ML20005G496

Exam Rept 50-254/OL-89-04 on 891113-17.Exam Results:All Candidates Passed Operating Exam.One Senior Reactor Operator & Five Reactor Operators Passed Written Exam.One Reactor Operator Failed Exam

ML20005G496
Person / Time
Site:	Quad Cities
Issue date:	01/04/1990
From:	Bielby M, Draper D, Jordan M, Muth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20005G495	List: ML20005G494 ML20005G496
References
50-254-OL-89-04, 50-254-OL-89-4, NUDOCS 9001190241
Download: ML20005G496 (16)

Text

{{#Wiki_filter:-.. gi".. m.,. i 3 i) ..U.S. NUCLEAR REGULATORY.C0FNISSION-REGION III-l s l g ; Report No. 50-254/0L-89-04 . Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 g "r Licensee:- Commonwealth Edison Company Post Office Box 167-Chicago, IL' 60690 Facility Name: Quad Cities Kuclear. Power Station ] P Examination Administered At: Quad' Cities Nuclear Power Station Cordova, Illinois . Examination Conducted: November 13-17, 1989 Examiners:?- - //4/fo i M. E. Bielby, Chiqf Examiner D~ater f //f/fo ~J. Muth /- Date hh* J 'D. Draper (/ Date ' 'NpprovedByi. ( Y)7d Michelfgordan, Operator Date Licensihg, Section No. 1 ^ ' Examination Summary - Examination administered on November 13-17, 1989 Report No. 50-254/0L-89-04: Written.and Operating Examinations were administered to six Reactor Operator (RO) candidates and one Senior Reactor Operator (SRO) candidate. L Results: All-candidates successfully passed the operating examinations. One l - SRO and'five R0s passed the written examination. Overall, one R0 failed the b examination. y l l L PC y b d w-v$ we--- -Oq t -e g w W**

V. X ) REPORT DETAILS j 1. Examiners M. Bielby, Chief'Examinerr RIII NRC J. Muth, Battelle Pacific Northwest Laboratories (PNL) D. Draper, PNL x J. Hammer.(under instruction). RIII NRC G 2. Exit Meeting An exit meeting was conducted on November 17, 1989. The following i personnel attended this exit meeting: l Facility Representatives 'R. Bax, Station Manager, Quad Cities J..Sirvoy,. Services Director J. Wethington, Quality Assurance Superintendent-i J, Swales, Operations Assistant Superintendent l Ji Neal,-Training Supervisor-- T. Barber, Regulatory Assurance .j F T. Schares, Training Instructor 1 NRC Representative .p-J l :. R. Higgins, Senior Resident Inspector-i M. Bielby, Chief Examiner J.: Hammer, Examiner u 1 -The.following: items were discussed during the exit meeting: L a. Security. Radiation Protection and Operations Personnel were J cooperative in assuring there were no delays associated with badging; dosimetry and accessing the station during administration .i 3 of the examinations. L b. The following training strengths were identified during the examinations: (1) Candidates immediately referred to appropriate procedures to confirm Immediate Actions and review Subsequent Actions, i i (2) Candidates recognized entry conditions for Emergency Procedures (QGAs) and were familiar with procedural steps of the j ficwcharts. l, L 2

~ y g q.. .c + -7 f ATTACHMENT I a ~ NRC RESPONSE TO FACILITY COMMENTS ...ON;THE R0/SRO WRITTEN EXAMINATIONS ADMINISTERED NOVEMBER 13, 1989.. WHICH ONE'(1) of the.following equipment will be affected -QUESTION' 2.12: _by a loss of Instrument Air? ~ a.. Feedwater regulating low flow' control valve b. Reactor Water Cleanup filter demineralizer

c.

0ffgas system pressure control valves d.' LStandby Liquid Control system '^ ANSWER: 'C.-

COMMENT:-

This. question' does' not' give enough information in order to make'a' selection.

