ML20199E379
| ML20199E379 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/23/1998 |
| From: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Greenman R TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 9901200410 | |
| Download: ML20199E379 (102) | |
Text
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December 23, 1998 Tennessee Valley Authority ATTN: Mr. Robert Greenman Training Manager Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, AL 35609-2000
SUBJECT:
MEETING
SUMMARY
- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - BROWNS FERRY NUCLEAR PLANT
Dear Mr. Greenman:
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.
Enclosure 1 was the agenda used for the Training Managers' Conference, and Enclosure 2 is the list of attendees. We appreciate the participation of you ard your 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
... Operator Licensing and Human 9901200410 981223 ;
Performance Branch
[h Division of Reactor Safety Docket Nos.: 50-259,50-260, and 50-296 License Nos: DPR-33, DPR-52, and DPR-68
Enclosures:
As noted ;
cc w/encts: /
K. W. Singer, Site Vice President, Browns Ferry Nuclear Plant T. E. Abney, Manager, Licensing &
Industry Affairs SMs
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Revised November 3,1998-TRAINING AND OPERATIONS MANAGERS' CONTERENCE 1
l U.S.-Nuclear Regulatory Commission, Region II Atlanta, Georgia
- Meeting Agenda November 5,1998 Richard B. Ru? sell Building Auditorium Thursday.11/5/98 8:00 a.m. Conference Registration l 8:20 a.m. Introduction Thomas A. Peebles, Chief, Operator Licensing & Human Performance Branch 8:30 a.m. Opening Remarks William Travers, ,
Executive Director of Operations t
8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety 1
, 9:15 a.m. break i 9:45 a.m. Other Issues Robert M. Gallo, Chief Operator Licensing Branch, NRR 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 l
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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 1
4:30 p.m. Adjorn J
,e-ATTENDEES AT THE NRC REGION 11 TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 Sid Crouch ATTSi David Lane Sonalysts, Inc.
- - Bill Fitzpatrick INPO 1
CP&L Rick Garner HR Supv Ops Tmg ,
William Noll BK Ops Tmg Supv l Max Herrell BK Trng Mgr i Scott Poteet RB Exam Team Leader Ralph Mullis BK Ops Mgr i Tony Pearson BK Ops Tmg Anthony Williams RB Tmg Mgr I 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 Reg Team Leader Ronnie B. White, Jr MG Tmg Mgr W. H. " Soap" Miller CT Site Trng Mgr Paul Stovall OC Mgr Oper Tmg l Bentley Jones OC Trng Mgr James Teofilak CT Ops Tmg Mgr Alan Orton MG Ops Tmg Mgr l
Richard Bugert Corp . Ops Trng Spec FP&L l Maria Lacal TP Tmg Mgr Dennis L. Fadden SL Services Mgr Jo Magennis Corp Trng Assessment Spec Tom Bolander SL Exam Development Steve McGarry TP Maint Trng Supv Southern Nuclear (SNC) l John C. Lewis HT Trng & EP Mgr Bill Oldfield FA Nuc Ops Trn Supv Steve Grantham HT Ops Trng Supv I Scott Fulmer FA Mgr Tmg & EP Joel Deavers FA Sr Pit Inst Bob Brown VG Trng Mgr Dan Scukanec VG Ops Trng Supv l
Virainia Power Steve Crawford NA Sr Inst Nuc Harold McCallum SR Supv Ops Tmg
'1Vb Dick Driscoll SO Tmg Mgr Walt Hunt SQ Ops Trng 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 Trng Supv NRC Particioants Tom Peebles R 11 Operator Lic. Br. Ch.
Rick Baldwin R 11 Sr. Examiner George Hopper R ll Sr. Examiner Ron Aiello R ll 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
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FY 99 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 RO SRO-l SROU 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 RESULTS TO DATE 4 4 5 5 9 9 18 18 100 100 100 100 l
No initial exams scheduled for: Brunswick, North Anna aad Vogtle l
FY 00 region 11 write part of Summer & Hatch i
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1 FY 00 INITIAL EXAM SCHEDULE AND RESULTS l
D:c:;mber 14,1998 l
RO SRO-l SRO-U TOTAL Dr.ta Plant Chief Pass # Pass # Pass # Pass O g.. 6-- - < >
9/27/99 Summer GTH 6 6 r:gion II write 10/18/99 Hatch DCP 10 2 12 region II write l 12/13/99 Vogtle RSB 3 5 2 10
! DCP 2/14/00 Brunswick & 12 3 15 2/28/00 03/"/00 Oconee ? 10 i
704/10/00 Harris (maybe 1otoo) 10 l
705/03/00 St. Lucie GTH 6 5 11 J05/"/00 B. Ferry 6 3 3 12 705/03/00 McGuire 4 8 12 l
706/07/00Farley RSB 10 2 12 l 707/26/00 Crystal River RFA 3 3 3 9 region ll write?
! 708/"/00 Sequoyah 4 2 2 8 i
! 709/04/00 Surry? 10 l 709/11/00 North Anna 12 l
0 0 42 0 40 0 27 0 149
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'?' d:;signates tentative No initial exams scheduled for: Catawba Robinson
( Turkey Point Watts Bar l
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Opersfor' Licensing lSSueS .
