ML20199E399

Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl

ML20199E399
Person / Time
Site:	Crystal River
Issue date:	12/23/1998
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Thomas Taylor FLORIDA POWER CORP.
References
NUDOCS 9901200414
Download: ML20199E399 (102)

Text

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4.

' .f December 23, 1998 i

l Florida Power Corporation ATTN: Mr. Thomas Taylor, Director Nuclear Operations Training 8200 West Venable Street Crystal River, FL 34429

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - CRYSTAL RIVER NUCLEAR PLANT Dear Mr. Hickle-  !

l 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 and your staff and believe that the  ;

goal of providing an open forum for discussion of operator licensing issues was met. Mr. Gallo, l Chief of the Operator Licensing and Human Factors Branch, Office of Nuclear Reactor l Regulation (NRR), made a presentation as noted in the slides in Enclosure 3.

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. l If you have any questions regarding the content of this letter, please contact me at (404) 562-4638.

Sincerely, Original signed by c Thomas A. Peebles Thomas A. Peebles, Chief l Operator Licensing and Human Performance Branch Division of Reactor Safety l

l Docket No.: 50-302 l License No.: DPR-72 200089 l

Enclosures:

As noted ,

i cc w/encls:

J. P. Cowan, Vice President, Nuclear Operations Crystal River Nuclear Plant -

9901200414 PDR 981223 ADOCK 05000302 PDR

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FPC 2 Distribution w/encis:

PUBLIC B. Michael, DRS Ril:DRS Ril:DR BMICHAEL: lPEBLES 12/# /98 12/j//98 Doc Name:

~ . ._ - _ - _ _ _ - .- - - . - . ~.

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Revised November 3,1998 TRAINING AND OPERATIONS MANAGERS' CONFERENCE U.S. Nuclear Regulatory Commission, Region II Atlanta, Georgia l

Meeting Agenda November 3,1998 Richard B. Russell Building Auditorium Thursday. I1/5/98 8:00 a.m. Conference Registration 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 8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety break- I 9:15 a.m.

9:45 a.m. Other Issues Robert M. Gallo, Chief I 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

. I1:30 a.m. Lunch

~

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 4:30 p.m. Adjorn t

h v

License Applicant Acfmirdstrative Walkthrough Examination--NRC-1 'N Examiner Sheet A InShift Staffing -

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 shift RO, What additional requirements must be met by the RO before he may fill in for the vacationing RO? 3 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, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT UNSAT i

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l ATTENDEES AT THE NRC REGION 11 l TRAINING MANAGERS CONFERENCE l

NOVEMBER G,1998 I

. Sid Crouch ATTSi David Lane .

Sonalysts, Inc. ,

)

Bill Fitzpatrick-- INPO CP&L Rick Gamer. HR Supv Ops Tmg l

William Noll BK Ops Tmg Supv '

. Max Herrell BK- Tmg Mgr L . Scott Poteet RB Exam Team Leader  !

- Ralph Mullis BK. Ops Mgr

' Tony Pearson BK Ops Tmg Anthony Williams RB Tmg Mgr f

l i Crystal River - FPC

l. . Wes Young CR ' Supv OpsTng I

!  : Tom Taylor CR Dir Nuc Ops Tmg Ivan Wilson CR Ops Mgr:

' Ken McCall- CR Mgr Ops Tmg -

l. Duke Power l GabrielWashburn 'OC Req Team Leader  ;

l Ronnie B. White,'Jr MG. Tmg Mgr '  !

. W. H. " Soap" Miller CT Site Tmg Mgr .

I Paul Stovall .OC Mgr Oper Tmg Bentley Jones OC- Tmg Mgr l James Teofilak - CT , Ops Tmg Mgr l Alan Orton MG Ops Tmg Mgr -

Richard Bugert Corp . Ops Tmg Spec l

! FP&L L Maria L acal TP Tmg Mgr Dennis L. Fadden .SL Services Mgr L -Jo Magennis Corp Tmg Assessment Spec -

l' Tom Bolander SL~ Exam Development i

' Steve McGarry TP Maint Tmg Supv Southem Nuclear (SNC)

- John C. Lewis . HT LTmg & EP Mgr Bill Oldfield .FA' Nuc Ops Tm Supv Steve Grantham .HT Ops Tmg Supv

. Scott Fulmer -FA Mgr Tmg & EP

'Joel Deavers FA Sr Pit Inst Bob Brown VG Tmg Mgr

- Dan Scukanec - VG Ops Trng Supv i

i r

O A

Virainia Power Steve Crawford NA Sr inst Nuc Harold McCallum SR Supv Ops Tmg TVA .

Dick Driscoll SQ 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 ll Sr. Examiner George Hopper R 11 Sr. Examiner Ron Aiello R ll Sr. Examiner Charlie Payne R ll Sr. Examiner William Travers NRC Executive Dir. Ops. l R. M. Gallo NRR Br. Ch. OL )

Bruce Mallett R 11 Div. Dir. Reactor Safety l

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e FY 99 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 l

l i

RO SRO-l SRO-U TOTAL l l

l Date Plant Chief Pass # Pass # Pass # Pass # l 1

9/28/98 Sequoyah GTH 4 4 4 4 1 10/5/98 Harris RFA 2 2 5 5 7 7 11/30/98 Oconee GTH 2 2 5 5 7 7 l l 11/30/98 St Lucie & RSB 6 3 9 l

12/14/98 1/25/99 McGuire & DCP 6 3 2 11 2/8/99 1

I 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 l

9/13/99 136 RESULTS TO DATE 4 4 5 5 9 9 18 18 l

100 100 100 100 l

No initial exams scheduled for: Brunswick, North Anna and Vogtle FY 00 region 11 write part of Summer & Hatch l

{-

a

,o FY 00 INITIAL EXAM SCHEDULE AND RESULTS .

