ML20148G802

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Exam Rept 50-261/OL-87-03 on 871214-17.Exam Results:All Operators Passed Written Exams.All Four Senior Reactor Operators & Three of Four Reactor Operators Passed Operating Test.Both Crews Rated Satisfactory During Simulator Exam
ML20148G802
Person / Time
Site: Robinson 
Issue date: 01/12/1988
From: Casto C, Munro J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148G765 List:
References
50-261-OL-87-03, 50-261-OL-87-3, NUDOCS 8801270037
Download: ML20148G802 (164)
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Text

ENCLOSURE 1 EXAMINATION REPORT 261/0L-87-03 Facility Licensee: Carolina Power and Light Comp n P. O. Box-1551 Raleigh, NC 27602 Facility Name:

H. B. Rcbinson Steam Electric Plant Facility Docket No.: 50-261 Examinations administered at H. B. Robinson Steam Electric Plant near Hartsville, South Caro 'na.

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Chief Examiner:

Ch~arlbs~ A.' Cas to 06te Approved by:

I / s2 /s6 fin F. Nunro, Section Chief f Date Summary:

Examinations on December 14-17, 1987.

Written examinations and operating test were administered to four SR0s and four R0s. All operators passed the written examinations.

For the operating test four of four SR0s passed and three of four R0s passed.

The facility did not identify any of the operators as failures on the operating exam.

Both crews were rated satisfactory on their performance during the simulator examination.

8801270037 $0 M

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REPORT DETAILS

1. ' Facility Employees Contacted
  • D. McCaskill, Shift Foreman
  • F. Lowery, Manager Operations
  • T.~ Byron, Senior Specialist-0perations Training
  • J. Allen, Senior Specialist-0perations Training
  • 0. Crook, Specialist-Regulatory Complience
  • R. Allen, Project Specialist-0perations Training
  • C. Bethea, Manager-Training
  • G. Beatty, Vice President, Robinson
  • R. Morgan, General Manager, Robinson B. Blaisdell, Senior Specialist-0perations Training A. Sanders, Senior Specialist-Simulator Support V. Smith, Senior Specialist-0perations Training R. Moore, Shift Foreman G. Stein, Technical Aide
  • Attended Exit Meeting 2..

Examiners L. Wiens, OLB R. Eaton, OLB J. Munro, RII

  • C, Casto, RII W. Dean, RII C. Rapp, RII M. Ernstes, RII R. Temps, RI D. Shepard, RIII R. Latta, Resident Inspector
  • Chief Examiner 3.

Examination Exit Meeting At the conclusion of the site visi,.he examiners, the Branch Chief of Region II Operations, Caudie Julian, and the Branch Chief of Operator Licensing, John Hannon, met with the representatives of the plant staff to discuss the results of the examination.

The NRC provided an overview of the expected status of the requalification program for future examination development, e.g., a bank of simulator scenarios, performanced based walk-through examinations, and a bar k of open book written examination questions derived from valid learning objectives. The NRC expressed the need tc have the INFO process vigorously implemented to enable the Pilot Requalific6 tion method to be successfull in evaluating programs.

2 cThere-were some generic weaknesses noted during the. operating examinations, particularly with communications and the use-of PEP 101. These areas-should be. considered for review and/or possible remediation as appropriate.

Also, the examiners discussed with ti.e facility-representatives the need to dafine "normal" as related to the use of Path 1 of the Emergency Procedures.

The NRC expressed its appreciation to the H. B. Robinson personnel involved in the Javelopment of this Pilot Requalification Examination.

The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.

The' licensee did not idantify as proprietary any of the material provided to or reviewed by the examiners.

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NUCLEAR REGULATORY COMMISSION SENIOR / REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

H.

B. Robinson REACTOR TYPE:

PWR-WEC3 DATE ADMININSTERED: 12/17/87 OPERATOR:

NOTE TO OPERATOR A grade of 80% overall for Sections A and B combined is the standard for successful completion of the written examination.

X OF SECTION CATEGORY OPERATOR'S CATAGORY VALUE SdORE VALUE A

Plant Proficiency

_ /_ _' f]5 All work done on thi s examination i s my own.

I have nei ther given nor received aid.

Operator's Signature

ffC RtLES (WD GJIDREE FCR EXRlltEES

i. Rest room trips are to be limited and cnly one examinee at a time may leave. You nust avoid all contact with anyone outside the examinaticn room to avoid even the appearance or possibility of creating.

2.

Use black ink or dark pencil CM_Y to facilitate legible reproductions.

3.

Print ycur nane in the olenk provided cn the cover sheet of the examinaticn.

4.

Fill in the date on the cover sheet of tPe examinaticn, if necessary.

5.

foswer each questicn on the examinaticn.

If additional paper is required, use cnly the lined paper provided by the examiner.

6.

Use abbt eviaticns cnly if they are commonly used in facility literature.

7.

The point value for each questico is indicated in pareotteses af ter the question and con be used es a guide for the depth of. answer required.

8.

Shcw all calculaticos, nethods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the questico or not.

9.

Lhless solicited, the location of references need not te stated.

10.

Partial credit may be given.

Therefore, RGER (U_ P/FTS OF TK CLESTICN 40 DO POT LEfAE 4# 4GEhs E1.4K.

ii.

If parts of the examinaticn are not clear with respect to their intent.

ask questions of the examiner only.

12, Ycu nust sign the statetent on ttva cover shset that indicates the wrk cn tFe examination is your cun and that ycu have not received cn been given any assistance in ccepleting the examinaticn.

This aust te signed 4 TER the examinatico has teen conpleted.

13.

Cheating cn the examinatico muld result in a revocaticn of your license l

and could result in nore severe penalties.

t 14.

TFe examinaticn is designed to take approximately Wi minutes to cceplete.

l Homver, this guideline will POT te strictly adtered to. and each I

examinee will te provided a "reasonable" arctnt of tine in which to ccmplete the examinaticn.

L 15.

Due to the existence < ' questicns that will require all examince to refer to tPe sane indiceticos or controls particular care nust te taken to maintain individual exam security and avoid eny possibility of j

ccmpromise or eprearance of cheating.

1 16.

When ycu are finished and have turned in ycur ccepleted examinaticn.

l leave the examination area.

If you are still fo.od in this area while tre examinatico is still in prcgress, ycur license ney te revc4'ed.

=

SCENARIO #2 EE UNIT WAS INITIALLY AT:

1034 PWER liQUILIBRI W XENCH STEADY STATE ALL COMROLS IN AUIO/ NORMAL BORON = 950 PEM A STEAM LINE BREAK ON "C" MAIN STEAM LINE OCCURRED. PLMT RESPONSE WAS AS EXPECTED. 'IHE BOP FLOWPAE-1 WAS EEERED AND PROGRESSED NORMALLY LWTIL A TRANSITION TO EPP-11 WAS CONDUCTED. EPP-11 HAS JUST BEEN OWPIETED AND THE OPERA'IORS HAVE BEEN DIRECTED TO FLWPNIH-1, ENTRY POIE C.

THE FIRST OUT ANNUNCIATOR WAT WAS RECEIVED WAS "TURBINE TRIP / TRIP".

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'IEE FOLLOWINGXQUESTIONS PERTAIN TO WIS TRANSIENT AND 'IEE ASSOCIATED PLANT RESPONSE.

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SECTION A PLANT PROFICIENCY QUESTION 1 (1.00)

Control board conditions show that the pressurizer heaters are not ener-gizcd even though their control switches are in the "ON/ AUTO" position.

A..What plant condition caused the loss of the pressurizer heaters?

B.

What o'perator actions at the control board would be necessary to rostore power to the pressurizer heaters?

SECTION As. PLANT PROFICIENCY QUESTION 2 (1.50)

BceGd on the INITIAL baron concentration of 950 ppm

A.

Dhtkrmine t'he boron concentration required to cooldown to less than 230 F while maintaining a 4*/. shutdown margin.

(1.00)

B.

D9termine the proper CVCS boron control potentiometer setting for the boron concentration determined in part "A".

(primary water set at 100 GPM)

(0.50) i l

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SECTION A: PLANT PROFICIENCY QUESTION 3 (1.00)

Explain why all the RCP's were required to be stopped by the operator.

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SECTION As PLANT PROFICIENCY

QUESTION 4 (1.00)

Which one of the f ollowing describes the location of the steam break?

A.

Inside containment, upstream of the steam line flow transmitters.

B. Insid, containment, downstream of the' steam line flow transmi tters.

C.

Outside containment between "C" MSIV and "C"

main steam line check velve.

D.

Outside containment between "C" MSIV and "C" main steam line containment psnetration.

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.l SECTION As PLANT PROFICIENCY

-QUESTION 5 (1.00)

Which one of the following is the most probable cause of the turbine trip that.

initiated the reactor trip in this event?

A.

Turbine thrust bearing trip DUE TO the rapid load shedding.

'i B.

Gsneritor motoring trip DUE TO loss of steam.

C.

Loss of both main f eed pumps DUE TO low suction pressure.

D.

HI/ I S/G 1evel on "C"

S/G due to swell in the steam generator H

after the steam line break.

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SECTION At PLANT PROFICIENCY QUESTION 6 (2.50)

Datcrmine if p1 ant conditions satisfy the requirements of foldout "B"

SI TERMINATION CRITERIA. Justify your answer with specific values of any roquired plant parameters.

