ML20151M058

Forwards Comments on Reactor & Senior Reactor Operator Written Exams Administered on 880418.Dependence of Several Questions on Rote Memorization of Ref Matls Criticized

ML20151M058
Person / Time
Site:	McGuire
Issue date:	04/21/1988
From:	Mcconnell T DUKE POWER CO.
To:	Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20151M045	List: ML20151M042 ML20151M046 ML20151M058
References
NUDOCS 8808040252
Download: ML20151M058 (53)

Text

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! ENCLSOURE 3 l

- o r 2 Duke Mgr Cmany (704) 815 4000

%fcCuire NuclearStation P.O Ba 48S Cornelia<, NC 28031-0488 DUKEPOWER April 21, 1988 Mr. Ken Brockman Operator Licensing Section U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street N.W.

Atlanta, Georgia

Subject:

McGuire Nuclear Station Review of Written License Examinations

Dear Sir:

Attached are our specific comments on the Reactor Operator and Senior Reactor Operator written examinations administered April 18, 1988 at McGuire Nuclear Station.

In addition, as a general comment, several questions depended too heavily on rote memorization of reference material e.g. question 4.02 which referred to a table in a tech spec interpretation; question 4.09 which referred to fuel maneuvering limit tables in the data book; and question 4.15 which referred to reactor site boundary criteria in 10CFR100.

Very truly yours, j l

l8 p 2 .A SOnstff T.L. McConnell Manager McGuire Nuclear Station TLM/wms i

cc: R.B. Travis L.E. Weaver l D.A. Baxter

! D.M. McGinnis Plant File 8808040252 880721 PDR V

ADOCK 05000369' PNU l

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-e t REACTOR OPERATOR EXAM COMMENTS Page 1 QUESTION 1.06 Concern:

The question requires the RO to determine the net result between two off setting effects; faster dilution of NCS at high boron concentration versus higher differential boron worth at lower boron concentrations; without the use of differential boron worth curve or dilution rate tables which include 1200 ppm. -

Recommendation:

Accept answer C and B as correct. Or at least partial credit for C since it demonstrates knowledge on the part of the operator.

Reference / Reason:

During operation in the control room, the operators have these curves available to them for reference and are not required to memorize them. Selecting item C or B indicates sufficient knowledge of effects.

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. i QUESTION 1.08 Page 2 I

Concern:

This question involves two effects on axial flux distribution:

1) Rod position - inserting Rods drives AFD more negative

2) Power level - Reducing power shifts AFD toward the  ;

positive l Answer C could also be correct since AFD being more negative )

than the target value of -3.0 implies that the axial power distribution has shifted more negative than the full power axial distribution. j J

Recommendation:

Allow credit for C or D. Or at least partial credit if item C s selected since it demonstrates knowledge on the part of the operator.

1 Reference / Reason:

OP-MC-CTH-CP pg 54, 55 and pg 35-36 I

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-QUESTION 1.15C Page 3 Concern:

McGuire Unit #1 and #2 differential boron worth for-EOL and EOL are opposite from each other i.e. Unit 2 differential boron worth is more negative at BOL while Unit 1 is more negative at EOL for the same boron concantration. .This would result in an answer of higher or lower depending on what the operator assumed.

Recommendation:

Accept higher or lower Reference / Reason:

McGuire Data Book Unit #1 OP/1/A/6100/22 Enc 1 4.3 Curve 6.2 McGuire Data Book Unit #2 OP/2/A/6100/22 Enci 4.3 Curve 6.2 l

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QUESTION 1.16C Page 4 Concern: .

Answer key is wrong the magnitude of the moderator temp.

coeff, will increase l

Recommendation:

Change answer. key to increase Reference / Reason:

l OP-MC-RT-RCO pg 22-23 l l

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QUESTION 1.17a Page 5 Concern:

When calculating SDM at Power, Xenon is not included per OP/0/A/6100/06 Enci 5.4 Xenon does not effect long term SDM but it does effect the instantaneous SDM.

Recommendation:

Allow credit for remains the same or increase. Or at least partial credit for remains the same-Reference / Reason:

OP/1/A/6100/06 Enci 5.4 l

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QUESTION 1.21 Page 6 Concern:

The Tech. Spec. "word" definition for FH and FQ(z) should also be acceptable.

Recommendation:

For F H - Answer the answer key is fully acceptable, but the following should also be allowed.

F H - The ratio of the integral of linear power along the Rod with the highest integrated pcwer to the average Rod Power.

