ML20151U628
| ML20151U628 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/16/1986 |
| From: | Douglas W, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151U615 | List: |
| References | |
| 50-338-OL-86-03, 50-338-OL-86-3, NUDOCS 8602110069 | |
| Download: ML20151U628 (111) | |
Text
,- _
ENCLOSURE 1 EXAMINATION REPORT 338/0L-86-03 Facility Licensee: Virginia Electric and Power Company Richmond, VA 23261 Facility Name: North Anna Facility' Docket No.: 50-338 and 50-339 Written and sinolator examinations were administered at North Anna near
. Mineral, Virginia.
Chief Examiner: ld b cwt I/? b/86 W. G. Douglas 0 'Date Signed Approved by: w- . i m I!!(,!95 ByeA. Wilson.SectionChief Date Signed Sunnary:
Raqualification examinations-on December 4-6, 1985 Written and simulator examinations were administered to nine licensed operators, six of whom~ passed.
The Requalification Program Evaluation for North finria is marginally acceptable.
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REPORT DETAILS
- 1. Facility Employees Contacted:
- E. R. Smith, Jr., Assistant Station Manager
- C. G. Meyer, Senior Instructor, LORP
- D. C. Fellows, Senior Instructor Simulator
- R. O. Enfinger, Superintendent, Operations
- L. R. Buck, Supervisor, Training
- L. L. Edmonds Superintendent, Training
- D. C. Hawkins, Senior Instructor
- B. P. O'Brien, Senior Instructor
- Attended Exit Meeting
- 2. Examiners:
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided the facility staff with a copy of the written examinations and answer keys for review. The following coments were made by the facility reviewers:
- a. R0 Exam Facility Ccmments and Recommendations - See Enclosure 4.
NRC Resolutions:
(1) Question 1.6 - This question does not require the use of curves to answer. It is testing the integrated effects of the factors that affect the power coefficient (defect). Operators are expected to know the relationship between defect and coefficient. NUREG-1122, K/A No. K5.49, P. 3.1-3 gives this an importance factor of 3.4 for F an R0 and 3.7 for an SRO. The theory reference provided by the facility was " Westinghouse Nuclear Training Operations." Power coefficient .is defined and explained on page I-5.26. The utility's recommendation is not accepted.
(2) Question 1.12 - Fuel pellet swell and clad creep does not adequately answer the question and warrants only partial credit.
The answer key indicates the partial credit to be given for each part of the answer. The utility's recommendation is not accepted.
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(3) ' Question 2.01 - This comment incorrectly references question 2.01 which has no typographical error. It should reference question 2.10. In.this instance, the typographical error was identified by the NRC prior to administering the examination. The typographical error was . pointed out to the examinees during the examination .
pre-briefing.- The utilities' recommendation is not accepted.
(4) Question 2.07 - This question does not require the memorization of all electrical loads. NUREG-1122 gives the following important factors for the loads in-this question: (a) K/A 006/000-K2.01 -
3.6 R0, 3.9 SR0; (b) K/A 078/000-K2.01 - 2.7 R0, 2.9 SR0; (c) K/A 056/000-K2.01 - 1.6 R0, 1.7 SR0; (d) K/A 012/000 - K2.01 - 3.3 R0, 3.7 SRO. In the case of Part c, only knowledge of whether it was a vital or non-vital load and its voltage was required'to answer the question. Even with a K/A of less than 2.0, this is a reasonable requirement. The utility's recommendation is not accepted.
(5) Question 2.13 - The plant condition specified on the answer key is the reason the seal bypass valve is necessary. The utility's recommendation is not accepted.
(6) Question 2.14 - Utility's recommendation acce~pted and answer key has been revised.
(7) Question 2.15 - Although we believe this question is relevant knowledge for an operator, NUREG-1122 does not give it an importance factor. The utility's recommendation is therefore accepted and the question has been deleted from the examination.
(8) Question 3.07.c - Utility's recomendation accepted and answer key has been revised.
(9) Question 3.08 - The reference does support N-44 as an anticipatory signal to the bypass valves at low power levels, but the question.
asks about the steam gene'rator level program input. The utilities' recommendation is not accepted.
(10) Question 3.10 - Understanding of instrument design and limitations is operationally important when it is used to mitigate the consequences of an accident, therefore, the question is not deleted. However, an explanation of the general methods used for compensation is acceptable. No modification to the answer key is required since values for partial credit were already given.
(11) Question 3.11.b - The intent of the question was not to provide setpoints. The utility's recommendation accepted and the answer key has been changed.
3 (12) Question 3.15.a - An explanation of the automatic start signals equivalent to the answer key is required. -Partial credit will be awarded in accordance with the answer key. The utility's recomendation is not accepted.
(13) Question 4.06.b - Utility's recomendation accepted and the answer key has been changed.
(14) Question 4.09 - Utility's recomendation accepted and the answer key has been changed.
(15) Question 4.08 - This was not a facility comment but was found by the NRC during review of the examinations. The answer required was not complete .as given in the reference. The answer key was changed to require the complete answer for full credit.
(16) Question 3.14 - This was not a facility comment but was found by the NRC during review of the examinations. The holdup tank influent valve is also called the clarifier influent valve. The answer key was changed to accept either holdup tank influent valve or clarifier influent valve for full credit.
(17) Question 4.10 - This was not a facility coment but was a coment for the identical question given at Surry Nuclear Plant on the same date. Only the last two items given on the answer key are necessary to perform emergency boration and thus received full credit. No change to the R0 exam and answer key were required,
- b. SR0 Exam Facility Coments and Recomendations - See Enclosure 4.
NRC Resolutions:
(1) luestion 5.04.a - The stated reference supports the NRC's answer for Part a. However, a utility supplied reference contradicts this.
We believe that the reference stated on the answer key is correct and that the utilities' reference is in error. But, since there are conflicting references, Part a. is deleted from the examina-tion.
(2) Question 5.06.c - The utility's recomendation accepted.
(3) Question 5.07 - See R0 Exam, Question 1.6 (4) Question 5.11 - See R0 Exam, Questian 1.12 (5) Question 6.05 - See R0 Exam, Question 3.07 (6) Question 6.06 - See R0 Exam, Question 2.07
4 (7)\ Question 6.09 - See R0 Exam, Q'uestion 3.10
-(8) Question 6.12 - See R0 Exam, Question 3.11 (9) Question 7.02 - The utility's recommendation accspted and the answer key has been changed.
(10) Question 7.04'- The Emergency Response Guidelines, E-1, p. 47 and the Executive Volume, Generic Issues, p. 3 expects the operators to know what items comprise the Critical Safety Functions. Also,
^ since Foldout Pages contain information that is. continuously monitored, it is expected that the operators would be sufficiently aware of entry level conditions to the CSFs. The utility's recommendation is not accepted.
(11) Question 7.07 - Question asks for knowledge of important param-eters checked during the head lifting procedure, not memorization of steps. Review of the procedure (OP-4.1) revealed two other parameters that are checked 'during this evolution. These param-eters are radiation levels and operation of load cell. The answer key has been changed- to accept any three of the five possible answers for full credit. The utility's recomendation that the question be deleted is not accepted.
(12) Question 8.03 - The utility's recommendation accepted and the answer key has been changed.
(13) Question 8.12 - The utility's recommendation accepted and the question has been deleted from the examination.
(14) Question 8.13 - The utility's recommendation accepted and the answer key has been changed. t (15) Question 7.09 - See R0 Exam, Question 4.08 (16) Question S.09.b - Choice three (middle) is the correct response for a symmetrical (ideal) axial flux shape. However, choice four will be accepted with justifying explanation, i.e., practical situation vs.. ideal (reference; General Physics Corp. , Heat Transfer, Thermodynamics and Fluid Flow Fundamentals, page 229).
(17) Question 5.10.a - Choices one (conduction) and two (convection) were accepted for full credit. Another reference (Duke Power
~
Company Thermodynamics, Heat Transfer and Fluid Flow, page 190) supports the contention of heat transfer by both mechraisms.
(18) Question 6.17 - See R0 exam, Question 3.14.
(19) Question 7.10 - See R0 exam, Question 4.10.
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(20) Question 8.14 - This was not a facility comment but was a comment for the identical question on another examination given the same date. The question tests knowledge of a non-restrictive specifi-cation and it is inappropriate to expect memorization of such a low priority item. The question has been deleted from the exami-nation.
- c. Gene'ral Comments (1) Ensure that written examination questions are valid when compared to actual work assignments.
Resporse: The NRC has issued NUREG-1122, "Knowledges and Abili-
~ ties Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors." Still under development is the Examiners Handbook, NUREG-1121, which provides implementing guidance for NUREG-1122. These NUREGs are scheduled for pilot-test efforts in Region II in February and March 1986, although much of the guidance contained in NUREG-1122 has been used extensively on our examinations for the last six months. NUREG-1122 was used as a basis for determining if several of the questions which had specific comments- by VEPC0 were performance based.
(2) Comply with the NRC policy restricting the number of multiple choice questions used on written examinations.
Response: The present NRC policy is that each written examination shall contain no more than 25% true-false and multiple choice questions. This policy was fully complied with on both the Surry and North Anna written examinations. On the Surry examinations, for example, the final version of the R0 examination contained eight multiple choice and six true-false questions out of a total of 65 questions. On the SR0 examination, there were twelve multiple choice and two true-false questions from a total of 64 The percentages were 21.5 and 21.9, respectively on the R0 and SR0 examinations. Approximately 27% of the questions were also highly objective, i.e. , matching, fill-in-the-blank, and single word responses. These were not included in the category of multiple choice /true-false. The remaining 50% of the questions were more subjective, f.e., explain, describe, list, etc. The North Anna examination was very similar in construction.
(3) Conduct simulator evaluations using an anticipated shift complement.
Response: The sinulator examinations were conducted in full compliance with applicable Examiner Standards. The candidates selected for examination represented the percentage of licensed.
personnel at each site, i.e., R0s, SR0s, and staff personnel. Two of the three crews at North Anna and three of the four crews at
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Surry consisted ' of two R0s and one SRO. The remaining crew at each site was of necessity, comprised of three SR0s. Each of the SR0s in the latter type of crew, functioned in both an'SR0 and an R0 capacity. This is consistent with their license which permits them to "... direct the licensed activities of licensed operators at, and to manipulate all controls ..." of their applicable facilities. In addition, VEPC0 staff instructors functioning in the capacity of Shift Technical Advisors, were made available to and were utilized by each of the crews at each site. We can therefore find no basis for this general comment.
- 4. Exit Meeting At the conclusion of the' site visit the examiners met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the simulator examination were identified.
There:was no generic weaknesses- (greater than 75 percent of candidates giving incorrect answers to one examination topic) noted during the simulator examinations.
The cooperation given to the examiners was noted and appreciated.-
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
e- -4 ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY.: NORTH ANNA 1&2 REACTOR TYPE: PWR-WEC3 DATE ADMINISTERED: 85/12/04 FXAMINER: JERRY DOUGLAS APPLICANT: _________________________
INSTRUCTIONS TO APPLICANT lise e,arate paper fnr the answers. Write answers on one side only, f Staple question sheet ~on top of the answer sheets. Points for each l question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at 1 cast 80%. Examination papers will be picked up si 'S) hours after the examination starts. Spun (%)
% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 18 0 75 0 -
PRINCIPLES OF NUCLEAR POWER
___1__0-_____1_0 _ ___________ ________ 1
-PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 14.50 g
+0 vee 25.00 PLANT DESIGN INCLUDING SAFETY
_..______.______ ___________ ________ 7.
AND EMERGENCY SYSTEMS 18 0 25.00 INSTRUMENTS AND CONTROLS
___1_0 ___ ______ ___________ ________ 3.
18 0 '5 0 PROCEDURES - NORMAL, ABNORMAL,
___I_0___ .,'__1_0 _ ___________ ________ 4.
EMERGENCY AND RADIOLOGICAL CONTROL 70 5 %)
94 wee 100.00 TOTALS FINAL GRADE _________________%
011 work done on-this e:: amin a tion is my own. I have neither given nor received aid.
5PPLICdUTI5~55GU5 TURI ~~~~~~~~~~~~~~
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
--- isEER557sERiE5- REAi iEEs5 FEE As5 FEUi5 FE5E GUESTION 1.01 ,
(1.00)-
Attached-Figure # 220 shows a power history and four possible samarium traces (reactivity vs time). Select (a, b, er or d) the correct curve for displaying ~the expected samarium transient for the given power history.
UllFSTION 1.02 (1.00)
Attached Figure # 219 shows a power history and four possible xenon traces (reactivity vs time). Select (a, be e, or d) the correct curve
-for. displaying the expected xenon transient for the S i ven power history.
QUESTION 1.03 (1.00)
For a PWR designed to operate like the Rankine Vapor Cycle shown on
' Figure 4 210, which of the followin3 equations is used to calculate the cycle's thermodynamic efficiency?
- a. . AREA WITHIN (a-b-e-d-a) / AREA WITHIN (a-d-f-e-a)
- b. AREA WITHIN (e-a-b-e-d-f-e) / AREA WITHIN (a-b-e-d-a)
- c. AREA WITHIN (a-d-f-e-a) / AREA WITHIN (e-a-b-e-d-f-e)
- d. AREA WITHIN (a-b-c-d-a) / AREA WITHIN (e-a-b-e-d-f-e) -
(xxxxx CATEGORY 01 CONTINUE 0 ON NEXT.PAGE.****x)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3
--- iAEER557sERIC5- REsi iEAssFEE Es5 FEUi5 FE5E
'OllFSTION 1.04 ,
(1.00)
Which of the following equations used to perform a PWR heat balance calculation is correct?
a.- Grx = M(s).Ch(s) - h(fw)3 + M(bd) [h(bd) - h(fw)] + Orep
- b. Grx = M(s) Ch(s) - h(fw)] + M(bd) Ch(bd) - h(fw)1 - Grcp
- c. Orx = M(s) [h(s) - h(fw)] - M(bd) Ch(bd) - h(fw)3 - Grcp
- d. Orx = M(s) Ch(s) -
h(fw)1 - M(bd) Ch(bd) - h(fw)1 + Orep NOTE: Notation Key G = Power fu = Feedwater M = Mass Flow Rate rx = Reactor
- = F. team bd = Blowdown h = Specific Enthalpy GUESTION 1.05 (1.50)
Indicate whether the following statements concerning rod worth are . RUE or FALSE
- a. One reason for overlappin3 rod groups is to minimize the effects of rod shadowing on' total rod worth,
- b. 'Both an RCS temperature increase and a buildup of fission product poisons will DECREASE tod worth,
- c. The maximum differential rod worth occurs at the point where the integral rod worth is maximum.
41tESTION 1.06 (1.50)
Indicate whether the Total Power Coefficient gets MORE NEGATIVE, LESS NEGATIVE, or DOES NOT CHANGE for the following conditions,
- a. .From low power to high power at BOL.
- b. From low power to high power at EOL.
- c. From BOL to EOL at a constant power level.
(***** CATEGORY 01' CONTINUED ON NEXT PAGE **xxx) i I
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4
--- inEEs557aAsiEi- AEAi iEAs5 FEE As5 FE5i5 FE5E
. OllF S TION 1.07 (1.50)
Indicate whether the followins will INCREASE, DECREASE, or HAVE NO
, EFFECT on the available (actual) Het Positive Suction Head (NPSH).
- c. Increasing pump flow rate
- b. Increasins pump suction temperature
- c. Increasins system pressure QUESTION 1.08 (1.00)
.The reactor is critical at 10,000 eps when a S/G PORV fails open.
~Assumin3'BOL conditionsr no rod motion, and no reactor trip, indicate *
- c. Whether the final steady state Tavs will be GREATER THAN, LESS THAN, or EQUAL TO the initial Tavs.
- b. Whether the final steady state power will be GREATER THAN, LESS THAN, or EQUAL to the point of adding heat'.
QUESTION 1.09 (1.50)
The reactor is operating at 25% power.when one RCP trips. Assuming no reactor trip or turbine load change occur, indicate whether the following parameters will INCREASE, DECREASE, or REMAIN THE SAME.
- a. Flow in operatin3 reactor coolant loops
- b. Core delta T
- c. Operatins loop steam senerator pressure (xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
- t. a 1.- PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5
--- isEER55isisiEE- AEAi iEAsiFEE As5 FEUi5 FE5s 4HFSTION 1.10 ,
(1.50)
Assuming a symmetrical (ideal) axial flux shape, match the CONDITION in Column A to the LOCATION that it would occur in Column 8.
COLUMN A COLUMN B
- e. MINIMUM Critical Heat Flux - 1. BOTTOM
- 7. Between BOTTOM & MIDDLE
- b. MAXIMUM Actual Heat Flux 3. MIDDLE
- 4. Between MIDDLT & TOP
Match the heat transfer process in Column A to the equation that applies to that process in Column B.
COLUMN A COLUMN B
- a. Between cold les and hot les 1. 0 = m e aT of reactor-(normal FC. flow)
- 2. G = Am AT
- b. Across S/G tubes (primary to secondary) 3. G = 11 A AT
- c. Across S/G (feedwater to steam) 4. G = m e ah
- 5. G=mah QUESTION 1.12 (1.00)
As the core ages, the buildup of Pu-240 causes the Fuel Temperature Coefficient (pcm/ degree F) to become more negative. With this change occurring, why does the Doppler Only Power Coefficient (pcm/% power)
.become less negative as the core ages?
RilFSTION 1.13 (2.00)
TWO major factors affect differential boron worth over core life. List these-TWO factors AND indicate how (MORE NEGATIVE or LESS~ NEGATIVE) they affect differential boron worth.
(**xxx CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF. NUCLEAR POWER PLANT OPERATION, PAGE 4
--- isEEs55isAsiEs- REAi iEARsFEE As5 FEUi5 FEiis QUESTION 1.14- (1.00)
~
What is-the quality of a 540 degree F vapor-liquid mixture whose specific Enthalpy is 1175 BTU /lbm?
(xx*r* END OF CATEGORY 01 was**)
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- 2. PLANT DESIGN' INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGk 7 QUESTION 2 .' 01. (1 00)
-The cold les accumulators are desi3ned so that ______ accumulator (s) will: cover ______ of the~ core,
- a. 1, 50%
- 16. 2, 50%
- c. 1,.100%
- d. 12 , 100%
-QUESTION 2.02 (1.00)
Ccn the outside' recirculation spray pump dischar3e be-aligned to_the-LHSI-pump discharge? Choose the correct answer from below.
-a. Yes, for Unit 1 only.
- b. Yes, for Unit 2 only,
- c. Yes, for both Units.
- d. No, both Units are aligned.at the suction of the LHSI pump.
QUESTION 2.03 (1.^0)
The Main Steam Trip Valves are which of the following?
- a. . swing check valves.
- b. sate valves.
- c. slobe valves.
- d. throttle valves..
QUESTION 2.04 ( .50)
Containment Ph ase B isolation will prevent any further operation of the pressuriner PORVs. TRUE or FALSE?
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE R LQUESTION _2.05 ( .50)
Hydrazine is added to the main condensate and feedwater systems by two cotor driven positive displacement pumps. TRUE or FALSE?
ftVFSTION 2.06 (1.50)
Indicate whether the'following.CVCS valves will fail OPEN, CLOSED or AS IS en a loss of Instrument Air.
- p. Low pressure letdown valve (PCV-1145) (0.5)
- b. Charging flow control valve (FCV-1122) (0.5)
- c. Letdown. orifice isolation valves (HCV-1200A, B and C) (0.5)
QUESTION '2.07 (2.00) l Match the loads in Column A to their normal power supply in Column'B.
COLUMN A COLUMN B
- a. LHSI pumps 1. 4160 VAC buses A, B, and C
- b. Instrument air compressor 2. 480 VAC emergency buses H and J
- c. Condensate pumps
- 4. 4160 VAC emergency buses H and .)
- 5. 750 VDC non-vital bus
- 4. 125 VDC vital bus QUESTION 2.08 ( .50)
The 125 VDC batteries have sufficient capacity to supply essential station
~DC power requirements for a total of ______ hour (s).
'(***** CATECORY 02 CONTINUED ON NEXT PAGE *****)
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2.. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9
' QUESTION 2.09 (1.00)
The Residual Heat Removal System is designed to operate when the Reactor Coolant System pressure is less than ______ and temperature less than l GUESTION 2.10 ('.50)
What is-the maximum purification flow rate the mixed bed demineralizers I
-are sized to r"rr-t?
accept HUESTION 2.11 ( .50)
How much steam load is the steam dump system designed to dump to the condenser without causing a reactor trip?
I UUFSTION 2.12 (1.00)
What chemical is added to the containment ~ spray subsystem AND what is its purpose?-
HUESTION 2.13 (1.00)
Why is a seal bypass necessary for the reactor coolant pump ti seal?
OUESTION. 2.14 (1.00)
Explain what happens to the auxiliary steam condensate from the various loads it is used to heat.
HHFSTION 2.15 (1.50)
Unfer what THREE operating conditions is the S/G moisture separating equipment designed to limit carryover to 0.25%?
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
1
- 2. PLANT DESIGN INCLUDING 1 SAFETY.AND EMERGENCY SYSTEMS PAGE to QUESTION 2.16 (1.00)
Name the TWO 3as systems that are part of the fire protection system.
-QUESTION 2.17 .(1.50)
What are the THREE sources of heat that are within the design capacity of the AFW System?
ItufSTION 2.18. (1.00)
Why is MS-109 (Steam traps t.o condenser isolation. valve) designed'to close on a safety injection signal?
(***** END OF CATEGORY 02 *****)
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- 3. INSTRUMENTS AND CONTROLS PAGE 11 QUESTION 3.01 (1 00)
- Which of the following malfunctions could cause one of the over temperature dalta T trip bistables to trip?'
- a. Controlling turbine impulse pressure channel failing low.
b.- Power range N43 lower detector failing low,
- c. Reactor coolant flow detector failin3 lowe
- d. Controlling pressuricer level' channel failin3 loWa QUESTION 3.02 (1.00)
Which of the following statements concerning enerization of the source rcnge detectors if IR N35 compensation voltage fails to 0 volts during n reactor shutdown is correct?
- a. Both source range detectors will automatically ener3 i re at a higher power level than normal.
- b. Both source range detectors will automatically ener3 i ne when IR N36 drops below the P-6 setpoint regardless of the IR N35 indication.
- c. Source range N31 will need to be manually energized after N32 automatically energizes.
- d. Both source range detectors will have to be manually energized whenever IR N36 is below P-4.
QUESTION 3.03 (1.00)
The motor driven.AFW pumps will automatically start on which of the following?
- a. 1/2 breakers open on 2/3 main feedwater pumps.
- b. 1/3 Lo/Lo levels in 2/3 steam generators.
- c. Iow main feedwater pump discharge pressure.
- d. 2/3 high containment pressure signals.
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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- 3. . INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.04 (1.00)
Which of the following correctly describes the response of the Safety Injection system doe to the given operator action?