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SECTION As PLANT PROFICIENCY QUESTION 7 (1.00)

BScsd on PRESENT plant conditions, determine what four (4) emergency buo components would automatically start / restart if BKR 52-18B (E-1 normal

- cupply breaker) was inadvertently tripped?

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SECTION As PLANT PROFICIENCY OUESTION 8 (1.00)

D;tcrmine if SI has been reset. Explain your answer.

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SECTION A PLANT PROFICIENCY QUESTION 9 (1.00)

Prior to isolating "C"

steam generator (per EPP-11) it was noted that the trensducer fed auxiliary feed flow indicators for "C"

steam generator w;re reading greater than the flow indicators to "A" and "B"

steam gancrators. Explain the reason for this flow deviation.

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SECTION At PLANT PROFICIENCY

' QUESTION 10 (1.00)

I

. During the course of the steam break accident on "C"

steam generator,

.did the RHR and/or SI pumps inject any water into the RCS?- Justify your cnswsr.

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SECTION At PLANT PROFICIENCY QUESTION 11 (1.00)

All three RCP "STANDPIPE HIGH" level alarms are illuminated. What is the a

most likely cause.of this?

A.

Elevated CV temperatures caused standpipe fluid expansion.

  • /

B.

Phase'"B" isol ation of RCP seal water return valve, CVC-301.

C.

Annunciator power supply failure.

D.

Reduced RCS pressure.

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'SECTION As-PLANT PROFICIENCY

' QUESTION 12 (1.90)

Liot FOUR (4) automatic. actions.that will occur for each HVH unit (1-4)

- en a result of the steam break accident.

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SECTION As PLANT PROFICIENCY QUESTION 13 (1.00)

Indicate whether each of the parameters below would INCREASE, DECREASE or REMAIN THE SAME if "C"

S/G were also to have a tube rupture. ( 'approximately 400 GPM )

A.

CV pr9ssure B.

CV hydrogen concentration

SECTION As PLANT PROFICIENCY QUESTION 14 (1.00)

If the feedwater regulating valve controllers ( FR-478,488,498 ) were g

placcd in.the automatic mode at this time:

A.

They would all indicate 100%

B.-FR-478 and 488 would indicate-100%; FR-498 would indicate 0%

C.

All would indicate 0% due to the FEEDWATER ISOLATION " signal.

D. They would not shift to automatic due to the "FEEDWATER ISOLATION" signal.

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SECTION As PLANT PROFICIENCY

.-QUESTION ~ 15 (1.00)

Wnuld it be possible to reset RTB's and withdraw the Shutdown Banks at thio time? Explain.

SECT 23N A: PLANT PROFICIENCY QUESTION 16.(1.00)

Which one of the f ollowing is the reason LC'/-460 A and B are closed?

A.

Phass "A"

isolation has not been reset.

B.

PZR level has not. returned to a sufficient level to reopen LCV-460A,B

.C.. Suf f i c i en *, air pressure is not available D.

The control switch f or LCV-460 A & B i s not in the correct position.

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NO MORE QUESTIONS ON THIS

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'SECTION As PLANT PROFICIENCY 4 ANSWER 1-A.

Low pressurizer level letdown isolation occurred. (during the coolcown of the RCS) C3.50]

B.

Ecch control board pressurizer control switch would have to be rotated to the,"OFF" position and then back to the "ON/ AUTO" posi ti on. C O. 50]

3REFERENdE

'PLR-LP-35 PLR-LP-3 K/A:

3.3/3.6 3.2/3.5 OBJ:

PLR/SRO-LP-35, #3

SECTION As PLANT PROFICIENCY s.

.* ANSWER 2

0) 13-1400 ppm

(+1.00).

.b) 6.75-0.6

(+0.50)

  • REFERENCE CURVE GOOK, OP-301, Sec t '. 6.2 K/A 3.2/3.6 3.9/3.7 DBJ:

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SECTION A PLANT PROFICIENCY

  • ANSWER 3 (COP flowpath-1 direction) Due to containment isolation Phase "B"

signal.

(or due to loss of component cooling water to RCP's caused by C.V.. Phase "B"

isolation signal) [1.003

  • REFERENCE EOP FLOWPA,TH-1 K/A:

3.b3.7 OBJ:

WOG

SECTION A PLANT PROFICIENCY

  • ANSWER 4 A C1.00]
  • REFERENCE SECTION A, SCENARIO #1 K/A 4. 0 /,,4. 1 4.2/4.7 OBJ:

PLR/SRO-LP-49, #2 i

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7 SECTION--As PLANT PROFICIENCY.

-

  • ANSWER 5

- D C1.003 8 REFERENCE CECTION "A",

SCENARIO'N'1 K/A

3. 7/,3. 9 2.8/3.1

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OBJ:

PLR/SRO-LP-38, #4 i

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SECTION A: PLANT PROFICIENCY

'4 ANSWER 6 YES. Criteria are met. CO.503

- RCS presrure > 1520 (1550) and stable or increasing

- Total flow to intact S/G > 300 GPM OR Level in at least 1 S/G > 10% (25%)

- PZR level > 10% (30%)

- RCS subcooling > 25 F (45 F)

-C four (4) G 0.50 each 3

  • REFERENCE, EOP FOLD 00T "W"

K/A:

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SECTION As PLANT PROFICIENCY

~tANSWER 7 "A" SW pump (

"A" SW booster pump when >= 30 psi at booster pump suction) i "A"

AFW pump

-:"B" CCW pump

."A" containment spray pump

[ four (4)- @ 0.25 each 3 84CFERENCS LOGIC DRAWING K/A 3.1/3.4 3.5/3.9 OBJ:

LOGICS 5

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SECTION As PLANT PROFICIENCY

  • ANSWER 8

.YES. SI has been reset. [0.503 Alarm and status light for AUTO SI OVERRIDDEN are illuminated. CO.503 8 REFERENCE CECTION "A",

SCENARIO #1 K/A:

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SECTION As PLANT PROFICIENCY

sANSWER 9 Since "C"

S/G is f aulted, "C" S/G pressure is much less.than "A"

and "B"

'S/G's CO.503 and would theref ore have a lower delta-P between AFW and steam

. proceure causing the majority of flow to be diverted to "C"

S/G. [0.503

$ REFERENCE SECTION "A",

SCENARIO #1 K/A 4.2/4.7 OBJ:

FW-LP-3, #4 4

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SECTION As PLANT PROFICIdNCY

  • ANSWER 10 YES. CO 253 The SI pumps injected water. CO.253 RCS pressure decreased i

bolow shutoff head of the Si pumps (1500 psig) but remained above RHR l

pump shutoff head.CO.503

  • REFERENCE

- SECTION SCENARIO #1 K/A 4.1/3.9 OBJ:

PLR/SRO-LP-40, #1 1

SECTION As PLANT PROFICIENCY

  • ANSWER 11 0 C1.003
  • REFERENCE SECTION "A',

SCENARIO #1 K/A:

2.8t2.9 OBJ:

PLR/SRO-LP-35, #1 l

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SECTION A PLANT PROFICIENCY

  • ANSWER 12

- HVH 1-4 will auto start "butterfly" valves (dampers) open

- ccrvice water outlet valves will open

- normal inlet dampers close C four (4) 9 0.25 each 3 4REFERENCG

. PLR/SRO-LP-44 K/A:

4.1/4.3 OBJ:

PLR/SRO-LP-44, #2 P

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SECTION At-PLANT PROFICIENCY

$ ANSWER 13 A.

INCREASES

~B.

INCREASES C TWO (2) W 0.50 EACH 3 SREFERENCE CECTION '8 f)", SCENARIO #1 ( with a 400 GPM leak on "C" S/G )

K/A - 4.4/4.6 t

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SECTION As PLANT PROFICIENCY

  • ANEWER 14 A [1.003
  • REFERENCE SECTION "A",

SCENARIO #1 K/A:

3.042.9

1 SECTION As PLANT PROFICIENCY t

4 ANSWER 15 NO. CO.50] ALL reactor trip signals must be clear to reset the reactor trip breakers, te.503

  • REFERENCE

. SD 011, Section 2.5 K/A:

3.7/4.2 j

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o SECTION A PLANT PROFICIENCY

  • ANSWER 16 A or C C1.00]
  • REFERENCE SD
021, Section 3.1.1 i

K/A 3.4/,3.6

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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

H.

B.

Robinson REACTOR TYPE:

PWR-WEC3 DATE ADMININSTERED: 12/17/07 OPERATOR:

NOTE TO OPERATOR A grade of 80% overall for Sections A and B combined is the standard for successful completion of the written ex ami nati on.

% OF SECTION CATEGORY OPERATOR'S CATAGORY VALUE SCORE VALUE 1

9 Limits and Controls t.h_I__

All work done on this examination is my own.

I have neither given nor received aid.

Operator's signature

r NRC BULES AND GUIDANCE FOR EXAMINEES 1.

Rest mce trips am to be limited and only one examinee at a time my leave. You nust avoid all contact, with anyone outside the examination mce to avoid even the appearance or possibility of cheating.

2.

Use black ink or dark pencil ONLY to facilitate legible reproductions.

3.

Print your name in the blank pmvided on the cover sheet of the examination.

4.

Fill in the date on the cover sheet of the examination, if necessary.

5.

Answer each question on the examination.

If additional paper is required, use only the lined paper provided by the examiner.

6.

Use abbreviations only if they are commonly used in facility literature.

