Text

Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl
	ML20199E474
Person / Time
Site:	Vogtle
Issue date:	12/23/1998
From:	Peebles T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Beth Brown; SOUTHERN NUCLEAR OPERATING CO.
References
	NUDOCS 9901200435
	Download: ML20199E474 (102)
	v • d • e

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December 23, 1998 Southern Nuclear Operating Company, Inc.

ATTN: Mr. Bob Brown, Plant Training and Emergency Preparedness Manager Vogtle Electric Generating Plant P. O. Box 1600 Waynesboro, GA 30830

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED ON NOVEMBER 5,1998 - VOGTLE ELECTRIC GENERATING PLANT

Dear Mr. Brown:

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

Enclosure 1 was the agenda used for the Training Managers' Conference, and Enclosure 2 is the list of attendees. We appreciate the partic!pation of you and your staff and believe that the goal of providing an open forum for discussion of operator licensing issues was met. Mr. Gallo, Chief of the Operator Licensing and Human Factors Branch, Office of Nuclear Reactor Regulation (NRR), made a presentation as noted in the slides in Enclosure 3.

Additionally, I am enclosing our preliminary schedule for FY 1999 and FY2000 as Enclosure 4.

Please review the schedule and supply comments to my staff or myself, if you have any questions regarding the content of this letter, please contact me at (404) 562-4638.

Sincerely, Original signed by Thomas A. Peebles Thomas A. Peebles, Chief

':0008,a Operator ucensing and Human Performance Branch Division of Reactor Safety Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81

Enclosures:

As noted cc w/encts:

J. T. Gasser, General Manager, g

Plant Vogtle 9901200435 981223

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Revised November 3,1998 l 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. I1/5/98 8:00 a.m. Conference Registration 8:20 a.m. Introduction Thomas A. Peebles, Chief, Operator Licensing & Human Performance Branch 8:30 a.m. Opening Remarks William Travers, ,

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

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, License Applicant Administrat,ive Walkthrough Examination--NRC-1 oo !

Examiner Sheet A;1:FShift Staffing' ~

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

.- informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shins in the control room as the OATC during the past month under the direction of a shin RO.

What additional requirements must be met by the RO before he may fill in for the vacationing RO? 3 References Allowed? YES1NO 1 Answer: The RO must complete an additional 24 (40 - 16) hours of"under direction" on-shift time that must include a plant tour and shift turnover.

Reference:

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

Applicant Response: SAT UNSAT i

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[ ATTENDEES AT THE NRC REGION 11 l TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 L'

Sid Crouch ATTSI

' David Lane . Sonalysts, Inc.

. Bill Fitzpatrick INPO-CP&L Rick Gamer ! HR Supv. Ops Tmg William Noll BK - Ops Tmg Supv-g . Max _Herrell BK Tmg Mgr Scott Poteet RB Exam Team Leader

" Ralph Mullis . .BK Ops Mgr Tony Pearson BK Ops Tmg i Anthony Williams RB- Tmg Mgr i

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Crvatal River- FPC i .Wes Young 'CR Supv OpsTng Tom Taylor ' CR Dir Nuc Ops Tmg Ivan Wilson CR. Ops Mgr Ken McCall CR ' Mgr Ops Tmg Duke Power Gabriel Washburn OC Req Team Leader Ronnie B. White, Jr MG Tmg Mgr W.: H. " Soap" Miller, CT Site Trng Mgr Paul Stovall OC Mgr Oper Tmg

' Bentley Jones OC- Tmg Mgr

James Teofilak . CT . Ops Tmg Mgr

. Alan Orton MG Ops Tmg Mgr Richard Bugert Corp , Ops Trng Spec !

EEAL Maria Lacal - TP -Tmg Mgr Dennis L. Fadden SL- - Services Mgr Jo Magennis Corp Tmg Assessment Spec l Tom Bolander SL- Exam Development Steve McGarry TP Maint Tmg Supv l Southem NucleariSNCI

John C. Lewis HT: ' Tmg & 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 Tmg Supv h

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s Virainia Power .

Steve Crawford NA Sr Inst Nuc Harold McCallum SR Supv Ops Trng 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 Vc C. Summer- SCE&G Al Koon SM Ops Tmg Supv -

NRC Participants Tom Peebles R ll Operator Lic. Br. Ch.

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

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

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4 FY 99 INITIAL EXAM SCHEDULE AND RESULTS i

D9cember 14,1998 RO SRO-l SRO U TOTAL Date Plant Chief Pass # Pass # Pass # Pass #

9/28/98 Sequoyah GTH 4 4 4 4 10/5/98 Harris RFA 2 2 5 5 7 7 11/30/98 Oconee GTH 2 2 5 5 7 7 11/30/98 St Lucie & RSB 6 3 9 12/14/98 1/25/99 McGuire & DCP 6 3 2 11 2/8/99 2/8/99 C, River & GTH 6 0 12 2/22/99 2/8/99 B.Feny MEE 4 1 5 3/29/99 Surry & RSB 5 2 4 11 .'

