Text

Refers to 991105 Training Managers Conference Conducted at RB Russel Bldg.Agenda Used for Training Conference & List of Attendees Encl.Goal of Providing Open Forum for Discussion of Operator Licensing Issues Was Met
	ML20199E708
Person / Time
Site:	Sequoyah
Issue date:	12/23/1998
From:	Peebles T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Driscoll R; TENNESSEE VALLEY AUTHORITY
References
	NUDOCS 9901210058
	Download: ML20199E708 (102)
	v • d • e

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% l December 23, 1998 Tennessee Valley Authority ATTN: Mr. Richard F. Driscoll Training Manager Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, TN 37379-2000

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - SEQUOYAH NUCLEAR PLANT

Dear Mr. Driscoll:

This letter refers to the Training Managers' Conference conducted at the Richard B. Russell Building on November 5,1998. Representatives from all utilities in Region 11 participated in the meeting.

Enclosure 1 was the agenda used for the Training Managers' Conference, and Enclosure 2 is the list of attendees. We appreciate the participation of you and your staff and believe that the goal of providing an open forum for discussion of operator licensing issues was met. Mr. Gallo, Chief of the Operator Licensing and Human Factors Branch, Office of Nuclear Reactor Regulation (NF.R), 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

.00073

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Thomas A. Peebles, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety Docket Nos.: 50-327 and 50-328 License Nos: DPR-77 and DPR-79 i

Enclosures:

As noted

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cc w/encls:

M. Bajestani, Site Vice President, /

Sequoyah Nuclear Plant 9901210058 98122337 PDR ADOCK 05 azYs

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TVA 2 Distribution w/encls:

PUBLIC B. Michael, DRS

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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 Bu;' ding Auditorium 1 Thursday.11/5/98 l 8:00 a.m. Conference Registration ,

8:20 a.m. Introduction Thomas A. Peebles, Chief, Operator Licensing & Human Performance Branch i

8:30 a.m. Opening Remarks William Travers, l Executive Director of Operations l 8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety l 9:15 a.m. break i

9:45 a.m. Other Issues Robert M. Gallo, Chief 1 Operator Licensing Branch, NRR l

10:15 a.m. I.essons 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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l 1:00 p.m. Written Examination Questions and Answers Rick Baldwin / George Hopper j l

2:30 p.m. JPM Examples of questions Rick Baldwin / George Hopper I l

3:30 p.m. Open Session - Other Issues Training Managers 4:00 p.m. Meet with Principle examiners All 4:30 p.m. Adjorn 1

.a. , n.n.. _..m .~.,.s,.-~.a-. ~-~a-nu&- =.-~suu-~~~~ ~ ~ a+a ~>* + " - - ' - - -

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l l License Applicant Administrative Walkthrough Examination--NRC-1

l Examiner Sheet A.1: Shift Staffing ' i i

l Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is l

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

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

l l

Reference:

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

Applicant Response: SAT UNSAT i

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

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

William Noll BK Ops Tmg Supv l Max Herrell BK Trng Mgr l Scott Poteet RB Exam Team Leader I Ralph Mullis BK Ops Mgr i Tony Pearson BK Ops Tmg j Anthony Williams RB Tmg Mgr i

Crystal River - FPC Wes Young CR Supv OpsTng i Tom Taylor CR Dir Nuc Ops Tmg l Ivan Wilson CR Ops Mgr l Ken McCall CR Mgr Ops Tmg Duke Power Gabriel Washbum OC Req Team Leader Ronnie B. White, Jr MG Tmg Mgr l

W. H. " Soap" Miller CT Site Tmg Mgr 1 Paul Stovall OC Mgr Oper Tmg l

Bentley Jones OC Tmg Mgr l l James Teofilak CT Ops Tmg Mgr

! Alan Orton MG Ops Tmg Mgr

' l Richard Bugert Corp Ops Tmg Spec l

FP&L Maria Lacal TP Tmg Mgr Dennis L. Fadden SL Services Mgr -

l Jo Magennis Corp Tmg Assessment Spec Tom Bolander SL Exam Development i Steve McGarry TP Maint Tmg Supv Southem Nuclear (SNC)

John C. Lewis HT Trng & EP Mgr Bill Oldfield FA Nuc Ops Tm Supv

> Steve Grantham HT Ops Trng Supv Scott Fulmer FA Mgr Tmg & EP Joel Deavers FA Sr Pit Inst Bob Brown VG Tmg Mgr Dan Scukanec VG Ops Tmg Supv ,

1 l

l ._ , ,

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

Virainia Power Steve Crawford NA Sr Inst Nuc Harold McCallum SR Supv Ops Tmg TVA Dick Driscoll SQ Tmg Mgr Walt Hunt SQ Ops Trng Mgr Denny Campbell BF SRO Ops inst Jack Cox WB Tmg Mgr John Roden WB Ops Tmg Mgr Tom Wallace WB Ops Supt V. C. Summer - SCE&G j AlKoon SM Ops Trng Supv i

1 NRC Particioants l Tom Peebles R 11 Operator Lic. Br. Ch.

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

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

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

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FY 99 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 RO SRO-l SRO U TOTAL D:te Plant Chief Pass # Pass # Pass # Pass #

4 4 4 4 ;

