Text

Exam Rept 50-320/86-12OL on 860903-05.Exam Results:All Candidates Passed & Issued Licenses
	ML20211C102
Person / Time
Site:	Crane
Issue date:	10/14/1986
From:	Coe D, Keller R, Kister H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20211C086	List: IR 05000320/1986012; ML20211C082;
References
	50-320-86-12OL, NUDOCS 8610210269
	Download: ML20211C102 (39)
	v • d • e

.

U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.

50-320/86-12(0L)

FACILITY DOCKET NO. 50-320 FACILITY LICENSE NO. DPR-73 LICENSEE: GPU Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 17057 FACILITY: Three Mile Island Unit 2 EXAMINATION DATES: September 3-5, 1986 CHIEF EXAMINER:

/

LU

/6 o!.%

,

D. Coe, Ledd Reactor Engineer (Examiner)

'Da te REVIEWED BY:

M [4

+

/~04 OM/[

W[8 Robert Keller, Chief, Projects Section 1C Date APPROVED BY:

/

/M Harry 7,is%r(Chief,ProjectBranchNo.1 Cater SUMMARY: Written and oral examinations were administered to three Reactor Operator candidates. All three candidates passed both portions of the examination and were issued licenses.

!!Bp2;gggggaggp V

-

.

REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:

l R0 l

l Pass / Fail l

I I

I IWritten Exam I 3/0 l

I I

10ral Exam I

3/0 l

I I

I i

10verall I

3/0 l

I I

I i

1.

CHIEF EXAMINER AT SITE: Mike King, EG and G Idaho 2.

OTHER EXAMINERS: None 3.

Summary of generic strengths or deficiencies noted on oral exams:

None noted.

4.

Summary of generic deficiencies noted from grading of written exams:

a.

Reasons why the end effector handling tool is water filled, b.

Basic principle of operation of the debris vacuum system flow meter.

5.

Personnel Present at Exit Interview:

NRC Contractor Personnel Mike King, EG and G, Idaho

l

'

.-

'

Facility Personnel Adam W. Miller, Manager Plant Operations William W. Thompson, Operator Training Manager Christopher J. Dell, Licensing Technical Analyst Ronald H Maag, Supervisor Licensed Operator Training 6.

Summary of NRC Comments made at exit interview:

The NRC Contractor Examiner did not give preliminary results of the oral examinations. However, he stated that these candidates exhibited marked improvement over the previous class of operator candidates.

Attachments:

1.

Written Examination and Answer Key (RO)

2.

Facility Comments on Written Examinations made after Exam Review and Examiner Responses to Facility Comments

(

!

Arrachmed i

..

,

.

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_IMI-2 REACTOR TYPE:

PWR-B&W177 DATE ADMINISTERED: 86/09/03 EXAMINER:

_ KING. M.

CANDIDATE:

Nk 5 MR IE11BMCIICES TQ_ CANDIDATE:

Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question.

The passing grade requires at least 70% in each categcry and a final grade of at least 80%.

Examination papers will be picked up six (6)

hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE_ _IRIAL SCORE VALUE CATEGORY 25.00-

_25.51 1.

PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 2s e0

_2s 31 S.

eLANT DESIGN INCLUD1No SAFETY AND EMERGENCY SYSTEMS

_25.00 25.51 3.

INSTRUMENTS AND CONTROLS

_02.20

_22.11 4.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_23 QQ__

Totals Final Grade All work done on this examination is my own.

I have neither given nor received aid.

_

Candidate's Signature

..

,

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

.

During the administration of this examination the following rules apply:

1.

Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2.

Restroom trips are to be limited and only one candidate at a time may leave.

You.must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3.

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

4.

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

5.

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

6.

Use only the paper provided for answers.

7.

Print your name in the upper right-hand corner of the first page of each

.

section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a agw page, write onlY 2n an2 side of the paper, and write "Last Page" on the last answer sheet.

G.

Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least thr22 lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

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

13. 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.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the graminer only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been complete _

..

,

19. When you complete your examination, you shall:

a.

Assemble your examination as follows:

'(1)

Exam questions on top.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer.

b.

Turn in your copy of the examination and all pages used to answer the examination questions.

c.

Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d.

Leave the examination area, as defined by the examiner.

If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke c-

,,

.

1.

PRINQIELES OF NUCLEag POWER ELANT OEEEAIIQHm PAGE

IHEEEDIE6MICS. HEAT TRANSFER AND FLUID FLOW

.

CUESTION 1.01 (1.00)

What TWO conditions must exit for suberitical multiplication to occur?

QUESTION 1.02 (2.00)

Explain the differences between slow (thermal) and delayed neutrons.

QUESTION 1.03 (1.00)

Boron is added to the RCS to absorb neutrons. What neutron energy level (fast, epithermal, or thermal) does boron " prefer" 7 QUESTION 1.04 (3.00)

Because of a misalignment of valves a dilution of the RCS begins. The only indication to the operator is the following source range indications from the logs.

Inspecting the readings yields:

Time 1200 1300 1400 1500 1600 1700 NI.1 1.25 1.25 1.47 1.79 2.22 2.97 a.

If the cause of the increase is not found when would (could) the reactor go critical. [1.5]

b.

