ML20153H129

Provides Summary of Workshop on Operator Licensing Exam Techniques Held on 980715.Extends Invitation for Staff to Attend 1998 Training Manager Conference in Atlanta,Ga. List of Attendees & Slides Encl

ML20153H129
Person / Time
Site:	Sequoyah
Issue date:	08/24/1998
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Driscoll R TENNESSEE VALLEY AUTHORITY
References
NUDOCS 9809300322
Download: ML20153H129 (96)

Text

s August 24,1998 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

AND

PUBLIC MEETING ANNOUNCEMENT

- JULY 1998 NRC REGION 11 EXAMINATION WORKSHOP AND NOVEMBER 1998 TRAINING MANAGERS' CONFERENCE - SEQUOYAH NUCLEAR PLANT

Dear Mr. Driscoll:

Region 11 facilitated a workshop on Operator Licensing Examination Techniques on July 15, 1998, conducted at the Richard B. Russell Building. The workshop attendees included

. representatives from all Region ll facilities. It is our opinion that the workshop was beneficial and provided an excellent opportunity for open discussion on the operating test portion of the operator licensing examination process.

During the workshop, we covered a preliminary response to concerns expressed at the January 1998 workshop and a synopsis was promised, but due to the status of the program, cannot be provided. The slides used for our discussions are enclosed.

Also, I would like to extend an invitation to you, and to members of your operations and training staff, to attend this year's Training Managers' Conference to be held on November 5,1998. Our goal for the meeting is to provide an open forum for discussion of operator licensing issues.

The site for this year's conference will be in the Richard B. Russell Building Auditorium on Spring Street in downtown Atlanta. As of this date, the agenda is open. We encourage you to submit, via telephone, a list of topics that you would like to have discussed.

Additionally, we would appreciate an update of the home addresses of your licensed operators.

Please send them in an envelope marked "To Be Opened by Addressee Only" to either Ms.

Beverly Michael or myself. If you have any questions or need additionalinformation, please contact Bev at (404) 562-4640 or me at (404) 562-4638.

Sincerely, (Original signed by T.A. Peebles)

Thomas A. Peebles, Chief

{

t Operator Licensing and Human Performance Branch i

Division of Reactor Safety Docket Nos.: 50-327 and 50-328 License Nos: DPR-77 and DPR-79

Enclosures:

As Stated 9809300322 990824 PDR ADOCK 05000327, V

PDRl;

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cc w/encls:

M. Bajestani, Site Vice President, Sequoyah Nuclear Plant i

Distribution:

PUBLIC B. Michael, DRS r

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0-l OPERATING TEST WORKSHOP Richard B. Russell Auditorium July 15,1998 8:00 Opening Remarks (Johns Jaudon) -

8:20 Standard JPM format (SSNTA) 8:40 ' JPM critical tasks (Hopper & Mellen) l What constitutes a critical task? '

The importance of measurable criteria?

• Good examples

• Bad examples Discrimination (it has to be failable!)

• Good examples

• Bad examples 9:30 JPM Questions (Baldwin)

Direct look up. As defined in ES-602. Attachment 1, B.2.e (p.15)

• examples

• " fixes" to those examples Use of Open ar,a Closed Reference items as defined in ES-301, D.1.1(p.9) which states: " closed reference items may be used to evaluate the immediate actions for emergency and cbg: procedures, certain automatic actions, operating characteristics, interlocks, and set points.. "

• examples

• " fixes" to those example -

l 10:30 Administrative JPMs (Steiner) 11:00 Scheduling (Steiner)

• ways to optimize the material developed

• simulator bottle necks

• control room JPMs

~ reasonable daily work loads

• candidate stress

• exam delays -

11:30 Lunch 1:00 Exam predictability and exam security (Payne) l 1:30 Simulator scenario development (Payne & Hopper).

l

• scheduling and crew makeup

• evaluation tool

• malfunctions in relation to major event

• level of detail l -.-

l 3:30 Questions and Answers 4:30- Closing -

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1 REGION il WORKSHOP - OPERATING TEST JULY 15.1998 Richard B. Russell Building Strom Auditorium David Lane Examiner - Sonalysts Larry Kelley Training Advisor-OHN/Pickering John Brewer Manager - Authorization Training - Ontario Hydro Nuclear Carolina Power and Licht Company I

Tom Hackler Requal Training - Brunswick Curtis Dunsmore Initial Training - Brunswick Tony Pearson initial Training - Lead - Brunswick i

Terry Toler instructor-Harris Rick Garner Sperviisor - Ops Training - Harris Dwayne Coffey LOCT Supervisor - Robinson Dave Neal OIT Lead - Robinson Scott Poteat Support Lead - Robinson j

Duke Enerav Corporation - Catawba. McGuire. and Oconee i

David Re Training instructor

- Charles Sawyer Senior Tech Spec James Presten

' Instructor i

Brent Moore Instructor Bill Caudill Nuclear instructor E. T. Beedle instructor - Catawba Reggie Kimray Nuclear Inst _ructor - Catawba John Supte Operations - Catawba Rob Billings Instructor - McGuire Steve Helms Instructor - McGuire Robby Pope Supervissor - Mcguire Rick Robinson Ops Training Coordinator - Oconee Robin Lane Training Instructor - Oconee J. R. Steely Training Instructor - Oconee David Covar Nuclear Instructor - Oconee Randall Yarbrough Nuclear Instructor - Oconee Bobby Ayers Ops Instructor - Oconee Florida Power Corporation Ivan Wilson Ops Manager

~

Supervisor - Training - Crystal River Jack Springer Johnie Smith Ops Training Supervisor - Crystal River J

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

Operating Test Workshop 2

July 15,1998 Florida Power and Liaht Comoany Dave Brown Initial Training - St. Lucie Tim Bolander Simulator and Exsms - St. Lucie Mike Croteau Instructor - Training - Turkey Point Rich Bretton LOCT Supervisor - Training - Turkey Point South Carolina Electric and Gas Company Jim Callicott Senior instructor Perry Ramicone Instructor - V. C. Summer Southern Nuclear Operatino Company. Inc. (SNC)

Tom Blindauer Senior Plant instructor - Simulator - Farley Bill Oldfield Training - Farley Steve Be Training - Hatch Ken Drawdy Training Instructor - Vogtle Thad N. Thompson Ops Training Instructor - Vogtle 1

Perry Tucker Ops Training Instructor - Vogtle Michael Henry Nuclear Instructor - Vogtle Leon Ray Ops Training Supervisor - Vogtle Fred Howard Ops Reg Instructor-Vogtle Perry Vannier Initial Training - Vogtle Charlton Sal Requal Training - Vogtle Steve Dyer Requal Training - Vogtle Tennessee Vallev Authority Phillip H. Case Simulator Instructor - NC Training Denny Campbell '

Ops Instructor-Browns Ferry Marvin Meer Ops Instructor-Browns Ferry Jim Kearney Ops instructor - Sequoyah Dave Davidson Ops Instructor - Sequoyah Steve Taylor Ops instructor - Sequoyah Ricky C. King Senior Ops Instructor-Sequoyah Ed Keyser Simulator Instructor - Sequoyah Tom Wallace Supervisor-Watts Bar Terry L. Newman Ops Instructor - Watts Bar Jack Cox Training Manager-Watts Bar John Roden Ops Training Manager-Watts Bar Randy Evans HLT Lead - Watts Bar

r 4

Operating Test Workshop 3

July 15,1998 Virainia Electric and Power and Power Company

- Walt Shura Supervisor - Training - North Anna Steve Crawford

~ Senior Instructor (Nuclear) - North Anna Ken Grove Senior Instructor - Surry Ray Simmons.

- Senior instructor - Surry 4

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I EXAH REVIEW GUIDELINES I.

TECHNICAL ACCURACY Is there more than one correct answer?

l Is the given answer correct?

l Adecuate data in the stem?

Is cata in the stem consistent and plausible?

II.

PSYCHOMETRICS: The process of applying sound qualitative processes to mental measurements.

PSYCHOMETRIC FLAWS THAT COULD DIMINISH THE VALIDITY OF THE EXAMINATION!

FLAW

. GUIDANCE APPENDIX B REFERENCE

1. Low level of Question should be written to reflect App. B

./

knowledge the level of knowledge most 1.d appropriate for a specific K/A.

When there is a choice. try to write the question to reflect the higher level.

i

• SEE LEVEL OF KNOWLEDGE BELOW

2. Low operational Does the question test the intent of App. B validity the K/A?

1.a/b/e Could someone do the job safely and 2.k effectively without being able to answer the question?

3. Low discriminatory Will a less than competent candidate App. B validity miss the item?

1.d Can a person understand the principle 2.g being tested and still miss the item?

• SEE LEVEL OF DIFFICULTY BELOW.

4. Implausible Can a distractor be eliminated with App. B Distractors out understan. ding the concept being 2.b/f/h/m tested?

l

5. Confusing or State the question as concisely as App. B ambiguous language possible but provide all necessary 1.c information.

6. Confusing negatives Avoid negative stems.

App.B 2.e

7. Collection of Each item should focus on one K/A App.B true/ false item determined by the stem.

1.f 2.c l

8. backwards logic Examine on a topic in a way that is App.B l

consistent with how the K/A should be 1.h remembered and used.

1

LEVEL OF DIFFICULTY Establish a level of difficulty that will enable an ap)licant who is capable of safely operating the plant to complete and review t1e examination within four hours and achieve a grade of 80 percent or greater. [ES-401 p.4]

Since item difficulty can usually be decreased or increased by revision, the examination author need not be overly preoccupied with difficulty when writing the items.

The author should focus on achieving a valid measure of the concept he is attempting to evaluate.

[ Appendix B p.

6]

LEVEL OF KNOWLEDGE Level 1: FUNDAMENTAL KNOWLEDGE The recall or recognition of discrete bits of information.

- knowledge of terminology

- definitions

. /

- set points

- other specific facts Level 2: COMPREHENSION Involves the metal process of understanding the material through relating it to its own parts or some other material.

- describing or recognizing relationships

- recognizing how systems interact

- consequences or implications of events H

Level 3: ANALYSIS, SYNTHESIS OR APPLICATION Involves assembling. sorting or integrating information to predict an i

event or outcome.

