ML20212H089

Exam Rept 50-237/OL-87-01 on 870126-27.Exam Results:Two Senior Reactor Operators & One Reactor Operator Passed Exams & One Reactor Operator Candidate Failed Written Portion of Exam.Exam & Answer Key Encl

ML20212H089
Person / Time
Site:	Dresden
Issue date:	03/02/1987
From:	Bishop M, Burdick T, Clark F, Dave Hills NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20212H073	List: ML20212H067 ML20212H089
References
50-237-OL-87-01, 50-237-OL-87-1, NUDOCS 8703060016
Download: ML20212H089 (107)

Text

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U.S.-NUCLEAR REGULATORY COMMISSION REGION III

Report No.iS0-237/0L'87-01 Dockets No. 50-237; 50-249- License Nos. DPR-19; DPR-25 Licensee

Commonwealth Edison Company Post Office Box-767 LChicago, IL 60690 Facility Name: Dresden Nuclear Power Station 2 Examination Administered At: Dresden Nuclear Power Station Examination. Conducted: January 26-27, 1987 Examiners: D. Hills hMf9 I

pr 9/c M y

-M.: Bishop S/Mf7 Date F. Clark- 8 7 Date ~

- Approvcd By: T. M. Burdick, Chief- 'D Operator Licensing Section Date

< . Examination Summary Examination administered on January 26-21 1987 iRyortNo. 50-237/0L 87-01 Written examinations were acmiiiEtered to tiB_enior% actor 'Ofe candidates and one Reactor Operator (RO) candidate. In addition, an oral examination was administered to one additional RC candidate.

Results: Two SR0 candidates and one R0 candidate passed these examinations.

The remaining RO candidate failed the written portion of the examination.

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0703060016 870302 PDR ADOCK 05000237' V PDR_

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' REPORT DETAILS

1.  : Examiners '

~D. Hills - Chief Examiner M. Bishop

.F. Clark-

2. Examination Review Me'e_t_ing _

Specific facility comments concerning written examination questions, followed by the NRC response, are enumerated in the attachment.

3. Exit Meeting

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At the conclusion of the examinations, an exit meeting was conducted.

.The following personnel attended this exit meeting.

Facility _ Representatives _

E. Eenigenburg, Station Manager

.R. Flessner, Services Superintendent

.J. Wujciga, Production Superintendent B. Zank, Training Supervisor R. Stols, Q. A. Engineer NRC Representatives .

T. Burdick, Chief, Operator Licensing Section D. Hills, Operator Licensing Examiner R. Lanksbury, Operator Licensing Examiner J. Bjorgen, Operator Licensing Examiner F. Clark, Operator Licensing Examiner E. Hare, Operator Licensing Examiner M. Bishop, Operator Licensing Examiner L. McGregor,- Dresden Senior Resident Inspector As requalification examinations were administered concurrently with these replacement examinations, discussions concerned requalification program evaluation guidelines, criteria, and responses, as well as, specific

-requalification examination concerns.

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ATTACHMENT FACILITY C041ENTS AND NRC RESOLUTIONS FOR DRESDEN STATION OPERATOR EXAMINATION JANUARY 26, 1987 t

_ Question:

R0 Requal .

- 1.0lb R0 Replacement - 1.03b SR0 Replacement - 5.03b Facility Coment:

Answer key states that the mode of heat transfer from the fuel pellet to the -

cladding is conduction. The listed reference states " convection." However, this concept of heat transfer across the gas filled gap between the pellet and clad has been a point of discussion in the past. The mode would be considered conduction if the gaseous area were completely stagnant, but would be considered convection due to the pure definition of convective heat transfer.

This question was used on the Dresden Requalification Exam of.1986 test No. 2, in which the answer key allcwed either conduction or_ convection as an acceptable answer. Dresden requests that either answer be accepted for this exam since each answer is correct. (See attached reference)

NRC Resolution:

Coment is valid. Answer key will be changed to accept convection or conduction. Point value remains unchanged.

Question:

R0 Requal - 1.04a SR0 Requal - 5.02a SR0 Replacement - 5.06a R0 Replacement - 1.06a Facility Cement:

This question was apparently written to be simple in nature, but actually is vague and misleading. Control red worth is a function of themal neutron flux; however, this staterrent is incceplete. As explained by the Dresden Exam Bank question / answer Ho. 12-020317, page 27:

...As power is increased, the flux also increases, this actually has no effect on the worth of the rod unless the local flux is increased rr. ore than the core average. This explanation was also used on Dresden initial NRC license examinations:

5/24/83 question 1.03 and 5.05 and 6/25/84 question 5.03. Due to the question being misleading and incomplete, Dresden requests that either True or False be acceptable. (Seeattachedreference)

NRC Resolution: Comment is not valid. The referenced question 12-020317 is in regard to the differential worth being "0NLY" dependent on the local flux. This question neither states nor implies this is the case but only that the CRW is a

" function" of local flux, which is true. The answer key remains unchanged.

Question:

! R0 Requal - 2.05 R0 Replacement -

2.07 Facility Comment: There is an additional acceptable answer due to operational experience. Operating with excessive number of RBCCW ptros could raise RBCCW system pressure above the service water L

pressure and therefore defeat the design purpose of the l

RBCCW system. (See attached reference) i NRC Resolution: Comment is valid. It would be reasonable to expect this l

response from an operational point of view. This answer will be added to the answer key as a possible correct answer. Point value remains unchanged.

Question:

R0 Requal -

2.07 R0 Replacement -

2.12 Facility Comnent: There is an additional acceptable LP answer: Make-up tc the Condenser Hotwell, Gland Seal Steam Loop Seal Fill, and Condensate Demineralizer Resin Transfer System. The answer key references the lesson plan for its list. The lessor plan is not the controlling document for operation. These additional answers should be acceptable due to the fact that it displays a knowledge of the system and interrelations 5ips.

(See attached reference)

MRC Resolution: Comment is partially valid. The make-up to the Hotwell is from the " Condensate Make-up Pumps" which only start whe, the " Emergency Makeup Valve" OPENS and are separate fror the Condensate Transfer System referred to in the question.

This answer will not be added. The other two suggested answers are correct per P&ID's M-27, M-40, and M-35 and will be added to the answer key as possible correct answers.

Point value remains unchanged.

l Question:

R0 Requal -

2.09a f - 2.15a R0 Replacement 2

. Facility Comment: Additional acceptable answers: 125 VDC and Permanent Magnet Generator LP (PMG) (See attached reference)

NRC Resciution: Coment is partially valid. The answer key is wrong since the question asks for the " NORMAL" power supply for EHC Electronics which is the PMG. The answer key will be changed to "PMG" as the correct answer. The point value remains the same.

The other suggested answers are redundant power supplies and as such are unacceptable for credit.

Question:

R0 Requal -

2.09e R0 Replacement -

2.15e-Facility Comment: Check at facility: Answer is Essential Service Bus (See attached reference)

NRC Resolution: Ar.swer verified per D0A 6800-1, Rev. 3 page 5 of 8. This will be added to the answer sheet as the acceptable response.

Question:

R0 Requal -

3.06 R0 Replacement -

3.10 SR0 Replacement -

6.12 SR0 Requal - 6.08 Facility Comment: Additional acceptable answer: Manual operator action is a trip available to the operator (placing the control switch in pull-to-lock, PTL)

Question is vague to the point that it does not mention how many trips are required for full credit. Additionally, since setpoints were not required, Dresden recuests that "overcurrent" be accepted as a complete answer for " instantaneous and time delay overcurrent".

1 NRC Resolution: Corrnent is partially valid. A MANUAL TRIP is available to the operator and will be added to the answer key as a re-quired correct response. The question point distribution will now reflect four responses instead of three (4 at 0.25 each).

The question is not vague as it quite plainly asks for the trips. Although the number of responses required were not specified it is assumed that this will not be a problem for the operators since Dresden's Exam Bank has numerous examples of questions where this is not specified. For example:

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12-020153 12-020168 12-020157 12-020114 However, for future use of this question the number of responses will be specified.

Question:

R0 Requal -

3.07a R0 Replacement -

3.12a Facility Comment: The question and answer key is written to determine the examinee's knowledge of the level setpoint reduction feature on a scram and from that standpoint the answer-key is correct. However, the wording of the question is vague, and several examinees took a "real world" approach to the answer.

Operational experience has proven that a scram at high power will result in a Feedwater Pump auto trip on high level (+55"). This occurs due to leak-through of the Feedwater Regulating Valves and the fact that the Feed Pumps are not required to be manually tripped. The interpretation of steady state as written in the question is also vague and could afffect the examinee's interpretatfor, of the question. " Steady state" could be interpreted to be a few minutes to a few hours or longer.

i NRC Resolution: Comment is partially valid. It is understandable for operators to take "real world" approaches to problems and respond accordingly. Credit will be given if the "real world" answer is given with an explanation of what should l

have happened. However, the question is not vague as plant

f conditions are clearly set out and steady state is defined

! as "after scram" in the text of the question. The answer key remains unchanged.

l Question:

R0 Requal -

3.07b R0 Replacement -

3.12b Facility Comument: This question is vague. The expected answer is "The master l

controller dual setpoint current output is returned to normal l

when the scram is reset". The question asked "what action is

! required by the operator to return vessel level to the master controller?" In the phrasing of the expected answer, vessel level was never lost from the controller, just reduced.

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This question could have been gnterpreted such that 6duc to feedwater flow at 12.5 x 10 (setpoint 11.2 x 10 ),

the runout flow controller had-taken' over. Considering-this, the action required by the operator to return vessel -

level to the master controller would'be resetting of the runout relay using the pushbutton. (See attached reference)

WRC Resolution: Comment is partially valid. The questio, is.not vague but the answer is incorrect. Further analysis of the interaction of the master controller and run-out controller indicates that no operator action would be required.to return vessel' level control to the master controller. However, the question implies some operator action is require'd. Therefore, the answer key will be changed to accept either of the following:

"No operator action required" or " Depressing the run out rela'y rest pushbutton." Point value unchanged. Verified by Lesson '

Plan Book 2 Chapter 6 Page 9-10 & 11.

Question: '.

R0 Requal -

3.08 l R0 Replacement -

3.14 Facility Comment: Answer key is incorrect: 2301-8 would be closed: The 2301-8' I.

(discharge to the vessel) would not have been open during the full flow test. Therefore,.it would remain closed after the turbine is manually tripped. (See attached reference)

NRC Resolution: Coment is valid. Answer key will be changed to CLOSED for

, part D. Verified by Table 1 of HPCI L.P. BK-3 #10 Table 1,.

1 pp.29 Section F.2.c.(b) and Figure 1. Point value remains ,~

unchanged.

Question:

R0 Requal -

4.03 R0 Replacement -

4.06 SR0 Replacement - 8.06c, 8.06d, 8.13 and 8.14 SR0 Requal -

8.04c and 8.04d Facility Commsent: Dresden considers this question to be inappropriate. We do not require or expect our operators.to commit the steps of' Operating Orders to memory unless they are immediate operstor actions. '

NRC Resolution: Comment is not valid. The operating orders referenced in this cossnent, such as 29-86, 38-86, and 39-86 are not in the form of procedural steps but rather in the form of

" General" or " Specific" CAUTIONS which must be observed l

by the operators during the performance of their atsigned

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.s r-duties. Since there was no documentation furnished to show that the procedure the operator would be using referenced or directed the operator to the Operating Orders the only I method of complying with them is to " Remember" that they are in place. The answer key remains unchanged. Procedure DAP 7-3 Rev. 5, OPERATING ORDERS, specifically discourages

'9 the use of procedural steps (Section* 2.a.) in operating orders.

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e i Question:

R0 Requal - 4.06

, R0 Replacement -

4.10

/ ,

Facility Comment: Dresden considers tm nuestion to be faappropriate. To correctly answer this question requires memorization of a particular list contained in a precaution of a normal

,; T" procedure (DOP 5670-1). This is contrary to the examir.er's standard (ES-202) which states the candidate is not expected to have normal procedures comitted to memory tut should be

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able to explain reason, cautions and limitatio. s. *

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In addition, this question does not conform to the Dresden Station Requalification Program Objectives. (See attached reference) , , ,

NRC Resolution: Comment is not valid. No copy of the Dresden Requalification 4 .

Program Objectives was supplied so no resolation can be made i to this portion of the Facility Coment.

The candidates are not required to respond word-for-word in accordance with the answer key to receive full credit. The requirements for tripping EGC in D0P 5670-1 are general l_ . conditions and not generally specific events. Candidates R: would be given credit for answering with specific instances covered by Abnormal and Annunciator Procedures in the

, Immediate Operator Actions Secticns. To make this clear the answer key will be modified by adding the following i l ;- statement: "Will also accept specific events requiring

~ - the unit be removed from EGC". The following procedures are examples of DOA's with Imediate Operator Actions requiring the unit to be removed from EGC:

'1. DOA 040-2 Localized Flooding in Plant Step C-4

- 2. DOA 202-1 Recirc Pump Trip Step C-1 e 3. D0A '300-5 Inop or Failed'CR's Step C-1 1 -4. D0A 300-6 RPIS Failure Step C-1

5. DOA 3300-2 Loss of Condenser Vacuum Step C-1

6. 00A 5650-3 Turbine Control Valve or Bypass Valve Failed Open -

Step C-4b

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t Question:

R0 Requal - 4.09 '

R0 Replacement - 4.16 SRO Requal - 7.10' Facility Comment: Dresden considers this question to have an inappropriate assignment of point value. This one question is worth 19% of the section.

Additionally, the question is incomplete regarding the expected response. The question asks for immediate operator actions for each unit upon a loss of 125 VD;.

It does not specify which unit has experienced the loss of 125 VDC. The specified D0A 6900-2 is for the loss occurring on Unit 3. DOA 6900-3 concerns the loss of 125 VDC for Unit 2. Operators are not required to have all procedure designation numbers memorized, therefore, immediate actions referenced in DOA 6900-3 should be allowed as additional acceptable answers.

NRC Resolution: Comment is partially valid. The question point value is within the constraints of the Examiner Standards and will remain at its present value.

It is reasonable to expect that the operators would r.ot know which unit is addressed by DOA 6900-2 and may include the actions for either or both units loss of 125 VDC power.

Full credit will be given if the Unit is specified and the correct actions listed. For future'use of this question the procedure title will be added so there is no misunder-standing of the intent of the question.

l Question:

SR0 Requal - 5.04 SR0 Replacement -

5.09 l~

Facility Comnent: Additional acceptable answer: Equalize control rod exposure.

l (See attached references)

NRC Resolution: Comment is valid. This answer is included in the " Control Rod Blade and Drive Mechanism" Lesson Plan Section E.1.b.3.d.

l but not in the " Reactor Physics Review" Lesson Plan the l

question was generated from. The answer key will be changed l

to include " Equalize Control Rod Exposure" as an acceptable answer and the notation "Any 2 at 0.75 .each" will also be added.

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Question:

SR0 Requal -

5.08b SR0 Replacement -

5.13b Facility Comment: Answer could also be "Yes". Dresden requests that the candidate's response and explanation be graded on its correctness, not solely by the expected response in

'the answer key.

NRC Resolution: Comment is valid. The following notation will be added to answer key: "Will also accept YES if proper explanation is included." For future use of this question it will include a note that the cooldown is terminated after 30 minutes.

l_ Question:

SR0 Requal -

6.01b SRO Replacement -

6.0lb Facility Comment: Additional acceptable answer: Unexplained increase in Isolation Condenser side water level. (See attached reference)

NRC Resolution: Comment is valid. This answer is provided in DOA 1300-1 i Revision 4, Isolation Condenser Tube Leak, Section A.4.

and not in the referenced document the question was generated from. The following will be added to the answer key as an acceptable answer: "7. Unexplained increase in Isolation Condenser side water level." Point value remains the same.

Question:

l SR0 Requal -

6.03c SR0 Replacement -

6.03c l

Facility Comment: Additional acceptable answer: To prevent violation of the RPS design (failure of one component or power supply will neither cause nor prevent a scram). (See attached references) l NRC Resolution: Comment is valid. This answer will be added to the answer key

! as a required correct response. The point distribution will be changed to (0.25) each for each of the two responses. Total point value remains the same. Verified by Lesson Plan, A/C Electrical Distribution System Revision 7 Section E.5.a.2) 8 1'

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i Guestion:

SRO Requal -

6.04a SRO Replacement -

6.05a Facility Comment: Additional acceptable answer: The list contained in 3e answer key is correct. However, it is a list of conditions which automatically cause a " lock-up". Manual operator action is an additional condition which will cause a " lock-up".

(See attached references)

IstC Resolution: Comment is valid. " Manual actuation" will be added to the answer key as an acceptable response. Point value remains the same. Verified per 00P 202-12 Revision 3 Section F.1.a and F.1.b.

