ML20199E741

Refers to 981105 Training Managers Conference Conducted at RB Russell Bldg with Representatives from All Utils.Agenda Used for Conference & List of Attendees Encl.Goal of Providing Open Forum of Operator Licensing Issues Was Met

ML20199E741
Person / Time
Site:	Hatch
Issue date:	12/23/1998
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Lewis J SOUTHERN NUCLEAR OPERATING CO.
References
NUDOCS 9901210070
Download: ML20199E741 (101)

Text

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l December 23, 1998 Southern Nuclear Operating Company, Inc.

ATTN: Mr. John C. Lewis, Training Manager, Plant Hatch E. l. Hatch Nuclear Plant U. S. Highway 1 North l P. O. Box 2010 .

Baxley, GA 31515

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - E.1. HATCH NUCLEAR PLANT

Dear Mr. Lewis:

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 u.;ed 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. j Sincerely, Original signed by Thomas A. Peebles

,,0 0 M 4 '"**^'"**b'**' hi*'

t- Operator Licensing and Human Performance Branch Division of Reactor Safety l Docket Nos.: 50-321 and 50-366 l License Nos.: DPR-57 and NPF-5 l

Enclosures:

As noted )

cc w/encis: /

P. W. Wells, General Manager, Plant Hatch 9901210070 981223 PDR ADOCK 05000321 P PDR e

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1 SNC 2 1

Distribution w/encls:

PUBLIC l B. Michael, DRS 1

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l Rll:DRS Ril:DRS BMICHAEL:

Q' TP EBLES I 12/// /98 12//j f/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 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 8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety 9:15 a.m. break 9:45 a.m. Other Issues Robert M. Gallo, Chief Operator Licensing Branch, NRR 10:15 a.m. lessons learned from Recent Exams Charlie Payne Sampling exam criteria i

11:00 a.m. Examination Communications Ron Aiello Exam Development & Coordination 11:30 a.m. Lunch

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1:00 p.m. Written Examination Questions and Answers Rick Baldwin / George Hopper 2:30 p.m. JPM Examples of questions Rick Baldwin / George Hopper 3:30 p.m. Open Session - Other issues Training Managers 4:00 p.m. Meet with Principle examiners All 4:30 p.m. Adjorn I

P License Applicant Adm9nistrative Walkthrough Examination--NRC-1 4 ,

Examiner Sheet A'.1: Shift Staffing Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is infonned 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 l a shift RO..

What additional requirements must be met by the RO before he may fill in for the l vacationing RO? 3 l 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 l K/A 2.1.4 (2.3/3.4) t Applicant Response; SAT UNSAT

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1 l ATTENDEES AT THE NRC REGION 11 l TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 Sid Crouch ATTSi David Lane Sonalysts, Inc.

l Bill Fitzpatrick INPO CP&l, Rick Gamer HR Supv Ops Trng William Noll BK Ops Tmg Supv Max Herrell BK Trng Mgr Scott Poteet RB Exam Team Leader Ralph Mullis BK Ops Mgr Tony Pearson BK Ops Tmg 1 Anthony Williams RB Tmg Mgr Crystal River - FPC Wes Young CR Supv OpsTng Tom Taylor CR Dir Nuc Ops Tmg ,

Ivan Wilson CR Ops Mgr l Ken McCall CR Mgr Ops Trng Duke Power Gabriel Washbum OC Req Team Leader Ronnie B. White, Jr MG Tmg Mgr l l W. H. " Soap" Miller CT Site Tmg Mgr i Paul Stovall OC Mgr Oper Trng Bentley Jones OC Trng Mgr l James Teofilak CT Ops Tmg Mgr Alan Orton MG Ops Tmg Mgr Richard Bugert Corp . Ops Tmg Spec l FP&L Maria Lacal TP Tmg Mgr Dennis L. Fadden SL Services Mgr Jo Magennis Corp Trng Assessment Spec l Tom Bolander SL Exam Development

! Steve McGany TP Maint Tmg Supv l

l Southern Nuclear (SNC)

' John C. Lewis HT Trng & EP Mgr Bill Oldfield FA Nuc Ops Tm Supv Steve Grantham HT Ops Tmg Supv Scott Fulmer FA Mgr Trng & EP Joel Deavers FA Sr Pit inst Bob Brown VG Trng Mgr Dan Scukanec VG Ops Trng Supv

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l Virainia Power Steve Crawford NA Sr inst Nuc Harold McCallum SR Supv Ops Trng i TVA Dick Driscoll SQ Trng Mgr Walt Hunt SQ Ops Trng Mgr Denny Campbell BF SRO Ops Inst Jack Cox WB Trng Mgr John Roden WB Ops Trng Mgr Tom Wallace WB Ops Supt V. C. Summer- SCE&G Al Koon SM Ops Trng Supv NRC Participants Tom Peebles R ll Operator Lic. Br. Ch.

Rick Baldwin R 11 Sr. Examiner George Hopper R 11 Sr. Examiner Ron Aiello R 11 Sr. Examiner Charlie Payne R 11 Sr. Examiner William Travers NRC Executive Dir. Ops.

