ML20199F603

Submits Summary of 981105 Training Managers Conference.List of Attendees & Matl Used in Presentation Enclosed

ML20199F603
Person / Time
Site:	Mcguire, McGuire
Issue date:	12/23/1998
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Barron H DUKE POWER CO.
References
NUDOCS 9901210366
Download: ML20199F603 (84)

Text

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December 23, 1998 Duke Energy Corporation ATTN: Mr. H. B. Barron, Vice President, McGuire Site 12700 Hagers Ferry Road Huntersville, NC 28078-8985

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - MCGUIRE NUCLEAR STATION

Dear Mr. Barron:

This letter refers to the Training Managers' Conference conducted at the Richard B. Russell Building on November 5,1998. Representatives from all utilities in Region ll participated in the meeting.

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, 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 n Performance Branch 20007 to Division of Reactor Safety Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17

)

Enclosures:

As noted cc w/encls:

A. Orton, Operations Training Manager, McGuire Nuclear Station M. T. Cash, Regulatory _ Compliance G. A. Copp, Licensing 9901210366 981223 PDR ADOCK 05000369 P PDR g

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l DEC 2 Distribution w/encis:

PUBLIC B. Michael, DRS Ril:DRS I:DRS 60 BMICHAEL: TP EBLES 12/ // /98 Doc Name: 12//[/98

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Revised November 3,1998 TRAINING AND OPERATIONS MANAGERS' CONTERENCE

-U.S. Nuclear Regulatory Commission, Region II l Atlanta, Georgia j Meeting Agenda November 5,1998 \

Richard B. Russell Building Auditorium Thursday.11/5/98

'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 l 8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety  :

9:15 a.m. break l 9:45 a.m. ' Other Issues Robert M. Gallo, Chief l Operator Licensing Branch, NRR l

10:1$ a.m. Lessons Learned from Recent Exams Charlie Payne Sampling exam criteria 11:00 a.m. Examination Communications Ron Aiello Exam Development & Coordination 11:30 a.m. Lunch

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1:00 p.m. Written Exanunation 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 l i

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License Applicant Adminis,tr,ative Walkthrough Examination--NRC-1 ,

Examiner Sheet i

A.1:L Shift Staffing =

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

shifts in the control room as the OATC during the past month under the direction of  :

a shift RO.

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

f Answer: The RO must complete an additional 24 (40 - 16) hours of"under direction" on- l shift time that must include a plant tour and shift turnover. i

Reference:

SSP-12.1, Conduct of Operations, p. 61 and 62 l K/A 2.1.4 (2.3/3.4) l Applicant Response: SAT UNSAT l l

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t ATTENDEES AT THE NRC REGION 11 TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 l

Sid Crouch ATTSi l David Lane . Sonalysts, Inc. ,

' Bill Fitzpatrick INPO  ;

i CP&L .

Rick Gamer HR Supv Ops Tmg  !

William Noll - BK Ops Tmg Supv  !

Max Herrell- BK Tmg Mgr l

~ Scott Poteet . RB Exam Team Leader i Ralph Mullis BK- Ops Mgr l Tony Pearson BK OpsTmg t Anthony Williams RB Tmg Mgr .  !

Crystal River - FPC I 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 j Gabriel Washbum OC Req Team Leader Ronnie B. White, Jr MG- Tmg Mgr W. H. " Soap" Miller CT Site Tmg Mgr- i Paul Stovall OC Mgr Oper Tmg l Bentley Jones OC Tmg Mgr James Teofilak . CT , Ops Tmg Mgr Alan Orton MG Ops Tmg Mgr Richard Bugert Corp Ops Tmg Spec EEAL Maria Lacal TP Tmg Mgr Dennis L. Fadden SL Services Mgr .

Jo Magennis Corp Tmg Assessment Spec Tom Bolander SL Exam Development Steve McGarry TP Maint Tmg Supv

- S'outhem Nuclear (SNC)

John C. Lewis HT Tmg & EP Mgr Bill Oldfield FA Nuc Ops Tm Supv Steve Grantham HT. Ops Tmg Supv i Scott Fulmer FA Mgr Tmg & EP

' Joel Deavers FA Sr Pit Inst '

Bob Brown VG Tmg Mgr Dan Scukanec- VG Ops Tmg Supw l

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9 Virainia Power -

Steve Crawford NA Sr inst Nuc '

Harold McCallum SR Supv Ops Trng TVA '

Dick Driscoll SQ Tmg Mgr Walt Hunt SQ Ops Tmg Mgr Denny Campbell BF SRO Ops inst Jack Cox WB Tmg Mgr John Roden WB Ops Tmg Mgr Tom Wallace - WB Ops Supt j V. C. - Summer - SCE&G Al Koon SM Ops Trng Supv l NRC Particioants Tom Peebles R 11 Operator Lic. Br. Ch. ,

Rick Baldwin R 11 - Sr. Examiner George Hopper R 11 Sr. Examiner i 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 i t

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FY 99 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 RO SRO-l SRO-U TOTAL 4

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 l t

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 i

,. 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 16 l 5/24/99 Catawba & PMS 8 5 3 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 No initial exams scheduled for: Brunswick, North Anna and Vogtle FY 00 region 11 write part of Summer & Hatch

FY 00 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 RO SRO-l SRO-U TOTAL D0te Plant Chief Pass # Pass # Pass # Pass 0

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9/27/99 Summer GTH 6 6  :

region II write 10/18/99 Hatch DCP 10 2 12 I region II write I 12/13/99 Vo9tle RSB 3 5 2 10 f 2/14/00 Brunswick & DCP 12 3 15 2/28/00 03/"/00 Oconee ? 10

-704/10/00 Harris (m yt.1om 10 705/03/00 St. Lucie GTH 6 5 11 705/"/00 B. Ferry 6 3 3 12 705/03/00 McGuire 4 8 12 706/07/00Farley RSB 10 2 12 707/26/00 Crystal River RFA 3 3 3 9 region II 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 q, .

