ML20056A973

Forwards Facility Written Exam Comments for NRC Insp Repts 50-352/90-10 & 50-353/90-11.Written Exam for Reactor Operator & Senior Reactor Operator Considered Comprehensive & Thorough

ML20056A973
Person / Time
Site:	Limerick
Issue date:	07/25/1990
From:	Leitch G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RTR-NUREG-1021 NUDOCS 9008100296
Download: ML20056A973 (13)

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PHILADELPHIA ELECTRIC COMPANY LIMERICK GENER ATING ST ATION P. O. DOX A  !

s AN ATOG A. PENNsYLV ANI A 194s - July 25, 1990 (tis) 327.i200. ext. 3000 Docket Nos. 50 352 '

. awau u. seitew 50 353 t u...........,.........

License Nos. NPF.39 NPF 85 e

Mr. Thomas T. Martin, Regional Administrator U. S. Nuclear Regulatory Commission Region 1 . i 475 Allendale Road King of Prussia, PA 19406 SUBJ ECT: Limerick Generating Station Units 1 and 2 14/S14 Written Exam Comments for Combin<d NRC Inspections 50 352/90 10 and 50 353/90 11 i

Dear Mr. Martin:

Attached you will find the Limerick Operations and Nuclear Training Section responses to selected questions and answers associated with the NRC RO/SRO written examinations, administered on 7/23/90, at the Limerick Generating Station. These comments are being submitted using the guidance of NUREC 1021, to

, clarify areas where alternate correct answers should be considered, and to correct errors on the exam and answer keys. References have been indicated to justify the comments made. ,

The written examinations for both the RO and SRO candidates were comprehensive and thorough. The opportunity for the pre-exam review was beneficial in developing a thorough and fair examination.

If there are any questions concerning these comments, please contact V. J.

Cwietniewier., LCS Superintendent-Training, at 327 1200, extension 2080.

Very uly rs, I

/

PTD:km1 Attachments )

xc: T. J. Kenny, USNRC, Senior Resident Inspector, LGS R. J. Conte, Operations Branch, Region 1 NRC F. Paul Bonnett, USNRC Region 1 Document Control Desk, USNRC, Washington, D. C.

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.NRC SENIOR' REACTOR OPERATOR EXAM (7/23/90) RESPONSES

. Question: 14 Unit I reactor is operating at 54 power with the MODE SWITCH'in STARTUP. The operator increases the recirculation flow which increases the power to lit as i read on APRMs. SELECT the response (s) caused by this action:

l l a. No response

b. IRN UPSCALE alarm and ROD BLOCK

c. IRM UPSCALE alarm and SCRAM

d. IRM UPSCALE alarm, ROD BLOCK, and SCRAM l- Answer: 14 b.

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Reference:

Limerick . LOT.0250, Obj .10 and p.10 13 & T. LOT.0250 9 j K/A: 215005 K401 (3.7/3.7) 215005 K402 (4.0/4.0) 215003 K4.02 215003 K401 l

l Request answer key to be changed to read "a.

No response" as correct rnswer.

i.

Reference:

LOT.0250, Obj. #3, page 4, I.A.2  !

(Similar question RO 18) y Question: 15 l' Select the plant conditions which will result in the LPCI mode of the RHR system INJECTINC into the Reactor Vessel.

l a. Reactor Pressure 155 psig I Drywell Pressure 1.58 psig i Reactor Level -129"  !

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b. Reactor Pressure 155 psig . l Drywell Pressure 1.68 psig Reactor Level 38"

c. Reactor Pressure 465 psig Drywell Pressure 1,68 psig Reactor Level 129"

d. Reactor Pressure 465 psig Drywell Pressure 1.58 psig Reactor Level 38"  !

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' Answer: 15 i i

a. i

Reference:

Limerick LOT.0370, Obj . 6 and page 23 K/A: 203000 K401 (4.2/4.2) i Request alternate correct answer as b. Reactor Pressure 155 psig l Drywell Pressure 1.68 psig l Reactor Level 38"  !

