ML20199E597
| ML20199E597 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/23/1998 |
| From: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Gabe Taylor SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 9901210028 | |
| Download: ML20199E597 (102) | |
Text
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I December 23, 1998 South Carolina Electric and Gas Company ATTN: Mr. Gary J. Taylor, Vice President
' Nuclear Operations Virgil C. Summer Nuclear Station
)
P. O. Box 88 Jenkinsville, SC 29065 l
l
SUBJECT:
MEETING
SUMMARY
- TRAINING MANAGERS' CONFERENCE CONDUCTED i
ON NOVEMBER 5,1998 - VIRGIL C. SUMMER NUCLEAR STATION i
Dear Mr. Taylor.
i This letter refers to the Training Managers' Conference conducted at the Richard B. Russell Building on November 5,1998. Representatives from all utilities in Region 11 participated in the meeting.
, was the agenda used for the Training Managers' Conference, and Enclosure 2 ts l
the list of attendees. We appreciate the participation of you and your staff and believe that the l
goal of providing an open forum for discussion of operator licensing issues was met. Mr. Gallo, Chief of the Operator Licensing and Human Factors Branch, Office of Nuclear Reactor l
Regulation (NRR), made a presentation as noted in the slides in Enclosure 3.
l Additionally, I am enclosing our preliminary schedule for FY 1999 and FY2000 as Enclosure 4.
l Please review the schedule and supply comments to my staff or myself.
l If you have any questions regarding the content of this letter, please contact me at (404) l 562-4638.
t Sincerely, i
Original signed by l
Thomas A. PEebles l
9901210028 981223 PDR ADOCK 05000395 T omas A. Peebles, Chief V
PDR Oherator Licensing and Human i
Perforgance Branch j
l Division of Reactor Safety Docket No.: 50-395 License No.: NPF-12 1
- 00030 lf i
Enclosures:
As noted cc w/encis:
/
T. Matlosz, Manager, Nuclear Training, V. C. Summer Nuclear Station
- S. Byrne, Plant Manager, V. C. Summer Nuclear Station A. Rice, Manager, Nuclear Licensing and Operating Experience M
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SCE&_G 2
Distribution w/encls:
PUBLIC B. Michael, DRS Ril:DRS Ril:DRS M
7M BMICHAEL:
TPEEBLES 12/ // /98 12//' /98 Doc Name:
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Revised November 3,1998 1
TRAINING AND OPERATIONS MANAGERS' CONFERENCE l
l l
U.S. Nuclear Regulatory Commission, Region II j
Atlanta, Georgia l
Meeting Agenda I
November 5,1998 Richard B. Russell Building Auditorium 1
Thursday.11/5/98 8:00 a.m.
Conference Registration 8:20 a.m.
Introduction Thomas A. Peebles, Chief, Operator Licensing & Human l
Performance Branch 8:30 a.m.
Opening Remarks William Travers, Executive Director of Operations 8:50 a.m.
Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety 9:15 a.m.
break 9:45 a.m.
Other Issues Robert M. Gallo, Chief Operator Licensing Branch, NRR I
10:15 a.m.
Lessons Learned from Recent Exams Charlie Payne Sampling exam criteria 11:00 a.m.
Examination Communications Ron Aiello Exam Development & Coordination 11:30 a.m.
Lunch
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1:00 p.m.
Written Examination Questions and Answers Rick Baldwin / George Hopper 2:30 p.m.
JPM Examples of questions Rick Baldwin / George Hopper 3:30 p.m.
Open Session - Other Issues Training Managers 4:00 p.m.
Meet with Principle examiners All l-4:30 p.m.
Adjorn I
License Applicant Adrainistrative Walkthrough Examination--NRC-1 Examiner Sheet A.1: t Shift Staffing ~
Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of a shift RO.
What additional requirements must be met by the RO before he may fill in for the vacationing RO?
References Allowed? YES _2L NO Answer:
The RO must complete an additional 24 (40 - 16) hours of"under dir'ection" on-shift time that must include a plant tour and shift turnover.
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT i
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1 S
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ATTENDEES AT THE NRC REGION 11 TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 Sid Crouch ATTSi David Lane Sonalysts, Inc.
Bill Fitzpatrick INPO CP&L Rick Garner HR Supv Ops Tmg William Noll BK Ops Tmg Supv Max Herrell BK Tmg Mgr Scott Poteet RB Exam Team Leader Ralph Mullis BK Ops Mgr Tony Pearson BK Ops Trng Anthony Williams RB Tmg Mgr Crystal River - FPC Wes Young CR Supv OpsTng Tom Taylor CR Dir Nuc Ops Tmg Ivan Wilson CR Ops Mgr Ken McCall CR Mgr Ops Tmg Duke Power Gabriel Washbum OC Req Team Leader Ronnie B. White, Jr MG Tmg Mgr W. H. " Soap" Miller CT
- Site Trng Mgr Paul Stovall OC Mgr Oper Tmg Bentley Jones OC -
Tmg Mgr J mes Teofilak CT Ops Tmg Mgr Alan Orton MG Ops Tmg Mgr Richard Bugert Corp. Ops Tmg Spec FP&L Maria Lacal TP Trng Mgr Dennis L. Fadden SL Services Mgr Jo Magennis Corp Tmg Assessment Spec Tom Bolander SL Exam Development Steve McGarry TP Maint Tmg Supv Southern Nuclear (SNC)
John C. Lewis HT Trng & EP Mgr Bill Oldfield FA Nuc Ops Trn Supv Steve Grantham HT Ops Tmg Supv l
Scott Fulmer FA Mgr Tmg & EP Joel Deavers FA Sr Pit inst Bob Brown VG Tmg Mgr l
Dan Scukanec VG Ops Trng Supv i
Virainia Power Steve Crawford NA Sr inst Nuc Harold McCallum SR Supv Ops Trng TVA Dick Driscoll SQ Tmg Mgr Walt Hunt SQ Ops Tmg Mgr Denny Campbell BF SRO Ops Inst Jack Cox WB Tmg Mgr John Roden WB Ops Tmg Mgr Tom Wallace WB Ops Supt V. C. Summer-SCE&G AlKoon SM Ops Tmg Supv NRC Participants Tom Peebles R 11 Operator Lic. Br. Ch.
Rick Baldwin R 11 Sr. Examiner George Hopper R ll Sr. Examiner Ron Aiello R 11 Sr. Examiner Charlie Payne R 11 Sr. Examiner William Travers NRC Executive Dir. Ops.
R. M. Gallo NRR Br. Ch. OL Bruce Mallett R ll Div. Dir. Reactor Safety 1
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1 1
4
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FY 99 INITIAL EXAM SCHEDULE AND RESULTS D cember 14,1998 RO SROl SRO-U TOTAL Date Plant Chief Pass Pass Pass Pass 9/28/98 Sequoyah GTH 4
4 4
4 10/5/98 Harris RFA 2
2 5
5 7
7 11/30/98 Oconee GTH 2
2 5
5 7
7 11/30/98 St Lucie &
RSB 6
3 9
12/14/98 1/25/99 McGuire &
DCP 6
3 2
11 2/8/99 2/8/99 C. River &
GTH 6
6 12 2/22/99 2/8/99 B. Ferry MEE 4
1 5
3/29/99 Surry &
RSB 5
2 4
11 4/12/99 4/12/99 Watts Bar &
MEE 6
3 5
14 4/26/99 5/10/99 Farley GTH 7
1 8
5/24/99 Catawba &
PMS 8
5 3
16 6/7/99 6/28/99 St. Lucie RSB 1
4 5
07/26/99 Robinson MEE 3
2 2
7 08/30/99 Turkey Pt &
RFA 20 20 9/13/99 136 i
RESULTS TO DATE 4
4 5
5 9
9 18 18 100 100 100 100 i
No initial exams scheduled for:
Brunswick, North Anna and Vogtle FY 00 region 11 write part of Summer & Hatch c
FY 00 INITIAL EXAM SCHEDULE AND RESULTS Dec:mb:r 14,1998 RO SRO-l SRO-U TOTAL D:t3 Plant Chief Pass Pass Pass Pass 0
9/27/99 Summer GTH 6
6 region ll write 10/18/99 Hatch DCP 10 2
12 ragion ll write 12/13/99 Vogtle RSB 3
5 2
10 l
2/14/00 Brunswick &
DCP 12 3
15 2/28/00 03/"/00 Oconee ?
