ML20247C981

Forwards Comments on Written Exam Administered on 890612, Per Discussion W/G Hopper

ML20247C981
Person / Time
Site:	Hatch
Issue date:	06/16/1989
From:	Nix H GEORGIA POWER CO.
To:	Casto C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20247C933	List: ML20247C928 ML20247C954 ML20247C981
References
LR-GM-015-0689, LR-GM-15-689, NUDOCS 8909140146
Download: ML20247C981 (11)

Text

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ENCLOSURE 3

' GIorgia Pow:r Company Post Office Box 439

Baxley. Georgia 31513 Telephone 912 367-7781 912 537-9444 x

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Edwin I. Hatch Nuclear Plant June 16, 1989 PLANT E. I. HATCH T&TTxam Comments Rtype: A04.43 Log:

LR-GM-015-0689 Mr. Charles Casto U. S. Nuclear Regulatory Commission Region II 101 Marietta Street Suite 2900 Atlanta, Georgia 30323

Dear Mr. Casto:

As previously discussed with George Hopper, our comments on the written examination administered June 12, 1989 are attached.

If you have any further quettions, please call Mr. Curtis Coggin at 912-367-7851, extension 2S96.

D/

General Mar.(ager Nuclear Plant H. C. Nix HCN/vcc attachments 8909140146 890906 PDR ADOCK 05000321 V

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Plant'E.I. Hatch Reactor' Operator and Senior Operator g g,'

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, Written License Examination Utility Comments

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June 12, 1989

QUEEU ON 2.Q1/L Q2 0M Question _2.01/5.02 asks candidate to select the' statement that provides the correct actions based lon the given conditions M

following'a reduction in recirculation pump speeu while operating ri

.at rated power.

The answer key requires the "C" response, however

?

Lthel"D" response is"also a correct statement if the candidate:

Lg"n iassumes.that,the plant has entered the Region Of Potential p

Instabilities. -Without the-information being given to the Z

1 candidate to determine?if.the plant is in this region or.not, the 4

' candidate may assume the plant has entered the Region of Potential Instabilities due to the power oscillations occuring.

M-9.

, ; RECOMMENDATION: Modify key to accept either "C"'or "D" response for 1A full; credit.

~

REFERENCE:

34AB-OPS-058-2S.

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QV3SD.O]L.2 03DM.

Question 2.03/5.03 asks why a loss of condenser vacuum will occur in, response to a loss of-instrument and' service air.

Question does-notfspecify-initial conditions. 'At low loads there would be no change in' main condenser vacuum if only F000 isolates Loss'of-air

_r to'thezsteam jet air ejector thirdLstage steam supply valve will

-result in a1SJAE third stage low flow condition. This low flow conditio'n will result'in the FOO4 (SJAE Suction) valve closing.

'The closure of the F004 valve would result in a loss of vacuum at

,any power level.

This problem was identified during teet preview.

L Suggestion was made to change F004 valve to F001 valve, but. change was not. incorporated.

. RECOMMENDATION: Modify key to accept either "C" or "D" for full credit.

REFERENCE:

LT-IH-02501-00, Page 16 and Figure 02501-4

' Elementary Drawing H21056 m

2 1+

F1 l

't QUISJLQN_2.,14/5. 03 Question 2.14/5.05 requires candidate to identify the MOST significant contributor to reducing Reactor Power when water level is lowered during a Failure to Scram event. This knowledge has not been identified as being a required knowledge for execution of the emergency operating procedures.

Objective 18 in LT-IH-20103-02 was referenced.

This objective requires students to be able to state the purpose of level power control during an ATWS.

The answer to

/

this objective is to control reactor power during an ATWS until sufficient boron can be injected to shut down the reactor.

Upon reviewing the Plant Hatch Plant Specific Technical Guideline and contacting General Electric personnel it was determined that the answer required by the key would be the most correct answer gnlY if specific assumptions were made.

These assumptions included specific reactor water levels and flow rates through the core.

The required answer was not specified in the Hatch Training Material or PSTG.

RECOMMENDATION:

Deletion of question.

If question is not deleted, as a minimum, modify the answer key to accept either "A" or "C"

for full credit.

REFERENCE:

Plant Hatch Specific Technical Guideline, Appendix B pages 348, 350, and 351 pM SHQH.2 10/5.11 Quer, tion discusses actions taken to mitigate heat additions to suppression pool during and ATWS.

Statement "A"

states that Boron injection is commenced if temperature approaches 110 degrees F to ensure that the Technical Specification limits are not exceeded.

