AECM-87-0104, Forwards Comments Re Written Exams Administered to Two Senior Operators & Eight Reactor Operators on 870518,per Request

Forwards Comments Re Written Exams Administered to Two Senior Operators & Eight Reactor Operators on 870518,per Request

ML20235W402
Person / Time
Site:	Grand Gulf
Issue date:	05/26/1987
From:	Kingsley O SYSTEM ENERGY RESOURCES, INC.
To:	Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20235W361	List: AECM-87-0104, Forwards Comments Re Written Exams Administered to Two Senior Operators & Eight Reactor Operators on 870518,per Request ML20235W357 ML20235W388
References
AECM-87-0104, AECM-87-104, NUDOCS 8707230549
Download: ML20235W402 (12)

Text

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ENCLOSURE 3

. . il D SVETEM ENERGY nesoonces, wc. j 7 ,': y Pj: g5 May 26, 1987

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U. S. Nuclear Regulatory Commission Region II.

101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Attention: Mr. Ken E. Brockman, Operator Licensing Section

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Comments Regarding NRC License Examinations AECM-87/0104 On May 18, 1987, examiners from the Nuclear Regulatory Commission (NRC) gave written examinations to two (2) Senior Operators and eight (8) Reactor Operators as a part of the Grand Gulf Nuclear Station (GGNS) Operator Licensing Process. Upon completion of the examinations, a copy of the examinations was supplied to System Energy Resources, Inc. (SERI) with the request that SERI review the examinations and furnish any appropriate comments to the NRC.

The attached comments are supplied pursuant to that request.

Should you require additional information, please contact Mr. W. M. Shelly of the GGNS Plant Staff at (601) 437-6303.

Yours t ly, ODK:rg Attachments 1 I

cc: (See Next Page) 8707230549 870715 PDR ADOCK 05000416 V PDR

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• AECM-87/0104 Page 2

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cc: Mr. T. H. Cloninger (w/o)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Frank Clark (w/a)

U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 J12AECM87052201 - 2 --

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i ATTACHMENT I NTRAEC COMMENTS ON NRC EXAMS -

COMMENTS REGARDING NRC OPERATOR EXAMINATIONS GENERAL Numerous questions were asked concerning emergency procedure steps, what  ;

actions are. required if the list of conditions exist, and basis for individual steps. GGNS lesson plans covering emergency procedures contain a condition in the objectives that given a copy of the flow chart EPs these objectives should be met. None of the flow charts were provided to aid the candidates in formulating their answers for the EP questions.

I. REACTOR OPERATOR EXAMINATION Question 1.01 - The question asks the student to determine if the listed parameters decrease, increase, or remain the same for the given transient while the recirculation flow control system is in the flux auto mode. Two different situations must be addressed as the initial plant power level and core flow were not given.

1) Flux auto with core flow less than 100%

a) Flow for the failed jet pump will decrease due to loss of the drive and driven flow. There will be some reverse flow, but it should be less than its original flow. -

Answer A - initial - decrease final - decrease b) Core differential pressure will initially decrease and ,

then return to its original value due to flux auto mode. I Since rod pattern is not changed, in order for flux auto !o bring power back to its original value, core flow mu:t return to its original value, and therefore core delta pressure must return to its original value.

Answer B - initial - decrease final - return to original NOTE: Return t7 original and remain the same are 4 not the same wh3n looking at transient situations.

Return to original was not one of the allowable answers provided in the question. {

l c) Reactor pressure will initially decrease and return to j its original value as stated in part b) above.

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Answer C - initial - decrease final - return to original (See NOTE above).

d) Indicated core flow will initially decrease due to loss of flow from failed jet pump. As recirculation flow control system opens the flow control valves te recover power, flow will increase in both jet pump loops. The intact jet pump flows will increase to a higher flow to I compensate for the lost flow through the failed jet pumps. Since indicated core flow is the sum of the 24

. jet pump flows, indicated core flow will be the sum of the 22 operating jet pump flows plus the reverse flow through the failed jet pumps. (NOTE: since both recirculation pumps are still operating, the flow through the failed jet pumps is seen as a positive flow, not negative)

Answer D - initial - decrease final - increase e) Actual core flow will initially decrease due to loss of i flow from failed jet pumps. Recirculation flow control system will increase recirculation system flow to bring power back to original value to null out it flux controller. Since rod pattern has not changed, in order for the system to achieve the original power level, it must bring core flow back to its original ,

value.

Answer E - initial - decrease final - return to original (See NOTE above concerning this answer)

2) Flux auto with core flow at 100%.

The explanations for what happens to the individual parameters is basically the same. The difference is that the recirculation flow control system has a flow limiter of 102.5% which will not allow parameters to return to their original values. The answer would be:

a. initial - decrease

! final - decrease l

l b. initial - decrease final - decrease

c. initial - decrease final - decrease J12AECM87052201 - 2

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l d. initial - decrease final - decrease / increase - depends on the amount of reverse flow

e. initial - dricrease final - decrease l The question becomes very complex with all things considered.

