ML20212D912

Forwards Comments Re Written Exam on 860616,w/intent of Providing Assistance to NRC Examiners in Establishing Appropriateness of Exam Questions

ML20212D912
Person / Time
Site:	Browns Ferry
Issue date:	06/22/1986
From:	Champion A TENNESSEE VALLEY AUTHORITY
To:	Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20212D722	List: ML20212D850 ML20212D912
References
NUDOCS 8608120587
Download: ML20212D912 (44)

Text

,.

ENCLOSURE 3 TENNESSEE VkLLEY AUTHORITY Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35602 Mr. John Munro, Chief Operator Licensing Section U.S. Nuclear Regulatory Connaission, Region II 101 Marietta Street, NW Atlanta, Georgia 30323

Dear Mr. Munro:

In accordance with the provisions of NUREG-1021 " Operator Licensing Examiner Standards," Standard ES-201, Section H.1, enclosed are conuments by the Browns Ferry Operator Training Section staff concerning the written examinations administered at Browns Ferry Nuclear Plant June 16, 1986.

The enclosed comments are offered with the intent of providing assistance to the NRC examiners in establishing the appropriateness of the examination questions; e.g. concerning those questions which require rote memorization without reference material, whether the question was appropriate given the level of technical expertise required, and whether the learning objectives established for the accelerated retraining program were exceeded. Also, the comments serve to clarify and expand the answers on the NRC answer key as rupported by TVA reference material.

With respect to any questions deleted, NRC is requested to consider allowing the examinee full credit for these questions in light of the time, effort and concentration required of the examinee.

These comments are respectfully submitted, and it is hoped the enclosed conuments and proposed resolutions afford the examinees every opportunity to sucessfully pass the examination based upon the knowledges and skills required

to safely operate the facility.

Very truly yours, I

TENNESSEE VALLEY AUTHORITY 0 2 %pa A. R. Champion, Acting Supervisor BFN Operator Training Group 8608120587 860801 PDR ADOCK 05000259 V PDR - _

l An Equal Opportumty Employer

r

?

John Munro Enclosures cc (Enclosures):

r n. Brockman/

Operator Licensing Branch NRC Region II 101 Marietta St.

Atlanta, GA 30323 Gary Sly ,

Pacific Northwest Laboratory Bate 11e Blvd.

Richland, Wash. 99352 I

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R0 HLT l Section 1 )

i

,,- l 1.01

• Problem:

i

a. Answer should read as follows: Since the major production and removal of xenon are based on two independent variables, flux and decay, Io vs. power is not linear.

b. Answer should read as follows:

No. Peak on downpower occurs in 4-6 hrs. (.5) Peat following a scram occurs in 7-11 hrs. (0.5)

Comment:

The question was derived from old material.

Resolution:

Answers as stated are not drawn from currently used material. Students should not lose points for not~ mentioning zenon peak time varies by the square root of power in part "b".

Reference:

GE Academic, Rx. Theory Text, Chapter 6.

6-22-86

R0 HLT Section 1 l

1.02 problem:

Answer as stated is not as students were taught. The question should be deleted since the formula sheet does not contain the transient period equation which is needed to explain this answer. (NUREG 1021 ES202, page 6 of 6).

Comment:

ReactorperiodwillreachinfinitywhentheAp+fE term is equal to zerowhichcanoccurwithanet+pinthecere,buta-fE to overcome it. Therefore, if rod insertion is stopped the E = 0 and with a +p in the core, the reactor is supercritical.

OR As rod insertion is started, a prompt drop in reactor period is ceen due to the immediate decrease in prompt neutron population. As rod insertion is stopped this rate of prompt neutron population decrease is stopped which effectively causes a prompt jump. Therefore, if the rod was stopped at the instant the reactor was critical, this prompt jump will cause the reactor to return to a slightly supercritical state.

Resolution:

The question should be deleted or accept the answer in comment section.

Reference:

Rz Theory Text, Chapter 4.

6-22-86 I

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R0 HLT Section 1 1.03b Problem:

Answer as stated is not from current material. NRC should accept the following as correct. I Comment:

For change in void coefficient reactivity from BOL to EOL, NRC should accept "no change". The current reactor theory text states the following concerning void coefficient with respect to core age:

" Depending on core-design and exposure, the veld coefficient may increase, decrease, or remain the same." Rather than generalizing av with core age, it is more appropriate to discuss some of the individual parameters of core age and their effect on av.

Resolution: -

Answer key should be adjusted to accept 'no change'.

Reference:

Ex. Theory Text Chapt. 4 page 4-22 & 4-23. -

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R0 HLT Section 1 1.04.

Problem:

The answer as stated in the key is not from current material.

Resolution:

NRC should accept the following for full credit on the effect of shallow rod rovement on power:

" Shallow rod movements affect the axial power shape and have little affect on core power."

Reference:

Ex Theory Text, Chapt. 5; page 5-25.

1.05 Problem:

GOI 100-1 does not clearly define ' minimum permissible sustained period permitted'.