10 704/10/00 Harris (maybe 10/oo) 10 705/03/00 St. Lucie GTH 6
5 11 705/"/00 B. Ferry 6
3 3
12 705/03/00 McGuire 4
8 12 706/07/00Farley RSB 10 2
12 707/26/00 Crystal River RFA 3
3 3
9 region ll write?
708/"/00 Sequoyah 4
2 2
8 709/04/00 Surry?
10 709/11/00 North Anna 12 0
0 42 0
46 0
27 0
149 i'?' d:signates tentative No initial exams scheduled for:
Catawba l
Robinson Turkey Point Watts Bar
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Operator Licensing
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Issues i
j Region 11 j
Training Managers' Conference i
November 5,1998
)
i Robert M.
Gallo, Chief l
Operator-Licensing and 4
i Human Performance Branch
4 i
l OPERATOR LICENSING ISSUES i
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Part 55 Rulemakings o
l Status Schedule Final Revision 8 of NUREG-1021 o
Examination Quality and Results o
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Generic Fundamentals Exam o
Requal inspections IIP-710.01?
o Recent Information Notices o
Exam Integrity (IN 98-15)
Sampling Plans (IN 98-28)
Eligibility (IN 98-37?
RECENT LESSONS LEARNED by Charlie Payne
~
Southeastern Training Manager's Conference
^ November 5,1998 l
' ' ~ ' ' ' ' '
PC'LLCY CLARIFICATIONS 9
In general, the NRC prefers that the written exam be administered after the operating tests are complete.
Allows more time to finalize test.
More flexibility if delays occur.
Less stressful on candidates.
I 2
PC1LICY C_LARIFICATIONS 9
In general, license class sizes of greater tlan H candidates will be scheduled for 2 weeks as follows:
1
- exam week off-week for documentation of week 1 performance 2"d exam week I
t 3
POLICY CLARIFICATIONS O
Examination submittals - 2 copies of draft and final exams { written, JPMs, and simulator scenarios). Elsctronic copy is also desired.
9 Written exams submittals will be reviewed by following a sampling process. When critena are met, review will be stopped and licensee called.
Criteria - 10 unacceptable questions out of 30 questions sampled j
i 4
l
RE_ CENT LE_SSONS LEARNED SRO-only Questions intended to sample those K/As specific to SRO duties (above and beyond those needed by an RO).
purpose is to meet the requirements of 10 CFR 55.43(b) (items (1) - (7)}.
K/A catalog cross-references K/As to associated portions of 10 CFR 55.
5
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2.0 GENERIC KNOWLEDGES AND l
ABILITIES 2.1 Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements.
l (CFR: 41.10 / 45.13)
IMPORTANCE RO 3.7 SRO 3.8 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
l (CFR: 41.10 / 45.13)
IMPORTANCE RO 3.0 SRO 4.0 2.1.3 Knowledge of shift turnover practices.
(CFR: 41.10 / 45.13)
IMPORTANCE R O 3.0 SRO 3.4 l
2.1.4 Knowledge of shift staffing requirements.
M (CFR: 41.10 /43.2) j IMPORTANCE R O 2.3 SRO 3.4 l
2.1.5. Ability to locate and use procedures and directives related to shift staffing and activities.
(CFR: 41.10 / 43.5 / 45.12)
2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.
4 (CFR: 43.5 / 45.12./ 45.13)
IMPORTANCE R O 2.1 SRO 4.3 2.1.7 Ability to evaluate plant performance and make operationaljudgments based on operating characteristics / reactor behavior / and instrument interpretation.
(CFR: 43.5 / 45.12 / 45.13)
IMPORTANCE RO 3.7 SRO 4.4 2.1.8 Ability to coordinate personnel activities outside the control room.
- - +-
(CFR: 45.5 / 45.12 / 45.13)
i 2-1 h" REG-1123. Rev. 2 l
]
i i
2.1 Conduct of Operations (continued) 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.
(CFR: 45.12)
IMPORTANCE RO 3.0 SRO 3.0 2.1.20 Ability to execute procedure steps.
(CFR: 41.10 / 43.5 / 45.12)
~
2.1.21 Ability to obtain and verify controlled procedure copy.
(CFR: 45.10 / 45.13) l IMPORTANCE RO 3.1 SRO 3.2 2.1.22 Ability to determine Mode of Operation.
t (CFR: 43.5 / 45.13)
IMPORTANCE RO 2.8 SRO 3.3 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.
(CFR: 45.2 / 45.6)
IMPORTANCE RO 3.9 SRO 4.0 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
(CFR: 45.12 / 45.13)
IMPORTANCE R O 2.8 SRO 3.1 l
2.1.25 Ability to obtain and interpret station reference materials such as graphs /
monographs / and tables which contain performance data.
(CFR: 41.10 / 43.5 /45.12)
IMPORTANCE R O 2.8 SRO 3.1 2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical /
high temperature / high pressure / caustic / chlorine / oxygen and hydrogen).
(CFR: 41.10 / 45.12)
IMPORTANCE R O 2.2 SRO 2.6 i
i 2-3 h"J.EG-11 3, F.ev. 2 l
l
4 l
2.4 Emergency Procedures / Plan (Continued)
I 2.4.32 Knowledge of operator response to loss of all annunciators.
j (CFR: 41.10 / 43.5 / 45.13) l IMPORTANCE RO 3.3 SRO 3.5 l
2.4.33 Knowledge of the process used track inoperable alarms.
l (CFR: 41.10 / 43.5 /45.13) j IMPORTANCE RO 2.4 SRO 2.8 1
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2.4.34 Knowledge of RO tasks performed outside the main control room
~during emergency operations including system geography and system implications.
(CFR: 43.5 / 45.13)
IMPORTANCE RO 3.8 SRO 3.6 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations l
including system geography and system implications.
- - = = >
(CFR: 43.5 / 45.13)
IMPORTANCE R O 3.3 SRO 3.5 t
1 l
2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.
l (CFR: 43.5)
IMPORTANCE RO 2.0 SRO 2.8 2.4.37 Knowledge of the lines of authority during an emergency.
(CFR: 45.13)
IMPORTANCE RO 2.0 SRO 3.5 2.4.38 Ability to take actions called for in the facility emergency plan / including (if required) supporting or acting as emergency coordinator.
(CFR: 43.5 /45.11)
IMPORTANCE R O 2.2 SRO 4.0 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.
(CFR: 45.11)
IMPORTANCE R O 3.3 SRO 3.1 l
l 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.
(CFR: 45.11)
t 2.4.41 Knowledge of the emergency action level thresholds and classifications.
r (CFR: 43.5 / 45.11)
IMPORTANCE R O 2.3 SRO 4.1 l
NUREG-1123, Rev. 2 2-14 l
REC _ENT LE_SSONS LEARNED SRO-only Questions (Cont'd;'
.. SRO-only questions will be based on following categories: A.2, G2.1, G2.2, G2.3, anc G2.4.
differences between SRO and RO outlines shifts only 11 K/As from Tier 2 to Tiers 1 & 3.
- Other 14 flexible.
I 6
ES-401 BWR SR0 Examination Outline Form ES-401-1 Facility:
Date of Exam:
Exam Level:
K/A Category Points Tier Group Point K
K K
K K
K A
A A
A G
Total 1
2 3
4 5
6 1
2 3
4 i
- ga w:c 1.
1 A@sh.m@g@y
%:...ag 26 n
-v n
i Emergency &
gg y y
s g g (%g.x
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17 P1 ant Tier gj g
m
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y.
l Evolutions g
&gj gjf syj 43
+7 g
di h4 Totals iW %
1%!r Mdi iR E
$4r et 22 e ej #
1 23 l
2.
2 Plant 13 Systems 3
4 Tier 40
_.jj Totals i
l 3.
Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17
+Y Note:
Attempt to distribute topics among all K/A categories: select l
at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the j
associated outline.
The shaded areas are not applicable to the category / tier.
1 i
NUREG-1021 10 of 39 Interim Rev. 8, January 1997
ES-401 BWR R0 Examination Outline Form ES-401-2 Facility:
Date of Exam:
Exam Level:
K/A Category Points Tier Group Point K
K K
K K
K A
A A
A G
Total 1
2 3
4 5
6 1
2 3
4
- m ggs ;g 1.