R. M. Gallo NRR Br. Ch. OL Bruce Mallett R 11 Div. Dir. Reactor Safety i

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l FY 99 INITIAL EXAM SCHEDULE AND RESULTS i

l D:ccmber 14,1998 i

I RO SRO-l SRO-U TOTAL l

Dite Plant Chief Pass # Pass # Pass # Pass #

9/28/98 Sequoyah GTH 4 4 4 4 10/5/98 Harris RFA 2 2 5 5 7 7 11/30/98 Oconee GTH 2 2 5 5 7 7 11/30/98 St Lucie & RSB 6 3 9 12/14/98 I

1/25/99 McGuire & DCP 6 3 2 11 2/8/99 ,

2/8/99 C. River & GTH 6 6 12 2/22/99 2/8/99 B. Ferry MEE 4 1 5 3/29/99 Surry & RSB 5 2 4 11 4/12/99 4/12/99 Watts Bar & MEE 6 3 5 14 4/26/99 5/10/99 Farley GTH 7 1 8 5/24/99 Catawba & PMS 8 5 3 16 6/7/99 ,

6/28/99 St. Lucie RSB 1 4 5 07/26/99 Robinson MEE 3 2 2 7 08/30/99 Turkey Pt & RFA 20 20 9/13/99 136 RESULTS TO DA,TE 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 il write part of Summer & Hatch l

FY 00 INITIAL EXAM SCHEDULE AND RESULTS D:c:mbsr 14,1998 RO SRO-l SRO-U TOTAL D::ta Plant Chief Pass # Pass # Pass # Pass 0 9/27/99 Summer GTH 6 6 r:gion 11 write 10/18/99 Hatch DCP 10 2 12 region 11 write 12/13/99 Vogtle RSB 3 5 2 10 2/14/00 ' Brunswick & DCP 12 3 15 l

l 2/28/00 03/"/00 Oconee ? 10 j 704/10/00 Harris (maye woo) 10 t

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 j region 11 write?  !

708/"/00 Sequoyah 4 2 2 8 l

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709/04/00 Surry? 10 l

709/11/00 North Anna 12 I i

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O O 42 0 46 0 27 0 149

?' dssignates tentative No Initial exams scheduled for: Catawba Robinson Turkey Point l Watts Bar l

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i Operator Licensing i

Issues .

) Region 11 -

j Training Managers' Conference l

November 5,1998 j Robert M. Gallo, Chief l Operator-Licensing and I. Human Performance Branch i

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OPERATOR LICENSING ISSUES o

Part 55 Rulemakings .

Status Schedule o

Final Revision 8 of NUREG-1021 o

Examination Quality and Results

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o Generic Fundamentals Exam o

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

Sampling Plans (IN 98-28)

Eligibility (IN 98-37) 1

f RECENT LESSONS LEARNED by

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Charlie Payne i

Southeastern Training Manager's Conference

~ November 5,1998 t

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POLEY CLARIFICATIONS t

t 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 C_LARIFICATIONS e in general, license class sizes of greater than 8 candidates will be scheduled for 2 weeks as

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follows:

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-1 exam week off-week for documentation of week 1 3erformance 2"d exam week e

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

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

Criteria - 10 unacceptable questions out of 30 questions sampled ,

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

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

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

i' 2.0 GENERIC KNOWLEDGES AND ABILITIES 2.1 Conduct of Operations i

l 2.1.1 Knowledge of conduct of operations requirements.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 3.7 SRO 3.8 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

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(CFR: 41.10 / 45.13) -

IMPORTANCE R O 3.0 SRO 4.0 2.1.3 Knowledge of shift turnover practices.

(CFR: 41.10 / 45.13)

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

M (CFR: 41.10 / 43.2)

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

(CFR: 41.10 / 43.5 /45.12)

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 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 I

l 2-1  ?."JRE G - 112 3 , Rev. 2 l

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2.1 Conduct of Operations (continued) l I l'

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

(CFR: 45.12) i IMPORTANCE RO 3.0 SRO 3.0 l 2.1.20 Ability to execute procedure steps.

l (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE R O 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 l 2.1.22 Ability to determine Mode of Operation.

O (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 l

different modes of plant operation. i (CFR: 45.2 / 45.6)

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

l (CFR: 45.12 / 45.13) l IMPORTANCE R O 2.8 SRO 3.1 l

l 2.1.25 Ability to obtain and interpret station reference materials such as graphs /

monographs / and tables which contain performance data.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE R O 2.8 SRO 3.1 1

2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical / l l high temperature / high pressure / caustic / chlorine / oxygen and hydrogen). l (CFR: 41.10 /45.12) i IMPORTANCE R O 2.2 SRO 2.6 4

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I 2.4 Emergency Procedures / Plan (Continued) 2.4.32 Knowledge of operator response to loss of all annunciators.

(CFR: 41.10 /43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5 1

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

(CFR: 43.5 / 45.13)

IMPORTANCE RO 3.8 SRO 3.6 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations 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. l (CFR: 43.5)

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

(CFR

45.13)

IMPORTANCE '

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 RO 2.2 SRO 4.0 l

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

! (CFR: 45.11)

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

(CFR: 45.11)

IMPORTANCE RO 2.3 SRO 4.0 2.4.41 Knowledge of the emergency action level thresholds and classifications.

, , (CFR: 43.5 / 45.11)

, IMPORTANCE RO 2.3 SRO 4.1 NUREG-1123, Rev 2 2-14 l

_R_E_C_ENT LESSC'NS LEARNED  ;

SRO-only Questions (Cont'd) .

.. SRO-only questions will be based on "o owing 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 flexiale.

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ES-401 BWR SR0 Examination Outline Form ES-401-1 i'

Facility: Date of Exam: Exam Level:

K/A Category Points Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 1* 12! D !g

• me ed g!sN 1 26 Emergency &

E s*@

yy ..

1. y ,.

I Abnormal 2 F5ir $36 'ID eF' Md 17 l fiF i$d @$ hj' $$9 P1 ant .m..... .y, ,,

g l Evolutions Tier {jp g gg g,, 43 +7 Totals :w: *y .w c n gg in %g W M $;sl 2c 9 ,  : ~e w l

1 23  ;

2.

2 13 P1 ant t

l Systems 3 4 l

l l Tier 40 _g; l Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 +Y Note: -

Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.

1 Actual point totals must match those specified in the table.

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Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

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

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

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

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ES-401 BWR R0 Examination Outline Form ES-401-2 l 4

i facility: Date of Exam: Exam Level:

K/A Category Points Tier Group Point ,

K K K K K K A A A A G

- Total 1 2 3 4 5 6 1 2 3 4 I 3* I ih 13 i

Emergency & se m. g gg g

! Abnormal 2

m g g g g 19  !