. Question:

SRO Requal - 6.06 SRO Replacement - 6.09 Facility Comunent: Additional acceptable answers: 1) Main Steam line drain

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valves close, 2) Recirculation loop sample valves close,

3) Isolation Condenser vent valves close, 4) Scram valves open. (See atteched references)

NRC Resolution: Comment is valid. Verified by Lesson Plan Book 3 Chapter 16 Table 1, ISOLATION GROUPS - VALVE CLOSURES and Lesson Plar Book 3 Chapter 12 Section F.3.c, Isolation Condenser. These additional answers will be added to the answer key as possible correct responses. Point value remains the same.

Question:

SRO Requal -

7.01 SRO Replacement -

7.01 Facility Consnent: Dresden considers this question to be inappropriate. To correctly answer this question requires memorization of j

j a particular step within the text of an emergency proced'-e I

(DEOP 100-2). This step is not an immediate action. This 1s contrary to the examiner's standard (ES-402) which states l

the candidate should be able to describe generally the i

objectives and methods of emergency operating procedures.

Additionally, this question does not conform to the Dresden Station Requalification Program objectives.

NRC Resolution: Coment is valid. This question will be deleted from the l exam and the point value edjusted accordingly.

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, a Question:

SR0 Requal -

7.08 SRO Replacement - 7.12 Facility Comment: For the examiner's information: High end of the Narrow Range Instrument is +60". (See attached references)

NRC Resolution: This will be added to the answer key in parenthesis to show it is an acceptable response. Point value remains unchanged.

Question:

SR0 Requal -

8.02b SRO Replacement -

8.03b Facility Comment: Additional acceptable answer due to recent procedure change, refer to attached procedure (EPIP 200-20 Rev. 3). (See attached references)

NRC Resolution: Due to the very recent revision to this procedure (10 days since official approval) full credit will be given for answers based on either Revision 2 or Revision 3, but not if they are mixed. Future use will require answers based on Revision 3 and part a_ of this question will be deleted.

l Question:

l SR0 Requal -

8.03 l SR0 Replacement - 8.05 t Facility Comment: Dresden requests that full credit be granted for ESDA vs IESDA and DNS vs IDNS since this is how these agencies are always referred to during actual and drill situations.

NRC Resolution: These designators will be added to the answer key as acceptable correct answers since they are tems commonly used at Dresden Station.

Question:

SR0 Replacement - 6.0tb Facility Comment: Drywell Pneumatics are no longer used. The correct answer is Pumpback and N, Makeup Systems. (See attached reference)

NRC Resolution: Comnent is valid. Since this system is no longer used Drywell Pneumatics will be deleted and these two systems, Pumpback and N, Makeup, will be the correct response on the answer key. Verified by telecon with Steve Stiles on 2/5/87.

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r Question:

R0 Replacement -

2.08d Facility Comment: Dresden considers this to be an inappropriate question because the HPCI Booster Pump discharges directly to the Main HPCI Pump (approximately 10 feet of discharge piping) and there is no instrumentation on this pump.

MRC Resolution: Comment is valid. Since there is no indication that the operator could refer to for Booster Pump Flow and the only instrumentation available is Booster Pump Suction Low Pressure, it is not reasonable to expect the operator l

to remember this parameter. Therefore, this portion of question 2.08 will be deleted and the question point value reduced by 0.5.

Question:

R0 Replacement -

3.04 Facility Comment: Additional acceptable answers: Oil Level, Coolant Level, Diesel Oil Day Tank Level. (See attached reference) l l NRC Resolution: Comment is valid. Parameters verified by High Voltage Operators Round Book, Unit 2 D/G. These three items will be added to the answer key as possible correct answers. Point value renains the same.

ADDITIONAL DRESDEN COBOENTS ON THE JANUARY 1987 MRC REQUALIFICATION EXAMINATION FACILITY COMMENT: In regards to the January 1987 requalification examinations, l

Dresden feels that the question difficulty and the assignment I of point values should be approximately the same for all questions. The shortened version of the exams necessitates this type of examination construction. It is not fair to the examinees or the station to have a failing criteria based on only two questfor.s. Every section of both January 1987 requalification exacinations had at least two questions .

worth a minimum of 13% of that section. In three particular l

sections, 19 - 20% of the section was based solely on one question. Dresden considers that an inappropriate weighting of questions that the point values be revised to make the examinations more representative of the examinee's knowledge level.

NRC Resolution: ES-107 establishes criteria for question weighting per section as follows: " Verify that no single question and/or topic is worth more than 20% of that category".

The January, 1987 Dresden Requalification Exam did not deviate from these criteria.

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.. .a Facility Comment: The Dresden Station Training Department has done an analysis of the SRO and R0 requalification examinations, comparing the questions contained in the examinations to Dresden's Requalification Program Exambank and Requalifica-tion Program Objectives. The results of these analyses are contained in Table IA, IB and 2.

NRC Resolution: The relationship of the ' questions to the Dresden Requal Objectives, R0 72%, SR0 83% is consistant with the re-quirements of ES-601 as follows: "The facility objectives for the requalification program shall be the PRIMARY subject areas tested on a requalification examination."

There is no existing requirement (or is it desirable) to construct an examination solely from the facilities examination bank.

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Ne e EXAMINER CHANGES TO ANSWER KEY DURING GRADING Question:

R0 Replacement -

(2.02)

R0 Requal -

(2.01)

Change: Additional acceptable answers:

HPCI Drain Pot Cooling Water

Reference:

Dresden Lesson Plan, Book 3, Section, Figure 8.

Question:

R0 Replacement - (2.06)

R0 Requal -

(2.04)

Change: Answer key correct if candidate assuced manual pushbutton initiation. However, if candidate assumed manual actuation of CARD 0X valves, correct answer is:

1. Cardox flows immediately (no time delay) (0.42)

2. No alarm in D/G room (0.42)

3. Anyone inside room must be warned before initiation (0.41)

Reference:

Dresden Lesson Plan, Bock 4, Chapter 5, pp. 6-7.

Question:

R0 Initial -

(3.01)

Change: Answer #2 is changed to:

2. Inserts an SRM scram (5 X 10 ES cps) OR provides a

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method of bypassing the SAM scrar. (0 5)

Reference:

Dresden Lesson Plan, Book 1, Chapter 15, p. 26.

Question:

R0 Replacement -

(4.08)

R0 Requal -

(4.05)

Change: Corrected Typo 13

[

. U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION' (s.

. FACILITY: REEEDEN REACTOR TYPE: BWR-GE3 s == gg p DATE ADMINSTERED: 87/01/26 3) lc si EXAMINER: BISHOP. M.

CANDIDATE INSTRLCTIONS TO 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 category 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 SCORE VALUE CATEGORY

.VALUE_ TOTAL 24.4:-

24.00 -24.0a 1. PRINCIPLES OF NUCLEAR POWER

'" PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 24 7S 25. Thd

2. PLANT DESIGN INCLUDING SAFETY'

. : ._ et-if

1. ' AND EMERGENCY SYSTEMS 2544 25 ?; 3. INSTRUMENTS AND CONTROLS 25.00 24.50 4. PROCEDURES - NORMAL, ABNORMAL,

'W EMERGENCY AND RADIOLOGICAL .

CONTROL 98.zs  % Totals

- C C . ? 5 ta Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

- C

)

\

\ 0 F

o. NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 3

LDuring 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 sheet of the examination.

9

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 new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. 1

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

10. Skip at least three 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 assumpticns 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 examiner 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 ex&mination has been completed.

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a 16 .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 revoked.

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11d PRINCIPr.wR OF NUCT EAR POWER PLANT OPERATION& .Paca .'4; g 1.;p TIMEMODYNAMICS. HEAT TRANSFER AND FLUID FLOW

}'

-QUESTION 1.' 01 ~ (3.00)

~ Match'each of the following terms in Column:"A" with.the appropriate.

definition from Column."B". Use each choice only once. .,

' Column ?A- Column B Terms -Definitions

1. Enthalpy a. The state of a. substance at which any further addition of thermal

-2. Condensate Depression energy will result in. vaporization (boiling)~at a constant temperature.

A further removal of1 thermal energy.

will result in lowering the

3. Subcooled or Compressed temperature of the substance.

Liquid

b. The heat content of steam or water, expressed in Btu /lbm.

4. Latent-Heat of Vaporisation c. A measure of'the energy content of a' substance which is unavailable for

5. Saturated Liquid conversion ~to useful work.

6. Saturated Vapor d. The state of a liquid when its pressure is above-the saturation

7. Superheated pressure for a given temperature.

vapor

e. The state of a substance when the

8. Entrepy temperature of its vapor is above the saturation temperature for a given pressure.

' f. The thermal energy which must be added or removed from a substance to change its state between saturated liquid and saturated vapor.

g. The state of a substance at which any further addition of thermal j energy will result in a tempera-

' ture increase of a vapor above the saturation temperature. If any heat is removed at this point, the temperature will remain constant and the vapor will condense.

L -

L ..

i h. The subcooling of condensate below I saturation temperature for a given pressure.

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1 L

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. Para 5 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW 3:

QUESTION 1.02 (1.00)

.The quality of steam to the turbine refers to: (CHOOSE ONE)

~

a. 1The ratio of the liquid mass to the sum of the liquid and vapor masses,

b. The ratio of the vapor mass to the sum of the liquid and vapor masses.

c. The ratio of the vapor mass to the liquid mass.

d. The ratio of the liquid mass to the vapor mass.

QUESTION 1.03 (1.00)

Match the major form of heat transfer with the condition described.

Form of Heat Transfer (1) Radiation (2) Convection (3) conduction CONDITION

a. Across a fuel pellet.

b. Fuel pellet to the cladding.

c. From the cladding to the coolant.

d. From fuel rod to fuel rod in a voided core.

QUESTION 1.04 (1.00) l.

When using the neutron monitoring instruments to identify a partially uncovered core during accident conditions, the neutron flux Might show a drop-off as the detector enters the uncovered region of the core

> Why MIGHT this indication occur on the nuclear instruments?

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

T .

Pcco 6-

1. PRINCIELES OF NUCLEAR' POWER PLANT OPERATION.

.. THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW s

QUESTION 1.05 (1 50)

a. What is the effect of core age on the doppler coefficient of reactivity (MORE NEGATIVE or LESS NEGATIVE) choose one? ,

(0.5)

-b. Explain why this change takes place. (1.0)

QUESTION 1.06 (2.00)

TRUE or FALSE 7 Answer the following concerning factors affecting control rod worth,

a. The worth of a control rod is a direct function of the thermal neutron flux to which it is exposed.

b. A control rods worth decreases as moderator temperature increases.

c. As the void content inceases, the control rod worth increases.

d. Control rod worth increases as the fuel temperature increases.

QUESTION 1.07 (1.00)

Fill in blanks 1 and 2.

A control rod blade which is inserted < 1/3 into the core is referred to.as a 1__ rod while a blade which is inserted > 2/3 into the core is referred to as a __2__ rod.

QUESTION 1.08 (1.50) l l Briefly explain how a control rod withdrawal of one or two notches can result in a decrease in bundle power.

QUESTION 1.09 (1.50)

WhatareTWOreasonsforperformingrodpatternexchangesi l

l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

l

P 1'. '-PRINCIPLES OF NUC W AR POWER PLANT OPERATION. :Pcca 7

_ THERMODYNAMICS. HEAT TRANSnx AND FLUID FLOW -

i QUESTION 1;10 (2.00)

-Discuss how xenon changes for a reactor power increase from 50% to-100%. Assume steady state operation at 50% power for two days: prior to the maneuver. Include time frames and why they occur in your

. answer.

~ QUESTION 1.11 .(2.00)

Refer to the attached Figure 1, Keff vs Exposure and explain why the change in Keff occurs from the following points-(TWO reasons required for each set of points) ,

a. A to B

b. B to C

' QUESTION .1 ~ 12

. (1.00)

If reactor power-is increased with recire flow, does the temperature of the steam going to the turbine (INCREASE, DECREASE or REMAIN THE SAME)? BRIEFLY explain your answer.

QUESTION 1.13 (2.50)

a. Why is it necessary to operate with some Condensate Depression?

-(0.5)

b. What would be the affect (INCREASE, DECREASE or REMAIN THE SAME) on cycle efficiency if the amount of condensate depression were increased? Explain your answer. (1.0)

c. List TWO methods of reducing condensate depression. (1,0)

QUESTION 1.14 (1.50)

What are THREE interlocks / trips associated with the recire pumps that insure adequate NPSH is available? .

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

l '. PRINCIPLER OF NUCLEAR POWER PLANT' OPERATION. Pca 8 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW s

QUESTION 1.15 (1.50)

What are FIVE positive reactivity effects.which must be overcome by the standby. liquid control system to maintain a shutdown margin of 3%

Delta-K7

(***** END OF CATEGORY 1 *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pcco 9

. SYSTEMS s.

QUESTION 2.01 (2.00)

Using the attached Figure 2, identify the below listed

. items.with the correct letter from the figure.

1. . Accumulator Charge Line-2.. Inlet Scram-Valve

3. Withdrawal Line

4. Scram Pilot Solenoid Valve QUESTION. 2.02 (2.00)

List four liquid / steam influents to the HPCI gland seal' condenser.

QUESTION 2.03 (1.00)

Which one of the below best describes the location of the standby liquid control pumps relief valve discharge to the system?

A. the 55 gallon drum.

B. the individual pump suction.

C. the standby liquid control tank.

D. the test tank.

~

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

e + ~ - -

,. r s --y 3 y, ,.,,w.- y--g +-v..----,------ m-, - v, - - , -- - r-,.m, -- , - , s - - - . , --

.= - .

=. g 1, PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Paca 10

.- SYSTEMS

-i

. QUESTION 2.04. (2.00)

For the below listed isolation valves in the RWCU System, state whether the power supply to the motor is 480v or 250 v dc. ,

A. MO - 1A Cleanup inlet, inboard bypass valve B. MO-2 Outboard primary containment isolation valve C. MO - 3~ -Cleanup inlet, outboard bypass valve D. MO-7 Cleanup system return isolation valve QUESTION 2.05 (2.00).

The plant is operating at 100% power. A complete loss of instrument air occurs.

With NO Operator action, answer the below questions?

A. The level in the hotwell would ( increase, decrease, remain the same ).

B. Service water flow to the TBCCW heat exchangers would ( increase, decrease, remain the same ).

C. Scram Discharge Vol. drain valves would ( open, close, remain as is ).

D. Main feedwater regulating valves would ( open, close, remain as is ).

QUESTION 2.06 (1.25)

Breifly describe the operation of the CARDOX SYSTEM in the Unit 2/3 D/G Room when the system is MANUALLY INITIATED.

QUESTION 2.07 (1.50)

List two reasons why the number of RBCCW pumps in service must equal the number of heat exchangers being used.

Note: Procedural requirements is an unacceptable answer! .

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

~2. ~ PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pcco 11

, .: SYSTEMS

- c; f.SO

' QUESTION 2.08 . (e-te)

List the capacity and the discharge pressure for each of the below listed pumps. .

A. LPCI B. CS C. HPCI

-0. "?CI 0003!En t

. QUESTION 2.09 (2.00)

Identify which group isolation would affect each of the below systems / components.

A. Isolation condenser condensate return valves.

B. Shutdown cooling isolation valves.

C. HPCI auxiliary oil pump interlocks against (preventing) an auto start.

D. Drywell air sample isolation valves.

QUESTION 2.10 (1.00)

Which of the below best describes the location of the discharge of the RECIRC MG Set, DC Oil pump relief valve return to the system?

A. returns directly to the fluid coupler reservoir.

B. returns to the suction header for all the oil pumps.

O. returns to the discharge side of the A-1 oil pump.

D. returns to the suction of the DC oil pump.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pcco 12

. SYSTEMS QUESTION 2.11 (1.50)

A. What physically controls the closing speed of the MSIV's? (0.5)

B. The allowed range of closing speed of the HSIV's prev 4nts what two events? (min & max closing speed design requirements) (1.0)

QUESTION 2.12 '(1.50)

List three systems receiving makeup water from the Condensate Transfer System.

~ QUESTION 2.13 (1.00)

TRUE or FALSE A. The reactor feed pump runout relay when energized sends an electronic CLOSE signal to the MANUAL-AUTO Controller for the Bypass Valve.

B. -The Total Feedflow Summer is the input signal to the Reactor Feedpump Runout Relay.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

's .

2 .- PLANT' DESIGN INCLUDING SAFETY AND EMERGENCY Pcco 13

.. SYSTEMS QUESTION 2.14 (2.50).