December 14,1998 RO SRO-l SRO-U TOTAL i Dcto Plant . Chief Pass # Pass # Pass # Pass 0

." 9/27/99 Summer GTH 6 6

region ll write 10/18/99 Hatch DCP 10 2 12 region II write

)- 12/13/99 Vogtle RSB 3 5 2 10 2/14/00 Brunswick 80 DCP 12 3 15 2/28/00 03/"/00 Oconee ? 10 704/10/00 Harris (mayb. moo) 10 705/03/00 St. Lucie GTH 6 5 11 705/*o/00 B. Ferry 6 3 3 12 i i

705/03/00 McGuire 4 8 12 706/07/00Farley RSB 10 2 12 707/26/00 Crystal River RFA 3 3 3 9 l region 11 write?

708/"/00 Sequoyah 4 2 2 8 709/04/00 Surry? 10 )

709/11/00 North Anna . 12 0 0 42 0 46 0 27 0 149

'?' designates tentative No initial exams scheduled for: Catawba Robinson Turkey Point Watts Bar J

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l l Operator Licensing

l Issues -

Region II -

j Training Managers' Conference j November 5,1998 e

i Robert M. Gallo, Chief Operator-Licensing and Human Performance Branch

)

l OPERATOR LICENSING ISSUES j o Part 55 Rulemakings _

Status l

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Schedule i

o

! Final Revision 8 of NUREG-1021 l

l o Examination Quality and Results i

l o

Generic Fundamentals Exa'm

o Requal inspections (IP-710.01) 3 1

L o Recent Information Notices Exam Integrity (IN 98-15) j -

Sampling Plans (IN 98-28?

) -

Eligibility (IN 98-37) c i

t E

RECENT LESSONS LEARNED .

I by

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Charlie Payne .

Southeastern Training Manager's Conference November 5,1998 l

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. _ . _ _ _._.m _____a ._.__....__.-s-____ ____..__.__-.-_-_.-__-_m m _ __ .___m. -_m _m_ _

.j PO_LICY CLARIFICATIONS j O 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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POLICY CLARIFICATIONS ,

O in general, license class sizes of greater than B_ candidates will be scheduled for 2 weeks as follows:

1S' exam week off-waek for documentation of week 1 performance 2"d exam week I

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(, . _ . . . . . . . . . . . . . . ...

POLICY CLARIFICATIONS 9 Examination submittals - 2 copies of draft and final exams (written, JPMs, and simulator i scenarios). Electronic copy is also desired.

9 Written exams submittals will be reviewed by following a sampling process. When criteria are met, review will be stopped and licensee called.

Criteria - 10 unacceptable questions out of 30 questions sampled ,

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t. _ _ - - - - _ - _ _ _ _ _ _ - - - _ _ . _ - - - - - _ - - _ _ _ _ _ _ _ - - - - - _ _ - - _ _ _ - - - - - _ _ _ _ - _ _ _ - - - _ - . - - - - -

RECENT LESSONS LEARNED SRO-only Questions i

intended to sample those K/As specific to SRO duties a'above and beyond those <

needed by an RO).

i purpose is to meet the requirements of 10 CFR 55.43(b) (items (1) - (7)). ,

i K/A catalog cross-references K/As to associated portions of 10 CFR 55.

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m. _ .._.__ ___________ _ _.___________ _ ____ _ ____ _ _ ______.__ _ _ _ _ ____._ _ _ _ _____ _ _ ____ _ _

2.0 GENERIC KNOWLEDGES AND ABILITIES 1

2.1 Conduct of Operations 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 plant 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 R O 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)

IMPORTANCE RO 2.3 SRO 3.4 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 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 l 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 l

2-1 N:JREG - 112 3 , Rev. 2 l

2.1 Conduct of Operations (continued) 1 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status. l (CFR: 45.12)  !

IMPORTANCE R O 3.0 SRO 3.0 t.

{

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.

(CFR: 45.10 / 45.13)

IMPORTANCE RO 3.1 SRO 3.2 2.1.22 Ability to determine Mode of Operation.

0 (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) I

IMPORTANCE RO 3.9 SRO 4.0 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 45.12 / 45.13)

IMPORTANCE 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. ,

l (CFR: 41.10 / 43.5 /45.12)

IMPORTANCE RO 2.8 SRO 3.1 2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical /

high temperature / high pressure / caustic / chlorine / oxygen and hydrogen).

l (CFR: 41.10 / 45.12) l IMPORTANCE RO 2.2 SRO 2.6 f

2-3' NURIG-1123, Rev. 2 l t 4

_. __ . __ _ _ _ _ . _ _ - . ~ . . _ - ._ _ _ . _ . . _

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 R O 3.3 SRO 3.5 l

2.4.33 ' Knowledge of the process used track inoperable alarms.

(CFR: 41.10 /43.5 / 45.13)

IMPORTANCE RO 2.4 SRO 2.8 1

2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications.

(CFR: 43.5 / 45.13)

IMPORTANCE 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.

! (CFR: 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5 1

2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

(CFR: 43.5) l

'IMPORTANCE RO 2.0 SRO 2.8 l 2.4.37 Knowledge of the lines of authority during an emergency.

(CFR

45.13)

IMPORTANCE ' R O 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

'!.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 R O 2.3 SRO 4.1 NUREG-1123, Rev. 2 2-14 l

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RECENT LE_SSONS LEARNED SRO-only Questions (Cont'd?

.. SRO-only questions will be based on following categories: A.2, G2.1, G2.2, G2.3, and G2.4.

differences between SRO and RO outlines shifts only 11 K/As from Tier 2 to Tiers 1 & 3. I

=> Other 14 flexible.

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1 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 j

]* 3 Mf M tg W es Emergency &

Nk b# 9Ejh EN M- -

20 33E Mi whim w an Abnormal 2 I 20 0 kW si hMi V 17

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[h... g y I

g Evolutions Tier ps 43 +7 j Totals E sn tige!

n 6 Mid s= 44; 4:Pt ~5C gg :gg -eg m.~. _

gr gn 3 23 2.

2 13 Plant Systems 3 4 Tier 40 _ fg Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 + 't 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 l associated outline.

The shaded areas are not applicable to the category / tier.