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Plant 3 $1 M NI ma me E we, $Ei w 4 Tier E MN f$i[ M$ 36 l

1 Totals ( % %) N ilfr 1 28 2.

2 19 l Plant Systems 3 4 Tier 51 Totals l

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

l Abilities 13 i

Note: -

Attempt to distribute topics among all K/A categories; select i i at least one topic from every K/A category within each tier.  !

Actual point totals must match those specified in the taF,e.  !

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.

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

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O BEGENT LERSONS LEARNED Samplinc Criteria intent of proc'ess is to avoid exam predictability.

also to avoid excessive use of repeat test items.

first use systematic process to develop sample plan using topics from K/A catalog, then use facility question resources to accomp ish the alan. .

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RE_C_ENT LES_ SONS LEARNED Sampling Criteria (Cont'd) each topic in each tier & group should be samp ed at least once unless insufficient questions exist to do this. If all topics have been sampled once and other questions need to be selected, the process should be systematic and unbiased. l final sample plan should have a fairly even balance across all Ks & As.

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RECENT LE_S_ SONS LEARNED ,

1 Sampling Criteria (Cont'd?

u3 to 25 questions from last two NRC exams, facility icensee exams, tests & quizzes

(exceat final audit test) may be used.

Chief Examiner (CE? has the option to uni aterally shift or change the selected K/As.

up to 5 site-saecific priorities may be identified with CE concurrence (K/A va ue may be < 2.5 with suf"icient justification).

OTHER 1 Record Keeping .

per 10 CFR 55 are required to provide

evidence that the applicant has successfully completed the facility licensee's requirements to be licensed as an operator.

this includes successful manipulation of the controls of their facility. As a minimum,5 significant control manipulations which affect reactivity or power level.

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OTHER

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Record Keeping (Cont'd) this informatipn should be retained and  ;

availaale for inspection from time of license i application to license expiration.

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OTHER -

1 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 alant priorities.

some manipulations are individual operator  ;

oriented, most would be team oriented.

f i2

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 i i

! Examination Development

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l i Coordination \

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Ronald F. Aiello  !

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Facility Suggested improvements

1. The exam cevelopment team anc leac examiner shou c meet at t1e beginninc o

t7e deve oament process to establis, common grouncs for the ceveloament anc execution o' the examination:

-> Changes anc interpretations to t7e NUREG.

-> Scope o' the exam ceveloament anc administration arocess.

-> Lessons learnec rom t1e last exam administerec.

2. Move due cates for t7e outline and the exam back to 90 and 60 days prior to prep week. This wiI provide more time for examination review by the examiner (s).

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

4. Examiners maintain a list of who (alant) does the exam process the best. This should probably be broken down to each portion of the examination. Provide your i ratings to the utilities in Region 2, so we can meet your expectations and improve.

5. T1e princiaal and t1e utility representative should meet ear y to establish a working re ationslia and expectations. If aossiole tais slou d include sama es of questions, JPMs, etc.

1 l6. T1e exam shou c lave no outstanding I j issues /cuestions tlat arise anc neec l repair at the last minute. These issues should all have been identified by the arep wee <, to a low time to ma<e c1anges that meet a I the criteria.

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

8. Always check on badging prior to coming I on site.

9. As soon as a Chief Examiner is assigned to an exam, the Faciity Rep and the Chief should verify the ability to communicate via all channels (inclucing e-mai). When we converted to Lotus Notes, the faciity was suddenly unaale to send e-mail to his Chief Examiner. This

became somewhat o" a linc rance anc slou d be avoicec if 30ssible.

10. It would be helafulif the Chief Examiner cou d 3rovide his schedu e to the Facility l Rep. This includes providing u3 dates for any changes to the Chief Examiner's  ;

schedule along the way. The facility rep '

l needs to be aware of when the Chief Examiner is available to assist in exam areaaration activities.

11. A face-to-face meeting should be promptly scheduled in order for the Chief to communicate his exaectations to the Faciity Rep. T1e face-to-face requirement could be waivec if t1e Chief and t1e Facility Rep lave previously worked tocether and the Faciity Rep is conficent that le/she understands the Chief's expectations. In any case, a l

4: -- +

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! l l: conference cal woulc be the minimum to l satisfy this important first step.  !

12. The Chief and the Facility Rep should i

work togetler to establish a firm schedule

for the exam wee <(s). This will ensure the i most efficient schedule is developed (with j respect to crew composition and '

l personnel movement) to minimize the l amount of exam material required.

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! 13. The Chief Examiner and Utility Rep MUST

! remain fixed during the entire 180 day j period. Handing off the responsibility is l both disru ative and destructive to l communication. The exaectations of the clief examiner must ae defined / communicated ear y.

14. T1e " time ine" must be enhanced to identify specific times and dates for communication / working meetings between

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

15. If an examiner and a utility rea lave not worked together before, the timeline for

" deliverables" must be expanded.

Working meetings (face to face) must be estab ished for the examiner to review 5-10 questions,1 scenario,1 jpm,5 jam knowledge questions,5 admin questions, etc. to assure that the standards and expectations are clear early in the process and that the utility can produce a product that meets the expectation.

16. 398 and 396 forms need to be available e ectronically. We took the time to deve op an e ectronic version ourselves but I would prefer that t1e e ectronic master coales came directly from the NRC

so that we have more conficence that everything is exact y the same. We wou c all benefit from this improvement.

17. 'A face to face wor <ing meeting of eig1t (8) to twelve (12) hours, approximate y two (2) weeks before the thirty (30) cay submittal must be establis 7ed to resolve any issues BEFORE the submittal. The exam materials should be reviewed, line by line, at this meeting to communicate all changes necessary.

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

A face to face meeting, arior to the 30 day submittal, to resolve any/al issues must be scleduled suc1 tlat adequate time (suggest 2 weeks) is available to resolve

l c .

l comments before the 30 cay imit. No one l wants to see 30 c ues.tions reviewec and j the exam rejected. Spending ~24 hours in l 3-4 face to face meetings is a small/ smart

! price to pay to avoid hundreds o" lours of

re-development, the emotional stress on  !

