ML20238F387
| ML20238F387 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/27/1987 |
| From: | Elin J, Royack M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20238F377 | List: |
| References | |
| 50-206-OL-87-02, 50-206-OL-87-2, NUDOCS 8709160118 | |
| Download: ML20238F387 (185) | |
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b U. S. NUCLEAR REGULATORY COMMISSION REGION V Examination Report No. 50-206/0L-87-02 Facility Name: San Onofre Nuclear Generating Station Unit i Docket No.: 50-206 Examinations Administered at: San Onofre NGS, San Clemente, California from July 28, 1987 through August 5, 1987 Chief Examiner: -W / 8!M f'2 M. J. Royac p6rator Licensing Examiner Dats Signed Approved by: b,b. '
t7 I J 0.~ Elinv, Chief, Operations Section DayeSi(gned' Summary:
Examinations on July 28 to August 5, 1987 Written and operating examinations were administered to six (6) initial candidates for Reactor Operator (RO) licenses. Written and operating examinations were administered to two initial candidates for Senior Reactor Operator (SRO) licenses. Five of the six candidates passed the written examination for Reactor Operator and the two candidates for Senior Reactor Operator passed the written examination. All candidates passed their operating examinations.
As a result of these exams, five of the six candidates for Reactor Operator and two of the two candidates for Senior Reactor Operator were found to meet the minimum qualifications for licensing.
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- 1. Examiner s M. J. Royack, RV
- 2. Persons Attend _ing the Exit Meetings {
- M. J. Royack, RV ,
- M. J. Kirby, SCE s
- J. T. Kroeger, SCE
- R. J. Maisel, SCE
- G. Tilton, SCE
- D. J. Riley, SCE
- L. C. Falcone, SCE
- d. H. Custer, SCE
- L. Simmons, SCE t
- Denotes Meeting on July 31, 1987 i
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- Denotes Meeting on August 6, 1987
- 3. . Written Exam and Facility Review The written exadit;ation was conducted on July 28, 1987 at the facilities training center. At the conclusion of the examination, copies of both the Senior Reactor Operator and the Reactor Operator examination keys werelgiven to the facility staff for review and comment. -'
The facility provided comments and proposed resolutions as a result of their review of the SR0 and R0 examinations, in accordance with NUREG 1021, Revision 4. Facility comments and final NRC resolutions are included 'es attachment 1 to this report. Based on the facility codeents and NRC ;
resolutions the SR0 and R0 examination keys were revised and the candidates' examinations were graded.
.n Duringthereviewoffacilitycommentsand'Nuestionsaskedbycandidates during the examination the examiner noted that many comments were due to incomplete or inaccurate reference materi4, supplied by the facility .to ,
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the NRC.
TwoexamplesN"outofdate"informationwerepointedouttothefacility staff: ,
. T:le alarm function fer ORMS detector R-1214. is indihted in .
system description,- 5D-S01-550, as alarming in the fontrol room and in Sacramento. A design change has been made to have the alarm '
function to Sacramento come from radiation monitor R-1254, which is not reflected in information provided 1or the exam preparation.
. System Description SD-501-270 states that there are two conditions that will cause a turbine runback, a dropped rod and low frequency.
The turbine runback on a dropped rod is no longer in service.
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Two' additional areas of concern regarding reference material were pointed !
out.
I_n, complete Da' ta The examiner pointed out the use of the term "LATER" in the Auxiliary Feedwater. System description SD-501-620 as an example of incomplete information. The use of the term "LATER" for a unit that has been in operation for 20 years is-unacceptable, especially for the Auxiliary Feedwater pump turbine governor cor. trol and overspeed trip.
Key Information Exclusion
[ The exclusion;of " KEY" system descriptions and procedures from the 1 reference material sent to the NRC was pointed out to the facility 6 staff. These system descriptions and procedures were not listed on the system description or operating procedure lists provided with the reference material. The numbers and titles'for the system descriptions and procedure were obtained by the examiner from reference lists in
, operating procedures and other system descriptions. Four KEY documents, y that were excluded from the original package were:
- f. .1.. SD-501-260, Feedwater Control System.
- 2. SD-S01-390, Primary Process Instrumentation.
- 3. 50-S01-350, Fuel Handling Transfer and Storage.
- 4. S01-12.9-2, Reactivity Calculations.
These documents were subsequently requested and obtained from the p facility. staff.
The examiner indicated to the facility. staff that it is the facility's
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responsibility to provide complete, correct, and up to date material for exam preparation.
- 4. Operating Examinations The' oral examinations were conducted on July 29, 30 and. August 4 and 5, 1987. General areas of weakness that were noted were the understanding of spent fuel handling equipment and the operation of the hydrogen recombiners.
5.. Exit Meeting On July 31 and August 6, 1987 an exit meeting was conducted with licensee representatives, as noted in paragraph 2 of this report.
During the meeting the examiner described the inadequacies of the written material provided by the facility to the NRC, as noted in paragraph 3 of this report. The examiner noted that it was the responsibility of the facility to provide up to date and complete information to the NRC, as requested in attachment 1 to the letter to
- Mr. Harold Ray, dated March 11, 1987. Also noted was that if the material supplied for the preparation of the examination was found to be inadequate then the examination could be cancelled and rescheduled for a later date.
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ATTACHMENT 1 .
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LICENSEE COMMENTS' c AND NRC RESOLUTIONS A
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SENIOR REACTOR OPERATOR i
AND REACTOR OPERATOR
=I EXAMINATIONS ,
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'5 LICENSEE COMMENTS e
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- NRC RESOLUTIONS 3
REACTOR OPERATOR EXAMINATION i
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m QUESTION 1.03(b)
SCE' COMMENT:
It.'is unclear as.to whether or not the question of part (b) required the
. stated conditions to be modified by the answer to part (a). Interpolation of steam tables based on the answer to part (a) can lead to different answers in part(b). .
SCE REQUESTED RESOLUTION:
Modify the answer key to, accept the value for steam enthalpy based on either the stated conditions or on the stated conditions as amended by.part (a) eg; for b.985' steam enthalpy calculates to 1192.9 BTU /lbm which when substituted into the_ equation results in a % Power ~of 88.6%.
NRC RESPONSE QUESTION 1.03 Facility comment' accepted.
The response to part (b) of question 1.03 is revised to accept an alternative
- answer of 88.6% power, however the 88.6% power must be based on correct results obtained_from. response (a).
QUESTION 1.10 SCE COMMENT:
Equation used in answer key is different from equation provided.on equation
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sheet. Also equation sheet has a different value for J
- than given in the question SCE REQUESTED RESOLUTION:
to accept calculations utilizing the equation provided Modify the' answer on the answer sheet key (which has a Keff term not used in the answer key) and also accept answers based on either value of * .
NRC RESPONSE QUESTION 1.10 Facility coninent accepted.
Answer key is revised to accept responses using Keff term in answer. <
The value for 'j" is given in the problem, therefore, that is the value to be .
used in the response. The answer key will not be revised to use alternate value 3 of"j".
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QUESTION 1.13 SCE COMMENT:
The term " Axial Flux Difference" (AFD), is not used at SONGS. The' reference is a Generic Theory manual used to explain the theoretical concept of axial l flux changes over core life. The answer key refers to a limit for AFD.
Operational questions should come only from plant specific procedures or Technical Specifications. SONGS has no 5% limits above 50% power for Axial Offset. (Reference Technical Specifications Section 3.10)
SCE REQUESTED RESOLUTION:
Delete the question as it is not applicable to SONGS Unit I and redistribute the points.
NRC RESPONSE QUESTION 1.13 Facility comment accepted.
- Question 1.13 is deleted and section point value adjusted.
QUESTION 2.01 SCE COMMENT:
SCE does not require operators to memorize component power supplies to the specific bus level of detail. They are required to know power supplies with respect to the voltage ie; what loads are 4KV. 480V etc. They should know that there is one of each type of pump on each 4KV bus (Condensate pLr.ps have two on each bus). Operators do not normally use letter designatar but rather location for pump names ie; North, south, etc.
t SCE REQUESTED RESOLUTION:
Modify the answer key to accept: 1 Heater Drain Pump. 1 Feed Pump, 1 TPCW Pump, and 2 Condensate Pumps per bus (without letter designator).
Accept Charging Pump and Safety Injection Pump on either bus.
NRC RESOLUTION QUESTION 2.01 Facility comment not accepted.
However, the key is revised to accept nonsafety related pumps (heater drain pumps, condensate pumps and turbine plant cooling water pumps) without letter orlocation(north, south) designator. Safety related pumps, main feedwater, charging and, safety injection pumps, must have letter or location designation (A, B, north, south) associated with them. This is in accordance with Examiners Standards ES-202, paragraph A.2 and NUREG 1122 KSA catalog knowledge requirements.
I QUESTION 2.04(c)
L SCE COMMENT:
The answer key requires the examinee to identify the source of the Containment Spray System water, however; the question does not request this information.
SCE REQUESTED RESOLUTION:
' Modify answer key to delete reference to RWST and accept borated water for full credit.
NRC RESPONSE QUESTION 2.04(c):
Facility comment accepted.
The response to question 2.04(c) is revised to accept "the water for containment spray is from a barated water source" for full credit.
QUESTION 2.06(a)
SCE COMMENT:
The stated answer. to the backup power' supply is correct, however, the answer may also reference Regulated Bus #4 since this bus is fed from Vital Bus #4.
SCE REQUESTED RESOLUTION:
Modify.the answer key to accept either Regulated Bus #4 or Vital Bus #4 as the backup power supply to NIS instruments 1201 and 1206.
NRC RESPONSE QUESTION 2.06(a)
Facility comment accepted.
The response to question 2.06(a) is revised to accept " Regulated Bus #4" for vital bus #4 as the backup power supply.
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.l H SCE' COMMENT:
. , The stated answer to the alternate' source of power to Vital Bus #1 is correct, L" ,
'however, the answer may also state the 37.5KVA transformer or transfer switch 1
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NT ' SCE REQUESTED RESOLUTION:
Modify, the answer key. to ' accept 37.5KVA transformer and/or transfer switch #7 in addition to MCC-2..
NRC RESPONSE QUESTION 2.06(b)
Facility. comment not accepted.
The original. response to the question includes 37.5KVA transformer as an
- alternative response,.
A transfer switch is not a source of power, therefore, it will not be accepted H as.a source of power.
l QUESTION 2.06(c)
L SCE' COMMENT:
s Operator memorization of color codes for vital buses is not' required. The lesson objective in the lesson plan'on the maintained 120VAC system, 1XE205, H states " Explain how Maintained 120 VAC system color dot-identification system supports plant operation".
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- SCE REQUESTED RESOLUTION
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Modify the answer key to delete this question requiring memorization of color f dot codes. =Notwithstanding the above the answer for' Vital Bus 3A would be
" WHITE / BLUE" not WHITE per S01-2.6-3 page 30 (copy attached).
NRC RESPONSE QUESTION 2.06(c):
Facility comment not accepted.
- . The facility uses color coding to identify electrical circuits, therefore, I. operators should be able to identify that circuit with its color code. This p it'in accordance with Examiner Standard ES-202, paragraph A.2 and NUREG 1122 l KSA catalog.
l' l: The response to question 2.06(c) is revised to show vital bus 3A coded as
. white / blue..
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4 QUESTION 3.02-SCE COMMENT:
Part (c) The answer key requires more information then the question requested: the term " power supplies" generally applies only l to electrical power sources. The question was not worded
appropriately in that it is apparent from the answer key that the intent of the question was to request the " motive force" for the PORV's. Also, since the question did not specify the number of required responses or power supplies,.it would be. o appropriate to only discuss 120 VAC as the power supply to the PORY Block Valves.-
SCE REQUESTED RESOLUTION:
Modify answer key.part c to accept 120 VAC for full credit if Instrument Air and Nitrogen sources are not included in the answer.
NRC RESOLUTION QUESTION'3.02(c):
Facility comment accepted.
Instrument ' air and nitrogen are deleted.from the answer and the point value of the question is reduced to-(0.5) making 120 VAC the acceptable ~ answer.
QUESTION 3,04 SCE-COMMENT:
The question asks for'the two inputs to the variable low pressure trip. The answer key addresses the inputs for the variable low pressure trip setpoint or calculation, not for the variable low pressure trip. There are actually three (3) inputs to the variable low pressure-trip: Pressure, differential Temperature,'and Tavg.
SCE REQUESTED RESOLUTION:
Modify the answer key to accept any two of the thrte inputs to the variable low pressure trip as indicated above.
NRC RESPONSE QUESTION 3.04 Facility comment accepted.
Reactor Coolant System (RCS) pressure will be added to question 3.04 response.
The point value of the responses are revised to 0.5 points for each correct response with a remaximum of 1.0 points.
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QUESTION 3.05, t
SCE COMMENT::
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The answers in part b and'dLdiscuss Rod Speed in units of-inches per minute.
only. ' At SONGS.1 it is common practice to. refer to. rod speed in either inches perminute~or. steps:(pulses)perminute.
SCE REQUESTED RESOLUTION:-
"* Part (b)- Accept 15 steps (pulses) per minute as well'as 5 inches per minute as.a correct answer to part b.
Part'(d) Accept 40 steps.(pulses).per minute as a. correct answer to part d.
NRC RESPONSE QUESTION 3'.05(b) AND (d):
Facility comment accepted.
Response 3.05(b)'isrevisedtoalso' accept 15 steps (pulses)perminuteas=an alternate response. Response 3.05(d) is revised to accept 40 steps (pulses) per minute as an alternate response.
QUESTION'3.07(b),(c)
SCE COMMENT:
Parts b.and'c' request four responses each. The answer key states that each response is worth 0.2 points,'which would yield a maximum score of 0.8 points'.
SCE REQUESTED RESOLUTION:
Modify the answer key to reflect a value of 0.25 points for each response, for a total of 1.0 points in parts b and c.
NRC RESPONSE QUESTION 3.07(b) and (c): j
' Facility comment accepted.
The point values for each response in 3.07(b) and (c) are corrected to indicate 0.25 points for each response with a maximum of 1.0 point.
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,r QUESTION.4.03(l'.5)
'SCE COMMENT:
Part (a)(b) 'The scenario described in the examination question is inappropriate. With the reactor op'erating at 92%. power, a" reduction in loop flow to 70% would
". cause a reactor trip. The Abnormal Operating Procedure 501-2.1-1, " Loss'of Reactor Coolant Flow" would not- be entered for this condition above 50% power.
.Part(c) Additionally, the P-8 setpoint stated in the answer key is incorrect. The correct P-8 setpoint is 50%
v not 85%.
- SCE REQUESTION RESOLUTION:
Part(a)(b)- Since some of the candidates were advised during the examination that the scenario provided is correct,
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full credit should be given.for responses responding as a partial loss of flow in accordance with 501-2.1-1.
However, some candidates may respond with "immediately trip.the reactor and enter 501-1,0-10," which is' actually the correct response for the scenario provided.
Part(c) Modify-the answer key to reflect the correct P-8 setpoint of 50%.
NRC RESPONSE QUESTION 4'03: .
Facility comment not accepted.
'The header of the question states the specific conditions. Each question ;
requests specific information relating to that condition or a set point.
Clarification of the question was provided during the exam.
QUESTION 4.04 SCE COMMENT:
Part(a) Point value given to the question is stated as 1.0 but the answer key only gives a point value of 0.5 for the correct answer.
SCE REQUESTED RESOLvTION:
Modify the answer key (part c) so the point value distribution between the question and the answer kay is consistent.
NRC RESPONSE QUESTION 4.04?a,j Facility comment accepted.
The point value for response 4.04(a) is corrected to read (1.0).
I' QUESTION 4.11(b)
SCE' COMMENT:
l The question asks for actions contained in the subsequent actions portion of the A01.. SCE does not require operators to memorize subsequent actions.
SCE REQUESTED RESOLUTION:
Modify the answer key to accept a general discussion of the actions rather than verbatum action statements from the procedure.
NRC RESPONSE QUESTION 4.11(b):
Facility comment-accepted.
The response to question 4.11(b) is noted to accept a discussion of response, however, the four (4) key points must be addressed in the response.
Trip the reactor Stopreactorcoolanteffectedpump(s)
Enter S01-1.0-10 Remove the reactor trip breakers i
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LICENSEE COMMENTS AND NRC RESOLUTIONS SENIOR REACTOR OPERATOR EXAMINATION
QUESTION 5.03 SCE COMMENT:
The Xenon table in the reference (Cycle 9 book) shows the peak at six hours and the answer key inappropriately states that peak Xenon occurs from 7-8 hours after shutdown as a true statement.
SCE REQUESTED RESOLUTION:
Change the answer key to " FALSE". A copy of Table 4.8-1 (page 67) of Cycle 9 book is attached.
NRC RESPONSE QUESTION 5.03 Facility comment accepted.
The response to question 5.03 is revised to " False".
QUESTION 5.12 SCE COMMENT:
Part (d) From the given conditiens, Qinitial = Qfinal immediately following the pump trip; the heat transfer area "A" has decreased (2 vice 3 steam generators), Tave will remain essentially constant, therefore Tstm must decrease to keep Q constant in the equation Q=UA (Tave-Tstm). Since the S/G is a saturated system Pstm must also decrease (seeattached). Therefore, the answer should be decrease, not remains the same.
SCE REQUESTED RESOLUTION:
Change the answer key (part d) to " decrease."
NRC RESPONSE QUESTION 5.12(d)
Facility comment accepted.
The response to 5.12(d) is revised to " decrease".
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QUESTION 6.03 SCE COMMENT:
Part(c) SCE does not require operators to memorize specific bus power supplies to components.. This information is available to operators in the control room in various operating documents. However, the voltage of the power supplies is required knowledge.
SCE REQUESTION RESOLUTION:
Modify answer key (part c) to accept voltage (120 VAC) for full credit.
NRC RESPONSE QUESTION 6.03(c)
Facility comment not accepted.
Identification of power supplies and sources is in accordance with Examiner Standard ES-402, paragraph A.2 and NUREG-1122 KSA catalog.
QUESTION 6.04 SCE COMMENT:
Part(c) Turbine Generator Impulse Pressure is the same as Turbine First Stage Pressure. The answer Key correctly indicates that the Turbine Generator Impulse pressure is used to develop Tref. However, SCE utilities the term Turbine First Stage Pressure.
SCE REQUESTED RESOLUTION: ;
i Modify'the answer key (part c) to accept either the Turbine Generator Impulse Pressure or the Turbine First Stage Pressure as the correct answer.
NRC RESPONSE QUESTION 6.04(c):
Facility commant accepted.
The response to Question 6.04(c) is revised to accept turbine first stage pressure as a correct answer.
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QUESTION 6.06 SCE~ COMMENT: l l
Part(c) The question is potentially misleading due to it's vague wording.
.We also understand that additional' clarification was provided by the examiner.
SCE REQUESTED RESOLUTION:
Review and' modify the answer-key as appropriate to include answers consistent with the clarification provided to the candidates during the exam.
NRC RESPONSE' QUESTION 6.06(c) ,
. Facility connent ' accepted.
The wo'rding of 6.06(c) was' corrected and passed onto the candidates during the exam to-read... signal to the steam dump pressure controller is lower than...The... key is revised to reflect the correction.
QUESTION 6.10 SCE ' COMMENT:
'Part(c) The signal from R1214 to Sacramento has been deleted.
Currently R1214 only alarms in the control room. -The System Description has recently been modified to reflect this design
' change..
SCE REQUESTED RESOLUTION:
Modify the answer key (part c) to reflect the control room as the correct answer.
NRC RESPONSE QUESTION 6.'10(c):
Facility comment not accepted. ,
The candidates were directed to indicate any updates in alarm signals when they indicated that it was modified to another channel. No revision to response 6.10(c) required. The facility did not provide updated reference material to support connent.
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i QUESTION 6.11 SCE COMMENT:
Part(b) SCE does not require operators to memorize power supplies to the bus level; only voltage level memorization is required.
Part(c) Question does not state the number of responses required for !
full credit.
SCE REQUESTED RESOLUTION:
Part(b) Modify the answer key to accept voltage (480V) only.
Part(c) Modify the answer key to accept either answer for full credit.
NRC RESPONSE QUESTION 6.11(b):
Facility comment not accepted.
Identification of power supplies and sources is in accordance with Examiner Standards ES-402, paragraph A.2 and NUREG 1122, KSA catalog. Revision to response 6.11(b) not required.
NRC RESPONSE QUESTION 6.11(c):
Facility comment accepted.
The response to question 6.11(c) is revised to accept either response presently listed as acceptable for full credit. However, the point value of question 6.11(c) is reduced to 0.5 points for full credit.
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l QUESTION 7.03
.SCE COMMENT:
The question does not specify which 4KV bus is being transferred. Answer f applies only to 4KY Buses 1C and 2C but not to 1A and IB.
Also loss of IC or 2C does not trip all 4KV breakers. The words in the ,
reference are "ALL 4KV BREAKERS ASSOCIATED WITH THE 194 RELAYS ON THAT BUS".
An appropriate reference drawing of.what is tripped is attached.
SCE REQUESTED RESOLUTION:
If 1A or 1B is lost then their loads (2 RCP's on 1A, 1 RCP on 18) will trip immediately on loss of voltage (no diesel operation).
For IC or 2C answer given must be modified to reflect that not all of the breakers will trip (see attached).
NRC RESPONSE QUESTION 7.03 Facility comments accepted. d Question 7.03 is deleted due to number of correct answers based on additional information supplied by the facility.
QUESTION 7.05(b),(c)
SCE COMMENT:
The referenced procedure is not an Operational Procedure but a Health Physics procedures. The operator training program does not train operators 0 :. . this procedure. Operators are required to know the requirements of 10 CFR 20.
SCE REQUESTED RESOLUTION:
Modify answer key to provide answers in accordance with 10 CFR 20 only.
The terms " caution,' and " danger and extremely" should not be required for full credit.
NRC RESOLUTION QUESTION 7.05:
Facility comment not accepted.
However, the response to 7.05(b) is revised to put the words " Danger Extremely" in parenthesis.
The word caution or damage is used in 10 CFR 20 for posting, therefore, will be considered as part of the answer.
The testing of 10 CFR 20 and facility radiological regulation is in accordance with Examiner Standard ES-402, paragraph A.3 and NUREG 1122, KSA Catalog.
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QUESTION 7.06 SCE COMMENT:
Part (d) The question did not specifically state that the examinee was to '
remain within the stated conditions, therefore, additional correct <
answers are "when'RCS. 500psig" and "no fuel in the reactor".
SCE REQUESTED RESOLUTION:
Moddfy the answer key (part d) to accept "when RCS 500 psig" or "no Fuel in the reactor" in addition to the listed answer.
NRC RESPONSE QUESTION 7.06(d): k Facility comment not accepted.
1 The leader of the question states that the reactor is shut down and the pressure is 450 psig. . Therefore, the comment that there is no fuel in the reactor is not applicable. However, RCS pressure greater than 500 psig is acceptable and will be added to (d) for full credit. i QUESTION 7.08 ,
SCE' COMMENT:
Part(a) The answer key has a typographical error. The Technical Specification is 40'-3" not 43'-3".
Part(b) The Technical Specification gives two reasons for having the minimum level above the flange.
SCE REQUESTED RESOLUTION:
Part(a) Change the answer key to 40'-3.
Part(b) Modify answer key to accept either reason. The second response is "there will be at least twelve feet of water above the top of the fuel rods of a withdrawn fuel assembly so as to limit dose rates at the top of the water in accordance with Section 4.2.6 of the facility FSA." Ref: Technical Specification page 3-88.
NRC RESPONSE QUESTION 7.08(a)
Facility comment accepted.
The response to question 7.08(a) is revised to 40'-3".
NRC RESPONSE QUESTION 7.08(b): ;
Facility comment accepted.
The response to question 7.08(b) is revised to accept the " twelve feet of 1 water above the top of a withdrawn fuel assembly so as to limit the dose ;
rates at the top of the water" as an acceptable answer.
QUESTION 7.10 SCE COMMENT:
Part(b) The answer key provides more information than is required by the question in that the question asks what action takes place, not what causes the action, i SCE REQUESTED RESOLUTION:
Modify answer key (part b) to place the reference to P-6 HI SUR Rod Stop !
in parenthesis, ie, not required in the response.
NRC RESPONSE QUESTION 7.10(b):
Facility comment accepted.
P-6 HI SUR Rod Stop is placed in parenthesis.
QUESTION 7.11 SCE COMMENT:
Part(a) The answer key provides only 1 of 2 acceptable responses. Either of the two responses should be accepted to satisfy the Subcriticality status tree.
I SCE REQUESTED RESOLUTION:
Modify answer key (part a) to accept either answer: 1) Source range SUR zero or negative, 2) Intermediate Range SUR more negative than .20PM.
NRC RESPONSE QUESTION 7.11(a):
Facility comment accepted.
Intermediate Range SUR more negative than -0.2 DPM is added as an acceptable answer for full credit.
QUESTION 8.13 SCE COMMENT:
Answer number 3 is correct, however, the examinees may respond, " site evacuation" due to the training they have received.
SCE REQUESTED RESOLUTION:
Modify the answer key to accept " site evacuation," as well as the answer provided.
1 NRC RESPONSE QUESTION 8.13:
Facility comment accepted.
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" Plant and beach evaluation" will be placed in parenthesis. l l
y JacmiTy cortrtEMT5 INCO31902ATED -
i AS CeEADeo To Copy U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: SONGS-1 Reactor Type: PWR WESTINGHOUSE 3 LOOP Date Administered: JULY 28, 1987 Examiner: MIKE ROYACK Candidate: KEY 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.
Category % of Candidate's % of Value Total Score Cat. Value Category 24 2.44 2d M I. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 25.9 25 _ 25' d 2. Plant Design Including Safety and Emergency Systems 24.6 zus 281 4 .2F 'b 3. Instruments and Controls 25 254 Jr 4 4 Procedures - Normal, Abnormal. Emergency, and Radiological Control 9854 JetT TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
KEY Candidate's Signature l
l
ES-201-1 Enclosure 2 ATTACHMENT 1 (continued)
Enclosure 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS 1.
A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as te prevent contact with all other facility and/or contractor personnel during the duration of the written examination. If necessary, the facility should or moteli make other arrangements building. Obtaining for the use of a suitable room at a local school, the licensee. this room is the responsibility of 2.
Minimum by the chief spacing examiner. is required to ensure examination integrity as determined with a 3-ft space between tables. Minimum spacing should be one candidate per table, l No wall charts, models, and/or other training materials shall be present in the examination room.
3.
Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above.
examiner and/or proctor. These arrangements shall be reviewed by the 4.
The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination.
vide formal written comments with supporting documentation on the e tion and answer key to the chief examiner or to the regional office section chief.
5.
The facility licensee shall provide pads of 8-1/2 by 11 in, lined paper in unopened packages for each candidate's use in completing the examination.
The examiner shall distribute these phds to the candidates. All reference material examiner.needed to complete the examination shall be furnished by the Candidates can bring pens, pencils, calculators, or slide rules into the examination room, and no other equipment or reference material shall be allowed.
6.
Only black questions. ink or dark pencils should be used for writing answers to i
l l
l Examiner Standards 12 of 17
, _m_. , - ----- ~ ~ - - - - - _ _ _ _ - - _ - - _ - . - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^- -~ ~ ~ ~
ES-201-1 Enclosure 2 e
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS-lDuring the administration of this examination the fo11owing rules apply:
1.. Cheating on the examination means an automatic denial of your application L and could result in more severe penalties.
' 2. - Restroom trips are to be limited 'and only one candidate at a time may
-leave. You must avoid all' contacts with anyone outside tthe examination room to avoid even the appearance or possibility of cheating.
- 3. Use black inkLor. 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.. 0 a. only the paper provided for answers.
- 7. Print your name in the upper. right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper,.and write "Last Page" on the last answer sheet.
- 9. Number 'each answer 'as to category and number, for example,1.4, 6.3.
- 10. ' Skip _at least three lines between each answer. -
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the. depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer ;
to mathematical' problems whether indicated in the question or not. ;
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 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.
Examiner Standards 13 of 17 -
l.
C--_-_-_____- _ - _ - - - - - - _ -
ES-201-1 Enclosure 2
- 18. When you complete your examination, you shall: '
- a. Assemble your examination as follows- ~1 I
- (1) Exam questions on top. !
