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Exam Repts 50-266/OL-87-01 & 50-301/OL-87-01 on 870217-19. Exam Results:All Five Reactor Operator Candidates & One Senior Reactor Operator Upgrade Candidate Passed
	ML20207R994
Person / Time
Site:	Point Beach
Issue date:	03/12/1987
From:	Burdick T, Hare S, Higgins R, Kingsley I; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20207R987	List: ML20207R986; ML20207R994;
References
	50-266-OL-87-01, 50-301-OL-87-01, NUDOCS 8703180392
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U.S. NUCLEAR REGULATORY COMISSION

-REGION III Report No. 50-266/0L-87-01 Docket Nos. 50-266; 50-301 Licenses No. DPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan, Room 308 Milwaukee,- WI 53201 Facility Name: Point Beach Examination Administered At: Point Beach Examination Conducted: feb uary 17-19, 1987 01 bh'l }-l2-67 Examiner (s): .L.Higgins[p Date

d. M. Hare

- Date 3 //2-[87

. . Kingsley ' } - f ] -Q Date Approved By: f 3 ~ I b' Operating Licensing Section Date Examination Summary Examination administered on February 17-19,1987 (Report No.50-266/0L-87-01 DRS))

to Five Reactor Operator Candidates and one Senior Reactor Operator Upgrade Candidate.

Results: All candidates passed the examinations.

8703180392 870313 PDR ADOCK 05000266 V PDR a

1 DETAILS

1. Examiners E R. L. Higgins, Chief Examiner S. M. Hare I. G. Kingsley T. M. Burdick

2. Examination Review Meeting Refer to Attachment A.

3. Exit Meeting .

On February 19, 1987, at the conclusion the the examinations, NRC representatives met with facility representatives to discuss generic findings observed during the course of the examinations.

NRC Representatives in attendance were:

R. L. Higgins, Chief Examiner S. M. Hare, Examiner I. G. Kingsley, Examiner (Sonalysts)

T. M. Burdick, Operator Licensing Section Chief R. L. Hague, Senior Resident Inspector R. J. Leemon, Resident Inspector Facility representatives in attendance were:

Ken Draska, Shift Supervisor Ron Bruno,-Superintendent of Training Tom Koehler, General Superintendent Jim Reisenbuechler, Superintendent, Quality and Regulatory Services Rick Parlotto, Training Specialist Jim Knors, Regulatory Engineer Fritzie Fleutie, Administration Specialist Greg Maxfield, Superintendent of 0,r ! rations The following issues were discussed during the exit meeting.

1. The control room operators and the training department personnel were extremely helpful during the administration of the examinations.

2. The candidates were proficient in the use of procedures.

3. The candidates were very knowledgeable in plant areas outside of the control room. Their knowledge testifies to their extensive auxiliary operator experience and thorough auxiliary operator training.

4. The following generic weaknesses in the candidates' knowledge were observed during the examinations:

a. rod control component and function familiarity

b. radiation limits c .' understanding of nuclear, thermodynamic and electrical theory.

5. The reference material supplied by the facility to the NRC is considered to be an improvement over the reference material previously supplied, but is still viewed as needing improvement.

The reference material was contained in ACC0 press binders, rather -

than in three-ring hardcover binders. These binders would often fall apart when used. In addition, the reference material was not indexed or tabbed.

Not all required reference material requested was initially sent. A complete copy of the Emergency Contingency Actions and the Critical Safety Parameters were not sent until the NRC specifically asked for them. The first copy of Technical Specifications was incomplete, only half of the pages were duplicated. Three relevant documents-the Special Orders, Duty and Call Superintendent Handbook, and Setpoint Document were not provided to the examiners. These were later obtained at the site when the examiners noticed these documents-in the control room during the administration of the exams.

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ATTACHMENT A An examination review meeting is no longer conducted. At the conclusion of the written examinations the facility is given a copy of the examination and the answer key for both the SR0 and R0 examinations. The facility then has five working days in which to provide written comments concerning_the examinations to the NRC. The following paragraphs contain the facility comments concerning the R0 exam, followed by the NRC comments. ,

i QUESTION 1.01 Facility Comment: Parts 3 and 4 ask the R0, in effect, to analyze a plant design change. We feel this would require an engineering analysis and is not in the task inventory for an R0. We request that these parts of the question be deleted.

REFERENCE:

COT program

.NRC Response: Partially concur. The question does not require an engineering analysis for evaluation. Instead, proper application of thermodynamic principles is required and is described in the first paragraph of Training Handbook 39.2, Page 33. However importance rating, given

, Parts this 4topic's 3 and relatively low are deleted.

QUESTION 1.068 Facility Comment: Other responses may also be correct such as increased water hole peaking, lower rod worth, more even fuel burnup, and lower hot channel factors.

NRC Response: Partially concur. NUREG-1122

. asking this question (3.1/000/provides 001/K6.01). the basis for However, alternate answers will be considered for credit.

QUESTION 1.10B Facility Comment: The explanation for the answer states that other rods will withdraw; but, in fact, an auto rod withdrawal block will be generated as well as a turbine runback. Shutdown margin may not change because the negative reactivity added by the rod will be compensated by a temperature decrease. Also, it should be noted that enough control rod worth may not be present to compensate for the dropped rod.

REFERENCE:

Logic Drawing 883 D195, Sheet 16 NRC Response: Concur. The answer key has been modified.

QUESTION 1.15A,B Facility Comment: The Mollier diagram given was quite difficult to read due to the reduction of the' copy provided. More tolerance in 1

the-answer.should be allowed due to interpolation inaccuracies.

NRC Response: Do not concur. Although compressed to fit on a 8.5 x 11 inch sheet of paper, the Mollier Diagram provided was adequate to yield answers in the acceptable range.

QUESTION 2.20A Facility Comment:- A statement to ensure the RHR system is at its design concentration of > 2000 ppm should also be acceptable.

Proper boron concentration should infer a negative reactivity addition.

REFERENCE:

OP-78 NRC Response: Do not concur. Full credit will not be given unless reference is made to negative reactivity addition for ESF use.

QUESTION 2.04C Facility Comment: Facility design calls for RHR suction to be switched to Sump B at 6 percent RWST level. However, we feel a correct trainee response would also be to cite PBNP E0Ps which direct the operator to begin pump suction switchover at 10 percent RWST level and to stop all pumps at 6 percent RWST level. This question from the PBMP exam bank is used in evaluating trainee's knowledge of system

' design early in the training program, prior to E0Ps and integrated operations being taught.

REFERENCE:

Caution between Steps 9 and 10, E0F 1.3.

NRC Response: Concur. Alternate answers will be considered for credit.

QUESTION 2.06 Facility Comment: Any three of the following five should be considered for full credit:

1. Unisolates standby tank

2. Aligns standby tank to gas analyzer

3. Isolates on-line tank

4. Isolates on-line tank to gas analyzer

5. Alarms C-59

REFERENCE:

TRHB 10.15, Page 26 NRC Response: Concur. The answer key has been modified.

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QUESTION 2.088' Facility Comment: The work "immediate" should be removed from the key. A pressure drop of 100 psi / minute is not immediate.

REFERENCE:

SI at 1736 lbs_- Setpoint Document. SI pump ,

shutoff head - 1550 lbs - TRHB 10.8, Table 10.8.4.

NRC Response: Concur. The answer key has been modified.

QUESTION 2.09C Facility Comment: This part of the guestion is not clear regarding plant condition. Charging pumps is also a correct answer.

REFERENCE:

Auxiliary Spray shown TRHB 10.6, Figure 10.6.1, also E0P 3.0, Step 20a.

NRC Response: Concur. The answer key has been modified.

QUESTION 2.11A Facility Comment: Additional correct answers are:

1. Decreasing VCT level (alarm to level)

2. Increase in charging aump speed (high speed alarm)

3. Excessive makeup to tie CVCS

REFERENCE:

AOP-1A NRC Response: Concur. The answer key has been modified.

QUESTION 2.11B Facility Comment: The outlet flow to actuate CCW isolation is total CCW flow-return from RCP. In addition, a high radiation signal will cause the surge tank vent valve to shut.

REFERENCE:

P&ID 110E018, Sheet 2 of 4 and P&ID 110E018, Sheet 3 of 4 NRC Response: Partially concur. References illustrate that A0V-761(B) closes when high flow is detected in CCW return line from RCPA(B)TBHXtoisolatethatlineonly. CCW return from RCP A(B) motor oil coolers is unaffected. However, the answer key has been modified to accept shutting of the surge tank vent valve on high radiation.

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. QUESTION 2.12

. Facility Comment: A, C, D are 480 V pumps, not.4160 V. .Thus, the trainee ,

. may answer that these are not.4160 V loads. The trainee 4

may also answer with-the ;gpropriate 4160 V bus which

feeds the 480 V bus.

A. 1A06 feeds 1804 .

B. This is a 4160 load but from 2A01, not 2A02, not 2A02.

as stated in'the key.

- C. 2A05 feeds 2B03

(> D. 1A05 feeds 1803

REFERENCE:

TRHB 12.5, Figures 12.5.1, 12.6.5A, 12.6.58 NRC Response: Concur. The answer key has been modified.

QUESTION 2.14B Facility Comment: The key is correct for an auto SI. If a manual SI is the cause, the valve will not close.

3EFERENCE: Logic Drawing 883D195, Sheet 9-NRC Response:' Concur. The answer key has been modified.

4 QUESTION 3.03A(3)

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Facility Comment: Circulating pump running should be an alternative-to correct answer.

REFERENCE:

TRHB 11.7, Pages 14-15 NRC Response: Concur. Answer key modified.

QUESTION 3.09C Facility Comment: If examinee assumes the entire bank drops into the core and demand is greater than 35 steps a runback would come from rod bottom bistable. A NIS negative rate runback ,

could also be generated from a dropped bank.

REFERENCE:

PBNP Logic Drawings

_NRC Response: This question has been deleted since the stated conditions are a violation of Technical Specifications.

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QUESTION 3'.10C' .

Facility Coment: Answer should be FALSE. Source range is blocked by P-10, P-6 unblocks the source range.

REFERENCE:

PBNP Logic. Drawing 883D195 NRC Response: Concur. The answer key has been modified.-

-QUESTION 3.13 Facility Coment: Part "A" should be considered three parts, SI/UV/ MANUAL-(0.5 points each, not 5' parts,. separating units as in:

answer. key).

REFERENCE:

TRHB 12.8, Page 4, 1.3a, b,-d NRC' Response: Concur.' The answer key has been modified.

QUESTION 3.14 W

F&cility Coment: Answer to Part 1 should be begins to divert at 56 percent full open at 78-percent.

REFERENCE:

TRHB 10.6, Table 10.6.4 (LT-141)

NRC Response: Concur. The answer key has been modified.

JQUESTION 4.02B Facility Coment: Accumulator injection should be considered as an alternative answer.

REFERENCE- ECA 0.0, Page 16 NRC Response: Do not concur. The cited reference does not support this coment.

QUESTION 4.05A Facility Comment: The R0 task inventory does not contain any reference to this material. The question should be deleted.

REFERENCE:

COT program NRC Response: Concur. Part a. has been deleted.

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QUESTION 4.09 Facility Comment: In the answer key, Number 6 should be manual containment l isolationnotsafetyinjection.

REFERENCE:

A0P-10A NRC Response: Concur. The answer key has been modified.

QUESTION 4.14B Facility Comment: The question, as stated (solid-cooldown-RHR) does not have l two answers. With the plant solid and in cooldown on RHR, i the only correct answer is steam generator water temperature less than 50 above RCS temperature.

REFERENCE:

The answer is a Technical Specification requirement and the statement is in OP-3C NRC Response: Concur. The answer key has been modified.

The following paragraphs contain the specific facility comments concerning the SR0 written exam, followed by the NRC response.

QUESTION 5.07 Facility Comment: The Mollier diagram given was quite difficult to read due to the reduction of the copy provided. More tolerance in the answer should be allowed due to interpolation inaccuracies.

NRC Response: Disagree. Two Mollier diagrams were provided, as was the pertinent portion of the steam tables. These references provide ample detail for the candidate to obtain an answer within the specified tolerance. The answer key is not changed.

QUESTION 5.10 Facility Comment: If Delta I is out of the band at the coint in time when the graph ends, the operator should,'if possible, withdraw control rods to bring Delta I up and then use rod insertion as Delta I approached target Delta I. This should also be considered a correct answer.

NRC Response: Agree. The answer key was modified to grant full credit if the candidate assumed that corrective action began when the graph ended with Delta I strongly negative, with corrective action resulting in Delta I asymptotically approaching the target value from the negative region.

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QUESTION 5.14 Facility Comment: Delta flux being exceeded may also be correct.

NRC Response: Disagree. Delta flux is a completely different limitation l than rod insertion limits. The answer key is not changed. '

QUESTION 6.05 Facility Comment: Corrections to key as follows:

Number 7: SI pumps start and headers unisolate Number 12: accumulator isolation valves are already open; however, they do receive an SI signal to open.

REFERENCE:

SI Logics NRC Response: Agree. The answer key is modified per facility request.

QUESTION 6.11 Facility Comment: Circulating water pump running should be an alternative correct answer.

REFERENCE:

Logic Drawing 883D195, Sheet 12 NRC Response: Partially, agree. Theanswerkeyischangedtoaccept

" circulating water pump running' for " circulating water pump breaker closed. The phrase " associated discharge valve open" is still required for full credit.

QUESTION 6.16 Facility Comment: Additional correct answers / corrections:

1. DG output breaker in auto

2. NOTE: FSK SHOULD BE FSX

3. UV on bus

4. Normal supply breaker open

5. Tie breaker open

6. No lockout on bus

7. No lockout on breaker

8. DC control power available

REFERENCE:

TRHB 12.5, Page 5, TRHB Figure 15.5.5E NRC Response: Partially agree. Most of the additional answers proposed by the facility were already included in the answer key. The key is changed to "FSX" instead of "FSK," and the answer "DC control power available" was added as an acceptable response. The reference cited by the facility should be TRHB Figure 12.5.5E, not 15.5.5E.

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f 799 ROOSEVELT RO AD GLEN ELLYN, ILLINOIS 60137 QUESTION 7.01A Facility Coment: - Alternative answer: Another concern is that the pressurizer may contain a lower boron-concentration adding positive reactivity on an outsurge.

NRC Response: The key is modified to accept the following statement: ,

" Prevent adding positive reactivity when an outsurge from the pressurizer introduces water with a lower baron concentration into the RCS."

QUESTION 7.03 Facility Coment: Alternative answer: Covers the tubes to inhibit steam bubble collapse, which minimizes required RCS depressurization to stop leak.

REFEREN'CE: Background document E0P-3, Step 4 NRC Response:. The facility-proposal-is simple a rephrasing of the answer key. Any wording which encompasses the key points specified in the key will be awarded full credit.

QUESTION 7.07A-Facility Coment: Control rods are full out at > 225 steps.

REFERENCE:

PBNP Technical Specifications 15.3.10-Al NRC Response: Agree. The answer key is changed to 225 steps.

QUESTION 7.078 Facility Coment: Additional answers

1. Physics test

2. Control rod exercise

REFERENCE:

Technical Specifications 15.3.10.A.2 NRC Response: Agree. The key is modified to grant credit for the responses " physics test" and " control rod exercise."

' QUESTION 7.09 Facility Comment: Number 1: Both units are already tripped since both RCPs are stopped and the plant is in a natural circulation cooldown per the posed question. In this condition the CRDMs must be deenergized so tripping.the reactor has already occurred. This item should be deleted.

Number 6: _ Initiate manual CI (containment isolation) not SI-(safetyinjection)

REFERENCE:

A0P-10A NRC Response: Partially agree. Verification that both reactors are tripped is the first immediate action step and will remain in the key. Immediate action Step 6 is modified to

initiate manual containment isolation."

QUESTION 7.11 Facility Comment: " Shortwave" should not be required (radio enough for full credit).

NRC Response: Agree. The key is modified per facility request.

QUESTION 8.03

-Facility Comment: Part A - The first part of the answer completely answers the question.

Part B - OTAT should not need to be in the answer.

REFERENCE:

Technical Specifications 15.2.2 Basis Part E - The first four words completely answer the question.

REFERENCE:

Technical Specifications 15.2.2 Basis, Pages 15.1.3-7.

NRC Response: Part A - Agree. The key is changed per facility request.

Part B - Disagree. OTAT is the principal reactor trip designed to protect against DNB. Some mention of 0 TAT must be included to receive full credit.

Part E - Agree. The key is changed to accept " Loss of heat sink" for full credit.

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QUESTION 8.13 Facility Comment: HP 2.5 lists other reasons for which an RWP must be written. This answer is true, HP 2.5 lists other conditions that would require an RWP prior to entering containment. (Steps 2.1-2.5,HP2.5) These other conditions should also be accepted.

NRC Response: Agree.~ The key is modified to grant full credit for any answer which includes any of the condition specified in HP Manual Chapter 2.5, Steps 2 ' through 2.5.

QUESTION 8.14 Facility Comment: Additional correct answers:

1. -DSS

2. Health Physicist

3. PAB A0

4. HP Supervisor

5. HP Station

REFERENCE:

HP 2.6, 2.1.1, 2.1.2, 2.2, 2.2.2, 2.2.3 NRC Response: Agree. The key is modified to grant full credit for any two of the following:

1. DSS

2. Health Physicist

3. PAB A0

4. HP Supervisor.

5. HP Station i

FAASTER CO?' Y U. S. NUCLEAR REGULATORY C0tHISS10N REACTOR OPERATOR LICENSE EXAMINATION FACILITY: POINT BEACH 182 REACTOR TYPE: PWR-WEC2 DATE ADMINISTERED: 87/02/17 EXAMINER: __K_INGSLEY,. I .

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 CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 2Sill(,

25.00 ^5.Gv 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 7C/24 25.00 % 90 2. PLANT DESIGN INCLUDING SAFETY

. AND EMERGENCY SYSTEMS Ob{6 2L]. 611-

-?E 00 25.00 3. INSTRUMENTS AND CONTROLS 25.00 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 100.00- % Total s Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature -

- NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

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

2. Restroom trips are to be limited _ and only one candidate at a time ray 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. 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 af 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.

b 13. The point value for each question is indicated in parentheses after the questien 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 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.

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

a. Assemble your examination as follows:

1 (1) Exam questions on top. l (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. l i

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2 THERMDDYNAMIC5, HEAT TRANSFER AND FLUID FLOW QUESTION 1.01 (2.00)

State whether each of the following will INCREASE, DECREASE, or have NO EFFECT on secondary cycle efficiency. (0.50 each)

1. Circulating water temperature increases. I,0

2. RCS Tave program is raised by 5 F.

3. Feedwater heating steam is taken from main steam header instead of turbine staging.

4. Feedwater heating steam is taken from cold reheat s' team instead of turbine staging.

QUESTION 1.02 (1.00)

If the equilibrium count rate in a subcritical reactor increases by a factor of FOUR due to a reactivity addition, what happens to the margin to criticality?

QUEST 10ll 1.03 (1.00)

The Reactor Protection System would become unreliable for DNB protection from the OT delta-T trip if excessive voids were allowed to form in the Reactor Coolant System because: (Select the correct answer.)

a. the heat transfer coefficient of the cladding is reduced significantly.

b. reactor power is no longer proportional to delta T as measured by the loop RTDs.

c. thermocouples respond much slower in voids as compared to a subcooled fluid.

d. voids in the downcomer region will cause the NI detectors to indicate in error.

QUESTION 1.04 (1.50)

After a secondary calorimetric and adjustment of the power range inst-ruments, it is discovered that the recorded values of main feed flow were higher than actual. HOW and WHY does this occurence affect the current power range instrument readings?

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

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3 THLRMDDYNAMICS, HEAT IRAN 5FtR AND FLUID FLDW QUESTION 1.05 ( .50)

While performing a natural circulation cooldown and depressurization, pressurizer level rapidly increases. What is the MOST PROBABLE cause?

QUESTION 1.06 (2.50)

a. Why are the control rods withdrawn and inserted in an overlapping program? (0.50)

b. List TWO reasons for using control rods designed with several small fingers instead of solid large rods? (1.00)

c. How does INTEGRAL R0D WORTH vary from:

1. BOL to EOL (0.50)

2. HZP to HFP (0.50)

QUESTION 1.07 (1.25)

Assume that you have established a 1 DPM SUR on the reactor while the source range meters indicate 1000 cpm on both channels. After 30 seconds what will be the indicated source range neutron level? SHOW ALL WORK!

QUESTION 1.08 (2.25)

Describe HOW and WHY Moderator temperature coefficient will vary for the following conditions. The reactor is operating at 80% power. Consider each case INDEPENDENTLY and assume no other parameters vary. Assume the reactor does not trip.

a. RCS Tave decreases by 20 F. (0.75)

b. Control rods are withdrawn 50 steps. (0.75)

c. RCS boron concentration is reduced by 50 ppm. (0.75)-

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

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW l QUESTION 1.09 (2.00)

Compare the CALCULATED Estimated Critical Rod Position (ECP) for a startup to be performed 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a trip from 100% power, to the ACTUAL critical control rod position (ACP) if the fellowing events / conditions occurred. Indicate whether the ACP is HIGHER thar, LOWER than, or the SAME as the ECP AND BRIEFLY EXPLAIN the reason for your answer. Consider each INDEPENDENTLY. The plant is at E0L.

a. The startup is delayed until 10.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months af ter the trip. (Refer to Figure 1.2) (1.00)

b. The condenser steam dump pressure controller setpoint is increased to just below the SG atmospheric steam dump controller setpoint. (1.00) i QUESTION 1.10 (2.00)

The plant is operating at 70 percent power with all systems in automatic unless stated otherwise. Explain HOW and WHY SHUTDOWN MARGIN is affected by the following conditions or situations. Assume no operator actions (unless stated) and the reactor does NOT trip. Consider each case INDEPENDENTLY.

a. The Reactor Coolant System is borated by 10 ppm. (1.00)

b. A control rod in a shutdown bank drops. (1.00)

QUESTION 1.11 (1.00)

Explain HOW and WHY the positive reactivity insertion rate affects the source range count level at which criticality is achieved.

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

PRINCIPLES OF NUCLEAR' POWER PLANT OPERATION, PAGE 5 -

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THERMOUTNAMIC5, HEAT TRAN5FLR AND FLUID FLOW QUESTION 1.12 (1.50)

Point Beach Unit 1 has just restarted following a refueling outage while Unit 2 is near EOL.

a. Critical data has just been taken at 10 E-8 amps and the operators add equal amounts of reactivity. Which unit will have the higher steady state startup rate and WHY? (0.75)

b. While at 50 percent power, a control rod worth -150 pcm drops into the core of both units. Assuming no operator actions, no runback occurs, and the reactor does NOT trip, WHICH UNIT will have the HIGHER steady state Tave and WHY? (0.75)

QUESTION 1.13 (1.50)

The reactor is producing 100% rated thernal power at a core delta-T of 56 degrees and a RCS mass flow rate of 100% when a station blackout occurs. Natural circulation is established and core delta-T goes to 28 F.