For FQ(z) - Answer key is fully acceptable, but the following should also be allowed.

FQ(z) - The maximum local heat flux on the surface of a fuel Rod at core elevation Z divided by the average fuel Rod Heat Flux.

Reference / Reason:

Tech. Specs. Bases 3/4.2 page B 3/4 2-1 i

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, . l QUESTION 1.21C Page 7 l

l (1) Concern.

Point value for answer assigns 1/2 total point value for putting particular core height. I i

l (1) Recommendation:

1 Point value be assigned as (.8) for limit maximum Heat Flux l and (.2) for at particular Core Height. l (1) Reference / Reason: j Weight point value according to importance.

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(2) Concern: i I

Question may be answered in terms of limiting core damage following a LOCA.  ;

i (2) Recommendation: J Answer key is acceptable but would also like to include the following as acceptable FQ(z) is used to help limit peak local power density and to help ensure minimuni DNBR is not l exceeded so that Peak Clad temperature will not exceed 2200 F l (ECCS acceptance criteria) following LOCA. )1 l

(2) Reference / Reason: )

i Tech. Spec. Bases 3/4.2.2 and 3/4.2.3 pg B 3/4 2-2a. j J

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4 4 QUESTION 1.22a Page 8 9~

concern:

Opera (Jrs.may not put all three Pump Head Curves on same Graph. The point break down in the answer key gives .2 for "correct placement". If the correct placement means the telationship between the ND, NT, and NV Pump Curves on the smne Graph, some operators may be penalized unnecessarily.

The question doesn't clearly emphasize that all three Pump Head Curves should go on the same Graph so the relationship betwat" them can be shown.

Recommendation:

, ~rators should not be penalized if they put the Head Curves on separate Grap.9 such that the relationships are not shown.

Reference /Rssson:

When reviewing question it was not apparent that all three curves needed to gc on one Graph until we looked at the answer key.

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QUESTION 2.03 Page 9 Concern:

At McGuire, The Plasma Display for RVLIS for the given condition would have invalid indicated with no values shown.

Therefore the operator would not see 70% and 106% as described in the question.

Recommendation:

The question has too many technically incorrect conditions / assumptions to be salvaged. Throw out question If question is not thrown out accept C as an alternate answer since it is partially correct just as answer A is partially correct i.e. for Pump's running with UR RVLIS failed it would indicate pegged high which would be 120% not 106%, also for Pump's running UR RVLIS normal indication is pegged low at 70% not 106%.

Reference / Reason:

The Lesson Plan Referenced in the answer key reflects the indications which would be seen on RVLIS vhen the read out was meter indication. The McGuire Plant no longer has meter indication. The indication now is computerized plasma display. These displays will only indicate P when the instrument is valid i.e. Pumps on or off.

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QUESTION 2.09 Page 10 icncern:

Answer key item "e" states Low Stator Water Cooling Flow whicn is correct. However, the flow is determined by 4P and the setpoint for low flow is a aP.

Recommendation:

Inaddition to Low Stator Water Cooling Flow, Low Stator Water AP should also be fully acceptable.

Reference / Reason:

Drawing MC-IC-EHC 13 I

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QUESTION 2.10 Page 11  ;

Concern:

Inaddition to the items listed in the answer. key, ND58 and NS43 must also be closed.

Recommendation:

Add ND58 closed and NS43 closed as possible interlocks which could be listed to answer key.

Reference / Reason:-

Drawing MC-SYS-NI-7 i

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QUESTION 2.11C Page 12 Concern:

Valve nomenclature in question is incorrect. ND-43 should be NS 43. Valve ND-38 should be NS 38. The name "ND Aux Spray Valves is Correct." Some Operators may have caught this and assumed it was a "Trick" question. Inaddiclon, ND to Aux Spray would only be available if ND was on the containment Sump since NS 38 and NS 43 require the Sump Valve to be open before they can be opened.

Recommendation:

Inadditon to accepting true; false should be accepted if it is stated that valves are NS 43 and 38 and not ND 43 and 38 or if it is stated that the statement is not always true since ND to Aux Spray is not.always available since it must be aligned to the containment Sump in order to open NS 43 and 38.

1 Since the question only required a true or false, many operators may not qualify their answer. If a large number of operators miss this question, it should be re-evaluated as to whether it should be thrown out.

Reference / Reason: l Drawings MC-SYS-ND-1 and MC-SYS-NI-7 I

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QUESTION 2.16a Page 13 Concern:

i To answer four(4) modes of operation of this system the operator must include "train A".and "train B". The two basic modes of operation of this system are "Series" and "Parallel" and train related modes of operation.are normally not referred to as such.