Region 11 -
Training Managers' Conference November 5,1998 Robert M. Gallo, Chief Operator-Licensing and Human Performance Branch d
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OPERATOR LICENSING ISSUES *- -
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j o Part 55 Rulemakings _
l Status j -
Schedule i ,
o Final Revision 8 of NUREG-1021 !
i j o Examination Quality and Results
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! o Generic Fundamentals Exam
,i .
l l 0 Requal inspections i lP-710.01)'
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[
o Recent Information Notices I
Exam Integrity i'IN 98-15)
Sampling Plans (IN 98-28?
Eligibility ilN 98-37) h
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RECENT LESSONS LEARNED by .
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Charlie Payne Southeastern Training Manager's Conference
~ November 5,1998 i
PC'LLCY CLARIFICATIONS e 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.
2 !
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.I PO_LLCY CLARIFICATIONS -
O In general, license class sizes of greater than B candidates will be scheduled for 2 weeks as follows:
i t
-1 exam week off-week for documentation of week 1 performance 2"d exam week 3
POLICY CLARIFICATIONS l
l 9 Examination submittals - 2 copies of draft and i
final exams (written, JPMs, and simulator 1 scenarios). E15ctronic copy is also desired.
O 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 ,
l
t RECENT LESSONS LEARNED SRO-only Questions intended to sample those K/As specific to '
SRO duties (above and beyond those
- needed by an RO).
i purpose is to meet the requirements of 10 CFR 55.43(b) (items (1) - (7)).
l 1
K/A catalog cross-references K/As to associated portions of 10 CFR 55.
1 l
2;0 GENERIC KNOWLEDGES AND ABILITIES 2.1 Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements.
(CFR: 41.10 / 45.13) 1 IMPORTANCE RO 3.7 SRO 3.8 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
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(CFR: 41.10 / 45.13) -
IMPORTANCE R O 3.0 SRO 4.0 2.1.3 Knowledge of shift turnover practices.
(CFR: 41.10 / 45.13)
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 i activities.
(CFR: 41.10 / 43.5 / 45.12)
2.1.6 Ability to supervise and assume a management role during plant transients ar '
upset conditions.
4 (CFR: 43.5 / 45.12 / 45.13)
IMPORTANCE RO 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)
IMPORTANCE RO 3.8 SRO 3.6 2-1 FJREG-1123, Rev. 2 l l
j-2.1- Conduct of Operations ( ontinued) '
l l- l l 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.
(CFR: 45.12)
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2.1.20 Ability to execute proc' edure steps.
- (CFR: 41.10 / 43.5 / 45.12) !
IMPORTANCE RO 4.3 S'd.O 4.2
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j i l 2.1.21 Ability to obtain and verify controlled procedure copy. '
l (CFR: 45.10 /45.13)
l 2.1.22 / Ability to determine Mode of Operation. '
O (CFR: 43.5 / 45.13)
IMPORTANCE R O 2.8 SRO 3.3
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2.1.23 Ability to perform specific system and integrated plant procedures during t different modes of plant operation.
l l (CFR: 45.2 / 45.6) l IMPORTANCE- R O 3.9 SRO 4.0 1
2.1.24' Ability to obtain and interpret station electrical and mechanical drawings. '
l (CFR: 45.12 / 45.13)
L IMPORTANCE R O 2.8 SRO 3.1 t
- 2.1.25 Ability to obtain and interpret station reference materials such as graphs /
j monographs / and tables which contain performance data.
(CFR: 41.10 / 43.5 / 45.12)
2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical /
, high temperature / high pressure / caustic / chlorine / oxygen and hydrogen).
l (CFR: 41.10 /45.12) l IMPORTANCE R O 2.2 SRO 2.6 L
i 2-3 NUREG-1123, Rev. 2 (
2.4 Emergency Procedures / Plan (Continued) l l
2.4.32 Knowledge of operator response to loss of all annunciators.
(CFR: 41.10 / 43.5 / 45.13)
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 system geography and system implications.
1 (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 systera geography and system implications.
- (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 e nergency.
- (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 RO 3.3 SRO 3.1 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.
(CFR: 45.11)
IMPORTANCE RO 2.3 SRO 4.0 2.4.41 Knowledge of the emergency action level thresholds and classifications.
r (CFR: 43.5 / 45.11)
IMPORTANCE RO 2.3 SRO 4.1 NUREG-1123, Rev. 2 2-14 l
.RE_C_ENT LESSONS LEARNED 4
r 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. I l
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ES-401 BWR SR0 Examination Outline Form ES-401-1 I
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
_.~' ;
3- I Pg;
/ Me $% #2s y 13; 26 m wg1c ggis:e Emergency & _. ;
- _=_
a n Abnormal 2-
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{ f. 17 Evolutions Tier Totals f[f h[f E E@ iM[
h; {fjf 4;p 43 +7
@ $jpg i we me RL cag
- 4f? Ei gy 93y4 l l
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! 1 23 2.
2 13 I
/lant l
- Systems 3 4 I Tier 40 _.f; Totals l
l 3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 +Y i
l Note: -
Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table. !
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to
! plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
f t
NUREG-1021 10 of 39 Interim Rev. 8, January 1997 l
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ES-401 BWR R0 Examination Outline Form ES-401-2 Facility: Date of Exam: Exam Level:
l K/A Category Points l Tier Group Point l K K K K K K A A A A G'
- Total !