NUREG-1021 10 of 39 Interim Rev. 8, January 1997 l

l i

d ES-401 BWR RO Examination Outline Form ES-401-2 I

Facility: Date of Exam: Exam Level:

K/A Category Points i 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 1.

Emergency &

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gg h h[

g gp 13 Abnormal ~ -- ->e N O 19 Plant Evolutions 3

p h ( h!j s[ hh m

4 Tier . m} ;m ag/ ;@:.

g  ;.ng; 4 36 Totals @d % k@dl$$1 1

28 l

2. I Plant 39 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.

l The shaded areas are not applicable to the category / tier. -

NUREG-1021 16 of 39 Interim Rev. 8, January 1997 l

RE_C_ENT LESSONS 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 c uestion resources to accomplish the alan. .

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Sampling Criteria (Cont'd}

each topic in each tier & group should be .

sampled at Idast once unless insufficient question's exist to do this. If all topics have been sampled once and other questions need to be selected, the process should be systematic and unbiased.

final sample plan should have a fairly even balance across all Ks & As. ,

8

RE_C_ENT LESSONS LEARNED l i

Samaling Criteria (Cont'd) t up to 25 questions from 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-specific priorities may be identi"ied with CE concurrence (K/A value may be < 2.5 with sufficient justification).

9 i

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 contro s of their facility. As a minimum,5 signi"icant control manipulations which a fect reactivity or power level.

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s 10

OTHER

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Record Keeping (Cont'd}

this informatipn should be retained and available for inspection from time of license aaplication to license expiration.

i e

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_ - - - - - - _ _ - _ _ - _ _--- __--- _ - _ - - _ L

-l CTHER -

. I Requal Control Manipulations if have 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 w~ould be team oriented. j i

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OTHER Requal Control Manipulations (Cont'd}

credit for accomplishment should only be given for active participation in the manipulation.

NOTE: control manipulations are not synonymous with reactivity manipulations.

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Examination Communications t l 4

l l Examination Development i

i Coordination i

l By j Ronald F. Aiello i

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l Facility Suggested improvements i

l 1. The exam development team and lead j examiner should meet at the beginning of j the deve oament arocess to estab isl j common grounds for the development and l execution of the examination:

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• Changes and interpretations to the i NUREG.

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• Scoae of the exam development and administration process.

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• Lessons learned from the last exam ac ministered.

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i-4 3

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! 2. Move due cates for t1e outline and the

! exam back to 90 and 60 days prior to arep week. This will provide more time for examination review ay the examiner (s).

4 l 3. SSNTA continue with efforts to i

standardize document formats for j examination too s (JPMs and scenarios).

4. Examiners maintain a list of who-(plant) ,

does the exam process 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 improve.

5. T1e arincipal and the utility re3resentative slou c mee: early to establish a working relationship and exaectations. If possible tais should inc ude sam ales of c uestions, JPMs, etc.

[.

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6. The exam shou d lave no outstandinc j issues /c uestions that arise and need j repair at the ast minute. These issues

! slou d all have been identified by the prep l week, to allow time to make changes tlat j meet all the criteria.

7. The chief examiner should exalain up I front all the forms in 1021 that need to be com aleted.

i

8.

i 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 shou d veri"y the ability to communicate via all channels (inclucing e-mail). W1en we converted to Lotus Notes, the faci ity was suddenly unable to senc e-mail to lis C1ief Examiner. This i

i became somewhat of a hindrance anc

)

slou d be~ avoided if aossible.

l 10. It would be helafulif the Chief Examiner j could provide his schedu e to the Facility l Rep. This includes providing uadates for any changes to the Chief Examiner's j schedule along the way. The facility rep l needs to be aware of w1en the Chief j Examiner is available to assist in exam j 3 reparation activities.

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11. A face-to-face meeting should be promptly scheduled in order for the Chief to 1 communicate his expectations to the j Facility Re3. The face-to-face j rec uirement cou d be waived if the Chief

! and the Facility Rea have previously worked together anc the Facility Rea is

con"icent tlat le/sle understands the j Chief's exaectations. In any case, a i

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l l conference call would be the minimum to j satisfy this important first ste 3.

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i 12. The Chief and the Facility Rep should l work together to estab is, a firm schec ule j for the exam week (s). This will ensure the j

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most efficient schedule is developed (with respect to crew composition and l personnel movement) to minimize the j amount of exam material required.

i i 13. The Chief Examiner and Utility Rep MUST remain fixed during the entire 180 day period. Handing off the resaonsibility is both disru ative and destructive to communication. The exaectations of the chief examiner must be defined / communicated early.

14. The " time ine" must be enhanced to identi"y specific times and dates for communication / working meetings between

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the examiner and the utility rep. These

meetings shou d be " face to face" to

! assure expectations are understood, and i being met, early on.

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l j 15. If an examiner and a utility rea have not

{ worked together before, t;1e timeline for i " deliverables" must be expanded.

! Working meetings (face to face) must be l established for the examiner to review 5-10 questions,1 scenario,1 jpm,5 jpm knowledge questions,5 admin questions,

)i etc. to assure tlat the standards and i expectations are clear early in the process l and that the utility can produce a aroduct i

that meets t1e expectation.

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16. 398 and 396 forms need to be availab e electronically. We took the time to develoa an electronic version ourselves but I wou d arefer tlat t1e e ectronic master coales came directly from the NRC

7.---

l' l so t1at we have more conficence that

! everything is exact y the same. We wou d i all benefit from this improvement.

i 17. =A face to face wor <ing meeting of eight (8) l to twe ve (12) 1ours, ap aroximately two j (2) weeks before ':he thirty (30? day l submittal must be established to resolve any issues BEFORE the submittal. The j exam materials should be reviewed, line l by line, at this meeting to communicate all

[ changes necessary.

! 18. Exaectations must be established early so i

that the utility clearly understands tie rules and the examiners exaectations. Smal samales of deve oament must be reviewed early to assure exaectations are being met.