4/12/99 4/12/99 Watts Bar & MEE 6 3 5 14 4/26/99 5/10/99 Farley GTH 7 1 8 5/24/99 Catawba & PMS 8 5 3 16 6/7/99 6/28/99 St. Lucie RSB 1 4 5 07/26/99 Robinson MEE 3 2 2 7 08/30/99 Turkey Pt & RFA 20 20 9/13/99 136 RESULTS TO DATE 4 4 5 5 9 9 18 18 100 100 100 100 No Initial exams scheduled for: Brunswick, North Anna and Vogtle FY 00 region 11 write part of Summer & Hatch

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

i -- I FY 00 INITIAL EXAM SCHEDULE AND RESULTS i l I

i December 14,1998

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RO SRO-l SRO-U TOTAL i . .

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D:te Plant Chief Pass # Pass # Pass # Pass 0 9/27/99 Summer GTH 6 6

[ region II write 10/18/99 Hatch DCP '10 2 12 i

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region II write ,

~ 12/13/99 Vogtle RSB 3 5 2 10 2/14/00 Brunswick & DCP .12 3 15 2/28/00 i

03/"/00 Oconee ? 10 704/10/00 Harris (m.m woo) 10

! 705/03/00 St. Lucie GTH 6 5 11 i

705/"i00 B. Ferry > 6 3 3 12 705/03/00 McGuire 4 8- 12

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} 706/07/00Farley RSB 10 2 12 {

! 707/26/00 Crystal River RFA 3 3 3 9 ragion 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 i

?' disignates tentative No initial exams scheduled for: - Catawba Robinson -

Turkey Point Watts Bar

I Operator Licensing lSSueS .

Region 11 -

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

OPERATOR LICENSING l ISSUES .

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, 1 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 [lP-710.01) o Recent Information Notices Exam Integrity i'IN 98-15)

Sampling Plans (IN 98-28)

Eligibility (IN 98-37)

1 RECENT LESSONS LEARNED .

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. Charlie Payne ,

Southeastern Training Manager's Conference

^ November 5,1998 I

PC1L10Y CLARIFICATIONS i

G 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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. t POLICY CLARIFICATIONS ,

G In general, license class sizes of greater than B candidates will be scheduled for 2 weeks as

follows:

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

-l POLICY CLARIFICATIC'NS G Examination submittals - 2 copies of draft and final exams (written, JPMs, and simulator scenarios). Elsctronic copy is also desired.

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

Criteria - 10 unacceptable questions out of 30 questions sampled ,

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, RE_ CENT LESSONS LEARNED SRO-only Questions i

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

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

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

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.. 1 2.0 GENERIC KNOWLEDGES AND 1 ABILITIES 2.1 Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements.

(CFR: 41.10 /45.13)

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

(CFR: 41.10 / 45.13) -

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

(CFR: 41.10 / 45.13) l IMPORTANCE RO 3.0 SRO 3.4 2.1.4 Knowledge of shift staffing requirements.

(CFR: 41.10 / 43.2) I 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.

l (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE R O 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 opere.tionaljudgnEnts based on operating characteristics / reactor behavior / and instrument interpretation.

(CFR: 43.5 / 45.12 / 45.13)

IMPORTANCE RO 3.7 SRO 4.4 2.1.8 Ability to coordinate personnel activities outside the control room.

.+- (CFR: 45.5 / 45.12 / 45.13)

IMPORTANCE RO 3.8 SRO 3.6 2-1 NUREG-1123. Rev. 2 l

l 2.1 Conduct of Operations (continued) 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on ;

system or component status. '

(CFR: 45.12)

IMPORTANCE R O 3.0 SRO 3.0 i

2.1.20 Ability to execute procedure steps. I (CFR: 41.10 / 43.5 / 45.12) I IMPORTANCE RO 4.3 SRO 4.2 ~

2.1.21 Ability to obtain and verify controlled procedure copy.

(CFR: 45.10 / 45.13)

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

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 different modes of plant operation.

(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.

(CFR: 45.12 / 45.13)

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)

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

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

(CFR: 41.10 / 45.12)

IMPORTANCE R O 2.2 SRO 2.6 2-3 !mRIG - 1123 , Rev. 2 !

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

(CFR: 41.10 /43.5 / 45.1',

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 sysIem geography and system implications.

(CFR: 43.5 /45.13)

IMPORTANCE R O 3.8 SRO 3.6 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.

7 (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.

(CFR: 45.13)

IMPORTANCE -

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

(CFR: 43.5 / 45.11)

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

(CFR: 45.11)

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

(CFR: 45.11)

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

r (CFR: 43.5 / 45.11)

IMPORTANCE R O 2.3 SRO 4.1 i

N'aEG-1123, Rev. 2 2-14 l

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

.. SRO-only questions wiI be based on fo owing categories: A.2, G2.1, G2.2, G2.3, and G2.4.

f only 1 As rom Tier to Tie & 3.

=> Other 14 flexible.

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s ES-401 BWR SRO Exanination Outline For.n 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 WL m mm tm 55

1. I g 3.;9 g jg; gg 26 ,

Emergency & .g. -

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mk EQ Abnormal l@ Oj? s 17

% ws31 ft Evolutions Tier Totals ff h f,fjf c.w sp :gt fgy w h m;

43 +7 hb hbh hY $h h 1 23 2.