Comment:

The candidates ability to resolve the problem, should be examined based on 60 sec. or 30 sec.

Resolution:

NRC should accept full credit for use of 30 seconds or 60 seconds period, since GOI-100-1 does not specify the" minimum permissible sustained positive period permitted". (pages attached)

Reference:

GOI 100-1 (attached) 6-22-86

R0 HLT Sectirsn 1 1.08d Problem:

The answer key accepts a i 50 psig pressure range, but does not give tolerance for temperature.

Comment:

The reactor temperature part of the answer should include a range the same as for reactor pressure. The second part of answer should read:

445'F - 467'F. Temperatures listed are Tsat for pressures given in answer.

Resolution:

The answer key should be expanded to accept 445-4670F

Reference:

Combustion Engineering Steam Tables 1.09a Problem:

The answer key states static pressure, but other terminology could be used.

Comment:

NRC should also accept " total pressure available" in place of " static pressure" for full credit. The pressure is a combination of system pressure and static pressure, minus head losses.

Resolution:

Answer key should be expanded to accept ' total pressure available'

Reference:

GE Heat Transfer and Fluid Flow, Chapter 6.

6-22-86

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RO HLT Sectior. I 1.09b Problem:

Answer key does not agree with material used.

Comment:

2. The correct answer is increase (vs. decrease). If FW heating is lost, downcomer subcooling will increase, therefore P sat Of fluid being pumped decreases and available NPSH increases.

3. The correct answer is decrease. As speed increases P available at pump suction decreases due to increased head losses. Same question was asked on the RO requalification examination and the answer was decrease, which is correct and is the way it was taught.

Resolution:

The answer key should be changed, to give full credit for these responses:

1.09b 2. - increase 1.09b 3. - decrease

Reference:

l GE Heat Transfer and Fluid Flow, Chapter 6 1.14 l Problem / Comment:

The phrase "several hours" is not clear enough to answer the question.

(Several is defined in the dictionary as more than two and fewer than many) The first 2-6 hours, which is several, rods would have to be withdrawn and following this, which is several hours, rods would have to be inserted.

Resolution:

Answers a or e accepted for full credit.

Referenc_e:

i GE Reactor Theory, Chapter 6 6-22-86 l

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l R0 HLT Section 2 2.01 Problem:

Candidates were given a list of components to place in sequence. Five of the eight listed have parallel flow paths.

Comment:

Due to the fact that components #1 (SPE condenser), #3 (Off-gas condenser), and #4 (SJAE condenser) are parallel. Also #2 (Start-up bypass valve), and #6 (Reactor feed pumps) are parallel. The order in which they are listed should be accepted.

Resolution:

Components #1, #3, #4 should be accepted in any consecutive sequence.

Components #2 and #6 should be accepted as #2, #6 or #6, #2.

Reference:

OPL171.011, Figure 1.

2.03 Problem:

A typographical error in the problem, suction head versus suction header, may have led to confusion.

Comment:

The responses of the candidate will have to be reviewed to determine if this tIpo caused any misunderstanding.

Resolution:

The review of responses will determine the validity of the question.

If any one candidate responds incorrectly, his response should be validated. Did he respond correctly to a wrong assumption? Another option would be to delete the question.

Reference:

OPL171.048 6-22-86

l R0 HLT Section 2 2.05 Problem:

Answer key needs to be expanded to include all responses from our material.

Comment:

a. OPL171.016 page 25 states ' reduce pressure increase due to Hydrogen on a LOCA' as a reason for inerting.

b. Air space is for 'non-condensibles'.

Resolution:

a) 2.05a: should accept reduce pressure increase due to Hydrogen on a Loss of Coolant accident as well as reduce potential explosive concentrations of Oxygen and Hydrogen.

b) 2.05b: answer key should be changed to 'non-condensibles' in free air space.

~

Reference:

OPL171.016 l

l 6-22-86 l

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M HLT Section 2 2.06 Problem:

Answer key is not complete.

Comment:

a. 2.06b answer key should be expanded to accept:

(1) 'SLC Loss of Squib valve continuity' (OI-63 III D 3.b.2 page 4)

(2) 'SLC Injection Flow' (OI-63 III D3.d page 4)

b. 2.06c: The boron concentration 660 ppm and 1075 ppa are not referenced in our material. The Tech Spec. minimum is 600 ppm.

with 25% for conservatism (600 ppm + 150 ppm = 750 ppa.) to compensate for ' imperfect mixing'. RHR dilution flow is not addressed in our Lesson Plan or Technical Specification. Full credit should be given for imperfect mixing.

Resolution:

Answer key should be expanded to accept comment a) 1 and 2; comment b) -

' imperfect mixing' should receive full credit.

Reference:

OPL171.039 page 13 and T.S. p. 140 and 141 BFARP panel 9-5

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6-22-86 i

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RO HLT Section 2 2.09b Problem:

The answer key is not complete Comment:

a) OI-66 states any combination of Hi-Hi-Hi, downscale or inop trip occurring simultaneously in both trip channels, will isolate FCV66-28. Since this entails different conditions, more than one answer could come from this statement, b) Loss of power causes closure of FCV 66-28 and should be added for full credit.

