Text

Exam Rept 50-327/OL-85-02 on 851112-15.Exam Results:Four Reactor Operator Candidates Passed & Four Failed
	ML20151Y475
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Site:	Sequoyah
Issue date:	01/16/1986
From:	Bill Dean, Wilson B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
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ML20151Y445	List: ML20151Y440; ML20151Y475;
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	50-327-OL-85-02, 50-327-OL-85-2, NUDOCS 8602120715
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-o -o ENCLOSURE 1 EXAMINATION REPORT 327/0L-85-02 Facility Licensee: Tennessee Valley Authority 6N11 B Missionary Ridge Place 1101 Market Street

' Chattanooga, TN 37402-2801 Facility Name: Sequoyah Nuclear Plant Facility Docket No. 50-327 Written simulator and oral examinations were administered at Sequoyah Nuclear Plant near Soddy-Dajsy, Te see.

Chief Examiner: [ ////

/l / /6 [

' Date Signed WiTliam A. Dean

( ' ' ~ ~

. Approved by: Ah C,t . I ce I!1b !fb Date Signed Brige A. Wilson, Section Chief Summary:

Examinations on November 12-15, 1985 A written examination was administered to one reactor operator candidate who did not pass. - Complete examinations were administered to four reactor operator candidates and three senior reactor . operator candidates. Two reactor operator candidates and two senior reactor operator candidates passed all portions of the exam. One reactor operator candidate did not pass the oral and written examinations 'and the remaining two candidates did not pass the written examina-tion.

8602120715 860128 7 DR ADOCK 0500

5 9' REPORT DETAILS

1. Facility Employees Contacted:

R. J. Johnson, Nuclear Training oranch

C. M. Noble, Superintendent (Operations and Engineering)

C. T. Benton, Unit Supervisor

L. C. Bush, Assistant Operations Supervisor

J. M. Anthony, Operations Supervisor

C. H. Noe, Nuclear Training Branch

B. C. Lake, Training _

C. O. Brewer, Simulator Section Supervisor

E. Keyser, TVA Senior Engineer

Attended Exit Meeting

2. Examiners:

William M. Dean (did not attend exit meeting)

Lawrence L.. Lawyer (Acting Chief Examiner Onsite)

William A. Douglas

Chief Examiner

3. Examination Review Meeting At the end of the examination week, the facility provided comments regarding the written examinations and answer keys. These are included as an attach-ment to this report. The NRC resolutions below refer to each question commented on by the facility.

NRC Written Examination, Comment Resolutions

a. R0 Exam (1)- Question 1.09: Accept ' radiation' or ' convection' for part (b)

(2) Question 2.03: Misprint resulted in incorrect answer on the key.

(b) is the correct answer.

(3) Question 2.12: Accept " Train A" and " Train-B" as alternate answers l

for the first two responses.

(4) Question 3.16: Delta T will be deleted as a required answer.

(5) Question 4.02: Material provided to the examiners did not list inventory as a monitored CSF. Question will be deleted.

l e

2 (6) Question'4.15: Knowledge of evacuation sites and operations personnel assembly points is considered to be basic elements of emergency plans of which reactor operators should be cognizant. Question stands.

b. SR0 Exam (Applicable R0 Exam Questions are in Parenthesis)

(7) Question.5.09(1.12): Question ' does not refer to Pressurized Thermal Shock, but conditions required to cause brittle fracture in a metal.

Flexibility in grading the answers will be utilized, as long as the three criteria in the key are present in acceptable form.

(8) Question 5.10(1.13): The additional training material provided the NRC af ter the examination does not change the ordering of isotopes in terms of relative importance. A wider range of

% of contribution (47-57% -0235, 36-46%

-Pu239) will be accepted.

(9) Question 5.15: The term " precursors" was not intended to be part of the question. This makes the question ambiguous with no easily defined response. It will be deleted.

(10) Question 5.16(1.18): The referenced information in the facility training material does not coincide with information on actual plant performance. Answer key will be modified to identi fy the decrease in boron concentration due to fuel burnout as the overriding factor.

(11) Question 5.21: Facility made no recommendation regarding the disposition of this question or references supporting their comment.

Question stands.

(12) Question 5.22(1.21): For the conditions given in the question, it would take an extraordinary situation to achieve a situation where Tc, Th and Tavg are equal. This question was also examining candidates' knowledge- of programed temperature. Answer key stands.

(13). Question 6.02(3.03): Due to erroneous material provided by the facility to the NRC, both (a) and (b) will be accepted as correct answers.

i .

3 (14) Question 6.'J6(3.09): As the question asked for " engine shutdown troubles" and the overcurrent relay only trips the feeder breaker, it will not be required as part of the answer. Note that material provided by the facility to the NRC listed "overcurrent relay" as an engine shutdown trouble bypassed on an emergency start..

Material provided subsequent to the exam contradicted this.

(15) Question 6.07: The diffuser pond is in the facility controlled area, and does not adequately fit within a reasonable description of the " environment". Answer key will remain'as is.

(16) Question 6.08(2.09): The answer for (a) will be changed to reflect recent Tech Spec change and the answer for (b) will be expanded to allow steam leakage causing valve damage as an alternate answer.

(17) Question 6.09: The body of the question clearly states

" crane" giving the candidate a significant clue as to which interlocked device is in question. The' answer key will stand as is.

(18) Question 6.12(2.13): In'the situation described in the body of the question, the containment . spray system operates in a recirculation path through the containment. Answer key stands as is.

(19) Question 6.13: SIS is not an appropriate answer.

Partial credit will be given to Aux.

Bldg. Isol. signals. Will include the high temperature in the ventilation

. supply as an additional required answer, using the same +atal point value.

(20) Question 6.14(2.15): Reference material supplied by the facility listed condensate recirc as an automatic action. Based on post-exam material brought to the NRC's attention, this answer will not be required, and the question point value will be decreased by

.25.

4 (21) Question 6.17: The answer key will be modified to reflect " prevention" of automatic transfer.

(22) Question 6.22(3.20): Only a Failure High Channel I will cause all the events listed and in the sequence given. Answer key stands as is.

(23) Question 7.06(4.07): Based on. minimal . interaction of facility operators with this aspect of health physics; question will be deleted.

(24) Question 7.09(4.11)(c): Answer key will be changed to reflect change that was not included in material sent to the NRC.

(25) Question 7.14(a): The answer key covers all components

" sequentially loaded" and will remain unchanged.

(26) Question 7.15: Answer key will be modified to not require memorization of surveillance required. Answers will be evaluated for adequate coverage of required personnel and other facility notifications.

(27) Question 7.20(4.23): The question asks for those parameters monitored for "cooldown" not natural circulation. The parameters listed in the answer key are required for full credit per SQN-ES.0.3. Additional natural . circulation parameters will not result in any peralties to the candidate.

(28) Question 7.23(4.25): SQNP-A01-2 is very specific about steam dumps being put in Tavg Mode after rods are in Auto. There is some flexibility in the time of occurrence of the subsequent steps regarding 6.9 Ky Unit Board. Transfer and putting feed reg valve in Auto so sequence 4, 3, 2, I will also be accepted.

(29) Question 8.03: Misprint in the answer key. (b) is the correct answer.

(30) Question 8.07(a): Agree, "Yes" is the correct answer.

5 (31) Question 8.08(a)&(b): Question may not be clear in its intent to elicit only those trips which provide protection according to accident analysis. Will also accept answer "5" for (a) and "1" for.(b).

(32) Question 8.18: A ' broader answer will be accepted as long as " personal hazards" and " incapacitating equipment electrically" are discussed.

(33) Question 8.19: The facility supplied PLS manual should either be updated to match other facility instructions and precautions, or eliminated as a source of information due to the multitude of contradictions contained -within the PLS. Answer key will be modified to change (a) to 15 psig and (c) to 3 F.

(34) Question 8.23: Both NUREG-1021 and 10 CFR.55.22 require senior reactor operators to be examined on their knowledge of design limitations in technical specifications, operating characteristics, and reactor thermal limits. Question stands.

5. 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 individ-uals who had clearly passed the simulator and oral examinations were identi-fied.

There were no generic weaknesses noted during the oral and simulator exams.

The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was noted and appreciated.

ATTACHMENT (1.5) 1.09 Indicate the most significant type of heat transfer that is taking place in each of the following conditions. (i.e.

Condletion, Convection or Radiation)

a. Nucleate boiling on the cladding surface of the fuel assembly.

b. Accident condition in which steem is passing through the coolant channels.

c. Heat from fission accross a fuel pellet.

ANSWER a.) Convection (+.5 ea) b.) Radiation 1

c.) Conduction REFERENCE Nuclear Power Plant Oper. Teng. Program, HTFF & Thermo, pp 193-206 002/000; KS.01 (3.1/3.4)

TVA COMMENT Statement places no restriction on what the accident condition is (Small-break LOCA, Large-break LOCA) and on the state of the steam passing through the core. A low-quality.steen mixture is j highly likely in some small-break LOCA's which have relatively high convective heat-transfer coefficients and small radiation i

heat transfer coefficients. Convection is still the most significant type of heat transfer in these cases.

Radiation heat transfer would be more significant for only high-quality steam or superheated steam conditions. However, the question only states " steam" states.

The non-specification of " accident condition" and " steam" ma?

this part of the question (b) ambiguous and not acceptable as a test question.