2 13 P1 ant Systems 3 4 Tier 40 ff Totals

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

Abilities 17 + 't Note: -

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

Actual point totals must match those specified in the table.

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

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

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

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

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

K/A Category Points Tier Group Point K K K K K X A A A A G

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Total 1 2 3 4 5!6 1 2 3 4 1.

Emergency L I h h,.h

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13 Abnormal E 35 39 P1 ant 3 O.M w n u@w ES n a%n.M 4 Tier M M ffM $$$ $ 36

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Totals $ %% hk j$

1 28 2.

Plant 39 Systems 3 4 Tier 51 Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 13 Note: -

Attempt to distribute topics among all V,/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 36 of 39 Interim Rev. 8, January 1997

REGENT LE_SSONS LEARNED Sampling Criteria intent of prodess is to avoid exam predictability. .

also to avoid excessive use o" re3 eat test items.

first use systematic 3rocess to deve 03 samale plan using topics from K/A catalog, then use faciity question resources to accomp ish the alan. .

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REGENT LESSONS LEARNED Sampling Criteria intent of proc'ess is to avoid exam predictability.

also to avoid excessive use of repeat test items.

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

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RE_C_ENT LESSONS LEARNED Samplinc Criteria (Cont'd) eac1 toaic in each tier & group should ae sampled at east once unless insufficient c uestions 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 samp e plan should have a fairly even balance across all Ks & As.

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RECENT LESSONS LEARNED -

Sampling Criteria (Cont'd}

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

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

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

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OTHER '

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

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

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.j OTHER -

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

available for inspection trom time of license aaplication to license expiration.

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C'THER -

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

strictly followed.

should have something similar based on plant JTA and specific plant priorities. ,

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

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OTHER o 1 Requal Control Manipulations (Cont'd) i credit for accomplishment should only be

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given for a_ctive participation in the i manipulation.

2 NOTE: control manipulations are not .

synonymous with reactivity manipulations.

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\ Examination Communications l Examination Development i

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\ Coordination By Ronald F. Aiello

9 Facility Suggested improvements J

1. The exam develoament team and lead examiner should meet at t1e beginning of the development process to estaalis, common grounds for the deve opment and l execution of the examination:

Changes and interpretations to the '

NUREG.

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Scope of the exam development and administration process.

Lessons learned from the last exam l administered.

2. Move due dates for the outline and t1e exam back to 90 and 60 days prior to arep wee <. This will provide more time for examination review by t1e examiner (s).

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

4. Examiners maintain a list of w1o (alant) does the exam process the best. This i s1ould arobably be bro <en down to each l portion of the examination. Provide your l ratings to the utilities in Region 2, so we can meet your exaectations and improve.

5. T1e principal and the utility rearesentative should meet early to establish a working relationslia and exaectations. If possible this shou d include samples o" c uestions, JPMs, etc.

6. The exam should have no outstanding issues / questions that arise anc need reaair at the ast minute. These issues should a I have been identified by the prea wee <, to allow time to make changes that meet all the criteria.

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7. The chief examiner shou d explain up front all the forms in 1021 that need to be completed.

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

9. As soon as a Chief Examiner is assigned to an exam, the Faciity Rep and the C1ief slou d verify the ability to communicate via al channels (including e-mail). When we converted to Lotus Notes, the faciity was suddenly unable to send e-mail to lis Chief Examiner. This

i became somewhat of a hindrance and s1ould be avoided if 30ssia e.

10. It would be helpfulif the Chief Examiner ;

cou d provide his schedule to the Facility Re3. This includes providing updates for any changes to the Chief Examiner's !

schedule along the way. The facility rep needs to be aware of when the Chief l Examiner is available to assist in exam preaaration activities.

11. A face-to-face meeting should be promptly scheduled in order for the Chief to communicate his exaectations to the Faciity Re3. The face-to-face requirement could ae waived if t1e Chief and the Facility Rep have previously wor <ed together and the Facility Rep is con"ident tlat he/she understands t1e C1ief's exaectations. In any case, a

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i l conference ca I would be the minimum to l

! satisfy this im aortant first ste 3. '

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! 12. The Chief and the Facility Rep should

! work together to estaa ish a firm schedule l l for the exam week (s). This will ensure the )

l most efficient schedule is developed (with respect to crew composition and j

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

l l 13. The Chief Examiner and Utility Rep MUST remain fixed during the entire 180 day ,

aeriod. Handing off the responsibility is bot 1 disruative anc destructive to communication. The exaectations of the clief examiner must be defined / communicated early.

14. T1e "timeline" must be enhanced to identify specific times and dates for communication / working meetincs between

the examiner and the utility rep. These meetings shou d ae " face to face" to assure exaectations are understood, and being met, ear y on.

15. If an examiner and a utiity rep have not wor'<ed together before, the timeline for

" deliverables" must be exaanded.