l l
j
-(2) Exam aids - figures, tables, etc. '
(3). Answer pages including figures which are a 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, l
- 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. ,
Examiner Standards 14 of 17 cz.______...___________ _ -
EQUATION SHEET f = ma v = s/t w = ag
-s = v,t + lsat 2 Cycle efficiency = - "I E = mC KE = 1 gmv a = (vf - v )/t v
f=v +a A = AN A = A,e" PE = agh w = 0/t W = VAP A=in2/tg=0.693/t(-
(t, )(t )
~
AE = 931am
- Q = [nCpAT (tg+t)3 y , y ,4x Q = UAAT l y ,7 ,-px Pwr = Wf m ~
I=I 10 *I P = P, 10 SUR(t)
TVL = 1.3/p i P = P,et/T HVL ='O.693/p SUR = 26.06/T T = 1.44 DT
/A SCR = S/(1 - K,ff)
SUR = 26 l g* o) CR x = S/(1 - K,ffx)
T = '(1*/p ) + {(g cp )fxdf) CR I (1 - Keff)l = CR 2 (1 ~Keff)2 7 . g*/ (p _ p M = 1/(1 - K,gf) = CR /CR 3 0
~E D eff M = (1 - K ff) /(1 . g,ff
# " ( eff~ )! eff
- OEeff/Keff ,
sp3 = (1 . g.gg)/geff p= [1*/TK,ff ] + [E/(1 + A,ffT )] , g* = 1 x 10 seconds
~
P = I4V/(3 x'1010) geff = 0.1 seconds
~
I = No . Idlg=1d22 WATER PARAMETERS Id g =Idy
,1 gal. = 8.345 lbm 2 R/hr = (0.5 CE)/d (meters) l l' gal. = 3.78 liters R/hr = 6 CE/d (feet) 1 fc = 7.48 gal. 4 MISCELLANEOUS CONVERSIONS }
Density = 6.2.4 lbm/ft 3
" 3 1 Curie = 3.7 x 10 Odps Density = 1 gm/cm . I kg = 2.21 lbm Heat of valorization = 970 Itu/lbm I hp = 2.54 x 103 BIV/hr j
Heat of fusica = 144 Btu /lbm 1 Hw = 3.41 x 100 Btu /hr I 1 Atm = 14.7 psi = 29.9 in. Ig. 1 Btu = 778 ft-lbf l j 1 ft. H y0 = 0.4333 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 "C = 5/9 ( F - 32) d
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.d 001388 2179847874 0366652949 3702457891 97688841 g 691222 2197530741 8406284950 6172722223 345682151 ta iu s 346789 0112345567 7899001123 3445567890 123457936 666666 7133377337 1773888888 8888888889 99999990 S iq 000000 0000000000 0000000000 0000000000 000000011 L -
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a ph 8.3 3.3 8 8 3404390108 6283814566 - 63060352.13 - 30.3883 421974 2075207418 5295280233 329590316 Sa V 444321 000000 222222 098%999888 099 2111111111 8877776665 1111111111 5544433210 1111114111 986532930 000000999 111 1111111111 1111111111 1111111111 111111 111, y p g l a pg 8645444332 ah 513092 - - 865.3049520 1862823308 6631343 h v 753200 9999000123 3456789012 3345566664 172548960 t E 654321 9876654321 0987654432 1098764208 63185165 n 777777 6666666666 6555555555 3544444443 3332221 E
.d g 359.396 9847.361589 8638370245 5554318520 353718 tiu a q h 79011 1 0986420741 8528518406 2840623579 147051456 Si 346789 0012345567 7899011233 4456678901 345780270 l 444444 5555555555 5555666666 6666666677 777778889 t
.r o 8 927536 767745 4%090%4c35 9 215 2574 %178191517 93711 0450 3128011236 1657430737 804500238 619020567 apV 171985 9830252002 5951976556 7802585210 011345460 Sa 324605 0630742086 4210876543 2110987654 321098755 V 098376 6555444433 3333222222 -
22221111 - 11 11.l 10 e 100000 0000000000 0000000000 0000000000 000000000 m u - lo p 473215 288610 0978467393 8096634651 620 r425938 3081965367 925183110 0257873547 V aVig v 271985 102483 8819040880 8417520754 3728532111 2097654321 6956968008 2357928642 0987664321 076757790 211110710 098765310 ic E 098766 5554444333 3322222122 211111111 1 1 000000 f 100000 0000000000 0000000000 0000000000 000000000 ic e p - S 454320 9753197542 0987766778 0257155970 98942812 579135 6802457913 5680246802 5191461629 532362877
.i d I 999000 001 1111122 2223333344 4445556677 89012464 111222 2222222222 2222222222 2222222222 223333345 a u t
q V 000000 0000000000 0000000000 0000000000 00000000 Si 000000 0000000000 0000000000 0000000000 00000000 L 814098 4145983829 8227009753 2236206591 113623887 pr 209280 8229355281 34307.25801 1085283481 195923204 mh e a F t
%76643 444445 67890 0851840617 1123345566 5555$55555 2727160493 7788990001 5555556666 7148252952 1222334456 6666666666 839405055 677899000 666666777 T -
s . s n ei 9O0900 8808s900II 08380O849I r PgP 5.O80800880 888880082 505M59505M 8e0S00 080 09008 08808 8088 s/ S 5e5O59 4S5S67 788S998112 50505M5059 7334455667 0e80800800 5g50500909 7e89901234 880000008 000000099 567890122 b lb 111 11 111 11 1 1111 1l11122222 222223333 A P5
y---,- ,. APPENDIX B SUPERHEATED STEAM TABLES l l 7 4 I B-1
l i t i I 1 I i (Intentionally Blonk) J 1 l 1 t , B-2
L I l Tatste 3. Superheated Steam Abs Pfess tb/Sg in 581 Sat h*8stwe Degrees Femenheit (Set lemp) Watet $ team 200 258 300 350 800 450 500 800 fee Ice 900 test 1100 !!go -
, he 98 ?$ .148 26 198 26 24826 298 26 348 26 398 26 498 26 598 26 698 26 798 26 898 26 998 /P 10# 26 v 0 01614 3336 392 5 422 4 462 3 482 1 ' 611 9 ' 641 7 671 6 631 1 6907 730 J 809 8 866 4 9?90 . 98s 6 (10174 h 69 73' 1806 8 !!$0 2 1172 9 ills 7. 1218 7 1741 8 1266 1 1288 6 1336 1 1384 5 143J 7 1483 8 lis4 9 1986 4 1619 7 6' 0 1326 1 9781 2 0$09 2 0641 2 1152 21445 2 3722 2 1986 2 2237 22708 2 3144 2 3551 2 3934 2 41 % 7 4640 2 ste b 37 76 87 76 :137 76 187 76 237 76 28776 337 76 43776 537 76 63776 717 76 837 76 937 76 1037 76 8
e 0 01641 73 53 78 14 84 21 90 24 96 2S 10??4 108 23 114 21 176 15 138 08 15001 n194 17386 .185 78 197 70 (162 241 h 130 20 1131 1 list 6 1171 7 !!94 8 1218 0 124l 3 1264 7 1288 2 1335 9 1384 3 1833 6 1483 7 15M 7 1586 7 1639 6 s 0.2349 1 % 43 18716 1 9054 1 9369 19%4 1 9943 2 0208 2 0460 2 0932 ? !)69 2 1776 2 2159 2 2621 2 28 % 2 3194 - gg $4 6 79 % 79 106 79 1 % 79 206 79 2 % 79 306 79 406 79 606 79 606 79 706 79 806 79 906 79 1006 79 j 1193 211 ,e 0 01659 3842 38 84 - 41 93 44 98 4802 $103 64 04 67 04 63 03 69 00 7498 80 94 86 91 92 87 9a 84 661 M 1843 3 184 6 1170 2 1193 7 1217 3 1240 6 1264 1 17878 1335 $ 1384 0 14334 1483 6 1634 6 15866 1639 h 6 0 28M 1 7879 1 7928 1 8273 1 8593 1 8892 1 5173 1 9439 1 % 92 - 2 01 % 2 0603 2 1011 2 1394 2 1757 2 2l01 2 2430
$4 38 00 - 88 00 138 00 188 00 - 238 00 288 00 388 00 488 00 664 60 688 00 784 0; 888 OC 988 00 14 696 e 9167 24 799 . 28 42 - 30 52 37 60 M 67 36 72 38 77 42 86 46 9) St h %% $913 6319 67 7$
0 12 001 e 180 17 1150 $ 1l68 8 1192 6 1216 3 1739 9 1763 6 12874 113$ 2 1383 8 14 u ? 1483 4 1614 6 lbl6 6 1619 4 s 3121 - l7%8- 1 1833 18t58 8 8459 1 8743 1 9010 1920 1 9739 2 8177 2 0S8h 2 0969 2 1332 2 1616 2 200$
^
Sh 36 97 86 97 136 97 18697 2M 97 28697 386 97 48697 S86 97 68697 78697 886 97 98697 4 e 0 01673 26 290 837 29 899 31 939 33 % 3 35977 37986 41986 45918 49 964 63 946 67976 61 995 65 882 01303,,. A ' 888 21 11$0 9 "1 47 l192 6 1216 2 1239 9 12636 1287 3 133$ 2 13838 14332 1483 4 1534 6 1586 6 1639 4 s 0 3137 17%7 1 7809 1 8134 14437 8 8720 1 8988 1 9242 I til? 2 0!$$ 20%3 2 0946 2 1309 216$3 21982 78 Sh 22 04 72 04 122 04 172 04 222 04 272 04 372 04 47204 572 04 67204 772 04 87204 972 04 e 00483 20087 20788 22 3 % 23 900 25 428 26 946 28 e7 31 4 % 34 466 37 4t8 40447 41435 46 420 49 40$ O 27 96 n 39627 11% ) l!67 1 ingl e 1215 4 1239 2 1263 0 1286 9 1334 9 13835 14329 14832 !$34 J 1586 3 1639 3
$ 6 73$4 1 7320 17475 I 7805 I 8111 18397 1 86 % l 8921 1 9397 I 6836 2 0244 2 0628 2 0991 2 1336 2 6665 sh 9 93 $993 0993 16991 209 93 25993 359 93 45993 56993 65993 7 % 93 859 93 95993 25 e 00493 16 301 16 M8 17 829 9 076 20 301 21 S?? 22 740 25 lb) 27 % 7 29954 32 M6 34 740 37 130 39 Sie 040 071 h ?o8 62 116h !!666 !!90 2 214 5 1738 6 !?62 5 !?86 4 1334 6 1383 3 143? ? 14830 1634 2 1586 2 1639 2 1- 0 Jt3% i 1.41 1 2212 1 7547 . 78% ' i 814$ I 8415 1 8672 1 9149 8 9588 1 9997 2 0381 2 0744 21089 2 le18 56 4966 99 % 149 % 99 % 249 % 349 66 449 % 549 % 649 % 749 % Sa9 66 949 66 38 e 0 0170i l) 74 4 14 810 1$ 8$9 16 892 7 914 18 979 20 945 22 9$1 24 952 26 449 28 943 30 9M 32 977 0$0 341 a 218 93 11631 1889 0 !?!)6 1231 8 261 9 1286 0 1334 2 .13830 143? 6 1482 8 1634 0 1586 1 1U90 s 0 3e8? 169 % 1 7334 1 7647 17937 8210 18467 1 8946 19386 1 9795 2 0179 2 0543 2 0888 21217 C 3 pg,879, Sh e 0 01708 11 896 h 2?$ 03 !!67 I 40?! 90 71 140 71 190 ?! 240 71 340 11 440 71 54071 640 71 740 71 840 21 940 71 12 654 13 % 7 14 453 15 334 16 207 17939 19 M2 21 379 23 092 24 803 26 512 28 220 1187 8 !!!? 7 1237 1 1761 3 1285 5 1333 9 13828 1432 3 1882 7 1533 9 1646 0 1638 9 s 0 3809 1 6872 1 7152 1 7468 1 1761 1 8035 1 8294 1 4774 1 9214 1 9624 2 0009 20372 2 0717 2 1046
$n 32 7$ 8? ?S 132 75 182 75 232 7$ 33? ?5 43??S 532 75 632 75 732 25 832 75 932 75 48 e 0 01715 10497 Il0M 11 838 12 624 13398 14 n$ 16686 17195 18 699 20 199 21697 23 194 24 689 067 2$1 h 236 14 ;)69 8 1186 6 1211 7 1236 4 1260 8 12850 1333 6 1382 6 14321 143? $ 1533 7 168S 8 1638 8 s 0 3921 1 6765 8 6992 1 7312 17 08 1 7883 1 8143 8 8624 1 9065 1 4476 1 9860 2 0224 20%9 2 0899 45 Sh 2$ % 75 % 125 % Ph % 225 % 325 % 4& M S25 % 626 % . 725 % 825 % 926 56 07448) e 0 01721 9 399 9 777 LJ a97 16 261 1 89? 12677 13 932 16 276 16 614 17 950 19 252 20 613 21 943 h 243 49 1872 I lit $ 4 1210 4 1236 7 260 2 1284 6 1333 3 1382 3 1431 9 1882 3 1533 6 1$85 7 1638 7 s 0 4021 1 M71 1 6849 1 7173 4 7471 11748 8 8010 1 4492 l 8934 8 934$ 1 9730 2 0093 2 0439 2 0768 88 Sh - 18 98 68 98 118 98 168 98 ?!8 98 318 98 418 98 $18 98 618 98 718 98 818 98 918 98 08102) = 0 01727 8 614 8 769 9 424 30 062 10 688 18 306 17 629 13 741 14 947 16 150 17 350 18 649 19 746 h 250 ?! ll741 1184 1 1209 9 1234 9 12696 1284 1 1332 9 1382 0 1431 7 14422 I$33 4 158S 6 1638 6 8 0 4112 1 6586 16720 1 7048 I 7349 1 7628 1 7890 1 8374 1 8816 1 9227 1 9613 1 9977 2 0322 2 0652
>$ Sh 12 93 6293 Il2 91 %293 212 93 31293 412 93 512 93 612 9) 712 93 812 93 91293 1281 47' e 0 01733 7 945 8 546 913'J 9 702 IG 267 ti 381 12 48) 13 583 le 677 !$ 169 16 $$9 17 948 h 2$6 43 lis? 9 !?vt t 1234 2 1259 1 1283 6 13326 138) t 1411 b 1402 0 !$33 3 l$8$ 6 1638 6 s 0 4196 > El 1 6913 1 1237 1 7538 8 7781 1 82 % I 8710 t 9121 1tw? I 987 2 022 2 Oti 88 SR 7 29 $129 10729 157 29 20729 307 29 407 29 507 29 607 29 707 29 807 29 907 29 092 Fil e 0 01738 7 174 7 257 7 815 8 354 8 881 9 400 10425 al438 12446 13450 14 452 15 452 16 450 h 262 24 1877 6 11816 120P 0 1733 S 1758 5 1283 2 11323 1381 $ 1431 3 1481 8 15332 1685 3 1634 4 s 04273 1 6440 1 6492 1 6829 1 7134 1 7417 1 7681 1 8168 1 8612 1 9024 1 9410 1 9774 2 0120 2 04h0 Sh 2 02 52 02 10202 !$? 02 20202 302 02 40202 502 02 60202 702 02 802 02 902 02 si e 0 01743 6 653 6 676 7196 7 69? 4 186 8%7 9 615 10 % 2 11484 12 412 !) 337 14 261 IS I83 097981 h 267 63 11791 Il8a 3 12c7 g 1232 7 12579 1242 7 13319 1381 3 1431 1 1481 6 1533 0 1685 2 % 38 3 s 0 4344 16375 J 63%0 1 6736 3 1040 1 7324 1 M90 1 8077 88522 1 8936 3 932) 1 9685 2 0031 2 0361 Sh 47 07 9707 141 07 19707 297 07 39707 49707 59707 697 07 79707 89707 Il e 0 01748 6 20$ 66% 7 133 7590 8 039 8 922 9 793 10 6S9 11 522 17 382 13240 14 097 (302 938 h 272 74 trac t !?D6 0 1232 0 1257 3 1282 2 13316 1381 0 1430 9 1881 5 1532 9 1585 1 1638 2 s 04411 1634 1 % 40 169$1 1 7237 I M04 4 7993 1 8439 1 8852 1 9238 8 9603 1 9949 2 0279 Sh - 4? )9 9239 142 39 192 39 292 39 M2 39 492 h $97 39 69239 792 39 892 39 15 0 01713 6 834 6 204 664 7 074 7494 4 320 9 ;36 9 94) 10 750 lI %3 12 3 % 13 1 %
1307 616 ,e pF7 % 1181 9 1205 0 1231 2 12S6 7 !?B17 1331 3 1380 7 1430 7 1881 3 1632 7 !$8s 0 1638 i s 0 4474 4 6260 16%4 1 6868 1 71 % ! 7424 1 7915 18M1 1 8774 8 9161 1 9626 I 9872 2 0202 l
$h * $UDerhe81. I in = enthalpy Stu per ib v u Spe0!Ist volume. CU !! per lb 5 m efilt0py. Btu per R per Ib B-3
y- -l 1 Table 3. Superheated Steam-Continued ti n Sal . Sat . Temperature- Degrees f ahrenkeit . . o Set tem 0) water Steam 358 400 454 les 850 let 200 000 000 1000 1108 1788 - 1300 1400 Sh 37 % 87 96 137 % 187 % 237 % 287 % 387 % 48796 587 96 68796 787 96 887 96 N7 96 1087 96
- m. e 0 01757 5 471 5 801 6 218 6 622 7 018 7 408 7 794 8 %0 9319 to 075 to 829 11 Sol 12 331 13 081 13 829 0 12 041 h 282 Il 11831 1204 0 1230 5 1756 1 1281 3 1306 2 1330 9 1380 5 1430 5 let! 1 1532 6 15W 9 1638 0 1692 0 1744 8 s 04534 1 6208 1 6473 . I 6790 1 7000 1 7349 3 7602 1 7842 1 8289 1 8702 1 9089 L 9454 1 9000 2 0131 2 0446 2.0750 Sh 33 74 83 74 133 74 -!83 14 233 74 283 74 383 74 48374 M3 74 683 74 783 74 883 74 983 74 1043 74 88 01626) 'he 0 01762 5 167 5445 5 440 6 223 6 %7 6 %6 7 330 8 052 8 768 9 480 10 190 10 998 11 604 12.310 13 014 206 52 llM 2 1203 0 1229 7 12 % 5 1200 8 1305 8 1330 6 1380 2 1430 3 1441 0 15324 15M 7 1637 9 1691 9 !?46 8 i s 04590 1 6159 1 63 % 16716 1 7004 11279 13532 1 7772 1 8220 1 8634 1 9021 19386 19733 2.0063 2 0379 2.0682 l Sh 29 72 ' 79 72 129 72 17972 229 72 279 72 379 72 47972 579 72 679 72 779 72 879 72 979 72 1079 72 W' e 0 017 % 4 095 5 120 5 505 5069 6 223 6 572 , 6 917 7 600 8277 8 950 9 621 10 290 10 M8 11 625 12 290 020181 6 '. 290 69 1185 3 1202 0 1228 9 1254 9 !?80 3 1305 4 1330 2 1300 0 14Jo 1 1480 8 15323 15h 6 16378 1691 8 1746 7 s 0 4643 1 6113 1 6323 1 6646 I 6940 1 7212 11467 1 7707 8 81 % 18570 I4M7 8 9323 19H9 2.0000 2.0316 2d619 th 25 87 75 87 12587 ' l75 87 22587 275 87 37587 47587 57587 675 57 77587 875 67 975 87 107587 95 e 0 01770 4651 4 WS 5 205 S MI 50s9 6 221 6 548 7 196 7838 8477 9 113 9 747 10 380 !! 012 11643 024131 9 FM 70 1186 2 1200 9 1228 1 1254 3 1279 8 1305 0 13299 1379 7 1429 9 1480 6 15321 1584 5 1637 7 1691 7 1746 6 s 0 4694 56069 3 6253 1 6580 1 6876 I 7149 13404 1 7645 1 8094 1 85 &3 1 8897 I 9262 1 9609 1 9940 2 02 % 2 0559 Sh -- 22 18 22la 12218 172 18 222 18 272la ' 37218 47218 57210 672 II 172 18 872 II 972 18 1072 18 188 C27 821 ' h e 0 01774 - 4 431 4 590 4 935 52% 5 588 5 904 4 216 6 833 7443 8 050 86% 9 258 9 860 10 460 18 060 298 54 ^ lI47 2 1199 9 12274 1253 7 1279 3 13046 1329 6 1379 5 1429 7 1880 4 1532 0 1584 4 1637 6 1691 6 . !?46 5 s 04743 1 6027 1 6187 '1 6516 14414 1 7088 13344 1 7586 8 8036 I M51 1 8439 I 9205 1.M52 1.9083 2.0199 2 0502 Sh 1863 68 63 118 63 16863 218 63 268 63 . 368 63 468 63 M8 63 664 63 764 63 h443 968 63 1968 63 106 e 0 01778 4 231 4 359 4 690 5 007 5 315 5 617 5 915 6 504 7 086 7ES 8 241 8 816 9 339 9 El 10 532 G313h 68 302 24 1148 0 lite 8 ' 1226 6 1253 1 1278 8 13042 1329 2 1379 2 1829 4 1480 3 1531 I 1584 2 1637 5 lett 5 1746 4 04790 1.5988 1 6122 1 64 % 147% 1 7031 1 7288 1 7530 17MI 1 83 % 1 8785 1 9151 1 9498 1.9828 2 0145 2 0444 h 15 21 &$ 21 115 21 16521 215 21 26521 365 21 465 21 % 5 21 66521 76521 865 21 965 21 1065 21 110 03479) o 0 01782 4 048 4149 4 468 4 712 5 068 5 357 5642 6 205 6 761 7 314 7865 8 413 8 961 9507 10 053 h 305 80 1188 9 1197 7 1275 8 1252 5 1278 3 1303 8 1328 9 1379 0 1429 2 1480 1 1531 7 ISM i 16374 16 % 4 1746 4 l s 0 &&34 1 5950 a 6061 1 63 % 1 6698 16975 1 7233 1 7476 1 7928 8 8344 1 8732 1 9099 I 9446 19??? 2 0093 2 0J97 Sh ~ l1 92 61 92 11192 16192 211 92 26I 92 36I 92 46192 56I 92 El 92 76192 061 92 961 92 1961 92 115 e 0 01785 3081. 3 M7. 4 265 4 M8 4 841 5119 5 392 5 932 6 465 6 994 7 521 8 Os6 8 570 9 093 9 615 03408) h 309 25 1189 6 lit 6 7 1225 0 1251 8 1777 9 1303 3 1328 6 1378 7 1429 0 1476 9 1531 6 !$84 0 16p 2 1691 4 17463 s 0 4872 34913 1 6001 4 6340 i H44 16922 1 7131 1 7425 1 7871 1 8294 1 8682 1.9049 1.9396 19727 2 0044 2 0347 D 8 73 58 74 108 73 158 73 208 73 258 73 358 73 458 73 558 73 658 73 758 73 858 73 M4 73 1058 73 130 v 0 01789 3 ???5 3 7815 4 0786 . 4 3610 4 634: 4 9009 5 1637 5 6813 61928 6 7006 7 2060 7 7096 8 2119 8 7130 9 2134 0412h 6 312 54 1190 4 1195 6 1224 1 1251 2 12774 1302 9 13?8 2 1378 4 1428 8 14798 1531 4 1583 9 16371 1691 3 1746 2 s 0 4919 i 5879 15943 1 6286 1 6592 1 6872 1 7132 13376 1 7829 1 8246 I 8635 1 MCI 1.8349 1 9680 1.9996 2 0300 Sh 2 67 52 67 102 67 15267 202 67 25267 352 67 45267 552 67 652 67 75267 852 67 952 67 1052 67 830 e 0 01796 34%4- 3 4699 3 7489 4 0129 4 2672 4 5t51 4 7589 5 7384 5 7118 61814 6 6486 7 1140 75781 8 0411 8 5033 047331 h 318 95 1191 7 !!93 4 1222 5 1249 9 1276 4 1302 1 1327 5 1377 9 1428 4 14794 1531 1 1583 6 1636 9 1691 1 1746 1 s 04998 1 5813 15433 1 6182 14493 16775 1 7037 ! ?283 1 7737 1 81 % 1.8545 1.8911 1.9259 1.9591 1.9907 2 0211 Sh 46 % %% 14696 196 96 246 % M6 96 446 96 546 96 648 96 746 % B46 % M6 96 1046 96 lel = 0 01803 3 2190 3auI 3 7143 3 9526 4 1044 44119 4 8588 5.2995 6 7364 6 1709 6 6036 7 0349 7 4652 7 8946 0 53 041 h 324 96 8193 0 1220 8 1248 7 1275 4 1301 3 1326 8 1377 4 1478 0 14791 15308 1543 4 1636 7 1690 9 174 9 8 0 5071 1 5752 1 6085 1 6400 1 6686 86949 11196 11652 1 8071 1.8461 1 8828 1.9176 1.9500 1.9825 2 0129 9 4157- 9tSF 14857 191 57 24157 341 57 441 57 54157 641 57 741 57 841 57 W157 104 57 490 e 0 01809 3 0139 32208 34%5 3 6799 3 8928 41112 4 5294 4 9421 53507 57568 6 1612 6 % 42 49ul 7 3671 058431 h 330 65 1194 1 1219 1 12474 1274 3 1500 5 13?6 1 1376 9 14?? 6 1478 7 15305 1583 4 1636 5 1690 7 17457 s 0 5141 1 5695 1 5993 1 6313 1 6602 1 6867 17115 1 7573 1 7992 1 8383 .3 8751 1 9099 1.9431 19748 2 0052
.p 36 45 8645 136 45 186 45 236 45 336 45 436 45 53645 63645 736 45 536 45 93645 103645 180 e 0 01815 2 8336 3 00b0 3 ??pa 3 4413 3649 38480 4 2420 4 6295 5 0132 5 3945 6 7741 6 1522 6 5293 6 90 %
06355i 6 33607 1195 1 12174 1246 0 3273 3 1299 6 1325 4 1376 4 1427 2 14784 1530 3 . 1582 9 1636 3 1690 5 1745 6
- 8. 9 5706 2 % 41 1 5906 3 6231 16522 1 6790 1 7039 1 7499 1 7919 1 8310 1.8678 1 9027 899 i M76 1 9980 h 31 58 81 54 131 58 181 58 231 58 331 58 431 58 531 58 631 58 731 58 831 58 93158 1031 54 lie e 0 01821 2 6738 2 8162 3 0288 32306 3 42 % 3 6158 3 9879 4 3536 4 7155 5 0749 5 4325 5 7488 6 1440 6 4983 068421
- M124 1196 0 1215 6 1244 7 1272 2 1794 8 1947 1375 8 1426 8 14780 1530 0 1582 6 1636 1 169c 4 1745 4 s 0 52t>9 i 559) 1 5823 1 6152 1 6447 1 6717 16968 1 7428 1 7850 1 8241 1 8610 1 1959 1.9291 1 9608 1 9913 Sh 26 92 76 92 126 92 176 92 226 92 326 92 426 92 526 92 626 92 726 92 826 92 926 92 1026 92 180 e 0 018?? 2 5312 2 6474 2 8508 3 0433 3 2286 3 4093 3 7621 4 1084 4 4506 4 7907 5 1789 54657 5 8014 6 1363 0 73 081 h 34619 1896 9 1213 8 1743 4 127) 2 1297 9 1324 0 1375 3 1426 8 1477 7 1529 7 1582 4 16359 1690 2 !?in 3 s 0 5320 1 5543 IA743 1 6078 1 6376 I H47 1 6900 1 7362 17784 I 8176 1 4545 I 8894 I 9227 89545 1 9849 Sh 2247 72 47 12247 17247 22247 322 47 422 47 52247 622 47 72247 822 47 92247 1922 47 190 s 0 01833 24030 2 4961 2 6915 287% 3 0525 32246 3 % 01 3 8889 4 2140 4 5365 4 8572 5 17 % 54949 5 8124 0 77 531 h 350 94 8197 6 12l2 0 1242 0 1270 1 17971 132J 3 1374 8 1425 9 14774 15294 1582 1 1635 7 169; 0 17451 s 0DM i 5498 i M67 1 6006 86307 1.658) 1 6835 1 7299 1 7722 13115 1 8484 1 8&34 1.9166 1HH I 9749
> 1820 6820 118 70 168 20 21820 318 70 418 20 518 20 618 20 718 20 818 20 918 20 1018 20 se e 0 Ol139 2 2873 2328 2 5480 2 7247 2 8939 3 0583 3 3743 36915 4 0008 4 3077 4 6128 4 9165 5 7191 5 5209 001 801 6 3 % 51 1198 3 1210 1 1240 6 1769 0 1796 2 1122 6 1374 3 1825 5 le 77 0 1529 l 1581 9 1635 4 1689 8 17450 8 ( 5431 1 5454 1 5593 1 5938 I 6242 1 6518 1 6773 1 7239 17%) 1 8057 i H26 1 8776 1 9109 1 9427 8 9732 Sh = superhest. I y = specific volume. CU ft per Ib h - enthalpy, Btu per Ib
$ = entropy. Blu per F per Ib Jl, '
1 i l B-4
Yable 3. Superheated Steam-Continued fb\5 S8t 5 81 I'*D"atwe- Degree 5 f ahrenheit (Sat lemot VWer Steam 488 450 500 550 666 390 800 988 1940 1100 1280 1350 1480 1580 Sh 18 09 64 09 !!4 09 19 09 214 09 314 09 414 09 514 09 614 09 714 09 814 09 914 09 1014 09 1114 09 719 e 0 01844 21822 22%4 2 4181 2 5880 2 7504 2 9078 32137 3 5128 3 8080 4 4007 4 3915 4 6811 4 9695 5 2571 5 % 40 (385 911 h 359 91 !!99 0 1208 07 1239 2 1268 0 1295 3 1321 9 - 1373 7 14?5 1 1476 7 1528 8 1581 6 1635 2 1689 6 1744 8 1800 8 9 0 5490 1 5413 1 5522 1 5872 1 6180 i H58 16715 1 7182 1 7607 1 8001 18371 1 8721 1 9054 1 9372 1 % 77 8 9970 Sh 10 12 6012 11012 160 12 210 12 31012 410 12 51012 610 12 710 12 810 12 910 12 101012 !!!0 12 278 e 0 01850 2 0863 f t?40 2 2999 2 4638 26199 2 7710 3 0642 3 3504 3 6327 3 9125 4 1905 4 4671 4 7426 5 0173 5 2913 (389 881 h % 417 1199 6 - 1206 3 1237 8 !?M 9 1794 5 1321 2 1373 2 14i4 7 1476 3 1528 5 1581 4 1635 0 1689 4 1744 7 1800 6 s' 0 5540 .1 5374 1 5453 . 1 5808 1 6120 1 6400 ! %58 1 7128 1 7553 1 7948 1 8318 laul 1 9002 1 9320 1 9625 1 9919 Sh 6 30 % 30 106 30 1 % 30 206 30 306 30 406 30 506 30 406 30 706 30 806 30 906 30 1006 30 1106 30 218 e 0 018 % 1 9985 2 0212 2 1919 23503 2 5006 2 6461 2 9276 3 2020 34726 3 7406 4 0068 4 2717 4 53 % 4 7984 5 0606 (393 706 h 368 28 1200 1 I?os 4 1236 3 12 % 7 !?93 6 1320 4 1372 7 1424 2 1476 0 1528 2 1581 1 1634 8 1689 3 1744 5 Isoc 5 5 06%8 1 5336 1 5385 15747 1 6062 16344 1 Mod I 7075 1 7502 1 7897 1 8268 1 8618 8 8952 1 9270 1 9576 I 9869 Sh 261 52 61 102 61 152 61 202 61 302 61 40261 502 61 602 61 70261 802 61 902 61 1902 61 !!02 61 P48 e 0 01860 1 9177 1 9?68 2 0928 2 2462 2 3915 2 5316 2 8024 30%1 3 3259 3 5831 3 8385 4 0926 4 34 % 4 5977 4 8492 (39739) # 37227 1200 6 1202 4- 1734 9 1764 6 !?92 7 1319 7 1372 1 1423 8 14756 1527 9 1580 9 1634 6 1689 I i744 3 1800 a s 0 % 34 1 5299 i 5320 1 % 87 1 6006 1 6291 1 6552 1 7025 1 7452 1 7848 ! $219 1 8570 1 8904 1 9223 1 9528 1 9822 Sh 49 03 99 03 149 03 199 03 799 03 39903 499 03 599 03 699 03 799 03 899 03 999 03 1099 03 298 e 0 01865 1 8432 2 0016 21504 2 2909 2 4262 2 6872 2 9410 31909 34382 3 6837 3 9278 4 1709 4 4131 4 6546 N00 97) n 376 14 1701 1 1733 4 1263 5 !?91 8 1319 0 1371 6 1423 4 1475 3 1527 6 1580 6 16344 1688 9 1744 2 1800 2 s 0M79 3 5264 1 % 29 1 5951 1 6239 16502 16976 1 7405 1 7801 1 8173 1 8524 I 8858 1 9177 8 9482 1 9776 Sh 4556 95 % 145 % 195 56 295 % 395 56 49556 595 % 695 56 70 56 895 56 995 % 1095 % 288 e 0 01870 1 7742 I 9173 2 0619 2 1981 2 3289 2 5808 28256 30%' 3 3044 3 5408 3 7758 4 0097 4 2427 4 4750 N04 44) # 379 90 1201 5 1231 9 1262 4 1290 9 1318 2 1371 1 1423 0 147# !!273 1580 4 1634 2 1688 7 1744 0 18001 s 0 5722 1 5230 1 5573 1 5899 1 6189 3 6453 1 6930 1 7359 1 71 18128 1 8440 1 8814 1 9133 1 9439 1 9732 Sh 42 20 9220 14220 192 20 292 20 H2 20 49220 592 20 69220 792 20 892 20 992 20 1092 20 278 e 0 01875 1 7101 1 8391 1 9799 2 1121 2 2388 24824 2 7186 2 9509 3 1806 34084 3 6349 3 8603 4 0849 4 3087 H07 80) h 383 56 1201 9 1230 4 1261 2 1290 0 1317 5 13 to 5 1422 6 1474 6 1527 1 1580 1 1634 0 16ss 5 1743 9 1800 0 s 0 6764 15197 1 5518 1 5848 1 6140 1 6406 11885 1 1315 1 7713 1 8085 1 8437 18771 1 9090 1 9396 1 9690 la 38 91 88 93 138 93 18893 288 93 388 93 48893 588 93 68893 788 93 88893 988 93 1088 93 348 e 0 01880 16505 17%5 1 9037 2 0322 21%I 2 3909 2 6194 2 8437 3 0656 328 % 3 5042 3 7217 3 9384 4 1543 C Wil 071 6 38712 1202 3 s 0 H05 1.51 % 1228 8 1260 0 1289 1 1316 8 1370 0 1422 I le74 2 1526 8 1579 9 1633 8 1688 4 1743 7 1799 8 1 5464 1 5798 1 6093 16361 1 6841 1 7273 1 7671 1 4043 1A395 1 8730 1 9050 1 93 % 8 % 49 Sh 35 75 8575 135 75 185 75 285 75 385 75 485 75 585 75 68575 785 ?S 985 75 985 75 1085 75 298 e 0 01885 15948 1 6988 1 8327 1 9578 2 0772 2 3058 25269 2 7440 29585 3 1711 3 3824 3 59?6 3 8019 4 0106 H14 251 h 390 60 1202 6 1227 3 1258 9 1288 1 1316 0 1369 5 1421 7 1473 9 15?6 5 1579 6 1633 5 1688 2 1743 6 1799 7 s 0 5844 1 5135 1 5412 1 5750 1 6048 1 6317 16799 1 7232 1 7630 1 8003 1 8356 1 8690 1 9010 1 9316 1 9610 Sh 3265 8265 13265 18265 28265 38? 65 48265 582 65 68265 18265 482 65 982 65 1082 65 388 e 0 01889 1 5427 163 % 17%5 1 8883 2 0044 22763 2 4407 26509 2 8585 30643 3 7688 34721 3 6746 3 8764 HIFJS1 h 393 99 1202 9 1225 7 1757 7 12872 1315 2 1368 9 1421 3 14736 1526 2 1579 4 1633 3 1688 0 1743 4 17996 s 0 5882 13105 1 5351 1 5703 1 6003 1 6274 I 6758 1.7192 1 7591 17%4 3 83)7 1 8652 1 8912 1 9278 1 9572 th 29 64 79 64 129 64 179 64 279 64 379 64 479 64 579 64 679 64 779 64 879 64 979 64 1079 64 818 e 0 01894 14939 3 5763 1 7044 I 8233 1 9363 2 1520 2 3600 2 % 38 2 7650 2 9644 31625 3 3594 3%% 3 7509 4420 361 6 39730 1203 2 1224 1 12 % 5 1286 3 1314 5 1368 4 1420 9 14732 1525 9 1579 2 1633 1 1687 8 1743 3 17994 s 05920 1 5076 i A311 1 % 57 1 5960 1 6233 1 6719 11153 17%3 1 7927 1 4280 1 8615 1 8935 I 924l 1 9536 Sh 26 69 76 69 126 69 .76 69 276 69 37669 476 69 576 69 676 69 776 69 476 69 976 69 1076 69 328 e 6 01899 1 4480 15207 1 6462 1 7623 8725 2 0823 22843 24821 2 6?74 2 8708 3 0628 3 2538 3 4438 3 6332 M23Jll n 400 53 120J 4 1222 5 12 % 2 1785 3: .313 7 IHf8 1420 5 1472 9 1525 6 1578 9 1632 9 1687 6 1743 1 17993 s 0 5956 14048 14261 13612 1 5918 li l192 1 6680 17136 1 7516 11890 13243 1 8579 1 8899 1 9206 1 9500 Sh 2382 73 82 .2382 173 82 273 82 373 82 47382 573 82 673 82 77392 47382 973 82 1073 82 388 e 0 02903 1 4048 1 4684 1 5915 7050 1 8125 20168 22132 2 4054 2 5950 2 7828 2 9692 3 1545 3 3389 3 5227 (426 181 4 40370 1203 6 1220 9 1254 0 2844 13130 th7J 14?0 0 1472 5 1525 3 1578 7 1632 7 1687 5 1742 9 17992 s 0 5991 150?! . 1A213 15%8 .5876 1 6153 1 E43 1 7079 1 7480 178% 1 8208 8 8544 1 8864 1 9171 1.94 % Sh 21 01 71 01 121 01 71 01 27101 371 01 47101 571 01 67101 771 01 871 01 971 01 1071 01 M8 e 0 01908 13640 1 4191 1 5399 1 6511 . 7%I 19%2 21463 23333 2 5175 2 7000 2 8811 3 0611 32402 3 4186 1429 991 4 406 to 1203 8 312 2 13 % 7 1419 6 14722 1525 0 1578 4 1632 5 1687 3 !?42 8 17990 4 0 6026 14994 1219 125i25 151H !?S28 12834 ..6114 1 5836 1 % 06 11044 11445 11820 13174 1.8510 1 8831 1 9138 1 9432 sh 1827 6&27 11827 16827 26817 368 27 % 8 27 % 8 27 ut 27 768 27 868 27 968 27 1068 27 388 e 0 01912 1 32 % 3 3725 1 4913 16m? I 7028 IWO 2 0832 2 2652 24445 2 6219 2 7980 2 9730 3 1471 3 3205 6434 731 6 409 83 1204 0 1717 5 1251 5 1282 4 1211 4 3h62 1419 2 14718 1524 7 1578 2 16323 1687 1 1742 6 1798 9 s 0 6059 14968 1 3I19 l b483 1 5797 14017 1 6571 1 7009 1 7411 11787 1.8141 1 8477 1J 798 1 9105 1 9400 Sh 15 59 65 59 15H 165 59 265 % 365 59 46559 M5 59 66559 765 59 86559 965 59 1065 59 888 e 0 01917 1 2991 13285 14454 ' 5571 i6525 1 8421 2 0237 22009 237% 2 5482 2 71 % 2 8898 3 0592 3 2279 N34 41) h 412 si 1204 1 1215 8 1250 3 191 5 .310 6 1365 6 le18 7 14715 1524 4 15779 1632 1 1686 9 1742 5 11988 4 0 6092 14943 15073 1 544I . 3 754 .6040 3 6536 16976 1 7379 1 7754 1 4109 1 8445 1 4766 1 9073 19h8