Requires mentally using the knowledge and its meaning to solve problems.

1 l

L

l NUREG-1021. APPENDIX B. GUIDANCE l

1.

Generic Princioles a.

Ensure that the concept being measured has a direct, important relation ship to the ability to perform the job.

b.

Make sure that the question matches the intent of the K/A.

c.

State the question unambiguously and precisely.

d.

Writ' the question at the highest level of knowledge reflected in the e

testing objective.

e.

Avoid questions that are unnecessarily difficult or irrelevant.

.f.

Limit the question to one concept or topic unless a synthesis of

~

concepts is being tested.

g Avoid copying text directly forma training or other reference material.

h.

Avoid backward logic questions.

2.

Other Construction Guidelines a.

Use four answers.

b.

Do not use "none of the above" or all of the 'above~

c.

Do not oresent a collection of true-false statements, d.

Define the question, task or problem in the stem.

e.

Avoid using negatively stated stems when possible.

f.

Provided sufficient counter balance in questions with multi-part answers.

g.

Include common misconceptions as Distractors.

h.

Make all answer options homogeneous and highly plausible.

I.

If the answers have a logical sequence, put them in order.

j.

Avoid overlapping answer options.

k.

Do not include trivial distractors with more important distractors.

1.

Vary the location of the correct answer.

m.

Avoid specific determiners that give clues as to the correct answer.

l

1 (1) distractors that do not follow grammatically from the stem.

(2) options that can be judged correct or incorrect without reading the stem.

(3) equivalent and /or synonymous options which rule out both options.

(4) an option which includes another option.

(5) implausible distractors.

(6) a correct answer which is longer that the distractors.

(7) cualifiers in the correct answer unless they are used in c istractors.

(e.g. probably. ordinarily)

(8) words such as "never", "always" which suggest a wrong answer.

(9) a correct option that differs from the distractors in

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favorableness. style, or terminology.

= _

1 III.

BEANS 1

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BEAN LIMIT REFERENCE Knowledge level questions

< 50 ES-401 p.4 SRO / RO overlap 5 75 ES-401 p.5 Questions from training class quizzes 5 25 ES-401 p.5 OR last two NRC exams.

Questions from licensee audit exam 50 ES-401 p.5

.(same author for audit exam)

./

Ouestions from licensee audit exam 55 ES-401 p.5 (independent author for audit exam)

Questions from licensee bank 5 50 ES-401 p.5 New questions at comprehension or

> 10 ES-401 p.5 analysis i

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4 JPM CRITICAL TASKS AND MEASURABLE CRITERIA G.

-O m R

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Develop Performance Criteria

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The JPM should have meaningful performance requirements that will 4

provide a legitimate basis for evaluating the examinee's ability to i

i safely operate the system or the plant.

Artificially subdividing.,

existing tasks to generate new ones may dilute the value of the JPMs to a point where they become meaningless.

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The JPM shall identify specific performance standards, or check points, that will permit the examiner to evaluate successful progress toward completing the task in accordance with the procedural references.

Detailed control an~d indication nomenclature and criteria l

positions and meter readings) should be identified whenever(e.g., switch

possible,

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even if these criteria are not specified in the procedural step.

The JPM should also note any important observations that should be made by the examinee while performing the task.

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The JPM must clearly identify the task standard; i.e., the predetermined outcome (qualitative and/or quantitative) against which task performance will be measured. Hv.erygp.t;o.gedural. step that.the e.xaminee must perform (dbyVeotJylg(3itreg!la?complishthe ~ task staccurately,iin the proper

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Eiili)Mniordento andard shallibe identified as'*d Tctiticalistep and shall have an associated performance standard.

Ifi there are any specific procedural restrictions on the sequence in I

which the steps are performed they shall be clearly noted in the JPM.

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,ieasurai e Jer"ormance

ncica : ors

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A measuraJ e Jer =ormance incica:or consiS :s o~' Josi :ive ac: ions

la : an o.Jserver can oJjec:ive~y icen:i=y

acen Jy an incivicua~(/ crew).

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Exam'J es:

Ac: ions

eken in

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o an A~~t/S.

Con:ro~

maniJu a: ions suc1 as a

manua reac:or tri'3 or

le star: of

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an ECCS 'Jum3.

reJor:s or no: 1~"1 cation of VerJa ~

aJnorma Jarame:ers or conci: 1ons.

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\\on-measuraJ e 3erformance

nci,ca : ors:

Veri =ica: ion

la: an exJec:ec resJonse las occurrec:

.) Veri =ica: ion anc/or ensure s:e'Js w1ic1 recuire no ac: ion.

JassiVe o.Jserva: 1ons suc, as moni:oring

le :Jer =ormance of a sys:em.

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~~ as( s:ancarcs slou c inc~ uce oJjec:ive.recuiremen~:s wi:1 a ~

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=aci~ i :y anc

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1e acce7:ance cri:eria mus: Je af e to ciscrimina:e/icen:i=y aoor aerformance 3ac

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Jressure fa~

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JumJ is a Jerformance measure

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1e oJera :or Jer =orming

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le Jrocecure, even

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le ~=acili:y icensee exJects the oJera:or

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=aci~i:y ~1censee slou c

agree in wri:ing

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=or eac1 CS or C~~ are acceJta] ~ e Je= ore

le examina: ion Jegins.

or

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acceJtaJ e Jressure to erance (e.g.,

wi :lin 200 Jsi) wou~ c c~ ari =y t1e stan,carc o = :Jerformance

la : is ex'Jec:ec.

" :mmecia :e.~ y Jora :e

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1ere is no ce =ini: ion o

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Anywlere

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mus: Je accura:e anc.inc~uce a~~

ex'Jectec inc.ica : ions.

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JOB PERFORMANCE MEASURE i

f Provide this page to the Candidate Initial conditions:

A Station Blackout has occurred on Unit 2. Unit 1 is in a LOOP with both Emergency Diesel Generators in service. The NPS and ANPS have determined the need to crosstie electrical power from the 1 A EDG to the 2A3 4.16 KV switchgear via the SBO AB Bus Crosstie.

Initiating Cue:

The ANPS has directed you to accomplish the Unit to Unit crosstie to the 2A3 4.16 KV Bus by performing 2-EOP-99, Table 7 and then 2-EOP-99, App. V within 10 minutes.

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0521129. Rev D2 Page 15 et 16

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JOB PERFORMANCE MEASURE d

2 (C) Indicates a Critical Step PERFORMANCE CHECKLIST 1.

(C)

Element / Step OPEN and GREEN FLAG the following startup transformer breakers:

A.

Standard:

S.U. Transformer 2A (2-30102) l Cue:

GREEN LIGHT ON, FLAG GREEN l

B.

Standard:

S.U. Transformer 2B (2-30202)

Cue:

GREEN LIGHT ON, FLAG GREEN C.

Standard:

S.U. Transformer 2A (2-20102)

Cue:

GREEN LIGHT ON, FLAG GREEN D.

Standard:

S.U. Transformer 28 (2-20302)

Cue:

GREEN LIGHT ON, FLAG GREEN 2.

(C)

Element / Step Ensure the following breakers are GREEN FLAGGED and OPEN:

A.

Standard:

Aux Transformer 2A (2-30101 ) (2WB7)

Cue:

GREEN LIGHT ON, FLAG GREEN Standard:

Aux Transfoimer 2B (2-30201) (2W85)

Cue:

GREEN LIGHT ON, FLAG GREEN Comments:

C32H 29. Rev C2 Pay 6 eN 6

JOB PERFORMANCE MEASURE (C) indicales a Critical Step PERFORMANCE CHECKLIST

2. (Cont'd)

'B.

Standard:

Aux Transformer 2A (2-20101) (1W86)

Cue:

GREEN LIGHT ON, FLAG GREEN Standard:

Aux Transformer 2B (2-20301) (1WB4)

Cue:

GREEN LIGHT ON, FLAG GREEN C.

Element / Step Tie breakers between normal and emergency 4160V buses:

Standard:

4.16 KV Bus Tie 2A2-2A3 (2-20109)

Cue:

GREEN LIGHT ON, FLAG GREEN Standard:

4.16 KV Bus Tie 2A3-2A2 (2-20209 Cue:

GREEN LIGHT ON, FLAG GREEN Standard:

4.16 KV Bus Tie 2B2-283 (2-20309)

Cue:

GREEN LIG'HT ON, FLAG GREEN Standard:

4.16 KV Bus Tie 283-2B2 (2-20411)

Cue:

GREEN LIGHT ON, FLAG GREEN p-D.

Element / Step 4.16 KV Bus 2AB Tie breakers Standard:

Feed to 4.16 KV Bus 2AB (2-20206)

Cue:

GREEN LIGHT ON, FLAG GREEN Standard; incoming feeder from 4.16 KV bus 2A3 (2-20505)

Cue:

GREEN LIGHT ON, FLAG GREEN 0221129, Rev D2 Page 7 of16

JOB PERFORMANCE MEASURE

?'

(C) Indicates a Critical Step PERFORMANCE CHECKLIST 2.D. (Cont'd)

Standard:

incoming feeder from 4.16 KV bus 283 (2-20504)

Cue:

GREEN LIGHT ON, FLAG GREEN t

Standard:

Feed to 4.16 KV Bus 2AB (2-20409)

Cue:

GREEN LIGHT ON, FLAG GREEN

]

3.

(C)

Element / Step Off,N the following 4.16 KV feeder breakers to the station service fransformers:

A.

Standard:

Station Service Transformer 2A1 (2-20110)

Cue:

GREEN LIGHT ON B.

Standard:

Station Earvice Transformer 2A5 (2-20210)

Cue:

GREEN LIGHT ON C.

Standard:

Station Service Transformer 2A2 (2-20213)

Cue:

GREEN LIGHT ON

..?

D.

Standard:

Station Service Transformer 2B1 (2-2D310) i I

l Cue:

GREEN LIGHT ON I

Standard:

Sta on Service Transformer 282/255 (2-20402) l Cue:

GREEN LIGHT ON 0821129. Rev D2 Page B of 15

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JOB PERFORMANCE MEASURE U

(C) Indicates a Critical Step PERFORMANCE CHECKLIST I

4.

(C)

Element / Step OPEN and GREEN FLAG the following 480V feeder i

breakers from the station service transformers:

A.