I g g %
gp gy 13 Emergency &
k-akUb
- M' Di 19 2
Abnormal 4*e*
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E MA N Sk Th_
4 w
a ra w w.a:.; w.
Evolutions pp g g.
g y 1er 36
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Totals (if % ($j N i!L i
1 28 2.
2 Plant 19 Systems 3
4 Tier 51 Totals 3.
Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 13 Note:
Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.
1 Actual point totals must match those specified in the table.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
NUREG-1021 16 of 39 Interim Rev. 8, January 1997
REGENT LEB_ SONS LEARNED Sampling Criteria intent of 3rodess is to avoid exam predictability.
also to avoid excessive use of repeat test items.
first use systematic process to develop sample plan using topics from K/A catalog, then use facility question resources to accomplish t7e plan.
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RE_C_ENT LES_ SONS LEARNED
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Sampling Criteria (Cont'd) each topic in each tier & group should be sampled at least once unless insufficient questions exist to do this. If all topics have been sampled once and other questions need to be selected, the process should be systematic and unbiased.
i final sample plan should have a fairly even I
balance across all Ks & As.
J i
8
i RECENT LES_ SONS LEARNED l
Sampling Criteria { Cont'd}
j up to 25 questions from last two NRC exams, facility licensee exams, tests & quizzes j
(except final audit test) may be used.
Chief Examiner (CE) has the option to unilaterally shift or change the selected K/As.
up to 5 site-specific priorities may be identified j
with CE concurrence (K/A value may be < 2.5 with sufficient justification).
OTHER
~
t Record Keeping per 10 CFR 55 are required to provide evidence that the applicant has successfully j
completed the facility licensee's requirements i
to be licensed as an operator.
this includes successful manipulation of the controls of tleir facility. As a minimum,5 significant control manipulations which affect j
reactivity or power level.
l 10 l
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_OTHER
~
Record Keeping (Cont'd)
{
this informatipn should be retained and available for inspection from time of license aap ication to license expiration.
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11 l
t OTHER l
i Requal Control Manipulations 1
if have arogram based on SAT process, list in 10 CFR 55.59(cX3) does not need to be strictly followed.
should have something similar based on plant l
JTA and specific plant priorities.
some manipulations are individual operator oriented, most would be team oriented.
12
d OTHER Requal Control Manipulations (Cont'd) credit for accomplishment shou d only be given for active participation in the mani3ulation.
NOTE: control manipulations are not synonymous with reactivity manipulations.
f t
I 13
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1 i
Examination Communications i
1 l
Examination Development 4
l l
Coordination l
By i
i Ronald F. Aiello
Facility Suggested improvements
- 1. The exam cevelopment team and leac examiner shoulc meet at the beginning o' the develoament 3rocess to estaalis, common grouncs "or t7e ceveloament anc execution of the examination:
-> Changes and interpretations to the NUREG.
-> Scope of the exam cevelopment and administration arocess.
-> Lessons learnec from t7e last exam i
administerec.
4 1
4
i l
l 2.
IV ove due dates for the out ine anc the l
exam back to 90 and 60 days prior to area j
week. This wil provide more time for j
examination review by the examiner (s).
f 3.
SSNTA continue with efforts to standardize document formats for l
examination tools (JPMs and scenarios).
i 4.
Examiners maintain a list of who (31 ant) l does the exam process the best. This j
should probably be broken down to each l
aortion of the examination. Provide your j
ratings to the utilities in Region 2, so we l
can meet your expectations and improve.
l l 5.
The 3rinciaal and the utility rearesentative s1ould meet early to establish a working re ationslip anc ex3ectations. If possible l
this should inc ude sam ales o' questions, l
JPMs, etc.
l 4
6.
T1e exam should have no outstancing issues / questions tlat arise anc neec repair at the last minute. These issues s1ould all have been identified by the prea week, to a low time to ma' e changes that meet all the criteria.
t 7.
The chief examiner should explain up front all the forms in 1021 that need to be com aleted.
8.
Always check on badging prior to coming on site.
J 9.
As soon as a Chief Examiner is assigned l
to an exam, the Facility Rep and the l
Chief should verify the ability to communicate via a I channels (including e-mail). When we converted to Lotus Notes, the "acility was suddenly unable to j
send e-mai to lis C1ief Examiner. This l
became somewhat of a hindrance and s1ould be avoided if 30ssiale.
- 10. It would be helaful if the C1ief Examiner could provide his schedu e to the Facility Rep. This inc udes aroviding uacates for any changes to the Chief Examiner's schedule along t7e way. T1e facility rea needs to be aware of when the Chief Examiner is available to assist in exam areaaration activities.
i
- 11. A face-to-face meeting should be promptly scleduled in order for the Chief to communicate his exaectations to the Facility Rep. The face-to-face rec uirement could be waived if t1e Chief and t1e Facility Rep have areviously worked togetler and the Faciity Rep is confident that le/she understancs the Clief's exaectations. In any case, a
1 I'
{
conference call would be the minimum to j
satisfy tais im aortant first ste3.
l
- 12. The Chief and the Facility Rep shoulc i
work together to establish a firm schedule i
for the exam week (s). This wi ensure the j
most efficient schedule is developed (with
)
respect to crew composition and j
personnel movement) to minimize the amount of exam material required.
- 13. T1e Chief Examiner and Utiity Rep MUST remain fixed during the entire 180 day aeriod. Handing off the resaonsibility is
-bot, disruptive and destructive to communication. The expectations of t1e clief examiner must be de"ined/ communicated early.
- 14. T1e "timeline" must be enlanced to identi"y saecific times and dates "or communication / working meetings aetween
r the examiner anc the utility rep. These meetings should be " face to face" to assure expectations are uncerstood, anc being met, early on.
- 15. If an examiner and a utility rea have not worked together before, the time ine for
" deliverables" must be exaanded.
Working meetings (face to face) must be established for the examiner to review 5-10 questions,1 scenario,1 lpm,5 jpm knowledge questions,5 acmin questions, etc. to assure that the standards and expectations are clear early in the arocess and that the utility can aroduce a aroduct that meets the expectation.
- 16. 398 and 396 forms need to be availaole electronically. We too< the time to develoa an electronic version ourselves but I would prefer tlat t7e e ectronic master coaies came directly from the NRC
3 i
j so tlat we have more con"icence that l
everything is exactly the same. We would
)
al benefit from this improvement.
i
- 17. 'A face to face workinc meeting of eight (8) to twelve (12) hours, approximately two (2) weeks before the thirty (30) day submittal must be established to resolve any issues BEFORE the submittal. The j
exam materials should be reviewed, line j
by ine, at this meeting to communicate all l
changes necessary.
i j
- 18. Expectations must be established early so that the utility clearly understands the rules l
and the examiners expectations. Small samales of develoament must be'reviewec early to assure exaectations are being met.
l A face to face meeting, prior to the 30 cay i
l submittal, to resolve any/all issues must be scheduled suc1 that adec uate time I
(suggest 2 weeks) is available to reso ve 4
I 1
i l-i comments before the 30 cay limit. No one wants to see 30 questions reviewed anc l
t7e exam re ectec. Saencing ~24 hours in l
3-4 face to face meetings is a sma 1/ smart l
3 rice to aay to avoid hundreds of hours of j
re-development, the emotional stress on j
candidates when the exam must ae l
rescheduled and the impact on the plant when candidates are not licensed to meet l
plant needs.
) 19. The "new" SSNTA "ormat for JPM level of
]
detail is NOT what you have liked in the past and needs to be either accepted by j
the NRC as a standard or optimum format, or modified, or rejected. The JPMs we j
submittec to you were in the format and
]
level of detail you had "ounc acceatable in I
t1e past, and we were surarisec to "ind that t1ey needed signi"icant last-minute rework (additiona evel of cetail).
l
- 20. Mayae Chief Examiners could send some co3ies of gooc written questions, JPMs, and JPM questions up front that could help a new developer survive the exam writing process and see where you as an examiner are coming from.
k i
Facility General Comments 1.
The limited number of NRC license examiners auts the Region and the sites at a disadvantage with resaect to getting timely interchange. If t1e examiner is out i
of the office on a trip for several weeks, the time you have to arovide the licensee with feedback is very limited and results in a real struggle to ensure a quality exam.
The limited resources and interaction time increases the risk of lower quality.