Limit of 110 F will be exceeded regardless of SBLC injection at 110 F.

The 110 degree value is the temperature at which Technical Specifications requires the operator to initiate a manual scram.

C.indidates could assume that question was testing their knowledge of plant response to the SBLC initiation at 110 degrees since the 9S F Technical Specification Limit has already been exec *ded.

Statement "D"

states that level reduction is required if power is

>3%, suppression pool temp is > 110 F, and an SRV is open. Level should be reduced until either level is at top of active fuel gr all three conditions are corrected.

This is also a true statement.

If level is at the top of active fuel you should stop

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lowering level.

If all three conditions listed are corrected you should stop lowering level.

Since the question is not written to define the or as being inclusive, the candidate may read the or as being exclusive.

RECOMMENDATION: Modify key to accept either A or D answer for full credit.

REFERENCE:

Unit 1 Technical Specifications 3/4.6.2, ACTION "D"

Unit 2 Technical Specifications 3.7.A.1.e LT-IH-20107-03 Pages 18, 21 & 22

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'OUESTION 2.15/5.17-Question 2.15/5.17 Part-A requires the answer _to contain #1 (Transfer'of'4160.V BUS 2A & 2B) which is not a required knowledge to execute the response procedure.

This is not an.immediate s.,

F

operator-action.in the response procedure for.a loss of 2R22-S016.

Question 2.15/5.17 Part-C requires the candidate to have the

immediate operator: actions for the loss of 12f V DC Cabinet 2C,

-2R22-SO17,. committed to memory.

Hatch Operators are not required to. memorize:immediate operator. actions to abnormal procedures which are:not. time' critical. These. time critical immediate operator actions are identified in~LT-IH-20201-01 (Introduction to Abnormal Operating Procedures).

There is no signi.ficant consequence to

. Plant safety related to 2a & 2B 4160 Volt k.ises not being immediately placed on thei' start up supply.

. RECOMMENDATION: Deletion of #1 ' rom Part-A Answer Deletion of Part-C of question

~

REFERENCE:

LT-IH-20201-01 34AB-OPS-013-2S,Section I OUESTION 5.19 Question 5.19 requires candidate to state two possible causes of damage if the main steam lines are flooded.

This is not a required knowledge to' execute related procedures.

Answers given are just' two examples of possible causes for damage.

The referenced objective'was "Given a general or specific caution from the PSTG or SOFI charts determine its purpose."

The purpose for the closing of MSIVs when RPV level exceeds 100 inches is to prevent steam line_

.damace.(one purpose). Answer to objective is given in question.

RECOMMENDATION: Modify key to accept alternate answers which would be viable causes of damage.

REFERENCE:

LT-IH-20114-00, Page 15 of 35 O U E S T I O N a.,_0._3 E. 0 3 0

The "B"'distracter on the RO exam is a correct response due to

._using the word " Cycle On" instead of " Start".

The heaters will cycle on before, after, and during SBLC injection.

This question on the SR) exam was acceptable due to modification being made as recommended during test' preview.

RECOMMENDATION: Modify key to accept either "B" or "D"

for full credit on question 3.03 i

REFERENCE:

LT-IH-01101-00 1

_-.____m

QUESTION ~3.'11 Question 3.11 has candidate select the conditions that will cause an Emergency Diesel Generator to tie to its respective bus.

Answer key requires answer "C", but either less than 90% voltage for greater than 1 second gr less than 60% voltage for-greater than 1 second.will result in the-Diesel Generator tieing. This point was

' discussed during the Exam Preview.

.RECOMMFNDATIONi Accept either "B"

or "C"

for full credit.

REFERENCE:

HATCH RELAYING DATA SHEET, SCHEME 20.

QUESTION 3.13/6.12 Question 3.13/6.12 asks why CRD pumps are not necessary to be in operation to support the full insertion of all control rods on a reactor scram with the reactor-at NORMAL PRESSURE.

Students will interpret normal pressure as rated pressure.

With the reactor at rated. pressure the CRD accumulators are not needed.

At >800 PSI reactor ~ pressure, the scram can be initiated by reactor pressure without assistance from the CRD system.

Hatch Loss of CRD procedure does not require scramming the reactor due to accumulators going inop, unless less than 800 PSI reactor pressure.

RECOMMENDATION: Modify key to accept explanation of reactor pressure for full credit.

Do not requias bnD accumulators in answer.

REFERENCE:

HNP-2-FSAR-4, Page 4.2-77.

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. OUESTIQN 3.16/6.15

-Question 3.16/6.15 Part-C answer is given in seconds from bus being energized.