7.

The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

8.

Show all calculations, methods or assumptions used to obtain an answer to a mathematical pmblem, whether asked for in the question or not.

9.

Unless solicited, the location of references need not be stated.

10. Partial endit rsay be given. Therefore, ANSWER ALL PARIS OF 'IHE QUESTION AND DO NCTT LEAVE ANY ANSWERS BLANK.

11.

If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.

12. You must sign the statment on the mver sheet that indicates the work on the examination is your own and that ycu have not received on been given any assistance in ccepleting the examination. This aust be signed AETER the examination has been ccepleted.
13. Cheating on the examination would result in a revocation of your license and oculd result in rcre severe penalties.
14. The examination is designed to take appmximately 90 minutes to oceplete.

However, this guideline will NCfr be strictly adhered to, and each examinee will be provided a "reasonable" amount of time in which to i

cceplete the examination.

15.

Individual sets of reference material, as well as an abridged set of Plant Operating Manuals have been provided. Do not write on or make any notations or markings on any of the reference material.

16. When ycu are finished and have tumed in your ccepleted examination, leave the examination area.

If ycu are still found in this area while the examination is still in pmgrees, your license may be revoked.

r SECTION B: LIMITS AND CONTROLS QUESTION 1 (1.00)

HBR Unit #2 had been operating at 50 % power for several days.

("A" COND pump O.O.S.

for maintenance) A severe plant transient occurs. The result 10 coveral automatic trip si gnal s being generated wi t'.iout the reactor trip

- brook er s, o,p en i ng ; however, a manual trip WAS successfully performed. While otcbilizidg the plant at Hot Shutdown a review of control room recorders indicated the following simultaneous peak readings occurred during the tecnoient:

- RCS pressure = 1810 psig

- Reactor power = 52%

- RCS Th = 624 F

- RCS Tc = 610 F

- RCS flow = continuous operation of all RCP's A.

D3termine if a Safety Limit has been exceeded.

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SECTION B LIMITS AND CONTROLS QUESTION 2 (1.00)

H"R Unit #2 power level is being increased following repairs to "A"

Main Food Pump. Present power level is 85%

The Allowable Power Limit (APL) is 93X. The PDC 11 function of the ERFIS computer is out of service. The control operator initiates an excessive dilution requiring insertion of centrol Fdds. Two channels of delta flux are observed to be outside the tcrgot band limitations. What actions, if any, are required?

1 SECTION B LIMITS AND CONTROLS QUESTION 3 (1.00)

HBR Unit #2 is at Hot Shutdown, 541 F and RCS pressure at 2235 psig.

D gacsing of the RCS (per OP-918) is in progress prior to initiating a co31down in accordance with GP-007. RCS temperature is observed to be d: creasing,approximately 25 F/hr due to secondary leakage and various cccondary.' steam drains being throttled open. Since steps may be perf ormed out of sequence in the GP, a decision is considered to allow the cooldown to progress prior to depressurization to 1950 psig. Describe any adverse offccts on plant status that may occur as a result of this decision.

SECTION B LIMITS AND CONTROLS QUESTION 4 (1.00)

Tho unit is at 100% power, steady state. The outside Auxiliary Operator notifies the control room that the service water line to the upper oil coolcr on "B" condensate pump has ruptured. The Shift Foreman directs that unit power be reduced to 50% at a rate of 4 X/ min in order to secure "B"

condensaty pump. An operator suggests using MOV-350 ( emergency boration to charging pump suction) in order to allow a faster boration during the

-paw;r reduction. Would you agree to this use of MOV-350? Explain your antw;r.

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i SECTION B LIMITS AND CONTROLS QUESTION 5 (1.00)

' From the statements below dotermine the statement that is NOT correct rcgceding independent verification.

A) Minual, val ve posi tion may be veri fi ed by stem posi ti on.

B) Throttled valves should be verified during the throttling evolution.

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C) A blank flange installation may be verified by observation of a static upstream pressure indicator.

-D)

Independent verification of valves included in OWP's must be performed by qualified licensed oprators.

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a SECTION B LIMITS AND CONTROLS

. QUESTION 6 (1.00)

Approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> after a LOCA it is necessary to switch f rom cold ICg recirculation to hot leg recirculation. Which ONE of the f ollowing is thW reason for this realignment requirement?

A) To minkmize the amount of boron plating out on the surfaces of the fuel.

B) Prevent sediment or loose pieces from inhibiting downcomer flow.

C) Prevant uneven heating and annealing of the thermal shield.

D) The SI flow requirement is reduced due to reduction in decay heat.

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SECTION B LIMITS AND CONTROLS QUESTION 7 (1.00)

Which ONE of the f ollowing are DWP's (Operations Work Procedures) used for?

A) Properly aligning equipment for maintenance.

B) DscumdNt testing requirements.

C). Providing instructions for proper system alignment.

D) All of the above.

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

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SECTION B LIMITS AND CONTROLS QUESTION 8 (1.75)

.HBR Unit #2 is at 100 % power, steady state. The HP-97 calcul ator in the centrol room is 00S. Based on the values given below, determine the "QUADRANT POWER TILT" as defined in Technical Sp ec i f i c a t i on s..

NORMAL UPPER DETECTOR CURRENTS

,/

N-41 = 230 N-42 = 235 N-43 = 232 N-44 = 236 NORMAL LOWER DETECTOR CURRENTS N-41 = 233 N-42 = 238 N-43 = 231 N-44 = 240 PRESENT INDICATED DETECTOR CURRENTS UPPER LOWER N-41 232 236 N-42 238 243 N-43 235 234 N-44 239 243 I

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SECTION B: LIMITS AND CONTROLS QUESTION 9 (1.00)

Whilo operating steady state, 100 % power, maintenance requests a local clocrance on the flow ori fice for FI-944 (SI test line on CV spray hoodcrs) due to excessive flange leakage. An OWP for this component does not oxist. Which one of the f ollowing would be an acceptable course of action? ", ' '

A) Since this component cannot ne isolated, inform maintenance it must be repaired in cold shutdown.

B) A local clearance may be issued as no OWP is required for this component.

C) Inf orm maintenance that an OWP for this component must be prepared prior to maintenance.

D) Inform maintenance that a special repair procedur.e will be required cince an OWP does not exist for this component.

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SECTION B LIMITS AND CONTROLS a

QUESTION 10 (1.50)

Tho plant is operating at 100% power steady state, all systems in AUTO /

NORMAL. No equipment is out of service. A fitting on the sensing line at PT-485

("B" main steam line pressure transmitter) is discovered to have a cignificant steam leak. The decision is made to take the transmitter out of ccrvie9 in accordance wi th OWP-SGP-8. Discuss any possible transient thct may 'bccur due to failing to adhere to precaution No. 1 on this OWP.

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SECTION B: LIMITS AND CONTROLS QUESTION 11 (1.50)

Fcr cach of the following situations listed below, indicate.YES or NO as to l

whOther or not it would require entry into AOP-023, "Loss of Cont ai nment Intcgrity".(plant status is 100% power, steady state)

A.

H alth.. Physics personnel report that the outer CV personnel hatch has been found unlocked, but closed.

B.

The inside Auxiliary Operator reports that he has discovered station oir aligned to the CV.

C.

A small CCW 1eak is discovered on the control rod drive mechanism fcn cooler in the CV.

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SECTION B LIMITS AND CONTROLS QUESTION 12 (1.00)

A caution at the beginning of FRP-H.1 reqaires RCS bleed and feed to be etcrted at STEP 9 if ANY S/G wide range level decreases to less than 60 7. [63 %3. Which i tem below is the basis for this caution?

A) Steps t through B deal only with diagnostic evaluation of the event cnd maV be time consuming.

B) Steps 1 through 8 consist of a "loop" that is difficult to exit from.

C) Wide range level is not calibrated (theref ore not accurate) for

< 60 % C63 %3.

D) This level assumes S/G dryout is imminent and RCS bleed and feed must be started immedi ately f or core cooling.

SECTION B: LIMITS AND CONTROLS

' QUESTION 13 (1.00)

D3tcrmine the posting required for a room using the results of the f ollcwing radiological surveys

- 1.' AIRBORNE ACTIVITY:

6.34 E-9 uct/cc (Co-60) 2.

FLOOR' SMEAR:

Beta-610 dpm/cm squared Alpha-4 dpm/cm squared

3. EQUIPMENT SMEAR: Beta

'iB00 dpm/cm squared Alpha-16 dpm/cm squared 4

GENERAL RADIATION LEVEL: 110 mr/hr 4

(

SECTION B LIMITS AND CONTROLS QUESTION 14 (1.50)

HBR Unit #2 is at 100% power. AOP-19, "MALFUNCTION OF RCS PRESSURE CONTROL" hco been implemented to deal with a decreasing pressurizer pressure.

Stcp 2.3.2.2 requires three action steps if the auxiliary spray valve is diccovered open AND will not close. These actions are:

1) Close'hCV-121
2) S:curi normal letdown
3) Place excess letdown in service Explain the purpose for EACH action above.

SECTION Be LIMITS AND CONTROLS QUESTION 15 (1.00)

HBR Unit #2 is at 100 % power with all controls in AUTO / NORMAL. You are notified by maintenance (I&C) that they intend to perform maintenance on the level control system for "B" auxiliary boiler condensate tank. They inform you that the circuit has been deenergized for a month by use of a non -caf ety rel ated wire removal. The tags are still in place. What would bo your response with regard to their compliance with clearance / wire fecmoval procedures? Explain your ansper.