$h 10 39 60 39 110 39 160 39 260 39 360 39 460 39 % 0 39 % 0 39 760 39 860 39 % 0 39 1060 39 388 e 0 01575 1 2718 1 7472 1 3606 1 4635 15%8 1 7410 1 9139 2 0825 21484 24124 25750 2 7366 2 8973 3 0572 44)961# A 418 % 1204 4 1212 4 1247 7 1279 5 1309 0 1364 5 14179 1470 $ ?523 8 1577 4 1631 6 M86 5 1742 2 17985 s 0 61 % 14894 14982 15360 1 M83 1 5969 16470 1 6911 1 7315 1 7692 1 8047 1 8384 13705 1 9012 1 9307 f Sh = Superheat.F v = 5pecific volurne, cu ft per Ib li - enth8tpy. Btu per Ib 5 = entr0py. Btu per R per ib B-5
i' ~ { [4 1 I 1 1 l ll
)
Table 3. Superheated Steam-Continuest i b/$ in $at $at hmwawMWs F8MM ($al lemo) twater $ team 458 500 $50 000 050 200 000 900 lets 1100 1200 1300 1400 1900 5h 540 5540 '0540 15540 20540 75540 3 % 40 4 % 40 5 % 40 . 65540 75540 8 % 40 9 % 40 1055 40 l det e 0 01934 11610 1 1738 1 2841 34 % 14763 1 % 46 1 6499 1 815) 19759 2 1339 2 2908 24450 21987 2 7515 2 9037 4444 601 h 424 17 1204 6 !?o88 1745 1 2775 13074 1335 9 1363 4 1417 0 14701 1523 3 157r 9 1631 2 1696 2 1741 9 1798 2 s 0 6217 IAN7 14894 1 5282 5611 1 5901 1 6163 1 6406 1 6850 1 7255 3 7632 1 7984 I 8325 1SM7 1 8955 I 9250 W Sh $ 60 50 60 10060 150 60 200 60 250 60 350 60 450 60 550 60 650 60 750 60 850 60 950 60 1050 60 438 e 0 01942 11057 11071 1 2148 13113 14007 1 48 % 1 % 76 17?t8 1 8795 20304 2 1795 2 3273 24739 2 6196 2 7647 6449 40) h 429 56 1204 7 1705 2 1242 4 1775 4 13058 1334 5 1362 3 1416 2 1869 4 1522 7 1576 4 1630 8 1685 8 174I 6 1798 0 8 0 6276 14802 14804 1 $206 15542 1 5435 1 6100 16345 16791 1 7197 1 7575 1 7932 1 8269 1 8591 1 8899 I 9!95 Sh 4597 9597 145 97 9597 24597 34597 44597 54597 64597 74597 84597 945 97 1045 97 448 e 0 01950 1 0554 11517 1 7454 1 3319 4138 14926 1 6445 1 7918 19363 20790 21203 2 % 05 24998 2 6384 8854 03) h 43477 !?D4 8 1239 7 1273 4 1304 2 333 2 1361 1 1415 3 1468 7 ~ 152? ! 1575 9 16304 1685 5 1741 2 1797 7 s 0 6337 14759 1 5132 1 5474 15772 ;6040 1 6286 8 6734 1 7142 1 7528 1 7878 1 8216 38538 1SM7 8 9143 Sh 41 50 9150 i41 50 191 50 241 50 341 50 44150 54150 641 50 741 50 MI 50 941 50 1041 50 4 488 e 0 01959 ' 1 009? 1 0939 l 1852 4458 501 Peti 1 3442 1 424? 15703 1 7117 1 8504 1 9872 2 17?6 2 2569 2 3903 2 5230 ' h 439 J3 1204 8 1236 9 1271 3 .302 5 1331 8 1360 0 14 44 1468 0 1521 5 1575 4 1679 9 1685 1 1740 9 17974 s 06387 14718 1 5060 1 5409 .3711 1 598? I 6230 16MC 1 7089 1 7469 1 7826 1 8165 1 8488 88797 1 9093
$h 37 18 8718 137 18 8718 23718 33718 437 le 53718 63718 73718 837 18 937I? 1037 18 488 e 0 01967 09E8 1 0409 11300 1 2115 2881 1 %IS 1 5023 16384 1 7716 1 9030 2 0330 2 1619 !?90b 2 4173 4462 821 h 444 75 1204 8 12M I 1269 1 1300 0 330 5 1358 8 le13 6 14673 1520 9 1574 9 1629 5 1684 7 1740 6 17972 s 0 6439 4 4677 ' i 4990 1 5346 15652 .5925 1 6176 1 6628 1 7038 1 7419 8 7777 1 8116 8 8439 18148 I 9045
$h 32 99 87 99 132 99 42 99 232 99 332 99 43299 532 99 632 99 732 99 832 99 932 99 1037 99 488 e 0 01975 0 9276 0 9919 1079) 11584 2327 13037 14397 1 5708 16992 1 82 % 1 9507 2 0746 2 1977 2 3200 6447.01) h 449 52 1204 7 12312 1267 0 1799 1 329 1 1357 7 1412 7 1466 6 ISto 3 1574 4 1629 l 1684 4 1740 3 17% 9 s 0 6490 14639 I 4921 1 5284 1 5595 5873 1 6123 1 6578 1 6990 11371 1 7730 1 8069 ) 8393 18702 3 8998 Sh 2893 78 93 128 93 7893 22893 328 93 42893 57893 628 93 72893 8?8 93 928 93 1028 93 178 e 0 01982 0 8914 0 94 % 1 0321 1 1994 1816 1 2504 1 3819 I 5c85 16323 i M42 1 8746 I 9940 2 1125 2 2302 4471 071 h 45418 1204 5 1228 3 1764 8 12974 327 7 1356 5 1411 8 14659 1519 7 1573 9 16?8 7 1684 0 1140 0 17 % 7 s 06540 14601 1 4853 1 5223 1 5539 5818 1 6072 1 6530 16943 1 7325 3 M84 ' 51024 1 8348 1 8657 1 8954 Sh 24 99 74 99 24 99 174 99 ??4 99 324 99 424 99 524 99 624 99 ??4 99 824 99 924 99 1024 99 948 e 8 01990 0 8577 0 9045 0 9884 0640 11342 1 2010 1 3264 14508 1 5704 1 6880 1 8042 1 9193 2 0336 ? !471 4475 Oli n 458 71 1204 4 1225 3 1262 5 295 7 1326 3 13 % 3 1410 9 1865 l 1519 i !$73 4 1628 2 1643 6 1739 7 17964 s 0 6587 14%5 1 4786 1 5164 5485 15767 16023 1 6483 1 6897 1 7280 11640 11981 1.8!05 1 8615 1 8911 Sh 21 16 7116 12116 L7116 221 16 371 16 42316 52116 671 16 72116 821 16 921 16 1021 16 888 e 0 01998 0 8764 0 8653 0 9479 10?!? 0902 11%? 11787 13972 5 5129 1 6266 1 7338 1 8500 1 9603 2 0699 4478 MI h 463 14 - 1204 2 122? ? 1260 3 1293 9 324 9 1354 2 14100 1464 4 1518 6 1572 9 1677 8 1883 3 1739 4 !?% )
s 0 H34 14529 34720 1 5106 1 5431 5717 I 5975 1 6438 1 6853 1 7237 1 M98 11939 1 8263 1 8573 1 8870
$h 1743 4743 11743 16743 21749 31743 41743 51743 61743 71743 81743 91743 101743 SOS e 0 07006 0 7971 0 8?87 0 9100 0 98?4 1 0492 1 8125 12324 1 3473 1 4593 1 5693 16780 1 78 % 18f121 1 9980 4442 571 h 46747 1703 9 1219 1 1258 0 1792 1 1323 4 1353 0 1409 2 1463 7 1518 0 15724 1627 4 1682 9 1739 1 1795 9 s 0 M79 14495 14654 1 5049 45380 1 5668 15929 i 6394 1 6811 1 71 % !4% 1 7898 I 8223 3 8533 1 8831 Sh 13 80 6380 113 80 163 80 213 80 31380 413 80 51380 613 80 713 80 813 80 913 80 1013 80 an e 0 02013 0 7697 0 7944 08746 0 94 % 1 0109 1 0726 1 1892 1 3004 1 4093 15160 1 6211 1 7252 1 8284 1 9309 (486 201 h a?! 70 1203 7 1215 9 !?% 6 !?90 3 1322 0 135) 8 1408 3 1463 0 1517 4 1571 9 16?? O 1682 6 1738 8 17956 s 06723 14468 14%0 1 4993 15329 I M?! 15884 1 6351 16769 1 7155 1 417 11859 1 8164 1 8494 1 8792
$m 511 55 11 10511 15511 205 11 305 11 40511 50511 60511 705 11 80511 90511 1005 11 me e 0 02032 0 7084 0 7173 0 7954 0 86M 0 9 ?54 0 98M i 0929 11969 11979 33%9 84944 1 5909 I 6864 1 7813 1494 891 h 481 89 !?02 8 1207 6 1749 6 1785 7 1318 3 1348 7 1406 0 1461 2 1515 9 1570 7 1625 9 1681 6 1738 0 1794 9 s 1 6428 14381 1 4430 14858 1 5207 35507 1 5775 1 6249 i M11 11059 1 7422 11765 1 8092 1 8403 1 8701 56 46 92 M 92 146 92 1 % 92 296 92 3 % 92 496 92 5 % 92 49692 796 92 896 92 996 92 188 e 0 0?O50 0 65 % 0 7271 0 7928 0 8520 0 9072 1 0102 11078 11073 11948 13858 14757 1 %47 1 6530 1 6 03 086 h 491 60 1201 8 1243 4 1281 0 1314 6 iM56 1403 7 1459 4 1514 4 1569 4 1624 8 1680 7 17372 1794 3 !
s 0 6928 14304 14726 1 5090 1 5399 I M73 1 6154 16540 1 6970 1.1335 1 7679 1 8006 1 8318 1 8617 Sh 2916 8916 139 16 18916 289 16 389 16 489 16 54916 68916 789 16 889 36 999 16 118 e 0 02069 0 6095 Our6 0 7313 0 7882 0 8409 0 93s6 1 0306 1.1195 1 2063 11916 1 3759 14592 1 5419 610 H1 h 500 69 1200 1 1236 9 1276 1 1310 7 IM25 1401 5 14576 1512 9 1%82 1623 4 1679 8 1736 4 17936 s 0 7022 3 4232 34M8 3 4977 1 5296 15577 1 6065 1 6494 1 6886 1 7252 1 M98 1 7926 3 82J9 1 8538 Sh 31 79 81 79 131 79 181 79 281 79 381 79 481 79 581 79 681 79 781 79 all79 981 79 8e e 0 0?o87 0 5690 0 6151 0 6774 0 7323 0 74?8 08759 0 % 31 1 0470 1 1289 12093 12885 13M9 1 4446 6 18213 h 509 81 1199 4 1230 1 12?l i 1306 8 1339 3 1399 1 14 % 8 1511 4 1%69 1672 7 1678 9 1735 7 !?92 9 s 0 Till ! 4163 1 4472 34869 14198 3 5444 85980 1 6413 3 6807 IJin 3 7522 1 7851 1 8164 1 8464 Sh 24 76 74 76 124 76 174 76 274 76 374 76 474 76 574 76 674 76 774 76 874 76 974 76 38 e 0 02105 0 5330 0 % 83 0 6296 0 68?9 0 7315 0 $?os 0 90M 0 9830 1 0606 1 1366 1 2115 1 28 % 1 3588 6 25 241 h Sl4 40 lits 0 1223 0 126') 9 1302 8 13 % 0 13 % 8 1454 0 1510 0 1%57 1621 6 1678 0 1734 9 17923 s 0 7197 14096 84M7 14763 1.5102 15J96 IS899 1 6336 14733 1 7102 11450 11780 1 8094 1 4395 th 18 05 68 05 11805 168 05 268 05 368 05 468 05 % 8 05 M8 05 768 05 868 05 968 05 MB e 0 02123 0 5009 0 5263 0 5869 0 6388 0 6858 0 7713 0 8504 09262 0 9998 1 0720 1 1430 1 2131 1 2825 6 31 953 h 526 70 1196 4 1215 5 !?60 6 1298 6 1332 7 1394 4 1452 2 1508 5 1%44 1620 6 14773 17M I 17916 4 0 7279 1 4032 34223 1409 1 5010 1 5311 1 5422 4 6263 16E2 1 7033 1 7382 11713 3 8028 1 4329 Sh = superhe8t,F h = enth81py. Btu per le v = specific volume, tu ft per Ib 5 = entropy. Etu per F per Ib B-6
I l Table 3. Superheated Slesm-Conti7 ued Abn Press tbl50 in Sal I'*P4'4e - De8 vee 5 I onecaheit 541 480 all get 1960 1108 1200 1300 1800 1586 (581 tem 0) noter. Steam 150 See $50 200 258 Sh 18 61 61 63 11181 181 61 211 61 261 6) 311 6) 363 61 46161 % 1 61 % 1 61 761 61 86161 961 61 58 e 0 02141 04721 0488J 0 5485 0 5993 06449 0 6871 0 1272 0 76 % 08030 0 8753 0 94 % 1 0142 1 08)? 1 1484 1 7143 (538 391 h 534 74 1194 7 1207 6 12M I 1794 4 1329 3 1361 5 13920 1421 5 1450 3 % 07 0 1%32 1619 5 1676 2 1733 3 17910 s 0 7358 13970 14098 14557 1 4921 1 5228 15500 1 5748 1 5977 1 6193 1 6595 16%7 1 7317 1 7649 IFMS 1 8267 p 542 % 42 10542 1 % 42 20542 255 42 305 42 3 % 42 4 % 42 5 % 42 65542 7% d2 8M 42 9942 1850 v 9 02159 0 4460 045% 0 5137 . 0 %M 06080 0 6489 0 6875 0 7245 0 7603 0 8295 08%6 0%22 1 0266 1 0901 1 1529 6 44 581 h 54 2 % lit? 9 1199 3 17493 1790 1 1325 9 1358 7 IJe9 6 1439 4 1448 5 1505 4 1%I9 16184 1675 3 1732 5 1790 3 s 0 7434 1 3910 1 3973 1 4457 14833 15149 L 5426 1 % 77 1 5908 1 6126 1 6530 1 6905 1 72 % 1 7509 1 7905 I 8207
$h 4947 9947 14947 199 47 249 47 299 47 34947 44947 549 47 64947 749 47 M947 94947 150 v 0 02177 0 4222 04871 0 5311 05145 0 6142 0 6515 0 6877 0 7216 0 7881 0 8524 0 9151 09767 10373 1 0973 t%053) * # 550 15 1198 0 1243 4 1285 i 3322 4 13 % 8 1387 2 1417 3 1446 6 1503 9 1%07 1617 4 1674 4 1731 8 17896 s 0 7507 1 3851 14358 14748 1 5072 1 5354 1 % 08 1 5842 1 6062 3 6469 1 6045 1 7197 1 7531 1 7848 1 8151 D 43 ?? 93 72 14372 19372 243 72 29372 34372 44372 54372 64372 74372 M172 943 72 ties . e 0 02195 0 4006 04531 0 5017 0 5440 O t826 0 6188 0 6533 0 6465 0 7505 0 412) 0 8723 0 9313 0 9094 1 0468 (5% 28) # $57 $5 1189 1 1737 3 1283 2 1318 8 13529 1384 7 1415 2 1444 7 1502 4 IM94 1616 3 1673 5 1731 0 1789 0 s 0 7578 1 3794 1 4259 14%4 14996 1 5284 1 % 42 15179 1 6000 1 6410 1 6787 1 7141 1 7475 17793 1 8097 Sh 39l4 $918 139 18 18918 239 18 29918 339 18 43918 53918 639 18 739 18 63918 939 t4 1138 e 0 02234 0 3807 0 4263 04746 . 0 5162 0 % 38 0 5589 0 6223 0 6544 0 7161 0 7754 0 8332 0 8099 0 94 % 1 0007 6 61 821 h 56478 ll87 0 1230 9 1276 6 1315 2 1349 9 1382 2 14130 1442 8 1500 9 1%81 1615 2 16726 1730 2 17883 s 0 7647 13738 1 4360 14542 14923 1 5216 1 5478 3 5717 35941 1 6353 16732 1 7087 1 7422 1 7741 1 8045 i
Sh 32 81 82 II 13241 182Il 232Il 282Il 332 41 432 81 532 81 632 41 732 81 632 81 932 81 ! 13ee v 0 02232 0 3624 04016 04497 04905 0 5273 0 %I5 0 5939 0 6250 06845 0 7410 0 7974 0 8519 0 90 % 0 9584 1 % 7 19) h $7185 1144 8 I??4 ? 12718 ! Jill 1346 8 1379 7 14:08 1440 9 1499 4 15 % 9 1614 2 1671 6 1729 4 17876 s 0 7734 1 3643 1 4061 14501 14851 1 5150 1 54 % 1 % 58 1 5883 1 6298 1 % 79 1 7035 1 7371 1 7691 1 79 %
$h 22 58 72 58 122 58 I??l8 222 58 27258 322 58 477 58 522 58 ' 6?? $8 722 54 822 58 822 58 13ee v 0 02269 0 3299 0 3570 04052 0 4451 04404 0 5129 0 5436 0 5729 0 6287 06422 0 7341 0 7847 0 8345 0 8436 (577 421 h 585 58 1180 2 1209 9 !?61 9 1303 9 1340 $ 1374 6 1406 4 14371 1496 3 1%43 1612 0 1669 4 1727 9 1786 3 s 0 1843 13572 1 3860 14340 14711 1 5022 1 5296 I D44 1 5773 1 6194 1 6578 1 6937 1 7275 1 75 % 1 7902 h 129? 62 53 112 93 162 93 212 93 262 93 31293 412 93 51293 512 93 71293 81293 912 93 14e8 e 0 02307 0 3018 0 3174 L 3667 0 8050 0 4400 04712 0 5004 0 5282 0 5809 06313 06798 0 7272 0 7737 0 8r 95 (587 07) n 59883 1175 3 11% ' 1751 4 12 % i 1334 5 1369 3 14020 14332 1493 2 1%)8 1609 9 IMS0 1726 3 . 1785 0 6 0 79 % 1 3474 1 3652 14181 14575 14900 1 5182 1.5436 1 % 70 1 6096 iM84 16845 11185 1 7508 1 7415 Sh 3 80 53 to 10380 15380 203 60 253 80 303 80 403 80 503 80 603 to 703 80 803 80 903 80 1648 e 0 02346 0 2772 02820 0 3328 0 3717 04049 04350 0 4629 04894 0 5394 0 5869 06327 0e773 0 7220 0 7639 (596 201 h 61168 1170 1 1176 3 1240 2 17879 1328 0 1364 0 13974 )429 2 1490 1 15492 1607 7 1666 2 1724 8 178) 7 s 0 8085 1 3373 1 3431 14022 3 4443 14782 1 5043 1 6333 1 % 72 1 6004 1 6495 1 6759 1 7101 1 7425 1 7734 9 4513 9513 14513 195 13 24513 29513 39513 49513 595 13 69513 795 13 895 13 itse e 0 02387 02%5 0 3026 0 3415 0 3741 04032 04301 045% 0 5031 0 5482 0 5915 0 63M 06748 0 7153 (60484 h 62420 1164 5 !?28 3 12794 1321 4 1358 5 1392 8 14252 1486 9 !$46 6 16056 1%43 !?23 2 1782 3 s 0 8199 1 3274 1.3861 14312 3 4667 14968 1 5235 1 5478 15916 16312 1 6678 1 7022 1 7347 17657
$h 36 87 86 87 13687 186 87 236 87 286 87 386 87 486 87 586 87 68687 786 87 886 87
- 0 02428 02M1 0 2754 03147 0 3468 0 3751 04011 04?% 04711 0 5140 0 % 52 0 5951 0 6)41 06724 1100 1215 3 1270 5 1314 5 1352 8 1388 1 1423 2 1483 8 1544 0 1603 4 1662 5 172; 7 1781 0 1613 131 h 636 45 !!58 6 s 0 8309 1 3176 1 3697 1 4I83 145 % 14067 3 5140 1 5388 15833' 1 6232 i Hol I 6947 1 7274 1 7585 Sh 2898 78 98 12898 178 98 228 98 278 98 378 98 470 98 571 98 678 98 178 98 87898 less e 0 02477 0 2186 0 7505 0 2906 0 3223 0 3500 0 3752 0 3988 0 4426 048 % 0 5229 0 5609 0 5980 0 6343 (621 021 h H849 1152 3 1701 2 1261 1 13074 13472 1383 3 14371 1880 6 1541 4 1601 2 1%07 1720 1 ' 1779 7 s 0 8417 1 3079 6 3526 14054 1 4446 147% 15049 I 5302 15753 1 61 % 1 6528 1 6876 1 7204 1 7516 Sh 21 44 71 de 121 44 !?! 44 221 44 271 44 371 44 47144 571 44 67144 77144 87144 19ee e 0 0?517 0 20?8 0 2274 02687 0 3004 0 3275 0 3521 0 3749 04171 04%5 04940 0 5303 0%% 0 600?
n28 %) 6 %C% lie 6 !!85 7 1251 3 1300 ? 13414 13784 14 :29 14774 153e 8 1599 1 1658 I 1718 6 1778 4 1 0 Bb22 12981 13346 l 3925 1 4338 I 4672 14960 1 5219 1 % 77 1 6084 4 6458 3 6808 1 2138 1 7451 D 14 20 6420 114 20 164 20 214 20 264 20 364 20 464 20 % 4 20 E4 20 764 20 864 20 300e e 00?%5 0 1883 020% 0 2488 02805 0 3072 0 3312 0394 0 3942 04320 04680 0 5027 05365 0 % 95 1635 80t ti 672 11 1138 3 1168 3 1240 9 1292 6 13M 4 6373 5 14087 1474 1 1536 2 15 % 9 16570 1717 0 177l l 6 0 8625 1 2881 1 3154 13794 1 4231 14578 14874 1 5138 1 5603 1 6014 1 6391 16743 1 7075 1 1389 Sh ? ?4 5? ?4 10724 157 24 207 24 257 24 35? ?4 45724 55724 657 24 75724 857 24 2108 e 0 0?615 01750 01847 0 2304 C 2624 02888 0 3!23 0 3339 03734 04099 04445 04770 0 5101 0 5418 t642 76) n 68379 1130 5 1148 5 !??9 8 1784 9 13?9 3 IE84 14044 14709 1533 6 D94 7 16 % 2 1715 4 1775 7 s 0 8127 17780 17942 13MI 14125 1 4486 84190 3 5060 I $532 1 5948 16327 1 % 81 1 7014 1 7330 Sh 55 50 % 100 % 150 % 200 % 25055 350 % 450 % %0 % 450 % 750 % 850 % 17ee e 0 02669 01627 0164 0 2134 0 2458 02720 0 2950 0 3161 0 3545 0 3897 04?3) 04%I 04862 0 5165 ft 695 46 1122 2 1123 9 1718 0 1276 8 1323 1 1;63 3 1400 0 1467 6 1530 9 1592 5 1653 3 1713 9 1774 4 4649 4W a 0 8828 1 2676 l 2691 1 3523 1 4020 14395 14708 14984 8 5463 1 6883 16266 iE22 169 % 1 7273 56 44 l i 94 il 144 11 na 17 244 11 w4 il 444 ll 544 n 64411 744 11 644 11 2NS e 0 02727 01513 0 1975 0 2305 02%6 02793 0 2999 0 3372 0 3714 04035 04x4 04643 0 49n 16 % 89i 6 707 18 1113 2 !?ot 3 1268 4 1316 7 1358 1 1395 7 1864 2 1528 3 1590 3 1651 5 1712 3 1773 i e S 8929 3 25e9 13MI 1 3914 14305 146?8 14910 I $397 15821 1 4207 16%$ 1690 1 7219
$h = supe 7 heat, F h = erith8tpy. Btu per Ib V = Specific volum8, Cu ft per Ib 5 = eritropy, Btu per R per Ib s
B-7 i
t I TatHe 3. Superheated Slesm-Continued ' Ae> Press Lbl5a in $st sa, temperature- Degwed omenheit (581 lem0) Weie' steem 700 754 Ist 858 000 950 - 1000 1858 ff?e 113# 1790 1300 1400 1500 Sh 3789 8739 137 89 18789 23789 28769 33789 38789 43789 48789 53789 63789 73719 83789 7480 e 0 02790 0 1408 01824 0 ?!64 0 2424 07648 0 7850 0 3037 03?l4 0 3382 0 3545 03703 0 38 % 0 41 % 04443 0 4724 M62 411 h 718 95 !!D3 7 1191 6 1759 7 1310 1 1352 0 139l ? 1476 9 1460 9 1493 7 15?5 6 1%70 1588 1 1649 6 !?IO 8 17718 s 0 9031 17460 1 3237 1 3808 1 4717 18549 14837 1 5095 1 5332 15%3 1 5761 1 5959 1 6149 1 6509 16887 1 7167 Sh 31 89 81 89 131 19 18189 73189 781 89 331 89 381 89 43189 48189 531 89 63189 731 89 831 89 2500 = 0 0?859 0 1307 0 1681 0 703? 0 ??93 0 7514 02712 0 7896 0 3068 0 3232 03390 03543 0 3692 03980 04?S9 0 4529 668 lIl n 731 71 1093 3 1176 7 !?S06 1303 4 13474 1386 7 1873 1- 1675 1490 7 1522 9 1946 1585 9 1647 8 1709 ; 17704 s 0 9139 12345 .43076 33701 14!?9 I 4477 147% 1 5079 3 5269 1 5497 1 5703 1 5903 16094 3 6456 I 6796 I ?!)6 Sh 26 09 76 C9 176 09 176 09 2?6 99 276 09 376 09 376 09 476 09 476 09 526 09 6?6 09 776 09 876 09 j 2000 e 0 0?938 0171) 0 1544 01909 0 ?!?! 0 7390 0 2585 0 7765 0 2933 0 3093 03247 0 3395 03540 0 3819 0408s 04n0 - 1673 911 h 74447 1087 0 1860 ? !?di a !?% 6 1341 9 1382 1 1419 ? 1454 1 1487 7 1520 ? 1%?? 1583 7 1646 0 1707 7 1769i s 09247 12??5 1 2908 1 3592 14047 14395 146 % 14964 1 5708 1 5434 1 %46 1 5848 1 6040 1 6405 16746 1 7068 Sh - 2047 7047 17047 17047 72047 77047 32047 37047 47047 47047 52047 62047 ??047 820 47 flee e 0 03079 O ll19 0 1418 01794 0 7058 02??5 0 2468 0 7644 0 2809 02%5 0 3:14 0 3759 0 3399 0 3670 0 3931 0 4184 (679 5Ji n 757 34 1069 7 1142 0 1731 8 !?89 5 13M 3 13775 1415 ? 1450 7 ' 1484 6 1517 5 1549 8 !$815 4644 1 1706 1 17678 s 0 9J56 12097 12777 4.3481 13954 14Ji9 14628 I 4900 1 5648 1.5316 1 % 91 15794 15988 1 63 % l %97 1 70?! Sh 15 04 - 6504 115 04 16504 ?!5 04 765 04 315 04 365 04 415 04 46504 515 04 615 04 115 04 815 04 80I8 e 0 03t34 01030 01778 01685 0 1952 0 7168 0 7358 0 ?b31 0 2693 0280 0 7991 0 3137 0 3768 0 3532 03785 0 4030 1884 961 ) 77069 10 % 8 1821 ? 1220 6 178? ? 1330 7 1372 8 le117 14477 14816 15l4 8 15473 1579 3 4642 ? 1704 5 17% 5 s 0 9468 1 1954 12527 13%8 1 3867 14?45 14%I 14838 1 5089 1 5321 1 % 37 1 5742 # 5938 16306 1 6651 1 6975 5h 9 78 59 78 109 78 159 78 209 78 759 78 309 78 359 78 409 78 459 78 509 78 609 78 109 78 809 70 2006 e 0 03262 0 0942 0 1138 0 1541 01853 02068 0 ??% 0 24?? 0 2585 07734 02877 0 3014 03147 0 3403 03649 0 3887 1690221 h 18513 1039 8 1095 3 !?09 6 I??47 1324 9 1368 0 1407 ? 1443 7 14785 1517 1 1544 9 1577 0 1640 4 1703 0 1765 2 s 0 9588 1 1803 1 2283 1 3251 - ! 3780 14171 1 4494 14177 1 5032 1 52 % 1 5485 1 5692 1 5889 1 8259 ) MOS I 6931 Sh 4 67 54 67 10467 15467 704 67 Fu 47 30467 354 67 404 67 45467 504 67 604 67 704 67 804 67 8018 - e. 0 03428 0 0850 0 0982 0 1483 0 1759 01975 0 ?l61 0 2329 0 2484 0 2630 0 7770 0 7904 0 3033 0 3282 0 n22 0 3753 1695 331 h 301 84 1020 3 1060 5 4197 9 !?67 0 1319 0 JM32 1403 6 1440 2 14754 1509 4 1542 4 1574 8 1638 5 1701 4 17638 s 0 9778 1 1619 11%4 1 3131 1 3692 14097 1 4479 14117 14976 1 5713 1 5434 15642 1 5841 1 6214 16%1 1 6888 Sh 49?? 997? 149 ?? 199 ?? 749 77 799 77 349 72 399 7? 449 77 49977 599 ?? 699 77 799 72 8188 e 0 03681 0 0745 0 1389 01671 01887 0 2071 0 7237 0 7390 0 7533 0 7670 0 ?800 0 ?9?7 0 3170 0 3403 0 M28 (70020) h 42397 993 3 1185 4 1259 1 1313 0 1358 4 1399 0 1436 7 14773 1506 6 1539 9 1572 6 1636 7 1699 8 17625 s 0 9914 1 1373 1 3007 1 3604 14024 Iand 14658 14920 1 5161 1 5384 1 994 15794 1 6169 I 6518 1 6447 5h 44 9/ 94 92 144 97 194 97 744 92 794 97 344 97 394 97 444 97 494 97 594 9? 694 92 794 97 3708 e 0 04417 00%6 01300 01588 O l804 0 1987 0 ?!51 0 7301 0 744? 0 2576 0 ??04 028?? 0 3065 0 3?91 0 3510 (705 08) > 875 54 931 6 l17? ) lh09 1306 9 in34 1394 9 . 14331 1469 7 1503 8 1537 4 1570 3 1634 8 1498 3 17617 s len! 1 0832 I ?877 1 3515 1 3951 1 4300 1 4600 148 % 1 5110 1 5335 1 % 47 1 5149 1 6126 1 6477 1 6806 Sh . 83st e 0 1713 0 1510 0 17?? 0 1908 0 2070 0 ??ll 0 7357 0 7488 0 ?613 0 ??34 0 7966 0 3:87 0 3400 h 1158 7 174 ? ! IJ00 7 6348 4 .3390 7 14?9 5 1466 1 15010 1534 9 1%81 1632 9 1696 7 47599 8 1 2747 1 3425 13879 ) 4237 ~ l 4542 1 4813 1 5059 ) 5287 1 5501 1 5704 1 6084 164 M iU67
~ Sh MOI v 0 Il?9 01435 01653 018M 01998 0 ?!4') 0 ???6 0 2405 0 75?B C 2646 0 2872 0 3088 0 12 %
h 11437 1733 7 !?94 3 13434 1386 4 14?5 v 146? 9 1498 3 15324 1%58 1631 1 1695 1 1758 5 s 1 2600 1 3334 1 3807 1 4174 1 4486 1 4761 4 5010 1 5?40 1 54 % i % 60 1 6042 1 63 % ! 6728
$h 8ese v 0 1048 0iM4 0 1583 0 1764 0 19?? 0 20 % 0 ??oo 0 2376 0 2447 0 ?$63 0 7784 0 7995 0 3198 h 1127 8 !??a 6 !?878 1338 2 138? ? 142?? 1456 7 44955 1579 9 l%36 16?1 7 1693 6 17572 s 1 2450 1 3742 1 3734 1 4:17 1 4430 1 4109 84967 1 5194 1 5412 l %28 , 6007 1 6358 1 669) 5h IIst e 0 09 % 0 I?% 0 1517 0 1697 0 1854 0 19 % 0 ?!?8 0 ??52 0 ? ) 71 0 7485 ( 7707 0 7908 0 3106 h 1108 6 I?l5 3 !?ll ? 1333 0 1377 9 4418 6 14 % 5 14926 15274 1%13 16273 1692 0 17% 9 s I ??81 1 3148 .13M? I 4050 14374 1 4658 1 4914 1 5149 1SM9 1 5576 4 5962 1 6320 1 Mbe Sh IN8 e 0 0799 0 1169 0 1395 0 1574 0 1729 0 1868 0 19 % 0 2116 0 ??31 0 ?)do 0 7549 0 7746 0 79 %
h 10ha ? 1895 5 17676 13?? 4 13691 1411 7 1450 1 14870 15??4 1968 16?)6 1688 9 17532 6 l 1888 1 79 % 135t ? I 3978 1 4265 14%8 1 4871 1 506) 1 5284 1 5495 1 5886 1 6247 1 6584 sh 4818
- 0 0631 0 105? 0 1284 0 1463 016% 0 1752 01877 01%4 0 7105 0 ??lo 0 7411 0 ?601 0 ??B3 h 10014 1874 3 11534 IJ716 13602 64076 14436 4481 3 15173 1%27 16198 1685 7 17506 s i 13 % 1 7754 13371 1 J807 1 4158 14461 1 4730 1 4976 1 5703 1 5417 1 5817 1 6177 1 6516 Sh 8MI e 0 0498 0 0445 0 1183 01M2 0 1513 01647 0 1769 0 1883 0 1991 0 7093 0 ??87 07470 0 7645 6 tso l 11516 !?)36 1300 4 13512 1396 0 1437 1 1875 5 151? ? 15476 16161 6682 6 17480 8 8 0905 1 2544 1 3223 1 % 86 1 4053 143h6 1 464? I 4893 1 5124 1 5341 1 574? I 6109 ) 6452 Sh dass e 0 04?1 0 0846 0 1090 0 l? ?0 0 1420 01%7 0169 0 6 7t2 D is87 0 19s6 0 ?!74 0?nt 0 7519 h
909 5 ll77 3 I??33 !?89 0 lH2O 13h8 s 14304 1469 7 1%71 15430 1612 3 16794 1745 3 6 1 05 % a 2375 1 3073 1 J5% 1 3949 I 4772 1 4556 14817 ) 5048 1 5768 i M73 4 6044 8 6389 Sh = Superhe8t. F h = enth81py. Btu per Ib v = specshc v0lume, eu tt per Ib 5 = entropy. Bru per R pe? lb
}
B-8
Table 3. Superheated Steam-Continued'
' Abs Press .