If Keff of the core before the unplanned dilution was.7.

what was Keff at 1600. (1.5]

QUESTION 1.05 (3.00)

A variable speed centrifugal pump operating at 3600 rpm requires 250 horsepower to pump 100 gpm at 125 peig.

Suppose you change the pump speed such that discharge pressure is 75 psis.

What is the new SPEED, FLOW, and POWER (Show all formulas and work.) ?

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

,..

,

1.

EEINCIPLES OF NUCLEAR POWER _oLANT OPERATION.

PAGE

IHERMODYHAMICS. HEAT TRANSFER AND _ FLUID FLOW

.

QUESTION 1.06 (3.00)

Select one advantage and one disadvantage for each type of pump below.

PUMP a.

positive displacement b.

jet c.

centrifugal ADVANTAGE DISADVANTAGE 1. Ore ste in harsh environments.

1.

Low capacity.

3. Hig). flow rates.

2.

pump light fluids only.

3. Metered flow.

3. Additional piping

required.

QUESTION 1.07 (1.00)

Heat exchangers are designed to have turbulent flow : (choose the correct answer)

a.

To increase heat transfer.

b.

To reduce tube fouling.

.

c.

To prevent water hammer, d.

To reduce tube vibration.

(***** CATEGCEY 01 CONTINUED CN NEXT PAGE *****)

.

,

i

1, PRINCIPLES OF NUCLEAR POWER _ELANT OPERATION.

PAGE

IEEEMODYNAMICS. HEAT TRASSEER AND FLUID FLOW l

QUESTION 1.08 (3.00)

,

Identify each of the following temperature pressure pairs as sub-cooled, saturated, or superheated. (Assume water systems)

-a.

280 F, 34.5 psig b. 204 C, 232.3 psig c.

320 F, 105.5 psig d. 360 F,.

145.4 psig

[4 @ 0.75 ea.]

QUESTION 1.00.

(3.00)

a. Explain how insufficient ficw thru a pump can cause damsge to the pump. [0.0]

b. List a method of maintaining sufficient flow thru the pump. [1.0]

QUESTION 1.10 (2.00)

Explain why neutrons are best shielded by light materials and gammas are best shielded by heavy materials.

QUESTION 1.11 (3.00)

Describe HOW and WHY centrifugal pump discharge flew is affected by the each of the following.

a.

Suction pressure decreases, b. Throttling down on the discharge valve, c. An increase pump speed (RPM's).

(****+

END OF CATEGORY 01 *****)

r

.

2.

PLANT DESIGN IECLUD?NG SAFETY AND EMERGENCY FYSTEMS PAGE

.

QUESTION 2.01 (3.50)

Concerning the END EFFECTOR HANDLING TOOL a.

What design feature protects the hydraulic hoses from damage or entangling (0.5)?

b.

Why is the handling tool water filled (3 reasons) (3.0)?

GUESTION 2.02 (2.50)

List five different tanks that relieve to the waste gas relief header through relief valves.

QUESTION 2.03 (3.00)

List five end effectors AND briefly describe the use or function of each.

QUESTION 2.04 (2.00)

How and why is the BANDING TOOL used ?

GUESTION 2.05 (2.00)

What two design features prevent radiation streaming through the work platform of the Shielded Work Platform ?

QUESTION 2.06 (1.00)

What is the purpose (function) of the Debris Vacuum system ?

QUESTION 2.07 (1.00)

Why must loaded canisters be removed from the vessel through the canister removal port ?

(r****

CATEGORY 02 CCNTINUED ON NEXT PAGE

rt**)

..

.

2.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMR PAGE E

.

QUESTION 2.08 (1.50)

Name three scurces of electricity to the 230 KV Substation at TMI.

QUESTION 2.00 (2.50)

Draw a one'line diagram _of the normal RCS letdown to a RCBT.

(Include RCS connection, all major valves and equip, letdown flow instrument, and location of containment boundry)

QUESTION 2.10 (1.00)

After a station blackout occurs, when (time) AND how many NSRW pumps will start ? (Assume diesel generators auto-start normally)

QUESTION 2.11 (2.00)

Briefly describe the Bulk Defueling Phase that will be used after the "Early Defueling Phase." Include an overall description of the tools and description of expected core conditions.

QUESTION 2.12 (3.00)

A required action due to a leak in SDS is to secure the appropriate feed pump. For SIX of the SEVEN following SDS feed pumps (your choice),

list one location to stop (secure) each pump.

a. SWS-P-1 (RB jet pump)

I b. WDL-P-5A (RC waste transfer pump)

c. DWC-P-5 (DWC booster pump)

d. WDL-P-6A (Misc. waste transfer pump)

e. WDL-P-8A (Neutraliser tank pump)

f. FCC-P-1 (FTC deep end pump)

g.

SDS-P-1A (monitor tank pump)

(***** END OF CATEGORY 02 *****)

=. -

.

._.

..-

'

..

.

c

.

INSTF.UMENTS AND CONTROLS PAGE

3.

.

QUESTION 3.01 (2.00)

What is the purpose (function) of the 30 second timer in the NSRW control circuit AND why is it needed ?

!

OUESTION 3,02 (1.00)

The diesel generators'can operate up to a

without cooling water flow [1.0].