2.
Region 11 examiners have been very arom at in getting back to us when we have a question even though you may be at a remote location.
3.
The cuality of t1e communications has been good. Al of t1e examiners t1at I have ta kec to 1 ave been thoroug 1, arecise and lave aerformed listening chec<s to
i 4
verify that the correct messages were sent j
and received. I wou d however, like to see more communications by e-mail where j
appropriate. That would help ensure the i
clarity of the communications even more.
)4.
With respect to the exam saecifically; there j
were a number of changes that were made j
and we had to transmit those by expensive l
overnight or next day delivery. If we could figure out a secure e-mail method it would
{
save all of us numerous heacaches as well j
as dollars.
I j
5.
During my first face-to-face meeting with i
the Chief Examiner (to review c raft exam material), I gained much-needed insight j
into his exaectations. T1is alleviated much i
stress on my 3 art and, from then on, the j
arocess went much more smoothly. The l
Chief was very he afu curinc subsecuent tele 31one conversations and our seconc i
i l-i meeting in Atlanta. He was very easy to j
work with and very understanding j
concerning my inexaerience in tais arocess. His patient guidance was the key j
-to our success in.t1is endeavor. Next time, j
with all we've learned, we'll do even better.
i j6.
The biggest problern that I encountered i
during that exam came from the written portion that was being developec by the j
contractor. Since he had written exams l
before, I assumed that the quality of
(
questions he was submitting to us were the qua ity of questions that were acceptable to i
the NRC. We reviewed his work, made technica corrections and assumec that the
]
questions would be acceated by t1e NRC.
l l had very little communication wit, the i
NRC on t1e subject of the written exam l
and a great ceal of communication on the j
suaject of the operating exam. When t1e i
submittal was fina ly made, t1e focus went l
l to the written exam anc most of the communication was mace over s3eaker phones (about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />). It became a very 3ainful process anc coulc have been svoided had I not put so much faith in the contractor's exam writing exaerience anc l
communicated more on the subject of the written exam with the chief. We had a 100% 3 ass rate on the exam, but the exam re3 ort was brutal in the area of the written exam.
7.
Know the chief examiners expectations l
from the beginning (prior to any l
develoament).
8.
Never assume you know what you're doing
- the chief is just a phone cal away.
9.
It's better to deliver material and review it in j
3erson rather than over t1e alone.
I alan l
"or four or five trias between t1e start of I
l development and arep week. It may sound like over<i I, but it works (It's also safer in the area of security).
10.' Submit material early (es aecially the written).
I like to have t1e written exam a done deal prior to the actual submittal date.
l l 11. You can never talk to the Chief Examiner too much. During the process, I talk to him more tlan I talk to my mother.
- 12. The bottom line is that frequent communication, personal contact, and
~early submittal of materials is the key to a successfu NRC exam.
- 13. ALL 3roblems/ changes must be resolved at t1e level of the examiner and the utility reo. In no case s1ould aroolems/clanges be reaorted/ escalated to senior l
management of the utility or NRC unless
both the examiner and the utility rep are at an absolute, and mutual y agreed, impasse.
- 14. We often fe t that we were working in the l
dark, writing questions on toaics you may not want (as we were waiting for comment on our skyscraaers), possibly wasting resources, but seeing no other option to meet our rec uired cast-in-stone deadlines.
- 15. It's difficult to <eep JPMs short and plausible at the same time.
yuesuun:
iv The unit is operating at 20% power with all systems in automatic. Bank 'D' control rods are at 120 steps. Control Bank 'C' rod H6 drops to the bottom of the core. No rod control urgent failure alarms occur.
Where will thermal power and RCS Tavg stabilize in response to the dropped rod without any operator action?
A.
Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg l
will be more than 5'F lower than the temperature prior to the dropped rod.
B.
Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will be within l'F of the temperature prior to the dropped rods.
C.
Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg e
will be within l'F of the temperature prior to the dropped rod.
l D.
Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod.
i l
l Answer:
C Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be within l'F of the temperature prior to the dropped rod.
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Reference Page
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l SRO Question 10 RO Question 10 i
SRO Tier / Group 1l1 RO Tier / Group 112 i
SRO Importance 3.7 ROImportance 3.2 JOCFR5545(b) 10CFR55.41 8
I ItemAddressed Item Addressed KA Number 000003 AKl.01 KA Statement Knowledge of the operational implications of the following l
concepts as they apply to Dropped Control Rod: Reason for turbine following reactor on dropped rod event SHNPP Objective AOP-LP-3.1-2 RECOGNIZE automatic actions that are associated with AOP-001, Malfunction of Rod Control and Indication Systems l
References AOP-LP-3.1 AOP-001 AOP-001 Malfunction of Rod Control and Indication l
Systems SD-104 Rod Control System i
i Question Source New Justification l
(A) Select if he does not recognize that rods will step out to restore temperature and power was restored due to the l
previous decrease in temperature.
(B) Select if he recognizes that rods will step out, but the decreased temperature adds positive reactivity to restore
)
power.
l (C) CORRECT - Power will initially decrease du'e to the dropped rod. As power decreases, temperature will decrease. As i
temperature decreases, positive reactivity is added to restore power. Bank D rods in auto will cause rods to step out. Rods stepping out will restore power and temperature to the original l
value.
i (D) Select if he recognizes that power was restored due to the L
previous decrease in temperature, but does not recognize that rods will step out to restore temperature and l
~e-ee-
INITIAL EXAMINATIONS i
QUESTIONS AND ANSWERS i
f TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 i
l RICK BALDWIN i
i i
. GEORGE HOPPER i
t l
i f
I
O Initial Written Examinations
Reference:
All written examinations are written IAW ES-401, " Preparation of Site-Specific Written Examinations for Power Reactors." Using ES-401-1, ES-401-2, ES-401-3, ES-401-4, BWR/PWR, RO/SRO EXAMINATION OUTLINES, and ES-401-6 Written Examination Quality Assurance Checkoff S' heet."
2
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l OBJECTIVES i
i e BEI l ER EXAMINATION PRODUCT i
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1 O LESS NRC/ FACILITY REWORK 4
1 t
t I
O SHARED EXPECTATIONS t
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[
1 3
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SESSION OBJECTIVE:
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To review validity concepts affecting the NRC written examination for the purpose of:
instructing licensee personnel toward construction of more VALID and CONSISTENT NRC license examinations.
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[
COVERAGE G 3 Levels of Validity G 3 Levels of Knowledge e Discrimination, Sampling 9 Psychometrics 5
f VALIDITY A valid test is one which tests what it intends i
to test.
In training examinations, testing specific skills and knowledge outlined and taught in the objectives.
In licensing examinations, testing specific skills and knowledge that SHOULD have been outlined in the objectives.
l 6
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a d
3 LEVELS OF VALIDITY O Content O Operational O Discriminant i
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CONTENT VALIDITY Addresses K/A coverage and sampling plan coverage.
I
OPERATIONAL VALIDITY '
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Addresses two aspects:
- 1. Is the test item important to be known as a part of the operator's job?
- 2. Does the test item require the candidate to perform a job RELATED mental or physical operation?
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DISCRIMINANT VALIDITY Addresses:
O The cut score is the performance level that we use for making a pass / fail decision 80 1
percent.
O The exam must be written at a level of difficulty that intends to discriminate at
{
the 80 percent level.
9 The question, its stem and distractor, interplay, by DESIGN, at least 80 percent of the candidates taking the exam should answer the item correctly.
j w
VALIDITY
SUMMARY
i
- 1. The exam must be content valid, i
l encompassing job safety significance and sampling.
- 2. The test item should be operationally oriented: a expected mental or psychomotor requirement of the job. The
{
items should be written at the l
comprehension or analysis level vice j
simple memory. Items that measure problem solving, prediction, analysis which are essential to job performance.
11
VALIDITY
SUMMARY
I
- 3. The exam must discriminate at a moderate level of difficulty, set by the cut score.
Meaning the test items as written should provide opportunity for at least 80 percent j
of the candidates taking the test should answer the item correctly.
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LEVEL OF KNOWLEDGE e Bloom's Taxonomy, NRC Reference Benchmark to classify levels of i
knowledge.
O Bloom's Taxonomy, a classification scheme that classifies items by depth of t
mental performance required to answer the items.
O Bloom's Taxonomy, can be applied to written, scenarios or JPM questions.