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i Operator Licensing issues .

Region II -

Training Managers' Conference l November 5,1998 Robert M. Gallo, Chief  ;

Operator-Licensing and Human Performance Branch 1

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l- OPERATOR LICENSING l ISSUES l

[ o Part 55 Rulemakings i -

Status Schedule o

Final Revision 8 of NUREG-1021 I

l o Examination Quality and Results

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o Generic Fundamentals Exam o

Requal Inspections i lP-710.01) o Recent Information Notices Exam Integrity (IN 98-15)

Sampling Plans (IN 98-28? l Eligibility (IN 98-37) l l

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l l RECENT LESSONS LEARNED ,

by l

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Charlie Payne Southeastern Training Manager's Conference

' November 5,1998 I

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POLLCY CLARIFICATIONS i

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.

Less stressful on candidates.

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PC1LICY CLARIFICATIONS l 9 In general, license class sizes of greater than

_8_ candidates will be scheduled for 2 weeks as '

follows:

1*' exam week -

off-week for documentation of week 1 performance

- 2nd gygg wggg f

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PC'LICY CLARIFICATIONS O Examination submittals - 2 copies of draft and final exams (written, JPMs, and simulator scenarios). El5ctronic copy is also desired.

e 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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RECENT LES_ SONS LEARNED l

SRO-only Questions intended to sample those K/As specific to SRO duties (above and beyond those needed by an RO).

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

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

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S 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) e 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) -

BiPORTANCE RO 3.0 SRO 4.0 2.1.3 Knowledge of shift turnover practices.

(CFR: 41.10 / 45.13)

BfPORTANCE RO 3.0 SRO 3.4 2.1.4 Knowledge of shift staffing requirements.

M (CFR: 41.10 / 43.2)

IMPORTANCE RO 2.3 SRO 3.4 2.1.5. Ability to locate and use procedures and directives related to shift staffing and activities.

(CFR: 41.10 / 43.5 / 45.12)

BIPORTANCE RO 2.3 SRO 3.4 N

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)

BfPORTANCE 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)

BfPORTANCE 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 R O 3.8 SRO 3.6 2-1 WTrIG-1123, Rev. 2 l

4 2.1. Conduct of Operations (continued)

' 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.

(CFR: 45.12)

IMPORTANCE RO 3.0 SRO 3.0 2.1.20 Ability to execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4.3 SRO 12 -

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)

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. ,

(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).

(CFR: 41.10 /45.12)

IMPORTANCE R O 2.2 SRO 2.6 s

2-3 NUREG-1123 Rev. 2 l

2.4 Emergency Procedures / Plan (Continued) .

i 2.4.32 ~ Knowledge of operator response to loss of all annunciators.

L (CFR: 41.10 / 43.5 /45.13) >

IMPORTANCE RO 3.3 SRO 3.5 l 2.4.33 Knowledge of the process used track inoperable alarms.

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. (CFR: 41.10 /43.5 /45.13)

IMPORTANCE RO 2.4 SRO 2.8 I 2.4.34 Knowledge of RO tasks performed outside the main control room  !

during emergency operations including sysiem geography and system implications.

(CFR: 43.5 /45.13) i IMPORTANCE RO 3.8 SRO 3.6 i I

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 l t

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

(CFR: 43.5) '

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

(CFR

45.13)' j IMPORTANCE ~ RO 2.0 SRO 3.5 l 2.4.38 Ability to take actions called for in the facility emergency plan / including (if l required) supporting or acting as emergency coordinator.  !

(CFR: 43.5 / 45.11)

IMPORTANCE RO 2.2 SRO 4.0 .

2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation. i

_ (CFR: 45.11)  !

IMPORTANCE RO 3.3 SRO 3.1 -i 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation. ,

(CFR:' 45.11)  !

! IMPORTANCE RO 2.3 SR.O 4.0 l l ,

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L  ?.4.41 Knowledge of the emergency action level thresholds and classifications.

I r (CFR: 43.5 /45.11)

L IMPORTANCE R O 2.3 SRO 4.1 .

I NUREG-1123, Rev 2 2-14 l  ;

RECENT LE_SSONS LEARNED SRO-only Questions (Cont'd) .

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

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

- Other 14 flexible.

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ES-401 BWR SR0 Examination Outline Form ES-401-1  ;

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4 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 i 1 2 3 4 5 6 1 2 3 4 i

i I M4 mg =i e us;;

Emergency &

D ES h!fk mm.

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g, m. m Evolutions Tier y%g g,g pg [ g%.: 43 +7 l Totals itsc s%g SE g$Fs#;;

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13 Plant Systems 3 4 Tier 40 _ff Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 + 'f 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 l or three K/A topics from a given system unless they relate to plant-specific priorities.

Systems / evolutions within each group are identified on the j associated outline. I The shaded areas are not applicable to the category / tier. l 1

i NUREG-102) 10 of 39 Interim Rev. 8, January 1997 i

ES-401 BWR R0 Examination Outline Form ES-401-2 j 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 1.

Emergency &

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Totals $h [Ei h j% l l

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Tier 51 Totals 1

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 l 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.

Systems / evolutions within each group are identified on the j associated outline.