.

QUESTION 3.03 (1.50)

"

I List three systems or sub-systems that have liquid radiation monitors i

QUESTION 3.04 (2.00)

Match the following radiation instruments with the type (s) of radiation they are used to monitor.

INSTRUMENTS TYPES OF RADIATION a.

E-520 1. ALPEA b.

RO-2 2. GAMMA c.

PAC-6 3. BETA d.

PNR-4 4.

NEUTRON

,

(4 @ 0.5 EA.)

QUESTION 3.05 (2.50)

What are five'preoperational checks to be made prior to use of survey instruments 7 (5 @ 0.5 ea.)

'

QUESTION 3.06 (1.50)

Explain the method used to position the in-core monitor cameras.

(Include in your answer what is used to manipulate the cameras.).

(***** CATEGORY 03 CONTINUED ON NEXT PAGE

- - - - )

. - -.. - -.

.

-

-.

--.

-

...

.. -. - - !

=

.

PAGE

3.

INSTEUMENTS AND CONTROLS

.

QUESTION 3.07 (2.00)

Explain the basic principle of operation of the debris vacuum system flow meter.

QUESTION 3.03 (2.00)

a.

What is the purpose (function) of the sleeve locking device on the canister positioning system (CFS)?

b.

How is the sleeve locking device actuated ?

QUESTION 3.00 (3.50)

a.

List five alarms associated with the Debris Vacuum System [2.5).

b.

With the vacuum system in use, what common action should be taken upon

-

receipt of one of the above alarms [1.0]?

QUESTION 3.10 (2.00)

What two signals will automatically trip the hydraulic system pump ?

QUESTION 3.11 (3.00)

Describe the automatic actions which will occur as a result of an undervoltage on the IE bus due to a loss of all offsite power.

i i

I

'

QUESTION 3.12 (2.00)

The MDHR system is operating at a flow of 100 gpm through the debris filter in preparation for RCS cleanup operations via the SDS System.

Loose material from the RCS dislodges and completely clogs the MDHR filter.

List four indications available to you in the Centrol Room that would alert you to this condition.

!

.

(***** END OF CATEGORY 03 *****)

_

.

,

4.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE'

BADIOLOGICAL CONTROL

.

QUESTION 4.01 (.00)

e Question / answer / reference d'eleted from exam.

QUESTION 4.02 (2.00)

,

Explain why knockout canisters are loaded only at the 324' 11" elevation AND fuel canisters are loaded only at the 321' 0" or i

317' 0" level ?

QUESTION 4.03'

(2.00)

Concerning tho. fuel transf.er system:

a.

What are three prerequisites for carriage movement ?

[3 @ 0.33 ea.]-

b.

What are three prerequisites for upending a canister ?

[3 @ 0.33 ea.]

QUESTION. 4.04 (2.00)

What.must be performed prior to the addition of any hydraulic fluid to the hydraulic pump reservoir ?

<

QUESTION 4.05 (2.00)

What are the major differences between a TCN and a TCN-2 ?

QUESTION 4.06 (2.50)

List five documents that should be reviewed during the course of the shift per procedure 4210-ADM-3020.01, Conduct of Plant Operations.

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

,- -____.. - - - _

.

. -

_

. _ -

_ _ _.

- _ _. -.

-

,.

.

4.

FRCCEDURES - NORMAL APNORMAL, EMERGENCY AND PAGE

BADIOLOGICAL CONTROL i

.

i

,

QUESTION-4.07 (2.00)

Explain the following terms as they apply to a UWI.

!

a.

QC witness point [1.0]

b.

QC Hold Point [1.0]

,

QUESTION 4.08 (2.00)

The cancellation date of a TCN-shall not exceed a

from the date of the b

.

QUESTION 4.09

'(2.00)

A UWI-WRA requires a revision.

Under what provisions may work continue?

!

QUESTION 4.10 (2.00)

a.

What is required by procedure 4000-ADM-3240.01, Access to and Work in t

the Containment Bldg, to remove equipment from the containment [1.0]?

b.

Who's (position title) approval is required [1.0]?

'

QUESTION 4.11 (2.50)

List five indications of a leak in the SES per procedure 4210-EAP-3527.03, Leakage in the SDS Submerged Ion Exchanger.

!

QUESTION 4.12 (1.00)

Why is RCS sampling frequency increased if the IIF processing

system is in automatic control mode ?

!

(***** CATEGORY 04 CONTINUED CN NEXT PAGE *****)

.. -

..-

-

--.

-_--

'

4.

PROCEDURES - NORMAL, AENORMAL. EMERGENCY AND PAGE

RADIOLOGICAL CONTROL

.

GUESTION 4.13 (1.00)

If the diesel is started and cooling water is lost the operator must:

(choose the correct answer) [1.0]

a.

monitor diesel temp locally.

b.

trip the diesel.

c.

cperate the diesel at <= 50 % load.

d.

unload the diesel until cooling water flow is restored

.

s

.

(***** END OF CATEGORY 04 *****)

(************* END OF EXAMINATION ***************)

.

..

1.

PRINCIPLES OF NUCL_ EAR POWER PLANT OPERATION.

