ML20206R878
| ML20206R878 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/23/1998 |
| From: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Herrell M CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 9901200438 | |
| Download: ML20206R878 (102) | |
Text
5 o
December 23, 1998
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Carolina Power and Light Company ATTN: Mr. Max E. Herrell Training Manager Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429
SUBJECT:
MEETING
SUMMARY
- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - BRUNSWICK STEAM ELECTRIC PLANT
Dear Mr. Herrell:
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 ll participated in the meeting. was the agenda used for the Training Managers' Conference, and Enclosure 2 is the list of attendees. We appreciate the participation of you and yoJr staff and believe that the 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 Regulation (NRR), made a presentation as noted in the slides in Enclosure 3.
Additionally, I am enclosing our preliminary schedule for FY 1999 and FY2000 as Enclosure 4.
Please review the schedule and supply comments to my staff or myself.
If you have any questions regarding the content of this letter, please contact me at (404) 562-4638.
Sincerely, Original signed by Thomas A. Peebles Thomas A. Peebles, Chief
.,0008G' per t r Li ensing nd Human Performance Branch Division of Reactor Safety Docket Nos.: 50-325 and 50-324 License Nos.: DPR-71 and DPR-62
Enclosures:
As noted
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cc w/encis:
J. S. Keenan, Vice President,
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f Brunswick Steam Electric Plant 9901200438 901223 ADOCK0500g4 PDR V
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PUBLIC
'B. Michael. DRS i
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BMICHAEL:
T E LES 12/ h /98 12// /98 Doc Name:
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Revised November 3,1998 l-i I
TRAINING AND OPERATIONS MANAGERS' CONFERENCE L
U.S. Nuclear Regulatory Commission, Re'gion II Atlanta, Georgia i.
1 Meeting Agenda 1
November 5,1998 Richard B. Russell Building Auditorium
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,' Thursday.11/5/98 8:00 a.m.
Conference Registration 8:20 a.m.
Introduction Thomas A. Peebles, Chief, l
Operator Licensing & Human l
Performance Branch j
8:30 a.m.'
Opening Remarks William Travers, Executive Director of Operations 1
t
~ 8:50 a.m.
Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director i
Division of Reactor Safety l
1 9:15 a.m.
break l
9:45 a.m.
Other Issues Robert M. Gallo, Chief Operator Licensing Branch, NRR l
l 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 Exammation Questions and Answers Rick Baldwis / G rge Hopper 2:30 p.m.
JPM Examples of questions Rick Baldwin / George Hopper 3:3_0 p.m.
. Open Session - Other issues Training Managers 1
4 00 p.m.
Meet with Principle examiners All 4:30 p.m.
Adjorn i
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ATTENDEES AT THE NRC REGION 11 TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 l
Sid Crouch ATTSi David Lane Sonalysts, Inc.
Bill Fitzpatrick INPO i
CP&L Rick Gamer 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 Tmg 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 1
Duke Power Gabriel Washbum OC Req Team Leader -
j Ronnie B. White, Jr MG Tmg Mgr W. H. " Soap" Miller CT Site Tmg Mgr Paul Stovall OC Mgr Oper Tmg Bentley Jones OC Tmg Mgr James Teofilak CT Ops Tmg Mgr Alan Orton MG Ops Tmg Mgr Richard Bugert Corp. Ops Tmg Spec EE&L Maria Lacal TP Tmg Mgr Dennis L. Fadden SL Services Mgr Jo Magennis Corp Tmg Assessment Spec
. Tom Botander SL Exam Development Steve McGarry TP Maint Tmg Supv Southem Nuclear (SNC)
John C, Lewis HT Tmg & EP Mgr Bill Oldfield FA Nuc Ops Trn Supv Steve Grantham HT Ops Tmg Supv
Jcel Deavers FA Sr Plt Inst Bob Brown VG Tmg Mgr Dan Scukanec VG Ops Trng Supv
. - = _. - -. -. -..-.
1 l
Virainia Power.
' Steve Crawford
'NA Sr Inst Nuc Harold McCallum L
.SR Supv Ops Tmg 1
l TVA..
i Dick Driscoll ~
SQ Tmg Mgr Walt Hunt SQ Ops Tmg Mgr.
Denny Campbell BF-SRO Ops Inst j
-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 l
NRC Particioants Tom Peebles R ll Operator Lic. Br. Ch.
Rick Baldwin R ll Sr. Examiner George Hopper R 11 Sr. Examiner Ron Aiello -
R 11 Sr. Examiner Charlie Payne
' R ll Sr. Examiner i
William Travers NRC Executive Dir. Ops.
R. M. Gallo ~
. Bruce Mallett -
R ll.
Div. Dir. Reactor Safety i
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..-7..____.__.____,____._..
FY 99 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 '
RO SRO-l SRO-U TOTAL I
Date Plant Chief Pass Pass Pass Pass l
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 I
1/25/99 McGuire &
DCP 6
3 2
11 1
1 2/8/99 2/8/99 C. River &
GTH 6
6 12 2/22/99 2/8/99 B. Ferry MEE 4
1 5
l 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 i
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 j
i 1
08/30/99 Turkey Pt &
RFA 20 20 9/13/99 l
136 RESULTS TO DATE 4
4 5
5 9
9 18 18 100 100 100 100 l
No initial exams scheduled for:
Brunswick, North Anna and Vogtle j
FY 00 region 11 write part of Summer & Hatch i
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. -...-._..-... ~
....--.-_~
~ -... -.-...- -
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FY 00 INITIAL EXAM SCHEDULE AND RESULTS 1
December 14,1998 -
RO SRO-l SRO-U TOTAL D:te Plant Chief Pass Pass Pass Pass 0
9/27/99 Summer GTH E
6 region ll weite 10/18/99 Hatch DCP 10 2
12 i
region II write 12/13/99 Vogtle RSB 3
5 2
10
]
2/14/00 Brunswick &
.DCP 12 3
15 2/28/00 03/"/00 Oconee ?