! candidates when the exam must ae l rescheduled and the impact on t1e plant l l when candidates are not licensec to meet  !

! plant needs.

19. The "new" SSNTA format for JPM level of detail is NOT what you have liked in the past and needs to be either accepted by the NRC as a standard or optimum format, or modified, or rejected. The JPMs we submitted to you were in the format and evel of detail you had "ound acceatable in the aast, and we were surprised to find that t1ey needed signi"icant last-minute rework (additional level of detail).

l 20. Mayae Chief Examiners could senc some l co3ies of good written c uestions, JPMs, and JPM questions ua "ront t7at coulc hela 1 a new developer survive t1e exam writing process anc see where you as an examiner are coming from. l l

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l 1

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Facility General Comments i

l 1. The limited number of NRC license

{ examiners puts the Region and the sites at

a disadvantage with resaect to getting

i. timely interchange. If the examiner is out j of the office on a trip for several weeks, the j time you have to provide the licensee with l feedback is very limited and results in a j real struggle to ensure a quality exam.

l T1e limited resources and interaction time

! increases the risk of lower quality.

l 2. Region ll examiners have been very

3rompt in getting back to us when we have l a question even though you may be at a l remote ocation.

l l

l 3. The cuality of the communications has

! been good. A I of t1e examiners tlat l l have talked to lave been thorough, arecise j and have performed listening checks to l

! l 4

j- l i

4 verify that the correct messages were sent ,

i and received. I would however, like to see 1 l more communications by e-mail where i appropriate. That would help ensure the  !

clarity of the communications even more. l

)4.

With resaect to the exam specifically; there were a number of changes that were made j and we had to transmit those by expensive

! overnight or next day de ivery. If we could l figure out a secure e-mail method it would

save all of us numerous headaches as well l 1 as dollars.

i j 5. During my first face-to-face meeting with

! the C1ief Examiner (to review craft exam j materia ), I gained much-needed insic ht j

into his ex3ectations. T1is a leviated much

! stress on my aart and, from then on, the l 3rocess went much more smoothly. The

] Chief was very 1elaful during subsecuent i teleahone conversations and our second 4

i

! meetinc in Atlanta. He was very easy to j

4 work with and very understanding

{ concerning my inexperience in this l process. His aatient guidance was the key

) -to our success in this endeavor. Next time,

with al we've learned, we'll do even better. l i

I 6. The biggest problem that I encountered l during that exam came from the written  !

, portion that was being developed ay the contractor. Since he had written exams  !

j before, I assumed tlat the quality of l questions he was submitting to us were the j quality of questions that were acceatable to l

-the NRC. We reviewed his work, made j

technical corrections ancl assumed that the j c uestions wou d be accepted by the NRC.

I had very itt e communication with the j NRC on the subject of the written exam j and a great dea o" communication on the i subject of the operating exam. W1en t1e i submittal was fina y made, the focus went i

b_ __ _ - - -

i to the written exam and most o" the l communica': ion was made over saeaker

! 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 i pain"ul process and could have been l avoided had I not out so much fait, in the j contractor's exam writing experience and j communicated more on t1e subject of the l written exam with the chief. We had a 100% pass rate on the exam, but the exam l re3 ort was brutal in the area of the written l exam.

i

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

)

l8. 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 aerson ratler tilan over t1e phone. I 3 an for four or five trias between the start of

l 1

deve oament and prep week. It may sound i<e over<ill, but it works (It's also safer in t1e area of security).

10.'Suomit materia early (especially tie written). I i<e to have t1e written exam a J done deal arior to the actual submitta date.

11. You can never talk to the Chief Examiner too mucl. During the process, I tal< to him more than I talk to my motler.  ;

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

~early submittal of materials is the key to a successful NRC exam.

13. ALL 3roblems/ changes must be reso ved at the leve o" the examiner and t1e utility rep. In no case s1ould aroblems/ changes be re3orted/ escalated to senior management of the utility or NRC unless

1 1

both the examiner and the utility rep are at an absolute, and mutually ac reed, l impasse.

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14. We often felt t1at we were working in the  !

dark, writing questions on toaics you may I not want (as we were waiting for comment  ;

on our skyscrapers), aossibly wasting resources, but seeing no other option to l meet our rec uired cast-in-stone deadlines.

15. It's difficult to keea JPMs short and alausible at the same time.  :

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16. What is a good " admin JPM", especially for '

ROs?

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j yue3uuu: iv l 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. ,

i Where will thermal power and RCS Tavg stabilize in response to the dropped rod without  ;

any operator action?

A. Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod.

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

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

D. React.or 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.

l Answer:

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

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,, Keterence Page i l

SRO Question 10 RO Question 10 SRO Tier / Group 111 RO Tier / Group l/2 SRO Importance 3.7 ROImportance 3.2 10CFR55.43(b) 10CFR55.41 8 frem Addressed item Addressed XA Number 000003AKl.01 XA Statement Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Reason for turbine fcilowing 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 1

l ' Question Source New Justification (A) Select if he does not recognize that rods will step out to j restore temperature and power was restored due to the '

previous decrease in temperature.

(B) Select if he recognizes that rods will step out, but the decreased temperature adds positive reactivity to restore  !

power.

(C) CORRECT - Power will initially decrease du'e to the dropped rod. As power decreases, temperature will decrease. As temperature decreases, positive reactivity is added to restore power. Bank D rods in auto will cause rods to step out. Rods stepping out will restore power and temperature to the original value.