PAGE

ISERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW

ANSWERS -- TMI-2-86/09/03-KING, M.

,

ANSWER 1.01 (1.00)

1.

neutron source present [0.5]

2.

fissionable fuel present [0.5]

REFERENCE TMI-2 Lesson Plan #55, 11.2.01.179, pg 4 ANSWER 1.02 (2.00)

" Slow" refers to the energy level of the neutron.

A fast neutron that-has been thermalised[0.5].

Slow or thermal neutrons could have come from either instantaneous or delayed sources [0.5].

Delayed refers to neutrons that are not direct results of fission [0.5]but rather appear as a result of the decay of fission-products [0.5].

REFERENCE TMI-2 NET 2-12, pg 12.1-5 & NET 3-1 ANSWER 1.03 (1.00)

Thermal neutrons REFERENCE TMI-2 NET 3-1 pg 14-2

.

I h

I

..

.

1.

PRINCIPLES OF NUCLEAR POWER PLANT OPERATION.

PAGE

IHERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 1.04 (3.00)

a.

[0.75 for 1/m plot] [0.75 for answer]

1.0 q

\\

s 0.8

\\.

I

\\

I

0.s

\\

I N

.

m 0.4 g

N I

s

,

\\

'O.2

\\

'

0.0

14

1s

18

20-b.

crl/cr2 = (1-k2)/(1-ki)

[0.5 for formula]

1.25/2.22 = (1-k2)/(1.7)

= 1-k2

[0.5 for math]

.563 (.3)

.169 = 1-k2 1.169 = k2

.831 = k2

[0.5 for answer]

,

REFERENCE

,

~

TMI-2 NET 3-12, pg 12.2-1 - 12.2-3

.

,

g i

'1.

PRINCIPLES OF NUCLEAR POWER PLAMI OPEPATION.

PAGE

THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW

ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 1.05 (3.00)

(E = exponent,

~ = proportional)

SPEED N-E2

~- head

[0.33 for formula]

(3600-E2)/(x-E2)

=

125/75

[0.33 for math]

x-E2 = (3600-E2)(75)/125 x = 2788 rpm (new pump speed)

[0.33 for answer]

FLOW N ~ flow

[0.33 for formula]

3600/2788 = 100/x 1.292 = 100/x

[0.33 for math]

x = 77.4 gpm

'[0.33 for answer)

POWER N-E3 ~ power

[0.33 for formula]

(3600-E3)/(2788-E3) = 250/x 2.1529 = 250/x

[0.33 for math]'

x = 116 HP

[0.33 for answer]

REFERENCE TMI-2 Lesson Plan #52, 11.2.01.114, pg 44-46 ANSWER 1.06 (3.00)

a.-

1 b.

3

c.

2 (6 @ 0.5 ea.)

I

!

.,,

, _. _ _ _ _

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

, _ _ _ _. _,

__._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _.. _.. _ _ _ _ _. _ _

._

~

1.

PRINCIPLES CHF NUCLEAR POWER FLANT OPERATION.

PAGE

IHEEMODYNAMICS. HEAT TRANSFER AND FLUID FLOW

' ANSWERS -- TMI-2-86/09/03-KING, M.

REFERENCE TMI-2 #52, 11.2.01.114, pg 14, 23-25, 39 ANSWER 1.07

'(1.00)

a REFERENCE TMI-2 Lesson Plan #48, 11.2.01.047, pg 16-17 ANSWER 1.08 (3.00)

a.

saturated b.

saturated c.

sub-cooled d. super-heated

[4 @ 0.6 ea.]

REFERENCE Steam Tables ANSWER 1.09 (3.00)

a.

Heat is added to the fluid in the pump due to " pump work".

If the flow is insufficient to remove this heat then cavatation may result and cause damage to the pump components. Pump components (such as seals) may be damaged by heat / temp alone.[2.0]

b. A recire line to allow minimum required flow.

OR Maintain system flow greater than the minimum required flow.

[1 @ 1.0]

REFERENCE TMI-2 NET 4-6, Pumps and Fluid flowhermodynamics

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

..

.

-.

.

...

r

1,

' PRINCIPLES OF NUCLEAR PCWER PLASI OPERATIOHm PAGE

~

THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 1.10 (2.00)

Neutrons have no electrical charge and lose / reduce their energy by collisions.

Maximum energy is lossed with collisions with small/ light atoms. [1.0]

Gammas have neither mass or electrical charge and lose / reduce their energy thru gamma interactions with matter. This require a high density / heavy material to maximise the gamma interactions with the chield. [1.0]

REFERENCE TMI-2 NET 2-7, pg 7.4-1 ANSWER 1.11 (3.00)

.

a.

Pump flow decreases. AND/OR: As NPSH approches sero the pump cavitates, flow will fluctuate or go to sero.[1.0]

b. Flow decreases as the system resistance increases.[1.0]

c. Flow will increase as pump speed increases, i.e.

pump laws.[1.0]

REFERENCE TMI-2 NET 4-6, Pumps and fluid flo '

2.

PLAET DESIGN INCLUDIEG S&FETY AND EMERGENCY SYSTEMS PAGE

ANSWERS -- TMI-2-86/09/03-KING, M.

,

.

s ANSWER 2.01 (3.50)

a.