Standard:

480V Bus 2A1 Feeder (2-40103)

Cue:

GREEN LIGHT ON, FLAG GREEN B.

Standard:

480V Bus 2A5 Feeder (2-40361)

Cue:

GREEN LIGHT ON, FLAG GREEN l

C.

Standard:

480V Bus 2A2 Feeder (2-40219) i I

Cue:

GREEN LIGHT ON, FLAG GREEN l

D.

Standard:

480V Bus 281 Feeder (2-40419)

Cuu-GREEN LIGHT ON, FLAG GREEN E.

Standard:

480V Bus 2B5 Feeder (2-40653)

Cue:

GREEN LIGHT ON, FLAG GREEN F,

Standard:

480V Bus 2B2 Feeder (2-40503)

Cue:

GREEN LIGHT ON, FLAG GREEN SAT UNSAT Comments:

l 0821129. Rev C2 Page 9 of 15 l

V JOB PERFORMANCE MEASURE (C) Indicatis a Critical Step PERFORMANCE CHECKLIST 5.

(C)

Element / Step DEF.N the following 480V bus tie breakers A.

Standard:

480V Bus Tie 2A2-2AB (2-40220)

Cue:

GREEN LIGHT ON B.

Standard:

480V Bus Tie 2AB-2A2 (2-40702)

Cue:

GREEN LIGHT ON C.

Standard:

480V Bus Tie 2AB-2B2 (2-40706)

Cue:

GREEN LIGHT ON D.

Standard:

480V Bus Tie 2B2-2AB (2-40504)

Cue:

GREEN LIGHT ON SAT UNSAT 4

i Comments:

0821129. Rev C2 10of16

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JOB PERFORMANCE MEASURE (C) indicat'is a Critical Step PERFORMANCE CHECKLIST l

6.

(C)

Element / Step Establish communications with Unit 1 Standard:

ESTABLISH COMMUNICATIONS with Unit 1 via Gai-Tronics or plant radio (if available).

1 Cue:

COMMUNICATIONS ARE ESTABLISHED 7.

Element / Step PLACE the following pump switches in the PULL TO LOCK position:

(C)'

A.

Standard-2A ICW Pump Cue:

SWITCH IN PULL TO LOCK B.

Standard:

2B ICW Pump Cue:

SW1TCH IN PULL TO LOCK i

Standard:

2C ICW Pump 1

Cue:

SWITCH IN PULL TO LOCK (C)

D.

Standard:

2A CCW Pump Cue:

SWlTCH IN PULL TO LOCK E.

Standard:

2B CCW Pump Cue:

SWlTCH IN PULL " LOCK Standard:

2C CCW Pump Cue:

SWITCH IN PULL TO LOCK SAT UNSAT Comments:

0221129, Rev C2 Page 11 of 16

JOB PERFORMANCE MEASURE (C) indicates a Critical Step PERFORMANCE CHECKLIST 8.

(C)

Element / Step Verify the EDG output breaker on the selected 4.16 KV bus is open Standard:

VERIFY the EDG output breaker on the selected 4.16 KV bus (2-20211)is OPEN Cue:

GREEN LIGHT IS ON. REPORT UNIT 1 IS READY TO CROSSTIE AB 4.16 KV BUSES.

9.

(C)

Element / Step Close in the Unit 2 SBO breaker Standard:

CLOSE IN the Unit 2 SBO breaker 2-20501.

Cue:

RED LIGHT ON 10.

(C)

Element / Step Request the Unit 1 control room to close the Unit 1 SBO breaker Standard:

REQUEST the Unit 1 control room to close the Unit 1 SBO breaker 1-20501.

i Cue:

UNIT 1 ACKNOWLEDGES REQUEST.

END Element / Step TERMINATION Standard:

Student requests Unit 1 to close the Unit 1 SBD crosstie breaker.

Comments-0821129, Rev D2 Page 12 of 15

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JOB PERFORMANCE MEASURE (C) indicates a Critical Step PERFORMANCE CHECKLIST 1.

Element / Step:

Review the EOOS log and determine if channel RM-26-18 (PAG-203) has been declared out of senrice.

Standard:

Verifies RM-26-18 is not out of service.

.,,*" p d

Cue:

RM-26-18 IS NOT OUT OF SERVICE p

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2.

Element / Step:

. Check the Met Towerfor operability Standard:

Verifies Met Tower chart recorder working properfy..

Cue:

MET TOWER CHART RECORDER TRACKING PROPERLY.

t 3.

Element / Step:

Verify gas release permit properly filled out and authorized, enter release permit number and tank to be released on procedure.

Standard:

Verifies permit filled out property and authorized, enters release permit number (98-007) and 2C GDT on procedure.

Cue:

98-007 AND 2C GDT ENTERED ON PROCEDURE

4. (C) Element / Step:

Verify the following vaive alignment:

V6745 Closed V06142 Open V7071 Open V7070 Open V7072 Locked Closed V6742 Locked Closed Standard:

Verify all above listed valves in proper positions

~

Cue:

V6745 FULLY CLOCKWISE V06142 FULLY COUNTERCLOCKWISE V7071 FULLY COUNTERCLOCKWISE V7070 FULLY COUNTERCLOCKWISE V7072 FULLY CLOCKWISE WITH LOCK ATTACHED V6742 FULLY CLOCKWISE WITH LOCK ATTACHED SAT UNSAT Comments:

D!'.21153. Rev DO Page 5 ef 12

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JOB PERFORMANCE MEASURE i

(C) Indicates a Critical Step PERFORMANCE CHECKLIST i

4.

Element / Step Check closed FCV-25-9," Continuous Containment / Hydrogen Purge Control Valve Fifter inlet."

Standard:

At the NON-SAFETY VENTILATION HVAC PANEL:

VERIFY CLOSED FCV-25-9 j

Cue: -

0%, GREEN LIGHT ON, RED LIGHT OFF SAT' UNSAT i

Comments:

i

5. (C) Element / Step Throttle FCV-25-28," Continuous Containment / Hydrogen Purge Control Vaive Bypass" to approximately 10% OPEN position.

Standard:

At the NON-SAFETY VENTILATION HVAC PANEL: POSITION FCV 28 to the open position UNTIL the valve position indicates 1D% OPEN Cue:

10%, BOTH RED & GREEN LIGHTS ON SAT UNSAT Comments:

6.

Element / Step Start HVE-6B," Shield Building Exhaust Fan."

Standard:

At the B TRAIN EMERGENCY VENTILATION HVAC PANEL:

POSITION HVE-6B control switch to START Cue:

RED LIGHT ON, GREEN LIGHT OFF SAT UNSAT Comments:

oe21ose.Rev 06 Pasp 6 eM2

JOB PERFORMANCE MEASURE C. 8 The system / equipment status reflects the overallintent of what the JPM required upon completion.

D.

Correctfy perform all critical steps.

All steps where procedural guidance exists may be considered critical. Performance of Off-Normal Operating Procedure immediate actions will be from memory.

During the course of the JPM, there may be some tasks you will have to perform that will require you to implement contingency actions in order to complete them. Even in l

these' cases, you are expected to make decisions and take actions based on the indications available and in accordance with the facility's' procedural guidance.

j Initblinc Cue (s):

The ANPS has directed you to respond to the abnormal alarm LAW 1-0120035.

References:

ONP 1-0120035, Rev 18 During the performance of the task I will tell you which steps to simulate or discuss.

Verbalize each step before you do it. This gives you a chance to self-check and use STOP during the performance of each task element.

Verify the position or condition of equipment or compor ents by pointing to the instrumentation and providing a brief explanation of how the indication is used for verification.

I will provide you with the appropriate cues for steps which are simulated or discussed.

You may use any approved referen::e materials normally available in the execution of this Job Performance Measure, including logs.

Do you understand these directions?

ff you have any questions, ask them now, and I will answer them.

During the test I cannot answer questions.

When you corrplete all steps corre::'Jy, you will pass this job performance measure.

Begin the task now.

DE21G43, Rev D6 Pap 4 cf 10

~

JOB PERFORMANCE MEASURE 8

PERFORMANCE CHECKLIST

/

1.

Eiement/ Step Verify pressurizer spray, pmportional and backup heaters are operating properly in automatic.

Standard:

OBSERVE any of the following Pressurizer pressure indications on RTGB 103 and/or RTGB 106 to DETERMINE improper automatic response:

PR-1100 PIC-1100X PIC-1100Y Pi-1102A Pb1102B Pb1102C PI-1102D PIA-1102ALL PIA-1102BLL PIA-1102CLL PIA-1102DLL Observe the proportional heater control and indication for P-1 and P-2 Observe the B/U heater control and indication for banks B-1 through B-G Observe the moray valve controller HIC-1100 NOTE TO EXAMINER: The CUES should provide sufficient information to diagnose the failure of the selected pressure channel LOW. It should be recognized that Pressurizer pressure is actuallyincreasing. All of the indicators listed may not be used by the operator v. hen diagnosing this probiem. The student may refer to Appendix "A" for expec'cd automatic response.

Cue:

For PR-1100, PIC-1100X, PIC-1100Y :

SELECTED CHANNEL-DOWNSCALE LOW, NONSELECTED CHANNEL IS =2300 PSIA AND SLOWLY INCREASING For other PI instruments:

vNDICATED PRESSURE IS =2300 PSIA AND SLOWLY INCREASING For Pressurizer heaters:

SWITCHES IN AUTO, HEATERS LIGHTS INDICATE ON

?

For Pressurizer spray controller HIC-1100:

INDtCATES NO OUTPUT SAT UNSAT Comments:

082100. Rev 06 Page 5 of 10

JOB PERFORMANCE MEASURE (C) Indica [es a Critical Step PERFORMANCE CHECKLIST s

2.(C) Element / Step H the selected pressure channel has failed, Then shift to the operable pressure channel.

Standard:

At RTGB 103: POSITION HS-1100 to the attemate pressure control channel Cue:

ALTERNATE CHANNEL SELECTED. PROPORTIONAL HEATER OUTPUT REDUCING, SPRAY VALVE OUTPUT RISING, PZR PRESSURE RETURNING TO NORMAL /

NOTE - The ANPS directs that the rest of the ONP be carried out.

SAT UNSAT Comments:

3.