Lb/$0 in - 5 41 Sal l'*D"84'e - Deg'ees f abreerit ($st iem0) Water $leam MS ' 000 ISO 900 050 1000 1950 1100 - 1150 - !!00 1790 1300 1400 1500 D 4EIB e 0 0380 0 0751 0 1005 01106 0 1335 0 1465 0 1582 0 1691 0 1792 0 1889 0 1982 0 2071 0 2242 0 2404 n 'i 883 8 !!00 0. 12073 12772 1332 6 13805 1423 7 1463 9 1501 9 1538 4 1573 8 1608 5 1676 3 1 74 ? ? s 1 0331 120N 3 2922 1 3446 1 3847 - 1 4I81 1472 1 4734 1 4974 1 6197 1 5407 1 %C7 1 5982 1 6330
~ 4WB e 0 0355 0 0665 0 0927 01109 O l?$7 0 1385 0 1500 0 1606 0 1706 01100 0 1890 0 1977 0 2142 0 7299 h 366 9 1071 2 1190 7 12652 13231 13726 1817 0 1458 0 1496 7 1533 8 1%97 1604 7 1673 1 17400 s . 1 0180 1 1835 11764 1 3327 1 3745 1 4090 1 4390 1 4657 . I 4901 1 5128 1 5341 J $543 1 5921 1 6272 9
IIIB e 0 0338 0 0591 0 Os% 0 1038 0 1185 0 til? 0 1425 0 1529 0 1626 0 1718 0 1806 0 1890 0 2050 0 2203 6 854 9 1042 9 !!?36 1252 9 13135 1%46 14102 1452 1 1491 5 1529 ) 1%55 1600 9 1670 0 17374 8 1 0070 1159J l 2612 1 3207 1 3645 I 4001 1 4309 1 4582 3 4831 1 5061 1 5277 3 5481 1 5863 1 6216 sh , 8I00 v 0 0326 0 0531 0 0789 0 0973 ' 1119 0 1244 0 1356 0 1458 01%1 0 1642 0 1728 0 1810 0 1966 0 2114 6 4458 3016 9 1156 0 12404 1403 7 13 % 6 14034 Im62 1486 3 35245 15613 IH72 1%68 1734 7 s 0 9985 1 1370 1 24 % 1 3084 1 3545 1.3914 1 4229 I 4509 I 4762 3 4995 1 5214 1 5420 1 6806 1 6161 Sh 0808 e 0 0317 0 0483 0 0729 0 0912 0 1058 0 1182 0 1792 0 1392 0 1485 0 1572 0 1656 0 1736 0 1888 0 2031 h Ele 5 994 3 1838 1 1227 7 12937 1348 4 13 % 5 luo3 14811 1519 8 1557 1 15934 IH37 1732 I s 0 9916 I 1175 1 22 % l.2969 1 3446 3 3827 1 4151 1 4437 1 4694 1 4931 1 6153 1 6362 1.5750 1 6109 Sh Ist e 0 0309 0 0447 0 06?? O 00 % 0 1001 0 1124 01232 0 1331 0 1422 01500 0 1589 0 1667 0 1815 01954 h 832 4 975 0 1119 9 12 48 1283 7 13402 1389 6 1434 3 1475 9 ' 1515 2 1%29 15A9 6 JM05 17295 s 0 98 % 1 8008 1.2137 1 2850 1 3348 1 3742 1 4075 143M 1 4628 14869 1 5093 1 5304 1 M97 1 6058 Sh IIIe v 0 0303 0 0419 0 0622 0 0805 0 0949 0 1070 01177 0 1274 01%3 01447 0 1527 0 1603 0 1747 0 ies)
# 8273 958 8 1101 8 1201 8 1273 6 1332 0 13826 1428 3 1470 6 1510 5 1%87 15858 16574 1726 8 s 0 9803 1 0867 1 1981 1.2732 1 3250 1 3654 IJ999 4 4297 14%4 1 4808 1 5035 1 6248 1 %A4 I 600s Sh W v . 0 0298 0 0397 0 0579 0 0757 0 0900 0 1020 0 1126 0 1221 0 1309 0 1391 0 1469 0 1544 0 1684 0 1817 h 822 9 tell 1084 6 1888 8 12934 13236 1375 7 1422 3 1465 4 15059 1544 6 1582 0 1654 2 1724 2 e 0 9758 1 0746 1.1833 1 2615 1 3154 1 3574 1 3925 14??9 1 4500 1 4748 1 4978 1.5194 1 5593 1 5960 Sn 5e e 0 0287 0 0358 0 0495 0 36 % 0 0793 0 0909 0 1012 01104 0 1188 0 1266 0 1340 0 1411 0 1544 0 1669 h 813 9 919 5 10467 11% 3 12378 1302 7 13581 1407 3 1452.2 1494 2 15341 1572 5 16464 17176 s 0 M61 1 0515 1 1506 1 2328 1 2917 1 2310 1 3743 1 4064 4 4347 1 4604 1 4841 1 5062 3 5471 1 5844 Sh IIIB
- 0 0279 0 033# 0 0438 0 0573 0 0704 0 0816 0 0915 0 1004 0 1085 0 1160 0 1731 0 1298 0 1424 0 1542 h 806 9 901 8 1016 5 1124 9 1212 6 1281 7 13405 1392 2 14391 1482 6 1523 7 1%31 1638 6 1711 1 8 0 9582 1 0350 1 1243 1 20 % 1 2689 1.3171 iM7 1 3904 1 4200 144u 14710 1 4930 1 53 % 1 5735 IIW e 0 0272 0 0318 0 0399 0 0512 0 % 31 0 0737 0 0833 O M18 0 09 % 0 1068 0 1136 0 1200 0 1321 0 1433 6 801 3 089 0 982 9 10977 1188 3 1261 0 1322 9 13772 1426 0 14710 1513 3 1553 7 1630 8 17046 s 0 9514 1 0224 11033 1 1818 1.2473 1.2900 1.3397 1 3751 1 4059. I 4335 145E I 4819 1 5245 1 % 32 Sh WM e 0 0267 0 0306 00371 0 0465 0 0571 0 0671 0 0762 0 0845 0 09M 0 0909 0 1054 0 1115 0 1230 0 1338 6 796 6 879 1 9744 1074 3 1165 4 1241 0 1305 5 13622 1413 0 1459 6 1503 ) !$44 5 1623 1 16981 s 0MM 1 0122 iOne 1.1613 1 2271 1.2790 1 3233 3 3603 3 3924 1 4206 1 4467 4 4705 1 6140 1 5533 Sh WW v 0 0?62 0 0?t6 0 0350 0 0429 0 0522 0 0615 0 0701 0 0780 0 0s53 0 0919 0 0952 0 1041 01151 0 1254 6 192 7 871 2 959 8 1054 % 1144 0 1221 9 1288 5 13475 1400 2 14482 1492 9 1535 3 1615 4 1691 7 4 0 9402 1 0037 1 0727 1 143i 120a4 1.2627 1 3076 1.3460 1.3793 1 4087 1 4352 1 4597 1 5040 1 5439 Sh IIII e 0 0258 8038 00335 00e02 0 0483 0 0500 0 e649 0 0724 00794 0 0858 0 0918 0 0975 0 1081 0 1179
# 72 3 864 7 948 0 10376 11254 12D41 1212 1 1333 0 1387 5 14371 1482 9 1526 3 1607 9 1685 3 ,
s 0 9354 0 9964 18613 1 1295 1 1918 12468 1 2926 13J23 IJ667 t3970 14243 14492 1 4944 1 5149 Sh NSB e 0 0?54 0 0282 00322 0 0300 0 0451 0 0578 0 0603 0 0675 0 0742 0 0e04 0 0062 0 0917 0 1019 0 1113 6 706 4 859 2 ' 838 3 50734 1108 9 11877 12 % 6 1318 9 13751 1426 1 1473 1 15173 16004 16790 s 0 9310 0 9900 J b516 1 1153 ! !771 11320 1,2795 1J191 1 3546 13858 14137 14392 1 4851 1 5263 p . . 10000 v 0 0?51 0 0776 0 0312 0 0362 0 0425 0 0495 0 0565 0 0633 0 0697 0 0757 0 Os12 0 0665 00 0 0 1054 6 783 8 854 5 930 2 1011 3 094 2 !!72 6 12420 13053 1%29 1415 3 14634' 35086 1593 1 1672 8 s 0 9270 0 ts42 1.0432 3 1039 1638 1.2185 17652 1.3065 1 3429 1.3749 I 4035 8 4295 1 4763 4 5180 m imes = 0 0248 0 0271 0 0303 0 0347 0 0404 0 0467 3 0532 0 0595 0 06 % 0 0714 0 0764 0 e:18 0 0913 0 1001 n 7 15 850 5 923 4 10010 losis 11589 1228 4 !?t2 4 1881 1404 7 1453 9 1500 0 15858 1666 7 4 0 9232 0 9790 1 0358 1 0939 1 1511 L 2060 1.2529 1.2946 1 3371 1 3644 !Jt37 3 4202 34677 1.5100 Sh = superheat. F h = enthalpy. 8tu per Ib v = specifs volume, cu ft per ib s = entropy, Stu per F per Ib B-9
6 . I-h k-Table 3. Superheated Steam-Continued Aos Prest . Lb/$0 ln $41 Sat hmpmtn -Degree 6 Fahrweit ($41 Temp) Watee $ team 2tg 300 $$g gge 950 1300 1950 1100 1150 1290 1250 1390 1800 1980 1158 e 0 0245 0 0267 0 02 % 0 0335 0 0386 0 0443 0 0503 0 0562 0 0620 0 0616 0 0727 0 0776 0 0868 0 0952 n 779 5 W69 9175 992 ) 1%99 1146 3 !?!5 9 t/80 ? 1339 7 1394 4 1444 6 1491 5 ' 1578 7 IM06 s 0 91 % 0 9742 1 0292 1 0051 . I 14!? ! 1945 1 2414 1.2833 13209 1 3544 1 3842 3 4112 34595 1 5023 11880 s 0 0243 0 0263 0 0290 0 0325 0 0370 0 0423 0 0878 0 0534 0 0588 0 064) 0 0691 0 0739 0 0827 0 0909 h 177 7 4438 912 4 984 5 10594 !!34 9 1204 3 1268 7 1328 8 1384 4 1435 5 1483 2 15718 1654 7 s 0 9163 0 M98 1 0232 10712 1 1316 1 1840 1 2308 1 2727 1 3107 1 3446 1 3750 1 4025 1 4515 1 4949 13W0 s 0 0241 0 0260 0 0284 0 0317 0 0357 0 0405 0 0456 0 0508 0 0560 0 0610 0 0659 0 0704 0 0790 0 0869 n 176 1 841 0 907 9 9778 10509 1124 5 1193 7 12580 1318 5 1374 7 1426 6 14751 1564 9 1648 8 s 0 9131 01657. 1Ol?? I 0701 1 1229 1 1142 1 2209 1.2627 1.3010 1 3353 1 3662 1 394I I 4438 14877 12:e0 e 8 0238 00?s6 0 0279 0 0309 0 0346 0 0390 0 0437 0 0486 0 0535 0 0583 0 0629 0 0673 0 0756 0 0832 h 174 7 838 6 903 9 971 9 1043 1 1115 2 1184 1 12479 1308 8 13654 1418 0 1467.2 3558 2 16431 s 0 9301 0 % 18 1 0127 1 0637 1 !!51 1 1653 1 2117 1 2534 1 2918 1 3264 1.3576 1.3860 1 4363 1 4808 18ess e 0 0?36 ' 0 0253 0 0275 0 0302 0 0336 0 0376 0 0420 0 0466 0 0512 0 0558 0 0602 0 0645 0 0725 0 0799 9 773 5 836 3' 900 4 %68 1036 2 1106 7 1174 8 !?38 5 1299 6 1356 5 1409 6 1459 4 1551 6 16374 6- 0 907,1 0 9582 1 0080 1 0578 11979 11571 120JO 1 2445 1 2833 1 3179 1 3494 1 3781 1 4291 1 4741 13000 e ~ 00235 0 025! '0 0271 0 0297 0 0328 0 0364 0 0405 0 0448 0 0491 0 0535 0 0577 0 0619 0 06 % 0 07(4 A 272 3 834 4 8972 %22 1030 0 1099 I 1166 3 1229 7 1291 0 1348 l 1401 5 1451 8 15452 16319 s . 0 9045 0 9548 1 0037 1 0524 1 1014 1 1495 1 1948 1 2361 1 2749 1 3098 1 3415 1.3705 1 4221 1 4675 14 egg e 8 0233 0 0248 0 0267 0 0291 0 0320 0 0354 0 0392 0 0432 0 0474 0 0515 0 0555 0 0595 0 0670 0 0740 6 27t J 832 6 894 3 958 0 1024 5 1092 3 !!$8 5 1221 4 1283 0 13402 1393 8 1444 4 15388 1626 5
- s 0 9019 0 9515 0 9996 1 0473 1 0953 11476 11872 1 2282 12671 1.3021 1 3339 3 3631 4 415J l 4612 tones e' 0 0231 0 0246 0 0264 0 0287 0 0314 0 0345 0 0380 0 0418 0 0458 0 0496 0 0534 0 0573 0 0646 0 0714 n 770 4 831 0 891 7 954 3 10196 1086 2 11514 12138 12754 1332 9 1386 4 1437.3 til2 6 16211 s 0 8994 0 9484 0 9957 1 0426 1 0897 1 1362 I I801 1 2208 1 2597 1.2949 1 3266 1 3560 1 4087 145D tegel 0 0230 0 0244 0 0261 0 0282 00308 0 0337 0 0369 0 0405 0 0443 6 0479 0 0516 0 0552 0 0624 ~0 0690 9 7696 829 5 889 3 950 9 1015 1 10806 1144 5 1206 8 !?68 1 1326 0 13794 1430 3 1526 4 15159 s 0 9970 0 9455 0 9920 1 0382 1 0646 1 1302 1 1735 1 2139 1.2525 11880 1 3197 1 3491 1 4022 3 4491 18 egg e 0.0??8 0 0242 0 0258 0 0??g 0 0302 0 0329 e 0360 0 0393 0429 0 0464 0 M99 0 0534 0 0603 0 0668 n 7bs t $20 2 3872 9478 !0ll i 1075 7 1139 0 3200 3 76 1 ' 31196 ,,2 8 IG23 6 15204 16108 s O 8946 0 9427 0 9886 ' 1 0340 1 0797 1 1247 1 1674 1 2075 ; , ', 1.3131 1 3424 1 3959 2 4433 Sh = superbe8t F h = =^ b ".a perIb v = speutic volume, cu ft per Ib , ,,,. ocu per R per tb l
B-10 l
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION THERMODYNAMICS, HEAT TRANSFER, and FLUID FLOW 1.01' QUESTION (1,0) MULTIPLE CHOICE (Select the correct answer.) One steam generator safety relief valve (SRV) is leaking to atmosphere. Steam generator pressure is at 570 psia (steam enthalpy of 1204 BTU /LBM). Changes to the physical properties of the leaking steam can be identified on the provided Mollier diagram (Figure 1.01). Which of the following statements correctly describes the condition of the exhaust steam from the leaking steam generator SRV 7 a, The leaking SRV exhaust steam is saturated at 10% moisture content,
- b. The leaking SRV exhaust steam is ,
superheated at 10% moisture content. !
- c. The leaking SRV exhaust steam is ;
saturated at 305 degrees F. j
- d. The leaking SRV exhaust steam is superheated at 305 degrees F.
i 1.01 ANSWER (1.0)
"d"
REFERENCE:
WEFf1NGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAPTERS 2 & 3. ] 1 i l i s _ _ _ _ _ _ _ _ _ _ _ _ _ _ . i
fi wgr n of 1.000- - 1.335 1650 '1965 2.300
.1810,
, , , , _a__ _ _ _ __ _ 1810 1.0 1.2 : 1.4 - 16 1.8 ~ 2. 0 22
, , # [.
/ .
1700 - 1703
- CnnR1 l -
/ /
- E'
[ '
~
1600 1500 1500 1500
/-
/ /
- / / i 1400 /
1400
/ / ttenutust r/ _/ /____
/
l 3 / 5 1300 8/ [' / # 1300 a.
. f. I t '
- " # ip . / / / *"
/pA,ijvy;y
, g r--- --
-7 S4 1000 y- -,.
l//,/
'O
~ '-
//
/ .
0 }$! \ / / v / '* B00' B00 1.0L / II.2 / / 1.4' / 1.6 1.8 2.0 2.k \ 1000 1.335 1650 ENTROPY, s, Stu/lbm , R 1.965 2 300
1.02 OUESTION (1.0) MULTIPLE CHOICE (Select the correct answer.) A pressurizer safety valve le leaking to atmosphere. The pressurizer is at 2120 psia (steam enthalpy of 1129 BTU /LBM). Changes to the physical properties of the leaking steam can be identified on the provided Mollier diagram (Figure 1.01). Which of the following statements correctly describes the condition of the exhaust steam from the leaking Pressurizer SRV ?
- a. The pressurizer safety relief exhaust steam is saturated at 20-50% moisture content.
- b. The pressurizer safety relief exhaust steam is saturated at 2-5 % moisture content.
- c. The pressurizer safety relief exhaust steam is superheated at 750 degrees F.
- d. The pressurizer safety relief exhaust steam is saturated at 250 degrees F.
1.02 ANSWER
.. b
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, , CHAPTERS 2 & 3. l 4 l 2
i i 1.03 QUESTION (2.0) Dry saturated steam is exiting the three stegm generators at 580 psia with a feedwater temperature of 402 F and a total feedwater flowrate of 5.0 x 10 lbm/hr. Rated-thermal power for the SONGS 1 reactor is 1350 MWt. Using the steam tables and Mollier diagram provided, answer the following questions: (a) What is the steam quality (X) exiting the steam ; generators if its moisture content is 1.50 % ? (0.5) l (b) What 4s the actual percent power of the SONGS 1 ' rer.ctor with the secondary plant conditions given above? (1.5) 1.03 ANSWER-(2.0). (a) 98.5 % (0.985) (0.5) [ steam quality is the converse of moisture content identified on Mollier diagrams: X: 1-M] (b) b: m (h steam -hfeedwater) (0.5) 6
- 5.0 x 10 lbm/hr(1203.9 btu /lbm-377.3 btu /lbm) (0.25) h = 4.133 x 10'9 btu /hr (0.15) 6 6 Mw = (4.133x10 btu /hr) x (1 Mw/3.41x10 btu /hr) (0.25) 1212 Mw (0,1) 1212 Mw/ 1350 Mw = 90% (0.25)
(Accept 88.6% if the candidate used the result of part (a) to answer part (b). hsteam (at 98.5% quality): hf + xhfg
= 467.5 + (0.985) 736.5 : 1192.95 BTU /LBM 9
h: 5.06x10 0 lbm/hr ( 1192.95 - 377.3) = 4.08x10 BTU /HR 9 6 Mw : 4.08x10 BTU /HR ( 1Mw/3.41x10 BTU /HR) : 1195.97 Mw 1195.97 Mw / 1350 Mw : 88.6%
REFERENCE:
WESTINGHOUSE THERHAL-HYDRAULIC PRINCIPLES CHAP. 6. 3
l l l i 1.04 QUESTION (1 5) j The residual heat removal system is operating with a process flow rate of 1000 gpm (500,000 pounds per hour). The RHR and the RHR heat heat exchanger inlet temperature temperature reads reads 355 324 {F on local exchanger outlet indication. What is the heat removal rate of the RHR system at these conditions? (Cp of water = 1.0 BTU /LBM) 1.04 ANSWER (1.5) U : mCp21T (0.5)
= 500,000 lbm/hr*1 BTU /LBM (355 - 324) (0.75) i 7
= 1.55x10 BTU /HR (0.25)
REFERENCE:
SONGS 1 SYSTEM DESCRIPTION SD-S01-320 AND WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES, CHAPTER 3, Pg. 3-9. i 4 L_ _ ___ .
I i 1.05 QUESTION (1.0) MULTIPLE CHOICE ( Select the correct response ) During startup and at operating conditions the condenser removes the unused heat energy and latent heat of vaporization of the steam to convert it to a liquid. Which of the following statements correctly identifies the reason for the condenser process discussed above ? (1.0) (a) Condensate depression is used to prevent condensate and feedwater pump thermal shock. (b) Condensate depression is used to prevent cavitation in the condensate and feedwater pumps. (c) The latent heat of vaporization is removed from the steam to minimize feed water heater corrosion. (d) The latent heat of vaporization is removed from the steam to maximize feed water heater efficiency.
- ANSWER (1,0)
(b)
- REFERENCE i
.i WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES General Physics, pages 182 - 185 l
l 1 l 5
1.06 QUESTION (1.5) MULTIPLE CHOICE ( Refer to the provided steam-water tables, and Select the correct response )- What is the condensate depression for a condenser operating at 1.0 psia, with a condensate temperature of 97 degrees F ? (a) 198.7. degrees F (b) 80 psia (c) 4.74 degrees F (d) 80 psig
- ANSWER (1.5')
(c) [ 1.0 psia saturation temperature = 101.74 degrees F ] [ condensate depression = the difference between saturation temperature and condensate temperature = 101.74 - 97 = 4.74 degrees F ]
- REFERENCE General Physics, pages 180 - 185 5
d l ! 6
l 1.07 QUESTION (1.0) MULTIPLE CHOICE ( Select the correct response ) The plant is operating at 100% power with the turbine control system in the manual MODE. The Reactor Operator notices the Pressurizer heaters have remained on without spray initiation with Pressurizer pressure increasing abcve control setpoint. The reactor has not tripped. How will this transient immediately effect the departure from nucleate boiling ratio (DNBR) 9 (a) DNBR remains the same (no effect) (b) DNBR decreases (c) DNBR increases (d) DNBR reaches the safety limit
- ANSWER (1.0)
(C)
- REFERENCE WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES Chapter 13, pages 13-15 to 13-25 7
. - - - _ - _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1.08 QUESTION (1.0) MULTIPLE CHOICE ( Select the correct response ) With the plant is at 100 % power, the reactor operator trips one of the three operating Reactor Coolant Pumps due to high middle seal temperatures. How will-this evolution immediately effect the departure from nucleate boiling ratio (DNBR) ? (a) DNBR remains the same (no effect) (b) DNBR decreases (c) DNBR increases (d) DNBR reaches the safety limit
- ANSWER (1.0)
(b)
- REFERENCE WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES Chapter 13, pages 13-15 to 13-25 8
1.09 QUESTION (1.5) MULTIPLE CHOICE ( Select the correct response ) Ro'ds have been pulled out of the core adding reactivity sufficient to increase the count rate from 1000 CPS to , 4000 CPS in 30 seconds. What is the start up rate, in DPM?
- a. 0.6 DPM.
- b. 0.8 DPM.
- c. 1.0 DPM.
- d. 1.2 DPM.
l 1.03 ANSWER.(1,5)
"d" 4
[P = Po'10 SUR(t) In(P/Po) = SUR(t) In(10) In(4000/1000) : SUR(30 sec) In(10) In(4) = SUR(30) 2.3026 {1.3863/(30 sec)(2.3026}{60 sec/ min) = SUR = 1.204 DPM]
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAPTER 7.
)
l l 9 l
>- 4 l 1 l 1 1.10 QUESTION (2.0) How much reactivity,in PCM, must be added to a core to produce g eff = a0.0065 stable 1 DPM SUR iij sec, a reactor and has j a= 0.1 sec'I?(2.0)
/=5x10 ~
1.10 ANSWER (2.0) T = 26.06/SUR = 26.06/2DPM = 26.06 sec. (0.5) p= f/T+ jeff/1+ hT (0.5)
-5
=(5x10 sec/26.06) + 0.0065/1+(0.1 sec-1)(26.06) (0.5)
= 1.92x10-6 + 0.0065/1 + 2.606
= 1.92x10-6 + 0.0065/3.606
= 1.92x10-6 + 1.8x10-3
-3
= 1.8x10 = 180 PCM (0.5)
(Accept alternate methods of obtaining 180 PCM p=
.// T keff + [eff/1+ 5 T or SUR = 26 ( heffp/ jdp ))
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR PHYSICS CHAPTER 7, page 7-50 10
i
.)
i i 1.11 QUESTION (1.0)
)
MULTIPLE CH01CE ( Select the correct respo .se ) 1 During a refueling the insertion of a fuel assembly int 8 the , core increases the count rate from 100 cps, at a 1
-Keff = 0.95, to 135 cps.
What-will be the new Keff at the 135 cps? a, 0.990
- b. 0.982
- c. 0.971
- d. 0.~963 1.11 ANSWER (1.0)
"d"
[ Cr y (1 - Keff)y : Cr 2 Il ~ *fI)2 (100/135)(1 - 0.95) = 1 - Keff 2 1 - 0.037 = Keff 2 Keff2 = 0.963 ]
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAPTER 8. 11
1.12 QUESTION (1.0) MULTIPLE CHOICE ( Select the correct response ) Which of the following phenomena would have an effect on the Doppler-only power defect over core life?
- a. The depletion of burnable poisons
- b. The change in control rod Boron concentration
- c. The generation of Cm-244 from PU-239
- d. Fuel cladding creep.
1.12 ANSWER (1.0)
"d"
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 2, Pgs. 2-40 thru 2-46. l 1 12 _ _ - _ _ _ _ _ - _ _ _ _ - . - _ _ b
' ;,N" ~ y; I .
t F \; _;
.l,i q ,s h
I 1 1.13 QUESTION (1,d) (DELETED) l Select the correct statement for Axial Flux Dii'ference.
- a. At end of core life (EOL) axial power! distribution is at t the bottom of the core with AFD more negative. J
- b. When axial flux difference is negative more power is being produced in the top of the core.
- c. For power levels greater than 50% axial flux difference is maintained within 15%.
- d. When power distribution is distributed equally through the core the AFD is 1.
1.13 ANSWER (1.0)
"c" (DELETED)
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 8, Pgs. 8-25 & 8-26. f I i 13 ) - _ _ - _ _ - - - - - \
d,. if(-< i l .-
-' 1.14 QUESTION (2.0, ,
l A reactor is shutdown by - 5.072iK/K with all control rods fully inserted and the most reactive rod worth is 2.5% /iK/K. 1 1 (CONSIDER EACH QUESTION SEPARATLEY)
- a. What is Keff for the reactor when it is shutdown by 5% tsK/K? (1.0)
- b. What is the " Shutdown Margin" of the reactor in % 21K/K?
(1.0) 1.14 ANSWER (2.0)
- a. lsK/K = -0.05 : Keff-1/Keff (0.5) 1: Keff + (0.05) Keff (0.25) 1 = 1.05 Keff Keff : 1/1.05 : 0.95 (0.25)
- b. 5% - 2.5% = 2.5% 4LK/K, (1.0)
(Shutdown Margin is the amount the reactor would be suberitical from its present condition, all rod fully ! inserted, with the most reactive rod fally withdrawn.) { l'
REFERENCE:
FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAPTER 7, AND SONGS 1 TECHNICAL SPECIFICATION DEFINITION 1.22. l a 1 14 4
.1.15 QUESTION (1.0) .
MULTIPLE CHOICE ( select the correct response)- Which of the following statements correctly describes soluble boron reactivity control?
- a. The differential boron worth (pcm/ ppm) increases in magntude with increased boron concentrations.
- b. The differential boron worth (pcm/ ppm) decreases with increasing water temperature.
- c. The moderator temperature coefficient becomes more negative with increasing boron concentration,
- d. The differential boron worth (pcm/ ppm) increases with the build up of fission products.
.1, M ANSWER "b"
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 5, Pgs. 5-3 thru 5-13. l l 15
l: L 1.16 QUESTION (1.5) MULTIPLE CHOICE ( select the correct response) Which of the following statements correctly describes the the operational effects ~of the fission product poision Damarium?
- a. The removal mechanism for samariura is burnup by neutron flux snd decay. ,
- b. Following a power decrease to a constant lower power level the reactivity insertion of samarium decreases to a constant lower equilibrium value.
- c. After a reactor shutdown samarium increases and remains constant until the reactor is restarted
- d. Following a power decrease to a constant lower power level the reactivity insertion of samarium increases to a higher equlibrium value.
i 1.16 ANSWER "c" l
REFERENCE:
REACTOR CORE CONTROL, CHAPTER 4, Pgs. 4-30 thru 4-34. { I i j l l 16
4 1.17 QUESTION (2.0) How must each of the following parameters change (INCREASE or DECREASE) to make the moderator temperature coefficient more effective in inserting negative reactivity 7 ( Consider each parameter independently)
- a. Pressure
- b. Temperature
- c. Voiding
- d. Boron concentration 1.17 ANSWER
- a. decrease -
(0.5)
- b. increase (0.5)
- c. increase (0.5)
- d. decrease (0.5)
REFERENCE:
WESTINGHOUSE CORE CONTROL, CHAPTERS 2 and 3, Pgs. 2-9, 3-3 thru 3-5. 17 L_____________.
1.18 QUESTION (1.0) l MULTIPLE CHOICE ( select the correct response) The Main Generator is tied to the grid system and operatinc at its load limit for 100% power. The Load Dispatener has been maintaining a 0.95 lagging power factor. A large capacitive load is inadvertently added to the grid system. Which one of the following control room indications correctly describes the initial response of the Main Generator System? (a) The power factor becomes more lagging. (b) Real Main Generator power decreases. (c) The power factor becomes less lagging. (d) Real Main Generator power increases.
- ANSWER (1.0)
(c) 4 REFERENCE SD-S01-100, Main Generator and 18 KV System i l I-l 18
, 1.19 QUESTION (1.0)
MULTIPLE CHOICE ( select the correct response) Emergency Diesel Generator (D/G) number one is loaded onto its 4160 KV bus for surveillance testing, but not paralleled to the Main grid system. Which of the following D/G control board indications correctly describes the initial response when the operator places the D/G No. 1 voltage regulator switch to the " raise' position 7 (a) D/G output voltage decreases (b) D/G output frequency decreases (c) D/G output voltage increases (d) D/G output frequency increases
- ANSWER (1.0)
(c)
- REFERENCE SD-SO1-100, Main Generator and 18 KV System SD-SO1-600, Diesel Generator Systems END OF SECTION ONE li a
19
SECTION TWO PLANT DESIGN, SAFETY AND EMERGENCY SYSTEMS 2.01 QUESTION (3.5) The emergency diesel generators tie directly onto their respective 4160 V buses 1C and 2C, inorder to supply selected emergency class 1E loads in the event of a station loss of power. The following is a list of some of the major unit pumps.directly supplied by these buses: (1) South TPCW pump (6) Feed pump A (2) Heater Drain pump A (7) Condensate pump A (3) Heater Drain pump B (8) Condensate pump D (4) North TPCW pump (9) Safety Injection pump A
.(5) Charging pump B (10) Feed pump B (a) What are five(5) loads, specifically from the above l list, that are normally supplied by 4160 V bus IC ?