-Select the best purpose (s) from column'B for each of the EHC

. components listed in column A. (one component from column A will match up with more than one purpose from column B)

Column A' Column B

1. Haster Trip Relay A. To provide a mechanism for most turbine trips.

2. Master Trip Solenoid Valve {

3. Mechanical Trip Valve- testing.

4. Lockout Valve C. To act as supervisory component for trips.

D. To interrupt FAS fluid during overspeed conditions.

E. To convert FAS fluid into ETS fluid QUESTION 2.15 (2.00)

List the normal power supplies.(or buses) for each of the following system or components. (be specific - i.e. if there are two buses st ate which bus. }

A. EHC electronics B. Reactor Man. Control C. Channel B Primary Containment Isolation System Logic D. CRD Scram Pilot Solenoid Valves (117)

E. Main Steam Line Rad Monitor Channel B.

F. Recharging Motor for 4 kV Breakers on Bus 23. .

(***** END OF CATEGORY 2 *****)

', k __

3. INSTRUMENTS AND CONTROLS Peca 14

=

QUESTION. 3.01 (1.00)

List two functions of the SRM Shorting links (RPS).

QUESTION 3.02 (2.50)

List FIVE of the SIX conditions required for~an auto start of a standby feed pump. (include applicable setpoints.)

QUESTION 3.03 (2.00)

A 4kv breaker has neither red or blue' lights illuminated, the control switch is not in pull to lock and the bulbs checkout good. List TWO probable CAUSES of this condition AND the RESULTS.

QUESTION 3.04 (2.00)

List four LOCAL instruments / indications for the U-2 Diesel.

(NOT the Generator)

QUESTION 3.05 (1.00)

For each of the level instruments listed in column A, identify the type of compensation used from column B.

Column A Column B A. Narrow Range GEMAC 1. Pressure Compensation B. Medium Range Rosemount 2. Temperature Compensation

( C. Medium Range Yarway 3. Calibration Curve if at l other than sero psig.

3 D. Wide Range GEMAC

4. Is not pressure nor temperature compensated f

i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

i

50.. .;

-e

3. ' INSTRUMENTS AND CONTROLS Pcg1 15 3L .

QUESTION '3.06 (1.00)

List three of the~ signals capable of causing an "RPIS INOP" Alarm.

QUESTION 3.07 (1.50)-

The APRM meters on the 902-37 have an function switch containing seven positions.

For each.of the positions below, describe the indication available when the function switch is in each position listed.

A. -AVERAGE B. COUNT C. FLOW QUESTION 3.08 (1.50)

A. What is the trip / alarm setpoint for the Reactor Building Ventilation Exhaust radiation high - high?

B. Briefly describe or define the trip logic for the Reactor Building Refueling Floor Radiation Monitoring System.

QUESTION 3.09 (1.00)

The following question concerns the Isolation Condenser System.

Briefly describe the switch operation required for the 3-valve to decrease the cooldown rate. Assume no automatic signal is present.

QUESTION 3.10 (1.00)

Assume a Core Spray initiation signal is present, list the trips available for the 2A Core Spray Pump. Setpoints are not required! ,

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

s. .

!b'

3. INSTRUMENTS'AND CONTROLS Pcca 16 QUESTION 3.11 (2.75)

A. FILL IN THE-BLANK The recire pump speed control mismatch circuitry prevents exceeding a a.  % speed mismatch between the two recire pumps. (0.25)

B. What is the primary and secondary reason speed mismatch is limited? (1.0)

C. What protective function occurs if the mismatch exceeds the limits established in a. above? (0.5)

D. Under what conditions will the circuit trip a recire pump? (0.5)

E. What function (associated with mismatch) allows restart of an idle recire pump? '(0.5)

QUESTION 3.12 (2.00)

• The reactor is operating at ~90% thermal power, a spurious scre.m (full) is received. The reactor vessel level tape was set at 30 inches and two RFW pumps were operating (the third pump is out of service).

The total feedflow increased to 12.5 X10E6 lbs/hr and level decreased to 15 inches.

A. Assuming no operator action and all facility systems function properly, what will be the steady-state {after scram} vessel

--level?

B. What action is required by the operator to return vessel level

, to the master controller?

QUESTION 3.13 (1.75)

With respect to the RWM, what signal (s) are utilized to ACTUATE AND DEACTUATE the LPSP and LPAP (include applicable setpoints and times).

l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

g.'

'3; -INSTRUMENTS AND CONTROLS -paca 17 QUESTION 3.14 .(2.00)

Assuming the HPCI system is in operation for full flow testing. list the position of the below listed valves after the turbine is MANUALLY tripped.

'A. 2301 - 4 Steam supply inboard containment isolation ~va,1ve B. 2301 - 36 Suction valve from torus C. - 2301 - 14 Torus return minimum flow valve D. 2301 - 8 HPCI injection valve QUESTION 3.15 (2.00)

List the AUTOMATIC initiation signals and setpoints for the Low Pressure

' Coolant Injection System.

m l .

i

(***** END OF CATEGORY 3 *****)

.C:

.4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pc72 18 c .AND RADIOLOGICAL CONTROL r

QUESTION 4.01 (2.00)

DOA 202-1, recirculation pump trip requires the operator'to reduce the speed of the running recirc pump. ,

A. What are the limits for each unit at Dresden?

B. What is the reason for this difference?

QUESTION 4.02 (2.50)

List FIVE automatic actions initiated by a main steam line High Radiation Alarm at 3 X normal.

QUESTION 4.03 (1.00)

DAP 7-2 specifies a licensed operator cr senior licensed operator

. shall be "at-the-controls" at all times.

What is the meaning of "at-the-controls"?

QUESTION 4.04 (1.00)

A coupling check is performed when withdrawing control rods to position 48.

A. EXPLAIN HOW this coupling check is performed. (0.5)

. B. WHAT indication would tell the operator the rod was uncoupled? (0.5)

QUESTION 4.05 (2.50)

Cther than a decreasing neutron flux, list FIVE other check's the operator can make to assure Standby Liquid Control is injecting.

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) <

p- -

F ".' ,

i&

J4. -PROCEDURES - NORMAL. ABNORMAL, EMERGENCY Pcsa 19

. .AND RADIOLOGICAL CONTROL QUESTION- _4.06 (1.00)

-Why'must control rod ~"L-2" of Unit 3 be only notched out during reactor startup? ,

. QUESTION 4.07 (2.00)

-List the entry. conditions for DEOP 100, Reactor Control.

(Include applicable setpoints)

QUESTION 4.08 (1.75)

List the MINIMUM nuclear monitoring system requirements / restrictions during core alterations. Positions and locations

'are required for full credit.

QUESTION 4.09 (1.00)

Procedure DGP 3-4, Control Rod Movements Control Rod Sequences, estabishes the general rules for control rod movement.

Who has to approve changes to the CRS or Special CRS7 QUESTION 4.10 (2.00)

. List four of the conditions / requirements of DOP 5770-1, Economic Generation Control Operation, directing the NSO to remove the unit from EGC.

QUESTION 4.11 (0.50)

Normally, operation of the drywell coolers is determined solely by interior drywell temperatures. What is the normal or operating range of the drywell temperature?

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

F-~"7 >

-e? 'FROCEDURES - NORMAL. AEliORMAL. EMERGENCY Page 20

.- .AND RADIOLOGICAL CONTROL ,

J d '

t QUESTION 4.12 .(1.00) ,

. List the actions required by DGP 1-1, Normal Unit Startup, if during a

-reactor startup a period of 15 seconds is observed. .

' QUESTION 4 .~ 13 (1.00)-

~

LIST the steps-(2) required to lock out an MG set scoop tube locally.

QUESTION 4.14 (1.50) -

List six of the Immediate Operator Actions for " Loss of Condenser Vacuum" DOA 3300-2

-QUESTION 4.15 (1.00)

List the Automatic Actions occurring if the stator cooling water

. systems fails while the unit is at 100% power.

Assume no operator action and restrict your answer to the main generator only. (Include applicable limits and times)

QUESTION 4.16 (2.75) /

List the Immediate Operator Actions for EACH Unit upon a loss of 125v DC power supply. DOA 6900-2, /,u ,# v4,4 J as a p syg i

i

(***** END OF CATEGORY 4 *****)

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

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ngureK CR0 Hydraulic Centrol unit Cwpenents R EV.11 2/82

~

EQUATION SHEET f = ma v = s/t 2 Cycle efficiency =

w = ms s = v,t + hac *]*I '

E = aC a = (vg - v,)/c

• gg = hay 1 v g = v, + at A = AN A =,A,e PE = gh ,= ,/t 1 = in 2/tg = 0.693/tg ,

u = vaP- tg(eff) = (t,,)(q) . . .

AE = 931Am ( ,

)

6,=GCAT P

. , z = ro .-rx ,

, ,, Q = UAAT I I g,"UX , ,

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y=y to M (t). TVI. = 1.3/u et/T H7L a 0.693/u P=P

~

SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg) f1*ff oy

. SUR = 26 g ,

CR x = S/(1 - K,gg )

~

T = '(d/ o ) + [(i

• o)/1,g,g] 1( eff}1 " 2 Il ~ Eeff)2 y = t*/ (, . p M = 1/(1 - K,gg) = CR /CR0 g

" ~8 #

eff M = (1 g,,g)0/II ~ Eeff)1 8"I aff~I) eff " A eff/Keff SDM = (1 - K,gg)/K,gg

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p= [1*/DC,'gg .] + [I/(1 + 1,ggT )] ,

t* = 1 x 10 seconds

~I P = E6V/(3 x 1010) A,fg A= 0.1 seconds I = No Idgg=1d22 UATER PARAMETERS Id g =Id 22 2

1 gal. = 8.345 lba R/hr = (0.5 CE)/d (meters)

I gal. = 3.78 liters R/hr = 6 CE/d (feet) -

1 ft = 7.48 gal. MISCELL\NEOUS CONVERSIONS .

3 10 Density = 62.4 lbm/f t 1 Curia = 3.7 x 16 dps Density - 1 ryi/cm i kg = 2.21 lbm Heat of vsfori:ationi = 970 Ecu/lba 1 hp = 2.54 x 10 ETU/nr 6

Hest of fusica = 144 Bru/lba 1 Mw = 3.41 x 10 Beu/hr 1 Atm = 14.7 psi = 29.9 in. I g. 1 Btu = 778 f t-lbf

- a 1 ft. H 2O = 0.4333 lbf/in 1' inch = 2.54 cm F = 9/5'c + 32 "C = 5/9 ("T - 32)

IMh.l,y. Stullt (nt,opy. Stu/lb a F Volum. fl'/lb 7 w., c ., .. .., c, .. 79 u., c.. , ....

779 97, a, a,. a, ., .,, .,

, ,. 4 1075.5 0.0000 2.1873 2.1873 32 3305 3305 -0.02 1075.5 22 0.08859 0.01602 1076.8 0 0061 2.1706 2.1767 35 2948 3.00 1073.8 0.09991 0.01602 294S 1079.0 0.0162 2.1432 2.1594 40 35 2446 2446 8 03 1071.0 0.12163 0 01602 1081.2 0 0262 2.1164 2.1426 45 40 2037.8 13.04 1068.1 0.14744 0.01602 2037.7 1083.4 0.0261 2.0901 2.1262 50 45 1704.8 18.05 1065 3 0.17796 0.01602 1704.8 1067.7 0.0555 2.0391 2.0946 60 50 1207.6 28.06 1059.7 0.2561 0.01603 1207.6 60 0.0745 1.9900 2.0645 70 868 4 38.05 1054 0 1092.1 0.3629 0.01605 8G8.3 1096.4 0.0932 1.9426 2.0359 80 70 613 3 48.04 1048.4 0.5068 0.01607 633.3 1100.8 0.1115 1.8970 2.0086 60 80 468.1 468.1 58.02 1042.7 0.6981 0.01610 1105.1 0.1295 1.8530 1.9825 100 90 350.4 68 00 1037.1 100 0.9492 0.01613 350.4 77.98 1031.4 1109.3 0.1472 IJ105 1.9577 110 0.01617 265.4 265.4 110 1.2750 1.9339 120 1025.6 1113.6 0.1646 1.7693 203.25 203.26 87.97 130 1.6927 0.01620 1019.8 1117.8 0.1817 1.7295 1.9112 320 157.32 157.33 97.96 2.2230 0.01625 1122.0 0.1985 1.6910 1.8895 140 330 122.98 123.00 107.95 1014.0 2 8892 0.01629 1126.1 0.2150 1.6536 1.8686 150 140 97.05 97.07 117.95 1008.2 3.718 0.01634 1130.2 0.2313 1.6174 1.8487 160 150 77.27 77.29 127.96 1002.2 360 4.741 0.01640 1134.2 0.2473 1.5822 1.8295 170-62.04 62.06 137.97 996.2 ISO 370 5.993 0.01645 1138.2 0.2631 1.5480 1.8111 50.21 50.22 148.00 990.2 100 350 7.511 0.01651 1142.1 0.2787 1.5145 1.?734 40.94 40.96 158.04 984.1 200 390 9.340 0.01657 1146.0 0.2940 1.4824 1.7764 33.62 33.64 168.09 977.9 200 11.526 0.01664 1149.7 0.3091 1.4509 1.7600 210 27.80 27.82 178.15 971.6 210 14.123 0.01671 1150.5 0.3121 1.4447 1.3568 212 26.78 26.80 180.17 970.3 212 14.696 0.01672 1153.4 0.3241 1.4201 1.7442 220 23.13 23.15 188.23 965.2 220 17.186 0.01678 1157.1 0.3388 1.3902 1.7290 230 19.364 19.381 198.33 958.7 230 20.779 0.01685 1160.6 0.3533 1.3609 1.7142 240 16.304 16.321 208.45 952.1 240 24.968 0.01693 1164.0 0.3677 1.3323 1.7000 250 13.802 13.819 218.59 945.4 250 29.825 0.01701 938.6 1167.4 0.3819 1.3043 1.6862 MO 0.01709 11.745 11.762 228.75 1.6729 270 260 35.427 931.7 1170.6 0.3960 1.2769 0 01718 10.042 10.060 238.95 250 270 41.856 924.6 1173.8 0.4098 1.2501 1.6599 0.01726 8.627 8.644 249.17 290 200 49.200 917.4 1176.8 0.4236 1.2238 1.6473 0.01736 7.443 7.460 259.4 1.6351 303 290 57.550 910.0 1179.7 0.4372 1.1979 0.01745 6.448 6.466 269.7 300 67.005 1182.5 0.4506 1.1726 1.6232 310 5.626 280.0 902.5 310 77.67 0.01755 5.609 0.4640 1.1477 1.6116 320 4.914 290.4 894.8 1185.2 89.64 0.01766 4.896 0.4902 1.0990 1.5892 340 320 3.788 311.3 878.8 1190.1 117.99 0.01787 3.770 0.5161 1.0517 1.5678 360 340 2.957 332.3 862.1 1194.4 153.01 0.01811 2.939 0.5416 1.0017 1.5473 380 360 2.335 353.6 844.5 1198.0 195.73 0.01836 2.317 340 1.5274 400 g 825.9 1201.0 0.5667 0.9607 1.8444 1.8630 375.1 420 400 247.26 0.01864 806.2 1203.1 0.5915 0.9165 1.5060 1.4808 1.4997 396.9 440 420 30S.78 0.01694 785.4 1204.4 0.6161 0.8729 1.4890 1.1976 1.2169 419.0 460 440 381.54 0.01926 763.2 1204.8 0.6405 0.8299 1.4704 0.9746 0.9942 441.5 480 460 466.9 0.0196 739.6 1204.1 0.6648 0.7871 1.4515

! 0.7972 0.8172 464.5 460 566 2 0 0200 l

0.6890 0.7443 1.4333 500 0.6749 487.9 714.3 1202.2 500 680.9 0.0204 04545 1199 0 0.7133 0.7013 1.4146 520 0.5386 0.5596 512.0 687.0 540 520 812.5 0.0209 657.5 1194.3 0.7378 0.6577 1.3954 r

04437 04651 536 8 1.3757 560 540 962.8 0.0215 625.3 1187.7 0.7625 0.6132 0.3651 0.3871 562.4 1.3550 580 SEO 1133.4 0.0221 0.3222 589.1 589.9 1179.0 0.7876 0.5673 580 1326.2 0.0228 0.2994 550 6 1167.7 0.8134 0.5195 1.3330 500 0.2435 0.2675 617.1 1.3092 620 600 1543.2 0.0236 506.3 1153.2 0.8403 0.4659 0.1962 0.2208 646.9 1.2621 640

$20 1786.9 0.0247 454.6 1133.7 0.8656 0.4134 0.1543 0.1802 679.1 1.2458 660 640 20199 0.0260 392.1 1107.0 0.8995 0.3502 0.1166 0.1443 714.9 0.2720 1.2056 680 660 2365 7 0 0277 310.1 1068.5 0.9365 0.0808 0.1112 758 5 640 2708.6 0 0304 172.7 995.2 0.9901 0.1490 1.1390 700 0.0386 0.0752 822.4' 0 1.0612 705.5 700 3094.3 0 0366 0 906.0 1.0612 0 0.0508 906.0 705.5 3203 2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)

A.3 i

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. Pcga 21 I' ,

IHERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ANSWER 1.01 (3.00)

1. B-

2. H

3. D'

4. F

5. A

6. G 9

7. E

8. 'C [8 @ 0.375 each = 3.0]

REFEREN'E C Dresden,' Lesson Plan Thermo, HTFF, PP. 4 and 5 ANSWER 1.02 (1.00) b.

