ML121280573

Initial Exam 2012-301 Post Exam Comments

ML121280573
Person / Time
Site:	Vogtle
Issue date:	04/26/2012
From:	Brown R Southern Nuclear Operating Co, Southern Co
To:	Michael Meeks NRC/RGN-II
References
NOT- 04406
Download: ML121280573 (10)

Text

Southern Nuclear Operating Company, Inc.

Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830 Tel 706.724.1562 Augusta Line 706.554.9961 Waynesboro Line SOUT HE RN COMPANY NOT- 04406 April 26, 2012 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission, Region 11 Marquis One Tower Suite 1200 245 Peachtree Center Avenue, N.E.

Atlanta, Georgia 30303-1257 AflN: Mr. Michael Meeks VOOTLE ELECTRIC GENERATING PLANT NRC WRITFEN POST EXAM

Dear Mr. Meeks:

Attached please find the VogUe Units I & 2 Written Post Exam Package. This exam was administered on Friday, April 20, 2012. This exam package is being submitted in accordance with NUREG-1021 Revision 9, Supplement 1.

Please contact Bob Brown at 706-826-3901 if you have any questions.

Sincerely, Robert J. Brown, Jr. /

VogUe Units I & 2 Training Department Manager RJB/cmh

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ILT-17 NRC WRIHEN EXAM QUESTION #32

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32. 039K5OS 001 Given the following plant conditions:

- Unit I is at EOL.

- A Reactor Startup is being planned.

- The Estimated Critical Condition (EGG) calculation predicts criticality at 100 steps on Control Bank 0.

Which one of the folLowing conditions will result in critical rod height being HIGHER than the value predicted by the ECC?

For your answer, consider that no operator actions are taken to mitigate or compensate 1

(or the below events.

A. A dilution of 500 gallons is performed.

B. Aux Feedwater flow is RAISED to all SGs.

C! A Post Maintenance Test results in the closure of all MSIVs.

D. A Reactor startup to occur 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> alter unit shutdown from 100% power.

VogtleUnit1and2

ILl-li NRC WRITtEN EXAM QUESTION #32 039K5.O8 Main and Reheat Steam Knowledge of the operational implications of the following concepts as they apply to the MSRS (CFR 41.5145.7):

Effect of steam removal on reactivity K1A MATCH ANALYSIS The question presents a plausible scenaros where the candidate must determine reactivity effect on the ECC, three of which are secondary system perturbations and two of these are main steam including the correct answer.

ANSWER/ DISTRACTOR ANALYSIS A. Incorrect. A diluhon results in positive reactivity addition. 2CC rod height will be sower.

B. Incorrect, More AFW flow will lower RCS temp adding positive reactivity (Negative MTC at EOL). 2CC rod height will be lower.

C. Correct. MSIV closure will increase ACS temp to ARV lift setpoint (approx 5 degrees) adding negative reactivity (Negative MTC at EOL). ECC rod height will be higher.

D. incorrect. Xenon decay is occurring and less negalive Reactivity is being produced.

therefore ECC rod height will not have to be further cut of the core.

REFERENCES Watts Bar 2008 RO NRC exam question # 41 V-LO-TX-33600-03 Reactor Theory, Fission Product Poisons VEQP learning objectives:

V-LO-LP-6 1201-02 During subcritical condiUons, state the possible effect on subcritlcality of the following:

a. Rod withdrawal/insertion

b. Boron concentration changes

c. Xenon concentration changes

d. Heat remova[Jaddition Plant Vogtle Unit land 2 fl

ILT-17 NRC WRITTEN EXAM QUESTION #32 We would like to 5ubmit the following for your consideration regarding VEGP HL-17 written license examination administered on 4/20/2012.

Question #32.

Recommendation Recommend accepting both answers C and D as correct choices for question #32 for all applicants.

The bases for answering the question correctly involved determining the core reactivity balance change that would result in a critical control rod height higher than the predicted ECC. The answer key list choice C as the correct answer, which would result in a net negative reactivity addition to the core and thus a higher critical rod height, this choice is correct as written and is not in contention. However, we would like to summit the following discussion for your consideration related to distracter 0. The timeline for the Reactor startup was not made clear in the given stem of the question and as a result this answer could also be correct.

Xenon concentration at 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> post trip will be greater than either 100% power equilibrium conditions or 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> post trip. The first clarification referenced 100% power equilibrium conditions, the second clarification referenced 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> post trip conditions. Both of these clarifications reinforce choice D as an additional correct choice to this question.

The following PTDB curves and references are provided to support this core condition:

Vogtle Electric Generating Plant lent Technical Data Book I

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I-. .4 !i it-it-- r4, Plant Vogtle Unit 1 and2

ILT-17 NRC WRIflTN EXAM QUESTION #32 Ivealillghouse Tropnctnrw (rid* 2 I NO.