The reference for the question, OP-B33-1-03, was checked, and it was found that, although a discussion of failed jet pumps is in the reference material, the material does not approach the specific-question asked in the detail required to answer.

We recommend that the question be deleted for the following reasons:

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1) Originally no mode of operation of the recirculation flow.

control system was given. This was added by the proctor.

2) No initial power level or core flow was given which has a major effect on the answer.

3) The question did not state if the answer should consider the initial change in parameters, final conditUn of the parameters, or both.

4) If final conditions were to be considered, " remain the same" is not a correct answer es none of the parameters remain the same for the transient. " Return to original" is more appropriate. .

_uestion Q 1.02 - The term " gross enthalpy" is not used in GGNS training material. The reference for the answer key was checked, and no reference to this term was found. Also, part b of the question can not be answered correctly unless part a. is answered correctly. This constitutes a double jeopardy question in accordance with Examiner Standard 202 of NUREG 1021. We recommend that future questions contain terminology from GGNS training material, and that part b. of the question be deleted due to the double jeopardy situation.

Question 1.03 - Part b. of the question asked the student to determine if available NPSH would increase, decrease, or remain the same on recirculation pumps as the recirculation flow control valve was opened. The question reference, GGNS HT&FF, Chapter 6, was checked and revealed that there are many factors involved in determining available NPSH for the condition given. If the recirculation flow from steam separators / dryers is considered, the downcomer temperature increases resulting in decreased available NPSH. When the increase in feedwater flow is considered, subcooling increases resulting in increased available NPSH. Attachment 11 contains page 6-81 of the reference Chapter 6. No overall effect of opening the recirculation flow control on available NPSH is stated. We recommend that either increase or decrease be accepted as the correct answer since the material referenced does not draw a specific conclusion.

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n Question 1.04 - The answer key for this question gives only one correct answer. Per the reference for the question, OP-E22-1-501/Rev.

2, two possible correct answers can be found. In addition to the answer in the answer key, the following is also correct: injection time for the system would increase due to the header not being completely filled. We recommend that either of these answers be accepted as correct. Attachment III contains page 7 of OP-E22-1-501/Rev. 2 for reference.

Question 1.09 - Part b. requests identification of various points on the suppliec graphs as based on part a., which required identification of the transient the graphs represented. We consider this a double jeopardy question and request deletion of the question. (SEE'ES 202)

Question 2.10 - Part a. of the question requests the pressure at which the diesel driven fire pumps automatically start. The answer key states 120 psig. Actual setpoint for this auto start signal is 125 psig. Attachment IV contains the page of the Master Equipment List showing the setpoint as 125 psig. We recommend that the answer key be changed to 125 psig, and we will revise OP-P64-501 to indicate the 125 psig setpoint.

Question 2.15 - The question asks the student to " Explain the effect(s) on SBGT Train A for the following conditions". Part b. of the question gives a set of conditions. The answer key has the effect(s) of the condition and also contains potential effects if conditions other than those given occur. This question was on a previous SRO examination for GGNS, but the wording has been changed.

The phrase " potential or actual" effects has been deleted. We recommend that the answer to part b. be reduced to "SBGT Train A will stop".

Question 2.16 - Part b. of the answer key contains setpoints for some of the signals listed. The question only asked for signals to be identified. We recommend the setpoints be deleted from the answer key.

Question 3.02 - The question requests four (4) interlocks that inhibit recirculation ficw control valve motion. The answer key lists four answers of which two have various failure modes that will have the same resulting effect. Attachment V contains pages 5.4-23 & 24 of the UFSAR, and Table 2 and page 9 of OP-B33-2-501. Based on the information contained in the attachment, we recommend the answer key be changed to add the following:

Analog circuit demand high Velocity feedback high Position feedback rate of change high I Velocity controller oscillations Hydraulic fluid tank low-low level  ;

Hydraulic fluid high-high oil temperature J12AECM87052201 - 4 l

1 l' Ouestion 3.03 - Part a. of the question has FALSE as the answer, with l Eich we agree. The reason, in parenthesis on answer key, is not correct. The question stated steam dome pressure as the measured parameter. The actual measured parameter is the pressure between the

. testable check valve and the injection valve. This makes the statement false. Referring to Attachment VI, the pressure is sensed I between the testable check valve (E21-F006) and the injection valve (E21-F005) by PT-N050 (See M-1087). Referring to E-1182-29, PT-N050 energizes K50 when pressure is below the setpoint. On E-1182-26 K50 contact shuts to energize K102, whose contact can be found on E-1182-002 in the open circuit for E21-F005. As long as K102 is energized the valve may be opened using the handswitch. K102 also energizes K150 (15 minutes TDPU) on E-1182-26 and shuts seal-in path to itself. After 15 minutes K150 will open the normally closed contact in line with the K102 seal-in. If pressure sensed by PT-N050 has gone above the setpoint at this time, the valve can no longer be operated l

to the open position with the handswitch. Based on the above, it can be seen that the valve could be opened when the pressure sensed by PT-N050 is below setpoint without the 15 mirute time delay as stated in the answer key. Therefore, the reference to the 15 minute time delay is improper, and we recommend it be removed from the answer key.