Element / Step Verify SE-02-03 and SE-02-04 " Auxiliary Spray Valves", are closed Standard:

At RTGB 103: DETERMINE keyswitches and indicating lights for SE-02-03 and SE-02-04 to be CLOSED Cue:

SE-02-03, SE-02-04 GREEN LIGHTS ON AND RED LIGHTS OFF SAT UNSAT Comments:

4.

Element / Step Verify power operated relief valves are closed.

~

Standard:

At RTGB 103:: DETERMINE position indicating lights for both power operated relief valves CLOSED Cue:

PORV-1402, PORV-1404 GREEN LIGHTS ON AND RED LIGHTS OFF SAT UNSAT Comments:

l l

Oc21GQ Rev 06 Page 6 cf 10

l JOB PERFORMANCE MEASURE 8

PERFORMANCE CHECKL1ST 5.

Element / Step Ensure that PORVs V1402 and V1404 hand switches are in the proper position for existing plant conditions.

Standard:

At RTGB 103: DETERMINE PORVs hand switches are in NORMAL Cue:

PORVs HAND SWITCHES IN NORMAL SAT; UNSAT Comments:

l S.

Element / Step Verify pressure anomaly is NOT caused by a large rate of change of Tavg.

Standard:

At RTGB 103: OBSERVE any of.the following indications and DETERMINE that Tavg is fairiy stable:

TR-1111X/1121X, Tb1102A, TR-1115/1125, Tb1102B, TIA-1111X, Ti-1102C, TIA-1121X, Tb1102D, TIC-1111Y, TIC-1121Y Cue:

Tavg HAS BEEN STABLE THROUGHOUT THE EVOLUTION SAT UNSAT Comments:

END Ekment/ Step TERMINATION Standard:

The pressurizer pressure control system is responding property to control pressure at 2250 psia.

l l

i I

l i

M

,kW l

l

l OPERATING TEST WORKSHOP l

RUSSELL BUILDING i

i JPM QUESTIONS RICK BALbWIN JULY 15,1998

!~

ES-301, D1(l}

i S :a :es~:

T1e 3rescriatec cues: ions ~or Ca':egories A anc B may incluce a com 3l nation o" 03en-anc c osec-re erence items. Open-reference i~: ems tlat rec uire a33 icants :o anolv t1eir l

knowledge o ~ t1e 3 an: to '30s':u'atec norma a3 norma anc emercency si':uatio,ns are oreferre_d. Cl5 sed-I reference i~:e.rhs may be used to.

eva ua~:e ~:le immecla~:e ac':lons o~

emercency anc.o~:ler arocec ures, t

cer:ain au:oma~:Ic ac: ions 03 era':inc clarac: eristics inter oc<s,, se: aoinis as a33roariate to he "aci i:y. Minimize t1e use o" closed-reference c ues~:lons :la:

re y so e y on memory, anc avoid :le

~

use o 03en-re~erence qu_e_sti_ons_

who_s_e ans_w_er c_an sim alv b_e lo_oked up if the applicant can "idd the_

corre_c1_d_o_cument.

~Re"er :o.Section 3.6 o" A more guidance regarc.

ppendix C =or ing :le ceve oomen~: anc use o~ 03en re erence c ues:lons or :le wa < :1roug 1 :es:.

i l

Appendix C:

=

I S':ates:

6. Develoa Pre-scriatec Follow-ua l

Questions I" ~:he JPM wi 3e usec curinc an initia licensinc examination, it shal"incluce a suf"icieri: num 3er o" arescriatec cuestions lwitl answers anc l

re"erencesh to eva uate t7e examinee's uncers':ancinc o" two <now ecqe anc/or 3iity (K/A1 s:atements re atec to the a

sys:em or fas<. More.tlan one c uestion may.3e rec uirec to e.ec:ive y eva uate some </A s':a':ements.

1e mos': a33roarlate "ormat "or tlis a33 ication is t7e short-answer c uestion to com.po, w1ich recuires t7e examinee se a response rat er tha.n se ect " rom amonc a se': o~ al':ernative res3onses as is fle case wi':1 mu ti3 e-cloice, ma,tclinc, anc true/"a se c ues: ions.

Kee3 ~:le =o owinc c'uice ines, in accition ~:0 tle ceneric P:em cons':ruc': ion 3rincia es iri Ap3encix

B, in minc w1en are3arinc

':le c uestions:

a. Provice clear, exa icit cirections

/c uice ines "or answerinc t1e c"uestion so tlat the exa"minee uncerstancs what constitutes a fully correct response.

Choose words carefully to ensure tlat the stiau ations anc rec uirements o" t1e c ues': ion are a33roariate y conve ec.

Worcs suc1 as ','eva u. ate " y'ou~: ine_,"

ang tlai: is n,o': necessar.a o~: o~ cetal exo aln can Invi:e i y re:evan~:.

.3. Ma<e sure tla: :le answer key to) ponse matches {and is limitedquestion.quiremen in the res the re W1en a33roariate, incicate t7e amoun: o~ 3ar:la crecr:

to 3e grantec "or an incom3 ete answer.

For cuestions recuirinc com3uta: ion, specify the_dearee of precision expecfed.

ry'to ma <e t7e answer turn ou: to 3e w1o e num3ers.

.c. Avoic giving away Dar: or a

.o~ t.le answer 3)c:le way t7e cuestion is worc ec

-or exam 3.e:

"I~' the letcown ine 3ecame 03structec, coulc 3 oration o~ t1e olant 3e accomolislec slort y a~ ter a reactor tria ':o au': the 3 an~:

in co c shutcown?

I so, how?"

A tes':-wise examinee can realize tlat t1e answer las to.3e yes, or.

e se :he seconc 3ar: o- :le cues: ion woulc lave reac sometlinc ike "

not, wly not?"

c. Avoic waa: cou c 3e consicerec

" trick" cuestions in w1ica :le answer

<ey coes no~: 3recise y matc, t1e c uestion.

For exama e as<inc "Fow co' t1e SI ~:ermination c, riteria"

~

61dnce 'ollowinc a S reinitia': ion?"

irn;3 iss tlat :le":ermina': ion. criteria wi clange, w1en in ac':ua r:y

ley c o no':.

e. Avoid direct look-up questions that only require the examinee to recall where to find the answer to the question.

~

~ 1e 03 era:iona orien:a: ion recuirec o

c uestions on t7e wa <-throuc 1 :est anc :le examinee's access to" re erence cocumen:s. arcue acainst

~

~

le use o cuestions :la: test "or reca anc memoriza: ion. Any questions that do. not requi.re any analysis, synthesis, or application of inTormafion by the examinee should be answerable without the aid of reference materials.

Re er

o ES-602., A::acamen~: :, or a more ce:al ec ciscussion o-cirec: oo <-u 3 c ues :lons.

=orm.ES-602 "N RC Clec< is: or 0 3en-Re-erence, _ es:

. ems, contains a is: or c ues:lons. :la.:.can De u.sec :o eva ua:e

le sul:a 31 r:y o--

le o ow-u:3 cues:lons

,3 a_nnec or

le wa

< :1rouc 1 Jor:lon o

le o3 era:inc :es:." A :louc 1

le clec< is: was ceve 03ec or use in

eva uatinc recua i"ication writ:en examinations, t 9 most o" t7e criteria

< i.e., a exce 3 a 3 3l.ra':ing on i':em,10,

' ', anc t 7e

</A

7) are generica y Ica,3le aric. cou c 3.e usec as a 3 asis for revisinc or rejec':Inc aro30sec walk-througl cues: ions.

ES-602 NRC Checklist for Form ES-602-1 Open-Reference Test items Test item Level 1.

Does each test item have a occumented link to important licensee tasks, K/As, and/or facility learning objectives?

2.

Is each question operationally oriented (i.e., is there a correlation between job demands and test demands)?

3.

Is the question at least at the comprehension-level of knowledge?

4.

Is the context of the questions realistic and free of window dressing and backwards logic?

5.

Does the item require an appropriate use of references (i.e., use of analysis skills or synthesis of information either to discern what procedures were applicable or to consult the procedures to obtain the answer)?

6.

Is the question a " direct look-up" ques.* ion, or does one question on the examination compromise another? A "clirect look-up question"is defined as a e restion that immediately directs an licensee to a particular reference where the

wer is readily available.

7.

.oes the question possess a high K/A importance factor (3 or greater) for the job i asition?

8.

Does the question discriminate a competent licensee from one who is not?

9.

Is the question appropriate for the written examination and the multiple choice format?

10.

Do questions in Section A take c%antage of the simulator control room setting?

1 11.

Does any question have the potential of being a " double-jeopardy" question?

12.

Is the question clear, precise, and easy to read and understand?

13.

Is there only one correct answer to the question?

14.

Does the question pose situations and problems other than those presented during training?

15.

Does the question have a reasonable estimated response time?

l l

l l

l

l CONCLUSIONS

!'i

@ 03en-re erence cuestions w1ose l

answer can sima y 3e ookec ua i

':he a33 icant can finc :he correc':

cocumen~: are NOT acce ata a e.

l

@ Analy. sis, Synthesis, Comarelen.sion cues': ions slou c 3e usec to avoic j

cirect ook-ua pro 3l ems.

@ On al cuestions where the ex3ectec resaonses are multi 3 art. we will j

notry the cancicate o t7e numoer o

<nown correc': answers anc t7e num3er neecec or u

crec it.

@ Examiners will ask non-arescriatec fo low u3 cue 57: ions, as necessary, to c arify or con irm t7e cancicate's uncerstancing of 3rescriatec cues: ions or are-alannec :as(s.

The followu] c ues': ions shoulc 3e to

~ urtler ex3 lore the ac< o cancicate cuest.ecge in the saecific area in

<now ion i

@ Assign Joint va ues to each answer that n.as multio.e aar:s,istency.

to ensure examiner gracing cons

@ Icentify on the cancica':e's sheet t7e status o reference material usage.

@ There is aro30 sal to im30se an a lowance o on y 30% closec-reference c uestions o" eitler Category A or B.

l i

l l

DIRECT LOOK QUESTIONS l

WITH ACCEPTABLE CORRECTIONS l

I RO Admin. A.1 (Fuel Handling), Question 1

. 2.1.23 3,9/4.0 QUESTION:

Given the following plant conditions:

Reactor shutdown for refueling outage Unit offline:

1/1/9712:01 AM Entered Mode 3: 1/1/97 2:10 AM e

~

Entered Mode 4: 1/1/97 6:17 AM

.. Entered Mode 5: 1/1/97 11:45 PM What is the earliest date/ time core ofYload can conunence?