A " ace to face meeting, prior to t7e 30 day submittal, to reso ve any/all issues must be scleduled such that adec uate time (suggest 2 wee <s) is availab e to reso ve

comments before the 30 day limit. No one wants to see 30 c uestions reviewed anc t7e exam rejected. Saending ~24 hours in 3-4 face to face meetings is a smal / smart

,arice to pay to avoid hundreds of hours of re-development, the emotiona stress on candidates when the exam must ae rescheduled and 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 aast and needs to be either accepted by the NRC as a standard or oatimum format, or mocified, or rejected. The JPMs we

submitted to you were in the format and j level of cetail you had found acceatable in l t1e aast, and we were surarisec to finc that j'

they needed significant last-minute rework (adcitiona leve o' detail).

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20. Mayae Chief Examiners could send some cooies of good written c uestions, JPMs, and JPM questions u a front that could hela a new developer survive the exam writing process and see where you as an

examiner are coming from.

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j Facility General Comments l 1. The limited number of NRC license

! examiners puts the Region and the sites at

{ a disadvantage with resaect to getting

{ timely interclange. If the examiner is out l of the office on a trip for several weeks, the j time you have to provide the licensee with feedbac< is very limited and results in a real strugg e to ensure a quality exam.

j T1e limited resources and interaction time j increases t1e risk of lower quality.

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) 2. Region 11 sxaminers have been very i arompt in getting back to us when we lave l a c uestion even though you may 3e at a remote ocation.

l 3. T1e cuaity of the communications has j been good. A of the examiners tlat l l have ta ked to have been t1orough, arecise l and lave performed listening checks to i

i j verify that t1e correct messages were sent j anc received. I wou d however, i<e to see i more communications by e-mail where j aapropriate. That would hela ensure t1e l clarity of t7e communications even more.

L l 4. Wit, resaect to the exam specifically; there l were a number of changes that were made l and we had to transmit those by expensive j 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 j as dol ars.

l 5. During my first face-to-face meeting with

! t1e C1ief Examiner (to review draft exam

materia ?, I gained much-needed insig ht j into lis exaectations. This alleviated much j stress on my part and, from then on, the ,

i arocess went much more smoothly. The l C1ief was very helpful during subsec uent j telephone conversations and our seconc j l

meeting in Atlanta. He was very easy to wor < with and very understanding concerning my inexperience in this process. His patient guidance was the key

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-to our success in tais endeavor. Next time, with all we've learned, we'l 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 questions he was submitting to us were th'e c uality of c uestions that were acceptable to tie NRC. We reviewed his work, made technical corrections and assumed that the c uestions would be acceatec by the NRC.

I 1ad very little communication with the NRC on the subject of the written exam and a great deal of communication on the subject of t7e oaerating exam. W7en the submittal was final y made, the focus went

to the written exam anc most o" the communication was mace 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 aainful process and could have been avoided had I not put so much fait, in t1e contractor's exam writing exaerience and communicated more on the subject of t1e written exam with the chief. We had a 100% pass rate on the exam, but the exam re3 ort was brutal in the area of the written

. exam.

7. Know the c,1ief examiners expectations from the beginning (prior to any development).

8. Never assume you know what you're doing

- the chief is just a ahone cal away.

9. It's better to deliver materia anc review it in person rather tlan over the pione. I alan for four or five trias aetween the start of

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l develoament and arep week. It may

! sound li<e overki I, but it wor <s (It's a so

{ safer in the area of security).  !

10. Submit material early (especia y the l c written). I like to have the written exam a I

! done dea prior to the actual submittal date.

i l 11. You can never talk to the Chief Examiner too much. During t7e process, I talk to lim  !

more than I talk to my mother. l

12. The bottom line is that frequent i communication, aersonal contact, and

~early submittal of materials is the <ey to a l successful NRC exam.

13. ALL aroblems/ changes must 3e reso ved at t1e evel of the examiner and the utility rep. In no case should aroblems/ changes be reportec/esca ated to senior management of the utility or NRC unless

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c j both the examiner and the utility rep are at i l an absolute, and mutually agreed, impasse.

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{ 14. We often felt that we were working in the .

! dark, writing questions on topics you may l l not want (as we were waiting for comment l l on our skyscrapers), possibly wasting i

resources, but seeing no other option to

! meet our required cast-in-stone deadlines.

i l 15. It's difficult to keep JPMs short and plausible at the same time.

l 16. W1at is a good " admin JPM", especially for i ROs?

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The unit is operating at 20% power with all systems in automatic. ' Bank 'D' control rods )

l are at 120 steps. Control Bank 'C' rod H6 drops to the bottom of the core. No rod -

- control urgent failure alarms occur.

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Where will thermal power and RCS Tavg stabilize in response to the dropped rod without any operator action?

l- 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.

l B. ' Reactor thermal power will be lower than prior to the dropped rod: RCS Tavg l will be within l'F of the temperature prior to the dropped rod.

l l _ 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 thermsl 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.

l Answer:

'C Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg l-will be within l'F of the temperature pdor to the dropped rod.

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., Reference Page SRO Question 10 RO Question 10 SRO Tier / Group 1/1 RO Tier / Group 112 SRO Importance 3.7 RO Importance 3.2 10CFR55.43(b) 10CFR55.41 8 Item Addressed item Addressed EA Number 000003AKl.01 XA 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 A OP-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. l (C) CORRECT - Power will initially decrease duTto 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 value.

(D) Select if he recognizes that power was restored due to the previous decrease in temperature, but does not recognize that rods will step out to restore temperature and t -

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wa.; 44. wa .u4A A E hM h e .t.4 6an 4 4 h sa -he.g ss A &&A4e--44 4 JW4, -4 4 A A%h+b.'**3A***A'**'*A*'""E' "" * * * ' ' -'

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INITIAL EXAMINATIONS QUESTIONS AND ANSWERS i i

TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 t

l RICK BALDWIN GEORGE HOPPER i

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initial V/ritten Examinations i

Reference:

All written examinations are written IAY/ ,

l ES-401, " Preparation of Site-Specific 1

V/ritten 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

! V/ritten Examination Quality Assurance

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. Checkoff Sheet."

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OBJECTIVES  ;

O BEi I ER EXAMINATION PRODUCT .