REFERENCE Dres, den, Lesson Plan Thermo, HTFF, P. 5 ANSWER 1.03 (1.00)

a. 3

b. %2.

c. 2

d. 1 [4 @ 0.25 each = 1.0)

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. Pega 22

. THEEMODYNAMICS. HEAT TRANSFER AND FLUID FLOW REFERENCE.

Dresden, Lesson Plan Thermo, HTFF, PP. 14-16

~

ANSWER 1.04 (1.00)

With a loss of water level, the instruments which indicate

~the thermal flux would be in a fast flux field and indicating low.

REFERENCE Dresden, Lesson Plan, Degraded Core Response, P. 5 .

ANSWER 1.05 (1.50)

a. More Negative (0.5) ,

~

b. Because of the buildup of PU 240 (which is a large resonance

. absorber). (1.0)

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 32 ANSWER 1.06- (2.00)

a. -TRUE

b. FALSE

c. FALSE

d. FALSE REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 36

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1

e-@

1. PRI}{gIELES OF NUCMAR POWER PLANT OPERATION. Page 23 IllERMODYNAMICS. HEAT TRANSFEE_AND FLVID FLOW ANSWER 1.07' (1.00)

.1. Shallow

2. Deep [2 9 0.5 each = 1.0]

REFERENCE Dresden, Lesson. Plan, Reactor Physics Review, P. 38 ANSWER 1.08 (1.50)

The steam bubbles generated by withdrawal of a shallow rod increase the void fraction, which adds negative reactivity off-setting the positive reactivity effects of the rod withdrawal.

REFERENCE-Dresden, Lesson Plan, Reactor Physics Review, P. 39 ANSWER 1.09 (1.50)

1. Maximize fuel burnout (by' flattening the flux).

2. Limit the power peaking (that would occur from a subsequent rod withdrawal after the buildup of Pu-239).

~

REFERENCE Dresden,-Lesson Plan, Reactor Physics Review, P. 41 l

l ANSWER 1.10 (2.00)

The initial power increase will cause a decrease in the xenon concentration [0.5]. The low peak occurs 4-6 hours after the power increase [0.5]. The power production term takes over [0.5] and a new

equilibrium level is reached in 40-50 hours [0.5].

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

l l

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. 'Page 24

.- -THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 45 ANSWER 1.11 . (2.00) .

a. 1. Buildup of xenon.

2. Buildup of. samarium.

b. 1. Gadolina burnup.

2. PU-239 buildup. [4 9 0.5 each : 2.0]

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, Figure 62, P. 47 ANSWER 1.12 (1.00) l INCREASE [0.25] due'to saturated conditions [0.75]~.

REFERENCE-Dresden, Requal Q/A Thermo. P. 2 ANSWER ,.

1.13 (2.50) a.- To ensure sufficient NPSH for the Condensate Pumps. (0.5)

'b. DECREASE [0.5]. The heat loss from the feedwater must be made up by the nuclear fuel'[0.5].

c. Reduce cire water flow Increase cire water temperature Increase condenser pressure [any 2 9 0.5 each = 1.0]

REFERENCE .

Dresden, Lesson Plan Thermo, HTFF, P. 8

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1. PRINCIPT.ES OF NUCLEAR POWER PLANT OPERATION. Page 25

. THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ANSWER 1.14 -(1.50)

1. Minimum speed until feed flow > 20%.

2. Suction valve closed trip.

3. Low vessel water level trip. [3 e 0.5 each'= 1.5]

REFERENCE Dresden, Requal Q/A Thermo, P. 5 ANSWER 1.15 (1.50)

1. Elimination of steam voids.

2. -Moderator temperature change from hot to cold (125 F).

3. Reduced doppler effect.

4. Decreased control rod worth as the moderator cools.

5. Xenon decay. [5 @ 0.3 each = 1.5]

REFERENCE Dresden, Student Text #3, PP. 3-10-3-11

(

~

(***** END OF CATEGORY 1 *****)

, - - - - ~ . , ,.m..- w y-, -

w -- m

-2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY ' Paco 26

. SYSTES ANSWER 2.01 (2.00)

.1. J

~

2. F-

3. A

4. D (4 @ 0.5 ea = 2.0)

REFERENCE DRESDEN - Studednt Text, Chapter 6, Control Rod Drive Hydraulic, Fig One. -

ANSWER 2.02. (2.00)

1. Turbine seals

2. Stop valve below seat drains

3. ' Turbine first stage drain and casing exhaust drains

4. Casing exhaust drains G. #per dd,- p+

b. Turbine exhaust piping (any 4 @ 0.5 ea = 2.0)

REFERENCE DRESDEN - Student text, Chapter 10, HPCI, page 8 h e b hss~ R ,0. k 3 , S w./D, Ay. 8.

l l ANSWER 2.03 (1.00)

C (1.0)

~

i l

, (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

b. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Paga 27'

. SYSTEMS-REFERENCE DRESDEN - Student Text, Chapter 3. Figure 1.

. ANSWER 2.04- (2.00)

A. 480V B. 250 VDC C. 250'VDC D. 480V (4 @ 0.5 ea = 2.0)

REFERENCE DRESDEN - Student Text, Chapter 5, page 17. (

^

ANSWER 2.05 (2.00)

A. Decrease B. Increase C. Close D. Remain as is (4 @ 0.5 ea = 2.0)

REFEREN'CE

~

DRESDEN - Student Text, Book 4, Chapter 3, page 14.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Paso 28

. SYSTE&S ANSWER 2.06 (l.25 .

TS w d:L/- us .J &) lA L*" "'.#'.~ ' " * ' ' -

1. Energize a siren in the room (0.25)

2. Stops the vent fan in the room (0.25).

i- 3. Opens the storage tank discharge valve (0.25).

-4. Opens the selector valve for the room (0.25).

5. The pilot valves will remain open (for approximately 97 seconds)

(0.25). r 4. nede Ah, w* *. *..

gp w;;g,t. ,ua,J pn I. 0 ),or /%.aikan M 4 (P*d**. /*& ) (0.42)

2. A p,,,,,,. p g , co.43) (5 @ 0.25 ea = 1.25)

. ; siL sjs /. . est L mJ (0.41) x REFERr.C DRESDEN - Student Text, Book 4, Chapter 5, page 6.

Ansdnlesse- f/ , A 4 4 chy/+ S g ti 7.

ANSWER 2.07 (1.50)

1. The use of two pumps with one heat exchanger would exceed the design capacity flow of the heat exchanger. ( excessive vibration).

2. The use of two heat exchangers with one pump would approach the load limits for the pump. Ar 5 **

• 1'0)

.T. }tud d8CCfr*uwe- A ,.oere.* & w uu J ,. p _ (),,'g("E

• O' REFERENCE DRESDEN - Student Text, Book 3, Chapter 17, page 21.

Aut tass, /L-,sawS p t w, St. g. L.b. 2.) yy- l1.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Peca 29 SYSTEMS 1.50 ANSWER 2.08 6. 26)

A. 5000 gpm (+/-10%) 160 psig-(+/-10 psig)

B. 4900 gpm (+/-10%) 250 psig (+/-15 psig)

C. .>/= 5000 gpm (+/-10%) 1150_-150 psig (+/-50 psig)

- D. 5000 . ,... C'/ 10*:' 200 7;ig :t/-15 p-ic' t 6 - 0. J *? (/.5)

-' (g 9 dih464.ea = -t-0-)

dise REFERENCE DRESDEN - Student Text, Jook 3, Chapter 14, page 4 Chapter 13, page 4 Chapter 10, pages 3 and 4 ANSWER 2.09 (2.00)

A. GROUP V B. GROUP III C. GROUP IV D. GROUP II (4 9 0.5 ea = 2.0)

REFERENCE DRESDEN - Student Text, Book 3, Chapter 16, page 60.

ANSWER 2.10 (1.00)

D (1.0)

REFERENCE DRESDEN - Student Text, Book 2, Chapter 10, Figure 10.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

w -

- , , ---es - ,--,w w w- * - - - , --s --sy- -- +- y,

-2. PLANT-DESIGN' INCLUDING SAFETY AND EMERGEHQY Pzga 30

. . SYSTEMS r

ANSWER 2.11 (1.50)

A. The throttle valve on the hydraulic dashpot. (0.5)

B. 1. Fast'enough to prevent a gross release of fission-products to the environs. (0.5)

2. Slow enough to minimize the severity of the pressure transient resulting from an isolation. (0.5)

REFERENCE DRESDEN - Student Text,-Book 2, Chapter 3, page 12.

ANSWER 2.12 (1.50)

1. Fuel Pool Cooling and Cleanup System.

~

2. Reactor Water Cleanup System.

3. Isolation Condenser.

4. -The ECCS fill header. { alternative supply}

(any 3 @ 0.5 ea = 1.5)

Jr. (4 / M<.J.,,.6 S / 5/w Q 5' / M//.

t. %d d ; n sfw Sp/e .

REFERENCE DRESDEN - Student Text, Book 2, Chapter 4, page 27.

0$ Am $, W%b .5 f*'l-fs-- My 18.

pres /n ff 7Ob M -35, / M o,a, / pt r1.

ANSWER 2.13 (1.00)

A. FALSE (0.5)

B. FALSE (0.5)

REFERENCE DRESDEN - Student Text, Book 2, Chapter 6, Figure 3 and Figure 8.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

t

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Para 31 SYSTEMS ANSWER 2.14 (2.50)

1. C

~

2. A&E

3. D

4. B (5 @ 0.5 ea = 2.5)

' REFERENCE DRESDEN - Student Text, Book 2, Chapter 8, pages 13, 14, and 15.

ANSWER 2.15 (2.00) fu m M % .t w*r d*r (W A. -Instrument Sue '

B. Instrument Bus C. Essential Service Bus D. RPS Bus A Asswfa/ f**v a f.a

- M r -. ,,. g g h n g m g E.s ^^" " " =.: " 3

-Ch;.nn:1 0. CL%i a "- 4 ' 4 + y _

F. 125V DC (T.B. Main Bus #2A-1 ESS Div I & Non-ESS)

(6 @ 0.33 ea = 2.0)

REFERENCE

. DRESDEN - Student Text, Book 2, Chapter 13, Table 5.

Chapter 14, page 4.

hr*J)s lWie~ & ,/)lro; Turl?- g 12 A t3 A" L4.*>l /m Le< , dos 48ao-L /*<. 3, lau o / $* A f"Al f*'E'

. n &d. Ba s . pA L.

(***** END OF CATEGORY 2 *****)

r

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

3. INSTRUMENTS AND CONTRQLE Pcca 32 ANSWER 3.01 (l.00)

1. Provides a noncoincident nuclear instrumentation scram '

(0.5)

(any single SRM,-IRM, or APRM trip)

2. Inserts an SRM scram (5 X 10E5 cys) or f n; b A* .(0.5) m e t.s 1 >? L y g .* : * ~y th e  : u .~~ ;s < w ,

REFERENCE DRESDEN- Student Text, Book 1, Chapter 15, page 26.

$ *d~ k b One k J , cJ.yh. is zc.

ANSWER 3.02 (2.50)

1. Supply breaker trip on a running feed pump.

2. A standby RFP is selected.

3. Suction pressure above the trip setpoint of 120 psig.

4. At least one ventilation fan is operating.

5. Oil pressure is greater than 20 psig

. 6. Rx water level less than 55" [5 required @ 0.5 each] (2.5)

REFERENCE Dresden Student Text #4, Book 2, PP. 23 and 24

' ANSWER 3.03 (2.00)

1. A loss of control power preventing breaker operation. (1.0)

2. Loss of trip circuit continuity which would prevent the breaker from being tripped from the control room. (1.0)

REFERENCE DRESDEN - Student Text, Book 2, Chapter 14, page 12.

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

3. INSTRUMENTS-AND CONTROLS-- Pcgi 33 ANSWER- 3.04 (2.00)

-1. Starting air pressure

2. Lube oil temperature into filter .

3. Cooling water temperature (engine inlet and outlet)

4. Lube oil pressure

5. Cooling Water pressure

6. Fuel oil pressure

1. ol 1 ,,/ (any 4 @ 0.5 ea = 2.0)

REFE Nk DRESDEN - Student Text, Book 2, Chapter 15, page 6 kej/~ $&l v.ll ye ofn.tws dea ~d Sok y rif 3f & . 7

. ANSWER 3.05 (1.00)

A. 1 B. 2 C. 2 D. 4 (4 @ 0.25 ea = 1.0)

REFERENCE' DRESDEN - Student Text, Book 1 Chapter 4, pages 5, 6, & 7.

ANSWER 3.06- (1.00)

1. Invalid probe data

2. Card pulled

3. Loss of power supply .

.4. Internal logic stall (any 3 @ 0.33 ea = 1.0)

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

3; INSTRUMENTS AND CONTROLS Pago 34

• REFERENCE-DRESDEN - Student Text, Book 1, Chapter 7, page 14.

~

ANSWER 3.07' (1.50)

A. The meter reads the core bulk thermal power.

B. The meter indicates the number of assigned LPRM's which are in " operate" C. The meter reads the percentage of rated total recirculation loop flow.

(3 @ 0.5 ea =.1.5)

REFERENCE DRESDEN - Student Text, Book 1, Chapter 12, page 15.

ANSWER 3.08 (1.50)

A. 11-MR/hr (-1 +4 MR/hr) (0.5) (0.5)

B. One high level trip (0,5) OR Two downscale trips (0.5) (1.0)

REFERENCE DRESDEN - Student Text, Book 3, Chapter 1, page 14.

ANSWER 3.09 (1.00)

Throttling of the 3-valve is accomplished by placing the HAND-RESET Lwitch in the " HAND" position and operating the 3-valve Control Switch from CLOSE to AUTO as necessary to achieve the desired cooldown rate.

REFERENCE DRESDEN - Student Text, Book 3, Chapter 12, page 7. -

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

3. INSTRUMENTS AND CONTROLS Pcco 35 ANSWER 3.10 (1.00)

1. Instantaneous Overcurrent

2. Time-delay Overcurrrent ,

4- D. 35

3. Undervoltage (7 @.S-e9 ea = 1.0) 4.. ps .att f/**~ s ~ik i l A /I* " * " # 0 REFERENCE DRESDEN - Student Text, Book 3, Chapter 13, page 4.

ANSWER 3.11 (2.75)

A. 10% (0.25)

B. Primary: to avoid confusing the LPCI loop select logic (0.5)

Secondary: To prevent flow-induced vibration in the jet pumps (0.5)

C. Prevents the high speed pump from increasing and the low speed pump from decreasing. (0.5)

D. If the mismatch exceeds 10% and the discharge valve on the low speed pump is closed. (0.5)

E. A time delay. (0.5)

REFERENCE Dresden Student Text #2, Book 2, PP. 12-14

, ANSWER 3.12 (2.00) l

! A. ~15 (+/-10%) inches. (1.0)

(Upon full scram, the master controller dual setpoint current supply output is reduced by 50%. This effectively halves the

! level as demanded by the sepoint adjust tape.)

" h ope A,. u n m .ae M ~ on " & % 44s r*~ trel-y & P sb W ,,

B.4 N ---ter centroller d"-1 te+rair+ -nve-t cupp1; cutput in,. (1.0) r-t' r.md W c.crnni ^. n the scrom

.o m s s-.

i

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l

3. INSTRUMENTS AND CONTROLS Phga.36

• REFERENCE DRESDEN - Student Text, Book'2, Chapter 6,-page11.f /D ANSWER 3.13 (1.~75) ,

LPSP Actuato Total steam flow >/= 20% AND feed flow >/= 10% for at least 60 seconds (0.75)

Deactuate steam flow </= 20% OR feed flow </+'10% -(0.5)

LPAP Actuate Total steam flow >/= 35% (0.25)

Deactuate total steam flow </= 35% (0.25)

REFERENCE i

Dresden Lesson Plan #8, Book 1, P.7 1

ANSWER 3.14 (2.00)

A. OPEN B. CLOSED C. OPEN D.. sW.Ei?

(4 @ 0.5 ea = 2.0)

REFERENCE

- DRESDEN - DOP 2300 -T1 and Student Text, Book 3, Chapter 10.

ppsik- lsss~ f/~. llfc'C. 7sJ /~ $ .

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

3 '. INSTRUNENTSANDCONTROLS~ Peca 37.