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SECTION B LIMITS AND CONTROLS QUESTION 16 (1.00)

Which ONE item below is the basis for requiring RCP's to be tripped if the cri tcri a on "Fol dout A" are met?

- A) Minimize the depletion of RCS inventory during a small break LOCA.

- B) Rsduce RCS heat input during a loss of all feedwater event.

C) R3 duce RCS heat input during an ATWS event.

D) Minimize rapid depressurization of the RCS during a small break LOCA.

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SECTION Bi LIMITS AND CONTROLS QUESTION 17 (1.00)

DSP-502 requires the Auxiliary Building Operator to manually close SI-B64 A or B (RWST outlet isolation valves). Which item below is the purpose for this step?

A) Thi s pr, events bac k f l ow from the CV sump to the RWST due to spurious volve.dperation B) Icelation of the RWST is required to prevent backflow from the RCS to the RWST through the idle Si and Spray pumps.

C) Prevents draining the RWST to the CV sump due to spurious operation of CV sump isolation valves.

D) Prevents flooding the RHR pit due to imminent RHR pump seal failure.

SECTION B LIMITS AND CONTROLS

. QUESTION'18 (1.00)

Which DNE statement below is correct regarding REFUELING?

. A) _ Fuel movement in the CV is not allowed unless relative humidity is

<= 70 %.

B) At leist ONE RHR pump must remain in continuous operation.-

- C)-RCS boron must be verified >= 1950 ppm boron once per day.

D) The core fuel assemblies shall not be moved unless 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> have olapsed after shutdown.

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l SECTION B: LIMITS AND CONTROLS QUESTION 19 (1.00)

Which ONE of the below-li sted items would constitute an UNSAFE CONDITION co dafined in OMM-011,"Operational Response to Deliberate Acts Against Plcnt Equipment".-

A)

"B" SIjpump discharge valve locking device allows freedom of valve movement of 2 turns.

B) The breaker for HVS-1 (Auxiliary Building Supply Fan) air wash pump to found open.

C) The service water booster pump "Dil Reservoir Bowl s" are reported missing by the inside A.O.

D) The lock and chain on LO-12, lube oil storage tank drain, is found missing.

END OF SECTION B

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4

.1 4

4 a

d SECTION B: LIMITS AND CONTROLS

  • ANSWER 1

'A.

YES. A Saf ety Limit has been exceeded. [1.003

  • REFERENCE TS Fig. 2.1-1

- PEP-101,, od.

1, page 7 of 17 K/A 3.1/4.4 3.5/4.0 OBJ:

SRO-LP-55, # 2, - SRO-LP-64, #3 h

t

SECTION B LIMITS AND CONTROLS

  • ANSWER 2 Eithcr eliminate the deviation immediately OR reduce reactor power to

< 83.7 */. (0.9 APL) C either answer for 1.00 3

3.b3.8 3.1/3.8

_OBJ:

PROC-LP-47,-#4 l

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1 SECTION B LIMITS AND CONTROLS 8 ANSWER 3 A3 tCmperature drifts down, S/G pressures decrease.CO.253 When S/G proccures decrease to < 485 psig a High Steam Line Delta-p signal CO.253 will be generated resulting in an inadvertent safety injection. [0.503

( HI steam flow in coincidence with low Tave/Lo Steam Pressure SI MAY oico be received)

$ REFERENCE GP-007; HBR LER 86-6 K/A 3.2/3.4 OBJ:

DEF Action Items, Week 4 1986 RTNG, #1

  • s SECTION B LIMITS AND CONTROLS 4AN'mWER 4

_ edo. CO.503 MOV-350 should only be used if the intent is to shutdown the rocctor or maintain it shutdown. [0.503

4.1O4.4 03J EOF Action Items, Week 2,

  1. 9 i

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SECTION B: LIMITS AND CONTROLS

  • ANSWER 5 C [1000]
  • REFERENCE PLP-030; D.

-1 K/A 3.6(3.7 l

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SECTION Ba~LI,MITS AND CONTROLS a'

- 8 ANT 4WER 6.

A C1.993

  • REFERENCE ~

WOG Background Documents (ES 1.4 page 2)

K/As.

4.3/.4.4 1

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i SECTION B LIMITS AND CONTROLS

  • ANSWER 7 D C1.003

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AOP-LP-6 I

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CECTION B LIMITS AND CONTROLS sANSWER 8 PRESENT DETECTOR CURRENT NORMALIZED FRACTION CO.253

=

NORMAL DETECTOR CURRENT

  • 'i UPPER FRACTIONS LOWER FRACTIONS N-41 1.0087 1.0129 N-42 1.0128 1.0210 (MAX)

CO.253 N-43 1.0129 (MAX) CO.253 1.0129 N-44 1.0127 1.0125 (AVG) = TOTAL /4= 1.0118 (AVG)= 1.0148 CO.253 MAX / AVG UPPER = 1.1029/1.0118=1.001 CO.253 MAX / AVG LOWER = 1.0210/1.0138=1.0061 CO.253 QPTR= 1.0061

.CO.253

  • REFERENCE FMP-007 K/A 3.3/3.6

=

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s SECTION Be LIMITS AND CONTROLS

  • ANSWER 9 C C1.003
  • REFERENCE OMM-004 K/A
3. 7/.4.1 02J AOP-LP-6, #2 l

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  • s SECTION B LIMITS AND CONTROLS

. s 8ANSE.'ER 10 If "FR-488" (steam flow selector switch) is selected to "484" (steam flow trcncmitter FT-484),the steam flow signal sent to the steam generator wntcr level control system (SGWLC) will fall to minimum. [0.503 The SGWLC cystcm will respond by closing the feed water regulating valve.CO.503 A rocetorjtrip will li kely result. [0.503 (from SF/FF mismatch coincident with low'S/G 1evel on redundant nonaffected channel)

  • REFERENCE LER 85-017 K/A 3.4/3.6

CECTION B LIMITS AND CONTROLO

$ AN'2WER 11 A. No-B.

Ycs C. N3 C three 9 0.50 each 3 4 REFERENCE]

AOP-0233*/OP-923 K/At 3.8/4.1 PLR/SRO-LP-55, #1 1

)

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  • 's i

a' SECTION B: LIMITS AND CONTROLS

. =

4 ANSWER 12 D C1,993 8 REFERENCE WOG Background Documents (FR-H.1)

K/A:

4.444.6 3.6/3.6

SECTION B: LIMITS AND CONTROLS

$AN WER 13 Room should be posted as f ollows:

- Airborne radioactivity area

- Contaminated process equipment area

- High radiation area C three G B.33 each 3

  • REFERENC5 HPP-Cel K/A:

2.8/3.4 i

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SECTION B: LIMITS AND CONTROLS

  • ANSWER 14 1.

Secure flow to the charging line, hence auxiliary spray CO.503 2.

Reduce letdown due to limited charging potential OR prevent excessive letdown temperatures due to isolating flow through the regenerative heat exchanger. [0.503 t,1 y 15 GPM will 3.

Provide for pressurizer level control since approxit i

be added to the RCS via the seal injection path. CO.bO3

  • REFERENCE SD-021 K/A 3.7/4.1 l

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SECTION B LIMITS AND C.,NTROLS

  • ANSWER ~15 They should be informed that a wire removal is not to be used in lieu of a local clearance CO.503, and they should obtain a clearance prior to working

'on the circuit. CO.503

  • REFERENCE
  • /

OMM-012

]

K/A 3.7/4.1 t

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SECTION B LIMITS AND CONTROLS

  • ANSWER 16 A C1.003
  • REFERENCE WOG Emergency Response Guidelines K/A 3.9/,4.2 i

(

SECTION B LIMITS AND CONTROLS

. n -

  • ANSWER 17 C [1.00]
  • REFERENCE ARP-LP-2 K/A 3.3/,4.1 OBJ:

ARP-LP-2, #3 I

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SECTION B: LIMITS AND CONTROLS

  • ANSWER 18 D C1.003

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s a SECTION B: LIMITS AND CONTROLS ci ^ "

  • ANSWER 19 C [1.003

2.5/.3.4 OBJ:

AOP-LP-6A, #2 i

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NUCt. EAR REGULATORY COMMISSION SENIOR / REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

H. B. Robinson REACTOR TYPE:

PWR-WEC3 DATE ADMININSTERED: 12/17/87 OPERATOR:

NOTE TO OPERATOR A grade of 80*/ overall for Sections A 40d B combined is the standard for succet.ful completion of the written examination.

  • /. OF SECTION CATEGORY OPERATOR'S CATAGORY VALUE SCORE VALUE 3

A Plant Proficiency

_/jhj_h_f 1 All work done on this examination is my own.

I have neither given nor received aid.

Operator's Signature i

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MC RtLES (ND CUIDCtE FCR EXft11tfES 1.

Rest room trips are to te limited ard cnly one examinee at a tine may leave. You cust avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of CPeating.

2.

Use black ink or dark pmcil OLY to facilitate legible' repecductions.

3.

Print your nane in the blank provided on tFe cover sheet of tre examinatico.

4.

Fill in the date on the cover steet of the examinaticn, if necessary.

5.

Answer each question en the examinaticn.

If additional paper is required, use only the lined paper provided by the examiner.