)

Reference:

LOT.0370, Obj. #6, page 23, V. B.1.a j i

(Similar question RO 20) 1

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Question: 30 FILL IN THE BLANKS Fill in the Unit designation in the statement that describes the differences between Rod Worth Minimizer (RWM) systems for that unit.

Unit RWM receives rod position information from the process computer /PMS while Unit RWM supplies rod position information to the process computer /PMS, AND Unit RWM has alternate insert and withdraw limits for all rod positions while Unit has one for position 48. . ,

Answer: 30 2, 1, 1, 2

Reference:

Limerick LOT.1870, Obj. #1 and page 15 16 K/A: 2010053 0007 (3.0/3.3)

Request answer key read: 1, 2, 1 2

Reference:

LOT.1870, Obj. #1, page 16, XXII, K and XXXI, F.

(Similar question RO 36)

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-Question: 60-A gaseous odor is noticeable in the Control Room and some Control Room personnel l have passed out. Using the provided copy of EP 101, SELECT the appropriate level classification.

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a. Unusual Event I

b. Alert 5 1

c. Site Emergency (

d. General Emergency Answer: 60 i

b. l i

Reference:

1) Limerick EP 101, page 5 and 11 1 Limerick LOT-1520, Obj . 6.a and page 911 of 17,Section IV 2)

K/A: 294001 A116 (2.9/4.7)

Request alternate correct answer as "c" Site Emergency, based on question wording. "Some (more than 1) Control Room personnel have passed out", leads the ;

candidate to believe lack of access to the Control Room for relief personnel i exists and thus constituting a reactor safety hasard due to reduced operating crew.

Reference:

EP-101, page 5, Site Emergency, 1.a. and 1.b.

(No similar R0 question) i e

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Question: 66 With Unit 1 at 35% power and in 3 element feedwater control, the selected level transmitter fails low. SELECT the ONE statement that describes the expected PLANT RESPONSE and related EMERGENCY / ABNORMAL PROCEDURE that should be used,

a. The Master Controller decrer.ses feedwater pump speeds causing a reactor water level low alarm only OT 100 is implemented to increase feedwater flow,

b. The Master Controller decreases feedwater pump speeds causing a reactor water level low alarm and acram. OT 100 and T 100/101 are implemented to correct feedwater flow and respond to the scram,

c. The Master Controller increases feedwater pump speeds causing a reactor water level high alarm and turbines trip. OT 110 is implemented to reduce feedwater flow,

d. The Master Controller increases feedwater pump speeds causing a reactor water level high alarm and turbines trips. OT 110 and T 100 are implemented to reduce feedwater flow and respond to the scram.

Answer: 66

d. [+1)

Reference:

1) Limerick LOT 0550, Obj. #7.c and page 19 of 32 section 5

2) Limerick OT 110. Section 2 K/A: 295008 AK203 (3.6/3.7) 295008 AK 208 (3.4/3.5) 295008 SG11 (3.9/4.1)

Request the word alarm be removed from answers a. thru d.

Reference:

LOT-0550, page 5 III. A. 2. c. 2)

(Similar question RO 68)

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Question: 73 >

A core off load on Unit 1 is 50% complete. The A SRM is in the affected quadrant where core alterations are taking place.  :

SELECT the ONE condition that would require core alterations to be suspended.  !

ASSUME SRM channels are operable unless otherwise stated below,

a. All SRMs have continuous indication in the control room with shorting links removed, i

b. C SRM is the only SRM with an audible alarm in the control room,

c. The B and D SRM is inop and the C SRM has a special movable detector  !

connected to a normal SRM circuit in the B quadrant.

d. The A SRM is indicating 1.0 cps with a signal to noise ration of 10.

Answer: 73

c. [ +1,1

Reference:

1) Limerick TS 3,9.2

2) Limerick LOT.1830, Obj . #2 K/A: 295023 SO4 (2.7/3.8) 295023 C004 Request alternate correct answer as "d" based on being below allowab s curve shown on Figure 3.3.6 1.