A 4

4 - ,

I 4

s

, , ,_,,4_,.-----,---, - - - _ - - - - - - - - - - + - - - - = - - - - - - * - * - ' - - - - - - ' ' - - ' ' ' - ~ " " ' * - ' ' - " - - - - ~ - ' ' " ' ' '

(1.0) 2.03 Which of the following is the preferred order of valve operation for initiation of Emergency Boration as stated in AOI-34?

a.62-135 & 136 (RWST Suction Valves), BIT Injection Valves, HCV-62-929 (Emergency Borate Manual Valve), FCV-62-138 (Emergency Borate MOV)

b. FCV-62-138 HCV-62-929,62-135 & 136 BIT Injection Valves

c. FCV-62-929, FCV-62-138,61-135 & 136 BIT Injection Valves

d. FCV-62-138,62-135 & 136, BIT Injection Valves, FCV-62 929

e. HCV-62-929, BIT Injection Valves,62-135 & 136, FCV-62-138 ANSWER c

REFERENCE SQNP Lesson Plan "CVCS" pp 14 & AOI--34A EPE-024; PWG-11 (4.0/4.0) & EA2.02 (3.9/4.4)

TVA COMMENTS AOI-34 does not list flow paths in preferencial order as indicated in c. Refer to your copy of AOI-34 and re-read instruction you will find that the answer is b.

(1.0) 2.12 Fill in the blanks below to complete the statement concerning Auxiliary Control Air:

The Containment Building is supplied with redundant headers, each supplying and valves. These headers are isolated on . The Auxiliary Control Air compressors are cooled by the system.

ANSWER

PZR spray; PORV; Hi-Hi containment pressure; ERCW (+.25 ea)

REFERENCE l Westinghouse PVR Systems Manual " Air Systems", pp 12.3-2 078/000; K1.04 (2.6/2.9) & Kl.03 (3.3/3.4) & PWG-10 (3.4/J.7)

TVA CONMENTS The answers given are correct; however, train A and Train B are also correct for the first two blanks.

Q Q

(1.50) 3.16 List ALL of the signal inputs to the OT Delta T trip point calculator.

ANSWER Delta T; Tavg; PZR Pressure; Delta Flux; Delta I at rated power; Tavs at rated power (+.25 ea)

REFERENCE Westinghouse PWR systems Manual "RPS", pp 9-10 SQNP TS Table 2.2-1

~012/000; K6.11 (2.9/2.9) & A2.05 (3.1/3.2)

TVA COMMENT OTAT trip point calculator does use the loop AT parameter, The AT parameter enters tie comparator. SEE ATTACHED BLOCK DIAGRAM.'

t i

E

(1.0) 4.02 Which of the following is NOT a Critical Safety Function?

a. Core Cooling

b. Heat Sink

c. Suberiticality

d. Containment

e. Inventory ANSWER-e REFERENCE NcG, EP/2/A/5000/10 Status Trees SQN FR-0, Status Trees PWG-10: Recognizing E0P Entry-level conditions (4.1/4.5)

TVA CONMENT All of the above are Critical Safety Function. SEE ATTACHED PAGES.

(1.0) 4.15 a. What is the primary evacuation shalter for contaminated personnel if a total plant evacuation is required?

b. Where is the assembly point for Operations personnel on a Site Emergency?

ANSWER a.) Watts Bar Nuclear Plant.(+.5ea) b.) Control Building Lunch Room (Evelation 732)

, REFERENCE .

l SQNP IP-7, pp 1 & IP-B, pp5 i PWG-36: Actions in Facility E-Plan (2.9/4.7) l 1

TVA COMMENT Delete this question. This is SRO level knowledge of the REP, RO i

-candidates are taught the REP on a basic level as part of certification training but do not receive detailed REP training in prelicense.

l l

QUESTION 5.09/1.12 (1.50)

List the 3 conditions necessary for brittle fracture to occur in metal.

ANSWER 5.09 (1.50)

Nominal tensile stress (+.5)

Temperature below RTndt (+.5)

Sufficient sized surface defect (+.5)

REFERENCE SQN TS, B3/4.4.9 002/000; K5.18 (3.3/3.6)

TVA CONNENT Expand acceptable answer to include PRESSURIZED THERMAL SHOCK (PTS) conditions. Emphasis in training is placed on PTS events which require slightly different conditions for initiation conditions are:

1. Reactor vessel beltline region must have a very large degree of neutron radiation embrittlement.

2. A flaw or crack of critical size.

3. High thermal stress must be induced by cold water cascading by the beltline region of the vessel.

4. The RCS must be pressurized following the thermal shock.

REFERENCE:

SQN WK 3&4 REQUAL LESSON PLAN, Day 10 Page 5 of 15 QUESTION 5.10/1.13 (1.50) l List the three main power producing isotopes in the core at end of life and l

Indicate their approximate contribution (in %) to power.

ANSWER 5.10 (1.50)

U-235 Approx 491 (+.25 for isotope, +.25 for contribution to power +/-2%)

l Pu-239 Approx 441 U-238 Approx 7%

l REFERENCE SQN/WBN License Cert Trng, " Reactor Kinetics" pp 6 l 001/000; K5.47 (2.9/3.4)

TVA COMMENT The numbers used on the key and the allowable tolerance implied for an acceptable answer are not necessarily true and may differ from reference to reference. These numbers are discussed in " ball park" terms, usually with the l addition of Pu241 as the fourth isotope of concern, i

i Attached are excerpts from three other documents used for training. Any

~

Qne,al Thys$cs S SIT *** M S'W EI J ,

ir

6.2cker Scog b 'c.W w

U-235: 0, = 0.0064 s #33 ,

U-238: s, = 0.0157 m 0,3, Pu-239: p, = 0.0021 s #,3, Pu 240: p, = 0.0053 e s,,,

2. Fission Sharing Percentage, 7, 7, a the percentage of the total core power produced by an individual type of fuel.

The . fission sharing percentages of the individual. fuels are a function of core age, due to the production of Plutonium and the depletion of U-235. At BOL, about 7% of the total core power results from fast fissioning of U-238; the . remaining 93% is. produced by fast and thermal fissioning of U-235.

As the core ages, Pu-239, Pu-240 and Pu 241 are produced as follows:

23s #~ 888 sU+o n- s2ss U 23 min .ss 28' Np 2.3 da 84 Pu fission (73%)

23sPu + 2n sjo Pu (27%)

240 Pu + 2 n 8j8 Pu At EOL, the individual fission sharing percentages are: '

_-cc- w 7:ss = 50%

72 ss

7%

72 ss = 38%

, _ 7 241 = 5% -

3. Core velayed Neutron Fraction, #

i p s the fraction of all fission neutrons which are born as l delayed neutrons.

~

l number of delayed neutrons produced l 0 " number of fission neutrons produced I

t _

l 15.1 13 l-

{ DELAYED NEUTRON FRACTION FOR REACTOR CORE SAam puheAR. D >JT- DCTOC ME0f f hr '

U ** U **'Pu Delayed Neutron Fraction, 0.0064 0.0156 0.0021 Power (Fission) l;. Fraction, [

'( BOL 93 % 7% 07.

EOL 55 7. 77. 38 7.

l

f

T

/ ) T (235j'+' 238 */

(239j

. I 235 d d238j'+( 239 d L

(

DELAYED NEUTRON FRACTION l FOR REACTOR CORE 238* '/238 +

/ .

239 '/239 235 .d 235 +

At B O L:

(BOL) = (0.0064)(0.93) + (0.0156)(0.07)

= 0.0059 + 0.0011

~

(BOL) = 0.0070 (

At EOL:

(EOL) = (0.0064)(0.55) + (0.0156)(0.07)

+ (0.0021)(0.38)

= 0.0035 + 0.0011 + 0.0008 i -

l h gOL) = 0.0054

[i-W c 1

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

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..,:. 6.2 (C:nt.) f OSLT5 5/19/80 r- Tha Delaved Neutron Fraction (S). is a fraction of the total neutrons that are delayed.

0 " neutrons that are delaved h total neutrons from fission .

Each fuel has a different fraction of neutrons that are delayed:

'f-U-235 8 = .0065 U-238 8 = .0157 -

, PU-239 8 = .0021

.E PU-241 8 = .0049 q .

_J 6.3 .

To determine what the average neutron lifetime .(1) is, you need to multiply prompt neutron lifeti=e (I p) by the oronot neutron fraction and c:ultiply the delayed neutron lifetime (l d) by the delayed neutron fraction, and then add these two together.

'I = 1 p (1-8) + Id 8 iI = (2 x 10-5 sec). (1

- ' .007) + (12.5 sec) (.007)

~L. ~ .

t

, = 1.986.x 10 -5 sec + .0875 sec.

p.

= .087519 sec.

= .09 seconds ..- .

generation .

" 11 8'""#*EI ""

.09 Mp -

second .

k. '

_ NOTE: This longer lifetime results in 11 generations per second' rather than 50,000 generations per second. (If only proept neutrons were

[_ present.) This gives much better centrol of the reactor.

6.4 To determine what the Weichted Averace Delaved Neutron Fraction (5) you -

't need to know what percentage of the total fissions each fuel is providing-j f. ,~ , and the Delaved Neutron Fraction (S) for each fuel.

u

' ~ .

6.4.1 At BOL 93% of fissions come from U-235

.Il 7% of fissions come from U-238 -

l U-235 U-238 .

,.. 8 = ( 93)(.0065) + (.07)(.0157) = .007144 -

6.4.2' At EOL 49% of fissions come from U-235 7% of fissions core from U-238

," 38% of fissions _come_from_PU-239

!)

l

%1 f fissions come from PU-241 m U-235 U-238 5 = (.49)(.0065)+(.07)(.0157)+(.33)(.0021)+(.06)(.0049)

PU-239 PU-241

~x y

=

.003135 + .001099 + .000798 +.000294 = .005376

,E

QUESTION 15.15 (1.50)

What are the two factors associated with delayed neutron procursors that influence the value of Beta Bar Effective and what effect do they have?