6.

Use abbreviations cnly if they are commcnly used in facility literature.

7.

The point value for each question is indicated in parentteses af ter the questico and can te used as a guide for the depth of. answr r req. tired.

G.

Show all calculaticos, nettcds or asstynptions used to obtain an answer to a nethematical problem, whetter asked for in tPe qtestico or not.

9.

Lhless solicited, the locaticn of references need not te stated.

10.

Partial credit may be given. Therefore, fNENER fli. Ff6TS CF 'n-E O_ESTIG4 f4D DO TDT LElWE fHY (4EMERS ELRK.

11.

If parts of the examinatim are not clear with respect to their intent, ask questicos of the examiner only.

12.

Ycu nust sign the statercet cn tre cover staset that irdicates the work cn the examinatico is ycur cun and that ycu have not received cn teen given any assistance in ccmpleting tre examinaticn.

This nest te signed (FTER j

tre examinaticn has teen cowpleted.

13.

Creating cm the e>:aminatico waild result in a revocation of yoJr license l

and cculd result in norc severe penalties.

14.

The examinaticn is designed to tal e approximately 90 minutes to cceplete.

l Fb ever, this guideline will PDT te strictly adFered to, ard eech l

examinee will te provided a "reescnable" arount of tine in which to cceplete the examinatico.

15.

Due to the existence of qtesticns that will require all examinms to refer to the sane indicaticns or centrols, particular care nest te taken to maintain individual e <am security end avoid any pcssibility of ccmpecmise or appearar<e of creating.

16.

Whv=n yco are finished and have turncd in ycur completed examinatico, I

leave the examination area.

If you are still found in this area while l

the e>reminaticn is still in progress, ycur license ney te revcled.

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SCENARIO #1 15 MINUTES AGO, THE UNIT WAS AT:

1.02% POWER, STEADY STATE BORON = 950 PEN BANK "D" 00NTROL RODS @ 220 STEPS ALL CONTROLS IN AUTO / NORMAL THEN A TRANSIENT OCCURRED, INITIATED BY EE FAILURE OF POWER RANGE CHANNEL N-41.

THE FAILURE WAS CAUSED BY BLOWN INSTRUMENT POWER FUSES. EE PLANT WAS STABILIZED AND NI-41 HAS BEEN RDf0VED FROM SERVICE,IN ACCORDANCE WITH OWP-NI-1 THE FOLILWING 8 QUESTIONS PERTAIN TO EIS MALFUNCTION AND ITS ASSOCIATED PLANT RESPONSE.

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o SECTION At PLANT PROFICIENCY i

i QUESTION 1 (1.00)

Tho I&C technician that has been assigned to investigate the failure of power range channel NI-41, requests permission to remove NI-41 control pow 3r fuses. What would be your response? Justify your answer.

~..

.. _... ~.. _

SECTION At PLANT PROFICIENCY QUESTION 2 (1.00)

With power range channel NI-41 removed from service per OWP-NI-1, which one of the f ollowing is the present DEGREE OF REDUNDANCY of nuclear flux power ecngs af f oro~ed by the nucl ear power range channels?

A..O B.

1 C.

2 D.

3 I

SECTION As PLANT PROFICIENCY QUESTION 3 (0.50)

Indicate what type of turbine runback occurred: LOAD LIMIT, LOAD i

REFERENCE or BOTH.

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SECTION As PLANT PROFICIENCY QUESTION 4 (1.00)

Hcd this failure occurred on power range channel NI-44 rather than power ccngo channel NI-41, which one of the following best describes the INITIAL (firct 15 seconds) response of the plant? ( Assume all controls are in AUTO and that a turbine runback is initiated for each of the following)

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A) Contro1 rods start STEPPING IN, steam dump system inhibited due to the rcduction in NI-44 power.

B) Auto rod control OUT SIGNAL DEMANDED, no initial rod motion due to suto rod withdrawal blocked, steam dumps operate as required.

C) Control rods begin STEPPING CUT, steam dump system operates as required.

D) Control rods start STEPPING IN, steam dump system operates as required.

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i SECTION A PLANT PROFICIENCY

-QUESTION 5 (1.00)

Datormine the control rod insertion limit (per Technical Specifications) for the present plant conditions. (use figure 3.10-1 attached)

"A

SECTION As PLANT PROFICIENCY QUESTION 6 (1.00)

Prior to the NI-41 failure transient, several annunciators / abnormal indications related to the RCS occurred, resulting in OST-051 RCS LEAKAGE EVALUATION " being performed. RCS leakage was calculated to be 2.8 GPM.

2.3 GPM leakage was being collected in the reactor coolant drain t a(k'. 0.5 GPM leakage was unidentified.

Which RCP and which seal failure is the most likely cause of these cbnormal RCS-related indications?

i

t SECTION As PLANT PROFICIENCY QUESTION 7 (0.50) j Whet operator action (s) would be required to clear the steam dump armed cnnunciator?

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SECTION As PLANT PROFICIENCY QUESTION 8 (1.00)

Onco the reactor operator has stabilized the unit after the failure of pow r range channel NI-41, he notices that three (3) channels indicate that exici offset ir. out of the target band. What is the most correct action to tako to get back within the target band? (select ONE choice from below)

A) Using normal boration procedure, slowly borate the rods out.

B) Block open FCV-113A and FCV-1138, start a boric acid pump and borate continuously until offset is back within the target band.

C) Rsduce power to 50%, allow the xenon transient to subside, then establish offset back within the target band using normal boration procedure.

D) Open MOV-350 to rapidly borate rods out prior to exceeding limit on panalty point collection.

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LAST QUESTION ASSOCIATED WITH THE SIMULATOR TRANSIENT l

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,?

SCENARIO #1 1HE EXISTING PLAW 00NDITIONS DO NCTF APPLY TO THE FOLLOWING 8 QUESTIONS.

THE SIMULATOR IS 70 BE trfILIZED AS A FRAME OF REFERENCE ONLY.

,s

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v.

w...w y-,.-., -.

,,,.,,m-

SECTION As PLANT 9ROFICIENCY QUESTION 9 (1.00)

You are manually withdrawing "B" control bank during a reactor startup.

You notice that "B" control bank step counters indicate 120 steps, but "C" control group has not started stepping out yet.

"A" control bank step counters indicate 228 steps. The RPI's coincide with the bank step count er s.",Whi ch one of the following is the most probable cause for this?

A) The rod control sel ec t or switch is in the "B" control bank position.

B) The P/A converter in the logic cabinet is incorrectly set for "C"

control group.

C) The bank overlap fcr "C" control group in the logic cabinet is incorrectly set.

D) These indications are correct for current rod positions.

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SECTION As PLANT PROFICIENCY QUESTION 10 (1.00)

Tho unit is at 100% power, steady state, all controls in normal / auto. The fosdback linkage on "C"

feed regulating valve, between the valve stem and positioner, becomes disconnected. Which ONE of the following best describes the Gxpec,ted valve re conse?

A) The valve will begin closing as the control system senses the false full open signal.

B) The valve will fail open as the control system senses the false full closed signal.

C) The valve will remain stationary because no "feedback" signal is sensed.

D) The valve would respond as in "B"

above but since the feedwater regulating valves are full open at 100% power, no transient will result.

SECTION A PLANT PROFICIENCY QUESTION 11 (1.00)

With tne unit at 100% power, steady state, all systems in normal / auto, a fitting on the LT-476, "A"

steam generator narrow range level d/p cell, REFERENCE LEG separates. Which one of the following is the most probable plcnt respone?

LT-475'~ fails high, level input to steam generator water l evel control A) goes high. Feed flow is rapidly reduced and the li kely result would be a reactor trip.

B) LT-476 would fail l ow, no adverse plant effects since 2 of 3 channels must fail to generate a reactor trip.

C) LT-476 would fail low, no plant effects since LT-476 is used for indication only.

D) LT-476 fails high, no plant effect since 2 of 3 channels must be greater than 75% to generate a turbine trip.

A-m

. c SECTION As PLANT PROFICIENCY a

QUESTION 12 (1.00)

With the unit at 100% power, steady state, all systems in normal / auto, e rcdiation monitor alarm on R-17 has been received. The CCW surge tank loval is increasing slowly. Which one of the coolers listed below is the most likely cause of these indications?

A) Excess

  • letdown heat exchanger B) An SI pump seal water heat exchanger C) An RHR heat exchanger D) Pressurizer liquid space sample cooler

SECTION As PLANT PROFICIENCY QUESTION 13 (1.00)

While at power, average core' exit thermocouple temperatures on the ICCM tre generally several degrees higher than wide range Th temperatures.

What is the reason for this relationship?

SECTION As PLANT PROFICIENCY QUESTION 14 (1.00)

Wnich statement below correctly describes how each reactor trip breaker will be tripped upon receipt of an automatic reactor trip signal?

A) The undervoltage coil will energize and the shunt trip coil will da-energize.

j B) The undervoltage coil will de-energize and the shunt trip coil will energize.

C) Only the undervoltage coil will de-energize.

D) Only the shunt trip coil will energize.

SECTION As PLANT PROFICIENCY QUESTION 15 (1.00)

Volves SI-856A and 856B (High head SI test line to RWST) are mechanically blocked open. Which ONE of the following is the reason for blocking these valves open?

A) Due tojthe "in-series" valve configuration, failure of either valve could' result in SI pump damage.

B) These valves have a history of inadvertently failing closed.