- a. Closing the reactor-. trip breakers will re-initiate SI following reset and termination-if the initiating conditi~ons still exist.
- b. Manually initiating spray actuation and containment phase B will initiate SI.
c.- Inadvertantly energizing _two Hi-Hi containment pressure bistables during testing will initiate SI.
- d. -Depressin3 Train A and Train 8 SI reset switches will~ secure all emergency core coolin3 water systems except the cold les accumulators.
QUESTION 3.05 (1.00)
Which of the following is a post-accident monitoring instrument / system?
- a. Main feedwater flow rate indication.
- b. Axial Power Distrubution Monitoring System.
- c. Loose Parts Monitoring System' .
- d. Pressuri=er PORV block valve position indication.
QUESTION 3.06 ( .50)
The cold les accumulator isolation valves are sent an open signal upon en SI actuation. TRUE or FALSE?
(r**** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
3._ INSTRUMENTS AND CONTROLS PAGE 13 QUESTION 3.07 (2.00)
M3tch the conditions in Column A with the expected indication provided by the rod speed indic~ation meter.given in Column B.
t COLUMN A COLUMN B
- o. Immediately before an operator removes the N44 1. 0 s/m.
fuses because of a failed high detector. Rods in AUTO with no temperature mismatch, 2. 8 s/m.
- b. Rods in MANUAL with a 10 F temperature 3. 40 s/m.
mismatch.
- 4. 48 s/m.
- c. Rods in AUTO.with a 1 F temperature mismatch.
~ 5, 72 s/m.
- d. Rods in AUTO with a 4 F temperature mismatch.
- 6. 88 s/m.
QUESTION 3.08 (' .50)
The SG 1evel program uses ______ as an input for reactor power.
QUESTION 3 09 (1.00)
The S/G 1evel bypass control valves will automatically operate through their. full range from cero to _____ % reactor power. The controller is also capable of anticipating feed flow changes by a si3nal from _____.
QUESTION 3.10 (1.00)
Explain how the Reactor Vessel Level Indicating System is compensated.
to maintain the required' accuracy during a LOCA.
BillFSTION 3.11 (1.00)
Explain the meaning of the following status lights for the temperature sensors on the Core Cooling honitor,
- a. All lights out (0.5)
- b. Yellow (0.5)
(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx) l
- 3. INSTRUMENTS AND CONTROLS PAGE 14
-QUESTION 3.12 (1.00)
'What is the minimum logic that must be satisfied for the condenser to be cvailable for the steam dumps (C9)?
HUESTION 3.13 (1.00)
- o. How is the reduced pressure operation modification in Unit 2 placed into service? (0.5)
- b. At what Reactor Coolant System temperature will this system auto-
~
natically reduce its setpoint? (0.5) 40FSTION 3.14 (1.50)
What THREE automatic actions occur on a high clarifier effluent monitor
-clarm?
UUESTION 3.15 (1 70)
Fxplain what will start the emergency diesel generator with its selector cwitch is in each of the following positions.
- a. AUTO REMOTE (0.5)
- b. REMOTE (0.5)
- c. LOCAL (0.5)
GUESTION' 3.14 (1.00)
List the automatic start signals for the service water pumps.
QUESTION 3.17 (1.00)
Which PCS pressure detectors will automatically shut RHR inlet valves MOV 1700 and MOV 1701?
f***** END OF CATEGORY 03 **x**)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15
~
~~~~RA6E6LU5565L 66UTRUL'~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.01 ,
(1.00)
It is required to exit a radiation area and report to HP whenever your 0-200 nr self-readins dosimeter reaches ______ mr.
- a. 100
- b. 125
- c. 150-
- d. 175 GUESTION 4.02 (1.50)
Match.the action listed in Column A with tne approximate power level in Column B at which this action is taken on a unit startup to 100% power.
COLUMN A COLUMN B
- o. Place a second Main Feed pump in service 1) 15%
- 2) 30%
- b. Stop increasing power and check fnr a 3) 50%
chemistry hold 4) 60%
- 5) 70%
- c. Perform a calorimetric 6) 90%
ffuESTION 4.03 (1.50)
Match the descriptions below with the appropriate Pressure / Temperature cperating curves labelled A throosh G on .ae 'tached graph.
- b. Point at which Over pressure protec. ion must be inserted (0.5)
- c. Mode 4 RCS Limitation (0.5)
QUESTION 4.04 (1.00)
List the 4 methods given in the S/C Tube Rupture E0P to identify which S/G is ruptured.
(rxxus CATEGORY 04 CONTINUED ON NEXT PAGE surxx)
- 4. . PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14
~~~7 R 5656[66f6AE~C6UTR6i QUESTION 4.05 ~( 2.00)
An Excluded Radiation Worker is a Radiation Worker with an accumulated whole body. quarterly dose exceeding _____ mrem or a calender year dose exceeding _____ mrem. Any planned exposures which will result in an individual exceeding 750 mrom in a calender quarter must be approved by the _____ while the _____ must give permission for anyone to exceed 5000 arem in a year.
HilESTION 4.06 (1.50)
Give the location of the followins support conters that are manned during a plant emergency.
- o. ~0perations Support Center (0.5)
- b. Technical Support Cents- (0.5)
- c. Emergency Operations Facility (0.5)
GUESTION 4.07 (1 00)
If instrument air is lost outside the containment and the plant is solide what are your required immediate actions?
UllESTION 4.08 (1.00)
Following a valid reactor trip and safety injectionr what are the Reactor Coolant Pump Trip Criteria?
OUESTION 4.09 (1.50)
Excluding notifications, list the immediate actions the operator must take is a sin 31 e droppdd rod occurs. (Include any actions that are rnntingent upon the status of any RCS parameter (s).)
(*x*** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
I l
l I
L
- 4. PROCEDURES . NORMAL, ABNORMAL, EMERGENCY AND PAGE 17
~~~~R565dL55iEEL 55aTR L'~~~~~~~~~~~~~~~~~~~~~~~
4tlFSTION 4.10 ,
(1.50)
~
List the operator actions necessary to initiate emergency boration if it is required on an Anticipated Transient Without Trip condition.
QUFSTION 4.11 (2.00)
List ALL the immediate action sub-steps from EP-0, ' Reactor Trip or Safety. Injection *, that allow you to accomplish the following immediate
.cetions.
- c. Verify if SI is actuated (1.0)
- b. ' Verify Chs/SI pump valve lineup (1.0)
HilFSTION 4.12 (1.50)
List the SI termination criteria following a LOCA.
OllESTION 4.13 (1.00)
List the 4 DISTINCT hazards to which personnel are exposed when an entry into the reactor compartment is made during reactor operations.
(xxxxx FND OF CATEGORY 04 xxxxx)
(************* END OF EXAMINATION *******xxxxxxxx)
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,, g
PE = mgn vf = V, + at * = e/t t =
In2/t1/2 = 0.693/t1/2 ya y .p A= .7 D 2 t l/2' '
(t l}(b} 3 4 [;t1/2)
- 5ID I)
- .E = 931 sm m = V,yAc . r,x 0 = m.ah I = I,e Q = mCoat Q = UAai I = I e'"* '
Pwr = d fah I=I 10'*/UL TVL = 1.3/u sur(t) HVL = -0.693/u P = P,10 III P=Peo SUR = 26.06/T SCR = 5/(1 - K,f f)
CR, = S/(1 - Kefh)
SUR = 26a/t* + (s - o)T CR)(1 - K dfl) = CR2 II ' "eff2)
T = (a*/s) + [(8 - oV Io] M = 1/(1 - K,ff)'= CR /CR j 3 T = t/(o - 8) M = (1 - K ,ff,)/(1 - 4,ffj)
T = (s - o-)/(Io) SDM = ( - K,ff)/K,ff a = (K ,ff-1)/K ,ff = aK,ff/K,ff L' = 10 seconos I = 0.1 seconds-I o = [(t*/(T K,ff)] + [i,ff (1 / + IT)]
Ijj=Id d
P = (IsV)/(3 x 1010) I jd) 2 ,2g# 2 22 I = cN R/hr = (0.5 CE)/c 2(mete-s!
R/hr = 6 CE/c 2 gf,,;)
Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. I curie = 3.7 x 1010 eps 1 ga;.. = 3.78 liters 1 kg = 2.21 lem 1 ft* = 7.48 gal. 1 np = 2.54 x 103 Btu /nr .
Density = 62.4 1 /ft3 1 m = 3.41 x 100 5tu/hr Density = 1 gm/c. lin = 2.54 cm Heat of vaporization = 970 Stu/lem *F = 9/5'C + 32 Heat of fusion = 144 Btu /lem 'C = 5/9 (*F-32.3 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in, 2
e = 2.713
'
- Vitume, ft'/lb InthMpi.Ste/lb ttiterpy. Stu/lb a F C;tre Lep Stism Catre Ever Strom Cetit tv:p Stp:m he h h **
er
- s 's re e *te *e 3305 3305 -007 107b 5 10755 0 0000 2 1673 2 1873 32 32 0 0b8% 0 01602 0 01602 244F 29 '.P 3 04 1073P 1076 8 0 006) 21706 2 1767 35 25 0 09993 40 0 01602 Post 2446 F 03 1071 0 1079 0 0 016? 2 1432 2 1594 40 0 12163 45 0 03602 2037.7 2037.8 13 04 10681 1021 2 0 0262 2 1164 2 1426 45 014744 0 0361 2 1262 50 0 03602 1704 8 1704 8 18 05 1065 3 1063 4 2 0901 50 0 17795 0 01603 1207.6 1207.6 26 06 1059 7 10E7.7 00b35 2 0391 2 0916 60 60 0.2561 0.01605 268 3 868 4 38 05 1054 0 1092 1 0 0745 19900 20645 70 70 0.3629 633 3 633 3 48 04 10484 1006 4 0 0932 1.9426 2 0359 30 SO 0 5063 0.01607 0.01610 466 1 465 1 56 02 1042 7 1100 8 01115 1.8970 2.0026 50 80 0 69S1 3504 LS 00 1037.1 1105.1 0 1295 1.8530 1.9825 100 100 0.9492 0.01613 350 4 ~
265 4 265 4 77.98 1031.4 1109.3 0.1472 1.8105 1.9577 110 110 1.2750 0.01617 203 25 20326 87.97 1025 6 1113 6 0.1646 1.7693 1.9339 120 320 1.6927 0.01620 157.32 157.33 97.96 1019 8 1117.8 0 1817 1.7295 1.9112 130 130 2.2230 0 01625 122.98 123 00 107.95 10140 1122.0 0 1985 16910 1.8895 140 140 2 8892 0.01629 97.05 97.07 117.95 1008 2 1126.1 0 2150 1.65)6 1.8686 150 150 3.718 0 01634 77.27 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 160 4.741 0.01640 62.04 62.06 137.97 996 2 1134.2 0.2473 1.5822 1.8295 170 170 5.993 0.01645
$0.21 50.22 148 00 990 2 1138 2 0 2631 1.5460 1.8111 180 ISO 7.511 0.01651 40.94 40.96 158 04 984.1 1142.1 0.2787 1.5143 1.7934 100 ISO 9.340 0.01657 33.62 33.64 168 09 977.9 1146.0 0 2940 1.4824 1.7764 200 200 11.526 0.01664 27.80 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 210 14.123 0.01671 26.78 26 80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01672 23.13 23 15 188 23 965 2 1153 4 0 3241 1.4201 1.7442 220 220 17.186 0.01678 19.364 19.381 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 230 20.779 0.01685 16.304 16.321 208.45 952.1 1160 6 0.3533 1.3609 1.7142 240 240 24.% 8 0.01693 13.802 13 819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29.825 0.01701 11.745 11.762 228.76 938 6 1167.4 0.3819 1.3043 1.6862 260 260 35 427 0.01709 10.042 10 060 238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 270 41.856 0 01718 8 627 8 644 249.17 924 6 1173.8 0.4098 1.2501 1.6599 280 280 49.200 0.01726 7.443 7.460 259.4 917.4 1176.8 0.4236 1.2238 1.6473 290 290 57.550 0.01736 6.448 6.466 269.7 910 0 1179.7 0.4372 1.1979 1.6351 300 300 67.005 0.01745 5.609 5.626 280 0 902.5 1182.5 0 4506 1.1726 1.6232 310 310 77.67 0.01755 4.896 4.914 290 4 894 8 1185.2 0 4640 1.1477 1.6116 320 320 89.64 0 01766 3.770 3.788 311.3 878 8 1190.1 0.4902 1.0990 1.5892 340 340 117.99 0.01787 2.957 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 360 15301 0.01811 2.939 2.317 2.335 353.6 844.5 1198 0 0.5416 1.0057 1.5473 380 340 195.73 0.01836 1.8630 375.1 825 9 1701 0 0 5667 0.9607 1.5274 400 400 247 26 0.01664 1.8444 1.4997 396.9 806 2 1203 1 0.5915 0 9165 1.5060 420 420 30578 0 01694 1.4508 1.2169 419.0 785 4 1204.4 0.6161 08729 1.4890 440 440 381.54 0.01926 1.1976 0 9942 441.5 763.2 1204 8 0.6405 0 8299 1.4704 460 460 466 9 0.0196 0.9746 0.8172 464.5 739 6 1204.1 0 6648 0.7871 1.4516 480 450 565 2 0.0200 0.7972 06749 487 9 714 3 1202.2 06890 0 7443 1 4333 500 500 6PO 9 0 0204 06545 0 5596 512 0 687.0 1199 0 0 7333 0 7013 1 4146 520 5:0 812.5 00209 05356 540 0 4437 04651 5368 657.5 1194.3 0 7376 0 6577 1.3954 540 9628 0 0215 560 0 3!51 0 3E?! 562 4 625 ? 1187 7 0 7625 0 6132 1.3757 SCO !!)3 4 0C221 117s 0 0.7676 05673 1.3$50 550 550 1326.2 00226 02994 037 2 559 1 569.9 617.1 550 6 116?.7 0P134 05195 1.3330 #Ao 600 1543.2 0 0236 02433 0 2675 620 0 2208 646 9 506 3 1153.2 0 8403 0 46S9 1.3092 620 17869 0 0247 0.1962 640 01E02 6791 454 6 1133.7 0 8666 0 4134 1.2621 640 2019 9 0 0260 0.1543 660 01443 714 9 39? 1 1107.0 0.8995 0.3502 1.2498 660 23657 0 0277 0.1166 680 0 0808 0 1112 758 5 310 1 106P.5 0 9365 02720 1.2026 660 2708 6 0 0304 0 0752 822 4' 172.7 995 2 0 9901 0 1400 1.1390 700 700 3094.3 0 0366 0 0386 0 0508 906 0 0 906 0 1.0612 0 1.0612 705.5 705.5 3203 2 0 0508 0 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
volume. It'/it. lathsip, 8ts/It, Est'sps 8twhb a f Energy.Stw/ib P s 1 p Exp lep Cete Ever Ste m min Steam Ceta Steam V.:tr Ste am P'[('
b
- t No 's ** % e ** *In *e Ce t's oc486 32 018 0 01602 33324 33324 0 OD 1075 5 10755 0 2 1872 2 1872 0 10?!3 0.08s6 0 10 35 023 0 01692 2945 5 2935 5 3 03 1073 6 107tB 00061 2170) 21766 3 03 1022 3 0.10 0 15 4$ a:.3 0 01602 2004 7 20M 7 13 SD 1067 9 10b! 4 0 0271 21140 2 !411 13.50 1025 7 0 15 0 2D L3160 0 01603 1526 3 1L26 3 212/ 10t3 5 10347 0 0422 2 0728 21160 2112 1026 3 0.20 0.30 64 484 0 Olf 04 1039 7 1039 7 32 sa ICb71 1069 7 0Otti 2 0169 2 0839 3254 10320 0.30 0.40 72 869 0 01600 7920 792 1 4392 1052 4 10333 0 079) 3.9762 2 0562 439/ 10347 0 40 0.5 79.586 0 01607 641.5 641.5 47 62 1048 6 1096 3 0 0925 1.9446 2.0370 47.62 1036 9 0.5 0.6 85 216 0 01609 543 0 540 1 53 25 1045 5 1093 7 01028 19186 2.0215 5324 1038 7 0.6 0.7 90 09 001610 466 93 466 94 5B 10 10427 1100 8 0.3 18966 2 00"3 58 10 1040 3 0.7 0e 94 38 0 01611 41167 4116t 6239 1040 3 1102 6 01117 18775 1.9970 6239 1041.7 08 0.9 98.24 0 01612 368 41 368 41 66 24 10381 1104 3 0 1264 38606 1to70 66.24 1042.9 0.3 1.0 101 74 0 01611 333 59 333 60 69 73 1036 1 11058 0.1326 1.8455 1.9781 69.73 1044.1 3.0 2.0 126 07 0 01623 173 74 173 76 94 03 10221 til6 2 0 1750 1.7450 19200 94JD3 1051 8 2.0 3.0 14147 0 01630 118 71 11873 109 42 1013 2 1122 6 02039 1.6854 1.8864 109 41 1056 7 8.0 4.0 152.96 0 01636 90 63 90 64 12092 1006 4 1127.3 02199 1.6428 1.8626 12093 1060.2 4.0 S.0 162 24 0.01641 73.515 73 53 130 20 1000 9 1131.1 0.2349 1.6094 1.8443 13018 1063.1 5.0 6.0 170 05 0 01645 61.967 61 98 138 03 996 2 1134 2 0 2474 1 5820 1.8294 13401 1065 4' 6.0 7.0 176 84 0.01649 53 634 53 65 144 83 992.1 1136 9 02581 15587 1.8168 144 81 1067.4 7.0 40 182 86 0 01653 47.328 47.35 ISO 87 988 5 1139 3 02676 1.5384 1.8060 15324 1069.2 8.0 9.0 169 27 0 01656 42.385 42 40 156 30 965.1 1841 4 0.2760 1.5234 1.7964 156.18 10708 94 10 193.2) 0.01659 38 404 38 42 161.26 982.1 1143.3 0 2836 1.5043 1.7879 161.23 1072.3 30 14.696 212.00 0.01672 26 782 2683 18317 970.3 1153 5 0.3121 1.4447 1.7568 180 12 1077.6 14.696 15 213 03 0.01673 26 274 26 29 181.21 969 7 1150 9 0 3137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20 070 20 067 196 27 960 1 1156 3 0 3358 1.3962 1.7320 19621 1082.0 20 30 250 34 0 01701 13.7266 13 744 218 9 945.2 1164.1 0 3652 1.3313 1.6995 218 5 1087.9 30 40 267.25 001715 10 4794 10 497 236.1 933 6 1169.8 0.3921 1 2844 1.6765 2360 1092.1 40 80 281 02 0.01727 8 4967 8 514 250.2 923 9 1174.1 0 4112 1.2474 J.6586 250.1 1095.3 80 80 292.71 0.01738 7.1562 7.174 262.2 915 4 1177.6 0 4273 1.2167 1.6440 262.0 1098 0 80 70 302.93 0.01748 6 1875 6205 272.7 907.8 1180 6 0 4411 1.1905 1.6316 272.5 11032 70 40 312 04 0 01757 5 4536 5 471 232.1 900 9 11831 0 4534 1.1675 1 6208 281.9 1102.1 80 90 320 29 0O!?66 4 8777 4 895 293 7 894 6 1185.3 0 4643 1.1470 1$113 2934 1103.7 90 100 32782 001774 4.4133 4 431 298 5 888 6 1187.2 04743 1.1284 1.6027 298.2 1105.2 100 120 34;.27 0 01789 3 7097 3728 312 6 8772 1193 4 0 4919 1.0960 1.5879 312.2 1107.6 320 140 353 04 001833 3 2010 3 219 325 0 868 0 1193 0 0 5071 10681 1.5752 324 5 1109.6 140 160 363 55 00;8:5 2 f,155 2 834 3361 859 0 11951 0 5235 10435 1.5641 335.5 11!!.2 160 180 373 08 001827 2.5129 2 531 346 2 850 7 1196 9 0$328 10715 1.5543 345.6 1112.5 180 200 31,1 80 001829 2.26S9 2 287 3555 842.8 1198 3 0 5438 80016 1.5454 3543 1113.7 200 250 400 97 0 01855 1.8245 1.8432 3761 825 0 1201 1 0 5679 0 958% 1.5264 375 3 1115 E 250 303 417 3b 00;829 1.5234 15427 394 0 833 9 1702 9 0SES2 09223 1.5105 3929 1117.2 300 350 4;; 73 0C1913 13064 13255 409 8 7942 1234 0 0 60i! 08939 34958 409 6 11IB ! 350 400 444 60 00193 1.14162 1.1610 424 2 7634 1204 6 0 6217 0 8630 1 4647 422 7 11le 7 400 450 4t5 28 00195 1.01224 10318 437.3 767.5 1204 8 06360 0 8378 1.4738 435 7 1118 9 450 500 4f 7 01 00!99 0 90787 0 9276 4495 7551 1204 7 06493 0 8149 1.4639 447.7 11188 500 553 47t 94 00199 0 82163 0 8412 Af,0 9 743 3 1204 3 0 6t:1 0 7936 1 4547 45f9 1118 6 550 (03 O74962 07E93 4717 7320 1203 / 0f723 0 7738 14461 469 5 11If 2 600 700 4E31? 130C20; f 5L? 0 020! O63t05 06tte 491 ( 710 2 1701 8 0692* O7377 1 4334 4589 1116 9 700 8 : *, LI A 21 0 0239 054839 0 5f.90 503 6 689 6 119) 4 07!!l 07051 14163 506 7 1115 2 803 9 *,; L ~s ; 9'; 0 02i2 04790. 010:9 til 7 619 7 Il9t 4 0727) 0 6753 14032 5232 1113 0 993 locL ! 5.:4 55 0 0216 042435 0 44t3 542 f f 50 4 1192 9 07434 06416 1.3910 53 ~. 6 1110 4 1000 11W) 15tt 2r 0 0720 0 37o(3 0 4035 557 t 631 5 1189 1 0 7t 75 0 6216 13794 5t3 ? 11075 1100 1200 ':67 19 0 0223 0 34013 0 36?b 571 9 613 0 1864 8 07714 03969 1.3633 L56 9 1104 3 1200 1333 L7742 0 0227 0 30722 0 3297 585 6 594 6 1180 2 0 7E4) 0 57.13 1.3577 5531 1103 9 1300 ItC3 51707 0 0?31 0 7787; O3018 $9B B $76 0 1875 3 0 7966 0 5507 1.3474 592 9 1017 1 1400 1500 Lv. 20 0 62 h 025372 0 27/2 611 7 550 4 1170 1 0 8315 0'233 1.3373 60% 7 10331 1500' 20's3 ,63L ES 0 W.,7 0 16? % 01833 672 1 465 2 1133 3 01:02: 042%6 1.2b81 662 6 103 f, 2000 2500 6tt 11 0 02cf 0 1020's 01307 731 7 361 6 1093 3 09139 0 320e 12345 7t&S 1032 9 2500 3003 69513 0 0343 0 050/3 0 0S50 831 8 218 4 10733 0 9723 CIE91 1.1619 1828 9731 3000 32'9 2 70 47 0 05M 0 0 OL0d 936 0 0 9360 10512 0 10612 8759 875 9 370s :
TABLE A.3 PROPERTIES OT SATUPATED STEAM AND SATURATED WATER (PRESSURE)
A.4
- T** P*'ilw'*. I Abe pene.