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e LESS NRC/ FACILITY REWORK t

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3 SHARED EXPECTATIONS 3 I 1

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SESSION OBJECTIVE

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To review validity concepts affecting the NRC .

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written examination for the purpose of

Instructing licensee personnel toward 4

construction of more VALID and CONSISTENT NRC license examinations.

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COVERAGE i

9 3 Levels of Validity l 9 3 Levels of Knowledge I

i e D.iscrimination, Sampling i

O Psychometrics i 5

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l VALIDITY -

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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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3 LEVELS OFVALIDITY 4

O Content i

O Operational 4 Discriminant t

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i CONTENT VALIDITY f

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Addresses K/A coverage and sampling plan '

coverage.

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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?

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:

O The cut score is the performance level that

! we use for making a pass / fail decision 80 percent.

O The exam must be written at a level of difficulty that intends to discriminate at

! the 80 percent level.

9 The question, its stem and distractor, interplay, by DESIGN, at least 80 percent of the candidates taking the exam should answer the item correctly. ,

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VALIDITY

SUMMARY

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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 j comprehension or analysis level vice simple memory. Items that measure problem solving, prediction, analysis

which are essential to job performance.

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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 e Analysis, Application, Synthesis I

e Comprehension G Fundamental (simple memory) i i

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LEVEL OF KNOWLEDGE  !

O Bloom's Taxonomy, NRC Reference Benchmark to classify levels of knowledge.

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9 Bloom's Taxonomy, a classification scheme that classifies items by depth of ,

mental performance required to answer '

the items.  ;

e Bloom's Taxonomy, can be applied to written, scenarios or JPM questions.

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t LEVELS LEVEL 1

Fundamental, using simple mental processes, recall or recognition of discrete bits of information. ,

t i.e. setpoints, def. .t.ini ions, or specif.ic facts.

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LEVEL 2 Comprehension, involves understanding material through relating it to its own parts or other material:

i.e. including-rephrasing information in different words, recognizing relationships l

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, including consequences or implications.

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LEVEL 3 l

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 i parts so that the whole, and the sum can be j used to: predict and event or outcome, solve .

a problem or create something new.

i.e. using knowledge to solve problems.

DETERMINANTS OF DISCRIMINATION t

9 Level of examination knowledge e Level of examination difficulty e Passing Score i

O ltem bank use 18 i

NATURE OF EXAMINATIONS AND TESTS O TESTS are samples of PERFORMANCE O Infer overall performance based on a sample O Sample must be broad-based to make confident inference O Sample must NOT be fully predictable or inferences cannot be made on untested areas.

O items MUST discriminate otherwise it has little or NO value.

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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 j

8. Backwards logic 20

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006 Emergency Core.C,ooling System-/ JPM 136 Recovery From Safetylnjection j .and Solid Water Conditions'/. e a + -

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. e FR-C.1, " Response to Inadequate Core Cooling," is being implemented. ,

Core exit TCs are 720*F and increasing. '

L At this point FR-C.1 directs the crew to depressurize intact steam generators.  !

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?

References Allowed? YES X NO L

Answer:

a'.') To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.

i Reference-i KA: 006G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs. '

OPL271C398 pg 1215 l l

Applicant Response: SAT _.UNSAT 7  :

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STEP

" ACTIO N/EXP INADEOUATE ECTED CORE NOTE COO RESP LING .

c ONSE leBlo s kinglo s tha w the co ste nden 1920 amlinepr RESP v

nser psig willpr es sur Re. 8 a

Afterthelo occ urif w ste av ilable ev n e Sia eafor ste s

taninadvsoonaspr ONSENOTOBT AINED amlinepr S/G the highst m dump. erte n tM u dr depr ea mpr ess e SIV clo srizerpr \

in op tolesess ess sureaessureis 14 adequa tes tha uriza ten ureuraSisign a lis n 10 at r teis c ndkeep DEP coreco % the x exceeded.blo ked, mi RCS RESSU o ling [25%m a AD V mimu an pressurRIZE co rate ste m

s cSt e toleinta nditio n. ). Thisis ayc m e

a. W les s tha /Gs to acc aus eptablee S/G a lin ois nlatio

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will HENRCS n 125 red ce and enarrow s tha psig:u THEN n 1920pressur xpected ra PERF psig e forthisngelev e ls to ORM

1) B LOC the follo w ng: i St. Klo w ste

2) C / amlinepr ISOHECK essure EN AB L/SI STEAMLINEP

{M-4A,A4]LEpermis BLOCKRATEIS s

e RESS i DUMP v LIT. OL atm stea axim m to c um a r te. ondenser

b. D U UMP SING steam IF lo c s a c lco inta tS/Gatm axim atmo um rate necess ary, ntrolof spheric THEN atmo e DISP r lief (s).

U spheric SIN ATCH e (S GEA person tep co S/G PO nl r lief (s)is ntnu RVs.1-2 Lo e to du edonn cla Co mp ste x ntro lof am e tpag

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.~026, Containment Spray System /.JPM # 57AP Respond to High Containment

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_PressuresPJace RHR Sprayin Service? .

Ouestion 2: ,

Given the following plant conditions:

Unit I has tripped from 100% power due to a LOCA.  !

Containment pressure is 3.0 psid 4 Transfer of Containment Spray pump suction to the containment sump is being performed in ,

accordance with ES-1.3, Transfer to RHR Conte a ment Sump.

a.) Why must both CS pumps be placed in PULL-70-lock while transferring suction to the containment sump?

b.) What does placing both CS pumps in PL1L-TO-Lock prevent?  ;

References Allowed? YES X NO  !

Answer:

a.) While shifting to the contaimaent sump, both the RWST and the containment sump suction valves to the CS pumps will be closed a' 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 l

OPL271C024 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 Examiner Sheet A'.1:' Shift Staffing '

~. i 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 i satisfactory performance in the licensed operator requalification training program.

He is informed that he is needed to join a shift crew in 3 days to fill in for a '

vacationing Unit OATC.