10 J
704/10/00 Harris (maybe twoo) 10 705/03/00 St. Lucie GTH 6
5 11 l
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 II write?
708/"/00 Sequoyah 4
2 2
8 709/04/00 Surry?
10 709/11/00 North Anna 12 l
0 0
42 0
46 0
27 0
149 l
1 1
f?' d2signates tentative No initial exams scheduled for:
Catawba Robinson l
[:
Turkey Point Watts Bar 1
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Operator Licensing lSSueS Region ll Training Managers' Conference l
November 5,1998 Robert M.
Gallo, Chief Operator-Licensing and Human Performance Branch
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i OPERATOR LICENSING i
ISSUES l
Part 55 Rulemakings j
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Status Schedule i
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Final Revision 8 of NUREG-1021 o
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Examination Quality and Results o
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Generic Fundamentals Exam o
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Requal Inspections (IP-710.01?
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l Recent information Notices 0
l Exam Integrity (IN 98-15?
j Sampling Plans (IN 98-28?
i Eligibility (IN 98-37?
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t RECENT LESSONS LEARNED by Charlie Payne
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Southeastern Training Manager's Conference
^ November 5,1998 i
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POLICY 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.
I Less stressful on candidates.
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PO_LICY CLARIFICATIONS O
In general, license class sizes of greater than
_8_ candidates will be scheduled for 2 weeks as follows-I i
1S' exam week i
off-week for documentation of week 1 j
i performance 2"d exam week j
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O PClLICY CLARIFICATIONS 1
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Examination submittals - 2 copies of draft and final exams (written, JPMs, and simulator
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scenarios). Elsctronic copy is also desired.
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Written exams submittals will be reviewed by j
following a sampling process. When criteria are met, review will be stopped and licensee called.
Criteria - 10 unacceptable questions out of 30 i
1 ques": ions sampled j
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RE_ CENT LESSONS LEARNED SRO-only Questions i
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 ABILITIES l
2.1 Conduct of Operations l
2.1.1 Knowledge of conduct of operations requirements.
(CFR: 41.10 / 45.13)
IMPORTANCE RO 3.7 SRO 3.8 2.1.2 Knowledge of operator responsibilities during all modes of plar.c operation.
(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 RO 3.0 SRO 3.4 2.1.4 Knowledge of shift staffing requirements.
M (CFR: 41.10 / 43.2)
IMPORTANCE RO 2.3 SRO 3.4 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)
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2-1
!~JREG-112 3, Rev. 2
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f 2.1 Conduct of Operations (continued) l l
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)
IMPORTANCE RO 4.3 SRO 4.2 2.1.21 Ability to obtain and verify controlled procedure copy.
l (CFR: 45.10 / 45.13)
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 mechan. cal drawings.
(CFR: 45.12 / 45.13)
IMPORTANCE RO 2.8 SRO 3.1 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.S 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)
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2-3 IrJREG-112 3, Rev. 2
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3
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2.4 Emergency Procedures / Plan (Continued)
' 2.4.32 Knowledge of operator response to loss of all annunciators.
(CFR: 41.10 / 43.5 / 45.13)
IMPORTANCE RO 3.3 SRO 3.5 2.4.33 Knowledge of the process used track inoperable alarms.
(CFR: 41.10 / 43.5 / 45.13)
2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including sydem geography and system implications.
(CFR: 43.5 / 45.13)
.IMPORTANCE R O 3.8 SRO 3.6 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.
4
- (CFR: 43.5 / 45.13)
IMPORTANCE RO 3.3 SRO 3.5 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.
(CFR: 43.5)
IMPORTANCE R O 2.0 SRO 2.8 2.4.37 Knowledge of the lines of authority during an emergency.
e (CFR: 45.13)
2.4.38 Ability to take actions called for in the' facility emergency plan / including (if required) supporting or actirg as emergency coordinator.
(CFR: 43.5 / 45.11)
IMPORTANCE RO 2.2 SRO 4.0 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.
(CFR: 45.11)
IMPORTANCE RO 3.3 SRO 3.1 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.
(CFR: 45.11)
.IMPORTANCE R O 2.3 SRO 4.0 la 2.4.41 Knowledge of the emergency action lesel thresholds and classifications.
r (CFR: 43.5 / 45.11)
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i NUREG-1123, Rev. 2 2-14 l
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REC _ENT LEB_SDNS LEARNED i
i SRO-only Questions (Cont'd)
.. SRO-only questions will be based on following categories: A.2, G2.1, G2.2, G2.3, and G2.4.
differences between SRO and RO outlines shifts only 11 K/As from Tier 2 to Tiers 1 & 3.
)
=> Other 14 flexible.
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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 M6 -M %
1%
R$b iMi @%.
??4 f@A?
1*
1 20 Emergency &
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ggll g gjg Abnormal 2
17 Plant Tier g
g gp m.c gg Evolutions g) %ggjggg pgg qq 43
+7 Totals ny h
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- ier air s
1 23 2.
2 Plant 13 l
Systems 3
4 Tier 40 g
Totals 3.
Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17
+ 'f Attempt to distribute topics among all K/A categories; select Note:
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 l
or three K/A topics from a given system unless they relate to l
plant-specific priorities.
j Systems / evolutions within each group are identified on the l
associated outline.
l The shaded areas are not applicable to the category / tier.
i NUREG-1021 10 of 39 Interim Rev. 8, January 1997
I l
l ES-401 BWR R0 Examination Outline Form ES-401-2 l
l 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 l
1.
1 gl h h h h 13 Emergency &
w ram 6 pp l
Abnormal "8i 'Z h E
E'A 19 P1 ant 3
ipsh M @
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m a
w.
es Evolutions m
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m Tier M
Sug; 4M. tg/;
36 Totals N
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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.
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.
i NUREG-1021 16 of 39 Interim Rev. 8, January 1997
RECENT LEB_ SONS LEARNED Sampling Criteria intent of prodess 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 alan.