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

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

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RE_C_ENT LESS1DNS LEARNED Sampling Criteria intent of proc'ess is to avoid exam predictability.

also to avoid excessive use of repeat test items.

first use systematic process to develoa sample plan using topics from K/A catalog, then use facility question resources to accomplish the ,

, plan. .

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RECENT LESSONS LEARNED ~

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Sampling Criteria (Cont'd) each topic in each tier & group should be sampled at Idast once unless insufficient questions exist to do this. If all topics have been sampled once and other questions need to be selected, the process should be systematic and unbiased.

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

8

RECENT LESSONS LEARNED Sampling Criteria { Cont'd}

up to 25 questions from last two NRC exams, facility licensee exams, tests & quizzes (except final audit test) may be used. '

Chief Examiner (CE) has the option to unilateral y shift or change the selected K/As.

ua to 5 site-specific priorities may be identified with CE concurrence (K/A value may be < 2.5 with sufficient justification).

{

OTHER 1 1;

Record Keeping per 10 CFR 55 are required to provide evidence that the applicant has successfully l completed the facility licensee's requirements to be licensed as an operator.

this includes successful manipulation of the t

controls of their facility. As a minimum,5 significant control manipulations which affect reactivity or power level.

m

OTHER '

R Record Keeping (Cont'd}

i this informatipn should be retained and  ;

available for inspection from time of license application to license expiration.

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OTHER -

Requal Control Manipulations i" have program based on SAT process, list in 10 CFR 55.59(cX3) does not need to be strictly followed.

should lave something similar based on plant JTA and specific plant priorities.

some manipulations are individual operator oriented, most would be team oriented.

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OTHER .

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6 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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l Examination Communications Examination Development Coordination By Ronald F. Aiello

I Facility Suggested improvements

1. The exam ceveloament team anc lead

examiner shoulc meet at the beginning of

! t1e deve 03 ment 3rocess to estab isl

common grouncs "or the cevelopment anc i execution of the examination:

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-> Changes anc interpretations to t1e 4

NUREG. 1 1

-> Sco3e of t7e exam cevelopment and acministration arocess.

-> _essons learnec from t7e last exam adminis':ered.

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2. Move due cates for the out ine and t1e l exam back to 90 and 60 days prior to arep week. T1is wiI provice more time for examination review by the examiner (s).

3. SSNTA continue with efforts to standardize document formats for examination tools (JPMs and scenarios).

4. Examiners maintain a list of w1o (alant) does the exam process the best. This should probably be broken down to eac, portion of the examination. Provide your ratings to the utiities in Region 2, so we ,

can meet your expectations and improve.  ;

5. T1e arinciaal and the utility rearesentative shou d meet ear y to estab ish a wor <ing  :

relations 1ip and exaectations. If 30ssible l this shou d inc ude samples o" c uestions, JPMs, etc.

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6. The exam should have no outstanding issues /c uestions tlat arise and need repair at the last minute. These issues l should all have been identified by t7e prep l week, to allow time to ma<e changes t1at  !

meet all the criteria.

7. T1e chief examiner should explain up front all the forms in 1021 that need to be l com aleted. l l

8. A ways check on aadging arior to coming l on site.  !

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9. As soon as a Chief Examiner is assigned to an exam, the Faciity Rep and the Chief should veri"y t1e ability to communicate via a 1 channels (including e-mail). When we converted to Lotus Notes, t1e faciity was suddenly unable to senc e-mail to his Chief Examiner. T1is

became somewhat of a hindrance and slou d be avoiced i" aossiale.

10. It would be helpfulif the Chief Examiner i cou d arovide his schec u e to t7e Faciity l Rep. T1is includes aroviding u3 dates for l

any changes to the Chief Examiner's  ;

schedule along the way. The facility rep l neecs to be aware of when the Chief '

Examiner is available to assist in exam .

preaaration activities.

11. A face-to-face meeting should be promptly scleduled in order for the Chief to -

communicate his expectations to the Facility Re3. The face-to-face rec uirement could be waived if the Chief and the Facility Rep have areviously wor <ed together and the Facility Rep is confident tlat le/sle uncerstands the Chie"'s exaectations. In any case, a

conference call woulc ae t7e minimum to satisfy this im aortant first step.

12. The Chief and the Facility Rep shou c wor < together to establis7 a 'irm schedule

'or t1e exam wee <(s). T7is will ensure the most efficient schedule is develoaec (with respect to crew composition and personnel movement) to minimize the amount of exam material required.

13. The Chief Examiner anc Utility Rep MUST remain fixed during the entire 180 day i period. Handinc o'f the resaonsibility is l both disru ative and destructive to communication. The exaectations o the clie' examiner must be definec/ communicated early.

14. The "timeline" must be enlancec to identify saecific times anc cates for communication / wor <ing meetings between 1

the examiner and t7e utility rea. These meetings should be " face to face" to l assure expectations are understood, and i being met, early on.

i

15. If an examiner and a utiity rep have not i worked together before, the timeline for -

" deliverables" must be expanded.

l Working meetings (face to face) must be

! established for the examiner to review

[ 5-10 questions,1 scenario,1 jpm,5 jpm j knowledge questions,5 admin questions, j etc. to assure that the standards and j expectations are clear early in the arocess

! and that the utility can produce a product

! that meets tie expectation.

i 16. 398 and 396 forms need to be available .

electronical y. We took the time to develop an electronic version ourselves but I would prefer that the electronic master copies came directly from the NRC

l

! so that we have more confidence that l everytlinc is exactly the same. We woulc j all benefit from this improvement.

l 17. 'A face to face wor <ing meeting of eight (8) l to twelve (12) hours, a 33roximately two

! (2) weeks before the thirty (30) day j submittal must be established to resolve j any issues BEFORE the submittal. The

[ exam materials should be reviewed, line l by line, at this meeting to communicate all j changes necessary.