C) This prevents inadvertent closure due to Phase "A"

isolation.

D) The mechanical blocks ensure the test line is maintained open to ensure valid results from SI pump testing.

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s SECTION As PLANT PROFICIENCY QUESTION 16 (1.25)

HBR. Unit #2 has been placed in cold shutdown in accordance with GP~007.

Dictcbles for HIGH STEAM LINE FLOW (FC-474 and FC-485) are both placed in the tripped position while perf orming a maintenance surveillance tout.

s[gn al (s )

will be generated?

A.

What B. List THREE DIFFERENT alarms that will be received as a result of the bistable actuation.

LAST QUESTION NOT RELATED TO SIMULATOR TRANSIENT

SECTION As PLANT PROFICIENCY

  • ANSWER 1

'DO NOT give permission.CO.50] Removal of the control power fuses would (roinstate the dropped rod circuit and) initiate another turbine runback.CO.503

  • REFERENCE OWP-NI-1<j OP-002 Precaution K/A: 4.1/4.2 I

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m SECTION A PLANT PROFICIENCY

  • ANSWER 2 C.E1.003
  • REFERENCE PLR/SRO-LP-37 K/A:
3. 2 / '5,. 5 3.1/3.8 02J PLR/ RO-LP-37, 43

SECTION As PLANT PROFICIENCY

  • ANSWER 3 BOTH CO.503
  • REFERENCE
          • NO FACILITY REFERENCE SUPPLIED *****

K/A:

3.?/,4.3 l

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CECTION As PLANT PROFICIENCY

  • ANSWER 4 8 C1.003
  • REFERENCE PLR/SRO-LP-36 K/A:

3.'3/3.5 3.7/3.9 OrJ PLR/SRO-LP-36, #2 and #3 l

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SECTION As PLANT PROFICIENCY-

  • ANSWER 5 65 oteps (D BANK) +- 10 steps C1.003 OR 32%

(+/-

1%)

. g 4 REFERENCE Tcchnical Specifications, Fig. 3.10-1

-K/A 3.3.3.5 3.3/3.6 OBJ PROC-LP-38, #2

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SECTION As PLANT PROFICIENCY 4 ANSWER'6 "B" RCP CO.503 via #2 seal failure CO.503

$ REFERENCE I

SECT-"A",. Scenario #2 K/A:

2.8/,2.8 3.3/3.2 OBJ:

PLR/SRO-LP-35, #1 I

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SECTION A: PLANT PROFICIENCY l

8 ANSWER 7 Tho operator must place the steam dump control mode selector switch to recot. CO.503

  • REFERENCE PLR/SRO-LP-49 K/As-
2. S f3.' O 2.8/2.9 OBJ:

PLR/SRO-LP-49, #2 J

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o SECTION A: PLANT PROFICIENCY

  • ANSWER 8 A C1.003
  • REFERENCE FMP-E09, 6.1.4 K/A:

3.3/3.6 3.3/3.6

". 'i 02J:

PROC-LP-47, #3

e SECTION As PLANT PROFICIENCY

  • ANSWER 9 D C1.003
  • REFERENCE RDCNT-LP-1 K/A:

3.9(4.1 OBJ:

SIM SCENARIO I

e SECTION A PLANT PROFICIENCY

  • ANSWER 10 B C1.00]

'i

  • REFERENCE LER ( # not supplied )

K/A 3.1/3.4 3.1/3.2

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-SECTION As. PLANT PROFICIENCY 8 ANSWER 11 A C1.003

  • REFERENCE

'PLR/SRO-LP-50

.'K/A 3. 4. /.3. 6 3.2/3.5 OBJ:

PLR/SRO-LP-50, #3 i

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

. -. - ~.

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1 SECTION As PLANT PROFICIENCY

^

'* ANSWER 12 D _ C 1. 88 3.

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  • REFERENCE ~

Normal Plant. Operations,' System Alignment K/A:

4 3/3.3 t

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SECTION As PLANT PROFICIENCY 8 ANSWER 13 Coro exit temperature is reduced slightly due-to the mixing of core

.g bypocs flows. C1.003 sREFERENCE Initial Conditions IC-5, 100*/. Power K/A

$3.5/2.8 OBJ:

PLR/SRO-LP-34,.#1 i

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SECTION As PLANT PROFICIENCY

  • ANSWER-14 B - f. 1'. 0 0 3

~3 REFERENCE PLR/SRO-LP-38.

K/A 3.7/4.2 3.9/4.0 OBJ:

PLR'/SRO-LP-38, #2 F

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-SECTION As PLANT PROFICIENCY 4 ANSWER 15 A C1.003

  • REFERENCE

~ IE Notice 85-94 K/A:

'2.7/3.0 l

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DBJ:

DEF Action Items (week 3 1986 retraining) #2 4

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SECTION A PLANT PROFICIENCY 4 ANSWER 16 A.

A main steam line isolation signal will be generated. (causing MSIV closure if originally OPEN) CO.503 D.

"STEAM LINE ISOLATION" C0.253 "HIGH STEAM FLOW" annunciators for "A"

"B" steam lines wiiY be actuated.CO.503

$ REFERENCE Lcgic DWG's; 5379-2759 & 2758 (sheets 7 & 8 of 18), APP-006 K/A 3.7/3.7 OBJ:

PLR/SRO-LP-40, #2 l

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S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

H.

B.

Robinson REACTOR TYPE:

PWR-WEC3 DATE ADMININSTERED: 12/17/87 OPERATOR:

NOTE TO OPERATOR A grade of 80% overall for Sections A and B combined is the standard for successful completion of the written examination.

% OF SECTION CATEGORY OPERATOR'S CATAGORY VALUE SCORE VALUE B

Limi ts and Controls

_c[h; _3 _ _

All work done on thi s ex amination is my own.

I have neither given nor received aid.

Operator's Signature

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NRC RULES AND GUIDANCE FOR EXAMINEES 1.

Rest roce tripe are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination rece to avoid even the appearance or possibility of cheating.

2.

Use black ink or dark pencil ONLY to facilitate legible reproductions.

3.

Print your name in the blank provided on the cover sheet of the examination.

4.

Fill in the date on the cover sheet of the examination, if necessary.

5.

Answer each question on the examination.

If additional paper is required, use only the lined paper provided by the examirer.

6.

Use abbreviations only if they are coneonly used in facility literature.

7.

The point value for each question is indicated in parer 1 theses after the question and can be used as a guide for the depth of an.cuer required.

8.

Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.

9.

Unless solicited, the location of references need not be stated.

10. Partial emdit may be given. Therefore, ANSWER ALL PARTS OF ' IRE QUESTION AND DO NUT LEAVE ANY ANSWERS BLANK.

11.

If parta of the examination are not clear with respect to their intent, ask questions of the examiner only.

12. You unst sign the statment on the cover aheet that indicates the work on the examination is your own and that you have not received on been given any assistance in ccepleting the examination. 'Ihis must be signed AFTER the examination has been ccepleted.
13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
14. The examination is designed to take approximately 90 minutes to cceplete.

However, this guideline will NUT be strictly adhered to, and each examinee will be provided a "reasonable" amount of time in which to cceplete the examination.

15.

Individual sets of reference material, as well as an abridged set of Plant Operating Manuals have been provided.

Do not write on or mke any notations or markings on any of the reference material.

16. When you are finished and have turned in your ccepleted examination, leave the examination area.

If you are still found in this azea while the examination is still in progress, your license may be revoked.

8 SECTION B LIMITS AND CONTROLS e

QUESTION 1 (1.00)

HBR Unit #2 is in cold shutdown recovering from a brief (3 day) maintenance cutcge. Since several maintenance items on the CCW system (CCW pumps, ccmpl e cool er s, RCP oil coolers) have been performed, the Operating Super-vicor has decided to perform a complete Component Cooling System Checklist, OP-3E6, A t't.

9.1.

Tho RHR heat exchanger room is a "LOCKED HIGH RADIATION AREA" due to CRUD cccumulation in several locations. Sel ec t the appropriate statement from bolow that is CORRECT regarding independent verification.

A) Due to the sensitive nature of the CCW system, the valve lineup must ce pcrformed by licensed operators.

B) The Shift Foreman may N/A any second checks he determines do not have to be performed.

C) All valve checks must be performed.

D) Independent verification in the RHR HX room may be deleted (temporary change per AP-004) due to personnel exposure considerati ons.

SECTION B LIMITS AND CONTROLS QUESTION.2 (1.00)

Tho unit is in Hot Shutdown with RCS Th at 525 F, and RCS pressure at 1403 psig. DSP-003 is being used due to a fire in the charging pump room.

Stcp 2.2.12 is being performed and ONLY pressurizer backup group "B"

hoatcrs are available. Determine the maximum */. per minute pressurizer level increase using ONE (1) SI pump.

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i SECTION B LIMITS AND CONTROLS l

QUESTION 3 (1.00)

A G:neral Emergency has been declared. CV high range monitors are reading cpprox. 3,000 R/hr Determine the appropriate initial minimum PROTECTIVE ACTION RECOMMENDATIONS that would be required based on the above informa-tion.

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SECTION B LIMITS AND CONTROLS QUESTION 4 (1.50)

HBR Unit #2 had been operating at 50 % power for several days.

