosed (0.50) 2.- . Multiple events are occurring (0.50) 3. An. event is in progress for which the appropriate Optimal Recovery = Proceduc'es is not maintaining safety function criteria. (0.50) REFERENCE - OP-902-008, p. 1 LP,-Safety Function Recovery Procedure, LO-1 000058G012 000058G011 ..(KA's) l' u l _(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) Iw_

C

12. ' EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS Page 47

. (27%)- g " ANSWER. 2.10 .(1.00) ,;----c---- REFERENCE- [Techn' cal' Specifications,-Definitions i

Tschnical-Specifications, LCO 3.5.2-

~ 000037G008i ..(KA's). ANSWER 2.11-(1.00) 1-1 gpm total-SGTL. (0.5) l2. 720 gpd (0.5 gpm) SGTL in any SG '( 0. 5 ) -REFERENCE Technical Specifications, Definitions .Tsca;nical-Specifications,'LCO 3.5.2 -000037G003 ..(KA's)' ' ANSWER. 2.12 ~(1.00) 'a. 3 b.- 1 c. 5 (1.0 for. correct sequence, .25 for each out of sequence) 'd. 2 c. 4- ' REFERENCE LP, Secondary System Off-Normals, LO-1.g ' OP-9 01 -03 6, p. 6 000051G011 ..('KA's) ' ANSWER 2.13 (1.00) ____c____ (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l l l a-~~_-__-_-____- J

2 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 48 (27%) REFERENCE Technical Specifications, Definitions '000003K107 ..(KA's) ANSWER 2.14 (0.75) To maximize purification flow. (0.75) . REFERENCE OP-901-021, p. 7 000076K305 ..(KA's) ANSWER 2.15 (1.50) a. 1. Condensate bypass to condenser (short-cycle recirc) valves open 2. Heater drains bypass to condenser (alternate drain) valves open 3. Condensate pump recirc valves open 4. Heater drain pump recirc valves open b. 65 psig (+/- 5psig) (0.50) REFERENCE OP-901-038, p. 7, 8 LP, Secondary System Off-Normals, LO-1.b 000065A206 000065K303 ..(KA's) ANSWER 2.16 (0.75) Main feedwater control valves fail as is (without instrument air). (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) )

JS$ ~ ( t 2< EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Page:14 9; -(27%)- t riREFERENCE

OP-901-038, p. 7,f8 LP,; Secondary System Off-Normals,-LO-1.b-T000054 G007 ':-

..(KA's) ' ANSWER 3,17 (1.00)

----c----

REFERENCE-OP-902-007, p. 5 000038A203

..(KA's) ANSWER 2.18 (1.50) 1.; Manually trip the. reactor. (0.50) ~ 2.L Emergency borate. (0.50) .3. Open SST.A32'and SST B32. breakers for 5 seconds and reclose._(0.50). - REFERENCE GP-902-000, p. 2 cLP, Introduction'and Emergency _ Entry Procedure, LO-8 000029G010 ..(KA's) ANSWER 2.19 (1.00)

---

a----

1 REFERENCE 'OP-901-002, p. 10 RCS Flow Diagram - LOU-1564, G-172 000027A215 ..(KA's) ) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) ) = - _ .j

7 -r r p m, gr.:. p:: s ,g. ][/.:. ( g, c,. 6 i2 ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS: Page.150. ,'(27%)' / L-ANSWER-. 2.20' (1.00):

(Q) < 23.

(b)- fuel. (O.5 each) 1_. REFERENCE nTxchnical-specifications,.Lco:3.9.10.2 000036G003 ..(KA's) L., p d t r" (***** END OF CATEGORY 2 *****) _-_--_-.--__O

r L 4 c, .,[' 3.= LFLANT'SYSTEMSl(38%) AND PLANT-WIDE GENERIC Page 51 RESPONSIBILITIES (10%) 1) l ! JANSWER: 3.01L (2.00) 12 'High' discharge temperature (120 F) (any 4 at.0.50 each) 2.. Low. suction pressure (1.5 psig)-

3.'

