ML20237L235

Forwards Util Comments Re Retraining Exams Given at Plant on 870622

ML20237L235
Person / Time
Site:	Farley
Issue date:	06/29/1987
From:	Woodard J ALABAMA POWER CO.
To:	Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20237K598	List: ML20237K620 ML20237L235
References
FNP-87-0292-TRN, FNP-87-292-TRN, NUDOCS 8708280014
Download: ML20237L235 (14)

Text

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($ g j ENCLOSURE 3

Alabama Power Company J, M. Farley Nuclear Plant

. P, O. orawer 470 '

Ashford. Alabama 36312 ..

Telephone 205 899-5156 -

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, . I V, E D l .

L 17 JUi :3' Ali : 50 AlabamaPower.

rw sann em:: . w F P-87-0292-TRN NA ET pne29,1987 The Regional Administrator, Region II Nuclear Regulatory Commission 101-Marietta St., N.W.

Atlanta, GA 30323 ATTN: Mr. John F. Munro, Chief.

Operator Licensing Branch Enclosed are Alabama Power Company's comments concerning the retraining examinations given at Farley Nuclear Plant on June 22, 1987.

Sincerely, afA N / (2A /

Jf DK ' od#r5 v"

& eral Manager - Nuclear Plant JDW/LSW:mj k cc: EG&G Idaho, Inc.

. Enclosure l

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8708280014 870813 PDR ADOCK 0 % yB c_ _ - - >

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L 2.10-(2.50) l l

QUESTION j 4

List FIVE loads supplied by the ESF/ primary loops of the Component Cooling Water System.

ANSWER 1 1.. Charging pumps

2. SFP Heat Exchangers

3. RHR Heat Exchangers

4. RHR Pumps j

5. Secondary Heat Exchanger i REFERENCE FNP 1987 License Retraining Objectives Cycle 2, OPS-52102G, items 2&3 FNP 1987 License Retraining Cycle 2, Volume 1, OPS-52102G, fig. 2 1 008000K101 ..(KA's) j t

COMMENT j i

'A recent change to the plant has included the oil cooler for the  !

charging pumps as a CCW load. A knowledgeable individual may list RHR pump,'RHR Hx, SFP Hx, charging pump seals, and charging pump oil coolers as the 5 loads.

RECOMMENDATION Accept any 5 answers listed below:

1. SFP Hx. I

2. RHR Hx.

3. RHR pumps.

4 Secondary Hx.

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5. Charging pump oil coolers. '

6. Charging pump seals.

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2.14 (2.00)

QUESTION What are FOUR sources of hydrogen in the containment structure following a Design Basis Accident?

ANSWER

1. RCS H2 inventory. "

2. Zirc-water reaction.

3. Radiolysis of core and sump water. <

4. Aluminum - Na0H reaction.

REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52102D, item 2 028000K503 ..(KA's) -

COMMENT Two additional sources of hydrogen in the containment following a DBA are iron-water and aluminum-water reactions. These reactions were discussed in retraining class.

RECOMMENDATION Accept these two additional reactions as part of the total 4 responses required for full credit. (Reference pages 43 and 44 of Mitigating Core ,

Damage lesson [0PS-532].)

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. um 4.07 (0.50)'

-QUESTION True or False?

Auxiliary'feedwater flow to any steam generator.must be limited to 150 GPM maximum any time that steam generator's level drops below 25%. In an eaergency, however, this flow limit may be disregarded.

ANSWER 1

True REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52102H, Item 3. i FNP-1-SOP-22.0, Caution Note.following Step 4.5.3.

061000K101. ..(KA's) 1 COMMENT

-In accordance with the reference cited, the limitation of 150 gpm only applies if S/G 1evel has dropped below 17%, then the limit applies until level is restored above 25%. )

RECOMMENDATION Change the answer key to false.

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l l 4.08 (2.00)

l. QUESTION Assume the reactor is operating at power with the control rods in automatic. According to FNP-1-A0P-19.0 " Malfunction of Rod Control System":

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a. What are the TWO imediate operator actions for a continuous bank  !

l insertion? J 1

b. What are the TWO immediate operator actions for a single dropped ]

rod? i ANSWER

a. 1. Place the bank selector switch in MANUAL.

2. If rod motion does not stop, then trip the reactor (and refer to EEP-0).

b. 1. Place the rod bank selector switch in MANUAL.