9/28/98 Sequoyah GTH 10/5/98 Harris RFA 2 2 5 5 7 7 11/30/98 Oconee GTH 2 2 5 5 7 7 11/30/98 St Lucie & RSB 6 3 9 12/14/98 1/25/99 McGuire & DCP 6 3 2 11 2/8/99 2/8/99 C. River & GTH 6 6 12 2/22/99 2/8/99 B. Ferry MEE 4 1 5 l

3/29/99 Surry & RSB 5 2 4 11 4/12/99 4/12/99 Watts Bar & MEE 6 3 5 14 4/26/99 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 l

07/26/99 Robinson MEE 3 2 2 7 08/30/99 Turkey Pt & RFA 20 20 9/13/99 136 l

RESULTS TO DATE 4 4 5 5 9 9 18 18 ,

i 100 100 100 100 No initial exams scheduled for: Brunswick, North Anna and Vogtle

! FY 00 region 11 write part of Summer & Hatch l

l 1

FY 00 INITIAL, EXAM SCHEDULE AND RESULTS tc ,mber 14,1998 I I

RO SRO-l SRO-U TOTAL D:ta Plant Chief Pass # Pass # Pass # Pass 0 9/27/99 Summer GTH 6 6 region ll write 10/18/99 Hatch DCP 10 2 12 region II write 12/13/99 Vogtle RSB 3 5 '2 10 2/14/00 Brunswick & DCP 12 3 15 2/28/00 1 03/**/00 Oconee 7 10 704/10/00 Harris <maybe 10/co) 10 705/03/00 St. Lucie GTH 6 5 11 705/"/00 B. Ferry 6 3 3 12 l 705/03/00 McGuire 4 8 12 706/07/00Farley RSB 10 2 12 707/26/00 Crystal River RFA 3 3 3 9 l region 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 j P dzignates tentative No Initial exams scheduled for: Catawba Robinson Turkey Point l Watts Bar I

1

l Operator Licensing lSSueS .

Region 11 -

Training Managers' Conference November 5,1998 Robert M. Gallo, Chief Operator-Licensing and Human Performance Branch

l- OPERATOR LICENSING i

ISSUES l -

i j o Part 55 Rulemakings _

t Status i

Schedule i

i o

Final Revision 8 of NUREG-1021 o

Examination Quality and Results ;

i, ,

! 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)

9 RECENT LESSONS LEARNED by

. Charlie Payne Southeastern Training . Manager's Conference

' November 5,1998

PC1LICY GLARIFICATIONS 9 in general, the NRC prefers that the written exam be administered after the operating tests are complete.

Allows more time to finalize test.

More flexibility if delays occur.

Less stressful on candidates.

I 2

i

I POLICY CLARIFICATIONS .

O In general, license class sizes of areater than B candidates will be scheduled for 2 weeks as follows:

1 St exam week off-week for documentation of week 1 performance 2"d exam week 3

PC1LICY CLARIFICATIONS 9 Examination suamittals - 2 copies of draft and final exams (written, JPMs, and simulator -

scenarios). Electronic copy is also desired.

i O 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 c uestions sampled ,

- - _ = _ - ._ -

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

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

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

5

2.0 GENERIC KNOWLEDGES AND ABILITIES l

l 2.1 Conduct of Operations l

2.1.1 Knowledge of conduct of operations requirements.

l (CFR: 41.10 / 45.13)

! -- IMPORTANCE R O 3.7 SRO 3.8 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

~

(CFR: 41.10 / 45.13) -

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

(CFR: 41.10 / 45.13)

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

M (CFR: 41.10 / 43.2)

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

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE R O 2.3 SRO 3.4 i -

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 2-1 WJREG-1123 Rev. 2 l

_. ___ ~. . _ _ _ _ . _ _ _ _ _ .._. _ . _ _ _ _ _ _ _ _ .

2.1 Conduct of Operations (continued) l l

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

l (CFR: 45.12) i IMPORTANCE RO 3.0 SRO 3.0

?

i l 2.1.20 Ability to execute procedure steps.

l (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE l RO 4.3 SRO 4.2 -

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l 2.1.21 Ability to obtain and verify controlled procedure copy.

(CFR: 45.10 / 45.13) l IMPORTANCE RO 3.1 SRO 3.2 l 2.1'.22 Ability to determine Mode of Operation.

i 0 (CFR: 43.5 / 45.13)

IMPORTANCE R O 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) l IMPORTANCE R O 3.9 SRO 4.0 l

l 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 45.12 / 45.13) I IMPORTANCE R O 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) t IMPORTANCE R O 2.8 SRO 3.1 i

I 2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotatmg eqmpment / electrical /

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

(CFR: 41.10 / 45.12) l IMPORTANCE R O 2.2 SRO 2.6 l

l 2-3 Z7 REG-1123, Rev. 2 l

]

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

(CFR: 41.10 /43.5 / 45.13)

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

(CFR: 41.10 /43.5 /45.13)

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.

M (CFR: 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

(CFR: 43.5)

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

W (CFR: 45.13)

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

(CFR: 43.5 / 45.11)

IMPORTANCE RO 2.2 SRO 4.0 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.

(CFR: 45.11)

^

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

(CFR: 45.11)

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

r (CFR: 43.5 / 45.11)

IMPORTANCE R O 2.3 SRO 4.1 l

NUREG-1123, Rev. 0 0-14 l

RE_C_ENT LE_S_ SONS LEARNED SRO-only Questions (Cont'd}

c. SRO-only questions wil 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.

