ML20235G723

Provides Comments Re Written Exam Administered 870413 at Facility.Comments & Recommendations Based on Technical Review of Questions & Answers

ML20235G723
Person / Time
Site:	Vogtle
Issue date:	04/20/1987
From:	Rushton P GEORGIA POWER CO.
To:	Arildsen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20235G564	List: ML20235G559 ML20235G618 ML20235G723
References
NUDOCS 8707140357
Download: ML20235G723 (31)

Text

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Georgia Power Ccmpany s

Nuc! ear Operations ENCLOSURE 3 Post Office Box 1600 Wsynesboro, Georgia 30830 Telephone 404 724-8114 404 554-9961 Vogtle Project Georgia Power e in c m u n n, x mc r y sm.m April 20, 1987 Plant Vogtle - Units 1 &2 NRC Written Examination File: X7BPO3 Log: NOT-01121 Security Code: NC Mr. Jesse Arildsen VEGP Principal Examiner Regional Operator Licensing Section U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303

Dear Mr. Arildsen:

This letter provides our comments regarding the written examination which was administered on April 13, 1987 at Vogtle Electric Generating Plant.

The enclosure contains specific comments and recommendations based on a technical review of the questions and answers.

Conments are forwarded to provide the examiners with additional information that could effect answers to questions.

Sincerely, 77% p N Paul D. RushtonV Plant Training & Emergency Preparedness Manager KRH:PDR:kss Enclosure cc: Mr. Anthony Vinola P. O. Box 1625 j 1520 Sawtelle Drive ]

Idaho Falls, Idaho 834:5 Mr. J. J. Badgett NO-NORMS B707140357 870702 PDR ADDCK 05000424 V PDR

Question: 1.05 Comment: Student theory text gives equivalent explanation Recommendation: Also accept for full credit the concept that increasing boron concentration will reduce control rod worth, due to increased competition for neutrons in the core between the boron and control rods.

Reference:

Vogtle Training Text, Vol. 9, Pages 21-73, Paragraphs 3 & 4 i

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g' I Question: 1.23 Comment: 1. Proctor indicated that E0P indications were acceptable.

2. Many students derived answers from sources other than the question reference.

Recommendation: For part "b" also accept for full credit:

1. S.G. pressure stable or lowering

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Reference:

19001-1, Attachment D)

For part "c" also accept for full credit:

1. Subcooling stable or increasing (equivalent concept to establishment of adequate subcooling.

2. Subcooling greater than 28*F

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Reference:

19001-1, Attachment D)

For part "e" also acce-* for full credit:

1. Pressurizer level greater than or equal to 25%.

2. Pressurizer level trending to include setpoint of 25%.

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Reference:

LO-LP-34110, Page 4)

Reference:

See above i

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• Question: 1.24 Comment: Question did not state limit or infer depth or number of responses required for full credit. Since it is a broad-based generic question a student may have written a wide variety of answers.

Recommendation: Accept for full credit any response that indicates the candidate has an appreciation for the potential consequences of water hammer events.

Reference:

LO-LP-34203-01-c, Pages 26 - 28

Question: 2.04 Comment: Student identified more components / systems that discharged into PRT.

Recommendation: Also accept for full credit:

1. Discharge from reactor makeup water pumps (for spray cooling)

2. Discharge from RCDT heat exchanger

Reference:

P&ID 1X4DBil2 l

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o Question: 2.13.a i

Comment: Part "a": Proctor stated that decay heat load was at the instant of the reactor trip. Student knew that at approx. 1 i second after trip, decay thermal power is about 6-7% RTP.

Student answered FALSE based on proctor response, since he .

knew one AFW pump cannot support 6-7 RTP during low power.

Recommendation: N.A. ,

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Reference:

LO-LP-20101, Page 19

l Question: 2.13.b Comment: Vogtle Text and FSAR indicate that AFW will perform design l- function with concurrent single passive and single active ,

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Recommendation: Accept TRUE as the correct answer for 2.13.b.