The hoses are inside the (3") tool se'gments. (0.5)

b.

1.

Prevent radiation streaming. [1.0]

2.

Make the tool more stable when in use. [1.0]

3.

Make the tool lighter (when out of the water) [1.0]

REFERENCE TMI-2 Lesson Plan #29, 12.2.01.145, pg 6.0 ANSWER 2.02 (2.50)

1. Reclaimed boric acid tank 2. Concentrated waste tank 3. Misc. waste hold-up tank 4. Spent resin storage tank 5. Aux. Bldg. sump tank 6. Reactor coolant bleed tank 7. Reactor coolant evap.

8. Waste gas decay tank.

(5 @ 0.5 ea.)

REFERENCE TMI-2 Lesson Plan #19, 12.2.01.093, pg 12-13

,

- -

..

.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE

.-

ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 2.03 (3.00)

1.

Single rod shears (vertical,horisontal)[0.30]. Used to cut single fuel rods [0.30].

(0.6)

2.

Parting wedge [0.30]. Used to separate core material for handling or easier vacuuming [0.30].

(0.6)

3.

Grippers (3 point and 4 point) [0.30]. Used to pick up odd shaped pieces [0.30]. (0.6)

4.

Heavy duty tong tool [0.30].

Used to grasp partial length fuel assemblies (from any two sides) [0.30].

(0.6)

5.

Spade bucket tool [0.30].

Used to scoop debris from the core to deposit it into a debris bucket (Fuel / Filter canister)[0.30].

(0.6)

6.

Clamshell tool [0.30].

Used to scoop debris from the core (like spade bucket) to deposit it into a debris bucket (Fuel / Filter canister)[0.30]. (0.6)

7.

Partial fuel assembly loading tool [0.30]. Used to pick up partial fuel assemblies (with upper end fittings intact) [0.30].

(0.6)

8.

Heavy duty shear [0.30].

Used to cut fuel' bundles to sises suitable for insertion into fuel canisters OR to remove end fittings [0.30].

(0.6)

9.

Grapple [0.30].

Used to lift end fittings for disposal OR move debris (to allow easier vacuuming) [0.30].

(0.6)

(5 of 9 @ 0.6 ea.)

REFERENCE TMI-2 Lesson Plan #29, 12.2.01.145, pg 7-10 ANSWER 2.04 (2.00)

HOW: Used to " band" (wrapistrap, tie,etc.) fuel bundles in the area of a (desired) cut.

Why: To keep the cut pieces wrapped in shape so they will fit into fuel canisters.

(2 @ 1.0 ea.)

...

-.. - - -

-

- - -.

- - - - - -

- _ - _ _ _ _.. - - - _.

. -. _ _ - -..,

-

_2. ' PLANT DESIGN INCLUDING SAFETY AND EMERGEHCY SYSTEMS PAGE

"

-

ANSWERS -- TMI-2-86/09/03-KING, M.

,.

REFERENCE-TMI-2 Lesson Plan #29, 12.2.01.145, pg 15 ANSWER 2.05 (2.00)

1.

The plates (3" SS shielding plates) are placed with the joints over " webs" (I-beam) when.possible [1.0].

2.

Joints, not over webs, are " stepped" [1.0].

REFERENCE TMI-2 Lesson Plan #30, 12.2.01.147, pg 14 ANSWER.

2.06 (1.00)

To remove particles [0.33] up to the sise of fuel pellets [0.33] from the core region [0.33].

REFERENCE TMI-2 Lesson Plan #-34, 12.2.01.155, pg 9 ANSWER 2.07 (1.00)

The cannister removal port is designed with extra radiation shielding specifically for canister removal.[1.0]

REFERENCE TMI-2 Lesson Plan #35, 12.2.01.156, pg 6 ANSWER 2.08 (1.50)

,

1.

Unit 1 generator output (Accept Unit 1 main)

2.

500 KV substation (Accept Auto-transformer i

3.

Middletown Junction Line 4.

Jackson Line (3 @ 3.5 ea.)

REFERENCE TMI-2 Elec. Diagram, Dwg 3002

!

..

.

2; PLANT DESIGN INCLUDING SAFETY AND EMEEGENCY SYSTEMS PAGE

ANSWERS -- TMI-2-86/09/03-KING, M.

.

ANSWER 2.09 (2.50)

^

-

.

-

v'

<>f*A

,

A 11 k i s v

"

><>

?<>) v

<

1.

RC5Re-P.1ApupsuctionQ.15]

9.

v376 (.15]

2.

VIA [.15]

10. 1100 (.1s]

-

E

-

3. vis [.15]

"- I151

.

4.

C.1A [.1s]

12. stock Orifice (.15]

s' c.s [.1s]

13-

'5 I'53 H.

Flow Inst. (.1s]

y s v2s (.1s]

G w v2A [.15]

15-

05 I'51 1*

N A

f s. contain nt (.15j 1s. vs (.15]

f

"

v v

v

\\

17. Acer [.11

.

REFERENCE TMI-2 DWG 2024, rev 29 ANSWER 2.10 (1.00)

The pumps will start in 21 sec ('+/- 3). [0.5]

2 pumps start (one in each loop). [0.5)

REFERENCE TMI-2 Lesson Plan #45, 12.2.01.175, pg 23 j

F

2.