6

ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Date of Exam: Exam Level:

K/A Category Points Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4

1. I MM. :W 3a en g%e.t W We m, - .;.au.g 26

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Emergency & mqg -2 L.,

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3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 + 't Note: -

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

Actual point totals must match those specified in the table.

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

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

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

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

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ES-401 BWR R0 Examination Outline Form ES-401-2 Facility: Date of Exam: Exam Level:

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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Plant 39 Systems 3 4 Tier 51 Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 13 l

Note: -

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

Actual point totals must match those specified in the table.

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

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

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

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

1 RE_C_ENT LES_S1DNS LEARNED ,

Sampling Criteria intent o" prodess is to avoid exam predictability.

1 a so to avoid excessive use of repeat test items.

first use systematic arocess to develoa samale plan using topics from K/A catalog, then use facility c uestion resources to accomp ish the alan. .

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RECENT LES_ SONS LEARNED Sampling Criteria (Cont'd) each topic in each tier & group should be sam aled at least once unless insufficient questions exist to do this. If all topics have .

been sampled once and other questions need to be selected, the process should be systematic and unbiased.

final sample plan should have a fairly even balance across all Ks & As. t 8

BEGENT LES_ SONS LEARNED -

Sam aling Criteria (Cont'd?

ua to 25 questions from last two l\ RC exams, facility licensee exams, tests & quizzes (exce at final audit test) may be used.

Chief Examiner (CE) has the option to unilaterally shift or change the se ected K/As.

up to 5 site-saecific priorities may be identified with CE concurrence (K/A value may be < 2.5 .

with sufficient justification).

i i

l 9 &

i

CTHER j Record Keeping per 10 CFR 55 are required to provide evidence that the applicant has successfully com aleted the facility licensee's requirements to 3e licensed as an operator.

this includes successful manipulation of the controls of t1eir facility. As a minimum,5 significant control manipulations which affect reactivity or power level.

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OTHER :

Record Keeping (Cont'd) this informatipn should be retained and available for inspection from time of license application to license expiration.

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11 i

OTHER -

Requal Control Manipulations 1 if have program based on SAT process, list in 10 CFR 55.59(cX3} does not need to be strictly followed.

should have sometling simi ar based on plant JTA and specific plant priorities.

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

r 12

C>THER Requal Control Manipulations (Cont'd) credit for accomplishment should only be given for active participa1: ion in the manipulation.

NOTE: control manipulations are not synonymous with reactivity manipulations. i l

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13

- _ . . - = . . . .

Examination Communications Examinatio:: Development Coordination By Ronald F. Aiello

i l Facility Suggested improvements j 1. The exam development team and lead l

! examiner shou c meet at the beginning of l l t1e development arocess to establish l common grounds for the development and l

! execution of the examination: l i i l

C1anges anc interpretations to the l NUREG.

l l

Scope of the exam develooment anc administration process.

l

Lessons earned from t1e last exam ac ministerec.

I

l

2. Move due cates for t1e out ine and t1e exam back to 90 and 60 cays prior to prep week. This will provide more time for examination review by the examiner (s).

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

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

5. T1e arincipal and the utility representative should meet early to establish a workinc relationship and exaectations. If possible this should inc ude sam ales o" c uestions, JPMs, etc.

6. The exam should have no outstancing issues /c uestions that arise and need repair at the last minute. These issues should all have been identified by the prea week, to allow time to ma<e clang 's that meet all the criteria.

7. The chief examiner should explain up

~ front all the forms in 1021 that need to be.

completed.

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

9. As soon as a Chief Examiner is assigned to an exam, the Facility Rep and the C1ief should verify the ability to communicate via all channels (including e-mail). When we converted to Lotus Notes, the facility was suddenly unable to senc e-mail to lis C1ief Examiner. This f

became somewhat of a lincrance anc sloulc be avoiced if oossible.

10. It would be helpfulif the Chief Examiner could arovide his schecule to the Facility Rep. This inc udes arovidinc uadates for any changes to the Chief Examiner's schedule along the way. The facility rep needs to be aware of when the Chief Examiner is availab e to assist in exam preaaration activities.

11. A face-to-face meeting s'1ould be promptly scheduled in order for ~he Chief to communicate his exaectations to the Facility Re3. The face-to-face rec uirement coulc be waived i' the Chief and the Facility Rep have previously wor <ec togetler and t1e Facility Rea is confident that le/she understands the Clief's exaectations. In any case, a

) .

conference ca I woulc be the minimum to satisfy this im aortant first step.

12. The Chief and the Facility Rep should work together to establish a firm scledule for the exam week (s). This will ensure the most efficient schedule is ceveloped (with respect to crew composition and personnel movement) to minimize the amount of exam material requirec.

13. The Chief Examiner and Utility Rep MUST remain fixed during the entire 180 day period. Handing off the responsibility is both disruative and destructive to communication. The expectations of the clief examiner must be defined / communicated ear y.

14. T1e "timeline" must be enhanced to identify saecific times anc cates for communication / working meetincs aetween

l the examiner and the utility rea. These j meetings slou d be " face to face" :o l assure expectations are understood, and j being met, early on. I i 15. If an examiner and a utiity rep have not j worked together before, the timeline for :

l " deliverables" must be expanded.