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i REC _ENT LES_ SONS LEARNED 1
Sampling Criteria (Cont'd) 9 each topic in each tier & group should be l
sampled at least once unless insufficient l
questions exist to do this. If all topics have been sampled once and other questions need to be selected, the process should be l
systematic and unbiased.
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final sample plan should have a fairly even
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balance across all Ks & As.
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REslENT LES_ SONS LEARNED Sampling Criteria (Cont'd) up to 25 questions from last two NRC exams, facility licensee exams, tests & quizzes (except final audit test) may be usec.
Chief Examiner (CE) has the option to uni aterally shift or change the selected K/As.
up to 5 site-saecific priorities may be identified i
with CE concurrence (K/A value may be < 2.5 with sufficient justification).
9
l OTHER 1
Record Keeping per 10 CFR 55 are required to provide evidence that the applicant has successfully l
completed the facility licensee's requirements to be licensed as an operator.
l this includes successful manipulation of the controls of their facility. As a minimum,5 sic nificant control manipulations which affect reactivity or power level.
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OTHER
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l Record Keeping (Cont'c) this informatipn should be retained and i
available for inspection from time of license 1
aaplication to license expiration.
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OTHER Requal Control Manipulations if lave program 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 JTA and specific plant priorities.
some manipulations are individual operator oriented, most would be team oriented.
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-l OTHER i
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Requal Control Manipulations (Cont'd) i r
credit for accomplishment should only be i
given for active participation in the i
manipulation.
f NOTE: control manipulations are not synonymous with reactivity manipulations.
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i Examination Communications
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l Examination Development i
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Coordination i
I By Ronald F. Aiello
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i Facility Suggested Improvements l
- 1. The exam development team and lead examiner should meet at the beginninc of l-the develoament process to estaalish I
common grounds for the development and execution of the examination:
Changes and interaretations to the NUREG.
Scope of the exam development and administration arocess.
Lessons learned from the last exam ac ministered.
se
-m.
.s.a l
l ll2.
Move due cates for t1e out ine and t1e j
exam back to 90 and 60 days prior to arep j
week. This will provide more time for i
examination review by t1e examiner (s).
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i 3.
SSNTA continue with efforts to l
standardize document formats for j
examination tools (JPMs and scenarios).
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t 4.
Examiners maintain a list of who (plant) does the exam arocess the best. This should arobably be broken down to each portion of the examination. Provide your ratings to the utilities in Region 2, so we can meet your expectations and im arove.
5.
The principal and the utility representative should meet early to establish a working relationshia and exaectations. If possible j
this shou d inc ude sam a es of c uestions, JPMs, etc.
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l 6.
The exam s1ould have no outstanding l
issues / questions that arise and need j
repair at the last minute. These issues j
should a I have been identified by the arep j
week, to allow time to make changes that l
meet al the criteria.
i 7.
The chief examiner should explain up l
front all the forms in 1021 that need to be j
completed.
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8.
Always check on badging prior to coming on site.
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9.
As soon as a Chief Examiner is assigned to an exam, the Facility Rep and the i
Chief should verify the aaility to communicate via all channels (including e-mail). When we converted to Lotus Notes, the faciity was suddenly unab e to send e-mail to his C1ief Examiner. This
became somewhat of a hindrance anc should be avoiced if oossiale.
- 10. It would be helpfulif the Chief Examiner could arovide his scledule to the Facility Rep. This includes aroviding uadates for any changes to the Chief Examiner's schedule along the way. The facility rep nee'ds to be aware of when the Chief Examiner is available to assist in exam preaaration activities.
- 11. A face-to-face meeting should be aromptly scheduled in order for the Chief to communicate his expectations to the Facility Rep. The face-to-face requirement cou d be waived if the Chief and the Facility Rep have previously worked togetler and the Facility Rea is confident that he/sle uncerstancs the Clief's exaectations. In any case, a
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conference call would be the minimum to l
satisfy this important first ste 3.
- 12. The Chief and the Facility Rep shou d l
wor < together to establish a firm schedule
]
for the exam week (s). This will ensure the j
most efficient schedule is developed (with l
respect to crew com aosition and personnel movement) to minimize the j
amount of exam material required.
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- 13. The Chief Examiner anc Utility Rep MUST
{
remain fixed durinc the entire 180 day period. Handing off the responsibility is both disru ative and destructive to communication. The expectations of the I
chief examiner must be defined / communicated early.
l
- 14. The " time ine" must be enhanced to l
identify saecific times and dates for i
communication / wor <ing meetings between i
k l
the examiner and the utility re3. These j
meetings shou d ae " face to face" to l
assure expectations are understood, and being met, early on.
l
- 15. If an examiner and a utility rea have not worked together before, the timeline for
" deliverables" must be expanded.
i Working meetings (face to face) must be established for the examiner to review 5-10 cuestions,1 scenario,1 jam,5 jpm knowledge questions,5 admin questions, etc. to assure that the standards and expectations are clear early in t1e process and that the utility can produce a aroduct that meets the expectation.
- 16. 398 and 396 forms need to be availaale electronically. We too< t1e time to develoa an e ectronic version ourselves aut I wou d prefer that the electronic master coaies came directly from the NRC
1 4
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l so : hat we have more conficence that everything is exactly t1e same. We wou d j
all benefit from this im arovement.
j
- 17. =A face to face wor <ing meeting of eight (8) l to twe ve (12) 1ours, approximately two l
(2) weeks before the thirty (30) day l
submittal must be establishecl to resolve any issues BEFORE the submittal. The exam materials should be reviewed, line j
by line, at this meeting to communicate all i
changes necessary.
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- 18. Exaectations must be established early so that the utility clearly understands the rules and the examiners expectations. Small samales of development must be' reviewed early to assure exaectations are being met.
A " ace to face meeting, prior to the 30 day submittal, to resolve any/all issues must ae scleduled suc1 tlat adec uate time (suggest 2 weeks) is availaale to reso ve
- O comments before the 30 day limit. No one wants to see 30 questions reviewed anc the exam rejected. S3ending ~24 hours in 3-4 face to face meetings is a small/ smart price to aay to avoid hundreds of hours of re-deve cament, the emotional stress on candidates when the exam must be rescheduled anc the impact on the plant when candidates are not licensed to meet plant needs.