ANSWER 5.15 (1.50)

1. Delayed neutrons born at lower energies, so less likely to leak out providing a positive effect (+.75)

2. Delayed neutrons are born at an average energy too low to cause fast fission which provides a negative effect (+.75)

REFERENCE SQN/WBN License Cert Teng, " Neutron Kinetics" 001/000; K5.47 (2.9/3.4)

TVA COMMENT Question is poorly written, in that the answer key implies the question is addressing knowledge of IMPORTANCE FACTORS. Quite frankly, there is no answer to the question as written and therefore the question should be removed from the examination.

Note: Remove question as written from exam bank. Replace with question directly related to IMPORTANCE FACTOR.

QUESTION 5.16/1.18 (1.25)

Over core life there are two effects that cause differential boron worth to change. List these two effects, their relative impact on differential boron worth and indicate which effect is the overriding factor.

ANSVER 5.15 (1.25)

1. As the fuel burns out, less boron is required, which increases the boron worth (+.5)

2. Fission products build up, decreasing the boron worth (+.5)-this is the overriding effect (+.25)

REFERENCE SQN/WBN License Cert Teng, " Core Poisons", pp 4 004/000; K5.06 (3.0/3.3)

TVA COMMENT Reference lesson plan is in error. The differential boron worth increases (becomes more negative) over core life, as shown in SQN Curve Book TI-28, Figure B.9.1 for Unit 1, Cycle 3. Answer is based purely on a theoretical vs real-life answer. Boron worth is less at ECL.

TI-28 Figura B.9.1 -

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QUESTION 5.21 (1.50)

The following data was obtained during a core refueling.

Number of Assemblies Loaded Neutron Count Rate 0 40 cps 5 70 cps 10 90 cps 15 115 cps Determine the number of assemblies it will take to reach criticality. Use the attached graph paper if desired. (Assume equal assembly worth)

ANSWER 5.21 (1.50) for 0-5 assemblies, 1/M=.571 (+.25) for 0-10 assemblies, 1/M=.444 (+.25) for 0-15 assemblies, 1/M=.348 (+.25) for 10-15 assemblies, 1/M=.782 See attached graph for curves (+.75)

REFERENCE NUS, Vol 3. Units 12.2, 12.3 SQN/WBN License Certification Trng, " Neutron Sources and Suberitical Mult" 001/010; KS.16 (2.9/3.5)

TVA COMMENT EDITORIAL ONLY please refrain from such questions in the future, because of the obviously erroneous use of 1/M during fuel loading.

CRITICALITY is not the ultimate goal. This question is applicable to research type facilities only.

'1

) ', $

QUESTION 5.22/1.21 (1.00)

Using the attached steam tables, what is the amount of primary subcooling if the pressurizer is at 2235 psig and Tavs is 575 degrees F?

ANSWER 5.22 (1.00) for 2250 psia, sat temp = 652 (+.5) with Tavs = 575 TH =

_ 607 (+.5) -give +/- 2 degrees in determining TH 45 degrees F REFERENCE Steam Tables and SQN PLS 002/000; Al'.04 (3.9/4.1)

TVA COMMENT An alternate answer is acceptable in this case, where power conditions were

-not specified. If in an accident T , T . hT ,g may all be the same and in that case subcooling would be 653 Fg - 575 F g= ~78oF.

i

QUESTION 6.02/3.03 (1.00)

Which statement below regarding Diesel Generator load sequencing is correct if a LOCA occurs AFTER a LOSS OF POWER?

a. - Loads already sequentially connected will remain connected.

b. Loads awaiting sequential loading that are required for an accident will have their sequential timers reset to time zero.

c. The non-accident loads not yet connected will be sequenced on once all

-accident related loads are connected,

d. All loads will be stripped, then ONLY the accident related loads will be sequentially connected.

ANSWER 6.02 (1.00) b REFERENCE SQNP System Descrip, " Electrical Distribution" pp 19/20 064/000; K4.10 & K4.11 (3.5/4.0)

TVA CONMENT Both answer a. and b. are correct for SQN and therefore full credit should be awarded for either answer. Page 19 of the quoted REFERENCE makes the statement that implies that an SIS will strip loads or block loads--that is in error.~ The only difference between the listed Nonaccident and Accident Condition Columns in Table 5-2 is the PZR heaters, and the heaters are unaffected by SIS.

I w- *-g - -wew -e nyam --,*w -r-r- -e-gw-- --y ,g -p- ,y--p- ---c** - - --- ,---m---,- -w-- * -- - i + M g -w'e' -' --'

j %, *, 1 -

'g 4

TABLE S-2 DIESEL CENERATOR LOAD SEf}UENTIALLY APPLIED FOLloutilc A LOSS OF llDCLEAR UNIT AND PREFERRED (OFFSITE) POWER Time Total in Load App 1ted

_Equipnient Name lir Starting

_ Seconds

Load Nonaccident Accident

__kVA _ Condition Hiscellaneous Loads Condition 0 760 4KG Yes Yes Centrifugal Charging Pump & AllU 5 603 3630 Yes Safety Injectfun Fump & A11U Yes i 10 403 2460 j lio Yes vi Residual liest Removal Fump & Al4U 15 403 2395 j b Essential Raw Cooling Water Fump No Yes 1 20 600 i 3470 tes Yes Component Cooling System Finop 25 350 1905 Yes Yes Aux 111ary Feedwater rump 30 500 2569 Yes

Yes Containment Spray rump & AalU 35 705 4060 No Yes Pressuriser Heaters 90 485 kw 485 kw Yes Fire Fump llo 120 200 5 = 878 Yes Yes i Spare Component Cooling System Pumpen 125 350 1905 i Yes Yes

{ Diesel Ceneral Rating: 4000kw continuous or 4400kw for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

- Applies only to diesel generator IA-A or 23-8* Time is measured generatorfromtothethe time powerof tratn.closing of the AllU - Air Handling Unit ,

l 4

. o QUESTION 6.06/3.09 (1.75)

List,the 7 Diesel engine shutdown troubles which are bypassed when there has been an emergency start.

ANSWER 6.06 (1.75)

1. Low Lube Oil Pressure (+.25 ea)

2. High Crankcase Pressure

3. Phase Balance Relay

4. Reverse Power Relay

5. Loss of Fleid Relay

6. Overcurrent Relay

7. High Jacket Water Temperature REFERENCE NA NCRODP 90.4 "EDG" SQNP Diesel Generator Handout pp 8 064/000; K4.02 (3.9/4.2)

TVA CONNENT Only 6 of the 7 listed are true. The overcurrent relay is not bypassed.

6 Overcurrent Relay is not an engine shutdown it only trips the feeder bkr to the shutdown bd and is only placed in service when the 6.9L.v. unit bd and.

6.9k.v. shutdown bd are paralleled.

Reference 45N765-2

QUESTION 6.07 (1.50)

a. Fill in the blanks in the following statement regarding liquid waste processing:

< Liquid, whose tritium concentration is % or more of

[

the tritium concen? ration, is designed to be processed as tritiated liquid.

(0.5)

I b. List the flowpath of Radioactive Liquid from the Liquid Waste Processing System starting with the Waste Condensate Tanks and Ending with the Environment. Include the piping through which it passes. (1.0) l ANSWER 6.07 (1.50) i 4

a. 10%; primary coolant (+.25 ea response)

b. Blowdown line from cooling twoers; diffuser pond; diffuser pipes; j river (+.25 ea)

REFERENCE SQNP Sys Descrip, 8.2, " System Design and Operation (Liquid Waste)" pp 4,16 068/000; PWG-4 (3.1/3.3) & K4.01 (3.4/4.1) l TVA CONMENT i

The normal interportation of "the environment" ends with the diffuser pond.

QUESTION 6.08/2.09 (1.25)

a. What is the maximum differential temperature allowed by Tech Specs betweer. the pressurizer spray and the pressurizer?

b. What is the purpose of the loop seal located below each pressurizer safety valve?

(0.5)

c. What is the driving force for normal spray flow?

(0,5)

ANSW8R 6.08 (1.25)

a. 320 deg F (+.25)

b. Inhibit H2 leakage which may wire guide the valve seat (+.5)

c. Delta P between the RCP discharge and the PZR (+.5)

REFERENCE SQNP PLS pp 42; SQNP Lesson Plan "RCS", pp 27 & 29 010/000; K6.03 (3.2/3.6) & K6.02 (3.2/3.5)

TVA CONMENT A. T.S. 3/4.4.9.2 lists maximum differential temperature between spray and PZR as 5600F. Surveillance requirement still requires logging of conditions when spray AT exceeds 320 0 F for tracking of cycles in section 5.0 " Design Features."

b. Loop seal is used to prevent steam leakage through safety valves. Loop seal is heat traced to ensure that upon opening of a safety valve the water in the loop seal will flash to steam thus reducing watet hammer dacage. This information should be accepted as an alternate answer.

4 s

1

... s QUESTION 6.09 (1.25)

Fill in the blanks to complete the following statements concerning fuel hand 11ag interlocks:

a. The refueling canal lifting arm is interlocked with the . The lifting are cannot'be lifted unless the is in the poisition or the crane is

. (1,0)

b. Bridge and trolley drive operation is prevented except when are actuated.

(0.25)

ANSWER 6.09~ (1.25) i a. manipulator crane; manipulator crane gripper tube; fully retracted; over the core (+.25 ea)

b. both gripper tube up position switches (+.25) e

! REFERENCE t

SQNP Sys Descrip. 9.0, " Fuel Handling System" pp 5 & 7 034/000; E4.02 (2.5/3.3)

TVA CONNENT I a. Transfer cart (Trolly); transfer cart; fully down position.

- The refueling canal lifting arm is also interlocked with the above as well as the manipulator crane.