Working meetings (face to face) must be established for the examiner to review 5-10 questions,1 scenario,1 jpm,5 jam knowledge c uestions,5 admin questions, etc. to assure that the standards and ex3ectations are clear early in the process and that the utility can produce a product tlat meets the ex3ectation.

16. 398 and 396 forms need to be available electronically. We took the time to develoa an e ectronic version ourselves out I would arefer that the electronic master coales came directly from t1e NRC

l so that we have more conficence that everything is exactly t1e same. We wou c all benefit from this improvement. l l

17. 'A face to face working meeting of eig1t (8) ;

to twe ve (12) hours, approximately two '

(2) weeks before the thirty (30) day submittal must be established 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. Ex3ectations must be established early so that the utility clearly understands the rules and the examiners expectations. Small samales of develoament must be reviewed early to assure expectations are being met.

A face to face meeting, arior to the 30 day submittal, to resolve any/all issues must 3e scleduled suc1 that adec uate time (sug g est 2 wee <s) is available to reso ve

1 comments before the 30 day limit. No one wants to see 30 c uestions reviewed and the exam rejected. Saending ~24 hours in 3-4 face to face meetings is a sma l/ smart price to aay to avoid hundreds of hours of I re-development, the emotional stress on cancidates when the exam must be !

rescheduled and the impact on the plant i when candidates are not licensed to meet l plant needs.

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19. The "new" SSNTA format for JPM level of l detail is NOT what you have liked in the i

past and needs to be either acceated by the NRC as a standard or optimum format, or modified, or rejected. The JPMs we submittec to you were in the format and level of cetail you had found acceatable in the aast, and we were surarisec to finc that they needed significant last-minute rework l (additional level of cetail).

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20. Maybe Chief Examiners could send some copies of good written cuestions, JPMs, and JPM questions ua front that could help a new developer survive t1e exam writing process and see where you as an examiner are coming from. ,

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Facility General Comments

1. The limited number of NRC license examiners puts the Region and 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 l time you have to provide the licensee with feedback is very limited and results in a real struggle to ensure a c uality exam.

The limited resources and interaction time increases the risk of lower c uality.

2. Region ll examiners have been very prompt in getting back to us when we have a question even though you may be at a remote location.

3. The cuality of the communications has been good. A I of the examiners tlat I lave talked to lave been thorough, arecise and lave 3erformed listening clec<s to ;

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i l verify that the correct messages were sent l and received. I would however, ike to see j more communications by e-mail where l approariate. Tlat would help ensure the

clarity of the communications even more.

i I4. With respect to the exam specifically; there l were a number of changes that were made l and we had to transmit those by expensive j overnight or next day delivery. If we could j figure out a secure e-mail method it would l save all of us numerous headaches as well j

as dollars.

15. During my first face-to-face meeting with j the Chief Examiner (to review draft exam j material), I gained much-needed i~nsight into his expectations. This alleviated much l stress on my part and, from then on, the j 3rocess went much more smoothly. The

) Clie" was very lelafu during subsecuent i tele 3 hone conversations and our second

i- i j meeting in Atlanta. He was very easy to j work with and very understancing

! concerning my inexperience in this l process. His patient guidance was the key l -to our success in this endeavor. Next time, ,

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

l6. The biggest pro alem that I encountered i

during that exam came from the written j aortion that was being developed by the i contractor. Since he had written exams

! before, I assumed that the quality of l questions he was submittinc to us were the quality of questions that were acceptable to j the NRC. We reviewed his work, made j tec1nical corrections anc assumec that the i c uestions wou'd be accepted by the NRC.

I 1ad very little communication with the NRC on the subject of the written exam and a c reat deal of communication on the suaject of the 03erating exam. When t1e submittal was fina ly made, t1e focus went

i a a

i j to the written exam and most of the

! communication was made over s3eaker phones (about 40 lours). It became a very j aainful 3rocess and could have been j avoided had I not put so much faith in the i

contractor's exam writing ex3erience and !

communicated more on the subject of the !

! written exam with the clief. We had a l l 100% pass rate on the exam, but the exam report was brutal in the area of t1e written l i exam.

! 7. Know the chief examiners expectations i from the beginning (prior to any

develo ament).

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! 8. Never assume you know what you're doing l - the chief is just a pione call away.

! 9. It's 3etter to de iver material and review it in i

i aerson ratler than over tie alone. I 3 an for "our or five trias between the start of

i l develoament and prep wee <. It may sounc like overki , aut it works (It's also j safer in the area of security).

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! 10.' Submit material early (esaecially the i written). I like to have t1e written exam a

! done deal prior to the actual submittal date.

j 11. You can never talk to the Chief Examiner j too much. During the process, I talk to him 1 more than I talk to my mother.

) 12. The bottom line is that frequent l communication, personal contact, and j ~early submittal of materials is the key to a l successful NRC exam.

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13. ALL 3roblems/ changes must be resolved '

at the evel of the examiner and the utility rea. In no case should aroblems/clanges be re3orted/ escalated to senior 1 management of the utility or NRC unless

30th the examiner and the utility rep are at an a3 solute, and mutually ac reed, impasse.

14. We often fe t that we were wor <ing in the dark, writing questions on toaics you may not want (as we were waiting for comment on our skyscrapers), possibly wasting resources, but seeing no other option to meet our rec uired cast-in-stone deadlines.

i 15. It's difficu t to keep JPMs short anc

plausible at the same time.