If decay heat is 2% _ rated thermal power, what is the core mass flow rate in percent?

QUESTION 1.14 (2.00)

Will the Departure from Nucleate Boiling Ratio (DNBR) INCREASE, DECREASE, or REMAIN THE SAME for the following changes in plant conditions? The plant is initially operating at 85 percent power with all control systems in AUTOMATIC (unless stated otherwise) and Bank D control rods at 150 steps. Consider steady state power operation unless stated otherwise.

Consider each change INDEPENDENTLY and assume the reactor does NOT trip.

a. All pressurizer heaters are energized with spray valves in manual.(0.5)

b. RCP bus frequency increases to 60.5 Hz. (0.5)

c. The RCS is inadvertantly borated by 100 pcm. (0.5)

d. Turbine load is increased to 100 percent using RCS boron adjustment to maintain a constant rod height. (0.5)

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

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. 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 6 THERMODYNAMIC 5, HEAT TRANSPER AND FLUID FLOW QUESTION 1.15 (1.50)

The plant is in Hot Standby with pressurizer pressure at 985 psig. A pressurizer PORY begins leaking to the pressurizer relief tank which is at 5 psig.

a. What is the downstream tail pipe temperature? (0.50)

b. What is the enthalpy of the fluid entering the PRT? (0.50)

c. The fluid entering the PRT is a: (SELECT ONE) (0.50)

1. Superheated vapor

2. Wet vapor

3. Saturated vapor

4. Subcooled liquid QUESTION 1.16 (1.50)

Indicate how the following system changes will affect the available Net Positive Suction Head (NPSH) (INCREASE, DECREASE, or NO EFFECT) of the condensate pumps. Consider each case separately.

a. Hotwell level increases. (0.50)

b. Condensate temperature increases. (0.50)

c. Condensate flow rate increases. (0.50)

P t

( ***** END OF CATEGORY 01 *****)

. 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7 QUESTION 2.01 (1.25)

List FIVE permissives/ conditions which must be met for a steam generator feed pump to start when its control switch is placed in the START position.

Include SETPOINTS.

QUESTION 2.02 (2.00)

a. WHY is it necessary to " Borate" the RHR system after removing it from service? (1.00)

b. Describe the flow path used to cool and borate the RHR system af ter it has been removed from service. (1.00)

QUESTION 2.03 (1.50)

a. List the normal source (s) of makeup water for the following.

1. SI accumulators (0.50)

2. RWST (0.50)

b. When venting the SI accumulators to red;ce pressure, the vented gas is discharged to: (Select the correct answer.) (0.50)

1. The purge exhaust stack

2. The containment atmosphere

3. The PRT

4. The RCDT

5. The auxiliary building vent stack QUESTION 2.04 (1.50)

What is the PURPOSE for the following RWST alarms.

a. RWST Low Level Alert - 96% (0.50)

b. RWST Low Level - 28% (0.50)

c. RWST Low-Low Level - 6% (0.50)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

't . PLANI ULSIGN INCLUDING SAFliY AND EMERGENCY SYSILMS PAGt 8 QUESTION 2.05 (1.00)

What is the PURPOSE of the 2 minute time delay between containment spray system actuation and spray additive valves (836A and 836B) opening?

QUESTION 2.06 (1.50)

List THREE automatic actions that will occur when the inservice gas decay tank reaches 95 psig.

QUESTION 2.07 (1.00)

Each RC pump motor is equipped with an anti-reverse rotation device. List TWO reasons for using this device.

QUESTION 2.08 (2.50)

a. Excluding Manual Initiation, list ALL conditions that will generate a l Safety Injection Signal. Include setpoints and coincidences where applicable. (0.90)

b. Indicate the order in which the ECCS subsystems will inject into the.

RCS and the pressure at which each will inject during a continued RCS depressurization of 100 psig/ minute caused by a LOCA. (Assume each active component was started by a Safety Injection Signal.) (1.60)

QUESTION 2.09 (2.00)

a. List TWO reasons for maintaining a minimum pressurizer spray line flow during normal "at power" operations. (1.00)

b. List TWO annunciators available to alert the operator that minimum spray flow is not being maintained. (0.50)

c. List TN0 sources of the driving force for pressurizer spray flow.(0.50)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 i

QUESTION 2.10 (1.50)

State how the following components respond (FAIL OPEN, FAIL CLOSED, REMAIN FUNCTIONAL, DIVERTS TO .... ETC.) when instrument air pressure is lost with I the plant at 100% power.

a. Letdown pressure control valve (PCV-135) (0.25)

b. VCT outlet isolation valve (LCV-112C) (0.25)

c. Pressurizer PORV(RC-430) (0.25)

d. Main steam isolation valve (CV-2018) (0.25)

e. Letdown line divert valve (TCV-145) (0.25)

f. Pressurizer spray valve (RC-4318) (0.25) i QUESTION 2.11 (2.00)

a. List TWO indications or symptoms which will be observed if a tube leak occurs in a RC pump thermal barrier heat exchanger. Assume NO alarm setpoints are reached. (1.00)

b. If the tube leak continues to increase in severity, WHAT AUTOMATIC action will occur and WHAT CONDITION will cause this automatic action?

(1.00)

QUESTION 2.12 (1.50)

For each of the following electrical loads, supply the 4160 volt bus from which each load is DIRECTLY ENERGIZED.

a. Containment Spray Pump 1P14B

b. Main Condensate Pump 2P25A

c. Residual Heat Removal Pump 2P10A

d. Service Water Pump P32B ,

i

e. Safety Injection Pump 2P15B

f. Steam Generator Feed Pump 1P28B ,

i N

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 !

i.e Q j l r.

\

i QUESTION 2.13 (2.75) , 1 .

a. List the THREE unique signals which will: initiate a motor-driven I auxiliary feedwater A'JTO-START signal. (0.75) )

b. List the Normal and Emergency sources of wcter to the Auxiliary '

Feedwater Pumps. (1.00)

c. With an auto start signal initiated, H0W and under.WHAT CONDITIONS .

is the AuxiliaryVeed Pump water supply shif ted from the normal supply to the emergency supply? Include SETPOINTS. (1.00)

. QUESTION 2.14 (3.00) ;

The following condern the CVCS. j! ks

a. List the TWO functions (purposes) of the Letdown Pressure Control Valve

, ( PC'l-135 )? (1.00) ,

\ <l ; I

b. If lef t in automatic control, what position should PCV-135 be found in s 7

two mir.utes after a safety injection initiation? (0.50)

c. Why is letdown flow limited to 120 gpm? i' (0.50)

, f List the INTERLOCKS that must be satisfied in order to open an orifice d.

isolation valve? , (1.00)

I i> 1

.s .

\

.! t 4

j. .8 .

\

k .

!'\

r s

1 i

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

-}. - ..-..,,m. . , . -_ . - _ _ , . , . - . . , , . , , .

i

3. -INSTRUMENTS AND CONTROLS PAGE 11 i i

1 1

QUESTION 3.01 (1.50)-

The plant is operating at 80 percent power with all systems in automatic.

a. The CHANNEL IV (controlling) pressurizer pressure channel FAILS HIGH.

List the IMMEDIATE AUTOMATIC action (s) which occur (s) because of the failure. Alarms are not required. Assume no operator action. _( 1.00)

b. After completing all required operator actions, the plant is stabilized at the previously existing conditions with an ALTERNATE pressurizer pressure channel selected for control and the APPROPRI ATE BISTABLES TRIPPED. At this time, the. CHANNEL III Tcold instrument FAILS LOW.

List the IMMEDIATE AUTOMATIC action (s) which occur (s) as a result of this. additional failure. (0.50)

.QJf1!!0N 3.02 . (1.00)

Scir?t the condition which will result in the main feedwater control valves c1ctias in approximately 20 seconds.

a. keactor trip with Tave > 554 F

b. Reactor trip with Tave < 554 F

c. Safety injection signal

d. Low-low steam generator water levels

e. High-high steam generator water levels QUESTION 3.03 (2.25)

a. List ALL permissives/ conditions required to arm the Steam Dump System (SDS) with the Mode Select Switch in AUTO. Include SETPOINTS. (1.25)

b. Assume the SDS has been armed as described in part a. due to prior testing of related instrumentation. The plant is operating at 50 percent power with all control systems in automatic. How will the SDS respond to a Channel II Tave instrument failure to 569 F? Assume no reactor trip. (1.00)

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

,. 1 - -..-e- :---3 -w. ,,e-w-, , ,--.--%+ ,r--.-- -_-,,.%--.,-e . - - -.,, ..m- , . _ , . - . , , , - - . - - - - - - . . . - , . ,

. ---,..-,--ee- --

3. INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.04 (1.50)

The plant is operating at 100 % steady state power with containment pressure channel III failed high. A technician troubleshooting the failed channel inadvertently de-energizes the control and instrument power for containment pressure channel II. Will a Containment Spray Signal be actuated? (0.5)

EXPLAIN WHY or WHY NOT? (1.0)

QUESTION 3.05 (2.00) ,

a. Describe an IR instrument response if the circuitry is undercompen-sated during a reactor shutdown, INCLUDING any potential effects on SR instrumentation. Include any applicable setpoints. (1.0)

b. WHAT operator e, tion (s) is required to continue a reactor shutdown if one IR channel has failed high and WHEN should this action be taken?

(1.0)

QUESTION 3.06 (1.50)

a. Explain the PURPOSE of the steam pressure input s' red in the development of a steam flow signal for the S/G water level v.w.';rol system. (1.00)

b. How would INDICATED steam flow compare to ACTUIL steam flow at 20%

power if, during a power decrease from 100% to 0% power, the steam pressure signal stuck at its 50% power value. (0.50) 1

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

_. . . , - _y. ._.s ., ,__. - _ _-_,._. _ . _ , _ , _ - _ _ _ _ _ . _ , . _ . - . -

.n-

3. INSTRUMENTS AND CONTROLS PAGE 13 QUESTION 3.07 (3.00)

The plant is operating at 50% power with all control systems in automatic.

Bank D rods are at 150 steps. Given the following conditions / situations, describe the INITI AL rod motion which occurs. Your answer should contain IN, OUT, or NO MOTION with a brief EXPLANATION. Assume no operator action (unless stated) and the reactor does NOT trip. Consider each case separately.

a. B steam generator MSIV inadvertantly closes (turbine load constant).

(0.75)

b. Loop A narrow-range Thot instrument fails high. (0.75)

c. Loop $ narrow-range Tcold instrument fails low. (0.75)

u. Turbine load is ramped to 20% at 5%/ minute. (0.75)

QUESTION 3.08 (1.75)

The reactor is critical at 5% rated thermal power during a normal reactor startup. List ALL reactor trips which are DISABLED in this condition.

/, SD QUESTION 3.09 -(2.00)

For each of the following conditions, state if the condition WILL or WILL NOT result in a turbine runback. (0.50 each)

a. Turbine load equals 65% with OT delta-T 2 degrees below the trip setpoint.

b. Turbine load equals 85% with OP delta-T 2 degrees below the trip setpoint.

c. T;.Line ivoo equais 95. witn i,ontroi Bani 0 r0d fe!!; in;;.-ted.

d. Turbine load equals 75% with one shutdown rod on the bottom.

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

3. INSTRUMENTS AND CONTROLS PAGE 14 QUESTION 3.10 (2.00)

The reactor is operating at 100% power when an inadvertent Safety Injection signal is generated. All systems respond as expected except that only the Train B reactor trip breaker opens. Indicate whether the following are TRUE or FALSE. Assume no operator action unless stated. (0.50 each)

a. The turbine trips.

b. Feedwater isolation will occur before Tave decreases below 554 F.

c. Source range instruments will automatically energize at P-10.

d. The safety injection signal can immediately be manually reset.

QUESTION 3.11 (1.50)

List THREE automatic rod stops that DO NOT cause manual rod stops.

Setpoints are not required.

QUESTION 3.12 (1.25)

List FIVE (5) COMP 0HENTS RESET by the Control Step Counter Reset Switch.

QUESTION 3.13 (2.00)

a. List the FIVE conditions that will cause a " Fast Start" of the emergency diesel generators. (1.50)

b. If the first " Fast Start" attempt is unsuccessful, HOW MANY ADDITIONAL starting attempts will be made automatically assuming each attempt is unsuccessful? (0.50)

QUESTION 3.14 (1.75) ,

The Volume Control Tank (VCT) level irstrumentation, in addition to control board readouts and alarms, initiates THREE unique automatic actions at various levels in the VCT. List these AUTOMATIC ACTIONS including the LEVELS at which they occur.

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

4

--, ,-, - ,~ , , ,,---,.----.-----,---,-n , ,~, v--, , ,-

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

. 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15 RADIDLOGICAL CONTROL QUESTI0H 4.01 (2.00) i What are the FOUR conditions referenced in Technical Specifications that ensure the Hot Channel Factor limits are being maintained within limits during normal power operations?

l l

QUESTION 4.02 (2.00)

During a loss of all AC power, ECA 0.0 has the operator depressurize the RCS using steam generator atmospheric dump valves.

a. What cooldown rate should be attained during the depressurization?

(0.50)

b. Why must the RCS be depressurized? (0.50)

c. Why shouldn't the RCS be depressurized below 220 psig? (0.50)

d. Regarding the depressurization, HOW should the operator respond if pressurizer level is lost or vessel head voiding occurs? (0.50)

QUESTION 4.03 (1.00)

Which of the following operator actions is NOT among the immediate actions of E0P-0, Reactor Trip or Safety Injection?

! a. Check if Safety Injection is actuated.

. b. Check if main steamlines should be isolated.

l

c. Check RCS temperature stable et or trending to 547 F.

d. Verify total AFW flow at least 200 gpm.

e. Verify at least four Service Water pumps running.

QUESTION 4.04 (1.00) :

a. When must a Self Reading Pocket Dosimeter (SRPD) be rezeroed? (0.50)

b. When is a Neutrak-ER TLD badge required to be worn? (0.50)

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

.- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 l

RAD 10LUtilLAL LUNIROL

. 1 QUESTION 4.05 ( .00)

a. Match each Emer'e nse anization menber to the location to which h re p > pon decl on of an emergency classification.(1.50)

ERO Me er Location 1 , c crha eMn {

a. Technical Support Center

?. fMai ance porvisor b. Operations Support Center k 3. ite Manager c. Control Room

4. Emergency Support Manager d. Emergency Operations Facility

5. Health Physics Director

6. Shif t Support Coordinator

b. List the EMERGENCY ACTION LEVELS in order of severity (1 = most severe). (0.50)

QUESTION 4.06 (1.00)

Which ONE of the following CSF conditions would have the HIGHEST priority in requiring operator response?

1. RCS Inventory - Orange Path

2. Core Heat Sink - Red Path

3. Containment Integrity - Red Path

4. Subcriticality - Orange Path

5. RCS Integrity - Red Path

6. Core Cooling - Orange Path QUESil0N 4.07 (2.00)

a. The foldout for the E0P-0 series lists TWO conditions that TOGETHER require the operator to trip all RCPs. What are these TWO conditions?

Include SETPOINTS as applicable. (1.00)

b. According to the foldout for the E0P-1 series, two parameters must be monitored to determine if Safety Injection must be reinitiated. List these TWO parameters. (1.00)

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

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17 RADIOLOGICAL CONTROL QUESTION 4.08 (1.00)

Select the group of indications which are characteristic of natural circulation in accordance with E0P-0.2, Natural Circulation Cooldown.

I CORE EXIT l RCS SG SUBC00 LING PRESSURES Thot Tcold THERM 0 COUPLES

a. 33 F Decreasing Decreasing Decreasing Decreasing

b. 38 F , Constant Constant Decreasing Constant

c. 43 F Decreasing Increasing Decreasing Constant

d. 48 F Constant Constant Constant Constant

e. 53 F Decreasing Decreasing Constant Decreasing QUESTION 4.09 (1.25)

Both plants are in Hot Standby in natural circulation cooldown following a luss of offsite power. Prior to restoring offsite power, a telephone call is received reporting a bomb in the control room. A quick search reveals a

" suspicious" package which prompts the Duty Shift Supervisor to order evacuation of the control room. List FIVE operator IMMEDIATE actions which should be taken, if possible, prior to exiting the control room.

QUESTION 4.10 (2.00)

a. Provide the following exposure limits (non-emergency) for a 25 year old male licensed operator. (1.00)

1. Maximum ADMINISTRATIVE QUARTERLY whole body limit

2. Maximum 10 CFR 20 QUARTERLY whole body limit

3. Maximum ADMINISTRATIVE MONTHLY whole body limit (w/o extension)

4. Maximum 10 CFR 20 LIFETIME whole body limit

b. What INDIVIDUALS may authorize an extension of an ADMINISTRATIVE MONTHLY whole body limit for a licensed operator? Include the MAXIMUM LIMIT that can be authorized by each individual. (1.00)

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

. 4. PROCEDURES --NORMAL,' ABNORMAL, EMERGENCY AND PAGE 18 I

RADIOLDGICAL CONTROL QUESTION 4.11 (2.25)

Refer to figure 4-1 for the following question.

Given each of the following indications, determine whether axial flux difference is being maintained within the appropriate Tech. Spec. limits and EXPLAIN briefly why or why not. '(0.75 each)

POWER AFD AFD AFD AFD LEVEL CHANNEL 1 CHANNEL 2 CHANNEL 3 CHANNEL 4

1. 60% +15 +11 +12 +13

2. 70% -18 -19 -18 -30

3. 90% -12 Out of service -15 -10 1

QUESTION 4.12 (1.00)

During a Natural Circulation cooldown using E0P-0.2, cooldown rate is limited to 25 F/hr. What is the REASON for this limit?

QUESTION 4.13 (2.00)

a. During a reactor startup in accordance with 0F-1B, Reactor Startup, neutron level is stabilized at 10E-7 amps'for critical data. What DATA is reco.rded? (1.00)

b. List TWO conditions which require an Inverse Count Rate Ratio to be plotted during the approach to criticality in accordance with OP-1B?

(1.00)

QUESTION 4.14 (2.50)

a. Technical Specifications and OP-3C, Hot Shutdown to Cold Shutdown, allow deenergizing both RCPs with the reactor subcritical and Tave

> 350 F provided three conditions are met. List these THREE conditions. -

(1.50) ,

b. With the plant solid and in cooldown on Residual Heat Removal, under what TWO conditions may an RCP be started? (1.00)

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

?s

. 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 19 RADIOLOGICAL CONTROL QUESTION 4.15 (2.00)

The following questions refer to the current Standing Orders:

a. What requirements exist in the Standing Order Book for LOGGING equipment readings which are out-of-specification in operating logs?

(1.00)

b. What POSITION should a red-tagged control switch for non-operating equipment be placed in? (0.50)

c. WHO is responsible for affixing an "out-of-service" sticker to a malfunctioning instrument? (0.50)

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

( **** * *** ** * *

E ND OF EX AMI N ATION ****** * * * * * * * * * )

EQUATION SHEET f = ma v = s/t Cycle efficiency = (Net work out)/(Energy in) w = mg s=V,t+1/2ad 2

E = mc -ht KE = 1/2 av Z

a = (Vf - V,)/t A = AN A=Aeg PE = agn Vf = V, + at w = e/t A = an2/t.1/2 = 0.693/t1/2 uD 2 *l/2

W = v AP- A= 4 [(t /2)

I*bI3 aE = 931 am -Ix m = V,yAn ,

Q = niCoat . h = kifi3 (NC) 6 = UAAT AT = krn*2 (NC) I=Ie"# n Pwr = Wfah I = I ,10**/ M TVL = 1.3/u P = P 10 sur(t) HVL = -0.693/u .

t P = Po e /T SUR = 26.06/T SCR = S/(1 - K,ff)

CR, = S/(1 - K,ffx)

SUR = 26p/t- + (a - p)T CRj (1 - K ,ff)) = CR2 (I ~ Seff2) y . (g=f,) + [(s - p yip] M = 1/(1 - K,ff) = CR j/CR, T = t/(p - s) M " (I - Keffo)/(I ~ Eeff1)

T = (8 - p)/(Tp) SDM = ( - K,ff)/K,ff a = (K,ff-1)/K,ff = AK,ff/K eff t' = 10 second A = 0.1 seconds e = C(t=/(T K,ff)] + ts,ff/(1 + IT)]

d Ij j = I d2gd ,2 2 P = ( nV)/(3 x 1010) Id i 22 2 I = oN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (f,,g)

Water Parameters Miscellaneous Conversions

~

I gal. = 8.345 lem. 1 curie = 3.7 x 1010eps 1 ga]. = 3.78 liters } kg = 2.21 lbm 1 ft4 = 7.48 gal.

1 np = 2.54 x 10 3 Stu/nr Oensity = 62.4 lbm/ft3 1 mw = 3.41 x 106 5tu/hr Density = 1 gm/c.r3 lin = 2.54 cm Heat of vacorizath e = 970 Stu/lem *F = 9/5'C + 32 dett of fusion = 144 3tu/Itm *C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf I f t. H 2O = 0.4335 lbf/in.