1 2 3 4 5 6 1 2 3 4 l
1.
Emergency &
I j hh hh gg gg 13 Abnormal - - h N EN 19
! P1 ant 3 O N E$ @fi$ 4 j@ind #G %@+: k';s m:*.
! Evolutions seg. gg w N
l Tier est ?Mi. ;ps 36 l
Totals M4 5 Gt gg; 491 4#g.
c w 3-g g l 1 28 2.
2 19 Plant Systems 3 4 Tier 51 Totals l
- 3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 13 i
l 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.
l Systems / evolutions within each group are identified on the l associated outline.
The shaded areas are not applicable to the category / tier.
l NUREG-1021 16 of 39 Interim Rev. 8, January 1997
-l RE_ CENT LESSONS LEARNED ,
i Sampling Criteria l intent of prodess is to avoid exam predictability.
I a so to avoid excessive use of repeat test ;
items.
first use systematic arocess to develop sample alan using topics from K/A catalog, then use facility c uestion resources to accomplish the plan. .
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- RECENT LESSONS LEARNED L
Sampling Criteria (Cont'd?
i each topic in each tier & group should be sam aled at least once unless insufficient questions exist to do this. If all topics have been sampled once and other questions need to be selected, t7e process s 7ould be systematic and unbiased.
final sample plan should have a fairly even balance across all Ks & As.
t 8
RECENT LESSONS LEARNED -
l Samp ing Criteria (Cont'd) up to 25 questions " rom last two NRC exams, facility licensee exams, tests & quizzes (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-saeci"ic priorities may be identifiec with CE concurrence (K/A value may be < 2.5 wit 1 sufficient justification).
OTHER .
Record Keeping per 10 CFR 55 are required to provide evidence that the applicant has successfully completed the facility licensee's requirements to be licensed as an operator.
this includes successful manipulation of the controls of their facility. As a minimum,5 significant control manipulations which affect reactivity or power level.
I 10
-O OTHER -
Record Keeping (Cont'd) this information should be retained and available for inspection from time of license application to icense expiration.
1I
. _ - _ _ - _ _ - - - = - . -
OTHER - -
1 Requal Control Manipulations if have program based on SAT process, list in 10 CFR 55.59(c)(3) does not need to be strictly followed.
should have something similar 3asec on alant JTA and saecific plant ariorities.
some maniaulations are individual oaerator t orientec, most would be team oriented.
i 12 t
OTHER Requal Control Manipulations (Cont'd)
)
credit for accomplishment should only be given for active participation in the manipulation.
NOTE: control maniaulations are not synonymous with reactivity manipulations.
I 13
Examination Communications Examination Development Coordination By Ronald F. Aiello
Facility Suggested improvements
- 1. The exam development team and lead examiner should meet at the beginninc of the development arocess to establis, common grounds for the development and execution of the examination:
- Changes and interpretations to the NUREG.
- Scope of the exam development and administration arocess.
- Lessons learned from the last exam administered.
1
- 2. Move due dates for the outline and t1e exam back to 90 and 60 days arior to prep week. This will provide more time for examination review by the examiner (s).
- 3. SSNTA continue with efforts to standardize document formats for i examination tools (JPMs and scenarios).
- 4. Examiners maintain a list of who (plant) does the exam 3rocess the best. This s1ould probably 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 improve.
- 5. The principal and the utility rearesentative should meet early to establish a working relationship and exaectations. If possible this shoulc inc ude samples of questions, JPMs, etc.
- 6. The exam should have no outstanding issues / questions that arise and need repair at the last minute. These issues s1ould all have oeen identified by the prep week, to allow time to make changes that meet all the criteria.
7.
The chief examiner should explain up
. front all the forms in 1021 that need to be completed.
- 8. Always check on badging prior to coming on site.
- 9. As soon as a Chief Examiner is assigned to an exam, the Facility Rep and the Chief should verify the ability to communicate via all channels (including e-mail). When we converted to Lotus Notes, the facility was suddenly unable to send e-mail to his C7ief Examiner. This
i became somewhat of a lindrance and
! s1ould be avoiced if possible.
i
- 10. It would be he pfulif the Chief Examiner l
- could provide his schedule to the Facility Rep. This includes aroviding uadates foi j any changes to the Chief Examiner's schedule along the way. The facility rep l needs to be aware of when the Chief l Examiner is available to assist in exam
! preparation activities.
i l 11. A face-to-face meeting should be promptly
! scheduled in order for the Chief to
{ communicate lis expectations to the i
Facility Rep. The face-to-face requirement could be waived if the Chief anc' t1e Facility Rep have previously worked together and the Facility Rep is confident that he/she understands the Chief's exaectations. In any case, a
l conference call would be the minimum to l satisfy this im aortant first step.
l 12. The Chief and the Facility Rep s1ould work together to establish a firm schedu e for the exam week (s). This will ensure the ,
most efficient schedule is developed (with respect to crew composition and personnel movement) to minimize the amount of exam material required.
- 13. The Chief Examiner and Utility Rea MUST remain fixed during the entire 180 day period. Handing off the responsibility is both disruptive and destructive to communication. T1e exaectations of t1e chief examiner must be defined / communicated early.