Resolution:

Expand answer key to accept any combination of Hi-Hi-Hi and downscale/inop occurring simultaneously in both trip channels; and Loss of Power to FCV 66-28.

Reference:

OI-66, OPL171.030, OI-57 pages 95,97.

6-22-86

RO P..T Section 2 2.15 Problem:

The alarm ' Control Seal Leak Abnormal' is common to High or Low flow.

This alarm warns of possible failure. The ARP instructs the operator to monitor #2 seal cavity pressure. This pressure will increase on: a failure of #1 seal or plugging of #2 restricting orifice. Therefore, control room indications will be similar for both failures, and responses a or d are equally correct.

Comment:

At BFN (see attached ARP) the alarm is ' Control Seal Leak Abnormal'.

Answer a or d should be accepted due to the fact that the alarm is brought in by High or Low Seal Leak Flow and #2 seal pressure increases for both type failures.

Additionally, as part of program delivered to candidates ('Eram taking Techniques') they are instructed, on multiple choice questions, when they see a correct answer to mark it and continue to next question.

Resolution:

i Response a or d should be credited, and are equally correct.

Reference:

OPL171.007 Fig. 3; Alarm Response Procedures l

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6-22-66

R0 HLT Section 3 3.01 Problem:

The answer key should be changed to RPS specific functions. The clarification given by the Proctor specified all instruments of the same variable and reference leg. Our normal control range reference legs contain RPS assigned pressure switches.

Comment:

a. Normel Control Range contains the scram Bartons 203A, B, C, D.

These switches perform RPS and PCIS functions. (OPL171.003 page 11.)

b. Emergency System Range does not perform RPS trip functions, only ECCS and PCIS functions. We teach " specific functions" (ie PCIS, ECCS, or RPS). This range does protect the reactor but is not RPS specific. OPL171.003 indicates which trip functions are performed. (pg. 14.)

Resolution:

3.01a answer key should state: used for trip functions.

3.01b answer key should state not used for trip functions.

• The question clarification given by the examiner specified all instruments off the same variable and reference leg, not just the level indicators.

Reference:

OPL171.003 pages 11.14 6-22-86

R0 HLT Section 3  !

l 3.05 l Problem:

Expand answer key to accept OI-69 setpoint.

Comment:

l Per OI 69, page 1, high temperature in the equipment area or floor i drains will cause isolation at 170*F. Technical Specifications give 1 160-180*F as the setpoint range.

Resolution:

Answer key should accept 160 - 1800F or 1700F for full credit.

Reference:

OI-69 page 1, T.S. table 3.2.A page 56.

3.07a Problem:

Answer key should be adjusted for terminology used in lesson plan.

l Comment:

Our load shedding logic (480v) is looking for an accident signal and loss of normal AC power. Loss of normal AC is signified by diesel generator voltage available. This DGVA relay initiates 480v load shedding and is signified by a D/G being the only source to a shutdown board.

l Resolution:

The following should be accepted and receive full credit for ' Loss of Normal AC Power and Accident Signal':

a) Initiation of 480 v Load Shed Logic or b) Accident signal and D/G powering a shutdown board.

l

Reference:

l OPL171.047 6-22-86

l l

R0 HLT l Section 3 l 3.12 Problem:

When a group 2 PCIS signal is received the TIP receives a withdraw signal, which internally shifts to manual reverse mode.

Comment:

l An operator needs to verify that withdrawal has begun when a Group 2 )

PCIS is received. Primary Containment integrity should also be verified by ' ball valve closure'. The actual internal circuitry is beyond the scope of knowledge required to operate safely.

Resolution:

Full credit should be given for response that includes withdrawal of TIP and includes closure of ball valve.

Reference:

OPL171.023 3.13 Problem:

The answer key assumes minimum level assignment input requirements; however, these are not found in our Technical Specifications.

Comment:

3.13b - The Technical Specification in effect at BFN have no requirements for minimum number of operable LPRM's per given level.

(Ref. T.S. 3.1 section)

• Resolution Credit should be given for a 'yes' response since BFN requires 14 operable LPRM inputs for a channel to be operable.

i

Reference:

i T.S. page 36 notes for Table 3.1.A i

6-22-86

R0 HLT Section 4 s

4.01 Problem:

Answer key should be adjusted to accept a different answer.

Comment:

4.01a " Valve being open" should receive full credit since the question stated that power would be removed. To remove power requires turning power off at the breaker.

4.01b - If resetting at the RCIC turbine is assumed, then answer key is correct. However,- RCIC must be reset manually from the control room on any trip. Since the question did not indicate if the action was local, alther answer should receive full credit.

Resolution:

Expand answer key to extend full credit for responses above.

Reference:

OI-71 x

4.04 Problem:

The answer key is not complete per our procedures.