A loss of-Instrument Air will affect all of the systems or components listed (all of the answers are correct). The most direct effect.will be seen .in the Feedwater Regulating low flow control valve and the Offgas system pressureLcontrol valves. Therefore, both answers a.'and c. are equally the most correct' answers for this question. y Referencei Q0A 600-1, Rev. 8 'Q0A 4700-6, Rev. 1 LIC-600, Rev. 4

RESPONSE

Comment accepted. Question deleted. QUESTIONS 2.14 5.16a. Unit I is operating at 100% core power. A failure of the master recirculation flow controller causes both recirculation pumps to runback to minimum speed-(less than 44 million 1b/hr). No reactor protection trip occurs and all attempts to return-the recirculation system to normal are ineffective. With respect to Q0A-400-2, Rev. 2, " Core Instabilities." WHAT TWO (2) conditions would require the operator to scram the plant IMMEDIATELY? ANSWER: 1. APRM or LPRM peak to Peak oscillation > 10% 2. Periodic LPRM upscale or downscale alarms. COMMENT: The two conditions stated as the answer to this question actually constitute four conditions. These conditions are + 4 o, t

y3 )[ ,;( a qe ; -s ! stated in one sentence in Q0A 400-2, Rev. 2, step C.2, and-m s y consist of:the following:. il. APRM peak-to peak oscillations' of greater than 10% 2., LPRM peak-to peak oscill.ations of greater than~10% j

3.

Periodic LPRM upscale alarms .e ' 4. -Periodic LPRM downscale alaras Any:one of these four would-require the operator to manually scram the reactor. Any two of these conditions stated should be counted as. E full credit. ,jp

RESPONSE

Comment accepted. Answer Key modified. w i i 2 QUESTION 2.20. During a-startup with reactor pressure at 550 psig and j increasing, the operating control rod drive pump-trips. . HICH ONE (1).of:the following is an immediate action W

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.per.Q0A-300-1, " Control Rod Drive. Pump Failure?" a. . verify correct valve lineup for the standby-pump. b. start the standby CRD pump c.- -verify recirculation system-in individual manual' control. ' d. . scram the reactor ANSWER:- .d. 1 COMMENT: A new procedureirevision has come out for Q0A 300-1, which may affect this question. i

Reference:

Q0A 300-1,.Rev. 9 ' RESPONSE: Comment-not accepted. Major. emphasis is still the SCRAM requirement. In addition Rev. 9 came out in April, 1989 and the pre-exam review accepted question as written.

QUESTION 3.17b.,c.

MATCH the RHR System valves listed in Column B to the interlock restrictions described in Column A. Each valve may be used more than once or not all. Each interlock in Column A may have more than one valve associated with it. - A drawing of the "B" RHR loop is attached for reference. lw 5 )

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~ v m 1 El . Column A-Column B-L (Interlocks)- (Valves)_ 1 h 'a. . Interlocked closed if-1.- M0-1001-1, E reactor pressure ~is above Suppression _ Pool .,T 100 psig ^ Suction-ll b. Interlocked closed on a

2.,

M0-1001-43i. Shutdown U ' Group 2 isolation in any Cooling Suction g, mode 1 3. M0-1001-16; Hx Bypass. l c. I~nterlocked closed on a 4 p LPCI initiation but can 4. M0-1001-18,- Minimum-L be opened anytime the' Flow ~

p Containment Cooling h

Permissive Switch is 5.' M0-1001-19,~ RHR' g "0N" -Loop d.- Interlocked open on a.. 6. M0-1001-23, Drywell ' LPCI initiation but can Spray be throttled after a ' .30,second TD

7. -

MO-1001-28,;LPCI 4 Injection Out e, -Interlocked open on a 8. M0-1001-29, LPCI .LPCI initiation but can ' Injection be throttled after a five-minute TD 9. M0-1001-37, Suppression Pool Cooling 10. M0-1001-37, Suppression Pool Spray 11. M0-1001-58, Head . Spray FCV i 12. M0-1001-60, Head Spray Isolation -ANSWER:- a. 12 b. 12 c. 9 i d. 3 e. 7 -COMMENT: Part-b. of this question asks for RHR valves that will close on a Group 2 isolation in a_ny mode. This can be interpreted two different ways. It may be interpreted as asking for valves that would close in any of a number of conditions, 6 1

