ML20247C075

Forwards Comments on Initial Reactor Operator Licensing Exam Administered on 890410

ML20247C075
Person / Time
Site:	Fort Calhoun
Issue date:	04/14/1989
From:	Morris K OMAHA PUBLIC POWER DISTRICT
To:	Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20247C036	List: ML20247C032 ML20247C050 ML20247C075
References
LIC-89-389, NUDOCS 8905240340
Download: ML20247C075 (22)

Text

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 )

April 14, 1989 LIC-89-389 Mr. John L. Pellet Chief, Operator Licensing Section U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

Reference:

Docket No. 50-285

SUBJECT:

Technical Review of Initial Reactor Operator Licensing Examination Administered by the NRC at Fort Calhoun Station on April 10, 1989 Personnel at Omaha Public Power District have reviewed the Initial Reactor Operator licensing examination administered on April 10, 1989. Enclosed are our comments on the examination in accordance with the requirements specified in ES-201.

Sincerely, ,

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/ KA. f ' Morris l Division Manager Nuclear Operations I i l

KJM:ket  !

Enclosure l

l cc:

p l LeBoeuf, Lamb, Leiby & MacRae w/o l P. D. Milano, NRC Project Manager w/o P. H. Harrell, NRC Senior Resident Inspector w/o Document Control Desk w/o 8905240340 890509 PDR ADOCK 05000205 V PNU G5 5124 Employmen ual Opoanunny

QUESTION 1.09 (1.00)

From the following possible combinations of parameters, select the one combination that indicates natural circulation cooling. (1.0)

TCS SG Core Exit Subcooling Pressure Thot Thermocouple Tcold

a. 40 F Stable Decreasing Increasing Tsat for SG Press

b. 30 F Decreasing Decreasing Stable Stable

c. 20 F Stable T t for Decreasing Stable R Press

d. 20 F Decreasing Stable Decreasing T sat for SG Press ANSWER 1.09 (1.00)

d. (1.0)

REFERENCE E0P-20, P. 97 193008K122 ..(KA's)

RESPONSE

OPPD requests this question ba deleted.

The criteria for verifying natural circulation are specified in the reference, E0P-20 page 97. These criteria and E0P-06 (Loss of Feedwater) cannot be applied to the offered choices. None of the answers satisfy the four criteria in E0P-20.

Also, the answer on the key states Tho+ is stable while CET's are decreasing; E0P-20 states there should be no abnor$al difference between Thot and CET's.

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. O QUESTION 1.13 (1.00)

Which one the following describes Wide Range Log Channel indication during a artial core uncovery compared to the indication just PRIOR to core uncovery p(uncovered / covered)?

a. 10%.

b. 50%.

c. 100%.

d. 200%.

1 ANSWER 1.13 (1.00) c.

REFERENCE FCS LP 7-12-18, p. 103 191002K117 ..(KA's)

RESPONSE

l OPPD requests the correct answer be changed to choice (d), 200%.

The reference, LP 7-12-18 II. J. 2. e., states "a sudden spike in indicated power is the most likely effect of voiding..." (d) is the only choice which

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would reflect an increased indication following core uncovery.

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QUESTION 1.17 (1.50)

Fill in the blanks in the following paragraph dealing with condcnser tube fouling at Fort Calhoun Station. Blanks may contain one or more words or numbers. (1.5)

The major source of condenser fouling is _(a)_ from the Missouri river.

During high fouling periods, condenser flow is reversed as often as _(b)_.

When condenser flow is reversed, plant indications may show a reactor plant change _(c)_.

ANSWER 1.17 (1.50)

a. sticks, sand, gravel, & similar debris

b. twice per shift

c. 10~20 mw (3 answers 0 0.5 ea.)

REFERENCE FCS LP 7-13-5, p. 72 191006K111 ..(KA's)

RESPONSE

OPPD requests the correct answer for part (b) be changed to either as often as necessary, or between 1 and 4 times per shift; and for part (c) to "5-15 MWe".

The frequency for performing condenser flow reversals, from past operating experience, is on an as-needed basis, typically between 1 and 4 times per shift.

Lesson Plan 7-11-3 states "there will be a small dip (approximately 10 MW) in station ontput "

Operations personnel have indicated that a 5-15 MWe drop, depanding upon river temperature, is typical.