18. Exaectations must be established early so that the utility clearly understands the rules and the examiners expectations. Small samales of development must be' reviewed early to assure exaectations are being met.

A face to face meeting, prior to the 30 day submitta , to resolve any/all issues must be sclec uled such that adequate time (suggest 2 weeks) is available to resolve

comments before the 30 cay limit. No one wants to see 30 c uestions reviewed anc the exam rejected. Spending ~24 hours in 3-4 face to face meetings is a small/ smart  ;

3 rice to aay to avoic huncreds of hours of re-develoament, the emotiorial stress on l

candidates when the exam must be i rescheduled anc the impact on the plant  !

when candidates are not licensed to meet l plant needs. l i

19. The "new" SSNTA format for JPM level of detail is NOT what you have liked in the past and needs to be either acceated by the NRC as a standard or optimum format, or modified, or rejected. The JPMs we submitted to you were in the format and level of detail you had found acceptable in the aast, and we were surprised to finc that t7ey needed significant last-minute rework (additiona level of detail).  !

l l

20. Maybe Chief Examiners could send some  ;

copies of gooc written cuestions, JPMs, .

and JPM questions ua front that could hela a new developer survive the exam writing process and see where you as an examiner are coming from.  :

Facility General Comments

1. T1e 'imited number of NRC license examiners outs the Region anc the sites at a disadvantage with resaect to getting timely interchange. If the examiner is out ,

of the office on a trip for several weeks, the time you have to provice the licensee with feec back is very limited and results in a real struggle to ensure a quality exam. l The limited resources and interaction time increases the risk of lower quality.

2. Region 11 examiners have aeen very 3rompt in getting back to us w1en we lave a cuestion even though you may ae at a remote location.

3. The cuaity of the communications las aeen gooc. A of t7e examiners tlat I lave tal<ed to lave 3een t1orough, arecise and have aerformec listening clec<s to i

i.

! verify that the correct messages were sent ,

! and received. I wou c however, li<e to see I i more communications by e-mail where j aaproariate. That would hela ensure the l clarity of the communications even more.

i l 4. With resaect to the exam specifically; there l were a number of changes that were made j and we had to transmit those by expensive l overnight or next day delivery. If we could j figure out a secure e-mail method it would j save all of us numerous heacaches as well j as do lars.  !

i i

5. During my first face-to-face meeting wit,

t1e Chief Examiner (to review draft exam j material), I gained much-needed insight into his expectations. This alleviated much stress on my aart anc, from then on, the arocess went much more smooth y. The Chief was very helafu durinc subsecuent te ealone conversations anc our second i

i

l T

meeting in Atlanta. He was very easy to wor < with and very understancing

concerning my inexperience in this

) process. His patient guidance was the key l -to our success in this endeavor. Next time, j with al we've learned, we'l do even better.

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j 6. The biggest problem that I encountered  !

l during that exam came from the written portion that was being developed by the  ;

contractor. Since he lad written exams l l before, I assumed that the quality of

! c uestions he was submitting to us were the l quality of questions that were acceptable to <

l the NRC. We reviewed his work, made '

l technical corrections and assumed that the j

] c uestions would be accepted by the NRC.

I had very ittle communication with the  ;

NRC on the subject of the written exam .

and a great deal of communication on the  ;

subject of the oaerating exam. When tie  :

submitta was fina ly made, the focus went j f

to the written exam anc most of the communication was made over saea<er <

ahones (about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />). It became a very painful process and could have been svoided had I not put so much fait, in the contractor's exam writing experience 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 report was brutal in the area of the written exam.

7. Know t1e chief examiners expectations from the beginning (prior to any development).

8. Never assume you <now what you're doing

- the chief is just a ahone call away.

9. It's better to de iver material and review it in person rather tian over t1e ahone. I alan for four or five trips between the start of

develoament and arep week. It may sound li<e overkil , but it works (It's a so safer in the area of security).

10. Submit material early (esaecial y the written). I like to have the written exam a c'one deal prior to the actual submitta date.

, 11. You can never talk to the Chief Examiner .

too much. During the process, I talk to him i more than I talk to my mother.

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

~ ear y submittal of materials is the key to a  !

successful NRC exam.

13. ALL 3 rob ems / chances must be resolved at the level of t1e examiner and the utility rep. In no case s1ould proalems/ changes be reaorted/ escalated to senior management of the utiity or NRC unless

i-  !

! i l both the examiner and the utility rea are at l an absolute, and mutually agreed,  ;

j impasse.

i  !

l 14. We often felt that we were working in the l j dark, writing questions on toaics you may  !

l not want (as we were waiting for comment  !

j on our skyscraaers), possibly wasting  !

! resources, but seeing no other option to  !

l meet our required cast-in-stone deadlines. l j

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

!1 l 16. What is a good " admin JPM", especially for i ROs?

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., Que511Uta

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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 l control urgent failure alarms occur. l l

Where will thermal power and RCS Tavg stabilize in response to the dropped rod without i any operator action? l A. Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg j will be more than 5'F lower than the temperature prior to the dropped rod.