4-jf : m g %n. hW \\ with-the actual valves that do close varying from condition to condition.* It.could also be. interpreted as those. valves that will always go closed on a Group 2: isolation, regardless of conditions.- Based on this ambiguity, item- ~ ,No. 8 should not be counted as incorrect, since the si M0-1001-29 valve will close on a Group 2 isolation, if the' RHR: system is in:the-Shutdown Cooling mode of operation. 4 Part c. of this question suffers from the same ambiguity as part bi by the use of-the work anytime. Based on this, items No, 6-and No. 10 should not be counted as incorrect, 'as the use of the Containment Cooling Permissive switch'in the "0N" position will enable the use of these valves with a LPCI initiation signal present. Ws

Reference:

LIC 1000, Rev. 3, p. 16-20 b = RESPONSE:: Comment: accepted. No pre exam comment. Answer Key modified. + QUESTION 3.18' 'Concerning the Rod Worth Minimizer System: a. 'WHICH ONE (1) of the following conditions describes the MINIMUM flowrate at which-the Rod Worth Minimizer System could by BYPASSE0? 1. steam flow OR feed flow greater than 20% 2. steam flow AND feed flow greater than 20% 3. steam flow OR feed flow greater than 30% }M

4. -

steam flow AND feed flow greater than 30% 'b. WHICH'ONE-(1) of the'following responses will NOT occur if the RWM fails? 1. rod blocks-will'be applied regardless of reactor power 2. rod blocks will be applied if the system is UNBYPASSED 3. the system will fail to apply needed rod blocks 4. .the system will auto transfer to the backup computer ANSWER: a. 2 b. 4 COMMENT: Part b. of this question has some very confusing distractors. In looking at the choices presented, and trying to determine what will NOT occur if the RWM fails, item 1 or 2 cannot be true if item 3 is true. The reverse 7

" l]7, lll J-)y jk~. + also h' olds - if-item'l or item 2 is true,- then item 3 must be-false. Item 4~is independent of items 1, 2, or 3.- By. process of elimination, this-'would mean that there are at least-2 correct answers to this question. This question 4 should be deleted. r .[,

Reference:

None-q':

RESPONSE

Comment not. accepted.: Using the True/ False logic could ^'also indicate that two of the distractors were false. In F: ' addition,:the selections'are to be considered independently. There were no references-provided and-the question was previously. reworded per pre-exam comment. QUESTION'3.20b.

MATCH the power supplies listed in Column B with the loads-in Column:A for which they are the primary feed.

Each bus may be used more than once or not at all. O Column A Column B a. Core Spray Pump 1B 1. Bus 11 b. U-l' Diesel Generator 2, Bus 12 Cooling Water Pump 3. Bus 13 c. Reactor Feed Pump 1A 4. Bus 13-1 d. Recirc MG Set 1B 5. Bus 14 5-e. RHR Pump 10 L 6. Bus 14-1 f. RHR. Service Water Pump.1D 7. Bus 15 8. Bus 16 9. Bus 17 10. Bus 18 11. Bas 19 ANSWER: a. 6 b. 10 c. I d. 2 e. 6 f. 5 8

&ML t ...s ry c.. ..o d Y e y'y COMMENT! 'The: answer for this item should be 11 (vs. 10). IThe power-l supply to_.the U-1 Diesel Generator Cooling Water Pump is Bus 19..

Reference:

Q0A 6700-5, Rev.' 6

RESPONSE

Comment' accepted.- No pre-exam comment. 1 Answer Key modified. 1- -QUESTION 3.24a MATCH the correct refueiing interlock from Column B with and 6.01a . the situation in Column A to which it applies. Items in Column A may have more than one answer. Interlocks in Column B may be used more_than once or not at all. t Column A Column B (Situation) -(Refueling lnterlock) - a.

the refuel platform is 1.

rod block a over the reactor and a . control rod is withdrawn 2. prevent movement of and a load is on the bridge towards grapple reactor b. a control rod is withdrawn 3. stop operation of and the platform is on fuel hoist switch refuel No. 1 and a fuel assembly is on the 4. stops upward movement hoist-of the overhead crane only c. 'a radiation monitor reading of 16 mR/hr (high rad alarm) .on the refuel floor d. the' Bridge is located outside . of the zone computer limits , ANSWER: a. 1, 3 b. 2 c. 4-COMMENT: Part a. of this question specifies that items No. 1 and No. 3 are the correct answers for'this situation.