Table 1. Saturated Steam: Temperature Table kihalpy Entropy Abs Press. Specific Volume Sat. Temp Sat. Sat. Sat.

tb per Sal. Sat. Vapor Fahr Temp Vapor Liquid Evap Vapor Liquid Evap SqIn. Liquid Evap 5 I Fahr Sig i p vt Vie vg hl h f8 hr 51 0 0000 2.1873 2.1873 32.5 3304 7 0 0179 1075.5 1075 5 32 8 0 08859 0 016022 3304 7 0 0041 2.1762 2.1802 34 8 3061.9 1.996 1014 4 1076 4 34 8 0 09600 0 0160?! 3061.9 0 0081 2.1651 2 1132 36 8 2839 0 2839 0 4 008 1073 2 1077.2 36 8 010395 0 016020 0 0122 2.1541 2.1663 38 8 2634.2 6.018 1072.1 1078.1 38 8 011249 0 0160!9 26341 8.027 1071.0 1079 0 0 0162 2.1432 2.1594 48.0 1.12163 0 016019 2445 8 2445 8 2.1325 2.1527 42 8 48 8 10 035 1069 8 1079.9 0 0202 0 016019 2272.4 2272.4 44 8 42 8 0 13I43 12.041 10683 10803 0 0242 2.1217 2.1459 0 14192 0 016019 2112 8 2112.8 2.1111 2.1393 46 I 44 0 14 047 1067.6 1081 6 0 0282 0 15314 0 016020 1965 7 1965.7 2.1006 2.1327 40 0 46 8 16 051 1066 4 1082.5 0.0321 4

016514 0 016021 1830 0 1830 0 48 8 0 0361 2.0901 2.1262 58 0 1704 8 1704 8 18 054 1065.3 1083.4 50 8 0 17796 0 016023 0.0400 2.0798 2.1197 52 0 1589 2 1589 2 20 057 1064 2 1084.2 52 0 0 19165 0 016024 0 0439 2.0695 2.1134 54 8 1482.4 1482.4 22 058 1063.1 1085.1 54 8 0 20625 0 016026 0 0478 2.0593 2.1070 56 8 1333 6 1383 6 24 059 1061.9 1086.0 56 8 0 22183 0 016028 0 0516 2.0491 2.1003 58 8 1292 2 1292.2 26 060 1060 8 1086.9 58 8 023843 0 016031 0.0555 2.0391 2.0946 EE 8 1207.6 1207.6 28 060 10593 10873 EO 8 0 25611 0 016033 0 0593 2.0291 2.0885 E2.0 1129.2 1129.2 30 059 1058.5 1088.6 E2 8 0 27494 0 016036 0 0632 2.0192 2.0824 64 8 1056.5 32 058 10574 1089.5 54 0 0 29497 0 016039 1056 5 0 0670 2.0094 2 0764 EE I 989 0 989.1 34 056 1056.3 1090 4 ES O 0 31626 0 016043 0.0708 1.99 % 2 07G4 EI O 926.5 926.5 36 054 1055.2 1091.2 E8 0 0 33889 0 016046 0 0745 1.9900 2 0645 78 8 868 3 868.4 38 052 1054.0 1092.1 78 I 0.36292 0.016050 0.0783 1.9804 2 0587 12.8 814.3 814.3 40 049 1052.9 1093.0 12 8 0.38844 0 016054 0 0821 1.9708 2 0529 14 9 7641 764.1 42 046 105).8 1093 8 14 8 0 41550 0 016058 0 0858 1.%I4 2 0472 15 0 717.4 717.4 44 043 10503 10943 TE B 044420 0 016063 0 0895 1.9520 2.03:5 JII 673.8 673.9 46 040 1049.5 1095 6 78 8 0 47461 0 016067 0.0932 1.9426 2.0355 88 8 633.3 633.3 48 037 1048.4 1996 4 80 0 0 50683 0 016072 0 0969 1.9334 2 03:3 82.8 595 5 595.5 50 033 1047.3 1097.3 12 8 0 54093 0 016077 0 1006 1:9242 2 0245 84 8 1

560 3 560 3 52 029 10461 10982 84 8 057702 0 016082 527.5 54 026 1045 0 1099 0 0.1043 1.9151 20!i3 86 8 IE S 0 61518 0 016087 227 5 0.1079 1.9060 2.0135 88 8 496 8 4% 8 56 022 1043 9 1099 9 80 0 0 65551 0 016093 0.1115 1.8970 2 00!! 88 8 4681 468.1 58 018 1042.7 1100 8 90 D 0 69813 0 0lbOW 0.1152 1.8881 2 002: 92 0 441 3 441.3 60 0lJ 1041 6 1101 6 92 0 0 74313 0 0161rb 1101 5 0 1188 18792 1 99i. 94 8 94 0 0 19062 0 016111 416 3 4I63 62 010 1040 5 0 1224 I8104 1 93:i SE B 392 8 392 9 64 006 1039 3 1103 3 9E O OS4072 0016117 66 003 19382 l104 2 0 1260 18617 I 92 ? 98 8 0 89356 0 016123 370 9 370 9 98 0

Enthalpy Entropy Abs Press. Specific Volume Sal. Sal. Temp Sat. Sal. Sal.

Temp tb per Sal. Evap Vapor LiquH Evap Vapor Fahr Liquid Evap Vapor Liquid Fahr SqIn. hg sig sg t vg he h ig se I p vg vtg O.1295 1.8530 1.9825 100.0 350 4 350 4 67 999 1037.1 1105i 102.0 ISO 8 0 94924 0 016130 69 995 1035.9 1:05 9 0.1331 1.8444 1.9775 0 016137 331.1 331.1 1.8358 19725 1M I lef t 100789 313.1 313 1 71992 1034 8 1.J6 8 0.1366 ISEI 184 8 1 06 % 5 0 016144 73 99 1033 6 1107.6 0.1402 1.8273 1.9675 1.1347 0 016151 29616 29618 0.1437 1.8188 1.9626 IIII IIII 280 30 7598 1032.5 1108 5 12030 0 016158 28028 188 8 0.1472 1.8105 1.9577 110.I 265.39 77.98 1031.4 1109.3 1 2750 0 016165 26537 0.1507 1.8021 1.9528 112 I IIII 251.38 79 98 1030 2 1110 2 1.3505 0 016173 251.37 0 1542 13938 1.9480 114.0 I12 8 23822 81 97 1029.1 till 0 1.4299 0 016180 238 21 0.1577 13856 1.9433 115 8 114 8 225 85 83 97 1021.9 1111.9 1 5133 0 016188 225 84 0.1611 13774 1.9386 110.0 186 8 214.21 85 97 1026.8 1112.7 0016196 21420 IIIB 1.6009 0.1646 13693 1.9339 128.8 .

203.26 87 97 1025 6 1113.6 122 0 1.6927 0 016204 203 25 0.1680 1.7613 1.9293 IIII 192.95 89 96 1024.5 1114 4 124.0 13891 0 016213 192 94 0.1715 13533 1.9247 122 8 183 24 91.% 1023.3 1115 3 12E I 124 8 1 8901 0 01622I 183 23 93 % 1022.2 1116.1 01749 13453 1.9202 0 016229 174 08 174.09 0 1783 13374 1.9157 12OI 1253 1.9959 95 96 1021.0 1117.0 0 016238 165 45 165.47 178 8 2.1068 0.1817 1.7295 1.9112 130 0 157.33 97.96 1019.8 1117.8 2 2230 0 016247 157.32 0.1851 13217 1.9068 132 I 138 8 99 95 1018 7 1118 6 0 016256 149.64 149 66 0.1884 13140 1.9024 134.0 132e 2.3445 101.95 1017.5 1119 5 0 016265 14240 142.41 0.1918 13063 I.8980 136 I

( 134 8 2 4717 103 95 1016 4 1120.3 2 6047 0 016274 135 55 135 57 0.1951 1.6986 1.8937 138I l 136 8 105.95 1015.2 1121.1 0 016284 129 09 129.11 138 0 2.7438 0.1985 1.6910 1.8895 1488 122.98 123 00 107.95 1014.0 !!22.0 142 5 i

i4II 28892 0 016293 1012.9 1122.8 02018 1.6534 1.8852 3 0411 0 016303 117.21 117.22 109.95 1123 6 02051 1.6759 1.8810 Ita l 142 8 11134 11136 111.95 1011.7 145 I 144I 31997 0 016312 1010.5 1124.5 02084 1.6684 1.8769 106.58 106 59 113 95 148 I 146 8 3 3653 0 016322 1009.3 1125.3 0.2117 1.6610 1.8727 0 016332 101.68 10130 115.95 I48 8 3.5381 0 2150 1.6536 1.8686 150.0 97.07 117.95 1008.2 1126.1 3 7184 0 016343 97.05 0 2183 1.6463 1.8646 152 I 158 8 92.68 119.95 1007.0 1126 9 154I 3 9065 0 016353 92.66 02216 1.6390 1.8606 152I 88 50 88 52 121.95 1005.8 11273 155 0 1548 4 1025 0 016363 1004.6 !!?36 0 2248 1.6318 1.8566 84 56 84.57 123.95 158 I 15E I 4 3068 0 016374 1003.4 1129.4 0.2281 1.6245 1.8526 )

0 016384 80 82 E0.83 125 96 158 8 45197 1.6174 1.8487 158 8 12796 1002.2 1130 2 0.2313 4 7414 0 016395 77.27 77.29 01345 i.6103 1.8448 182 8 168 8 7392 12996 1001.0 1131.0 164 8 4 9722 0 016406 13 90 02377 1.6032 1.8409 IE2 8 70 72 131 96 999.8 1131.8 ISE I 5 2124 0016417 7030 0 2409 1.5%1 1.8371 164 8 6768 13397 998.6 1132.6 54623 0 016428 6767 0.2441 1.5892 1.8333 150.0 IEE 8 64 80 135 97 997.4 1133.4 158 5 5 7223 0 016440 6438 1.5822 1.8295 178 0 137.97 996 2 1134 2 0 2473 59926 0 016451 62 04 62 06 0.2505 1.5753 1.8258 172 I 178 8 139 98 9950 1135 0 lis t 6 2736 0 016463 5943 59 45 02537 1.5684 1.8221 172 0 5697 141.98 993 8 1135.8 176 I 6 5656 0 016474 56 95 02568 1.5616 I8184 1740 54 61 143 99 992.6 11366 6 8690 0 016486 54 59 0 2600 1.5548 1.8147 till 116 0 52 36 I45 99 991.4 1137.4 11840 0 016498 5235 178 0

Enthalpy Entropy Abs Press. Specific Volume Sat. Sal. Temp Sat. Sat. Sat.

Lb per Sat. Liquid Evan Vapor Fahr Temp vapor Liquid Evap Vapor SqIn. Liquid Evap t Fahr vg hl h ig hg 5, sig_s _

i p v, vig 0.2631 1 5480 1.8111 188.8 50 22 148 00 990.2 1138 2 102.0 7.5110 0 016510 50 21 0.2662 1 5413 1.8075 less 48.172 18.189 150 01 9895 1139.0 1848 182 5 7.850 0 016522 152 01 987 8 1139 8 0 2694 15346 I8040 0.016534 46 232 46 249 02725 1.5279 I8004 106 0 184.8 8203 44.400 154 02 926 5 1140.5 8.568 0 016547 44 383 0 2756 1.5213 13969 188 0 ISE O 42.621 42.638 156.03 985.3 1141.3 188 8 8.947 0 016559 0.2787 1.5148 13934 100 8 40.957 158.04 984.1 1142.1 9.340 0 016572 40.941 02818 I.5082 13900 192.8 19e t 39.354 160.05 982.8 1142.9 194 I 9 747 0.016585 39 331 02848 1.5017 13865 192 8 37.824 162 05 981 6 11433 10.I68 0016598 37.808 0 2879 1.4952 13831 195.0 194 0 36.364 164 06 980 4 1144 4 10.605 0016611 36.348 0.2910 1.4888 13798 190 0 196I 34.954 34.970 166 06 979.1 1145 2 190 e !!.058 0 016624 0 2940 1.4824 13764 200 0 33.639 168 09 977.9 1146 0 0 016637 33.622 1.4697 1 7698 284 8 2003 11.526 31.135 31.151 172.11 975 4 !!475 0 3001 2000 12 512 0 016664 11490 0.3061 1.4571 1 7632 204 8 28 862 28 878 176.14 972 8 212 8 208 8 13.568 0 016691 18017 970 3 1150 5 0.3121 1.4447 13568 14 696 0 016719 26 782 26399 0.3181 1.4323 13505 216.0 212.0 0.016747 24 878 24.894 184.20 96 8 1152.0 215 8 15 901 03241 1.4201 13442 228 8 23.148 188 23 965.2 1153.4 17.186 0.016775 23.131 0 3300 1.4081 13380 224 I 220.0 21.545 192.27 962.6 1154.9 18.556 0.016805 21.529 03359 1.3%1 13320 220 8 224I 20 056 20.073 196 31 960 0 1156.3 232 8 20 015 0 016834 957.4 1157 8 03417 I.3842 13260 220 0 18318 200 35 21.567 0 016864 18301 0.3476 13725 13201 23E 8 232 0 17.471 204.40 954 8 1159.2 23.216 0.016895 17.454 236 8 248 8 208.45 952.1 1160 6 0.3533 1.3609 13142 24.% 8 0 016926 16.304 16.321 0 3591 1.3494 11085 244I 248 8 15 260 212 50 949.5 1162 0 26 826 0016958 15 243 03649 1.3379 13028 248 8 2448 14.28I 216 56 946 8 1163.4 28396 0016990 14.264 0 3706 1.3266 1 6912 252 0 248 8 13.358 13.375 220 62 944.1 11643 256 8 I

2528 30 883 0 017022 0.3763 1.3154 16911 12 520 12.538 224 69 941.4 1166.1 1

PSE 8 33 091 0 017055 0.3819 1.3043 1.6862 258 0

!!362 22836 938 6 1167.4

35.427 0.017089 .11345 03876 1.2933 16808 264 8 250 0 11.025 11.042 232 83 935 9 1I68 7 258 8 37.894 0 017123

!!70 0 0.3932 1.2823 16755 254 8 10 375 236 91 9331 258 8 40.500 0 017157 10 358 240 99 930 3 1171.3 0.3987 12715 16702 272 0 43.249 0 017193 9738 9355 OA043 1.2607 1.6650 216 8 212.0 9.162 9.180 24508 927.5 1172.5 275 0 46.147 0 017228 0 4098 12501 16599 280 0 8627 8 644 24917 924 6 ll738 16548 284 0 280 8 ' 49 200 0 017264 9213 1175 0 0 4154 12395 8 1280 8.1453 253 3 208 8 284 8 52 414 0 01130 257 4 918 8 1176.2 04208 12290 1.6498 '

55 795 0 01734 76634 76807 0 4263 12186 16449 292 0 288 5 72301 72475 261.5 915 9 11774 296 I 59 350 0 01738 0 4317 12082 16400 292 8 0 01741 6 8259 6 8433 265 6 913 0 1178 6 296 0 63 084

Enthalpy Entropy Abs Press. Specific Volume Sat. Sal. Sal. Temp Sat. Sal. Vapor Fahr Temp lb per Sal. Evap Vapor Liquid Evap Liquid Evap Vapor Liquid I Fahr SqIn. hg hg l hg sg sig st i p vg vit 't 16351 300 0 269 7 910 0 1179 7 0 4372 11979 67 005 0 01745 6 4483 6 4658 0 4426 1.1877 16303 384 0 38s e 61130 273 8 907 0 1180 9 11.119 0 01749 6 0955 0 4419 I.I176 16256 388 e 384 I 5 7655 5 7830 278 0 9040 1182.0 308 O 15 433 0 01153 9010 11831 0 4533 11676 I6209 312 8 0 01757 5 4566 54742 2821 16162 JIE I 312 8 79 953 286 3 897.9 11841 04586 11576 i

' 84 688 0 01161 51673 51849 ,

315 0 04640 1.1477 1.6116 328 0 48%1 4.9138 290 4 8948 1185 2 324I 32s t 89 643 0 01766 891.6 1186 2 0 4692 1.1378 1.6071 94 826 0 01770 4 6418 0 595 294 6 04745 1.1280 16025 328 8 324.8 298 7 888.5 1187.2 0 01774 4 4030 4 4202 1.1183 15981 332.0 328 9 100 245 302 9 885.3 1188 2 0.4798 0.01779 4 1788 4.1 % 6 336.0 332.0 105 907 307.1 882.1 1189.1 04850 1.1086 1.5936 111.820 0 01783 3%81 3 9859 335 8 04902 10990 15892 3488 33699 3 7878' 311 3 878 8 11901 3448 348.8 117.992 0 01787 875 5 1191 0 0 4954 10894 1.5849 3 5834 3 6013 315 5 3488 3445 124 430 0 01792 319 7 872 2 1191.1 0 5006 1.0799 1.5806 131.142 0 01797 3 4018 3 4258 0 5058 10705 I5763 352 8 348 8 323 9 868 9 1192.7 138.138 001801 3 2423 3 2603 05110 10611 1.5121 356 8 3528 328I 865 5 !!93 6 145 424 O01806 3 0863 3.1044 l 355 8 0 5161 1.0517 1.5678 358 8 2 9392 2 9573 332 3 8621 1194.4 364 e 358 8 153 010 0 01811 858 6 Il95 2 0 5212 10424 15637 0 01816 2.8002 2 8184 336 5 15595 368 e

354.s 160 903 855I 1195 9 0.5263 10332 0 01821 2 6691 2 6813 340 8 372 8 358 8 169 113 8516 11 % 7 0 5314 1 0240 1 5554 2 5451 25633 345 0 376 I 0 01826 1.0148 15513

! 372.8 177 648 848.1 1197 4 0 5365 0 01831 2 4279 2.4462 349 3 375 8 186 517 0 5416 1.0057 1.5473 388 8 2 3170 23353 353 6 844.5 1198 0 384 8 300 0 195329 0 01836 3579 840 8 1198 7 0 5466 09%6 1.5432 205 294 0 01842 2.2120 2 2304 0 5516 0 9876 1 5392 388 8 1 384 8 362 2 837.2 1199 3 215 220 0 01847 2.1126 2 1311 0 5567 09786 1.5352 392 8 3880 366 5 833.4 1199.9 2.0369 392 8 225 516 0 01853 2.0184 0 5617 0 9696 I5313 39E 8 l 1.929! I.9477 370 8 8293 1200.4 i 395 8 236 193 001858 0.5667 0 9607 1.5274 400 8 1.8444 1.8630 375.1 825.9 1201.0 404 8 488 I 247 259 0 01864 0 5717 0 9518 1.5234 l 13640 1.7827 3794 822 0 1201.5 400 e 484 8 258 725 0 01870 0 5766 0 9429 1.5195 I6877 13064 383 8 818 2 1201.9 412 s 488 I 270 600 0 01875 0 5816 09341 1.5157 1.6152 1.6340 3881 814.2 1202.4 416 8 412 0 282.894 0 01881 0 5866 0 9253 1.5118 1.5463 1.5651 392 5 810 2 1202.8 415 8 295 617 00iB87 0 5915 0 9165 1.5080 470 0 1.4808 1.4997 396 9 806 2 1203.1 424 I 428 I 308 780 0 01894 05%4 0 9077 1.5042 1.4184 1.4374 4013 802.2 1203.5 428 0 4248 322 391 0 01900 0 6014 0 8990 15004 1359I I.3782 405 7 798 0 12033 428 8 336 463 001906 793 9 1204 0 0 6063 0 8903 14966 432 0 0 01913 1.30266 1.32179 410 1 436 0 432 6 351 00 189 7 1204.2 0 6112 0 8816 1.4928 0 01919 124887 1 268 % 414 6 43E B 366 03 l 06161 0 8729 I4890 440 8 121687 419 0 785 4 1204 4 440 0 38154 0 01926 I19761 731.1 1204 6 0 6210 08643 14853 4440 0 01933 I14814 I16806 423 5 449.0 4440 397 56 776 7 1204 7 06259 0 8557 14815 0 01940 110212 112152 428.0 4430 414 09 772 3 1204 8 0 6308 0 8411 14778 452.0 43114 0 01947 1 05764 1 07711 4325 I4731 ess.e 4 528 4310 767 8 1204 8 0 6356 0 8385 ma mn 0 01954 101518 103412 i

i

Specific Volume- Enthalpy Entropy Abs Press. Sat. Temp Sal. Sat. Sal. Sal. Sat.

Temp lb per Vapor liquid Evap Vapor Fahr SqIn. Liquid Evap Vapor Liquid Evap Iabr hg s, sg I v, vtg vg hg h rg sgg i p 0 97463 0 99424 441.5 763.2 1204.8 0.6405 0.8299 1.4704 468.0 46D 8 466 87 0 01961 0 6454 0 8213 I.4667 464.0 0 01969 0 93588 0 95557 4461 758 6 12043 464 8 485 56 0 6502 0.8127 1.4629 468.0 0 01976 0.89885 0.91862 4503 754.0 1204.G 468 8 504 83 0.6551 0.8042 1.4592 472.5 0 0l984 0 86345 0 88329 455 2 749.3 1204 5 472 8 524 67 0 6599 03956 1.4555 476 0 0.84950 459.9 744.5 1204.3 416 8 545.11 001992 0 82958 0 81717 464.5 739.6 1204.1 0.6648 03871 1.4518 488.8 480 0 566 15 0 02000 0.79716 0 66 % 03785 1.4481 484I 0 02009 036613 0 78622 4691 7343 1203 8 4B4 0 587 81 0.6745 03700 1.4444 488 0 610 10 0 02017 033641 0 75658 473.P 7293 1203.5 til 8 032820 478.5 724.6 1203.1 0 6793 01614 1.4407 492.0 492 0 633 03 0 02026 030794 0.6842 03528 1.4370 496.0 010100 493 2 719.5 1202.7 496 8 656 61 0 02034 0 68065 0.C7492 487.9 714.3 1202.2 0.6890 01443 1.4333 500.8 5000 680 86 0 02043 0 65448 0 6939 03357 1.4296 564.0 0 02053 0.62938 064991 4923 7090 1201.7 564 0 705 78 0 62592 497.5 703.7 1201.1 0.6981 012il 1.4258 Set 8 508 0 73140 0 02062 0 60530 0 7036 01185 1.4221 517 8 0 60289 502.3 698.2 1200.5 517 1 75732 0 02072 0.58218 a.7085 0.7099 1.4183 516.8 784.76 0 02081 0 55997 0 58079 507.1 6923 1199.8 516 0 03133 01013 1.4146 520.0 0.53064 0 55956 512.0 687.0 1199.0 570 0 812 53 0 02091 03182 0.6926 1.4108 524.8 0.53916 516.9 681.3 1198.2 5740 841.04 0 02102 0.51814 01231 0.6839 1.4070 528 8 0 51955 521.8 675.5 1197.3 5780 870 31 0 02112 0 49843 03280 0.6752 1.4032 532.0 0.50070 526 8 659 6 1196 4 537 8 900 34 0 02123 047947 1195.4 01329 0.6665 1.3993 536.0 0 02134 0.46123 0.48257 5313 663.6 5360 931.17 0.46513 536.8 657.5 1I94.3 0 7378 0 6577 1.3954 548.0 5400 96239 0 02146 0 44367 0 7427 06489 1.3915 544.0 0 44834 541.3 651.3 1193.1 5440 995 22 0 02157 042677 645.0 1191.9 03476 0.6400 1.3876 548.0 1028 49 0 02169 0 41048 043217 546.9 552.5 548 O 041660 552 0 638.5 1190 6 03525 0 6311 1.3837 557 0 1062 59 0 02182 0.39479 0 7575 0 6222 1.3797 556.0 0 40160 557.2 632.0 1189.2 556 0 1097.55 0 02194 0 37966 0.38714 562.4 625 3 1187.7 0.7625 0.6132 1.3757 560.0 5600 1133 38 0 02207 0 36507 1186.1 0.7674 0 6041 1.3716 564 0 0 35099 0.37320 5676 618.5 564 0 1170 10 0 02221 0 7725 0 5950 1.3675 568 8 0 02235 0 33741 035975 572 9 611.5 !!84.5 572.0 5650 120132 604 5 11823 03775 0.5859 1.3634 0 02249 0 32429 0 34678 578 3 576 8 577 0 1246 26 1180.9 07825 0.5766 1.3592 0 33426 583 7 597.2 516 0 128574 0 02264 0 31162 03876 0.5673 1.3550 580.0 0 32216 5891 589.9 1179 0 580 0 1326 17 0 02279 0 29937 07927 05580 1.3507 584.8 0 31048 594 6 582.4 1176 9 5840 13673 0 02295 0 28153 0 7978 0 5485 1.3464 588.8 0 02311 027608 029919 6001 5743 1174 8 588 0 1410 0 6053 566.8 II72 6 0 8030 0 5390 1.3420 592.0 0 02328 0 26499 0 28827 596I 597 0 1453 3 0 27770 611.4 558 8 1170.2 0 8082 0 5293 1.3375 5960 14978 0 02345 0 25425

Specihc Volume Enthaf.aY Entropy Abs Press. Sat. Sat Temp Sal. Sat. Sat. Sat.