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

16. 398 anc 396 forms need to be available electronically. We took the time to develoa an electronic version ourselves but I wou d arefer that the electronic master coales came cirectly from t1e NRC

so tlat we have more confidence that everything is exactly t7e same. We would all benefit from this improvement.

17. =A face to face working meeting of eig1t (8) to twelve (12) hours, ap 3roximately 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. Exaectations must be established early so that the utility clearly understands the rules and the examiners expectations. Small sam a es of deve opment must be reviewec ear y to assure exaectations are being met.

A " ace to face meeting, arior to the 30 day su 3mittal, to reso ve any/all issues must be scleduled such tlat adequate time (suggest 2 weeks) is available to resolve

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! comments before t7e 30 cay limit. No one

! wants to see 30 questions reviewed anc j the exam rejected. S3ending ~24 hours in

! 3-4 face to face meetings is a small/ smart j price to pay to avoid hundreds of hours of re-development, the emotional stress on candidates when the exam must be I rescheduled and the impact on the plant j when candidates are not licensed to meet j plant needs.

! 19. The "new" SSNTA format for JPM level of i detail is NOT what you have liked in the j 3ast and needs to be either accepted by l the NRC as a standard or oatimum format, 1

or modi"ied, or rejected. The JPMs we i j su amitted to you were in the format and l leve of detail you had found acceptable in j tie past, and we were surprised to finc that they needed significant last-minute rework !

(additional level of cetail).

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20. Maybe Chief Examiners could send some co3ies of good written c uestions, JPMs, I

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

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l i Facility General Comments 4 .

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l 1. The limited number of NRC license l examiners puts the Region and the sites at a disacvantage with respect to getting j timely interchange. If the examiner is out l of the office on a tria for several weeks, the l

time you have to provide the licensee with '

feedback is very limited and results in a j real struggle to ensure a quality ex~am.

! T1e limited resources and interaction time i increases the risk of lower quality.

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2. Region ll examiners have been very 3 rom at in getting back to us when we have j a c uestion even though you may be at a j remote location.

3. The cuality of the communications has been good. All of the examiners that I lave ta <ec to have been taorough, arecise and have aerformed listening checks to

verify that the correct messages were sent and received. I wou d lowever, like to see more communications by e-mail where appropriate. That would 1elo ensure t1e c'arity of the communications even more.

4. With respect to the exam specifically; there were a number of clanges that were made anc we had to transmit those by expensive overnight or next daf delivery. If we could figure out a secure e-mail method it would save all of us numerous headaches as well as dollars.

5. During my first face-to-face meeting with the Chief Examiner (to review draft exam materia ), I gainec much-neeced i~nsight into his exaectations. This alleviated muc1 stress on my aart and, from then on, the 3rocess went much more smooth y. The Clief was very helpful durinc subsequent tele alone conversations and our second

,_-,,,.,,s, meeting in Atlanta. He was very easy to

-work wit 1 and very understancing concerning my inexperience in this process. His patient guidance was the key

-to our success in tais endeavor. Next time, with a we've earned, we'll do even better.

6. The biggest 3roblem that I encountered during that exam came from the written portion tlat was being develoaec by the contractor. Since he had written exams before, I assumed that the qua'ity of questions he was submitting to us were the c ua ity of questions that were acce atable to the NRC. We reviewed his work, made technical corrections and assumec that the c uestions would be accepted by the NRC.

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

to the written exam and most of the communication was made over saea<er ahones (about 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months ). It became a very painful process and could have been avoided had I not out so muc1 faith in the contractor's exam writing exaerience and communicated more on the subject of the written exam with the chief. We had a 100% pass rate on the exam, but the exam report was brutal in the area of the written !

exam.

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7. Know the chief examiners expectations I from the beginning (prior to ariy ;

develoament).

8. Never assume you know 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 rather tlan over t1e ahone. I alan for four or five trias between the start of

development and prep week. It may sound ike over<ill, but it wor <s (It's also safer in the area of security).

10. ~ Submit material early (es aecia ly the written). I like to have the written exam a done deal prior to the actual submittal cate.

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

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

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

13. ALL 3roblems/ changes must be resolved at the level of the examiner and the utility i re 3. In no case should problems /clanges

[ 3e re3orted/ escalated to senior i management of the utility or NRC unless

i 30th the examiner and the utility re3 are at an absolute, and mutually agreed, '

im aasse.

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

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

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

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

Answer:

C Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg

'will be within l'F of the temperature prior to the dropped rod.

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, Ref erence l' age SRO Question 10 RO Question 10 SRO Tier / Group llI RO Tier / Group i12 SRO Importance 3.7 RO Importance 3.2 1

10CFR55.43(b) I 10CFR55.41 8 Item Addressed item Addressed KA Number 000003 AK1.01 -

, KA Statement K.nowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Reason for turbine following reactor on dropped rod event i

SHNPP Objective AOP-LP-3.1-2 RECOGNIZE automatic actions that are associated with l AOP-001,14alfunction of Rod Control and Indication Systems References AOP LP-3.1 AOP-001 I l AOP-001 Malfunction of Rod Control and Indication Systems SD-104 Rod Control System i

Question Source New

\ Justification (A) Select if he does not recognize that rods wil. 'er out to restore temperature and power was restored i.ue r the

! previous decrease in temperature.