- 14. The " time ine" must ae enhanced to identify saecific times and dates for communication /workinc meetings between l 1
j the examiner and the utility re3. These j meetings should be " face to face" to j assure expectations are understood, and being met, early on.
I
} 15. If an examiner and a utility rep have not l l worked together before, the timeline for '
' " deliverables" must be expanded.
Working meetings (face to face) must be established for the examiner to review l 5-10 questions,1 scenario,1 jpm,5 jpm '
knowledge questions,5 admin questions, etc. to assure that the standards and expectations are clear early in the process and that the utility can aroduce a aroduct tia: meets the expectation.
- 16. 398 and 396 "orms need to be available electronically. We took the time to develoa an electronic version ourselves out I would prefer that tie electronic master copies came directly from the NRC
i
! so that we lave more confidence tlat
{ everything is exactly the same. We would i all benefit from this improvement. l l
l 17. =A face to face working meetinc of eight (8) l to twe ve (12) hours, a 33roximately two I l (2) weeks before the thirty (30) day l l submittal must be established to resolve l
) any issues BEFORE the submittal. The exam materials should be reviewed, line l ay line, at this meeting to communicate all i changes necessary.
I j 18. Exaectations must be established early so l that the utility clearly understands the rules j and the examiners exaectations. Small j
samales of develoament must be reviewed j early to assure expectations are being met.
j A face to face meeting, arior to the 30 day j submitta , to resolve any/all issues must be
! scleduled such that adec uate time
! (suggest 2 weeks) is available to resolve
comments before the 30 day limit. No one wants to see 30 c uestions reviewed and the exam rejected. Spending ~24 hours in 3-4 face to face meetings is a small/ smart price to pay to avoid hundreds of hours of re-development, the emotional stress on candidates when the exam must be rescheduled and the impact on t1e alant when candidates are not licensed to meet l plant needs.
! 19. The "new" SSNTA format for JPM level of i detai is NOT what you have liked in the i j past and needs to be either accepted by i j the NRC as a standard or optimum format, l or mocified, or rejected. The JPMs we j submitted to you were in the format and l level of detai you had found acceatable in the aast, and we were surprised to find that j
l they needed significant ast-minute rework (additional level of detai).
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l 20. Maybe C1ief Examiners could send some l copies of good written questions, JPMs, j and JPM questions u a front that could help l
a new developer survive the exam writing l process and see w1ere you as an examiner are coming from.
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j Facility General Comments i
l 1. The limited number of NRC license j examiners auts t1e Region and the sites at a disadvantage with resaect to getting timely interc1ange. If the 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 strugg:e to ensure a quality exam.
The limited resources and interaction time increases the risk of ower quality.
- 2. Region ll examiners have been very prompt in getting back to us when we have a c uestion even though you may be at a remote location.
- 3. The quality of the communications has been good. All of t7e examiners tlat I have talked to 1 ave 3een t1orough, arecise and lave 3erformed listeninc checks to
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i verify that the correct messages were sent anc received. I would however, li<e to see more communications by e-mail where appropriate. That would hela ensure the clarity of the communications even more.
- 4. With respect to the exam specifically; there l were a number of changes that were made l and we had to transmit those by expensive !
overnight or next day delivery. If we could figure out a secure e-mail method it would save all of us numerous headaches as well as dollars.
- 5. During my first face-to-face meeting with the Chief Examiner (to review draft exam material), I gained much-needed insight into his expectations. T1is alleviated much stress on my part and, from then on, the process went muc1 more smoot1ly. The C1ief was very he afu durinc subsecuent teleahone conversations and our second
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l l meetinc in Atlanta. He was very easy to
! work wit 1 and very understanding j concerning my inexaerience in this process. His aatient guidance was the key
-to our success in this endeavor. Next time,
- wit 1 all we've earned, we'l do even better.
l 6. The biggest problem that I encountered j during that exam came from the written j portion that was being developed by the l contractor. Since he had written exams l before, I assumed that the quality of c uestions he was submitting to us were the l qua ity of questions that were acceptable to
! t1e NRC. We reviewed his work, made l technical corrections and assumed that the l questions would bo acceated by the NRC.
l l had very little communication with the i
NRC on t1e subject of the written exam )
and a great ceal of communication on the sub.ect of the operating exam. W1en t7e submittal was finally made, the focus went a
to the written exam and most of the communication was made over speaker 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 lave been avoided lad I not put so much faith in the contractor's exam writing experience and !
communicated more on the subject of the written exam with the chief. We had a l 100% pass rate on the exam, but the exam report was brutal in the area of the written I exam.
- 7. Know the chief examiners expectations from the beginning (prior to any develo ament).
- 8. Never assume you know what you're doing
- t1e chief is just a ahone cal away.
- 9. It's better to de iver material and review it in I person rather than over the phone. I 3 an for four or five trias between the start of
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deve opment and prep week. It may j sound ike overkill, but it works (It's a so
! safer in the area of security).
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- 10. ~ Submit material early (esaecia y the j written). I like to have the written exam a i done deal prior to the actual submittal date.
i 11. You can never talk to the Chief Examiner j too much. During the process, I talk to him j mo.re than I talk to my mother.
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! 12. The bottom line is tnat frec uent l communication, personal contact, and l ~early submittal of materials is the key to a j successful NRC exam.