Comment:

Radiation area (< 100 mr/hr.) should be added to answer key.

Resolution:

Expand answer key to accept < 100 mr/hr, ar definition of radiation area.

Reference:

RCI-1 page 20 6-22-86

RO HLT Section 4 I

4.05 i Problem:

Answer key did not include response "e".

Comment:

During training the Technical Specification requirements on page 35 note 7 were stressed for a suberitical and < 2120F reactor. This note requires responses: b,c.e.g.

Resolution:

Expand answer key to include "e".

Reference:

RPS table 3.1 notes: #7 page 35 9

4.07 Problem: -

The answer key did not include all steps listed in the referenced procedure.

Comment:

Answer key should be expanded to include all steps of the referenced procedure.

Resolution:

Full credit should be given for candidates who respond with: ' check RFPIs and main turbine on turning gear with oil pumps on'.

Reference:

l EPM - Control Room Abandonment.

i 1

i 6-22-86

RO HLT Section 4 4.08 Problem:

Answer key has incorrect water level limits and drywell temperature.

Comment:

Pool level > -1 inch or <- 6.25 inches; drywell temp. of 1600F are correct.

Resolution:

Answer key should be changed to give full credit for > -1 inch or

<- 6.25 inches, and drywell temp. of 1600F.

Reference:

E0I-2 entry conditions.

4.09 Problem:

This exam question was written from an out of date procedure.

Comment:

This caution has been deleted from the E0I's and is not applicable.

Resolution:

Delete from the exam.

t

Reference:

E0I-2 (attached) 6-22-86

R0 HLT Section 4 4.10 Problem:

The question referenced a statement taken from old E0I's and not the latest revision. The graph is a plot of Suppression Chamber Temperature vs. Drywell Pressure, not D/W Temperature vs. Drywell Pressure.

Resolution:

The basis of the curve as found in the E0I LP and App. A EPG's is as follows:

Prevent exceeding the negative design pressure of containment (D/W &

suppression pool) upon initiation of D/W sprays.

The above should be accepted for full credit.

Comment:

The rate of depressurization is no longer limiting on this curve. The rate of depressurization limit was based upon having two separate D/W ~

spray curves, one based on a 100% humidity D/W condition and the other -

addressing a 0% humidity condition. The low humidity condition is the most limiting because of " evaporative cooling" occurring, result in a depressurization rate beyond the capacity of the vacuum breakers. This graph and concern is done away with by limiting the flow rate of drywell spray and subsequencly there is one drywell spray curve. This has bean done at BFN. Tho current curve ensuras that adequate air /non-condensibles are in the suppression chamber prior to initiating sprays, such that negative design pressure is not exceeded.

1

Reference:

EPG Appendix A, OPL155.001 1

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6-22-86

RO HLT Section 4 4.12 Problem: ,

The answer key was developed from old material.

Comment:

The new E0I's were sent and the answer key should be changed to reflect these entry conditions.

Resolution:

The answer key should be modified as follows:

(1) Ex water level below +11 inches (low Ex water level scram setpoint) either acceptable (2) Ex pressure above 1043 psig (high Rx pressure scram setpoint) either acceptable (3) Drywell pressure above 2.45 psig (high drywell pressure scram setpoint) either acceptable (4) A condition which requires a reactor scram, -

and Rx power above 3% (APRM downscale trip) either acceptable or cannot be determined (5) A condition which requires a MSIV isolation

Reference:

E0I-1 l

6-22-86

RO HLT Section 4 4.15.

Problem:

The answer key is incorrect.

Comment:

Defeating of ADS in the situation mentioned has nothing to do with the answer. The answer actually describes one of the three reasons the operator enters C-5 and why the actions for control of water level are different in C-5 than in RC/L.

Resolution:

The answer key should be changed to give full credit for the correct answer which should include the following:

" ADS is disabled as long as Ex shutdown is not assured (or may be contingent upon SLC) to prevent injection of ECCS (large volumes of relatively cold water) which may result in a reactor power excursion leading to substantial core damage.

Reference:

E0I 7P155.001 (attached)

Resolution:

NONE 4.16b. Problem:

The " Flag System" per Plant Operations Review Committee E0I's was deleted and the new method of carrying out setion was implemented per E0I-1 section 4.0, paragraph 4.10.

Comment / Resolution:

NRC should also accept " action is required and you will be directed to take that action."

Reference:

E0I-1, Section 4.0, paragraph 4.10 6-22-86

SRd HLT Section 5 5.01 Problem / Comment:

Answers as stated are not drawn from currently used material. Student should not lose points for not mentioning zenon peak time varies by the square root of power in part "b".

Resolution:

a. Answer should read as follows: Since the major production and ,

removal of xenon tre based on two independent variables,' flux and )

decay, Ie vs. pc se is not linear. i

b. Answer should read as follows:

No. Peak on downpower occurs in 4-6 hrs. (.5) Peak following a scram occurs in 7-11 hrs. (0.5)

Reference:

GE Academic, Rx. Theory Text, Chapter 6.