ANSWER:

1/5/97 6:10 AM 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown REFf-,_. CE:

GP-010, " Refueling", step 5.3.1 1

+

1 01/06/98 5:43 AM.

AUTHORIZED COPY c

INIT

^

~

IF needed for SFP water clarity, THEN place the SFP 5.2.28 skimmer in service IAW OP-910.

~ ~ ~ ' " ~ ~ '

5.3 Fuel Assembly and Core Component Movement NOTE:

A case evaluation has been performed IAW PLP-037 for each major evolution in this section. The case determination is defined prior to each applicable evolution, 3 5.3.1 Check that the Reactor has been subcritical for at least h

100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> AND record hours suberitical. (TRMS 3.12) hrs 5.3.2 Verify EST-001 is complete.

ENG NOTE:

The following equipment tests need to be completed prior to moving fuel.

5.3.3 Verify the following equipment necessary to support fuel off-load has been tested IAW EST-030 AND mark the equipment

~.

that is not needed to support fuel off-load N/A.

- Fuel Transfer System (Section 8.6.2)

ENG

- Manipulator Crane (Section 8.6.3)

ENG

- CV RCC Change Fixture (Section 8.6.4)

ENG

- New Fuel Handling Equipment (Section 8.4)

ENG

- NFB New Fuel Lift (Section 8.5.1)

ENG

- SFP New Fuel Monorail (Section 8.5.2)

ENG

- SFP Bridge Crane (Section 8.5.3)

ENG

- SFP New Fuel Elevator (Section 8.5.4)

ENG m

Rev.36 Page 24 of 79

l Decay Time 3.12 3.12.. DECAY. TIME TRMS 3.12 Movement of fuel within the core shall not be '

(CTS 3.8.1.h) initiated prior to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.

APPLICABILITY:

MODE 6.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.

Requirements of TRMS A.1 Sus and movement of fuel Immediately not met.

witlin the core.

TEST REQUIREMENTS TEST FREQUENCY i

None.-

NA l

l 5

t l

3.12 1

. ~ _ _ _.. _ _. _. _.. _ _

_. _ _. _. _ ~

Decay Time B 3.12 8 3.12 DECAY TIME BASES The restriction of not moving fuel in the reactor for a period of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown reduces the consequences of a fuel handling accident by providing for decay of short-lived fission products and the reduction of fission gas inventory in any potentially failed fuel.

Fuel handling accidents in containment and the Spent Fuel Building have been evaluated by postulating that the failure of all fuel rods in one assembly occurs 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.

1 1

4 P

B 3.12-1

~

i 1

RO Admin. A.1 (Fuel Handling), Question 1 2.1.23 3.9/4.0

-REFERENCE ALLOWED t

QUESTION:

Given the following plant conditions:

Reactor shutdown for refueling outage Unit offline:

1/1/9812:01 AM

~

. Entered Mode 2: 1/1/9812:38 AM

e. Entered Mode 3: 1/1/98 2:10 AM Entered Mode 4: 1/1/98 6:17 AM

=

Entered Mode 5: 1/1/98 11:45 PM e

What is the earliest date/ time core offload can commence?

ANSWER:

1/5/98 6:10 AM (100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown)

REFERENCE:

GP-010," Refueling", step 5.3.1

~

PLP-100 (Technical Requirements Manual), section 3.12 4

h kUSN 02/13/98 9:58 AM

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

RO JPM CR-019, Question 2 006 Ki 03 4.2/4.3 s

QUESTION:

Given the plant conditions:

Mode 1,100% power

. ' Accumulator levels / pressure "A"

68 %

600 psig "B"

70 %

630 psig "C."

70%

645 psig Annunciator APP-002-B4 "SI ACCUM A HI/LO PRESS" illuminated Describe the basis for NOT being allowed to raise the pressure in the "A" Accumulator and lower the pressure in the "C" Accumulator by simultaneously opening the vent 1 -

valves for the two accumulators.

ANSWER:

Sjmultaneously opening the accumulator vent valves would connect the two accumulator

- gas spaces. If a large break LOCA were to occur on either of the loops ("A" or "C") both accumulators would depressurize invalidating the LOCA analysis.

(Not required for credit: Accumulator design capacity is based on one accumulator spilling to the containment floor through the break, the other two accumulators fill the core to the mid-plane.)

REFERENCE:

FSAR section 6.3.2.2.6 OP 202, step 4.20 i

APP-002-B4"SI ACCUM A HI/LO PRESS" 01/06/98 5A3 AM II

- w

(

p we

-+

+

6-e

4 UPDATED FSAR 3.

Finally the second low level alarm on the RWST sounds. At this l

tim 1, the: operator performs the switchover operation.

The changeover from injection to recirculation is effected by the operator in the Control Room via a series of manual switching operations according to written procedures. Valves SI-856A and B are manually closed at the valves.

Remotely operated valves for the injection phase of the SIS. (Figures 6.3.1-1 and 6.3.1-2) which are under manual control, (this is, valves which normally are in their ready position and do not receive a SI signal) have i

their positions indicated on a common portion of the control board.

At any time during operation, when one of these valves is not in the ready position for injection, it is shown visually on the board. Table 6.3.2-1 is a listing of the instrumentation readouts on the control board which the operator can monitor during recirculation.

In addition, an audible annunciation alerts the operator to the condition.

6.3.2.2.5.1 Location of the major components required for recirculation. The RHR pumps are located in the RHR pump pit (Elevation 203 ft 0 in.) which is below the basement floor of the Auxiliary Building (Elevation 226 ft 0 in).

The RHR pump pit is located between the Containment Building and the Auxiliary Building.

The residual heat exchangers are located on the first floor of the Auxiliary Building.

The high head SI pumps, component cooling pumps and component cooling heat exchangers are located in the Auxiliary Building (Elevation 226 ft 0 in).

The service water pumps are located in the intake structure, and the redundant piping to the component cooling heat exchangers is run underground.

6.3.2.2.6 Accumulators. The accumulators are pressure vessels. filled with barated water and pressurized with nitrogen gas.

During normal plant operation, each accumulator is isolated from the RCS by two check valves in series.

Should the RCS pressure fall below the accumulator pressure, the check valves open and borated water is forced into the RCS. Mechanical operation of the swing-disc check valves is the only action required to open the injection path from the accumulators to the core via the cold leg.

The accumulators are passive engineered safety features (ESF) because the gas forces injection; no external source of power or signal transmission is needed to obtain fast-acting, high-flow capability when the need arises.

One accumulator is attached to each of the cold legs of the RCS.

The design capacity of the accumulators is based on the assumption that l

flow from one of the accumulators spills onto the containment floor through l

the ruptured loop.

ine flow from the remaining accumulators provides sufficient water to fill the volume outside of the core barrel below the nozzles, the bottom plenum, and one-half the core.

l 6.3.2-6 Amendment No. 12

.~

l-4.0 (Continued)

~

16.

A case evaluation has been performed for each section of this procedure IAW PLP-037 The case determination and any associated additional requirements are defined at the beginning of each section.

l 17.

The Dedicated Operator utilized for filling SI Accumulators shall l

be any active licensed individual other than the Reactor Operator i

l on watch, and shall remain at the RTGB until the filling evolution is complete.

18.

Ir any SI Accumulator level increases greater than 10% (70 gal) l

[

due to inleakage when the RCS pressure is >1000 psig, then the affected accumulator shall be sampled within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(ITS SR 3.5.1.4) 19.

When drawing an oil sample from an SI Pump, remove the Control Power Fuses.

Reinstall the Control Power Fuses when sampling has l

been completed AND the oil resczvoir has been refilled to the normal level. During the interval with fueses removed, the SI Pump is inoperable.

20. ;Do E2I open more than one SI Accumulator Vent valve at a time l

when the SI Accumulators are required to be operable to prevent invalidating the LOCA Analysis. (Westinghouse Memo CPL-96-210)

L 21.

Operation with RWST level greater than the high level setpoint l

should be avoided to prevent water level at the Spring Line of l

the BNP':

i I

l OP-202 Rev. 44 Page 10 of 120

RO JPM.CR-019, Question 2 006 Kl.03 4.2/4.3 REFERENCE ALLOWED 1

QUESTION:

Given the plant conditions:

Mode 1,100% power Accumulator levels / pressure "A"

68 %

600 psig "B"

70%

630 psig "C"

70 %

645 psig Annunciator APP-002-B-4 "SI ACCUM A HI/LO PRESS" illuminated QUESTION A:

Determine which accumulator parameter (s) are outside the normal operating band.

ANSWER A:

"A" Accumulator pressure is low (normal band = 614 to 646 psig)

REFERENCE ALLOWED QUESTION B:

Can this evolution be performed and describe the basis for your response.

ANSWER B:

No, not allowed. Simultaneously opening the accumulator vent valves would connect the

..two accumulator gas spaces. If a large break LOCA were to occur on either of the loops

("A" or "C") both accumulators would depressurize invalidating the LOCA analysis.

(Not required for credit: Accumulator design capacity is based on one accumulator spilling to the containment floor through the break, the other two accumulators fill the core to the mid-plane.)

REFERENCE:

FSAR section 6.3.2.2.6 I

OP 202, step 4.20 APP-002-B4 "SI ACCUM A HI/LO PRESS" 02/13/98 9:58 AM T

RO JPM CR-025, Question 1 005 K4.07 3.2/3.5 QUESTION:

Given the following plant conditions:

RCS cooldown is in progress Plant is in Mode 4 RCS T.yg is 348*F RCS pressure

+, Irr-402 = 468 psig

+ FT-403 = 470 psig

+ PT-404 = 472 psig What must be done to open',MOV-750/751 to place RHR in service?

ANSWER:

Reduce RCS pressure (sensed by PT-403) to less than 465 psig Verify SI-862A/B "RWST TO RHR" and SI-863A/B "RHR LOOP RECIRC" closed with breakers closed and control power switches in " NORMAL"

REFERENCE:

OP-201, " Residual Heat Removal System", : _

System

Description:

Residuel Heat Removal System l

l

[

i 01/08/98 12:51 PM

_ _ _ _ _ _ _ _.. _ ~. _ _ _ _ _...