I Please note that backwashing the condenser causes a drop in electrical output due to a loss of efficiency, but there is no change in reactor power observable in the control room. It is recommended that the question be revised, in part, to read: "... plant indications may show a station electrical output char.ge of (c) ,

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RESPONSE (continued)

The keyed enswer could not be investigated since LP 7-13-5 is entitled

" Emergency Diesel Generator".

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b, QUESTION: 1.18 (1.00) _-

_W hich one of the answers below-describes the location of the-onset.of cavitation in a centrifugal pump? (1.0) m a. Front face of the blade.

b. Top of the volute.

c. Top'of.the-inlet.

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d. Rear face of the blade.

ANSWER 1.18 (1.00) d.

REFERENCE FCS LP.7-7-21, p. 6.4-4 191004K101 ..(KA's)

RESPONSE

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1 PPD requests also accepting as a correct answer'(c), top of~the inlet.

'he reference, LP_7-7-21 page 6.4-4,. refers to an' axial flow pump (propeller type); for this type of 3 ump the' cavitation will occur as indicated on the key t the rear face of the .) lade. However, the question refers to a centrifugal jump; for this type of pump cavitation occurs in the eye of the impeller.

I Since eye of:the. impeller was not a choice, top of the inlet would be the best possible alternative. On the previous page of the reference, the conditions

.that lead to cavitation are described. This discussion states cavitation occurs when the fluid pressure drops below the fluid saturation 3ressure for a give temperature. It also explains this may occur even before t1e fluid enters the pump. For future use, it is requested that the question provide eye of the impelier as a choice or the question specify an axial flow pump.

QUESTION 1.19 (1.00)

Which one ofcontrollers the feedwater the following(describes FIC-1101/2)7 the reason to maintain zero deviation (1.0) on

a. To establish the manual control point.

b. To provide a "bumpless" transfer between control modes.

c. To enable switching to the HIC standby controller.

d. To ensure the bypass valves are closed at high power.

ANSWER 1.19 (1.00) a.

REFERENCE FCS LP 7-12-15, p. 23 I

191003K111 ..(KA's)

RESPONSE

1 OPPD requests this question be deleted.

The question references FIC-1101/2. However, the controllers discussed in LP

( 7-12-15, ). 22, 23 are HIC-1101/2. The FIC controllers do not have a deviation i

meter. Tierefore, none of the alternative answers are correct.

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OVESTION 1.20 (1.00)

Which one of the answers below correctly describes how and why the wide range steam generator level channels (911 & 912) do not correspond to the narrow range readings? (1.0)

a. The wide range read low because they lack temperature compensation and flow errorswereencountered(venturieffect).

b. The wide range read high because downcomer density is not constant and flow errors were encountered (venturi effect).

c. The wide range high because they lack temperature compensation and flow errors were encountered (venturi effect).

d. The wide range read low because downcomer density is not constant and flow errors were encountered (venturi effect).

ANSWER 1.20 (1.00) d.

REFERENCE FCS LP 7-12-28, p. 39 191002K106 ..(KA's)

RESPONSE

OPPD requests this question be deleted.

The referenced lesson plan describes why the wide range and narrow range do not correspond E oredicted. Answer (d) correctly explains the lack of correspondence. However, the question omits the important words "as predicted", completely changing the meaning. The correct answer to the question, as written, is that WR measures level from the hand-hole cover to the top of the dryers. NR only measures level from the feed ring area to the top of the dryers. Since this is not one of the alternative answers, the examinee is left to choose from four (4) that are incorrect.

QUESTION 1.21 (1.00) i Which one of the answers below descriNs failure modes for steam generator level sensor failure due to diaphragm ropture? (1.0) f

a. Those used for RPS wil! read high while those used for FRS will read low,

b. Those used for RPS will read high and those used for FRS will read high.

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c. Those used for RPS will read low while those for FRS will read high.

d. Those used for RPS will read low and those used FRS will read low.

ANSWER 1.21 (1.00) c.

REFERENCE FCS LP 7-12-28, p. 33, 35 191002K109 ..(KA's)

RESPONSE

OPPD requests the correct answer be changed to choice (b).