Recommendation:

Change question point values to place more weight on the "Series" and "Paralled" alignments and less importance on the train relationship. Request a change to reflect "Sericsd (0.4) "Parallel" (0.4) and the remaining (.2) pts applied to the train relationship.

Reference / Reason:

OP-MC-PSS-V6 Lesson Plan; (pg 8; 1-3, A, 3.)

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- QUESTION 2.17a Page 14 Concern:

NC Pump Standpipe is also a correct answer and is not reflected 4'.1 the answer key.

Recommendation:

Include NC Pump Standpipofas correct answer.

Reference / Reason:

OP-MC-FH-FW Lesson, drawing FW-1 and OP-MC-CM-NCP Lesson, drawing NCP-5.

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QUESTION 2.18b' Page 15 l

i concern:

Answer key reflects "less than or equal to" is worth (.25)

' and "27 degrees" is worth (.25). Question asks for maximura temperature and "27 degrees F" is the maximum temperature.

i Recommendation:

Allow full credit for both "less than or equal to 27 degrees F" and "27 degrees F".

Reference / Reason:

"27 degrees F" fully answers question asked.

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QUESTION 2.20 Page 16 Concern:

Question asks why "A" RN Pump instead of "B" RN Pump supplies containment ventilation units. It does not ask why RN supplies these units during a blackout situation. The answer key requires that_the operator state that the RV Pumps have lost power (.S pts).

Recommendation:

No requirement in answer key for student to state that the RV Pumps have no power. Full credit given for "greater NPSH" or "Cooler Water Supply".

Reference / Reason:

Answer key requires more than question asks.

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QUESTION 2.21a Page 17 l

Concern:

Answer states one(1) throttle valve at the discharge of the <

pump. There are four(4) throttle valves and they are l located in the four discharge lines into the loops.

Recommendation:

Accept "throttle valves are used to limit total flow".

Reference / Reason:

OP-MC-ECC-NI Lesson, pg. 9, d and OP-MC-ECC-NI drawing NI-1.

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e QUESTION 3.08b- Page 18 Concern:

Answer key implies not only the parameters that can be monitored but also seems to require the range of that parameter (such as: NC Hot Leg Wide Range Pressure). The question only asks for parameters monitored.

Recommendation:

Accept shorter answers for full credit such as: NC Temperature, S/G level; NC Pressure.

Reference /Roason:

Answer key reflects more required information than the question asks.

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QUESTION 3.09b Page 19 Concern:

"D/G Emergency Start Relay" may be used as well as "D/G Automatic Start Relay".

Recommendation:

Allow full credit for either "D/G Automatic Start Relay" or "D/G Automatic Start Relay".

Reference / Reason:

Common Plant Terminology 1

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l Concern:

Part a) Operators have no ETQS task related with the operation of the Incore Instrument Panel.

Operation of this panel is normally conducted by  :

plant performance personnel. Due to this the l answer key seems to require too much detail in the answer required for full credit. Also, the point j value is higher than is reasonable for the '

question.

Part b) Answer states "Honeywell Indicator". Honeywell is the vendor name and should not be part of required answer. Also, answer does not reflect the possible answers: Inadequate Core Cooling Monitor (ICCM) display or SSF which also have temperature displays of the Incore Temperatures, and are separate from the OAC.

Recommendation:

Part a) Allow less detail in answer for full credit example:

1) Calibrate - allows calibration of detectors

2) Emergency - back-up path

3) Common Group - back-up to calibration path

4) Storage - stores detectors Reduce overall point value of question Part b) Allow full credit for either c( the following answers:

1) Temp. Indicator on panel i

2) ICCM display Reference / Reason: l

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1) No ETCS related task on this system l

2) Recently installed Inadequate Core Cooling Monitor System provides readouts on Incore Temperatures. This new monitor has not been incorporated into existing 4 lesson plan to date. l

3) OP-MC-CP-AD Test portion of lesson page 40, 1.5, A. l l

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QUESTION 3.12d Page 21 Concern:

Answer key refers to P8 as > 49%. Due to instrumentation accuracy and allowable tolerance in Tech. Specs. requiring this specific number maybe overly restrictive.

Recommendation:

Accept either 48% or 49% for P8 setpoint Reference / Reason:

Tech. Specs. table 2.2-1 (Rx Trip INST and Trip STPT)

OP-MC-IC-IPE 1

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QUESTION 3.14a Page 22 )

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Concern: i i

The question is not clear about whether it wants the l immediate eftects of the S/G level channels failing or if a  !