Temp Lb per liquid Evap Vapor Fahr Liquid Evap Vapor Liquid Evap Yapor Fahr SqIn. sg I y, v ,, hl h ig hg sg sig t p v8 0.8134 0.5196 1.3330 000.8 l 0.26747 617.I 550 6 1167.7 SN I 580 8 15432 0.02364 0 24384 542.2 1165.1 0.8187 0.5097 1.3284 0 02382 0 23374 0 25757 622.9 588.8 0.4997 1.3238 584 8 1589 7 628.8 533 6 1162.4 0.8240

) 16373 0.02402 0.22394 0.24795 0.8294 0.48 % 1.3190 512.0 588 8 0 23865 634.8 524.7 1159.5 1686 1 0.02422 0.21442 0.8348 0.4794 1.3141 515.0 512 8 640.8 515.6 1156 4 i

1735 9 0 02444 0.20516 0.22960 515 5 0.8403 0.4689 1.3092 820.0 0 22081 646.9 5063 1153.2 524.0

' 573 8 1786 9 0.02466 0.19615 4?6.6 1149 8 0.8458 0.4583 1.3041 0 02489 0.18737 0.21226 653.1 548.8 524 8 1839 0 659.5 486 7 11461 0.8514 0.4474 1.2988 j

1892 4 0 02514 0.17880 0 20394 0.8571 0 4364 1.2934 532.0 4 528 8 665.9 476.4 1142.2 19470 0 02539 0.17044 0.19583 0.8628 0.4251 1.2879 535 I 532 8 672.4 465.7 1138.1 2002 8 0 02566 0.16226 0.18792 t 535 8 0.8686 0.4134 1.2821 548.0 0.18021 679.1 454.6 1133.7 2059 9 0.02595 0.15427 0.8746 0.4015 1.2761 544.0 540 8 0.17269 685.9 443.1 1129.0 544 8 2118 3 0 02625 0.14644 431.1 1I24 0 0.8806 03893 1.2699 548.8 0 02657 0.13876 0.16534 692.9 552.0 i 548 8 21781 700 0 418.7 1118 7 0 8868 03767 1.2634 0 02691 0.13124 0.15816 03637 1.2567 555.0 552 0 2239 2 405.7 1113.1 0.8931 0.02728 0.12387 0.15115 707.4 555 8 23017 l 0.8995 03502 1.2498 558.8 0.14431 714.9 392.1 1107.0 554.8 558 8 2365 7 0.02768 0.11663 377.7 1100.6 0.9064 03361 1.2425 0 02811 0.10947 0.13757 72 2.9 558.0 554 8 24311 362.1 1093.5 0.9137 03210 1.2347 0 02858 0.10229 0.13087 731.5 572.8 558 8 24981 345.7 1085 9 0.9212 0 3054 1.2266 0 02911 0.09514 0.12424 1402 575.8 572 8 2566 6 328.5 1077.6 0.9287 0.2892 1.2179 0 02970 0.08799 0.11769 749.2 575 3 26368 l 0.9365 0.2720 1.2086 500.0 758.5 310.1 1068.5 GH.S 2708 6 0.03037 0.08080 0.11117 0.9441 0.2537 1.1984 580.5 768 2 290.2 1058.4 588 t 2782.1 0 03114 0.07349 0.10463 0.9535 0.2337 1.1872 EH 8 778.8 268.2 1047.0 28574 0.03204 0.06595 0.09799 0 9634 0.2110 1.1744 592.8 588 0 0 09110 790 5 243.1 1033.6 595.0 597 8 2934.5 0 03313 0 05797 212.8 1017.2 0.9749 0.1841 1.1591 0.03455 0.04916 0.08371 804.4 555 8 ,,3013.4 780 0 172.7 995.2 0.9901 0.1490 1.1390 0 03662 0 03857 0.07519 822.4 0.1246 1.1252 702 0 780 8 30943 144.7 979.7 1.0006 0 03824 0 03173 0 06997 835 0 0.0876 1.1046 TH.S 702 8 3135 5 102.0 956.2 1.0169 0 04108 0 02192 0 06300 654 2 0.0527 1.0856 785 8 704 8 3177.2 61.4 934.4 1.0329 l 0 04427 0.01304 0 05730 873 0 0.0000 1.0612 78547' 785 8 31983 0.0 906.0 1.0612 i

0.05078 0 00000 0.05078 906 0 705 47* 32082 l

j i

Table 2: Saturated Steam: Pressure Table

t Enthalpy Entropy l Specific Volume Liquid Evap Vapor Liquid Evap Vapor Lb/Sq In. i bl in fan L quid Evap Va hg s, sig sg P p t V ig Vg hg hgg

{ V:

a 0 0000 2.1872 2 1872 080865 088865 32.018 3302 4 3302.4 0 0003 1075.5 1075 5 0.016022 0 0542 2.0425 2 0967 0 25 '

- 0 25 59 323 0 016032 1235 5 1235 5 27 382 1060.1 1087.4 0 0925 1.9446 2.0370 8 58 8.58 19 586 0 016071 641.5 641.5 47.623 1048 6 1095 3 i 0.1326 1.8455 I.9781 II 10 101.74 0 016136 333 59 333 60 69 73 1036.1 1105 8 i

1131.1 0 2349 1.6094 1.8443 58 58 16234 0.016407 13 515 73 532 130 20 1000 9 i 1143.3 0 2836 1.5043 17879 Ill i III 193 21 0 016592 38 404 38.420 161.26 982.1 970.3 !!50 5 0.3121 1.4447 13568 -14 696 14.596 212.00 0 016719 26182 26399 18017

9693 1150 9 0.3137 1.4415 13552 15 8 15.0 213.03 0 016726 26.274 26 290 18131 l

20 087 196.27 9601 1156.3 0.3358 1.3%2 13320 20 8 28 8 227.96 0 016834 20 070 133436 218.9 945 2 1I64.1 0.3682 1.3313 16995 38 9 3e e 250.34 0 017009 133266 16765 40 g 10 4 % 5 236I 933 6 1169 8 0 3921 1.2844 40 0 26725 0 017151 10 4794 1.2474 1.6586 Sa g

{

84%7 8.5140 250 2 923 9 !! 14 1 0.4112 Se e 281 02 0 017274 1.2167 16440 lei 29211 7.1562 7.1736 262 2 915 4 1177.6 04273 68 8 0.017383 1.1905 I6316 78 8 l

7e e 302.93 0 017482 51875 6 2050 2723 9078 !!80 6 0.4411 1

5.4711 282.1 900 9 1183 1 0 4534 1.1675 16208 Se s se e 312 04 0 017573 5.4536 90 8 290.7 834 6 !!85.3 0.4643 1.1470 1.6113 90 0 320.28 0.017659 4 8779 4.8953 298.5 888 6 1187.2 0.4743 1.1284 1.6027 les 8 lesI 327.82 0.017740 4.4133 4.4310 ligI 305 8 883.1 1188.9 0 4834 1.1115 1.5950 j 110 3 33439 0 01782 4 0306 4.0484 3.7275 312.6 877.8 !!90.4 0.4919 1.0960 15879 128 8 120 0 341.27 0 01789 3 7097 138 8 l

319 0 872.8 11913 0.4998 1.0815 1.5813

148 8 347.33 0.0!?% 3.4364 3.4544 868 0 1193.0 0.5071 1.0681 1.5752 les e 14e 3 353.04 0.01803 3 2010 3.2190 325 0 l

330 6 863.4 1194.1 05141 1.0554 1.%95 - 158 O 15ee 358 43 0.01809 2.9958 3 0139 336.1 859 0 11951 0 5206 10435 1.5641 ist O 1 15e 8 363 55 0.01815 2.8155 2.8336 341.2 854 8 !!96 0 0 5269 1.0322 15591 178 8 178.8 368 42 001821 2 6556 2 6738 l 8503 '1196 9 0 5328 1.0215 15543. Ise e Ise B 373 08 001827 2.5129 2.5312 346 2 8

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9 P y J

Enthalpy Entropy Specific Volume Sat. Sat. Sat. Abs Press.

Sat. Sat. Sat. Vapor tb/5q In.

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!!$5 6 08363 0 4765 I3I28 1758 I 0 22713 642 5 513 1 13079 1888 8 1750 0 617.12 0 02450 0 20263 1152.3 0.8417 0.4662 0 19390 0 21861 648 5 503.8 13030 18588 1800 0 621 02 0 02472 494 6 !!49 0 0 8470 0 4561 624 83 0 02495 0 18558 02l052 654 5 1145 6 08522 0 4459 12981 1988I 1958 8 0 20278 660 4 485 2 12931 19588 1908 8 628 56 0 02517 0 11761 1142 0 0 8574 0 4358 019540 666.3 475 8 12881 2008 0 19588 632 22 0 02541 0 16999 1138 3 0 8625 0 4256 0 18831 612.1 466 2 12180 218e B 635 80 002565 0 16266 IJ 30.5 08727 0 4053 20008 0.14885 011501 683 8 4463 12676 2290 8 2188 8 64236 0.02615 4263 1122.2 0 8828 0.3848 0 02669 0 13603 0.16212 695 5- 03640 12569 2300 I 2208 8 649 45 406 0 1113 2 0.8929 002727 0.12406 0 15133 707.2 1 2460 24000 2380 0 655 89 384.8 11033 0 9031 0.3430 0 02790 0.11287 0.14076 719 0 2488.8 662.11 0 3206 1 2345 2580 0 731 7 361 5 1093 3 0 9139 668 11 0 02859 0 10209 0 13068 0 2977 12225 2688 0 25808 744 5 3376 1082 0 0.9247 673 93 0 02938 0 09172 0.12110 0 9356 0 2741 1 2097 2700 5 2600 8 757 3 312.3 1069 7 679 53 0 03029 0 08165 011194 0 9468 02491 11958 2800 0 .

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. 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 38 RADIOLOGICAL CONTROL ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 4.01 (2.00)

1) Control rods within + or - 15 steps of group demand position (0.5 ea)

2) Proper sequencing 1nd overlap of rod groups

3) Control rod insertion limits are maintained

4) AFD is maintained within limits REFERENCE TECHNICAL SPECIFICATIONS, P. 15.3.10-10 TAA, LP0454, P.5 001/000; K5.08 (3.9/4.4) & K5.58 (2.7/3.2)

PWG/5/2.9/3.9 ANSWER 4.02 (2.00)

a. Maximum attainable. (OK to exceed 100 F per hour) (0.50)

b. To minimize RCS inventory loss (0.25) via the RCP seals.(0.25)

c. To prevent injection of accumulator nitrogen into the RCS. (0.5)'

d. Continue depressurizing. (0.5)

REFERENCE ECA-0.0, P.13 PWG/7/3.5/4.0 ANSWER 4.03 (1.00) c.

REFERENCE E0P-0, P. 3,4,5,28 PWG/11/4.3/4.4

?

a l

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 39 RADIOLOGICAL CONTROL

- 87/02/17-KINGSLEY, I.

ANSWERS -- POINT BEACH 182 ANSWER 4.04 (1.00)

a. Prior to exceeding 100 mr. (0.50)

b. When entering the Containment Structure during power operation. (0.50)

REFERENCE HP MANUAL, SECTION 1.7, P. 2 HP MANUAL, SECTION 1.10, P. 1 PWG/15/3.4/3.9 PWG/16/3.4/3.9 ANSWER 4.05 pf9,4&f N

a. 1. d. N i

3. d or a. (either one)

4. d.

5. a.

6. b. M'I2r --" '-- - +^* ' "' ' "#

b. 1. General Emergency

2. Site Area Emergency

3. Alert .9# *f#

4. Unusual Event (08for each classification, Mor proper order)

REFERENCE E-Plan, APP. A PWG/36/2.9/4.7 PWG/30/3.5/4.5 ANSWER 4.06 (1.00) -

2 I

y - , _ _ . . _ . _ . _ . _ _ . , . , , _ , , _ , , . . . , _ .-._.m . , _ _ _ . ., - , _ _ _ _ . , _ - . . , , , - _ _ . , ,_, - _. . , . . , - ,-v.-----

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40 RADIOLOGICAL CONTROL ANSWERS -- POINT BEACH 142 -87/02/17-KINGSLEY, I.

I REFERENCE LP0159, P. 15 PWG/10/4.1/4.5 l

ANSWER 4.07 (2.00)

a. At least one SI pump running (0.50), and RCS subcooling less than 30 F.

(0.50)

b. RCS subcooling (0.50) and pressurizer level. (0.50)

REFERENCE E0P-0 FOLD 0VT E0P-1 FOLD 0UT 3.4/000/003/A2.02/3.7/3.9 3.3/009/000/EK3.23/4.2/4.3 3.3/009/000/EA2.34/3.6/4.2 ANSWER 4.08 (1.00) d.

l REFERENCE E0P-0.2, P.7 3.3/009/000/EA2.37/4.2/4.5

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41 RADIOLOGICAL CONTROL ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 4.09 (1.25)

1. Verify both reactors tripped.

2. Place atmospheric steam dump valves in Manual and shut.

3. Shut MSIVs.

4. .Open P29 steam supply valve and feed B steam generator at 80 - 100 gpm.

5. Place main feed valves; 466,476,480,481 in Manual and shut.

Initiate Manual S'a+y hdRC x4 MS*M ,

7. Notify CAS that A0P-10A has been initiated.

8. Shift Telex to main office.

9. Remove portable radios. (any five at 0.25 each for a total of 1.25)

REFERENCE A0P-10A PWG/11/4.3/4.4 ANSWER 4.10 (2.00)

a. 1. 2500 mrem

2. 3000 mrem (0.25 each for a total of 1.00)

3. 450 mrem

4. 35000 mrem (5 x (N - 18) = 5 x 7 = 35 rem)

b. 1. Immediate supervisor (0.25) up to 1050 mrem /qtr. (0.25)

2. Group head (0.25) up to 2500 mrem /qtr. (0.25)

REFERENCE HEALTH PHYSICS MANUAL, SECTIONS 1.2, 1.3, AND 2.1.2 PWG/15/3.4/3.9 PWG/16/3.4/3.9

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42 RADIOLOGICAL CONTROL ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

l ANSWER 4.11 (2.25)

1. No (0.50) Two channels exceed limits. (0.25)

2. Yes (0.50) Less than two channels exceed limits. (0.25)

3. Yes (0.50) Less than two channels exceed limits. (0.25) ,

REFERENCE Technical Specifications, P. 15.3.10-12

PWG/8/3.5/4.5 ANSWER 4.12 (1.00)

To prevent voiding (0.50) in the reactor vessel upper head (0.50).

REFERENCE E0P-0.2 PWG/7/3.5/4.0 ANSWER 4.13 (2.00)

a. 1. Rod position (bank and step) (0.50)

2. RCS. temperature (0.50)

b. 1. Reactor has been subcritical for > or = 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to approach to criticality. (0.50)

2. Reactor is not critical by ERP + 400 pcm. (0.50)

REFERENCE OP-1B, P. 1,5,6 PWG/12/3.5/3.4 6

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 43 RADIOLOGICAL LUNTRUL ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

.:..;J ANSWER 4.14 Hh"J0)f;8g 7

.o

a. 1. No RCS boron dilution operations are permitted.

2. RCS subcooling is maintained > or = 10 F.

3. The reactor trip breakers are open. (0.50 each) b.

""'a arietc ia th: pr ;;..-!;;r r CC 'J-t.L;;, ;; 'C.507"~~

9J5 SG water temperature < 50 F above RCS temperature. (d 00h

REFERENCE A pp OP-3C, P.1 and 2 TECHNICAL SPECIFICATIONS, P. 15.3.1-1 PWG/34/2.8/3.3 PWG/8/3.3/4.5 ANSWER 4.15 (2.00)

a. 1. Red-circled (0.50)

2. Explained in remarks section (0.50)

b. Pullout (0.50)

c. The originator of the maintenance request. (0.50)

REFERENCE STANDIh4 ORDER BOOK, SECTIONS 4.12.1 and 4.12.3 1

l l

l

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 20 THtKMUDYNAMIC5, HEAT TRAN5FER AND FLUID FLOW

~

ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 1.01 (2.00)

1. DECREASE (060 each)

2. INCREASE

5. DECREASE g

4. DECREASE REFERENCE TRHB 39.2, P. 20-35 3.5/000/039/K5.04/2.1/2.1 ANSWER 1.02 (1.00) 1 Margin to criticality decreases by 3/4.

REFERENCE TRHB 32.4, P. 43,47 001/000; K5.18 (4.2/4.3) l ANSWER 1.03 (1.00) b REFERENCE TRHB 43.1, P. 18 3.9/000/016/K1.01/3.4/3.4 ANSWER 1.04 (1.50)

Power range instruments indicate a higher value than actual reactor power.

(0.50)

This is because the higher value of feed flow used in the calorimetric calculation yielded a higher than actual heat transfer rate across.the steam generator U-tubes.(1.00) (Therefore, since NIs were adjusted to indicate this higher power level, they are indicating too high.)

REFERENCE Steam Tables and Mollier chart , .- -

3.9/000/015/K5.04/2.6/3.1 1 C 0 Oc-'*

\ t!;'CD {V?4 b

~

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 21 THERMODYNAMIC 5, HEAT TRAN5FER AND FLUID FLOW ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 1.05 ( .50)

Voiding in the RCS (during depressurization).

REFERENCE TRHB 40.2, P. 48 LP0378, E0 1.3 017/000/EK1.01/4.4/4.6 4

ANSWER 1.06 (2.50)

a. Provides for a more uniform reactivity addition rate. (0.50)

1. There is more control area available for the same mass of poison.

2. Localized flux depression is minimized. (0.50 for each)

c. 1. IRW increases

2. IRW increases (0.50 for each)

REFERENCE TRHB 32.5, P. 21,22,27 3.1/000/001/K5.58/2.7/3.2 3.1/000/001/K5.02/2.9/3.4 3.1/000/001/K6.01/2.2/2.5 ANSWER 1.07 (1.25)

P(f) = P(i)

10expSUR(t)

P(f) = 1000

10exp1(.5)

P(f) = 1000

10exp.5 (0.75 for proper method)

P(f) = 1000

3.160 i P(f) = 3160 cpm (3000 - 3250 is acceptable) (0.50)

REFERENCE TRHB 32.4, P. 21 ,

3.9/000/015/A1.03/3.7/3.7

--m- -

. - , - - . _ - . . ~ - _ _ , . - - - - , , - - - y --.ew -- - - - - - . . - - .

L

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 22 IHLKMUUTNAMIC5, HEAT TRANbrtR AND FLUID FLDW ANSWERS -- POINT BEACH 182 -87/02/17-XINGSLEY, I.

ANSWER 1.08 (2.25)

a. DECREASE (0.25)

At lower Tave moderator density changes a smaller amount per degree than at higher Tave. (0.50)

b. DECREASE (0.25)

With rods withdrawn furtner within the core, the increased slowing down length of neutrons which accompanies a Tave increase will have a smaller effect (less absorption in rods). (0.50)

c. INCREASE (0.25)

As RCS boron concentration decreases, thermal utilization increases which causes MTC to increase (become more negative). (0.50)

(ALTERNATE JUSTIFICATION MAY BE ACCEPTED FOR FULL CREDIT)

REFERENCE TRHB 32.5, P. 35 3.1/000/001/K5.49/3.4/3.7 ANSWER 1.09 (2.00)

a. SAME [0.50] Xenon will peak at 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months af ter trip and then decrease.

At 10.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after the trip, Xenon will have the exact same reactivity effect as it did at 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the trip.[0.50] (1.00)

b. HIGHER [0.50] The corresponding temperature increase (and associated negative reactivity) must be compensated for by a higher critical rod position. [0.50] (1.00)

REFERENCE OP-1B, APP. A 3.1/010/001/A2.07/3.6/4.2 ANSWER 1.10 (2.00)

a. INCREASES (0.50) Rods will withdraw (to compensate for boration).(0.50)'

b. NO CHANGE (0.50) Other rods will withdraw (to compensate). (0.50)

& ACS Tm A&(#y.)

I

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 23 THERMUDTNAMIC5, HEAT TRAN5FLR AND FLUID FLOW ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

1 REFERENCE OP-3B, APP. A 3.1/010/000/K5.35/3.3/3.5 ANSWER 1.11 (1.00)

The faster the rate, the lower the source range counts at criticality (0.5) due to the reduced time for subcritical multiplication. (0,5)

REFERENCE TRHB 32.4, P. 43 3.1/000/001/K5.18/4.2/4.3 ANSWER 1.12 (1.50)

a. Unit 2 (0.25) due to a lower value of Beff.(0.50)

b. Unit 2 (0.25) due to a more negative MTC.(0.50)

REFERENCE TRHB 32.4, P. 12 TRHB 32.5, P. 38 3.1/000/001/K5.47/2.9/3.4 3.1/000/001/K5.49/3.4/3.7 e

9

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 24 IHtKMUUYNAMIC5, HEAT TRAN5PLM AND FLUID FLOW ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,I.

ANSWER 1.13 (1.50)

To determine flow in NC:

Q=$cpdelta-T => 100 = 100

cp

56 Q1=Elcpdelta-T=> 2=El*cp*28 100 100

cp

56

__.....__ = ___________..___.

2 ml

cp

28 (1.00 for acceptable mettod) 200 50 = ---------

ml

$1 = 4.0 percent (0.50)

REFERENCE TRHB 39.1, P.40 3.2/020/002/K5.01/3.2/3.6 ANSWER 1.14 (2.00)

! a. INCREASE (0.5 each)

b. INCREASE

c. REMAIN THE SAME or INCREASE if Tave is assumed to decrease

d. DECREASE REFERENCE TRHB 39.3, P. 82 3.9/020/015/K5.09/3.5/3.7 i

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 25 THERMODYNAMIC 5, HEAT TRANSFER AND FLUID FLOW ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,I.

ANSWER 1.15 (1.50)

a. 300 F (290-310 F acceptable) (0.50)

b. 1192 BTV/LBM (1190-1195 BTU /LBM acceptable) (0.50)

c. 1. (0.50)

REFERENCE TRHB 39.1, P. 124 STEAM TABLES COMPONENT-VALVE /2.0/2.3 COMPONENT-HX and CONDENSER /3.1/3.2 ANSWER 1.16 (1.50)

a. Increases (0.50)

b. Decreases (0.50)

c. Decreases (0.50)

REFERENCE TRHB 40.2, P. 10 COMPONENT / PUMPS-CENTRIFUGAL /2.9/3.2 0

i

'. 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 26 ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,I.

ANSWER 2.01 (1.25)

1. Seal water delta-P (0.125) > 10 psid (0.125) D /O *

2. Discharge valve closed (0.25)

Pump suction pressure (0.125) > 184 psig (0.125) f /0 #

3.