I Can the RO fillin for the vacationing RO? Why or why not?  %

References Allowed? YES_Z_.NO -

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

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l' License Applicant Administrative Walkthrough Examination--NRC-1 l Examiner Sheet-A 1: JShift Staffing 2 Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour

~ shifts in the control room as the OATC during the past month under the direction of a shift RO.

What additional requirements must be met by the RO before he may fill in for the

. vacationing RO?  :

References Allowed? YES1NO l 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 l K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT UNSAT t

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Given.the following conditions:

i l 1. The reactor has experienced a Steam Generator Tube Rupture.

t 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?

l 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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l i l Reactor Operator Examination ,

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65. Given the following conditions:  :

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l. The reactor has experienced a Steam Generator Tube Rupture. .j All systems responded as expected. l The performance of EOP-04 is in progress.-

One steam generator has been isolated.

l-RCS cooldown using natural circulation is in progress.  ;

Which ONE of the followinF escribes d the concem associated with the affected SG pressure prior .

to placing the RCS on SDC7  : .,

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a. The SG pressure would be too low due to excessive cooldown causing RCS water to enter l- the SG and reducing RCS inventory.  ;

.The SG pressure would be slightly less than RCS pressure causing water to enter the RCS i b.

resulting in a dilution.

t c; The SG temperature would be too high to allow for SG depressurization.

1 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 charging pump on each emergency bus 5 minutes after it is energized by the diesel.

d. One charging pump is automatically started onto each emergency bus immediately after it is energized by the diesel. -

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5 b

. . ... . .. -. . . . . -.=- .- - . . - . _ - - _ . - _ _ _ _ . .- ..

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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 ,

i, electrical lineup and all equipment is operable.

l l a. Only one charging pump is automatically started on each emergency bus 5 minutes aner it ,

! is energized bythe diesel. l

. b.. All charging pumps are automatically started immediately after their respective bus is ,

energized by the diesel, j l c. All charging pumps are automatically started 5 minutes after their respective buses are energized by the diesel.

l .d. Only one charging pump is automatically started 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 RWT,

d. continue to run and become gas bound.

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Reactor Operator Examination 1

27. Charging pumps are running on Unit I and an SIAS is present. (Assume no operator action) l Which ONE of the following lists the charging purap response when the BAM tanks are emptied?

- The charging pumps will:

a. ' trip on thermal overload.

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b. , trip on low suction pressure. I

c. automatically align to the RWT.

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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Reactor Operator Exammation 2- 59.. ! Given the following conditions:

. Unit 1 CEDM fan HVE-21 A is in AUTO after START.

- Unit 1 CEDM fan HVE-21B is in AUTO after STOP.

' Unit 1 CEDM fan HVE-21 A trips on overcurrent.

' Which ONE of the following lists the signals required by the logic needed to start HVE-21B?

a. The trip signal from HVE-21 A.

b. "Ihe trip signal from HVE-21 A concurrent with a low flow signal,

c. A low flow signal.

d. The trip signal from HVE-21 A concurrent with a low flow signal and air inlet temperature signal to the cooling coils is greater than 100

• F.

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13. Given the following plant conditions:

. Unit 1 was at 73% power

. A reactor trip / safety injection on low steam line pressure 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 9

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 fiow is less than 440 gpm.

b. Incorrect because RCS temperature is 325'F (core exit T/Cs less than 1200*F).

c. Incorrect because containment pressure is less tnan 12.0 psid.

d. Incorrect because RCS temoerature is 325'F (T-cold is greater than 250*F).

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.3 F

? . RCS pressure is.225'psig i%SO #

. All S/G pressures are DECREASING slowly

• 2 and #3 S/G levels are 5% NR and DECREASING slowly

. #13/G levelis 6% NR, and INCREASING slowly

. c4 S/G levelis STEADY at 2% NR Total feedwatepflow is 340 gpm

. PZR levet is'JT% and INCREASING

. RCS T-cold temperature is 325'F and DECREASING slowly

. Containment pressure is 5 psid and INCREASING slowly y At tnis point, which ONE of the following Cntical Safety Functions is the MOST degraded?

a. Heat Sink

b. Core Cooling

c. Containment

d. Pressurized Thermal Shock Answer: A K/A: 000040K101 [4.1/4.4J

Reference:

E-0, Foldout Page Oojective: OPL271C3 A B.1 Level: Analysis ,

a t

Source: 000040K101 001 History: Stem and distracters a and d modified (7/7/98)

Note: Provide PTS curve with this question.

Justt5:ation:

a. Corre:t answer because all S/G ieve!s are Jess tnan 10% NR and total feeowater fiow is less than 440 gpm.

b. Incorrect because RCS temperature is 325'F (core exit T/Cs less tnan 1233*:).

1

c. Incorrect because containment pressure is less inan 12.0 psid.

d incorrect because RCS temperature is 325'? (T-Eoid is greater inan 250*F)

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20. Given the following plant conditions:

. The control room has been evacuated due to a fire

. All controis have been transferred per AOP-C.04

. MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing Which ONE of the following describes the response of the auxiliary feedwater system?

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 generatof 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: 000068A1C2 001 Histcry: Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distracters a, b, c, and d reordered (7/22/98). Distracter be restructured (7/29/98)

Note: Selected from% exam bank with minor modification of text 4

V h-

\ 4

/

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 1B-B are injecting into the steam generators

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing Q s'6 wk % uS\ U ek8e014 sqo-C.O{

Which ONE of the following describes thezeccen _ v. i;m a..,y ,'eed,Mestem?

~

a. The TDAFW pump will automatically restan whan 2/4 steam geneiscrs reach low low level, e ~ h k -"' M OioN u i g e I, - 2 '/ .

(Cow

b. The MDAFW pump level control valves will automatically control steam generator ,

, levels at 33%.

The MDAFW pump level control valves will have to be manually adjusted using the Manual Output Adjust in the L-381 cabinet.

/W

~ ?[,,.g[

y

d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by thro"J:ng the manual valves at the LCVs.