4 Reference. FHI-7 QUESTION 6.12/2.13 (1.00)

! Describe the flow path of the Containment Spray System when the RWST is too i low to support spray operation, assuming there is still ice in the Ice Condenser. (Identify a11' components, excepting valves in the path)

ANSWER 6.12 (1.00)

Emergency sump +++Contain: tent Spray Pumps *-++ Containment Spray. Ht Exchges+++ Containment Spray Nozzles +++ Upper Containment Compartment +++2 Drains in the bottom of the Refueling Canal &++ Lower Compartment +++ Emergency Sump (+.15 ea)

REFERENCE SQNP Sys Descrip. 4.5, " Cont Spray Sys" pp 17/18 026/000; K4.01 (4.2/4.3)

TVA CONMENT Adequate response to this question would include all components to the containment spray nozzles. Remaining information, however true, is not required to describe flow path.

QUESTION 6.13 (1.50)

What signals will automatically initiate the operation of the Auxiliary Building Gas Treatment System?

ANSWER 6.13 (1.50)

-Phase A Containment Isolation signal from either Unit (+.5 ea)

-High Radiation signal from fuel handling b1dg area rad monitors

-High Radiation signal from Aux Bldg exhaust vent rad monitors.

REFERENCE SQNP Sys Descr. 4.4, " Cont Air Purif and Cleanup Sys" pp 15 EPE-060; PWG-10 (4.1/4.4)

TVA CONNENT

-SIS and Auxiliary Building Isolation Signals should also be acceptable, even though they are general.

Another acceptable answer is high temperature in auxiliary building general supply fan suction, either unit, +1150F; 1-TS-30-103/103A, 2-TS-30-104/104A - Ref. SQN SOI 30.6A page 6 of 22, Rev. 13.

QUESTION 6.14/2.15 (1.75)

a. List the signals which will cause an automatic isolation of the Feedwater System.

(0.75)

b. List the automatic actions that occur due to the feedwater isolation signal.

(1.0)

ANSWER 6.14 (1.75)

a. Hi-Hi level in any S/G ( 75%) (+.25 ea)

SI signal Reactor trip with lo Tavg ( 554 deg F)

b. Both MFP trip (+.25 ea)

MFWRV and Bypasses shut Condensate system recircs to condenser Feedwater isolation valves close REFERENCE SQNP Lesson Plan " Con (snaate and Feedwater Review". pp 10 059/000; K4.19 (3.2/3.4)

TVA COMMENT General agreement with key, except for " condensate recices to condenser".

This action occurs indirectiv upon feedwater isolation signal. Ref. SQN Logic Print 47W611-3-2.

~

Q ESTION 6.15 (1.25)

Where are 1sleeesa\socihtedwithRCSpenetrationslocated?

1 ANSWER 6.15 ,

(1.23)\

-Return lines from RHR 100 (SI lines)/(+.25 ea)

-PZR Surge line, both ends

-PZR spray into PZR '/

-Chg line connection /

-Aux chg line connection /

REFERENCE /

SQNP Lesson Plan,"RCS", pp 34/35

/

002/000; K1.06 (3.7/4.0) & Kl.08 (4.5/4.6) & Kl.09 (4.1/4.1)

/

TVA COMMENT

/

Editorial Only This section does question the candidates knowl ge of system design, however, this particular point is Esquest.ing informationthatis(intheopinionofthetrainingDy'f) at-best-e-pese-measure Of design-knowledge.

QUESTION 6.17 (.75)

List three interlocks that would prevent the AUTOMATIC transfer of a 6.9 KV Shutdown Board from its normal supply to its alternate supply.

ANSWER 6.17 (.75)

-alternate feeder has normal voltage (+.25 ea)

-transfer switch is in AUTO

-trip was not due to overcurrent REFERENCE SQNP " Review of Electrical Distribution" pp 4 062/000; K4.03 (2.8/3.1)

TVA COMMENT Answer key lists conditions that would ALLOW transfer, NOT PREVENT transfer.

. r (1.0) 6.22/3.20 With the pressurizer level control selector switch in position I/II, a failure causes the following plant events. (Assume no operator actions taken.)

1. Charging flow reduced to minimum

2. Pressurizer level decreases

3. Letdown secured and heaters off

4. Level increases until high level trip Which instrument failed (I or II) and in what direction did it fall?

ANSWER Level I Channel (+.5) failed high (+.5) i REFERENCE Westinghouse PWR Systems Manual " Primary System Control", pp 12-14 011/000; K3.01 (3.2/3.4) & K3.03 (3.2/3.7)

TVA CONMENTS A failure low of the channel II (backup channel) will cause some of the same plant events, effects are close enough to be debatable.

1. Letdown will isolate / heaters will turn off upon low failure.

2. After letdown isolates, as actual pressurizer level increases control circuit will reduce charging flow to minimum.

3. Level will increase until high level trip.

4. Failed channel will indicate pze level decrease. Either answer should be acceptable.

(1.0) 7.6/4.7 Which of the following describes what is meant by "Nothing Detectable" as it is utilized in determining the existence of Beta-Gamma contamination ca skin or clothing surfeces?

a. Less than 100 dpm above background as measured with a pancake probe.

b. Less than 100 dpa above background as measured with a smear.

c. Less than 5 times background counts as measured with a smear as counted for one minute.

d. Less than 3 times the square root of a one minute background count as measured by a smear counted for 1 minute.

ANSWER d

Reference SQNP RCI-1, pp12 PWG-15: Knowledge of facility Radeon (3.4/3.9)

TVA CONMENT Question is inappropriate. If taken in context, "Nothing Detectable" limit is associated with smears and skin smears are not to be used unless totally unavoidable due to possibility of worsening condition. This question is not appropelate based on the duties / responsibilities of local H.P. section utilized at SQN. 10CFRSS does state that operator examinations test knowledge of radiological procedures and controls, however emphasis should be placed on areas of concern to operations personnel. This is DIFINITELY NOT NEED TO KNOW INFORMATION FOR FACILITY SRO PERSONNEL.

l

(1.0) 7.09/4.11 Fill in the blanks with the appropriate limits listed in the precautions section of the GOIs:

a. A load change of +/- 1/ min or a step change of %

should not be exceeded.

b. The boron concentration difference between the pressurizer and the RCS must not exceed opm.

c. The arming temperature setpoint for UNIT l's Pre PORVs is des F.

ANSWER

a. 5; 10 (+.25 es response)

b. 50

c. 380 REFERENCE SQN GOI-3B and GOI-5 PWG-7; Limits and Precautions (3.5/4.0)

TVA CONMENT Answer key for part c.) is in error. Arming setpoint for COPS Function on Unit 1 is 350*F (Refer to attached pg 54 of GOI-1) i

w-w

.2 2 s a a , n

~

2CO[D n

7 se-r DVERPRESSURE PROTECTION CURVE - UNIT'1 DNLY : -- - A.a l

@ PORV i 1 c

I E RCS Temp. (OF) Setpoint (psig) 70 h $

a l

130 450 g 450

- 190 440 -

h, . o

230 485 e

250 550 ~

ps 8

~~

270 285 630 710 4 e 350 710 oO -

1*. -

h L

S !

I w

J. o --

e

-j

, PORV # 2 8

(d ir

)

s

-}

RCS Temp. (OF) 70 SetPoint (psig)

~ 470 g -

p 190 470 210 490 so m, _ -

__ T 230 520 250 -

590 Cd i l j i 270 c- , 670 4

Q- -

i ~~y i 4 285 755 J j 350 755

$, _4_L.

co, . -

y i

dl I' I s *

^ #1 pats m.

" l._ J ' ..

' C0!!S Arming Temperature 350 F 6%&R -4 f} _ .

l f ~

g g _

~[

'l ,1

-_h

- ' ~

/s Eontti.-r ??N@8E f

. % g ; 7 ig 8

g rl e i 6 l 'I p i 6 l'_ _"Tii c

<n. .-

-C'

-' C&T 62240A_

.t u,n["*~

e, -

30.00 95.00 010.30 1t15.00 230.00 275.00 320.00

~gg RCS TEMPERRTURE - DEG F ,

9 O

(2.0) 7.14 a. On a station blackout, whgat are the 8 loads that are sequentially loaded automatically onto the diesels,

b. There is a precaution in the Loss of Offsite Power procedure (AOI-35) to ensure that the diesels are loaded to

>1600 EW within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (assuming the diesels are required that long). What is the purpose of this precaution?

ANSWER

a. 1.) Centrifugal Charging Pump 2.) ANU 3.) ERCW Pump 4.) CCS and Booster Pump. S.) Space Component Cooling Pump 6.) AFW Pump 7.)

Pressurizer Heaters 8.) Fire pump (+.15 ea)

b. To clear the diesel exhausts and superchargers of accumulated combustibles (+.8)

REFERENCE SQNP AOI-35, pp 3/4 a.)064/000; E4.10 (3.5/4.0) b.)064/000; A2.06 (2.9/3.3)

TVA CONNENTS Part a.) answer is not correctly stated on key - see attached page 4 of AOI-35.

(1.50) 7.15 List the immediate actions in AOI-7, " Probable Nazimun Flood",

assuming the plant has been notified by the Division of Water Management that flood producing conditions may develop.

ANSWER

-Notify Management personnel listed for call duty (+.25 ea)

-Refer to IP-1 and implement REP for FLOOD

-Notify load coordinator if unit loaded or scheduled to be loaded

-Nake radio contact with Fontana Das if they are involved in flood warning

-Perform SI-216 (Flood Protection Surselliance)

-Initiate SI-215 (Flood Protection Communication)

REFERENCE 1 SQNP AOI-7.pp 1/2 PWG-2 (2.7/3.8) & PWG-11 (4.3/4.4)

TVA CONNENT l If this particular instruction is put in proper perspective, immediate operator actions are then some twenty seven hours in advance of any actual flood condition and then actions are not i required in a compressed time frame. This question, as asked, is

, inappropriate and should be deleted from this esamination.

l I

l l -

SQNP AOI Units 1 cnd 2

, Page 4 of 17 Rev. O IV.. SUBSEQUENT OPERATOR ACTION (Cont.)