PLANT DESIGN INCLUDING SAEETY AND EMERGENCY SYSTEMS PAGE

ANSWERS -- TMI-2-86/09/03-KING, M.

,

ANSWER !

2.11 (2.00)

The BDP will be used at-the completion of the early defueling phase.

The remaining debris will vary in thickness from O' to 6'and be fused together. The BDP tool will be heavy duty equipment to break up, fracture, cut or lift remaining fuel / material from the vessel.[2.0]

(Answer need not be verbatim to the above.)

REFERENCE TMI-2 Lesson Plan #46, 12.2.01.177, pg 4-5 ANSWER 2.12 (3.00)

a.

Near CN-PNL-1 or controller on east wall.

b. PNL9-C.R. or Rad, waste panel c. DWC-LCP-1 d. Radwaste panel c. Radwaste panel f. CN-PNL-1 (Fuel Handling Bldg.)

g.

Next to pumps and FHB east wall (347' elevation)

(6 @ 0.5 ea.)

REFERENC2 TMI-2 Proc. 4210-EAP-3527.02, pg 3 Lesson Plan for each system for pump control

-

~

3.

INSTRUMENTS AND CONTROLS PAGE

ANSWERS -- TMI-2-86/09/03-KING, M.

,

ANSWER 3.01 (2.00)

Automatically opens the discharge valve 30 seconds af'.er pump start [1.0].

Allows purging of air in the pump discharge through the vent / vacuum breaker to prevent water hammer [1.0].

REFERENCE TMI-2 Lesson Plan #45, 12.2.01.175, pg 20 ANSWER 3.02 (1.00)

2 minutes REFERENCE TMI-2 Lesson Plan 345, 12.2.01.175, pg 19 ANSWER 3.03 (1.50)

DC-R-3399 DHCCW loop a DC-R-3400 DHCCW loop b NS-R-3401 NSCCW SF-R-3402 Spent Fuel CN-RE-IXO4 SDS Ion Exchanger CN-RE-LC05 Leakage Containment ALC-RM-7 CC-T-2 influent (EPICOR II)

(3 @ 0.5 ea.)

(NOTE: Instrument designation not required, SYSTEM name is required)

REFERENCE 12.2.0'.070, pg 20 TMI-2 Lesson Plan 359,

ANSWER 3.04 (2.00)

a.

2 (gamma)

,

b. 2/3 (beta, gamma)

c. 1 (alpha)

d. 4 (neutron)

REFERENCE TMI-2 Lesson Plan #28, 12.2.01.143, pg 5-8

'

3.'

INSTRUMENTS AND CONTROLS PAGE-23 ANSWERS -.TMI-2-86/09/03-KING, M.

,

ANSWER 3.05 (2.50)

,

' 1.

CAL date check.

2.

Phycical inspection.

3.

Battery check 4.

Meter zero check 5.

Response time setting.

6.

Source check.

(5 @ 0.5 ea.)

REFERENCE TMI-2 Lesson Plan #28, 12.2.01.143, pg 9-11 ANSWER 3.06 (1.50)

The cameras are manually [0,5) positioned through the long handled tool slot [0.5] with (special) camera handling tools.[0.5]

. REFERENCE TMI-2 Lesson Plan #33, 12.2.01.152, pgG ANSWER 3.07 (2.00)

.The flow meter functions on the cooling effect [0.5] of water flow

~

[0.5] on a heated wire [0.5] changing the wires resistance [0.5].

REFERENCE TMI-2 Lesson Plan #34, 12.2.01.155, pg 23 ANSWER 3.08 (2.00)

a.

To lock the canister support sleeves to the CPS at the various (3)

levels [1.0]

b.

Manually, by a long handled socket tool.[1.0]

REFERENCE TMI-2 Lesson Plan #35, 12.2.01.156, pg 10

,

.*

.

INSTRUMENTS AND CONTROLS PAGE

3.

ANSWERS -- TMI-2-86/09/03-KING, M.

,

ANSWER 3.09 (3.50)

a.

1.

Knockout canisters wet weight high (>= 2343.5 lbs).

2.

Filter canister wet weight high (>= 2345.4 lbs)

3.

Filter canister dp high (>=38 psid)

4.

Knockout canister dp high (>=

14 psid)

5.

Backflush dp high (>=40 paid)

6.

Low flow (<

60 gpm)

(5 @ 0.5 ea.)

b.

If an alarm is received, cease vacuuming operations. (by " pulling the nossle up") [1.0]

REFERENCE TMI-2 Lesson Plan #34, 12.2.01.155, Precations & limits (4.6.2)-

ANSWER-3.10 (2.00)

1.

Low fluid level [1.0]

2. Suction line valve position (closed) [1.0]

REFERENCE TMI-2 Lesson Plan #38, 12.2.01.159, pg 12 ANSWER 3.11 (3.00)

1.

Upon UV, Bus Sheds. loads 2.

Normal supply breaker opens

.

3.

Alternate supply breaker closes.

4.

Diesel generator starts.

5.

Alternate breaker opens.

6.

Diesel generator breaker closes.

7.

Commence sequence loading.