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SRO HLT Section 5 5.02 Problem:

Answer as stated is not as students were taught. The question should be deleted since the formula sheet does not contain the transient period equation which is needed to explain this answer.

ES202, page 6 of 6). (NUREG 1021 Consnent:

Reactorperiodwillreachinfinitywhenthe4+htermisequalto zerowhichcanoccurwithanot+pinthecore,buta-htoovercome it.

Therefore,ifrodinsertionisstoppedtheh=0andwitha+p in the core, the reactor is supercritical.

~~

OR As rod insertion is started, a prompt drop in reactor period is seen due to the immediate decrease in prompt neutron population. As rod insertion is stopped this rate of prompt neutron population decrease is stopped which effectively causes a prompt jump. Therefore, if the rod was stopped at the instant the reactor was critical, this prompt jump will cause the reactor to return to a slightly supercritical state.

Resolut. ion:

The question should be deleted or accept the answer in comment section.

Reference:

Ex Theory Text, Chapter 4.

6-22-86

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SRO HLT.

Section 5 5.05 Problem / Comment: ,

Answer key used wrong " rated core flow".

Resolution:

100% core flow is 102.5 x 105 lbm/HR, not 108.5 x 10' lba/HR. The correct value should have been provided.

For Condition 1

% core flow = 54.25/102.5 = 53%

from Figure 3.5.2, Kr = 1.18 i .03 + (should have therefore the CPRLIM = 1.26 (1.18) = 1.487 ranges for this) delta (MCPR) - 1.57 - 1.487 = .083 For Condition 2

% core flow = 81/102.5 = 79%

from Figure 3.5.2, Kr = 1.07 i .03 +

(should have therefore the CPRLIM = 1.26 (1.07) = 1.348 ranges for this) delta (MCPR) = 1.37 - 1.348 = .022 Condition 2 is closer to limits

Reference:

OPL171.007 Lesson Plan; U1 Tech Sp6 s

5.07b Problem:

Answer as stated is not from current material.

Resolution:

NRC should accept following as correct:

For change in void coefficient reactivity from BOL to EOL, NRC should accept "no change". The current reactor theory text states the following concerning void coefficient with respect to core age:

" Depending on core design and exposure, the void coefficient may lacrease, decrease, or remain the same." Rather than generalizing av with core age, it is more appropriate to discuss some of the indiviudal parameters of core age and their effect on av.

Reference:

Rx. Theory Text, Chapter 4, pages 4-22 and 4-23 6-22-86

SHO HLT Section 5 5.07c Problem / Comment:

Agree with the direction of change for the moderator temperature coefficient. Disagree with void and fuel coefficient. The change in fuel temperature cannot be determined. Cannot really state the direction of change for the void coefficient for a down power condition from 100% to 50%. The candidates were instructed that void content i DECREASES from 100% rod pattern (50% power) and minimum recirc speed to 100% rod pattern and rated recirculation (core) flow. Therefore, on a decrease in reactor power from 100% to 50%, the void fraction will INCREASE. The candidates were also instructed that the void coefficient becomes MORE NEGATIVE as void content increases and less negative as fuel temperstare decreases.

Conclusions:

1. The answer for the direction of change in void coefficient is not an absolute since two parameters are changing which have opposite affects.

2. A definite statement CANNOT be made that "the fuel temperature

' change will be smaller," based on the information provided, since the change in av versus power is not readily known and aD versus power is constant.

Resolution:

The reference used in the answer key was outdated material. Part 'c' of question should be deleted.

References:

Reactor Theory, General Electric Company, Page 7-19, 4-19/20 and Figure 4-23.

1 6-22-86

SRO HLT Section 5 5.08 Problem:

The guestion in part 'b' refers to Points A, B, and C. The attached drawing did not show any such labelled points. The copy given the facility did not have these points marked.

Comment:

On a timed examination, more care should be used to ensure that all necessary information is available for applicant.

Resolution:

The 'b' part of this question should be deleted.

Reference:

NRC Examination

. 5.09 Problem:

Question approach is beyond scope of SRO knowledge. Formulae needed to answer were not on the formula sheet provided.

Comment:

The ability to answer part "a" is totally based on making the assumption that all flow from tank via pump stops when it loses NPSH and starts cavitating. This is not a realistic assumption and all operators know a pump will pump a lot of water and last a long time if NPSH is lost.

Resolution:

Delete part 'a' from question.

I 6-22-86

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SR0 HLT Section 5 5.10 Comment:

According to our procedures, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

Resolution:

Should also accept for full credit the following actions:

" initiate corrective action to restore limit within 15 minutes."

Referonce:

Tech Spec Section 3.5.I.

5.13 Problem / Comment:

The phrase "several hours" is not clear enough to answer the question.

(Several is defined in the dictionary as more than two and fewer than many.) During the first 2-6 hours, rods would have to be withdrawn and subsequently, rods would have to be inserted. Both time periods could be considered "several hours."