AUTHORIZED COPY i

n.

l

(

l 4.0 PTIECAUTIONS AND LIMITATIONS i

4.1 Reactor Coolant System temperature and pressure shall be less than 350*F and 375 psig before the Residual Heat Removal System is l t iriservice, and the i0 RHR system will be removed from sentice before RCS pressure and temperature are raised above these values.

4.2 To prevent boiling the CCW liquid contained in an RHR HX, CCW flow should not be isolated to an RHR HX when the temperature of the RHR System is greater than 200*F. (CR 95-00565) 9.3

[Neither RHR-750 nor RHR-751 will open unless ttie following conditions are

$atisfied;

- The breakers fo'r SI-862A and B are closed.

- The breakers for SI-863A and B are closed.

- The control power switches for SI-862A and B are in NORMAL.

The control power switches for SI-863A and B are in NORMAL.

~s

, Valves SI-862A and B are closed.

- Valves SI-863A and B are closed.

- RCS pressure is less than 465 psig.

4.4 SI-862A & B, and SI-863A & B are interlocked so they cannot be opened unless the RHR loop pressure is less than 210 psig.

4.5 When the Residual Heat Removal System is providing Core Cooling AND seal injection flow is desired to maintain a positive AP across the Thermal Barrier of the Reactor Coolant Pumps, letdown flow through HCV-142 and PCV-145 should be maintained to provide makeup to the VCT.

4.6 When RHR-757C or RHR-757D is closed,3,350 gpm flow, indicated on F1-605, with one RHR pump running or 6,700 gpm flow with two RHR pumps running shall not be exceeded, except as allowed / required by approvec' test procedures for which flowrates on FI-605 may be as high as 3800 gpm for one pump or 7600 gpm for two pumps.

l Rev. 34 Page 6 of 67

l RO JPM CR-025, Question 1 005 K4 07 3.2/3.5 s

l REFERENCE ALLOWED QUESTION:

l Given the following plant conditions:

RCS cooldown is in progress i-Plant is in Mode 4 RCS T,,,is 348'F

+

RCS pressure l

+ PT-402 = 461 psig l

+ PT-403 = 470 psig

+ PT-404 = 472 psig l

l What conditions must be satisfied to open MOV-750/751 to place RHR in service?

ANSWER:

i i

[.5] Reduce RCS pressure (sensed by PT-403) to less than 465 psig e

[.5] Verify SI-862A/B "RWST TO RHR" and SI-863 A/B "RHR LOOP RECIRC" e

l closed with breakers closed and control power switches in " NORMAL"

REFERENCE:

OP-201, " Residual Heat Removal System", step 4.3 System

Description:

SD-003, Residual Heat Removal System l

)

l AS

& lum 02/13S8 9:58 AM

___ -_ _. _ -.=. -

RCS Specific Activity 3.4.16 ACTIONS (continued) s CONDITION REQUIRED ACTION COMPLETION TIME l

C.

Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion T., < 500 F.

Time of Conoition A not met.

E DOSE EQUIVALENT I-131 in the unaccepteble region of i

Figure 3.4.16 1.

1 i

'.'.URVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific 7 days activity 5 100/E pCi/gm.

h SR 3.4 16.2

- NOTE ---

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT-14 days I 131 specific activity s 1.0 Ci/gm.

{

AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of a 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period t

(continued) l 3.4-46

RCS Specific Activity B 3.4.16 BASES (continued)

SURVEILLANCE SR 3.4.16.1 RE0UIREMENTS SR 3.4.16.1 requires performing a gamma isotoaic analysis as a measure of the gross specific activity of t1e reactor coolant at least once every 7 days. The analysis shall consist of a qualitative measurement of the total radioactivity of the primary coolant in units of yCi/gm.

While basically a quantitative measure of radionuclides with half lives longer than 15 minutes, excluding iodines, this measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken. This Surveillance provides an indication of any increase in gross specific activity.

Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LC0 limit under normal operating conditions. The Surveillance is applicable in MODES 1 and 2. and in MODE 3 with T at least 500 F.

The7dayFrequencyconsiderstheunlikelY$oodofa gross fuel failure during the time.

SR 3.4.16.2 This Surveillance is performed in MODE 1 only to ensure iodine remains within limit during normal operation and following fast power changes when fuel failure is more apt to occur. The 14 day Frequency is adequate to trend changes in the iodine activity level, considering gross activity is monitored every 7 days. The Frequency, between 2 and

[4 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power change a 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peak during this time following fuel failure: samples at other times would provide inaccurate results.

SR 3.4.16.3 A radiochemical analysis for ! determination is required every 184 days (6 months) with the plant operating in MODE 1 equilibrium conditions. The E determination directly relates to the LCO and is required to verify plant operation within the specified gross activity LCO limit. The analysis for E is a measurement of the average energies per disintegration for isotopes with half lives longer than (continued)

B 3.4-102

o O

SRO(I) Admin. A.1,(Plant Chemistry), Question 1 l

2.1.14.2.5/3.3 REFERENCE ALLOWED i

QUESTION:

Given the following plant conditions:

The plant is at 100% power, equilibrium Xenon, all systems aligned for normal operation (Jan 15,1998,12:01 AM)

Chemistry personnel uport they have completed obtaining RCS and Pressurizer liquid samples (9:00 AM)

A runback due to a dropped rod occurred at 9:15 AM Recovery actions are in progress e

QUESTION A:

What are the chemistry sampling requirements for this plant condition?

ANSWER A:

[.5] Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a reactor power change of t 15% in I hour (in Mode 1), RCS Dose Equivalent I-131 shall be verified i 1.0 micro-curies / gram.

(Between 11:15.AM and 3:15 PM)

NO REFERENCE ALLOWED QUESTION B:

What is the basis for the time frame after the power change?

l ANSWER:

[.5) Ensure Iodine remains within limit following fast power changes when fuel failure is more apt to occur. 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a power change of 215% in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period is established because this is when the Iodine level in the I'CS would peak due to fuel failure.

REFERENCE:

OMM-001-13," Plant Chemistry", section 5.2 ITS, SR 3.4.16.2 A5 6tae.J 02/13/98 9:58 AM l

l

SRO(I) Admin. A.1,(Plant Chemistry), Question 1 2.1.14 - 2.5/3.3

]

l QUESTION:

Given the following plant conditions:

The plant is at 100% power, equilibrium Xenon, all systems aligned for normal 1

operation (Jan 15,1998,12:01 AM)

Chemistry personnel report they have completed obtaining RCS and Pressurizer liquid samples (9:00 AM)

A runback due to a dropped rod occurred at 9:15 AM The plant is now stable at -68%

Recovery actions are in progress I'

What are the chemistry sampling requirements and basis for this plant condition?

ANSWER:

Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a reactor power change of 215% in I hour (in Mode 1),

i RCS Dose Equivalent I-131 shall be verified s.1.0 micro-curies / gram. (Between 11:15 AM and 3:15 PM)

Ensure Iodine remains within limit following fast power changes when fuel failure is more apt to occur. 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a power change of 215% in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period is established because this is when the Iodine level in the RCS would peak due to fuel J

failure.

REFERENCE:

Plant Chemistry", section 5.2 5R 3.4.16.2 I

l l

l l

01/0*/98 10:38 AM I.

POOR QUESTIONS KA: 062AA1.01 Importance: 3.4/3.8 Reference allowed (FSAR)

Question: What is the limiting factor on the amount of current that can be passed from Unit 1 to Unit 2 through the SBO crosstie?

Expected Response: The electrical cable between the two units is the limiting factor.

i i

\\

i I

4

-a

KA: 033000K303 Importance: 3.0/3.3 Reference allowed Question: What is the response of the Spent Fuel l

Pool Cooling System KF:, and why, regarding l

temperature and level following a Blackout?

' NOTE: Assume NO operator action is taken:

l Expected Response: Spent Fuel Pool level and temperature will increase due to decay heat of the l

spent fuel assemblies.

l l

.. -. -. ~

. - ~..

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

4 1

Conduct of Operation (SRO 1)

Fire Brigade 2

KA:

194001K116 3.5/4.2 Lesson Plan:

EAP-SEP

Reference:

Fire Plan, (E-Plan) RP/1000/29 Fire Brigade Response, NSD 112, Fire Brigade Organization, Training, and Responsibilities Task:

2610000, 3710001 Source:

NEW PRA 3-18-97 4.

As the Operations Shift Supervisor serving as the Fire Brigade Leader during an actual fire or fire drill, you have several responsibilities.

Describe the normal duties as the Fire Brigade Leader at the fire scene?

ANSWER:

1-Serve as the Fire Brigade Commander and direct the Fire Brigade during the event.

2-obtain support as needed such as Security, Radiation Protection, Chemistry, Offsite Fire Department and Hazmat.

\\

(3-Ensure all fire protection equipment is restore to full

+

capability immediately following tne event).

(4 -

Complete the Fire Emergency Report and forward the report to the EP (Emergency Planning) Section).

l l*

i I '

m.

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KA:

062000A401 (3.3/3.1)

Lesson Plan:

EL EPD Objective R8 page 25

Reference:

OMP Task:

002630001 Source:

Bank EL 96 (JPM CRO 08) RO l

QUESTION:

Describe the safety and personnel requirements for manual operation of switchyard disconnects.

ANSWER:

Rubber safety gloves and safety glasses must be worn.

At least two people in the crew performing the task, one of which is a supervisor.

Nomex suits should be worn by the breaker operator.

4 l

e i

i l

i

Conduct of Operations (SRO 1)

Self Checking / STAR KA:

194001K101 (3.6/3.7)

Lesson Plan:

ADM-OMP

Reference:

OMP 1-22, Job Assignments Task:

3610052 Source:

PRA 3-6-97 NEW 1.

As an SRO (Shif t Supervisor) you have the responsibility of performing Pre-Job Briefs with other operators on your shift, you make the decision of the level of detail and information within the Pre-job Brief.

What are several guidelines that you will use to determine the amount of detail of the Pre-Job Brief presentation and describe the " STAR" component of the Pre-Job Brief?