400 500 400 700 800 900 1000 1100 12M 1300 1430 1500 I pl 103 203 300 I
W5 4 *c 3 511 9 571 A 631 1 6%7 e 00181 I e 6A 00 I t '@ 7 !!9 7 1241 ft 12M t 1330 1 1384 *.
110174) e 0129 2030) 21152 2 1722 2 2237 2 2708 2 3144 let 78 197 70 ?@ 62 221 53 233 45 '
o 00161 76 14 90 74 107 24 314 21 I?6 15 13P OA 15: 01 It 194 173 8' 5 6 68 01 1140 t- 1194 8 1241 3 12M 2 1335 9 13e4 3 14334 140 7 1534 7 15tb 7 1639f 169) 3 17480 IWt (16? 24) s 017v5 18716 19369 19943 2 04t D 20937 7130 2 1770 2 2159 2 2521 2 2856 2 3194 2353) 2 3dll 2 e 0 0161 39 84 44 93 51 03 5704 63 03 64 00 74 #P 80 94 85 91 92 87 98 84 10483 110 76 116 72 30 6 68 02 1146 ( 1193 7 1243 6 12tc 8 13355 13840 1433 4 14h3 5 1534 6 1586 6 1639 5 1693 3 1747 01296 1792ir 18593 1.9173 1.9692 2 0166 2 0t33 21011 2 1394 2 1757 2 2101 2 2433 2.2744 2 (192.21) s l
e 00161 0 0166 29 899 33 963 37.955 41 9 % 45 978 49964 $3 946 57.926 619M 65 862 69858 73 833 7 15 h 68 04 168 09 1192 5 1229 9 1287.3 1335 2 1383 8 14332 1483 4 1534 5 158t 5 1639 4 16932 1747.8 (213 03) e 0 1295 0.2940 1.8134 18720 1.9742 1.9717 2.01% 2 0563 2 0946 2 1303 2.1653 2.1982 2.2297 2.259 00161 0 0165 22 356 25 428 28 457 31466 34 465 37 458 40 447 43 435 46 420 49 405 52.388 SS 3
~
e 20 6 68 05 16811 1191 4 1239.2 1286 9 1334 9 1383 5 1432 9 1443 2 1534 3 1586 3 1639 3 16931 1747 (227.96) s 0 1295 0 2940 1.7405 1.8397 1.8921 1.9397 1 9836 2 0244 2 0628 2.0991 2 1336 2.l M 5 2.1979 2 e 00161 0 0165 11 03( 12 624 14165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26183 27.6
. 40 6 68 10 16315 1186 6 1236 4 1785 0 1333 6 1382 5 1432 1 1482 5 1533 7 15858 1638 8 *1992 7 17 (267.25) s 0.1295 0 2940 1 6992 1.7608 1 8143 1A624 1.9065 1.9476 1.9860 2 0224 2 0569 2.0899 2 1224 2.1 7.257 8354 9 400 10 425 11 43S 12 446 13 450 14 452 15 452 16.450 17.448 18445 1 1
e 0.0161 0 0156 60 4 68 15 16S 20 1181 6 1233 5 1783 2 1332 3 1381 5 1831 3 1481 8 1533 2 1595 3 1638 4 1692 4 174 (292 71) e 0.1295 0.2939 1.6492 3.7134 1.7681 1.8168 1 8612 1.9024 1 9410 1 9774 2.0120 2.0450 2 0765 2.1 e 0 01'61 0 01 % 0 0175 6 218 7.018 7.794 8 560 9 319 10 075 10 829 11 541 12.331 13 081 13 329 14.577 80 6 68 21 168 24 269 74 1233.5 1781 3 1330 9 1380 5 1430 5 1441.1 1532 6 1584 9 1638 0 1692 0 17468 18 (312.04) e 0.1295 0 2939 0 4371 1 6790 1.7349 1.7842 14289 18702 19089 1.9454 1.9800 2 0131 2.0446 2.0750 2.104 e 0 0161 001M 00175 4935 5 $88 6 216 6 833 7.443 8 050 8 455 9 258 9 860 10 460 11.000 11.659 100 h 68.26 168 29 269 77 1.45161279.3 !?27.4 1.7088 1329 6 1379 5 1429 7 1480 4 1532.0 1564 4 1637.6 1691.6 1746.5 1 1.7586 1 8036 1A451 1.8839 1.9205 1.9552 1.9883 2A199 2.0502 2 (327.42) e 0.1295 0.2939 04371 o 0 0161 0 0166 0 0175 4 0786 4 6341 51637 $66J1 61929 6 7006 7.2060 7.7096 8.2119 8.7130 9.2154 9.713 120 h 64 31 168 33 26981 1224.1 1277.4 13281 1378 4 14288 1479 8 1531.4 1543 9 1637.1 189L3 17442 180 (341.27) e 0.1295 0 2939 0 4371 1.6286 1.6872 1.7376 1.7829 1A246 1 M35 I9001 1.9348 1.9680 1.9996 2.0300 2 e 0 0161 0 01 % 0 0175 34651 3 9526 4 4119 4 8585 S2995 57364 6 1709 66036 7.0349 7.4652 7.8946 8 140 6 64 3' 168 38 269 85 1220 8 1275 3 1326 8 13774 I428 0 1479 1 1530 8 1583 4 1636 7 1890 9 17459 18 (353 04) e 0 1295 0 2939 04370 16055 1.M86 1.71 % 1 7652 1 8071 lA461 1 8428 1.9176 1.9508 1.9825 2.0129 2.0 e 0 0161 0 0166 0 0175 3 0060 3 4413 3 8483 4 2420 4 6295 50132 53945 $7741 61522 6 5293 4 9055 7.2 160 6 68 42 ItB 42 269 89 1217 4 !?73 3 1325 4 1376 4 1427.2 3478 4 !$33 3 1582 9 1636 3 1990 5 1745 6 18 (363 55) e 01234 0 2538 04370 15936 1 6522 1.7039 1.7499 1.7919 18310 1.8678 1.9027 1.9359 1.9676 1 9980 e 0016! 0C166 0 0174 2 6474 3 0411 3 4093 3 7621 4 1084 4 4505 4 7937 $1289 $4657 Sa014 41363 183 6 68 47 16i 47 PE' 9/ 1213 6 1271 2 1324 0 1375 3 142t 3 1471 7 15297 1582 4 1635 9 1640 2 17st3 180 (173 C&1 s C 1294 01638 04373 15743 1 6376 16930 1 7362 1 7784 1.8176 1 8s45 1.8894 1 9227 1 9545 1.% 43 e 0 01(1 0 01 % 0 0174 23598 2.7247 3 0583 3 3783 3 6515 4 0008 4 3077 4 6128 4 9165 S?!91 5 5209 200 6 68 12 108 51 209 96 1710 1 12(9 0 1322 f 1374 3 1425 5 1477 0 1529 1 1581 9 1635 4 1689 8 1745 0 (th 6]; e C 1794 C 2535 04309 35593 1.6242 1677C 17239 17663 18357 15426 18776 1.9109 1.9427 1 9732 2 00 e C ( !(! 00Mt CC;74 0 0!E6 2 150 24ft? 2 6C72 2 941C 3 1939 343f2 3 6837 3 9278 41709 4 4131 4 654f .
250 P 61 % 1(6 03 2 70 Ci 3/t lo 1263 5 1319 0 1371 6 1423 4 1475 3 1527 6 1583 6 16344 1688 9 17447 18 30 U;; 971 s 0;294 0263? O4305 Ct%7 11951 16502 16976 1.74M l7631 18173 18524 I8458 1.9177 89482 1.977 0 CCMt C 3174 0C186 1 70 % 2 0944 22763 24437 2C539 2 61 % 3 0643 3 2656 3 4721 3 6740 3 87 330 Ae 6 74 IM 74 27v ?4 37",15 1237 7 13152 1368 9 1421 3 14 ?) ( lt26 2 15794 1633 3 16860 1743 4 1799 I (0161 (417 351 s 01294 02937 04D7 C %65 1 5703 1 6214 1 6/58 1.7192 1 7591 17964 1 8317 1 8052 18372 1.9278 1.95 e 00161 0 C106 0 0174 0 018C 14913 1 7028 17970 2 0332 22652 2 4445 2 6219 2 7983 2 9730 3 1471 3 32 350 > 68 92 16 85 270 7 375 21 1251 5 1311 4 13662 1419 2 1471 6 1524 7 1578 2 1632 3 1067.1 1742 6 17 15483 I t,077 16571 1.7009 17411 17787 88141 18417 1279S 19605 1.940 (431 73; o 01293 029 M 04347 0SK4 e 00161 0 0!L6 0 0174 0 0162 1 2841 14763 16493 18151 1 9763 21334 22901 2 4450 2 5937 2 7515 2 933 400 e 69 05 16847 270 33 31b 27 12451 1337 4 1363 4 1417 0 1470 1 1523 3 1576 9 1638 2 1656 2 1741 9 17 1.5782 1 %;l 1 6406 1 6950 1 72 % 1 7612 1.79BS 1 8325 18647 1.8055 1 925 (444 60; s $1293 0293k 0 43 % 05%)
e 0 0161 0 0106 0 0174 0 018t 0 9919 11584 130'7 14397 1570E 1 69)? 1 87 % 19507 2 0746 21977 2.32C 500 m (9 32 1% 4 270 51 3 ", M 1231 2 1299 1 1351 / l#1? ? 1466 6 l's201 1574 4 16291 1684 4 1743 3 1796 (407.01) s 01292 L2934 04F4 C tto I49?l 1 % 95 1 U2J l(5/8 1(090 1 7371 17733 18069 18133 18702 1 89.
TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)
A.5
, , Abt poets. DPMIM I C/ta la (ut. tesap) 100 200 300 400 BOO 600 700 800 900 1000 1300 3200 1300 1400 1500 e 0 0lf.1 0 0168 0 0174 0 0185 0 7944 0449 1 0726 llP9? 1300P 1400 1 5160 1 6211 172 >2 le?na 193y 600 6 (9 tB 164 42 270 70 37544, 123*,9 12% ) 13',1 F 1406 3 l a t..* O I!.17 4 1571 9 16?70 168? 6 li3E 8 1793, (480 20) e 01792 0 2933 043L7 0 M57 ' 14W 15324 i % 44 163L1 1 67t9 171tb I7517 17tn9 I Sits 4 IW4 3 87%
e 0 0101 0 0ltr. 0 0174 O u1Ps 0 0704 0 7978 09'7? 1010? 1 1076 12CD 17448 1 39 % I 4737 1 % 47 I g53 7D? > 69 r.4 169 6S 270F's 375 01 4P i 43 1781 0 134% t 1401 7 law 4 1514 4 1%94 16246 f f40 7 1737 2 1794 i (503 Ce) s 01291 02932 D ano 0 %% 06 bis 1 50 % 1St'3 I t>l54 16560 It910 1 7335 17b79 I 8ch 16338 l ect; e 0 0161 0 0146 0 0174 0 0186 0 0704 0 6774 0 76?S 0 8759 0 903) I N70 1 1784 1 2093 12Fn 13%9 1 444 800 6 70 11 169 88 271 07 375 73 48788 1271 1 1339 2 13991 14t5 8 151! 4 1%69 16?? 7 167E 9 17h 0 1792*
(5182.) . 01790 0 2910 0 4358 0 5052 0 6885 14669 15484 1 % 60 16413 1 MO7 1.7175 17522 17651 18164 18464 e 0 0161 0 0106 0 0174 0 0166 O C2J4 0 5669 0 6E 58 0 7713 0 8504 0 92E2 0 9915 10720 1 1430 1 2131 1 262' 900 6 70 37 170 10 271.26 375 84 48783 1260 6 1332 7 1394 4 1452 2 1506 5 1564 4 1620 6 1677 1 17341 1791e (531.95) s 01290 0 2929 0 4357 05649 06881 14659 35311.1.5822 16263 1 6C62 1.7033 1.7382 37713 1 6028 I 832' e 0 0161 0 0166 0.0174 0 0186 0 0204 0$137 0 6000 0 6875 0 7603 0 8295 0 8966 0 % 22 1.0266 10901 1 152!
1000 6 70 63 17033 27144 375 % 487 79 1249 3 1325 9 1349 6 1448 5 1504 4 1561 9 1616 4 1675 3 17325 1790; (544.58) s O1269 02928 04355 05647 06876 14457 1.5149 1. % 77 16126 16530 16905 17256 1.7589 1.7905 1 820'.
e 00161 00166 0 0174 0 0185 0.0203 0 4531 05440 0 6188 06865 0 7505 0 8121 08723 0 9313 0 9894 1.0461 1100 4 70 90 170 % 271 63 376 08 447.75 1237 3 1318 8 1384 7 1844 7 . 1502 4 15594 1616 3
- 1673 5 1731 0 1769I (5 % 28) s 01269 0.2927 04353 0 % 44 0 6872 14259 1 49 % 15542 16000 1 6410 16787 1.7141 1.7475 1.7793 1.8 09:
e 00161 00166 0 0174 00185 0 0203 04016 0 4905 0 5615 0 6250 0 6845 0 7418 C 7974 0 8519 0 9055 0 9584 3200 4 71.16 170 7A 271.82 376 20 487.72 1224 2 1311 5 1379 7 1440 9 1449 4 1556 9 1614 2 16716 1729 4 1787t
(%7.19)s 0.1288 0.2926 0.4351 0.5642 0.6868 1.4061 1.4851 15415 1.5883 16298 1 M79 1.7035 1.7371 1.7691 1.799t e 001(I 0 0166 0 0174 00185 0 0203 0.3176 0 4059 0 4712 0 5282 0 5809 06311 0 67M 07272 0.7737 0 819!
1400 4 7168 171 24 272 19 376 44 447 65 1194.1 12 % 1 1369 3 1833 2 1493 2 15518 1609 9 1668 0 1726 3 1785t (587.07) s 0.1287 0 2923 0.4348 05636 Q M59 1.3652 1 4575 1.5182 1.5670 1.60M 1.6484 14845 1.7185 1.7508 1.781!
e OC161 0 0166 0 0173 00185 0 0202 0 0236 0.3415 04032 0 4555 0 5031 0 5482 0 5915 08336 0 6748 0.715' 1808 4 72.21 171.69 272.57 376 69 487.60 616 77 1279 4 13585 1425 2 1486 9 1546 6 1605 6 1664 3 1723.2 17822 16C4.87) s 0 1286 0 2921 0 4344 0 % 31 O M51 0.8129 1.4312 1.4963 1.5478 1.5936 1 6312 1 6678 1.7022 1.7344 1.765:
e 0 0160 0 0165 0 0173 0.0185 0 0202 0 0235 0 2906 0 3500 0 3988 0 4426 0 4436 0 5229 0 5604 05980 06?4:
1800 a 72 73 172.15 272.95 376 93 487.% 615 58 1261.1 1347.2 1417.1 1440 6 1541.1 1601.2 1660 7 1720.1 1779.:
(621.02)s 0.1284 0 2918 0 4341 0 5626 0 68*3 0 8109 14054 1.4768 1 5302 1.5753 3.61 % 1452A 1 6876 1.7204 1.7518 e 0 0160 0 016, O C173 0 0184 0 0201 0 0233 0 2488 'O 3072 0 3534 03942 0 4320 0 4680 0.5027 0 5365 0 569' 2000 4 73 26 172 60 273 32 377.19 487.53 614 48 1240 9 1353 4 14087 1447.1 1536 2 15% 9 1657.0 1717.0 1777.'
(635 80) s 0.1253 . 0 2916 0 4337 0 % 23 0 6834 0.8091 1.3794 1.4578 1.5138 1.%C3 1.6014 1.6391 1.6743 1.7075 1.7381 e 0 0160 0.0165 0.0173 0 0184 0 0200 0 0230 0 1681 0 2293 02712 0.30f8 0 3390 0 1692 0.3980 0 4259 0 452' 2500 6 74 57 173 74 274 27 377 82 487.50 612 08 1176 7 1303 4 1386 7 1457 5 1522 9 1585 9 1647.8 1709 2 1770e
(%8.11) s 01280 0 2910 0 4329 0 % 09 0 6815 0 8048 1.3076 1.4129 1.47M 1.5269 1.5703 1.6094 1.6456 1 6796 1.711s e 0 0160 0 0165 0 0172 00183 0 0200 0 0228 0 0982 0 1759 0.2161 02424 0 2770 0 3033 0 3282 0 3522 0.375:
3000 6 75 63 17tSS 275 22 378 47 467.52 610 06 10$0 5 1267 0 1363 2 1440.2 1503 4 1574.8 16335 1701 4 17f16 (t95.13) s 0127? 0 29.4 0 4320 0 5597 0 6796 0 8009 1.1966 1.3092 1.4429 14975 1.5434 1.5641 1.621.' l .6%I i M88 e 0 0160 C 0165 0 0172 0 0183 0 0199 0 0227 0 0335 0 1588 0 1987 0 2301 0 2576 0 2827 0306% 03291 0.3510 3200 6 76 4 1753 2756 378 7 487.5 6094 800 8 1250 9 1353 4 14331 15038 1570.3 16343 1698 3 1761.2 (705 CE: s C1276 0 2902 0 4317 0 5592 0 6768 0 7994 0 9708 1.3515 14300 14466 1 5335 1.5/49 14126 16477 1.6806 e OC160 0C154 C C172 C Cit) 00199 0 0225 0 0327 01364 C1764 0 20f 6 0 2326 025E3 0 2784 04995 0 319?
3500 6 77.2 176C 276 2 3791 457 E W4 7794 1224 6 1333 2 1422 2 1495 5 1563 3 16292 I(93 6 17t ? I s e1274 C 259) 04312 05585 06777 0 7973 0 9508 1.3242 1.4112 14709 15194 15618 16002 16353 1669:
e 0 0159 0 0164 C0172 00182 0 0195 0 0223 0 0287 0 1052 0 1463 0 1752 0 1998 02210 0 2411' 0 2C1 0 2783 4000 6 75 177 2 277 1 3 71, 8 487.7 t<6 5 703 0 1174 3 13116 1403 6 1451.3 1552 2 1619P 1655 7 17501 s h271 0pa91 0 4304 05573 0 6760 0 7940 0 9343 1.2754 1.3807 1 tall 1497G 1.5417 1.5812 16177 1.651t e D 0!$9 0 0164 0 0171 0 0181 0 01 % 0 0219 0 0268 0 0501 0 1038 0 1312 01%29 0 1718 016*3 0 2050 0 2203 5000 4 81 1 179 5 2791 331 2 4881 604 6 746 0 1042 9 1252 9 1364 6 14$21 15291 IEW9 It 70 0 17273 s C.1S65 0 PE61 04267 05550 0 672t 07820 0 9153 1.1593 1.3207 3.4001 14582 1.5061 1.M81 1.56(J 1.6J1(
e 00159 0 0163 0 0170 C 040 0 01 % 0 0216 0 025. 00%7 0 0757 01020 0 1221 0.1391 0lk4 01684 0 1811 6000 4 63 7 1817 281 0 362 7 471 6 602 9 736 I 9451 1168 8 1323 6 1422 3 1505 9 IM20 IM42 1724i e 01258 0 2670 0 4271 0 % 28 0 M93 0 7826 0 9026 10176 12615 1.3 m 1.4229 I4743 1.5194 15593 159o1 e 00158 0 0163 0 0170 0 0180 0 0193 0 0713 0 0246 0 0334 0 0573 0 0318 0 1004 01360 0129E 01424 0154' 7000 6 862 IPs 4 283 0 3e4 2 489 3 601 7 729 3 901 8 1124 9 12Pl ? 1392 2 1492 6 15631 IEP 6 1711 1 s 01252 0 2819 04756 0 t',0 7 0t063 0 7.77 0 8976 10350 12055 121,1 1 1934 144uG I4932 1SP5 1 573:
TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATEh (TEMPERATURE AND PRESSURE) (CONTINUED)
A.0
,r,t >
,o ,,
, ,j T, ,, &J;L,l],D, .
'l Muf4,,,
f / N 71 nic
/ /4 ~
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/ll'$fN A // M / / rs'
/
k/
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K / / Mi / / / Nw/
> 38
,. /}l'/E/ $9 Nk
/ X i / gr /
LL / N soo
/ im
- /
M[
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4,%idd W 7p i
- b soo WHKh%27M/iW 3
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\ to in IP s3 a4 15 16 si is 19 20 21 22 23" l
i FIGURE A.5 MOLLIER Et:THALPY-L!;TROPY DI AGPAM A.7 I ,
4 .