' ANSWER 3.15 -(2.00)

The system is initiated when one of the following conditions exist:

1. High Drywell Pressure (0.25) ,

2.0 psig (0.25)

• • OR **-

2. Low Low Water Level (0.25)

-59 inches (0.25)

1. 1. and ##

Reactor Low Pressure (0.25)

Less than 350 psig (0.25)

-** OR **

3. Low Low Water Level (0.25)

Maintained for greater than 8.5 minutes. (0.25)

(2.0)

~ REFERENCE-DRESDEN - Student Text, Chapter 14, page-13.

4 1

I' l

~

(***** END OF CATEGORY 3 *****)

l

w-- .

~4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY- Paro 38

. AND RADIOLOGICAL CONTROL ANSWER 4.01 (2.00)

A. Unit 3 = 60%

Unit 2 = 43% [2 ,@ 0.5 each] (1.0)

B. Inadequate jet pump riser in Unit 2 which causes large jet pump vibrations during single loop operation. (1.0)

REFERENCE DRESDEN - DOA 202-1, PP. 1 and 4 ANSWER 4.02 (2.50)

1. Reactor scram

2. Group 1 isolation

3. Chimney isolation valve closure

4. Air ejector suction valve closure 5.

~

Mechanical vacuum pump trip [5 @ 0.5 each] (2.5)

-REFERENCE DRESDEN-- DGA 16, page 1.

ANSWER 4.03 (1.00)

"At-the-c'ontrols" means the unit operator is in line of sight of.the

! unit front panels. (1.0)

REFERENCE DRESDEN - DAP 7-2, P. 4

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

4 L4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Page 39 6- AND RADIOLOGICAL CONTROL ANSWER 4.04 -(1.00)

A. By attempting to withdraw the rod past position 48. (0.5)

~

'B. Rod overtravel alarm. (0.5)

-REFERENCE

-DRESDEN - DOP 400-1, P 4 DOP.400-2 ANSWER 4.05 (2.50)

1. Amber light of squib-firing continuity circuit not lit.

2. Flow indicating pilot light lit.

3. Rx water cleanup system isolation.

4. Decreasing level of Standby Liquid Storage Tank.

5. ' Standby liquid squib valve circuit fail annunciator light lit.

[5 @ 0.5 each] (2.5)

REFERENCE DRESDEN - DOP 1100-2, P. 3 ANSWER 4.06 (1.00)

The timing has been found to be out of specification (1.6 see) and controling withdrawal by notch withdrawal will eliminate a possible "short period" startup. (1.0)

REFERENCE DRESDEN - Operating Order #29-86

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

~

-~ 4 . PROCEDURES --NORMAL. ABNORMAL. EMERGENCY -Page~40

's -

'AND RADIOLOGICAL CONTROL ANSWER 4.07 (2.00)

1. RPV water level cannot be maintained above +8 inches'OR cannot be determined. -.

2. RPV pressure above 1060 psig.

3. Drywell pressure above 2.0 psig

4. A-condition which requires a reactor scram,'and reactor power is either:

a. above 6%

OR

b. cannot be determined.

(4 @ 0.5 ea = 2.0) ,

' REFERENCE DRESDEN - DEOP 100 ANSWER' 4.08 (1.75)

SRM's One in the core quadrant where fuel or control rods are being moved (0.5) and one in an adjacent quadrant (0,5)

IRM's-One in each reactor protection system trip channel may be

' bypassed with the following restrictions: (0.25)

1. at least one IRM must be in service in the core quadrant where refueling is taking place.(0.25)

2. No more +he one of the four center -IRM's may be bypassed during core alterations (0.25) (1.75)

REFERENCE DRESDEN - DFP 800-1

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) -

V

+.

' PROCEDURES - NORMAL .' ABNORMAL'.' EMERGENCY Page 41' AND RADIOLOGICAL CONTROL n

, LANSWER 4.09- ' ( l'. 00 ) .

Qualified Nuclear Engineer REFERENCE

~

~DRESDEN - DGP 3-4, page 7.

ANSWER 4.10 (2.00)-

1. When unstable ~ conditions exist.

2. If load must be dropped below the Low Megawatt Electric Limit.

3. If : load must be raised above the High Megawatt Electric' Limit.

~4. During weekly Turbine' Surveillance and Control Rod exercises.

'5. Loss of Control Rod indication or any rod movement.

6. Whenever there is any unusual reactor steam system pressure changes.

. - 7. If there are any unusual large condenser vaccuum problems.

i (any 4 @ 0.5 ea = 2.0)

( u,71 esme.J Sk , g&c ) AL su~d.s o.y ,;.,;-j th nid es h m y e y REFERENCE DRESDEN - DOP 5670-1, page 2.

4

' ANSWER 4.11 (0.50) 100 TO 135 F (any answer within this range is acceptable)

REFERENCE DRESDEN - DOP 5750-11, page 1. .

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

'4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY PaSa 42 MD RADIOLOGICAL CONTROL ANSWER 4.12 (1.00)

1. IMMEDIATELY' insert control rods until a period of 30 seconds or more

-is indicated. ,

2. Contact-the Shift Supervisor before continuing control rod withdrawal.

(2 @ 0.5 ea = 1.0)

REFERENCE DRESDEN - DGP 1-1, Attachment A.

ANSWER 4.13 (1.00)-

1. - Place the local scoop tube ON-OFF Switch to the OFF postion.

2. Place the local scoop tube ON-OFF Switch to the ON position.

(2 @ 0.5 ea = 1.0)

REFERENCE DRESDEN - DOP 202-12, page 3.

l -

l l

I I -

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

A PROCEDURES'- NORMAL.' ABNORMAL.' EMERGENCY Page 43 AND RADIOLOGICAL CONTROL AN3WER 4.14 (1.50)

1. If the unit is operating in Economic Generation Control, remove the unit from EGC operation in accordance with.

DOP. (DOP 5670-1 = Not required for full credit)

2. Stop any power increase is-in progress..

3. Check ejector off-gas flow on Ejector off-gass flow recorder.

4. If air ejector' flow is high, bypass the filter building and recombiner in accordance with DOP.

5. Dispatch an. Operator to shift the steam jet air efectors as appropriate in accordance with DOP.

6. Start the standby circulating water pump as appropriate.

7. -Reduce recirculation flow as necessary to. help maintain vacuum.

e. Trip hydrogen addition ( Unit 2 )

9. If loss of. vacuum is imminent, scram Unit.

(any 6 @ 0.25 en = 1.5).

. REFERENCE DRESDEN - DOA 3300-2, page 1.

ANSWER 4.15 (1.00)

1. The turbine will run back in two minutes to 7,380 stator amperes as seen on the generator.

2. The generator will trip in three minutes if stator amperes are still greater than 7,380.

(2 @ 0.5 ea = 1.0)

REFERENCE

~

-DRESDEN - DOP 5300-1, page 1.

l

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

' ~

v  :-

PROCEDURES - NORMAL. ABNORMAL. EMERGENCY' Paga 44 AND RADIOLOGICAL CONTROL ANSWER 4.16 (2.75)

UNIT 2

~

-1. Reduce the speed of the MG set 2A to the acceptable speed for single loop operation. (0.25)

2. Trip recirculation MG set 2B locally at Bus 32 (0.25)

3. As long as the reactor-remains in'a safe condition, do not (0.75) attempt to shut down until 125v DC can be restored.

UNIT 3

1. Manually scram the reactor and follow DPG 2-3. (0.75)

2. Trip all reactor building vent fans. (0.25)

\

3. Start either standby gas treatment train. (0.25)

4. Trip OCB's 9-10 and 10-11 locally at the 345 KV Switchyard. (0.25)

( w ,Il /,o m e 4 + r u <es~ a A D u ~ e f /ns i u~Id t d sf ~ A N REFERENCE DRESDEN - DOA 6900-2, pages 2 and 7.

(***** END OF CATEGORY 4 *****)

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

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cl6 " TEET.: CROSS REFERENCE

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I -QUESTION sl%kME REFERENCE

' 4~

A 1.01 3.00 ZZZOOOOO98 1.02 -1.00 ZZZ0000100' 1.03 1.00 .ZZZ0000101 y 1.04 1.00 ZZZ0000102  !-

1.05 1.'50 2Z20000105~

1.06 2.00 .ZZZ0000106 i 1.07 1.00 ZZZ0000108 ~

1.08 .1.50' ZZZ0000109 ,

7/ .1.09 1.50' ZZZ0000110 i

-1.10 2.00 ZZZ0000111 1.11 2.00 ZZZ0000112 1.12 ZZZ0000099 1.00 x 1.13 2.50 ZZZ0000103 '

1.14 1.50 ZZZ0000104 ~

1.15- .1.50 ZZZ0000107 7 L 24.00 >.

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2.00-

.- 2.01 ZZZ0000113 2.02 2.00- ZZ'0000114 2.03 1.00 ZZZ0000115 -

2.04 - 2.00 "' ZZZ0000116 2.05 2.00 ZZZ0000117 2.06 1.25- ZZZ0000118 2.07 1.50 ZZZ0000119 2.08 2.00 ZZZ0000120 2.09 2.00 ZZZ0000121 2.10 1.00 ZZZ0000122 2.11 l':50 ZZZ0000123 2.12 1.50 ZZZ0000124 2.13 1.00 ZZZ000012E 2.14 2.50 ZZZ0000126 2.15 2.00 ZZZ0000127 25.25 3.01 1.00 ZZZ0000142

. 3,02 2.50 ZZZ0000139 3.03 2.00 ZZZ0000128 3.04 2.00 ZZZ0000131 3.05 1.00 ZZZC000132 3.06 1.00 ZZZ0000133 3.07 1.50 ZZZ0000134 3.08 1.50 ZZZ0000135 3.09 1.00 ZZZ0000136 3.10 1.00 ZZZ0000137 3.11 2.75 ZZZ0000138 3.12 2.00 ZZZ0000129 3.13 1.75 ZZZ0000140 3.14 2.00 ZZZ0000141 .

3.15 2.00 ZZZ0000130 25.00 1 4.01 2.00 ZZZ0000144

c. --

TEST CROSS REFERENCE . Pcco 2 QUESTION VALUE REFERENCE.

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4.02 2.50 ZZZ0000143 4.03 1.00 ZZZ0000145 4.04 1.00 ZZZ0000146 4-05

. -2.50 ZZZ0000147.

4.06 1.00 ZZZ0000148 4.07 2.00 ZZZ0000149 4.08 1.75 ZZZ0000150 -

4.09 1.00 ZZZ0000151 4.10 2.00 ZZZ0000152 4.11 0.50 ZZZ0000153 4.12 1.00 ZZZ0000154 4.13 1.00 ZZZ0000155 4.14 1.50 ZZZ0000156 4.15' 1.00 ZZZ0000157

~4.16 2.75 ZZZ0000158 24.50 98.75 e , - - n , - - , -- g e v -

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION i s FACILITY: DRESDEN REACTOR TYPE: EEE-GE3

,j ==

4i DATE ADMINSTERED: 17/01/26

-< i .=,

ll l. i.i LE EXAMINER: BISHOP. M.

CANDIDATE INSTRUCTIONS TO 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 category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF l\

CATEGORY  % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.51 25.00 -25.10 "m 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS zs.sI

_g5.00 _;;_4g 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 2s.15 23. '1L "M--?5. -21. 7. PROCi2 MES - NORMAL, ABNORMAL,

" # EMERGENCY AND RADIOLOGICAL CONTROL 25,25 24.75 C' ?~ V 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS

, 99. DD Of E 25p  % Totals 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 sheet of the examination.

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

6. L e 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 new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

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

10. Skip at least three 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.

l 16. If parts of the examination are not clear as to intent, ask questions of the examiner 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 completed.

18.'When you complete your examination, you shall:

o

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 revoked.

e

-+. .. ,

1$. -T'EORY H OF NUCLEAR POWER PLANT OPERATION. Psca 4 ELUIDS.AND THERMODYNAMICS t

-QUESTION 5.01- (3.00)

< Match each of the following terms in_ Column "A" with the appropriate definition from Column "B". Use each choice only once. *

' Column A. -Column B Terms Definitions

1. Enthalpy a. The st' ate of a substance at which any further addition of' thermal

2. Condensate Depression energy will-result in vaporisation (boiling) at a constant temperature.

A further removal of thermal energy will result in lowering the.

3. Subcooled or Compressed temperature of the substance.

Liquid

b. The heat content of steam or water, expressed in Btu /lbm.

T -4. Latent Heat of Vaporisation c. A measure of the energy content of a substance which is unavailable for

5. Saturated Liquid conversion'to useful work.

6. Saturated Vapor d. The state of a liquid when its pressure is above the saturation

7. Superheated pressure for a given' temperature.

vapor

e. The state of a substance when the

8. Entropy . temperature of its vapor is above the saturation temperature for a given pressure,

f. The thermal energy which must be added or removed from a substance to change its state between saturated l .

liquid and saturated vapor.

! g. The state of a substance at which l

any further addition of thermal i energy will result in a tempera-ture increase of a vapor above the saturation temperature. If any heat is removed at this point, the l

f temperature will remain constant and the vapor will condense,

h. The subcooling of condensate below saturation temperature for a given pressure.

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

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6

-5. THEORY OF NUCLEAR POWER-PLANT OPERATION. Pega 5 FLUIDS.AHD_ THERMODYNAMICS QUESTION 5.02- (1.00)

=The quality of steam to the turbine refers to: (CHOOSE ONE)

~

a. The ratio of the liquid mass to the sum of the liquid and vapor masses.

.b. The. ratio of the vapor mass to the sum of the liquid and vapor masses.

c. The ratio of the vapor mass to the liquid mass.

d. The ratio of the liquid mass to the vapor mass.

QUESTION 5.03 (1.00)

Match the major form of heat transfer with the condition described.

Form of Heat Transfer (1) Radiation (2) Convection (3) Conduction CONDITION

a. Across a fuel pellet.

b. Fuel pellet to the cladding.

~

c. From the cladding to the coolant.

d. From fuel rod to fuel rod in a voided core.

i QUESTION 5.04 (1.00) l TRuen using the neutron monitoring instruments to identify j a partially uncovered core during accident conditions, the neutron flux Might show a drop-off as the detector enters the uncovered region of the core Why MIGHT this indication occur on the nuclear instruments?

l t

i 1

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

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5 ~. -TliEQBY OF' NUCLEAR POWER PLANT OPERATION. . Pass' 6

, FLUIDS.AND THERMODYNAMICS' j QUESTION' 5.05 (1.50)

a. What is the effect'of core age on the doppler coefficient of reactivity (MORE NEGATIVE or LESS NEGATIVE) choose one? (0.5)

b. . Explain why this change takes place'. (1.0)

QUESTION 5.06 (2.00)

TRUE.or FALSE 7 Answer the following concerning factors affecting control rod worth,

a. .The worth of a control rod is a direct function of.the thermal neutron flux.to which it is exposed.

b. A control rods worth decreases as moderator temperature increases,

c. As the void content inceases, the control rod worth increases.

d. .Controi rod worth increases as the fuel temperature' increases.

QUESTION -5.07 (1.00)

. Fill in blanks 1 and 2.

A control rod blade which is inserted < 1/3 into the core is referred to as a 1__ rod while a blade which is inserted > 2/3 into the core is referred to as a __2_ rod.

i QUESTION. 5.08 (1.50) i j Briefly explain how a control rod withdrawal of one or two notches can result in a decrease in bundle power.

l l

QUESTION 5.09 (1.50) ,

^

-What are TWO reasons for performing rod pattern exchanges?

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

'5. THEORY OF NUCLEAR POWER PLANT OPERATION. Paga 7 FLUIDS.AND THERMODYNAMICS QUESTION 5.10 (2.00)

Discuss how xenon changes for a reactor power increase from 50% to

'100%. Assume steady state operation at 50% power for two days prior to the maneuver. Include time frames and why they occur in your answer.

QUESTION 5.11 (2.00)

Refer to the attached Figure 1, Keff vs Exposure and explain why the change in Keff occurs from the following points:

(TWO reasons required for each set of points)

a. A to B

b. B to C

' QUESTION 5.12 (1.50)

Match the failure mechanism in Column 1 and the limiting condition from Column 2 with the associated power distribution limits (A-C) 8 below.

a. Linear. Heat Generation Rate (LHGR)

b. Average Planer Linear Heat Generation Rate (APLHGR)

.c. Minimum Critical Power Ratio (MCPR)

Column 1 Column 2

. Failure Mechanism Limiting Condition

1. Fuel clad cracking due to 1. 1% plastic strain lack of cooling caused by DNB.

2. Fuel clad cracking due to high 2. Prevent transition boiling stress from pellet expansion.

i 3. Grose clad failure due to decay 3. Limit clad temp. to 2200 F i heat and stored heat following a LOCA.

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

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5: T'HEORY OF NUCfRAR' POWER PLANT OPERATION. Pega 8 FLUIDS.AND THERMODYNAMICS QUESTION 5'.13 (2.00)

During a cooldown'of the reactor vessel-following a control room.