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

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yuesnun; tv The unit is operating at 20% power with all systems in automatic. Bank 'D' control rods are at 120 steps. Control Bank 'C' rod H6 drops to the bottom of the core. No rod control urgent failure alarms occur.

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

A. Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg 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 1*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.

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

Answer:

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

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, Reference Page l

SRO Question 10 RO Question 10 1

SRO Tier / Group 111 RO Tier / Group 112 SRO Importance 3.7 ROImportance 3.2 l

l 10CFR55.43(b) 10CFR55.41 8

\ Item Addressed 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 l turbine following reactor on dropped rod event i

SHNPP Objective AOP-LP-3.1-2 RECOGNIZE automatic actions that are associated with AOP-001, Malfunction of Rod Control and Indication Systems l

References AOP-LP-3.1 AOP-001 AOP-001 Malfunction of Rod Control and Indication Systems SD-104 Rod Control System Question Source New Justification (A) Select if he does not recognize that rods will step out to restore temperature and power was restored due to the previous decrease in temperature.

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

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

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

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2 INITIAL EXAMINATIONS i I

QUESTIONS AND ANSWERS TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 l

RICK BALDWIN l

GEORGE HOPPER j

Initial Written Examinations i

Reference:

All written examinations are written IAW l 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

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Checkoff Sheet."

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OBJECTIVES -

9 BETTER EXAMINATION PRODUCT ,

f O LESS NRC/ FACILITY REWORK e SHARED EXPECTATIONS l 3

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - - _ - _ - -A

SESSION OBJECTIVE:

To review validity concepts affecting the NRC .

written examination for the purpose of:

Instructing licensee personnel toward 4

construction of more VALID and

CONSISTENT NRC license examinations.

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' VALIDITY i !

i A valid test is one which tests what it intends to test. i in training examinations, testing specific skills and knowledge outlined and taught in the objectives. j i

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

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3 LEVELS OF VALIDITY i

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i e Content .

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G Operational O Discriminant ,

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CONTENT VALIDITY !

. L Addresses K/A coverage and sampling plan coverage.

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.b OPERATIONAL VALIDITY '

Addresses two aspects:

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

2. Does the test item require the candidate to

. perform a job RELATED mental or physical operation?

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l DISCRIMINANT VALIDITY Addresses:

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

O The exam must be written at a level of difficulty that intends to discriminate at the 80 percent level. !

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. t 10

p 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 s.olving, prediction, analysis which are essential to job performance.

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VALIDITY

SUMMARY

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

Meaning the test items as written should provide opportunity for at least 80 percent of the candidates taking the test should answer the item correctly.

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- . - .-. - - - - - - _ - 7 3 LEVELS OF KNOWLEDGE Bloom's Taxonomy i

e Analysis, Application, Synthesis ;

O Comprehension 9 Fundamental (simple memory) t 13

-li LEVEL OF KNOWLEDGE -

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

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

G Bloom's Taxonomy, can be applied to j written, scenarios or JPM questions. j 14 i r

LEVELS i LEVEL 1 :

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

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

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

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

, including consequences or implications.

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LEVEL 3 -

Analysis, synthesis, and application testing is more active and product-oriented testing which involves the multi-part mental process of assembling, sorting, or integrating the parts so that the whole, and the sum can be used to: predict and event or outcome, solve a problem or create something new.

i.e. using-knowledge to solve problems.

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DETERMINANTS OF DISCRIMINATION l

O Level of examination knowledge O Level of examination difficulty O Passing Score G ltem bank use i

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NATURE OF EXAMINATIONS AND TESTS O TESTS are samples of PERFORMANCE O 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.

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1 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

g . ._ . -.- -..- - - .-. . .__ - .-. ... . _. - . - . . = - - - . .

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

.and SoTid Water Conditions '.* * ? N

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Question *

Given the following plant conditions:

Unit 2 was operating at 100% power. l The plant experienced a large break LOCA with a failure of the ECCS system. l FR-C.1, " Response to Inadequate Core Cooling," is being implemented.

Core exit TCs are 720*F and increasing.

At this point FR-C.] 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? l 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.

OPL271C39S pg 12-15 1

Applicant Response: SAT UNSAT l 1

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o INADEQUATE CORE COOLING Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i- NOTE . Blocking low steamline pressure Si as soon as prusurizer 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

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drop to less than 10% [25% ADV). This is a eptable and expected for this

. inadequate core cooling condrtion.

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

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

1) BLOCK low steamline pressure SI. . ;-

2) CHECK STEAMLINE PRESS i ISOUSl BLOCK RATE ISOL l ENABLE permissive LIT.

{M-4 A, A4)

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

l IF local control of atmosphen relief (s) is necessary, THEN DISPATCH personnel to dump steam USING E A-1-2. Local Control of S/G PORVs.

(Step cominued on next oage.)

M Pace 13 of 19

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1 026, Containment Spray System /.JPM # 37AP Respond to High Contamment

. Pressure 4PJace RHR Sprayin Service}- -

Question 2:

Given the following plant conditions:

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

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

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

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

References Allowed? YES X NO Answer:

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 I

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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

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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 1

References Allowed? YES J__.NO -

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l Answer: I No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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) i

Applicant Response: SAT UNSAT 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 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 l program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour l shifts in the control room as the OATC during the past month under the direction of i - asMARO.

, 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.

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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 l

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Given the following conditions:

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

2. All systems responded as expected.

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

P. 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. ,

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.