The reference, LP 7-12-28 3 ages 31 - 36, and the calibration procedures (CP-1101, CP-A/8901) for t1e RPS and FRS steam generator level sensors indicate f both would read high on a diaphragm failure. The RPS detectors are Foxboro type; the FRS detectors are GE/MAC type. Both are connected to the same instrument taps and use the same condensing pots. Their operation is identical. The note on page 35 of the lesson plan pertains to both the RPS and FRS detectors. Rupture of the diaphragm would result in a low d/p and a high level.

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QUESTION 2.04 (2.00)

According to AOP-19, Loss of Shutdown Cooling, what are the "LAST RESORT" methods (Flow Paths) for residual heat removal for each of the following conditions. For each case, describe the complete open/ closed loop path,

a. The reactor head installed. (1.0)

b. The reactor head removed, transfer canal open. (1.0)

ANSWER 2.04 (2.00)

a. SIRWT > HPSI Pumps > 1rimary system > PORV's OR Loop Drains > RCDT > RCDT drain pump > SIRWT. : 0.15 for each component in flow path and 0.02 for each manipulation to attain correct order.]

b. SIRWT > Fuel Transfer Canal Drain Pump > SFP > SFP pumps > SIRWT. [0.16 for each component in flow path and 0.02 for each manipulation to attain correct order.]

l REFERENCE AOP-19, p. 3 LP 2-1-41, L.0. 1.0, 1.2 000025K301 000025K101 ..(KA's)

RESPONSE

OPPD requests this question be deleted.

The lesson plan and the procedure that were referenced are out-of-date. The current A0P does not mention "LAST RESORT" flow paths. These references should be discarded.

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QUESTION 2.21 (1.50)

Fill in the blanks in the following statements concerning process radiation monitors measuring RCS activity. Blanks may concern one or more words or numbers.

a. Process Radiation Recorder RR-214 in high alarm indicates RCS activity is high. (0.5)

b. Process Radiation Monitor PRM-1 in high alarm indicates RCS activity is high. (0.5)

c. Process Radiation Monitor PRM-2 in high alarm indicates RCS activity is high. (0.5)

ANSWER 2.21 (1.50)

a. gamma (gross)

b. gamma (gross) l

c. iodine -135 ,

REFERENCE FCS A0P-21-1 000076K201 ..(KA's)

RESPONSE

OPPD requests accepting as equally correct answers gamma or gross or selected (specific) isotope I-135 for part (a); gamma or gross for part (b); and selected (specific) isotope I-135 for part (c).  ;

As indicated in drawing 11405-EM-214, RR-214 is the recorder for both PRM-1 and PRM-2. Therefore, the answer to part (a) must be a combination of those l correct answers for (b) and (c). The control room label on PRM-2 reads

" selected isotope I-135."

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QUESTION 3.03 (1.50)

MATCHING. Match each of the alarms below with the appropriate cause. Each cause may be used more than once or not at all. (1.50)

ALARM

a. Rod Position Deviation Low Limit

b. Rod Position Deviation Reed Switch

c. Out of Sequence Rod Block

d. Power Dependent Insertion Limit

e. Rod Drive Power Interrupt CAUSE

1. During rod withdrawal, any group above Lower Limit Setpoint before all lower group D have reached their Upper Sequential Permissive.

2. Any one of the shutdown rods is below its 120-inch exercise limit.

3. The group deviation is four (4) inches, as sensed by the plant computer.

4. Thegroupdeviationiseight(8)inchesassensedbytheplant computer.

5. The group deviation is eight (8) inches as sensed by the Metroscope.

6. Rod block.

7. Excessive group overlap.

8. Power greater than 10EE-04% with group one less than 118 inches.

9. Power greater than 10EE-04% with group two less than 122 inches.

ANSWER 3.03 (1.50)

a. 3

b. 5

c. 1

d. 8

e. 6 (5 answers 0 0.3 ea.)

REFERENCE FCS LP 7-12-26, p. 53-58 001050A201 ..(KA's)

RESPONSE

OPPD requests accepting as equally correct answers 1, 5, 7, and 8 for part (e).

For part (e), all of the conditions listed above as alternative answers will cause Rod Block and therefore, result in a Rod Drive Power Interrupt alarm.

These conditions are specifically linked to a discussion of this alarm in LP 7-12-26 (old No. 1-3-15).