PHOPEHTIES OF WATER Density c (Ibslil')
PSIA Temp Saturated 2400 2500 3000 2000 2100 2200 2300
(* F) Liquid 1000 62.888 62.909 62.93 62.951 63 056 62.414 62.637 62.846 62.867 32 62.846 62.87 62.99 62.55 62.75 62.774 62.798 62.822 50 62.38 62.446 62.465 62.559 62.185 62.371 62.390 62.409 62.427 100 61.989 60.587. 60.606 60.702 60.314 60.511 60.53 60 549 ' 60.568 200 60.118 57.859 57.882 57.998 57.537 57.767 57.79 57.613 57.836 300 57.310 54 342 54.373 54.529 53.903 54.218 54.249 54.28 54.311 ,
400 53.651 53.925 53.95 54.11 53.79 53.825 53.66 53.89 410 $3.248 53.475 53.69 53.425 53.46 53.50 53.53 52.798 53.025 53.36 53.40 420 53.02 53.065 53.09 53.265 52.575 52.925 52.95 52.99 430 52.356 52.54 52.56 52.275 52.42 52.45 52.475 52.51 440 51.921 52.125 52.41
$2.10 62.14 62.175 62.21 51.546 51.66 52.025 52.065 450 61.68 51.725 51.76 51.96 51.175 51.56 61.61 61.64 460 51.020 51.25 61.30 51.50 50.70 61.1 51.14 51.175 61.22 470 50.505 50.78 50.825 51.035 50.62 50.66 50.7 50.74 480 50.00 50.20 50.35 60 575 50.175 50.22 50.265 50.31 4iG 49.505 49.685 50.13 1
49.762 49.8.1 49.858 50.098 49.097 49.618 49.666 49.714 500 48.943 49.254 49205 49.56 49.05 49.101 49.152 49.203 510 48.31 48.51 49.01 48.57 48.625 48.64 48.735 47.85 47.91 48.46 48.515 520 48.037 40.096 48.155 48.45 47.29 47.86 47.919 47.978 530 47.17 47.494 47.56 47.89 47.23 47.296 47.362 47.428 540 46.51 46 862 46.93 47.27 46.59 46 658 46.726 45.794 550 45.87 46.216 46.29 46.66 45 92 45.994 46.068 46.142 550 45.25 45.54 45.62 46.02 45.22 45.30 45.38 45 46 570 44.64 44.844 44.93 45.36 44.50 44.585 44.672 44.758 530 4366 44 015 44.11 44.205 44.66 43.73 43 825 43.92 550 43.10 43.33 43 434 43 956 42.913 43.017 43.122 43.226 600 42.321 42.432 42.55 43.14 41.96 42.08 42 196 42.314 1' 1 610 41.49 41.483 41.616 42283 <
40.950 41.083 '41.217 41.35 620 40.552 41.44 39.53 l
633 40.388 640 38 491 39 26 650 37.31 39.005 <
660 36.01 36.52 670 34A8 34.638 633 32.744 32.144 l 690 3D.516
\
I TABLE A.6 PROPERTIES OF WATER, DENSITY ,
I
~ A.8
F
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 18
--- iEFER557Assi25- Aisi iEssiFEE AE5 FE5i5 FC54 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY D0ljGLAS ANSWER 1.01 (1.00) ,
d
' REFERENCE FIHi- L-RG-606, pp 4, 5; Fig. 4 BSEP: 02-2/3-A, pp 177 - 180; 02-0G-A, pp 60 - 61 BFNP: Xenon and Samarium LP, pp 5, 6; R0 84/03/05
-W;stinghouse Nuclear T.ainin3 Operations, pp. I-5.77 - 79 ANSWER 1.02 (1.00) c REFERENCE EIH: GPNT,Vol VII, Chapter 10.1-83-86 BSEP: L/P 02-2/3-A, pp 172 - 176; 02-0G-A, pp 57 - 60 Hestinghouse Nuclear Reactor Theory, pp. I-5.77 - 79 ANSWER .1.03 (1.00) d REFERENCE General Physics, HT&FF, pp. 137 - 142 ANSWER 1.04 (1.00) b REFERENCE General Physics, HT&FF ANSWER 1. 0'S (1.50)
- a. FALSE (0.5) b '. FALSE (0.5)
- c. FALSE (0.5)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 19
'--- isEss55isssiEs- sEsi iRAsiFEE As5 ECUi5 fC55 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY 00UGLA9
~
RFFERENCE Wastinghouse Nuclear Training Operations, p. I-5.36 - 43 ANSWER 1.06 (1 50)
- n. LESS NEGATIVE (0.5)
- b. MORE NEGATIVE (0.5)
- e. MORE. NEGATIVE (0.5)
REFERENCE Hestinghouse Nuclear Training Operations, p. I-5.29 ANSWER 1.07 (1.50)
- a. DECREASE (0.5)
- b. DECREASE (0.5)
- e. INCREASE (0.5)
REFERENCE
':ener al Physics , HT&FF, p. 320 ANSWEP 1.08. (1.00)
- o. LESS THAN (0.5)
- b. GREATER THAN (0.5)
REFERENCE Wastinghouse Reactor Physics, Section I-5, HTC and Power Defect DPC, Fundamentals of Nuclear Reactor Engineering 002/000-K5.02 (3.3/3.6) l l
=
. .. 1- .
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 20
--' iREER557RAsiEi! sEAi iEAssFEE AR5 FE5i5 FE5s ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 1.09 (1.50)
- o. INCREASE (0.5)
- b. INCREASE (0.5)
- c. DECREASE (0.5)
REFERENCE General Physics, HT & FF - Fluid Flow Applications for Systems and Components 002/000-K5.01 (3.1/3.4)
ANSWER 1.10 (1.50)
- o. 5 (0.5)
- 6. 3 (0,5)
- c. 4 (0.5)
REFERENCF f;eneral Physics, HT&FF, pp. 228 - 230.
ANSWER 1.11 (1.50)
- a. 1 (or 5) (0.5)
- b. 3 (0.5)
- c. 5 (0.5)
REFERENCE f:eneral Physics, HT & FF, pp. 180 and 181 001/000-K5.47 (2.4/2.9) 6
,, , , - - - - . - - , - - - , , . . - - . , . , - - , , ~ , , . . - . . , ,, .. --, .,,,a
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PACE 21
~~~~ ~ ~
TUER566YA555C57~55IT TR 5FER 5E6~FL0i5 Ft5E ANSWERS -- NORTH ANNA 182 -85/12/04-JERRY DOUGLAS ANSWER 1.12 (1.00)-
As the core ages, the pellet and clad creep together causing an increase in gap conductivity (0.4 pts.). This causes a smaller delta T of the fuel for a given power chan3e (0.3 pts.). The smaller delta T of the fuel causes a smaller chan3e-in reactivity for a given power change (0.3 pts.).
(pen /F) X.F/% power) = pcm/% power more neg. less less.nes REFERENCE Hestinghouse Nuclear Training Operations, p. I-5.22 ANSWER 1.13 (2.00)
- 1. Boron Concentration Decreases (0.5 pts.) - MORE NEGATIVE (0.5 pts.)
- 2. Fission Product Buildup-(0.5 pts.) - LESS. NEGATIVE (0.5 pts.).
REFERENCE
' Westinghouse _ Nuclear Training Operations, p. I-5.31-ANSWER 1.14 (1.00) 97%-(+/- 1%)
REFERENCE ~
5: team Tables
- . i
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 22 ANSWERS -- NORTH ANNA 182 -85/12/04-JERRY DOUGLAS ANSWER 2.01 (1 00) b REFERENCE SPS SI Sys Des.
NAPS SI or ECCS ESF Lesson Resources.
ANSWER 2.02 (1.00)
D REFERENCE NAPS ESF.RSS Lesson Plan.
ANSWER 2.03 (1.00) e REFERENCE NAPS Main Steam Lesson. Resources.
ANSWER' 2.04 ~ ( .50)'
FALSE.
REFERENCE-
.SPS Primary Systems Sys Des.
NAPS RCS Press. Inst. Lesson Plan.
. ANSWER 2.05 ( .50)
'TRUE
' REFERENCE SPS Condensate Polishin3 Sys Des.
NAPS. Chem Feed.Sys Des, Plant Man.-Vol. 1.
)
- 2. PLANT DESIGN INCLUDING. SAFETY AND EMERGENCY SYSTEMS PAGE 23 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 2.06 .
(1.50) 0 0.5 points each'
-(a) open
-(b) open
-(c) closed REFERENCE NAPS NCRODP 88.3, CVCS
. ANSWER 2.07 (2.00)
- a. 4 (0.5)
- b. 3 (0.S)
- c. 1 (0.5)
- d. 2 (0.5)
RFFFRENCE-NAPS Plant Manual, Inst. Air, RCSr sir Condensater Elect. Dist.
ANSWER 2.'08 ( .50) 2 REFERENCF ~
NAPS Plant Man. 125 vde Power Supplies.
' ANSWER 2.09 (1.00)
~450 psis CO.51.
350 F-CO.53.
~ REFERENCE NAPS RHR System Lesson Plan.
ANSWER 2.10 ( .50) 120 spm.
p-
L 4 . .
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 24 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE SPS CVCS Sys Des.
NAPS CVCS Advance Skills Training.
ANSWER 2 11 ( .50) 40%
REFERENCE SPS Main Steam Sys Des.
NAPS Steam Dump Advance Skills Training.
ANSWER -2.12 (1.00)
Sodium hydroxide E0.53 to remove iodine from the containment atmospheret.53 REFERENCE-SPS Containment Spray Subsystem Sys Des.
NAPS Quench Spray Sys Lesson Resource.
ANSWER 2.13 (1.00)
To get additional flow, and therefore more cooling to the pump bearing CO.5 3 when they are operating at low RCS pressure [0.53.
ANSWER 2.14 (1.00)
Heating drips are collectedEO.53 and then pumped back to'the condensate storage tank Co . 53 . ( or h +vve.tt) . W69 REFERENCE'.
SPS Aux. Steam Sys Des.
NAPS Aux. Steam Sys. Plant den. Vol. 1.
,_ o .
. 2 .. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 25 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
' ANSWER 2.15 . (1.50)
DELETED W@
tCC" ru w e ,: . ru.O>
3- *
- 0% step unouse beiwwen iM. one 100% ,2
- urr-
'O.5?
REFERENCE SPS Primary Sys Des.
NAPS-RCS, SG Lesson Resource.
ANSWER 2.16 (1.00)
Halon CO.53 002 [0.5J REFERENCE NAPS Fire Protection Advanced Sills Training.
ANSWER 2.17 (1.50)
- 1. Core decay heat. (0.5)
- 2. Heat from RCPs. (0.5)
Th Stored heat in RCS/SG metal. (0.5)
REFERENCE HAPS AFW Lesson Resources.
ANSWER 2.18 (1.00)
To contain radioactive steam in the event of a SGTR.
REFERENCE NAPS Main Steam Lesson Resources.
, 3'o- [ INSTRUMENTS AND CONTROLS PAGE 26 ANSWERS -- NORTH-ANNA 1&2 -85/12/04-JERRY' DOUGLAS
~
ANSWER 3.01 .,
(1.00) b REFERENCE SPS TS 2.3-2.
~ NAPS RPS'Adv. Skills Training.
ANSWER 3.02 -(1.00) d REFERENCE-SPS Excore Inst. Sys Des.
NAPS Nuclear. Inst. Sys. Lesson Plan.
ANSWER 3.03 (1.00) d REFERENCE NAPS Lesson Plan AFW-para. D.
ANSWER 3.04 (1.00) a REFERENCE NAPS Safeguards Actuation Signal Diagram, Sheet 8.
ANSWER- 3.05 (1.00)
'd REFERENCE
' NAPS TS, Table 3.3-10.
-3. ~ INSTRUMENTS AND CONTROLS PAGE 27
. ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
-ANSWER 3.06 .( .50)
TRUE.
REFERENCE
. NAPS SI or ECCS ESF. Lesson Resources.
ANSWER 3.07 (2.00)
- c. 1 (0.5)
- b. 4 (0.5)
- c. ~-1 (Om M w (,S - (0.5)
- d. 3 (0.5)
RFFERENCE SPS Rod Control Sys Des.
NAPS Rod Control Lesson Plan.
ANSWER 3.08 ( .50)
Turbine first staSe Pressure.
REFERENCE f;PS SGWLC Sys. Des.
' NAPS SGWLC &~P Advance Skills Training.
ANSWER 3.09 (1.00)
- 1. 30%.(design) or 25% (actual) (0.5)
- 2. N44 .(0,5)
REFERENCE NAPS SGWLC & P Advance Skills Training.
- 3. INSTRUMENTS AND CONTROLS PAGE 28 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANCHER 3.10 ,
(1.00) 0 0.25-points each:
Tt. receives inputs from each of the following -
- 1. Temperature of impulse line.
7 RCS temperature.
- 3. Wide ranse pressure.
and
- 4. The d/p cell is located outside of containment.
NAPS RVLIS Advance Skills Trainin3+
ANSWER 3.11 (1.00)
- e. Manually or automatically disabled (0.5) 6.- Octc ctir - : ;ir brtucca ^ 1r: d 10 dr5;;;; by RTL (0.25) s- r-A-- ~: d ? de5 rec; Ly T/C 4pprome,% g g b mboM W E,9 (0.5)
REFERENCE SPS Core Cooling Monitor Sys' Des.
NAPS.CCM Advance Skills Training.
ANSWER 3.12 (1.00) 0 .5 points each' For NAPS
- 1. 2/2 pressures.
- 7. 3/4 cire water pump breakers shut.
REFERENCE NAPS Steam Dump Advance Skills Training.
ANSWER 3.13 (1.00)
- a. Place key switcher to AUTO (0.5)
- b. 140F (0.5)
- 3. INSTRUMENTS AND CONTROLS PAGE '29 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE.
NAPS RCS Pressure Inst. Lesson Plan.
ANSW'ER 3.14 (1.50)
.1. Shuts clarifier effluent valve (0.5)
- 2. Shuts holdup tank influent valve (0.5)
-3. Trips S/G blowdown pumps (0.5)
REFERENCE NAPSlii Range Rad Monitors Lesson Plan.
ANSWER 3.15. (1.50) c.. Start automatically on SI, degraded bus vn1tager undervoltage, normal or alternate supply breaker.open with either normal or alternate feeder breaker.open. -(0.5)-
- b. Starts all automatic signals of (a) and allows manual starting from control room.- (0.5)
- c. Local start only. (Disables a and b) (0,5)
RFFERENCE NAPS EDG Lesson Resources.
ANSWER 3.16- (1.00)
- 1. SI. signal-Train,related [0,53,
- 2. Loss' of power ort the units transf er buses. (U-irDEF; U-2, 'ERF)CO.53 REFERENCE NAPS SWS Lesson Resources.
ANSWER 3.17 (1.On)
P-402 shuts 1700 (Wide range loop C hot leg)CO.53 P-403 shots 1701 (Wide range loop B hot leg)CO.51-
a .. s.
- 4. PROCEDURES . NORMAL, ABNORMAL, EMERGENCY AND PAGE- 30
~~~----~~-
~~~~R565UL65565E~5 IR5t ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 4.01 (1.00) c REFERENCE Verco GET, p.21.
PNG-15: Radeon Knowledge (3.4/3.9)
ANSWER 4.02 (1.50) a) 4 (+.5 es) b) 2 c) 6 (5 for Surry)
REFERENCE NA OP-2.1, pp 10-13 Surry OP-2.1,.pp 9/10
.PNG-12: Perform Integrated Plant ops (3.5/3.4)
ANSWER 4.03 (1.50)
.a) F (+.5 ea) b )~ D c\ '8-REFERENCE NA-OP-3.0, Attachment 1
- PWG-7: Ability to explain limits / precautions (3.5/4.0).
ANSWER 4.04 (1.00)
'-Unexpected rise in S/G Level (+.25 ea)
-High radiation on a S/G blowdown line
-High radiation on an MS line monitor
-High radiation as determined by sampling and analysis REFERENCE Sorry EP-4.00, pp 3 NA 2-EP-3, pp 2
. .- ;c 4.: PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 31
--~~ Rd6 UL55iEAL E5 sir 5t ANSWERS -- NORTH ANNA 1&2 -85/12/04-' JERRY DOUGLAS EPE-0381.EA2.03 (4.4/4.6)
ANSWER 4.05 (2.00)
- 1. '2750 (0.5) 2.- 4800 (0.5) 3 '. Supervisor Health Physics (or designee) (0.5)
- 4. Vice President ~ Nuclear Operations (0.5)
PFFERENCE
'NA HP Manual, pp 2.3-7 PNG-15: Knowledge of Facility Radeon Rqmiits (3.4/3.9)
ANSWER 4.06 (1.50)
North-Anna (+.5 es response) l Surry
_--------- i ,,,,,
3rd floor conference room of Mntnce Bldg 13rd floor conf rm of Mntnce-Blds
"- a'"-
o---
Service Bldg (adj. 4e CR) W 69 IAdjacent to Station Control Room Training Bldg INext to Training Complex Simul.
I REFERENCE Eurry SEP, pp 1.5-7 NA NAEP, pp 1.5-9 PNG-36: E-Plan (2.9/4.7)
ANSWER 4.07 (1.00) 0 0.25 points each:
- 1. Start all available service air compressors.
- 7. S t.a r t all available instrument air compressors.
- 3. Secure reactor coolant pumps.
- 4. Secure charging pump.
REFERENCE HAPS 1-AP-28.1, p.3.
-EPE-065; PWG-11 (3.9/3.9)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 32
~~~~ - ------------------------
RA65UL665EAL 55UTR5L ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
~
ANSWER 4.08 (1.00) gggg) 11 Verify Charging /SI flow (+.% aa) (SI is os)
Ced -e* RCS P r e s s u r e < 1600 psis (Surry) oR CC.vd LOST (02.)
Co**) <
1230
( 0.t p) sis (NA) [1490 ( c.1 p)sig'}
REFERENCE SUNP Foldout Page NA Foldout page for 2-EP-0 Sorry Foldout page for EP-1.00 003/000; PWG-10 (4 1/4.4)
ANSWER 4.09 (1.50) 0.3 Shift rod contrcl to manual ( + rB6) e,3 Control turbine to a d j ,v e,t Tavs consistent with T r e r ( + ,44 ) o,3 If Tavs < 541 De3 I (+ Ma),
it mus,g&)
be restored within 15 minutes (+re6) or the reactor must be tripped (+-c
": ^ f y t h <. Si.i f . Svye. ..mu, ( . 25 E LA3 69 REFERENCE u4 2_pp_i,4, pp 3 7Pr-O';3; PWG-11 (4.2/4.4)
ANSWER 4.10 (1.50)
- 1. Verify SI/CHG pumps- running ( Ve ri(y pou)) W($ (0.5)
- 2. Switch BATP to FAST speed (0.5)
- 3. Open MOV-( ) (0.5)
REFERENCE Sorry ECA-1, pp 4 NA 2-ECA-1, pp 7 EPE-029; PNG-11 (4.5/4.7)
E. _ .k.
. ** s
- 4. . PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~RI65ULU5EEdL C6 TRUL ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSW'ER 4.11 (2.00)
- e. 1. Charging /SI pumps running '(40.33)
- 2. LHSI Pumps runnin3 (0.33)
- 3. EDGs running (0.33)
'b. 1. RWST Suction Open (MOV-2115 B & D) (0.25)
- 2. VCT Suction Closed (MOV-2115 C & E) (0.25)
- 3. Normal. Charging Closed (MOV-2289 A & B) (0.25)
- 4. Letdown Isolation Closed (HCV-2200 A, B'& C) (0.25)
REFERENCE NA EP-0, pp 2/3 '
006/000; A3.02 & A3.03 (4.1/4.1)
ANSWER. 4.12. (1.50)
SURRY (+.25 ea) INORTH ANNA (+.3 ea)
---_- g_--_---__-
-Containment Conditions Normal 1-RCS Press > 2000 psi 3 & increasing
-RCS Pressure > 2000 psig l-RCS Subcooling > 50 Des F
-RCS Subcooling > 50.Deg F l-PZR Level > 50%
-PZR Level > 50% l-SG Level > 10% or > 30% Advrs Cnte
-SG Level > 65% (WR) or > '17 % (NR) I OR OR l-AFW Flow > 730 GPM
-AFW Flow > 540 CPM i
\ I REFERENCE f;urry EP-2.00 foldout NA EP-0 Foldout page 006/050; PWG-7 (3.8/4.2)
ANSWER 4.13 (1.00) ioinizin3 radiation; heat stress; differential pressure; 02 deficiency
.(+.25 ea)
REFERENCE Sorry ADM 38, pp 3 NA.ADM 20.9, pp 1
3 :. . ~ .g
~4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34
~~~~E56 LU55EIL'EU iRUE~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
-PWG-18: Knowledge of Safety Procedures (3.0/3.1)
4 **:o TFST CROSS REFERENCE PAGE 1 LQUESTION' VALUE. REFERENCE 01.01 1.00- WGD0000764 01.02 1.00 WGD0000767
.01.03 1.00 WGD0000769 01.04 1.00 WGD0000771 01.05 1 . 50 WGD0000765 01.06 1.50 WGD0000763 01.07 1.50 WGD0000777 101.08 1.00- WGD0000817 01.09 1.50 WGD0000819 01.10 1.50 WGD0000773 01.11 1.50 WGD0000790 01.12 1.00 WGD0000762 01.13 2.00 WGD0000744 01.14 1.00 WGD0000770 18.00 02.01 1.00 WGD0000843 07.02 1.00 WGD0000860 02.03 -1.00 WGD0000873 02.04 .50- WGD0000847 02.05 .50 WGD0000853 02.06 1.50 WGD0000875 02.07 2.00 WGD0000862 07 08 .50 WGD0000861' 02.09 1 ~. 0 0 WGD0000871 02.10 .50 WGD0000838 02.11 .50 WGD0000844 02.12 1.00 WGD0000845 02.13 1.00 WGD0000848 02.14 1.00 WGD0000852 02.15 1.50 WGD0000054 02.16 :1.00 WGD0000858-02.17 1.50 WGD0000859 02.18 1.00 WGD0000874 18.00 03.01 1.00 WGD0000841 03.02 1.00 WGD0000850 03.03 1.00 WGD0000865 03.04 1.00 WGD0000866 u03.05 1.00 WGD0000867 03.06 .50 WGD0000846 03.07 2.00 WGD0000842 103.08 .50 WGD0000839 03.09- 1.00 WGD0000856 03.10 1.00 WGD0000840
.03.11 1.00 WGD0000851 03.12 1.00 WGD0000855
+
. o es n. ,
TEST CROSS REFERENCE PAGE. 2 QUESTION. VALUE REFERENCE
'03.13 1.00 WGD0000857 03 14- -1.50 WGD0000861
-03.15 .1.50. WGD0000848 103.14 1.00 WGDV000869-03.17 1.00 WGD0000872 18.00 04.01 1.00 WGD0000821 04.02 - 1.50 :WGD0000836 04.03 1.50 WGD0000880 04.04 1.00 -WGD0000830 04.05' 2.00 WGD0000832 04.06' 1.50 WGD0000833 04.07 1.00 WGD0000823.
-04.08 1.00 WGD0000824 04.09 1 50 'WGD0000827 04.10 1.50 WGD0000828 04.11. -2.00 WGD0000831 04.12 1.50 WGD0000837
.04.13 1.00. WGD0000877 18.00
-72.00
6 -3 ENCLOSURE 3 H. S. NitCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: NORTH ANNA 1&2 REACTOR TYPE: PWR-WEC3 DATE ADMINISTERED: 85/12/04 FXAMINER: JERRY DOUGLAS APPLICANT: _________________________
INSTRUCTIONS TO APPLICANT:
Hse ~~ 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 t+P '6) hours after the examination starts. Foun (9)
% OF CATEGORY. % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
________ ______ __-----__-- -------- ----_--------------------------~~~~
n.so
+e,44 %' 75.00
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 18.00 25.00 6. PLANT SYSTEMS DESIGN, CONTROLr AND INSTRUMENTATION
_[_1______l__ ___________ ________ 7 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
- 87. 0 0 beve+ 0 25.00 g, - ADMINISTRATIVE PROCEDURES, 79 7c.509
,46 100.00 TOTALS FINAL GRADF _________________%
All work done on this examination is my own. I have neither siven nor-received aid.
EPPLEC5 T s sissATURF--------------
1 b
So THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 y
UUESTION 5.01 ., (1.00) i For a PWR designed to operate like the Rankine Vapor Cycle shown on Figure # 210, . which of the following equations.is used to calculate the: cycle's thermodynamic efficiency?