(D) Select if he recognizes that power was restored due to the l previous decrease in temperature, but does not recognize that i

i rods will step out to restore temperature and

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.,-.n - - ' ~ ~ '

INITIAL EXAMINATIONS '

QUESTIONS AND ANSWERS TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 RICK BALDWIN GEORGE HOPPER  :

I 6

e 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, B'VR/PWR, RO/SRO EXAMINATION OUTLINES, and ES-401-6 Written Examination Quality Assurance Checkoff Sheet."

t 2

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OBJECTIVES -

O BEi i ER EXAMINATION PRODUCT G LESS NRC/ FACILITY REWORK G SHARED EXPECTATIONS l

3

SESSION OBJECTIVE: -

To review validity concepts affecting the NRC .

written examination for the purpose of:

Instructing licensee personnel toward i

construction of more VALID and CONSISTENT NRC license examinations.

A l

m COVERAGE G 3 Levels of Validity 9 3 Levels of Knowledge e Discrimination, Sampling 9 Psychometrics 5

i VALIDITY -

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 j been outlined in the objectives.

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3 LEVELS OF VALIDITY O Content 9 Operational O Discriminant t

7

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.i OPERATIONAL VALIDITY ' i i

Addresses two aspects:

i i

1. Is the test item important to be known as a l part of the- operator's job?

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

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DISCRIMINANT VALIDITY Addresses:

O The cut score is the performance level that we use for making a pass / fail decision 80 percent.

e 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. -

10

o VALIDITY

SUMMARY

1. The exam must be content valid, encompassing job safety significance and sampling. .

2. The test item should be operationally oriented: a expected mental or psychomotor requirement of the job. The items should be written at the comprehension or analysis level vice simple memory. Items that measure problem solving, prediction, analysis i which are essential to job performance.

II

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VALIDtTY

SUMMARY

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

Meaning the test items as written should

provide opportunity for at least 80 percent

of the candidates taking the test should l

answer the item correctly.

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3 LEVELS OF KNOWLEDGE  !

i Bloom's Taxonomy 9 Analysis, Application, Synthesis O Comprehension i

t G Fundamental (simple memory) i I

13

~!

l LEVEL OF KNOWLEDGE .

i O Bloom's Taxonomy, N~RC Reference Benchmark to classify levels of knowledge.

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

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

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LEVELS LEVEL 1  :

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

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

15

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

, including consequences or implications.

I 16

{

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-l LEVEL 3 .

Analysis, synthesis, and application testing is more active and product-oriented testing which involves the multi-part mental process ,

of assembling, sorting, or integrating the parts so that the whole, and the sum can be used to: predict and event or outcome, solve a problem or create something new.

i i.e. using knowledge to solve problems.

17

DETERMINANTS OF DISCRIMINATION I I

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O Level of examination knowledge O Level of examination difficulty 9 Passing Score e item bank use 18

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NATURE OF EXAMINATIONS AND TESTS I

O TESTS are samples of PERFORMANCE 9 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 j untested areas.

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

19 i i

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 20

006 Emergency Core. Cooling System-/ JPM 136 Recovery From Safetylnjection

.and Solid Water Conditions '. > '-

Question 2:

Given the following plant conditions:

Unit 2 was operating at 100% power.

The plant experienced a large break LOCA with a failure of the ECCS system.

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

Core exit TCs are 720*F and increasing.

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

a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators? -

b.) Why is this action taken?

References Allowed? YES X NO Answer:

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

Reference:

KA: 006G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs.

OPL271C398 pg 12-15 Applicant Response: SAT UNSAT __

l *

. . 1

' - C.1 INADEQUATE CORE COOLING Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I

NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is j less than 1920 psig will prevent an inadvenent MSIV closure and keep I the condenser available for steam dump.

. After the low steamline pressure SI signal is blocked, main steamline isolation will j occur if the high steam pressure rate is exceeded.  :-

l

. S/G depressurization at the maximum rate may cause S/G narrow range levels to

~

drop to less than 10% [25% ADV]. This is acceptable and expected for tnis

. . inadequate core cooling condition.

- 14. DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:

a. WHEN RCS pressure less than 1920 psig, THEN PERFORM the following:

1) BLOCK low steamline pressure SI. 7

2) CHECK STEAMLINE PRESS ISOL/S! 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 atmosphere relief (s).

IF local control of atmospheric relief (s) is necessary, THEN DISPATCH personnelto dump steam USING EA-1-2, Local Control of S/G PORVs.

(Step continued on next page.)

4 Page 13 of 19

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

. Pressure 4 Place RHR Spray.in Service +- -

Question 2:

Given the following plant conditions: i Unit I has tripped from 100% power due to a LOCA. j Containment pressure is 3.0 psid

)

Tiansfer of Containment Spray pump suction to the containment sump is being performed in accordance with ES-1.3, Transfer to RHR Containment Sump. ,

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

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

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License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A'.1: Shift Staffing '

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• Question 1: A licensed RO has been off-shift for 6 months teassist in scheduling an upcoming outage. He had his last physical examination 18 months ago and has had satisfactory performance in the licensed operator requalification training program.

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

Can the RO fillin for the vacationing RO? Why or why not? w References Allowed? YES _.X_.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 A (2.3/34)

Applicant Response: SAT UNSAT i

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l I l:

License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet '

A.1: Shift Staffing  !

J l 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 1 l shift RO. He had a satisfactory physical examination 18 months ago and has l

l maintained satisfactory performance in the licensed operator requalification training i program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of a sMR RO.

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

. vacationing RO? #

i 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.

1

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

t e

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Given the following conditions:

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

2. All systems responded as expected.

~

2. The performance of E0P-04 is in progress.

3. One Steam Generator has been isolated.

4 All RCPs have been stopped.

5. RCS cooldown using natural circulation is in progress.

Which One of the following describes the concern associated with the isolated

.SG pressure prior to placing the RCS on SDC?

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

b. The strategy during the performance of E0P-04 is to maintain the affected SG pressure slightly less that RCS pressure to prevent secondary water entering the RCS.

c. Since the RCS cooldown rate was maintained greater than 30deg/hr, the affected loop has not been cooled sufficiently to allow SG depressurization.