14 I
LEVELS LEVEL 1 Fundamental, using simple mental processes, recall or recognition of discrete bits of information.
i.e. setpoints, definitions, or specific facts.
I 15
LEVEL 2 t
Comprehension, involves understanding material through relating it to its own parts or 1
other material:
i.e. including rephrasing information in
)
different words, recognizing relationships j
, including consequences or implications.
1 t
16
f LEVEL 3 Analysis, synthesis, and application testing is more active and product-oriented testing which involves the multi-part mental process of assembling, sorting, or integrating the parts so that the whole, and the sum can be used to: predict and event or outcome, solve i
l a problem or create something new.
l i.e. using-knowledge to solve problems.
e 17 I
DETERMINANTS OF DISCRIMINATION 9 Level of examination knowledge O Level of examination difficulty 9 Passing Score 9 Item bank.use i
18
f i
NATURE OF EXAMINATIONS AND TESTS i
O TESTS are samples of PERFORMANCE O Infer overall performance based on a s
sample e Sample must be broad-based to make confident inference 9 Sample must NOT be fully predictable or inferences cannot be made on
)
untested areas.
9 Items MUST discriminate otherwise it i
has little or NO value.
19 t
t PSYCHOMETRICS Items may have one or more of the following i
psychometric errors:
- 1. Low level of knowledge (fundamental) b
- 2. Low operational validity (not job related)
- 3. Low discriminatory validity ( hard or easy)
- 4. Implausible distractors l
- 5. Confusing language or ambiguous
)
questions
- 6. Confusing or inappropriate negatives
- 7. Collection of true/ false statements t
- 8. Backwards logic 20
006 Emergency Core. Cooling System J JPM 136 Recovery From Safetylnjection
.and Solid Water Conditions.
Question 2:
Given the following plant conditions:
Unit 2 was operating at 100% power.
The plant experienced a large break LOCA with a failure of the ECCS system.
FR-C.1, " Response to Inadequate Core Cooling," is being implemented.
Core exit TCs are 720*F and increasing.
At this point FR-C.1 directs the crew to depressurize intact steam generators.
a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?
b.) Why is this action taken?
References Allowed? YES X
NO Answer:
a'.') To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.
Reference:
KA: 006G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs.
OPL271C398 pg 12-15 Applicant Response:
SAT _._UNSAT__
I 1
l l
INADEQUATE CORE COOLING STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Blocking low steamline pressure Si as soon as pressurizer pressure is NOTE less than 1920 psig will prevent an inadvenent MSIV closure and keep the condenser available for steam dump.
After the low steamline pressure Sl signal is blocked, main steamline isolation will occur rf the high steam pressure rate is exceeded.
S/G depressurization at the maximum rate may cause S/G narrow range levels to drop to less than 10% [25% ADV). This is acceptable and expected for this inadequate core cooling condition.
~ 14 DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:
- a. WHEN RCS pressure less than 1920 psig, THEN PERFORM the following:
~
- 1) BLOCK low steamline pressure St.
y
- 2) CHECK STEAMLINE PRESS ISOUSl BLOCK RATE ISOL
(
ENABLE permissive LIT.
{M-4A, A4]
- b. DUMP steam to concanser
- b. DUMP steam at maximum rate at maximum rate.
USING Imatt S/G atmospheric relief (s).
IF local control of atmospheric relief (s) is necessary, THEN DISPATCH personnel to dumo steam USING EA-1-2, Local Comrol of
~
S/G PORVs.
(Step cominued en next oage.)
esD Pace 13 of 19
t 026, Containment Spray System /.JPM.# 57AP Respond to High Contamment Pressure 4PJace RHR Spmyin Service 9-Question 2:
Given the following plant conditions:
Unit I has tripped from 100% power due to a LOCA.
Containment pressure is 3.0 psid Transfer of Containment Spray pump suction to the containment sump is being performed in accordance with ES-1.3, Transfer to RHR Containment Sump.
a.) Why must both CS pumps be placed in PULL-TO Lock while transfening suction to the containment sump?
b.) What does placing both CS pumps in PULL-TO-Lock prevent?
References Allowed? YES X
NO Answer:
a.) While shifting to the containment sump, both the RWST and the containment sump suction valves to the CS pumps will be closed at the same time, b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of water.
Reference:
K/A: 026G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs OPL271CO24 pg 14-1S CCD NO:1-47W611-72-1 ES-1.3,pages Il-13. OPL271C388 pg 9 Applicant Response:
SAT UNSAT l
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J
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A'.1: Shift Staffing
~.
Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming i
outage.
He had his last physical examination 18 months ago and has had
~
satisfactory performance in the licensed operator requalification training program.
He is informed that he is needed to join a shift crew in 3 days to fill in for a vacationing Unit OATC.
Can the RO fillin for the vacationing RO? Why or why not?
f 3
References Allowed? YES_2LNO
' Answer:
No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of "under direction" on-shift time.
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 i
K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT i
i
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l s
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License Applicant Administrative Walkthrough Examination--NRC-1 j
Examiner Sheet A'.1: Shift Staffing Question 1: A licensed RO has been off shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of a shift RO.
What additional requirements must be met by the RO before he may fill in for the vacationing RO?
References Allowed? YES1NO Answer:
The RO must complete an additional 24 (40 - 16) hours of"under direction" on-shift time that must include a plant tour and shift turnover.
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT 7
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Given the following conditions:
\\
1.
The reactor has experienced a Steam Generator Tube Rupture.
2.
All systems responded as expected.
2.
The performance of E0P-04 is in progress.
~
3.
One Steam Generator has been isolated.
4.
All RCPs have been stopped.
5.
RCS cooldown using natural circulation is in progress.
Which One of the following describes the concern associated with the isolated j
l
. 3G pressure prior to placing the RCS on SDC?
a.
The isolated SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS inventory.
l l
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l b.
The strategy during the performance of E0P-04 is to maintain the affected SG pressure slightly less that RCS pressure to prevent secondary water entering the RCS.
c.
Since the RCS cooldown rate was maintained greater than 30deg/hr, the t
affected loop has not been cooled sufficiently to allow SG depressurization.
l t
d.
The affected SG pressure is high due to thermal stratification of the l
secondary water.
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- 3 1
Reactor Operator Examination
- 65. Given the following conditions:
The reactor has experienced a Steam Generator Tube Rupture.
' All systems responded as expected.
The performance of EOP-04 is in progress.
- One steam generator has been isolated.
_ RCS cooldown using natural circulation is in progress.
Which ONE ofthe following describes the concern associated with the affected SG pressure prior to placing the RCS on SDC7 a.
The SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS inventory.
b.
The SG pressure would be slightly less than RCS pressure causing water to enter the RCS resulting in a dilution.
The SG temperature would be too high to allow for SG depressurization.
c.
d.
The SG pressure would be too high due to thermal stratification of the secondary water.
4 l
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i I
l Which one of the following describes the response of the Unit I charging pumps i
following receipt of an automatic SIAS signal. coincident with a Loss of Offsite Power?
a.
One charging pump is automatically started on each emergency bus 5 minutes after it is energized by the diesel, b.
All charging pumps are automatically started immediately after their respective bus is energized.
c.
The operator must manually start one charging pump on each emergency bus 5 minutes after it is energized by the diesel.
d.
One charging pump is automatically started onto each emergency bus immediately after it is energized by the diesel.
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- 19. Which ONE of the following describes the response of the Unit-1 charging pumps following receipt of an automatic SIAS signal, coincident with a Loss of Offsite Power? Assume normal electrical lineup and all equipment is operable.
a.
Only one charging pump is automatically started on each emergency bus 5 minutes after it is energized by the diesel.
b.
All charging pumps are automatically started immediately after their respective bus is energized by the diesel.
c.
All charging pumps are automatically started 5 minutes after their respective buses are energized by the diesel.
d.
Only one charging pump is automatically started onto each emergency bus immediately after it is energized by the diesel.
s s
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Charging pumps are running on Unit 1 an SIAS is present.
(Assume no operator action)
Which one of the following lists the charging pump response when the BAM tanks are emptied?
The charging pumps will:
a.
trip on low oil pressure.
b.
trip on low suction pressure.
c.
automatically align to the RWT.
d.
continue to run and become gas bound.
l
. - - _.. - - -. ~.