'cil/ gas. leak detector activated (20 psig) (1st or12nd stage). 4.. Iow oil level. (0 inches) 5. Undervoltage 6.' Overcurrent . REFERENCE 'LP-ZGWM-700-00, LO-6 & pg 8 071000A420 ..(KA's) ' ANSWER 3.02 (2.00) a. 1. Waste condensate tank A outlet valve not open (Any 3, 0.50 each) 2. Suction cross-connect (WCT outlet.X-connect)'not-open . 3.; Low level in waste condensate tank ~A ~4. Undervoltage .5. Overcurrent 'b. Liquid waste discharge valves (LWM-441/442) close REFERENCE 1 + LP ZLWM-700-00, LO-4,5 & pg 13,14 068000A404 ..(KA's) ANSWER 3.03 (2.00) 1. 3 Bus to 2 Bus tie breaker open ( > 5 sec) 2. Undervoltage cnr degraded voltage on 3 Bus (0.50 each) .3.- No lockout / trip signal 4. EDG at rated conditions (speed / voltage) REFERENCE LP ZEDG-7000-00, LO-9 & pg 56 - 064000A302 ..(KA's) i 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) )

i l 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 52 ) RESPONSIBILITIES (10%) i 1 ANSWER 3.04 (1.50) 1. SIAS start (Any 3, 0.50 each) 2. 3 Bus UV/DV start 3. Generator (phase) differential (87/DG) trip 4. Generator overspeed 5. Going to Stop on SIAS without IDSP (i. e., with bus tie brkr closed)

6. -

Both EDG output brkr and bus tie brkr closed (places DG in test mode) 7. Normal test mode shutdown (for cooldown cycle) REFERENCE LP ZEDG-700000, LO-6 and pg 30 064000K402 ..(KA's) ANSWER 3.05 (1.00) 1. 'To prevent LPSI pump runout (when no RCS pressure) (0.50) 2. To equalize flow in the injection lines (or to prevent all flow going to a loop / pipe with break) (0.50) REFERENCE LP ZSI-700-00 LO-15 & pg 16 006000A202 ..(KA's) ANSWER 3.06 (1.50) a. Goes to minimum (3900 rpm) (0.50 each) b. Goes to/ Remains at speed demanded by #1 FWCS Goes to/ Remains at speed demanded by B MFWP manual contoller c. REFERENCE LP ZFWC-700-00, pg 11,12,27 059000K405 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ____-________--_.-_________D

L 3-PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 53 RESPONSIBILITIES (10%) ] ANSWER 3.07 (1.50) 'n,. 3. b. 4. (0.5 each) c. 2. REFERENCE LP, Plant Protection System, p. 8 LP, Plant Protection System, LO-1 012000K402 ..(KA's) ANSWER 3.08 (1.00) ____c____ REFERENCE SD, SBCS, p. 7 041020K603 ..(KA's) ANSWER 3.09 (1.00)

---

a----

REFERENCE SD, SBCS, p. 24 001000K407 ..(KA's) ANSWER 3.10 (1.00)

---

c----

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ____-__-_-_-_--_J

Q,- R:pr u s r 3. ' PLANT SYSTEMS 1(38%)'.AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (10%) REFERENCE'- cLP,aRCP, p.-10, 11' 10P-1-002, p. 5,.-10 003000A201 ..(KA's). . ANSWER 3.11. - (i. 00)-

---

a---

REFERENCE .LP,-CPC;and-CEAC, p. 25, 32-LPe CPC1and CEAC, LO-3 '012000K607 ..(KA's).

ANSWER-3.'12 (2.00) a.

2.

b.

'3. c., 4. (0.5.each) 'd.- 1. REFERENCE LP, Excore NIS, p. 6 - 10 LP, Excore NIS, LO-2 015000K601- ...(KA's) ' ANSWER. 3.13 (2.00)' a.

1. '

Both-backup charging pumps start (0.5 each) 2. Letdown throttle valves close to minimum 3.' 'All pressurizer heaters deenergize (tripped or blocked) .b. Pressurizer heaters deenergize. (0.5) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) fc a

!N, I 'q- !; 39 -PLANT ~ SYSTEMS (38%) ' AND PrANT-WIDE GENERIC Page 55 RESPONSIBILITIES (10%) iz REFERENCE' .LP, Pressurizer. Level and Pressure Control, figure 48-LP, Pressurizer Leveljand Pressure Control, LO-4 L 011000A211 ..(KA's)-

. ' ANSWER.