ANSWER:

(2 of 5) 1)

Complexity of the task Consequences of the task Importance of the task Frequency of the task Unfamiliarly of the task to the performer 2)

" STAR" is a self checking method (that operators use to reduce the potential of errors).

("S"

- Stop)

("T"

- Think)

("A"

- Act)

("R" - Review)

ACCEPTABLE QUESTIONS importance: 2.6/3.0

Reference:

Steam Tables i

Question: The RCS is at 2250 psia, Quench tank pressure is 3.5psig.

If a small leak developed in the seat of Code Safety V 1201, what temperature would you expect to see on TIA-1107?

Expected Response: 230 degrees 4

i I

r

Question #1.

l KA: 001K5.02 Importance: 2.9/3.4

Reference:

Unit 2 Plant Physics Curves Question: Unit 2 has 6,000 EFPH on the core and experiences a dropped rod resulting in the NI power level changes from 100% to 93%, what is the approximate worth of the dropped rod?

Expected Response: Approximately 75 to 100 pcm.

Question # 2.

KA: 001K5.20 l

Importance: 3.5/3.8 l

Reference:

Unit 2 Plant Physics Curves l

Question:

In order to withdraw the same CEA without changing the power level or temperature of the RCS, how much would RCS boron concentration have to be changed?(PPM)

• • lf Question 1 is missed: Assuming the worth of a l

dropped CEA was 100 pcm, how much would boron concentration have to be changed to withdraw the l

rod without changing power level or temperature?

Expected Response: approximately 12 PPM (Boron worth for the present conditions is 8.38pcm/ ppm) j

l l

l l

i l

"HLC EXAM DEVELOPMENT EXAM BANK" TEST ITEM DATA SHEET

===========================================================

l I.

CROSS-REFERENCE DATA i

RECORD NUMBER: 1427 TYPE: General Use i

LESSON 1: LOR-SIM-JP-019-A05 LESSON 1 OBJECTIVES: 01 STYLE: Short Essay /Other POINT VALUE: 1.00 REVISION: 3 TIME TO COMPLETE: 4 Minutes ENTERED BY:

DATE ENTERED:

10/10/94 MODIFIED BY:

DATE MODIFIED:

04/27/98 DATE LAST USEU:

(approved by:

~~

ASSOCIATED TASKS:

No Tasks are currently referenced to this question.

ASSOCIATED K/A's:

206000 A1.01 ROI: 4.3 SROI: 4.4 Ability to predict and/or monitor changes in parameters associated with operating HIGH PRESSURE COOLANT INJECTION SYSTEM REACTOR WATER LEVEL:

BWR-2,3,4 controls

REFERENCES:

2 APP A-01 3-1 /R21

===========================================================

II. QUESTION:

HPCI started on high drywell pressure, but tripped on high RPV level.

Explain how HPCI responds as level lowers from the high level trip to Lo Level 3.

Additionally, if you wanted to restart HPCI at 120", what actions would be required to perform that action?

===========================================================

III. ANSWER:

As level lowers, HPCI will not restart until level reaches LL-2 (105").

HPCI will then reset its trips and start.and inject with no operator action.

HPCI will continue to run as level lowers to LL-3.

To restart HPCI prior to reaching LL-2, depress the high water level trip reset pushbutton, the drywell signal will then restart HPCI and '

cause it to inject.

?

l i

t i

PAGE 1 OF 1 r

t a

L l

"NRC JPM 98, Rev 0" EXAMINATION I

l QUESTION 3 POINT VALUE: 1.00 Using the attached diagram, explain how it is possible to reset a scram l

with the mode switch in SHUTDOWN.

l-l t

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J PAGE 3 l

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5 L

LCSC-C2 Re, l'

Page EC :! IC' r.

I l

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JOB PERFORMANCE MEASURE l

Provide this page to the Candidate Health Physics has performed a survey of the Unit 2 Charging Pump rooms and 4

hallway. Given a survey map, determine how each room and hallway should be posted.

l 1

9 l

Page 6 of 7

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l

M SC-EL::\\G CO\\S:: JERK ::0\\S Amount of material to be generated:

Licensee Cost.

Licensee Manpower.

Examiner Review Time.

Validation Time on Simulator During Prep-Week.

I The current trend is a shift towards a e

single JPM set, administered piece by piece, with all applicants receiving the same piece each day.

Considerations with this technique:

Availability of both Simulator and Booth Operators for two shifts.

Sequestering.

Candidate Stress.

Examiner Stress.

(No laughing please!)

CurreTT:

3 PO.J ems 1

JPMs are lasting 30 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Longer is not better.

1 1

Take the time it takes a staff instructor to perform the task, with f

questions, and double it.

The last three examinations have run i

past 10:00 pm and were scheduled to end at 6:00 pm.

j Applicants are arriving at 7:00 am and are

=

I not being exam.ined until 7:00 pm.

No margin for error or simulator failure.

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i ES-301 Specific Instructions for Category A I

Although Admin topics may be examined e

separately, it is preferable, whenever

possible, to link, associate, or integrate them with tasks and events conducted during Categories B and C i

Using a single Admin JPM is generally e

preferred, however, two prescripted questions may be used.

If the applicant has a "U" in only one e

Admin topic, the examiner may fail the applicant in Category A depending on the importance of the identified deficiency

- Topics in the administrative portion of the NRC initial examination are weighted the highest of all examination areas, and are thus the most likely to result in a failing grade.

- A single knowledge weakness / or applicant error can result in an initial examination failure.

t Common Single Failure Points:

Clearance Error.

Reactivity Balance Error.

The key is a balance between questions and JPM's.

All JPMs will result in a long Admin exam, with a high potential to fail a candidate for a single error.

All questions usually results in a weak Admin exam.

l l

4

1 Exami es o= Gooc Acmin JPXs Shutdown Margin Calculation.

e Approval of a Clearance Crder.

ECP Calculation.

Manual Leak Rate Calculation.

Risk Matrix Utilization.

Off-Site Dose Projection.

Review a Survey Map and Demonstrate e

Knowledge of Radiological Hazards in a Work 3

~

Zone.

Evaluate the Applicants Scenarins for Emergency Plan Application and Make

{

Protective Action Recommendations.

- The key to success with' these types of tasks is solid an! thorougn validation.

l

- If the task is not clear, and well

defined, the applicants will Decome t

confused.

- If the task is too long.

it will begin to loose its evaluating ability.

(

l Examples of Poor Admin JPMs i

Check out a key from the key 1ocker.

e l

Make a log entry.

e e

Frisk out an item.

Do you want an applicant to fail for touching the surface?

Make a call-in for emergent work while e-reading from a procedure.

Perform a pre-job brief.

These are items of L.ow Discriminatory Validity, and if performed poorly can result in severe grading.

9

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y w--

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s--,.,

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Otler Jifficu~ ties dit, Admin SRO applicants should be evaluated at e

greater depth on Admin topics.

There must be a difference between the R0 and SRO Admin examinations.

Control Room Software not available on the simulator or applicants don't have the proper password.

The question does not solicit the answer.

Put validators in the mind set of appli cant.

Assigning point values to multiple answer questions.

The limit is 80%.

If there are four

~

answers, the applicant must get a7 7 four correct.

Don't require applicants to catch integrity

issues, or misspelled words when approving clearances or valve line-ups.

Direct look-ups are prohibited!

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EXAMLNATI_QN SECURITY s

PER 10 CFR 55.49 -

" APPLICANTS, LICENSEES, AND FACILITY LICENSEES SHALL NOT ENGAGE-IN ANY ACTIVITY THAT COMPROMISE.S THE INTEGRITY OF ANY APPLICATION, TEST, OR EXAMINATION BY~THIS PART" RULE IMPLEMENTED IN NUREG-1021 ES-201 - C.1 & C.2 & C.3 (RESPONSIBILITIES)

ES-201 - D.2 (PERSONNEL RESTRICTIONS) s ES-201 - ATTACHMENT 1 (PHYSICAL SECURITY & EXAM BANK LIMITATIONS) e ES-201 - FORM ES-201-3 (SECURITY AGREEMENT) e e

ES-205 - GFES EXAM ADMINISTRATION 5

ES-402 - C.1 (RESPONSIBILITIES) e ES-402 - E.3 (POST-EXAM REVIEWS) e e

ES-501 - POST-EXAM DOCUMENTATION APPENDIX D, SECTION F (SIMULATOR SECURITY CONSIDERATIONS) e

EXAMPLES

!i INSTRUCTOR SIGNED SECURITY AGREEMENT AND DISCUSSED EXAM CONTENT WITH EXAMINEES REVEALING OF WHAT IS NOT ON THE EXAM (APPLICANTS SHOULD NOT BE ABLE TO PREDICT OR NARROW THE POSSIBLE SCOPE OR CONTENT OF EXAM BASED ON YOUR I

TEST DEVELOPMENT PRACTICES)

BIAS OF SCOPE, CONTENT, OR LEVEL OF DIFFICULTY OF AN EXAM TO ENHANCE CHANCES OF CANDIDATES PASSING TEST LOSS OF CONTROL OF EXAM MATERIAL (NOT LOCKED UP WHEN LEAVE OFFICE, PARTS OF EXAM LEFT IN COPIER, PART1 0F EXAM LEFT IN. SIMULATOR BOOTH AFTER VALIDATION) t INSTRUCTOR ON SECURITY AGREEMENT INTERACTS WITH SR0(U) CANDIDATE DURING REQUAL (TAUGHT CLASS, EVALUATED SIM. SCENARIOS, SAT-0N AUDIT BOARD)

WRITE EXAM TO SAME FORMAT EVERY TIME S0 IT BECOMES PREDICTABLE CHANGING K/A NUMBERS ON OLD QUESTIONS IN ORDER TO FIT NEW SAMPLE PLAN i

PERSONNEL NOT ON SECURITY AGREEMENT IGNORE WARNING SIGNS AND WALK IN ON EXAM DEVELOPMENT ACTIVITIES DRAFT EXAM MATERIAL NOT PROPERLY PACKAGED WHEN SENT TO NRC AND WAS DELIVERED OPEN i