Resolution:

Answers a or e should be accepted for full credit.

Reference:

GE Reactor Theory, Chapter 6 6-22-86

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SRO HLT l Section 6 6.01: Problem:

Answer key is not correct.

Comment:

Normal Control Range (GEMAC) contains the Scram Bartons 203 A, B C, D.

These switches perform RPS and PCIS functions. Emergency System Range (Yarway) does not perform RPS trip functions, only ECCS and PCIS functions.

Resolution:

Change answer key to:

Normal Control Range (GEMAC). Accept this for full credit.

Reference:

BFNP, OPL171.003 Lesson Plan D

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SRO HLT Section 6 6.02 _ Problem: 1 1.

The question does not require as much detail as the answer key requires.

2. The answer key for part 'b' does not include the " Explain how" part of the question.

Comment:

Part 'a' - To receive full credit for this question, < 130 psid across the valve should not required. This is not a " reason", but a mechanical limitation of the system.

Resolution: -

Part 'a' - Answer should be:

1. To equalize pressure across the valve (s)

2. To allow for warming of the turbine prior to rolling (shell and/or chest warming)

Part 'b' - Answer should be:

The purpose is to protect the turbine from overspeed on a turbine trip. If the turbine trips, air is bled from the air cylinder forcing the disc to fall partially down into the flow path. The disc slams shut if reverse flow begins to occur.

Reference:

BFN, OPL171.010, Page 10 and 11 l 6.03e.

i Problem / Comment:

The_e is no reference provided in the answer key for this question.

l The " Explain Why" portion of the question is not covered in the plant l training material and does not constitute part of the knowledge required to safely operate the plant.

Resolution:

The " Explain why" part of the question should be deleted.

Reference:

BFN OPL171.011 6-22-86

SRO HLT Section 6 6.04 a & c Problem / Comment:

Parts a and c of this question are not covered in the plant training material. The question asks for information which is well beyond the knowledge required for the safe operation of the plant.

Resolution:

Question 6.04 - Parts a and c should be deleted.

6.05a. Problem: -

Expand answer key to accept OI-69 setpoint.

Comment:

Per OI 69, page 1, high temperature in the equipment area or floor drains will cause isolation at 170*F. Technical Specifications give 160-180*F.

Resolution:

Answer key should accept 160 - 1800F, or 1700F for full credit.

Reference:

OI-69 page 1. T.S. table 3.2.A page 56.

6.10a. Problem / Comment:

l The answer key uses the phrase " Speed Demand Limiter"; this is not the l correct terminology for BFN and is not referenced on the figure provided.

Resolution:

Accept as correct answer for limiting component:

Master Controller. i

Reference:

NRC examination - Figure 474 BFN OPL171.008 Lesson Plan 6-22-86

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SRO HLT

. Section 6  ;

6.12 Problem:

Answer key should be adjusted for terminology used in lesson plan.

Comment:

Our load shedding logic (480v) is looking for an accident signal and loss of normal AC power. Loss of normal AC is signified by diesel generator voltage available. This DGVA relay initiates 480v load shedding and is signified by a D/G being the only source to a shutdown board.

Resolution:

The following should be accepted and receive full credit for ' Loss of Normal AC Power and Accident Signal':

a) Initiation of 480 v Load Shed Logic or b) Accident signal and D/G powering a shutdown board.

Reference:

OPL171.047 2 9

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SRO HLT Section 7  ;

7.01c. Problem:

The answer key is not complete per our procedures.

Comment:

Radiation area (< 100 mr/hr.) should be added to answer key.

Resolution:

Rxpand answer key to accept < 100 mr/hr, as definition of radiation area.

Reference:

RCI-1 page 20 -

7.03 Problem:

Answer Key is incorrect.

Resolution:

Change the answer key as follows:

above -1 inch vs -1 ft.

' below -6.25 inch vs -6.25 ft. ~

DW Temp. 160*F vs 165'F r

Reference:

E0I-2 page 1 7.04 Problem / Comment:

The Answer Key is not correct. The basis for defeating ADS in the situation mentioned has nothing to do with the answer given in the key. The answer key actually describes one of the three reasons the operator enters C-5 and why the actions for control of water level are different in C-5 than in RC/L.

Resolution:

The correct answer is:

" ADS is disabled as long as Rx shutdown is not assured (or may be contingent upon SLC) to prevent injection of ECCS (large volumes of relatively cold water) which may result in a reactor power excursion leading to substantial core damage.

Reference:

E0I LP155.001; attached.

6-22-86

SRO HLT Section 7 7.06 Problem / Comment:

The Answer Key is wrong and has you outside of the allowed operation curve for 75 psit Ha pressure.

Resolution:

The correct answers are:

a. Initial state: 1,2?5 120 MWE and 400 Kvar

b. Final State: 1,150 20 MWE and 550 Kvar

Reference:

GOI 100-1 o

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1 1

1 SRO HLT Section 7 7.07a. Problem / Comment:

The answer key requires more for full credit than the question would indicate is necessary.