- 19. The "new" SSNTA format for JPM level of detail is NOT what you have liked in the i
past and needs to be either acceated by the h RC as a standard or optimum format, or modified, or rejectec. The JPMs we submitted to you were in the format and eve of detail you hac found acceatable in the 3ast, and we were surarised to finc that t1ey neeced significant last-minute rework j
(additiona evel of detai).
j l
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- 20. Maybe Chief Examiners could send some coaies of good written questions, JPMs, l
and JPM questions up front that could help a new developer survive t1e exam writing process and see where you as an l
examiner are coming from.
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i Facility General Comments 1.
The limited number of NRC license examiners puts the Region and the sites at a disadvantage with respect to getting timely interchange. If t1e examiner is out of the office on a trip for several weeks, the time you have to provide the licensee with feedback is very limited and results in a real struggle to ensure a c uality exam.
The limited resources and interaction time increases the risk of lower quality.
2.
Region ll examiners have been very prompt in getting back to us when we have a question even t1ough you may ae at a remote location.
3.
The cuality of t1e communications has been gooc. A I of the examiners that I have ta ked to have 3een t1orough, precise and have performed listening checks to
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verify that the correct messages were sent l
anc received. I woulc however, li<e to see j
more communications by e-mail where j
appropriate. That would help ensure the l
c arity of the communications even more.
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4.
With respect to the exam specifically; there were a number of changes that were made and we had to transmit those by exaensive overnight or next day delivery. If we could j
figure out a secure e-mail method it would save all of us numerous headaches as well as collars.
5.
During my first face-to-face meeting with l
the Chief Examiner (to review draft exam j
material), I gained much-needed insight l
into his expectations. This alleviated much stress on my aart and, from then on, the process went much more smoothly. The j
Chief was very 1elaful during subsecuent te e3 hone conversations and our seconc l
meeting in Atlanta. He was very easy to work with and very understanding concerning my inexaerience in t1is orocess. His patient guidance was the key
-to our success in this endeavor. Nex: time, with all we've learned, we'll do even better.
6.
The biggest problem that I encountered during that exam came from the written portion that was being developed by the contractor. Since he had written exams before, I assumed that the quality of c uestions he was submitting to us were the quality of questions that were acceptaale to the NRC. We reviewec his work, made technical corrections and assumec that the questions would be acceated by t1e NRC.
I had very little communication with the NRC on the suaject of the written exam anc a great deal of communication on the subject of the oaeratinc exam. When the submittal was finally made, the focus went
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i to t1e written exam anc most o" the l
communication was made over saea<er 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 painful process and could have been avoided had I not aut so much faith in t1e l
contractor's exam writinc exaerience and j
communicated more on the subject of the written exam with the chief. We had a 100% pass rate on the exam, but the exam l
report was brutal in the area of the written i
exam.
t l
l 7.
Know the chief examiners expectations from the beginning (prior to any develoament).
j 8.
Never assume you know what you're doing l
- t1e clief is just a pione call away.
4 j
9.
It's aetter to de iver material and review it in 3erson ratler tlan over t1e alone. I alan l
for four or five trias between t1e start of 1
l-i i
development and arep week. It may l
sound like over<i I, out it works (It's a so j
safer in the area of security).
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- 10. ~ Submit material early (esaecia y the i
written).
I li<e to have the written exam a done dea arior to the actual submittal date.
- 11. You can never talk to the Chief Examiner too much. During the arocess, I talk to him more than 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 successful NRC exam.
- 13. ALL 3roblems/ changes must be resolved at the eve of t1e examiner and the utility re 3. In no case s1ould aroolems/clanges ae reported /esca ated to senior management of the utiity or NRC unless
l both the examiner and the utility rea are at an aaso ute, and mutua ly agreed, im aasse.
)
- 14. We often felt that we were wor <ing in t1e dark, writing questions on toaics you may not want (as we were waiting for comment on our skyscrapers), possibly wasting resources, but seeing no other option to meet our required cast-in-stone deaclines.
- 15. It's difficult to keep JPMs short and alausible at the same time.
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%-4
quesuun:-
w 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 j
control urgent failure alarms occur.
L Where will thermal power and RCS Tavg stabilize in response to the dropped rod without l
any operator action?
A.'
Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod.
i l.
B.
Reactor thennal power will be lower than prior to the dropped rod; RCS Tavg will be within l'F of the temperature prior to the dropped rod.
I
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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.
D.
Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg l
will be more than 5'F lower than the temperature prior to the dropped rod.
Answer:
l C
Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg l-will be within 1"F of the temperature prior to the dropped rod.
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.. _ _ =. - -.. - -
Reference Page SRO Question
'10 RO Question 10 i
SRO Tier / Group lIl RO Tier / Group 112 SRO Importance 3.7 ROImportance 3.2 1
'OCFR55.43(b) 10CFR55.41 8
\\
Item Addressed item Addressed KA Number 000003AKl.01 l
KA Statement Knowledge of the operational implications of the following 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 References AOP-LP-3.1 AOP-001 AOP-001 Malfunction of Rod Control and Indication Systems l
SD-104 Rod Control System l
Question Source New Justification i
l (A) Select if he does not recognize that rods will step out to restore temperature and power was restored due to the 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 temperature decreases, positive reactivity is added to restore l
power. Bank D rods in auto will cause rods to step out. Rods i
stepping out will restore power and temperature to the original value.