(B) Select if he recognizes that rods will step out, but the i decreased temperature adds positive reactivity to testore power. l (C) CORRECT- Power will initially decrease ddito the dropped rod. As power decreases, temperature will decrease. As temperature decreases, positive reactivity is added to restore

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i 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 I

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INITIAL EXAMINATIONS b

QUESTIONS AND ANSWERS TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 l

RICK BALDWIN l &

GEORGE HOPPER i

initial Written Examinations

Reference:

All written examinations are written IAW ES-401, " Preparation of Site-Specific Written Examinations for Power Reactors." Using ES-401-1, ES-401-2, ES-401-3, ES-401-4, BWR/PWR_, RO/SRO

EXAMINATION OUTLINES, and ES-401-6 Written Examination Quality Assurance

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Check.off Sheet."

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j OBJECTIVES -

e BETTER EXAMINATION PRODUCT O LESS NRC/ FACILITY REWORK O SHARED EXPECTATIONS u

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i SESSION OBJECTIVE:

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, i To review validity concepts affecting the

! NRC .

written examination for the purpose of:

Instructing licensee personnel toward construction of more VALID and CONSISTENT NRC license examinations.

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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

been outlined in the objectives.

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CONTENT VALIDITY i

I Addresses K/A coverage and sampling plan ,

coverage. :,

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OPERATIONAL VALIDITY ' -

l 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?

c)

, DISCRIMINANT VALIDITY Addresses:

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

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

, G The question, its stem and distractor, interplay, by DESIGN, at least 80 percent l

of the candidates taking the exam should answer the item correctly. -

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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 which are essential to job performance. .

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VALIDITY

SUMMARY

3. The exam must discriminate at a moderate i 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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1 3 LEVELS OF KNOWLEDGE Bloom's Taxonomy 9 Analysis, Application, Synthesis e Comprehension O Fundamental (simple memory) i 13 4

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.t LEVEL OF KNOWLEDGE -

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

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

the items. j 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.e. setpoints, definitions, or specific facts.

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LEVEL 2 i

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

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

, including consequences or implications.

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LEVEL 3 1

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

f i.e. using knowledge to solve problems.

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DETERMINANTS OF DISCRIMINATION i

O Level of examination knowledge O Level of examination difficulty O Passing Score i

e item bank use 1

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NATURE OF EXAMINATIONS AND TESTS O TESTS are samples of PERFORMANCE G Infer overall performance based on a sample G 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 Items MUST discriminate otherwise it has little or NO value.

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PSYCHOMETRICS Items may have one or more of the following psychometric errors:

1. Low level of knowledge (fundamental)

2. Low operational validity (not job related)

3. Low discriminatory validity ( hard or easy)

4. Implausible distractors

5. Confusing language or ambiguous questions

6. Confusing or inappropriate negatives

7. Collection of true/ false statements

8. Backwards logic 20

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

.and SMid Water Co'nditions *.C s ." 1 -

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Question 2

l 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.

Com exit TCs are 720*F and increasing.

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

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a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators? j b.) Why is this action taken? '

References Allowed? YES X NO i l

l Answer: ,

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

Reference:

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

OPL271C398 pg 12-15 Applicant Response: SAT __UNSAT__

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INADEQUATE CORE COOLING

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l. STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED f"

NOTE

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

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. After the low steamline pressure SI signalis blocked, main stitamline isolation will occur if the high steam pressure rate is exceeded. l l

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

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

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

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a. WHEN RCS pressure l l

less than 1920 psig.

THEN PERFORM the following:

1) BLOCK low steamline pressure St. .7 f 2) CHECK STEAMLINE PRESS ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT.

[M-4A, A4]

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

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

(Step continued en next page.)

Page 13 of 19

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

. Pressure 4 Place RHR Spray.in Service'!:-

Question 2:

Given the following plant conditions:

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

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

a.) Why must both CS pumps be placed in PULL-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 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 18, CCD NO:1-47W611-72-1, ES-1.3, pages Il-13, OPL271C388 pg 9 l j Applicant Response: SAT UNSAT l

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License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet N.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.

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

! vacationing Unit OATC.

Can the RO. fill in for the vacationing RO? Why or why not? w l

l References Allowed? YES X_ 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 l

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

l Examiner Sheet 1

1 'A 1:: Shift Staffing Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is l- informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing I

shin 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 l vacationing RO?

l References Allowed? YES1NO .

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

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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4 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 Examination j l l

65. Given the following conditions: l The reactor has experienced a Steam Generator Tube Rupture.

All systems responded as expected.

The performance ofEOP-04 is in progress.

One steam generator has been isolated.

I RCS cooldown using natural circulation is in progress.

l- Which ONE ofthe following describes the concem associated with the affected SG pressure prior l to placing the RCS on SDC7 j

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

L 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.

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' hich W 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

'OffsitePyaer?

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

b. All' charging pumps are automatically started immediately after their respective ~ bus is energized, c .- The operator must manually. start one charging pump on each emergency bus 5 minutes after it is energized by the diesel.