Reference:

TS 3.9.2 pages 3/4 9-3 and 3/4 9-4 TS 3.3.6 Figure 3.3.6-1 page 3/4 3-60b

'(No similar RO question) 4 e

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Question: 75 Unit 1-is in refueling operations and a spent fuel bunfle is inadvertently knocked against the transfer canal wall resulting in a damage to a fuel pin which you visually observe. The refueling floor area ventilation exhaust monitor s: alarms.

Using the provided copy of EP 101, SELECT the highest emergency classification level listed below for the event.

a. Unusual Event

b. Alert

c. Site Emergency

d. General Emergency Ar,swer: 75

c. {+1)

Reference:

1) Limerick EP 101

2) Limerick LOT L540, Obj, #6 K/A: 295023 SG11 (3.9/4.2) 295023 C011 Request alternate correct answer "b" Alert, due to the words damage to a fuel pin vice major damage.

Reference:

- EP-101, page 12, Alert 3.

ON-120, page 2, 2.3.4 O

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L question 93: ,

l You have confirmed a loss of off site power and all emergency diesel generators started except the D-24 diesel. SELECT the ONE verification that'is not an immediate action for the given conditions. ,

a. 2A CRD Water Pump running.

b. 2B Control Enclosure Chiller Unit running.  ;

c. A11' rods at notch 02 or less for Unit'l and 2.

d. 2A RECW Pump running.

Answer: 93

b. [+1)

Reference:

1) Limerick- SE E D24 and SE-E10/20 Section 2

2) Limerick LOT-1566 Obj. #2 and 3 K/A: 295003 SG10 (3.9/4.1)  ;

Request'to change answer "b" to read: "0B Contro1~ Enclosure Chiller Unit ,

running." )

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Reference:

E D13, Step 2.3 l

(Similar Question RO 86)

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,. .- l Question: 95-A startup on Unit 1 is at 654 power. The drywoll is being inerted and drywell i pressure is 1.5 psig and slightly increasing. There is 5 gpm leakage in the  !

drywell that is routed to the Equipment Drain Sump. The CO reports to the shift l supervisor that Drywell Unit Cooler condensate flowrate is 11 gpm. With respect i to the. Unit 1 Technical Specifications, SELECT the statement that describes your  !

required action (s). ASSUME all other plant parameters are in their normal range. I

a. Restore Drywell pressure to within limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. Reduce the RCS leakrate within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least hot  ;

shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I

c. Be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown I within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. )

d. Be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown in the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Answer: 95

b. [0,5)

Reference:

Limerick Unit 1 Tech. Spec. 3.4.3.2 and 3.6.1.6 K/A: 295010 SG8 (3.5/4.4) 295010 SG11 (4.2/4.5) 295024 SG8 (3.6/4.4) 295024 SG11 (4.3/4.5) I 295024 G011, G008; 295010 .G011, G008 I

Request question be deleted due to no correct answer for question, answer b incorrectly describes the action statemeret listed in Tech. Spec, J

Reference:

Unit 1 Tech. Spec. 3.4.3.2 action b page 3/4 4-9 I

i NRC REACTOR OPERATOR EXAM (7/23/90) RESPONSES Question: 18 r

~ Unit i reactor is operating at.54 power with the MODE SWITCH in STARTUP. The operator increases the recirculation flow which increases the power to lit as  ;

read on APRMs. -SELECT the response (s) caused by this action:

a. No response

b. IRM UPSCALE alarm and ROD RLOCK  ;

c. IRM UPSCALE alarm and SCRui ,

I d. IRM UPSCALE alarm, ROD BLOCK, and SCRAM Answer:- 18 r

I b.

Reference:

Limerick . LOT.0250, Obj. 10 and p. 10 13 & T-LaT 0250.'9 ,

K/A: 215005 K401 (3.7/3.7) 215005 K402 (4.0/4.0) 215003 K4.02 215003 K401 Request answer key to be changed to read "a.