.. -.. -... - -. -. - ~. ~ -..
~.....
Reactor Operator ExaTJnation 27.' Charging pumps are running on Unit I and an SIAS is present. (Assume no operator action)
. Which ONE of the following lists the charging pump response when the BAM tanks are emptied?
l l
The charging pumps will:
a.
trip on thermal overload.
' b.
trip on low suction pressure.
c.
automatically align to the RWT.
d.
continue to run and become gas bound.
I 1
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--. =.-
Given the following conditions:
Unit 1 CEDM fan HVE-21A is in AUTO after START Unit 1 CEDM fan HVE-21B is in AUTO after STOP.
Unit 1 CEDM fan HVE-21A trips on overcurrent.
Which ONE of the following completely lists the logic that will start HVE-21B?
a.
The trip signal from HVE-21A.
b.
The trip signal.from HVE-21A concurrent with a low flow signal.
c.
A low flow signal.
d.
The trip signal from HVE-21A concurrent with a low flow signal and air inlet temperature to the cooling coils is greater than 100 deg F.
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Reactor Operator Examination
- 59. Given the following conditions:
Unit 1 CEDM fan HVE-21 A is in AUTO after START.
Unit 1 CEDM fan HVE-21B is in AUTO after STOP.
Unit 1 CEDM fan HVE-21 A trips on overcurrent.
Which ONE of the following lists the signals required by the logie needed to start HVE-21B?
a.
The trip signal from HVE-21 A.
4 b.
The trip signal from HVE-21 A concurrent with a low Dow signal.
c.
A low flow signal.
d.
The trip signal from HVE-21 A concurrent with a low flow signal and air inlet temperature signal to the cooling coils is greater than 100
- F.
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13.
Given the following plant conditions:
Unit 1 was at 73% power A reactor trip / safety injection on low steam line pressure 0: Curred 21 minutes ago Average Core Exit TC temperature is 375'F RCS pressure is 225 psig All S/G pressures are DECREASING slowly
- 2 and #3 S/G levels are 5% NR and DECREASING slowly
- 1 S/G levelis 6% NR, and INCREASING slowly
- 4 S/G ievelis STEADY at 2% NR Total feedwater flow is 340 gpm PZR levelis 37% and INCREASING RCS T-cold temperature is 325'F and DECREASING slowly Containment pressure is 5 psid and INCREASING slowly At this po nt, which ONE of the following Critical Safety Functions is the MOST degraded?
a.
Heat Sink b.
Core Cooling c.
Containtnent d.
Pressurized Thermal Shock Answer-A K/A:
000040K101
[4.1/4.4)
Reference:
E-0, Foldout Page Objective:
OPL271C395, B.1 1
Level:
Analysis Source:
000040K101 001 History:
Stem and distracters a and d modified (7/7/9S)
Note:
Provide PTS curve with this question.
Justification:
a.
Correct answer because all S/G levels are Jess tnan 10% NR and total feeowater fiow is less than 440 gpm.
b.
Incorrect because RCS temperature is 325'F (core exit T/Cs less than 1200*F).
l
- . Incorrect because containment pressure is less than 12.0 psid.
d.
Incorrect because RCS temxrature is 325'F (T-cold is greater inan 250*F)
d I
l 13.
Given tne following p! ant conditions:
Unit 1 was at 73% power
=
A reactor trip / safety injection on low steam line pressure occurred 21 minutes ago Average Core Exit TC temperature is 3p#F RCS pressure is.225'psig i%SD
=
All S/G pressures are DECREASING slowly c2 and 3 S/G levels are 5% NR and DECREASING slowly
- 1 S/G levelis 6% NR, and INCREASING slowly
- 4 S/G levelis STEADY at 2% NR Totalfeedwatepflow is 340 gpm PZR levelis)T% and INCREASING RCS T-cold temperature is 325'F and DECREASING slowly Containment pressure is 5 psid and INCREASING slowly At tnis poin), which ONE of the following Critical Safety Functions is the MOST degraded?
a.
Heat Sink b.
Core Cooling
. Containment d.
Pressurized Thermal Shock Answer:
A K/A:
000G40K101
[4.1/4.4)
Reference:
E-0 Foldoet Page Objective:
OPL271C3$5, B.1 Level:
Analysis 9
Source:
000040K101 001 History:
Stem and distracters a and d modified (7/7/93)
Note:
Provide PTS curve with this question.
Justification:
a.
Correct answer because al! SIG ieve!s are Jess inan 1D% NR and total feeowater fiow is less than t-40 gpm.
b.
in:orrect because RCS temperature is 325'? (core exit T/Cs less inan 1200'F).
l
- . Incorred De:ause containment pressure is less tnan 12.0 psic.
d.
Incorre: ce:ause RCS temoerature is 325'? (T-5c:d is greater inan 25D'?).
/
,m i
, LL,,
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20.
Given the following plant conditions:
The control room has been evacuated due to a fire All controis have been transferred per AOP-C.04 MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators The TDAFW pump has been shut down Steam generator pressures and levels are decreasing Which ONE of the following describes the response of the auxiliary feedwater system?
The TDAFW pump will automatically restart when 2/4 steam generators reach low low a.
level.
b.
The MDAFW pump level control valves will automatically control steam generato.r levels at 33%.
~
c.
The MDAFW pumo level control valves will have to be manually adjusted using the Manual Output Adjust in the L-381 cabinet.
d.
The discharge pressure for the MDAFW pumps will have to be manually adjusted by throttling the manual valves at the LCVs.
Answer:
B K/A:
000058A102
{4.3 / 4.5)
Reference:
AOP-C.04, page 11 Objective:
OPL271 C423, B.4 Level:
Comprehension Source:
00005SA102 001 History:
Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distracters a, b, c, and d reordered (7/22/98). Distracter be restructured (7/29/98)
Note:
Selected from@ exam bank with minor modification of text
_L,
/ -
i i
/
20.
Given the following plant condmons:
The control room has been evacuated due to a fire i
All controls have been transferred per AOP-C.04 MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators The TDAFW pump has been shut down 4
Steam generator pressures and levels are decreasing
, s s& dr' % A U ch0 2M h4*-C.01 4
Which ONE of the following describes the resern:; -:iac. a..,y ic;d. vater-system?
- a. The TDAFW pump will automatically restart whan 2/4 steam cenerators reach low low 4Loif N u.siaag, [-3?/,
level. e ~ h k -aw (Cow j
b.
The MDAFW pump level control valves will automatically control steam generator ~
l
, levels at 33%.
The MDAFW pump level centrol valves will have to be manually adjusted using the Manual Output Adjust in the L-381 cabinet.
/Yg [
d.
The discharge pressure for the MDARN pumps will have to be manually adjusted by y
tnrottl:ng the manual valves at the LCVs.
yoc yj[j Answer:
B K/A:
0000SBA102
[4.3 / 4.5]
Reference:
AOP-C.04, page 11 Objective:
OPL271C423. BA Level:
Comprehension Source:
00005BA102 001 H: story:
Used on 9/97 RO NRC eram Text modified to correct grammar errors. Distror.ers a, b, C, and d reordered (7122/98). Distra ter be restructured (7/29/9S)
Note.
Selected fromMexam bank with minor modification of tert
~
l
23.
Given the following plant conditions:
FR-C.1, " inadequate Core Cooling", has been entered due to a RED path on Core Cooling Core exit temperatures (TCs) are 1250*F and increasing
^,
NO Feedwater / Aux Feedwater is available At step 12, the CRO checks the S/G NR levels and reports all are <10%.
As the SRO you should: (Select ONE of the following) a.
Go to FR-H.1, " Loss of Secondary Heat Sink".
b.
Depressurize allintact S/Gs to atmospheric pressure to dump accumulators, c.
Start RCPs one at a time, until core exit TCs are less than 1200'F.
r 4
d.
Prepare to initiate RCS Feed and Bleed if WR level in any 2 S/Gs is less than 60%.
Answer:
C K/A:
000074K307
.[4.0/4.4]
Reference:
FR-C.1, pages 10 & 17 Objective:
OPl271C398 Level:
Comprehension Source:
MExam Bank 101.
000074K307 001 History:
Used on HLC 9807 practice exam Distracters b and c reordered Note:
Selected frorMexam bank without modification of text
l g
INADEQUATE CORE COOLING FR-C.1 A.