Resolution:

" Valve must be opened" should receive full credit since the question stated that power would be removed. The removal of power requires turning power off at the breaker.

Reference:

OI-71, p. 3 7.07b. Problem / Comment:

The RCIC trip throttle valve has a local manual reset which must be reset after a mechanical overspoed trip and a remote (control room) reset which must be reset after any turbine trip. The question does not specify the manual reset, with which it is concerned.

Resolution:

Since the question did not indicate if action was local, then another ,

possible answer would be: Yes, all trips require manual electric ~

resetting of the trip throttle valve.

Reference:

OI-71, p.8 l

l I

/

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S R O Hl.T Sectiot, 7 7.10a. Problem:

Answer key is not correct.

Comment:

RCI-9, page 2, states:

"The RWP is issued for the duration of the job up to the end of the current calendar year."

Resolution:

Answer key should be changed to the above " Comment."

Reference:

RCI-9, p. 2 7.10b. Problem: ., .

Part 3 of answer key is not correct Comment:

RCI-9 does not state that the numbering scheme allows determination of -

whether or not the RWP is a routine RWP.

Resolution:

Delete this from the answer key.

Reference:

RCI-9, p. 1 and 10 i

6-22-86

SRO HLT Section 7 7.11 Problem:

The question referenced a statement taken from old E0I's and not the latest revision. The graph is a plot of Suppression Chamber Temperature vs. Drywell Pressure, not D/W Temperature vs. Drywell Pressure.

Comment:

The basis of the curve as found in the E0I LP and App. A EPG's is as follows:

Prevent exceeding the negative design pressure of containment (D/W &

suppression pool) upon initiation of D/W sprays.

The rate of depressurization is no longer limiting on this curve. The rate of depressurization limit was based upon having two separate D/W spray curies, one based on a 100% humidity D/W condition and the other addressing a 0% humidity condition. 'The low humidity condition is the most limiting because of " evaporative cooling" occurring, result in a depressurization rate beyond the capacity of the vacuum breakers. This graph and concern is done away with by limiting the flow rate of drywell spray and subsequently there is one drywell spray curve. This has been done at BFN. The current curve ensures that adequate air /non-condensibles are in the suppression chamber prior to initiating sprays, such that negative design pressure is not exceeded.

Resolution:

The following should be accepted for full credit:

Prevent exceeding the negative design pressure of containment (DW and Suppression Pool) upon initiation of D/W sprays.

Reference:

E0I Lesson Plan 6-22-86

SRO HLT Section 7 7.13 Problem:

The answer key did not include all acceptable answers.

Resolutions:

The answer key should be modified as follows:

(1) Rx water level be.1 w +11 inches (low Rx water level scram setpoint) either acceptable (2) Rx pressure above 1043 psig (high Rx pressure scram setpoint) either acceptable (3) Drywell przessure above 2.45 psig (high drywell pressure scram setpoint) either acceptable (4) A condition which requires a reactor scram, and Rx power above 3% (APRM downscale trip) either acceptable or cannot be determined -

(5) A condition which requires a MSIV isolation

Reference:

' *2 ,

E0I-1 7.14 Problem:

l The answer key should be expanded.

! Resolution:

NOTE:

Check REPT's and main turbine on turning gear with oil pumps on should be accepted as correct answers also.

Reference:

EPM - Control Room Abandonment i

6-22-86

I SRO HLT Section 8 8.01 Problem:

Answer key did not include response 'e'.

Comment:

During training the tech spec requirements on page 35 note 7 were stressed for suberitical and <212*F reactor. This note requires responses: b, c, e, g.

Resolution:

Expand answer key to include 'e'.

Reference:

RPS table 3.1 notes: #7 page 35 8.02 Problem: .

Answer key requires giving the surveillance number.

Comment:

Question stated that surveillance (SI) was being performed and did not specify that the applicant should state the SI number.

Resolution:

Accept for full credit: Yes (0.5), due to failure of SI(.5)

Reference:

BFNP Tech Spec; NRC Answer Key.

6-22-86

SRO HLT Section 8 8.03 Problem:

(a) The question states ' Applicable TSs are enclosed for reference.

(b) The candidate spent valuable time looking through enclosures for the Tech Spec.

and was informed Finally he asked the proctor if it was enclosed, "The information was pulled because it answered it out."

another question (8.01) and you should be able to figure Comment:

Questions 8.01 and 8.03 equal 20% of the section value, and require full memorization of the T.S. RPS tables. Operators are taught to utilize the Tech. Specs. and not operate from memory. Memorization of the information SRO knowledge. required to answer this question is beyond the scope of Resolution:

Delete the question.

Reference:

NRC SRO Examination; BFN T.S. Learning Objectives 8.06 Problem:

The attached Tech Spec lacked pages 243, 250-255, and Table 3.7.A which were stated as given to students on answer key. The question specified to answer "using the attached Technical Specifications."