3.14 (1.50)

1.

Mast bumper contact.- 2. ' Grapple.in or below Upper Grapple Operate Zone (UGOZ) '3. 'Holst operating. 4. Spreader on' fuel mast not retracted. E '5. Aligner on CEA mast'not' retracted. (any three (3) at 0.5 each) 6. Fuel hoist in-" fuel only" region with fuel on. '7.. CEA hoist in "CEA only" region with CEA on. t - 18. OneLhoist'not at Up Limit unless.in Upender Area. 9. ~In1upender region with upender not vertical. REFERENCE LLP, Fuel. Handling and. Storage Equipment, p. 15 LP,' Fuel Handling and Storage Equipment, LO-2.a 034000K402 ..(KA's)- L ' ANSWER 3.15 (1.50). l' " Remember" the last valid penalty' factors received from the failed' 'CEAc.(0.5) 2. Compare these factors with the penalty factors received from the operable CEAC.(0.5) 3.

Select the. largest of the compared penalty factors for use. (0,5)

REFERENCE- 'LP, CPC, p. 18 ' LP, CPC, LO-5 0?.2000K607 ..(KA's) 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) --__-______._______Q

....[%_. W n h @); Y $l W.:,.y v\\[ x, i: 3. - PLANT' SYSTEMS (38%)iAND PLANT-WIDE' GENERIC' .Page 56) RESPONSIBILITIES-(10%)- j L

LANSWER, 3.16-l(2.50):

e 's.-

4.

- b.' 11'. : c.. .5.3 1 , d. '. 3.: o, 8. .Gj.REFEREt:CT, 3. j LP,, CEDMCS. p. 19 - 21 L .LP,[CEDMCS, LO-E 001000K401- ...- ( KA ' s ). i ANSWER. 3.17 (1.00) '1. RCPs ~ ( O '. 5 ). 52. '.CEDM coolers ' (0.5)~ REFERENCE LP,2CCW, p. 4 , : LP, '. CCW, ' LO-6. a - ,008000K102 ..(KA's) o jANSWER 3.18' (l'. 50) .a.. Depress.the (Emergency Manual Actuate) pushbutton'on the~ Master Remote-Control-! Panel (0.75) ii. Remove ~lockpin and turn lever on top of the selected cylinder. (0.75) -REFERENCE .LP, Fire Protection and Detection, p. 22 .LP, Fire Protection and' Detection, LO-7 ls ~ ..(KA's) l ~086000A406 g l. (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l L'f _N-.',.-.-.-_______.__._.. __3 )

a 36 --PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC Page 57 RESPONSIBILITIES (10%) ANSWER 3.19 (1.50) a,- Ensures adequate heat transfer-(prevents thermal shock) across the regenerative. heat exchanger.. (0.5) b.- -Based on ma*ximum charging pump capacity minus RCP CBO flow. (0.5) c.- Slows the speed of'the letdown. flow control valve stroke (or prevents-steam flashing / water-. hammer instability in letdown' system). (0.5) l REFERENCE LP, Pressurizer Level and Pressure Control, p. 10, 17 LP, Pressurizer Level and' Pressure Control, LO-2, 3 011000K604 004020A101 004000G010 ..(KA's) l l ANSWER 3.20 (1.50) RWSP outlet valves (SI-106A/B) HPSI/LPSI pumps miniflow isolation valves (SI-120A/B) ~ HPSI/LPSI; pumps miniflow isolation backup valves (SI-121A/B) L (Valve numbers acceptable, but-not required.) (0.25 each) l-REFERENCE' LP, Containment Spray, p. 29 'LP, Containment Spray, LO-5 006020K401 ..(KA's) ANSWER 3.21 (1.50) 1. 86G1 or 86G2 signal 2. Synch. check (0.5 each) 3. Both generator OCBs open REFERENCE-SD ZMT-700-00, p. 29 & LO-4 062000K403 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****.) 1U . _ _ _ - _ _ _ _ _ _ _ _ ___________-_ _ a}}