7q Rev. 8
\\
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Use of a Fautted or Ruptured S/G during performance of the following steps may compound the emergency situation. When NO intact S/Gs are avaliable, a Fautted or Ruptured S/G may be used.
~
- 12. M AINTAIN Intact S/G narrow range leveis:
- a. Greater than 10% [25% ADV)
- a. MAINTAIN total feed flow greaterinan 440 gpm UNTil level greater than 10% [25% ADV) i in at least one S/G.
IF total feed flow greater than 440 gpm can NOT be established, THEN PERFORM theiollowing:
- 1) CONTINUE attempts to establish heat sink in at least one S/G.
- 2) GO TO Note pnor to Step 21.
- b. Between 10% [25% ADV) and 50%.
l i4 Page 10 of 19 l
?
FR-C.1 g
INADEQUATE CORE COOLING l.
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
j NOTE RCP darnage due to absence or loss of normal support conditions is an acceptable consequence in this procedure.
\\
- 21. CHECK if RCPs should be started:
l
- a., CHECK core exit T/Cs
- a. GO TO Step 22.
1 l
greater than 1200*F.
l
- b. CHECK if idle RCS toop available:
- b. PERFORM the following:
- 1) S/G narrow range level a) OPEN pressurizer PORVs and block greater than 10% {25% ADV) valves.
- 2) RCP in associated loop b) IF core exit T/Cs remain AVAILABLE AND STOPPED.
greater than 1200*F.
l THEN OPEN reactor vessel head vents:
FSV-68-394 l
f FSV-68-395 i
FSV-68-396
)
l FSV-68-397.
1
=
l c) GO TO Step 22.
- c. START RCP in one idle loop.
d.
GO TO Substep 21.a.
Page 17 ci 19
e 23.
Given the following plant conddions:
FR C.1, inade:;uate Core Cooling", has been entered due to a RED pain on Core Cooling Core exit temperatures (TCs) are 1250*F and increasing NO Feedwater / Aux Feedwater is available At step 12, the CRO checks the S/G NR levels and reports a!! are <10%
As the SRO you should: (Select ONE of the following) a.
Go to FR-H.1,
- Loss of Secondary Heat Sink.
b.
Depressunze allintact S/Gs to atmospheric pressure to dump a::umulators.
c.
Start RCPs one at a time, urtil core exit TCs are less than 1200'F.
M Port \\ls ac @ o d W.w5 d.
P_repare to-insete-RCC Ier.) end C:: d4-WR4eveHrrany-2-S/Gs4s4ess-than-sch Answer:
C.
K/A:
000074K307
[4.0/4.4]
Reference:
FR-C.1, pages 10 & 17 Objective:
OPL271C398 Level:
Comprehension Source:
000074K307 001 History:
Used on HLC 9807 practice exam Distracters b and c reordered Note:
Selected fromMexam bank without modification of text
.p.h p?//f!VW 7
i
49.
Given the following plant conditions:
Reactor power is at 20% during a unit shutdown Intermediate Range N-36 failed high Operators placed the level trip bypass swr:ch for N-35 to the bypass position i
Which ONE of the following describes the effect of this failure and action during the remainder of the shutdown?
a.
The reactor will automatically trip when the Power Range channels decrease below the P-10 setpoint.
b.
Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range chan:iel, so the unit must be manually tripped prior to Mode 2 entry.
- c..Both Source Range channels, N-31 and N-32, must be manually energized when the open.ble intermediate Range channel (N-35) decreases below the P-6 setpoint.
d.
Souce Range channel N-32 must be manually energized when the operable intermediate Range channel (N-35) decreases below the P-6 setpoint; Source Range channel N.31 will automatically energize.
Answer C
K/A:
015000K407
[3.7/3.8)
Reference:
AOP-1.01, page 10 ES-0.1, page 13 Objective:
OPL271 C352, B.4 Level:
Comprehension Source:
015000K407 001 History:
Not used on 9/97 or 5/98 NRC exams. Not used on practice exam i
Distracters e and d reordered Note:
Selected fromg exam t ank without moc'ification of text l
?
l l,, -
Js y E g / S/ # N 2- _/A WWW l
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3r i /.
49.
Given the following plant cendrtions:
l Reactor power is at 20% during a unit shutdown
\\.
intermediate Range N-351 ailed high
\\
f--Opera crs pia:ec-me wP-eypass-switerrfor+#36 to7heTypass pesitis d
Which ONE of the fo!!owing desenbes the effect of this failure and action during the remainder of the shutdown?
- a. The reactor will automatically 1np when the Power Range channels decrease below the F-10 setpoint.
b.
Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range channel, so the unit must be manually tripped prior to Mode 2 ent:y,
- c..Both Sour:e Range channels, N-31 and N-32, must be manually energized when the operadie intermediate Range channel (N-35) decreases below the P-6 setpoint.
d.
Source Range channel N-32 must be manually energized wnen tne operable Intermed4 ate Range channel (N-35) decreases below the P-6 setpoint; Source Range i
channel N-31 will automatically energize.
Answer C
K/A.
015000K407
[3.7/3.B]
Reference:
AOP-1.01, page 10 ES-0.1, page 13 Objective:
OPL271C352, B 4 Leve!:
Comprenension Source:
015000K407 001 History:
Not used on 9/97 or 5/98 NRC exams. Not used on practice exam.
Distracters c and d reorcered Note:
Scie:ted fromhexam bank without modification of text
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s 35.
Given the following plant conditions:
Unit 2 is operating at 29% power in accordance with 0-GO-6, Power Recuction From 30% Reactor Power to Hot Standby Unit 2 will be going to Cold Shutdown for maintenance Intermediate Range N-36 has just failed high Which ONE of the following actions must be performed before reducing reactor power below 5
10%7 a.
Manually energize N-31 and N-32, b.
Place N-36 Level Trip switch in BYPASS.
c.
Remove N-36 instrument power fuses.
d.
Manually trip the reactor to prevent an automatic reactor trip.
Answer:
B K/A:
000033K302
[3.6/3.9]
Reference:
AOP-l.01, page 10 & 13 i
l Objective:
OPL271C352, B.4 1
i Level:
Analysis l
Source:
New question (Developed 7/15/98)
Justification:
l l
Incorrect because manually restonng N-31 and N-32 to operation in the power range would a.
destroy the source rarige detectors.
b.
Correct because placing the level trip switch in BYPASS prevents high reactor tnp when j
the low power reactortnp signalis reinstated at the P-10 setpoint (10% power).
(
c.
incorrect because action does not bypass the trip signal.
d.
Incorrect because a manual reactortrip for the given conditions is not required. Placing N.
36 levelinp swnch in BYPASS allows an orderly reactor shutdown.
2 1
l I
O M
1 l
I l
50.
Given the following piant condnions:
l Large Break LOCA is in progress i
RCS pressure is 550 psig l
Exosensor indicates 25'F superheat No RCPs are operating Which ONE of the following indications would the operator use along wrth RCS pressure to accurately substantiate core cooling?
a.
Reactor Coolant Tavg value.
b.
Average value of all core exit thermocouples.
c.
Hottest Reactor Coolant wide range Thot value.
a d.
Average value of five hottest core exit thermocouples.
Answer:
D K/A 017000A402
[3.8 / 4.1)
Reference:
FR-0, page 3 OPL271C044, page 7, A.1.c Objective:
OPL271 C044, B.1.b Level:
Memory Source:
- 017000A402 001 History:
Used on HLC 9809 practice exam Distracters a, b, c, and d reordered (7/22/98)
Note:
Selected from xam bank without modification of text l
l 1
s 50, Given tne following plant conditions:
Large Break LOCA is in progress RCS pressure is 550 psig Exosensor indicates 25'F superheat No RCPs are operating Which DNE of the following indications would the operator use along with RCS pressure to accurately substantiate core cooling?-
,. p n-
,p
... p-
,_.-a
- r,-.
- n-r
/
T -Readci CodenM:c!E- % /i,W )q,,) et 'W&
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b.
Average value of all core ext:thermocouples.
c Hottest Reactor Coolant wide range That value.
d.
Average value of five hottest core exit thermocouples.