(D) Select if he recognizes that power was restored due to the previous decrease in temperature, but does not recognize that i
rods will step out to restore temperature and l
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.i INITIAL EXAMINATIONS QUESTIONS AND ANSWERS
~
TRAINING IV ANAGERS CONFERENCE NOVEMBER 5,1998 i
RICK BALDWIN 1
i
. GEORGE HOPPER i
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Initial Written Examinations i
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 j
EXAMINATION OUTLINES, and ES-401-6 I
Written Examination Quality Assurance Checkoff Sheet."
t 2
-OBJECTIVES e BEi iER EXAMINATION PRODUCT O LESS NRC/ FACILITY REWORK 9 SHARED EXPECTATIONS i
I
SESSION OBJECTIVE:
To review validity concepts affecting the NRC i
written examination for the purpose of:
Instructing licensee personnel toward i
construction of more VALID and CONSISTENT NRC license examinations.
4
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COVERAGE O 3 Levels of Validity l
O 3 Levels of Knowledge I
t G Discrimination, Sampling i
[
O Psychometrics j
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VALIDITY 1
A valid test is one which tests what it intends 1
to test.
In training examinations, testing specific skills and knowledge outlined and taught in the objectives.
1 In licensing examinations, testing specific skills and knowledge that SHOULD have been outlined in the objectives.
L 6
2
9 9
t 3 LEVELS OF VALIDITY f
O Content e Operational J
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G D.iscriminant 3
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CONTENT VALIDITY
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=
h Addresses K/A coverage and sampling plan coverage.
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l OPERATIONAL VALIDITY '
l Addresses two aspects:
1
- 1. Is the test item important to be known as a part of the operator's job?
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- 2. Does the test item require the candidate to perform a job RELATED mental or physical operation?
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i DISCRIMINANT VALIDITY Addresses:
9 The cut score is the performance level that we use for making a pass / fail decision 80 percent.
l O The exam must be written at a level of difficulty that intends to discriminate at the 80 percent level.
O The question, its stem and distractor, interplay, by DESIGN, at least 80 percent of the candidates taking the exam should answer the item correctly.
l 10
VALIDITY
SUMMARY
- 1. The exam must be content valid, encompassing job safety significance and i
sampling.
- 2. The test item should be operationally
)
oriented: a expected mental or i
psychomotor requirement of the job. The items should be written at the
^
comprehension or analysis level vice simple memory. Items that measure problem solving, prediction, analysis j
which are essential to job performance.
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i VALIDITY
SUMMARY
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- 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 of the candidates taking the test should answer the item correctly.
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3 LEVELS OF KNOWLEDGE Bloom's Taxonomy i
e Analysis, Application, Synthesis l
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e Comprehension O Fundamental (simple memory) l I
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LEVEL OF KNOWLEDGE O Bloom's Taxonomy, NRC Reference Benchmark to classify levels of knowledge.
O Bloom's Taxonomy, a classification scheme that classifies items by depth of mental performance required to answer
)
the items.
j G Bloom's Taxonomy, can be applied to written, scenarios or JPM questions.
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LEVELS LEVEL 1 Fundamental, using simple mental processes, recall or recognition of discrete bits of information.
i.e. setpoints, definitions, or specific facts.
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i LEVEL 2 t-Comprehension, involves understanding material through relating it to its own parts or other material:
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1 i.e. including rephrasing information in different words, recognizing relationships j
, including consequences or implications.
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i LEVEL 3 Analysis, synthesis, and application testing is more active and product-oriented testing i
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 a problem or create something new.
)
i.e. using-knowledge to solve problems.
17
DETERMINANTS OF DISCRIMINATION r
l s
e Level of examination knowledge j
O Level of examination difficulty O Passing Score 1
}
O ltem bank.use t
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NATURE OF EXAMINATIONS AND TESTS i
e TESTS are samples of PERFORMANCE 1
O Infer overall performance based on a sample O Sample must be broad-based to make' confident inference j
9 Sample must NOT be fully predictable or inferences cannot be made on untested areas.
i e items MUST discriminate otherwise it j
i has little or NO value.
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PSYCHOMETRICS i
Items may have one or more of the following psychometric errors:
- 1. Low level of knowledge (fundamental)
- 2. Low operational validity (not job related)
- 3. Low discriminatory validity ( hard or easy)
- 4. Implausible distractors i
- 5. Confusing language or ambiguous j
questions
- 6. Confusing or inappropriate negatives j
- 7. Collection of true/ false statements
- 8. Backwards logic i
20
6 006 Emergency Core. Cooling System-/ JPM 136 Recovery From Safetylnjection
.and Sdlid Water Conditions'.'
l 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?
j References Allowed? YES X
NO l
Answer:
l a'.') To reduce RCS pressure below 125 psig l
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.
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OPL271C398 pg 12-15 Applicant Response:
SAT __UNSAT l
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INADEOUATE CORE COOLING Rev. 8 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 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 tne high steam pressure rate is exceeded.
c' 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.
- 2) CHECK STEAMLINE PRESS ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT.
{M-4A, 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 atmospheric relief (s) is necessary, THEN DISPATCH personnel to dump steam l
USING EA-1-2, Local Control of i ~
S/G PORVs.
(Steo cominued en nex: page.)
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Page 13 of 19
026 Conraintnent Spray System /.JPM # 57AP Respond to High Contamment Pressure,sPjace RHR Spmyin Service?
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 transferring suction to the containment sump?
b.) What does placing both CS pumps in PULL-TO-Lock prevent?
Refereaces 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 14-18, CCD NO:1-47W611-72-1. ES-1.3, pages I l-13. OPL271C388 pg 9 l
Applicant Response:
SAT UNSAT m
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
~
outage.
He had his last physical examination 18 months ago and has had satisfactory perfonnance 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.
l Can the RO fill in for the vacationing RO? Why or why not?
References Allowed? YES.2._ NO Answer:
No. The RO mu:t 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 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT l
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-ere e
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet -
. 4 A.1: c Shift Staffing ~
1 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 l
shin 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 sMR RO.
What additional requirements must be met by the RO before he may fill in for the vacationing RO?
3 References Allowed? YES1NO i
1 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) i Applicant Response:
SAT UNSAT i
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I 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
_SG 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.
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 affected loop has not been cooled sufficiently to allow SG depressurization.
d.
The affected SG pressure is high due to thermal stratification of the secondary water.