Reference:

Vogtle Training Text, Vol. 7 Chapter 13.d, Page 13d-12 FSAR page 10.4.9-7

Question: 2.15 Comment: If one of the designated primary NSCW pumps in either train does not start, (2, 4) (1, 3), the train's standby pump will auto start from the sequencer at step, 30.5 seconds.

Recommendation: Accept for full credit auto-start of standby NSCW pump if one of two NSCW pumps failed to start.

Reference:

LO-LP-01401-01, Page 5 Elem. Dwgs: 1X3D-BD-K04A, K04E, 1X3D-AA-K02A LO-LP-06101-01-c l

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Question: 3.07 Comment: Submitted T.S. for this exam listed setpoint for steam line pressure rate high as less than or equal to 100 psi with a time constant of 50 seconds.

Recommendation: Accept less than or . equal to 100 psi with a 50 second time constant.

Reference:

T.S. Table 3.3-3, Pages 3/4 3-30 & 3-35 l

Question: 3.09.a Comment: Failure of either Data Card A or B will result in every other LED on DRPI moving.

Recommendation: Also, accept either Data Card A or Data Card B for full credit.

Reference:

LO-LP-27201-00, Page 8 Westinghouse - Vogtle DRPI 16C Text, Page 87 1

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Question: 3.18.c and 3.18.d Comment: The question reference (LO-LP-28101-00-c) does not support answers on key for parts c & d. Recommendation further ,

supported by attached documentation. '

Recommendation: Accept "1" as correct answer for both' parts "c" and "d".

Reference:

LO-LP-28101-00-c, Page 16, 17 l

Westinghouse SSPS Vendor Manual 1X6AX01-466 l

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Question: 4.03 Comment: The question states that you notice a rise in RCP seal package D/P while at 50% power. The range of this instrumentation is 0-400 psig and is normally off-scale high-whenever the RCS is at normal operating pressure.

Recommendation: Remove this question from the exam since the given conditions are not applicable to VEGP. {

Reference:

VEGP Scaling Manual, Volume 2 VEGP P&lD 1X4DB114 1

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I Question: 5.01

' Comment: Correct answer should be "a" for first 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> then "b" for next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> but not "c", rapidly inserting rods implies 48 steps / min continuously.

Recommendation: Delete question

Reference:

NRC Exam, Vogtle 1, 86/06/23 - Tom Rogers Reactor Core Control for Large PWR's, Westinghouse Text, Page 9-17 & 9-20 i

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Question: 5.05 Coment: Region C on curve is also known as transition boiling.

Recommendation: Also accept " transition boiling" as correct for region C.

Reference:

LO-LP-34105 Nuclear Heat Transport, M. M. EL-VAKIL l

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i Question: 5.06 1

Comment: There are many methods by which integral rod worth can be determined; and the question did not give plant or test conditions that would qualify or limit the students' responses. Also methods "a" and "b" are the same, since multiplication of the differential worth by the steps moved is a simplified form of integration.

Recommendation: Accept any two of the below for full credit, any of the following concepts, in addition to answers given on key,

1. Use of the formula CR) ,1-K 9 CR 1-K g to calculate the total change in reactivity due to control bank withdrawal.

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Reference:

Vogtle Text, Vol. 9 Pages 21-41 and 21-42)

2. Use of a test that maintained Tave or neutron flux constant while boron concentration is changed by dilution or boration, to offset rod motion.

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Reference:

Startup Test Procedure 1-6SF-06, Pages 6-9)

3. Use of the rod worth tables in PTDB to sum the values given there.

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Reference:

Plant Technical Data Book, Table 1.5.1-1 or 1.5.1-2, Integral and Differential Rod Worth)

4. Use of rod worth graphs in PTDB to sum the values given there.

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Reference:

Plant Technical Data Book, Figures 1.5.1-1 or 1.5.1-2, Integral and Differential Rod Worth)

Reference:

See above

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l Question: 5.07 v.