( 0. 25 pts,. each ) ( 1. 25 ) (b) What are five(53 1.oads, specifically from the above list, that are .rmally supplied by 4160 V bus 2C ? (0.25 pts.each)(1.25) (c) What are four(4) loads, specifically from the above list, that are automatically sequenced back onto protected 4160 V buses 1C and 2C after a Simultaneous Occurrence of Safety injection and Loss of Offsite Power (SISLOP) event. (0.25 pts. each)(1.0)
- ANSWER (3.5)
(Non safety related pumps (heater drain, condensate and TPCW) do not require letter or location (north, south) designations. Safety related pumps require designators. (a) (0.25 pts.each)(1.25) (b) (0.25 pts.each)(1.25) (1),(3),(5),(8),(10) (2),(4),(6),(7),(9) i (c) (0.25 pts. each)(1.0)
- i. (5),(6),(9),(10) i
- REFERENCE SD-SO2-120 4140 V (Figure 1), SD-SO1-590 (Sequencer) pages 10-42, SD-SO1-600 (D/G's) 20
s 2.02 QUESTION ('1.5)
'The-chemical and volume control system (CVCT balances RCS inventory.
- a. From what loop is the normal letdown drawn from and charging returned to? (0.5)
- b. Why.is a backpressure regulator va3ve provided downstream of the Residual Heat Removal heat exchanger?
(1.0) 2.02 ANSWER (1.5)
- a. (reactor coolant) loop A cold leg. (0.5)
- b. Prevents letdown flashing in the low pressure piping (down stream of the letdown orifices). (1.0)
REFERENCE:
SD-SO1-310 CVCS, P& ids 5178135, 5178130, ONE LINE DIAGRAM 5146828. L 1 l 21
2.03 QUESTION (3.0) Normal CVCS excess letdown flow is routed to the VCT via the seal water return piping. Excess letdown capabilities were designed to accommodate three(3) specific NORMAL plant evolutions. One(1) of these is to maintain letdown during the inoperability of normal letdown. What are the two(2) other of these three(3) NORMAL plant evolutions that would require the use of EXCESS letdown? (1.5 pts.each) (3.0)
- ANSWER (1.5 pts.each) (3.0)
(1) Used during PZR steam bubo 3e formation (upon startup) (2) To in^rease the cooldown rate during the initial phase of RCS cooldown (during RHR heat exchanger operations).
- REFERENCE SD-SOI-310 CVCS, page 5, figure I-l l
l l l 1 j-22 l 1 _ - - - _ _ _ _ . _ _ _ _ __ l
I I i i 1 2.04 QUESTION (3.0) i One of the design features of the containment spray system ) is to spray cool water into the containment sphere to reduce ; pressure in the event of a LOCA. !
- a. What is the other design feature of this system, specifically related to the containment atmosphere, that minimises the adverse consequences of a LOCA event? (0.75)
- b. Why is hydrasine added to the containment spray upon initiation ? (0.75)
- c. Why doesn't the cool water sprayed into the containment (and subsequently drained into the containment sump) cause a positive reactivity excurtion when it is i injected into the RCS after the recirculation phase of safty injection has begun? (1.5) 2.04 ANSWER (3.0)
- a. To absorb post LOCA iodine fdssion prodncts from the containment atmosphere. (0.75)
- b. Hydrasine is added to the CSAS to facilitate the scrubbing of post LOCA iodine fission products from the containment atmosphere.(makes water a more efficient l absorber of iodine) (0.75)
- c. Tha normal source of water for containment spray is borated water (from the refueling water storage tanks).
(1.5)
REFERENCE:
SD-SO1-580, Pgs. 52, 62,& 71, P&ID 5171820. SONGS 1 FSAR l 23
2.05 QUESTION (2.0) The Control Room HVAC system is designed to maintain the control room habitable to personnel during - all conditions for safe facility operations. What are the two(2) design features of this system that minimizes the possibility of airborne radioactivity in-leakage to the control room during emergency conditions?' (1.0 pt. each) (2.0) 2.05' ANSWER ( 1 )- The emergency emergency filtered air supply (1.0) (2) The CVCS maintains a positive pressure in the control room (1.0)
REFERENCE:
SD-SO1-640 Control Room and TSC HVAC
.24
2.06 QUESTION (3.0) The 120 volt AC system provides reliable regulated power for critical plant' controls and instrumentation,
- a. What are the normal and backup power supplies to NIS instruments 1201 and 1206? (0.5 pts. each) (1.0)
- b. What is the alternate source of power to vital bus No. 1?
(0.5)
- c. What are the color codes for vital busses 3, 3A , 4, and 5? (0.25 pts. each) (1.0)
- d. How do the pressurizer PORV's fail (open, as is, or ;
closed) upon loss of electrical power ? (0.5) ' 2.06 ANSWER (3.0)
- a. Normal . inverter no. 4 (0 5) backup : vital bus no. 4 or Regulated Bus no. 4. (0.5)
- b. MCC-2 (37.5 Kva transformer 480/120) (0.5)
- c. (0.25 pts. each) (1.0) 3 = BLUE 3A = WHITE / BLUE 4 = GREEN 5 = BROWN
- d. CLOSED (0.5)
REFERENCE:
SD-SO1-159, AND SO1-2.6-3. I l 25 u__1---_______________.__
2.07 QUESTION (2.0) i The plant fire protection system provides fire water to. various locations throughout the plant.
- a. What is the NORMAL source of water to the fire water protection system? (0.5)
- b. What is the minimum volume of water reserved for fire protection from the NORMAL fire water protection system source? (0.5)
- c. Which fire pump normally maintains the fire main pressure when the systen is in standby? (0.5)
- d. At what fire main pressure will the East and West fire pumps automatically start upon the isolation of the Unit-1 firemain from Unit 2/3? (0.5) 2.07 ANSWER
.a. Service ater reservoir (0,5)
- b. 300,000 gallons. (0,5)
- c. Unit 2/3 jockey pump (0.5)
- d. 40 to 60 psig (0.5) l
REFERENCE:
-SD-SO1-460 Fire Protection System '
l l f-p l L l 26 i - - . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
2.08 QUESTION (2.0) The Instrument Air System (IAS) is designed to supply clean, dry, normal and back-up air to operate vital system , equipment and valves. Normally the three(3) Service Air Compressors function to maintain IAS header pressure. (a) What are two(2) other system air compressors that can be used to supply the Instrument Air System header? (0.5 pts. each) (1.0) (b) How would the Main Feed Water Flow Control valves fail ( OFEN, AS IS, or Closed), if IAS header pressure was lost? (0.25) (c). How can the Reactor Operator remotely maintain the Safety Injection valves (HV-851,HV-852,HV-853, and HV-854) operable in the event IAS header pressure was lost? (0.75)
- ANSWER (2.0)
(a) (0.5 pts. each) (1 0)
- 1. Auxiliary Air Compressor
- 2. Diesel Air Compressor (b) Fail Open (0.25)
(c) Select the Nitrogen backup (0.75)
- REFERENCE SD-SO1-420, S01-2.4-2 IAS Malfunction 27
2.09 QUESTION (2.0) LThe pressurizer is connected to the reactor coolant system (RCS) in three locations,
- a. Where is the pressurizer surge line connected to reactor coolant system? (0.5)
- b. Where are the pressurizer spray lines'l & 2 connected to the reactor cool-ant system? (0.5 pts. each) (1.0)
- c. What Reactor Coolant System component provide the primary force (driving header pressure) for normal Pressurizer spray flow? (0.5) 2.09 ANSWER (2.0)
- a. Pressurizer surge line - loop S hot leg (between the RV and the S/G). (0.5)
- b. Pressurizer spray line (1) - loop A cold leg (between the RCP and the RV). (0,5)
Pressurizer spray line (2) - loop B cold leg (between the RCP and the RV). ( 0_ . 5 )
- c. Reactor Coolant Pump (s)(associated with each spray loop) (0.5)
REFERENCE . SD-SO1-280, Pgs. 5 & 6 of 46. 28
l 2.10 QUESTION (1.5) The pressurizer power operated relief valves (CV-545 and j 546) are designed to. limit RCS pressure to below the relief ' pressure of the pressurizer safety valves, a, Where do the POhY's vent steam to when actuated? (0.5)
- b. What is the backup actuating power supply to the pressurizer PORVs if instrument air fails? (0.5)
I
- c. What is the failure position of the PORVs if electrical power is lost (OPEN, CLOSED, REMAIN THE SAME) ? (O.5) (
2.10 ANSWER (1.5)
- a. PZR Relief Tank (PRT) (0,5) j
- b. Nitrogen backup for both PORVc. (0.5)
- c. closed. (0.5)
REFERENCE:
SD-SO1-280 , SD-SO1-150, S01-2.G-3. l 29 i um_.________a_____._____._..___.____ _ . _ _ _ _
2.11 QUESTION (1.5) The safety injection system is designed to mitigate core damage resulting frcm overheating following a loss of , coolant accident. When a safety injection signal is initiated why is there a 11 second time delay associated with the main feedwater pump restarting' 2.11 ANSWER (1.5) The 11 second time delay provides time for the feedwater , pump suction and discharge valves to realign for safety l' injection,(which prevents the injection of unborated water from the condesate system to the reactor causing a positive reactivity addition.) REFERENCE; SD-SO1-580, Pgs. 18, 14, 37, SD-SO1-590 Pg. 10. END OF SEC" ION TWO l i l 30
- /_ _
l SECTION THREE INSTRUMENTS AND CONTROLS 3.01 QUESTION (3.0) Channels R-1212 and R-1214 of the operational radiation monitoring system (ORMS) are being used to monitor a waste gas release through the stack. 1
- a. Other than detector failure, what would cause the indication to fail in the down scale direction? (1.0)
- b. What is the prefered method of manually terminating a waste gas release upon receipt vent stack high radiation alarm? (1.0)
- c. What ' control room indication is available to confirm a high radiation level indication on R-1212 & R-1214, when being used to monitor the vent stack? (1.0) 3.01 ANSWER
- a. R-1212 & R-1214 will fail in the downscale direction if they become saturated in a high radiation field. (1.0) i
- b. Pull R-1219 out (about 2", this deenegises and closes SV-99, gas discharge control valve). (1,0)
- c. ORMS recorders (RLR-1200, RLR-1203) and WRGM recorder (RR-1254B), (display a gradual increase, not a spike).
(1.0)
REFERENCE:
S01-2.2-1, Pgs. 7 thru 9 of 23, and SD-SO1-550. l l f 31
3.02 QUESTION (1.5) The pressurizer power operated relief valves (PORVs) provide overpressure protection for the RCS.
- a. At what instrument air pressure is the nitrogen backup system automaticly shifted to? (0.5)
- b. How are leaks through the-PORVs detected? (0.5)
- c. What are the power supplies to the PORVs block valves?
(1.0) 3.02 ANSWER
- a. 60 psig. (0.5)
- b. Temperature element in the common discharge header (downstream of the PORVs). (0.5)
- c. 120 volts AC. (0 5)
REFERENCE:
SD-SO1 280.
\
32
\'
- - - --- -_ m
3.03 QUESTION (1.5)
'What are the three conditions that must be met in order for the Variable Low Pressure. Trip (V.L.P.T.) to be defeated?
(1.5) 3.03 ANSWER
- 1. 3 Out Of 4 Power Range Channels less than 10%, (0.5)
- 2. Main Turbine First Stage Pressure less than 10%, (0,5)
- 3. No loss of power on buses 1C & 2C. (0.5)
REFERENCE:
SD-SO1-570, Pg. 9. ! 1 i 33 i
l i l I 3.04 QUESTION (1,0) What are the-two inputs to the Variable Low Pressure Trip? (1.0) 3.04 ANSWER (0.5 pts each max 1.0 pts.)
- 1. RCS delta T,
- 2. RCS Tave,
- 3. RCS Pres".!re.
REFERENCE:
SD-SO1-5/0, Pg.9. l 1 l 34 j
3.05 QUESTION (3.0) l l Tave is compared to Tref for control rod motion.
- a. What input is use] to produce Tref? (0.75)
- b. What will be tge rod speed and direction if Tave is less than Tref by 5 F? (0.75)
- c. What are the two other inputs to the rod cotrol system for rod speed control? (0.75)
- d. Whgt will be the rod speed if the is a Tave > Tref of 12 F7 (0.75) 3.05 ANSWER
- a. Turbine generator first stage pressure. (0.75)
- b. Five inches (15 steps or pulses) per minute in the out direction. (0.75)
- c. Pressurize pressure minus Pref (P - Pref), and the change in nuclear flux per change in time (dn/dt). (0.75)
- d. 15 inches (40 steps or pulses) per minute. (0.75)
REFERENCE:
SD-SO1-400, Pgs. 5 thru 37. 35
3.06 QUESTION (2.5) The turbine control system provides turbine speed contro), trips and runbacks,
- a. What are the two signals and set points that will cause the turbine Overspeed Protection Controller to actuate?
(1.0)
- b. What is the setpoint of the turbine backup overspeed trip? ~(0,5)
- c. What are the two conditions that will cause a turbine runback? (1.0) 3.06 ANSWER a, Low pressure tt:bine steam inlet pressure >50% of full steam flow. pressure, and Generator load is (20% of full load. (1.0)
- b. 104.5% (1882 RPM) of rated turbine speed. (0.5)
- c. 1. Low frequency (58 Hz) , (0,5)
- 2. Dropped rod, (0.5)
REFERENCE:
SD-S01-270, Pgs. 9 thru .23. I 36
Ii 3.07 QUESTION (3.0) The diesel generators have been automatically started by'a SIS / LOP.
- a. What are the two signals tnat will automatically trip the diesel generator? (1.0)
- b. What are.four of the mechanical diesel engine trips that are defeated during an automatic start of the diesel generator? (1.0)
- c. What are four of the electrical (generator) trips that are defeated during an automatic start of the diesel generator? (1.0) 3.07 ANSWER
- a. Engine overspeed, and (0.5)
Generator differential. (0.5)
- b. (0.25 pts ea. max. 1.0 pts.)
- 1. High lube oil return header temp.
- 2. High main bearing temp.
- 3. Low L.O. press, to turbocharger.
- 4. Low L.O. press. to engine.
- 5. High jacket water temp.
- 6. Engine / turbo hi vibration.
- 7. High cranchcase press.
- c. (0.25 pts ea. max 1.0 pts.) <
- 1. Generator overvoltage.
- 2. underfrequency.
- 3. Loss of field.
- 4. Negative phase.
- 5. directional power (reverse power).
- 6. Stator ground.
- 7. Voltage controlled overcurrent.
REFERENCE:
SD-SO1-600, Pgs> 103 thru 107. 37
i i 3.08 QUESTION (4.0) 1 There has been an automatic initiation of auxiliary feedwater (AFW).
- a. What will trip the turbine driven auxiliary feedwater pump (Trip and setroint)? (1.0)
- b. Why is a low discharge pressure trip provided for the motor driven auxiliary feedwater pump? (1.0)
- c. How is the steam generator protected from thermal shock on a motor driven AFW pump restarts after a loss of power? (1.0)
- d. What are the auxiliary feedwater flow control valves set at? (1.0) 3.08 ANSWER
- a. Low suction pressure, 0.6 psig, for 10 sec. (0.5)
Overspeed (4750 to 5000 RPM). (0.5)
- b. The motor driven AFW pump low discharge pressure trip protects the pump / motor from runout condition damage.
(1.0)
- c. The AFW pump flow is is allowed to increase with the pump speed, (allowing the gradual increase in flow since flow control valve isolation valves fail as is). {1.0)
- d. FCV - 2300 & 3300 (S/G A&C) set at 100%,(150 GPM). (0.5)
FCV - 2301 & 3301 (S/G B) set to 50%,(75 GPM). (0.5)
REFERENCE:
SD-S01-620, Pgs. 6 thru 14, S01-7-3, Pgs. 5 thru 7. 38
-- _---.____ _ a
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,,,- m 'l.~3/09 7 QUESTION ( 32 0 )'.
LTheimain steam system is.provided with safety. valves, t 't!
- 3. ' -
atmospheric-dump valves and. condenser steam dump valves. ia" Wh'atYissthe: lowest and-the' highest main steam safety
, valve, set points? '(1.0) ib..W' hat two: conditions must exist, at.'100% power to cause
,T
- 1 i_ $ ., ,
[y . < (; ' % - < the' condenser-steam steam. dump valves to quick open (1.0) (blow oper;)? ny '
* -; c. What will arm:the condenser' steam dump system is.in the
- p. q -
ipressure control mode? ( 1.' 0 ) c , s 3.09 ANSWER.
+
"^;, ' .a.kLows985 psig, (0.5)
,,, t
- High11035 psig. (O.5)
- b. Tave ? Tref d 5 F AND, (0.5)
- Loss of-:Mwe .(load) > 10% power.
(O'.5) L J 9 g jv, . r. .c. Condenser pressure > 2" Hg. (1.0). r p LREFERENCEi SD-S01-190, Pgs. 13, 26, 27, 37 & 43. l.-, s'- _t' , F: U. r , :r. .
- a. '
f ..' 4 r-b > . 'f _, '
,~
h 39 o_ ' z .
r ,e t 3.10 QUESTION (2.0) The steam generator water level control system is a thre.e element system.
- a. What are the three input sinals to the steam generator water level control system? (1.0)
- b. What is steam pressure used for in the steam generator water level control system? (1.0) 3.10 ANSWER
- a. Steam flow, (0.33) feed flow, (0.33) steam generator level. (0.33)
- b. Steam pressure is used for density compensation in the steam flow calculation. (1.0)
REFERENCE:
SD-SO1-260. END OF SECTION THREE { 1 1 40
SECTION FOUR PROCEDURES NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 4.01 QUESTION (2.5) SO123-0-03.1 " Valve Operations" provides guidence in manual operation of valves. a, Why must a safety related Motor Operated Valve (MOV) be declared inoperable if it has been seated or bachseated in other than its safety related position? (1.0)
- b. What action must b<: taken if an important to safety MOV is manually scated to prevent leakage? (1.0)
- c. Who may authorize a manually operated closed valve to be checked closed by turing it in the open direction? (0.5) 4.01 ANSWER
- a. Manully seating or bachseating a valve in other than the safety related position may cause it to be (electrically) unable to overcome the torque required to unseat or unbackseat it. (1.0)
- b. The power supply (to the MOV) must be opened and n caution tag hung indicating that the valve must be manually unseated prior to power being returned to the MOV. (3.0)
- c. SRO Operations Supervisor. (0,5)
REFEEENCE: SO123-0-23.1, Pgs. 5 & 6. 41
4.02 QUESTION.(1.0)' Keys are. issued to plant operating personnel for entry into locked areas.
- a. What operating staff position normally issues keys? (0.5) l
- b. During what modes of operation are unit 1 on-shift operators required to carry Safe Shutdown Security heys? (0.5) 4.02 ANSWER
- a. Nuclear Operations Assistant (NOA). (0.5) 1
- b. Modes 1 - 4. (0.5) i
REFERENCE:
S0123-0-27, Pgs. 3, 4 & 5. I l I l 42
i I.
-4.03_ QUESTION (1.5)
I The reactor is operating at 92% power when reactor coolant l loop "A" flow drops to 70% without a reactor trip. entering I you into Abnormal Operating procedure S01-2.1-1 , Loss of Reactor Coolant Flow. l
- a. Why are your.immediate_ operator actions to transfer i reactor control rods to manual? (1.0)
- b. What power level must the reactor be reduced to in 1 hour? (0.25)
- c. What is the P-8 setpoint (in % RCS loop flow), below which a reactor trip will not occur upon the loss of one RCP? (0.25) 4.03 ANSWER
- a. The loss reactor coolant flow will give a lower Tave causing the rods to move out if they are left in auto.
(1.0)
- b. 10%. (0.25)
- c. 85% (0.25)
REFERENCE:
AOP SO1-2.1-1, Pg. R. TECHNICAL SPECIFICATION 3.1.2. 43
1 4.04 QUESTION (3.0) Primary system leakage $ c monitored to insure Technical I Specification limits are not exceeded. 1 i
- a. What is the maximum identified leakage rate that the . I reactor can be safely operated at? ( 1. 0 )
- b. What are TWO of the FOUR primary to secondary leahage limits that will require the plant to be shutdown within-six hours, per Technics 3 Specifications? (2.0) I i
l 4.04 ANSWER l
- a. O gpm. (1.0)
- b. (1.0 pts-. ca. max 2.0 pts)
- 1. Increase of primary to secondary leakage of 140 gpd (0.1 gpm) over 24 hrs, in any S/G. 1 l
- 2. Any primary to secondary leakage in excer,s.of 215 spd 1 (0.15 gpm) in any S/G.
'3.' Measured increase in pimary to secondary leakage in i excess of 15 gpd (0.01 gpm) when measured primary to secondary leakage is above 340 gpd (0.1 gpm). q
- 4. Primary to secondary leakage in excess of 0.3 gpm in any S/G.
REFERENCE:
S01-2.1-5, Pg. 4, and TECHNICAL SPECIFICATION 3.1.4.
]
i 1 4 ll 44
]
- _ _ -- ___ __ _ i
.3-
},.' 1 i
-1 l
4.'05 QUESTION (2.0) ,
~j You have cntered Loss of Secondary Coolant procedure i T S01-1 0-30 due to a main steam line break outside of the -{;
containment. You are at the point of determining if safety injection (SI) can be terminated. ] What is the SI termination criteria for the following items under normal containment conditions?
- a. Reactor Coolant System pressure. (0.5) b, Pressurizer level. (0,5)
- c. Reactor Coolant subcooling. (0.5-)
- d. Reactor coolant system hot leg temperatures. (0.5) 4.05 ANSWER
- a. RCS pressure > 1250 psig and (0.05) stable or increasing. (0.25)
- b. Pressurizer level > 20%. (0.5)
- c. RCS subcooling > 40 F. (0.5)
- d. Stable or Decreasing. (0.5)
REFERENCE S01-1.0-30, Pg. 15. 4 i 45
.l l
1 l a 4.00 QUESTION (2.5) l During.a loss of secondary coolant in containment the 1 auxiliary feedwater (AFW) pumps are providing f eed i' low l to the steam generators.
- a. Based on 501-1.0-30, Loss of Secondary Coolant, what is .
the minimum combined total AFW flow rate (GPM) that sust , be maintained to the steam generators? ;).25)
- b. Based on S01-1,0-30, Loss of Secondary Coolant, what is the.feedwater flow rate (GPM) that must not be exceeded to a steam generator with a narrow range level of less than 26*4? (0.25)
- c. What mode of heat removal is to be established if a loss of secondary heat sink is diagnosed, in accordance with
'SO1-1.3-1, Loss of Gecondary Heat Sink? (0,5) d Based on S01-1.3-1, Loss of Secondary Heat Sinh, what are the three conditions (which are valid for both adverse and normal containment conditions) that indicate a loss of secondary heat sink? (1.5) i i
'l 4.06 ANSWER
- a. 165 gpm. (0.25)
- b. 150 gpm. (0.25)
- c. Reactor coo)cnt system feed and bleed. (0.5)
- d. Two S/G's < 30" Wide Range, (0.5)
RCS pressure and temperature increasing, (0.5) PORVs cycling on set point. (0.5) ,
REFERENCE:
S01-1.0-30, Pg. 5 and S01-1.3-1 Pga. 5, 13, 14 &
- 15. .
46
4.07 QUECTION (2.0) . AOP S01-2.1-4 states that the immediate operator action during an unplanned boration accident is to isolate all boric acid injection paths to the RCS.
- a. What are the five immediate operator actions t& ken to isolate all boric acid inject $on paths-to the RCG?
(Name of valve or valve numbers acceptable.) (0.75) b, What level (%) must the Volume Control Tank be at when MOV-11000 is opened? (0.25)
- c. Why must VCT level be checked when MOV-11000 opens?
(1.0) 4.07 ANSWER a.-(0.15 pts each max 0.75 pts) i 1. Stop all boric acid injection and transfer pumps.
- 2. Verify closed or close CV-334, PA transfer pump supply to charging pumps,
- 3. Verify closed or close CV-1102B, DA injection pump flow control valve.
I
- 4. Verify closed or close CV-333, BA transfer pumps l recire, valve.
L 5. Verify closed or close MOV-1100B &. D, RWCT supply to l charging pumps,
- b. >20% (0.25)
- c. To prevent cavitation of the charging pumps due to pumping f rota an empty tank (insure NPSH f or the charging purips ) . (1.0)
REFERENCE:
AOP SO1-2.1-4, Pg. 2. Technical Specifications 3.2 and Bases; SONGG-1 ' FSAR 3 I {
\
J
)
47 ) u__ _ - - _ _ - - -
't l
l 4.08 QUESTION (2.0) Technical Specifications state that in Mode 5, with alb reactor coolant loops filled, at least one Residual Heat Removal (RHR) train shall be operable but that the : associated pump may be de-energized for up to one hour. I What are the two conditione that must be met in order for i the operable train RHR pump to be de-energized for up to one ) hour? (0.0) 4.08 ANSWFR
- 1. No operations permitted that would cause dilution of {
RCS (boron concentration), and (1.0)
- 2. Core outlet temperature is maiatnined at least 40 F below saturation. (1.0)
REFERENCE:
SONGS 1 TECHNICAL SPECIFICATION 3.1.2, Pg. 3-3. ( 48 i ___
I i 4.09 QUESTION (2.5)
-i ications state that the RCS may not be The Technical increased aboveSpeci{F 200 unless the containment spray and the refueling water storage tank are operable.
- a. What are the Technical Specification requirements for the l RWST to be. considered operable? (1.0) )
I
- b. What conditions must be met in order for the hydrecine q tank in the containment spray system to be considered operable? (0.5)
- c. What are the other two conditions that must be met in j order for the containment spray system to be considered i operable? (1.0) 1 4.09 ANSWER j
- a. 1. Minimum elevation of 50' of borated water, and (0. 5 ) )
C. Boron concentration between 3750 ppm and 4300 ppm. (0.5)
- b. Minimum volume of 150 gallons of hydrazine, (not Jess than 21% by weight). (0.5)
- c. 1. Two refuciing water pumps are operable, and, (0-.5) l
- 2. Two hydrazine additve pumps operable. (0. 5 )- {
REFEENCE: SONGS 1 TECHNICAL SPECIFICATION 3.3, Pgs. 3-28, l
-29, -35, -36 1
l l
I 4.10 QUESTION =(3 0) Emergency Operating Instruction 501-1.0-1, Critical Saft.ty Function Status Trees provides critical safety functions and their prAority levels,
- n. When is a core considered adequately shut down with the source range instrumentation energized? (1.0)
- b. When is the. core cooling critical safety function considered satisfied? (1.0)
- c. What are the two criteria that will satisfy the heat sink critical safety function? (1.0) .
4.10 ANSWER
- a. Zerc or negative startup rate is indicated. (1.0)
- b. Whgn the RCS water cooling the core is subcooled by i 40 F. (1.0) !
- c. Operable RHR system. (0,5)
Operable steam generators with feedwater supply capability and operable steam dump path. (0.5)
REFERENCE:
EOI SO2-1.0-1. Pgs. 13, 10, 18, 20. i l l l 1 I l
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, U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: SONGS 1 Reactor Type: PWR WESTINGHOUSE 3 1.00P Late Administered: JULY 28. 1987 < Examiner: MIKE ROYACK - Candidate: ***** m **** 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 ppers will be picked up six (6) hours after the examination starts. f of Category 5 of Candidate's Category Value Total Score , Yalue Category M.4 25 25%t 5. Theory of Nuclear Power Flant Optration. Fluids, and Thermodynamics J&" % 2V _. _ 6. Plant Systems Design, Control and Instrumentation 2V Y X 7, Procedurer - Normal. Abnomal. Emergency, and Radiologteal Control g,9 25 25' ~
- 8. Administrative Procedures, Conditions, and Limitations 9BS for' Y -
Final Erode TOTALS All work done on this examination is my own I have neither given nor received aid.
****e m *****
Candidate's Signature 4
--.m _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _
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be MQUIRDENTS FOR ADMINISTRATION OF WRITTEN EXAMINATION 3 .
*, \
- e2.'f.{ 2. ' A single room shall be provided for completing the tvritten examina'-
tion. The facetion of this room and supporting restroom facilities ' I7. shall be such ac ta prevent contact with all other facility and/or 1 !~. sentracter personnel skreihg the duration of the trritten examination. < ' 7.~ If necessary, the facility #Sould mate arrangements for tha we of
.7 a suitable rees at a leesl school, motet, er other building. 0b-l p '. . taini4e this ross is the responsibility of the licensee.
- f. '
' i
- 2. Oltniana spacfag is required to ensu=e 4xamination faitsprity as detemined by the chief examiner. OliHiage spatirq slwuld be one .
{' candidate per table, with a 3-ft space between tables. No wall i
. shorts, models, and/or other training materials shall be present in the examinatico voos. ,
- 3. Suitable arrangements shall be made by the facility (Y the candi- i estes are to have lunch coffee or other refreshments. These arrangements shall compIy with Itas 1 above. These arrangements shall be sutrkmed by the examiner and/cr proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer kay after the last candidate has completed and handed in bis written examination. The facility staff shall then have five working -
days to provfile femal written commeats with supporting documentation on the asamination and answer key to the chief examiner er to the regional effice section chief.
~
- 5. . The licensee 'shall provide pads of 8-1/2 by 11 in. lined paper in unepened packages for each candtdate's use in completing the exam- ,
testion. The examiner shall distribute ttese pads to tfm candidates. ; All reference material needed to complete the examination shall be furnished by the exaniner. Candidates can bring pens,
.v calculators, or slide rules fato the examination room,and pencils, no ot her equipment er refersace material shall be allowed. ~ I
- 5. Only black fak or dark pencilti should be eased for writing answers to apuestions.
. 1 Esasiner Standards
1
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l
.' lutt RULES AND GUIDELI.NE.S FOR LICENSE , EX.AMINATIONS )
During the administration of this' examination the following rules apply: )
' ir 1. Cheating on the . examination means an automatic denial of your applicati r?. and could result in morc severe penalties. . ,.
,L
- W 2. Restroom trips are to be limited and only one candidate et a time ma'y
?. leave. You must avoid all cnntacts with anycne outside the examination 1 $ team to avoid even the appearance or' possibility of cheating. '
Y 3. Use black ink er dark pencil Rall to facilitate legible reproductions.
.+
's . . 4. Print your name in the blank provided on the cov6r shest of the M/.,q .
emaninetton. . .
- 5. Fill in the date en the cavar shest of the examination (if necessary).
- 6. Ose ma1y the paper provided for answers,
- 7. Print your name in the upper right-hand corner of the first page of g section of the answer shset.
8. Consecutively appropriate, startnumber each pn each categor{ answer e new sheet, write "End page, write'.on]y of Categor 3,ne of the paper, and write "Last Page on th 7 east answer sheet. l S. Number each answer as to category Imd pueber, for amasple,1.4, 6.3. 1
- 30. Skip at least three lines betweeh each answer.
. \
~
- 31. Separata answer sheets from I dren en your desk er table. pad and place - - fichhed answer sheets fal l
- 32. Ose alcreviattens only if they are commonly used in facility Ifteraturej 1
- 13. The point value'for each question is indicated in parenthaet, after the I quasi.len and cea be used as a guide for the depth of answer requtMd.
- 34. Show all calculations, methods, or assumptions used to obtain an answer ,
to mathematical problems whether indicated in the spottien or not. l
. 35. Partial credit may be yhtn. Therefore, ARSWEA ALL PARTS OF THE ilESTH Ale DO ICT LEAVE ANY AM$ssR'SLANK. . - 15. If parts of the examination are act clear as to intent, ask questiens o[
the examiner only. ,, l
- 17. You must sign the statenant on the cover sheet that indicates thiit the l '
work is your sun and you have not received or been given assittance in completing the examinatten. This aust be done after the turnination has been completed. - .
. l
, r= .s r st. oare. -
. 1 L
1g. Een you complete your examination, y2u shall: . 4 .
.c
- a. Assemble your examination as follows:
9
. . . (1) Exas questions on top. .
- L (2) Exam sids - figures, tables, etc. ." .
(3) Answer pages including figures which are a part of tse answer.
. . . t. .
,,,. b. Turn. in your copy of the examination and all pages used to ar.swer
, the examination questions. ,
- c. Turn in all scrap paper and the balance of the paper that you did M.b.
- 3. . - . .
#-4 not use far answering the spostions. ,
- d. I,save O.a 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 revokad. ;
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j Examiner standards , . e w________________ . l
EQUATION SHEET f = ma v = s/t '
=> = ag 2 Cycle effidency =
a = v,t + hat , (i , E = aC a = (v - v )/c l EE = ev2 Y =v +a A = AN A = A,e~AE-
- l , FE = ash . = e/t .
1 = in 2/cg = 0.693/f;g , si. W = v&P ,
,(g)(q) ,, , , , , , , ,
l e., AE = 931Am I!4+"b)
'. - - k " k AT
- p ,
y ,g o,-Ix { (=gaar
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L-
.-
- g ,2
- gx {
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/ ). F = P,10 NO TVL = 1.3/u j F = P, at/T IVL
- 0.693/u
~~
son > 26.Os/s . - - : - T = 1.44 37 - ECR = $/(1 - K,gg)
. fa gg oi
- SvR = 26 I ,
CR, = g/(1 . g ggg) T=ts*/,3+ [(f ,)/x,gg )
% U ~ *eff)1 " N1 -leftD
- l T ,= 1*/ (o E M
- I/Cl -
- gg) . = CR g/CRO f T = (I - p)/ 1erip I n = (1 . g,,,) f(t g,,,) j
* " "aff-I)/Keff " 'Kaff/*eff snx = (1 x,gg)/x,,,
~
T. p= (i"/%gg 3 + [I/(1 + 1,gg?)] s' = 1 x 10 ' seconds
]
F = E(V/(3 x 1010) g aff te 0.1 seconds"I
. . , 3 = 3, .