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

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. l

'D. Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod. j l

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Answer:

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

auf es N

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. Keterence Page ,

SRO Question 10 RO Question 10

~SRO Tier / Group lI1 RO Tier / Group 112 SRO Importance 3.7 ROImportance 3.2 10CFRSS.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 '

SHNPP Objective AOP-LP-3.1-2 I 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 i

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'ito the dropped f 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 em t

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4 INITIAL EXAMINATIONS i

i QUESTIONS AND ANSWERS TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 l

RICK BALDWIN GEORGE HOPPER I

~

-l 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."

l 2

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OBJECTIVES 9 BEi l ER EXAMINATION PRODUCT O LESS NRC/ FACILITY REWORK O SHARED EXPECTATIONS t

3

~i SESSION OBJECTIVE: -

To review validity concepts affecting the NRC written examination for the purpose of:

l l Instructing licensee personnel toward I

l l

construction of more VALID and l

l CONSISTENT NRC license examinations.

4 l

COVERAGE 9 3 Levels of Validity 5

! O 3 Levels of Knowledge 9 D.iscrimination, Sampling '

O Psychometrics 5

VALIDITY l

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.  ;

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l In licensing examinations, testing specific j skills and knowledge that SHOULD have l been outlined in the objectives.

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3 LEVELS OF VALIDITY O Content e Operational i e a O Deiscriminant t

7 2

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OPERATIONAL VALIDITY '

i Addresses two aspects: ,

Is the test item important to be known as a

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l part of the operator's job?

2. Does the test item require the candidate to perform a job RELATED mental or physical operation?

9 i

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l DISCRIMINANT VALIDITY '

l 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.

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

10

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 i comprehension or analysis level vice

simple memory. Items that measure problem solving, prediction, analysis

! which are essential to job performance.

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- - - - - - - - - . - - - - - - - - - - - - +-_ ---------.m -z'----. -- --

VALIDITY

SUMMARY

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3. The exam must discriminate at a moderate t level of difficulty, set by the cut score.

Meaning the test items as written should l provide opportunity for at least 80 percent  !

of the candidates taking the test should answer the item correctly.

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1

3 LEVELS OF KNOWLEDGE-Bloom's Taxonomy

, 9 Analysis, Application, Synthesis l 9 Comprehension O Fundamental (simple memory) t 13 4.

i LEVEL OF KNOWLEDGE G Bloom's Taxonomy, NRC Reference Benchmark to classify levels of knowledge.

O Bloom's Taxonomy, a classification scheme that classifies items by depth of mental performance required to answer the items.

l e Bloom's Taxonomy, can be applied to l

l I 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.

4 i.e. setpoints, definitions, or specific facts.

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l LEVEL 2 Comprehension, involves understanding l material through relating it to its own parts or.

other material:

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

! , including consequences or implications.

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DETERMINANTS OF DISCRIMINATION O Level of examination knowledge G Level of examination difficulty O Passing Score 9 Item bank.use t

18

NATURE OF EXAMINATIONS AND TESTS O TESTS are samples of PERFORMANCE e Infer overall performance based on a sample e Sample must be broad-based to make confident inference e 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 l

20

e 006 Emergency Core.C,ooling System,/ JPM 136 Recovery From Safetylnjection

.and Solid Water Conditions W .. ; ' ' - *

• 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 4

I

INADEOUATE CORE COOLING 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 H 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-4 A, A4]

b. DUMP steam to condenser b. DUMP steam at maximum rate at maximum rate. USING Intact S/G atmospheric relie1(s).

IF local control of atmospheric relief (s) is necessary, THEN DISPATCH personnel to dump steam USING EA-1-2, Local Control of

~

S/G PORVs.

(Steo continued en ner. page.)

O Pace 13 of 19

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l 026 Conrainment Spray System /.JPM y 57AP Respond to High Contamment

_ Pressure 4 Place RHR Spray.in Service? ' ~ .

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Question '-

Given the following plant conditiohs:  ;

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

Containment pressure is 3.0 psid i Transfer of Containment Spray pump suction to the containment sump is being performed in l accordance with ES-1.3, Transfer to RHR Containment Sump.

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

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

l 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 14-18. CCD NO:1-47W611-72-1, ES-1.3. pages I l-13, OPL271C388 pg 9 Applicant Response: SAT UNSAT l l

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License Applicant Administrative Walkthrough Examination--NRC-1

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

Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming

-~

outage. He had his last physical examination 18 months ago and has had satisfactory performance in the licensed operator requalification training program.

He is informed that he is needed to join a shift crew in 3 days to fill in for a vacationing Unit OATC.

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

References Allowed? YES 2LNO -

i Answer: No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of  ;

"under direction" on-shift time, i

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

r I

l

License Applicant Administrative Walkthrough Examination--NRC-1 I Examiner Sheet - i

'A;1: 4 Shift Staffing--

i Question 1: A licensed RO has been ort-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 sMA RO.

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

vacationing RO? i References Allowed? YES _X_ NO 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 K/A 2.1.4 (2.3/3.4) ,

i Applicant Response: SAT UNSAT  !

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.. . . r Givent'he following conditions:  ;

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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 i 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.. ,

i

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. i i

d. .The affected SG pressure is high due to thermal stratification of the i secondary water. j L  !

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Reactor Operator Examination l

65. Given the following conditions:  :

L The reactor has experienced a Steam Generator Tube Rupture.

A!! systems responded as expected.

The performance of EOP-04 is in progress.

One steam generator has been isolated.

RCS cooldown using natural circulation is m progress.

Which ONE of the following describes the concem associated with the affected SG pressure prior j to placing the RCS on SDC? _

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

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

resulting in a dilution.

c. . The SG temperature would be too high to allow for SG depressurization. r I

d. The SG pressure would be too high due to thermal stratification of the secondary water.