("A" COND

. pump O.O.S.

for maintenance) A severe plant transient occurs. The result ic coveral automatic trip signals being generated without the reactor trip brookers opening; however, a manual trip WAS successfully performed. While otcbilizing the plant at Hot Shutdown a review of control room recorders indicated'the following simultaneous peak readings occurred during the trcnoient:

- RCS pressure = 1810 psig

- Reactor power = 52%

- RCS Th = 624 F RCS Tc = 610 F

- RCS flow = continuous operation of all RCP's A. Using ALL information and data from above, determine the appropriate Gmergency event cl assi f i c at i on.

B.

D3termine if a Safety Limit has been exceeded.

s SECTION B LIMITS AND CONTROLS QUESTION 5 (1.00)

An off site release has occurred requiring calculation of offsite doses.

A00ume that atmospheric dispersion factors (X/Q) and radiation monitor rocdings are THE SAME in all accident conditions. Determine FROM column "B"

the accident condition that would result in the highest calculated d300 to the organs of c onsi der a t i on in column "A".

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.. B "

A.

The whole body 1.

Rupture of a waste gas decay tank B.

The thyroid 2.

Several spent fuel assembli es are damaged in the spent fuel pit 3.

A pressurizer PORV is stuck open, no present indication of clad failure

.I 0

SECTION B LIMITS AND CONTROLS t

QUESTION 6 (1.00)

-EPP-1, "LOSS OF ALL AC POWER", is being performed. The steam driven AFW purp will not start and all S/G levels are < 10% C25%3. Reactor power is

< 5% on N-42 & 43. Core exit TC's are approx. 710 F (subcooling < 45 F).

At this point you should ROmain,.in EPP-1 A)

B) Exit to FRP-H.1 C) Exit to FRP-C.2 3

D) Implement DSP-001

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SECTION B: LIMITS AND CONTROLS QUESTION 7 (1.00)

HBR Unit #2 is at Hot Shutdown. Tave = 547 F and RCS pressure = 2235 psig.

Maintenance is in progress in containment. A "SOURCE RANGE HI FLUX LEVEL TRIP" caused by a "spike" on N-31 causes a shutdown bank trip. The cause of the spike is thought to be due to welding activities, but cannot be vGr i f i ed.* ~jSel ec t the statement below that WOULD apply based on the above i n f ormat i'on.

A) The PNSC would be required to authorize withdrawing the shutdown banks.

B) The Unit #2 Operations Manager must approve withdrawing the shutdown banks.

C) The Shift Foreman woult' approve the startup.

D)' A PNSC meeting with subsequent approval of the Chairman would be required prior to startup.

SECTION B LIMITS AND CONTROLS QUESTION B (1.00)

In GP-007, the allowable cooldown limi tation below 170 F was changed from 5 F/hr to 3 F/hr The reason for the reduction ist A) This allows for stress relaxation of fuel clad prior to refueling.

B) Minimi"res reactor vessel stresses to allow an increase in PORV opening time criteria from 2.0 to 2.5 seconds.

C) Allows f or sufficient time (>100 hrs) prior to initiating fuel movement.

D) Cooling down at > 3 F/hr at <170 F is not addressed in the updated FSAR.

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SECTION B LIMITS AND CONTROLS QUESTION 9 (1.00)

HBR Unit #2 is operating at 100% power, steady state, no LCO equipment out of service. All systems aligned in NORMAL / AUTOMATIC. An "SI PUMP COOLING WATER LO FLOW" alarm is received. Local verification of FIC-658 indicates zero flow. Valve lineup is f ound to be normal and flow blockage 10 cuspected.

D3tcrmine the LCO requirement that would be applicable.

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SECTION B: LIMITS AND CONTROLS QUESTION 10 (1.00)

Tho f ollowing conditions / indications have occurred

1) A large fire is in progress in the E-1/E-2 room, fire brigade rcsponding.

's

2) A reactor trip from 100*/ power, steady state, has occurred.
3) Breakers will not close on ALL SW pumps.
4) Present plant status is difficult to determine due to various fluctuating indications and uncontrolled valve cycling.

Whct would the appropriate action for this event be?

A) R main in PATH-1 until directed to the appropriate FRP/EPP.

B) Trip all 4KV bus supplies and EDG breakers and implement EPP-1 C) R main.in the EOP network until directed to exit to the appropriate DSP.

D) Implement DSP-001 and subsequently DSP-002.

i

SECTION Be LIMITS AND CONTROLS QUESTION 11 (1.00)

Tho plant is stable at 100% power, no LCO equipment out of service and all cyotcms are aligned in AUTO / NORMAL. OST-252, "RHR COMPONENT TEST",

(qucrterly) is being performed. RHR-744A (RHR loop to cold leg valve) will net operate by use of the RTGB control switch. The valve is fully stroked ccnuc11y'With no difficulty noted. A decision to leave the valve in the opOn posi' tion (position required for safeguards actuation) is considered.

W:uld this decision be acceptable? EXPLAIN.

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SECTION B LIMITS AND CONTROLS QUESTION 12 (1.00)

FRP-S.1 (Response to Nuclear Power Generation /ATWS) has been implemented du3 to failure of the reactor to trip on demand. Approximately half way through the procedure, the reactor operator reports that both reactor trip brockers are open, all control rods are f ully inserted and the turbine is tripped.*yhich action below would be the proper one to take at this time?

A) Return to EOP Flowpath-1, initial entry point.

B) Return to EOP Flowpath-1, entry point A C) Complete FRP-S.1 D) Reset SPDS then monitor Critical Safety Function Status Trees. If no RED or ORANGE conditions are encountered, return to EOP Flowpath-1, initial entry point.

SECTION B LIMITS AND CONTROLS QUESTION 13 (1.00)

Tha plant is being placed back on the line after an extended maintenance outage (34 days). Power level prior to shutdown was 100% for 106 days.

.Which ONE of the following power ramp rate limits is applicable?

A) 3% ped / minute B) 5% per hour C) 3% per hour D) 10% step increase followed immediately by a 3% per hour ramp

n SECTION B LIMITS AND CONTROLS

-QUESTION 14 (1.00)

Which ONE of the f ollowing is correct regarding usa of the MEL (minimum cquipment list)?

A) The MEL is not required in cold shutdown.

B) All at'tachments of the MEL must be completed if RCS is >= 200F C) The MEL verifies the availability of LCO (limiting conditions f or operation) equipment on a shift to shift basis.

D) The MEL verifies operability of equipment / instrumentation.

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SECTION B: LIMITS AND CONTROLS QUESTION 15 (1.00)

OST-005 "NUCLEAR INSTRUMENTATION POWER RANGE" is being performed. During tcsting of NI-41, EXCORE NUCLEAR DETECTOR CHANNEL 41, the "overpower trip high range" occurs at 107.5% but the bistable does not reset until the tost signal is reduced to 104.5%. Does this af f ect the acceptance of this OST7,. Explain your answer.

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SECTION B: LIMITS AND CONTROLS QUESTION 16 (1.50)

Tho plant is operating at 100% power steady state, all systems in AUTO /

NORMAL, No equipment is out of service. A fitting on the sensing line at PT-485

("B" main steam line pressure transmitter) is discovered to have a significant steam leak. The decision is made to take the transmi tter out of eGrvige,in accordance with OWP-SGP-8. Discuss any possible transient that may.dccur due to failing to adhere to precaution No. 1 on this OWP.

-SECTION B LIMITS AND CONTROLS QUESTION 17 (1.50)

For cach of. the f ollowing si tuations listed below, indicate YES or NO as to whether or not~it would require entry into AOP-023, "Loss of Containment Intcgrity".(plant status-is 100% power, steady state)

A.

Haalth. Physics personnel report that the outer CV personnel hatch has boen found unlocked, but closed.

B.

The inside Auxiliary Operator reports that he has discovered station air aligned to the CV.

C. A small CCW 1eak is discovered on the control rod drive mechanism fan cooler in the CV.

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SECTION B LIMITS AND CONTROLS QUESTION 18 (1.00)

A ccution at the beginning of FRP-H.1 requires RCS bleed and feed to be oterted at STEP 9 if ANY S/G wide range level decreases to less than 69 % C63 %3. Which item below is the basis for this caution?

A) Steps.1.through 8 deal only with diagnostic evaluation of the event and may be time consuming.

B) Steps 1 through 8 consi st of a "loop" that is difficult to exit from.

C) Wide range level is not calibrated (therefore not accurate) for

< 60 % C63 %J.

D) This l evel assumes S/G dryout is i mmi nen t and RCS bleed and feed must be started immediately for core cooling.

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SECTION B: LIMITS AND CONTROLE

-QUESTION 19 (1.00)

D3tcrmine the posting required for a room using the results of the g

f ollowing radiological survey:

1.

AIRBORNE ACTIVITY:

6.34 F.-9 uci/cc (Co-60) 2.

FLOOR d!1 EAR:

Beta-610 dpm/cm squared Alpha-4 dpm/cm squared

3. EQUIPMENT SMEAR: Beta-1800 dpm/cm squared; Alpha-16 dpm/cm squared 4

GENERAL HADIATION LEVEL:.110 mr/hr t-

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SECTION B: LIMITS AND CONTROLS QUESTION 20 (1.00)

HBR Unit #2 is at 100 % power with all control s in AUTO / NORMAL. You are notified by maintenance (I&C) that they intend to' perform maintenance on the level control system for "B"

auxiliary boiler condensate tank. They inform you that the circuit has been deenergized for a month by use of a non-safety,related wire removal. The tags are still in place. What would bo your rdsponse with regard to their compliance with clearance / wire removal procedures? Explain your answer.