REFERENCE TMI-2 Lesson Plan #5, 12.2.01.020, pg 5 &_ figure (no page no.)

F

.

,

3.

INSTRUMENTS AND CONTROLS PAGE

ANSWERS -- TMI-2-86/09/03-KING, M.

,

ANSWER 3.12 (2.00)

a.

High dp alarm on filter (>65 psid)

b.

System low flow indication c.

System low flow alarm (<80 gym)

d.

MDHR pump low suction pressure indication e.

MDHR pump low suction pressure alarm (<16 psig)

f.

MDHR pump lcw discharge pressure indication

.

(4 @ 0.5 ea.)

REFERENCE TMI-2 Lessen Plan #13, 12.2.01.063, Sec A, Control & Instrumentation, pg 25

e

,

,,

.

'4.

MOCEDURES - NORMAL, ABNORMAL uEMERGENCY biR PAGE

RADIOLOGICAL CONTROL

.

' ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 4.01 (.00)

'

Question / answer / reference deleted from exam.

REFERENCE Question / answer / reference deleted from exam.

ANSWER 4.02 (2.00)

1.

The connections to the vacuum system are only at the 324' 11" elevation.' Knockout cannisters must be connected to the vacuum system [1.0].

2.

Fuel canisters are loaded at the 321' and 317' elevations due to shielding reasons [1.0].

REFERENCE TMI-2 Lesson Plan #35, 12.2.01.156, pg 7 ANSWER 4.03 (2.00)

a.1. The carriage control switch must be in the on position.

2. Transfer tube gate valve must be open.

3. & 4. Reactor building a fuel handling building upenders must be in the frame down position.

5. & 6. Reactor building & fuel handling building latches must be engaged.

[3 @ 0.33 ea.]

b.1. Carriage and upender must be properly aligned in the indexed position.

r 2. Winch brakes must be engaged.

3. Basket latch must be disengaged i

4.

Low hydraulic alarm cleared.

[3 @ 0.33 ea.]

REFERENCE TMI-2 Lesson Plan #37, 12.2.01.158, pg 17

.

-. -.

,,

-.. ~ -.

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

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

.,__,,.,,,,__,_,_._..._,,m_.

....

-

c-

.:

-

.

4.

PROCEDURES NORMAL. ABNORMAL. EMERGENCY AND PAGE

EADICLOGIfdL CONTR0L

_

.

ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER 4.04 (2.00)

All hydraulic lines, fittings, hoses, valves, pumps, gauges &

couplings must be inspected for looseness.

All fragile parts such as gauges, hoses and couplings must be inspected for damage such as cracks or distortion.

'This must include the hydralic tools on the SWP [1.0].

All additions of APPROVED hydraulic fluid to the hydraulic system must be AUTHORIZED by the FHSRO (and the amount of that fluid added recored in the FHSRO log.)[1.0]

REFERENCE TMI-2 Lesson Plan #38, 12.2.01.159 pg 14 ANSWER 4.05 (2.00)

A TCN may change the intent of a procedure (and a TCN-2 may not) and has to complete the full review, concurrence and approval requirements prior to implementation. A TCN-2 requires fewer (usually 4) signatures prior to implementation amd has 14 days to complete review and approval requirements.

REFERENCE TMI-2 Admin proc. 4000-ADM-3000.01, pg 12 ANSWER 4.06 (2.50)

a.

Active tagging book b.

Locked valve book c.

Surveillance schedules d.

TCN book e.

SOP book f.

Operations memo book g.

Revision Review Book (5 @ 0.5 ea.)

r

~

4.

PROCEDURES - NQE. MAL, ABNORMAL, EMERGENCY AND PAGE' 28

BADIQLQQICAL CQNTROL

ANSWERS -- TMI-2-

-86/09/03-KING, M.

REFERENCE

.TMI-2 Admin proc. 4210-ADM-3020.01, pg 4 ANSWER 4.07 (2.00)

a.

QC Witness Points may be intentionally deleted, by passed, or inserted at the option of the QC Supervisor.

Activities may continue provided QC was notified of the time to witness and is not present at the start time [1.0].

b.

QC Hold Points may not be by passed or deleted without documented

~

justification and the approval of the QC Manager.

The GC Inspector's signature on the UWI indicates satisfactory completion of the specific step (s) that the Hold Point addresses and permits the activity to proceed [1.0].

(Answers need not be verbatim per above.)

REFERENCE TMI-2 Admin proc. 4000-ADM-3000.01, pg 16-17 ANSWER 4.08 (2.00)

a.

90 days b.

Responsible Supervisors signoff REFERENCE TMI-2 Admin proc. 4000-ADM-3000.01, pg 16 ANSWER 4.09 (2.00)

Work not affected by the revision may continue [0.5] provided the planning group indicates to the work supervisor [0.5] the portions of the UWI that may and may not be worked [0.5] and the work or steps deferred as a result of the revision is/are clearly not a prerequisite or sequence dependent to the continued work or steps [0.5].

OR~

Work may be stopped or conti.'.ued as. directed by the Work / Shift Supervisor

-

.. -

n:

-

~

4 '.