~

No response" as correct answer. .;

Reference:

LOT.0250, Obj. #3 .page 4 I.A.2 L (Similar question SRO 14) 1

( . . . . . ....................................

Question: 20 l Select the plant conditions which will result in the LPCI raode of the RHR system INJECTING into the Reactor Vessel, b

L a. -Reactor Pressure 155 psig

! Drywell Pressure 1,58 psig l Reactor Level 129"

b. Reactor Pressure 155 psig .

Drywell Pressure 1.68 psig Reactor Level 38" 1'

c. Reactor Pressure 465 psig Drywell Pressure 1.68 psig Reactor Level 129"

d. Reactor Pressure 465 psig Drywell Pressure 1.58 psig Reactor Level 38"  ;

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. Answer: 20 a.

Reference:

Limerick LOT.0370, Obj. 6 and page 23 K/A: 203000 K401 (4.2/4.2)

Request alternate correct answer as b. Reactor Pressure 155 psig Drywell Pressure 1.68 psig Reactor Level -38"

Reference:

LOT.0370, Obj. #6, page 23, V. 8.1.a (Similar question SRO 15)

Question: 36 FILL IN THE BLANKS Fill in the Unit designation in the statement that describes the differences between Rod Worth Minimizer (RWM) systems for that unit.

Unit RWM receives rod position information from the process computer /PMS while Unit RWM supplies rod position information to the process computer /PMS.

AND Unit RWM has alternate insert and withdraw limits for all rod positions while Unit has one for position 48.

Answer; 36 2, 1, 1, 2

Reference:

Limerick LOT-1870, Obj. *1 and page 15 16 K/A: 2010053 G007 (3,0/3.3)

Request answer key read: 1, 2, 1, 2

Reference:

LOT.1870, Obj. el, page 16, XIII, K. and XXII, F.

(Similar question SRO 30)

Question: 68 With Unit 1 at 354 power and in 3. element feedwater control, the selected level transmitter fails low. SELECT the ONE statement that describes the expected PLANT RESPONSE and related EMERGENCY / ABNORMAL PROCEDURE that should be used.

a. The Master Controller decreases feedwater pump speeds causing a reactor water level low alarm only. OT 100 is implemented to increase feedwater flow,

b. The Master Controller decreases feedwater pump speeds causing a reactor water level low alarm and scram. OT.100 and T.100/101 are implemented to correct feedvster flow and respond to the scram.

c. The Master Controller increases feedwater pump speeds causing a reactor water level high alarm and turbines trip. OT 110 is implemented to reduce feedwater flow,

d. The Master Controller increases feedwater pump speeds causing a reactor water level high alarm and turbines trips. 07 110 and T.100 are implemented to reduce feedwater flow and respond to the scram.

Answer: 68

d. [+1]

Reference:

1) Limerick LOT 0550, Obj. #7.c and page 19 of 32 section 5

2) Limerick 0T.110, Section 2 K/A: 295008 AK203 (3.6/3.7) 295008 AK 208 (3.4/3.5) 295008 SG11 (3.9/4.1)

Request the word alarm be removed from answers a. thru d.

Reference:

LOT.0550, page 5 III. A. 2. c. 2)

(Similar question SRO 66)

Question 86:

You have confirmed a loss of off. site power and all emergency diesel generators started except the D.24 diesel. SELECT the ONE verification that is not an immediate action for the given conditions.

-a. 2A CRD Water Pump running.

b. 2B Control Enclosure Chiller Unit running,

c. All rodo at notch 02 or less for Unit 1 and 2.

d. 2A RECW Pump running.

-Answer: 86

b. [+1)

Reference:

1) Limerick SE E D24 and SE E10/20 Section 2

2) Limerick . LOT 1566 Obj . #2 and 3 K/A: 295003 SG10 (3.9/4.1)

Request to change answer "b" to read: "0B Control Enclosure Chiller Unit running."

Reference:

E-D13, Step 2.3 (Similar Question RO 93) k h

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