Candidates may give sequence in seconds from receipt of I

a.LOSP signal. Assumption of (T=12 sec) for'D/G to tie and for 2C RHR Pump to start. Then 10 seconds later (T=22 sec) A,B, and D.

RHR Pumps start.

RECOMMENDATION: Modify key to accept either time notation for full credit.

REFERENCE:

LT-IH-02801-00, Figure 02801-07.

OUESTION 6.16 Question requires candidate to briefly describe which RPS trips will be affected by removal or the shorting links and how it will affect them.

Answer key requires this information ANR a description of the logic network.

Question does not ask how many nuclear instrument trips there are in our RPS cystem.

Question does not ask the candidate to define what is meant by non-coincidence-tripping.

RECOMMENDATION: Modify key to accept either- "Any one of the 18 NI trips will 'cause a scram" fc r full credit -or "All Nuclear Instruments trip logic changes to non-coincidence".

REFERENCE:

LT-IH-01001-00.

QUESTION 3~17 i

Question 3.17 Part-B asks what physical conditions in the RWCU system caused the isolation.

The answer key requires " opening valves on a cool, depressurized system"._ This will result in hot water flashing to steam and then condensing as it cools thus resulting in a partially voided system.

The system being voided or not completely filled is what causes the system isolation.

RECOMMENDATION: Modify key to accept voided or partially filled system for full credit.

REFERENCE:

LT-IH-00301-01 HATCH LER 89-001-00 (Dated 3/6/89), Page 4 of 5.

'I~

i QUESILON 3.18 i

i This question asks the student to state the automatic actions which would occur if Core Spray was in test mode and received an.

inadvertent initiation signal.

The key requires the candidate to state that the minimum flow valve will open at setpoint when the F015B test valve closes and reclose when the F005B opens.

No initial plant conditions are stated in the stem of the question.

If reactor pressure was already less than 500 psig, the F005B would be opening, and at the same time, the F015B would be closing and the minimum flow valve would not cycle.

RECOMMENDATION: Do not require minimum flow valve cycling as p.4rt of the answer.

REFEREN5E: LT-IH-00801.

QRMIID1L1J946_J2

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I Question 3.19/6.17 Part-A asks for scram setpoints which are different between the units.

Points should not be deducted from Part-A for a response of #2 due to Technical Specification I

Limitations being specified differently for turbine control valve I

fast closure scram between units.

The point of actuation is the same, but T/S Limitations are different therefore a #2 response should not be required.

Question 3.19/6.17 Part-B asks for scrams which are never bypassed.

Response #5 and response #6 may be given due to actual scram circuits not being bypassed, but should not be required due

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to setpoint changes occurring when mode switch position is changed.

RECOMMENDATION: Part-A Do not deduct for #2. response Part-B Do not deduct for #5 and #6 responses

]

REFERENCE:

UNIT 1 Technical Specifications 2.1.A.4 BASES.

UNIT 2 Technical Specifications Pages B 2-12 & B 2-13.

LT-IH-01901-00, Page 43.

OUESTION 3.21Z6 18 i

1 i

Question 3.21/6.18 Part-C asks when IRM detectors are to be fully withdrawn from the core.

The present revision of 34GO-OPS-001-00 now requires IRMn to be withdrawn after placing mode switch to run.

Also the Plant Hatch objective referenced states that candidate would be given the procedure to answer the question.

RECOMMENDATION: Modify key for Part-C to accept "after placing mode switch to run" for full credit.

REFERENCE:

34GO-OPS-001-02 Rev 06.

QUES _TJpH_,3J 2/6.19 Question 3.22/6.19 Part-B asks which of RCIC turbine trips including setpoints is/are required to be reset locally.

The answer requires both the mechanical overspeed and local manual trips.

Candidates are not directed in the question to consider local manual tripping,_ additionally the mechanical overspeed and local manual actuate the same trip mechanism.

A note contained in

'the system operating procedure (3430-E51-001-2S) states that all turbine trips e. cept mechanical overspeed can be reset from the control room.

RECOMMENDATION: Modify key to accept either mechanical overspeed or local manual for full credit.

REFERENCE:

34SO-E51-001-2S REV. /.

OUESTION 3.23/6.20 Question 3.23/6.20 Part-B asks what size break ADS ic designed to protect against. The answer requires small break. FSAR Chapter 6.2 states that ADS is designed to reduce the RPV pressure to the operating range of the LPCI and CS systems for those events where HFCI system is unable to maintain reactor water level.

These events include small' breaks and intermediate breaks as covered in

'the ESAR' analysis.