- a. AREA WITHIN (a-b-e-d-a) / AREA WITHIN (a-d-f-e-a)
- b. AREA WITHIN (e-a-b-e-d-f-e) / AREA WITHIN (a-b-e-d-a)
- c. AREA WITHIN (a-d-f-e-a) / AREA WITHIN (e-a-b-e-d-f-e)
- d. AREA WITHIN (a-b-e-d-a) / AREA WITHIN (e-a-b-e-d-f-e)
QUESTION 5.02 (1.00)
Which of the following equations used to perform a PWR heat balance calculation is correct?
- a. Grx = M(s) [h(s) - h(fw)3.+ M(bd) Ch(bd) - h(fw)] + Orep
- b. Orx = M(s) . [h(s) - h(fw)3 + M(bd) Ch(bd) - h(fw)] - Orce
- c. Grx = M(s) Eh(s) - h(fw)3 - M(bd) [h(bd) - h(fw)3 - Grep
- d. Orx = M(s) Ch(s) - h(fw)] - M(bd) Ch(bd) -
h(fw)] + Orcp NOTE: Notation Key 0 = Power fw = Feedwater M = Mass Flow Rate r :: = Reactor e = Steam bd - Blowdown-h = Specific Enthalpy (xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE *****)
3
- 5. THEORY OF. NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 g--------------------------------------
QUESTION- 5.03 (1.00)
The reactor' trips from full powert . equilibrium xenon conditions. Six hours ^later .the reactor is brought critical at 10E-8 amps on the inter-tediate range. If power level is maintained.at 10E-8 amps which of the followin3 statements concerning rod motion requirements for the next two hours is correct?
- a. Rods will have to be withdrawn since xenon will closely follow _its normal build-in rate following a trip, b.- Rods will have -to be inserted since xenon will closely follow its normal decay rate following a trip,
- c. Rods will have to b,e rapidly inserted since the critical reactor-will cause a high rate of burnout,
- d. Rods will h' ave to be rapidly withdrawn since th'e critical reactor will cause a higher than normal rate of build-in.
QUESTION 5.04 (2.00)
Indicate whether each of the following fuel loading situations would result in a 1/h plot that was CONSERVATIVE (under predicts criticality) nr NONCONSERVATIVE (over predicts criticality).
a.- Detector located too far from core (source), (0,5)
- b. Detector located too near core (source). (0.5) c .- Loading core from conter (sourec) towards detector. (0.5) di . Loading highest worth assemblies first; lowest worth last. (0,5)
(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE *xxxx)
- 5. ' THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 4tlESTION 5.05 , (1.50)
Indicate whether the following statements concerning rod worth are-TRUE cr FALSE.
- c. One reason for overlapping rod groups is to minimize the effects
.of rod.shadowin3 on total rod worth,
- b. Both an RCS temperature increase and a buildup of fission product poisons will DECREASE tod worth.
- c. The maximum differential rod worth occurs at the point where the integral rod worth is maximum.
QUESTION 5.06 (1.50)
Assuming the reactor is initially operating at the optimum value of coderator/ fuel ratio, will the following changes cause the reactor to become UNDERMODERATED, DVERMODERATED, or HAVE NO EFFECT? Consider each change separately.
- 0. Increase in moderator temperature.
- b. Increase in. boron concentration.
- c. -Inserting group D rods from 220 steps to 180 steps.
QUESTION 5.07 (1.50)
Indicate whether the Total Power Coefficient sets MORE NEGATIVE, LESS NEGATIVEr or DOES NOT CHANGE for the-following conditions,
- s. From low power to high power at BOL.
-b. From low power to high power at EOL.
- c. From BOL to EOL at a constant power level.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)
' ~>
- 5. THEORY-OF NUCLEAR POWER PLANT OPERATION, FLUIDSr AND PAGE 5 QUFSTION 5.08 . (1.50)
Indicate whether the following will INCREASE, DECREASEr or HAVE NO EFFECT on the available-(actual) Net Positive Suction Head (NPSH).
- c. IncreasinS Pump flow rate
- b. Increasing pump suction temperature
- c. Increasin3 system pressure QUESTION 5.09 (1.50)
Assuming a symmetrical (ideal) a::ia l flux shaper match the CONDITION in Column A to the LOCATION that it would occur in Column B.
COLUMN A COLUMN B
- c. MINIMUM Critical Heat Flu:: 1. BOTTOM
- 2. Detween BOTTOM & MIDDLE
- b. MAXIMUM Actual Heat Flux 3. MIDDLE
- 4. Between MIDDLE & TOP
Match-the heat transfer location in Column A with its NAJOR heat transfer process in Column B.
COLUMN A COLUMN B
- a. From edge of fuel pellet to inside of clad 1. CONDUCTION
- b. From outside of clad to coolant 2. CONVECTION
- c. Across S/G tubes (primary to secondary) 3. RADIATION teliFSTION 5.11 (1.00)
As the core ages, the buildup of Pu-240 causes the Fuel Temperature Coefficient (pcm/ degree F) to become more negative. With this change occurring, why does the Doppler Only Power Coefficient (pcm/% power) become less negative as the core ages?
(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE *****)
.s >
5.: . THEORY OF. NUCLEAR POWER PLANT OPERATION, FLUIDSr AND PAGE 6 g g--------------------------------------
GUESTION 5.12 . (2.00)
TWO major factors affect differential boron worth over core life. List these TWO factors AND indicate how (MORE NEGATIVE or LESS NEGATIVE) they affect differential boron worth.
' QUESTION 5.13 (1.00)
K(=), the height-dependent correction factor, is used to modify the Nuclear Heat Flux Hot Channel Factor limit Siven in the Technical Specifications. Why is this correction factor necessary?
(xxxxx END OF CATEGORY 05 xxxxx)
60 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 7 QilESTION 6.01 (1.00)
Which of the following malfunctions could cause one of the over temperature delta T trip bistables to trip?
- a. Controlling turbine impulse pressure channel failing low.
- b. Power range N43 lower detector failing low.
- c. Reactor coolant flow detector failing low.
1
- d. Controlling pressurizer level channel failing low.
GUESTION 6.02 (1.00)
Which of the following statements concerning enerization of the source range detectors if IR N35 compensation volta 3e fails to 0 volts during a reactor shutdown is correct?
- a. Both source range detectors will automatically energine at a higher power level than normal.
- b. Both source range detectors will automatically energine when IR N36 drops below the P-6 setpoint regardless of the IR N35 indication.
- c. Source r.ange N31 will need to be manually enerSi zed after N32 automatically ener3 ire 5'
- d. Both source range detectors will have to be manually energized whenever IR N36 is below P-6.
GUESTION .6.03 (1.00)
The cooling water normally supplied to the head of each waste gas compressor is supplied by which of the following.
- a. component cooling water system.
- b. chilled water system.
- d. service water system.
(***** CATEGORY 06 CONTINtlED ON NEXT PAGE *****)
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8 QUESTION 6.04 ( .50)
Containment phase B isolation will prevent any further operation of the pressurizer PORVs. TRUE or FALSE?
'40FSTION 6.05 (2.00)
Match the conditions in Column A with'the expected indication provided by the rod speed indication meter Si ven in Column B.
COLUMN A COLUMN B
- a. Immediately before an operator removes the N44 1. O s/m.
fuses'because of a failed high detector. Rods in AUTO with no' temperature mismatch. 2. 8 s/m.
- b. Rods in MANUAL with a 10 F temperature 3. 40 s/m.
mismatch.
- 4. 48 s/L.
- c. Rods in AUTO with.a 1 F temperature mismatch.
- 5. 72 s/m.
- d. Rods in AUTO with a 4 F temperature mismatch.
- 6. 88 s/m.
QUESTION 6.06 (2.00)
Match the loads in Column A to their normal power supply in Column B.
COLUMN A COLUMN B
- a. LHSI pumps 1. 4160 VAC buses A, B, and C
-b. Instrument air c o mp r es s o'r 2. 480 VAC emergency buses H and J
- d. Vital Battery charger
- 4. 4160 VAC emergency buses H and J
- 5. 750 VDC non-vital bus
- 6. 125 VDC vital bus
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
.,- f
- 4. PLANTESYSTEMS DESIGNe CONTROL, AND INSTRUMENTATION PAGE 9 QUESTION 6.07 (1.00)
The S/G 1evel bypass control valves will automatically operate through their full ranse f~ rom mero to _____ % reactor power. The controller is miso capable of anticipating feed flow changes _by a signal from _____.
QUESTION 6.08 ( .50)
The 125-VDC batteries have sufficient capacity.to supply essential station DC power requirements for a total of ______ hour (s).
UllFSTION 6.09 (1.00)
Explain how the Reactor Vessel Level Indicating System is compensated to' maintain the required accuracy during a LOCA.
OllFSTION 6.10 ( .50)
How much steam load is the steam dump system designed to dump to the condenser without caut'ns a reactor trip?
UllFSTION 6.11 ( .50)
What plant condition.must exist to allow manual blocking of the HI Steam Flow Line SI actuation signal?
itlIFSTION 6.12 (1.00)
Explain the meaning of the following status lights for the temperature sensors on the Core Coolins honitor.
a.- All lights out (0.5)
- b. Yellow (0,5)
OllFSTION 6.13 (1.00)
What'is the minimum logic that must be satisfied for the condenser to be available for the steam dumps (C9)?
(***** CATEGOPY 06 CONTINUED ON NEXT PAGE xxxxx)
1 s 5
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND.INSTRUMENTATIDH PAGE 10
-QUESTION 6.14 (1.00)
- o. How'is.the red _uced pressure operation modification in Unit 2 placed into service? (0.5)
- b. At what Reactor Coolant System temperature will this system auto-matica11y reduce its setpoint? (0.5)
.fttlESTION 6.15 (1.00)
Name the TWO gas systems that are part of the fire protection system.
QUESTION 15.16 (1.50)
What are the THREE sources of heat that are within the design capacity of the AFW System?
(filESTION 6.17. (1.50)
What THREE automatic actions occur on a high clarifier effluent monitor alarm?
(rxxxx END OF CATEGORY 06'**xxx)
a :s
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R d6f6L6656dL 66 TR6L QUESTION 7.01 (1.00)
~
If one of the circulating water pumps trips during a radioactive liquid waste release, which action below is required?
- a. The release must be terminated immediately.
- b. No action is required if there is at least one other circulating water' pump running.
- c. Attempt to restart another circulating water pump. If this fails, then terminate the release.
- d. Two circulating water pumps must be-restarted for dilution in order to continue the release.
QUESTION 7.02 (1.00)
Which of the following statements regarding Axial Flux Difference (AFD) requirements for Unit 2 is correct?
- a. Reactor power CANNOT be increased above 50% rated thermal power unless the indicated AFD is within the target band.
- b. If the' indicated AFD is outside the target band for more than 1 HOUR CUMULATIVE ovor'a 24 HOUR. period, with reactor power between 50 and 90% of rated thermal-power, .r educe thermal power to less than 50% and reduce-the power range Neutron Flux High setpoint to less than 55% within 30 minutes.
- c. If indicated AFD is_outside the target band and thermal power is greater than 00% rated thermal power, within 1 HOUR AFD must be restored witisin the band or power reduced to < 90%.
- d. Below 50% rated thermal power, there is NO penalty for being outside the target band due to the fact that uneven xenon buildup in the core does not have an adverse impact at low.
power levels.
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
.7 ,.
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12 66NTR6E-~~---------------------
~~~~R5656[6G5C5L QUESTION 7.03 , (1.00)
Which of the following describes a temporary change which alters the INTENT of a procedure?
- a. A~ change that corrects an incorrect valve lineup.
- b. A change that modifies the criteria by which a system's operability is determined.
- c. A change that allows partial use of a procedure to test a
.subtrain'without affecting-remaining equipment in that train.
- d. A change that allows you to change incorrectly specified instruments for data taking.
QUESTION 7.04 (1.50)
Indicate whether (YES or NO) the following~ conditions violate critical cofety function (CSF) red path criteria. Consider each separately.
- c. ' Pressurizer level of 5% and RVLIS upper head 80%. (0.5)
- b. Total AFW flow 400 spa with all S/G levels < 6%. (0.5)
- c. Containment pressure 65 psi 3 (0.5)
QUESTION 7.05 (1.00)
List the 4 methods given in the S/G Tube Pupture E0P to identify which S/G is-ruptured.
UllFSTION 7.06 (2.00)
~An E::cluded Radiation Worker .is a Radiation Worker with an accumulated whole body quarterly dose exceeding _____ mrem or a calender year dose exceeding _____ mrem. Any planned exposures which will result in an individual exceeding 750 mrem in a calender quarter must be approved by the _____ while the _____ must give permission for anyone to exceed 5000 mrem in a year.
l
(**xxx CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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- 7' . PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13
- ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~E56I6L55iEAL 55NTR6L QUESTION 7.07 (1.50)
While removing the ~ reactor vessel head,.the lifting process is stopped when
.the head is at a height of 1 inch, 2 feet and 128 inches to verify three ccnditions are being met (or are not occurring). List these.THREE. items of interest.
UUESTION :7.08 (1.00)
If instrument air is lost outside the containment and the plant is solid, what are your required immediate actions?
UUESTION '7.09 (1.00)
Following_a valid reactor trip and safety injection, what are the Reactor Coolant. Pump Trip Criteria?
ffUESTION 7.10 (1.50)
List the operator actions necessary to initiate emer3ency boration if it is required on an Anticipated Transient Without Trip condition.
QUESTION 7.11 (1.50)
List, in order of priority from high to low, all the personnel (by title) who may relieve the Interin Station Emergency Manager.
I!UESTION 7.12 (1.50).
List the SI termination criteria following a_LOCA.
.UUESTION -7.13 ( .50)
What is the purpose of a '15 hinute Headway' tag?
(***** CATEGORY 07 CONTINUED ON NEXT PACE xxxxx.).
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14
~
'~~~~Es656L66565L 66 TE6[~~~~~~~~~~~~~~~~~~~~~~~~
-QUESTION 7.14 ..('t.00)~
On a steam _ generator tube rupture casualty, list'the correct priority (in order _of highest to lowest) of methods to depressurize the RCS from t.he choices below!
- 1) . Auxiliary Spray
?)f ' Normal Spray
.3) Pressuriner PORV fillESTION 7.15 (1.00)
List ALL.t'he immediate action sub-steps from EP-0, ' Reactor Trip or
' Safety Injection *r that allow you to verify Chs/SI pump valve lineup.
(uxxxx END OF CATEGORY 07 *****)
P S
f
's i s'
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 15 QUESTION 8.01 (1.00)
Hith the Unit i reactor at 360 degrees F, which of the RCS chemistry cnalysis values.given below is between the steady state chemistry limit-and the transient limit?
- a. Fluoride.1.4 ppa
- b. Boron 2000 ppm
- c. Dissolved oxygen 1.4 ppm
-d. Chloride 0.14 ppm QUESTION 8.02 (1.00)
Which of the following conditions requires action according to Technical
' Specifications in.less than 1. hour if in Mode 2 on Unit 1?
- a. The shutdown-margin is 1.8.
- b. One trair; of heat tracing on the BAST is inoperable, c.- The reactor coolant system lowest operating loop temperature (Tave) is 520 degrees F.
- d. Two of the three charging pumps are inoperable.
QUESTION' 8.03 .(1.00)
During Unit i startup with-the reactor about 2% power, you find that the PORV block valve is stuck open and incapable of closin3 Which of-the following is a CORRECT action (see the attached LCO, Fig 8.1)?
a '. Continued operation is allowed provided the PORV is operable and power is removed from the block valve.
- b. Even if action b is satisfied you are NOT allowed to increasa power into Mode 1. (Block valve cannot be restored to operable)'.
- c. The PORV must be' closed, power removed from the solenoid valve 9nd the block valve must be repaired prior to going to Mode 1.
- d. Since the block valve is-incapable of closing, you must proceed to Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within
-the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
8.- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16
. QUESTION 8.04- (1.00)
Which of the following' situations,fwhile in Mode 1 on Unit 1, requires come action to be taken in i hour or less? (No surveillance testin3 in process).
- a. One shutdown rod not fully withdrawn.
- b. With control bank C at 228_ steps,-bank D is at 120 steps.
- c. Two demand' position indicator channels, each in a separate bank, inoperable with all individual rod position indicator channels operab'le.
- d. One group C full length rod is misaligned from another group C full lenSth rod by-20 steps.
(xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 17 QUESTION 8.05 (2.00)
Match the positions in Column A with the authority and ' responsibility ctatements in Column B insofar as they relate to lines of authority or administrative controls.during fuel handling on either Unit 1 or 2. The
-parenthetical number following the Column A position indicates the proper number of choices from' Column B.
COLUMN A COLUMN B
- o. auxiliary operator (1) 1. has veto authority over the shift supervisor, superintendent of ops and engineerin3 supvr. in all matters concerning rad safety.
- b. licensed reactor oper. (2) 2. must be in the control room during refueling.
- c. e'ngineering supvr. (1) 3. must be in containment during refueling.
- d. licensed senior oper. (2) 4. assists the shift supervisor.
- o. shift supervisor (2) 5. responsible for. ensuring that all routine chemical analyses and evaluations are properly performed durin3 refuelin3'
- f. health physics senior rep 6. reports di'rectly to the station on site (1) manager,
- g. supervisor-health phys. (1) 7. direction over technical support for the entire refueling operation.
- 8. reports directly to the supt of ops
- 9. directly supervises all core alter-stions and has no other concurrent responsibilities
- 10. directs the fuel handling operation
(*xxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)
e
.c e 8 .- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS -PAGE 18 QUESTION 8.06 (1.00)
Complete the follo, wing Technical Specification requirements.
- a. .The quantity of radioactivity contained in each Unit 1 gas storage tank shall be limited to less than or equal to ______ curies of noble gases.
b '. With the quantity of radioactive material in any gas storage tank
~
exceeding the above limit, immediately ______ and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
- QUESTION 8.07 (1.00)
A quarterly surveillance requirement of Technical Specifications may be extended up to ______ days without declaring the component inoperable due to the surveillance testing not being performed. Assume all previous curveillances on the component were performed exactly on their due date.
UNESTION 8.08 (1.00)
FILL IN THE BLANKS.
- a. The specific activity of the secondary coolant system shall be less
.than _____ microcuries/cc Dose Equivalent I-133.
- b. The accident this is based on is a _____.
QUESTION 8.09 (1.00)
According to administrative procedures, an individual shall not be permitted'to work more than ______
hours in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor core than ______ hours in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than ______
hours in any seven day period (excluding shift turnover time) unless authorized'at the assistant station manager (ORM) level or above.
QUESTION' 8.10 ( .50)
According to emergency plan implementing procedurer EPIP 5.03, during a site emergency, personnel inside the protected area and unaccounted for chall be determined within ______ minutes of declaration of~the emergency.
(***** CATECORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. -ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 19 QllE STION 8.11 (1.50)
Aasume the fire' protection spray and sprinkler system to the cable vault is INOPERABLE. State your immediate actions to comply with Technical Specifications including lthe following, as applicable: personnel cesignment, changes to reactor operating status, equipment rerouting or provision, and action times.
QUESTION 8'12
. (1.00)
List, in general, the SIX notifications and determinations that must be orde after initiating EPIP-5.05, ' SITE EVACUATION *, but prior to actually soundin3 the emergency alarm.
QUESTION 8.13 (1.00)
Is a pump operable if its control switch is in PULL-TO-LOCK? Explain.
QUESTION 8.14~ (1.00)
When is the Unit 2 incore monitoring system required by Technical Specifications to be OPERABLE?
ffUESTION' 8.15 (1.00)
If you are the shift supervisor on duty: 1) where (location) would you expect to find the oncoming operating shift if they have reported to the station during the1 course of an emergency? 2) what do you expect the oncoming shift to do if shift turnover is taking place at the time the caergency condition ~is initiated?
QUESTION 8.16 (1.00)
Administrative procedure ADM 14.1 gives the shift supervisor approval authority over jumpers to-be installed or removed. Describe what is meant by ' jumper' by stating the definition from ADM 14.1 GR by giving five of the six generic jumper classification types.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20
' QUESTION 8.17' (1.00)-
~ Definer using a major reactor system o r. component, what is meant by CONTROLLED LEAKAGE as th'at term is used in Unit 2 Technical Specifi-rations.
(xxxxx END OF CATEGORY 08 *****) ~
(xxxxxxxxxx*** END OF EXAMINATION xxxxxxxxxxxxxxx)
a .
C -
i l
ass e 3 f I FIGURE f 210
flG 63 6-2-81 REACTOR COOLANT SYSTEM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3.2 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
- a. With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore 28 the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 Each PORV shall be demonstrated OPERABLE:
- a. At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
- b. At least once per 18 months by performance of a CHANNEL CALIBRATION.
4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through a complete cycle of full travel.
NORTH ANNA - UNIT 1 3/4 4-7a Amendment No. 32
e a.a~ ~. w/@!@ @001ciency o (tet work
. . Cut;/(Ener y in,
,.n s a 13 t
- 1/2 at'
[s mc'
<E . 1/2 mv 2
,, (jf, f, ) f ; , ;y ; ,;,,~, .
PE = mgn
/f = V, + a t * = e/t x = zn2/t1/2 = 0.693/t1/2 W = v ,P ! nD 2 t
1/2'
- b*l/Md3 A= 4 [(t 1/2 I
- 5tD))
eg = 931 sm -
. m = V,VAo - T2 0 = s, hah I*Iec Q r. mCpat ,
Q = UA A T I = I,e pwr = w ah f
I = I,10-*/U L TVL = 1.3/u 5
P = P,10 ""II) HVL = -0.693/u P = P,e*/I SUR = 26.06/T ' SCR = S/(1 - Kdf)
CR, = S/(1 - K,ffx)
SUR = 26e/t* + (s - o)T CR;(1 - Kdfl) = CR2 II ~ Ieff2)
T = (1*/s) + [(a - oV Io] M = 1/(1 - Kdf) = CR /CR j 3 T = s/(o - s) M = (1 - Kg f,)/(1 - Kdfl)
T = (s - o)/(Io) SDM = ( -Kdf)/Kdf a = (Kdf"II/Kd f * 'Kdf /K df t= = 10 seconos I = 0.1 seconds ~I o = [(t*/(T Kgf)] + [idf /(1 + T)]
Idjj=Id P = (reV)/(3 x 1010) I jd) 2 ,2gd 2
22 2
I = eN R/hr = (0.5 CE)/d (meters)
R/hr = 6 CE/d2 (f,,g)
Water Parameters Misc.*llaneous Conversions 1 gal. = 8.345 lem. I curie = 1.7 x 1010 ep3 1 ga: . = 3.78 liters 1 kg = 2.21 lbm ,
I ft* = /.48 gal 1 np = 2.54 x su o w/:.. .
Density = 62.4 1 /ft3 1 mw = 3.41 x 106 Btu /hr Density = 1 gm/c lin = 2.54 cm Heat of vaporization = 970 Btu /lom 'F = 9/5'c + 32 Heat of fusion = 144 Btu /lbm 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf I ft. H O = 0.4335 lbf/in, 2
e = 2.718 VM w , _ ,,,,,,,_ -%M
Wtume ft'/lb ieth5tpp. 91w/lb (ritrspy. Stu/lb n F Stygm P !