2. Confirm diesel generators loads are less than 4000 kW each for

. continuous operation and less than 4400 kW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

a. D/G 1A KV 1- b. D/G IB KW

, c. D/G 2A KW

d. D/G 2B KW

,y 3.. Send AUO to the diesel building to check the condition of the D/G's

4. In the event of loss of Unit 1 or Unit 2 station "B" train power supply (6.9-kV shutdown boards IB-B or 2B-B) verify that ERCW header crosstie valves open:

l

a. 1-FCV-67-223 open

b. 2-FCV-67-223 open

c. 1-FCV-67-424 closed i

1 5. Following equipment energized and/or operating.

CAUTION Equipment started by blackout will not stop until B.O.

is reset. If required to stop equipment " Pull To Lock" 1 control switch.

DIESEL GENERATOR LOAD SEQUENTIALLY APPLIED TOLLOWING A LOSS OF NUCLEAR UNIT AND PREFERRED (OFFSITE) P0hIR Time in Equipment Name Seconds (1)

Miscellaneous Loads 0 Centrifugal Charging Pump & AHU 2 Essential Raw Cooling Water Pump 15 CCS Pump & Booster Pump 20 Spare Component Cooling System Pump (2) 20 Auxiliary Feedwater Pump 25 Pressurizer Heaters 90 Fire Pump 120 Diesel Generator Rating: 4000 kw continuous or 4400 kw for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I

Time is measured from the time of closing of the breaker connecting the diesel generator to the power train.

2 Applies only to diesel generator IA-A or 28-B 4

a

.~ ..

(1.0) 7.20/4.23 What are the three parameters that are monitored to determine RCS cooldown in accordance with ES-0.3 " Natural Circulation Cooldown"?

ANSWER Core Exit T/C (+.33 ea)

T-Mot RCS Subcooling REFERENCE SQN ES-0.3, pp6 EPE-074; EA1.02 (3.9/4.2)

TVA COMMENT Actually there are five parameters listed in ES-0.3, any of which are acceptable answers. Se attached excerpt fcom ES-0.3.

(1.0) 7.23/4.25 Place the steps listed below, which are performed during a plant startup, in the proper sequential order.

1.) Transfer 6.9 kw unit board 1A from Start Bus la to unit station transformer IA.

2.) Transfer S/G feedwater regulating valve cor. trol to AUTO.

3.) Transfer steam dumps to Tavg mode.

4.) Transfer rod control to AUTO ANSWER 4 (+.25 es in correct order) 3 1

2 REFERENCE SQNP GOI-2, pp 22/23 PWG-12: Performance of Integrated Operations (3.5/3.4)

TVA CONMENT Question is not valid. Startup steps listed above are NOT sequence critical during plant operations. Actual sequence is dependent on plant conditions and will vary from startup to startup. Question should be removed from the examination.

4 l

SQNP ES-0.3 Unit 1 or 2 Page 2 of 9

. Rev. O NATURAL CIRCULATION COOLDOWN STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If SI actuation occurs, then E-0, Reactor Trip Or Safety injection, should be used. .

Note: If at any time an RCP can be restarted, then go to appropriate normal cooldown instruction 1 Trv To Restart An RCP g an RCP can NOT be started,

a. Loop 2 preferred THEN verify natural circulation

b. Refer to SOI-GS.2

~

RCS subcooling

c. Start an RCP and go to appropriate plant S/G press stable or instruction decreasing -

T-hot stable or decreasing Core exit T/C stable or decreasing T-cold at saturation temp for S/G press IF natural circulation NOT verified, THEN increase dumping steam e

4 2-

(1.0) 8.03 While in Mode 1, a Pressurizer Code Safety Valve is determined to be INOPERABLE. How long do you have to restore the Code Safety to operability before Tech Specs require you to initiate shutdown to Hot Standby?

a. You must immediately start your shutdown procedure

b. 15 minutes

c. 30 minutes

d. I hours ANSWER c

REFERENCE FNP/SQNP TS 3.4.3 010/000; PWG-5 (2.9/4.1)

TVA CONMENT Answer Key is in error. Correct answer is b. 15 minutes. See attached Tech. Spec. LCO 3/4.4.3.

(2.0) 8.07 Indicate WHETER or NOT the following conditions REQUIRE that the plant be in Hot Standby within one hour.

s. In Mode 1 with one cold leg injection valve failed in the closed position.

b. In Mode 1 with UNI accumulator at 1850 ppe boron.

c. In Mode 1 with RCS pressure having exceeded 280 psig,

d. In Mode 1 without primary containment integrity.

ANSWER

a. NO

b. NO

c. YES

d. NO REFERENCE CAT & SQNP TS, pps. 2-1, 3/4 5-1, 5-3, & 6-1 PWG-8: Recognition of TS entry level conditions (3.5/4.5)

TVA CONMENT

a. Is also a condition which requires plant shutdown so proper answer is YES. See attached sheet 3/4.5.1.

, {REACTORCOOLANTSYSTEM

3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING -

SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.1 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG 2 1L a APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable

.a!,e to OPERABLE status within 15 minutes or be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

, SURVEILLANCE REQUIREMENTS 4.4.3.1 No addit'ional Surveillance Requirements other than those required by Specification 4.0.5.

aihe lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

Y

) SEQUOYAH - UNIT 2 3/4 4-7

o ,i w 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS COLD LEG INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:

a. The isolation valve open,

b. A contained borated water volume of bet.een 7857 and 8071 gallons of borated water,

c. Between 1900 and 2100 ppm of boron, and

d. A nitrogen cover-pressure of between 385 and 447 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a. With one cold leg injection accumulator inoperaole, ev:ept as a result of a closed isolation valve, restore the inocerable

('#

accumulator to OPERABLE status within one hour or te in 'at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

~

b. With one cold leg injection accumulator incperable due to the isolation valve being closed, either immediately ocen the isolation valve or be in HOT STANCBY within one hour and ce in HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REOUIREMENTS 4.5.1.1.1 Each cold leg injection accumulator shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1. Verifying, by the absence of alarms or by measurement of levels and pressures, the contained borated water volume and nitrogen cover pressure in the tanks, and

2. Verifying that each cold leg injection accumulator isolation valve is open.

"Pressur uer pressure above 1000 psig.

SEQUOYAH - UNIT 2 3/4 5-1

-% O \

(1.50) 8.08 Match the following reactor trips with the condition each is designed to protect against.

s. Overpower Delta T 1. Power excursions during low power operation

b. Intermediate Range High Flux 2. Control rod drop

c. Undervoltage RCP Bus, 3. DNB

d. Overtemperature AT 4. Control rod drive housing rupture

e. Power Range Positive 5. No fuel pellet melting Rate

6. Loss-of heat sink

7. Uncontrolled rod cluster assembly withdrawal from suberitical conditions

8. No credit taken for this in accident analysis ANSWER

a. 8

b. 8

c. 3

d. 3-

e. 4 REFERENCE CAT /SQNP TS, pp 8 2-3 to 7 012/000; pwg-5 (3.2/4.0)

TVA COMMENT Multiple answers are accepted for a. an b.

a. 8 and 5

b. 8 and 1

6 . . .

2.2 LIMITING SAFETY SYSTEM SETTINGS 8ASES Manual Reactor Trio The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and prov des manual reactor trip capability.

i Power Rance. Neutron Flux The Power Range, Neutron Flux channel high setpoint provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry. The low set point provides redundant protection in the power range for a power excursion beginning from low power. The trip associated with the low setpoint may be manually bypassed when P-10 is active (two of the four power range channels indicate a power level of above approximately 9 percent of RATED THERMAL POWER) and is auto-matica11y reinstated when P-10 becomes . inactive (three of the four channels indicate a power level below approximately 9 percent of RATED THERMAL POWER).

Power Rance. Neutron Flux. High Rates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of rod ejection events from any power level. Specifically, this trip complements the Power Ranga Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power.

The Power Range Negative Rate trip provides protection to ensure that the minimum DN8R is maintained above 1.30 for control rod crop accidents. At high power a single or multiple rod drop accident could cause local flux peaking whicn, when in conjunction with nuclear power being maintained equivalent to turbine power by action of the automatic rod control system, could cause an unconservative local DNBR to exist. The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rods.

Intermediate and Source Rance. Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startuo. These trips provide redundant protec-tien to the low setpoint trip of the Power Range, Neutron Flux,ghannels. The Source Range Channels will initiate a reactor trip at about 10

counts per second unless manually blocked when P-6 becomes active. The Intermediate b

( SEQUOYAH - UNIT 2 8 2-3

r

( . e

(.75) 8.18 Recent failures of PK-2 test block terminal posts utilized during routine testing of circuits has occurred recently at Sequoyah Nuclear Power Plant. Though the root cause of this problem is as yet undetermined, what are the potential problems associated with a terminal post failure?

ANSWER

-result in an open circuit making equipment unavailable, which may go undetected. (+.5) Potential personnel safety hazard if an open circuit is developed on a current transformer cirucit during testing. (+.25)

REFERENCE USNRC I&E Notice #85-83 of 30 October 1985.

TVA CONMENT Accept a broader answer than on key. The answer, if it includes comments on potential damage to equipment and/or personnel or damage to the circuit, should be accepted.

(1.0) 8.19 What are the tolerances within which the following control systems must be maintained while in manual control in a steady state conditionf

a. Pressurizer pressure

b. Pressurizer level

c. Tavs

d. Steam Generator level ANSWER a.) +/-30 psig (+.25 ea) b.) +/-51 span c.) +/-4 deg F d.) +/-5% span REFERENCE SQNP PLS, ppl PWG-7: Explain / apply Limits & Precautions (3.5/4.0)

TVA COMMENTS Some of these spans are outside of allowable Tech Spec or procedural limits. Specifically

a. Pressurizer Pressure DNB >2220 psia

b. All procedural references state maintain on pro 6 ram - no tolerance is speelfled

c. Tavg i 3*F is given as tolerence in GOI-2 step 60 This question is not valid and should be removed from the esamination.

e so *-

(1.0) 8.23 What is the factor W(z) a function of and what does it account for as it applies to the heat flux hot channel factor Fq(z) determination?