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

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Reactor Operator Exavination l 65. Given the following conditions:

p-The reactor has experienced a Steam Generator Tube Rupture.

l l All systems responded as expected.

l The performance of EOP-04 is in progress.

One steam generator has been isolated.

RCS cooldown using natural circulation is in progress.

l

- Which ONE ofthe following describes the concern associated with the affected SG pressure prior

[

t to placing the RCS on SDC?

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

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

resulting in a dilution.

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

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

5 l

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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 eacn emergency bus 5 minutes after it is energized by the diesel.

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

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

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

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

electrical lineup and all equipment is operable,

a. Only one charging pump is automatically started on each emergency bus 5 minutes after it is energized bythe diesel. I i

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

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

d. Only one charging pump is automatically started onto each emergency bus immediately after it is energized by the diesel. t P

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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?

l The charging pumps will: l i

a. trip on low oil pressure.

I b. trip on low suction pressure.

c. automatically align to the RWT.

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d. continue to run and become gas bound.

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Reactor Operator Examination

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

The charging pumps will:

a. trip on thermal overload.

b. trip on low suction pressure.  !

c. automatically align to the RWT.

d. continue to run and become gas bound. '

... . . . . . . . . - - . . ...--. - - - =-

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-cw- p p- - _-_ y

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 1 inlet temperature to the cooling coils is greater than 100 deg F.

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

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Reactor Operator Examination

'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 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.

I

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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d

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13. Given the following plant conditions:

. Unit 1 was at 73% power l . A reactor trip / safety injection on low steam line pressure o: Curred 21 minutes ago l.,

. Average Core Exit TC temperature is 375'F

. RCS pressure is 225 psig

. All S/G pressures are DECREASING slowly l

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

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

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

. Total feedwater flow is 340 gpm

. PZR levelis 37% and INCREASING

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

. Containment pressure is 5 psid and INCREASING slowly ,

At this po nt, which ONE of the following Critical Safety Functions is the MOST degraded?

a. Heat Sink

b. Core Cooling

c. Containment

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

Reference:

E-0, Foldout Page Objective: OPL271C395, B.1 4

Level: Analysis Source: 000040K101 001 History: Stem and distra ters a and d modified (7/7/98)

Note: Provide PTS curve with this question.

1 Justification:

a. Correct answer because all S/G levels are Jess tnan 10% NR and total feeowater fiow is less than t.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 than 12.0 psid.

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

b

13. Given the following plant tendi: ions:

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

. *F Average Core Exit TC temperature is y3 #

. RCS pressure is,22fpsig iW

. All S/G pressures are DECREASING slowly l

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

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

. #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 y At this poin , which ONE of the following Cntical Safety Functions is the MOST degraded?

a. Heat Sink

b. Core Cooling

. Containment

d. Pressunzed Thermal Shock Answer: A K/A: 000040K101 (4.1/4.4]

Reference:

E-0, Foldout Page Objective: OPL271C3g5 B.1 Level: Analysis ,

a

's Source: 000040K101 001 History: Stem and distracters a and d modified (7/7/95)

Note: Provide PTS curve with this question.

Justrii:ation:

a. Corre:t answer because al! S/G levels are Jess tnan 1D% NR and total feedwater flow is less than 440 gpm.

b. Incorre:: because RCS temperature is 325'? (: ore exit T/Cs less inan 1200'F).

c. In:ctreet oe:ause con:ainment pressure is less inan 12.0 psid.

d. incorrect because RCS tempers:are is 225'F (T-5cid is greater inan 250'F) i /

- . . .,*, W~ k

,.A.c $9./4 ' <' -~ '- - " ' ' '

,.I

' a .c .~ = %s c.h T d A,b u. i tyh'i

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' }' lr.:yu Q4/

l

.j.(, g ,i / :. , .a w W 2 = '*'^, -

{. A -e 1

l e l \

t I

20. Given the following plant conditions:

. The control room has been evacuated due to a fire

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

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

. The TDAFW pump has been shut down

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

a. The TDAFW pump will automatically restart when 2/4 steam generators reach low low level.

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

levels at 33%.

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

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

Answer: B K/A: 000058A102 (4.3 / 4.5]

Reference:

AOP-C.04, page 11 Objective: OPL271C423, B.4 Level: Comprehension Source: 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)

Note: Selected from@ exam bank with minor modification of text I

i

-- - i.

20. Given tne fo!!owing p! ant condmons:

. The control room has been evacuated due to a fire

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

. t/DAFW pumps 1 A-A and 18-B are injecting into the steam generators

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing 4 s G w 4 r- La el M\ L. oh[ 3M /t4 -C.M C

Which ONE of the following describes the recorns; s: i.n: ed.ciy .isd.vate*-system?

~

x The TDAFW pump will automatically restart whan 2/4 steam generates reach low low level e ~ E k **

• Ook # u 5'dJ) e 6n -M/ .

TCo

b. The f4DAFW pump leve! control valves will automatically control steam generator ,

, levels at 33%.

'9 The f4DAFW pump level control valves will have to be manually adjusted using the tAanual Output Adjust in the L-381 cabinet.

/W

,Yg#

~

y

d. The discharge pressure for the (ADAFW pumps will r ave to be manually adjusted oy tnrottf:ng tne manual valves at the LCVs.

, L/ M

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

Reference:

AOP-C.04, page 11 Objective: OPL271C423, B.4 Level: Comprehension Source: 00DD5BA102 001 H: story: Used on 9/97 RO NRC exam Text modified to Octrett grammar errors. Disterers a, b, c, and d reorcered (7/22/98). Distracter be restructured (7/29/98)

Note: Selected fromMexam bank with ruinor modification of text l

23. Given the following plant conditions:

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

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

. NO Feedwater / Aux Feedwater is available

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

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

~

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

b. Depressurize allintact S/Gs to atmospheric pressure to dump ace'amulators,

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 level in any 2 S/Gs is less than 60%.