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- 13. ALL aroalems/ changes must be resolved at the leve' of the examiner and the utility rep. In no case should prob ems /clanges be reaortec/ escalated to senior management of the utiity or NRC unless
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! both the examiner and the utility rep are at~
j an absolute, and mutually agreec, j impasse. ,
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l 14. We often felt that we were working in the l l dark, writing questions on topics you may l
{ not want (as we were waiting for comment l on our skyscrapers), possibly wasting :
! resources, but seeing no other option to l meet our required cast-in-stone deadlines.
! 15. It's difficult to keep JPMs short and
! plausible at the same time.
l 16. W1at is a good " admin JPM", especially for
! ROs?
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tjuestiust; 4v 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
- l. 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.
l B. Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will oc within 1 F of the temperature prior to the dropped rod.
C. Reactor thennal 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 will be more than 5'F lower than the temperature prior to the dropped rod.
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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.
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, Keterence Page SRO Question 10 RO Question 10 i
... SRO Tier / Group 1/l RO Tier / Group 112 SRO Importance 3.7 ROImportance 3.2 10CFR55.43(b) 10CFR55.41 8 ItemAddressed Item Addressed KA Number 000003AKl.01 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 i-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 SD-104 Rod Control System Question Source New Justification (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.
(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 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.
(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
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-e INITIAL EXAMINATIONS QUESTIONS AND ANSWERS :
TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 RICK BALDWIN GEORGE HOPPER
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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 Sheet."
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l OBJECTIVES ;
O BEi iER EXAMINATION PRODUCT :
i lt O LESS NRC/ FACILITY REWORK I
O SHARED EXPECTATIONS :
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f SESSION OBJECTIVE: -
I 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. ;
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ij VALIDITY ;
i A valid test is one which tests what it intends 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.
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A-3 LEVELS OF VALIDITY O Content
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G Operational i
t 9 Discriminant i
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i CONTENT VALIDITY i
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1 Addresses K/A coverage and sampling plan coverage.
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J OPERATIONAL VALIDITY ' !:
Addresses two aspects:
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- 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 R. ELATED 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 percent.
9 The exam must be written at a level of difficulty that. intends to discriminate at the 80 percent level.
e The question, its stem and distractor, interplay, by DESIGN, at least 80 percent l of the candidates taking the exam should answer the item correctly. '
VALIDITY
SUMMARY
- 1. The exam must be content valid, 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 comprehension or analysis level vice 1 simple memory. Items that measure problem solving, prediction, analysis which are essential to job performance.
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VALIDITY
SUMMARY
- 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 t
O Comprehension O Fundamental (simple memory) l 13
LEVEL OF KNOWLEDGE G Bloom's Taxonomy, NRC Reference Benchmark to classify levels of knowledge. .
G Bloom's Taxonomy, a classification scheme that classifies items by depth of mental performance required to answer I
the items. j 9 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 i.e. setpo.in ts, definitions, or specific facts.
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LEVEL 2 '
i Comprehension, involves understanding .
material through relating it to its own parts or other material: j t
i.e. including rephrasing information in
- different words, recognizing relationships
, including consequences or implications.
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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 a problem or create something new.
i.e. using-knowledge to solve problems.
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DETERMINANTS OF DISCRIMINATION e Level of examination knowledge 9 Level of examination difficulty i
G Passing Score
- 9 Item bank use 18 j
-l NATURE OF EXAMINATIONS AND TESTS O TESTS are samples of PERFORMANCE 9 Infer overall performance based on a sample 9 Sample must be broad-based to make confident inference 9 Sample must NOT be fully predictable or inferences cannot be made on untested areas.
O ltems MUST discriminate otherwise it has little or NO value. '
19
PSYCHOMETRICS 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
- 5. Confusing language or ambiguous questions
- 6. Confusing or inappropriate negatives
- 7. Collection of true/ false statements
- 8. Backwards logic I
20
006 Emergency Core. Cooling System-/ JPM 136 Recovery From Safetylnjection
.and Sdlid Water Co~nditions'. 2.i ? A 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___
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'~ FR-C.1 l INADEQUATE CORE COOLING l Rev. 8
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- l. STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is 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. r
. S/G depressurization at the maximum rate may cause S/G narrow range levee 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. 7
- 2) CHECK STEAMLINE PRESS ISOL/S1 BLOCK RATE ISOL ENABLE permissive LIT.
{M-4A, A4]
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- b. DUMP steam to condenser b. DUMP steam at maximum rate at maximum rate. USING Intact S/G atmospheric relief (s). j IF local control of atmospheric relief (s) is necessary, 1 THEN I DISPATCH personnelto dump steam l USING EA-1-2, Local Control of i C Ti PORVs. l l l l
(Step continued en next page.)
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.~026, Containment Spray System /.JPM y 57AP Respond to High Contamment
. Pressure,iPlace RHR Sptuy.in Service 94 ~
i-Question 2:
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.
f- a.) Why must both CS pumps be placed in PULL-TO-1.ock while transferring suction to the containment sump?
b.) What does placing both CS pumps in PULL-TO-Lock prevent?
References Allowed? YES X NO Answer:
y a.) While shifting to the containment sump, both the RWST and the containment sump suction :
l valves to the CS pumps will be closed at the same time.
j b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of ,
water.