4. Lube oil pressure (0.125) > 10 psig (0.125) t /aIo

5. No protective relay tripped (0.25)

REFERENCE LP0946, TP-6 3.5/000/059/K4.14/2.1/2.3 ANSWER 2.02 (2.00)

a. Ensures that negative reactivity will be added to the RCS (0.50) if the RHR system is required to inject in an accident condition (safety injection) (0.50).

b. RHR pumps take suction on RWST and discharge to SIP suctions (0.50).

Flow goes through SI test line back to RWST(0.50)

REFERENCE OP-78 3.4/000/005/K5.09/3.2/3.4 ANSWER 2.03 (1.50)

a. 1. RWST (0.50)

2. RMWT and BAST (via blender) (0.50)

b. 2. (0.50)

REFERENCE P8 EXAM BANK T#P0605 COT Q#13 :

PB EXAM BANK T#P0601 COT Q#11 PB EXAM BANK T#P0607 COT Q#15 3.2/020/006/K1.03/2.4/2.6 3.2/020/006/K4.02/3.3/3.6

F

~

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 27 l

. ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 2.04 (1.50)

a. Alerts operator that level is approaching Tech. Spec. limit. (0.50)

b. Alerts operator to start preparing to shift to recire. phase of safety injection. (0.50)

c. Alerts operator to transfer RHR suction to containment sump B (loss of suction from RWST is imminent). (0.50)

REFERENCE PB EXAM BANK T#P1904 COT Q#23 3.2/020/006/A1.09/3.3/3.9 3.2/020/006/A4.02/3.9/3.8 ANSWER 2.05 (1.00)

It allows the operator time to take manual control of the valves and maintain them closed (0.50) in the event (the containment pressure increase is due to a secondary coolant leak for which) NA0H addition is not required. (0.50)

REFERENCE TRHB 10.12, P. 6 3.6/000/026/A2.03/4.1/4.4 3.6/000/026/A2.05/3.7/4.1 2.06 (1.50) /,

ANSWER

1. Places backup tank ervice. (0.50 2. e 14 4

2. Isolate service tank. (0.50) 4 ." ? S d 2, m as analyzer aligns to sample backup tank. O.

REFERENCE F

TRHB 10.15, P. 26 ,

3.11/000/071/K4.01/2.6/3.0

. 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 28

. ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,I.

ANSWER 2.07 (1.00)

1. Minimizes motor starting current (by holding the motor idle instead of allowing it to rotate in reverse). (0.50)

2. Minimizes the total amount of NC system flow which bypasses the core (via the idle NC pump by preventing reverse rotation). (0.50)

REFERENCE LP0125. E0 1.2.1 3.4/000/003/K4.05/2.3/2.7 3.4/000/003/K6.08/2.1/2.5 ANSWER 2.08 (2.50)

a. Low pressurizer pressure (0.10) 1735 psig(0.10) 2/3(0.10)

High contalmen.t pressure (0.10) 5.00 psig(0.10) 2/3(0.10)

Low steamline pressure (0.10) 530 psig(0.10) 2/3(0.10)

(0.90)

b. High head injection (0.25) 1550 + or - 50 psiglt :di.;;)*'(0.25)

Accumulators (0.25) 750 + or - 50 psig (0.25)

Low head injection (0.25) 160 + or - 20 psig (0.25)

(0.10 for the correct order) (1.60)

REFERENCE TRHB 10.8, P. 5,24 TRHB 13.4, P. 11,12 3.2/000/006/K4.05/4.3/4.4 3.2/000/006/K6.02/3.4/3.9 3.2/000/006/K6.03/3.6/3.9 3.2/000/006/K5.06/3.5/3.9 4

0

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 29

. ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 2.09 (2.00)

a. 1) To reduce thermal stress to the spray line and spray nozzle. (0.50)

2) To maintain Pzr. chemistry uniform with the RCS. (0.50)

b. 1) Pressurizer Spray Line Lo Temperature alarm (0.25)

2) Pressurizer Surge Line Lo Temperature alarm (0.25)

c. 1) Differential pressure across the reactor vessel (will also accept '

delta-P from spray connection to surge connection). - 0.25) -

2) Velocity head of the RCS flow via sp ay scoo s. 3 Ja '25t

$) b f f f:'-j k REFERENCE TRHB 10.3, P. 6,7,21 Y y gyy 3.3/000/010/K4.01/2.7/2.9 3.3/000/010/K1.03/3.6/3.6 3.3/000/010/A2.02/3.9/3.9 3.4/000/003/A1.06/2.9/3.1 ANSWER 2.10 (1.50)

a. Fall open

b. Remain functional (electric operator)

c. Fail closed

d. Fail closed (0.25 each)

e. Divert to VCT

f. Remain functional (N2 backup supply)

REFERENCE A0P-5B 3.8/000/078/K3.02/3.4/3.6

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

P 1

~

, 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 30

. ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

l ANSWER 2.11 (2.00) 4yc7 M

1. Rising CCW surge tank level 4GO l g ypg

a. y ce gg g

2. Increasing CCW system radioactivit

3. Increasing thermal barrier heat exchanger CCW outlet temperature

4. Increasing thermal barrier heat exchanger CCW outlet flow (any two at 0.5 each)

b. The CCW outlet valve on the affected thermal barrier heat exchanger will shut (0.5) on high thermal barrier heat exchanger CC outlet flow (0,5).

g g gMy

~

REFERENCE d's (Af) art. 2? N4 TRHB 10.2, FIGURE 10.2.31 3.10/000/008/K1.04/3.3/3.3 b' I')

3.10/010/008/K4.02/2.4/2.4 ANSkER 2.12 (1.50)

a. 1804 or /4 06

b. e A40/

c. 2003 et Jt, AOS

d. 1803 et/40 5 (0.25 each for a total of 1.50)

e. 2A06

f. 1A02 REFERENCE TRHD 12.5, FIGURE 12.5.1 LOGIC DWG., SHEET 8 3.7/000/061/K2.01/3.3/3.4

. 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 31 ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY. I.

ANSWER 2.13 (2.75)

a. 1. S/G low-low level on 1 steam generator

2. Safety Injection sequencer signal

3. Trip of both Main Feed Pumps (0.25 each for a total of 0.75)

b. 1. Normal - CSTs (0.50)

2. Emergency - Service Water System (0.50)

c. The operator must manually shift water sources-(from the control room)

(0.50) when CST level drops to 4.5 feet (0.50).

REFERENCE LP0169, P. 7,11 E0P-0, P.13 3.2/000/013/K4.04/4.3/4.5 3.5/000/061/K4.02/4.5/4.6 3.5/000/061/K1.07/3.6/3.8 ANSWER 2.14 (3.00)

a. - Maintain backpressure on orifices to prevent flashing.

- Maintain RCS pressure when solid.

- Prevent two-phase flow in the nonregenerative heat exchanger.

' (any two at 0.50 each)

b. SHUT (dN# it //r" 7.7 M '-' (0.50)

c. Prevent resin channeling in demineralizers. (0.50)

d. - LCV-427 (letdown stoo valve) must be open (0.50)

- At least one charging pump must be running. (0.50)

REFERENCE LP0079, P. 6,7 TRHB 10.6, P. 7,8 3.1/020/004/K4.03/3.0/3.4 3.1/020/004/K6.12/2.9/3.1 .

3.1/020/004/A2.02/2.7/2.7 ,

P. . .

3. INSTRUENTS AND CONTROLS PAGE 32 1

ANSWERS -- POINT BEACH 142 -87/02/17-KINGSLEY, I.

i ANSWER 3.01 (1.50)

a. 1. Both spray valves open. (0.50)

2. All pressurizer heaters turn off. (0.50)

' b. The reactor trips (on OT delta-T). (0.50)

REFERENCE Logic dwg. 883D195, SHEET 15,18,19 3.9/000/016/K3.08/3.5/3.7 3.9/000/016/A2.02/2.9/3.2 ANSWER 3.02 (1.00) b.

REFERENCE TRHB 13.7, P. 26 3.5/000/059/K4.19/3.2/3.4 ANSWER 3.03 (2.25)

a. 1. 10 percent load decrease (0.25) in < 120 seconds (0.25).

2. Condenser vacuum > 22" Hg (0.25).

3. At least onedischarge circulatingvalve wateropen pump(0.25).

breaker04,c1psed (0.25) and it __

' associated CWPnypt,,tp

b. Two groups (4) of SOS valves will trip open (0.50). The other two groups (4) will modulate open as necessary (0.50).

REFERENCE TRHB 13.9, FIGURE 13.9.6 TRHD 13.9 P. 8 3.5/020/041/K4.07/2.4/2.7 .

l

3. INSTRUMENTS AND CONTROLS PAGE 33 o ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 3.04 (1.50)

NO. (0.5)

Channel II must energize to actuate for an unsafe condition (to avoid inadvertent spray act on) (1.0) j REFERENCE

/w ^+1'd F r S & .

LP0064, P. 8 3.9/000/016/A2.02/2.9/3.2 ANSWER 3.05 (2.00)

Z t.s not -/O

a. Undercompensation results in a higher than actual reading, (0.50) and if > 10E-10 amps will prevent the SR detectors from automatically energizing (0.50).

b. The operator must manually energize the SR detectors with the Source Range Manual Reset pushbuttons (0.50) when the operable IR channel drops below the P-6 setpoint(0.50).

REFERENCE TRHB 13.1, P. 14,15 3.9/000/015/K6.02/2.6/2.9 3.9/000/015/A2.02/3.1/3.5 ANSWER 3.06 (1.50)

a. Steam pressure is used to compensate the steam flow signal (0.50) for density variations in the steam (as steam pressure varies) (0.50).

b. Indicated steam flow will be lower than actual. (0.50)

REFERENCE LP0315, P.12 TRHB 40.1, P. 33 3.4/010/035/K4.05/3.1/3.4 ,

3.4/010/035/A2.03/3.4 3.5/020/041/K4.13/2.2/2.4 COMPONENT-SENSORS / DETECTORS /3.0 e-

PAGE 34

$. 3. INSTRUMENTS AND CONTROLS o ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,I.

ANSWER 3.07 (3.00)

a. IN (0.25) Loop B Tcold increases to Thot causing loop B Tave to increase abova Tref. (0.50)

b. IN (0.25) Loop A Tave will become the auctioneered high Tave which is sensed to be higher than Tref. (0.50)

c. NO MOTION (0.25) Loop C Tave will b2 low and not be passed through the auctioneering circuitry. (0.50)

d. IN (0.25) N a -!: st9 cier"i+ = = == te dic., m , unreasinv '~

4 J., r eh m... -1 ~ a= r _ rn Sa; ,

b' REFERENCE TRHB 13.8, FIGURE 13.8.1 7 , ( p, f#)

3.2/010/001/KS.07/3.2/3.6 3.9/000/016/K4.03/2.8/2.9 3.1/000/001/K4.03/3.5/3.8 ANSWER 3.08 (1.75)

1. urce range high flux

2. P low voltage

3. P underfrequency

4. Pressurizer low pressure

5. Pressurizer high level

6. Loop low flow

7. Turbine trip (0.25 each)

REFERENCE TRHB 13.3, P. 6-8 3.9/000/012/K6.03/3.1/3.5 3.9/000/012/K6.04/3.3/3.6

/<S'O ANSWER 3.09 42.00)

a. Wit.L

b. WILL NOT '

.. 4 :.i. "^T (;ete. hjpess)

d. WILL (0.50 each)

REFERENCE THRB 13.11, FIGURE 13.11.17 -

THRB 13.3, P. 30,31

PAGE 35

['. 3.

INSTRUMENTS AND CONTROLS ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY,1.

0 3.5/000/045/K4.12/3.3/3.6 3.1/010/001/K4.07/2.9/3.1 ANSWER 3.10 (2.00)

a. TRUE (0.50 each)

b. TRUE

c. W F#L.sE

d. FALSE REFERENCE TRHB 10.16, FIGURE 10.16.3 TRHB 13.3, FIGURE 13.3.1 3.1/000/001/K2.02/3.6/3.7 3.9/000/012/K4.04/3.1/3.3 3.9/000/012/K6.10/3.3/3.5 ANSWER 3.11 (1.50)

1. Insufficient turbine load (< 15%) (0.50 for each)

2. One or more rod on bottom

3. NIS rod drop signal REFERENCE TRHB 10.5, P. 10.11 3.1/000/001/K4.03/3.5/3.8 3.1/000/001/K4.07/3.7/3.8 9

e

'. 3. INSTRutdiNTS AND CONTROLS PAGE 36 ANSWERS -- POINT BEACH 182 -87/02/17-KINGSLEY, I.

ANSWER 3.12 (1.25)

1. Demand position counters

2. Master cyclers

3. Slave cyclers

4. Bank overlap unit counter

5. All alarms associated with rod control circuits except Urgent Failure alarms

6. PA converter (any five at 0.25 each) (1.25)

REFERENCE TRHB 10.5, P. 10 3.1/010/001/X4.02/2.5/2.6 ANSWER 3.13 (2.00) 3 g , ggyg ; gu LL c46st 7-

a. 1. SIS at Unit 1 {,f.co-+d

2. SIS at Unit 2

3. UV on either 4160 volt safeguards bus at Unit 1

4. UV on either 4160 volt safeguards bus at Unit 2

5. Manual start (from local panel) (0.30 each for 1.50)

b. Two (three total) (0.50)

REFERENCE TRHB 12.8, P. 4-7 3.7/000/064/A3.01/4.1/4.0 ANSWER 3.14 Af J4IO ( NO M7?*

1. Divert to holdup tank (0.25) n '9 _ in yp g[M

2. Automatic makeup control (0.25) On at 17%. (0.25) Of f at 281.' (0.25)

3. Emergency makeup from RWST (0.25) at 2%. (0.25)

. 3. INSTRMNTS MD CONTROLS PAGE 37 ANSWERS -- P0 INT BEACH 142 -87/02/17-KINGSLEY, I.

REFERENCE TRHB 10.6, P. 29 LP0079, P.9 3.1/004/020/A4.04/3.3/2.9

MASTER COPY U. S. NLICLLAR REbulAlOkY COllN I Sb l ON SENIOR REAClOR OPLh410h LICENSE EXAMINATIOil F AC I L 11 Y : _ F;'p I,U T,,,LR,4C U,,1,b *g ,, _ .. ., _ ,, _ ,

REACIOR 1YPE: _PWR-Wb,gE___,,,,__,,,,,_,____,__

DATE ADMINISTERED: _ O Z / 0 2 f ) Z _ _ _ ,_ _ _ _ _ _ ,, _ _ _ _ _ ,,,

Ex6111iif-10 ,_ !!phL , s,. . . _ ,, , , _ _ _ _ _ _ , _

C At4D 1 L'A 6 L : , , , _ , , , , _ _ . , , _ , , , , , . . , , _ , , . , , ,

Iflil HI)C f 1001) _1,9,,Gi,3NI],1, pt I,[i t.

Une sup.ieaLo paper 4 or the ar e. wer 3. Write ancwert, on one i,ade onty, titspl o que stion ulwot on top of the antswer shoots. Pointo for eucli quetst t ori ar e indicated in parentheset, after the quantion. T h e p a s., t. i r io grade requtreu at l era s t /O% i n u.u;h ca t egory and a final orado of at Ieast 00%. Eneminataori paporn wi11 be ptcled u p t.,i n (6) h our t, o f i er the eu .a m i n a l. t on utarts.

% Uf CAih' GORY % OF CANDIDATE'S CAllbOkt VAL UE K'I.0L. _.. UGOFC. _. .V O L.U L _ . . .. . .. . _ ._ . . C 01 thu6 Y

,, p t ,_ { n >_ , '/ b . e u > b. lHEORY OF NUCLI AR FUWLU F Lolai OlERAI!ON, FLUIDS, AND 1HERMODYflANll'b Uh'.'9_. ?'3. 00 _ _ . . _ __

6. l'L AN I SYGIENG DESIGN, l:Utll hllL ,

AllD I N'S i kUME N I A l'l Of 4

..Mk> . L'!-!_

. 2Dr.QO 7. FHOCEl'URLG - NOhMAL, A l<Ntih M A L ,

EMElii)Ll4CY AND RADIOLUO!CnL CONIROL

.. ?10" _ e% !.") _ . . . . . . _ _ . . _ . _ . . .

U. ADMINiulkAIIVE FRUCLDilhiU, CUlll) i I Illiti, AND l. INI T AI IUlla 1 ! ".'z !N . _ . . . . _ , .

. . . _.. IotalD f i n.41 Ul* eidi?

01I wor i dor et e ten t l i t t, en anit ha t 1 on ny en y t i6.'n . I have- nottfier na voti r ior r et el vtal a i tl.

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Nf(C RULES AND GUIDELINES FOR LICENSE EXnMINATIONS '

During the adminiotratton of this examination the following rulos apply

i

1. Cheatiog on the antaminot on means an automat c denial of your applacation and could rouult in enero novare penaltion.

2. Rentroom trips are to be limited and only one candidato at a timo may loavo. You muut avoid all contacts with anyone outside the naamination ;

room t o evoid even t he appenrance or pocsibility of cheating. I a

i 3. Uso black ink or- dark poncti gnly to facilitato legible reproductions.

l 4. Print your n orno in the blanh providod on the cover about of the rat timi n a t i on .

!:. . Fill in the dato ori t hu cover cheet of the examinatnon (if tiec ot t+r y ) .

6. Use only the paper providod for annwors.

, 7. F'r i n t your nemo in the upper right-hand corner of the f ir st page- of t +,q tt i section of tho anhwor sa h uu t .

, G. Consecutively number oat.h antwer shoot, write "End of Category _ , , " no appr opr i a t.o , utert each category on a yOew pago, wri to only 90 90(' M du ,

of the papor, and writo "Last Paijo" on the last annwur ohnet.

9. Numlier each anr. uter a t. to cat ensory and number , for oxemplo, 1.4 6.0.

1 j IV. Skip at l u a s t .t. b t tr g lisius botwoon poch anowor.

11. Separato answer shoutu from pad ated placo finiuhud notwer as h oe; t t iero down on your dock or tablu.

l 12. Ut>v abbreviationt. on!y 1f they oro common!y usud i n f oc 11 i t y 1.1.t.1 Lr hir u.

)

13. The point valuu for each quottion is indicated in par onthetsht ofter thu quention and can bo ocod au a guido for tho depth of annwor required.

14. Shnw all calculations, methodn, or an9uinptionn unnd to obtain en ontwer l t o inathiamoti c al probleme whother indicatud in the quet> tion tr not. ,

15. Par t. t ol crudit may ho givun. therotore. ANUWER ALL PAhlb OF ' lib Otl0tJ110H AND DO Nul LE AVE ANY ANSWilt 14L ANh . {

16. If parte of tho ottaitiination arn not cloar at to intant. ent quoStions of !

j the egeqi.itmt only. I 17 You ennut nign the bl atome nt on the cover t.hes t that i n til e n t et. t, h o l. the

{

wart i tt your own and you havn not rucosseed or h o u n e,lt v e n c o u l v t. atic e t ai i

templ et i no t he onomitiot t ore. Ibin tuu o t ho dune' after the e n omi tiet ion hoo been coinpl et ed.

l I 1

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fB. When you completo your eti ami na t i on , you challs

a. Anunmbie your o):aminotion as fol1 owns (1) L:am quentiuns on top.

(2) Ex.am aidu - figuros, tables, etc.

(3) Answer pagus includinq figurus which are part of the answtar.

ti . Turn in your copy of the unamination and all p.igos used to annwor the ettamtnation queantione.

c. ~lurn in all scrap paper and the balanco of the paper th6t you did not uso for ariuworing the quo'stions.

d. Leave the u>tami nat ion arna , as dpfined by the c.caminor. i f aitor loaving, you aro found in thin area while thu e>< amination in v,till in progrous, your licence may no denied or revoked.

6 m

"h__IUE98LQE_UUCLg68_E9 WEB _EL69I_gEEB61190. _ELVIDL_004 PAGE 2 ISEBdggyB601GS QUESTION 5.01 (1.00)

Eaplain whach of the reactivity confficients of the power dofect act firut to affect reactivity on a sudden power change due to rod niovement and why.

0U1: S T 1 Oil !; . 02 (2.50)

a. Under what condition can Point T<each operete with an ov er moder a t ent core? (0.5)

b. Explain the reiponso of an overmoderated core to a steam demand increano. (annume no rod movemeint) (2.0)

OULGT 1OfJ 5.03 (1.00)

Whun the flow rate through a centrifugal puinp increasus, avni l abl o NfSH (increat.cs or decreases) and required flPSH (incronuos or decreaues). Choose correct responoon. (1.0) i UULS ilOli 5.04 (1.60)

The Peactor F'rotoc t i on Synt em wool d become unr el i abl e 4 or DNH protetttore from the 01 dolta T trip if voids wuro allowud to form in the Reactor Coolent Syntum becauces (Choose correct answer)

n. Tht* huat trantefor centficinnt of the cladding is roduced t.1 gn i f 1 c en t l y .

b. Fleettor power i 14 no 1onger proportianal to delta T au measured by the 1 cop Rl'D9.

c. The thermocouples rompond much t. lower in voidu as compared t o .i subcoolud fluid.

d. Tho voidt. 1n the downeomer routon wi11 taoue the til det.ector% to indicato in error.

UULis ! I UN ti. US ( l . e >U)

A notic.ir plont c1ms1nr t n }'on nt hent h h.it. retrnt!y hoon pl aqued in t h L1 pi tie.p d,un.pg o iluu to operatoru not. sns t .a b l i n h i ng a d i ttt.h ar q u flow p u t. h .

l~npi hi n how t hat t osi l e.uj to pump dimeye.

- - - - s t***** t%)l.UURY US t;Util I tillhD l>N fik i T l'Ohk

h__IUE9BY_9E_Uug6ge8 EOWE8_EL6N1_DEE80llgN2_E(UIDE2,_9ND PAGE 3 IUE80QQyUeDigS QUESTION 5.06 (2.00)'

During natural circulation cooldown, how do the fol1owing indications rer. pond assuming successful natural circulation is in progress?

a. RCS cold 1eg iemperature.

b. RCS hot l eg t etoperature.

c. RCS wtde range delta T.

d. Core enit thermoccupl09.

QUESTION S.07 (l.50)

The plant is in Hot Standby with pressurizer pressure at 985 psig. A prensuricer PORV beginu Icaking to the pressurizer relief tank which is at 5 psag.

a. What is the downstream tail pipe temperature? (0.5)

b. What in the enthalpy of the fluid entering the PRT7 (O.D)

c. The fluid entering the PRT 1s as -

(SELEC1 ONE) (0.5)

1. Superheated vapor

. 2. Wet vapor

3. Saturated vapor

4. Subcooled liquid DUESTION U.00 (1.00)

The 2200 degreou F manimum peak cladding temperature limit is used hec aufle I (Solect one)

a. It in 500 degreen F below the fuel cladding melting point.

b. Any clad temperature higher than this correlates to a fuel center line temperature at the f uel 's mel ting point.

c. A ::ircal l oy-wa t er reaction in accelerated at temperatures above 2300 drgrcou F.

d. Ihn t hur mel conduct i vi t y of zircalloy decreasec et temperatures abovo 2200 degrees F cauntnq an unacceptably sharp rise in the fuel

, ceriterl t he t on.perature.