, got g jes Answer; B K/A' 00005BA102 [4.3 / 4.5]

Reference:

AOP-C.04, page 11 Objective: OPL271C423, B.4 Level: Comprehension Source: 000058A102 001 History: 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 (7/29/98) ,

Note: Selected fromMexam bank with minor modification of text l

I i

l

i

23. Given the following plant conditions:

. FR-C.1, Inadequate Core Cooling", has been entered due to a RED path on Core Cooling l

. Core exit temperatures (TCs) are 1250'F and increasing

. NO Feedwater / Aux Feedwater is available

. At step 12, the CRO checks the S/G NR levels and reports all are <10%.

As the SRO you should: (Select ONE of the following)

a. Go to FR-H.1, ' Loss of Secondary Heat Sink".

b. Depressurize allintact S/Gs to atmospheric pressure to dump accumulators.

c. Start RCPs one at a time, until core exit TCs are less than 1200'F. r

d. Prepare to initiate RCS Feed and Bleed if WR levelin any 2 S/Gs is less than 60%

Answer: C K/A: 000074K307 .[4.0/4.4]

Reference:

FR-C.1, pages 10 & 17 Objective: OPL271C398 Level: Comprehension Source: MExam Bank 101. 000074K307 001 History: Used on HLC 9807 practice exam Distracters b and c reordered Note: Selected frorMexam bank without modification of text l

I l

I l

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A. INADEQUATE CORE COOLING FR-C.1 y Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Use of a Fautted or Ruptured S/G during performance of the following steps may compound the emergency situation. When NO Intact S/Gs are available, a Faulted or Ruptured S/G may be used. ~

12. MAINTAIN Intact S/G narrow range  :

levels:

a. Greater than 10% [25*4 ADV] a. MAINTAIN total feed flow greater than 440 gpm UNTillevel greater than 10*4 {25*4 ADV]

in at least one S/G.

IF total feed flow greater than 440 gpm can NOT be established, THEN PERFORM theiollowing:

1) CONTINUE attempts to establish heat sink in at least one S/G.

, 2) GO TO Note prior to Step 21.

b. Between 10% {25*4 ADV] and 50%

Page 10 of 19

F -C.1 g INADEQUATE CORE COOLING STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 NOTE RCP darnage due to absence or loss of norrnal support conditions is an acceptable  ;

consequence in this procedure. l

21. CHECK if RCPs should be started:

O

a. , CHECK core exit T/Cs a. GO TO Step 22.

greater than 1200*F.

b. CHECK if idle RCS loop available: b. PERFORM the following:

1) S/G narrow range level a) OPEN pressurizer PORVs and block l 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, l THEN i OPEN reactor vessel nead vents:

. FSV-66-394

. 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.

Page 17 of 19

o s

23. Given tne following plant conditions:

. FR-C.1, Inadequate Core Cooling", has been entered due to a RED path on Core Cooling

- . Core exit temperatures (TCs) are 1250*F and increasing

. NO Feedwater / Aux Feedwater is available

. At step 12,the CRO checks the S/G NR levels and reports all are <10%

As the SRO you should: (Select ONE of the following)

a. Go to FR-H.1,

• Loss of Secondary Heat Sink".

b. Depressurize allintact S/Gs to atmospheric pressure to dump accumulators.

c. Stan RCPs one at a time, until core exit TCs are less than 1200*F. #

W PortN1.s ar e 3 L o d \/M,w.5

d. Brepare.so4nitiaNOC raJ ,n JGeed-4WR4eveHn-any2-S/Gs4s-4ess4harHK)b.

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 g yph Nl$$5 /

1 l

1 l

l

49. Given the following plant conditions:

. Reactor power is at 20% during a unit shutdown  !

. Intermediate Range N-36 failed high i

. Operators placed the level tap 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:

AOP-1.01, page 10 ES-0.1, page 13 Objective: OPL271 C352, B.4 Level: Comprehension 1

Source: 015000K407 001 1

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 j l

1

- 1

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49. Given the following plant condrtions: ,

• Reactor power is at 20% during a unit shutdown \

. intermediate Range N.-36 failed high __

\

N 6pera:orsytacec me :cecgypass-switettfor-hp3mo the-Dypamd'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 F-10 setpoint.

b. Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range chantv;l, so the unit must be manually tripped prior to Mode 2 entry.

c Poth 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 setooint: 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: OPL271C352. B.4 l Level: Comprehension i Source: 015000K407 001 History: Not used on 9/97 or 5/98 NRC exams. Not used on practice exam.

Distracters c and d reordered Note: Selected fromMexam bank without modification of text

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35. Given the foffowing plant co_nditions:

, . Uni:2 is operating at 29% power in accordance with 0-GO-6, Power Reduction From 30% Reactor Power to Hot Standby

'.' . Uni' 2 will be going to Cold Shutdown for maintenance

. Intermediate Range N-36 has just failed high Which ONE e, 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 LevelTrip switch in BYPASS.

c. Remove N 36 instrument power fuses. c'

d. Manually trip the reactor to prevent an automatic reactor trip.

Answer. B K/A: 000033X302 [3.6/3.9]

Reference:

AOP-LO1, page 10 & 13 Objective: OPL271C352 B.4 Level: Analysis Source: New question (Developed 7/1S/98) '.

' Justification:

a. Incorrect because manually restoring N-31 and N-32 to operation in the power range would aestroy the source rarige detectors. ,

b. Correct because placing the levet trip switch in BYPASS prevents high reactor trip when tne low power reactor trip signal is reinstated at the P-10 se point (10% power).

c. Incorrect because action does not bypass the trip signal

d. Incorrect because a manual reactor trip for the given conditions is not required. Placing N-35 level trip swrtch in BYPASS allows an orderly reactor shutdown.

l b

50. Given the following piant condrtions:

. Large Break LOCA is in progress

. 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.

b. Average value of all core exit thermocouples.

c. Hottest Reactor Coolant wide range Thot value.

4

d. Average value of five hottest core exit thermocouples.