~ evacuation, reactor pressure decreates from 800 psig to.450 psig in 30 minutes.

a. What is the APPROXIMATE cooldown rate per-hour? .(1.5)

b. Has the tech. spec. cooldown limit been exceeded? Explain your answer. (0.5)

-QUESTION 5.14 (1.50)

-Provide a brief discussion how natural circulation flow is achieved in-

.the reactor. Include in your discussion the flow path and the. motive force for the flow.

QUESTION 5.15 (2.50)

a. What are the TWO primary sources of hydrogen following a design basis accident with core damage from inadequate cooling. Exact reactions are not required. (1;0)

.b. What are the THREE methods / systems utilized at Dresden to prevent combustion of hydrogen and oxygen following a LOCA? (1.5)

(***** END OF CATEGORY 5 *****)

g 1',

S B. ' PLANT SYSTEMS DESIGN. CONTRQL. AND INSTRUMENTATION Paga 9

~ QUESTION ~ '6.01 (3.00)

Concerning the Isolation Condenser System:

a. List THREE systems IN ORDER of preference which can supply makeup water to the shell side of the Isolation Condenser. (1.0)

b. What'are FOUR indications of a possible leak in the tube bundle of the Isolation Condenser? -(2.0)

QUESTION 6.02 (1.00)

What THREE conditions must be met in order for the Rod Worth Minimizer to be AUTOMATICALLY bypassed?

QUESTION 6.03 (2.50)

Concerning the Reactor Protection System;

a. The shift supervisor is approached by an electrician who wants to transfer the RPS "A" bus to its Reserve power supply in order to perform preventive maintenance on the MG set. The reactor is at 75% power and operating with a Half-Scram signal on RPS channel B due to an inoperable pressure transmitter. Should the shift supervisor authorize the transfer? EXPLAIN your answer. (1.0)

b. What THREE conditions will cause the Electrical Protection

~ Assemblies (EPA breakers) to open? (1.0)

c. Why is the RPS Reserve Power interlocked to prevent supplying both

- busses at the same time? (0.5)

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

B. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcca 10 3' .

S QUESTION! 1 6.04 .(0.50)

Concerning the Main Steam System

a. Explain why the main steam isolation valves (MSIVs) are set to close between three and five seconds.[1.0] -

b. Identify what systems provide air to the inboard and outboard MSIVs ? Include in your answer which air system supplies which (inboard and1 outboard) MSIVs [1.0]

c. What' design feature physically'causes the MSIV closing speed

.during EXERCISING to be much slower than normal closing speed ? [0.5]

QUESTION 6.05 (2.00) (

In'the recirculation flow control system: [

a. What are 4 conditions which will cause the scoop tube actuator to

" lock up" (setpoints not required.) [1.0] ?

b. What action must be taken by the control room operator prior to resetting a locked out scoop tube 7 (Include WHY this must be done in your answer.) [1.0]

QUESTION 6.06 (1.50)

What are five methods available to the operator in the control room to determine proper operation of the standby liquid control system after manual initiation 7 (Do NOT include annunciators or alarms)

" QUESTION 6.07 (1.25)

How is the automatic depressurization system (ADS) initiation logic for a leak inside the drywell DIFFERENT from a leak outside the drywell 7 Be specific and include all setpoints in your answer. ,

t '-

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. I s

-8. PLANT SYSTEMS DESIGN'.' CONTROL. AND' INSTRUMENTATION Pega 11 -

QUESTION 6.08 (1.50)

How'do-the diesel generator lubricating oil system and the cooling water system-combine to maintain the diesel engine in standby

. readiness (i.e. warmed up)? Include in your answer WHAT provides the motive forces for the individual systems in the standby.

. condition.

QUESTION - 6.09 (2.00)

List four automatic valve or pump actions,cther than main steam line isolation valve closure which occur as a result of a 3 times normal main steam line radiation signal.

QUESTION 6.10 (2.00)'

The plant is' operating at 100% power. A complete loss of instrument air occurs.

.With NO Operator action, answer the below questions?

A. The level in the hotwell would ( increase , decrease, remain the same ).

B. Service water flow to the TBCCW heat exchangers would ( increase ,

decrease, remain the same ).

C. Scram Discharge Vol. drain valves would ( open, close, remain as is ).

D. -Main feedwater regulating valves would ( open, close, remain as is ).

QUESTION 6.11 (2.00) l Identify which group isolation would affect each of the below

!. systems / components.

I A. Isolation condenser condensate return valves.

B. Shutdown cooling isolation valves.

C. - HPCI auxiliary oil pump interlocks against an auto start.

D. Drywell air sample isolation valves.

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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~6: PLANT' SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcgo 12 QUESTION 6.12 (1.00)

Assume a core spray initiation signal is-present, list the trips.

available for the 2A Core Spray Pump. Setpoints are not required!

QUESTION 6.13 (2.75)

A. The recire pump speed control mismatch circuitry prevents exceeding a a.  %~ speed mismatch between the two recire pumps. (0.25)-

lB. What is the primary and secondary reason speed mismatch is. limited 7. (1.0)

C. What protective function occurs if the mismatch exceeds the limits established in a. above? (0.5)

D. Under what conditions will the circuit trip a recire pump? (0.5)

E. What function (associated with mismatch) allows restart of an idle

. recire; pump? (0.5)

(***** END OF CATEGORY 6 *****)

7. FROCEDURES-- NORMAL. ABNORMAL. EMERGENCY Peca 13 AND RADIOLOGICAL CONTROL I

QUESTION 7.01- (1.50)

DEOP 100-2, RPV Pressu e C'nt' as the-operators verify that Steam Cooling is-NOT requir . criteria are used to determine-that Steam Cooling i REQUIRED? (Include applicable setpoints)

QUESTION 7.02 (1.50)

What are THREE of the four immediate operator actions per DOA 3700-1 for a total loss of Reactor Building Closed Cooling water? (Include applicable setpoints)

-QUESTION 7.03 (1.50)

a. Complete the following statements;

1. Immediate operator actions for a Recirculation Pump trip (DOA 202-1) require the Unit 2 NSO to reduce running pump speed to (blank) percent of rated speed. (0.5)

2. If the same incident occurred on Unit 3, the NSO would be required to reduce running pump speed to (blank) percent of rated. (0.5)

b. Why must the Unit 2 recirculation pump be operated at a different speed than the Unit 3 pump during single loop operation? (0.5)

QUESTION 7.04 (1.00)

According to Operating Order #1-86, what immediate action is to be performed by the NSO when a Unit 2 Reactor Building Ventilation Radiation Monitor initiates the Standby Gas Treatment train?

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

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75 PROCEDURM - NORMAL. ABNORMAL. EMERGENCY- Pcga 14 AND RADIOLOGICAL CONTROL q

QUESTION 7.05 (2.50)

~

'What are the.FIVE entry conditions for'DEOP 200,. Primary Containment Control? (Include applicable'setpoints) ,

QUESTION 7.06 (1.50) i When refueling operations are being performed with the shield blocks removed and the reactor head off, what restrictions apply to personnel on the refuel floor ...

a.:during suberitical checks or operations which require withdrawal of one control-rod?

b. during performance'of Shutdown Margin checks?.

. QUESTION. 7,07 (2.00)-

According to DEOP.400-3 RPV' Flooding, when is BORON injection required? (Include applicable setpoints)

QUESTION 7.08 (2.00)

One of the entry conditions for DEOP 300 is "Offsite radiactivity release is expected to reach GSEP ALERT level." What are FOUR indications which are used to verify this condition?

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

7. FROCEDURES --NORMAL. ABNORMAL. EMERGENCY Paco 15 RID RADIOLOGICAL CONTERL QUESTION 7.09. (2.00)

a. During operation at 80% power an event causes feedwater temperature to decrease 25 F. What specific operator qction is required by the feedwater temperature decrease 7.(Include applicable setpoints)

b. Fill in the blanks with the correct choice from the lists provided:

The cause of the event cannot be corrected and feedwater  ;

temperature continues to decrease. If the temperature drops more than a F, then b .

Choices for a: Choices for b:

1. 70 1. Scram reactor.

2.-100 2. Insert CRAM arrays -

3. 130 3. Trip turbine

4. 160 4. Reduce power to < 25%

QUESTION 7.10 (1.50)

A-turbine trip setpoint has been exceeded. Turbine speed is not decreasing and the main steam valves (MSV) are open.

Per procedure DOA 5600-1, Turbine trip, What three actions are required ?

QUESTION 7.11 (2.00)

While monitoring the control room panels an operator discovers

. the generator is carrying less load. The unit is stable and no alarms have come in. While verifying other instruments, core flow is noticed to be higher than normal. What has occured ?

Explain why this problem causes the above indications.

QUESTION 7.12 (1.00)

Per DOA 600-1. Transient level control, when must the reactor be manually scrammed on an increasing level transient ?

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

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]

7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pcce 16 AND RADIOLOGICAL CONTROL QUESTION- 7.13 .(1.00)

A requirement of DOA 040-1, Slow Leak, is to. shutdown hydrogen

. addition (Unit 2 only). Why is this done 7 QUESTION. 7.14 (1.00)

DOP 1-1, Normal Unit-Startup, contains the step: Prior to reaching 500.psig verify that the MSIVs are open and the low vacuum alarm has cleared. -This is performed because: (Choose the correct answer)

a. a full scram will result if it is not, b.,it prevents excessive pressure across MSIVs.

c. it allows even'heatup of steam lines down stream of MSIVs.

. d. it' allows required testing of radiation monitors in the off gas system.

QUESTION. 7.15 -(2.75)

List the Immediate Operator Actions for EACH Unit upon a loss of 125v DC power supply. DOA 6900-2

(***** END OF CATEGORY 7 *****)

• ~

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. Pcsa 17:

AND LIMITATIONE

-QUESTION 8.01 (1.00)

What is the MAXIMUM valid length.that each of the following may remain

'in effect according to CECO Radiation Protection Standards?

a. Type 1 RWP

b. Type 2 RWP QUESTION 8.02 (2.00)

What are the Dresden radiation worker ADMINISTRATIVE limits for external whole body penetrating radiation for each of the following

. time periods? [Do not consider 5(N-18) limits.]

a. Daily

b. Weekly

^

c. Quarterly

d. Yearly

-QUESTION 8.03 (2.75)

According to EPIP 200-20, Control Room Evacuation / Shutdown,

a. WHY is the mode switch left in RUN after scramming the reactor?

(0,5)

b. What THREE additional actions must be performed by the NSO before leaving the control room when evacuation of the main control room is required? (2.25)

QUESTION 8.04 (1.50)

If a " temporary SYSTEM alteration" is required to be implemented on a weekend, what 3 conditions must be met to comply with DAP-7-4, Control of Temporary System Alterations?

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

F .

^ ~ 8 .' ADMINISTRATIVE PROCEDURES. CONDITIONS. Pega 18 AND LIMITATIONS QUESTION 8.05 (1.50)

What three " state and-federal" agencies are always notified if a GSEP classified event occurs, per EPIP 100-01, Station Director

• Checklist of Initial GSEP Responsibilities?

QUESTION 8.06 (3.00) a..For unit 2 and unit 3 what are the Tech Spec limits and actions for identified and unidentified leakage from the primary system ?

[1.0)

b. For the intent of the Tech Specs, how does the operator determine identified and unidentified leakage ? [0.5] ,

c. What additional limits and requirements are placed on unit 2 leak rates ? [1.0) ,

d. What additional limit and requirement are placed on unit 3 leak

- rates ?.[0.5]

QUESTION 8.07 (2.00)

Concerning control rods:

a. List 3 conditions that, per the Tech Specs, will cause the rod to be inoperable,

b. How many control rods may be inoperable during power operations ?

l QUESTION 8.08 (1.50) i With fuel in the reactor, The Standby Liquid Control system is required to be operable unless what 3 conditions are met ?

I QUESTION 8.09 (1.00) .

Under what condition may verbal a out-of-service request be

[- authorized for a " safety related" work request package ?

I l

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l.

, () '

- B. 'AbMINISTRATIVE PROCEDURES. CONDITIONS. Peca 19 AND LIMITATIONS

.Q EU STION 8.10 .(2.00)-

Identify.each of the following as TRUE or FALSE.

a. Personnel-protection cards alone are sufficient to protect personnel for locally operated equipment.

b. Personnel protection cards may.be transfered to another crew but must not tur transfered to another job.

, c..The " Competent Individual" signing the "After Outage" portion of an Equipment Outage Checklist confirms the outage checklist is-adequate.

d. An outage may not be partially cleared.

QUESTION 8.11 (1.0C)

Per the Dresden Tech Specs, when must the isolation condenser be operable ?

' QUESTION: 8.12 (1.00)

According to DAP 7-3, Operating Orders,

a. Who may initiate an daily order ?

b. Who must approve any daily order ?

QUESTION- 8.13 (1.00)

Operating Order #38-86 supplies specific instructions to ensure a motor operated throttle valve fully closes.

What are the instructions ?

QUESTION 8.14 (1.00) .

What action is required to be taken (including time requirement) after the receipt of an equipment drain sump (outside the.drywell) high level.

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

Pasa 20 8? ADMINISTRATIVE PROCEDURES. CONDITIONS.

AND LIMITATIONS QUESTION 8.15 (1.00)

According to the Unit 3 Tech Specs;

a. What is the basis for the maximum torus (suppression p6ol) water volume of 115,655 cubic feet ? [0.5]

b. What is the basis for the minimum. torus (suppression pool) water volume of 112,000 cubic feet 7 [0.5]

QUESTION 8.16 (1.50)

For each of the plant-conditions listed below indicate what actions are required by Unit 3 Tech Specs. (Include applicable setpoints and times)

a. HPCI' system in operation for surveillance testing and suppression pool temperature reaches 105 F. [0.75]

b. Reactor.is at 70 % power and suppression pool temperature reaches 110 F.

[0.25]

.c. Reactor has just scrammed due to a spurious group I isolation and suppression pool temperature reaches 120 F. [0.5]

(***** END OF CATEGORY 8 *****)

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

e.

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t 3

et

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3

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- $w 5

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. ~ . , . - , . . , - . ~ . . . , , , . . - - , . _ . . , , . , . - , , , . , - . ,-_,.,,,-.,_,,_._.,,n__.,_.-.,_-,.,,-.....__n, , - .,,,_,,._,,.n. , . _ _ _ . _ . _ _ , . .

,.~ . -. -..

/

, EQUATION SHEET

~.

f = ma v = s/t '

2 *I '

w = as Cycle efficiency =

s = v,e + ' Isac E = aC -

a =_(vg - y )/t 2 ,,{ A = AN EE = hav ,g ,Vg A = A,e'

• FE = agh a = e/c 1 = in 2/cq = 0.693/tg ,

w = v&P , , , ,

. t N(eff) = (e,,)(e,)

AE = 931Am .

(tg+t)h k " k AT p ,

g = Ig ,4X ,

= UAAT I = g -ux g , ,

• Pur = W g m" ~

, I = I, 10

• y=y to M (CI- TYL = 1.3/u y=y .t/T

• HVL s 0.693/u o .

• SUR = 26.06/7 I T = 1.44 DT SCR = S/(1 - K,gg)

/1 *I si SUR = 26 l j CR x = S/(1 - K,gg )

\ g , ,J ~

T = (1*/o ) + [(f *g)/1,g,p} 1( *ff}l = CR 2C1 ~ Xef*)2 T,= 1*/ (p - T) M " 1/CI ~ Keff) = CR /CR0 g T = (I - p)/ 1,ggo

( g " (g ~ K eff)0 /(1 ~ Keff)1 8 " (Eeff"I) eff " #eff/Keff SDM = (1 . g,gg)/g,gg p= [1*/TK,"gg -] + [I/(1 + 1,ggT )] 1* = 1 x 10" seconds F = I4V/(3 x 10 0) 1,ggA= 0.1 seconds" g=m Idgg=Id22 WATER PARAMETERS Id g =Id2 1 gal. = 8.345 1ha 2 R/hr = (0.5 CE)/d g,,,,,,)

1 gal. = 3.78 liters R/hr = 6 CE/d (feet) .