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QUESTION 3.10 (2.00)

With regard to an Engineered Safeguards Control Recirculation Actuation Signal (RAS):

a. What signal (s) is/are required coincident with a SIRWT low level signal to generate an RAS? (two answers required) (0.5)

b. What are three (3) control functions initiated by a RAS (valve nJmbers are NOT required)? (1.5)

ANSWER 3.10 (2.00)

a. PPLS(0.25)&CPHS(0.25)

b. 1. Trip / lock out the LPSI pumps.

2. Shift HPSI & containment spray suction to containment.

3. Isolate SI pump minimum flow recirculation line.

4. Establish full CCW flow through SDC hx. (any 3/4 0 0.5 ea.)

REFERENCE FCS LP 7-12-7, p. 14 006020A304 ..(KA's)

RESPONSE

1 OPPD PPLS orrequests CPHS inaccepting conjunctionfor part with (a), PPLS SIRWT or CPHS low level (recognizing)that will cause either RAS ; and for part (b), closure of the suction valves from the SIRWT and opening of the suction j valves from the containment sump as two individual control functions. i The request on part (a) is strictly semantics; the key states "PPLS & CPHS" technically the answer should be "PPLS or CPHS". Since logic is not asked for either &/or should be accepted. Lesson plan 7-11-22 identifies five individual system responses following an RAS. Each of these should be considered acceptable for part (b).

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QUESTION 3.13 (1.50)

MATCHING. Match each of the core mimic light colors to the appropriate rod height description. Each description may be used more than once or not at all.

(1.50)

COLOR DESCRIPTION  :

a. Amber 1. Upper electrical limit

2. Upper rod stop

b. Blue 3. Shutdown group lower limit

4. Rod motion occurring

c. Green 5. Rod deviation detected

6. Above four (4) inches

d. Red 7. Lower electrical limit

e. White ANSWER 3.13 (1.50)

a. 2

b. 3

c. 7

d. 1

e. 6 (5 answers 0 0.3 ea.)

I REFERENCE FCS LP 7-12-26, p. 44, 45 014008401 ..(KA's)

RESPONSE

OPPD requests accepting as an equally correct answer 4, rod motion occurring for part (e).

The reference, LP 7-12-25 (Old No. 1-3-15) page 45, states the white light indicates both CRDM above 4 inches and rod motion occurring.

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QUESTION '3.16. '(1.00) i Which one of the instruments below would 3rovide the first. observable.

L indication of a loss of.feedwater event w1ile at power? (l'. 0)

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.a. RCS pressure

b. . Pressurizer level

c. Reactor power

d. Hot leg temperature ANSWER 3.16 (1.00) b.

REFERENCE FCS LP 7-11-20, p. 54-57 035010K301 ...(KA's)

' RESPONSE OPPD requests accepting as equally acceptable answers both (a) RCS pressure, and.(d)HotLegTemperature.

The graphs ~in lesson plan 7-15-17 show RCS pre'ssure and Thot increasing at

.approximately the same time (about 3-5 seconds'into the transient). The reference on the key does not discuss Pressurizer level increasing. The question asks for the first observable indication; it is not apparent whether level, temperature or pressure will be the "first observable".-

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QUESTION '3.22 (1.50)

Y . MATCHING..Matchoperator' type +and'failureforlossof.motivepowermodeto

each'of the' isolation 1 valves listed below.

Each operator type may be use more than once or not at all. -(1.50) ts i

ISOLATION VALVE TYPE OPERATOR'& FAILURE MODE-f- a. Main Steam Isolation Valves 1. Motor'- fail as is

2. Motor.- fail closed

,' b '. Main Steam Bypass Valves 3.- Motor - fail open-

4. Air - fail as is h

c. .Feedwater Isolation' Valves 5. Air - fail closed

6. Air - fail.open

.d. Feedwater Containment Isolation .7. . Spring - fail open.

Valves 8. Spring - fail closed

e. Feedwater Regulating Bypass Valves ANSWER '3.22 (1.50)

a. 8

-b. 1. .

c. 1

'd. 1

3. 5' .(5 answers 0 0.3 ea.)

REFERENCE FCS LP 7-12-10, p. 39-46 059000K419 ...(KA's)

RESPONSE

OPPD requests accepting as an equally correct answer for part a:5. Air - fail closed.

The reference, LP 7-12-10 page 39, states the MSIV's are .. spring shut, pneumatically opened..". Lesson plan 7-11-17 page 15 states the MSIV's are

.. spring "

loaded, pneumatically operated.."