Reactor Trip would occur some time later as a result of the I failure. l I

our S/G level control circuits controls off of S/G level channel 1 normally. If this channel fails .aw the control I circuit will try to increase that S/G level back to program level. However with the channel failed level will continue  :

to increase until P14 (82% LVL) is reached. P14 will cause l the Turbine to Trip which in turn will cause the Reactor to l Trip. I l

1 Recommendation: l In additio.1 to the answer key, if the operator says yes the l Reactor Will trip because the failed channel 1 would cause A I S/G to feed up to P14 which will trip the Turbine which trips the Reactor, this should also be acceptable.

Reference / Reason:

Simulator / Plant Response to failed channel 4

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QUESTION 3.14b Page 23 '

Concern:

Answer key says OT DELTA P. This is obviously a typo.

Recommendation:

Change key to say OT DELTA T  :

Reference / Reason:

Typo i

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QUESTION 3.14c Page 24 Concern:

1) Answer key says Reactor will trip on OPDELTA T

2) OP DELTA T does not receive an input from Tave or Pressurizer Pressure.

3) The correct answer should be OT DELTA.T which does receive input from the failed indications.

Recommendations:

Change OP DELTA T to OT DELTA T on answer key Reference / Reason:

Tech. Spec. table 2.2-1 pg 2-8 thru 2-11

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QUESTION 3.15a Page 25 l l

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Operators may include in their answer that Pzr level would continue to increase until the Reactor Trip occurs at 92%

level.

Recommendation:

Operators should not be counted off if they state Rx trip occurs when Pzr level reaches 92%.

Reference / Reason:

See drawing MC-IC-ILE-3 F

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QUESTION 3.17 Page 26 l

Concern:

1) Answer key has too narrow of a band for %FP and %Pzr Lvl. l

2) Tc ccn be between 557 to 558 from 0% to 100% FP.

Tava can be 588 or 588.2 depending on reference document.

3) Factoring the above variations into the calculation, answers between 72% to 75% can be obtained.

4) Also using above variations, Pzr level calculations range between 51% to 53%.

Recommendation:

Make range on answer key for part A 72% to 75% FP Make range on answer key for part B 51% to 53% Lvl.

Reference / Reason:

Drawing OP-MC-IC-IRX-7 l

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QUESTION 4.02 Page 27 Concern:

This question requires noma ization of a table out of a Technical Specification 1cttrpretation. Since this document is readily available in the control room for review this is beyond the required knowledge of a Reactor Operator. We feel the operator should be aware that there is an interpretation associated with operating above 100% RTP and refer to this interpretation when necessary.

Recommendation:

Since the RO would have to be aware of a time limit associated with operating above 100% RTP, then we recommend i that both "C" or "D" be accepted for full credit since both answers show interpretation knowledge. Since the limit is 60 min. operating of 30 minutes would also be allowable.

Reference / Reason:

Tech. Spec. interpretations are readily available as  ;

reference material in the control room. Student Awareness that there are item limits for operating at 100.5% powec is sufficient to ensure that this interpretations would be referred to under conditions specified in the question.

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QUESTION 4.05a Page 28 Concern:

Answer key is incorrect. Answer should reflect as follows:

Heatsink - Highest priority (red path conditions)

Suberiticality - 2nd priority (orange path conditions)

Core Cooling does not require prompt action since with conditions specified it is yellow condition.

Recommendation:

Change answer key to correct deficiency i Reference / Reason:

Incorrect answer key 1

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QUESTION 4.08 Page 29 Concern:

Answer key reflects "Identify and Isolate" as one major step. Since these are separate steps in the procedure (EP-04) requiring them to be.placed together as one major step is inappropriate. Major action summary's are subjective and allowance should be given for each action as separate.

Recommendation:

Allow credit for Identify Rutu::ed S/G as one major action and Isolate Ruptured S/G as a separate major action. I Reference / Reason:

EP-04-SGTR 1

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QUESTION 4.09 Page 30 .

f Concern:

Question does not provide sufficient information for the operator to determine if the fuel is conditioned or not.

The question stated that the Reactor had operated at 70% for one week, but it did not say if this was following a refueling shutdown or if the Reactor had operated above 70%

FP prior to the past week of 70% FP operation.

Inaddition, the operating procedures directs the operator to refer to the Data Book for fuel manuevering limits prior to increasing power (OP/1/A/6100/01 page 18 note following step 3.2.75 and OP/1/A/6100 page 1 note following step 2.4).