ANSWER It is a cycle dependent function (+.25) that accounts for power distribution transients encountered during normal operations (+.75)

REFERENCE SQNP TS 3/4.2.2 001/000; KS.45 (2.3/3.6)

TVA CONNENTS Question asked is not pertinent. This is not handled by the SRO, but by the NUCLEAR ENGINEERS when the related surveillance performed. Question should be deleted.

? '

",.y- r MgW ENCLOSURE 3 U. ,s . NUCLtAn,. r c. u U L s, ,. 0 Fr . . . 3 n nt:_ .;t,. 0 N.

dENAvn R, t s C .,. .

. O R . O r, E R. s . T O R u u.,_ N :.t. . t xn.n a r4 -._.0N ne FACILITY: SE5UGfAH 1C FEACTOR T(PE: F4F-WEC4 D n, t_. _. .

schINI3icrED. c . 3 . ,. ,. 1,

. ..8., .Mii 0 l i l _t. r,. .

. -.Nfl*

vt W M gpc" ' - , ."*

.j .+I flb r.I.TIch. L : T u. n F F..ticn r. . N _i .

U5e G e C 5 r 3 f. e .acO- 'cr t .*i G s n ! L. e r i . '.J ? . In:wer. :r, 2ne i; 1 d .: Gnis.

5 l 3,71 C 7, U Q 5 t ; O r t 3hnet On t, 0 !"

I t h '. 2 n 3 6. e f

, in00*5 P3 int 3 fCP 03*n quei'.2n 3rJ inG ' :i .40 t in * ~: 7 2 n t. 9 e i O 3 iftir '. 9 que5 tion ~ TO O3iii*J

.3T3d? r e c. U l

C

1{ -lt*3 t " C '. in : -: : n '

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4 L '.1 00 s i .: 03 v '. .. i. GOUTd ifter tSY O - S r.1 r, i 4 1;< i +, I f *.1

. W

. , + ...

. .* tuu*

i.

, g.

3. ._. , ..

t* ..g.

.J

, , .. . J r_ i s. .o-. . - ,,.,. ,' J t._ ... ,., i c.. u..uL r.

_g_7___ _g- ___________ . . _ _ _ __ _____ ____.__ ____ ___________ _

.__-__._ _' W_ . .~- . .... -... . .. '.

..-(

j

' . L ,. .cnp

. e

- ] L*. t:

< . e . 4 ,.

b) 4 I 4 J ~4 5 ,

~ '

215' zi 5

= w . . . . .-..

h .

N h a e ..e .e =* e-e .e - .se . -_. e e.n_ e_e m .e

.e ,e ,

-. *

I l n re e-+=l" n ,

9 r--* .. .

._. 9 '- 14 t. '

4 t. .

n is i. a

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s - 6 mM. e._ S. & 6-W__ ..D ...-- _ 's.6d.we. . _S 9

-~-..-...-_.r -.>e~g. , 4e 49 k .

4 D =.

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. 4 ..

m ad e ee. e. e, .eD4.

ak4 ..d.

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$. THE0FY OF HUCLEAR F04E : '. A rd i GFERAT~0N. FLUIDS- AND

. FACE THERh0 DYNAMICS QUE3TICri 5.01 't.00)

The reactor i s critical at 10,000 T- s unen a 3 / G F 0 F ') f-ils open.

Assuming BOL conditions, no rod aiotien, and no rez: tor trip, choose the answer below that best describes the values of Tsv3 and nuclear power for the r e s vi t ing r.eu stecd, state. (POAH = point of adding hest),

s. Fins 1 73 3 j r ,> s t e r *,3n

, i+t51 Tav2 -

Finsi .ouer

' aoove F.u, n

. n..

b. cinst T s v .3 jrestor than :nitist Tsv3, Final scwer it FOAH.

c. rinal T3:3 '. e s s .ha n titti41 T v 3, Ftnsi power st PGAH.

d. ~ ins Te.3 le:; ' h a r, 2 n 1 +. :1 Tav3 F : r, = 1 .o-er abase POAH.

Af. 7_ Ps.'A. O, I*I 6.}. lJ C. >'%"

s-6 .

A C; ; *. C r 1

l '. d . ' i t i' L I '; 3 5 1 .

rii ?

. .5 - s ? ? s t in 3 5t i [GW fIcW Condition.

I C l- th?D *tEtt 33 en ti ; *MA ' l i r ~; *. 2i 6 s149 On th9 dis 0hEr 30 ilde. How w1I1 4iC1 :f t !" s /

1 '. C l f. -J . f f e C *. 6 0 ' 'Incr0- e* C O C 7 e 3 f. e C T' (JO Chan30i

" , ;i - ;5 ~c -

(G.$'

.. ..:r' .t-c s ' ' ') . g ..)

- ht: f3.5s sssss "ATECQF+ [ [QtJT[rJUED Qff rs[^ I ; A G f," ass 3se i

f I

t 9 l

5. THEOFY OF NUCLEAR F0WER PLANT OPERATION. FLUIDE, AC PACE I

~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

i TiiEEi15DYi4 AhiC 5 t

OVE5 TION 5.03 (2.00)

An ECP is calculated for a startup 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a snutccun from 100%

steady state power. Indicate whether the actual :tsti 21 c o s i t t o ri will be GREATEF. THAN, LESS THAN or the SAr1E as the ECF for the followin3 conditions.

1) The steam d ia n. 3 pressure ietc.oint ts increaseo ce H :st.3 (0.5)

) All s t e a u. 3ener ator levels ne iner cas m ey 5 *. one minute before the calculated ECF ts to be reached .0.5)

3) C O M e n s e r- v a c .iv a. . r e wred I ' W3 due to s sn: ell sit leat 'O.5)

Oi FaICtar i(!!*tbp 11 J .i 1 G '/ e Q for : horir 3 i9.!)

L);w;t_ -...y es . ,s -4. . .t' .

i_I In;;Iild lie the r f, I t * > [ F ! ! J u l. n j will: 5U50 the titferenti31 pcq worth (c Ti. : F E t. ? E . C EiF E AM t v- a r s. o NO E FECT.

=> u. ; o , 3 c 4 , t rao :

ins.:rtad t, t;.e ;;ae heijnt Padi I *. 3

t emper 3 tur _ - ~JC;EAEEC r

CE"EE' 0

l *-

. .: n0 9 t t i5' ; f,

$ An .~2 ,# isfni D ' ' ? n I D I -! 0*,s Gn '

-Q ~50 F . 6 t e i t

t i c.: , i 4. g g e.*r >

,s6 ,. n J

, . .J .

~

i #) J $ 19 9' e ,Ne k '} e3 t' s 3I no [QC 1)n - 5 S Q m f/ 8 1 f86) 1 C 3 k @

Wn?Te tne rh o I t idi;nt2Jeov3 locat10n Of the Lie s t IcUrte B r: r,,' tne he3t sinf d o ; i d b .1 r e l i l l . .- e e t;te to i m p . r 1.e. i i ra s t r e i n, ct 1.? w n : t r e g m u d ;: r ;..w. r' j

-- ra e (, .. -

a. ,

Mnsi li e the # CUP C J Ta d i t. i C f. 5 thGt I' e C h 3 p e C I' i3' .03 f .e met (Q in ii .T e t .* G rNcle:7 Enthalp'. F:s- Hct :hannel Fs: tor 1: a. e i r t i n e c within i ; a.2 t ; durin3 Fe';ods delWeen LA-C!re IUtYelll3nces7 L

C A T E "., O F Y 05 C0rJT:NUEC 3 r> HEi? PAGE

- - 2* ****-

1 i

r

f-t

3. THEORY OF t10 CLEAR POWER PLAtJT OPERATI0tl, CLUICS. Ar!D FAGE 4 QUE5TI0tl 5.07 ( .50 Attached is a curve showing the moderstar to fool rstic vs. Keff with the optimum point identifiec. This is the point when the hoderstcr Temperature coefficient would be joit :ers. If we were t; add boron how would the optimum point shift on thl: curvet GL'ESTI0t1 3.03 (l.50)

~

Attached are curves s h c w i rej .he uel Te.nperstore Coefficient ,s t E0L snc EOL. Compared to the LOL rotve. e.:plsin why tne FTC is more negative at low temperatores'EOL -s n d less ne3stt.e it h i .3 h t emp e r a tu r e s ,- EGL .

GUESTIOr! 3.0; 1 1.50

.. st the 3 .: s n c i t i c r. s necesast r:r brittle fracture to ,c:vr'in sie t 31.

GUESTIOr! 5.10 i1.50 List the tnree a, sin P:w:- - - r . a t a ., .= s in , , , :cre at or d :f life

l. .t En; ind1C3t9 thalt h7 F f C' : " 2 *. 21'* 1r * . S T- iT '. O I?d?T IuE'TI*>N 3.i1 !