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4 Reactor Operator Examina. ton l
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- 65. Given the following conditions:
The reactor has experienced a Steam Generator Tube Ruprure.
l All systems responded as expected.
The performance ofEOP-04 is in progress.
One steam generator has been isolated.
j l-RCS cooldown using natural circulation is in progress.
Which ONE of the following describes the concem 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.
c.
The SG tetnperature would be too high to allow for SG depressurization.
l d.
The SG pressure would be too high due to thermal stratification of the secondary water.
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=
' Which one_ of the following-describes the respdnse of the Unit 1 charging pumps 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.
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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 bythe 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 afterit is energized by the diesel.
?
to
Charging pumps are running on Unit 1 an SIAS is present.
(Assume no operator l
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.
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1 Reactor Operator Examination 27.' Charging pumps are running on Unit I and an SIAS is present.-- (Assume no operator action)
Which ONE ofthe following lists the charging pump response when the BAM tanks are emptied?
t The charging pumps will:
a.
- trip on thermal overload.
b.
trip on low suction pressure.
c.
automatically align to the RWT.
j d.
continue to run and become gas bound.
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4 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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-. -. ~. _.. -. ~ -.. --. -. _- -.-...
l Reactor Operator Examination
- C
- 59. Given the following conditions:
Unit 1 CEDM fan HVE-21 A is in AUTO after START.
f Unit 1 CEDM fan HVE-21B is in AUTO after STOP.
l Unit I CEDM fan HVE-21 A trips on overcurrent.
j 1
Which ONE of the following lists the signals required by the logie needed to start HVE-21B?
The trip signal from HVE-21 A.
a.
b.
The trip signal from HVE-21 A concurrent with a low flow signal.
c.
A low flow signal.
d.
The trip sigdal 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:
l Unit 1 was at 73% power A reactor trip / safety injection on low steam line pressure occurred 21 minutes ago I
Average Core Exit TC temperature is 375'F 3
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 levelis STEADY at 2% NR Total feedwater flowis 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.
Containment d.
Pressurized Thermal Shock Answer:
A K/A-000040K101
[4.1/4.4]
Reference:
E-0, Foldout Page Objective:
OPL271C395 B.1 4
Level:
Analysis Source:
000040K101 001 History:
Stem and distracters a and d modified (7/7/98)
Note:
Provide PTS curve with this question.
Justification:
a.
Correct answer because all S/G levels areJess tnan 10% NR and total feeowater fiow is less than 440 gpm.
b.
Incorrect because RCS temperature is 325'F (core ext: T/Cs less than 1200*F).
c.
Incorrect because containment pressure is less than 12.0 psid.
d.
Incorrect because RCS temperature is 325'F (T-cold is greater than 250*F) a
1 l
l 13.
Given the following p! ant conditions:
Unit 1 was at 73% power A reactor trip / safety injection on low steam line presr ure occurred 21 minutes ago Average Core Exit TC temperature is.3 SF 1
RCS pressure is,225'psig ilSD A!! S/G pressures are DECREASING slowly
- 2 and *3 S/G ievels are 5% NR and DECREASING slowly
- 1 S/G levelis 6% NR, and INCREASING slowly
- 4 S/G levelis STEADY at 2% NR Total feedwatepflow is 340 gpm
=
PZR levelis' 7 o and INCREASING
)
RCS T-cold ternperature is 325'F and DECREASING slowly j
Containment pressure is 5 psid and INCREASING slowly At this point, which ONE of the following Critical Safety Functions is the MOST degraded?
a.
Heat Sink b.
Core Cooling C.
Containment d.
Pressu-ized Thermal Shock Answer:
A K/A:
000040K101
[4.1/4.4J
Reference:
E-0, Foldout Page Objective:
OPL271C33h B.1 Level:
Analysis s
Source:
000040K101 001 History:
Stem and distracters a and d modified (7/7/98)
Note:
Provide PTS curve with this question.
Justdi ation:
i a.
Correct answer because all S/G levels are Jess than 10% NR and total fe-dwater fiow is less than t-40 gpm.
b.
Incorrect because RCS temperature is 325'? ( ore exit T/Cs less than 1200'F).
c.
Incorrect because con:ainment pressure is less inan 12.0 psid.
d.
Incorrect oe:ause RCS temperature is 225'? (T-Eoid is crea:er inan 250'F)
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20.
Given the following plant conditions:
f 1
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 decressing Which ONE of the following describes the response of the auxiliary feedwater system?
a.
The TDAFW pump will automatically restart when 2/4 steam generators reach low low level.
b.
The MDAFW pump level control valves will automatically control steam generator levels at 33%.
~
c.
The MDAFW pump 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 manua! valves at the LCVs.
i Answer:
B K/A:
00006BA102
[4.3 / 4.5]
l l
Reference:
AOP-C.04, page 11 l
Objective:
OPL271C423, B.4 Level:
Comprehension Source:
000058A102 001 l
History:
Used on 9/97 RO NRC exam l
Text modified to correct grammar errors. Distracters a, b, c, and d reordered (7/22/98). Distracter be restructured (7/25/98)
Note:
Selected from% exam bank with minor modification of text W
M 20.
Given the following piant condr:: ens:
The control room has been evacuated due to a fire All controls have been transferred per AOP-C.04 fADAFW pumps 1 A-A and 18-B are injectrng into the steam generators The TDAFW pump has been shut down Steam generator pressures and levels are decreasing
.a ss + w A k wfsD w Ae -c.o1 o
Which ONE of the following describes th: :::cen:; v. ;h=.d.. y iscd*ater-system?
The TDAFW pump will automatically restart whan 2/4 steam generators reach low low a.
4.o Nck v.swg(gL-3?/,
level. e ~ h k ~+
Cow b.
The fADAFW pump level control valves will automatically control steam generator
~
, levels at 33%.
c.
The fADAFW pump level control valves will have to be manually adjusted using the fAanual Output Adjust in the L-381 cabinet.
fW Y g [ y d.
The discharge pressure for the fADAFW pumps will have to be manually adjusted by y
thro
- ling the manual valves at the LCVs.