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Onechargingpumpis'automaticallystartedontoeachemergencybug 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 by the diesel.

b. All charging pumps are automatically started immediately after their respective bus is 4 energized by the diesel. I

c. All charging pumps are automatically started 5 minutes after their respective buses are ;

energized bythe diesel. !

d. Only one charging pump is automatically started onto each emergency bus immediately

afterit is energized bythe diesel.

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

! Which one of the following lists the charging pump response when the BAM tanks l .. are emptied?

The charging pumps will:

a. trip on low oil pressure.

b. trip on low suction pressure.

l C. automatically align to the RWT.

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d. continue to run and becoma gas bound.

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27.

Charging pumps are runmng on Unit I and an SIAS is present. (Assume no operator action) j Which ONE of the following lists the charging pump response when the BAM tanks are emptied? l The charging pumps will. 1 1

a. trip on thennal overload.

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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Given the following conditions: !

l Unit 1 CEDM fan HVE-21A 'is in AUTO after START I l Unit 1 CEDM fan HVE-21B is in AUTO after. STOP. l

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

i L Which DNE of the following completely lists the logic that will start HVE-21B? l t

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

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

c. A low flow signal:.

d. The trip signal from HVE-21A concurrent with a low flow signal and air !

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

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Reactor Operator Exammation

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59. Given the following conditions:

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

- Unit 1 CEDM fan HVE-21B is in AUTO aner STOP. l Unit 1 CEDM fan HVE-21 A trips on overcurrent. l 1

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

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

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

c. A low flow signal.

i d. : The trip signal from HVE-21 A concurrent with a low flow signal and air inlet temperature

l. signal to the cooling coils is greater than 100

F.

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13. Given the following plant conditions:

. Unit 1 was at 73% power

. A reactor trip / safety injection on low steam line pressure occurred 21 minutes ago

. Average Core Exit TC temperature is 375'F

. RCS pressure is 225 psig

. .All S/G pressures are DECREASING slowly

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

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

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

. Total feedwater flow is 340 gpm

. PZR levelis 37% and INCREASING

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

. Containment pressure is 5 psid and INCREASING slowly e At this po nt, which ONE of the following Critical Safety Functions is the MOST degraded?

a. Heat Sink

b. Core CooMng

c. Containment

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

Reference:

E-0, Foldout Page Objective: OPL271C395, B.1 9

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

Note: Provide PTS curve with this question.

Justification:

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

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

c. Incorrect oe ause containment pressure is less than 12.0 psid.

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

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l l 13. Given the following plant conditions:

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. Unit 1 was at 73% power A reactor trip / safety injection on low steam line pressure 3 Curred 21 minutes ago

. Averace Core Exit TC temperature is-3751F

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. RCS pressure is.225'psig il5D I##

. All S/G pressures are DECREASING slowly

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

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

. #4 S/G levelis STEADY at 2% NR l . Total feedwatepflowis 340 gpm PZR levelis)7% and INCREASING RCS T-cold temperature is 325'F and DECREASING s!owly Containment pressure is 5 psid and INCREASING slowly ,

At in.s point, which ONE of the following Crmcal Safety Functions is the MOST degraded?

a. Heat Sink

b. Core Cooling

. Containment

d. Pressurtzt.d Thermal Shock Answer: A 1

K/A: 000040K101 [4.1/4 4) l Referen:c: E-0, Foldout Pa;;e Objective: OPL271C3g5, B.1 Level: Analysis ,

e Source: 000040K101 001 1

History: Stem and distracters a and d modrfred (7/7/98)

Note: Provide PTS curve with this question.

Justrfication:

a. Correct answer because at! S/G levels are Jess than 10% NR and total feedwater fiow is less than e-40 gpm.

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

. incorrect because containment pressure is less tnan 12.0 psid, d incorre:; because RCS temperzture is 325'F (7-5cd is grea:erinan 250*F)

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5 20. Given the following plant conditions:

ef gi U;

. The contro room has been evacuated due to a fire

. All controls have been transferred per AOP-C.04 MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators

. The TDAFW pump has been shut down Steam generator pressures and levels are decreasing 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 reac low low level.

b.

The MDAFW pump level control valves will automatically control stean generatof

, levels at 33%. -

c, The MDAFW pump level control valves will have to be manually adjusted using e e 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 manusi 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: 3 000058A102 001 History: Used on 9/97 RO N',C exam Text modified to c: rect grammar errors. Distracters h, b, c, and d reordered (7/22/92). Distrae.er be restructured (7/29/98)

Note:

Selected fromM exam bank with minor modification of text i

i

& h

20. Given tne fo!!owing plant conditions'

. The control room has been evacuated due to a fire

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

. MDAFW pumps 1 A-A and 18-B are injecting into the steam generators

. The TDAFW pump has been shut down

. Steam generator pressures and levels are decreasing 4 s 6, whr M d k <d@ W /ro/ -C.o'( 3 Which ONE of the following describes 44e4esoonstv: inc . swam y IcedwateNtystem7

~

a. The TDAFW pump will automatically restart wh n 2/4 steam generators reach low low fevel. m ~ h k ~ad So& usiq , LM/ ,

SCom

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

, levels at 33%.