P- Q:ter Slesm Cater tysp Ste:m Qcter Evrp
', Ever
, ,,, , a, a,, a, ., .,, .,
0 06B59 0 01602 3305 3305 -0 07 1075 5 1075 5 0 0000 2 1873 21873 32 32 0.09991 0 01002 2945 294F 3 04 1073 P 1070 6 0 0001 21700 21707 35 35 0 010? 2 143? 2159t. 40 4
012163 0 01607 Past 2440 F 03 1071 0 1079 0
, 40 0 0702 2 1164 2.1470 45 45 014744 0 01602 2037.7 2037 8 13 04 10 % 1 10E12 0 01602 1704.8 1704.6 18 05 1065 3 1063 4 0 0361 2 0901 2.1702 50 to 017796 0.01603 1207.6 1207.6 20 06 1059 7 s007.7 0Ob55 2.0391 2.0940 60 60 0.2561 0.3629 0.01605 868 3 866 4 38 05 1054 0 1092.1 0 0745 1.9900 20645 70 70 0 093? 19426 2 0359 80 0 50E8 0.01607 633.3 633 3 4t! 04 1048 4 1006 4 SO 069B) 0.01610 466.1 du1 58 02 1042 7 1100.8 01115 1.6970 2.0086 le0 l 90 0.1295 1.8530 1.9825 100 0.9492 0.01613 350.4 350 4 68 00 1037.1 1105.1 100 0.1472 1.8105 1.9577 110 1.2750 0.01617 265.4 265 4 77.98 1031.4 1109.3
- Sto 1.6927 0.01620 203 25 203.26 87.97 1025 6 1113.6 0.1646 1.7693 1.9339 120
! 120 2.2230 0.01625 157.32 557.33 97.96 1019.8 1117.8 01817 1.7295 1.9112 130 330 0.1985 1.6910 1.8895 140 4
140 2.8892 0.01629 122.98 i 123 00 107.95 1014.0 1122.0 ~ f l 1126.1 0.2150 1.6536 1.8686 150 '
150 3.718 0 01634 97.05 97.07 117.95 1006 2 4.741 0.01640 77.27 ' 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 160 0.01645 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1.8295 170 170 5.993 0.01651 50.21 50.22 148 00 930 2 1138.2 0 2631 1.5480 1.8111 180 100 7.511 0.01657 40.94 40.96 158.04 984.1 1142.1 0.2787 1.514S 1.7934 100 190 9.340 0.01664 33.62 33 64 168 09 977.9 1146.0 0.2940 1.4824 1.7764 200 200 11.526 0.01671 27.80 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 210 14.123
~
0.01672 26.78 26 80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01678 23.13 23.15 188.23 965.2 1153 4 0.3241 1.4201 1.7442 220 i 220 17.186 0.3388 1.3902 1.7290 230 20.779 0.01685 19.364 19.381 198.33 958.7 1157.1 230 0.3533 1.3609 1.7142 340 -
240 24.968 0.01693 16.304 16.321 208.45 952.1 1160.6 0.01701 13.802 13.819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 l 250 29.825 0.01709 11.745 11.762 228.76 938.6 1167.4 0.3819 1.3043 1.6862 260 260 35.427 270 0 01718 10.042 10.060 238.95 931.7 1170.6 0.3960 1.2769 1.6729 1 270 41.856 '
0.01726 S.627 8.644 249.17 924.6 1173.8 0.4098 1.2501 1.6599 280 200 49.200 0.01736 7.443 7.460 259 4 917.4 1176.8 0.4236 1.2238 1.6473 290 ,
- 290 57.550 300 0.01745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 67.005 0.01755 5.609 5.626 280.0 932.5 1182.5 0.4506 1.1726 1.6232 310 810 77.67 0.01766 4.896 4.914 290 4 894.8 1185.2 0.4640 1.1477 1.6116 320 320 39.64 3.770 3.788 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 340 117.99 0.01787 0.01811 2.939 2.957 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 360 153.01 195.73 0.01836 2.317 2.335 353.6 844.5 1198.0 0.5416 1.0057 .1.5473 380 340 1.8444 1.8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 400 247 26 0.01864 1.4808 1.4997 396.9 BOA 2 1203.1 0.5915 0.9165 1.5060 420 420 305.78 0.01694 440 0.01926 1.1976 1.2169 419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 381.54 460 0.0196 0.9746 0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 466 9 1.4516 480 0.7972 0.8172 464.5 739.6 1204.1 0 6648 0.7871 480 566.2 0.0200 .
0 6749 487.9 714.3 1202.2 0.6890 0.7443 1 4333 500 500 680 9 0.0204 06545 05596 512 0 687.0 1199 0 0.7133 0.7013 1.4146 520 520 812.5 00209 053B6 0 465) 536 6 657.5 1194.3 0.7378 06577 1.3954 540 540 962 8 0.0215 04437 0 3871 562 4 625 ? 1127.7 0.7625 0 6132 1.3757 560 SCO 1133 4 0 0221 03E51 4
559.1 589.9 1179.0 0.7876 0.5673 1.3550 550 550 1326.2 0 0225 02994 0.3222 550 6 1167.7 0F134 0.5195 1.3333 r,00 600 1543.2 0 0236 02429 02675 617.1 0.2208 646 9 506.3 1153.2 08403 0.4659 1.3002 620
$20 1785.9 0.0247 0.1962 t
0.1802 679.1 454.6 1133.7 0.8666 0.4134 1.2521 640
! 640 2059 9 0.0260 0.1543 0 1443 714.9 392 1 1107.0 0.8995 0.3502 1.2498 660
! 660 2365.7 0 0277 0.1166 0 1112 7585 310.1 106P.5 0.9365 0.2720 1.2086 680 j 640 27086 0 0304 0.0808 0 0752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 700 3094.3 0 0366 0.0386 0 00508 906.0 0 S06 0 1.0612 0 1.0612 705.5 705.5 2203 2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE) 4
- A.3 i
. - - - - - . . ~ - - _ _ - . - _ _ _ _ _ _ _ - - _ . . - - _ . _ -
Vi tome. li*pt- Inthstay htwht. taf'ery Piobt> a i t evrgy. 86/:d
.I D"E Itap 6 team %8tt' Lap 6te em Cele
- 1re g. Steam V4tt' 6 teem E' Ceter ,,,
psie
- F h Ce U to % *e ** *O e ** *se *e s 3332 4 0 03 107b5 J07a.L 0 ? 1872 2 1872 0 1021 3 0 Deu 37 016 0 01632 333? 4 DJdM 0 0169? 294!.5 294L 5 3 03 1073 li 1074 B 0 0061 2170> 2 17 % 3 03 1022 3 0 10 0 to 35 003 0 0?71 21140 21411 13.50 1025 7 0 15 0 15 45 4:3 0 0163? 20047 2004 7 13 50 1007 9 10i<l d 0.20 Li l60 0 01603 1576 3 1L20 3 21 27 10t3 5 10M 7 0042 2 07?8 2 1160 2112 1028 3 0 20 1039 7 3? %4 10b71 106 7 0 0641 2016S 2 0809 32.54 1032 0 0 30 0.30 64 484 001634 1039 7 439/ 1034 7 0.40 72 86's 0 01600 792.0 7921 409? 1052 t. 10333 0 0799 1.9762 2.0562 0 40 0.5 79.586 0 02607 641.5 641.5 47.62 1048 6 1096 3 0 0925 1.9446 2.0370 47.62 1036 9 0.5 b401 53 25 104L 5 1033 7 01028 1.9186 2.0215 5324 1038 7 06 0.6 85.718 0 01639- 540 0 1 8966 2 0393 58 10 1043 3 0.7 0.7 90 09 001610 465 93 4%94 58 10 10427 11008 0.3 411.67 411.69 62 39 1040 3 110? 6 01117 1.8775 1.9970 6239 1041.7 08 08 94 38 0.01611 368 41 368 43 6624 10381 1104 3 0 1264 18606 1.9870 66.24 1042.9 0.9 0.9 98.24 0 01612 333 63 69 73 10361 11055 0 1326 1.8455 1.9781 69.73 1044.1 1.0 1.0 101.74 001614 33359 94A3 1051.5 2.0 2.0 126 07 0 01623 173 74 173.76 94 03 10221 1116 2 0 1753 1.7450 1 9200 118 71 118 73 109 42 1013 2 1122 6 02039 1.6854 1.8864 109 41 1056.7 8.0 3.0 141 47 0 01633 120.93 1060.2 4.0 4.0 152.96 0.01636 9063 93 64 120 92 1006 4 3127.3 0 2199 16428 1.8626 73.515 73 53 133 20 1000 9 1131.1 0.2349 1.6394 13443 130.18 1063.1 S.0 6.0 162 24 0.01641 61.98 138 03 996 2 11342 0 2474 1.5820 1.8294 138 01 1065 4' 6.0 60 170 05 0.01645 61.967 53 634 53.65 144 83 992 1 1136 9 02581 1.5587 1.8168 144 81 1067.4 7.0 7.0 17684 0.01649 47.328 47.35 150 87 988 5 1139 3 02676 1.5384 1.8360 15334 1069.2 8.0 80 182 86 0 01653 15628 10708 91 16927 0 01656 42.385 42 40 156.30 965 1 1141.4 0.2763 1.5234 1.7964 9.0 02836 1.5043 1.7879 161.23 1072.3 30 10 193.21 0.01659 38 434 38 42 161.26 982.1 1143.3 14.696 212 nn 0.01672 26.782 2683 183 17 970.3 1150.5 0.3121 1.4447 1.7568 180 12 1077.6 34.896 15 213 03 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20 O 20Ob7 196 27 963 1 1156.3 0.3358 1.3962 1.7320 19621 1082.0 20 30 250 34 0.01701 1 ' V2n 13 744 218.9 945.2 1164.1 0 36S2 1.1313 1.6995 2185 1087.9 30 40 267.25 0 01715 ;3 4794 10 497 236.1 933.6 1169A 0.3921 1.2844 1.6765 2360 1092.1 40 to 281.02 0.01727 84967 8.514 250.2 923.9 1174.1 0 4112 1.2474 J.6586 250.1 1095J 80 7.174 262.2 915 4 1177.6 0.4273 1.2167 1.6440 262.0 1098.0 00 GO 292.71 0.01738 7.1562 6205 272.7 907A 1180 6 04411 1.1905 1A316 272.5 1100.2 70 70 302.93 0 01748 6.1875 5 471 232.1 900.9 11831 0 4534 1.1675 1.6208 281.9 1102.1 80 80 312.04
- 31757 5 4536 4.895 293 7 894 6 1185.3 0 4643 1.1470 1.6113 293.4 1103.7 90 90 320.28 001766 4.8777 100 327A2 0 01774 4.4133 4.431 298.5 888 6 1187.2 0 4743 1.1284 1.4027 298 2 3105.2 380 120 341.27 0.01789 3 7097 3 728 312 6 877A 11934 0 4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 001833 3 2010 3 219 325 0 868 0 1193 0 0.5071 1.0681 1.5752 324 5 1109.6 140 160 363 55 00;815 2.E155 2 834 3361 859 0 11951 0.5205 1.0435 1.5641 335.5 1111.2 160 180 373 08 0 01827 . 2 5129 2.531 346.2 850 7 1196.9 05328 1 0215 1.5543 345.6 1112.5 180 200 351 83 0 01839 2.26S9 2.287 355.5 842.8 1198.3 0 5438 1.0016 1.5454 3542 1113.7 200 250 40097 001865 1.8245 1.8432 3761 825 0 1201.1 0 5679 0 9585 1.5264 3753 1115.8 250 300 417 35 0 018E9 1.5233 1.5427 394 0 832 9 J2L2 S. 0 5582 0 9223 1.5105 392 9 1117.2 300 353 All 73 001913 1.3364 33255 439 8 7942 1204 0 0 60M. 0 89 % 1.4968 4396 1118 1 353 424.2 763 4 1204 6 0 6217 08633 1.4847 4 22.7 Illt 7 400 400 44 t. 60 00193 1.14162 1.1610 453 4t6 28 0 0195 1.01224 .l.0318 437.3 767.5 1204 8 06360 0 8378 1.4738 435.7 1118 9 450 09276 449 5 755.1 1204 7 06493 0 814S 1.4639 447.7 11188 500
$00 46? 01 0O!99 0 90787 550 553 476 94 0 3199 0 821E3 08412 4639 743 3 1204 3 06611 07936 14547 456.9 1118 6 600 (33 44 f 13 0 0231 074962 07E93 471 7 732 0 1234 06723 0 7738 14461 4695 tile 2 ASS 9 1116 9 703 703 .532 32 0 0235 063i3t 06556 491.6 710 2 1201 8 0692E O7377 14334 509 8 6896 !!99 4 07111 0 7051 1 4163 506 7 1115.2 803 833 518 21 0 0239 054S39 0SE93 619 7 1196 4 0 727) 0 6753 14032 5232 1113 0 933 933 !)1 93 0 02i? 0 47965. 05039 526 7 042435 0 44t3 542 6 (50 4 1192 9 0743- 06476 1.3910 53.~ 6 Ii10 4 Ic33 1000 :544 Eb 00216 1807.5 1103 1100 0 0720 0 37ef 3 0 4035 557.5 631 5 1169 1 0 7575 0 6216 1.3794 553 ?
l S!! 2r 0 7714 05969 13693 L569 1104 3 1203 1233 sy 0 0223 0'l4013 0 3625 5719 613 0 07E42 05733 1.3577 553 : 1100 9 1303 1333 L7 7 42 0 0227 033722 0 3299 585 6 544 6 576 L 1175 3 0 7966 0 5507 1.3474 592 9 1097.1 1400, 14C3 857 07 0 0?31 0 ??8/1 0 3018 598 8 1500 % 0 20 0 02n 0Pb372 0 27/2 611.7 550 4 11701 0 8315 0'253 1.3373 6352 10931 1530 4652 1133 3 0 86?! O4256 1.?b81 662 6 10',5 6 2003 i 2003 , 625 B3 0 u2'.7
. 0 16? % 01883 6721 1032.9 2500 2503 65d 11 0 02c,( 0 1020's 01307 731 7 361 6 1093 3 C 9139 0 3206 1.2345 718 5 216 4 10703 09725 0 1691 1.1619 182 8 973.1 3000 3033 695 33 0 0343 0 050/3 0 0550 831 6 0OL0t 936 0 0 936 0 10512 0 10612 875 9 875 9 37082 32982 70147 00S33 0 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED l WATER (PRESSURE)
A.4 i
heri*ilva. I Abs ms> 15(y.i 300 400 600 600 700 400 900 1000 1100 1200 1300 1400
) 103 200
( 1 e 0 01,1 m m3 Sii g 5m oi, 6m 1 6 6A 00 IISD 2 119.,7 1741 F 12M t 133L 1 1384 A (10174) e 0 120'.- 2 0)D") 21152 2 17?? ?2237 2 270e 2 3144 e 0 0161 76 14 90 ?4 10? ?4 114 21 !?6 15 13P DF. 15001 1(19s 173 t( let 7P 197 70 2Cb 6? 2?l53 23*45 5 > M 01 1140 6 1104 8 1741 3 !?bt ? 133S9 13o4 3 143*t 14 k) 7 1534 7 15tt ? 16391 1693 3 17480 IUit (162 24) s 0!?95 1.8716 1.9369 1 % 43 2 0403 2OM2 21309 2 1776 22159 2 2521 2 2866 2.3194 2350) 2.3t'l i 2 41C,1 e 0 0161 38 34 44 93 51 03 5704 63 03 64 DO 74 08 80 94 86 91 9287 9884 104 80 110 76 116 72 6 68 02 1146 6 11937 12406 12N 8 1335 5 1384 0 1433 4 14h3 5 1534 6 1585 6 16395 1693 3 1747.9 18;3 4 10 i17926 _1.8593 19173 1969? 2 01 % 2.0603 21011 21314 2 17;,7 2 2101 2 2430 2.2744 2.3046 2.3337 (197.21) s 01795 e 0 0161 0 0166 29 f9) 33 963 37 *85 419F6 45978 49 964 53 946 57.926 61905 65 8B2 69858 73 833 77 15 h 68 04 168 09 1192 5 1229 9 1287.3 1335 2 1383 8 1433 2 1483 4 1534 5 1580$ 16344 16932 1747.8 18 (21'3 03) s ; 01295 0.2940 1.8134 1 8720 19242 1.9717 2.0155 2.0563 2 09 % 2 130) 2.1653 2.1982 2.2297 2.2599 2 e O'0161 00166 22.356 25 428 28 457 31 4 % 34 465 37 458 40 447 43 435 46420 49 405 52.388 55 37 20 6 68 05 168 11 1191 4 1239.2 1286 9 1334 9 1383 5 1432 9 1483 2 1534 3 1585 3 1639 3 16931 1747 (227.96) s 0 1295 0 2940 1.7805 1.8397 1.8921 1.9397 1.9836 2 0244 2 0628 2.0991 2 1336 2.1665 2 1979 2.228 e 00161 0 0166 11 035 12 624 le 165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26183 27.676 43 6 68 10 168 15 1186 6 1736 4 1285 0 1333 6 1382 5 1432) 1482 5 1533 7 1585 8 1635 8 1992 7 1747.5 (267.25) s 0.1295 02940 16992 1.7608 18143 1.8624 1.9065 1.9476 1.9860 2 0224 2 0569 2.0899 2 1224 2.1516 e 0.0161 0.0156 7.257 8 354 9 400 10 425 11 433 12 446 13 450 14 452 15 452 16 450 17.448 18 445 1 60 6 68 15 16520 1181 6 1233 5 1283 2 13323 1383 5 1831.3 1481.8 15332 1535 3 163E 4 1692 4 1747.
(292 71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1.8168 1A612 1.9024 1.9410 1.9774 2.0120 2.0450 2.0765 2.106 0 0161 0 0166 0.0175 6 218 7.018 7.794 8 560 9 319 10 075 10 829 11 581 12.331 13 081 13.829 14 577 e
to 6 68 21 168 24 269.74 1233.5 1281 3 1330.9 1380 5 14305 1481.1 1532 6 1584.9 1638 0 1692.0 1748 1802. ,
(312.04) s 0 1295 02939 0 4371 1.6790 1 7349 1.7842 1A289 1 8702 1.9089 1 9454 1.9800 2.0131 2 0446 2.0750 2.1 4935 5 588 6.216 6.833 7.443 8 050 8655 9258 9 860 1040 31.060 11.659 e 00161 0.0166 00175 100 h 68 26 168 29 269 77 1227.4 1.6516 1279.3 1329 6 1379.5 1429 7 1480 4 1532.0 1584 4 1637.6 1691.6 17M.5 180 1.708S 1.7586 1.8036 13451 1.4839 1.9205 1.9552 1.9883 2 A199 2.0502 2J0 (32722) s 0.1295 0.2939 0.4371 e 0 0161 0 0166 0 0175 4 0786 4.6341 5.1637 5 6831 6 1923 6 7006 7.2060 7.7096 8.2119 8.7130 9.2134 9.71 120 h 68 31 16833 269 81 1224 1 1277.4 13281 13784 1428 8 1479 8 1531.4 1583 9 1637.1 1691.3 174 2 180 1.6286 1.6872 1.7376 1.7829 13246 13635 1 9001 1.9349 1.9680 1.9996 2.0300 2.0 (341.27) s 0.1295 0 2939 0 4371 e 0 0161 0 0166 0 0175 3 4651 3 9526 4 4119 4.8585 5.2995 5.7364 6 1709 6 6036 7.0349 7.4652 7 2946 8 140 6 68 37 168 38 269 85 1220 8 1275.3 13268 1377.4 1428 0 14791 1530 8 1583 4 1636 7 1690 9 1745.9 1 (353 04) s 0 1295 02939 0 4370 1.6055 1.6686 1.7196 1.7652 1.8071 13461 1 8828 1.9176 1.9508 1.9825 2.0129 2.