Answer:
D f
/
M#
N5 "AI #7 ^
K/A 017000A402
[3.8 / 4.1)
~~ M 1
Reference:
FR-0, page 3 OPL271C044, page 7, A.1.c Objective:
O?L271 CD44, B.1.b Level:
Memory Source:
017000A402 001 History:
Used on HLC 9809 practice exam Distracters a, b, c, and d reordered (7/22/98)
Note:
Selected from exam bank without modification of text l
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4 88.
Given the following plant conditions:
Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a power increase to 100% in progress Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm Current time is 0100 Which ONE of the following actions must be taken?
a.
Immediately stop the power increase.
b.
Continue the power increase while restoring loop 1 accumulator boron concentration to 2400 to 2700 ppm boron within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, c.
If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, be in HOT:
4TANDBY by 0700.
d.
If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, reduce pressurizer pressure to 1000 psig or less by 1300.
Answer:
A i
K/A:
2.1.1
[3.7/3.S]
i
Reference:
SSP.12.1, Page 31 i
Objective:
OPL271C209, B.2 l
Level:
Comprehension Source:
New question (Developed 7/20/98)
Note:
Provide copy of Technical Specification 3.5.1.1 with the question (exam)
, Justification:
Correct becausegConduct of Operation (SSP-12.1) restnets power increase a.
when in an LCO action of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or less. RCS loop 1 accumuiator boron concentration of 2390 ppm boron places Unit 1 in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO.
b.
incorrect because power increase is not allowed wnen in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO action statement.
c.
Incorrect because if loop 1 boron concentration is not restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the Unit 1 must be in HOT standby by 0800.
d.
Incorrect because if loop 1 boron concentration not restored witnin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, pressurizer pressure must be reduced to 1000 psig or less by 1400.
3 /4. 5 EMERGENCY COPE COOLING SYSTEMS 3 /4. 5.1 ACCUMULATORS
[plD LEG INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:
The isolation,2i,e open, a.
A contained borated water volume of between 7615 and 8094 gallons of a131 b.
borated water,
~
Between 2400 and 2700 ppm of boron, c.
A nitrogen cover-pressure of batween 600 and 683 psig, and d.
RIS4 Power removed from isolation valve when RCS pressure is above e.
2000 psig.
APPLICABILITY: MODES 1, 2 and 3.*
ACTION:
With one cold leg injection accumulator inoperable, except as a result of boron concentration not within limits, restore the a.
inoperable accumulator to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure,to 1000 psig or less within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With one cold leg injection accumulator inoperable due to the boron b.
concentration not within limits, restore boron concentration to within!).imits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to 2000 psig or less within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- Pressurizer pressure above 2000 psig.
l December 27, 1994
- UNIT 2 3/4 5-1 A endment No. 113, 131, 133, 141, ISA
y Q
ff..Y W If//b I
88.
Given ine following plant condi:icns:
Unit 2 operating in a :ordance wnh 0-GO 5, Normal Power Operation at 73% with a power increase to 100% in progress Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm g
Current time is 0100 l,g A 4-/
- Which ONE of the following actions must be taken?
a.
Immediately stop the power increase.
b.
Continue the power increase while restoring tooy.1 accumulator boren concentration to 2400 to 2700 ppm boron,@.',1 hwr. hNw 72 4 og Cf.
If loco 1 accumulator boron ces entration is NOT restored wnhin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, be in HQT c.
STANDSY by 0700.
d.
If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, reduce pressunzer pressure to 1000 psig or less by 1300.
Answer A
K/A:
2.1.1
[3.7/3.8)
Reference:
SSP-12.1, Page 31 Objective:
OPL271 C209, B.2 Level:
Comprehension Source:
New question (Developed 7/20/98)
Note:
Provide copy of Te:hnical Specification 3.5.1.1 wr:n tne question (exam)
Justification:
a.
Correct becaus
- onduct of Operation (SSP-12.1) restri
- :s power increase when in an LCO acuan ci o nours or less. RCS loop 1 a::umulator coron con:entraton of 2390 ppm boron places Un!! 1 in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO.
b.
Incorrect beesuse power increase is not allowed wnen in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO action statement.
c.
incorrect because if loop 1 boron concentration is not restored witnin i hour, tne Unit 1 must be tn HOT standoy by 0800.
d.
incorre:: because if loop 1 boron concentraton not restored witnin 1 nour, pressurizer pressure must de reduced to 1000 osig or less by 1400.
l s
ll f.,> y st ir 71
/
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I
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a.u w w.
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,..s
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/
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s
006 Emergency Core Cooling System-/ JPM 136 -Recovery From Safetylnjection
.and Slid Water Co'nditions '. J. 2 b Question 2:
Given the following plant conditions:
)
Unit 2 was operating at 100% power.
The plant experienced a large break LOCA with a failure of the ECCS system.
1 FR-C.1, " Response to Inadequate Core Cooling," is being implemented.
Core exit TCs are 720'F and increasing.
At this point FR-C.1 directs the crew to depressurize intact steam generators.
a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?
b.) Why is this action taken?
References Allowed? YES X
NO Answer:
a.)To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.
i
Reference:
KA: 006G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs.
OPL271C398 pg 12-15 Applicant Response:
SAT UNSAT__
s'
tw FR-C.1 INADEQUATE CORE COOLING
~
Rev. 8 l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
Blocking low steamline pressure Si as soon as pressurizer pressure is NOTE
~-
less than 1920 psig will prevent an inadvertent MSIV closure and keep the condenser available for steam dump.
After the low steamline pressure Si signal is blocked, main steamline isolation will occur if the high steam pressure rate is exceeded.
S/G depressurization at the maximum rate may cause S/G narrow range levels to
~
drop to less than 10% [25% ADV). This is acceptable and expected for this
!nadequate core cooling condition.
14 DEPRESSURtZE Intact S/Gs to reduce RCS pressure to less than 125 psig:
- a. WHEN RCS pressure less than 1920 psig, THEN PERFORM the following:
- 1) BLOCK low steamline pressure SI.
- 2) CHECK STEAMLINE PRESS ISOUSl BLOCK RATE ISOL ENABLE permissive LIT.
{M-4 A, A4]
- b. DUMP steam to condenser
- b. DUMP steam at maximum rate
- -~
at maximum rate.
USING intact S/G atmospheric relief (s).
IF local control of atmosphenc relief (s) is necessary, THEN DISPATCH personnet to dumo steam USING E A-1-2, Local Control of S/G PORVs.
i (Steo continued on next page )
Page 13 of 19 l
l t
.O
.026, Containment Spray System /,JP.M.# 37AP Respond to High Contamment i
. Pressure,e:PJace'RHR Sp' ray.~in Service % ~.
r l
Question 2:
J Given the following plant conditions:
Unit I has tripped from 100% power due to a LOCA.
l Containment pressure is 3.0 psid l
Transfer of Containment Spray pump suction to the containment sump is being performed in accordance with ES-1.3, Transfer to RHR Containment Sump.
l a.) Why must both CS pumps be placed in PULL-TO: Lock while transferring suction to the l
containment sump?
b.) What does placing both CS pumps in PULL-TO-Lock prevent?
References Allowed? YES X
NO Answer:
l a.) While shifting to the containment sump, both the RWST and the containment sump suction valves to the CS pumps will be closed at the same time.
b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of water.
i
Reference:
K/A: 026G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs OPL271C024 pg 14-18, CCD NO:1-47W611-72-1, ES-1.3, pages I l-13, OPL271C388 pg 9 Applicant Response:
SAT UNSAT l
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A'.1:iShift StafEng Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming outage.
He had his last physical examination 18 months ago and has had satisfactory performance in the licensed operator requalification training program.
He is informed that he is needed to join a shift crew in 3 days to fill in for a vacationing Unit OATC.
I j
Can the RO fill in for the vacationing RO? Why or why not?
References Allowed? YES _X_ NO l
1 I
Answer:
No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of l
"under direction" on-shift time.
1
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62
[
K/A 2.1.4 (2.3/3.4)
I Applicant Response:
SAT UNSAT l
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Y l
I b
i 4
i l
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A.~1f? Shift Staffing Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift creiv in 2 weeks to fill in for a vacationing p
i shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of
~
a shift RO..
What additional requirements must be met by the RO before he may fill in for the vacationing RO?
3 References Allowed? YES _2L NO j
Answer:
The RO must complete an additional 24 (40 - 16) hours of"under direction" on-i shift time that must include a plant tour and shift turnover.
l
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4) l Applicant Response:
SAT UNSAT I
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