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

Reference:

FR-C.1, pages 10 & 17 Objective: OPL271C398

! Level: Comprehension Source: MExam Bank 101. 000074K307 001 History: Used on HLL 5807 practice exam Distracters b and c reordered Note: Selected frohM. exam bank without modification of text l

\

l a

1 i

I l

1 l

A. g INADEOUATE CORE COOLING FR-C.1

- Q Rev. 8 l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

CAUTION Use of a Faufted or Ruptured S/G during performance of the following steps may compound the emergency situation. When NO intact S/Gs are available, a Fautted or Ruptured S/G may be used. '

12. MAINTAIN intact S/G narrow range  :

levels:

a. Greater than 10% [25% ADV) a. MAINTAIN total feed flow ,

greater than 440 gpm l UNTIL level greater than 10% [25% ADV) l in at least one S/G.

l l

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

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

,, 2) GO TO Note prior to Step 21.

b. Between 10% 125% ADV) and 50%.

~

1 f

Page 10 of 19

FR-C.1

-- INADEQUATE CORE COOLING Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

NOTE RCP darnage due to absence or loss of normal support conditions is an acceptable consequence in this procedure.

21. CHECKif RCPs should be started: I

~

a. CHECK core exitT/Cs a. GO TO Step 22.

' greater than 1200*F. f l

1

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

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

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

. FSV-68-394

. FSV-68-395

. 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 ci 19

. l

23. Given tne following plant conditions:

. FR-C.1, *lnadequate Core Cooling". has been entered due to a RED path on Cc e Cooling

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

. NO Feedwater / Aux Feedwater is available i

. At step 12. the CRO checks the S/G NR levels and reports an are <10%. l 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. #

g Port \l.s a SL o t k \/M.5

d. PreparMaNCC Ic=J m JGeeck.-WR-4eveHrr-eny-24/Gs4s4ess-tharts0%

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 k/R $ , W '

• M

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 1:ip bypass switch for N-35 to the bypass position Which ONE of the following describes the effect of this failure and action during the remainder of the shutdown?

a. The reactor will automatically trip when the Power Range channels decrease below the P 10 setpoint.

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

c. Both Source Range channels, N-31 and N-32, must be manually energized when the operable intermediate Range channel (N-35) decreases below the P-6 setpoint.

d. Source Range channel N 32 must be manually energized when the operable intermediate Range channel (N-35) decreases below the P-6 setpoint, Source Range channel N-31 will automatically energize.

Answer: C K/A: 015000K407 [3.7/3.B]

Reference:

AOP-1.01, page 10 ES-0.1, page 13 Objective: OPL271C352, B.4 Level: Comprehension Souice: 015000K407 001 History: Not used on 9/97 or 5/98 NRC exams. Not used on practice exam.

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

l l

s ,

7/M' M [l_,d'/ O!&/#N?-- /W WW"W W$ / /

1I 3[ l

49. Given the following plant conditions: , ,

l '{,

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

. Intermediate Range N-35 failed high _ _\

F Operators placedinc 00*Mpasswt: Morn =35mhe Dypadss Which ONE of the following describes the effect of this failure and action during the remainder of ,

the shutdown? l

a. The reactor will automaticallyinp when the Power Range channels decrease below l

. the P-10 setpoint. I l

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.

)

I

d. Source Range channel N-32 must be manually energized when the operable l Intermediate Range channel (N-35) decreases below the P-6 setpoint; Source Range

channel N-31 will automatically energize. '

Answer. C K/A: 015000K407 [3.7/3.B]

Reference:

AOP-tol, page 10 ES-0.1, page 13 Objective: OPL271C352, B.4 Level: Comprehension Source: 015000K407 001 History: Not used on 9/97 or 5/98 NRC exams. Not used on practice exam.

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

\

e g, ,,pn

, '?- O C. b l

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

l i

35. Given the following plant condrtions:

, . Unit 2 is operating at 29% power in accordance with 0-GO-6, Power Reduction From '

30% Reactor Power to Hot Standby

,- . Unit 2 will be going to Cold Shutdown for maintenance

. Intermediate Range N-36 has just failed high Which ONE of the following actions must be performed before reducing reactor power below 10%7

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

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

c. Remove N-36 instrument power fuses.

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

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

Reference:

AOP-1.01, page 10 & 13 Objective: OPL271 C352, B.4 Level: Analysis Source: New Question (Developed 7/15/98) .

Justification:

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

b. Correct because placing the level trip switch in BYPASS prevents high reactor trip when the low power reactor inp signal is reinstated at the P-10 setpoint (10% power).

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

d. Incorrect because a manual reactortrip for the given conditions is not required. Placing N-

! 36 leveltnp switch in BYPASS allows an orderly reactor shutoown.

l

.2 1

50. Given the following piant conditions:

. Large Break LOCA is in progress f . RCS pressure is 550 psig

. Exosensor indicates 25'F superheat

. No RCPs are operating i

Which ONE of the following indications would the operator use along with RCS pre.,sure to  !

accurately substantiate core cooling?

! a. Reactor Coolant Tavg value. I

b. Average value of all core exit thermocouples.

l

c. Hottest Reactor Coolant wide range Thot value. r  !

d. Average value of five hottest core exit thermocouples.

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

Reference:

FR-0, page 3 l OPL271C044, page 7, A.1.c i Objective: OPL271 C044, B.1.b Level: Memory Source: 017000A402 001 History: Used on HLC 9809 practice exam Distracters a, b, c, and d reordered (7/22/98)

Note: Selected fr m xam bank without modification of text en 1

f

1 1

1 1

)

50. Given tne following plant conditions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig

. . Exosensor indicates 25'F superheat j . No RCPs are operating i

l Which ONE of the following indications would the operator use along wnh RCS pressure to accurately substantiate core cooling? - ., , ,

, , . _ ~

n_;- _= _

-- - _ _ , a . 9

',,g,f ;q

Y ~ Read =iC 4 5ntf &

:! E -- 7 / ,,J W M'*' '*

1

, t 72:. /.htr~ are c.?

b. Average value of all core exn therrnoccupies.

l

c. Hottest Ree: tor Coolant wide range Thot value. -

c. Average value of five hottest core exit thermocouples.