2/ac hg[/.
Answer-B K/A:
000058A102 (4.3 /4.5]
Reference:
AOP-C.04, page 11 Objective:
OPL271 C423. B.4 Level:
Comprehension Source:
00005BA102 001 Hrstory:
Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distra: ers a. b, c. and d reordered (7/22/98). Distracter be restructured (7/29/93)
Note:
Selected fromMexam bank with minor modification of text
.__________m
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 allir. tact S/Gs to atmospheric pressure to dump accumulators.
c.
Start RCPs one at a time, until core exit TCs are less than 1200*F.
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
g INADEQUATE CORE COOLING FR-C.1 7q Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Use of a Faufted or Ruptured S/G during performance of the following steps may compound the emergency situation. When NO intact S/Gs are available, a Fautted or Ruptured S/G may be used.
- 12. MAINTAIN Intact S/G narrow range leveis:
- a. Greater than 10% {25% ADV]
- a. MAINTAIN totalfeed flow greater than 440 gpm UNTIL level greater than 10% [25% ADV]
in at least one S/G.
IF total feed flow greater than 440 gpm can NOT be established, i
THEN PERFORM theiollowing:
- 1) CONTINUE attempts to establish heat sink in at least one S/G.
- 2) GO TO Note prior to Step 21.
- b. Between 10% {25% ADV) and 50%.
4 Page 10 of 19
= -. _ _.
F C.1 g
INADEQUATE CORE COOLING STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCP damage due to absence or loss of normal support conditions is an acceptable consequence in this procedure.
~
- 21. CHECKif RCPs should be started:
5
- a., CHECK core exit T/Cs
- a. GO TO Step 22.
greater than 1200*F.
- 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 tnan 1200*F, THEN OPEN reactor vessel head vents:
FSV-68-394 FSV-68-395 FSV-68-396 FSV-68-397.
c) GO TO Step 22.
- c. START RCP in one idle loop.
- d. GO TO Substep 21.a.
Pace 17 of 19
0 23, Given tne following plant conditions:
FR-C.1, *lnade:;uate 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)
Go to FR-H.1," Loss of Secondary Heat Sink".
a.
b.
Depressurize allintact S/Gs to atmospheric pressure to dump a Cumulators.
c.
Start RCPs one at a time, until core exit TCs are less than 1200*F.
M i: ort % me %o d \\/MS d.
Psepathete-RCO rewJ on : Oke#-WR4e veHrreny-2-S/G s-is4ess-tharr60%
Answer:
C.
K/A:
000074K307
[4.0/4.4]
Refere,,:.e:
FR-C.1, pages 10 & 17 Objective:
OPL271C398 Level:
Comprehension Source:
000074K307 001 History:
Used on HLC 9807 practice exam Distra:ters b and c reordered Note:
Selected from Mexam bank without modification of text jp/4/OMd
~
~
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l
1 l
i 49.
Given the fo!!owing plant conditions:
Reactor power is at 20% during a unit shutdown Intermediate Range N-36 failed high Operators placed the level trip bypass switch for N-36 to the bypass position 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 channel, 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 operable intermediate Range channel (N 35) decreases below the P-6 setpoint.
d.
Source 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 l.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.
Distracters e and d reordered Note:
Selected fromg exam bank without modification of text ed 1
x 7/Y4 p k a t &l & 2- /A SWW
/
ws v
I i I I b[
l l 49.
Given the fotfowing plant conditions:
Reactor power is at 20% during a unit shutdown Intermediate Range N-35 failed high f_ Operator:, p6 W ine :02 cmp-eypasswerrfor+tGfno7he Dypass positis Which ONE of tne following describes the effect of this failure and action during the remainder of the shutdown?
- a. The reactor will automaticallytrip 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 i
channel, 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 et,ergized when the operable interrnediate Range channel (N-35) decreases below the P-6 setpoint.
d.
Source Range channel N-32 must be manually energized when the operable intermediate Range channel (N-35) decreases below the P-5 setpoint; Source Range channel N-31 will automatically energize.
Answer.
C l
K/A:
015000K407
[3.7/3.8)
Reference:
AOP-LO1, 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.
Distracters c and d reorcered
\\
i Note:
Selected fromMezam bank without modification of text
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35.
Given the following plant conditions:
Unit 2 is operating at 29% power in accordance with 0-GO-6, Power Reduction 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 10%'?
a.
Manually energize N 31 and N-32,
- b. - Place N-36 LevelTrip 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-1.01, page 10 & 13 Objective:
OPL271C352, B.4 Level:
Analysis Source:
New question (Developed 7/15/98)
Justification:
Incorrect because manually restoring N-31 and N-32 to operation in the power range would a.
destroy the source range detectors.
b.
Correct because placing the level trip switch in BYPASS prevents high reactor trip when the low power reactor trip signal is reinstated at the F-10 setpoint (10% power).
c.
Incorrect because action does not bypass the trip signal.
d.
Incorrect because a manual reactor trip for the given condnions is not required. Placing N-36 level trip switch in BYPASS allows an orderiy reactor shutdown.
1 9
wr r
o s
50.
Given the following piant conditions:
Large Break LOCA is in progress RCS pressure is 550 psig Exose;Mor indicates 25'F superheat No :CPc are operating r
Which ONE of the following indications would the operator use along with 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.B / 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) x Note:
Selected from ram bank without modification of text 3
1 1
~
j 1
50.
Given the following plant conditions:
Large Break LOCA is in progress RCS pressure is 550 psig Exosensor indicates 25': superheat No RCPs are operating Which ONE of the following indications would the operator use along with RCS pressure to accurately substantiate core cooling?,
)
Y doiYooient-isY< ::!N7 Lkfh i,
~
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M t 72. /.btr~rarc rs i
b.
Average value of all core extt thermocouples.
1 l
c.
Hottest Reactor Coolant wide range Thot value.
d.
Average value of five hottest core exit thermocouples.
j i
Answer.