1 fc3 = 7.48 gal. MISCELLANEOUS CONVERSIONS ,

Density = 62.4 lbm/ft 1 Cu-ia = 3.7 x 1010dps 3

Density = 1 gm/cm 1 kg = 2.21 1ha Heat of valorization = 970 teu/lba 1 hp = 2.54 x 10 3BTU /hr 6

Hest of fusien = 144 Beu/lba 1 Hw = 3.41 x 10 Beu/hr 1 Atm = 14.7 psi = 29.9 in. I'g. 1 Stu = 778 *t-lbf 1 ft. H 2O = 0.4333 lbf/in 1' inch = 2.54 cm F = 9/5 C + 32 "C = 3/9 ('T - 32)

. , . , , _ . , - . . . _ . - _ _ . - - _ _ . _ . . , _ , , . , _ _ , . _ _ _ .,,..,_,_.-,,..._.m_.,_,,_.___.___.__..,_., . _ _ , _ - . . . . . _ , - _ _ . . _ , , , - , _ _ , , . , _ _ _ _ - _

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

Emhe8py, StwM Emtery, taunt a F Wesume,ft8 At

% weeer Evne 5seem water tve, 9 teem Weser tve, Seoem T a, a, a, 4, 4, e,

-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 A01602 3305 3305 at 0.088M 3.00 1073J 1076.8 0.0061 2.1706 2.1767 35 0.01402 2945 2948 2.1432 2.1594 40 35 OA9991 8 03 1071.0 1079.0 0.0162 0.12163 0 01602 2446 2446 0 0262 2.1164 2.1426 45 40 2037.8 13.04 1068.1 1081.2 45 0.14744 0.01602 2037.7 0.0161 2.0901 2.1262 50 1704.8 18.05 1065.3 1083.4 to 0.17796 0.01602 1704J 1087.7 0.0 M 5 2.0391 2.0946 60 1207.6 1207.6 28.06 1059.7 80 0.2561 0.01603 868.4 38.05 1054.0 1092.1 0.0745* 1.9900 2.0645 70 10 0.3629 0.01605 868.3 1096.4 0A932 1.9426 2.0359 80 633J 633.3 48.04 1048.4 041607 1AD70 2.0006 80 0.5068 58.02 1042.7 1100A 0.1115 to 1

0.01610 468.1 448.1 1A530 1.9825 100 d

to 0.1981 48 00 1037.1 1105.1 0.1295 0.M92 0.01613 350.4 350.4 1A106 1.9577 age 100 77.98 1031.4 1109J 0.1472 1J750 E01617 265.4 265.4 l als 1.7693 1.9339 120 87.97 1025.6 1113.6 0.1444 OA1620 203.25 203.24 1.9112 130 las 1A927 157.32 157.33 97.N 1019A 1117A 0.1817 1.7295 130 2.2230 0.01625 1122.0 0.1985 1.6910 1.8895 140 122.98 123AO 107.95 1014.0 540 2.8892 0.01629 97.07 117.95 2006.2 1126.1 0.2150 1.6536 1.0606 150 180 3.718 0.01634 97.05 E2313 1.6174 13487 ges 77.27 77.29 127.96 10022 1130.2 340 4.741 OA1640 996.2 1134.2 0.2473 1.5822 1.8295 175" 62.04 62.06 137.97

170 5.993 OA1645 50.22 144.00 930.2 1138.2 0.2631 1.5480 13111 180 380 7.511 0.01651 50.21 0.2787 1A148 1.7934 190 40.94 40.N 158.04 984.1 1142.1 j

100 9.340 041657 1144.0 0.2940 1.4824 1.7744 300

( 0.01664 3342 33.44 168A9 977.9 300 11.526 971.6 1149.7 0.3001 1.4500 1.7600 210 0.01671 27.80 27.82 174.15 330 14.123 970J 1150.5 OJ121 1.4447 1.5 88 212 0.01672 26.78 26.80 180.17 330 212 14.606 966.2 1153.4 0.3241 1.4201 1.7442 OA1678 23.13 23.15 188.23 330 320 17.186 958 7 1157.1 0.3388 1.3902 1.7290 0.01685 19.364 19.381 198J3 1.7142 See 230 20.779 952.1 1180.6 OJ533 1.3600 0.01693 16.304 14.321 208.45 380 240 24.968 945.4 1164A E3877 1.3323 1.7000 041701 13.802 13.419 218.59 300 29A25 228.76 938 6 1167.4 0.3819 1.3043 1.6882 380 0.01709 11.745 11.762 1A729 270 260 35.427 10.060 238.95 931.7 1170.6 0J980 1.2760 270 41.854 0.01718 10.042 0.4098 1.2501 1.6699 ISO S.427 8.444 249.17 924.6 1173A 300 49.200 0.01726 1176A 0.4236 1.2238 1.6473 290 7.443 7.440 259.4 917.4 390 57.550 0A1736 1179.7 0.4372 1.1979 1.4351 300 6.448 6.446 269.7 910.0 300 47.005 041745 1182.5 0.4506 1.1726 1.6232 310 5.609 5.626 280.0 902.5 310 77.67 0.01755 1185.2 0.4640 1.1477 1.6116 320 4.896 4.914 290.4 894.8 320 89.64 0.01766 1190.1 0.4902 1.0990 1.5892 340 3.770 3.788 311.3 878.8 340 117.99 0.01787 1194.4 0.5161 1.0517 1.5678 360 2.939 2.957 332.3 862.1 360 153.01 0.01811 1198.0 0.5416 1.0057 1.5473 300 2.317 2J35 353.6 844.5 340 195.73 0.01436 1201.0 0.5667 0.9607 1.5274 400 1.8444 IJ630 375.1 825.9 400 247.26 0.01864 1203.1 0.5915 0.9165 1.5080 420 1.4808 1.4997 396.9 806.2 440 420 308.78 0.01894 1204.4 OA161 0.8729 1.4890 1.1976 1.2169 419.0 785.4 460 i

440 381.54 0.01926 1204.8 0.6405 0.8299 1.4704 t .

0.9746 0.9942 441.5 763.2 480 440 466.9 0.0196 739.6 1204.1 0.4648 0.7871 1.4516 l 0.7972 0A172 444.5 480 564.2 0.0200

( 714.3 1202.2 0.8890 0.7443 1.4333 500 0.0204 04545 0.6749 467.9 1.4144 520 500 680.9 0.5596 512A 687.0 1199.0 0.7133 0.7013 520 - 812.5 0.0209 0.5386 0.7378 0.6577 1.3954 540 0.4651 536.5 657.5 1194.3 540 962.8 0.0215 0.4437 0.7625 0.6132 1.3757 560 0.3871 562.4 625.3 1187.7 560 1133.4 0.0221 0.3651 589.1 589.9 1179.0 0.7876 0.5673 1J550 500 0.0228 0.2994 0.3222 540 1326.2 550.6 1167.7 0 8134 0.5196 1.3330 600 0.2428 0.2675 617.1 1.3092 620 400 1543.2 0.0236 506.3 1153.2 0.8403 0.46S9 l

0.1962 0.2208 646.9 620 1786.9 0 0247 679.1 454.6 1133.7 0.8666 0.4134 1.2821 640 l 0.0260 0.1543 0.1802 0.3502 1.2498 660

' 640 2051 9 714.9 392.1 1107.0 0.8995 0 0277 0.1166 0.1443 1.2066 480 660 2165.7 0.0008 0.1112 758 5 310.1 1068.5 0.9365 0.2720 i

640 2700.6 0.0304

(

• 172.7 995.2 0.9901 0.1490 1.1390 700 0.0386 0.0752 822.4 700 3094.3 0 0366 0 906.0 1.0612 0 1.0612 705.5 0.0508 0 0.0508 906.0 705.5 2208.2 l

TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED l

' WATER (TEMPERATURE)

A.3

L5. TMEORY OF NUCLEAR POWER' PLANT OPERATION. Paco 21

-FLUIDS.AND THERMODYNAMICS ANSWER 5.01' (3.00)  !

1. B

~

2. H

3. D

~

4. F

5. A

6. G

7. E

8. C [8 @ 0.375 each = 3.0]

REFERENCE Dresden, Lesson Plan Thermo, HTFF, PP. 4 and 5 ANSWER 5.02 (1.00) b.

REFERENCE Dresden, Lesson Plan Thermo, HTFF, P. 5 ANSWER 5.03 (1.00)

a. 3

b. 4Z

c. 2 l'

[4 @ 0.25 each = 1.0]

d. 1 i

i

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5 .- ~ THE'ORY OF NUCLFAR POWER PLANT OPERATION. P ga 22' FLUIDS.AND THERMODYNAMICS REFERENCE Dresden, Lesson Plan Thermo, HTFF, PP. 14-16 ANSWER 5.04 (1.00)

With a loss of water level,.the instruments which indicate the thermal flux would be in a fast-flux field and indicating low.

REFERENCE Dresden, Lesson Plan, Degraded Core Response, P. 5 ANSWER 5.05 (1.50)

a. More Negative (0.5)

b. Because of the buildup of PU 240 (which is a large resonance

. absorbe.r) . (1.0)

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 32 ANSWER 5.06 (2.00)

a. -TRUE

b. FALSE

c. FALSE

d. FALSE 4 @ 0.5 each : 2.0 REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 36

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5. T'HEORY OF NUCLEAR POWER PLANT OPERATION. Page 23 FLUIDS.AND THERMODYNAMICS ANSWER 5.07 (1.00)

1. Shallow

2. Deep [2 @ 0.5 each = 1.0] -

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 38 ANSWER 5.08 (l.50) (

The steam bubbles generated by withdrawal of a shallow rod increase the void fraction, which adds negative reactivity off-setting the positive reactivity effects of the rod withdrawal.

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, P. 39 ANSWER 5.09 (1.50)

1. Maximize fuel burnout (by flattening the flux). ( 0. 7 5 )-

2. Limit the power peaking (that would occur from a subsequent rod withdrawal after the buildup of Pu-239). -(C 70'F

.3 . Esuohits Un/ A'.ol L:9ese*-

REFERENCE ( +7 2d 004 Dresden, Lesson Plan, Reactor Physics Review, P. 41 Ores h.- Lass.~ A,~ , C dr.: A'ed Ol~ h e.J 4 ; .. pa,j,_ l,,,, g,,,g y p ANSWER 5.10 (2.00)

The initial power increase will cause a decrease in the xenon concentration (0.5]. The low peak occurs 4-6 hours after the power increase [0.5]. The power production term takes over [0.5] and a new equilibrium level is reached in 40-50 hours [0.5].

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

• ~ Pcga 24 5m THEQRY OF NUCLEAR POWER PLANT OPERATION.

FLUIDS.AND THERMODYNAMICS REFERENCE Dresden, Lesson Plan', Reactor Physics Review, P. 45 ANSWER 5.11 (2.00) -

a. 1. Buildup of xenon.

2. Buildup of samarium.

b. 1. Gadolina burnup.

2. PU-239 buildup. [4 @ 0.5 each = 2.0)

REFERENCE Dresden, Lesson Plan, Reactor Physics Review, Figure 62, P. 47 ANSWER 5.12 (1.50)

Column 1 Column 2 Failure Mechanism Limiting Condition

a. LHGR 2 1

b. APLHGR 3 3

c. MCPR 1 2

[6 @ 0.25 each = 1.5]

REFERENC'E Dresden, Lesson Plant Thermo, HTFF, Figure 11

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

}

5. TkEORY OF NUCLEAR POWER PLANT OPERATION. Para 25 FLUIDS.AND THERMODYNAMICS

- ANSWER 5.13 (2.00)

a. 800 psig + 14.7 = 815 psig [0.25]

450 psig + 14.7 = 465 psig [0.25] ,

From Steam Tables 815 psig = 520 F [0.25]

465 psig = 460 F [0.25]

60 F 120 F 520 - 460 = ---- X 2 = -----

[0.5]

1/2 hr. Hour

b. No. [0.25] The cooldown rate limit of 100 F is averaged over a one-hour' period. [0.25]

(w;tl sho se,qi fis l$ f rap e&A- Es W=lb REFERENCE Dresden, Requal Q/A Thermo, P. 6 Dresden, Tech. Spec. 3.6.A.1

-ANSWER 5.14 (1.50)

As the water around the fuel is heated, it expands and becomes less dense (0.5]. The (weight) or downward force on the water in the downcomer area exceeds the force exerted by gravity on the water in the core [0,5]. The water in the jet pumps is pulled downward by gravity forcing the water in the core upward [0.5].

REFERENCE Dresden. Lesson Plan Thermo, HTFF, P. 15 i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

---

w- - . . _ . , - - - - - , , - . , , - . - , , . , ,, ,, , ,-,,,,n.. ,

- , . . . . - - ,,. ,,,,,,,,7

-5. Pcgo'26 YHEORY OF NU6 EAR POWER PLANT OPERATION.

FLUIDS.AND THEBdODYNAMICS ANSWER 5.15 (2.50)

a. 1. (Primary Source) is from the Zire, water reaction from cladding overheating. .

2. Radiolytic decomposition of water from fission product

-radiation,

b. 1. Containment inerted with nitrogen.

2. Dilution of volume in containment with compressed air from ACAD system.

3. Venting containment volume off-through the Standby Gas Treatment System.

[5 @ 0.5 each = 2.5]

P.EFERENCE -

Dresden, Lesson Plan, Degraded Core Response, PP. 2-4

(***** END OF CATEGORY 5 *****)

L9 Pcco 27=

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION

~ ANSWER 6.01 (3.00)

a. 1. Clean domineralized water system

2. Condensate transfer system

3. Service Water / Fire Protection system

[ 3 9 0.25 each + 0.25 for correct order = 1.0 total ]

b. Any 4 of the following @ 0.5 each;

1. High temperature in the inlet steam line

2. High shell water temperature

3. Increasing shell water temperature

4. Increasing loacal radiation levels

5. Increased noise in condenser area

6. Steam or fog coming out the vent on the side of the reactor building i heofLl=*J he., ',o- MA: %sn. so/- nfe /ml

• REFERENCE Dresden, Student Text #3, P. 12-3 thru 12-5, & 12-10 6.*,4 fre< *hw, doA t.soo L h.r. 4, hLu 4, le 7 b Me. WJ h ff /f3 ANSWER 6.02 (l.00)

1. Steam flow above 20% [0.33]

2. Feed flow above 10% [0.33]

3. 60 second timer timed out (0.33]

REFERENCE Dresden, Student Text #1, P. 8-7 and lesson plan pg. 5

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcca 28

^

ANSWER ~6.03 (2.50)

a. 'No [0.25], power to the RPS bus will be interupted during the transfer and a full reactor scram will reult. [0.75] .

.b. 1. Overvoltage

2. Undervoltage

3. Underfrequency

[ 3 @ 0.33 each ]

o.25 c.s.To prevent overloading the reserve instrument transformer EG-6-3

z. To prey e wal~hh~ o/ 4 ~ $/s h.> C 4;/.**- *P s s. + a e p s g

• • ,M p**46** 6*** me f wd e. stron, ) (p, g S)

REFERENCE Dresden, Student Text #1, P. 15-4 & 15-5 Dre a/r jwm f/~, JC.1/*otrial 431 $}.rd.,,fu.7',S/g,g,s,z,), pg, ANSWER 6.04 (2.50)

a. Five seconds is fast enough to prevent a gross release of fission products to the environs [0.5]. Three seconds is slow enough to minimize the severity of the pressure transient resulting from an isolation (0.5]

L h J.k**f Spl~s

b. Qw Inboard - e_ /_ :;11 p..:=: tim -istc= [0.5] ,

' outboard -- instrument air system [0.5]

c. The test valve exhaust line contains an orifice which bleeds the

~

air off slowly [0.5]

REFERENCE Dresden Student Text #2, Chap. 3, pg. 12 & 13

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pega 29 ANSWER 6.05 (2.00)

a. Any four of the following @ 0.25 ea.

. Function generator signal failure .

Drive motor bus low voltage

. Coupling lube oil low pressure (16 second time delay)

. Coupling lube oil high temp.

. Loss of power to scoop tube positioner.

. //we I %&

b. Null voltmeter is used to match the speed from the tachometer with the speed demand from the speed controller [0.5) in order to prevent a flow transient during reset (0.5].

REFERENCE Dresden Student Text. Book 2, Chap. 2, pg 22 and table 1.

Dea sJn goaaJaw, pop 2,s..;1,. f u,3 , fac&e js ,y 4 .r w s q ;,,b. O , w L Lt. A4. y 3f+.

ANSWER 6.06 (1.50)

Any five of the following @ 0.3 ea.

. Pump discharge pressure

. Pump indicating light illuminates

. Tank level decreases.

. Squib valve indicating lights extinguished

. flow indicator

, pcwer decreases

, reactor water cleanup isolation.

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

i

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

6. PLANT SYSTEMS DESIGN. CONTROL AND INSTRUMENTATION Paca 33

' REFERENCE Dresden Student Text s3, pg 3-12 thru 3-15 ANSWER 6.07 (1.25)

Leak inside drywell:

120 sec. [0.25] after low RPV water level of -59 in. [0.25] and high drywell pressure of +2 psig [0.25].

Leak outside drywell:

8.5 minutes [0.25] after low RPV water level of -59 in. [0.25].

REFERENCE Dresden Student Text #3, pg 11-5 ans 11-6.