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

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

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l Reactor Operator Exadation J

65. Given the following conditions:

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

All systems responded as expected. j The performance of EOP-04 is in progress.

. One steam generator has been isolated.

l RCS cooldown using natural circulation is in progress.

l Which ONE ofthe following describes the concem associated with the affected SG pressure prior 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 l resulting in a dilution.

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

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

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Which one of the following describes the response of the Unit 1 charging pumps following receipt of an automatic SIAS signal, coincident with a Loss of '

Offsite Power? ,

a. One charging pump is automatically started on each emergency bus 5 minutes after it is energized by the diesel.

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

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

d. Onechargingpumpisautomaticallystartedontoeachemergencybug immediately after it is energized by the diesel.

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

electrical lineup and all equipment is operable.

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

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

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

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

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- - _ _ __-_ - _____-____-___7__ _

Charging pumps are running on Unit 1 an SIAS is present. (Assume no operator action)

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

- are emptied?

The charging pumps will:

a. trip on low oil pressure.

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b. trip on low suction pressure,

c. automatically align to the RWT.

d. continue to run and become gas bound.

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_7 Reactor Operator Examination

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

Which ONE of the following lists the charging pump response when the BAM tanks are emptied?

The charging pumps will:

a. trip on thermal overload.

b. trip on low suction pressure.

c. automatically align to the RWT.

d. continue to run and become gas bound. '

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Given the following conditions:

l 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, l

c. A low flow signal, j 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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Resetor Operator Examination ,

f 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. ;

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

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

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

c. A low flow signal.

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

F.

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s 13, Given the following plant conditions:

. Unit 1 was at 73% power

. A reactor trip / safety injection on low steam line is a "e o: urred 21 minutes ago

,. . Average Core Exit TC temperature is 375'F

. RCS pressure is 225 psig

. All S/G pressures are DECREASING slowly

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

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

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

. Total feedwater flow is 340 gpm

. PZR levelis 37% and INCREASING

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

. Containment pressure is 5 psid and INCREASING slowly ,

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

a. Heat Sink

b. Core Cooling

. Containment

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

Reference:

E-0, Foldout Page Objective: OPL271C395, B.1 Level. Analysis Source: 000040K101 001 History: Stem and distracters a and d modified (7/7/9S)

Note: Provide FTS curve with this question.

Justfication:

a. Correct answer because all S/G ievels are Jess inan 10% NR and total feeowater flow is less than 440 gpm.

b. Incorrect oe:ause RCS temperature is 325'F (core exit T/Cs less tnan 1200*F).

c. Incorrect oe:ause containment pressure is less tnan 12.0 osie.

d. Incorrect because RCS temoerature is 325'F (T-cold is greater than 25D'F)

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13. Given tne following 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.3 *F

= RCS pressure is.225'psig liSO ^*

All S/G pressures are DECREASING slowly

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

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

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

. Totalfeedwatepflow is 340 gpm

. PZR levelis)7% and INCREASING

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

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

a. Heat Sink

b. Core Cooling

. Containment

d. Pressunzed Thermal Shock Answer: A K/A: 00004DK101 (4.1/4.4j

Reference:

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

a f

Source: 000040K101 001 History: Stem and distracters a and d modified (7,7/93)

Note: Provide PTS curve with this question.

Justr5:ation:

a. Correct answer because all S/G levels are Jess inan 10% NR and total feeowater fiow is less than t-40 gpm.

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

. Incorrect De:ause containment oressure is less inan 12.0 psid.

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d. Incorre:t be:ause RCS temoerature is 325': (T-5cid is greater inan 250*:)

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! 20. Given the following plant conditions:

. The control room has been evacuated due to a fire

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

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

. The TDAFW pump has been shut down

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

l i 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 generato.r

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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.

l d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by l

throttling the manual valves at the LCVs.

i Answer: B l

K/A: 000058A102 [4.3 / 4.5]

Reference:

AOP-C.04, page 11 Objective: OPL271 C423, B.4 Level: Comprehension Source: 00005SA102 001 History: Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distracters a, b, c, and d reorcered

(7/22/98). Distracter be restructured (7/29/98)

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

l l

l 1

l l

i

20. Given the following plant tendcons: ;

)

. The control room has been evacuated due to a fire )

. All controls have been transferred per AOP-C.04 )

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

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing 4 s6 h M A N co,hb W M'-C-@

Which ONE of the following describes the cer ns J i m ;u.ciy feed, vat 2c system?

. j

a. The TDAFW pumo wi!! automatically resta,rt whan 2/4 steam generators reach low low level, e ~ E k -*M 4 (.oii k d' u.s w ; g (. - M / ,

(Co w

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

leve!s at 33%. 1 1

The MDAFW pump level centrol valves will have to be manually adjusted using the l 1

Manual Output Adjust in tne L-381 caninet.

/W d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by

I,,d/

throttling the manual valves at the LCVs.

Om pe f[.I, Answer: B K/A: 00005BA102 [4.3 / 4.5]

Reference:

AOP-C.04, page 11 ,

1 l

Objective: OPL271C423, S.4 Level: C ~. prehension l Source: DD005BA1D2 001 History: Used on 9/97 RO NRC exam Text rnodined to corre:: grammar errors. Distra: ers a, b, c, and d reorcered (7C2/98). Distracter be restructured (7/29/9S)

Note: Seiected from6 exam bank with minor modification o,f text 1

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) l l

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. :

l

j

d. Prepare to initiate RC:1 iteed and Bleed if WR levelin any 2 S/Gs is less than 60%.