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Reference:
K/A: 026G4.18 [ 2.7 / 3.6 ) Knowledge of specific bares for EOPs OPL271C024 pg 14-18, CCD NO:1-47W611-72-1. ES-1.3,pages Il-13 OPL271C388 pg 9
.i Applicant Response: SAT UNSAT L
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l- License Applicant Administrative Walkthrough Examination--NRC-1 L Examiner Sheet
! A'.1: Shift Staffing '
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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 1 vacanonmg Unit OATC.
1 Can the RO. fill in for the vacationing RO? Why or why not? s References Allowed? YES _2L NO -
Answer: No. The RO must first reactivate his nicense 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.
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Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 i
K/A 2.1.4 (2.3/3.4) 9 Applicant Response: SAT UNSAT I '
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License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet
'A.1:; Shift Staffing j 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 shift RO. He had a satisfactory physical examination 18 months ago and has l 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
Tht additional requirements must be met by the RO before he may fill in for the l . vacationing RO? 3 l
l l 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.
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Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 l K/A 2.1.4 (2.3/3.4) i I
Applicant Response: SAT UNSAT l
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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
.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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/ e Reactor Operator Examination
- 65. Given the following conditions: l The reactor has experienced a Steam Generator Tube Rupture.
All systems responded as expected. ;
' The performance ofEOP-04 is in progress. j
- One steam generator has been isolated.
RCS cooldown using natural circulation is in progress.
Which ONE ofthe following describes the concem associated with the affected SG pressure prior ,
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- a. The SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS inventory,
resulting in a dilution. :
- 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 response 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 chargina 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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l 19. Which ONE ofthe 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 ,
- l. electrical lineup and all equipment is operable.
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- a. Only one charging pump is automatically staned on each emergency bus 5 minutes after it is energized bythe diesel.
- b. All charging pumps are automatically staned immediately after their respective bus is ;
energized by the diesel.
- c. All charging pumps are automatically staned 5 minutes after their respective buses are ,
energized by the diesel.
l l d. Only one chargmg pump is automatically staned onto each emergency bus immediately l afterit is energized bythe diesel. ;
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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 RRT.
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- d. continue to run and become gas bound.
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p Reactor Operator Exa:nination
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' 27.' Charging pumps are running on Unit I and an SIAS is prese tn . (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 thermal overload.
' b. .,
trip on low suction pressure.
- c. automatically align to the RWT. !
- d. continue to run and become gas bound. -
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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. l 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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, f-Reactor Operator Examination l 1
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i C 59. Given the following conditions:
l -
' Unit 1 CEDM fan HVE-21 A is in AUTO after START. l Unit 1 CEDM fan HVE-21B is in AUTO after STOP.
Unit 1 CEDM fan HVE-21 A trips on overcurrent. l Which ONE of the following lists the signals required by the logic needed to start HVE-21B?
l i a. The trip signal from HVE-21 A. l
- b. The trip signal from HVE-21 A concurrent with a low flow signal.
- c. A low flow signal.
l l 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 occurred 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 levelis 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. Containment
- d. Pressurized Thermal Shock Answer: A K/A- 000040K101 [4.1/4.4]
Reference:
E-0 Foldout Page Objective: OPL271C395, B.1 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 are Jess tnan 10% NR and total feeowater flow is ]
less than 440 gpm.
- b. Incorrect because RCS temperature is 325'F (core exit T/Cs less than 1200'F). j i
- c. Incorrect because containment pressure is less tnan 12.0 psid.
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[ d, incorrect because RCS temperature is 325'? (T-cold rs greater than 250*F) ;
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- 13. Given the fo' owing plant conditions:
. Unit 1 was at 73% power A reactor trip / safety injection on low steam line pressure o::urred 21 minutes ago
. . Average Core Exit TC temperature is 3755F
. RCS pressure is.225'psig I'.>SD 'I#
. 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 feedwatep, flow is 340 gpm PZR ievelis')7% and lNCREASING
. RCS T-cold temperature is 325'F and DECREASING slowly
. Containment pressure is 5 psid and INCREASING slowly At this 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: 000040K101 [4.1/4.4)
Reference:
E-0 Foldout Page Objective: OPL271C3Dy, 8.1 Level: Analysis ,, 3 Source: 000040K101 001 History: Stem and distracters a and d modified (7/7/93)
Note: Provide PTS curve with this question.
Justification:
- a. Corre t answer because all SIG leve!s are Jess than 10% NR and total feedwater fiow is less than 440 gpm.
- b. in:orrect because RCS temperature is 325'F (core exit T/Cs less inan 12DD*F).
- c. Incorrer, be:ause containment pressure is less tnan 12.0 ps:d.
l-l d. Incorre: ce:ause RCS temperature is 225'F (T-5cid is greater inan 250*F)
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- 20. Given the following plant conditions:
. The contro! 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?
- 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 manual valves at the LCVs. ,
Answer: B K/A: 000058A102 {4.3 / 4.5]
Reference:
AOP-C.04, page 11 Objective: OPL271C423. B.4 Level: Comprehension Source: 00006BA102 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) l Note: Selected from% exam bank with minor modification of text
h-
- 20. Given the fo!!owing plant conditions:
. The control room has been evacuated due to a fire
. All controls have been transferred per AOP-C.04
. MDAFW pumps 1 A-A and 18-B are injecting into the steam generators
. The TDAFW pump has been shut down
. Steam generator pressures and levels are decreasing
, us 4 s 6 wk % 0 N c y h l h 3 M irq * - C . 0 1 Which ONE of the fo!!owing describes the r comev ih= ad.my feedwater-system?