Question 3.05 - Part b of the question uses the term High Pressure Setpoint(HPSP). We recommend this be changed to the GGNS terminology of High Power Setpoint. Attachment VII contains page 5 of 04-1-01-C11-2 which contains the answer to part b. as we teach it. We agree with the two notch restriction but request that either answer, (i.e., that found in the answer key or that shown in Attachment VII) be accepted as correct.

Question 3.12 - Part c. in the ansm r key has recirculation flow control units as a correct response. The reference given for the Question was used to verify responses given in the answer key.

Attachment VIII contains Figure 7 of OP-C51-3-02 which illustrates the correct responses. We recommend the answer key be changed to reflect the responses from Figure 7.

Question 3.14 - Part b. of the answer key states wide level indication is from -150" to +60". Attachment IX contains Figure 5 of the B21 System Description and M-1077C which indicates wide range level instrument range is from -160" to +60". We recommend the answer key be changed to reflect this range.

Question 3.16 - Part c. of the question has the student identify what control circuit is out of the control scheme for turbine control when the generator is tied to the grid. The answer key states that the speed control circuit is out due to grid frequency controlling turbine speed. By procedure, Cold Shutdown to Generator Carrying Minimum Load, and LP-LO-SYS-LP-N32-2 page 46, see Attachment X, the speed control circuit is used to initially load the generator. This signal is additive to the load control circuit once generator load is greater than 157 MWe, and load control is switched on. Therefore, it is always in the control scheme while the generator is tied to the grid.

Therefore, we recommend that part c. of the question be deleted or that the answer to part c. be changed to "none".

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L l Question 4.02 - Part b. of the answer key has three (3) required actions for the given condition. ONEP 05-1-02-1-2, Attachment XI, Step 4.4 lists the required actions for generator tripped, turbine not tripped. Only two (2) required actions are listed. The third action in the answer key is step 4.5. This step is performed regardless of whether the condition of step 4.4 exists or not. Therefore, it is not a part of the response for the given condition in the question. We re:ommend the third response in the answer key for part b. be deleted.

Question 4.03-Partd.oftheanswerkeyadgressesthecorrect response concerning ECCS pump NPSH. The 140 F for RCIC is not addressed. We recommend that inadequate cooling of RCIC lube oil be added to the answer key for part d. See Attechment XII for justification. Also, since part d. response is based on a correct response to parts a., b., and c., we feel this is a double jeopardy question (ES 202).

Question 4.04 - Part a. of the answer key states that immediate initiation of containment spray is required. This is correct but not complete. . Referring to EP-3, Containment Control, Attachment XIII, there are two possible actions. In accordance with step PC/P-9, containment spray should be initiated. If based on information given

, by the question, the student assumes that containment pressure gets above 17.25 psig, then containment venting must also be accomplished in accordance with step PC/P-10. We recommend that containment venting be added as a correct answer to Part a.

Part b. of the question requires the basis for part a. This is considered as double jeopardy as the correctness of the answer for part b. is dependant upon'the answer for part a. Also, the answer key for Part b. gives three (3) separate reasons why the actions of part

a. are performed. These are:

1) No assurance that adequate core cooling can be maintained with containment failure.

2) Loss of source of water to ECCS components.

3) Loss of adequate core cooling.

Items 1 and 3 are identical, and item 2 leads to items 1 and 3.

Therefore, we recommend that the answer key be changed to reflect that adequate core cooling can not be assured with containment failure as the correct answer.

Question 4.05 - Part a. requires two (2) low level isolations that may be bypassed to be given. Referring to EP-14, Attachment XIV, only one (1) low level isolation is called out to be bypassed. We recommend that item a.2 of the answer key be deleted.

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Question 4.07 - This question requires the APRM values for transferring the Mode Selector Switch from STARTUP to RUN. Referring to 03-1-01-1 Attachment V, the only stated requirements concerning APRMs are that the APRM downscale indicator lights have extinguished and that all operable APRMs are greater than 4% power. Since this question as stated doesn't apply to GGNS, we recommend this question be deleted or the following answer be accepted:

1) Downscale indicator' cleared or 4%

2) 12%

Question 4.09 - Part a. of the question asks for three (3) conditions from EP-14 at which lowering of level is terminated. The answer key gives conditions based on BWROG guidelines and not how those guidelines were actually implemented at GGNS. Referring to EP-14, Attachment XIV, the guidelines as implemented become:

1) Power less than 4%

2) Level decreased to TAF

3) Drywell pressure less than 1.23 psig and no SRVs cycling We recommend the above be accepted as the correct answer for part a.