D
&'Y y& y ogne 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 j
Distracters a, b, c, and d reordered (7/22'98)
Note:
Selected from exam bank without modification of text i
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4 88.
Given the following plant conditions:
l Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a powerincrease to 100% in progress i
Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm Current time is 0100 l
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:
l GTANDBY 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 1
K/A:
2.1.1
[3.7/3.8)
Reference:
SSP-12.1, Page 31 Objective:
OPL271C209, B.2 Level:
Comprehension Source:
New question (Developed 7/20/98)
Note:
Provide copy of Technical Specification 3.5.1.1 with the question (exam) 1 Justification:
Correct becausegConduct of Operation (SSP-12.1) restricts 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 accumulator boron concentration of 2393 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 when 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 ii loop 1 boron concentration not restored within 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.
I I
l l
i I
3 /4. 5 EMERGENCY CORE COOLING SYSTEMS 3 /4. 5.1 ACCUMULATORS COLD LEG TNJECTION ACCUMULATORJ l
LIMITING CONDTTION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:
The isolation valve open, a.
A contained borated water volume of between 7615 and 8094 gallons of - R131 b.
borated water, r
Between 2400 and 2700 ppm of boron, I
c.
i A nitrogen cover-pressure of batween 600 and 683 psig, and d.
R184 Power removed from isolation valve when P.C5 pressure is above e.
2000 psig.
APPLICABILITY: MODES 3, 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 JPERABLE 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 withinil.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 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 />.
- Pressurizer pressure above 1000 psig.
l l
I Dece=ber 27, 1994 3/4 5-1 Amendment fio. 113, 131, 133 g - UNIT 2
[-
. jh
'Y -
h/
BB.
Gi' en tne following plant conditions:
Unit 2 operating in accordance with 0-GO 5, Normal Power Operation at 73% with a l
powerincrease to 100% in progress Chemistry reports Unit 2 RCS toop 1 accumulator boron concentration is 2390 ppm
/,j Current time is 0100 4 73 o
Which ONE of the following actions must be taken?
'mmediately stop the power increase.
i l
a.
b.
Continue the power increase while restoring looy.1 accumulator boron concentration i
to 2400 to 2700 ppm boron,;thh 1 hn hMW 72 4 ou C$.
If loop 1 accumulator boron concentration is NO"i 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 c.
- STANDBY by 0700, i
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 J K/A:-
2.1.1
{3.7/3.B]
Reference:
SSP-12.1, Page 31 Objective:
OPL2710209, B.2 i
i Level:
Compr: aension l
l-Source:
New question (Developed 7/20/93)
Note:
Provide copy of Techni:al Specification 3.S.1.1 wnh tne question (exam)
- 5 l
Justification:
a.
Correct becaus onduct of Operation (SSF 12.1) restri::s power increase when in an LCO acaon et o hours or less. RCS loop 1 accumulator 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 in:rease is not allowed when 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.
l c.
In:orrect because if loop 1 boron concentration is not restored witnin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,tne Unn 1 must be in HOT standoy by 0300.
i l
d.
Incorre:t because if loop 1 boron concentration not restored witnin 1 nour, oressurizer pressure must ce reduced 101000 psig or less by 1400.
/f
,,i t / ' l."'
p6.=
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I/
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pp yu i-s J
i I
l 006 Emergency Core Cooling System;/. JPM 136 Recovery From Safetylnjection
. arid Solid Water Co'n'ditions ' J G.* '
j
)
Question 2:
Given the following plant conditions:
l-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.
j Core exit TCs are 720*F and increasing.
l At this point FR-C.] directs the crew to depressurize intact steam generators.
1 t
l a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?
l b.) Why is this action taken?
L References Allowed? YES X
NO i
i Answer:
a.) To reduce RCS pressure below 125 psig l
b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.
i l
Reference:
l KA: 006G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs.
l OPL271C398 pg 12-15 l
Applicant Response:
SAT UNSAT
?
\\
i I
l l
~
i l
I I
l
~
i FR-C.1 INADEQUATE CORE COOLING i
Rev. 6
\\
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Blocking low steamline pressure Si as soon as pressurizer precsure 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 signalis 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 inadequate core cooling condition.
- 14. DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:
- a. WHEN RCS pressure less tnan 1920 psig, THEN PERFORM the following:
- 1) BLOCK low steamline pressure St.
g
- 2) CHECK STEAMLINE PRESS ISOUSl BLOCK RATE ISOL ENABLE permissive LIT.
[M-4A, A4)
- b. DUMP steam to condenser
- b. DUMP steam at maximum rate at maximum rate.
USING intet S/G atmospheric relief (s).
IF local control of atmospheric relief (s) is necessary, THEN i
DISPATCH personnel to dumo steam l
USING EA-1-2, Local Control of S/G FORVs.
(Step continued on next page.)
~.
l Page 13 of 19
)
d
.026.Conrainrnent Spray System /,JPM.# 57AP Respond to High Containment
. Pres'sifie4PJace'RHR Sp' ray.~iil ServiceW:
Question 2:
{
Given the following plant conditions:
Unit I has tripped from 100% power due to a LOCA.
j 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 transferring suction to the containment sump?
b.) What does placing both CS pumps in PULL-TO-Lock prevent?
References Allowed? YES X
NO i
Ansv er:
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 OPL27iC024 pg 14-1S. CCD NO:1-47W611-72-1 ES-1.3, pages Il-13, OPL271C388 pg 9 Applicant Response:
SAT UNSAT
License Applicant Administrative Walkthrough Examination--NRC-1 l
Examiner Sheet K.1UShift Staffing
~'
Question 1: A licensed RO has been off-shift for 6 months to assist in scheduhng an upcommg outage.
He had ' his last. physical examination 18 months ago and' has had satisfactory performance in the licensed operator requalification training program.
i 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 fill in for the vacationing RO? Why or why not?
w 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.
l
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT
?
+
J
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet i
A 1UShift Staffingt 1
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 shins 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 _X._ NO 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, donduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT UNSAT
?
Y.-
_ - =