Answer- D K/A 017000A402 [3.8 / 4.1)

Reference:

FR-0, page 3 OPL271C044, page 7, A.1.c Objective: OPL271 C044, B.1.b Level: Memory Source: 0'17000A402 001 History: Used on HLC 9809 practice exam Distracters a, b, c, and d reordered (7/22/98) i Note: Selected from xam bank without modification of text i

i l

50. Given the following plant condi: ions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig

. Exosensor indicates 259 superheat

. No RCPs are operating Which ONE of the following indications would the operator use along with RCS pressure to accurately substantiate core cooling?- , . , , , , ,,, I w.. -

_.n Y %:deiC;&l8ntiS5 N!NYl'fA~4 _,f)g,;;s,i) - ' W/W &

I T2; dot'~ (0!C W**

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 ,

y,., g p,,b' o#'wset W ~4 K/A 017000A402 [3.8 / 4.1) ~

/~~I2 - 6 . 2.-

Reference:

FR-0, page 3 OPL271C044, page 7. A.1.c Objective: OPL271C044 B.1.b Level: Memory Source: 017000A402 001 History: Ueed on HLC 9809 practice exam distracters a, b, c, and d reordered (7/22/98)

( Note: Selected from exam bank without modification of tex't i

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" 68, - Given the following plant conditions:

t

. Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a power increase to 100% in progress

. . Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm  ;

. Current time is 0100 f Which ONE of the following actions must be taken?

a.~ immediately stop the power increase.

1

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: ' i

< 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. '

i

' Answer: A

- K/A: 2.1.1 [3.7/3.B]

Reference:

. SSP-12.1, Page 31 ,

Objective: OPL271C209. B.2 Level: Comprehension i Source:. New question (Developed 7/20/98)

Note: Provide copy of Technical Specification 3.5.1.1 wnh the question (exam)

?- ,

Justification: i

a. Correct becausegConduct of Operation (SSP 12.1) restricts power increase  ;

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 e 2390 ppm boron places Unit 1 in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO.

b. Incorrect because power increase is not allowed 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 if loop 1 boron concentration not restored wnhin 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.

4

1 3 /4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULAT0gs l COLD LEG INJECTION ACCUMULATORS f

LIMITING CONDITION FOR OPERAT10r4 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:

a. The isolation valve open, A contained borated water volume of between 7615 and 8094 gallons of . a131 b.

borated water,

~~

. c. Between 2400 and 2700 ppm of boron,

d. A nitrogen cover-pressure of batween 600 and 683 psig, and R184

e. Power r: roved from isolation valve when RCS pressure is above 2000 psig.

APPLICABILITY: MODES 3, 2 ano 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 withinil.mits i 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.

i Dece:ber 27, 1991.

Amendment No. 113, 131, 133 3/4 5-1 g - UNIT 2 4

I L *

1. # l 0 'kl. 0'W hYf- i i*

BB. Given the fol!owing plant conditions: j

. Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a i powerincrease to 100% in progress j

= Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm  ;

j. . /,j

, . Currenttime is 0100 i

Which ONE of the following actions must be taken?  !

a. 'i mmediately stop the power increase. ,

b. Continue the power increase while restoring loop ,1 accumulator boron concentration to 2400 to 2700 ppm boronMh' ,1 hears h#vw 72 4 og Cf.

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 4 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 K/A: 2.1.1 [3.7/3.B]

Reference:

SSP-12.1, Page 31 .

Objective: OPL271C209, B.2 Level: Comprehension  ;

I Source: New question (Developed 7/20/98) j Note: Provide copy of Techni:al Specification 3.5/l.1 wr:h the question (exam)

J Justification:

a. Correct becaus onduct of Operation (SSP-12.1) restri::s power increase when in an LCO acuan ei o nours or less. RCS loop 1 a::umulator boron concentration of

^

2390 ppm boron places Unit 1 in a 1 hout 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 a ; ion statement.

c. incorrect be:ause if loop 1 boron concentration is net restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the Unit 1 must be in HOT standby by 0800. ]

d. incorrect because if loop 1 boron concentration not restored wrtnin 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.

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N

o 006; Emergency Core C,ooling Sy. stem +/. JPM 136 Recovery From Safetylnjection

.and So' lid Water Co'n'ditioris . J.s: :*V 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.

l 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 depassurize 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 LCCS accumulators and RHR pumps to inject water to the RCS.

Reference:

A.A: 006G4.18 ( 2.7 / 3.6 ) Knowledge of specific bases for EOPs.

OPL271C398 pg 12-15 Applicant Response: SAT UNSAT 4-4 i

l l

l . _ . _

FR-C.1 INADEQUATE CORE COOLING Rev. 8

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTA!NED 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 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 D!SPATCH personnel to dumo steam USING EA-1-2, Local Control of j

S/G PORVs.

t (Stec continued on next page.)

1 Page 13 of 19

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• .026 Gontainrnent Spray System /,JPM # 37AP Respond to High Containment '

_.PresiuW,& lace'RHR Spiray.in ServiceN, ~ .

w.

i Question 2:

Given the following plant conditions:

Unit I has tripped from 100% power due to a LOCA.

Contamment pressure is 3.0 psid j Tr'ansfer of Containment Spray pump suction to the containment sump is being performed in -

accordance with ES-1.3, Transfer to RHR Containment Sump. i L  ;

a.) Why must both CS pumps be placed in PULL-TO-1 ock while transfening suction to the containment sump?

b.) What does placing both CS pumps in PULL-TO-Lock prevent?

References Allowed? YES X NO Answer:

a.) While shifting to the containment sump, both the RWST and the containment sump suction -

valves to the CS pumlis 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 , ,

OPL271C024 pg 14-18, CCD NO:1-47W611-72-1. ES-1.3, pages Il-13, OPL271C388 pg 9 ,

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Applicant Response: SAT UNSAT I i

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License Applicant Administrative ~Walkthrough Examination--NRC-1

• I Examiner Sheet K.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 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? 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 i

"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-t t

e License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet Al:SShift Staffing ;

Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He hr.d a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shin crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of

. a shift RO.,

What additional requirements must be met by the RO before he may fill in for the vacationing RO? 3 References Allowed? YES _2L NO 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 i

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