SECTION B LIMITS AND CONTROLS QUESTION 21 (1.00)

'DSP-002 requires the Auxiliary Building Operator to manually close SI-864 A or B (RWST outlet i solation valves). Which item below is the purpose for this step?

A) This pr. events backflow from the CV sump to the RWST due to spurious valve operation B) Icolation of the RWST is required to prevent backflow # rom the RCS to the RWST through the i dle SI and Spray pumps.

C) Prevents draining the RWST to the CV sump due to spurious operation of CV sump isolation valves.

D) Prevents flooding the RHR pit due to imminent RHR pump seal failure.

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SECTION B: LIMITS AND CONTROLS QUESTION 22 (1.00)

Which ONE statement below is correct regarding REFUELING?

A) "uel movement in the CV is not allowed unless relative humidity is

<= 70 %

i fd) At lei t ONE RHR pump must remain in continuous operation.

C)' RCS boron must be veri fied >= 1950 ppm boron once per day.

D) The core fuel assemblies shall not be moved unless 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> have olapsed after shutdown.

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SECTION B LIMITS AND CONTROLS QUESTION 23 (1.00)

Which DNE of the below listed items would constitute an UNSAFE CONDITION cc defined in OMM-011,"Operational Response to Deliberate Acts Against Plent Equipment".

A)

"B" SI.. pump discharge valve locking device allows freedom of valve movement of 2 turns.

B) The breaker for HVS-1 (Auxiliary Building Supply Fan) air wash pump 10 found open.

C) The service water booster pump "Dil Reservoir Bowl s" are reported missing by the inside A.D.

D) The lock and chain on LO-12, lube oil storage tank drain, is found missing.

END OF SECTION B

1 SECTION B: LIMITS AND CONTROLS 8ANGWER 1 D.~C1.003

  • REFERENCE PLO-030,. LER 87-13, OMM-1 K/A 3.M/3.7 OBJ:

Week 3, 1987 Requal, OEF Items-OBJ #1 t

..~._.

SECTION B LIMITS AND CONTROLS

-* ANSWER 2 Using Att. 3.3 of DSP-003:

PZRLDackup group "B" heaters = 450 KW 453/100 =,,4.5

[0.503 From curve, 525 F and 1400 psig corresponds to approx. 0.116 (0.114-0.118)

( 4. 5) (0.116) = approx. 0.522 % (0.513-0.531) per minute [0.503

  • REFERENCE DSP-003 K/A:

4.2/4.3 OBJ:

ARP-LP-5, #1 8

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SECTION B LIMITS AND CONTROLS 4 ANSWER 3 Rscommend evacuation 0-2 mile radius CO.503 and shelter 0-5 miles downwind. [0.503

  • REFERENCE PEP-105,,Att. 5.4 K/A:

3.1/4.4 i

SECTION B LIMITS AND CONTROLS

  • ANSWER-4 A.

Classify as an ALERT CO.503

0. YES. A Saf ety Limit has been exceeded. C1.003
  • REFERENCE, TS Fig. 2.'1-1 PEP-101, Mod.

1, page 7 of 17 K/A 3.1/4.4 3.5/4.0 OBJ:

SRO-LP-55, # 2, SRO-LP-64, #3' I

SECTION B LIMITS AND CONTROLS

  • ANSWER 5 A.

3 CO.50]

D.

2 CO.50]

  • REFERENgE, HP-LP-20,.' PEP-301 K/A:

3.1/4.4 OBJ:

HP-LP-20, #2 l

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SECTION B LIMITS AND CONTROLS

  • ANSWER 6 A [1.003
  • REFERENCE OMM-22, EPP-1 K/A:

3.9/4.0

SECTION B LIMITS AND CONTROLS

  • ANSWER 7 D C1.003
  • REFERENCE OMM-G?10 K/A:
3. 7 /3. 9

SECTION B: LIMITS AND CONTROLS

  • ANSWER 8 B C1.00]
  • REFERENCE PROCEDURE CHANGE K/A:

3.4/3.9

~ - -

SECTION B LIMITS AND CONTROLS

  • ANSWER 9 S ction 3.0, Hot Shutdown in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> [1.003 (and Cold Shutdown in the next 30= hrs unless the condition is corrected or no longer applicable)

'K/A:

3.5'/4.2 3.6/4.2 OBJ PLR/SRO-LP-55, #1, PLR/SRO-LP-56, #1

SECTION B LIMITS AND CONTROLS

  • ANSWER 10 D [1.003
  • REFERENCE ARP-LP-1 through 9 K/A:

3.844.0

SECTION B LIMITS AND CONTROLS

  • ANSWER 11 This decision would not be acceptable. CO.503 RHR 744A also serves a function as a containment integrity isolation volve. Leaving the valve open, with no control, defeats the integrity icolatio(/ function of this valve. CO.503 OR ALTERNATE ANSWER OWP RHR-6 requires the valve to be closed f or maintenance. CO.503
  • REFERENCE OP-923; OWP RHR-6; IE NOTICE 86-38, Dual Function Valve Failures K/A:

3.1/3.9 OBJ:

DEF 1987, Week 1,

  1. 1

i 4

SECTION B LIMITS AND CONTROLS

  • ANSWER 12 C [1.003
  • REFERENCE OMM-022, page 13; EOP-LP-15, EOP-LP-W-A K/A:

4.1,[/4. 2

SECTION B LIMITS AND CONTROLS

  • ANSWER 13 C [1.00]

2.7f2.8 i

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SECTION B LIMITS AND CONTROLS

  • ANSWER 14 C C1.003

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SECTION Be LIMITS AND CONTROLS s

1

  • ANSWER 15 This would not affect acceptance of the OST. CO.503 The OST specifies that tha power reduction shoul d be approx i matel y 2*/.,

however, section 6 states that bistables loop width reset points are not to be included in the ccccptance criteria. [0.50]

  • REFERENCIE OST-005 K/A:

3.1/3.6

SECTION B LIMITS AND CONTROLS

  • ANSWER 16 If "FR-488" (steam flow selector switch) is selected to "484" (steam flow i

I trenemitter FT-484),the steam flow signal sent to the steam generator

- wntor level control system (SGWLC) will fall to minimum. CO.503 The SGWLC oystGm wi,1,1 respond by closing the feed water regulating valve.CO.503 A roactor.' trip will likely result.CO.503 (from SF/FF mismatch coincident with low S/G level on redundant nonaffected channel)

  • REFERENCE LER 85-017 K/A:

3.4/3.6 f

SECTION Br..LI,MITS AND CONTROLS

'8 ANSWER 17 A.

No B.

Yos

. C. ; No

[ three @ 0.50 each 3 4 REFERENCE

~ AOP-0233',OP-923 K/A:

3.0/4.1 PLR/SRO-LP-55, #1 4

1 I

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SECTION Be LIMITS AND CONTROLS

  • ANSUER 18 D C1.003
  • REFERENCE WOG Background Documents (FR-H.1)

K/A:

4. 4 /,.4. 6 3.6/3.6 l

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SECTION B LI,MITS AND CONTROLS

  • ANSWER 19 Rcom should be posted as follows:

- Airborne radioactivity area

- Contaminated process equipment area

- High radiation area

[ three 9 0.33 each 3

  • REFERENCG

.HPP-001 K/A 2.8/3.4 i

t l

SECTION B: LIMITS AND CONTROLS

$ ANSWER 20 Thsy should be informed that a wire removal is not to be used in lieu of a l ocal clearance CO.503, and they should obtain a clearance prior to working en the circuit. CO.503

  • REFERENCE OMM-012

/

K/A 3.7/4.1 s

i

SECTION B LIMITS AND CONTROLS

  • ANSWER 21 C [1.003
  • REFERENCE ARP-LP-2 K/A 3. 3 /.4. 1 OBJ:

ARP-LP-2, #3

(

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SECTION B: LIMITS AND CONTROLS

  • ANSWER 22 D C1.003 tREFERENCE TS 3.8.1 f

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SECTION B: LIMITS AND CONTROLS

,,, 4

  • ANSWER 23 C C1.003

2.5(3.4 OBJ:

AOP-LP-6A, #2

ENCLOSURE 3_

REQUALIFICATION PROGRAM EVALUATION REPORT Facility:

H. B. Robinson Steam Electric Plant Examiners:

C. Casto, W. Dean, R. Temps, D. Shepard, C. Rapp, M. Ernstes

. Dates of Evaluation:

December 14-17, 1987 Areas Evaluated:

.X Written X

Oral X

Simulator Examination Results:

R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S,M,orU)

Written Examination 4/0 4/0 8/0 S

Operating Test 3/1 4/0 7/1 S

Oral 4/0 _

4/0 8/0 S

  • Simulator 3/1 4/0 7/1 S
  • Unsatisfactory performance not identified by the facility. This data will be utilized during subsequent requalification examinations.

Evaluation of facility written examination grading Overall Program Evaluation

    • Satisfactory Marginal Unsatisfactory (List major deficiency areas with brief descriptive comments)
    • Insufficient number of operators to make a programmatic evaluation.

These results will be combined with the results of the next requalification examination.

Submitted:

Forwarded:

Approved:

Y W

E

/

N't t$t Charles Casto

/

John F. Munro

/

Caudle y JuliaC

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