OUEGTION 5.09 (1.00) .

4 T he e vs.c t or in productrn) luu;. reted thermal power et a cot e delta I of 56 duqreen and a m.4uu ilow rate of 100% whers a blaciout occura.

Natur al Lieculotton i t, et.t abi s t hed and c orte delta 'I tioes t o 2 t.

degroun. If decav hu al 19 2 7. . what in tho core mow flow rate (in %)>

(****e L A I LGuirs Ob LDril INut;D UN NE X 1 l'Abl ++****

e-

5. THEORY OF NUCLEAR POWER PLANT OPERATION2 _ FLUIDS3 _AND PAGE 4 1HEBOODyNOd1CS L

QUESTION 5.10 (2.00) because of Xenon oscillations delta I was out of band when you received chift turnover;

a. Explain how you would respond to the Xenon oscillation and return delca I back to target delta I. (1.5)

b. Show on the figure belew how your control manipulations would return delta I back to target delta I.

(0.5)

+ del t a I

_____ __________ ___________ ____ Target delta I

- delta I OUESTION 5.11 (2.00)

Will the Departure f rom Nucleate Boiling Ratio (DNBR) increase, decrease, or remain the same if the following plant parameters increase during power operation? Consider each parameter independently.

a. Reactor Coolant System (RCS) Pressure,

b. RCS Temperature.

c. RCS Flow.

d. Reactor Power.

QUESTION 5.12 (2.00)

Indicate and explain if you agree or disagree with the f ollowing st atements:

a. Within 10 minutes af t er a reactor trip, prompt

. neutron production within the fuel in non-existent. (1.0)

b. Thermal neutron flux levels within the fuel pellets are h8 gher than those in the coolant channel b e t. ween fuel rods. (1.0)

(***** CATEGORY 05 CONIIllULD UN NEXT PALE *****)

'I.5z__iUEgBy_QE_NQg(E88_EgWE8_E(8NI_QEE86IIQN2 _ELyJpS3_8ND PAGE: 5' IBE8dQQyNBdigS 4

QUESTION 5.13 (2.00)

a. Explain how the increase in reactor power from 10 percent to 100 percent. effects equilibrium samarium, if at all. (1.0)

b. Assume a reactor trip from 100 percent power with equilibrium xenon and samarium. _ Would the reactivity effect of samarium concentration changes be more negative or less ,.

negative ~than the reactivity effect of xenon concentration changes f rom immediately af ter the trip until:

1. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after the trip (0.5)

2. 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months after the trip (0.5) l OUESTION 5.14 (1.00) l During power operation, control rod insertion limits are in f orce.

l Explain the three possible consequences of not maintaining rod insertion limits. *-

DUESTION 5.15 (1.50)

Point Beach Unit 1 has just restarted following a refueling outage while Unit 2 is near EOL. .

a. Critical data has just been taken at 10 E-8 amps and the operators add i equal amounts of reactivity. Which unit will have the higher steady I state startup rate and WHY7 (0.75)

6. While at 50 percent power, a control rod worth -150 pcm drops'into the core of both units. Assuming no operator actions, no ruback occurs, and the reactor does NOT trip, WHICH UNIT will have the HIGHER steady l state Tave and WHY7 l (0.75) l OUESTION 5.16 (2.00)

Shutdown margin requirements change from the beginning of core life (DOL) to the end of core life (EOL). Doon the required shutdown margin increase

'or decrease from BOL to EOL7 (0.5) Why in the required shutdown mar gi n at E0l di f f erent than DOL 7 (1.5) .

r l

(+***+ END OF CA TEGORY 05 * * * * * )

I I

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Y }6__E66MI_SYSIENS_DE@l@y2_CQUIBQ62_8dp_INSIBUNENIBIJQN PAGE 6-4 OUESTION 6.01 -(1.50)

Foll owing a reactor- trip , the recorder trace of one of the intermediate-range detectors levels out at JOE-93 amps:

a. Is the detector li kely to be overcompensated or undercompensated?

(0.5)

b. What is the compensating voltage used for? (0.5)

c. What additional operator action ~ will be required in the above case per procedure EOP-0.1 to continue the shutdown if the detector leveled out at 10 E-10] amps? (0,5)

OUESTION 6.02 (2.00)

The plant is operating at 100%~ power when a 20% turbine runback occurs.

The operator receives various alarms and indications that the runback has-occurred,

a. What alarms and indications would indicate that the runback i s due to-an actual dropped rod? (List 3 alarms and/or indications) (0.4 each)

b. What-alarms and indications would indicate that the runback was caused by a momentary loss of an instrument bus? (List 2 alarms

. and/or indications) (0.4 each)

GUESTION 6.03 (1.00)

The procedure for putting RHR on the line has you red tagging shut the 851

. valves (stop valves ~on the line from containment sump recirculation to suction of the RHR pumps). The main purpose for this step is to (circle correct answer)

1. Prevent air binding pump by aligning suction to a dry pipe.

2. Prevent venting containment through the RHR. piping.

3. Prevent draining the RWS1 to containment due to difference in pressure of the RWST and containment.

4. Prevent flooding the containment with hot water when the RHH suction piping is pressurized from the RCS.

t I

l 1

(+*+n CATEGORY 06 CONTINUED UN NEX1 PAliE * * * * * )

6 1__pg6NI_Sy@lgdg_pg@l@N3_CQUlBQLg_6ND_]NSIBUdEUISIlgU PAGE 7 QUESTION 6.04 (2.00) ,

a. What two interlocks prevent inadvertent dropping of a fuel assembly from the manipulator crane? (1.0)

b. Why.aren't these interlocks foolproof? (0.5)

c. What indication (s) does the crane operator have of fuel elevation? (0.5)

QUESTION 6.05 (2.00)

State ten (10) automatic actions which take place on a saf ety injection actuation signal. Do not include redundant trains as seperate answers.

QUESTION '6.06 ( .50)

The THREE input signals to the Steam Generator Water Level Control are:

a. Tavg, compensated feed flow, uncompensated steam flow.

b. Feed flow, compensated steam fl ow, water l evel error.

c. Compensated feed flow, water level, compennated steam flow.

d. Uncompensated feed flow, compensated steam flow, water level.

QUESTION 6.07 ( .50)

A bypass reactor trip breaker may be racked in and closed around a single train main trip breaker to enable test or maintenance of the main trip breaker.

True or False?

QUESTION 6.08 (1.00)

If seal injection is lost to a Reactor Coolant Pump, is the contiriued operation of that pump permitted? Explain.

QUESTION 6.09 (1.50) -

When draining to half pipe wit.h the R}lR system in service, you are instructed by procedure to drain while maintaining 1500 gpm flow through Rf lR. Upon observing vortexing in the pump suction you ar e to reduce flow to less than 1000 gp.n. What is the reason for maintaining a high RHR flow rate while draining?

(***** CATEGORY 06 CONTINUED ON NEXT PAGE +++**)

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

i

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[6__5LONI_EYSIEMS_QESIGN3_CONIB963_6Hp_INgIBUdENI6IION t PAGE B

~

OUESTION 6.10. ( .75) 4 On a. decreasing pressure caused by water leakage in the Fire Protection System,. state what events occur at the following pressures:

at 120 psig

b. 95 psig

c. 80 psig .

4 DUESTION 6.11 (2.25)

a. List ALL permissives/ conditions required to arm the Steam Dump System (SDS) with the Mode Select Switch in AUTO. Include setpoints. (1.25)

b. Ascume the SDS has been armed as described in part a. due to prior

. testing of related instrumentation. The plant is operating at 50 percent power with all control systems in automatic.

~

How will the SDS respond to a Channel I'4 Tave instrument ~ failure to 569 degrees Fahrenheit? Assume no reactor trip.

QUESTION 6.12 (2.00)

What are the. ramifications of securing the steam generator feed pumps during a plant shutdown without placing their control' switches in pullout? -

QUESTION 6'13

. (1.50)

'Wtiat control actions automatically occur as a result'of a containment t _ spray initiation signal? -(1.5) 4 4

4 DUESfluN 6.14 (1.50) 7 tie plant is oper ating at 100 percent power and the Blue (III) instrument bus fails.

i

'a . Will.the plant immedi ately trip? (0.5)

b. What major system (s) will be affected and how? (1.0) 3

(+**** CATEGORY 06 CONTINUED ON NEXT PAGE *+***)

9 6 __ELOUI_SYSIEMg_ DESIGN 2_CQUIBg63_899_lygIBUMENIBIl99 PAGE 9 QUESTION 6.15 (2.00)

The.following readings or values are required to be monitored on a day to (day basis at the~ Point Beach Station.

.- Air Particle Monitor

. Radiogas Monitor 4

. Rel ative Humidity '

. Sump.A Drainage

. Computer or Manual Water Balance Leakage Calcul ation

. Service Water Temperature

a. Why are these r eadings/ values required tobe' plotted on a graph?

(0.4)

b. Why i s. moni toring service water temperature important? (1.6)

GUESTION 6.16 (2.00)

List the five conditions required for the-emergency on site source breaker to close if the primary off site source and secondary off site source fail

.to restore the bus.

8 OUESTION 6.17 (1.00)

The plant is operating at 80 percent power with all systems in automatic when the CHANNEL'IV (controlling) pressurizer pressure channel FAILS HIGH.

After completing all required operator actions, the plant is stabilized with an alternate pressurizer pressure channel selected for control and the appropriate bistables tripped. At this time, the CHANNEL II Tcold instrument FAILS LOW.

List the immediate action (s) which occur (s) as a result of this additional failure.

J

(***** END OF CATEGORY 06 ***++)

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

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7. PROCEDURES - NORMAL2_8pN9RMA62_EMERQENgY_ANQ PAGE 10 B891969GIC66_GQUIBg6 QUESTION 7.01 (2.00)

Procedure OP-5D entitled " Alternate Dilute" has a caution f;tatement that st'ates " equalize the boron concentration of the pressurizer.and reactor coolant within 100. ppm by increasing spray flow."

,a. Why is equalizing boron concentration important?_ (1.0)

6. What are two ~ met hods to ircrease spray fl ow. ( 1. 0)

OUESTION 7.02 (2.00)

What are the immediate action steps required by CSP-5.1 in the event of an ATWS with no normal manual reactor trip capability?

OUESTION 7.03 (1.75)

Why does the steam generator tube rupture procedure EDP-3 require that the feed flow be maintained to_the ruptured steam generator until level is greater than 8 percent narrow range?

i-OUESTION 7.04 (2.00)

A caution statement in Procedure "SGTR with loss of reactor coolant - subcooled recovery desired" ECA-3.1 states that voiding may occur in the RCS during RCS depressurization.

a. Why does this voiding occur? (1.0)

b. What would be the indication (s) that voiding occurred in the RCS? (1.0)

OUESTION 7.05 (2.00)

What are the critical safety function criteria for the red path summary for the EDP-O series foldout?

i

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

L.. ,

. Zi__68QQEDUBE@_ _NQBd@63_6ENQBM862_EMERGENgy_ANQ 'PAGE 11 B6D196001G86_QQNIBQL QUESTION 7.06 (1.00)

- Choose-the correct response.

When forming a steam bubbl e i n the pressuri zer~, steam bubble f ormation is indicated when:

a.. The PRT level i s constant and the- PRT pressure . i s increasing.

b. The PRT pressure is constant and the PRT level and temperature are increasing. _

c. Charging flow is greater than letdown flow with RCS pressure constant..

. rl . - Charging flow is less than letdown flow with RCS pressure constant.

QUESTION 7.07 (2.00)

Precaution 2.14 of..OP-1A, " cold shut'own'to d lower power operation,"

states, in part, that "the shutdown banks will be at the fully withdrawn position."

~ a. What rod height is considered the fully withdrawn position? (0. 5)-

. b. What are two conditions-in which this requirement may be waived.

- ( 1. 5)

.DLIESTION -7.09 (2.00)

Procedure EP-6 states that in_the event of a major radiation emergency, PBNP administrative dose limits may-be suspended by the Site Manager upon recommendation' by the Health Physics Director. What are the PBNP normal administrative dose limits for a:

a. Month (whole body)

b. Quarter . (whol e body)

If these administrative dose limits were suspended, what are the emergency dose limits when:

c. Emergency action is required. (not lifesaving)

j. d. You volunteered in a lifesaving situation.

I OUESTION 7.09 (2.00)

Units 1 and 2 are in Hot Standby in natural circulation c ool-down f o,1 ] owi ng a loss of offsite power. Prior to restoring offsite power, a telephone call is received reporting a bomb in the control room. A quick search reveals a " suspicious" package which prompts the Duty Shift Supervisor to order evacuation af the control room. List EIGHT operator IMMMEDIAIE actions which should be taken, if possible, prior to exiting the control room.

t

(***** CA'IEGORY 07 CONTINUED ON NEXT PAGE **+**)

l'

Zi__EBgGEDUBES_ _U980662_6BNQBd663_EUEBGEUgy_8NQ PAGE 12 669196991c66_C9NIBQ6 QUESTION 7.10 (2.00) .

You are in the process of heating up Unit 2 after refueling - The AO reports that.a valve on the "B" RTD Bypass loop is leaking. He states that the packing is at the maximum tightness and recommends bachseating the valve. Does this action meet your approval? Explain.

QUESTION 7.11 (1.75)

The power sup ply of f ice has the responsibility for determining the desired output of Point Beach Nuclear Plant. All power level changes should be coordinated through this office.

a. What are four means of communication between the Power Supply office and Point Beach Nuclear Plant?

b. Under what circumstance (s)-may power level changes be made without communication with the Power Supply office?

QUESTION 7.12 ( .50)

When the Residual Heat Removal System is in oper ati on , the component cooling water supply to the residual removal heat exchangers should be throttled to regulate temperatures in the RCS. (True/ False?)

OUESTIOt1 7.13 (2.00)

Steam binding of auxiliary feed pumps has been a problem for numerous

. plants across ttua country over the pact several years. What are five symptoms (local or remote) of steam binding of the auxiliary feed pumps?

OUESTION 7.14 (2.00)

Unit 1 it at 727. power after a reactor trip had occurred due to an instrument bus failure. Operators were verifying rod position after receiving a rod position deviation alarm on the plant process computer for control rods KO7 and C07. During the verification process, -the reactor power had risen to 80 percent. Bank demand was at 200 steps while rods KO7 and C07 were at 182 steps. What Technical Specification was violated and why would it be of concern?

(***** END OF CATEGORY 07 **+++)

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Bi__5Dd1NISIB611ME_BBQCEDUBEg2_CQNQ111QN@3_6ND_LidlI6IlgNS PAGE 13 i s

QUESTION 8.'01 (2.50)

a. Under what plant conditions should the Shift Supervisor arm the

" Potential Dilution in Progress". alarm per Procedure REI 19.0, enti tl ed " Prevention of-Uncontrolled Boron Dilution." (1.0) i '

b. Assuming you have-satisfied the conditions in part a. of this.

question, what are the number of charging pumps that must be tagged out for the following plant conditions: (use attachment 1)

. 3 Charging Pumps available (180 gpm)

. Baron concentration is 650 ppm

, . Shutdown mar gin is 1.4% delta K/K (1.5)

OUESTION 8.02 (- .75)

TheLTechnical Support Facility is required to be activated for what Point Beach emergency classification (s)?

i QUESTION 8.03 (2.50)

What are the f oll owing reactor trips specifically designed to protect ~against?

a. Power range high flux-high l evel trip. (0.5)

b. Low pressurizer pressure. (0.5)

c. Low RCS f l ow rate. (0.5)

d. High pressurizer level. (0.5)

e. Low-low steam generator water level. (0.S) l QUESTION 8.047 (1.50)

List five Te*h Spec conditions which must be met for ref ueling oper ati ons to proceed. l i

DUESTION B.O (2.00)

-One hour af1.h" a shi4t turnover, the Maintenance Supervasor comes to you anf asks if fa particular pi ece of equipment is out of service. What are icitr areas lin which you could look to determine if that piece of equipment he;l been tsken out of service?

i 4- (***** CATEGORY OD CONTINUED ON NEXT PAGE +++++)

4 I

4; _ -Wi__6DMINigIB8IlyE_BBQgEQUBES 2 _ggNgillgNS _8Ng_ 2 LIM 11811gNS PAGE ~.14 e.

-OUESTION 8.06 -( .50)

-The.______ ________ i s the pers6n responsi bl e f or the. review and. approval of out of service (005) . requests? Fill in the blank.

QUESTION 8.07 (2.00)

-In the basis for power distribution limits (Technical

-Specification 15.3.10.2) the following statement is made:

"For normal operation, it is not necessary to measure the hot channel factors. Instead it has been determined that,-provided certain conditions are observed, the hot channel = factor limits will be met." What are these 4 conditions?-

DUESTION 0.00 -(1.00)

Point Beach Technical Specification 15.3.7, AUXILIARY ELECTRICAL SYSTEMS,

, requires that 11,000 gallons of Diesel fuel be available.

What i s the basis f or. this requirement? '

OUESTION 8.09 (1.00)

What two criteria constitute adverse containment conditions?

OUESTION 8.10 (2.50)

By definition, containment integrity exists when five conditions are met. What are they?

i'

-QUESTION 8.11 (2.25)

PBNP 4.4, Main Control Room Conduct and Access, identifies those personne) i allowed in the control room during "off-normal" or transient events invol ving either unit. .

Name ihose personnel. Do not include reliei per sonnel .

i f

i I i,

(***** CATEGORY 08 CONTINUED ON NEX T PAGE *** * *)

f r

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

m.

vm .

7 8. -ADMINISTRATIVE PROCEDURES2_ CONDITIONS 2 AND LIMITATIONS PAGE 15 4

OUESTION 8.12 '(1.50)

During a refueling outage, while perf orming f uel movements, water level in

<the refueling cavity begins to drop. You receive a report from .

maintenance that the leakage cannot be stopped in the.short term and.the potential exists to uncover irradiated fuel in the refueling cavity. In whac: two areas may the irradiated fuel be placed until the leak is repaired?

DUESTION B.13 (1.00)

When is an RWP required for containment entry? t QUESTION 8.14 (1.00)

.Which two people have custody of the keys to-locked radiation areas?

! OUESTION 8.15 (3.00).

What are the three Tech Spec provisions which must be satisfied 2n order to obtain approval for. temporary changes and incorporate them into approved procedures?

9 2

1 4

s i

i

{-

(***** END OF CATEGORY 09 *****)

~

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

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

Sr.___IBEQBy_QE _,UUG(:EOB_EQWER_ PLANT _QPERATJ_QN t _,ELQlDS1 _AtJD PAGE 16 1HEBUggyUOUJ,CS ANSWERS -- POINT BEACH 162 -87/02/17-HARE, S.

MASTER COPY ANSWER 5.01 (1.00)

Doppler (FTC) (.50), fuel tenperature changes first (0.50)

REFERENCE kewaunee Reactor Theory I-D.21 Point Beach TRHB 32.5 pp. 42, 91 ANSWER 5.02 (2.50)

a. Reactor power <70% (0.5)

b. The decreace in the temperature of the coolant entering the reactor core following a steam demand increase will result in a d e t.r er e d e of the average moderator temperature. The moderator to fuel ratio will increase as the moderator temperature decreases, adding negative reactivity to the core. (0.5) The power of the reactor will initially decrease causing the fuel temperature to decrease. (0.5) The positive reactivity resulting from .he doppler effect will cause reactor power to increase. (0.5) The reactor power will increase to cause the heat production rate to equal the heat removal rate, and a new steady state equilibrium condition prevails. (0.5)

REFERENCE Point Beach TRHB 32.5 pp 85,86 ANSWER 5.03 (1.00)

(0.5 each) decrease, increase i

! REFERENCE l . Hewaunee Thermo/ Hydraulic, pnge 10-58 t Point Deach TRHB 40.2 sec. 1.1 ANSWER 5.04 (l.00) -

b.

REFERENCE j NNS lhermo, para. 2.6.

l Westi ricahouse T hermal-Hycir aul 3 c Principles arid Applitationc to PWR 11 1

5:__IUEgBy_QE_UUCLEGB_EgyEB_EL691_9EEBBI1992_E691gS3 _809 PAGE 17 IUEBUggyNOUICS ANSWERS -- POINT BEACH 162 -87/02/17-HARE, S.

Chapter 13, pp 53-56 Point Beach TkHB 43.1 p 18 ANSWER 5.05 (1.00)

Heat generated by the pump will cause cavitation due to el evated 1 sat /Psat in the pump.

REFERENCE Prairie Island LER Point Beach Exam Bank Duection 40-02-02 ANSWER 5.06 (2.00)

(0.5 each)

a. Cold leg temperature - near saturation temperature for steam generator pressure. Also accept stable or slowly decreasing.

b. Hot leg temperature - stable or sl owl y decreasi ng.

c. Initially at full power delta T, (or less), and slowly decreases,

d. Core exit thermocouples - stable or sl owl y decreasi ng. About the same as Thot.

REFERENCE Point Beach E::am Bank Question 40-02-05 ANSWER 5.07 (1.50)

(0.5 each)

a. 300 degrees F (290-310 F acceptable)

b. 1192 BTU /LBM (1190-1195 BTU /LBM acceptable)

c. 1 REFERENCE TRHD 39.1, p. 124 Steam Tables ANSWER 5.08 (1.00) -

c.

REFERENCE MNS Ibermo-Core Periormance, p.2.

Westinghouse Thermel-Hydraulic Principles and Applications to PWR II

Lz__IHEQ8f_QE_UQCLE68_EQWE8_E66NI_QEEB@llOUg_E6Q1Q@1_@NQ PAGE 18

. : T_HER_M_O_D_Y

_- ____ NA_M_I CS_

ANSWERS'-- POINT BEACH 1&2

-87/02/17-HARE, S.

Chapter 13, p. . 15 -

Pcsi n t Beach TRHD 39.3 p 66-ANSWER 5.09 (1.50)

To determine fl ow in NC:

. O = m cp deltaT => 100 = 100

cp

56 => cp a 100 100

56 cp = .0179 THEREFORE 2% = b * .0179.* 28 => b= 2%

l = 4.0%

.(0.5)

.0179

28 j (1.0 for right method)

REFERENCE General Physics, HT & FF, Section 3.2 ROWE Reactor Operator _ Training Manual, Sec. 2, pp 54-63 Wentinghouse Thermal-Hydraulic Principles and Applications to PWR II 3 Chapter 14,-pp 15-29 Point Beach TRHB 40.2 p 18

Point Beach TRHB 39.3 p 82 ANSWER 5.10 (2.00)

a. To stop th'e Xenon oscillation, the control rods may be inserted (0.5) when de.ita I is on an upswing causing a dampening of the l oscillation (0.5) rod insertion can be compensated for by boron I

dilution (0.5).

b. i

, + delta I 1 ..________________ -.