' h e r. ,: e r f o r n i r. g

- , isc :- '- - -

-ha.

n ro: - hcs es i+ # t 0 ! ! ( ?- i ; f ! O il f u '. . : -; ' - -: ". 3 i ' ' ' : A. *1 T.** 2 *. ' m i ri E ** '- I3ta II : C . 5 '. *' - .- 7: 6 +_ -* '; s .e r)U l d th5t Jffect waf )30d. '. t. 4 . . " _ t' th. ~ry g g , e i t .,,i c i. In. tic. ,e :i* . ; '

-, ; ; ,_;i. - tr:t;7t , ;; -

J 4. [+ $ ; 4 **Ta . 6 4 -

d $- # -

- .: . ., '[, "l

, } ,* [

I"["f .# 3

} [

,[4* { n. i j 7, ' C f, i: - - t 123

.- ; ;*_...'1. ;; ; r:. . -. u :

Exass ~ /, 7 E ~ 5 7. ! .5 ' " 4 7 ! -) ', ~ [

'[ -

" *

I ;*C snes I

i

REACTOR OPERATION

8. Coeffecients and Control (continued)

POINT OF OPTIMdM MODERATION 1 r a

Kg Nm/Ng l

l l

~ ' ~ " ~

FIGURE 1.1-6 0882

-1.2 EOL

,C - 1. 3 j BOL y - 1. 4 w

F o

C u.

W -1.5 ;

O o

w E

h - 1. 6 E

r w

A 2

= 8 '

- 1. 7 E

w

/

J o - 1. 8 O EOL

-1.9 400 600 800 1000 1200 1400 1600 1800 EFFECTIVE FUEL TEMPER ATURE( F)

DOPPLER TEMPER ATURE COEFFICIENT BOL,EOL i

l' AGE 1.1 -43

F

. . ,..._,s...

nt. r1 ur th.J a_ . tnm

_ , - -r u ,4 r- t,u n....

t4 o-. r E F r.i _ I t0 ;. , rL,JI .-

. i _:. n ts. c F..G-n t s

--- g g g g g--------------------------------------

. rs a U __ _ _; . _ . ..ua i.., .o

. . . ,v.

Ras, ir the resscn thst -ech Ipecs slioW op to tuc Mcurs cf operation with m su2orant rower .il . l ,. RIt1; in ercels of . n, _ :._

e.

s.,* ,

u t,. taei- _ _ ,. O.t1 ..vu d e r,* . f , the r.u c i t d e s : ]n.por n3 'he secandsrs scurce utill:ea in sour res: tor snd des:ri-e h o -. th:2 source is 're ynersted'.

N_

U

.ns ur ...-

z.e-sv What are toe two fsctors 2 3 3W~ .- 7CQ': e l s y e d neutron trecursars thst influence tne eslus '

'us : E:3r Eff 9 : t i v e 'iFrum t- e f f e c t d t. tney nave

-s uu i AG.4 r

.1: . ,._m. ,

Over cre itfe thers s r *: tWc ef sc*s that cruse o i f f e r e n t i a. l . .? a r o nonwo to cliterentiagth changc. Llit t 'e n s s '. w : re f i e : t s , tnelt relative 1 rip e c t coron .a o r t h ind .wicite C :. c 6 e f f e c t. is the overriding fsctor.

q. -l -: .;-. - t r. tq . i ..4- 4 . .

I ; e I iI g

. h O , I g g 5 * .

h g G C ' ' .1 10 7 101: 2 n 3 r0 : ?fiL iti ir.: hen 20.c, is tO be e c u c c. d tO 5 0 *, . Ine p97 SIC- " CEeT%t t '. '. 5 * " ~[ . : within &t~ 22n3 End decide! D C- [CW90 SGWar 39 CC'5 tin 3+ l s.: 1 ' 17. ; * :20 2 i' l ii e 4EI OC"It10* /e t t '.i E l I B v '3 follow 5 p r 0 3 r s :h ib e ;

i.

3 'l ) Q C '/ 1k C[(llr 2 *

g. g ea e s

- E<

1 1.1 6 3 ( r [ s". p.,

p d

[*3O~e3 . 'i 3 g, M l .. ", C I" - . r

~

i.s s*rU O' r 1 C r

.l

I a b j { g i A 4 ,

$ re .~.4 '3IT

, s s e Y:*~ Dh tN2 .: *

.Di .1 L' r t 1 f~T *~& i:$ a 1 *: }

i* r lh ? ~

.' 5 * :' : 1 i 1 ". E n *. ' ~ C3J.%,

i

=-= , =g g.* _* += e .use*

d b ,Me.*

e q - { - ) ' aE * *lj=* * * -,f g g ,g l es ey l} (

P- kkkkkl

F-

,5. THEORY-0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6-THERh0 DYNAMIC 5 0UESTION- 5.19 (1.50)

Sketch the K( ) height correction factor curve used in the heat flur act channel. factor calculation and ev. plain the basis behind any changes in the curve's deviation frco 1.0.

QUESTION 5.20 (1.75)

Sketch the reactor coolant channel Eciling.Jster curve. indicating the fcur msin boiling re3 ions and the point of DNB. Ensurs you 1soel the s: es correctly.

QUEETION 5.21 (1.50' .

The fcilowing dats As - -btained during a ccre ref.:eling.

Nuaber'of ;sseralles Loaded N eu t r or. Cwnt Fate

L.' c p' ;

e

--e w...

g .- .

AU - * %g c?!

m.. e ..# .-: .

Cet9"Line the nunc3r -2 # s f i : _,0113 5 it will t ?L 9 '

33:3 criticIlit'..

Og+ ' . - -

i t s c h .3 ? 3r 9ph o s p. r ;f -. e : , 4 ' a r.. .- p qi. - l s i s c. cd. ! . wOfth) 1.. ;3 e. .: ; ._ . , a v . . ..

c, ..,

.1 : '* M * :19 ittschec :*3:

tIJ1eir .4 h s t .I t's i' Tac U n t cf r i fh 3 r V . 3UOccoll,.]

t l' 0

s i LU T 12 9 - . 5 11 _ .___ _ . p5;3 Sn- _ 33 it ; __ Q ;- 3 001 .. r*

r- 7 *

, !a; - - - . ;.. .*-. .

S 4 . . % * ** s $ . n .o 6 d e O ' ; v' l i . idolt;Ln. "n?t niPPeni t :; tre m a r 31. . - .

-

l ' 1 s l i t ',- T a s s * .s E rJ C I _ Ji T E C ,', F 't 'T *taas

h

.,__a. .- - - - . -

+_a

,-me -ewem 6

e I

5 4

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

r

6. PLANT SYSTEh5 DESIGN, CONTROL, AND INSTRUhENTATION PAGE GUESTION 6.01 . (1.00)

The pressurizer. safety valves sre-desi3ned to limit RC5 pressure to. within the safety limit of 2735 psig following a complete loss of turbine generator load while at rsted thermal power. Which of the (311 cuing miti:3ating. events is assumed to have occurre in the snalysis for this desian basis?

i '

s. Resctor trip due t.c turbine las: ci Icao

b. P O P 'v' operstior.

c. Hi :' I R pressure trip

d. Both spray valves actaate

e. Relief >sives on all 3 5/Gs actuste GUESTION 6.02 (1.00' Which statement belcw regsrdin3 Giesel G e r. e r s t o r ics1 sequencing s cor sct if s LOCA occur 4-AFTEF :. LO5I 0F-F0WERT

s. Lass- :Irsadv sequentialls : ,r.n e : t e d. w i l l emein :onnected,

b. ' o sd5 awsiting s c- '. + n t. i s l 1 c a d i r.3 that see required for an s c c i a r- t will hsw their se.ven 131 trc : : reset to time cerc.

_. The .. ;n- se:ident 1,a d s not ce' : :.n n e : : w : .1 1 b3 sequencec on

,: - 311 ; c c ,10. r - +1: 6 0 .- gc; p ::. . g ; * ; ;

6 "Lu laads will be str:p:21- trer s!L i 'ne 3::: dent _relateo ~1ssos util be # e t. = . i - . ; ; ; 1 ' :or,n : ci.

GUEETION .33 (1,00 C st set of st3nais celow Ire tent to tac : e s c '. : t ~ r c:': n i j s -: n tc ind.:sie s Turcine T r i ,: :

3 . Th :- ' ; e 51.e: :1 sed Aut- :tcp i t '. :- s ; c e icw

, , r r. t t le .s1n- : lose $ & EHC cr s e : :.-

- 6cso ncr /sives ': 1 c s e d i Auto 5 tor. GI. eris.~- low

c. Gcverncr valves closed & EHC pt essor a law sas** CATEGGRt 's,. CONTINUED nu riEXT ; AGE spies

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE E QUESTION 6.04 (2.00)

Indicate whether the following situations will' ARd GNL'fr ARM AND ACTUATE

-or HAVE NO EFFECT on the steam dump system.

a) 507. Powere 18% step load increase. T s v g t:T r e f by 5 degrees Fr steam durap s in Tavs mode of operation b) 30% powerr 7.5 / min ramp decrease in tvebine load for 3 minutes, T a vg:: T r e f by 7 degrees F. steam dumps in Tavg mode of operation

) Hot Zer a F ower . Tavg=54? degrees F. steam dumps in 3TH PRESS mode with 1005 psig set I r. t o the s t o rar. Pressure controller di Turbine trip. 7 evg=50: degrees. Etesm d v aip s in Tsvg mode QUE5 TION 6.05 (1.50T

ndicate -het:er the fall mirig CVC3 vsl.es aill FAIL OPENr CLOSED or A5 15 on a Less c: . Instrument Air 4i ow ~ rersure '_ e t d c u n U s 1. e ( P C'J - s t b' Ch+rsing Flcw Conti:1 Valve (TCV-s: 02

) Letdown Grifice : 01stico $ ' 21 v e s ( F C 'l - 5 ; - r J r 4 snd -75)

.p .L t r. --

A J i; s.,-

_ .. 1 ,.___L

/

/ so)

$ ,i e r, thcre

_l- '.../ C ; ei ?1 en ji: . 5.u +:sn

r : .. c l .: s - ,i i c si e cypsssed

r.-

i._ ' a e T. ;r e.i.ii t 3 9 reJ + .

1 l l c.