Comment:

• Candidate would be unable to come up with the answer per answer key based upon the Tech Spec provided.

Resolution:

Following answer should be accepted for full credit, based upon the Tech. Specs. provided:

a.

Declare HPCI Inop. (based on MOV operability SI and definition of operable),

b. Must immediately demonstrate ADS logic, RCIC, LPCI, and CS operable.

Reference:

NRC SRO Examination; BFN T.S. Learning Objectives 6-22-86

SRO HLT Section B 8.07 Problem:

(a) No reference material included. On this section, the candidate was not provided the required reference material for 3 questions worth 7.5 pts (30%).

(b) Our student learning objective does not require memorization, but the ability to use the document.

(c) There is no 125V DC bus that furnishes control power to the control room.

Comment:

(a) 10 CFR 50.72 and 50.73 reporting requirements are the sole function of one person on shift. Documents BF 15.2 and 15.21 have been generated from 10 CFR as an aid to insuring compliance.

(b)

The five situations presented time constraints, without providing BF 15.21, and thus are beyond the scope of required memorization.

(c) Part "c" of question falls outside the realm of NUREG-1021, ES202, page 5, para. 15. -

, Resolution: '

Delete question from exam.

Reference:

BF SP 15.21; BFN Learning Objectives for Standard Practices 8.08 Problem:

Answer key has three parts (A, B, C) while question only had two parts.

Comments:

(1) The correct answer for part A is: False (2) The correct answer for part B is: True Resolution:

Correct answer key.

l l

Reference:

BF 12.24, page 8 6-22-86 i

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SRO HLT Section 8 8.09 Problem / Comment:

The terminology used in this question is internally inconsistent and inconsistent Browns Ferry.with BEN terminology. There is no " maintenance tag" at the " maintenance tag" or the " identification tag".The question is un Part 'a' tag is of Itconcern.

is unclear whether the " maintenance" or " identification" Part 'b' operator It is is unclear which tag (maintenance or identification) the retagging Part 'c' It is not clear that the opeator is performing a procedure at this point.

familiarization. He may be walking down the HPCI system for training or As to the " error".and " mistake" mentioned, it is unclear if these are the same problems or different problems. It is also unclear whether the error or mistake refers to the previous tagging problem or some new problem Part 'd'

- No equipment at BFN with hold order tags may be operated until the clearance is cleared.

Resolution:

Delete the question.

Reference:

BF 14.25 8.10 Problem:

The answer key does not include all possible answers.

Resolution:

Accept as a correct answer any of the items that are included on the Attachment 1 of OSIL 34 which is filled out in order to give the report.

Reference:

OSIL 34; Attached.

6-22-86

r-SRO HLT Section 8 8.13 Problem / Comment:

Part 'b'.

of the question is asking for the examinee to state the methods he should use to identify and sign-off steps or portions of the procedure which do not apply. The operator identifies the non-applicable are signed off by step theby SE. putting an N/A in the block and the N/A steps It is not specified that he must state how he knows if a step is required or can be marked N/A.

Resolution:

Full credit should be given for following answer:

1. Place N/A in procedure step

2. SE initials.

Reference:

GOI 100-1 8.14 Problem:

1 Unclear as to exactly what is required for credit Comment:

The applicant could have answered from the T.S. LCO requirements or from the Bases and could give two different correct answers for the same question.

Resolution:

Should also accept as a fully correct answer:

T.S. 3.3A.1 (p 120) - A sufficient number of control rods shall be operable so that the core could be made suberitical in the most reactive condition during the operating cycle with the strongest control inserted.rod fully withdrawn and all other operable control rods fully

Reference:

T.S. 3.3A.1 (page 120)

T.S. 3.3/4.1 Bases (page 127) 6-22-86

l SRO HLT Section 8 8.16 Problem:

As per Standard Practice 14.15 " Removal of Fire Protection Equipment from Service", STATE the requirements which must be met if a fire protection system is to be removed from service for testing or servicing for a period of time exceeding one (1) hour.

Key Answer

1. Establish an appropriate Fire Watch 2.

Implement plant procedures for the removal of fire protection equipment from service (PM, or designee approval; Posting of manual operating instructions near the manual actuation station or stationing of a properly instructed fire watch at the station).

Comment / Resolution:

The question and answer are word-for-word out of SP 14.15, however the part the answer is based on is missing an important phrase in the question which it " Fire Protection Systems may be removed from service for a period not to excoed one hour for testing or servicing." This implies that a test or service won't exceed 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />., then during the test it is discovered that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time limit will be exceeded. The question could have been read to imply that original intent is to exceed right 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> answer is: before the test or service starts. In this case the (1) have PM or designee approval (2) initiate from BF-31. (Implement Plant procedures for removal of fire protection equipment)

• Also some of the koy answer items deal with items having automatic functions (not specified in question).

Care must be taken to accept an answer based on the question and not only looking for word-for-word phrases out of an administrative procedure. The question could be answered as per answer key or as i

indicated above for full credit.

Reference:

SP 14.15 l

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