, g7 _ _

Begin rod 2nuertaon i

i

{ - delta I i

l REFERENCE .

l Point Beach TRHB 32.5 p.94 i

i i

t

~'52 __IUEQBf_QE_Nyg(g68_EQWEB_EL8UI_gEEB911QN1 _E6ylDg3_8ND PAGE ' 19f lHEBMQDyNOMig@.

ANSWERS -- POINT BEACH 1842 -87/02/17-HARE, S.

ANSWER 5.11 ~ (2.00)

a. Increase.

b. Decrease.

c. Increase.

d. Decrease.

.[0.5 ea.]

REFERENCE THERMAL' HYDRAULIC PRINCIPLES AND APPLICATION TO THE PWR CHAPTER 13-41

-Point Beach TRHB 39.3 p 67 Tech Specs 2.1-2 ANSWER 5.12 (2.00)

a. - Disagree: (0.5) prompt neutrons production will continue as long as fission continues. Fissioning does not stop after a trip.(0.5)

b. Disagree: (0.5) Thermal flux levels within the f uel are lower because of self shielding and because neutrons are thermalized in the moderator, not the-fuel (0.5).

REFERENCE Kewaunee Reactor Theory I-6.13.

Point Beach TRHB 32.3, P. 46

' ANSWER 5.13 (2.00)

'a. There is no effect on equilibrium samarium due to power changing (0.5) because both the production and removal terms for equilibrium are not flux level dependent. (0.5) b._ l. less negative (0.5)

2. more negative (O.S)

REFERENCE Kewaunee Reactor Theory, I-5.77 Point Beach TRHB 32.5 sec. 3.1 -

r.. , ,-. --

I

" 5 __IVEQBy_QE_NQCLEQ8_EQWE6_E6@NI_QEEB@IlQN 5 x_E(Q1QQi_6NQ PAGE .20

' ~

IHEBdQQYN@dlC@

- ANSWERS ' -- POINT BEACH 'I t<2 -87/02/17-HARE, S.

' ANSWER 5.14 (1.00)

(.33 each)

1. Potentially indequate trip reactivi ty 2.- No assurance that power distribution limits are met

3. Increase the consequences of a rod ejection accident REFERENCE' T/S 15.~3.10-8 ANSWER 5.15 (1.50)

a. Unit 2 (0.25) due to a lower value of Beff (0.5).

.b. Unit 2~(0.25) due to a more negative MTC (0.5).

REFERENCEL TRHB 32.4, p.12

.TRHB 32.5, p. 38

' ANSWER' 5.16 (2.00)

Increase The shutdown margin at EOL is based on the value used in analysis of the hypothetical s' team break. accident, (0.75) which is more severe at EOL because the moderator temperpture coefficient is more negative. (0.75)

REFERENCE

-Point Beach Tech. Specs. p 15.3.10-8

1

bz__ELONI_gySIEMg_ DESIGN 3 CONTROL 3_AND INSTRUMENTATION PAGE 21 l

. I ANSWERS -- POINT BEACH 1&2 -87/02/17-HARE, S. l l

1 l

l l

ANSWER 6.01 (1.50)

a. Undercompensated. (0.5)

b. It counteracts the signal produced by the gamma radiation so that only the neutron level is indicated. (0.5)

c. Verify that source range detectors are energized. (0.25) Transfer-one pen of the nuclear recorder to the source range and one pen to the intermediate scale. (0.25)

REFERENCE TRHD 13.1, Section 1.3, EOP O.1, Step 17 ANSWER 6.02 (2.00)

(0.4 each - Up to 2.0)

a. -

Annunciate " Rod control rod bottom rod stop" Illuminate rod bottom light associated with dropped rod Indicator for dropped rod indicates rod position on bottom EHC indication of turbine runback (Both load limit and ref erence reduction)

NIS dropped rod-rod stop signal

b. -

NIS dropped rod-rod stop signal Numerous signal channel alerts associated with the lost power supply Bistable status lights associated with the lost channel Possible control difficulties dependent on the power supply lost and duration REFERENCE Point Beach Exam Bank Ouestion 53-01-26 ANSWER 6.03 (1.00) 4 REFERENCE OP-7A 2.8

6___ELONI_@Y@lgd@_QESl@Ui_CQUISQ(i_6NQ_IN@l8gdgN1611QU PAGE 22 ANSWERS -- POINT BEACH 1&2 -87/02/17-HARE, S.

ANSWER 6'. 0 4 (2.00)

a. 1.- The gripper air solenoid will not function with weight suspended from the hoist. f (0. 5)

2. A mechanical wei ght-actuated l ock in the gripper. (0.5) 6.- A fuel assembly can bind and ease the load on-the hoist even though the f uel is not properly seated. (0.5)

c. Digital and tape. . (0.5)

. REFERENCE FSAR 9.5 Point Death 01-4 ANSWER 6.05 (2.00)

'Feedwater Isolation Containment Isolation Containment Vent Isolation Reactor Trip

'AFW Starts DG's Starts SI. Pumps Start and Headers I. . .e g, g pg RHR Pumps Start SW Pumps Start Containment Cooling Fans Start Radwaste Steam Supplies Isolation Accumulators Isol ati on Ope ++ I4/ves 8ecerva ** OfeN C'f dE l Reactor Vessel' SI Isolation Open SI Logs Isolation Open BAT isolations open or RWST Isolation Open SI Pump Header Isolation Open Possible SL Isolation (Any 10 at 0.2 each)

REFERENCE

- SI Logics ANSWER 6.06 ( .bO) b.

REFERENCE Point Deach Exam Ita n k Duostion 52-05-36

1

- 61__8609I_SISIEUS_DE@lGN3 _pjNIBg61_8ND_INSIBUDENI@llgN 'PAGE :23

' ANSWERS -4 POINT.DEACH 1&2 =-87/02/17-HARE, S.

ANSWER 6.07 ( .50)

True.

' REFERENCE Point Beach Exam Bank Ouestion 53-02-09 ANSWER 6.08 (1.00)

Yes. (0.5) Pump operation may continue as long as the thermal barrier heat exchanger cooling water inlet temperature remains below 105 degrees F. (0.5)

REFERENCE 01-1 ANSWER 6.09 (1.50)

If draining down while maintaining a low flow rate, the volutae of water 2n the system would be less when vortexing occurs (0.5) and it is possible to airbind the RHR system (0.5) and not have enough mass left to regain'a suction. (0.5)

REFERENCE Point Beach OF;-4D, p. 8 ANSWER 6.10 ( .75)

a. Jockey pump starts

b. Motor driven fire pump starts

c. Diesel driven fire pump starts (0.25 pts. each)

REFERENCE

'IRHB 11.14, Section 4.3

'6:__tLONI_Sy@lEdS_DEQIGN2_CQNIBQL1_69D_lySIBydENI@IlgN PAGE 24

-ANSWERS -- POINT BEACH 1&2 -87/02/17-HARE, S.

. ANSWER 6.11 (2.25)

a. 1. 10 percent load decrease (0.25) in< 120 seconds (0.25)

2. Condenser vacuum > 22" Hg (0.25)

3. At least one circulating water pump breaker closed (0.25) and its associated discharge valve open #9 (LtDu a tw

g (0.25)

(p) & g w. - j

j^ f'*

b. Two groups (4) of SDS va ves will trip open (0.5). The other two 9 groups (4) will modulate open as neccessary (0.5)

REFERENCE TRHB 13.9 P8 ANSWER 6.12 (2.00)

The AUX FW pumps (P3B ALB) will start (.75) and the blowdown valves in boch units will shut (.75) when the level in either steam _ generator drops below the low low level setpoint. (0.5)

REFERENCE

OP-13A, page 10, Logic Diagrams ANSWER 6.13 (1.50)

1. Both containment spray pumps start. (0,5)

2. Motor operated spray ring header isolation valves (MOV860 A, B, C, and D) open. (0.5)

3. Air operated additive eductor suction valves (HCV836 A & B) to the NaOH tank open. (0.5)

REFERENCE TRHB 10.12, Section 1.3 ANSWER- 6.14 (1.50)

a. No (0.5)

b. Feedwater "A" loop valve begins shutting -

REFERENCE 1RHB 13.7, pg. 31

6,__h(6NI_@iSIEU@_DE@lGN _GONIBQL3_QNQ_lNSIBQUENI611gN 2 PAGE 25 ANSWERS - POINT BEACH 1&2 -87/02/17-HARE, S.

ANSWER 6.15 (2.00)-

a. 'The values are plotted on a graph to look for trends'that would indicate RCS leakage (0.4) b.. The service water is important to' evaluate trends in Sump A drainage (0.4) and Relative Humidity (0.4) because a decreasing service water temperature can cause a decreasing humidity (0.4) and increasing-Sump.A drainage (0.4).

REFERENCE PBND 4.11,.Section 2.2.2 and 3.6 ANSWER 6.16 (2.00) 1.

Sr( A L/R switch in- Local" and loca C.S. not in " Pullout" or L/R switch in Remote and Remote C.S. not in " Pullout"

2. FSX Diesel Start Relay Energized u or LOCA C.S. Close

3. 271 x 2 or 272 x 2 Bus Undervoltage or dead bus v'

4. 52S Bus and: Supply Breaker tripped

5. 86AO Bus not locked open Trip Signal not in y

$. "$E REFERENCE ya.ca.iAn/A TRHB Figure 12.5.5E ANSWER 6.17 (1.00)

--The reactor trips (on OT delta T).

REFERENCE Logic dwg.883D195 E

2 F'ROggDgRgg_- _NgRtj%2_ABNgRMA61_gljg8GENCY_eNg PAGE 26 B09196991CeL_CgNIB06 ANSWERS -- POINT BEACH 162 -87/02/17-HARE, S.

ANSWER 7.01 (2.00)

a. Prevent power osci11ations/ changes when an outsurge of the pressurizer causes the higher boron concentrated ater t o, circulate through the RCS. (1.0) #1

b. Energine additional heaters.

Adjusting spray valve posi tion (0.5)

(0.5) - "

.4 h

Mfeh ik.;ene. Rcs.(f.o)

REFERENCE OP-5B ANSWER 7.02 (2.00)

1. Reactor will not trip - insert control rods by deenergizing rod drive MG sets or by manual insertion.

2. Verify turbine trip.

3. Verify AFW Pumps Running.

. 4. Initiate Rapid Boration of RCS.

(0.5 each)

REFERENCE CSP-5.1 ANSWER 7.03 (1.75)

The steam generator tubes in the ruptured steam generator will approach _the temperature of the reactor coolant when the RCS is cooled and the RCPs continue to run. (0.5) So when the steam space in the ruptured steam generator expands to contact these colder tubes, condensation will occur decreasing steam generator pressure (0.5), increasing the primary to secondary leakage-or-l evel will decrease the radioactive release rate. (0.75)

REFERENCE Westinghouse Owner's Group procedures, E-3, page 6, page 26

=5

, , , . .-.._y. . _ . . , p ,,_#w 3 m _ ._y.. ,_ - .- -.

r_

Zs__ PROCEDURES - NORMAL 3_8BNQRMAL1_EMERGEtjgy_ANQ PAGE 27-BBD196991C66_QQNIBQL ANSWERS -- POINT BEACH 1&2 -97/02/17-HARE, S.

ANSWER 7.04 (2.00)

a. The high temperature coolant in the upper head which has a slight amount of cooling flow will flash to steam creating voids in the upper head.

Check at facility for plant specific data. (1.0)

b. Rapidly increasing pressurizer level. (1.0)

REFERENCE ECA 3.1, page.9.

P ANSWER 7.05 (2.00)

(0.4 each)

' 1. Subtriticality-nuclear power greater than 5 percent

2. Core cooling-incore T/C greater than 1200 degrees F or core exit thermocouples > 700 degrees F and reactor vessel level narrow range < 29 ft, with no RCPs running

3. Heat sink-WR in steam generators l ess than 200 inches, and total feedwater flow less than 200 gpm

4. Integrity-cold leg teroperature decreases greater than 100 degrees F in last 60 minutes and RCS cold leg temperature less than 283 degrees F

5. Containment-pressure greater than 60 psig REFERENCE Foldout for EOP-O series ANSWER 7.06 (1.00) d.

REFERENCE l

Poi nt Beach Exam Dank Question 31-03-149

?___EB99ED96EE_:_N9BM8(3_$BNQBM863_gMEBGENgy_8ND PAGE. 28 B69196991986_GQN1Bg6 ANSWERS -- POINT BEACH 12<2 -87/02/17-HARE, S.

ANSWER 7.07 (2.00) 5'

a. 22) steps (0.5)

b. One bank of rods with a worth of at least 1% delta k/k withdrawn prior to any reactivity changes.

f 9%4k?

RCb has been borated to the Hot Xenon-free boron concentration and is being maintained at hot shutdown.

WQg . a a RCS has been borated to the cold shutdown boron coricentration.

(Any 2 O O.75 each)

REFERENCE PBNP OP-1A, LER, T.S. 15.3.10-A

. ANSilER 7.08 (2.00)

a. 450 mrem

b. 1050 mrem

c. 25 rem

d. 75 rem (O.S each)

REFERENCE EP-6.0, pg. 15, HP 1.4, HP 1.3 ANSWER 7.09 (2.00)

1. Verify both reactors tripped.

2. Place atmospheric steam dump valves in Manual and shut.

3. Shut MSIVs

4. Open P29 steam supply valve and feed B steam generator at

.80-100 gpm.

5. Place main feed v 4 0, 481 i n Manual and shut.

6. Initiate Manual . .. ' = - ' - r.. "

7. Notify CAS that AOP-10A has been initiated.

8. Shift Telex to main office.

9. Remove portable radios. -

(Any eight at 0.25 each for a total of 2.0) i REFERENCE l AOP-!OA, PWG/11/4.3/4.4 I

r r- y - . . . , -

-..n,.4 _ . . - , . , . , , - . , _ . . ..,.# . y ,,y._,,y.m_,,m,_y- _y_- . _ . - , , .,_,_y--,, .,ny , . , , . _..,__..,_-,7_,,.--..,7 .

'Zr__B8QQgQQ8ES'- NORMAL _ARNQBUALx_EMER@ENQy_ANQ t PAGE 29 EODJ.96901G06_QQNIBQL

' ANSWERS -- POlllT DEACH 1&2 -87/02/17-HARE, S.

ANSWER 7.10 (2.00)

'No. Standing Order 4.12.14 states that these valves should not be backseated during heatup due to separation of disc and stems caused by uneven expansi on.

REFERENCE 4.12.'14 ANSWER 7.11 (1.75)

a. Direct line (red phone) (0.25)

General telephone line (0.25)

Plant trouble alarm system (0.25)

(Short wave) radi o (0.25) -

b. During emergencies when time does not allow communication. (0.75)

REFERENCE PDNP 4.15 ANSWER 7.12 ( .50)

False.

REFERENCE OP-7A ANSWER 7.13 (2.00)

1. Pump glands steaming or discharging hot water.

2. Pump casing or piping hot to the touch.

3. Pump suction pressure high or suction relief lifting.

4. Water hammer felt or heard in the discharge or mini-recirc piping.

5. Dearing temperature alarms or ulevated bearing temperatures au read on TR 2000. .

6. The pump not deliverino rated fIow or discherge pressure during operation.

(Any 5 @ O.4 wach)

6 4

Z,,__ESQQgQURES - NORMAL 3 A@NQBMAL3 _EMgBQgNQy_@NQ PAGE 30 88DlR6991G86_QQNIBQL ANSWERS -- POINT BEACH 162 -87/02/17-HARE, S.

REFERENCE ADP-2C ANSWER 7.14 (2.00) 2 Technical Specification that prohibits increase in power to a level beyond 75'/. (0.5) with an RCCA misaligned greater than 7.5 inches (0.5) when the bank demand position is between 30 and 215 steps. (0.5)

Exceeding 75% power with such a rod misalignment could lead to 1

exceeding core thermal limits under both steady state and anticipated transient conditions. (0.5) r N

REFERENCE LER 86-002, Point Beach Tech Specs 4

5 1

s.

D I i

f L

e O

i b

1 i

j t i

a l

i I

?

i

~

l

' az- 6DdlNISIB0llyE_BBQQEQQBEQ2_QQNQlllQN@2_QNQ_61bil811QNQ PAGE 31

, ' ANSWERS -- POINT BEACH.1&2 -87/02/17-HARE, S.

ANSWER G .' 01 (2.50)

a. Plant in Cold Shutdown. (0.5)

No RCP's running. (0.5)

~b. Two pumps must be tagged out. (1.5)

REFERENCE REI 19.0 ANSWER B.02 ( .75)

Alert, Site Emergency, General Emergency (.25 each)

REFERENCE Point Beach Emergency Plan ANSWER 8.03 (2.50)

a. Prevents core power f rom reaching a value(0.2d at which fuel pellet centerline melting would occur. (0.25) (It acts during power excursions that are too rapid to be protecteds by temperature and pressure protective circuitry.) ;v.ZL)

b. Loss of coolant accident or DND and to limit range required for OT delta "T". (0.5)

c. Cladding f ailure from high temperature due to DND. (0.5)

d. RCS overpr' essure backup to code safety valves or It also protects tpe safeties against water damage. (0.5) ,

n. Loss of heat sink (during a loss of main feudwater accident due to auxiliary feedwater pump starting delays) (0.5)

REFERENCE Technical Specification 15.2-3

es__0DdlNISIB@IlyE_EBQCEQUBES2_CQNQlIlQN@2_@NQ_LidlI@IlgN@ PAGE ~32

, ANSWERS'- -POINT BEACH '1'tc2 -87/02/17-HARE,.S.

ANSWER 8.04 (1.50)-

'(Any 5 0 3 each) -

1. The equipment batch shall be closed and the personnel locks shall

+

be capable of being closed.

2. Radiation levels in the f uel handling ~ area,-the containment and spent fuel storage pool shall be monitored continuously.

3. Two neutron detectors operating, one audible in containment, two visual in control r o or.. .

4. ' One RHR loop in operation can be r emoved f rom service 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per B hours if it interferes with refueling.

5. 1800 ppm boron.in RCS.

6. Direct communications between control room and containment.

7. . Containment vent and purge system, including radiation monitors which initiate i sol ation shall . be operable.

REFERENCE Point Beach Exam Bank Ouestion 57-02-08, PBNP RP-1C ANSWER 8.05 (2.00) -

l (0.5 each)

Station Log 2 Status Board

, Turnover Noten j Danger Tag Log ,

REFERENCE LPO644, page 4 l

ANSWER 8.06 ( .50)

The Duty Shift Superintendent or his designated alternate - Duty Operating Supervisor.

- Accept Either -

REFERENCE Point Beach Administrative Procedure 4.13, paragraph D.2 1

i

8:__09d1NI@l89IlyE_EBgCEQQBES4_CgND111gNS3 _@ND_LJb11611gN@ . FAGE 33

, ANSWERS -- POINT BEACH 1&2' -87/02/17-HARE, S.

ANSWER 8.07 (2.00)

1. Control rods in a single bank move together with no individual rod insertion differing by more than 15 inches from the bank demand position. (0.5)

2. 1 Control rod banks are sequenced with a overlap banks. (0.5)

3. The full length control bank insertion limits are not violated. (0.5)

4. Axial power distribution limits which are given in terms of flux difference and control bank insertion limits, are observed. (0.5)

REFERENCE Basis for Technical Speci f i cati on 15.3.10.2, Power Distribution Limits pages 15.3.10-10 ANSWER B.08 (1.00) lt assures the operation of one diesel carrying design load of all the engineered safeguards equipment f,or at ,least 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months s.

REFERENCE TS 15.3.7 Basis ANSWER 8.09 (1.00)

1. Containment pressure greater than 10 psig

2. Containment radiation greater than 100000 R/hr REFERENCE EOP-O 1

f 6

n 6

[B__0RdlN1@lB811yE_ESQCEgyBE@z_QQNpillQN@2_6Np_bidllOllgN@

z PAGE 34

_, ANSWERS -- POINT BEACH i t<2 -87/02/17-HARE, S.

ANSWER. 8.10 (2.50)

.1. All nnn-automatic containment isolation valves and blind flances are closed as required. (0.5)

2. The equipment, hatch is properly sealed. (0.5)

3. At least one door in each personnel air lock is properly

, closed. (0.5)

4. All automatic / containment isolation valves are operable, secured in the' closed position or: isolated by closed manual valves or flanges as permitted by Cimitidd Conditions f or Operation. '

to.5)

5. The containment leakage rate satisfies Technical 7 Specificationf15.4.4 requir,ements. (0.5)

REFERENCE-

/'

./ -

~

~ ~

Point Beach T.S definitions,'page 1-4, also RGE-21, pag 5-11.

ANSWER- 8.11 (2.25) ,

1. DSS '

.(

. 2. DOS ~ '

,.l

s 7

3. Unit'CO's /_ '# L- '

' s

-^

-4. 3 AO's . , .,

5. 2 DCS's ,

6. I DTA' -

C '. . b.[

7. 1-if]Nupe% rvisor #'

O. 1 Recctor Engineer ,,.

-[ ,

9. 1 NMC' Ins'pector e, 7 (0.25 each) ff REFERENCE i PBNP 4.4

~

. ANS^WER B.12 (1.50) -

Reactor- (.75)

Spent fuel rocks (.75) ,

REhERENCE . -

RP-1C ~

/ ,c -

/ i'

' s a, .* +

r ,

d y

/ .

e o e

N

/

fs

. ez__6QUINISIBOIlyE_BBQCEQQBEQ2_CQUQlIlQUS S _6NQ_LlMII6IIQNS PAGE 35

. ANSWERS -- POINT BEACH 12<2 -87/02/17-HARE, S.

ANSWER 8.13 (1.00)

When RCS temperature exceeds 200 F. g7 4 kf/*

REFERENCE # ~

2' T*

.HP Manual 2.5 2II JT ANSWER 8.14 ( 00) a.y.2,(,c6, .y M) -

i P1 ant Health Physicist h) Duty A0 shif t SupervSor ~&and-3 PAB REFERENCE

4) H P I s) H PM HP Manual 2.6 4DTe m 2,/ . 2,1 ANSWER 8.15 (3.00) .

t

1. The intent of the original procedure is not changed. (1.0)

2. The change is approved by the cognizant group head (Duty, Shift Superintendent in Operations) (0.5) and one of the Duty and Call Superintendents. (0.5)

3. The change is reviewed by the Managers Supervisory Staff (0.5) and approved by the Manager (0.25) within two weeks (0.25).

REFERENCE Technical Spec,ification 15.6.8 4

e w ,_ , . _ . . . - _ _

AH A&wd r

I MINIMLM REQUIRED SHITIDOWN MARGIN '

VERSUS INITIAL RCS BOION CONCENTRATION 2000 ' 'i.' ' s. ' ':' ' s '\':- ' - -

s ':' s ': - ' ,'.. 'e.'.- s i

i

\

1 :. c

\i -

I. - ' {'

3 Pumps ' 2 Pumps

- crinr : -- kg~ 1 Pump i

-l !-

~ (180 gpm) *

'.\ , f (120 gpm) Li:E= 5_s ~;.". [_ (60 gpn) y. .a _

~

1800 t- -- r i ik , r- -

.[

n_-. ; [ ,

I...

t ! l .

t

\ r . i :. +:'_l'- iL T!; : _ \ . _ r. - :7.[L : 4. :

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~

t

j.