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

/W

,#f[,q4 My d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by y tnrotthng the manual valves at the LCVs.

,, A/ ci of[j. Answer: B K/A: 000058A102 (4.3 / 4 5)

Reference AOP-C.04, page 11 Objective: OPL271 C423. B.c Level: Comprehension Source: 00005BA102 001 History: Used on 9/97 RO NRC eram Text modified to correct grammar errors. Distra=ers a, b, c, and a reordered (7/22/98). Distracter be restructured (7/29/98)

Note: Selected fromMexam bank with minor modification of text

~~ ~~ -~~ ~ _

D orG h w N.

. h S/G h h ~~;x l NO Feedwater / AuxPWAt step 12,the CRO checkspD t e l

t ONE of the following)

As the SRO you should: (Se ecHeat Sink',

Secondary mulators.

a. Go to FR-H.1,* Loss mospheric of pressure to dump eaccu 0* F .

b. Depressurize allintact S/Gs to at e exitTCs are less than1

/

! c.

Start RCPs one at a time,until cord and Bleedif WRlevelin any

/

[

d. Prepare toinitiate RCS Fee C

Answer: .[4.0/4A) 000074K307 K/A:

FR-C.1, pages 10 & 17

Reference:

OPL271C398 Objective:

Comprehension 001 [

000074K307 Level:

Source:

MExam Bank 101. m Used on HLC 9807 practice exa i of text History: Distracters b and c reordered m bank without modific Selected fronMexa Note:

Q

. t.

.{

V

g[.

f t

a

.: . g INADEQUATE CORE COOLING FR-C.1 7T Rev. 8

~

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 1

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

l

12. MAINTAIN Intact S/G narrow range ;

levels:

]

a. Greater than 10% [25=4 ADV) a. MAINTAIN total feed flow greater tnan 440 gpm UNTil level greater than 10% (25% ADV]

, in at least one S/G.

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

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

, 2) GO TO Note prior to Step 21.

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

Page 10 of 19

\

1 FR-C.1

.+

g INADEQUATE CORE COOLING Rev. 8 j

l i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l'

i l

l NOTE RCP damage due to absence or loss of norrnal support conditions is an acceptable consequence in this procedure.

l

21. CHECK if RCPs should be started:

1

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

' greater than 1200*F. ,

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

1

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

2) RCP in associated loop b) IF core exit 77Cs remain l

AVAILABLE AND STOPPED. greater than 1200*F, l THEN l DPEN reactor vessel head vents:

l l ., . FSV-68-394

. FSV-68-395

. FSV-68-396

. FSV-68-397.

c) GO TO Step 22.

c. START RCP in one idle loop.

i

{ d. GO To Substep 21.a.

i -

l Page 17 oi 19 l

l

^

o 1

23. Given tne following plant conditions:

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

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

. NO Feedwater / Aux Feedwater is available

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

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

~

a. Go to FR-H.1,

Loss of Secondary Heat Sink". )

1

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

I

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

g PortV.s care @ockVMS

d. .BreparMedaitiate-RSSfeud anJ Geed #-WR-feveHrreny-2-S/Gs-is4ess-tharr60b-Answer C, K/A: 000074K307 [4.0/4.4]

Reference:

FR-C.1, pages 10 817 Objective: OPL271C398 Level: Comprehension Source: 000074K307 001 History: Used on HLC 9807 practice exam Distracters b and c reordered Note: Selected fromMeram bank without modification of text 7, .p. h jF//)SV E k ,

4E.

l

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 trip bypass sv :ch 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 priorto 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. 1

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]

l

Reference:

AOP-1.01, page 10 l

ES-0.1, page 13 l

Objective: OPL271C352, B.4 l

Level: Comprehension Source: . 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 l

l l

CK W

($ -4,

49. Given the following plant condrtions-b$' -

i l'

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

. Intermediate Range N-36 failed high \

(_ Opera: ors p6 g n; ; cmp-eypass-switetriorW367:rthe Dypass posse-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 Soume Range channels, N 31 and N-32, must be manually energized when the operable interrnediate Range channel (N-35) decreases below the P-6 setpoint.

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

l

, Answer. C e

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

Reference:

AOP-LO1, 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 reordered k Note: Selected fromhexam bank without modification of text

\

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9( /. pn a c'n cw 5 l

l i

l l

l

35. Given the following plant conditions:

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

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 ran'ge detectors.

b. Correct because placing the level trip switch in BYPASS prevents high reactor trip when the low power reactortrip signalis reinstated at the P 10 setpoint (10% power),

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

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

l

. I w

50. Given the following piant conditions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig j

. Exosensor indicates 25'F superheat ;

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

a. Reactor Coolant Tavg value.

b. Average value of all core exit thermocouples.