Comment: .The answer key list partial credit for calculating multiplication factor expected. It is also possible to j answer this question applying the " doubling" thumbrule. I Recommendation: Accept a discussion of fact that +1100 pcm reactivity was added and if countrate doubled then you have added 1/2 the reactivity necessary to make reactor critical. Therefore, initial reactivity given was incorrect.

' *?eference: N.A.

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Question: 5.13

- Comment: By tech specs requirements all choices are partially correct, none are completely correct.

Recommendation: Remove question from exam.

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Reference:

VEGP Tech Specs Surveillance, 4.1.1.2.b, Page 3/4 1-3

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i Question: 6.07 i

Comment: 1. Question requests 5 protection logic signals. There is j another logic signal generated by this system.

2. Latest low pressurizer pressure SI setpoint has been revised per tech specs to 1885 psig.  ;

l Recommendation: 1. Accept ~1885 psig as the correct low pressurizer pressure

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SI setpoint, q

2. Accept following as another acceptable answer:

Auto closure of PRZR PORVs and FORV block valves - less '

than 2185 psig, 2/4

Reference:

1. FSAR Figure 7.2.1-1, Sheet 6 ,

2. VEGP Tech Specs, Table 3.3-3, Pages 3-28 & 3-35 l

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Question: 6.09 Comment: Question solicits-three purposes for rod insertion limits.

The latest revision of tech specs provided, lists 8 reasons in the bases.

Recommendation: Accept 3 of the 8 reasons given in the tech spec basis in addition to those in the key.

Reference:

VEGP Tech Specs, Pages B 3/4 1-3 4 4 i

1 Question: 6.12.b Comment: The question was constructed such that part "b" could be construed as applicable to the statement that busses INB01 and INB10 are de-energized on a SI. In that case, the appropriate response to part "b" would be to prevent loading of non-1E loads while 1-E loads are being energized, as per the key.

The student may have taken part "b" to be app".icable to part "a", in that case it would be asking, why the installed control interlocks to allow re-energization of INB01 and INB10 are necessary. Therefore, the appropriate respons3 would be to allow re-energization of INB01 and 1NB10 to restore non-ESF. instruments and loads, such as radiation monitors or pressurizer backup heaters.

Recommendation: Accept'following as an alternate answer to part "b" - to allow re-energizing loads powered from these busses before the SI signal is reset.

Reference:

Change Control Package #B10018E, Page 16 i

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Question: 6.15

-Comment: The latest revision of tech specs provided, lists 22.5% as the SG 1011o level trip setpoint.

Recommendation: Accept 22.5% as the correct setpoint.

Reference:

VEGP Tech Specs, Table 2.2-1, Page 2-5 1

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l Question: 6.18 Comment: There is an additional purpose of the SG ARVs specified in the VEGP FSAR.

Recommendation: Accept "provides a means for safety-grade cooldown or maintenance of hot standby".

Reference:

.VEGP FSAR 7.4.1 & 7.4.2

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,. .. o Question: 6.21 l

Comment: There are additional design considerations given in the FSAR.

Recommendation: Accept functions listed on Page 5.4.4-1 of FSAR (attached).

Reference:

VEGP FSAR 5.4.4-1 l

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Question: 6.23 Comment: The lesson plan referenced for this question lists 3 reasons

- of the needle valves on the injection lines.

Recommendation: Accept any 1 of the 4 reasons listed in the referenced lesson plan.

Reference:

LO-LP-09202-01, Page 7 i

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l Question: 7.06.a Comment: This caution from page 5 in 18028-1, " Loss of Instrument Air", is incorrect for Vogtle plant design. Instrument air provides control for the PD pump fluid drive unit, while service air is used to purge the pump stuffing box for maintenance.

This procedural error was identified and a revision requested prior to the written examination, and students were aware that service air failures do not affect pump performance.

But no new revision of the procedure was issued, and most students answered the question as shown on the key.

1 Recommendation: Also accept for full credit that loss of service air to PD pump has no affect, if[ student qualifiel answer with statement that actual plant design uses instrument air for control of pump speed.