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

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o 800 .

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p . = :N : := = .1_

i=- + ) i....

sc ,

'\ . _ _ . . _ . __ .

no e, . . . . . . -_.

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m ._. - _.._- __.. . . - . . . . . - . -

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i 200 .

l . ; . ;;.. . . ._ : -

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4.5 4.0 3.5 ' ' ' ' .'3 0 ' 2'. 5 2.0 1.5 1.0 0.5 Minimun Required Shutdown Margin (t Ak/k)

(for 15 r.inutes of charging) k I

e I\

f~

jt EQUATION SEEET

-f = ma v = s/t w = ag a = v,t + hat 2 - Cycle efficiency = Ret Work (cut)

Energy (in)

E = aC a = (vg .v,)/t KE = 3pnr vg A = AN A = A,e' *

= v, + at .

PE = agh a = 9/t , A = In 2/tg = 0.693/tg W = vaP (t )(ts)

AE = 931A:::

(eg 4 e,)

I)=[ncAT

, P I=Ieo -h Q = UAAT I=ye-UX Pwr = U a f I=I o go -x / m P=P 10 SUR(t) TVL = 1.3/p P=P o

et /T EVL = 0.693/p ,

SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg)'

fA*gro)

SUR = 26 g,, CR x = S/(1 - Kaggx)

CR 3 (1 - Keff)g = cRg 1 ~xeff)2 T = D*/o ) + [(i 'p)/A,ffo]

T = 1*/ (p'- E M = 1/(1 - K,gg) = CR g/CRO.

~ ~# #

eff M = (1 - K,gg)O (l ~ eff)1 8"I eff" )! eff " #eff Kaff SDM = (1 - E,gg)/Kaff ,

~

p= [1*/TK,'gg .] + [B/(1 + A,gfT )] , 1* = 1 x 10 a=ds

-I P = I(V/(3 x 1010) A,gg = 0.1 seconds I = No 1d 33 =Id2y WATER PARAMETERS Idg =1022 1 gal. - 8.345 lba R/hr = (0.5 CE)/d (meters)

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

I ft3 - 7.48 gal. MISCELLANEOUS CENVERSIONS ,

lE Density = 62.4 lbafft 1 Curie = 3.7 x 10 dps 3

Density = 1 gn/cm 1 kg = 2.21 1ha

,- Heat of varorization = 970 Itu/lba I hp = 2.54 x 103bit!/hr l , Heat of fusica = 144 Btu /lba 1 b = 3.41 x 10 Stu/hr l k 1 Atm = 14,7 psi - 29.9 in. I's. 1 Stu = 778 f t-lbf I f t. H O = 0,433~, Ibf/in 2 I inch = 2.54 cm l F = 9/5 C + 32 C = 5/9 ( F - 32)

Eseh.4py.Cb4 Satropy.thsJtt a F vosome.Qhth .

. - - - - F

-. - . 6, t emne ** *= *s er ai, g

% 'e 'is 2.as72 3

-Om , 3075.5 3075.5 0.0000 2lan 3305 3305 sa esass E01402 3076A DA061 2.1)o6 21767 5 2948 380 3073A e

est03 E01602 2948 8 03 3071A 1079 0 0.01M 2.1432 2.15p 35 de E32163 001402 2446 2446 33A4 1968.1 1981.2 002M 2.1164 2.1426 e 6 34744 0.01602 2037.7 2037A 3SA5 3065.3 1083.4 04341 2.0001 2.1262 m 45 37044 a 30 E17796 001602 1704A 3&O6 1069.7 1067J 04655 2Astl 2246

&ol603 32074 1207A 80 82561 0A745 1Ag00 2A645 m 38A5 3054.0 1992.1 63629 E01605 468.3 368 4 45.08 10 4.4 1996.4 0.0932 1.9426 20369 m 30 433J 633J 1ApF0 2.0006 as go 83068 601607 94.02 3042 3 3300A 0till 463.1 468 1 0.1295 1A530 1.g825 tu, go Espel eL01610 48 00 3037.1 1105.1 SA1613 350.4 350.4 E1472 13105 3.9577 333 les EM92 366 4 77.9B 3031A 1105.3 1A750 801617 206.4 las 1113.6 E1646 IJets 3.333g g 30325 303J6 8737 3025.4 In 130 1AD27 E01620 97.96 8019A 1117A S.1817 1J295 1A112 0A1625 357.32 157.33 0.1985 1AB10 1A395 tas 130 22230 123.00 10735 3014.0 1122A 23392 0.01629 322.98 1006.2 1126.1 82150 1536 33606 3BB 140 1.718 0.01634 97.05 9737 11735 11302 02313 14174 134s7 as 130 601640 77J7 77m 12736 3002.2 140 4J41 1A295 33r-E.06 13737 996.2 11M.2 L2473 LSSE2 SA1645 62.04 0.3631 1Aem 13111 ms 370 S 353 30.21 9022 lasA0 900J 3138.2 1J334 as 7311 SA1651 1142.1 82787 13143 i 330 130 3340 SA1657 40.N 40.M 35sAs SES 334.1 9773 314 & O 02940 1AE24 1.7764 se 401664 3342 3344 E3001 1A8m 1JgGO me ago IL526 2730 3732 175 15 971A 1149.7 34.133 041671 110 970J 1390.5 E3121 1A447 L75m at2 26.78 36A0 151.17 ago 212 14AB6 0.01672 33.15 1323 965.2 1153.4 Estal RA201 1.7442 OA1678 23.13 03338 1m03 L73ge 330 220 37.186 19381 198.33 96& 7 1157.1 ang 401685 19.364 &M33 1 Jam 13142 230 30179 041693 1&304 16J21 SEE 962.1 1100.6

&3677 1ABE3 IJ W 3D 340 34365 11A19 214 2 94&G 11460 39A25 OA1701 13A02 350 &M19 km43 LW82 MB 11J62 32430 936 1167A ,

M 427 E01709 11.745 Int 5 1170 4 &3000 1Rm lA729 IIS 260 270 41356 0 01718 10.042 SQAGO RM4 389.17 331.7 W4.6 1173A &4098 12501 1.5 50 mage 48200 401726 EM7 E4236 1223 1.4473 age 7.443 7A40 3SDA 917A 11762 18351 as 350 N.550 0A1736

&444 W 910.0 1179.7 .44372 LIS79 WA05 401745 E448 300 E4506 1.1736 1.g232 310 SA26 30A 902.5 3182.5 3A136 me 310 77A7 0.01755 5.009 4314 aga4 SD4A 1185.2 CA440 Lt477 MA4 0.01766 4.896 378A 1190.1 64902 1Apto 1.Sett ses

320 3J70 3.73B 3112 1.3673 333 340 117.99 &01787 IB2J 382.1 11MA 45161 1517 CA1811 3.939 3357 03414 IA057 *1AsF3 m 360 153A1 2J17 3.335 5 14 844.5 1198.0 1gL73 CAla36 3a0 8253 1201A ES867 4937 LE274 30 1A444 1AERO 375.3 L9000 43 400 347.26 0.01864 1A937 asA 306.2 1203.1 RS015 &Sim 305.78 0.01894 Lesos 735.4 1204.4 EG161 82729 1AWBO 400 A20 L2140 41SA 440 3 1.54 0.01926 1.1976 44LS 763 2 1204 8 OA405 44299 L4704 50 OA196 03746 E9942 04644 RFE71 RASIS et 440 48&9 0.8172 464.5 735.6 1204.1 0.0200 0.7972 440 364J 0.8890 0.7443 1.4333 me 04749 4E73 714J 1202.2

-t 0.0204 0.0545 G87A 31994 OJ133 0.7013 1.4146 330 500 GBOLS 0.5306 44696 512A 1.3964 See 520 812.5 OA209 44651 S3&A e67.5 31M.3 0.7378 &G677

, SM.S E0215 0.4437 E7625 OA13t L3757 seg MO E 5.3 1187.7 He 1133A 0.0221 0.3651 0.3871 SE2A see.9 1179.0 0.7s76 036n man suo 0.29M a3222 set.1 ss0 1326.2 cm2s 1.333 me

&2675 E73 . BBC.6 Il67J Salk &5196 400 15412 0.0236 02428 es&S 306.3 3 n.2 a2403 teens 1Jost een cm47 0.1962 a220s SAM 4 RAIM IJett ses 620 37sE9 579 I 454.6 3113J 640 3599 SA260 18.1543 &1802 734A ana.1 1307A Smel a25aa Laonm OA277 0.11u &l443 83384 02m IJm8 30 See 2365.7 ,, A0008 41112 750 5 310.1 1050.5 640 2705.4 0.0304 3.3355 3ge 40752 SE2A 372J 995.2 E9901 R160 7c0 3m4J 0.0366 0.0386 0 9060 1.0612 0 La612 7e64 0.050s 0 SO90s 90Ea 705.s 320s.2 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATFD MATER (TEMPERATURE)

A.3

L C ,. Stas /Is Emetry Gene /o aF Gassgr.th./In 9eawme. Safe

.a . - Daae pee F 84 4, 6, *= % ab '6 *4 e, v. *a ager e em len.S 307S 5 0 a.ls72 a.Bar2 0 to:L3 asses l

aun 32 0is 0.01602 3302.4 90061 2170S 3.3386 3 8 10223 has Salen! 3945.S 3DESS 3 03 19738 'le M S

! 9.10 35 023 13 50 1967 9 3081 4 0 0771 31140 3nell 1130 1025.7 EIS 0.01632 2004.7 3ees 7 3122 10283 E30

! 9.15 43.453 1SM 3 21.27 3063 S 3084 7 0 0472 2 07M 2.1140

' g30 $3100 0.01603 ISM 3 32.54 10S7.1 3089 7 E0641 2 0165 3MDB Stad 1032 0 tan 64esa 001604 1039 7 3539J e192 1034.7 640 mJ0 792.0 752.1 40.92 8052A 2093J SA799 3.9762 3A662 gas 22A69 E01606 sus 47A2 304a 6 1996.3 00925 1.M46 3333 m R least ES ES 79.546 0.01607 M t.S S3.25 1045 5 1998 7 0.1028 1.91 M 3 a ll S324 1030.7 && '

001609 M00 SeEl ElO 10e&3 E7

' O.6 85218 as4 M SS 10 1042 7 1100 8 03 12966 3M gy 90 09 0.01610 446 93 M.39 3040 3 1102 6 0.1117 13775 1A970 MJ9 lest.7 43 ga E01611 41147 allAs 94Je 46.24 3033.1 Iles.3 EIM4 1A406 1m30 OL24 1042.9 ta E9 98.24 0.01612 354 41 M43 3RBAD E73 30M 1 185 3 0.1326 1AMS SAM 1 SJ3 less.1 33 1.0 101.74 E01614 333.99 MA3 9822.1 IllL2 ElFSO 1.Mbe LW tsAB 10SIA SA E01623 173.74 D3.M 3A IM 07 041430 114.71 3E73 109.G 1013 2 1122 4 0J009 1 ASS 4 late 189 41 totu te as 3.0 14147 0.016M 9043 WM 120.92 100L4 1127J 0.21M IA429 1525 1M30 19802 i A0 152 96 130.20 1000A 1131.1 02349 1A004 13e4 13k38 1963.1 Ea 8,0 16224 CAINI 73.51S 3LS3 l

61.M7 em 13e 03 996.2 1134J SJ474 8.9820 tm' la m lessd' as

&S 17405 OAIMS least 1067.4 FA CAIM9 13 634 WA6 144 E3 992.1 llM S 6.2541 LSSS7 1A15 ta i 7A 17654 0.016S3 47J23 47JS 15027 SELS 1139J 02676 1A3M 1m0 190A4 1089.2 as, i 3.0 132 84 42 40 IMJO 985.1 llelA 0J760 1.S234 1J954 IS6Je 19703 E0 188 27 0016M 42JBS 181J1 372J 30 l

193.23 E01659 38.404 R 42 161.26 32.1 1843.3 E2536 L9043 L3579 30 l

OA1672 E782 ESO 1 5 .17 970 3 1890.S E3121 RA447 1M SE12 197FA 34ms 1 Ages 212A0 c.3137 1A415 L752 181.16 18772 as 0.01673 26 274 aut 131.21 909.7 1150.9 B 15 213A3 mas 7 IMJ7 960.1 139L3 E3354 IJ962 L733 3148 83621 IMIA 0.016&3 20.070 IS7A N 30 227.96 0 01701 33.72M 11.744 21E9 MS.2 11M.1 03842 L3313 16 33&s legg.1 m 30 250 34 001715 10 47M 3E497 236.1 933 6 11092 03321 1344 tses m de 267JS SA1727 8.4 M 7 0.514 2942 923.9 1174.1 E4112 IJ474 Sm SE1 ISL3 30 51A2 7.1542 7.374 262.2 MSA 1177.s a4273 121s7 tasal ss2A leasa e 292.n n0173s 30 as 0.01748 4.1875 4205 272.7 907A 1130 6 0 4411 1.1905 1 s te 272.5 11002 70 302.93 0.01757 54S36 5471 332.1 90DL9 1881.1 E4%34 1.167S EM N12 1882.1 SB 30 312 04 SM S 1885.3 0.4 M 3 1.1470 1.R13 2944 1103.7 95 i

001766 42777 4A95 290 7 90 320.29 327A2 0.01774 4.4133 4A31 2M.S MB6 1187J 0A743 LIS4 16 2H2 18062 380 300 001709 3 7097 3.728 312.6 877A 1193 4 04919 latt0 km79 312J 8107A 830 l 120 34127 32SA 388 0 1193.0 0.5071 1.0841 137S2 324 3 1109.8 140 001803 3 2010 3 219 am 140 353 0s 0.01815 2.51$$ 2 234 336.1 359 0 11El 0.5236 Les33 1341 3MA 1111.2 n60 M1 SS 0 01827 2.S129 2.13I sal 2 950.7 IlM 9 05328 1A715 1343 3s14 1112.5 BAD 580 373 00 001829 3J689 EJB7 atLS 042A 119BJ EM3B IA016 BASA 3MA 1113J 3a 300 311 A0 37El 825.0 130).1 ESpt 4954S LW 3753 111SA BB 0 01865 1274S 1A432 age i 21 0 40337 001849 I S238 LS427 540 805.9 1202.9 R3sE2 9.9223 LSlet 3333 11172

( leo 411.3f LI2SS 409A 794 2 12040 Secti tetos labs acta lilEl 350 0 01913 1.3064 age 3SO 421J3 4:4A0 0 0193 3.14162 1.1410 424.2 780 4 120e 6 0 U17 Re630 1A87 422J 1112 7 acc 450 4tb28 0 0195 1A1224 1A318 437J M7.5 laeta 04360 SA378 1A75 43L7 1113.9 30 755.1 1204 7 0.6490 ES148 1559 447J !!!sa too 001M 0 90787 E1276 449.S 50 S19 4(7 01 0 82153 84418 480 9 743J 3204 3 O M11 07936 Im47 448 3 1118 8 553 47492 ,,0 0199 732.0 3203 7 05723 07738 1AeSt 4805 111U 800 403 44523 1 0201 0. 74M2 47098 471.7 3ep GMCS 0.6350S teSM 491 4 FIOJ 1201A cel2s 07377 1AB4 4GL9 111& 9 703 .503 3B G89 6 till4 01111 OJOSI 1ARE3 90L7 lins 2 me 833 514 21 0A209 ES4003 03HO 9093 00217 0479sa ES0st SM 7 M97 IIM 4 0 7279 067S3 1 m 32 S23 2 1113A See 900 Silas 04460 S42A eS0 4 IIES 0.7a3A 0 6476 1m10 SEl".A 11164 Beso ,.

54.55 00214 042436 431 5 1889 1 0 7!FS AUl4 late 963.1 11073 1880

l 1000 tit.Ft 0.0220 0.37N3 S4006 S$7.5 1100 0022) 0 M013 SJ62b S71.9 413.0 lite 8 07714 0.9999 RM 584 9 11043 130 !

1233 1367.19 00227 030722 R3299 BAS 6 994 4 1880 2 E7843 0.S733 8377 500.1 llent tage ,

2300 537.82

$76 5 1175.3 Oftes 0 $s07 1.as74 ser3 10a7.1 less 1400 strpr ho orn 0 77s71 0 301: Sta s 1see It&O 5 % 70 00236 0 2h372 42772 611.7 M84 II701 OAQRS 0f2&B 1mF3 0052 ' 1093.4 ,

2000 633,80 0.02'.7 0167U. S1883 472 3 444.2 1838 3 0 SCI O 42 % IJEBI 462A 10G5 6 3e00 2$00 0 02r.f 0 80209 01307 731 7 351 4 1093 3 C.9139 03206 12385 FlES 3032.9 2500 MLil 288.4 18703 09728 01998 Latl9 7323 973.1 gage l 3000 M%33 0 0343 0 05073 48B50 001 A 0 9060 l.0612 0 1 5 12 8713 475.9 spos.2 i 320e 2 701.s 7 0Os06 0 0 0808 906 0 TABLE A.3 PROFI2 TIES OF SATURATED STEAM AND SATURATED MATER (PRESSURE)

A.4

m . ..

.+ ,-

go,my,,,em ,y ate pr***-

/se 300 WO 9 51 to 3m W W BM 1100 13tm tal nece Igm 100 Sin

, epl61' 382 S 442.3 SI1.9 8713 Gal.l 900 7 3 e es to late 2 IBM 7 12413 SMS6 15361 Und S g131.743 e al295 t ense 3.1152 2.1722 33237 3270s 22144

, talet 35 M 90.74 102 24 31423 IM ll 15 85 ISO 03 361 M 173 06 19S 75 197 70 3596 114EA liesa 3241J 170s 2 1335 9 laba 3 1433 6 laS3 7 3534 7 ISS6 7 1639 6 in)3 174s 0 1g31 S s a to 01 (16724) e 0.1796 lA736 1A369 RAD 43 3AMO 2.0932 313C3 31776 32138 32521 IJ0 M 3JI94 235

, 00161 M es 44 98 51 03 57A4 63 03 5 00 M 9a 3 94 es 91 g2 37 gsSe les to lie M 11672 3186 6 18937 1740 6 las7A 133SS 3540 14334 tastS 1534 6 1986 6 1839 S Mp3J M47A Mc34 30 e 68 07 L795 IS$93 1A173 3.9 W2 2 AIM 2A603 3.1011 33 34 3.1757 SJ101 32430 32744 (19 213 s 01295

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g2s7JS) e 0.129S 42Da0 L4092 1.M00 LA143 1J624 1.5066 L9476 E M 18224 3AMS 3299 3.3224 3.18 l

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as0 a 08J6 3E29 369 n 1A61s L705 1.7386 1AD36 13451 8 5 W Lag e Leg 62 1 m a n s E m 33794 g327A2)e E1396 42339 OA371 e 00163 ta'IM 0.0175 40704 4.8341 S.1437 Sm31 &ltft &336 FJ000 7.3W6 &2119 E7130 talas 1713D 1224.1 12M.4 1325 1 137B 4 lefts 8E798 1531.4 1981.9 1837.1 331J 1745,2 Igens 130 h E31 tem #1 269 81 1A306 1AB72 3.7376 RJBat 1A246 1536 LegD1 LMe9 1J30 1986 a s c gaaet l g341J7) s 0.1295 52339 04371 90141 SSIM 00175 1.4661 3ASM 44119 4585 12995 523M &lF09 &mN PA989 7Adb2 7348 &3t33 e

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(

e 00161 telM 0 0174 2 M74 3.0433 3A053 3.M21 4.1084 455 4J907 1529 41389 7 1982.4 E457 IE75.9 53014 1sen2 17eSJ113E3 MOL2 Ea 1213 8 12712 1324 0 1375J 1426J REN.7 tse e e 47 3e5 47 M* 97 1.S743 1A376 BAe00 L7362 L7784 181M 1 Abel late 1A227 n.384S 1340 3Al42 0732:3) e 012M E2tM 04370 f e 00181 telu 00174 21210 3598 3.7247 SABE3 3.37E3 19515 dance 4J077 44128 49445 S2191 Esa 1 1269.0 1322.8 1374.3 142S.5 3477A 1529 I 1581.9 1835.4 les8 17eS son a es f.2 SES St M9 M plW) e 0 1294 0 29M 0 4359 13593 1A242 1AUG 1J239 LMG3 15157 13426 1ATM L9800 L94D LS732 3 e 0 0141 SalM 00lM 00186 2.1904 1319 2 4462 2AS72 2.9410 13305 3A382 3eE37 19278 41700 44131 a

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( 641735) e 41294 42937 0 4737 O M46 LS703 1A274 1A758 1.7192 EJtB1 IJ964 13317 4AI62 13B72 1 5 75 1A5 e 00161 Sclu 00174 0.0886 1.4913 83035 1A973 2A332 #smu 2 444S 2319 SJWD 1W730 11471 33BC 350 a ED15a 348 85 270 74 375.21 1251.5 13114 1366 2 M19J 38713 IS24.7 3S182 8832J IS7.1 17e2A 379E9 lA3L73) e 01293 829M G43GF 0.5664 1.b443 3.e077 1A671 L7000 1J431 L7787 13841 1A477 13795 RA6m L9sas e 0 0161 6 8164 0 0174 00162 12941 1.4763 1A499 1Allt L9PS9 2.1339 2J901 # aa** 3.9087 3JS15 3.9837 r

f age a man gen er 270 33 37S.27 124St 1307 4 13b3 4 tal?A 3870 3 1523 3 ISM 9 3831.2 ISL2 3748 9 17E2 1444 40) s $1298 S2935 0 4M6 0 %63 1.5762 L9901 16406 1.0050 12256 13632 L7M tatt BAS 47 1355 LatSe e ettel telu 00174 O plM 09919 1.1984 13037 IA397 1570B 1 9992 lano Lgl07 3A744 3.19D 233cu 12312 8299 1 1357.7 1417 7 goes 4 1 bat 3 IS74 4 1839.1 8344 17e 3 179E9 980 6 69 37 BES 19 270$1 375 38 14978 8.9995 IAs23 36See tasse IJ wl 3.n30 lAges 1An3 laset smes lu2 Ail e 01292 e29M e4M4 e36ee TABLE a6.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)

A.5

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,l j , 90161 00166 00lN 90lM 00704 R6774 07079 0A759 DM31 1 0470 11289 IJUD3 IJEWS 1 3669 14446 1271 1 1339 2 1399.1 leSS A ISI14 1546 9 Ig27 asse g 3735 0 1792 9 gas a 70.11 869 88 271 07 375 73 48738

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&me &me Omn uim term as2m em ute E39m rum &=. Sam &m. &M.S &c.

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A.6

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