Answer

D -

&W K/A 017000A402 ym p,' o#w ne.

{3.8 / 4.1) l

Reference:

r -R-0, page 3 i=f2- O. 2-OFL271C044, page 7, A.1.c l

l Objective: OFL271 C044, B.1.b

Level

Memory Source: 017000A402 001 History: Used on HLC 9809 practice exam l Distracters a, b, c, and d reordered (7/22/98)

Note: Selected from eram bank without modification of text l

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l

s S~a F

t=h e *~ 4 4 hU m 2 9 g" cE e5 8E 8E 85 gg gg g ce..

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, . . . . . . - . - - . . - - - - . - - - - . - - ~ - . - . - . . . . . . - . . .

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i l

88. Given the following plant conditions:

l

. Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a

, powerincrease to 100% in progress

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

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

l a. Immediately stop the power increase.  ;

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

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 3 l GTANDBY 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 [3.7/3.8}

Reference:

SSP-12.1, Page 31 l Objective: OPL271C209, B.2 l

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

! Note: Provide copy of Technical Specification 3 5.1.1 wrth the question (exam) i Justification:

a. Correct becausegJConduct of Operation (SSP-12.1) restricts power increase when in an LCO action of e nours or less. RCS loop 1 accumulator boron concentration cf 2390 ppm boron places Uri 1 in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO.

l 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 wrthin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, pressurizer l- pressure must be reduced to 1000 osig or less by 1400.

e t

i t

3 /4. 5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS COLD LEG INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION 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 between 600 and 683 psig, and R184

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

APPLICt JT1: MODES 3, 2 and 3.*

ET_LON -

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 HDT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure,to 1000 psig or less within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With one cold leg injection accumulator inoperable due to the boron concentration not within limits, restore boron concentration to within.' limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to 1000 psig or less within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• Pressurizer pressure above 1000 psig.

l 4

Dece ber 27 1991.

Amendment No. 113, 131, I

- UNIT 2 3/4 5-1 i

1

1. / .

f)}fb Q {_')l$.Y, '/! -

l 1

88. Given tne following pfant conditions: l

. Unit 2 operating in a:Cordance wrth 0-GO 5, Normal Power Operation at 73% with a )

I powerincrease to 100% in progress Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm

.j

,g A

/,j Current time is 0100 4-/

• Which ONE of the following actions must be taken? l I

a. Immediately stop the power increase. ,

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

to 2400 to 2700 ppm boron.4 .1 hcun he sw 72 4 ou 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

• 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: OPL271 C209, B.2 Level: Comprehension Source: New question (Developed 7/20/98)

Note: Provide copy of Technical Specification 3.5.1.1 witn the ouestion (exam) i Justification:

a. Correct becaus onduct of Operation (SSP-12.1) restricts power increase 1 when in an LCO acuan ci o nours or less. RCS loop 1 a::umulator coron concentration of l 2390 ppm boron places Unit 1 in a 1 hout LCO.

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

c. in:orrect because if loop 1 boron concentration is not restored witnin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the Unit 1 j mus* be in HOT standby by 0800.

)

1

d. in:orrect because if loop 1 boron concentration not restored witnin 1 nour, oressurizer l pressure must ce redo:ed to 1000 psig or less by 1400. I 1

~

l

• l

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v wA e, ; - s,: :; .:

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4

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l

\

i 006 Emergency Core Cooling System J JPM 136 -Recovery From Safetylnjection

.and Solid Water Co'n'ditions'.J ~ ~ "" ~

l l

Question 2: ,

! Given the following plant conditions: I

! Unit 2 was operating at 100% power.

The plant experienced a large break LOCA with a failure of the ECCS system.

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

Core exit TCs are 720*F and increasing.

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

1 a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?

b.) Why is this action taken?

l

! References Allowed? YES X NO Answer:

i a.)To reduce RCS pressure below 125 psig

b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.

l

Reference:

KA: 006G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs. i OPL271C398 pg 12-15 Applicant Response: SAT UNSAT._

/

I l

1 1

1 t

l

- l INADEQUATE CORE COOLING STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 1

NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is less than 1920 psig will prevent an inadvertent MS!V 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 depressuriration at the maximum rate may cause S/G narrow range levels to

~

drop to less than 10% [25% ADV). This is acceptable and expected for tnis inadequate core cooling condition.

14. DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:

~

a. WHEN RCS pressure less than 1920 psig.

THEN PERFORM the following:

1) BLOCK low steamline pressure St. e

2) CHECK STEAMLINE PRESS ISOL/SI SLOCK RATE ISOL ENASLE permissive LIT.

[M-4 A, A4)

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

IF local control of atmospheric relief (s) is necessary, THEN DISPATCH personnel to dumo steam USING EA-1-2, Local Control of S/G PORVs.

(Step con:inued on next page.)

Page 13 of 19

i l

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

.PressuredP] ace RHR Sp'my.in Service % ~

O Question 2:

Given the following plant conditions:

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

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

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

l 1

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

containment sump?

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

References Allowed? YES X NO i

i 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 mnning a CS pump without a source of water.

1

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

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License Applicant Administrative Walkthrough Examination--NRC-1 l

l Examiner Sheet '

l 1.1:? Shift Staffing '

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Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming l outage. He had his last physical examination 18 months ago and has had j" satisfactory performance in the licensed operator requalification training program.

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

_ Can the RO fill in for the vacaticaing RO? Why or why rot?  %

1 References Allowed? YES _2L 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.

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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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License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A.1: Shift Staffing' w.

l 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 I shift RO. He had a satisfactory physical examination 18 months ago and has l maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shins in the control room as the OATC during the past month under the direction of i a shift RO..

What additional requirements must be met by the RO Sefore 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 K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT UNSAT l

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