2. Place the turbine on HOLD.

REFERENCE FNP Tng Obj for Licensed Operator Retraining, Cycle 1, OPS-52201E Item 8 FNP-1-A0P-19.0, pp. 2-3.

0010SGA014 ..(KA's)

COMMENT A recent change to our AOPs has changed the first immediate operator action for a continuous rod bank insertion.

RECOMMENDATION Modify the answer key for part A-1 to read as follows:

" Attempt to stop rod motion by placing bank selector switch in AUTO or MANUAL."

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5.02 (1.00) q l

QUESTION In order to maintain a minimum 200 F subcooling margin in the RCS when l reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately: )j i

a. 200 psig

b. 245 psig

c. 260 psig

d. 275 psig ANSWER  !

l d

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i REFERENCE

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Steam Tables NVREG-1122 193003K117, 193008K115 FNP 1987 License Operator Retraining Cycle 4, Review Material,

p. HT-8/11 193008K115 193003K117 ..(KA's)

COMMENT An apparent mistake was made in the calculation. Using 1600 psig with 200*F, subcooling has a saturation pressure of approximately 265 psia or 250 psig. The correct value falls between choice b and c, although neither is correct.

RECOMMENDATION Accept either b or c as a correct response.

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i 5.03 (2.00)

QUESTION

a. Define.the term Departure from Nucleate Boiling Ratio (DNBR).

b. As the reactor coolant pressure decreases, explain how the DNBR changes INCREASE, DECREASE OR NO CHANGE and WHY.

ANSWER

a. The ratio of the heat flux that will cause DNB at some point to the  ;

actual heat flux at that point in the reactor.

b. As pressure drops the coolant is closer to saturation conditions.

Thus the DNBR decreases.

REFERENCE FNP 1987 License Operator Retraining Cycle 4, Review Material, p. HT-37 FNP 1987. License Retraining Objectives Cycle 4, OPS-309, item 6 193004K110 ..(KA's)

COMMENT Another way of describing DNBR would be using the terms critical heat flux (CHF) divided by actual heat flux (Q), or, simply, CHF/Q. This is the definition of DNBR used on page HT-2 of the reference material provided.

RECOMMENDATION Accept CHF/0 as a correct response.

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a c. . ,

.6.01 (1.50)

QUESTION State the RCP precaution / limitation associated with each statement

.below. (ONE precaution / limitation per statment.)

a. Ensures adequate seal water flow to.#2 seal. l

'b. Ensures #1 seal not riding on runner,' minimizes possibility of seal damage.

c. Provides overpressure protection during solid plant operation.

ANSWER I

a. Minimum back pressure of 15 psig on RCP #1 seal by maintaining at least 18 psig-in VCT.

.b. Minimum of 200 psid maintained across #1 seal (OR) RCS pressure

> 400 psig

c. Verify open loop 1A and 1C RHR suction and discharge valves prior

'to starting any RCP.

REFERENCE d FNP 1987 License Retraining Objectives Cycle 1, OPS-521010, item 5 003000K602 003000K104 ..(KA's)

COMMENT For part a of this question, candidate may respond with only 18 psig in the VCT because this is the only pressure that can be observed from the MCB.

For part c of this question, only the suction valves are required to be open. The four valves specified in the objective cited are the A and B train suction valves for each loop; this is supported by technical specification 3.4.10.3.

RECOMMENDATION For part a of this question, accept maintaining at least 18 psig in VCT for full credit.

For part c of this question, delete discharge valves from the answer key.

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7.03 (1.00)  !

QUESTION According to A0P-4.0, " Loss of Reactor Conlant Flow". Which one of the following is a true statement?

a. Reactor trip will occur if flow is lost in one loop above 35%.

TURBINE power.

b. -Steam generator water level will decrease on the loss of a RCP in the affected loop.

c. Reactor trip will occur if turbine power is above 10% and flow is lost in one loop.

d. Steam generi. tor water level will not be affected in the loop with the loss of a RCP.

ANSWER b

\

REFERENCE '

FNP-1-A0P-4.0 Loss of Reactor Coolant Flow 000017K103 ..(KA's)

COMMENT Part a may be construed by the candidates to be the correct answer. It

. s reasonable for a knowledgeable individual to assume that reactor power will be above 35% if turbine power is above 35%. Also, the key answer for part b is the initial response of S/G 1evel; S/G 1evel will probably rise in the long term.