I s

M er 4

I Which one of the following describes the response of the Unit I 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 l

' minutes after it is energized by the diesel. ,

t

b. ~All. charging pumps are automatically started immediately after their  !

respective bus-is energized, i i

c. 'The' operator must manually start one' charging pump on each emergency bus j 5 minutes after it-is energized by the diesel. i l

d. One charging pump is automatically started onto each emergency bus-  !

immediately after it is energized by the diesel. -

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29. Which ONE of the following describes the response of the Unit-1 charging pumps following receipt of an automatic SIAS signal, coincident with a Loss of Offsite Power? Assume normal .

electrical lineup and all equipment is operable. ,

n. Only one charging pump is automatically started on each emergency bus 5 minutes after it i is energized by the diesel. l

b. All charging pumps are automatically started immediately after their respective bus is energized by the diesel.

c. All charging pumps are autol;, vally started 5 minutes after their respective buses are i I

)- energized by the diesel.

i

d. Only one charging pump is automatically started onto each emergency bus immediately I afterit is energized by the diesel. i i I

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Charging pumps are running on Unit I an SIAS is present. (Assume no operator j action) >

l Which one of the following lists the charging pump response when the BAM tanks

.. are emptied?

The charging pumps will:

a. trip on low oil pressure.

b. trip on low suction pressure.

c. automatically align to.the RWT.

d. continue to run and become gas bound.

l-1 4

.. _ . . _ _ . . _ _ _ . _ . ~ . _ . ___.m _ _ . ~ . ..__..____..___.m.______._-__,

t Reactor Operator Examination '

i:  !

i 27.

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

~.

.Be charging pumps will:  !

a. ' trip on thermal overload.

b. trip on low suction pressure. *

. c. automatically align to the RWT.  :

t

. d. continue to run and become gas bound. '

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Given'the following conditions:  !

I 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. 3

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! Which ONE of the following completely lists the-logic that will start HVE-21B? i

' :a. The trip signal from HVE-21A. I o

b. The trip signal from HVE-21A concurrent with a low flow signal.

l- c. A low flow signal. ,

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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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i Reactor Operator Exammation f

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? ' 5 9. Given the following conditions:  ;

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

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

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

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

a. The trip signal from HVE-21 A. _

b. The trip signal from HVE-21 A concurrent with a low flow signal. l

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 ievels are 5% NR and DECREASING slowly r

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

. #4 S/G levelis STEADY at 2% NR

. Totalfeedwater flow is 340 gpm

. PZR levelis 37% and INCREASING

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

K/A: 000040K101 [4.1/4.4]

Reference:

E-0, Foldout Page l Objective: OPL271C395, B.1 1

Level: . Analysis Source: 000040K101 001 History: Stem and distracters a and d mod 6ed (7/7/98)  ;

~

I Note: Provide FTS 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 than 12.0 osid.

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

" 3. Given the forfowing p! ant conditions:

. Unit 1 was at 73% power A reactor trip / safety injection on low steam line pressure occurred 21 minutes ago

. . Average Core Exit TC temperature is,36F

= RCS pressure is.225'psig I'bSO Y#

. All S/G pressures are DECREASING slowly

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

. *1 S/G 1evelis 6% NR, and INCREASING slowly

. #4 S/G levelis STEADY at 2% NR -

. Totalfeedwatepflow is 340 gpm P2R levelis)7% and INCREASING

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

. Containment pressure is 5 psid and INCREASING slowly At this point, whi:h ONE of the following Cntical Safety Functions is the MDST degraded?

a. Heat Sink

b. Core Cooling i

c. Containment

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

Reference:

E-0, Foldout Page Objective: OPL271C3jf, B.1  !

l Level: Analysis ,

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

Note: Provide PTS curve with this question. l l

1 Justin:ation: l 1

a. Correct answer because al! S/G ievels are Jess tnan 10% NR and total feedwater flow is less than e-40 gpm.

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

c. Incorrect because containment pressure is less inan 12.0 ps:d. l

d. Incorrect because RCS temperature is 325'? (T-:oid is greater inan 250*F). l

/./'

3g, LL. 4 ;v..e .b xi'n -<w'*J u i W -t.s W ";,, C l

MS a.% -> a .c .~ t , .- r 1 ~ g" $ ~j'j y k d. if . l

,,.l{,

, j,i/ ,- . .aw.? W 2 =~'% j

-d . , . ,

v',  %.a i i

1

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 i levels at 33%. ,

l

c. The MDAFW pump level control valves will have to be manually adjusted using the 1 Manual Output Adjust in the L-381 cabinet.

d. The discharge pressure f r the MDAFW pumps will have to be manually adjusted by  !

throttling the manual valves at the LCVs.

Answer: B K/A: 0000SBA102 [4.3/4.5)

Reference:

ADP-C.04, page 11 Objective: OPL271C423 B.4 Level: Comprehension l Source: 00005BA102 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 l

l l

l 1

l l

1

A h-

20. Given the following plan: cendr:rons:

. The control room has been evacuated due to a fire

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

. MDAFW pumps 1 A-A and 16-B are injecting into the steam generators

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing 0

@ s G w4r- M M k oh@ >+'d A4 -C.01 Which ONE of the following describes theze:re = v:im ..d.c,y lccdwatc system?

a. The TDAFW pump will automatically restart wh n 2/4 steam generators reach low low level. * ~ $+ k ~* A O'ob U 5W) e LO/ ,

(Com

b. The MDAFW pump level control valves will automstr: ally c.ontrol steam generator ,

, levels at 33%.