~
- a. The TDAFW pump will automatically restart whan 2/4 steam generatob., reach low low level. x ~ E k ~*M OoN uhp e l, -M/ .
(C o ^
- 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.
fW
, ,I y,,.fj [ d. The discharge pressure forthe MDAFW pumps will have to be manually adjusted by tnrottling the manual valves at the LCVs.
, J/
- C
,j[j, Answer B K/A: 000058A102 (4.3 /4.5]
Reference:
AOP-C.04, page 11 Objective: OPL271C423, B.4 Level: Comprehension Source: 00005BA102 001 History: Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distra: ers a,6, c. and d reordered (7/22/98). Distracter be restructured (7/29/98)
Note: Selected fromMexam bank with minor modification of text
. 1 l
- 23. Given the following plant conditions:
. FR-C.1, *lnadequate 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.
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 P *nd c reordered Note: Selected froMexam 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 Faulted 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 total feed 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, THEN PERFORM the-following:
- 1) CONTINUE attempts to establish heat sink in at least one S/G.
j 2) GO TO Note prior to Step 21.
- b. Between 10% [25% ADV) and 50%.
I Page 10 of 19
d FR-C.1
+ INADEQUATE CORE COOLING Rev. 8 j STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RC'P damage due to absence or loss of norrnal support conditions is an acceptable consequence in this procedure.
- 21. CHECK if RCPs should be started:
- a. , CHECK core exit T/Cs a. GO TO Step 22.
l
! greater than 1200*F.
- b. CHECK if idle RCS loop avaifable: 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, THEN OPEN reactor vessel head vents:
. FSV-68-394
. FSV-68-395 4
. FSV-68-396 I
. FSV-68-397.
c) GO TO Step 22.
- c. START RCP in one idle loop.
- d. GO TO Substep 21.a.
Page 17 of 19
~
l l
- 23. Given the following plant conditions:
. FR-C.1. Inadequate Core Cooling *, has been entered due to a RED path on Core Cooling i
- . Core exit temperatures (TCs) are 1250*F and increasing j
. NO Feedwater / Aux Feedwater is available l
. 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) d
- a. Go to FR-H.1,
- Loss of Secondary Heat Sink".
- b. Depressurize allintact S/Gs to atmospheric pressure to dump accumulators.
~
d.
M PorW.s stre SLod \/OS P_reparc tc !-5ct: ",L%FeaJ oud Gee 64WR4eveHrreny-2-S/Gs-is4ess-tharHW/,--
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: SelectediromMexam bank without modification of text gfZ fA PS $ ' E
-w
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- 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 t:ip bypass switch for N-35 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:
ACP-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 E'98 NRC exams. Not used on practice exam.
Distracters e and d reordered Note: Selected fromg exam bank without modification of text ame
O
$5 6W "M f l 3r / /s
- 49. Given the 1ollowing plant condnions:
. Reactor power is at 20% during a unit shu:down \
. Intermediate Range N-36 failed high _
\
Opers: ors ptaceUsempeypass-swnctrfort#36 t:rthirDypass peskis d
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. .Botn Source Range channels, N-31 and N-32, must be manually energized 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-6 setpoint; Source Range channel N-31 will automatically energize.
, Answer. C K/A: 015000K407 [3.7/3.B]
Reference:
AOP-LD1, page 10 ES-0.1, page 13 Objective: OPL271 C352, B.4 Level: Comprehension Source: 015000K407 001 .
History: Not used on 9/97 or 5t98 NRC exams. Not used on practice exam.
Distracters e and d reordered I
Note: Selected fromMexam 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 l- Which ONE of the following actions must be performed before reducing reactor power below
! 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-1.01, page 10 & 13
- Objective: OPL271C352, B.4 Level: Analysis Source: New question (Developed 7/15/98) .
Justification:
- a. Incorrect because manually restoring N-31 and N-32 to operation in the power range would destroy the source rarige 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. I 36 level trip swnch in BYPASS allows an orderly reactor shutdown.
1
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- 50. Given the fo!!owing plant conditions:
. Large Break LOCA is in progress j
. RCS pressure is 550 psig
.- . Exosensor indicates 25'F superheat
. No RCPs are operating Which ONE of the following indications would the operator use along with RCS pressure to accurately substantiate core cooling?
- a. Reactor Coolant Tavg value.
1
- b. Average value of all core exit thermocouples.
- c. Hottest Reactor Coolant wide range That value.
- d. Average value of five hottest core exit thermocouples. l 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 fr m ram bank without modification of text l
~
- 50. Given the following plant conditions:
. Large Dreak LOCA is in progress
. RCS pressure is 550 psig f . Exosensor indicates 259 superheat
. No RCPs are operating Which ONE of the following indications would the operator use along wth RCS pressure to accurately substantiate core cooling?; , . , , ,
2#. _-
, ,- f, ~ ,- q ,,-
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, t 72. Abit tcre c.? e
- b. Average value of all core exit thermocouples.
c Hottest Reactor Coolant wide range Thot value. ~
- d. Average value of five hottest core exit thermocouples.