~
Idgg=Id22 i RATER PARAMETERS Id g =1d2 1 gal. = 8.3451ha 2 R/br = (0.3 CE)/d (meters) l 1 gal. = 3.78 liters 2 R/br = 6 CE/d (feet)
. I ft3 = 7.48 gal. MISCEU Mytous co w Enstoxs ,
3 tensity = 62.4 lbs/fc
~ 1 Curia = 3.7 a 1010dps Density = 1 gn/cm 3 1 kg = 2.21 2h.
Beat of wagorizatip = 970 ttu/lba , I hp = 2,54 s 10. 3BTU /hr ; Reat of fusica = 244 Stu/lba 1 W = 3.41 x 100 Stu/hr 1 Atm = I4.7 psi o 29.9 in. I't. 1 Stu = 778 f t-lbf - 1 ft. 3 0 = 0.633, ibf/in2 2 ' 1 inch = 2.54 cm
'T
- 9/5*C + 32
'C = 3/9 (*r - 32)
Table 1. Properties of Saturated Steam and Saturated Enter (Temperature) Temp. Press. Volume, it '/lbm Enthalpy, Btu /lbm Entropy, Bru/lbm x R Temp. F psia Water Evap. Steam Water Evap. Steam Water Evap. Steam F U f it g i b ig b g E l #g i *g 1T5 0 8.an?4 S.0M147 See.s 304.s 72.no 103e.t no?.* e.1M4 1. sus 1 970 305.0 494.s 1 96 % S 4 086144 313 8 313 1 71.992 8034 0 1806 8 393 3 1 93830 0 016140 382 0 8 18M 3 83Se 1 9725 10*.0 322 0 70.993 1935 4 1806.3 8 8349 1 0408 8 9?SO 103.0
!!#.9 1 94789 0.016137 331.1 331 1 69.995 103S.9 1105 9 0 1331 1 8464 1 9??S 102.0 108 8 8 9781F 8 816133 MO.6 340 6 64.997 1936 5 1805 6 8 1313 1.H 87 8 9400 101.0 100 0 9 94924 0.916130 350 4 350.4 67.999 1937.1 1105 1 9.1295 1 0510 8 942S 180.0 99 0 S.98103 8 916127 360.S M05 67.001 1037.6 110e.6 0 1278 1 85?3 1 90$1 99.0 98.S 9 993b6 9 816123 370 9 370 9 M.003 1930.2 110e.2 0 1260 1.M & ? 8 9876 94.0 C7 0 0.06679 as 016820 341 7 341 7 65.005 1934.8 1103 8 0 1242 1 4MO 8 9902 97.0 96 3 9 84812 S.016117 392 4 392 9 M.006 8039 3 1803 3 9 1224 1 8704 8 9920 96 0 95 0 9 81534 0.016114 494.4 444.4 63.004 1939 9 1802 9 0 1896 1.8740 1 9954 95.0 9est 0 79962 8.9M111 416.3 416 3 62.010 SHb.B 1802.5 0 1188 8 8792 1 9440 94.0 93 3 9.? MSS 8 916100 488 6 428 6 68 012 1941 0 1102 1 0 1170 1 8037 3 0006 93.0 98 8 0.?t313 S.086805 441 3 441 3 60.014 1M1 6 1101 6 8 1182 1 8081 3 0033 92.0 (f.se 5 78932 0 014102 494.9 464 5 99 016 8M2 5 1101 2 0.1134 1 0926 3 0059 91 0 9ese 0 69013 0 086999 464 1 468 1 94 080 8047.7 1180 8 0 1115 1 0970 f.9066 90 0 St e 8 61653 0 014096 482 2 482 2 S7 020 4 H 3. 3 1100 3 0 1997 S.9015 3 0117 99.0 88 5 9.MHS 6 016993 496 8 4M.0 M.022 AM3 9 1999.9 0 1079 8 9960 3 0139 88.0 07 3 8 43507 5 816090 S11 9 911 9 85.024 1944.4 1999.5 01M1 8 9105 3 01M 87.6 86 9 4 61518 S.916897 547 5 S27 5 94.026 4MB.O 1999.0 0.1943 1 9151 8 0193 46.0 Sles S.99643 4 916985 943 6 1,43 6 53.027 AMS.6 1998 6 8.1984 3 9196 3 0221 SS.9 Seet S.97702 S.086ter M03 MO.3 62.029 AMe.1 1998.2 8.4966 1 9842 3 02e0 84.0 43 0 S.SM72 Septu ?9 877 6 S??.6 S1 031 S pe.? 8097.7 4 9948 1 92ae 3.s275 83.0 Sieg 9.94093 S.9160?? S95 5 995 6 60.033 1947 3 1997 3 settet 1 9334 8 0303 82.0 taas S.98M4 S.8160?e Me.1 614 1 49 035 1947.6 8096.9 0 9951 8 9300 te0331 01.0 80 0 S.SM43
- 0.016072 633 3 633 3 68.037 8048 4 10%.e 0.9932 1 9436 2 0369 80.0 79 9 5 49949 8 916070 653 2 653 2 47.038 1949.0 1996.0 0 9914 8 9473 2 0387 79.0 12 0 9 41441 S.016067 673.8 673 9 44.6e0 1949 5 1995 6 S.9895 8 9520 3 9415 70.0
??.8 0 49919 8 04606S 695.2 695 8 45 042 1950 1 1995 1 9.9877 1.9567 8 0ee3 ??.0 1
he 0 44440 Se816063 717 4 787 4 44 043 1950 7 4994.7 9 9868 1 9684 8 04'2 76 0 75 9 8 489M 8 016060 740 3 740 3 43 045 8051 2 1994 3 4.9439 1.M61 3 9500 75.0 l 1 14st 9 41500 N.9160S8 764 1 764 1 48 046 8051 0 1993 0 0.6821 1 9709 f.0929 74.0 73.s e.401 >7 0.s16056 fee.s 704 0 41 008 3052.4 1943 4 8 8002 1 9756 3 015e 73 0
' 72 0 9.30eet 6.416054 814.3 814 3 40.0e9 195J.9 1993 0 5.0783 8.9004 2 0t 41 72.0 71st 8 37949 18 0 M852 840 8 840 9 St.050 195$.9 1952 8 0.0?M 1 9852 a.9616 71.0
? Sat 8 36092 18 016050 864 3 MS.4 34.052 19 feet 1992 1 8.8745 1 W80 3.Me5 70 0 8958 8 36073 B.014048 896 9 996 9 37.053 8 01>e .6 1991 7 8.0727 8 9948 2.M75 M.D St.s S.53a09 a.916046 946.S 416 5 36 954 1955 8 1991 2 0 8784 1.M96 3 0104 M.8 C?st S.307e0 0 016044 957.2 917.i SS.095 1 9'35.? 1990.8 0.0609 8 0045 3 0734 67.0 86s0 0 8486 0 086943 999 0 949 1 34 956 1854 8 1990 4 S.M10 8e0994 2 07M M.0 84 3 S.18648 S.016H1 1842 1 8022 8 33.957 8856.9 1999.9 S.Mt1 Ret 143 a.8794 M.f Stee S.99497 S.036039 1996 5 1950 8 38.058 1857.e 1949 8 0.0632 8 0192 feeste M.#
63 3 S.84400 4.tM034 3092.3 Se9A.3 38.058 1054 0 1899.0 B.M13 3.bfet 8 685e 63.9 Stet S.87494 S.8160M 1139 3 1134.2 30 999 1994 3 1948.6 8.9913 8 4291 8 9485 M.8 Sise 0 86S84 0 0M035 1M7 6 1867 6 #9.859 1899 1 890s.2 0.0$P4 8 4H1 R.9919 61.0
. 40st Setteil S.61M53 a 6 1907 6 88oM0 1999.? 1987.7 0 9955 3 0391 2 9946 40+0 i 99 9 S.84?13 S.816032 1 1 1 1 27.068 1960 2 1087 3 8.9536 8 9448 R.9977 09.0 SSs0 S.83843 0.016831 1992 2 1292 2 Me te0 1MO.8 1996.9 8 06 % f .M 91 97 0 S.83060 9.956e39 8 8000 Se t 1337.0 1331.0 RS .M0 1961 4 1944 0 S.9497 E.9542 8 1039 $1.f-96 8 S.88143 3.016689 1843 6 1383 6 34,059 1961 9 1986.0 8.9478 8.H93 8 8070 S4.0 95.8 S.81392 S.816837 1432 0 1432 0 32.059 lut S 1945.6 0. MSG 2 0M4 2 1182 5f6.9 84 0 9 80625 8 016826 8482 4 1442.4 34t.0Se 1963 1 1985.1 9.M39 8.M95 8 1134 S4.0 Sast 8 19843 S.916825 1534.? 1834 0 88.85e AM3 6 8804.7 8.M19 8 8746 8 1165 S3.0 Stet 8 1916S 8.086024 1989 2 1889 2 30.057 1964 2 1944.2 0 0400 8 0799 2 1897 52 0
$1 0 S.18449 S.916823 BMS.9 AMS.9 39.966 1@64.? 3083 6 S.8380 Settet 3 1230 $1.0 96 9 Self?M S.016823 1794 8 1794 8 18.054 1MS.3 8043.e 0 8361 8 9901 telM2 60 0
#930 S.87844 9 01682r S? Met 1966 2 17.953 1965 9 1882 9 8.9993 49.0 46 9 0.16914 0 0M1 8 1294 9 016041 1830 0 2830 0 36.051 10M.4 1942.5 0 8321 8 1996 8 1327 48.0 C?e3 9 19994 S.98 M23 1896.5 1996 5 15 949 AM?.0 1942.1 S.9381 8 8088 8 8360 47.0 46 9 0 88384 8.stSafo 3965.7 8943.? 14.M t 8861 6 1M1 6 8 8844 8 1141 8 1393 46.0 SteS 9 44?tt 4.916420 8437.7 &$37 0 13. pee S Mt.1 1981 2 49.0 44 0 0 14192 9 916019 Settet 8 1164 8 14M 3112 8 3113 0 12.k1 1968.? 3000.7 8.8348 3 1887 8 1499 44.0 l 43.0 S.13609 6.016e19 8891 0 3191 0 18 038 8M9.3 1940.3 8 8382 8 1873 3 4e93 43.9 4839 S.13443 3.g!M19 3272 4 3373 4 10.835 AM9 8 30?9.9 0.gett 8 1385 2 1527 48 8 C8st D.14Mt 8 814819 8397.3 8387 3 9.831 8070 4 1979.4 8 8188 8 18?8 8 1960 48.0 j 48 3 S.18143 8 0M019 8445 0 9445 8 8 827 8971 5 1979.0 9.3168 8 8432 8 1994 48.0 35s0 9 18698 S.9M019 SS34 0 3138 0 7.823 1871 5 1978.5 8 8142 38 0
- 8 11849 S.e Me19 3 3487 8 8629 39.0 8634 8 8464 2 6.cle left. 19?s.1 s.saag 3 3941 3 1M3 38 0 37 0 9 80815 S.816019 3734.4 2734.4 Setta 1872 7 18??.? 8 0101 8 1996 8 1697 37.0 6
h3 S.14395 S.tMete 8639 0 2439 0 4.00s 1973 2 8077 2 0.9441 8 1661 2 1782 36.0 [ SEst S.99991 S.886480 9948 1 9940 1 3.002 1973 8 88?6 8 S.0MP 34s0 3.l?M 2 1767 36.0 j 8 00600 S.316021 3e61 9 3063 9 1.996 8874 4 18?6 4 8.9641 8 1762 3 8002 34.0 8830 8 04443 Se tMea t 3840 7 3180 7 Setet 10?e.9 1975.9 38 418 Sete S.81M22 4348.4 s.sett 3 1s57 4 1831 31.0 5302 4 B 0003 1975 9 8075 5 e 9000 8 3372 8 1872 32.010 3 s. S.S MS M . S.nM22 Sn.4.7 aM .? .nn 1975 5 10tl.S . Den 8. set 3 8.u?3 M.0 l e Tw su?ct Mac See. ame mutu u l
Volume, ft*/lbm Enthalpy, Btu /lbm Entropy, Btu /Em x R Temp.
' Temp. Pre F psia . Water Evap. Steam Water Evap. Steam Water Evap. Steam F
s s. S',
A r A, s A, 8: 8 a8 8, tu.0 M3.o* e.019n 1.33M 1.M w .07 9 m .0 a03 9 e.Mn e.n46 1 4MS .n.0 SM.463 e.019M 1.H 91 1 3n2 .05.7 uC3 7 s.u 14 0.nu 1 5004 te.0 RM . 0 0.no s.9034 M.0 m .0 St9.M9 e.ntu 1. Mn 1 40?S 403 9 .?M 00.1. 0 n03 6 8 98?? 1.u 3 382.391 S.81990 1 4104 1 4374 401 3 802 2 1203.5 8 9964 1 9042 424.0 483.0 9 9940 9 9181 1 9061 482.0 482 0 p!9 949 S.91997 1 4492 1.4M2 399 1 30s.3 1203 3 304.780 0 61394 1 4000 1 4991 896 9 806 3 1803 1 9.Mll 0 9145 1 5000 430.0 t83 0 S.9890 8 9899 1 5099 410.0 418 0 348.le3 0 01990 1 5131 1 9320 394.1 800 3 1803 9 9.01887 1 9463 1.M51 392.S S10 2 1802 8 - S.99M S.9853 1 5112 416.0 413 0 899.617 8 9848 8 9897 1 9137 414.0 414.0 899.801 8 01864 1 5003 1.9991 390 3 812 2 1802 6 0 01881 1 6162 16MO 348 1 414 3 1802.s 0 9416 Se9341 1 5151 612.0 414.0 888 894 410 0 SM.694 0 01870 1 6810 1.M97 386 0 816.t 1802 1 0 9791 8 9385 1 5176 410.0 1 1 68?? 1 1964 383 4 1801 9 0 5166 8.9429 1 5195 404.0 1 280 0 8?S.600 0.01875 818.t 0 8742 0 9413 1 521S 406.0 (S6es 36e.611 8 91872 1 72S3 1.74e1 381 6 080 1 1301 7 Ste.S 398.789 0 01870 1.Mo D 1 1827 3?9.4 882.0 1801 5 0 9717 6 9816 1.Sf34 484.0 1 4423 3??.3 884.0 1301 8 S.M92 0 9962 1 5254 602 0 teSep 888 942 0 01M7 1 0037 1 4444 1.M30 375 1 48S.9 1801 0 8.M67 8 9607 1. Site 400.0 C48 0 847.899 0 01064 0 9651 1 5893 898.0 841.6?? 8.81M1 1 8462 1 0048 37# 4 887.0 1800.7 0.Me2 398 8 370 8 889.7 1800 4 e.ht? 9 9696 1 5313 396.0 396 0 836 193 9 91890 1 9891 1.94?? 394 0 830 807 0 01885 1 9731 1 9917 364 6 831 6 1800.2 8 8992 8 9?al 1 9333 394.8 433 4 1899.9 S.SH f 0 9786 1 9392 M2.1, 898 0 888.516 0 01053 8 0!Se 8 0M9 3M.S 300 0 339.381 0 01890 8 0649 8 9883 M4 3 835 3 1899.6 8.9842 0 9831 1 8372 300.0 8 1186 8.1311 362 2 83?+f 1899 3 0 8516 8 9016 1 5392 380.0 308 0 815.830 Settet? 1199.0 S.9491 0 9921 1 5412 386.0 306es 318 811 0 01044 8 1616 8 1801 M0 0 839 0 8 8180 8 230s altet See.8 1890 7 0 94M 8 9966 1 9412 384.0 304 0 805.89e 0 01848 0.M41 1.Mu SM.0 388 set.M7 e.n.M 8.MM 8.tui MS.? Me.? 11M.= 1.nia 8 3170 8 3393 MS.6 044.5 1898 0 S.9416 1 00ST 1 0473 300.8 aseet 199.789 S.01SM 398 0 191 480 Se988M 8 3716 8.3900 3St e 346 3 1897.7 8 5390 1 0103 1 9493 370.0 8 48?9 8 4462 Set.3 Ms.1 1897.4 8.SMS 1.elet 1 9513 376.0 Shea SM.817 0 01881 0 4340 #.8194 1 9034 3?4.0 313 8 ' tea.See 0 01489 8 48S7 8.5039 MT.3 0e9 0 1897.0 l 8.M33 345 0 ett.6 illM.? 8. Sale E.8840 1 999e 378.0 StaeS &??.6et 0 01aN 3 9451 8 6M4 8 6844 348 9 883 4 1896 3 0 5299 E.0806 1.SS?S 370.0 3? Sea $13.3M 0 01083 8 5863 1 0332 1 5995 368.0 360 0 469.113 9 81821 8 6691 8 6873 Sec.0 099 1 is95 9 8.?$19 330 7 094.9 1896 6 0.Sf38 1 0378 1.M16 3M .0
' 366 0 144.968 0. State 8 7337 1. M37 364.0 363.8 668.903 9 91816 8 8002 8.810e SM.S SSS.6 -1895 2 9. Salt 1 8484 8 0687 8 8868 33e.4 Ms.ti 1894 8 0 8147 1 94?1 1.MS8 368 0 364 5 606.917 5 41813 368 0 854 918 0 01e11 8 9392 8.9973 333 3 M8 1 1194.e 0 9161 1 9517 1.H?e M0 0 3.0890 330 2 M 3. C 1894.0 9.9135 3 9964 1 569P 398.0 354 0 	 179 0.01889 3 0117 356.0 9 01806 3 0463 3.104e 388 1 868,9 1893 6 8 8110 1.M11 1 8721 M6.e 34 Sense S.5884 1.Mle 1 87e2 300.0 384 0 841. Tee 8 01094 3.1632 3 1812 386 0 MT.2 1893 8 3.8603 383 9 64 9 1898.7 S.9558 1 0705 1 9763 352.0 358 8 138 138 0 01001 3 8483 3.3418 381 0 878.6 1898 3 - e.S$12 1 0?ft 1.S?se 300.0 388e9 134 694 9 81?99 3 3#30 3es.O 0 01797 3 4070 3.4250 319 7 472 2 1891 9 0 980i 1 0?t9 1.S806 344 0 831.tet 317 6 813.9 1891 4 9.4940 1 8047 1.SS27 SM.0 346 0 887.?S1 0.01794 3 49e3 3.813t a. sees 3.See9 344.0 0 01798 3 5034 3.6013 315 5 8?S.S 1891 0 8.49M 343 0 884.430 8??.8 1890 5 9 4981 1 9948 1 98?1 348.0 848 0 841 177 Seel?te 3 6788 3 6931 313 4 311 3 Ste.0 1890 1 0.4948 1 9990 1 9892 340.0 St048 817.998 9 41987 3.1099 3.?870 338.8 338.0 184 873 0.01785 3.MTS 3 8883 309 2 000.5 1889.6 4 4816 1 1038 1 8914 3.9999 381 1 488 1 1889.1 0.eef 0 1 1986 1 99M SM.0 336 0 $11.M0 0 01783 3 9681 8 48u4 1 113e 1 99S8 SM e t 33#.9 898 888 9 91781 4ettle 4.9896 308.s %883.? 1888 7 4.1966 Sof.9 SSS.3 1888.8 0.4N6 1 1181 1 9981 338.0 338 0 498.907 0 01??9 4 148 4.3M9 30s.s 306 9 Sas?.? 0.a178 1 1831 1 6003 330.0 330 0 843.948 0 01?M 4 8398 8 4749 1 1888 Se68tl 888.0 380 0 Set. Set 9 0!??e 4.4030 e.edes 894 7 ges.S 1887 8
, 306 8 97 946 0 01773 4.8805 4.5382 896 6 Steet 11M.? 8 4719 1 1389 1 6048 SM.0 4.6595 89e.6 991 6 1886.2 8.4692 3 1378 1 4071 384.0
.%
- 384 0 94 4M S.017?0 4.M10 893.8 1885 7 9 4M6 1 1427 1 6093 338 0 3 Bast 98 895 9 81M4 4 7669 4.1846 898 8 398.e 994.8 11M.8 8e4640 1 14?? 1 6116 380.0 388 9 99.M 3 S.91M6 4 0961 4 913e 318.8 318 8 87e137 8 41764 S.0899 5 84?1 80s.3 896 3 1884.7 8 4613 1 1986 1 4139 316 0 S.1673 S.Ste9 806 3 097.9 8184.1 SetSM 1 1976 1 6162 Sthe 94.688 S.etM1 1883 6 S tMO 1 1686 1 6105 314.0 313.s 88 893 e.91759 S.3096 S.3373 See.# 999.4 318 0 0 01797 S.4066 S.4742 802 1 981 8 8483 1 S.4833 1e1676 1 6809 318 0 79 983 S.6860 80s.0 908.S tatt.S 8 4SM 1 1?f6 1 6832 310.9 318 9 ??.M? Seel?tS 6 6089 8 4479 3 1??6 1 6856 308.0 308 9 19.433 9 81993 5 9655 S.?sse 878.e 9e4.0 slet.s 306.0 306 9 T3 861 S.9a?? 5.9462 8?S.9 995.8 1181.4 0.e4S3 1 1827 1 6279 '
S.ti?ti 8?J.8 SFt.s 1880.9 9 4486 3 18?? 1 6303 394.0 384 8 98 119 8 0!?e9 6 0955 6 1130 308.9 M8 0 49.838 9 91947 6 8849 6.8064 f?Les Sec.S $100 3 0 4399 1 1980 1 6327 Mt.1 916.0 18?9.7 9 4378 4 1979 1 63S1 300.0 49.005 Sett?t$ 6 4443 6 4698 890 0
'300.0 898 0 48.881 S.0!?e3 6 6139 6.6913 867 7 911 8 1179 8 8 4345 8 8031 1 6375 6.8433 848 6 913 0 18?s.6 0 4317 4 8988 1 6400 896.8 996 9 63.904 9 01?st 6 8859 S.4800 8 813e 1 6484 894.8 394 9 41.194 0 91?M ?.0745 7.8419 861.S 914.5 1878 9 7.8475 M1 5 911 9 18??.4 Se4MS 8 8106 1 6449 898 8 398 8 99 368 9 01134 7 8301 T.0603 899.4 917.4 11M.8 S.48M 1 8888 1.u ?3 898.0 890s4 St.950 0.01?M ?.4430 888 8 888 8 98.795 8 01784 7.66M ?.6807 887.4 918.8 !!?6.8 8 4800 8 8890 3 6890 806.8 896 8 94 083 S.81?&& ?.6916 7.9009 895 3 988.3 1875 6 S.4181 183e8 1 6923 804.4 0 91730 8 1880 SeteS3 883 3 981.? 1875 8 8.419e 3 8MS 1 6640 894 0 Stette 8 3908 891 8 983 8 1194.4 0.4186 1 8048 1 6974 802.5 888 0 SS.?se 0 98?80 3 3789 849 8 994.6 1173 0 0.409e 1 8M1 1.H99 808.8 200:4 49 800 0 01?t6 S.6847 6.MM 85
- O
- 1
" Table 2. Properties of Saturated Steam and Saturated 5 ster (Pressure) l Press. Temp. Volume, ft*/lbm Enthalpy, Btu /lbm Entropy, BruMbm x R Energy, Bru/lbr psia F Water Evap. Steam Water Evap. Steam Water Evap. Steam Mater Steam g # #g i 84 i is g 1 l #g "I U g
800.8 S18 21 0 02007 8 5400% 0.M496 509.0 689 6 1899.4 790.0 S16.76 s.02083 S.55584 3 7181 8.?tS1 1 4863 S06.? 1885 2 S.67667 508 1 691 6 1899.? 8 7094 s.?682 1 4176 S0S.0 1115.4 'j 700.0 515.30 S.92060 8.b63?? 9.584S7 506 3 693 6 1899.9 0 7076 8 7114
??0 0 $13.43 e.820?6 0 57198 1 4190 503 3 1135.S 0 5926? S04 5 695.? 1200 2 0.7058 8 7146 3 4204 901 5 3115 7 160.0 518 34 S.02072 e.S4025 04009? S02 7 697.? 1200 4 8 7040 0.7170 1 4218 499 8 1885 9 750 0 518.04 E.02069 9.$4880 0 60949 S00 9 699 8 1200.7 740.0 999 32 0 7022 0 7210 1 4232 494 0 1886 1 )
8 92045 S.99?SF 0 61822 499 1 701 9 1200.9 8.7003 0.?f43 1 4246 730 0 68?.78 0 92061 S.6 Del? 8.62719 494 2 1816 3 ' 497 2 703 9 1201.2 0 6905 9 7276 1.4760 494.4 1816.4 780.0 546 33 8.92058 8 61541 0.6h39 495.4 TD6.0 1201 4 9.6966 p.7309 718 0 504 67 S.Sach 0 62530 1 4275 492 6 1816 6 S.64545 493 5 704 1 1201 6 4.6947 se?343 1 4290 490 8 lite.e
?98.0 443.08 8 98988 S.63605 61 655 % 491 6 710 7 1201.8 S.6928 490.0 901.48 S.82047 8.73?? 1 4304 464.9 1816 9 8 64507 0.MS$4 449.7 ?!2.4 1802 1 S.6908 S.7411 1 4319 e40.0 499.M S.88043 S.65538 8 67501 447.8 457.1 1837 1 '
498.22 Tle.S 1202 3 8 6409 8.?446 1 4334 485 2 1817 2 l 670.0 S.82039 4.MS9e 8 66637 teS.8 116.6 1862 5 0.6869 0.7481 I e68.0 496 57 0 82036 S.67648 8 69724 483 9 1.4350 483 3 1817.4
?!8 8 1802.7 S.6449 0.?S16 1 4MS 411 4 !!17.S 699 0 494 99 0 88832 0 68811 0.70043 481 9 1/20 9 1202 8 S.6828 640.0 493.19 S.68828 S.69967 B.71995 0.?SS2 1 4341 479.4 1817 6 491 48 479.9 723 5 1803.0 0 6808 8e7948 1 4396 4??.S 1817 8 630.8 S. State 6.?!!S9 8.73183 4??.9 'F25 1 1803 2 8.6787 0.7625 680.0 489.?4 SettS21 S.78307 0.74400 475.8 727.1 1 4412 475.5 1817 9 610 8 487.98 1803 4 8 6766 8.?Mr 1 4420 473 5 1118.0 S.82917 S.73654 0 75671 473 0 729.7 1863 5 S.6745 e.??se 1 4449 471 5 1484 1 480 0 486 3f 0 08013 3 74962 3.?6975 471 7 732 0 1963.? 8 6723 8.??38 990.0 484.nh S.82909 S.M312 1 4461 M9.5 3118 2 0.74321 449 6 734 2 1803.8 8 6701 0.???? 1 4478 447.4 1110 3 !
SSO.S 468.Tl 9 980M S.???te 8.79712 467 5 734,5 870.0 1203 9 S.M?9 9.?$16 1 4495 465 3 L188 4 I l 400.fi S.62002 e.?91a8 0 81150 465.3 738.?  1 8.MS? 8.?eSS 1 4812 ! 968.8 478.64 S.01998 0 896&9 0 02637 463.1 463 2 '1188 5 741 0 1304 2 8.MM f.?S99 1 4549 461 8 1818 5 SSS.S 4?6.94 8 01994 8.stin3 p.341?? 460.9 743 3 1804 3 S.?t36 949.8 4 fl .81 S.01990 0.M11 1 4547 484.9 1818 6 9 93781 0.8S??! 484.7 749.? 1804.4 S.6507 S.?9?? 14MS eM.? 1818.? S30 0 473.05 0 01966 0 35437 0 87423 4S6.5 744.0 .5 580.0 471.07 8 81982 0 07165 9 49137 0.the 0 0019 1 4643 454.w tile.? 454 2 781.4 1304 9 0 4540 0.0062 1 4601 452 3 1818 8 510 8 849 98 9 01978 S.48937 s.90918 451 9 ?St *? 1804.6 8 6835 8 8105 1 46#0 480.0 1814 0 000.0 461.01 0 01975 S.9078? e.92762 449.S 751 1 1204,7 e.6490 e.8148 490.8 464.93 S.91971 S.tt?!O 8 94681 447.2 1 4639 447.7 1888 8 Vl f.6 1804.7 8.M65 S.4193 1 4488 445.4 1188.9 400.0 4M.82 0.01947 S.e4711 S.M& T T 444.7 ?s00 1304 0 S.6439 S.8338 1 46?? 443 0 1818 9 470e8 4M.68 0 01963 0 46?"3 0 98? % 442 3 702.S 1804 8 464.0 4688.50 8 01999 81g a 3 1 80921 046413 8.8284 1 4697 440.6 1830 9 439 0 7%6 0 1804 8 S.6387 0.8331 1 4718 438 8 1818 9 494.8 4M.90 0 019S4 1 01224 1 63179 437.3 767.5 1804.8 8 6362 8.8378 448.9 454.03 8 91950 1 05535 1 4738 435.7 1814.9 430.0 4f.1 74 3 83t?) 434.8 '/70.0 1804.8 0 6332 0 8427 1 4759 433 2 1818 8 0 01946 1.MOS A 3.07998 432 2 ??2.6 1804 0 9 6304 0 04?6 1 4701 430 6 1118 0 480 0 449.40 8.98948 1 0M31 1 10673 489 6 ?? Set 1804.? 8.6th 8 85t? 1 4461 418e8 447.84 480 0 !!! Set 9 91938 1 15E31 1 13869 486.9 ???.8 1804 7 4 6847 8 9978 1 4829 485 4 1818 7
.498.0 444 60 0 81534 1 14162 1.16095 484 2 780 4 &Se4.6 S.6887 400.9 448 13 0 01930 p.8630 1 4447 482.7 1818 7 488.9 3 17132 1 19961 441.4 783 1 1804 5 S.6187 0.0683 1 4470 430.0 1818 6 4M.61 S.91989 1 88262 1 32177 418 6 786 8 1804.4 S.6194 S.0738 1 4094 417.2 1810 5 378 9 437.04 9 81988 3.SM35 1.fM56 415.7 te8 6 1804.3 s.4135 8 8794 Steet 434.41 1 4918 414.4 1118 4 S.01917 8.M993 1 88910 418 8 791 3 1894.1 8 6092 8 8951 1 4943 411 5 1118 3 368.e 431 73 8.e1918 1 3e643 1.3 554 469.s 794 2 1ae4 0 e.6est 8e0909 345 8 484.M t.91919 1 4964 4et.6 111s.1 1.M 464 3 795.
pt.9 338.8 4M.99 427.99
..SiMe 8 41995 3 32542, 1.M49 1 36587
- 1. M.482 M 4M.. m.6 1843 &M3 9 9 8.6443 8.MM .S.pp9
.m9 3,4931 1 4994 4e7 1 1818 1 4.S.5 1:1 0 ;
l 1 30413 405 3 794 5 1803 7 Settet S.9999 1.S068 404 1 1187.9 838 0 4M.18 9 01983 1 38S?? 3 48488 483 7 199 9 ? 6 S.9993 0 9030 1.Seit 482 8 1187.8 Set.0 4M.?S 8 81901 1 40707 1 48600 403 1 001 4 1833.S 8.9974 388 8 403.31 8.01899 0 9061 1.M 35 481.0 1117.7 l 1 48902 1.44001 400 5 884 9 1803.4 S.99 % 0 9992 1 9848 M9.4 1817.7 ' 315.9 481.M 8.91996 1 48164 1 4?Me 398.9 e64.4 1303 3 8 9938 s.9134 318.8 480 36 S.9J894 1 4?t94 1 49390 397 3 leSett MT.0 1887.6 305 8 4&4.87 995 9 1203 8 8 9020 S.9187 1.9876 396 2 1817.5
- 9. Meet A.e90Aa 3 51793 MS.? 887.4 1803 9 4 9001 S.919e 1 9091 394 6 1817.4 j 308.0 417.39 0,91889 3.n8384 1 94274 394 0 895.0 418.01 Steet 1893 9 8.9442 8 9483 1 9105 Mt.9 1117 8 S.M at? 1 94940 3 56&SS MS. 3 410 4 1863 7 S.SM3 8 9857 1 8180 M1 3 1117 5 898.9 414 88 4.91be% 1 5799? 1.99402 Me.6 812 0 1868 6 S.S$44 906 9 413.61 0 01882 S.9891 1 5135 399.6 1817 0 3 443M 1 6221e 304.9 813 6 1802 4 8 54#4 0 9346 1 9160 387.9 1816.9 400.0 411 87 S.91880 1 43169 1.69949 387.1 SAS.1 > 3 8 8006 8 9M1 1 81M 3e6 1 1116.7 S?$.9 499.48 S.01878 1.M101 1 67978 345.4 416 7 1802.1 S.S?M 394.8 487.90 e.918?S 1 69137 1 71013 S.9397 1.Sitt 304.4 1116 6 383 6 418 3  9 0.8764 0.9433 1.!t97 Mt.6 1116.S 865.0 4M.13 0 01873 1 78204 1 74187 381 7 880.0 1801.? 6 8743 Sete?9 6. file 300 8 1816 3 I 868.8 484e44 8 81070 S.79948 1.??418 3?9.9 Sta.6  8 e.9782 8.900s 1. W e 379.0 lite.t 496.0 488.78 j 0 01864 1 79938 1 44002 378 0 8R3 3 1#01 3 8.8?st 0 9846 1 8947 3??.8 1816 0 l 898.0 400 97 8 8186S 1 49458 1 84317 376 1 895 8 nattel 8.5679 84S.8 399 19 8.01863 1.e6107 3 87970 8 9005 S ethe 378 3 1815 8 374 2 886 6 �.9 9 9687 0.96ft 1 8881 373 4 1885.6 948 4 397.39 S.91860 1.e9994 1 91769 378 3 488 4 1A00.6 8.9434 335.9 896.56 9.98897 0.9ul 1 5899 3?!.4 till.S 1 9306? 3 98?tS 370 3 430 1 1804.4 S.9411 0.9?M 1 8337 369 5 1819 3 438.9 983 78 9 91898 1 97991 1 99944 MS.3 431 8 1898 1 S.9948 8.9748 1 8336 MT.S !!! Set 838.0 301 88 S.elena 3 08791 8.M143 364 3 433 6 1899.9 0.SM4 0.9790 1 8364 MS.S 1814.9 889.8 309.08 S.0188D 8.M 779 8.SM39 M4. 2 838 4 1899.6 Sets 40 9.9034 1 53?4 816 8 407.91 M34 1814.&
0 01M7 4 11469 8 13315. 362.1 437.2 1899 3 0 8815 S.9878 1 5393 Mt.3 1884.4 818.9 884.91 0 01044 8 86373 8 14817 389.9 SM. ! 1899.0 0.9490 8.9933 806 9 883.88 S.SAMS 1.M13 399 2 1884 2 8 81548 8 83M9 397.7 M8 9 1898 7 S.8468 S.9949 1 94h 357 0 1813 9 808 0 381 44 0 014M 8. Mete 4 3873s MS.S 848 0 1898.3 8 9438 1 9016 1.9464 394 0 1113*?