e 00161 0 0166 0 0175 3 0060 3 4413 3 8480 4 2420 4 6295 5 0132 5 3945 5 7741 6 1522 6 5293 6 9055 150 6 68 42 168 42 269.89 1717 4 1773 3 1325 4 13764 1427.2 1478 4 1530 3 1582 9 1636.3 1E90.5 1745 6 1 15936 16522 1.7039 1.7499 1.7919 1 8310 1.8678 1.9027 1.9359 1.9676 1.9980 2 0273 ,i (363 55) s 0 1294 02936 0 4370 e 00161 00166 0 0174 26474 3 0433 3 4093 3.7621 4.1064 4 4505 4.7907 5 1289 5 4657 5 A014 6.1363 183 4 68 47 166 47 26C 9/ 1213 8 12712 1324 0 1375 3 1426 3 1477.7 1529 7 15824 1.8894 1635 1.9227 9 1640 19545 1.9649221745.3 0142 1 (373 C&1 s C1294 0.2638 04370 1 5743 1 6376 1.6930 1 7362 1.7784 1.8176 I E .,45 e 0 01E1 0 0166 0 0174 23598 2.7247 3.0583 3 3783 3 6515 4 0008 4 3077 4.6128 4.9165 52191 S.5209 200 > 68 02 168 51 269 93 12101 1269 0 1322f 1374 3 1425 5 1477.0 15291 1581.9 1635 4 1689 8 1745 0 1 (lii EW s 01294 02535 0 4309 1 5593 1.6242 1677G 1.7239 1.7663 1.8057 1 5426 1.8776 1 9109 1.9427 1.97
, OC161 0C165 0 0174 00166 2150: 24662 2 6872 2 9410 3 1939 3 43E2 3 6837 3 9278 4 1709 4 4!31 4 6546 250 > 68 55 166 63 2 70 C5 3/5 10 1263 5 13190 13716 1423 4 1475 3 1527 6 1583 6 16344 1688 9 1744 2 16JO2
( C 97) 0;294 02937 04305 0 5567 1.5951 16502 16076 1.7405 1.7631 18173 18524 1.8458 19177 1.9482 1,9776 00161 0 0165 C 0174 0 0186 17G65 2 0044 22263 24407 26509 2 6155 3 0643 3 2615 3 4721 3 6746 38764
~
e 300 e 66 74 1 % 74 270 14 37L 15 IM77 13152 1368 9 1421.3 1473 6 1526 2 15794 1633 3 1636 0 1743 4 1799 (417 35) s 01294 02937 0 4337 C5565 1 5703 1.6274 16/58 1.7192 17591 3.7964 1.8317 1.8652 1 8372 1.927E 1 e 00161 0C165 00174 0 018C I4113 17078 IP973 2 0332 2 2652 24445 2 6219 2 7923 2 9730 3.1471 3.32 350 4 68 97 165 85 270 ?? 375 ?! 1751 5 13114 13662 1419 2 14716 1524 7 15182 1632 3 Ita7.I 17426 1798 9 (43173; n 01203 0 29 % 043G7 0 56',4 1.5883 1 6077 1.6571 1.7009 17411 1 7787 18141 1.8417 12799 1.9:05 1.94 e 0 0161 0 0166 0 0174 0 0162 1 2841 1 4763 16493 18151 1 9753 21334 22901 2 4450 2 5937 2.7515 2 90 400 a 69 05 16847 270 33 375 27 1745 1 1337.4 1363 4 1417 0 1470 1 1523 3 1576 9 1631.2 16362 17419 179 (444 60; s '.,1293 0293h 0 4365 0 56G3 1.5782 1 5901 1 6406 1 6850 1 7255 1 7632 1.7988 1.8325 15647 1.8955 1 v 0 0161 0 0166 0 0174 0 01E6 0 9319 11584 13037 I4397 15706 1 6937 18756 1 9507 2 0746 2 1977 2.3200 500 m 69 32 1 % 14 27051 3't 38 1231 2 1799 1 1357 / l#12 7 1466 6 1520 1 1574 4 16291 1634 4 1740 3 17 149?) 1 550) 1 6'23 165/8 1 6093 1737; I7730 1 8069 1 8393 1 8702 189)5 (457.01) s 01292 6 2934 04M4 OttEO TABLE A.4 PROPERTIES OT SUPERHEATED STEAM AND COMPRESSED WisTER (TEMPERATURE AND PRESSURE)
A.5
1e mpt estset, I g ,,,g, g p) 100 200 300 400 600 600 700 000 000 1000 1100 3209 0 00 1400 1500
, 0 0)(.I 0 0108 0 0174 0 0lP., 07944 044M 1 072014IIP 4? IW 14003 151M 16711 1 7737 It?>4 1 91 %
% 3 let
- 0 1517 8 1571 9 It?7 0 168; t, 1/3t t, 176 g 800 , 69 Sp Ig4 47 27070 375 45. 121*.9 17W 4 1 h l l' 34593 153?9 1 % 44 1 63,1 167L5e 17th 17bl7 17tG9 188 tb4 1844 IL7b7 gag ;01 s 01797 02933 0 4 3L,7 O MS7 e 0 0lf.1 0 01tt. 0 0174 0 0lF' 0 0?04 012P.I 7978 0 9972 10102 1107b 1FC11 1 25*4P. I 3P ss. I 47.7 1tu? I g,5ys O I 34'. t 1403 7 1459 4 1!,14 4 1%94 1674b lut7 1737 2 1794 3 yo? 6 60 f;4 ] f.9 ( 5 270 F9 375(1 4P s e) i 50W 3SPJ l6154 It%O 3 t97C' 1713b I 7t,79 I Sob IL:16 1Scl7 (503Cale 01791 02932 0 esbo 0 % % 0 6b M e 0 0161 0 0166 0 0174 0 0386 0 0704 0 6774 0 7673 0 8750 0 9031 1 0470 1 1784 1 2093 1.2f?S 13tt9 1444t 800 & 70 31 169 88 27107 3M 73 487At 14609 1773 1 13392 139it i 14% A 1511 4 1%69 1622 7 16719 17h 0 1792 5 15484 15%D I6413 1 %;7 1 737!, 17522 17h51 1E164 5 bau (5182.) e 0 1790 0 2930- 0 43S8 0 % 52 0 688) i e 00161 0 01 % 0 0174 0 0166 0 C204 01760 5569 O f4 56 0 7713 0 8504 0 92C2 0 9995 1 0720 1 1430 1 2131 32E75 6 13327 1394 4 1452 2 ISC6 5 1%44 1670 t, 16771 17341 179; 6 900 4 70 37 170 10 271.26 375 84 487 83 1 4659 3.Mll 1.5822 1 6263 1 6Cb2 1 7033 1.M82 1 7713 1b028 18329 l (531.95) s 0 1290 0.2929 0 4357 0 % 49 0 6881 l e 0 0161 0 01 % 0 0174 0 0186 0 0204 05137 06080 0 6875 0 7603 C8295 0 8966 0 % 22 1 02(6 1 0901 11529 i 2000 & 70 63 17033 271.44 375 % 487.79 1 1249 3 1325 9 D89 6 1448 5 1504 4 1%I9 16184 16753 17325 1760 3 0 1269 0.2928 0 43 % 0.5647 0684 4457 1.5149 1.% 77 16126 16530 14905 1 72 % 17589 1.7903 13207 4 544.54) s e 00161 0 01 % 00174 0 0385 0 0203 0 4531 0 5440 0 6188 06865 07505 08121 0 8723 09313 0 9894 1 0468 1100 4 70 90 170 % 27163 376 08 467.M 1737 3 1318 8 1384 7 1444 7 15024 1%94 1616 3 1673.5 IMIO 1789 0 '
14259 1.4996 1 % 42 16000 1.6410 1.6787 13141 13475 1.7793 130g7 ,
(5% 28) s 0.1269 0.2927 0 4353 0 5644 0 6872 a
e 00161 0 01F.6 0 0374 0 0185 0 0203 0 4016 0 4905 0 % 15 06250 0 6645 07418 C 7974 08519 0 9055 09584 <
1200 & 71.16 170 7A 273.82 37620 487.72 1224 2 13115 13793 1440 9 14494 1556 9 3614 2 16716 17294 1787.6 1.4061 1.4851 15415 1.5883 16M8 16679 1.7035 1.U71 1.MD) 1.7996 067.19) a 0.1288 0.2926 0.4M1 0.M42 0 6668
~
e 0Olst-001H 00174 0 0185 0 0203 0 3176 0 4059 0 4712 0 $282 05809 06311 0 679 0 7272 0 7737 0 8195 3400 4 71.68 17324 272.19 376 44 447 65 1194.1 1296 1 3369 3 1433 2 1493 2 15518 1609 9 1668 0 1726 3 1785 0 OS7A7) s 0.1287 02923 0 4344 0 5636 0 6459 1.3652 1.4575 1.5182 1.% 70 1.6CM 14484 16845 3.7185 1J508 1.7815 e 0.0161 0 0166 0 0173 0.0185 0 0202 0.0236 0.3415 0 4032 0 4555 0.5031 0 5482 ' O 5915 0 6336 0 6748 0.7113 3808 4 72.21 371 69 272.57 376 69 487A0 616.77 1279.4 1358 5 1425.2 148E9 1546 6 1605 6 1464 3 17232 1782J 9G487)s 0 1286 0 2921 04M4 0.M31 0 6851 0A129 1.4312 1.4968 1.5478 1.5936 1 6312 1.M78 1.7022 1.7344 1J657 e 0 0160 0 0165 0 0173 0.0185 0 0202 0 0235 0 2906 0 3500 0 3984 0 4426 0 4836 0.5229 0 5809 0.5900 0 6743 2000 a 7213 172.15 272.95 34 93 487.M 615 58 1261.1 I M 7.2 1417.1 1480 6 1541.1 1401.2 1660.7 1720.1 37793 5 21.'32) s 0.1284 0.2918 04H1 0 5626 0A8*3 0 8109 1.4054 1.4M8 1.5302 1.5 M 3 1 41 % 3.M28 1 6876 1.7204 1.M16 I e 0 0160 0.0165 0.0173 0 0184 0.0201 0 0233 0 2488 0 3072 0 3534 0.3942 0 4320 0 4600 0.5027 0 5365 0.5695 3000 8 73.26 172 60 273.32 377.19 487.53 614 44 1240.9 1353 4 1408 7 1447.1 1536 2 1596.9 1657.0 1717.0 1777.1
! 33500) s 0.1263 0.2916 0 4337 0 % 21 064M 03091 1.3794 1.4578 1.5134 1.M03 1.6014 14391 1.6743 1.70M 1.7385 e 0 0160 0.0165 0.0173 0 0184 0 0700 0 0230 0 1681 0 2293 0 7712 0.3068 03390 0 1692 0.3980 04259 0 452$
2S00 4 74 57 173 74 274 27 377 82 487.50 612.08 1176 7 1303 4 1386 7 14575 1522.9 1585 9 1647A 1709.2 17704 (688.11) s 0.1280 0 2910 0 4329 0 M09 0 6815 0 8048 1.3076 1.4129 1.47M 1.5269 1.5703 14094 144% 1 6796 3.7131
]
e 0 0160 0 0165 0 0172 0 0183 0 0200 0 0228 0 0982 0 1755 0.2161 0.2484 0 2770 0 3033 0 3282 0.3522 0.3751 3000 A 75 63 17e 88 275.22 378 47 467.52 610 06 1050 5 12670 1363 2 1440.2 1503 4 15748 16155 1701.4 17(1.8 (49t.33)s 0.1277 0.29.4 0 4320 05%7 0 6796 0 8009 1.1966 1.3692 1.4429 1.4976 1.5434 1.% 41 1.621' 3.05E1 i M88 :
e 0.0160 C 0165 0.0172 0 0183 0 0199 0.0227 0.0335 0 1588 0 1987 0.2301 0 2576 0 2827 0J065 0.3291 03510 3200 & 76 4 175 3 275 6 3787 487.5 409 4 800 8 1250 9 1353 4 1433 1 15038 1570 3 16343 1698 3 17612 1.3515 1.4300 1.48 % 1.5335 1.5/49 1A126 1 6477 1 A806 '
! (70i O8: s 0 1276 0 2902 0 4317 05592 06768 07994 0 9708 e 0 0160 0 0154 0 0172 C CIE3 00199 0 0225 0 0307 01364 0144 0 20!6 02326 02%3 02784 01995 C 319T '
3500 4 77.2 1760 2762 3793 487 6 606 4 779 4 1724 6 1338 2 1422 2 14955 1%33 16292 It93 6 17 t 7.1.
s 01274 C.2899 04312 0 M85 0 6777 07973 09508 1.3242 1.4112 14709 1.5194 1.% 18 16002 3435$ 1669:
4 e 0 0159 C 0164 00172 0 0162 0 0196 0 0223 00287 01052 0 1463 0 1752 0 1994 02210 0 2411 0 2601 0 278:
4000 6 ys 5 177 2 277 3 379 8 4573 6065 763 0 1174.3 13116 1403 0 1481.3 1%22 1619F 1%57 IM0i !
e 01271 Opn93 0 4304 0 % 73 0 6760 0 7940 0 9343 12754 1.3807 14401 14976 1.5417 1.5812 1.6177 1.651f I e D 0159 0 0164 0 0171 0 0181 0 01 % 0 0219 0 0268 0 0591 0 1038 0 1312 0 1529 01718 0 IS*3 0 2050 0 220:
l S000 a al 1 179 5 279 1 381 2 4881 604 6 746 0 1042 9 1252 9 13(4 L 1452 1 15291 16DJ 9 It 70 0 17??.s e 0.1765 0 2Ebl 0 4267 0.5%0 0 6726 0 7880 0 9153 1.1593 1.3207 3.4001 1.4582 1.5061 1.t,481 1.%E3 I AJ18 ,
e 0 0159 0.0163 0 0170 C 0160 0 0195 0 0216 0 02 % 0 0397 0 0757 0.1020 0 1221 0.1391 0.lM4 O!6S4 0 18 40C0 4 837 1813 281.0 3b2 7 apt 6 602 9 736 I 9451 1168 8 1323 6 1402 3 1505 9 1%20 1654 2 17243 s 0 1258 0 2670 0 4271 0 % 28 0 M93 0 7826 0 9026 1.0176 1.2615 1.35'4 I.4229 1.4745 1.5194 1.5%3 159el e 00158 0 0163 0 0170 0 0180 0 0193 0 0713 0 0248 0 0334 0 0573 0 031 A 01004 01160 0129E D1424 0 154:
7000 A 86.2 184 4 283 0 3tle 2 489 3 601 7 729 3 9018 1124 9 12P17 13922 1490 6 1%31 16)* 6 1711 e 01752 0 2859 0 4256 0 t',07 0(563 0 7/77 0 8926 10350 12055 121iI i1904 I44o6 3493! !57-5 I 573 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED)
A.6 l
- - - - - - . . . . - - _ - - -_ - - - _ _ - - .0
,, ,, , ,, ; 7 ...,..,
" >>"n l
..a ,,
1,. .," .... ?.;
T~j ' NY$ D $,
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K i 747,jJg
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.. h7ALWs/n. itN w/// %~ > i n, ..
l}l$7g / N ///%j '~
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- /Rar2$f;j n, - ,
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b"' a,l f,//))h 7) y l,.
~
Wh ex w a ///n/ l ..
M Z W & yd ; dMA6n7gg -
UN#X7xgg5u U F
- A ## M 7x y 6 /y -
l JUt ' /w g/ ..
Zd<YM - ... , , , .
ni. ,. ,..,
l i
FIG N A.5 MOLLIER Et?THALpy-Ef!TROPY DIAGRAg A.7 i
. n 1
l PROPEHTIES OF WATEM Denelly c (Ibstiti PSIA Temp Esturated 2300 240D 2500 3000 Liquid 1000 2000 2100 2200
(* F) 62.909 62 93 62.951 63.056 62.637 62.846 62.867 62.888 32 62.414 62.846 62.87 62.99 62.75 62.774 62.798 62.822 60 62 38 62.55 62 465 62.559 62.390 62.409 62 427 62.446 100 61.989 62.185 62.371 60.702 60 549 60.568 60.587 60.606 60.118 60.314 60.511 60.53 200 57.836 57.859 57.882 67.998 57.537 57.767 57.79 57.813 300 57.310 64 342 64.373 64.529 54 218 54.249 64.28' 54.311 400 63.651 63.903 53.95 64.11 63.825 63.86 63.89 63.925 410 53.248 63.475 63.79 63.89 63.425 63.46 63.50 63.53 62.798 63.025 63.36 63.40 420 63.02 63.065 63.09 63.265 62.575 62.925 62.95 62.99 430 62.356 62.64 62.56 62.275 62.42 62 45 62.475 62.51 440 61.921 62.125 62.21 62.41 62.065 62.10 62.14 62.175 450 61.546 61.66 62.025 61.96 61.64 61.68 61.725 61.76
$1.020 $1.175 61.56 61.61 -
460 61.22 61.25 61.30 61.50 61.14 61.175 470 '- 60.505 60.70 61.1 60.74 60.78 60.825 61435 50.20 60.62 .60.66 60.7 480 60.00 60.31 60.35 60 575 49.685 60.13 60.175 60.22 80.265 490 49.505 49.81 49.858 60.098 49.097 49.618 49.666 49.714 49.762 600 48.943 49.254 49.305 49.56 49.05 49.101 49.152 49.203 610 48.31 48.51 48.735 49.01 48.515 48.57 48.625 48.68 620 47.85 47.91 48.46 48.45 47.978 48.037 48.096 48.156 47.17 47.29 47.86 47.919 630 47.428 47.494 47.56 47A9 47.23 47.296 47.362 640 46.51 46 862 46.93 47.27 46.59 46 658 46.726 46.794 650 45.87 46.216 46.29 46.66 45 92 45.994 46.068 46.142 560 45.25 45.54 45.62 46.02 45.22 45.30 45.38 45 46 570 44.64 M.844 44.93 45.36 44.50 44.586 44.672 44.758 530 43.66 44.11 44.205 44.66 43.73 43825 43.92 44 015 650 43.10 43.33 43.434 43.956 42.913 43.017 43.122 43.226 600 42.321 42.432 42.55 43.14 41.96 42.08 42 196 42.314 E10 41.49 41.483 41.616 42283 40.950 41.083 41.217 41.35 620 40.552 41.44 63*s 39.53 40.368 640 38 491 39.26 65r, 37.31 29000 660 36.01 36.52 670 34.48 34.638 633 32.744 32.144 690 30.516 l .
I TABLE A.6 PROPERTIES OF WATER, DENSITY
- A.8
4
. -s.
- 5. ' THEORY OF NUCLEAR POWER PLANT' OPERATION, FLUIDS, AND PAGE 21 y
ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 5.01 (1.00) d REFERENCE General Physics, HT&FF, pp. 137 - 142
. ANSWER 5.02 (1.00) b REFERENCE General Physics, HT&FF ANSWER 5.03 (1.00)
D REFERENCE WNTO, pp. I-5.63 - 77 1.50 ANSWER 5.04 (9,44)
- a. t$etteetteeRWrftvE ~OELETED wi6D a rts
- b. NONCONSERVATIVE (0.5);
- c. NONCONSERVATIVE (0.5r
- d. CONSERVATIVE (0.5')
REFERENCE Westinshouse Nuclear Training Operations, pp. I-4.19 - 21 ANSWER- 5.05 (1.50)
- a. FALSE (0.5)
- b. FALSE (0.5)
- e. FALSE (0.5) l
c-
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND. PAGE 22 y g--------------------------------------
' ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE -
Hestinghouse Nuclear Trainins Operations, p. I-5.36 - 43 ANSWER 5.06 (1.50)
- o. UNDERMODERATED (0.5) b.. OVERMODERATED (0.5)
- c. UNDERMODERATED (CVER- ts: AssuntD TEMP Deceshst AND (0.5)
E4PLA N 4Te oN)
REFERENCE Westinshouse Huelear Training Operations, pp. I-5.7, 9, a 10
. ANSWER' 5.07 (1.50)
- o. LESS NEGATIVE (0.5)
- b. MORE NEGATIVE (0.5)
- c. MORE NEGATIVE (0.5)
REFERENCE Hestinghouse Nuclear Training Operations, p. I-5.29 ANSWER 5.08 (1.50)
- n. DECREASE (0.5)
- b. DECREASE (0.5)
- c. INCREASE (0.5)
REFERENCE feneral Physics, HT&FF, p. 320 ANSWER 5.09 (1.50)
- c. 5 (0.5)
- b. 1 (0.5)
- c. 4 (0.5)
r-
- 5. . THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 23 g g ANSWERS -- NORTH-ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE .
General Physics, HT&FF, pp. 228 - 230 ANSHER 5.10 (1.50)
- o. 1 (0.5)
- b. 2 (0.5)
.c. 1 (0.5)
REFERENCE I;eneral Physics, HT&FF, pp. 99 & 218 ANSWiER 5.11 (1.00)
As +,he core a3es, the pellet and clad creep to3 ether causing an increase in gap conductivity (0.4 pts.). This causes a smaller delta T of the fuel for a given power change (0.3 pts.). The smaller delta T of the fuel causes a smaller change in reactivity for a given power change (0 2 pts.).
(pem/F) X F/% power) = pcm/% power more nes less less nes REFERENCE Westinghouse. Nuclear Training Operations, p. I-5.22 ANSWEP 5.12 (2.00)
- 1. Eoron Concentration De'eresses (0.5 pts.) - HORE NEGATIVE (0 5 pts.)
- 2. Fission Product Buildup (0.5 pts.) - LESS NEGATIVE (0.5 pts.)
REFERENCE Westinghouse Nuclear Training Operations, p. I-5.31 ANSWER 5.13 (1.00)
During a LOCA the core may be blown dry and reflooded by the CLAs.
Since the upper half will be reflooded last, more restrictive limits are placed on the upper half of the core durir,9 normal operations.
5.- THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 24
-ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUCLAS REFERENCE f:eneral Physics, HT&FF, p. 249
.. i 6.~ PLANT SYSTENS DESIGN, CONTROL, AND INSTRUMENTATION PACE 25 r -ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUCLAS i.
ANSWER 6.01 _ (1.00) b REFERENCE SPS TS 2 3-2.
NAPS RPS Adv. Skills Training.
. ANSWER 6.02 (1.00) d REFERENCE SPS Excore Inst. Sys Des.
NAPS Nuclear Inst. Sys. Lesson Plan.
ANSWER 6.03 (1.00)
D REFERENCE NAPS Plant Manual, Vol 3, Group 30.
ANSWER 6.04 ( .30)
FALSE.
REFERENCE f.PS Primary Systems Sys Des.
NAPS RCS Press. Inst. Lesson Plan.
ANSWER 6.05 (2.00)
- a. 1 (0.5)
- b. 4 (0.5)
.c. 1 ost E WW (0.5)
- d. 3 (0.8)
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 26 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY 00VGLAS REFERENCE
.SPS Rod Control Sys Des.
NAPS Rod Control'L'esson Plan.
-ANSWER 6.06 (2.00)
O. '4 (0.5)
- b. 3 (0 $)-
- c. 1 (0.5)
- d. 2- (0 5)
RFFERENCE NAPS Plant Manual, Inst. Air, RCS, sir Condensater Elect. Dist.
ANSWER 6.07 (1.00) l '. 30%-(design) or 25% (actual) (0.5)
- 2. N44 (0.5)
REFERENCE NAPS SGHLC & P Advance Skills Training.
ANSWER 6.08 ( .50) 2 REFERENCE NAPS Plant Man. 125 vde Power Supplies.
ANSWER 6.09 (1.00) 9 0.25 points each!
It receives inputs from each of the following:
- 1. Temperature of impulse line.
- 2. RCS-temperature.
- 3. Wide ranse pressure.
snd
- 4. The d/p cell is located outside of containment.
L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
1
- e *
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 27 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE SPS RVLIS Sys Des.,
NAPS RVLIS Advance Skills Training.
ANSWER '6.10 ( .50) 40%
REFERENCE SPS Main Steam Sys Des.
NAPS Steam Dump Advance Skills Training.
ANSWER 6.11 ( .50)
Tave less than or equal to 543 F (2/3 loops)-SPS REFERENCE SPS SGWLC Sys Des.
NAPS SI or ECCS ESF Lesson Resources.
ANSWER 6.12 (1.00)
- a. Manually or automatically disabled (0.5)
- b. Cet r+ 4 en -
3 .. between-0 1 ...d 10 dr;rrer b/ DTD '^ 25?-er '
^
=d C d:;reer hy s A.ppr o=e.kiwg Sak uts kied W69 (0.5)
REFERENCE c;PS-Core Coolins Monitor Sys Des.
NAPS CCM Advance Skills Training.
ANCHER 6.13 (1.00) 0 .5 points eacht For NAPS
- 1. 2/2 pressures.
- 7. 3/4 cire water pump breakers shut.
REFERENCE NAPS Steam Dump Advance Skills Training.
c' s
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 28 ANSWERS -- NORTH ANNA 182 -85/12/04-JERRY DOUGLAS CNSWER 6.14 ,
(1.00)
- a. Place key switches to AUTO (0.5)
- b. 140F (0 5)
RFFERENCE NAPS RCS Pressure Inst. Lesson Plan.
ANSWER 6.15 (1.00)
Halon [0.53 CO2 CO.53 REFERENCE NAPS Fire _ Protection Advanced Sills Training.
ANSWER 6.16 (1.50)
.1. Core decay heat. (0.5)
- 2. Heat from RCPs. (0.5)
- 3. Stored heat in RCS/SG metal. (0.5)
REFERENCE NAPS AFW Lesson Resources.
ANSWER 6.17 (1.50)
- 1. Shuts clarifier effluent valve (0.5)
- 2. Shuts holdup tank influent valva (0.5)
- 3. Trips S/G blowdown pumps (0.5)
REFERENCE NAPS Hi Range Rad Monitors Lesson Plan.