Part b. of the questions asks for all injection systems which are not terminated by Step LP-13. The answer key for this part has the correct systems, but also includes a reason as to why they are not terminated. This was not asked for in the question. We recommend the statement "because they are being used to control reactor power" be deleted from the answer key.

II. SENIOR REACTOR OPERATOR EXAMINATION Question 5.02 - See Question 1.01 Question 5.04 - See Question 1.03 Question 5.08 - See Question 1.09 Quest _i_on 5.09 - See Question 1.09 Question 6.01 - See Question 3.02 Question 6.08 - See Question 3.14 l Ouestion 6.09 - See Question 3.16 Question 6.14 - See Question 2.10 Question 6.16 - See Question 2.15 J12AECM87052201 - 7 1 _ _ _ _ _ _ _ _ _ _ _ _ _

Question 6.17 - See Question 2.16 Question 7.01 - See Question 4.02 Question 7.03 - See Question 4.03 Question 7.04 - See Question 4.04 Question 7.05 - See Question 4.05 Question 7.10 - The answer for candidate #2 is, " rejected for exceeding the quarterly administrative limit". Referring to 01-5-08-2, Exposure and Contamination Control, Attachment XVI, candidate #2 can be accepted if an extension is approved by the Radiation Protection Manager and the General Manager prior to entry into the area. We recommend that this answer or the one stated in the answer key be accepted for candidate

1. 2.

Question 8.02 - The question required the studerit to select which "0NE" of the listed duties is "NOT" a responsibility of the Shift Supervisor. The answer key indicates a. as the correct answer. Due to recent procedure changes, another possible correct answer is listed. 01-5-06-2, Conduct of Operations, Attachment XVII, states

, that ensuring a licensed operator is present at-the-controls, item c.,

is a Shift Superintendent function. We recommend that item c. be accepted as a correct answer based on the referenced procedure.

Question 8.03 - The answer key failed to list all checks required by the referenced procedure. 02-5-01-2, Attachment XVIII, states that

" breaker fuses installed" should be included in the local checks. We recommend this be added as a correct answer for the question.

Question 8.07 - The question states that action d.1 of Technical Specification 3/4.5.1 is being applied, and that one of the four given l conditions caused that action to be taken.

1 1 Answer d. is indicated as the correct answer. A detailed review of answer d. was performed with the following results:

ADS timer trip system ' A' is INOP - referring to Specification 3/4.3.3, action c. is applicable which requires restoration in 7 days if HPCS and RCIC are operable or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If it is assumed that the ADS l

initiation timer is the faulty component, then Table 3.3.3-1 applies which requires Action 31. Action 31 requires that the associated ADS trip system or ECCS be declared IN0P. The INOP ADS trip system was previously discussed. If you declare the associated ECCS IN0P, then you have LPCS and LPCI 'A' IN0P.

LPCI pump 'B' motor overcurrent lockout condition - This results in LPCI 'B' INOP.

One channel of the HPCS CST low level logic has been tripped - Table 3.3.3-1 of 3/4.3.3 requires two (2) channels per trip system or that J12AECM87052201 - 8 j

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Action 34-be taken. Action 34 requires that one channel be placed in the tripped condition within one. hour or declare HPCS System INOP.

Given in the condition, the channel is already in the tripped condition.

The action statement being applied by the question is 3/4.5.1 Action d.1. The action statement states that in order to apply this statement the following conditions are required:

1) Division 3 is operable - of the conditions given in answer d., none result in Division 3 being INOP.

2) LPCI 'A' IN0P - based on the ADS timer trip System LPCI 'A' could be IN0P.

3) LPCI 'B' or LPCI 'C' INOP - LPCI 'B' is INOP due to conditions given.

l If the option was taken to IN0P the ECCS associated with the INOP. ADS timer trip System 'A', you would have both LPCS and LPCI 'A' INOP which results in the given action not being applicable to the situation. Since LPCS, LPCI 'A', and LPCI 'B' are INOP, the resulting action should be 3/4.5.1 Action d.3, hot shutdown in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold I shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Based on the above, we recommend this question be deleted as there is no correct answer stated in the four choices given.

l Question 8.15 - The question requires that, based on the plant conditions given, the student state the LCOs requiring action within one hour. Based on Technical Specification 3/4.3.1, Attachment XIX, with only 1 channel of turbine control valve-fast closure trip System

'A' operable action a. applies which requires action within one hour.

We recommend this be added to the answer key as a correct answer.

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NTRAEC COMMENTS ON NRC EXAMS - 9

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