The operator is not required to memorize this information and it is readily available in the control room.

Recommendation:

Throw out question if question,will not be thrown out accept either of the following as correct.

1) Unconditioned fuel - 3%/HR all the way to 100% FP

2) Conditioned fuel - 10%/HR to 90% then 3%/HR to 100%

Reference / Reason:

We have no training objectives which requires an RO to memorize the fuel manuevering limits. The fuel manuevering  !

limits are readily available in the control room and the l procedures directs the operator to use them when required.  ;

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.a .. e QUESTION 4.11d Page 31 Concern:

Requires operator to memorize Tech. Spec. limits for an infrequent evolution which is highly controlled by procedures.

Recommendation:

Throw out part d Reference / Reason:

We have no training objective that requires this item to be memorized 1

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I QUESTION 4.15 Page 32 3

1 Concern: "

Requiring an RO memorize the "Reactor Site Criteria 10CFR100 dose limits is beyond the scope of an RO's Job. This also .

falls under the guidelines of NURLJ/BR-0122 Examiners  ;

Handbook for Developing Operator Licensing Examinations psge l 4-3 item (5) these comments apply to part A and B of this  ;

question. '

Recommendation:

Throw out question l

Reference / Reason:

1) We have no training objectives which require the operator to memorize this information

2) Beyond scope of Ro's Job.

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Page 33 i

g QUESTION 4.19 Concern:

, The K/A reference listed for this question has no relation to question asked. This question is not supported by a learning objective. The reference used is OP/0/A/6100/08 and this document is and and has been in the process of

, being modified and incorporated into the applicable operating procedures. This particular limit and precaution has been modified and incorporated into the Unit Start-up procedure OP/6100/01 and now reads: "Whenever possible, all shutdown banks should be fully withdrawn anytime reactivity is being added by boron, xenon concentration changes, or control banks."

There are no exceptions listed. OP/0/A/6100/08 is the only place that the limit and precaution as stated in the question appears and this document does not reflect the >

modified version that now appears in the Unit start-up procedure. 6100/08 is to be deleted in the future as all appropriate information is incorporated into applicable procedures.

Recommendation:

Delete question from exam Reference / Reason:

OP/1/A/6100/01 - Unit Start-Up procedure Limit and Precaution 2.12.

Page 34' SENIOR REACTOR OPERATOR EXAMINATION COMMENTS' QUESTION 5.01 Concern:

The answer for question 5.01 should be a not c.

Recommendation:

Change answer key Refereuce/ Reason:

Calculation

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• d2r Q,

= 3.57 e

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QUESTION 5.07 Same comment as question 1.06 on Reactor Operator Exam i

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Page 36 QUESTION 5.08 Same comment as question 1.08 on Reactor Operator Exam l

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- ,. -g Page 37 QUESTION 5.09 Concern:

i The answer should be d not b.

Recommendation:

Change key to agree with question 1.10 on RO exam.

Reference / Reason:

RO exam question 1.10 ,

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QUESTION 5.23 concern:

Key Places too much weight on use of average differential boron worth. Realizing that average differential worth is used in a small portion of the concept.

Recommendation:

consider full credit if candidate uses differential boron worth in answer versus average differential boron worth.

Reference / Reason:

Use of average differential boron worth is not essential to explanation of concept.

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8 O Page 39 QUEETION 6.02 Same as RO Exam 2.03 i

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j Page 40 QUESTION 6.08 Concern: .

Some candidates may include RF (Fire Protection) as a source of make up to the Spent Fuel Pool.

Recommendation:

Consider accepting "RF" as an alternate answer.

Reference / Reason:

Operational experience, 2 Fire Protection Hose Racks located on Fuel Pool Operating Deck.

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Page 41 QUESTION 6.09 Concern:

The question was based on a system which has not been installed at this time and which the candidates have not been trained.

Recommendation:

Delete question Reference / Reason:

The MSR Lesson Plan was revised to cover a modification to the system which has not been completed. The candidates were trained on the present system which does not have the features addressed in the question.

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Page 42 QUESTION 6.11 Concern:

The question does not implicity ask for the answer as given in that the question asks for why the VCT isolation valves are in series rather that why the VCT needs to be isolated.

Recommendation:

Accept one explanation of why safety related isolation valves are in series as an explanation i.e. single failure criteria, Reference / Reason:

Examiner Handbook 4.5.l(3) 1

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Page 43 l QUESTION 6.13 >

Concern:

The answer key gives equal weight to the second half of the statement excerpted from the Lesson Plan.