Answer: C j i

K/A: 000074K307 .[4.0/4.4] )

Reference:

FR-C.1, pages 10 & 17 j Objective: OPL271C398 l Level: Comprehension j Source: MExam Bank 101. 000074K307 001 l

1 History: Used on HLC 9807 practice exam Distracters b and c reordered Note: Selected frorMexam bank without modification of text l

l I

d

.:. . INADEOUATE CORE COOLING FR-C.1

- Q Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Use of a Fautted or Ruptured S/G during performance of the following steps may compound the emergency situation. When NO frrtact S/Gs are available, a Fautted or Ruptured S/G may be used. ~

l

12. M AINTAIN Inta::t S/G narrow range r levds:

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

IF total feed flow greater tnan 440 gpm can NOT be established.

THEN PERFORM theiollowing:

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

, 2) GO TO Note pnor to Step 21.

b. Between 10% {25% ADV) and 50%.

.ns l ..

Page 10 of 19

I FR-C.1

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

.~ l

21. CHECKif RCPs should be staned:

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

l greater than 1200*F.

l

b. CHECK if idle RCS loop available: b. PERFORM the following: 1

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/Os remain AVAILABLE AND STOPPED. greater than 1200*F, THEN OPEN reactor vessel head vents: ,

. FSV-68-394

. FSV-68-395

- FSV-68-396 l

. FSV-68-397. l I

c) GO TO Step 22. 1 l

l

c. START RCP in one idle loop.

d. GO TO Substep 21.a.

Page 17 ci 19

23. Given tne following plant conditions:

. FR-C.1, inade:;uate Core Cooling", has oeen entered due to a RED path on Core l Cooling

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

. NO FeedwaterI Aux Feedwateris available l

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

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

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. #

i M Portsl.s e Skod \/MwS l

d. ErepareWate-RCO raJ oud Ceed4WR4eveHirany-2-S/Gs4sess-than-60 .-

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 reo-dered Note: SelectediromMexam bank without modification of text

,, .. ) p//j W*/$ f a

a

49. Given tne following plant conditions:

. Reactor power is at 20*/o during a unit shutdown

. Intermediate Range N-36 failed high

. Operators placed the level trip 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 snutdown?

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 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 energi2e.

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 Source: 015000K407 001 History: Not used on g/g7 or 5/98 NRC exams. Not used on practice exam.

Distracters e and d reorderad Note: Selected fromg exam bank without modification of text 1

l 1

I l 1

- _ - 1 f,l l'/

3e ,

m(

t

49. Given the following plant conditions: , 9 l . Rea: tor power is at 20% during a unit shutdown {

intem,ediate Range N-35 failed high l . _

!. @perators p:s ein .ccageypasssw:t:ftforf*357:rthe Dypasmitis Which ONE of the following describes the effect of this failure and action during tne remainder of the shutdown?

I 1 J l a. The reactor will automatically trip when the Power Range channels decrease below )

l .

the P-10 setpoint. ,

l b. Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range l channel, so the unit must be manually tnpped prior to Mode 2 entry. l l 1 l 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-5 setpoint.

l

d. Source Range channel N-32 must be manually energized when the operable l Intermediate Range channel (N-35) decreases below the P-5 setpoint; Source Range l

. channel N-31 will automatically energize. i

)

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

Reference:

t.OP.LD1, page 10 l ES-0.1, page 13 Objective: OPL271C352, B.4 Level: Comprehension l

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

Distracters e and d reorcered

,\

l Note: Selected fromMexam bank without modification of text

'\

N .

s ~ g, o .,

i

^ ' '

ED*

- o cb No 5

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. g.l( pn.

[

_ _ _ , _ . . . . _ . _ . . . . _ _ _ _ _ . _ _ _ _ _ . . . - _ _ . _ -_...__..__m.. _ . - _ _ _ _ . _.

35. Given the following plant conditions:

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

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

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

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

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

F

c. Remove N 36 instrument power fuses. e

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

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

Reference:

ACP-l.01, page 10 & 13 Objective: OPL271 C352, B.4 Level: Analysis Source: New question (Developed 7/15/98) .

Justification:

a. Incorre::t because manually restonng N-31 and N-32 to operation in the power range would destroy the source rarige detectors.

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

c. incorrect because action does not bypass the trip signal. ,

d. Incorrect because a manual reactor tnp for the given conditions is not required. Placing N.

36 level trip switch in BYPASS allows an orderly reactor shutdown.

l l

l 1

i l " ,

l l

l l 50. Given the following piant condrtions:

1 1

. Large Break LOCA is in progress l l

. RCS pressure is 550 psig

. Exosensor indicates 25'F superheat

. No RCPs are operating l 1

Which ONE of the following indications would the operator use along wrth RCS pressure to accurately substantiate ,: ore cooling?

a. Reactor Coolant Tavg value.

b. Average value of all core exit thermocouples.

c. Hottest Reactor Coolant wide range Thot value. : )

d. Average valJe of five hottest core exit thermocouples.