Answer: D s j
M ~#
K/A 017000A402 [3.8 / 4.1)
NJ #C #7^
Reference:
FR-0, page 3
- 61 OPL271C044, page 7. A.1.c Objective: OPL271 C044, B.1.6 Level: Memory Source: 017000A402 001 History: Used on HLC 9809 pra::tice exam Distracters a, b, c, and d reordered (7/22/98)
Note: Selected from exam bank without modification of text d
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i' 88. Given tne following plant conditions:
. . Unit 2 operating in accordance with 0-GO 5. Normal Power Operation at 73% with a
, powerincrease to 100% in progress l . Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm
! . Current time is 0100 i l Which ONE of the following actions must be taken? ;
- a. Immediately stop the po wer increase. l l ,
t:
- b. Continue the power increase while restoring loop 1 accumulator boron concentration l 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 />. '
l .
- c. If loop 1 accumulator boron concentra' ion 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:
HiiTANDBY 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.
4 Answer: A 4
K/A: 2.1.1 [3.7/3.8)
Reference:
SSP-12.1, Page 31 L
Objective: OPL271C209, B.2 f
- ' Level
- Comprehension Source: New question (Developed 7/20/98) '
Note: Provide copy of Technical Specification 3.5.1.1 with the question (exam) l Justification:
l t
- a. Correct becausegConduct of Operation (SSP-12.1) restricts power increase
- l. 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 cf 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.
j 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.
l 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 l must be in HOT standby by 0800.
I ~-
' d. Incorrect because if 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.
t L
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l 3 /4. 5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMUIATORS i COLD LEG INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:
- a. The isolatio.n valve open, A contained borated water volume of between 7615 and 8094 gallons of a131 b.
barated water, e
- c. Between 2400 and 2700 ppm of baron,
- d. A nitrogen cover-pressure of batween 600 and 683 psig, and R184
- e. Power removed from isolation valve when P.C5 pressure is above 2000 psig.
APPLICABILITY: MODES J, 2 and 3.*
ACTION:
- a. With one cold leg injection accumulator inoperable, except as a result of boron concentration not within limits, restore the 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 />.
- b. With one cold leg injection accumulator inoperable due to the boron concentration not within limits, restore boron concentration to within.'l.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.
December 27, 199!
Amendment No. 113, 131, 1 3/4 5-1 g - UNIT 2
. _ ~ . -. .. . . - . . - ., - - . - - . . - ~. - - -.-. . . .~.-
/
0 { 0} . 5rl hW)' - ,
BB. Given tne following plant conditions:
. Unit 2 operating in accordance with 0-GO 5, Normal Power Operation at 73% with a powerincrease to 100% in progress
,e /,g - Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm
,gM2' - Currenttime is 0100 4-/
- Which DNE of the following actions must be taken? ,
- a. Imrnediately st p the power increase. ,
f
- b. Continue the power increase whi4 restoring looy ,1 accumulator boron concentration to 2400 to 2700 ppm boron,wNi,1 htmr, ivmW 72 4 og CL
- c. 11 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 HGT
- STANDBY 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 -
K/A: 2.1.1 {3.7/3.8)
Reference:
SSP-12.1, Page 31 4
Ob{ective: OPL271C209, B.2 Level: Comprehension Source: New question (Developed 7/20/98)
, Note: Provide copy of Technical Specification 3.5.1.1 with tne question (exam) l
?
Justification:
l f l'
- a. Correct becausMonduct of Operation (SSP-12.1) restri:ts power increase
- l. ,
when in an LCO acuan et a hours or less. RCS loop 1 a: umulator boron concentration of '
l 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.
l l.
- 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 be:ause 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 />, the Unit 1 must be in HOT standby by 0800.
- d. Incorre::t be:ause 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 ce reduced to 1000 psig or less by 1400.
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i 006pergency Core Cooling System-/ JPM 136 Recovery From Safetylnjection
.and Solid Water Co~n'ditions::Jv!:. W ~
Question 2:
Given the following plant conditions:
i 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. j At this peint FR-C.1 directs the citw to depressurize intact steam generators.
a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators? j b.) Why is this action taken? l 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 l
. Applicant Response: SAT UNSAT _ 1
=
9 d
=a
, ,- ,e--
- *l INADEQUATE CORE COOLING Rev.8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is 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 tnis
. _ , 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 SI. g
- 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 dumo steam USING EA-1-2. Local Comrol of S/G PORVs.
(Step cominued on next page.)
Page 13 of 19
- 026 Contamment Spray System /,JPM y 57AP Respond to High Contauunent
.PresstiiehPlace'RHR Sp' ray.in 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-TOlock while transferring 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 I l-13, OPL271C388 pg 9 Applicant Response: SAT UNSAT
License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet K.1:? Shift StafHng '
Question 1: A licensed RO has been off-shift for 6 months teassist 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.
_ Can the RO fill in for the vacationing RO? Winy 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.
Reference:
SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response:
SAT __ UNSAT z
l l
l
, l l
o License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A'.li: Shift Staffing t Question 1: A licensed RO has been off-shiR 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 shin RO..
What additional requirements must be met by the RO before he may fillin for the vacationing RO? 3 References Allowed? YES _2L 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, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)
Applicant Response: SAT UNSAT
?