Recommendation:

Accept as an alternate, operational answers, with most weight given to Heating the insurge of cooler water from the NC system to saturation. Less weight to flashing when level returns. +

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Page 44 QUESTION 6.14 concern:

The key answer is incorrect. As is the note in the RF Lesson Plan. All the back up Heater Feeder Breakers must be manually closed.

Recommendation:

Accept none as the correct answer.

Reference / Reason:

Electrical Controls System description - Pressurizer Heaters (ILE) MCSD-0149-00 4

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'Page 45 QUESTION 6.16 Concern:

Error on answer. key and Ref. Lesson indicates PORV's open at 2235 PSI instead of 2335 psig. Some candidates may 'nclude .

spray valves do nct open.

Recommendation:

a) correct answer key to read 2335 psig vice 2235 psig b) Do not penalize for including spray valves do not open.

c) Accept as an alternate response; Pzr PORV's cycle sinca setpoints were not specified as part of the question.

Reference / Reason:

OP-MC-PS-IPE pg 26 I

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Page 46 QUESTION 7.16a Concern:

The question does not illicit the entire answer key response. The answer key requires as part of the response "TRIP ALL NC PUMPS". The question asks for "NC Pump Trip criteria" with the implication to give the criteria for tripping the Pumps.

Recommendation:

Delete the statement "Then trip all NC Pumps" from the required resannse.

Reference / Reason:

OP-MC-RP-EP4 h

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• .: O Page 47 QUESTION 8.14 Concern:

Ancwer key is correct for provided Tech. Spec. however T.S.

3.1.2.6 Borated Water Sources Requires the Boric Acid Tank Available.

Recommendation:

Accept corrective action for T.S. 3.1.2.6 restore within 72 hr or . . . . as on alternative response.

Reference / Reason:

McGuire Tech. Spec. 3.1.2.6 1

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b Page 48 QUESTION 8.15 concern:

-Answer key does not consider acceptable alternate actions prescribed in the provided Tech. Spec.

Recommendation: ,

1 Accept the alternative to restore the valves to operable-within 4 hrs.

Reference / Reason: -'

T.S. 3.7.1.1 -

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Page 49 QUESTION 7.18a Concern:

The answer key addresses the reason for SI termination following a SGTR. The question asks for the reason for a specific element within the SI termination. criteria.

Recommendation:

In addition to the answer in the key, the following (or similiar wording) should also be correct: to ensure positive control over NCS pressure prior to terminating SI.

Reference / Reason:

OP-MC-RP-EP4

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Page 50 QUESTION 6.23a Concern:

i The answer key is correct, however there are other answers  :

that may be stated.

Recommendation:

In addition to the answer key either of the following should also be accepted as a correct answer. r

1) Carry its own individual load plus the loads of another ,

charger.

2) Output rating of 400 amps at 132 VDC.

Reference / Reason:

1) Lesson Plan OP-MC-EL-EPL page 11 of 26; col.a

2) Lesson Plan OP-MC-EL-EPL (same) page 14 of 26; c.2 ,

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Page 51 QUESTICN 8.02 concern: i The answer key indicates that the 3.25 surviellance interval '

was not violated when in fact it was. January the 8th through April the 18th is 101 days. The allowed interval can't exceed 3.25 (31 day) = 100.75 days. Since the surveillance test has not been completed as required then all of the flow paths would be declared inoperable thus invoking 3.0.3.

None of the selections in the quesiton are fully satisfactory.  :

i Recommendation:

Throw out question or accept a or d as correct.

Reference / Reason:

See concern f

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ENCLOSURE 4 SIMULATION FACILITY FIDELITY REPORT Facility Licensee: Duke Power Company Facility Licensee Docket No.: 50-369 and 50-370 Facility License No.: NPF-9 and NPF-7 Operating Tests administered at: McGuire Nuclear Station Operating Tests Given On: April 19-21, 1988 During the conduct of the simulator portion of the operating tests identified above, the following apparent performance and/or human factors discrepancies were observed:

During the exams, there were three instances when the exam area was entered by unauthorized personnel and two instances when outside telephone calls were received on the simulator floor, in each instance, examiners were present to ensure that exams were not compromised. The facility is reminded that even the

- appearance of potential exam compromise is to be avoided at all times.

Examinations given during the week of April 18, 1988, are the last to be given on this simulator. A new facility will be available for future training ano examinations, i

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