Answer D K/A 017000A402 [3.8 / 4.1]

Reference:

FR-0, page 3 OPL271C044, page 7, A.1.c Objective: OPL271 C044, B.1.b Level: Memory Source: 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

l I

4

50. Given tne following plant conditions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig

. Exosensor indicates 25'F superheat

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

3-

- p a.---

/

~ET % $-CJ5rtTE,g::!uT__ % A, g n ,,)..-gry,-~,.,W/Mt <W t T /.htr retc c.r ; .

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 .,

pp p,., '

o'n -ee K/A 017000A402 [3.8 / 4.1]

neference: _R-0, r- page 3 f r2- O. 2 OPL271C044, page 7 A.1.c Objective: OPL271 C044, B.1.b Level: Memory Scu :e: 017000A402 001 History: Used on HLC 9809 p a:tice exam Distracters a, b, c, and d reordered (7/22/98)

Note: Selected from exam bank without modification of text 1

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88. Given the following plant conditions:

. 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?

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

c. If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in HOT ~

GTANDBY by 0700.

d. If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 Level: Comprehension Source: New question (Developed 7/20/98)

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

Justification:

a. Correct becauseMConcu:t of Operation (SSP-12.1) restricts power increase when in an LCO action of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or less. RCS loop 1 accumulator boron concentration cf 2390 ppm boron places Unit 1 in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO.

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

c. Incorrect because if loop 1 boron concentration is not restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Unit 1 must be in HOT standby by 0800.

d. Incorrect because if loop 1 boron concentration not restored w:tnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , pressunzer pressure must be reduced to 1000 osig or less by 1400.

3 /4.5 EMERGENCY CORE COOLING SYSTEMS l

3 /4. 5. ] ACCUMULATORS COLD LEG INJECTION ACCUMULATORS

( LIMITING CONDITION FOR OPERATION 3.5.3.3 Each cold leg injection accumulator shall be OPERABLE with:

~

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

barated water,

~~

. c. Between 2400 and 2700 ppm of boron,

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

e. Power removed from isolation valve when PC5 pressure is above 2000 psig.

APPLICABILITY: MODES 3, 2 and 3.*

ACTION:

a. With one cold leg injection accumulator inoperable, except as a result of boron concentration not within limits, restore the inoperable accumulator to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure.to 1000 psig or less within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

Pressurizer pressure above 1000 psig.

l l

De:e ber 27, 1994 Amendment No. 113, 131, 1 g . UNIT 2 3/4 5-]

?

& d .

OMM/6 i

/JD '.D/M.

88. Given the following pl ant conditions:

. Unit 2 operating in accordance with 0-GO-5, formal Power Operation at 73% with a powerin:rease to 100% in progress j,

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

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

a. Immediately stop the power increase. ,

b. Continue the power increase while restoring loyo 1 accumulator boron concentration to 2400 to 2700 ppm boron,w ~ .1 hear hNw 72 4 og Cf.

c. if loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in H@T

STANDBY by 0700.

d. If loop 1 at umulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 Level: Comprehension Source: New question (Developed 7/20/98)

Note: Provide copy of Technical Specification 3.5.1.1 with the question (exam) l Justification;

a. Correct becaus onduct of Operation (SSP-12.1) restri:ts power increase when in an LCO acaon or o nours or less. RCS loop 1 at umulator coron concentration of 2390 pom boron places Unit 1 in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO.

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

c. incorrect because if loop 1 boron concentration is not restored witnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , tne Unit 1 must be in HOT standoy by 0800.

d. incorrect because if foop 1 boron concentration not restored witnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , pressuricer pressure must ne reduced to 1000 psig or less by 1400.

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

.and Solid Water Co~nditions '. '. "'e Question 2:

Given the following plant conditions:

Unit 2 was operating at 100% power.

i 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? l l

References Allowed? YES X NO A'nswer:

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.

OPL271C398 pg 12-15 l Applicant Response: SAT UNSAT.__

/

l l

r

l .

l l

FR-C.1 INADEQUATE CORE COOLING Rev. 8

_. 1

. STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED !

1 I

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

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

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

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

. . inadequate core cooling cond: tion.

14. DEPRESSURIZE intact S/Gs to reduce RCS pressure to less tnan 125 psig:

a. WHEN RCS pressure -

less than 1920 psig, THEN PERFORM the following:

1) BLOCK low steamline pressure St. g

2) CHECK STEAMLINE PRESS ISOUSl BLOCK RATE ISOL ENABLE permissive LIT.

[M-4A, A4]

b. DUMP steam to condenser b. DUMP steam at maximum rate at maximum rate. USING 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.

t (Steo continued on ner page )

l ear Page 13 ci 19

, ,~

l-l

.~026 Conrainment Spray System /,JPM y 37AP Respond to High Contamment

.Pressuh4PJace'RHR Sp'my:in Service1 9: #

l .

Question 2:

Given the following plant conditions:

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

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

I a.) Why must both CS pumps be placed in PULL-TOrLock while transferring suction to the

! containment sump?

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

i 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:

l 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 Il-13, OPL271C388 pg 9 x

Applicant Response: SAT UNSAT l

License Applicant Administrative Walkthrough Examination--NRC-1 "

Examiner Sheet 1.1:! 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? w References Allowed? YES _2L NO -

Answer: No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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 ,

I

[

5 s - - -,

~

=.. License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A 1HShift Staffing 1 Question 1: A licensed RO has been 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 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 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 l

l t

!

ML20199E708

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Dear Mr. Driscoll:

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ML20199E708

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Dear Mr. Driscoll:

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