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

/W 7~Y y g [

d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by tnrottling the manual valves at the LCVs.

y ot

,,f[j Answer: B K/A: 00005BA102 [4.3 / 4.5)

Reference:

AOP-C.04, page 11 Objective: OPL271C423, B.4 Level: Comprehension Source: 00005BA102 001 History: Used on 9.57 RO NRC exam Text modified to correct grammar errors. Distracers a, b, e, and d reordered (7/22/98). Distracter be restructured (7/29/9S)

Note: Seie ted fromMexam bank with minor modification of text d

23. Given the following plant conditions:

. FR-C.1,

• inadequate Core Cooling", has been entered due to a RED path on Core Cooling

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

. NO Feedwater / Aux Feedwater is available

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

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

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

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

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

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 fronMexam bank without modification of text i

- l I

l I

4, g INADEQUATE CORE COOLING FR-C.1 7q Rev. 8 ,

i 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 r leveis:

a. Greater than 10% [25*4 ADV) a. M AINTAIN total feed flow greater than 440 gpm UNTil level greater than 10% {25*4 ADV) in at least one S/G.

IF total feed flow greater tnan 440 gpm can NOT be established, THEN PERFORM tneiollowing:

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

, 2) GO TO Note pnor to Step 21.

a. Between 10=4 [25*4 ADV) and 50*4.

Page 10 of 19 l

FR-C.1

.+ INADEQUATE CORE COOLING Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCP damage due to absence or loss of norrnal support conditions is an acceptable consequence in this procedure.

.~

21. CHECKif RCPs should be started:

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

t greater than 1200*F.

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

i 1) S/G narrow range level a) OPEN pressurizer PORVs and block greater than 10% {25% ADV] valves, j

4

2) RCP in associated loop b) IF core exit T/Cs rernain AVAILABLE AND STOPPED. greater than 1200*F, THEN OPEN reactor vessel head vents:

1

y, . FSV-66-394

. FSV-68-395

. FSV-68-396

. FSV-68-397.

c) GO TO Step'22.

7 I c. START RCP in one idle loop.

I

d. GO TO Substep 21.a.

Page 17 of 19

23. Given the following p! ant condaions:

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

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

. NO Feedwater / Aux Feedwater is available

. At step 12, the CRO checks the S/G NR kvels and repor:s all are <10%.

As the SRO you should: (Select ONE of the followin;,)

~

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

b. Depressurize allintact S/Gs to atmospheric pressure to dump a:cumulators.

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

M PoRsl.s a "SL o d Wh.s

d. .BreparMete RSS-Few w JGee64-WR4eveHrt-any2-S/Gs-is-lessahan-50b.

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: SelecteditomMeram bank without modification of text g y#g~ ,'p2A W '" 0

• O 4

======-=se

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 F-10 setpoint.

b. Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range channel, so the unit must be manually tnpped 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 Source: 015000K407 001 History: Not used on 9/g7 or 5/98 NRC exams. Not used on practice exam.

Distracters e and d reordered Note: Selected fromg exam bank without modification of text

s r_ _

(W 5 @' 4 v g4 f O!&l&O?- /N Y # "[

j ,1 ( /

49. Given tne following plant condnions: 3 5~f ,i I w(

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

. Intermediate Range t -35 failed high \

COperators pic.W m; cJ;MP-eypass-switerriert#367:rthe Dypasswits Which ONE of the following describes the effect of this failure and action during the remainder of the snutdown?

~

a. The reactor will automatically tnp when the Power Range channels decrease below

. the P-10 setpoint.

b. Entry from (Aode 1 to (Aode 2 is prohibited with an inoperable interrnediate Range channel, so the unit must be manually tripped prior to (Aode 2 entry.

c .Both 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 [3.7/3.8)

Reference:

AOP-LD1, page 10 ES-0.1, page 13 Objective: OPL271 C352, B.4 Level: Comprehension l

Source: 015000K407 001 History: Not used on 9/97 or 5/98 NRC exams. Not used on practi:e exam.

Distracters c and d reorcered l

,\

Note: Selected fromMexam bank without modification of text

\ \

p3  % g( () b

• y o v7 I

i

i I e l

l l

35. Given the following plant conditions:

. . Unit 2 is operating at 29% power in accordance with 0-GO-6, Power Reduction From 30% Reactor Powerto 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 l 10%7 ,

. a. Manually energize N-31 and N-32.

l

b. Place N-36 Level Trip switch in BYPASS.

l

c. Remove N-36 instrument power fuses.  :-

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

l Answer: B K/A: 000033K302 [3.6/3.9)

Reference:

ADP-l.01, page 10 & 13 '

Objective: OPl271C352, B.4 i

Level: Analysis Source: New question (Developed 7/15/98) .

Justification:

l . a. Incorrect because manually restoring N-31 and N-32 to operation in the power range would I destroy the source tarige detectors.  ;

L

b. Correct because placing the level trip switch in BYPASS prevents high reactor trip when

tne low power reactor tnp signal is reinstated at the P-10 setpoint (10% power). ,

I" l c. Incorrect because action does not bypass the trip signal.

d. Incorrect because a manual reactor trip for the given condrtions is not required. Placing N-36 leveltnp switch in BYPASS allows an orderly reactor shutdown.

I l \

l l

l l

.l l

" l l

1

50. Given the following piant conditions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig ,

. Exosensor indicates 25'F superheat I

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

a. Reactor Coolant Tavg value.