Reference:

P&ID 1X4DB116-1 P&ID 1X4DB186-1, 186-7 Vendor Print PCN753719D

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Ques'. ion : 7.07 Comment: Examiner used an outdated-procedure (18003-1, Rev. 2 was submitted for use).

The answer on the key, choice "a"., cannot be correct. A dropped rod will reduce Tave, and the remaining rods would be withdrawn, not inserted, to match Tave and Tref.

Answer "c" could be correct if the rod dropped due to a failure that did not produce an urgent alarm in the rod control system. The remaining rods would then withdraw automatically to match Tave with Tref.

Answer "d" is correct since the RNO for step A.3 allows operators to dilute or borate to initially restore Tave to program if required, and step A.11 does not give the method for ensuring Tave and Tref are matched during retrieval of the dropped rod. In some cases, boration or dilution would be the preferred method due to power distribution considerations.

Recommendation: Accept for full credit either "c" or "d".

Reference:

Procedure 18003-1, Control Rod System Malfunction, Symptoms, Step'A.3, and Step A.11 i

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Question: 7.17 Comment: ECA-0.0, 19100-1, " Loss of All AC", is one E0P that may be entered directly without first performing E-0,19000-1,

" Reactor Trip and SI".

Recommendation: Students are allowed the option of entering 19100-1, " Loss of All AC", directly from symptoms or from step 3 of 19000-1, "Rx Trip and SI". Accept either choice "a" or choice "c" for full credit, or delete question.

Reference:

Vogtle E0P Training Text, Page V-5-6 Westinghouse Owner's Group Background Document for ECA-0.0, Page 2 1

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Question: 7.22.a Comment: In order for the question to be answered "TRUE", it must be l true all the time. AN ORANGE or RED path condition FRG may be suspended if a higher priority CSF is challenged and its FRG must be initiated. The question was not qualified enough to determine if it meant the FRG must always be completed once initiated, or if it can be suspended to complete a higher priority FRG.

Recommendation: Delete question; it is sometimes TRUE and sometimes FALSE.

Reference:

Vogtle E0P Training-Text, Page VII-1-9 Westinghouse ERG Users Guide 6689B:1, Page 11, 9/1/83 Westinghouse ERG Seminar for NRC Operator Licensing Observations (attached) l 1

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,, i;* i Question: 7.22.c Comment: Vogtle E0P 19200-1 CSF Trees, does not permit reduced monitoring frequency of CSFTs, regardless of Termini color, until core exit TCs read less than 200*F.

Recommendation: Accept only FALSE as the correct answer.

Reference:

Procedure 19200-1, CSF Trees, Steps 1 through 4 4

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• Question: 8.15 Comment: The answer in the key is incomplete per the procedure.

Depending on if the person can or cannot be contacted, the answers possible should be:

a.

1. OSOS or dept. supervisor if subclearance holder gives permission by phone.

2. OSOS and dept. supervisor if subclearance holder ,

cannot be contacted. '

3. General Manager, Plant Manager, or the Plant Support Manager if conditions of Figure 9 are not met.

b.

Notify subclearance holder upon his/her return to work if he/she could not be contacted while off-site.

Recommendation: Accept answer given above as the correct answer to the question.

Reference:

Procedure 00304-C, Rev. 8, Pages 4, 19, 20, 35

., e, 'o Question: 8.17 Comment: With one SI train (B) inoperable and.the A train RHR pump inoperable you are required by tech spec 3.0.3 to place the unit in a mode where the T.S. does not apply. This would be modes 4, 5, or 6.

Reason: T.S. 3.5.3.1 requires one train of ECCS subsystems to be operational. The inoperability of the B train RHR pump is covered by action statement "b" which requires maintaining RCS Tave less than 350*F (mode 4).

Recommendation: Accept modes 4, 5, or 6 as correct answers.

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Reference:

VEGP Tech Spec 3.0.3, 3.5.2 and 3.5.3.1 1

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