Vogtle Electric Generating Plant 1.0 2*

Page HuSer Plant Technical Data Book Unit I 18 of 37 I - .---

REACTIVITY CURVES 1*5 Xt?ION AflliA S8VTD04474 (ZOL) cYCX.z 17 SoronPce. Xenon Worth versa. lisa Following Plant Trip after Steady State Op.ration at 500..

(Applicable for Burnups 14000 34940/NTU) 90%.er ISsa (knarel 0 2 a 9 10 12 14 16 II 20 35 30 LenS 0 0 0 0 0 0 0 (5 5 0 0 0 0 0 9 887 894 879 845 790 77? 754 587 529 571 585 183 345 257 10 352 III)? 437 1370 307 269 (22* (40 1Q19 957 867 761 598 431 15 679 1785 18:1 1729 1701 666 1617 508 392 1279 1157 1043 7963 5996 20 926 1039 2146 21211 2050 2010 (935 0610 698 548 1415 1281 976 726 25 2119 2343 2430 1435 2369 2389 2261 2123 971 1812 1653 14962 IllS $54 30 226 254 2624 270 2643 2597 2531 1385 2220 2015 I 969 1696 299 971 35 2402 2755 2916 2367 2916 2835 2802 2947 241.4 2279 2084 1294 454 103$

40 2432 29,3 3128 394 3153 3104 314 2887 2992 2463 22.80 2074 5% 1895 45 25$? 3072 3330 3429) 3391 3341 3240 3114 2015 2690 24fl. 7254 739 (301 50 2672 3350 3.32 3617 3629 3583 3519 .44g 3139 22 2672 2434 929 1412 55 2734 3359 3764 3815 3340 3797 3733 9558 04 31281 2650 2599 2010 (512 60 2795 3459 3877 4048 4051 1010 3347 3759 3243 72292 3028 2764 2140 1611 65 25)8 3591 40111 4207 4223 4187 1(25 3944 3713 3452 317$ 29602 2250 1695 0 2*01 3693 4158 4370 4405 4755 8303 1120 3882 3512 3327 3040 2359 779 S 2924 3195 1298 4533 4575 4542 458) 82% 4041 3772 3117 3176 2169 18*2 40 2995 32477 1408 6639 4750 40119 45(9 4432 41143 3397 3594 3286 2554 162$

a 29% 3950 1554 47I 486 4817 4758 1562 4314 4022 3710 3394 2640 593 SO 3008 4005 4590 4874 4941 49(8 4*55 -8664 1407 410S 3792 3469 2796 2630 82 3030 1059 4666 4053 5030 5010 -1452 (760 4495 4(07 41474 3545 2760 26*3

.00 3052 4114 4742 5(452 5131 5107 5010 48)0 4592 4284 3956 3621 2920 2131 Xenon at 15

- hours EQUILIBRIUM XENON 100% -

REACTOR POWER Xenon ato hours Plant Vogtle Unit land 2

ILT-17 NRC WRlTEN EXAM QUESTION #32 The following clarifications were given:

5t 1

Question was asked: What is the time 5ince 5hutdown and from what power level for the original ECP calculation? Questioned asked at 08:52 hrs.

Response given: The reactor startup is being planned following a plant trip from 100% power after 100 days of steady state operation.

This response means that equilibrium Xenon conditions existed prior to the reactor trip and further reinforces the comparison of Xenon concentrations at 100% power and 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> post trip. The 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> post trip condition will result in a higher critical rod height making choice D correct in addition to choice C.

This response was given to all applicant s at 10:00 hrs.

21 Question asked: Given condition: A Reactor Startup is being planned. How many hours after the unit shutdown is the planned startup? Answer 0 states 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after unit shutdown. The planned Rx startup time is needed because a startup of 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after shutdown will have different reactivity concerns if it were planned at 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> (with reference to the 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> stated in the answer).

Questioned asked 12:53 hrs.

Response given: Consider that the ECC predicting criticality at 100 steps is calculated for a time 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> post trip.

This response was given to the 4 remaining applicants at 15:05 hrs.

15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> following a Reactor trip, Xenon concentration will be greater than at 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> post trip, resulting in choices C and D being correct.

Recommend accepting both choices C and D for all applicants.

Plant Vogtle Unit land 2

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ILT-17 NRC WRITTEN EXAM QUESTION #96

96. u2.1.12cg)]

Procedure list as foUows:

- 91101-C. Emergency Response Orgariation

• 9140-C. Asseinby and AccountabIity

- 91403-C. Se D;snissa Gi,en the followinq

- An on shfl Systems Oporatcr (not hoiding an ERO position) is inside 11w Protected Area.

- A Radiological Emergency is declared

- The Emergency Director orders assoniby and accountability.

Which one of the DIIcwing correcty completes the lnlcwing statement?

Per the procedures hsted abose. The SO will eporl t Va (1) and the MINIMUM Emergency Action Level (EAL) whore the Emergency Direclor is REQUIRED to order a Site Dismissal of all non-involved personnel (if feashIe) is

_( 2 )_.