_y
' Temp. Volume, >. ft*/lbm Enthalpy, A. Bru/lbm Entropy. s. Bru/lbm x R Temp.
F F' Pre *6. Psia 12. 13. 14. 16. 12. 13. In. 15. af. 13. 14. 15. Pres 6.. ps Inst 291 96 205 88 209.66 223 03 PUS.96 205 08 209 56 213 03 201.96 205.88 209 56 213 03 Isat 44t. 6 team 42 394 30.057 20 043 26 290 1846.7 1148.2 11e9.6 1150.9 1.7731 1.?667 1.7607 1 1352 Sat. 5:es*
&at. Sater 8 0166% 0 01668 0.01670 0.01673 170.01 176 00 177.71 181 21 0 2970 0 3029 8 3085 0 3137 Se t. E s te 760. 89.981 SS.362 68.602 47 971 140s.S lace.b 160s.4 ince.t 2 0609 2.9500 2 0*38 2.0362 750.
Teo. 89.e83 be.902 S0 975 47 573 1603.6 1603.5 1e03.5 3403.a 2 0568 2 0499 f.0397 2 0321 ?*0. 730. E4 98b St.442 68.664 47 1?* 1398.7 139e.6 1396 6 1396.5 2.8127 2.De38 f.0356 2 0260 730. 720. be.487 53.982 be.121 46.778 1393 7 1393.7 1393 6 1393 6 2 0485 2 0397 f.0315 2 0238 720. 710. 57.989 S3.523 49.49e 46 376 1388.e 1888.8 1388.7 1388.7 2.D443 2.8355 2.0273 2 0197 710. 760. 67.491 S3.063 49 2e? el.9?e 13e3 9 1383.9 1383 8 1383.8 2.0401 2 0313 2 0231 2 0155 700. 490. 56 993 E2.603 68.e40 46.S?9 1379.1 1379.0 1379.0 1378.9 2.0399 2 6271 2.0189 2 0117 690. 640. b6.e94 52.163 te.n13 e5 180 1374 2 1374.1 1374 8 137e.0 3 0316 f.&220 2 0166 2 0070 680. 670. St.996 SS.683 47.9e5 es.781 1369 3 1369.3 1369.7 1369.1 f.0274 2.01e5 f.0103 2 0027 670. , 660. 55 494 Sletta 47 568 **.382 1364.4 136e.4 1366 3 1364.3 0 0230 2r0142 2 0060 1 9983 660. 650. SS.000 50.762 47.130 43 983 13S9.6 1359.5 1359.5 1359.6 U.018? 2.0090 f.0016 1 99eo 650. eng. 54 501 60.302 46.793 43 584 13Se.7 135e.? 13Se.6 135e.6 1.01e3 2.00$e 1 9972 8 9896 640. 630. be.003 49.042 46 275 43 184 1349.4 1349.8 1349.0 1349.7 P.0099 2.0010 1.9928 1 9951 6:0. 420. E3 504 49.381 45.84e 42 785 1345 1 13*i5.0 13en.9 13e6.9 R.0054 1 9965 1.9883 1 9807 620. 610. E3 00b 48.928 45.420 42 306 1340 7 33#e0.2 1340 4 1340.0 R.0009 1 9921 8 9458 1 9762 680. etc. E2 607 68.460 44.992 41 946 1335 4 1335.4 1335 3 1335.2 :1 9964 1 9875 1 9793 1.9717 600. 290. E2 000 68.000 44.564 41 5e? 1830.6 1330.5 1330.5 1330.4 8 9910 1 9830 1.9741 1 9671 590. 180.
- St.509 47.S39 44.136 e1 187 1325.e 1325.7 1325.? 1325.6 8.9472 1 9784 1 9701 3 4625 580.
570. St.810 4?+078 43.70e 40 78? 1328 0 1320.9 1320 9 1320.8 1 9826 8.9737 8 9655 1 957a 570. See. be.510 h6.617 43 279 40 307 1316 2 1316.1 1316 1 1316.0 1.9779 1.9690 1 9608 1 9532 560. 250. be.011 44.166 42 851 39.987 1318 4 1h11.4 1381 3 8311 2 1 9732 1 96e3 1 9561 1 9496 950. 540. 49 512 45.694 42.423 39.S87 8306.7 1306.6 1306 5 1306.4 8 960s 1 9596 1.9813 1 9437 Dec. 530. 49.012 48.233 41.99e 39 107 1301 9 1!801. 8 1301.? 1301.6 1 9636 1.9548 1 9465 8 93e9 530. 520. 44 512 44.??! 41.56S 38 786 1297.8 Elt9 7.0 1796 9 1296.9 8 9580 1 9499 1 9el? 8 93ec S20. Sig. 44 042 44.310 41 136 38 305 1292 4 1792.3 1292 2 1292 1 8 9539 1 9450 1.9368 1 9291 510. 500. 47 512 43.848 40.707 37.985 8887.6 1207.5 1287.4 12s7.3 8 9490 1.9401 1.9319 8 92*2 500. e90. 47.012 43.386 40 277 37.See 1282.8 178J.8 1282.1 1282.6 8.Dese 8 9351 1.9269 1 9892 490. 480. 44 512 42.923 39.e48 37 182 1278.1 h278.0 8277.9 1271.8 1.9390 1 9308 1 9218 8 95et 480.
, 470. 46.011 alt.o68 39.eSe 36 781 8273 4 1273.3 I 2 1773.1 1 9339 1.9250 8.9168 1 9091 e70.
460. 46.510 48.998 38.900 36 379 1268.0 1768.5 1768.e 1268.3 1 9288 1 9199 8 9116 1 90e0 460. 450. 46.009 41.535 38.5be 35 9?? 1263.9 1263.8 1263.? 1263.6 1.9236 1.9147 3.9065 1.0908 450.
**W. Se.507 41.072 30 127 25 575 1299.2 1755.1 825e.9 1250.8 1 91t4 8 9095 1.9012 1 8935 680.
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Re6. 84.369 31 691 F9.4b &?.428 8164.2 186e.S 186=.2 1163.9 1.7998 4.7906 8.7421 1 17e1 teO. 230. 33.352 31.tte 38.9,66 37.D03 1860 1 1859.0 1859.4 1859 1 8.?930 1 7838 8.?? 8.?672 230. 220. &3 33 30.730 = =e. 1.7460 a.?t6e i.76.S2 210. ge am m #0.S12 89fth* 85s.3 1:55.0 my n;g2 Et.hs 8154 6 2 8 '' 8 76 8 ?*80 b3bdc t 220.
**C-a00. e.01664 e.e 6 4 . 0164. 0.0166. 16a.09 36e.e9 a6a.09 16e.09 0.29 0 0290 0.79e0 0.2940 t00.
190. 8 81657 0.01657 0.616b? 0.01657 SSs.0a 154 05 158 05 150.05 0.2707 0 2787 Cette? 0.2767 190. 880. 9 01451 0.81651 0.01651 0.01651 1a8.03 lae.01 3e8.01 gas.02 s.3631 0 7631 f.7638 0.7631 188. 170. S.35695 S.0 8 64 S 0.08645 0.016et 137.$9 137 99 137.99 138.00 8.2473 0.te?3 0.te?3 0.te?3 870. 160. 8 61639 4 91639 9.01639 0.01639 127.98 St?.98 127.90 127.98 0 2313 0.2313 0 2313 0 2313 860. 160. 8 01634 0.08634 0.0165e 0.0163e 187.97 117.97 117.98 117.98 0 2160 0.2150 8 2150 0 2150 150. leg. 3,68629 9.01629 0.01629 0.01629 j 107.97 107.9? 107.98 107.90 0.8985 0.1985 0.1985 0 89e5 leo. 130. S.08625 S.08625 3.01623 S.01625 97.9P 97 90 97.99 97.99 8.1817 S.1817 0 1817 0 1817 130. l 120. 8 06b29 0.01620 0.016s0 8.01620 87.99 88 00 88.00 83.00 0.8646 8.1646 8.16e6 0.1646 120. 888. 0 81686 0.01616 0.01616 8.01616 ?#.08 70 01 78.08 78 02 8. 84 F3 S.8472 9.le72 0.1472 110. 400. S.01613 9 81613 0.81613 9.81613 64 03 60 03 68.03 68.04 8.1795 9.1795 0.1795 0 8295 100.
- 90. 8.01610 9 91638 8.81610 9.01630 S8.05 St.CS S8.05 54 06 S.1115 S.5815 0.1115 0 8115 90. ,
- 80. 5.s8607 8.01607 9.08607 0.01607 as.07 40 07 40.0? as.De 0. p9 52 p.p%32 0.9932 6.0932 80. d
- 70. 0.0168b 5 98605 0.01695 0.016c3 Se.ee 38 09 38.09 38.09 0.0?es 8.0?al 9.0?s5 0.07e5 70.
60 6 41603 S.81603 0.01603 0 01603 28 09 28 10 28.10 28 80 8.tSSS 9 8156 S.055t 0 0555 60.
- 50. 8 61608 8 01602 S.01602 8.08602 18 09 10 09 18.09 18 30 0 0361 0.8368 0.0361 0.0368 S0.
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SECTION FIVE Theory of Nuclear Power Plant Operation, '* Fluids and Thermodynamics . 5.01 QUESTION (1.0) MULTIPLE CHOICE (Select the correct response.) The Residual Heat Memoval system is operating at a flow rate of 1000 Gallons Pe r Minute (500,000 pounds ger hour) with a RHR Heat Exchanger inlet temperature of g55 F and an RHR Heat Exchanger outlet temperature of 324 F. (Cp of water is 1.0 BTU /LBM) What is the Megawatts Thermal power (Mw) being produced by the decay heat in the reactor?
- a. 4.55 Mw
- b. 2 27 Mw
- c. 9.0 Mw
- d. 1.55 Mw 5.01 ANSWER (a) (1.0)
( h: mCpAT, h: 500,000 LB/HR* 1 * (355 - 324') Q = 15,600,000 BTU /HR 6 1 Mw = 3.41*10 BTU /HR 1.55*10 7 / 3.41*10 6 = 4.55 Mw) REFL3ENCE: SONGS 1 SYSTEM DESCRIPTION SD-SO1-320 AND WESTINGHOUSE THERMAL-HYDRAULIC PRINCI?LES, CHAPTER 3, Pg.3-9. i 005000 K/A 5.04 l l 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i
l 5.02 QUESTION (1.0) MULTIPLE CHOICE (Select the ccrrect response ) For the do11owing Axial Flux Difference (AFD) statements indiente'which statement is true.
.. Axial Flux Difference varies only with power level, i
- b. When power is distr 3buted equally throughout the core the AFD is one (1),
- c. As power levels increase the AFD becomes less negative.
- d. An AFD that is negative indicates that there is more power being produced in the bottom of the core.
'I 5.02 ANSWER "d"
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 8, Pgs. 25 and 20. l l
>n 5.03 QUESTION (0.5)
TRUE OR FALSE For beginning of life (BOL) cycle 9 xenon transients a xenon transient will peak at 7 to 8 hours after a shutdown from 100% power. 5.03 ANSWER
" False"
REFERENCE:
SONGS 1 CYCLE 9 BOL TRANSIENT XENON WORTH FOLLOWING REACTOR SHUTDOWN (pcm). 192006 K/A 1.13 3
i, f l .' 5.04 QUESTION (l'.0) .. MULTIPLE CHOICE (Delect the best response.) The reactor is at Hot sero Power End of Life (EOL) with l Control Bank 2 rods at 200 steps. The " control bank 2" rods l hre pulled out of the core at 5 inches per minute for 3 minutes. (Reference graph 5.04-1.) What is the rate, pcm/sec, at which reactivity is being l ndded to the core? (1.0) 1
- a. 0.40 PCM/SEC
- b. 0.46 PCM/SEC
- c. 1.00 PCM/SEC
- d. 1.22 PCM/SEC 5.04 ANSWER "c" (1.0)
[(5.0 in/ min)(1 step /3/8 in)(4.5 pcm/ step)(1 min /60 sec) l 1.00 pcm/sec or 86.07 pcm/ min)
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAP. 7, Pg. 71, SYSTEM DESCRIPTION i SD-SO1-400, Pg.4, SONGS 1 CYCLE 9 CURVES l 4.6-3 and 4.6-5. l l l h 4 L_--_-----_------ - - - _ ---
l l 1 5.04-l 1 l
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I \ I 1- 4 1 1 1 r e r... ... ... ... ..., ...,... ... ...;... aso-----eo-seo-~se--ano naam aus : - - ROD POSITION (STEPS WIT 2RAWN) { l DIFFERENTIAL RDD WORTH l VS. STEPS WITHDRAWN BANKS 1 AND 2 - l AT NZP. DOL AND EDL p . i " 96 .
L d 5.05 QUESTION (0.5) TRUE OR FALSE { l Decreasing the speed of the charging test pump (G-42) will j decrease its volumetric flowrate and discha:rge head i caprbility. s (0.5) { 5.05 ANSWER False (The volumetric flow rate of the positive displacement. pump decreases, however, the head capability reinains the same.) (0.5)
REFERENCE:
WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES, CHAPTER 10, Pgs. 10-36 thru 10-55, f i l I i 5
5.06 QUESTION (0.5) TRUE OR FALSE ,, 1 During natural circulation an increase in primary system pressure is one of the indications that natural circulation has been established. 5.06 ANSWER
" False" (0.5)
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIFLES CHAP. 14, Pgs. 15 thru 29 and SO1-1,0-60, Pg. 27. O _ _ _ _ _ _ _ _ _ _ _ _ _ _ -__ l
5.07 QUESTION (0.5) TRUE OR FALSE - A pump with a locked rotor wil] draw less current t.han the same pump would draw at normal 100% flow conditionc. l 5.07 ANSWER
" False"
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAP. l 10, Pgs. 10-36 thru 10-55. i 7
I l
'l
. 1 5.08 QUESTION (1.0) l MULTIPLE CHOICE (Select the best response.)
l What speed would a 1200 rpm pump have to be increased to in order to in order increase the pump discharge head from 100' l to 200'? (1.0)
- a. 1697 rpm
- b. 1512 rpm
- c. 2400 rpm
- d. 1897 rpm l
l 5.08 ANSWER "a" {(N(2) / N(1))2 = 200/100 N(2) = 1.41(1200) = 1697 rpm)) l
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAP. 10, Pgs. 10-30 THRU 10-55, SYSTEM DESCRIPTION SD-SO1-310, Pg.11 AND 13. 8 l
l 5.09 QUESTION (0.5) MULTIPLE CHOICE (Select the correct response.) ~ What would be the resulting effect on a reactor power calorimetric calculation if the throat all of the main feedwater flow venturies became larger.
- a. There would be no effect on the calorimetric calculat. ion, cin;e all of the flow signals would be equal.
- b. The calorimetric calculation would indicate a lower than actual power level.
- c. The calorimetric calculation would indicate a higher than actual power level.
- d. The calorimetric calcu)ation would not vary due to compensating input from the main steam flow meters.
5.09 ANSWER
.. b
(Q il 46 h since the mass flow -M e will indicate a smaller value the total output the S/G will appear to be lower therefore a lower calametric value.)
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES CHAPTERS, 11 AND 12, Pgs. 11-22 AND 12-39, I l l 1
)
l l 9
I i i l I ( L.10 QUESTION (2.0) Prior to an outage the steam generators were producing steam at 780 pria with a Tave in the reactor coolant system of 575 F. Dpring the outage 12% of the steam generator tubes were plug 6ed. (USE STEAM TABLES PROVIDED) What will the new full power steam pressure be if the RCS , Tave is to remain constant at the same power level? (2.0) L 5.10 ANSWER i h = UA AkT , (0.5) 6 = constant : 100(575 - 515) = 88(575 - Tsteam 2) (0.5) 100%/88% ( 575 - 515 ) = 575 - T steam 2 576 - 1.14 (60) =Tsteam ,c = 507 F (0.5) T sat for 507 F is 725 psia +/- E psia (0.5) i.
! REFERENCE WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES e CHAP.7, 9 and SYSTEM DESCRIPTION SD-SO1-280 l
Pgs. 3, 4 and 14. 9 9 9 T., 4
+
.f i i 10 A---- _ _ _ __ _ _.
5.11 QUESTION (1.75) ,, The treactor is shutdown by - 6% Zi K/K, all rods are fu13y insorted wieh the most reactive rod being worth 2.5% diK/K (CONSIDER EACH QUESTION SEPARATLEY)
- a. Ein t is K for the reactor when it is shutdown by l 6% ZsK/K? "II (1,25) b .. What is the " Shutdown Margin" of the reacto.v. in % /iK/K?
(0.5) 5.11 ANSWER
- a. tiK/K : 0.06 = 1 - K,ff /K ff (0.5) 1 : Kgff + 0.06 Keff (0.5) 1: 1.0G K eff l
K,ff : 1/1.06 : 0.94 (0.25)
- b. 6% - 2.5% = 3.5% 4LK/K, (0.5)
(Shutduwn Margin 1:, the amount the reactor would be subcritical from its present condition, all rods fully inserted, with the most reactive rod fully withdrawn.)
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAPTER 7 and SONGS 1 TECHNICAL SPECIFICATION DEF. 1.22. I 1 I l l
)
l L__ i
t. l l 5,12 QUESTION (2.0) l . L The reactor is operating at 50% power when a reactor coolant pump trips. Asrume no reactor trip and turbine output remains conctant. How will the following parameters change (increase, decrease or remain the same)?
- a. Flow in the remaining two reactor coolant locps. (0.5)
- b. Core delta T (core outlet to core inlet). (0.5)
- c. Feedwater flow to the steam generator in the loop with the tripped RCP. (0.5')
- d. Steam generator pressure. (0.5) 5.12 ANSWER
- a. Increase. (0.5)
- b. Increase (0.5)
- c. Decrease. (0.5)
- d. Decrease, (G . 5) -
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAP. 10. 12 -~ _ - _ - _ _ . - _ _ _ _
l' L h l' L 5.'13 CUESTION (1.0) l MULTIPLE CHOICE (Select the correct response.) >. A steam leak has been reported in the 400 lb steam supply piping to the condenser steam jet air ejectors (assume the steam is dry saturated steam while in the pipe). (USE STEAM TABLES PROV1DED) Which statement below best descibes the steam after it has escaped from the pipe. a.-Saturated steam at 780 btu /lbm and 325 F.
- b. Super heated steam at 780 btu /lbm and 450*F.
- c. Super heated steam at 1205 btu /lbm and 325 F.
- d. Satursted steam at 1205 btu /lbm and 450 F.
5.13 ANSWER
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAPTER 2. i i 1
'l i
l i k I i l i I l I i 13 !
)
I 5.14 QUESTION (1.0) MULTIPLE CHOICE (Select the correct response.) - I What is the st'artup rate (SUR) if Reactor power has i increased from 1000 cps to 5000 cps in 30 seconds.
- a. 1.0 DPM
- b. 1.2 DPM
- c. 1.4 DPM
- d. 1.6 DPM 5.14 ANSWER 1 "c" (1.0)
(P = P O 10 In (P/P O) SUR(t) In(10) In (5000/1000) : SUR (30) In (10) ' 1.61 = SUR (30) 2.30 SUR : (1.61/2.30 (30 sec)) 60 sec/ min : 1.40 DPM ) RFFERENCE: WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS, CHAPTER 7. i I ( l l 14 - _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - i
5.15 QUESTION (1 0) MULTIPLE CHOICE (Select the correct response.) Which of the following statements concerning Samarium is true?
- a. After a reactor shutdown samarium peaks at 200 hours and begins to decay off after 400 hours for an end of life core.
b -. 50% equilibrium samarium reactivity worth is equal to 100% equilibrium samarium reactivity worth,
- c. After shutdown samarium remains constant and begins to decay off after 400 hours for an end of life core,
- d. 50% equilibrium samarium reactivity worth is is one half of 100% equilibrium samarium reactivity worth.
5.15 ANSWER
.. b "
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 4, Pgs. 4-30 thru 4-36. l 1 l 15
. _m
i l 5.16 QUESTION (1.0) MULTIPLE CHOICE (Select the correct response.) - I An estimated critical position (ECP) has been calculated for a reactor startup 4 hours after a reactor trap from 100% equilibrium conditions. Which condition will cause the actual critical position i (ACP) to be lower than the ECP?
- a. A delay in the startup until 6 hours after the reactor trip.
- b. The steam dump pressure set point was lowered by 100 psi prior to the startup,
- c. Unknown to the operator a rod finger is separated from its spider assembly during the reactor trip.
- d. The actual boron concentration is 30 ppm higher than the predicted boron concentration.
5.16 ANSWER
. . b
REFERENCE:
SD-SO1-190 e MAIN STEAM SYSTEM, SO1-3-1 PLANT STARTUP FROM COLD SHUTDOWN. 16 l - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ]
i 5.17 QUESTION (0.5) True or False With a decrease in power the fuel temperature also decreases. At lower fuel temperatures the Doppler coefficient becomes more effectiva. .(0.5) 5.17 ANSWER "True" (0.5)
REFERENCE:
WESTINGHOUSE REACTOR C071E CONTROL CHAPTER 2, Pgs. 23 THRU 30. s
I
't ~5.18 QUESTION-(0.5)
TRUE OR FALSE - The Doppler coefficient becomes more negative over core life because of an increase absorption of' neutrons by Plutonium 240. 5.18 ANSWER True
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL CHAPTER 2, Pgs. 23 THRU 30. I j l , 4 i i 1 I I I 1 l 18 _-_________________-___-____--_a
l 1 l 5.19 QUESTION (1.0) : MULTIPLE CHOICE (Select the correct response.) " Figure 5-19-1 is.a plot of the temperature profile across a new fuel rod and an End of Life fuel rod respectively. Two reasons for the temperature profile change for the helium gap from the new fuel element to the spent fuel element are; (1.0)
- a. Changes due to the increased corrosion buildup on fuel cladding surface and increased fuel cladding creep due to irradiation.
- b. Changes due to fuel pellet swelling from fission gasses and increased fuel cladding creep due to irradiation.
- c. Cha,nges due to decreased cladding thermal conductiv2ty and increased fuel cladding creep due to irradiation.
- d. Changes due to decreased cladding thermal conductivity due to irradiation and fuel pellet swelling from fission gasses.
5.10 ANSWER
.. b
(The temperature profile of of the helium gap changes due to fuel cladding creep and fuel pellet swelling (due to fission product gasses). (0.5)
REFERENCE:
WESTINGHOUSE THERMAL HYDRAULIC PRINCIPLES, l CHAPTER 3, Pgs 3-57 thru 3-63. - 19
5-19~l - i l t I a etun '
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- 5. .- l i
.. i l
t
1 S.20 QUESTION (O.b) 1 MULTIPLE CHOICE (Select the correct response.) What in added to the reactor coolant system to raise the pH of the primary systen? (O.5)
- a. H0, (hydrogen peroxide).
22
- b. NH,22 (hydrazine).
c .. NH 0H, (ammonium hydroxide). 4
- d. LiOB, (lithium hydroxide).
5.20 ANSWER "d" , I
REFERENCE:
SD-SO1-310, CVCS Pgs. 30, 40 & 41, and SO1 - 10 , Pgs. 2 thru 5.
)
i l 1 l l 1 l l i 1 l 20
1 1 l 5.21 QUESTION (0.5) - 1 MULTIPLE CHOICE (Select the correct response.) l What is added to the volume control tank to control' 1 dissolved 1 oxygen when Tave is 350*F or greater? (0.5) l
- a. H2 (hydrogen).
- b. N2 (nitrogen).
- c. N02 2 (hydrasine).
- d. NH 0H (ammonium hydroxide).
4 5.21 ANSWER
REFERENCE:
SD-S01-310, CVCS Pgs. 30, 40 & 41, and SO1-4-10, Pgs. 2 thru 5. 21
5.22 QUESTION (0.5) - MULTIPLE CHOICE (Select the correct response.) What is added to the volume control tank for oxygen control when'the reactor is in Mode 5? (0.5)
- a. H2 (hydrogen).
- b. N (nitr gen),
2
- c. NH2 2 (hydrazine).
- d. NH 0H (ammonium hydroxide).
4 5.22 ANSWER
.. c "
REFERENCE:
SD-SO1-310, CVCS Pgs. 30, 40 & 41, and SO1-4-10, Pgs.. 2 thru 5.
)
)
l i l l l l 22
5.23 QUESTION (0.5) MULTIPLE CHOICE (Select the best response.) What type of detector is used for the source range? (0.5)
- a. Compensated ion chamber.
- b. Fission chamber.
- c. Boron Triflouride proportional counter.
- d. Uncompensated ion chamber.
5.23 ANSWER "c"
REFERENCE:
SD-SO1-380, Pg. 4. I 1 l l l 1 l
l- . 5.24 QUESTION (0.5) MULTIPLE CHOICE (Select the correct response.) How does the intermediate range nuclear instrumentation compensate for gamma radiation? (0.5)
- a. No compensation required.
- b. Pulse height discriminator.
- c. Campbelling circuit.
- d. Compensated ion chamber.
5.24 ANSWER "d"
REFERENCE:
SD-SO1-380, Pg. 6. i i l 24
.i c
1 5.25 QUESTION (0.5) i
,, I TRUE OR FALSE Increasing the temperature of a fluid will increase the net positive suction head of a pump, i
5,25 ANSWER J l False (0.5) '
REFERENCE:
WESTINGHOUSE THERMAL-HYDRAULIC PRINCIPLES, CHAP, 3. i l a 1 i l l l 25
5.26 QUESTION (0.5) , MULTIPLE CHOICE (Select the correct response.) What type of gamma discrimination is used by the source range nuclear instrumentation? (0.5)
- a. No compensation required.
- b. Pulse height discriminator.
- c. Campbelling circuit.
- d. Compensated ion chamber. i 5.26 ANSWER "b" 1 1
REFERENCE:
SD-S01-380, Pg. 4. l l 1
)
i 26 \_---_-___ _ _ _ _ _
I l I I l l
)
5.27 QUESTION (0,5) MULTIPLE CHOICE (Select the correct response.) Unit 1 has had the complete reactor core package removed for I internal vessel inspection. ! t Which of the following will HQI have an effect on the shape I of the 1/M plot during the fuel loading process? I
- a. The strength of the neutron' sources in the core. j i
- b. The location of the neutron sources in the core. l J
- c. The location of the neutron detectors around the core.
- d. The order of placement of fuel assemblies in assigned ;
locations. l 4 5.27 ANSWER "a" (1.0) i l l
REFERENCE:
WESTINGHOUSE FUNDAMENTALS OF NUCLEAR REACTOR j PHYSICS, CHAPTER 8. j I 1 3 1 i I ( 1 27 l l l
5.28 QUESTION (1.0) MULTIPLE CHOICE (Select the best answer.) - Initially the reactor is at "zero" % power, beginning of life (BOL), Tave : 555"F, with boron concentration at 1500 ppm. Using figures 5.28-1 and 5.28-2; What boron change is required for a power change to 75% power? (1.0) (Do not consider Xenon.)
- a. 140 ppm.
- b. 138 ppm
- c. 133 ppm
- d. 127 ppm 5.28 ANSWER "d" (1.0)
[ Power defect = -840 pcm, differential boron worth =
-6.6 pcm/ ppm,
(-840 pcm/-6.6 pcm) = 127 ppm)
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTROL, CHAPTER 5, and CYCLE 9 CORE DATA BOOK. I l
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5.29 QUE51 ION (1.0) .. l MULTIP!,E CHOICE (Select the correct reiperme. ) What is the amount ofscondensste'deprestion (subcooling) in ! I a congensar operatir.F. at 1 psia m.d a condmi>, ate temperature of 95 F7 (USE STEAM TABLES PSOVIDED) s . G. r*? E t 16.3 F t 0
- c. 1.6 F 0
- d. 1. '7 F 5.29 ANSWER t
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REFERENCE:
WESTINGHOUSE THEhMAL--E.^DRA!!LIC I RINCIPLES CHAPTEIJ '2, i vd ASME STEAM TAILES. 193004 K/A 1.11 q L se d i L. 4-29
l - ! U 1 l j 1 l l l 5,30 QUESTION (0.75) l MULTlPLE CHOICE (Select the correct response.) I l USE FIGURE 5.30 TO ANSWER THE FOLLOWING QUESTION. j Why does Xenon reactivity initially decrease upon a power increase (po$nt "A")? (0.75)
- a. Increase in the Xenon concentration from a decrease in burnout rate,
- b. Decrease in the Xenon concentration from a increase in burnout rate.
- c. Increase in the Xenon-concentration from a increase in-burnout rate,
- d. Lecrease in the Xeno.n concentration from a de(rease in barnout rate.
1 5.30 ANSWER "b" (0.75)
REFERENCE:
WESTINGHOUSE REACTOR CORE CONTRGL CHAP.4. Pg. l 4-24 192006 K/A 1.11 l END OF SECTION TIVE CONTINUE ONTO SECTION SIX i ( l f l
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l, i k SECTION SIX PLANT SYSTEMS 4 DESIGN, CONTROL, AND INSTRUMENTATION 6.01 QUESTION (1,0) The pressurizer is connected to the reactor coolant system (RCS) in three locations.
- 1. Where is the pressurizer surge line connected to reactor coolant system? (0.34)
- 2. Where are the pressurizer spray lines 1 & 2 connected to the reactor coolant system? (0.66) 6.01 ANSWER
- 1. Pressurizer surge lino - loop B hot leg (between the RV and the S/G). (0.34)
- 2. Pressurizer spray line (1) - loop A cold leg (between the RCP and the RV). (0.33)
Pressurizer spray line (2) - loop B cold leg (between the RCP and the RV). (0,33) REFERENCE : SD-SOI-280, Pgs. 5 & 6 of 46. l f l I l
- 31 L.-__ _ _ _ - _
6.02 QUESTION (1.5) The Pressurizer level controller (LC-430F) is in the aut</ manual-set posigion with the pressurizer st programn.ed level for Tave of 551 F. (Conrider each question separetly.)
- a. What will be the final pressurizer level if Tave is decreased to 535 F, assuming no operator action or trips?
(1.0)
- b. Whnt would be the response of the CVCS letdown system flow rate if the pressurizer level control switch was placed in agto/ cascade with reactor power at 75% and Tave at 551 F? (Increase, decrease, remain the same.)
(0.5) 0.02 ANSWER
- a. Programmed level for Tave of 551 F (16.9' or 37.5%
because level must be controlled by the operator). (1.0)
- b. Remain the came, (Actual pressurizer level will be higher than programmed 1cvel requireing a decrease in charging flow, letdown will not change.) (0 5)
REFERENCE:
SD-S01-280, Pgs. 25 and 35 of 46 and SD-SO1-390, Pg. 18. 32
w 6.03 QUESTION (2.0) The pressurizer power operated re]ief valves (CV-545ank 546) are designed to limit RCS pressure to below the relief pressure of the pressurizer safety valves,
- a. What are the NORMAL PORV (CV-545 and CV-546) set points in Mode 1 operation? (0.5)
- b. Whs.t is the backup actuating power supply to the pressurizer PORVs if instrument air fails? (0.5)
- c. What is the is the electrical power supply to PORV CV-546 (bus and voltage)?
3 (0.5) 1
- d. What is the fuilure position of the PORVs if electrical power is lost? (0 5) 0.03 ANSWER
- a. 2200 psig and 2185 psig. (0.5)
- b. Nitrogen backup for both PORVs. (0.5)
- c. 120 volt vital bus no. l . (0.5)
- d. closed. (0,5)
REFERENCE:
SD-SO1-280 , SD-SO1-150, S01-2.6-3. l i r 33 l p _ _ _ _ . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ -
6.04 QUESTION (2.5) , The rod control system controls the automatic movement of-the control rods.
- a. What is the electrical power supply for to the contro]
rod drive mechanisms? (0.5)
- b. Other than Tref what three (3) other signals are used to develop the programmed rod control signal? (1.5) .;
- c. What signal is used to develop Tref. (0.5) 6.04 ANSWER
- a. 125 VDC (0,5).