PROCEDURES'- NORMAL. ABNCRMAL, EMERGENCY AND PAGE

BADIOLOGICAL_g2NTROL

-

ANSWERS -- TMI-2-86/09/03-KING, M.

REFERENCE.

TMI-2 Admin proc. 4000-ADM-3000.01, pg 19-20 ANSWER 4.10 (2.00)

a.

A containment transfer record is required to be completed [1.0].

b.

Radwaste engineer approval (Accept Shift Supervisor, Fuel Handling Shift Supervisor, Rad Con Engineer or Radwaste engineer)[1.0].

REFERENCE TMI-2 Admin proc. 4000-ADM-3240.01, pg 3.0 ANSWER 4.11-(2.50)

.

1.

Visible leak 2.

Unexplained change in receiving tank level rise 3.

Unexplained pressure decrease / loss on system gauges 4.

loss of system flow indication.

5.

Unexplained increase on radcon instruments CN-RIT-LCOS (in containment)

RC a'rea or IX manifold area aux bldg. vent fuel handling vent.

SDS vent cation effluent (NOTE: each of these is a separate indication of a leak.)

6.

Unexplained increase in "B" spent fuel pool level.

7.

Unexplained increase in off-gas separater tank level (5 @ 0.5 ea.)

REFERENCE TMI-2 Admin proc. 4210-EAP-3527.03, pg 2-3 ANSWER 4.12 (1.00)

To detect any inleakage that could cause an undetected deboration of the RCS.

REFERENCE TMI-2 Lesson Plan #26, 12.2.01.136, pg 26-32

r

4.

EBOCEDUPES - NORMAL. AENORMAL. EMERGENCY AND PAGE

BA2JfQLOGICAL CONTROL

-

ANSWERS -- TMI-2-86/09/03-KING, M.

ANSWER-4.13 (1.00)

b.

(trip the diesel)

REFERENCE TMI-2 Lesson Plan #45, 12.2.01.175, pg 19

/

r

.

-a

..

ATTAC RM E N Y 2.

-

.

Resolution to Facility Comments on NRC R0 Operator Licensing Exam of 9/3/86.

Facility comment on question / answer 2.02:

Allow facility abbreviations Reclaimed boric acid tank - RBAT Concentrated waste tank - CWST Misc. waste hold-up tank - MWHT-Spent Resin storage tank - SRST (2)

Aux. Bldg sump tank - ABST Reactor coolant bleed tank - RCBT or RCBHT (3)

Reactor coolant evap. - RC Evap.

Waste gas decay tank - WGDT (2)

Examiner resolution:

Agree, per guideline 12 (NRC rules, guideline for license examinations) provided with exam, commonly used abreviations are permitted.

Facility comment on question / answer 2.08:

In answer part i do not accept aux. transformers. (main is okay)

.In answer part 2 allow auto-transformer in place of 500 Kv.

Refereence dwg 3002.

Examiner resolution:

Agree, per supplied marked-up print.

Unit 1 aux transformer deleted from answer 1 and changed answer 2 to

"500 Kv substation (500/230 Kv auto transformer).

Change does not affect question point value.

.

Facility comment on question / answer 2.12:

FCC-P-1 CN-PNL-1 (answer to CAF)

Reference TER 3527-006 App. No. 3 Examiner resolution:

Agree, supplied answer from Reference material incorporated as answer to part "f".

. -

-

.

- ---- -

-

- -

.

_ - _. -.

_ _. _ _. _ -.- - - - _ - _ _

_ _ _. -_-_..

r-

,

.

a

.

Facility comment on question / answer 3.03:

SE-R-3402 Spent Fuel (answer to CAF)

Add the following possible answers:

CN-RE-IX94 SDS Ion Excahnge Reference L.P. 12.2.01.132 p. 9.0 CN-RE-LC05 Leakage Containment Reference L.P. 12.2.01.132 p. 8.0 ALC-RM-7 CC-T-2 influent Reference L.p. L2.2.0L.023 Examiner resolution:

Agree, SF-R-3402 name incorporated into answer and 3 liquid monitors added to answer key. -Neschange does not affect question point value.

Facility comment on question / answer 3.09:

In answer parts 2 and 3, " fuel" should be " filter".

Examiner resolution:

Agree, fuel changed to filter.

Facility comment on question / answer 4.01:

The referenced evolution was never utilized and the lesson plan should be deleted. Some other answers should be added to the key.

possible answers about procedure requirements to prevent draining or recognize draining of the IIF follow:

Monitor RCS level periodically.

Reference 4210-0PS-3200.02 Step 4.1.4.1 Perform Reactor Coolant isolation checklist every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Reference 4210-0PS-3200.02 Step 4.2.6 Independent verification of valve lineups Reference 4210-0PS-3200.02 Step 4.2.9 Examiner resolution:

Agree, information supplied during exit meeting explained the procedure was a contingency procedure and never implemented during the IIF installation and fill. The question is deleted and section 4 reduced to 23 points.

Facility comment on question / answer 4.04:

v t e Inspection Report - Crane - 1986012
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1986 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 15(0) 16(0) 7(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 20(0) 21(0) 22(0) 23(0) 24(0) 98(0) 99(0) 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 15(0) Security Operator Exams Emergency Planning Other

IR 05000320/1986012

Text

Navigation menu

Search