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CONSEQUENCES 4

l NUREG-1600, " GENERAL STATEMENT OF POLICY AND PROCEDURES FOR-NRC t

ENFORCEMENT ACTIONS" APPLIES IF HAVE INDICATION OF COMPROMISE, ACTION WILL BE-TAKEN TO ENSURE AND RESTORE THE INTEGRITY AND SECURITY OF PROCESS.-

INCLUDES:

4

=

NOT GIVING EXAM

~nm

, o. i MAKING ADDITIONAL CHANGES TO EXAM e

f VOIDING EXAM RESULTS IF EXAH ALREADY GIVEN.

e REEVALUATING LICENSING DECISIONS PER 55.61(b)

. '~

L,.

a POSSIBLY IMPOSING ENFORCEMENT ACTIONS INCLUDING-e CIVIL PENALTIES ORDERS

[

IMPLEMENTATION OF DELIBERATE MISCONDUCT RULE (10 CFR 50.5) i

(

p I

EXAM PRFDICTABILITY i

APPLICANTS SHOULD NOT BE ABLE TO PREDICT OR NARROW.THE POSSIBLE t

OR CONTENT OF EXAM BASED ON YOUR TEST DEVELOPMENT PRACTICES

~

EXAM DEVELOPMENT TECHNIQUES OR RULES SHOULD NOT BE DISCUSSED WITH CANDIDATES (e.g., 25% OF WRITTEN WILL BE OFF THE MOST RECENT EXAM) 1 EXAM METHODOLGY SHOULD BE VARIED FROM EXAM TO EXAM(e.g., SECTION A.4 SHOULD NOT ALWAYS BE " CLASSIFY THE SCENARIO" FOR SR0's)

EXAM DEVELOPMENT CRITERIA LIMITATIONS SHOUI.D NOT ALWAYS BE THE BASIS THE EXAM CONTENT (e.g., NO OVERLAP WITH THE AUDIT TEST SHOULD NOT BE A RULE STRICTLY FOLLOWED WITH NO EXCEPTION) IF DONE CANDIDATES CAN EXCLUDE EVERY THING FROM THEIR AUDIT AS NOT BEING ON THEIR TEST WHIC NARROWS THE SCOPE.

ALLOW AUDIT AND LICENSE EXAMS TO DEVELOP INDEPENDENTLY AND IDENTIFY T!

THE CHIEF EXAMINER THOSE AREAS THAT OVERLAP WITH A PROPOSED RESOLUTION, i

IF NEEDED.

AREAS TO WATCH:

NO OVERLAP FROM AUDIT EXAM 25% FROM THE LAST TWO NRC EXAMS 50% FUNDAMENTAL KNOWLEDGE t.

l NO TEST ITEM REPEATS FRot! DAY TO DAY WRITTEN EXAM ANSWERS FAVOR a,b,c, OR d ALL JPMs DONE ONLY ON A SPECIFIC UNIT

I

\\

SIMULATOR SCENARIO DEVELOPMENT C.

JAY \\E G.

-033ER

}

1 l

l t

j

C R __.. C A _.

AS(S i

-~

-~

Ba~

cons :1~:u:es a cri :ica~

~~ a S (?

~~

~

1e recua 1 "ica: ion examina: ion uses cri :ica~ tas <s (C-~s)

=or~ eva ua :ing Crew 'Jer"ormance on

as to reduce power to 92% pump to be taken out of service. Shift and remove the 2A Heater Drain Pump from service.

Additional failures: 2A Containment Spray Pump fails to start on CSAS I

P

/.

Event Malf.

Event Event No.

No.

Tvoe' Description 1

N-BOP Power reduction from 100% to 92%

R-RO L-2 1-RO PIC-1100X (PZR pressure transmitter) dnfie-Web-3 C-BOP, 2AB Load Center deeneroizes

_ _, l.~., s,,L,~ A 4

C-RO 2B CCW Pump trios l

5 1-BOP FIC-9011,2A Steam Generator flow transmitter fails low.

6 M-2A Steam Generator tube rupture (250 GPM),2A BOP main steam line break inside containment on reactor M-RO trio.

mb iS WW

.i

(.

3n. ww em no r

i

'l i

i l

.,f.

- (N)omial, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor

'L_

hi

i #~

Facility' Scenario No.: 1a Op-Test No.: 1 Objectives: To evaluate the students ability to implement ONOPs for loss of a vital 480V load center, an off-normal Pressurizer pressure and Letdown condition, and failure of a Steam Generator steam flow transmitter; to perform a normal power reduction; and to execute EOPs for a Steam Generator Tube Rupture combined with a Main Feec, water line break inside containment (EOP-15)

Initial Conditions: Unit 2 is at 100% power, MOL.

Tumover: Unit 2 is at 100% power MOL. The 2A Charging pump is out of service for a lube oil PM, expected back m three hours. The 2B Main Feedwater Pump has a unisolable discharge flange leak requiring the pump to tre taken out of sen, ice. 2A Main Steam Line Radiation Monitor is out of service, not expected back this shift. 2-HVS-1 A containment cooler is out of service. Chemistry reports a 16 GPD tube leak on the 2B S/G. Management has decided to continue Shift instructions are to reduce power to 45% power operations due to the system load.

and remove the 2B Main Feedwater Pump from service. Thunderstorms have been reported to be approaching the St. Lucie County area Additional failures: A train CSAS fails to actuate and FCV071 A fails to fully open 2B Containment Spray pump develops a sheared shaft on start.

2A Main Feedwater pump fails to tnp on low suction pressure 2A Main Feedwater isolation valves fail to close on MSIS Event Event Event No.

Type

• Description

~

I 1

N-BOP Power reduction from 100% to 45%

R-RO 2

(-RO PIC-1100X (PZR pressure setpoint) drifts high 3

C-RO 2AB Load Center deenergizes,2B Cherging pump trip 6co 4

N-BOP Realignment of charging and letdown 5

C-BOP 2B CCW Pump trips

---6

' eon r" E"1", 2A S!G ctcar #c'e' PcMer 1:4 high 7

M-BOP 2A Steam Generator tube rupture (250 GPM),2A main

~

M-RO feed line break inside containment on reactor trip C

A train CSAS fails to actuate C

2A Main Feed isolation valves fail to close on MSIS (MFIV failure, continues to feed containment)

C FCV 071 A fails to fully open (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

3 ES-301 Simulator Scenario Quality Assurance Checklist Form ES-301-4 e

Feoility:

Date of Exem:

Soonerio Numbers:

/

/

Opersing Test No.:

2 GUAUTATIVE ATTVuBUTES irdtials a

b c

1.

The scenesios how cieerty stated obioenwes in the sceneno summaries.

2.

The irdtiel conditions are roeisstic,in that some equipment end/or instrumentatici rney be out of service, but it does not cue the operators into expected events.

3.

The sooneries consist mosdy of coleted events.

4 Each event 1 - w.coneests of the peiert in the scenario when it is to be initiated 4

the malfuncion(s) that are ovuoted to irutiste the event the symptoms / cues that will be visible to the crew the espected operator actions (by shift possoon)

=

the event acc - f. point (if soplicable) 5.

No more then one normnacherestic feiiure (e.g., pipe breek) is incorporated into the soonerio without a credibie preceding incident such as a seismic event.

6.

The events are welid with regard to phvoice end thermodynamics.

7.

Sequencing and dming of events is reasonabie, and allows the examination team to ootein complete evaluation resutts commensurete with the scenario o@ctives.

8.

(f time compreemon techruques are used, the sceneck summary cieerty so indicates.

Operators hows suffiosent ime to carry out expected activities without undue time constraints. Cues are given.

i y

r 9.

The ermulator modeling is not eftered.

j 10.

The scenarios hows been welidated.

j 11.

Every operecer will bs evaluated using at i.est one new scenerio. All other scenenes have been modif.ed in accordance with Socion D.4 of ES 301.

4 12.

Allindividual operecer competencies een be eweiunted as wori6ed using Form ES 301-0 (submit the form along with the simulator scorneries).

13.

Each appiicent will be sigraficarrdy irwaived in the rni.eimum number of transients and events specifed on Form ES-3015 (submi the form along with the sanulator scenarios).

'.14.

The iewel of dif6 cutty is sopreenste to erpoort licen=ng decsmens for each crew peerson.

TARGET Os4ANTITATIVE ATTRIBUT ES (PER SCENARIO)

Actual Attributes 1.

Tesel malfunctions (5-8;

/

/

2.

MeNunctions after EDP entry (1-f.)

/

/

3.

Abnormal ewnta (2-4)

/

/

4.

Maior trenesents 112)

/

/

5.

EDPs entered /reouiring s.ubstantive actions (12)

/

/

6.

EOP contmgencies re. wiring substantive actions (0-2)

/

/

7.

Cntical tesits (2-3?

/

/

f NUREG-1021 24 of 26 Inted m Rev. 8, January 1997

~

i ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.:

Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Nomal 1

Instrument 2

- RO Component 2

Major 1

Reactivity 1

Nomal 0

Instrument 1

As RO Component 1

Maior 1

SRO-I Reactivity G

Nomal 1

Instrument 1

As SR0 Component 1

Major 1

Reactivity 0

Nomal 1

SRO-U Instrument 1

Component 1

Major 1

Instructions:

(1)

Enter the operating test number and Form ES-D-1 l

event numbers for each evolution type.

(2)

Reactivity manipulations must be significant as defined in Appendix D.

Author:

i Chief Examiner:

4 NUREG-1021 25 of 26 Interim Rev. 8, January 1997 i

5 t-ES-301.

Competencies Checklist Form ES,,-301-6 I

Applicant #1 Applicant #2

. Applicant #3 R0/SRD-J /SRO-U R0/SRD-I/SRO-U R0/SRO-I/SRG-U Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 Understand and Interpret Annunciators and Alarus Diagnose Events and Conditions Understand Plant and System Response Comply With and Use Procedures (1)

Operate Control Boards (2)

Communicate and Interact With the Crew Demonstrate Supervisory Ability (3)

Comply With and Use Tech. Specs. (3) i Notes:

(1)

Includes Technical Specification compliance for an R0.

(2) Optional for an SRO-U.

(3) Only applicable to SR0s.

Instructions:

Circle the applicant's license type and enter the event numbers that test the competency for each scenario in the set.

Author:

Chief Examiner:

NUREG-1021 26 of 26 Interim Rev. 8, January 1997