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 K/A 017000A402 [3.8 / 4.1)

Reference:

FR-0, page 3 OPL271C044, page 7, A.1.c Dojective: 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 xam bank without modification of text

1 J

50. Given the following plant conditions:

. Large Break LOCA is in progress

- RCS pressure is 550 psig

. Exosensor indicates 25'F superheat j

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

, , . , l T c C ran:  ;; Ei$ -- 7 Ahh ,,d ~ M (' #'

. i Tc .wtr are 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 ,,

yh pp 'b o#' de MW 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) v Note: Selected from exam bank without modification of text

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

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

?

88. Given the following plant conditions:

I

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

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

. Current time is 0100  ;

Which ONE of the following actions must be taken? j

a. immediately stop the power increase.

b. Continue the power increase while restoring loop 1 accumulator boron concentration to 2400 to 2700 ppm boron within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

c. ff 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:

• 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  ;

Objective: OPL271C209, B.2 i

Level: Comprehension  !

Source: New question (Developed 7/20/98)

Note: Provide copy of Technical Specification 3.5.1.1 with the question (exam) 4 ',

Justification:  ;

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 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. i

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.  !

i

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 i must be in HOT standoy by 0800. l

. 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. 3

~

i r

i

3 /4. 5 EHERGENCY CDRE COOLING SYSTEMS 3 /4. 5.1 ACCUMULATORS COLD LEG INJECTION ACCUMULATORS LTHTTING CONDITION FOR OPERATION 3.5.3.] Each told leg injection accumulator shall be OPERABLE with:

a. The isolation valve open, gi31

b. A contained borated water volume of between 7615 and 8094 gallons of borated water, e

c. Between 2400 and 2700 ppm of boron,

d. A nitrogen cover-pressure of batween 600 and 683 psig, and RIS4

e. Power removed from isolation valve when RCS pressure is above 2000 psig.

APPLICABILITY: MODES 1, 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 ne::t 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 baron concentration not within limits, restore boron concentration to within fl.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.

Dece ber 27, 1994 Amendment No. 113, 331, 133

- UNIT 2 3 H 5-1 i

~  ;

e s , y . .. >

fj0. }j' Ye - Y 1

88. Given:ne following plant conditions: j

. Unit 2 operating in a::ordance wi:h 0-GO-5. Normal Power Operation at 73% with a l powerincrease to100% in progress

.~ Chemistry repons Unit 2 RCS loop 1 accumulator baron concentration is 2390 ppm l

.- /,j

/ . Currenttime is 0100

,g Which ONE of the following actions must be taken? [

i

a. Immediately stop the power increase. .,

l

b. Continue the power increase while restoring loop 1 accumulator boron concentration

- to 2400 to 2700 ppm bororv-%r.b.1 heer. ANw 72 4 or 7 C$.

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 l

• 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  ;

i pressurizer pressure to 1000 psig or less by 1300.

Answer: A j i

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

j i

Reference:

55P 12.1, Page 31

Objective

OPL271C209, B.2 I i

Level: Comprehension

Source

New question (Developed 7/20/98)  ;

' Note: Provide copy of Technical Specification 3.5.1.1 wnn tne Question (exam)

<? i

.. Justification:  ;

a. Correct becaus onduct of Operation (SSP 12.1) restrie:s power increase  !

when in an LCO acuan ol e nours or less. RCS loop 1 a::umulator coron concentration of [

^

2390 ppm boron places Unit 1 in a 1 hout LCO. .

. b. Incorrect because power increase is not allowed wnen in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO action statement.  !

(

Incorre:t because if loop 1 boron concentration is not restored witnin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the Unit 1  ;

c.

must be in HOT standby by 0800.  ;

i incorrect because if loop 1 boron concentration not restored wrtnin 1 nour, pressurizer i d.

pressure must oe reduced to 1000 psig or less by 1400.

.. i

-6 f 4 i I

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006 Emergency Core Cooling System V JPM 136 -Recovery From Safetylnjection

.and Solid Water Codditions' C.e .*

Question 2:

Given the following plant conditions: ,

Unit 2 was operating at 100% power. j 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. I i

Reference:

KA: 006G4.18 [ 2.7 / 3.6 ] Knowledge cf specific bases for EOPs.  ;

OPI.271C398 pg 12-15 l 6

Applicant Response: SAT UNSAT_ .

l P

P M

L i

i l

1 s

4 4

INADEQUATE CORE COOLING 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 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-4 A, A4]

b. DUMP steam to condenser b. DUMP steam at maximum rate at maximum rate. USING intact S/G atmospheri: relief (s).

IF local control of atmospheric relief (s) is i necessary, )

THEN DISPATCH personnel to dump steam USING EA-1-2, Local Control of

~

S/G PORVs.

(Step continued on next page.) l j

t

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026 Conrainment Spray System /,JPMy 57AP Respond to High Contamment

_ Pressure,e: Place'RHR Sp' ray:in ServiceM ~

Question 2:

l Given the following plant conditions.

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

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

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

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

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

References Allowed? YES X NO l 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.

l b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of (

water.  !

i

Reference:

K/A: 026G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs OPL271CO24 pg 14.I8, 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 4 Examiner Sheet A'.1:) Shift Staffing c : ~:- -

~' ' -

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 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 i vacationing Unit OATC. >

., Can the RO fill in for the vacationing RO? Why or why not?  %  !

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 l

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l r

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4 k

r

, License Applicant Administrative Walkthrough Examination-NRC-1 Examiner Sheet A.1UShift Staffing 5 Question 1: A licensed RO has ben off-shift for 6 months to assist in outage scheduling. He is e

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 shiA 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.. I What additional requirements must be met by the RO before he may fill in for the vacationing RO?

References Allowed? YES _2L NO Answer: The RO must complete an additional 24 (40 - 16) hours of"under 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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