1

c. Hottest Reactor Coolant wide range That value. :

l

d. Average value of five hottest core exit thermocouples. l Answer: D i l

K/A 017000A402 (3.8 / 4.1) I

Reference:

FR-0, page 3 OPL271C044, page 7. A.1.c j Objective: OPL271 C044, B.1.b Level: Mernory Source: 017000A402 001 History: Used on HLC 9809 practice exam Distracters a, b, c, and d reordered (7/22/98) z Note: Selected fromgram bank without modification of text

50. Given the 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?; ., , ,

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c ~ ,- , n -

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X ~ Read i Coofantikig v:!E fl, LW )q i,J -

, t 72:. A /dr~ for e t*.! <<

b. Average value of all core exit thermocouples.

c Hottest Reactor Coolant wide range Thot value. -

d. Average value of five hottest core exit thermocouples.

Answer: D s j

K/A 017000A402 [3.8 / 4.1)

N3 # C #7 ^ M#

- O. 2.-

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 (7/22198) v Note: Selected from exam bank without modification of text

SD 0 ". O "- 0" 0" 09 >

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4

88. Given the following plant conditions:

. 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

. Curr:nt 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:

< STANDBY 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)

,r Justification:

a. Correct becausegConduct of Operation (SSP 12.1) restricts power increase when in an LCO action c16 hours 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 ber.'use if loop 1 boron concentration not restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , pressurizer pressure must be reduced to 1000 osig or less by 1400.

4 z

i

l 1

3 /4. 5 EMERGENCY CORE COOLING SYSTEMS l

3/4.5.1 ACCUMULATORS !

i COLD LEG INJECTION ACCUMULATORS !

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

a. The isolation valve open,

b. A contained borated water volume of between 7615 and 8094 gallons of : n131 borated water, 3

c. Between 2400 and 2700 ppm of boron,

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

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

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a. With one cold leg injection accumulator inoperable, except as a result of boron concentration not within limits, restore the l 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,'l.imits uithin 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 2000 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.

~

i December 27, 1994 l Amendment No. 113, 131, 133

! - UNIT 2 3/4 5-1

~

4

y -

Q Of.. ! ' ,l s If})/{

B8. Given the following p! ant conditions:

. 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 baron concentration is 2390 ppm

. ,pN . 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.c4 .'.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; he%W 72 4 ou 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 HOT a STANDBY by 0700.

d. If loop 1 accumulator boron cotentration 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.B]

Reference:

SSF-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 wt:n the question (exam)

?

Justification:

a. Correct becaus .onduct of Operation (SSP 12.1) restricts power increase l when in an LCO acaon of o nours or less. RCS loop 1 a::umula:or coron concentration of

{

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

7

b. Incorrect because power increase is not allowed wnen in a 1 nour LCO a:: ion 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 , the Unit 1 must be in HOT standby by 0800.

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

!![!M l,lm.N

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006 Emergency Core Cooling Sy. stem V JPM 136 -Recovery From Safetylujection

.anc1 S6 lid Water Co'n'ditions '. J .6 .:47 -

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 f or the direction in FR-C.1 to depressurize intact steam generators?

b.) Why is this action taken?

References Allowed? YES X NO Answer:

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

Reference:

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

OPL271C398 pg 12-15 Applicant Response: SAT UNSAT 4

[.

INADEOUATE CORE COOLING Rev. B

. STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is less than 1920 psig will prevent an inadvertent MSIV closure and keep the condenser available for steam dump.

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

. S/G depressurization at the maximum rate may cause S/G narrow range levels to drop to less than 10% [25% ADV]. This is acceptable and expected for this inadequate core cooling condition.

14. DEPRESSURIZE intact S/Gs to reduce RCS pressure to lesc than 125 psig:

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

1) BLOCK low steamline pressure SI. y

2) CHECK STEAMLINE PRESS l ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT.

[M-4A, A4]

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

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

THEN l DISPATCH personnel to dump steam l USING EA-1-2. Local Control of l S/G PORVs. l (Step continued on next page.)

1 Pace 13 of 19

~

l 1

i

t L ;026.Conrainment Spray System /,JPM.# 57AP Respond to High Contamment l _Presstir^edlice'RHR Sp' ray 3ii ServiceW = .

l Question 2: i l

Given the following plant conditions:

i 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 -

l accordance with ES-13, Transfer to RHR Containment Sump.

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

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

References Allowed? YES X NO l

l Answer:

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

l 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 Applicant Response: SAT UNSAT l

l i

i l

l l

l

l License Applicant Adrninistrative Walkthrough Examination--NRC-1 Examiner Sheet

! A'.1:3 Shift Staffing '

/

~~~

'l

~' '

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 l- satisfactory perfonnance in the licensed operator requalification training program. '

}

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

_ Can the RO fill in for the vacationing RO? Why or why not? w F

References Allowed? YES 3 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.

l

Reference:

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

Applicant Response: SAT UNSAT 5

g __

.J License Applicant Administr:tive Walkthrough Examination--NRC-1 Examiner Sheet i

A:liFShift Staffingt -o 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? i 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) 4 Applicant Response: SAT UNSAT 3,

.,

ML20199E474

Contents

Text

SUBJECT:

SUMMARY

Dear Mr. Brown:

Enclosures:

Reference:

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ML20199E474

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Dear Mr. Brown:

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