RECOMMENDATION: Modify key to accept either small or intermediate for full credit.

REFERENCE:

Page 6.1-2 Unit Two FSAR (Section B.2).

I

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. QUESTION 6.21 This question asks the student to state the purpose of the Fuel 1

Pool Cooling system, including temperature. design limits per FSAR.

The referenced Hatch objective is valid, however according to the Examiners Handbook, section 3.2 "Some learning objectives may be relevant for training but not for licensing exams".

The KA referenced (KA233000G010) does not require that the candidate memorize this information, it requires the candidate be able to explain and apply any limits associated with the Fuel Pool Cooling System.

There are no operator actions associated with these design temperatures.

The required response to this question was not identified as knowledge needed to operate this system.

RECOMMENDATION: Delete question.

REFERENCE:

KA 233000G010.

REFERENCE:

LT-IH-04501-Ol, Page 5.

OUESTION 3.24 Question asks candidate to list five systeme or indications that utilize the dp (flow) signal.from the main steam line flow restrictors.

The material referenced only identifies four systems / indications.

The question should only require four responses.

RECOMMENDATION: Require only four correct responses for full credit.

REFERENCE:

LT-IH-01401 EO 5.C.

J t

1 QUE_STION 6.23 Question 6.23 asks for Diesel' Generator auto ctart signals and setpoints.

Setpoint for loss of power required by~ answer key is 80% nominal voltage.

Ref. Material LT-IH-02801-0 gives 60% nominal voltage as setpoint not 80%.

Actual setpoints are 90% or 60%

nominal voltage.

In many analysis the 90% nominal voltage relay is not recognized.

RECOMMENDATION: Modify key to accept either 90% (undervoltage condition) or 60% (degraded voltage) for full credit.

REFERENCE:

LT-IH-02801-00.

HATCH RELAYING DATA SHEET, SCHEME 20 OUESTJ_ON 6.24/3.27 Question 6.24/3.27 Part-F has candidate match the component in the off gas system with its function.

Question DOES NOT require candidate to match (f) " post treatment radiation monitor" to #9

" samples off-gas flow going up the main stack".

Due to question not'being specific as to samplo point candidate may interpret "off-gas flow going up to main stack" as a clarification of which gaseous effluent is being monitored and not the sample point.

If this assumption is made #9 would be a correct response to the Post Treatment Radiation Monitor.

' RECOMMENDATION: No point deduction for including #9 for "F" Answer.

REFERENCE:

LT-TH-03101 QUESTION 3.35/6.30 Question 3.35/6.30 Part-B #2 answer requires response of " Form 4 must be completed." This is a Federal form whica contains the person's previous exposure history.

l RECOMMENDATION: Modify key to accept " previous history known" for full credit.

RECOMMENDATION: 10CFR20.101, 102 l

g it "A,

OUESTION 4.'06

Question 4.06 requires candidate to select statement which explains why burnable poisons'are loaded in a BWR. The required answer is to allow more. fuel ~to be-loaded without increasing the number of control rods; required.

Statement "D" which states that loading

. burnable poisons protects fuel pellets from excessive peak' centerline temperatures in high power regions by limiting the thermal neutrons;available for fission is also correct.

Candidate may determine that the number of control rods and fuel bundles for Plant Hatch are set by design and.that we could not increase them.

This would lead to the selection of statement "D" due to the fact that we.do utilize Gad Rods to flatten flux peaks in high power regions.

RECOMMENDATION: Modify key to accept "A" or "D" for full credit.

REFERENCE:

Nuclear Reactor. Engineering (Third Edition), Page 20.

4 OUESTION 4.%0 Question 4.20 has three possible correct answers which may be given as determined by the candidate's assumptions made.

This was identified as.a problem question during the exam preview.

The question asks which of the given conditions would result in an increase lin-the outlet temperature of the oil in a lube oil' system.

The candidate is not supplied with any reference drawing, is not told if_ outlet _ temperature being discussed is measured at the outlet of a heat exchanger before or after the bypass valve line on the oil system returns.to the system, and is not told if the cooling water system is a closed loop system or a once through system.

The conditions given to choose from are as follows:

a.

Additional loads are placed on the cooling water system.

b. The bypass valve for the oil system is closed.

l

c. A flow blockage occurs in one of the tubes on the lube oil side l

of'the heat exchanger.

d. The outlet valve.for the cooling water is opened.

_Either "A",

"B",

or "C" could result in an increase in the outlet temperature of the oil in the lube oil system depending on the system configurations assumed.

RECOMMENDATION: Delete question 4.20 l

.