- b. Tave, Suelear Flux (NIS-1208), Pressurizer Pressure P minus Pref. (0.5 pts ea.) (1.5)
- c. Pref (Turbine generator impulse pressure or turbine first '
stage pressure.) (0.5)
REFERENCE:
SD-G01-400, Pgs, 5, 6, 37, i 1 34
I G.05 QUESTION-(3.0) I The reactor protection system provids nuclear overpower trips,
- a. What are the three (3) inputs to the shutdown margin alarm permissive P .5? (1.5) l
- b. Besides an automatic and manual rod withdrawal bloch I what other function does the Over Power Rod Stop Permissive, P-1, perform? (1.0)
- c. The Variable Low Pressure Trip (V.L.P.T.) set point is < 872 psig, what condition does the V.L.P.T. protect the reactor against? (0.5) 6.05 ANSWER {
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- a. (0.5 pts. ca. max. 1.5 pts.) l i
- 1. Rod position indication (anolog).
1
- 2. Tave.
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- 3. Delta T.
1
- b. Blocks the raise signal to the main turbine speed change )
notor. (1.0) J
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- c. Departure From Nuc3eate Boiling. (0.5) 1
REFERENCE:
SD-SO1-570. < l 1 1 i
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l 6.06 QUESTION (2.5) The steam dump system provides continuity of operation without a reactor trip during step load changes.
- a. Why is there a 5 F mismatch of Tave minus Tref margin provided before the steam dumps to the condenser-are opened on a load rejection / reduction? (1.0)
- b. What two signals will cause the atmospheric and condenser steam dump valves to blow open, aesume all condenser steam dump system requirements are met? ( 0 . 5.)
- c. How will Tave change if the pressure signal to the steam dump pressure controller is lower then actual steam pressure in the pressure control mode? fl.0) 6.06 ANSWER -{
i
- a. Allows time for the rod control system to take control L prior to the steam dump valves opening. (1,0)
- b. Tave - Tref greater than 5 F and a loss load of 2,10'%. ;
(0,5)
- c. Tave will increase.
REFERENCE:
SD-SO1-190, Pgs. 15, 26, 27 and 4 3. s I i l L i i 36 __ __ _ _---..-_.___--_________________________________)
1 l l l i l l 6.07 QUESTION (2.25) The Chemical and Volume Control System (CVCS) functions as as a safety system during safety injection. l
- a. Why is the Volume Control Tank isolated on a safety in s ection signal? (1.0)-
- b. Why is one charging pump maintained in the " locked out" i condition during normal plant operations? (1.0) !
c, What is the' source of water to the charging pumps during 1 the first stage of safety injection? (0.25) 4 6.07 ANSWER
- a. To prevent the charging pump from becoming gas bound and cavitating (This would be caused by the pump drawing in U2 when the VCT was drained causing pump fai. lure). (1.0) l l
- b. The locked out charging pump is held in reserve to insure its availability in case the other charging pump fails, (for cold leg injection and recirculation) after Safety Injection. (1.0)
- c. RWST. (0.25)
REFERENCE:
SD-S01- 310 Pgs . 3, 9, 10 and SO1-4-6.. I l 31
r l. l G.08 QUESTION (2.75) 1 The Chemical and Volume Control System controls 3etdown" I and charging flow. ' l
- a. Why is letdown flow bypassed around the letdown demineralingrs when letdown flow to the demineralizers enceeds 140 F? (1.0)
- b. Where is the letdown flow bypasseg to when letdown flow to the demineralizers exceeds 140 'F7 (0.5)
- c. Why is a backpressure regulator valve provided downstream of'the Residual Heat Removal heat exchanger in the letdown line? (1.0)
- d. In the automatic mode what system does Chsrging Flow control Valve (FCV-1112) recieve its ficw control signal from? (0.25)
G,08 ANSWER
- a. Exceeding 140 F letdown f 3cw to the diminealizers will damage the resins. (1,0)
- b. The letdown flow is bypassed to the VCT (inlet). (0.5)
- c. Prevents (letdown) flashing in the in the low pressure q piping (downstream of the letdown orifices). (1.0) l 1
- d. From the pressurizer programmed level control. (0.25) l I
REFERENCE:
SD-SO1-310 Pgs. 11, 12 and S01-4-6. j 1 0 1 i i 1 38
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1 1 f I 1 s 2 l 6.09-QUESTION (2.0) i The safety injectior; system is designed to mitigat.e corb ! damage resulting from overheating following a loss of , coolant accident. ) I
- a. What arc the two signals and setpoints for a Safety Injection System Actuation? l (1.0) i
- b. When a safety injection signal is initiated why is there i a 11 second-time delay associated with the main feedwater j pump restarting? (1.0) ;
.1 6.09 ANSWER J l
- a. Pressurizer low pressure / 1735 prig (0.5) 1 I
High containment pressure / 1.4 psig (0.5) l
- b. The 11 second time delay provides time for the feodwater i pump suction and discharge valves tc realign for safety !
injection,(which prevents the injection of unborated f water from the condesate system to the reacter causing I a positive reactivity addition.) (J.0) i l
REFERENCE:
SD-SO1-580, Pgs. 18, 14, 37, Sb-SO1-590 P6 10. ; 1, 1 i 1 I l 1 i l 1 39
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6.10 QUESTION (2.0) The function of'the operational radiation monitoring system (ORMS) ic to monitor and to prevent the uncontrolled release j of radioactivity to the environment,
- a. What valves automaticly close if a high radiation indication is received on R1212 (Containment sphere).
(1,0) {
- b. Where does the Stack Gas Monitor R-1214 provide indications? (0.5)
- c. Mhere does the Stack Gas Monitor R-1214 provide l alarms to? (0.5) l i
6.10 ANSWER ] 1
- a. Closes: POV-9 (Sphere purge supply)., (0.25) {
POV-10 (Sphere purge return), (0.25) ! CV-116 (Sphere equalizing), (0.25) ! CV-10 (Sphere instrument air vent). (0.25) ]
- b. Indications: Radwaste control panel and (control room) i computer indicator drawer. (0.5)
- c. Alarms: Control room and Sacramento (Office of Emergency l Services). ( Candidates may indicate that R-1214 j no longer provides the alarm function to j Sacramento however R-1254 now provides that l function.) (0.5) j
REFERENCE:
SD-501-550, Pgs. 9, 13, 17 & 18. I ( 40 1 6
6.11 QUESTION (3.0) , The auxiliary feedwater system provides feedwater to the steam generatore during abnormal or emergency conditions.
- a. What' signal (setpoint) will automatically initiate auxiliary feedwat-r? (1.0)
- b. What is the power supply (Bus and Voltage) for the motor driven auxiliary feedwater pump (AFW-G-10S). (0.$) j
- c. Other than to establish steam generator water level why is auxiliary feedwater regulated to 150 GPM or less cfter AFW initiation? (0.5)
- d. What are three of the four trips provided f or the motor driven AFW pump (AFW-G-10S) (1.0) 0.11 ANSWER
- a. Less than 5% / S/G Narrow range level. (1.0)
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- b. 480 volt bus 1. (0.5) i
- c. (0.5 pts each 0.5 pts. maximum)
- 1. tdinimise water hammer or
- 2. Control RCS cooldown rate.
- d. (0.33 pts. each max 1.0 pts)
- 1. Low suction pressure (0.04 psig, 30 see after start).
- 2. Lou discharge pressure ( 675 1 20 psig 30 see after start).
- 3. Overcurrent (Thermsl type set locally .at controller).
l 4. Loss of power (Under voltage) l
REFERENCE:
SD-SO1-620, Pgs.4, 6, 8, 14. END OF SECTION SIX CONTINUE ON TO SECTION SEVEN i I-41
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SECTION SEVEN PROCEDURES ,, NORMAL, ABNORMAL, EMERGENCY, and RADIOLOGICAL CONTROL f 7.01 QUESTION (1.0) A reactor +-rip and safety injection has occured. Electrien1 1 power is available and all emergency system have been checked and are functioning. The SI has been identified as spurious. 1 What sre four of-the six criteria for terminat$ng spuriouc j SI? (1.0) 1 7.01 ANSWER (0.25 pts. each max 1.0 ptsc) 1
- 1. Containment conditions normal, a
- 2. RCE Pressure > 1840 psig,
- 3. Pressurizer level > 25%,
- 4. RCS subcooling > 40"F, ,
- 5. AFW flow capability > 195 GPM, OR
- 6. One Steam Generator Narrow Range Level > 10%
REFERENCE:
EOI S01-1,0-12, Fg. 1. l i 1 l f-42
7.02 QUESTION (2.0) - - Abnormal operating instruction S01-2.6-6, 4Ky (System .. Grounds and Faults) states that the time two transformers , or a transformer and a diesel generator are paralleled must .. be minimized for other tnan surveillance testing. > r a. Why must the time two transformers or a transformer and a . ! diesel are paralled on a 4160 volt bus be minimist.W/(1,0) , . ,
- b. What is the time limit for having two transformers or a , .
transformer and a diesel generator paratied on a 4160 volt bus? (1.0) 7.02 ANSWER
- a. The 4160 volt switch gear is not rated to interupt faults that may occur (when a bus is supplied from two , fl _
transformers or a transformer and a diesel generator). (1.0)
- b. 10 to 20 seconds. (1.0) ..
REFERENCL': SO2-2.8-6, Fgs. 3, 5, 7, 12, and S01-9-2 Pgs. 4 & 7. '4, 5 s
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i 7.03 QUESTION (1.0) DELtTED .. Electrical operating procedure SO1-9-2 (4160 V System Operation) provides steps to transfer 4160 volt busses. What automatic actions will take plach if during a 4160 V Drop and Pickup trensfer the bus is de-energised for 12 seconds? (Plant is in mode 2.) (1.0) i 7.03 ANSWER (DELETED) (If the 4160 volt bu6 is not picked up in 11 seconds the following automatic actions will take place:) 1.. Station loss of. voltage will be. actuated (tripping all 4 Ky breakers for that bus) (0.5)
- 2. Auto start signal to the dietel generator (trip cien.L2 to hus tie breaker). '(0.5) 1 i
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REFERENCE:
S01-9-2,'Pg. 7. a l l 4 1 1 1 i 1 1
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l I l l l 7.04' QUESTION (1.0) .. j MULTlPLE CHOICE (Select the correct answer.) ; An operator wil) bc working $n an area 6 feet from a point source that reads 9 REM per hour at a distance of 4 feet. i 1 What will the dose rate to the operater be from the point source? (1,0)
- a. 3.0 REM /HR
- b. 4.0 REH/HR
- c. 5.0 REM /HR ,
- d. 6.0 REM /HR 7,04 ANSWER i
"b" (1.0) l 2
(I g d 7 2 * ;2 dg , (9 rem /hr)(4'/ 6') : I ,., = l 4 rem / hr) ;
REFERENCE:
STA!EriD DOSE RATE CALCULATIONS, 10 CFR 20. l l l l j l 1 45 l
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l l .\ l I l I 7.05 CUESTION (2.5) i l FAgure 7.05-1 is a survey sheet of radiation and <, l contamination levels made by health physics personnel, i I Portions of l'0 CFR 20 Appendix B (figure 7.05-2), Concentrations in air and water above natural background, i is provided, j
- a. What posting is required for the Chemistry Lab ? (3.S)
- b. What posting is required for the CVCS letdown heat J exchanger room? 0.5) !
- c. What posting is required for the RCS sample station?(0,5) l
- d. What areas must be locked or access otherwise controlled j in accordance with 10 CFR 20? (1.0) 7.05 ANSWER
- a. Caution Airborne Radioactivity area. (0.5)
- b. (0.5)
- 1. (DANGER Extremely) high radiation levels - (access prohibited),
- 2. Caution Airborne Radioactivity area, l
- 3. Caution Contaminated Area,
- c. (0,5)
- 1. Caution Radiation Area,
- 2. Caution Contaminated Area or Caution contaminated Area under valves (brem, tape and or rope).
- d. The CVCS Letdown Heat Exchanger Rootn, (0,5)
Valve Operating Room. (0,5)
REFERENCE:
SO123-VII-7.4, POSTING and ACCESS CONTROL,Pgs. 4, 5, 15, 16, and 10 CFR 20. 46 _m
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i 1 1 i 7.06 QUESTION (3.0) The reactor is shutdown with RCS pressure at 450 psig and 200 F. Technical Specification require that two positive barriers be provided between the feedwater and condensate system and the piping connections to the RCS system.
- a. What conditions constitute a " positive barrier" for a pneumatic / hydraulic operated valve? (1.09
- b. What conditions constitute a " positive barrier" for ,
safety injection isolation valves to the reactor coolant system MOV-850A and MOV-850B? (1.0)
- c. What conditions constitute a " positive barrie'r" for safety injection isolation valve to the reactor coolant system MOV-850C7 (0.5) .
- d. What plant condition allows the "two positive barrier" l criteria to be violated? (0.5) 7.06 ANSWER
- a. When valve is closed and the condition tagged with the I respective hydraulic block valve closed. (1.0)
- b. When the valve is closed and tagged with (safety) j switches open. (1.0) 6
- c. The three pole double draw switch must be be connected to the inverter with the inverter output breaker open. (0.5)
- d. During no-flow tests of the safety injection system. ,
OR if RCS pressure is greater than 500 psig. (0,5) j j
REFERENCE:
SONGS 1 TECHNICAL SPECIFICATION 3.3.2. I 1 i 47
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L l i i 7.07 QUESTION (2.0) ] During a loss of secondary coolant accident you have reached the point in S01-1.0-30, (Loss Of Secondary Coolant), where l safety injection can be terminated. ! What are four (4) of the five (5) conditions, as specified ! in S01-1.0-30, that must be met prior to the term $ nation of ; safety injection? l 7.07 ANSWER I (0.5 pts. ea. max 2.0 pts.)
- 1. RCS pressure > 1250 psig and stable or increasing,
- 2. Pressurizer level > 20% ( >50% with an adverse containment),
- 3. RCS sub cooling > 40 F,
- 4. Heat' sink : AFW > 165 GPM flow capability,
- 5. and RCS hot leg. temperatures stable or DECREASINC.
REFERENCE:
S01-1.0-30, EOI LOSS OF SECONDARY COOLANT, Pg. 18. G01-1.0-31, Pg.1. l l l 1 48
1 i l I J 7.08 QUESTION (3.0) Unit 1 is in mode 6 wit'i refueling in progress. As the SRO 1 you are supervising a refueling.
.i
- a. What is the minimum depth of water required above the j reactor pressure vessel flange during fuel movement? J (0.5) l
- b. What is the reason for maintaining a minimum level of water above the reactor pressure vessel flange? (1.0)
- c. What action must you take if a spent fuel element is being moved to the refueling channel and you are notified
)j that one of the two operating source range instruments {
has failed? (1.0)
- b. What is the set point for the source range shutdown high j flux level alarm? (0.5) '
l 7.08 ANSWER j J
- a. 23 feet ( elevation 40'- 3") (0.5) i
- b. Remove (99% of) the gap icdine activity in the event of i '
a dropped (and damaged) spent fuel element, or twelve feet of water above the top of withdrawn fuel assembly so as to limit the dose rates at the top.of the water. (1.0)
- c. Place the element in a safe (conservitve) position. (0.5)
Suspend further core alterations (until source range instrumentation is restored to minimum). (0,5) -
- d. Two (2) times the base count rate. (0.5)
REFERENCE:
501-13-3, Pg. 39, SO1-3-7,Pgs. 2, 3&4, TECHNICAL SPECIFICATION 3.8, Pg.3-88. l l i I l 1
)
49 m_ _ - - - - - - - - - . - - - - - - - - - - - - - - a
i 7.09 QUESTION (1.5) The operating Corcponent Cooling Water (CCW) pump has tripped and you are starting the standby CCW pump,
- a. What charging pump temperatures should you be aware of if CCW system pressure or flow remian low? (0,5)
- b. How is reactor coolant pump seal water maintained if both Charging-pumps must be tripped due to loss of CCW? (0.5)
- c. What RCG 1etdown path is used if centrifugal charging pumps are tripped due to the loss of CCW? (0.5) i 7.09 ANSWER
- a. Charging pump bearing temperatures (max 180 F). (0.5)
- b. The charging test pump is started. (0,5)
- c. Excess letdown flow. (0.5)
REFERENCE:
SO1-2.1-30 Pgs. 3, 8 & 9. 1 i 4 , ) 4 1 50 j l
i l l 1 1 q 1 7.10 QUESTION (2.0) )
. s ,-
)
The plant is being taken from Mode 3 to Mode 2 in , H accordance with S01-3-2 (Hot Standby to Minimum Load). I 4
- a. At what position would control bank 2 rods be in if the reactor just went critical to be in conformance. wi, tit ~ rf this procedure? (1,0) f'
- b. What automatic action has taken place if a startup rate of 42.5 DPM is seen on the nuclear instrumentation? (0.5) !
u
- c. Why must reactor power be maintained below 10% while the j turbine is being latched? (0.5) l i 1
/J 7.10 ANSWER .
- a. Control bank 2 100 steps 1 25 steps'. (1.0)
- b. The control rods would not be able to move out (due P-6 High Startup rate rod stop permissive)e ,
(0.5) q
< i
- c. To prevent a turbine trip - reactor trip. (0.5) {
l
REFERENCE:
SO1-3-2, Pgs. 4, 5, 7, ande13 and SO1-2.1-1 < l Pg. 3. ) I j l i i I g . 'l 1 1 1 51 1 l
./-
hr e' ' f, ,s
. i' '
- f. fv ' ;, ;'i%
3r (,p . , ( 7.11NUfbSTION.(1,0)' As the SRO you are monitoring the Critical Saf ety Function 1 v Status Tree (CSFST).
- f-~
- a. What is the criteria, in accorddnce with the CSFST, for a considering a reactor adequatly-shutdown? (0,5)
-b. As the Shift Supervisor whaI would you look for as a criteria for terminating the monitoring of the CSFST?
/
(0.5) 7.11 ANSWER 1 a. . Zero'or negative startup rate or intermediate range
- SUR more negative than -0.2 DFM.. (0,5)
- b. All' actions and instructions for the applicable event
/have been implemented. (0.5) q (Approval.of the Shift Superintendent is receinlci to discontinue their monitoring.) .
t i 1 1
REFERENCE:
EDI E01-1.0-1,;Pgs.1, 22. 7' .. / 1 t'
/
/
.A' l
j -f P 52
7.12 QUESTION (3.0) For each barrier to the environment there are critical safety functions that must be monitored if the barrier is to remain in tact or be restored,
- a. What are the three monitored critical safety functions for the fuel matrix and the fuel clad? (3.5)
- b. What are the three monitored critical safety functions for the reactor coolant system pressure boundry? (3.5) 7.12 ANSWER
- a. 1. Maintenance of suberiticality, (0.5)
- 2. Maintenance of core cooling, (0.5)
- 3. Control of reactor coolant inventory. (0.5)
- b. 1. Maintenance of heat cinh, (0.5)
- 2. Maintenance of reactor coolant system integrity, (0,5)
- 3. Control of reactor coolant inventory. (0.5)
REFERENCE:
EOI 501-1.0-1, Pgs. 11 thru 10, 1 1 53
,',i g.
'[ .
p
'[ i8 - 't
- g P
)
3 ; 5;
, s f'
t .h .(
( ,,,' , v r < t. , a
< g ,
,3 ,
1 ,c; .+ 4 , t l ,
.. l' i 6
.c ' ,
)q .
7.13 QUTSTION (1.0),, , l < l The reactor ha:., sustdineh'94ihrge,breah LOCA. The opergtcr.: ; are ti ansf e.aing., Yrom' cold lea re':1rculatior.: to hot leg
. i recirulat.i.bni c
'.- . . l c ,.
b i ' L 1 h~ What are the tub reacNos for shifting from cold leg l recirculation ta hgt legsrecirculationi) , (1.0) 1 1
< t
- 1 i 7.13 SNSWER .
4 l
) )
- 1. To terminatcr boiling in the core (if the. break is in
)
tne cold lea) . , i. (0.5) !
- 2. Prevent budo11 precipitation in the core. '
, (0.5) 1 4
REFEkENCE: EOI SO1-1:U k4, Pgs -1, N, 9 rand 301-i.0-123 ! Pg. 17. i r o, i l 1 l
\
l I i l t
\
0 1
.. J
'l .
t i s hF t l 54 _. ______t_: _ _ _ _ - _ - _ _ - -_. _ _ - .
g - , .
,l ' &
ir
, s:
n f 7.14 QUESTION N1,0) v
.- ., M!JLTIFLE CBCICE (Select the correct answer. )
g 3, How long will a previously unexposed operator bc: able te ctay in a root if the gamma / beta d^se rate was 900 mrem /hr
.m i' !
without erceed'2ng the 10 CFR 20 quarterly limits for whole body radiation? (1.0) a 30.6 hours i
- b. 8.3 hours k c. 2.8 hours c
, d. 1.4 lhours l
7,14 ANSWER "d" (10 CFR 20 quarterly limit = 1.25 rem ; i {1.25 rem / O.90 rem /hr] ! 1.39 hrs or 1.4 hrs )
REFERENCE:
STANDARD DOSE RATE CALCULATIONS, 10 CFR 20. s END OF SECTION SEVEN CONTINUE ONTO SECTION EIGHT I Y, 7
+
I l l I 1 1 7 55
, l l
l . SECTION EIGHT
. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 8.01 QUESTION (1.0)
What two conditions mus+, be met in order for all of the reactor coolant pumps to be de-energized in Mode 3? (1.0) 0.01 ANSWER
- 1. No operations are permitted that would cause dilution of the reactor coolant system boron concentration, (0.5)
- 2. Core outlet temperature is maintained at least 40 F below saturation temperature. (0.5)
REFERENCE:
SONGS 1 TECHNICAL SPECIFICATIONS 3.1.2, Pgt. 3-6 AND 3-7. 1 4 56
s b 8.02 QUESTION (1.0) Technical Specification 3.1.1 states that if the specific activity of the reactor coolant is greater than 1 micro curie / gram DOSE EQUIVALENT I-131 for greater than 48 hours ; the plant shall be brought to hot standby with Tave less i } than 535 F. q = What is thg basis for bringing the plant to hot standby with Tave < 535 F? (3.0) 1 1 8.02 ANSWER l l
- Prevents the release of activity from a steam generator tube rupture, (since the saturation pressure of the reector coolant is below the lift pressure of the atmospheric relief valves). (1.0) l l
I
REFERENCE:
TECHNICAL SPECIFICATION 3.1, Pgs. 3-3 and 3-4. 57
r 8.03 QUESTION (2.0) The Technical Specifications for modes 1, 2, & 3 requires the auxiliary feedwater pumps and the auxiliary feedwater storage tank be operable.
- a. Why must the auxiliary feedwater system be operable in Modes 1, 2 and 3? (1.0)
- b. What volume of water must be in the auxiliary feedwater storage tank for it to be considered operable. (0.5)
- c. What are the two unit 2 soutces of water to the unit 1 Auxiliary Feedwater Storage Tank. (0.5) 8.03 ANSWER
- a. Ensures that the reagtor coolant system can be cooled down to less tha 350 F from normal operating conditions in the event of a total loss of power. (1.0)
- b. 150,000 gallons of water (23' +/- 1.5'). (0.5)
- c. (0.25 pts ea max 0.5 pts.)
- 1. unit 2 makeup demineralized or ,
- 2. unit 2 condenscte storage tank.
REFERENCE:
TECHNICAL SPECIFICATION 3.4, s.4.3, and 3.4.4. and SD-SO1-620, Pg.16. 58
i 8.04 QUESTION (1.0) I As a Shift Superintendent you can approve actions that depart from a LCO or Technical Specification in an ' emergency. In accordance with 10 CFR 50.54 what are the two criteria ) used to justify a diviation from a LCO or Technical Specifications? (1.0) 8.04 ANSWER
- 1. Protect the public health and safety, (0,5)
- 2. No action consistant with licence conditions and Technical Specifications that can provide adequate or ,
equivalent protection is immediatly apparent. (0.5) i l itEFERENCE: 50123-0-1, Pc. 6 and 10 CFR 50.54 (x). 1 1 J 59
l-i 1 l l l ! i i i I ! 8.05 QUESTION (1.~$) j l 1 An individual begar, day shift turnover at 6:30 AM and assumed the duties of the Control Operator at 7:00 AM. He i had 1 hour for' lunch from 2 pm to 2 pm, and was due to be relieved at 4:00 FM. The operators' relief did not show up for work at 4:00 PM. ;
- a. How long can this control operator continue to remain on shift, without a break, before he is in violation of-Technical Specification.n requirements for overtime 4na 24 hour pericsd? (0.5)
- b. What is tne mhnimum break period between work periods after a person has worked the maximum overtime for one 24 hour period? (0.5) i
- c. What is the maximum number of hours, according tn Technien1 Specifications, en individual can work in a seven day period (nat including' shift turnov6r an1 meal time)? (G.5) 8.05 ANSWER
- a. 8 more hours or until midnight ( 16 hours max not including zhift turnover and meals). (0.5)
- b. 8 hours. (0.5)
- c. 72 hours. (0.5)
REFERENCE:
SONG 3 1 TECEINIChb SPECIFICATION 6.2.2 and S01-14-23, Pg. 2. 60
1
)
{ i j 8.06 QUESTION (2.0) j i 4
- s. What is the minimum solution volume of hydrasine for containment spray additive? (0.5)
- b. ' Why is hydracine added to the containment spray? (0.5) i
- c. Why is Anhydrous Trisodium Phosphate stored in the 1 containment? (0.5)
- d. Where is the Anhydrous Trisodium Phosphate Stored in the containment? (0.51 8.06 ANSWER i 0
- a. 150 gallons ( when ghe primary system is above 200 F, mode 4 - Tave > 200 F). (0.5)
- b. Post LOCA (acci@.nt) iodine removal. (0.5) c pH control (after a LOCA). (0.d)
- 4. In the containment sump. (0.5)
REFERENCE:
TECHNICAL' SPECIFICATION 3.3.4, Pg. 3-36, I i 1 l l, l l 1 1 I 61 j
8.07 QUESTION (1.0) MULTIPLE CHOICE-( Select the correct response ) - The fuel cladding is the first barrier against fission product release to the enviornment. Which of the following responses correctly deceribe how overheating of the fuel cladding is prc ented, according to Technical Specifications?
- a. Restricting fuel operation such that the reactor coolant operates at superheated conditions.
.b. Restricting fuel. operation to within the nucleate boiling regime.
- c. Restricting fuel operation such that the reactor coolant never exceeds subcooled conditions.
- d. Restricting fuel operation to within the steam cooling regime.
J
- ANSWER (1.0)
"b"
- REFERENCE J
SONGS-1 Technical Specifications 2.1 l i l 1 l i i ! j ) 4 1 : l
- l. 62 l
- l. . __ _
i
i
)
8,08 QUESTION (3.0~) 1 The diesel generators must be operable in Modes 1 thru 4.
- a. What three criteria have to be met in order for each of i the diesel. generators to be considered operable? (1.5)
- b. What two actions must be taken within one hour,.per the i Technical Specifications, if one of the diesel generators j is declared inoperable? (2.5) 1 8.08 ANSWER
- a. Each of the two diesel generators must have:
L.L l'. A separate day.containing a minimum of 290 gallons of fuel oil. I (0.5)
- 2. A separate fuel storage system containing a minimum of 37,500 gallons of fuel oil. (0.5)
- 3. A separate fuel transfer pump. (0. 5 ).
- b. 1. The operability of the twes offsite transmission circuits must be demonstrated, (0.75) !
- 2. The operability of the operable diesel generator must ce demonstrated (Per Tech. Spec. 4.4) (0.75)
I
- l l
REFERENCE:
TECHNICAL SPECIFICATION 3.7, Pgs. 3-80 & 3-81. l i G3
l i i 8.09 QUESTION (2.5) The unit is in mode 6 operation. o l l
- a. Per Technical Specifications, what are the minimum electrical bus requirements for Mode 6 operation? (1.5)
- b. What action is required if these minimum electrical source requirements are not met? (1.0)
)
l 8.09 ANSWER I
- a. 1. one 4160 volt AC bus, (0.25)
- 2. one 480 volt AC bus, (0.25) 1 3s AC vitel buses 1,-2 & 4, (0.75) l
- 4. one DC bus (including at least one full capacity '
battery charger, and batte.ry supply per bus). (0.25) k
- b. With less than the minimum required AC/DC electrical j sources suspend all operations involving core alterations l or positive reactivity changes. (1.0) {
l
REFERENCE:
TECHNICAL SPECIFICATIONS 3.7, Pg. 3-38. ' I l i I l 1 l l l 64
- t. _-. .
i i j 8.10 QUESTION (2.0) The reactor may not be made or maintained critical unless j the safety injection system is operable and the effective leakage from the recirculation loop cutside of the containment shall be less than 625 cc/hr. l,
- a. What is the minimum level in RWST when the SI system is required to be operable? (0.25')
- b. What are the minimum and maximum boron concentrations for l the RWST7 (0.5)
- c. What is reason for maintaining the leakage from the recirculation loop outside of the containment to less l
{ than 625 cc/hr? (1.25) { l 1 8.10 ANSWER I I
- a. 50 ft or' approx 240,000 gallons. (0.25) ;
i
- b. min 3750 ppm (0.25) max 4300 ppm (0.25) )
. \
- c. Ensures that the 10 CFR 100 thyroid dose limit will not '
be exceeded due to the combined leakage from the recirculation loop and containment leakage. (1.25)
REFERENCE:
TECHNICAL SPECIFICATION 3.3.1 & 3.3.3. 1 l l l j l l 65 1 _ _ _ _ _ _ _ k
j { 8.11 QUESTION (2.5) S0123-0-23.1 ' Valve Operations provides guidence in manual l- operation of valves.
- a. What action must be taken if a safety related motor operated valve (MOV) is manually seated or backsested in other than the sefety related position? (0.75)
- b. What action must be taken if an important to safety MOV is manually seated to prevent leakege? (0.75)
- c. What two (2) of three (3) criteria that must'be met in order to waive an independent valve lineup verification for radiological reasons? (1.0) 8.11 ANSWER
- a. The motor operated valve must be declared inoperable until it is positioned correctly using the motor operator) (0.75)
- b. The power supply (to the MOV) must be opened and a caution tag hung indicating that the valve must be manually unseated prior to power being returned to the valve. (0.75)
- c. (0.5 pts-each, max 1.0 pts.)
- 1. The most recent valve verification is on file.
- 2. Equipment status control has determined that there is is no misalignment.
- 3. System operation / indications confirm the component position.
REFERENCE:
S0123-0-23, Pg.11, and SO123-0-23.1 3, 4 & 5. I l l C6 ,
- --_- . _ _ _ _ - l
l i I l l l e . i 4 8.12 QUESTION (1,0) j I l Technical Specifications restrict ths movement of loads'in 5 excess of 1500 pounds over the fuel assemblies in the fuel storage pool. What are the two (2) reasons for restricting-the load to 1500 pounds? (1.0)
'I 8.12 ANSWER l
- 1. The reactivity released will be limited to that contained in a single fuel assembly. (0.5) 1
{
- 2. Any possible distortion of fuel in the storage racks wil) l not result in a critical array. (0,5) 1 1
REFERENCE:
TECHNICAL SPECIFICATIONS 3.8. 1 4
)
I I 1 l l 4 I I 67 o
f i i 8.13 QUFSTION (2.0) ;
.The unit is in an ALERT condition and you hatre assemed the duties of the Emergency Coordinator. There are five (5) authorizations you are required to make and CAN NOT .
f deligate, per SO123-VIII-10 (Emergency Coordinator Duties). What are four (4)-of the five (L) authorizations that you are required to inake? 3 (2.0) 8.13 ANSWER (0,5 pts. each, max 2.0 pts.)
- 1. Emergency Event declaration,
\
- 2. Notification of offsite agencies, {
l
- 3. Precautionary (plant)/ site /(beach evacuation), !
- 4. Offsite protective action recommendations, ]
1
- 5. Exceeding 10 CFR 20 exposure limits.
REFERENCE:
SO123-VIII-10, Pg. 3. 68
8.14 QUESTION (1.0) An Alert has been . declared for SONGS 1 at 3 : 4 5 AM aftd >- reclassified as a Sight. Area Emergency at 4:30 AM. i .
- a. By what time will the initial Event. Notification (ENF) have to'made by? (0,5)
- b. What time will the NRC portions of the NRC/ Follow-up Notification (FUN) Form have to be submitted after the event was reclassified? (0.5) 8.14 ANSWER
- a. 4:15 AM (within 30 minutes of the event declaration).
(0.5)
- b. 5':00 AM (within 1 hour of the event declaration /
reclassification). (0.5)
REFERENCE:
SO123-VIII-10, Pgs. 6 and 10. t Y-_______-___________-
p: I l
' l 8.15 QUESTION-(0.5)
I MIETIPLE. CHOICE ( Select the correct response') " Station. Order 501-0-100, (Station Operations) designates l: -the position responsible for the control room command
, function, I
j What person has the responsibility for the control room ccmmand function? I
- a. Plant Superintendent, i I
- b. Control Room Supervisor.
l c. Plant Manager.
' d. Shift Superintendent.
8.15 ANSWER "d"
REFERENCE:
SO1 0-100, Pg. 4. i 1 1 70
8.16 QUESTION (1.0) According to Technical Specificati>n 3.B, Fuel Loading nd Refueling', the reactor must be suberitical et.least 148 hours before the movement of irradiated fuel in the reactor vessel can cecnence. What isLthe reacon for the 148 hour tioe limit? (1.0) 8.16 ANSWER To allow time for fission product decay (such that radiation levels over the reactor vessel are within limits). (1.0)
REFERENCE:
Technical Specification 3.8 and BASIS, Fuel Loading and Refueling. END OF SECTION EIGHT END OF EXAMINATION I l 1 71 1 . ..}}