ANSWER 6.08 (l.50)

The electric immersion heater in the cooling water system heats the cooling water [0.5] which circulates through the-system and the lube oil cooler via natural circulation [0.5]. The lube oil circulating oil pump forces oil through the lube oil cooler and back to the sump to keep the lube oil system warm [0.5]

REFERENCE Dresden Student Text #2, pg 15-5 ANSWER 6.09 (2.00)

. A*n % Joes. 6 *~ .*/m ewA Any four of the following @ 0.5 ea. ' 74 j, ,,,4,. cust

. Chimney isolation valve closes , g

. Air ejector suction valve closes I , si,m ys . ,,or-

. Mechanical vacuum pump trips

. The off-gas line drain valve closes

. The off-gas sample vacuum pump suction valve closes A

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6. 1$LANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 31 e

REFEPINCE Dresden Student Text #2, pg 16-3 pr4J ~ bar" i% Cnde<~ars-r- sp t~s . &ble E.

drede lesse~ t % ,, Zsa L f** LJ+e , . %t: gj, c, ANSWER 6.10 (2.00) .

A. Decrease B. Increase C. Close D. Remain as is (4 @ 0.5 ea = 2.0)

REFERENCE DRESDEN - Student Text. Book 4, Chapter 3, page 14.

ANSWER 6.11 (2.00)

A. GROUP V B. GROUP III C. GROUP IV D. GROUP II (4 @ 0.5 ea = 2.0)

REFERENCE DRESDEN - Student Text, Book 3, Chapter 16, page 60.

ANSWER 6.12 (1.00)

1. Instantaneous Overcurrent

2. Time-delay Overcurrrent 4 o. zs

3. Undervoltage (3 9 0.^7 ea = 1.0)

4. $ Lolly $~ , w/ . AH- s . A A .

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcg2 32 REFERENCE DRESDEN - Student Text, Book 3, Chapter 13, page 4.

ANSWER 6.13 (2.75)

A. 10% (0.25)

B. Primary: to avoid confusing the LPCI loop select logic (0.5)

Secondary: To prevent flow-induced vibration in the jet pumps (0.5)

C. Prevents the high speed pump from increasing and the low speed pump from decreasing. (0.5)

D. If the mismatch exceeds 10% and the discharge valve on the low speed pump is closed. (0.5)

E. A time delay. (0.5)

REFERENCE Dresden Student Text #2, Book 2, PP. 12-14

(***** END OF CATEGORY 6 *****)

u

I i PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pro 33 AND RADIOLOGICAL CONTROL

~~-- ,

ANSWER 7.01 (1.50) 1

1. Any injection systen is nni

2. Reactor lev 'can m a e above -143 inches

3. Resctor pr ' r a less than 80 psig

[ 3 0 0.5 each ]

REFERENCE Dresden. DEOP 100-2 RPV Pressure Control, P. 3 k-ANSWER 7.02 (1.50)

Any 3 of the following 9 0.5 each;

1. Attempt to restore RBCCW flow

2. If flow is lost and cannot be restored within one minute, trip recirculation pumps A and B

3. Manually scram the reactor if equipment damage appears imminent

4. If drywell pressure reaches +2 psig, verify a reactor scram, enter DEOP 100 and DEOP 200.

REFERENCE Dresden, DOA 3700-1 Loss of RBCCW, P. 1

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

' c. ;

i. 7 ." 14to := 4 kiA'- NORMAL, ABNORMAL. EMERGENCY Pcco 34 AND RADIOLOGICAL _ CONTROL

. ANSWER 7.03 -(1.50)

a. 1. - 43 ,

l

2. 60

[ 2 9 0.5 each ]

b. Unit 2 has a different jet pump riser bracket (0.25] which allows larger vibrations during single loop operation (0.25]

REFERENCE Dresden, DOA 202-1 Recirculation Pump Trip, P. 4 ANSWER 7.04 (1.00)  ;

A high radiation trip is inserted on the Unit 3 Reactor Building Ventilation (or the Reactor Building Fuel Pool) radiation indicator and trip unit.

1 REFERENCE Dresden. Operating Order #1-86, July 1. 1986 t:

ANSWER 7.05 (2.50) l

1. Torus water temperature above 95 des F

2. Drywell temperature above 200 des F l

3. Drywell pressure above 2.0 psig l

^

4. Torus water level above -1.5 inches  ;

5. Torus water level below Tech Spec minimum (fig. 2-9) ,

( 5 9 0.5 each ] >

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) l l

r, 4, .

7.'~NROCEDUDER - NORMAL. ABNORMAL. EMERGENCY Pasa 35

=AND RADIOLOGICAL CONTROL REFERENCE

'Dresden, DEOP 200 Primary Containment Control P. 3 ANSWER 7.06 (1.50)

a. Personnel must stay out of line of sight of the reactor core.

(Also accept; Clear the refuel floor) (0.75)

b. All personnel must clear the refuel floor. (0.75)

REFERENCE Dresden DFP 800-1, Unit 2(3) Haster Refueling Procedure, Rev 12, P. 3 ANSWER 7.07 (2.00)

Reactor cannot be shutdown and reactor power is >6% or unknown (1.0) before Torus water temperature reaches 110 des F (1.0]

(also accept; All control rods are not inserted to or beyond Position 04 (1.0) and Torus water temperature cannot be maintained below 110 des F (1.0) )

REFERENCE Dresden. DEOP 400-3 RPV Flooding, P. 4

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

r

'7. PROCEDUprn - NORMAL. ABHORMAL. EMERGENCY Paco 36 AND RADIOLOGICAL CONTROL ANSWER 7.08 (2.00)

1. Chimney SPING .

2. Chimney G.E. Monitor

3. Reactor Building Vent SPING

4. Sample by Station Chemist 4 0 0.5 ea = 2.0 REFERENCE Dresden, DEOP 300 Sec Containment / Rad Release Control, P. 3 ANSWER 7.09 (2.00)

a. Reduce core flow 7.5 MLEM/hr (or Reduce core flow 3 MLBM/hr per 10 F drop.) (1.0]

b. a. 3 (130) (0.5] b. 1. (Scram reactor) (0.5]

REFERENCE Dresden DOA 3500-2 ANSWER 7.10 (1.50)

Scram the reactor (0.5)

Close the main steam isolation valves (MSIV) (0.5]

Verify the generator trips (0.5]

REFERENCE Dresden DOA 5600-1, pg 2

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

\t

. 7 .' ' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY PcC3 37 AND RADIOLOGICAL CONTROL ANSWER 7.11 (2.00)

Jet pump failure (0,5)

The failed jet pump reduces core flow (actual) and thus power. [0.5)

With reduced power, turbine control valves close to maintain header pressure reducing generator load. [0.5)

Reverse flow through the failed jet pump causes INDICATED core flow to increase. [0,5) .

REFERENCE Dresden DOA 201-1, pg 1 ANSWER 7.12 (1.00)

When the water level exceeds the range of the narrow range instrument.

_ (+so w )

• REFERENCE Dresden DOA 600-1, pg 3 ANSWER 7.13 (1.00)

To prevent H2 buildup in the drywell.

REFERENCE Dresden DOA 040-1, pg 4 ANSWER 7.14 (1.00) a

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

m t

5

7.

• 1 ROCEDURES - NORMA.L. ABNORMAL. EMERGEHGX Pcco 38 AND RADIOLOGICAL CONTROL REFERENCE'

- Dresden'l-1, Normal Unit Startup.

ANSWER 7.15 (2.75)

UNIT 2

1. Reduce the speed of the MG set 2A to the acceptable speed for single loop operation. (0.25)

2. Trip recirculation MG set 2B locally at Bus 32 (0.25)

3. As long as the reactor remains in a safe condition, do not (0.75) attempt to shut down until 125v DC can be restored.

UNIT 3

1. Manually scram the reactor and follow DFG 2-3. (0.75)

2. Trip al'1 reactor building vent fans. (0.25)

3. Start either standby gas treatment train. (0.25)

4. Trip OCB's 9-10 and 10-11 locally at the 345 KV Switchyard. (0.25)

REFERENCE e

DRESDEN - DOA 6900-2, pages 2 and 7.

4

(***** END OF CATEGORY 7 *****)

='

T __ '

,o 8.'" IDMINISTRATIVE PROCEDURES. CONDITIONS. Paco 39 AND LIMITATIONS

' ANSWER 8.01 (1.00)

-c. 1 year [0.5] ,

b. Length of the job [0.5]

REFERENCE Dresden, CECO Radiation Protection Standards, P. 11 & 13 ANSWER 8.02 (2.00)

a. 50 mrem / day

b. 300 mrem / week

c. 1250 mrem /qtr

d. 5000 mrem /yr

( 4 @ 0.5 each ]

REFERENCE Dresden, CECO Radiation Protection Standards, P. 33 & 34 ANSWER 8.03 (2.75)

a. So the reactor will isolate on less than 850 psig (0.5]

b. 1. Verify all rods in.

2. Trip the control rod drive pumps

3. Trip the turbine

[ 3 @ 0.75 each ] -

(l~nti a. lee sea s,,t er s %s).- rhe.J ef fnd-)

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) ,

'8. ADMINISTRATIVE PROCEDURM.' CONDITIONS. Fra 49 AND LIMITATIONS REFERENCE l Dresden EPIP 200-20, Control Room Evacuation / Shutdown, P. 1 & 2

' ANSWER 8.04 (1.50) -

Any 3 of the following at 0.5 each;

1. Form 7-4A and the backshift section of 7-4B (or safety evaluation) must be completed and reviewed by two SRO's, one of which must be an SEP.

2. Change must be authorized by the Shift Engineer.

3. Station Duty Supervisor shall be notified if a temporary system alteration is required.

4. Onsite Review should be conducted promptly following the change (normally the next working day).

REFERENCE Dresden, DAP-7-4, Control of Temporary System Alterations, Rev. 9, Sep 1986, P. 2 ANSWER 8.05 (1.50)

1. Illinois Emergency Services and Disaster Agency (IESDAf.,dK44)

2. Illinois Department of Nuclear Safety (IDNSI,, dvs)

3. Nuclear Regulatory Commision (NRC)

C 3 0 0.5 each ]

! REFERENCE Dresden, EPIP 100-C1, Station Director Checklist of Initial GSEP Responsibilities Rev 5 P. I thru 3 .

j (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l

.. w 8." $aMINISTRATIVE PROCEDURER. CONDITIONS. Pag] 41 AND LIMITATIONS ANSWER 8.03 -(3.00)

a. For unit 2 & 3 : 5 spm unidentified [0.25] and 25 apm unidentified and identified total [0.25]. If exceeded orderly shutdown to cold shutdown (in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) [0.5].

b. Identified leakage is leakage into the equipment sump [0.25].

' Unidentified leakage is leakage into the floor drain sump [0.25].

c. These limits apply to Unit 2 unidentified leakage:

At > 1 gym increase from previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or > 3 gpm total perform investigation of cause. (i.e. Drywell air & water samples, plant evolutions) [0.5].

A leak rate > 4 spm requires a containment entry and inspection.

[0.5]

d This limit applies to Unit 3 unidentified leakage:

If a 2 spm increase in the unidentified leakage rate occurs within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, immediately initiate an orderly shutdown to cold shutdown. [0.5]

I (NOTE: The specific time to reach Hot Shutdown and/or Cold Shutdown is not required for full credit in THIS question)

REFERENCE Dresden Tech Specs 3.6.D & 4.6.D, pg 3/4.6-5 and 3/4.6-6 & Operating Order l #6-86.

l f ANSWER 8.07 (2.00)

a. Cannot be moved with normal drive pressure (0.5)

Excessive scram time (0.5]

! Uncoupled rod [0.5]

b 8 [0.5]

l I (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l l

i

'8;' IDMINISTRATIVE PROCEDUnrR. CONDITIONS.

Page 42 AND LIMITATIONS REFERENCE Dresden Tech Specs 3.3, pg 3/4.3-1 ANSWER 8.08 (1.50)

Unit is in cold shutdown [0.5).

All rods in (0,5).

Shutdown margin Tech Spec is verified (0.5)

REFERENCE l

Dresden Tech Spec 3.4 (SLC system) t ANSWER 8.09 (1.00)

When the package was previously submitted by another supervisor.

REFERENCE Dresden DAP 3-5, pg 4 ANSWER 8.10 (2.00)

a. false (0.5)

b. false (0.5)

c. false (0.5)

d. true (0,5)

REFERENCE Dresden DAP 3-5, pg 9, 12. & 14.

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

3 . $

. s', ' InMINISTRATIVE ' PROCEDum. CONDITIONS .

Pasa 43 AND LIMITATIONS s

ANSWER' 8.11 (1.00)

When RPV is > 90 psig [0.5] with irradiated fuel in the vessel (0.5].

REFERENCE Dresden Tech Spec 3.5, pg 3/4.5-10 ANSWER 8.12 (1.00) .

a. Any individual who wishes to leave information or instructions for Operations or Maintenance crews. [0.5)

b. Assistant Superintendent- Operating. [0.5)

REFERENCE

. Dresden DAP 7-3, pg 1.

ANSWER 8.13 (1.00)

The control switch must be held in the close position.for at least 10 seconds after the fully closed indication is displayed. [1.0)

REFERENCE Dresden Operating Order #38-86 ANSWER 8.14 (1.00)

The NSO will attempt to reset the alarm within 10 minutes of its receipt (0.5). If the alarm will not reset an investigation of why will be initiated by the SS [0.5).

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

i . .

Q.

8 ADMINISTRETIVE PROCEDURTR.' CONDITIONS- Pag 3 44 AND LIMITATIONS REFERENCE Dresden Operating Order #39-86 ANSWER 8.15 (1.00)

a. To insure adequate air volume to accomadate all of the drywell gases which will be purged into the torus upon a LOCA. [0.5]

b. To insure adequate water volume to provide the heat sink for a LOCA. (0,5)

REFERENCE Dresden Unit 3 Tech Specs, B 3/4 7-33 & 34 ANSWER 8.16 (1.50)

a. Stop the HPCI surveillance (Stop heat addition to the suppression pool) (0.25). Continously monitor and log temperature every 5 minutes until the HPCI surveillence is stopped (0.25]. Reduce SP temp to 95 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (0.25].

b. SCRAM the reactor (0.25]

c. Reactor shall be depressuri=ed to <150 psig (0.25] at normal cooldown rates (0.25].

REFERENCE Dresden Unit 3 Tech Spec, pg 3/4 7-2 & 7-3

(***** END OF CATEGORY 8 *****)

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

r,

['** TEST CROSS REFERENCE Pcco 1

-, QUESTION VALUE REFERENCE 5.01 3.00 ZZZ0000001 5.02 1.00 ZZZ0000003 5.03 1.00 ZZZ0000005 5.04 1.00 ZZZ0000008 5.05 1.50 ZZZ0000009 5.06 2.00 ZZZ0000010 5.07 1.00 ZZZ0000011 .

5.08 1.50 ZZZ0000012 5.09 1.50 ZZZ0000013 '

5.10 2.00 ZZZO900014 5.11 2.00 ZZZ0000015 5.12 1.50 ZZZ0000002 5.13 2.00 ZZZ0000004 5.14 1.50 ZZZ0000006 5.15 2.50 ZZZ0000007 25.00 6.01 3.00 ZZZ0000016 6.02 1.00 ZZZ0000017 0.03 2.50 ZZZ0000018 6.04 2.50 ZZZ0000023 ,

6.05 2.00 ZZZ0000024 6.06 1.50 ZZZ0000025 6.07 1,25 ZZZ0000026 6.08 1.50 ZZZ0000027 6.09 2.00 ZZZ0000028 6.10 2.00 ZZZ0000019 6.11 2.00 ZZZ0000020 6.12 1.00 ZZZ0000021 6.13 2.75 ZZZ0000022 25.00 7.01 1.50 ZZZ0000029 7.02 1.50 ZZZ0000030 7.03 1.50 ZZZ0000031 7.04 1.00 ZZZ0000032 7.05 2.50 ZZZ0000033 7.06 1.50 ZZZ0000034 7.07 2.00 ZZZ0000037 7.00 2.00 ZZZ0000038 ,

7.09 2.00 ZZZ0000039 7.10 1.50 ZZZ0000040

. 7.11 2.00 ZZZ0000041 7.12 1.00 ZZZ0000042 7,13 1.00 ZZZ0000043

• 7.14 1.00 ZZZ0000044 7.15 2.75 ZZZ0000055 24.75 8.01 1.00 22Z0000035 i 8.02 2.00 ZZZ0000036 8.03 2.75 ZZZ0000045

." TEST CROSS REFERENCE Peca 2 QUESTION VALUE REFERENCE o

6.04 1.50 ZZZ0000046 8.05 1.50- ZZZ0000047 8.06 3.00 ZZZ0000048 8.07 2.00 ZZZ0000049 8.08 1.50 ZZZ0000050 8.09 1.00 ZZZ0000051 8.10 2.00 ZZZ0000052 8.11 1.00 ZZZ0000053 .

8.12 1.00 ZZZ0000054 8.13 1.00 ZZZ0000056 8.14 1.00 ZZZ0000057 8.15 1.00 ZZZ0000058 8.16 1,50 ZZZ0000059 24.75

_e____

99.50 I

e

. 1 w-