7. tem flo. 2 shculd not be counted as incorrect.

The circuitry for this interlock would actuate in this situation, even though its effects would not be seen under the conditions given. x 9

Sy y ;. m. 6"

q\\.

p.. y. b,

Reference:

Technical Specifications p '3.10.A.2.b if b

RESPONSE

_ Comment accepted. No pre-exam-comment. Answer Key modified. p LQUESTION 3.25 .During_a core trasverse by'the TIP' system with the TIP in the core conditions indicating a Loss of Coolant Accident (LOCA)' occur. WHICH ONE (1) of the fol^ lowing statements . describes the response of the TIP system? a.. It continues'its sequerce for the present core position and then transfers to manual, reverses, e and withdrawsLinto the' shield. V i b. -The ball valve closes regardless of the position of _p s .the probe,; shearing the probe-and isolating the TIP system,- c. The TIP system transfer to manual, reverse, and withdraws into the shield. l d. The TIP system transfers to manual, reverses to fast speed, and withdraws into the shield. ANSWER: c. 1 COMMENT: None of the available selections for this questions is correct, per the reference indicated (Lesson Plan LIC-0700-6, Rev. 2). None of the available choices reflect ectual plant operation. The TIPS do not automatically switch to MANUAL j s operation on a Group 2 isolation signal. This question should be deleted. 4 4

Reference:

LIC 0700-6, Rev. 2, P. 46-48 y

RESPONSE

Comment accepted, question deleted. No pre-exam comment. Answer Key modified. QUESTION 3.34 FILL'IN THE BLANKS to identify the MINIMUM shift staffing requirements per Technical Specifications for each condition below, Unit 1 at Cold Shutdown, Unit 2 at Hot Shutdown Operator License (a) Non-Licensed (b) l 10

4, +

i p y y ( L Both Unit 1-and Unit 2 at Cold Shutdown-p P Operator License (c) [: Non-Licensed (d)- L .) ~[

ANSWER:

(a) 3

.(b); 3

(c) 2 o

(d)1'3 J

)

KA 294001A103 ' COMMENT:. This question; or variations'thereof,-has been used a 1 number of times in the past. The K/A reference for this question is'- 294001A103,'which states: i A1.03 Ability to' locate and use procedures and station -directives related to shift staffing and activities. (Emphasis added) 'This is rated at 2.7 for R0s and 3.7 for SR0s. This indicates that this should be an open reference question. As the reference (Tech Spec 6.1) was not provided to the candidates, this question should be deleted.

Reference:

NUREG 1123, P. 2-2

RESPONSE

Comment accepted, question deleted. Answer Key modified. t QUESTION 5.08 During.the course of a startup with Rx pressure at 300 psia, the R0 reports to you as SR0 that HPCI ~ surveillance has caused the suppression pool temperature to reach 110'F. STATE the TWO (2) immediate actions in l accordance with Q0A-1600-3, "High Suppression Pool Temperature?" ANSWER: 1. Initiate suppression pool cooling 2. Enter 0GA-200-1, " Suppression Pool Temp Control" COMMENT: This procedure would be entered upon a TORUS WATER HIGH TEMP -alarm (90X-4-G-17), which occurs at a torus temperature of 90 F. That the conditions state that the i torus temperature is 110 F would indicate that the steps in this procedure would have been executed long ago. 11

e Em X [ g4 v~' w g P; Technical Specification 3.7.A.1.c.3) requires that the-reactor be scrammed from any operating condition if the temperature of the torus reaches 110"F. This-is also one of.the steps in QGA 200-1, which is specified as one of ~the-immediate actions (this is also one of the Subsequent -Actions of Q0A~1600-3). An answer of " scram the reactor".- 1 .or words to that effect, should be accepted for 0.75 ) points of credit. i

Reference:

Q0A 900-4-G, Rev.: 11. P. 6 Q0A 1600-3, Rev. 4 QGA 200-1, Rev. 3 Technical Specifications 3.7.A.1.c.3 RESPONSE:- Comment accepted. The pre-exam comments wanted " scram i the reactor" deleted because it was a subsequent action. .,s QUESTION 5.10c-FILL:IN THE BLANKS FROM THE' LISTED CH0 ICES. Unit II is ~ at:100% power. The Feedwater Level Control System has "A" controller in manual, "B" controller in automatic, Master' controller in automatic set at 30 inches and Low flow controller in automatic at 25 inches. If the feedwater master controller loses its signal, the feedwater regulator valves will (a) If the -reactor level decreases to +25 inches, the low flow control valve will (b) If air is lost to the low flow control valve it will (c) 1. FAIL FULL OPEN 2. FAIL FULL CLOSED 3. FAIL AS IS 4. BEGIN TO OPEN ANSWER: (a) 3. (b) 4. (c) 1. COMMENT: The lesson plan LIC 0600 states that the low flow control valve will fail "as-is" on a loss of air. pressure. This is also supported by recent revisions to Q0A 600-1 and Q0A 4700. For part c., an answer of "3." is the correct answer.

Reference:

Q0A 600-1, Rev. 8 Q0A 4700-6, Rev.1 LIC 600, Rev. 4, p. 8-10, fig. 3

RESPONSE

Comment accepted, however, QOA 600-1, Rev. 8 is dated March 1989, and Q0A 4700-6 Rev. 1 is dated March 1989. No pre-exam comment. Answer Key modified. 12

44- , = - , u 4 m .I + I y QUESTION 5.14ac MATCH the. equipment / systems in Column B which would be- _affected by a loss of the sy' stems in' Column A Items V ain Column:A may have more than one correct answer. Items. in Column B may be.~used more.than once or not at all. Assume all: systems are in-their normal line up. - n: Column A . Column B a.- Instrument Air System 1. Standby liquid ~ control. system 'b. ' Service Air System 2. CRDH flow control valves. 1 3. Breathing Air 4. Scram-Valves 5. Outboard MSIVs 'I 6. Target Rock valves i W _ANS ER: a. 1,:2, 4, 5, 6 b. .1, 3

COMMENT:

The Target Rock Valve is located in the drywell, and as such is. supplied by the Drywell Pneumatic System. Under operating conditions, a normal lineup would have'the Drywell pneumatic System being backed up by the station nitrogen . supply system. Therefore, item No.6 would be an incorrect + answer for part a., and the answer.for part a. should not require item No. 6 in order to get full credit. ~

Reference:

-LIC 0250, Rev.

2,' p. 14-18 LIC 4600/4700, Rev. 2, p. 32 and fig. 11 V RESPONSEi Comment accepted, item 6 deleted. The pre exam review requested " Target Rock-Valve"_vice " safety relief valves" as a selection. Answer Key modified. ~ QUESTION 5.15c WHICH ONE (1) of the following items are entry conditions for QGA-300, " Secondary Containment Control?" a. Rx building floor drain Sump "A" and "B" above the high level alarm for 10 minutes. b. Steam tunnel area temperature reading 150 F. c. Unit I CRD Hydraulic Control Units (South) area radiation reading 15 mR/hr. d. Rx building Differential pressure reading 1.2 psid. 13

\\W. 3 ~ ~ 1

p lc l

d 3 M-o y y; a [1 ANSWERt d- ' COMMENT': Item c should'also be considered a correct" answer. L 15 m4/hr is the Maximum Normal Operating Value for'the K .CRD hydraulic Control Units area. The entry condition for-P QGA 300 regarding radiation levels states "An area radiation 'q 1evel:AB0VE the Max Normal.0perating Radiation Level (QGA c" a should not be required.. However, the entry conditions of the QGAs supplied to the candidates.for the exam were-L blanked out,1 If the entry conditions were provided, then this distinction could be made; without the entry conditions supplied, the.QGAs would be entered AT the Max -~ Normal Operating Radiation Level. Also, if this radiation F level were reached at the' station, thereby giving an Area s 4', Radiation Monitor (ARM). alarm, QGA 300'would be entered. + p

Reference:

.QGA 300-1, Rev. 3 QGA 300-T2, Rev. 3 t QOP 1800 T2, Rev. 16, p. 1

RESPONSE

Comment not accepted; - QGA 300-1, Rev. 3. clearly states " ... AB0VE the Max Normal..." and operators are required-to know QGA entry conditions. The pre-exam review accepted. the question as long as Max Normal tables were provided. . QUESTION 5.16bi Unit I.is operating at 100% core power. A failure of -the master recirculation' flow controller causes both recirculation pumps to runback to minimum speed (less than 44 million 1b/hr). No reactor protection trip occurs and all attempts to return the recirculation system to normal.'are ineffective, b. WHY is thE (APRM) Average Power Range. Monitor Flow biased SCRAM ineffective in mitigating the core instability?' . ANSWER: b. (Time delay in the APRM flow based setpoint has a time delay to account'for fuel time constant.) If flux oscillations are less than time constant, the flow biased APRM trip would not see them. 1 COMMENT: This question should be deleted, since Quad Cities does not (and never has) use(d) a time delay circuit in the APRM flow-biased scram circuitry. 14

j

p

p

• g ei-l,

Reference:

. NED0-31708,_p. 6-4-15 l ~ 3 4 m" = RE'SPONSE:. -Comment' accepted. -This was a pre-exam comment. Answer. I fey modified.- 3 1 'l QUESTION 5.18b . CLASSIFY the following events using QEP 200-T1, [ " Classification of GSEP Condition." a.- A liquid discharge of insoluble iron-55 with a radionuclide concentration of 2.1 x 10**-2 uCi/ml. ? 2~ b. 'A gaseous release of. argon-41 with an instantaneous. a ' release concentration of 4 x 10**-6 uCi/ml. c. Primary containment activity'of 560 rem /hr. d. Sustained winds of 112 mph with both units in Cold-Shutdown.- e. .A fire in the' protected area which releases chloride Lin unbreathable concentrations in the protected ' area. ANSWERi 'a. ' alert b. unusual-event c. site emergency d. alert. e, alert ' COMMENT: The answer to part b. of this questions should be a GSEP , classification of " alert" instead of " unusual event". For-the-level of Argon-41 release specified, this comprises 2 . times the level specified in 10~CFR 20 App. B Table I. Per EAL'17 of QEP 200-T1, this would be an Unusual Event. This level' per EAL 17 of QEP 200-T1, this would be an Alert. 10 CFR 20.105 is the reference stated in EAL 17 of QEP 200-TI. 10 CFR 20.106' continues with specifics concerning allowable' gaseous activity release rates to unrestricted areas, specifying the use of App. B, Table II. Based upon this, the answer to part 6. is " Alert".

Reference:

10 CFR 20.105, Appendix B QEP 200-T1, Rev. 15, p. 8

RESPONSE

Comment accepted, however, recommend that QEP 200 T1, EAL-17 wording for UNUSUAL EVENT and ALERT be clarified with respect to referencing the proper 10 CFR 20 paragraph ._i' .and Appendix B table to use. Not a pre-exam comment. Answer Key modified. 15

,y m-

, y. ;

R 4; A 3l l + 97 g. [ '. U. '. l QUESTION 6:04c? . MATCH the' system ~r,esponse in: Column B with the systems'in L> ~M ' Column: A'under:the assumption that ONE safety relief valve' ige (SRV)' fails open-during 100% power operation, j 'v Column A- .. Column B.

a..-

.t 5 an MWE' - 1. . Increases Constantly n- - b. Indicated turbine. 2._ Decreases Constantly p\\" steam flow 3. Increases and then ( ', .c. Reactor water- . Stabilizes level 4. Decreases and then d.. Feedwater temperature < Stabilizes ~ E E', 5.- No Change. ,8 ANSWER:; a.. 4-b. 4 4 c.. L4 y~

d.

4 .: COMMENT: At Quad Cities, the Feedwater Regulating Valves (FWRVs) .are operated only in the Single._ Element mode.- Under the conditions given in this questions this would cause level to decrease, and then return to it-original value, since .the FWRVs;would open to restore-le.el to the setpoint. .The correct answer for this part should'be item No. 5, "No Change." x.

Reference:

LIC 0600, Rev. 4, p. 2,.18, 20-RESPONSEi Comment accepted. No pre-exam comment. Answer Key modified. t {' 16 m ~ .}}