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h ~3.26:

, QUESTION _. (1.00) g .Wh.ich'one of the following answers describes the control room ventilation y system response to a VIAS? ~(1.0) j a. . Place VA-64;in service.

b. Place VA-46A and VA-46B'in service.

! c. Trip VA-46A', VA-468, VA-63, and VA-49.

.d. Shut PCV-860A, PCV-8608, and PCV-860C.

f ANSWER 3.26 (1.00).

a.

REFERENCE FCS LP 7.-14-6, p. 8-19 072000A301 ..(KA's)

RESPONSE ~

OPPD requests ~ accepting as an eqilally correct. answer choice b.

A modification was done on the system during the last refueling outage. ..The latest revision of LP 7-14-6-explains that a VA-46 fan which is in standby will be automatically started by VIAS.

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QUESTION 3.34 (1.50)

MATCHING. Match each of the access descriptions listed below to the appropriate badge color. Each description may be used more than once or not at all. (1.50)

BADGE COLOR ACCESS DESCRIPTION

a. White 1. Unrestricted access to protected and vital areas.  !

b. Red 2. Access to non-vital areas outside protected area,

c. Green 3. Access to protected area and non-radiation vital.

d. Yellow 4. Access to vital areas outside RCA.

5. Visitor or escorted access only.

ANSWER 3.34 (1.50)

a. 5

b. I

c. 4

d. 2 (4 answers 0 0.375 ea.)

REFERENCE FCS Standing Order G-39, p.2-4 l 194001K105 ..(KA's)

RESPONSE

OPPD requests and deletion accepting),

of part (d . as an equally correct answer for part (c), choice 3, The reference, S0 G-39, clarifies the access descriptions. Choice 2 is not a valid statement: the word "outside" should be replaced with "inside". Choices 3 and 4 describe access to identical areas, specifically "non-radiation vital" is the same as " vital outside the RCA." The protected area at Fort Calhoun l

Station is the area inside of the security fence.

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QUESTION 2.10 (1.00) l Amalfunctioninthepressurizerpressuremeasurement"A" channel (A/P1A-102Y) causes the output to go to minimum. Which one of the following is the proper system response to the malfunction? (1.0)

a. High Pressure and TM/LP Channels "A" trip causing a reactor pre-trip.

b. High Pressure and TM/LP Channels "A" trip causing a reactor trip.

c. Only High Pressure Channel "A" trips causing a reactor pre-trip.

d. Only TM/LP Channel "A" trips causing a reactor pre-trip.

ANSWER 2.10 (1.00) d.

REFERENCE FCS LP 7-12-25, LO 1.03, 007-12-26-11-25-1.03-0001 000027A216 ..(KA's) i 2.10 Clarification '

-It is suggested that the words " reactor pre-trip" from choices (a), (c), and (d) be deleted. The term pre-trip refers to a condition on an individual RPS trip unit, different from the usage above. Also, in the question (A/P1A-102Y) should be replaced with (A/P-102). l l

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QUESTION 2.06 (1.00)

Which one of the following is the correct response from the main condenser pressure ins +rument as condenser vacuum goes from 29" to 15" Hg? (1.0)

a. a high condensate pressure alarm.

b. a reactor trip.

c. a main feed water pump trip.

d. an evacuation pump start signal.

ANSWER 2.06 (1.00) d.

REFERENCE FCS LP 7-11-4 000051A202 ..(KA's) 2.6 Clarification It is suggested the words "from the main condenser pressure instrument" be deleted. The instrument itself has no control functions. Reactor trip is probably not a good distractor because a reactor trip will occur as a result of a turbine trip at 21.35" Hg.

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QUESTION 3.06 (1.00)

(Th ) and cold leg  ;

Which one-of the (T ) temperature following response during answers a reactor describes coolantRCS pumphot leg (RCP) coastdown in a c

loss of forced cooling transient from 100% power 7

a. will decrease, Th and Tc

b. Th will increase and Tc will decrease.

c. Th will decrease and cT will increase.

d. Th and Te will increase.

ANSWER 3.06 (1.00) a.

REFERENCE FCS LP 7-11-20, p. 61 003000K502 . . (KA's) 3.6 -Clarification Since onset of. natural circulation is a dynamic phenomenon, more information is needed to describe correct plant conditions.

Specify power levels before and after, how long after the loss of forced cooling the question is addressing, and the condition of the steam dump and bypass system.

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