_( I)

A. 050 Alert Emergency B. OSC Site Area Emergency C. Control Room Alert Emergency Control Room Site Area Emergency Plant Vogtle I

April24, 2O12 [ILT17 NRC WRITTEN EXAM QUESTION #96 G2,4.12 Knowledge of general crew operating responsibilities during emergency operations (CFR 41.10! 45.12)

K/A MATCH ANALYSIS The question pmsents a plausible scenario where the Emergency Directors orders Assembly and AccountahUily during an emergency declaration. The candidate must determine wher9 a System Operator (on shift) not assigned an EPO position would report. In addition, the candidate will determine the minimum EAL whcio a Site Dismissal is requtrod.

SAC 1UCFRSS 43 [b)(5)f1 ssessment anc selection or procedures)

ANSWER! DISTRACTOR ANALYSIS A. Incorrect. The I rsl half is incorrect, on shift operators report to the Controi Room.

Oft shift operators are required to report to the OSC.

The second hail is incorrect, Ste Area is the mirimjm EAL where the ED is required to order a Site Dismissal witi orvAthout monitorir The ED coud decice to order Site Dismissal at the Alert level but is not pr000dLrahiy required lo do so.

B. Incorrect. The First half is incorrect, c-i shift operators report to the Controi Room.

Cli shift operators are requ red to report to the USC.

The second half is correct. Site Area is the minimum EAL where the ED is required to order a Site Dismissal with or without monitoring. The ED could decide to order Site Dismissal at the Alert level but is not procedurally required to do so.

C. Incorrect. The first half is correct, on shift operators rejort to the Control Room.

The second ha!t is incorrect. Site Area is the minimum EAL whee tIe ED is required to order a Site Dismissal with or without monitoring. The ED could decide to order Site Dismissal al the Alert level but not procedurally equired to do so.

D. Correct. The tirst halt is correct, on shifl operators report to the Control Room.

The second flail is correct. Site Area is the minimum EAL where the ED is required to order a Site Dismissal with or without nt oniloring. The ED could decide to order Site Dismissal at the Alert level but is not procedurally required to do so.

REFERENCES 91101-C, Emergency Response Organization 91 102-C, Duties of the Emergency Director 91202-C, Activation and Operation of the Operations Support Center 91401-C, Assembly and Accountability 91403-C, Site Dismissal VEGP learning oblectives:

LO-LP-4O101-24 State the circumstances requiring site dismissal with or without monitoring (SAC ONLY)

Plant VogUe

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[ILT-17 NRC WRITTEN EXAM QUESTION #96 We would like to submit the following for your consideration regarding VEGP HL-17 written license examination administered on 4/20/2012.

SRD Question #96 Recommendation Recommend deleting Question #96 from the exam based on the Post-Examination review, due to newly discovered technical information regarding the requirement of personnel not involved in the accident and not holding any ERO position. Per 91401-C, Assembly and Accountability, step 5.6.3 Alt other PA personnel and visitors with no responsibility in the ERO shall exit the PA following use of the exit card reader, and shall report to designated assembly areas. A complete list of assembly areas is provided in Table 1.

TABLE 1 DESIGNATED ASSEMBLY AREAS AND GROUPS ASSEMBLY GROUP ASSEMBLY AREA SUPERVISOR

1. Control Room Emergency Staff Control Room Shift Manager

2. TSC Emergency Staff TSC TSC Manager

3. OSC Emergency Staff OSC OSC Manager

4. Non-involved Protected Area Inside the Administration Building First Reporting Supervisor Personnel and Visitors Until Relieved (1985304904)

5. Non-involved Personnel and Remain at present location or First Reporting Supervisor Visitors outside the Protected assemble inside the Administration Building Until Relieved Area Plant VogUe

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• ILT-17 NRC WRITTEN EXAM QUESTION #96

6. Non-involved Outage Contractors Inside the Administration Building First Reporting Supervisor inside the Protected Area Until Relieved (1985304904)

7. Non-involved Outage Contractors Remain at present location or First Reporting Supervisor outside the Protected Area assemble inside the Administration Building Until Relieved

91401-C ASSEMBLY AND ACCOUNTABILITY 5.6 PLANT PERSONNEL 5.6.1 Personnel with primary or alternate responsibilities in the Emergency Response Organization (ERO) shall report to their assigned ERF for accountability prior to completing any emergency assignments unless otherwise directed by the plant page public address system announcement.

5.6.2 Personnel outside the PA who must enter the PA to assume their emergency positions shall follow normal PA entry procedures including proper use of the entry card reader.

5.6.3 All other PA personnel and visitors with no responsibility in the ERO shall exit the PA following use of the exit card reader, and shall report to designated assembly areas. A complete list of assembly areas is provided in Table 1.

5.6.4 Operators not badged into the CR, TSC or OSC should report to their location as soon as practical. (1985304678)

Plant vogUe I