~
, i. .
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 29
~
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Rd6YUL6656dL'EUUTR6L ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
~
. ANSWER 7.01 (1.00) a
. REFERENCE NAPS 1-OP-22.11, p.4.
075/000; X1.02 (2.9/3.1)
ANSWER 7.02 (1.00) y A or'O W6D REFERENCE NA TS 3/4.2.1 SilRRY TS 3.12-B.4 001/050; PWG-8 (3.6/4.5)
ANSWER 7.03 (1.00)
'b REFERENCE NA ADM 5.8, .pp 2/3 PWG-23:l Plant Staffing and Activities.(2.8/3.5)
ANSWER 7.04 (1.50) a) No (+.5 ea) b). No c) Yes REFERENCE NA CSF F-0.4, F-0.5, F-0.6 PWG-10: Recogni=e abnormal indications for E0Ps (4.1/4.5)
-m
'7 ' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 30
~~~~ ~ ~~~~~~~~~~~~~~~~~~~~~~~~
RI6EUL 656IL 6U IRUL ANSWERS -- NORTH ANNA 182 -85/12/04-JERRY DOUGLAS ANSWER 7.05 (1.00)
-Unexpected rise in S/G 1evel (+.25 ea)
~
-High radiation on a S/G blowdown line
-High radiation on an MS line monitor
-High radiation as determined b.y sampling and analysis REFERENCE' Surry EP-4.00, pp 3 NA 2-EP-3, pp 2 EPE-038; EA2.03 (4.4/4.6)
ANSWER 7.06 (2.00)
- 1. 2750 (0.5)
- 2. 4800 (0.5)
- 3. Supervisor Health Physics (or designee) (0.5)
- 4. Vice President Nuclear Operations (0,5)
RFFERENCE NA HP Manual, pp 2.3-7 PWG-15: Knowledge of Facility Radeon Rqmnts (3.4/3.9)
ANSWER '7.07 (1.50)
Surry!' levelness of the head, binding of guide studs, RCC drive shafts are
.not being lifted (+.5 ea response)
North Anna Levelness, Upper internals are not being lifted, no Control rod drive shafts are being lifted (+.5 ea)
REFERENCE F:orry OP-4.1, pp 17 NA OP-4.1, pp 26 034/000; PNG-7 (2.9/3.7)
1 l
- 7. PROCEDURES - NJRMAL, ABNORMAL, EMERGENCY AND PAGE 31
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R I65dL655E5L E TEUL ANSWERS -- NORTH ANVA 182 -85/12/04-JERRY DOUGLAS
~
ANSWER 7.08 (1.00)
O'O.25. points each!
- 1. Start all available service air compressors.
- 7. Start all available_ instrument air compressors.
3.. Secure reactor coolant pumps.
- 4. Secure char 3i ng pump.
REFERENCE NAPS 1-AP-28.1, p.3.
EPE-065; PWG-11 (3.9/3.9)
ANSWER 7.09 (1.00) ckt h1 Verify Chargins/SI flow ( + A ir- c e ) (ST.is ON)
C w3 d4 RCS Pressure < 1600 psig ( Sur ry ) OR CC.W LOIT (0.7.)
0.0 ' '
< 1230 psis (NA) L1680 pat [
REFERENCE (O' L) 01 SONP Foldout Page NA Foldout paSe for 2-EP-0 Sorry Foldout page for EP-1.00 003/000; PNG-10 (4 1/4.4)
ANSWER 7.10 (1.50)
- 1. Verify SI/CHG pumps running (Verify 4804)- '(0.5)
- 2. Switch BATP to FAST speed (0.5)
- 3. Open MOV-( ) (0.5)
REFERENCE f.orry ECA-1, pp 4 NA 2-ECA-1, pp 3 EPE-029; PWG-11 (4.5/4.7)
I
- 7. PROCEDURES - NORMAL, ABNORMAL; EMERGENCY AND PAGE 32
~~~~
R A65ULU55E AL"CUUYRUL'~~~ ~ ~~~~~~~~~ ~ ~ ~~~~ ~ ~~~
ANSWERS - ' NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 7.11 (1.50)
- 1) Station Manager (+.35 for title, +.15 in correct position)
'2) Assistant Station Manager
- 3) Superintendent Operations REFERENCE N A NAEP, - pp 5.10 PWG-36: E-Plan (2.9/4.7)
ANSWER 7.12 (1.50)
SURRY ( +.25 ea) IHORTH ANNA (+.3 ea)
_____ l__________
-Containment Condition.s Normal 1-RCS Press > 2000 psis a increasing
-RCS Pressure > 2000-psis I-RCS Subcooling > 50 Des F
-RCS Subcooling > 50 Des F l-PZR Level > 50%
-PZR Level > 50% l-SG Level > 10% or > 30% Advrs Cnte
-SG Level > 65% (WR) or > 17 % (NR) l OR OR l-AFW Flow > 730 GPM
-AFH Flow > 540 GPM i l
REFERENCE' 5urry EP-2 00 foldout NA EP-0 Foldout page 006/050; PWG-7 (3.8/4.2)
ANSWER 7.13 ( .50)
Informs _ operators to allow a 15 minute delay (+.25) before reclosing a breaker'should it trip open (+.?5)
REFERENCE.
NA'ADM 14.0, pp 9 Sorry ADM 29.7, pp 25 PWG-14 ' Knowledge of Tagging procedures ( 3 . 4 / 4 . '> )
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND. PAGE 33
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~RI65UL6656AL 66UTR L ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 7.14 (1.00)
Normal Spray >>>PZR PORV>>> Auxiliary Spray (+.33 for.each in correct spot)
REFERENCE Surry EP-4.00, pp 12/13 NA 2-EP-3, pp 9/10 EPE-0387-EK 3.01(4.1/4.3)
ANSWER 7 15 (1.00)
- 1. RWST Suction Open (MOV-2115 B & D) (0.25)
- 2. VCT Suction Closed (MOV-2115 C & E) (0.25)
- 3. ' Normal Charging Closed (MOV-2289 A & B) (0.25)
- 4. Letdown Isolation Closed (HCV-2200 A, B & C) (0.25)
REFERENCE NA EP-0, pp 2/3 006/000; A3.02 & A3.03 (4.1/4.1)
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS,.AND LIMITATIONS PAGE 34 ANSWERS -- NORTH ANNA 112 -85/12/04-JERRY DOUGLAS ANS'WER 8
. 01 - (1.00)
- D REFERENCE NA TS 4-20 SR TS 3.1-20
-004/010 K5.04 (2.6/3.3)
ANSWER 8.02 (1.00) c REFERENCE NA TS 3/4 1-1, 1-9, 1-7, & 1-12 ANSWER- 8.03 (1.00)-
b 4d W69 REFERENCE NA'TS 3/4 4-7a and 0-1.
ANSWER 8.04 (1.00) a REFERENCE NA TS 3/4 1-24, 1-26, 1-21, 1-18.
e ,e ,
w e, ,--r,,,.-w ,-~= wee-w --~<-ws-w---w>r-<,e-* * --s,-w - - + - ~ - - - - ~ - -w- - -v----- - ~-
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 35 ANSWERS ~--- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS ANSWER 8.05- _
(2.00)
(0.2 pts. per answer)
- c. 4
- b. 2, 4
- c. 7
- d. 3, 9
- o. 8, 10
- f. 1 3 6 REFERENCE NA ADM'19.23 p 1.
ANSWER- 8.06 (1.00)
- 0) SR 24,600 +or- 2,000 NA 25,000 +or- 2,000 b) SR&NA suspend all additions of radioactive material to the tank.
REFERENCE SR TS 3.11-7,8.
NA TS 3/4 11-17.
ANSWER 8.07. (1.00) 23 (+/- 2)
REFERENCE.
SR TS 4.0-1 NA TS 3/4 0-2.
ANSWER ~ 8.08 (1.00)
- a. 0.10 microCi/cc (0.5) I
- b. Steam line rupture (or any accident which results in the release of the entire contents of the Unit's steam generators to the atmosphere). (0,5)
- , e. <
'8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 36 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS REFERENCE SR TS 3.6-2, 3.6-5.
NA TS 3/4 7-8, B.3/4 7-3.
ANSWER 8.09 (1.00) 16, 24, 72 (0.33 pts. each)
REFERENCE SR ADM-3 p 4.
NA ADM-20.3 p 4.
ANSWER 8.10 ( .50) 30 REFERENCE f;R EPIP 5.03 p i NA EPIP 5.03 p 1~
ANSWER 8.11 (1.50)
Ectablish a continous fire watch (0.5) with backup fire suppression equipment (0.5) for the unprotected area within i hour (0.5).
REFERENCE SR TS 3.21-3
.NA TS 3/4 7-69a.
ANSWER 8.12 (- b 4 H H (0.16 pts. each) 1 determine appropriate ~ remote assembly-TFea
- 2) req road block (Louisa Co-sNeriff)
- 3) no t i f y seb.ir Ry,, ..- EWG
- 4) notify ERC "N
- 5) noti . EN ity post'i' N b 6 80 ify training department ant u vironmental lab N
REFERENCE NA.EPIP 5.05 pp 2,384
- ...'a
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND' LIMITATIONS PAGE 37 ANSWERS -- NORTH ANNA 1&2 -85/12/04-JERRY DOUGLAS
-ANSWER' 8.13 ; (1.00)
NO (0.5 pts.)
It is not capable'of performing its intended function. (0.5 pt.s)
REFERENCE OR YES , it no ado sta d ste ptred. W69 CR TS 10 1-1.
SR TS 1.0-2 NA TS 1.0 1-1.
ANSWER 8.14 (1.00)
SR During recalibration of.the excore symmetrical off-set detection system.
NA'When used fort
- a. Recalibrat'on i of the excore neutron flux detection system. (0.33)
- b. Monitoring the OPTR. (0.33)
- e. Measurement of hot channel factors. (0.33)
REFERENCE
!;R TS 3.18-1.
NA'TS 3/4 3-42.
ANSWER 8.15 (1.00)
-1) Onsite operations support center (0.5)-
- 2) Leave the control. room.unless'otherwise directed-by the shift supervisor. (0.5)-
REFERENCE NA ADM'20.11 p 3.
[,.
j.es 4
- 9. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATI0:!S PAGE 38-ANSWERS -- NORTH ANNA 182 -85/12/04-JERRY DOUGLAS ANSWER 8.16 _ (1.00)
Temporary modifications, e:: cept those specifically mentioned in the UFSAR, to existins systems or components which are operable or are to be made operable.
OR (any 5/at 0.2 pts. each)
' 1. point to point electrical connections
- 2. lifted electrical leads
- 3. point to point hose connections
- 4. piping or tubing bypass
- 5. piping or_tubins disconnect
- 6. altered flow path REFERENCE NA ADM 14.1 p 2.
ANSWER 8.17 (1.00)
NA Controlled leakage shall be that seal water flow supplied to the reactor coolant pump seals.
~
SR Leakage sources such as the reactor coolant pump controlled leakage seals.
REFERENCE NA TS p 1-2.
OR TS p.3.1-13.
, L. 4=
TEST CROSS REFERENCE PAGE 1
- QUESTI N. VALUE REFERENCE 05.01 1.00 WGD0000769
- 05.02 1.00 WGD0000771
- 05.03 1.00 WGD0000792' 05.04- 2.00 WGD0000760 05.05- 1.50. WGD0000765 NGD0000761 05.06 -1.50 05.07 1.50 WGD0000743 05.08 1.50 WGD0000772 05.09 1.50 -WGD0000773 05.101 1.50 WGD0000774 05.11 1.00 WGD0000762 05.12 -2.00 WGD0000764 05.13 1.00 WGD0000775 18.00 06.01 1.00 WGD0000841 WGD0000850 06.02 1.00 06.03 1.00 WGD0000863 06.04 .50 WGD0000847 06.05 2.00. WGD0000842 06.06 2.00 WGD0000862 06.07 1.00 WGD0000856 06.08 .50 WGD0000861
-06.09 1.00 .WGD0000840 06.10 .50 WGD0000844 06.11- .50 WGD0000849 06.12 1.00 WGD0000851 06.13 1.00 WGD0000855 06'14
. 1.00 WGD0000857 06.15 1.00 WGD0000858 06.16 1.50 WGD0000859 06.17 1.50 WGD0000864 18.00 07.01 .1.00 WGD0000822 07.02 1.00 WGD0000825 07.03 1.00 WGD0000876 o07.04 1.50 WGD0000829 07,05 1.00 WGD0000830 07.06 2.00' WGD0000832 07.07 1.50 WGD0000835 07.08 1.00 WGD0000823 07.09 1.00 WGD0000824 07.10 1.50 WGD0000828 07.11 1.50 WGD0000834 07.12 1.50 WGD0000837 07.13 .50 WGD0000078 07.14 1.00 WGD0000826
.,ci e TEST CROSS REFERENCE PAGE 2 OdESTION VALUE- REFERENCE 07.15 -1.00 NGD0000882 18.00 _
08.01 1.00 WGD0000798 08.02 1.00 WGD0000799 08.03 1.00 WGD0000800 08.04 1.00 WGD0000801 08.05 2.00 WGD0000811 08.06 1.00 WGD0000803' 08.07' 1.00 WGD0000806
=08.08 1.00- WGD0000807 08.09 1.00 WGD0000809 08.10 .50 WGD0000816 08.11 1.~50 WGD0000808 08.12 1.00 WGD0000814 08.13. 1.00 WGD0000804 08.14 1.00 WGD0000805 08.15 1.00 WGD0000812 08.16 1.00 WGD0000813-08.17 1.00 WGD0000802
~ 18.00
__m.__
72.00
Attsch: Int 1 Pigs 1 ENCLOSURE 4 12/0V85 ,
NORTH ANNA POWER STATION 8 COMMENTS ON WRITTEN NRC EXAMINATIONS ADMINISTERED ON DECEMBER 4,1985 A. Reactor Operator Examination
- 1. Question 1.6 Comment: Not performance based. We do not use Power Coefficient, we do not have power coefficient curves in the plant. This is not trained on at North Anna Power Station.
Recommendation: Delete the question.
Reference:
N/A - not used at NAPS
- 2. Question 1.12 t
Comment: It is unclear from the question that a more detailed ,
explanation as that required by the answer key is needed for ;
full credit. ,
~
Recommendation: Either accept stating that fuel pellet swell and clad creep cause the doppler only power coefficient to become less negative over core life for full credit or weight the response so that a much greater proportion of the credit is g given on the answer key for that portion of the response. ,
Reference:
WNTO I-5.22 i t
- 3. Question 2.01 Comment: The question contained a typographical error (except '
vs. accept) which changed the meaning of the question. Thus the examinee's would not know what information was being requested. .
Recommendation: Delete the queation.
- 4. Question 2.07 Comment: Memorization of all electrical loads are not required by the job task analysis therefore, MCC load lists and air compressor power supply are not required to be memorized by operators.
Recommendation: Delete the question. (If question not deleted, accept either 2 or 3 as the correct answer for 2.07b.-)
Reference:
Human Performance Evaluation Report 85-010 ,
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Attechunt 1 Pags 2 12/09/85
- 5. Question 2.13 Comment: The question did not _ask for the conditions under which the seal bypass was r.ecessary.
Recommendation: Delete the 0.5 point deduction for not including the condition under which the seal bypass is necessary.
Reference:
N/A
- 6. Question 2.14 Comment: The condensate can be sent directly to the hotwell or the condensate storage tank. (CST)
Recommendation: Accept either answer, condensate is pumped to either the hotwell or the CST.
Reference:
Print #11715-FM-85A-8 L-7 ;
- 7. Question 2.15 Comment: Expecting operators to recall from memory the design basis for this piece of equipment does not support performance based training. During the conditions listed on the answer key, an operator can take no actions that would affect the ,
performance of this equipment.
4 Recommendation: Delete the question.
Reference:
- 8. Question 3.07c Comment: The answer would depend upon previcis conditions.
Rod speeds would be different if the temperature mismatch was greater than 1, approaching 1 as compared to.a mismatch of less than 1, approaching 1.
Recommendation: Accept. choice 1 or 2 from column B as a correct answer.
Reference:
Westinghouse Rod Control Tech Manual i-I 1
Attcchmsnt~1 P:g2 3 12/09/85 ,
- 9. Question 3.08 8 Comment: Due to the question identification of " Reactor Power" l and not identifying initial power levels, N-44 would also provide an input to the bypass valves.
Recommendation: Accept either N-44 or turbine first stage pressure as an acceptable answer.
Reference:
SGWLC&P Lesson Plan
- 10. Question 3.10 Comment: ~The question is of limited operational importance since the operator does not control the factors. In addition, the verb, explain, indicates that a general description of the methods used is desired instead of a list of specific items.
If the question was phrased as " List the four means of RVLIS >
compensation to maintain the required accuracy during a LOCA," '
then it would be reasonable to expect all four responses, j Recommendation: Accept an explanation of the general methods ,
used to compensate for accident conditions or delete the question.
Reference:
NuReg 1021 ES-202 Part E #18 l
- 11. Question 3.11.b i
Counnent : Operators are not required to memorize the exact setpoints of lights on the Core Cooling Monitor. These setpoints are provided in the body of the procedure which is required to be used during malfunction conditions with these units. They are taught that the margin to saturation is reduced if this light is illuminated.
Recommendation: Accept " reduced margin to saturation" as a correct answer, in addition to the specified answer. ,
References:
NAPS CCM Instructor Guide IAR-2 IBF3 (Annunciator Response Procedure)
- 12. Question 3.15a Comment: The question does not specify that all conditions which will result in the' start of the emergency diesel general should be listed as indicated by the answer key. The verb (explain) indicates that a general discussion of the conditions or signals which initiate the general is expected.
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Attachment 1 Paga 4 12/09/85 ,
Recommendation: Accept a discussion of the conditions or signals which start the emergency generator without requiring a l list of all items.
Reference:
NuReg 1021 E S-202 Part E #18
- 13. Question 4.06b
-Comment: The new TSC is located in the service building adjacent to the main control room as opposed to the records building.
Recommendation: Accept above comment as the correct answer to 4.6b.
Reference:
Actual physical plant location
- 14. Question 4.09 1
Comment: The question specified that notifications should be j excluded from the answer. However, the answer key included ,
"netifying the shift supervisor. . ." ,
Recomunendation: Do 'not take points off for not including notification of S.S.
Reference:
N/A. f 1
B. Senior Reactor Operator Exam
- 1. Question 5.04.a
- a. answer incorrect.
Comment: Plot would under predict criticality which, using the same reference, is conservative.
~
Recommendation: Change answer key to " conservative".
Reference:
NAPS Reactor Theory Instructor Guide WNTO I-4.20, 21
- 2. Question 5.06.c Conunent : Answer for "c" could be "overmoderated" if the resultant temperature decrease from the rod insertion was considered. ,
Recommendation: Accept- reasonable explanation of the above ,
, vice three one-word answers given ,
I
Reference:
WNTO I-5.7 i
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Attcchxnt 1 P ga 6 12/09/85
- 3. Question 5.07 i comment: Not performance based. We do not use Power Coefficient, we do not have power coefficient curves in the plant. This is not trained on at North Anna Power Station.
Recommendation: Delete the question.
Reference:
N/A
- 4. Question 5.11 Comment: See comment on RO exam question 1.12.
- 5. Question 6.05 Comment: The answer would depend upon previous conditions.
Rod speeds would be different if the temperature mismatch was greater than 1, approaching 1 as compared to a mismatch of less than 1, approaching 1. ,
Recommendation: Accept choice 1 or 2 from column B as a correct answer.
Reference:
Westinghouse Rod Control Tech Manual
- 6. Question 6.06 Comment: See comment on R0 question 2.07.
Recommendation: Delete the question. (If question not deleted, accept either 2 or 3 as the correct answer for 2.07b.)
Reference:
Human Performance Evaluation Report 85-010
- 7. Question 6.09 Comment: See comment on RO question 3.10.
- 8. Question 6.12 Comment: Operators are not required to memorize the exact
.setpoints of lights on the Core Cooling Monitor. These setpoints are provided in the body of the procedure which is required to be used during malfunction conditions with these units. They are taught that the margin to saturation is ,
reduced if this light is illuminated.
Recommendation: Accept " reduced margin to saturation" as a l correct answer, in addition to the specified answer, i
References:
NAPS CCM Instructor Guide i IAR-21BF3 (Annunciator Response Procedure) ,
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Atttchant 1 P g2 7 12/09/85 j
- 9. Question 7.02 Comment: Answer "d" should also be an acceptable answer in that although operations 8 50% will be restricted, penalties will not be incurred. Penalty minutes are not given at all
'15%.
Recommendation: Accept answer "d" also.
Reference:
- 10. Question 7.04 Comment: Operators / Shift Supervisors are not required to memorize specific portions of Critical Safety Function Status Trees. Operators are trained to use these' instruments, however, it is generally an STA function. Furthermore, NuReg 1021 does not address memorization of CSF Status Trees in any portion. -
i Recommendation: Delete question
References:
- 11. Question 7.07 Comment: NuReg 1021 does 'not require memorization 'of in-the-body steps of operating procedures. This answer is listed on page 26 of OP-4.1 and requires memorization. It is non-conservative and specifically disallowed to rely on memory for operating procedures.
Recommendation: Delete question
References:
NuReg 1021 NAPS Administrative Procedures 19.1 and 19.2 NAPS Operations Standard 10-14-85
- 12. Question 8.03 Comment: B and D are both correct.
Recommendation: Accept both B & D
Reference:
- 13. Question 8.12 ,
Comment: Question requires memorization of EPIP 5.'05 which is not required IAW NuReg 1021. ,
Recommendation: Delete question i
Reference:
i I
- - J- Attcchm
- nt 1 PIga 8 12/09/85 ;
- 14. Question 8.13 I i
Comment: Answer could be either "Yes" or "No". RHR pumps have [
no auto start function and, therefore, are considered operable. ,
Various other pumps fit the same category. '-
~
Recommendation: Accept either "Yes" or "No" with a reasonable explanation.
Reference:
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f-ENCLOSURE 5 REQUALIFICATION PROGRAM EVALUATION REPORT Facility: North Anna Examiner: Douglas Dean Jaggar Date of Evaluation: December 4-6, 1985 Areas Evaluated: -X Written Oral X Simulator Written Evaluation
- 1. .0verall. evaluation of examination: Marginal
- 2. - Evaluation of facility examination grading: N/A Oral Examination .
- 1. .0verall evaluation N/A
- 2. Number conducted N/A-Simulator Examination
- 1. 0verall evaluation Satisfactory
- 2. Number conducted 9 Overall Program Evaluation Satisfactory Marginally Acceptable X Unsatisfactory i See Examination Report.
Submitted: Forwarded: Approved:
-idM (mtb Examinefs huu .
Branch Ctdef 1
>y
// 5.ection Chief 1
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