RECOMMENDATION l

Accept either answer a or b for full credit.

-1 d:,4* c.

I 7.10 (1.00) I QUESTION Which one of the following is an imediate action in accordance with A0P-9.0, " Loss of Train A or B Component Cooling Water"?

a. When high bearing temperature is indicated, then trip the RCPs.

b. If CCW surge tank indicates system leakage, then determine the location and isolate.

's . If required, fill the CW surge tank to -the normal level.

d. Refer to Technical. Specification 3.7.3.1 for limiting conditions  ;

for operation.

ANSWER a

REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 2, OPS-52102G, item 7 000026K303 ..(KA's)

COMMENT The key answer answer provided was correct prior to a recent change in our A0Ps. Selection a is no longer an immediate operator action, so there is no correct answer to this question.

RECOMMENDATION Delete this question from the examination.

L 7.11 (1.50) i QUESTION While in EEP-0, " Reactor Trip or SI", at step 15 the STA reports the following information:

Containment Pressure is 4.2 psig,.subcooling is 25 degrees based on core exit thermocouple and 50 degrees based on hot leg indications. Also ,

pressurizer level is at 5%, RWST is at 21 feet ?n6 CST is at 4 feet. l In accordance with the foldout page for EEP-0, WHAT action (s) are  !

required?

ANSWER

1. Verify SI actuated. _

2. Use adverse Containment condition numbers during procedure.

3. Shift AFW pump suction to service water. ,

REFERENCE FNP Exam 0'lestions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 3, OPS-52302, item 2 i FNP-1-EEP-0 foldout page 000007K301 ..(KA's)

COMMENT Due to the fact that being at step 15 indicates that all the steps of SI being actuated have been accomplished, the candidates may not respond to verify SI actuated. The subcooling requires that RCPs be tripped if at least one charging pump is running.

RECOMMENDATION Delete the requirement for SI actuated and include tripping of RCPs as a requirement for full credit.

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7.13 (2.00)

QUESTION List the FOUR immediate operator actions for FRP S.1, ATWT. l l

ANSWER I

1. Verify reactor Trip.

2. Verify Turbine trip indicated by all turbine stop valves closed.

3. Verify all available auxiliary feedwater pumps running.

4. Detenmine if ems'egency boration is required.

REFERENCE j FNP 1986 License Retraining Objectives, Emergency Response Procedures, item 8 000029K312 ..(KA's) i COMMENT The intent of the second step of the procedure is met by stating, )

" verify turbine trip". The method of accomplishing this is to check all '

stop valves closed.

RECOMMENDATION Accept " verify turbine trip" for full credit of part 2 of the answer key. i l

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1 8.15 (2.00)

QUESTION State the FOUR Technical Specification operability requirements associated with the accumulators in mode 1. Include applicable values and limits.

ANSWER

1. Isolation valve open.

2. Volume between 7555 (34%) and 7780 (58%) gals.

3.- Boron concentration 1900-2200 ppm.

4. Nitrogen cover pressure between 601 and 649 psig.

REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 Licence Retraining Objectives Cycle 3, OPS-52102B, item 7 191001K105 ..(KA's) j COMMENT The answer key for part 2 minimum volume apparently has.a typographical I error in it. The Technical Specification minimum volume in percent is 31.4, while the' answer key has 34%.

RECOMMEN0ATION Accept either the volume in gallons or volume based upon the level alarms as correct response for part 2 of the answer.

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ENCLOSURE 4 i

REQUALIFICATION PROGRAM EVALUATION REPORT l FACILITY: J. M. Farley Nuclear Plant >

EXAMINERS: Moorman, Rapp, Hemming, Picker, Jensen DATES OF EVALUATION: June 22-26, 1987 i AREAS EVALUATED: X WRITTEN X ORAL X SIMULATOR l EXAMINATION RESULTS:

R0 SRO TOTAL EVAL Pass / Fail Pass / Fail Pass / Fail (S,M,U)

Written Examination 6/6 12/12 18/18 S Operating Examination Oral 6/6 12/12 18/18 S Simulator 6/6 10/12 16/18 S s

OVERALL PROGRAM EVALUATION Satisfactory S Marginal Untisfactory i

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