" O

T. , * ,' ? _

3' . ' . ". .*

161 1I * 'l +3 C 1 i s~ I 3 in Ie I' f3 CWing i * ?. . Is C n t 'g3IdIng 1 1 2 './ i d .d 3 2 $ 3 prQCO3Iin3 I

1Ni;* *.3Ee t r i t l U lii !CDC2hti2ti2n i; _,,,,. :~ 1* G i e 3 i t .~* i _ _ _ _ , ,

' -- e;u : E s* ., ;E t r . ; I _ tt 4 - .,

l ' 11 1 i,7 ;Oa:Gietr !;;r,. 1- da?.jnu; r

-: . s *,

a L.$ -

L 1-I [ I E: '$oW 7 +: ' E 4 f. i 0 2, - I i . . .,~,s . IOe i .-l E > l f, L'.ikU E'

il;;iin3 3ystem '

?! ting idith *~. Usi's + ~ :ivs . 3 3 *. e T 3 .~. 2 I n c, ereding uite the i- n i i r O n D e n t . T r. ~. l t.. d s ,~2 !ifi- f 9'

+3r snl~' ! --iEel. 1.~

tJ*** ~E^.[L' ~;7 C.3NITNUEC $ 14 i i i' '* ' ^ ACE 3 18**

6. .. PLANT SYSTEMS DESIGN, CONTROLt AND INSTRUtiENT ATIDd PAGE T QUESTION 16.0S - (1.'"1 )

s) '4h a t is t h e' ai n i m u n. >1ffarentist tempersture ellowed 'cy-Tech Specs bet.seen the Pr e s sor iret spr3. snd'the pressuri:er; b) Whst i s the purpose of the Iccs seal loccted below esch pressurizer

- sv. s.

s a ,. se . y valve :

ci un .; t. is the d r i , i r. 3 fcrce for norms 1 spray ficw? (0 5) uy g_3. _ _.u ,J iy .

o.0~.. x. a.

In I, n. @ ' 0.1, s f. k 3 t o) i. 2 m G tr: t9

_.,1

-L. i

. ,'. 9 . 11 0ViGN. It3tO%@ng3

'0. .. CCOC0rnini. ~U91 h 3 f i CIl [ , e 3 i f > 4. O r i O Ck 3I 109 retU011hl. : 3 0 6 ,L 3, ,1? tin 4- 3 f4 L5 4 LG.9r12Cved W i ,w ,a ,dG

s w ___._. . tlc liftirQ Of th9 . 3r1 C3&nLi UO 1 1 # '. 0 :, O ri l . 12 th0

_____ i f in the _ ___ P05itiOO CPiG: '. s _____. (1.6)

h. E*idjY -fi.

l ? '.1 l e s ~- 1.- O GT. I t ; 0 rs 11 o. r e v e n t,e d 0 ,.". s p t wher. _____ .

-'.*_%. . V.

s/

e; ,.. _.

. m..

. -. a

. ms 9o ,) r t r- :p g c h e r. g .,CW t.ne i.. n t 3 [ n tu c p t mir g -

~a

t* . dnt ' C 0 rs c . - i n .3

.:. ..n..,

c. ...s ca_5-

- .: :.. .._ y . . ., 2 a . ,. a t.,

. .c ,

. + . . ,

.- . u, i .: I- g. ana1 . . .3 .*. p, .

o ,. 9 ase 1.2fto El3!t r. I f** _ _ _ _ _ . 11 im t (41. ' . 0 ,, , , , , _C ~; t 1 "i v n ; 3 l '. drSW Ilr i rom the IC E.s '*' . td- 3 r

s i r. a e a l ,d?Iel S n .; # TC.i t h ." " O l l.J w i n J G.CCfeted

~peC' * -

= 9 t. ; .

' . . . . . . ,, ., .c.

. c - ' .ie * . .:. . . a.

.,. - .6 . e.m .._

6..,

-i,. ., e.._.- 7-. :: v . ' u . v . .s. .

<.. .Y .

. , . , . s ,, . n. e.,

9, : ,. ..i, ., . . , v.

. ,: =. f _. ..

4. r, 4, s . , .-; . - -

.1 e,n-.- .._. -__-; .

.t ..,/ >

h*. L4

pii t" ') *ad h ,,, 6 h ah -) [e , ,h h ( $1 *h h =[h. h f $4 N ) P)* l ?]- .

h h 1CW t. 2 .1;. P D ! ! 1p*3j C pe r a t . Ore . .! ; 3 5 i d,

r, 3 ther e is 3till ice '1 ri the ice

--C f. C i n 3 4 r . . _ , 0 G ", i f / 3 ,6 _ . C % p -' '. e f t' . v . . C e p ,, i r. J '/ 31 V 0 5 16 t n.e 3 5 t.n)

.4 45*A1 C ATECO ' ii [ON'"I!!UED Of 2 NEEI i *(( t 1. * *

I f

4 1

. . ~ . , ,e .,--_.,,.,-c.,---m_m-mr,.,,~,,,,,,.e,._,,e...

7

. ' . : LANT 3YSTEMS DE3IGNr CONTRGL, AND INS T F U hC'iT A TIC N PAGE 10 GUE3 TION 6.13 - (1.50)

Whst signal 2 will automatically initiste the ' r. e r s t i o n cf the Auxilisry Building Gas Treatment Egstem?

GUE3 TION 6.14 - *

- ~ ' [l ib s) List the signals which will :suse sn sutcastic isolation :f the Feeduster Eystem. .~5>

b) t. i s t the s u t .o m s t i c ' = c t i o n s that cccur cue tc the feeduster i solstian. -

s.igns,. .

(U-)

GUESTION a.15 'i.:5i Where sre thermal sleeves sssociated sith PC3 oene tr atic: s lecsted OUtal.ON-o.,o Liit the CcnditiCn3 T940i'90 # OT A .' " C in d t I C 3w3Pcv6T f I C To .th9 Inject 1'n fiCd6 to thE i- GCif 2 01 - t 13 0. Made f C l l O w l is , 3- II r_ Waich v s lC s 3re AVICh A IIC AL .. t c C 31 i i : ". 6 d .

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

.-- -+ .

,:.s s

.;l'

_ 6.7'96 LnF.2 ,2Cr E r, : i - - .Je. -- ::. r, * '

. J. m - . i A T I .: ' snsier Of 3 6.7 [ i,8

; ,- 4.

-j ., :- __;

i- ,+

__.- ;,ar r. : : .;_. - i? -

,ta.r. - _. _ !_i ,- . , s 1 ,

._:.r . - . -. - . . -

t 3 .

. _s

-- i' n . ;

(>

ipe - - . .i.

,:i

1 3 .E

., ,7*..-+ 1.hi.: t',e r s i c ,. c r . : : :. ,....- -- f ' .._-

T-3 i.-_-....; e- .

-% i i. . _. .A ..--

-. < OI- - , i,1 [ G !

. I i. ', s_'

a O. s*. Q '..

.f. .$ g (r* *' 1 a

- Z ' - '

.ju . . &. .6. , - .; ..,.g 1

K T f--J9 n t T C ; 1 d -- ~ *. I ' .* C T- - ; ;- ]

- * . ~

~

4

= ' ~

f&K2 s s' /, I E .*; C C / * - " f p T '!E? _

?' ; ~ . ' ' ~ , ~ ~ :issa

6. PLANT SYSTEri5 DESIGN, CONTROL, AND IN5TRutiENT ATIDrJ RAGE il OUESTION s.20 (1.50)-

t ) Describe the crder of precessing elements in the Air Cleanup Units through which 2;T is drswn by the Air Cleanup E v'o s y s t e ra . (1.0) b .i How sre the processing eles.ents in an IN AC TI'!E sir clesnup Unit Icaded with radiosetive naterist F.ept cool ' (0.5)

GUE5 TION 4.21 !1.:5F The tetecter Current Comparator recei/es i n:o u t f r - i. 311 4 upper _snd lower power ringe detect?T3. h3W 3re theIG inpUti C O "n F- 5 ! er d t what is the 513rm setp0 int 3nd When iI thi? c i T C H i i r '< 1n OpeP3tiGr.'

GUe-_,0N t. :. # 4 o._-

i.1.v.v Uith the pressoricer leesi control telectar switch in pciition I/II, I fEllVTe CaV3tti the fOllOWirig plEnt event 3. lAI50me r. O OFeratar

' 3CtiGn3 l -3 k e n . Il

1. -Ch?rging flow PedVCGd t0 minimum I. . Ere55Vri er level de:reslei

3. Letdown secure 1 snc 3este: a cff

4. L e ,' e l i n c i _ 2 3 a .: un 2: v i ,j b .evc1 trit W. i c a i n 3 t r V '; e n t

311 t c ! r " I ', 3 - ;n q ,3 3 t *

--ti0n did it f3tl~

-e w J -e '*e.m d.

N .' , - " I t ?! e -; / ~ ? ? 1 I . ~ ' *

.t 4 '3 . I l2 '*i4 '

b 23 ' ~

t t & t.

E (; * 'r [ J, _ ,Jr s T ff 45

s .

'7 PROCECURES - ' NORMAL, ACNORMAL. EMERGENCY AND PAGE '1 RADIGLOGICAL CONTROL QUESTION T.01 (1.00)

Which of.the following would NOT require Emergency Boration'

s. Excessive control red withdrawal while st power.

b.- Uncontrolled resctor hestop following s reactor trip.

c. Failure of the Beric Acic . low Centec11er FC-62-139 to function while perfornir.3 s p o r s t i o r, to reduce power.

d. Encessive ccntrol roc insertien while at power.

GUtos20N .uu r.e~ :

yith the .eacter trtp cresters 3 HUT snd t h e L'G s under Nitrogen pressure.

the nittogen must be verted off prict to opening the MSIVs. Which of the 2

followin3 is ti - - e s _u n for this orecsuticn2 l

4. To present 5IE a c t'..s t i o n o r: 5JG Higi Differential Fr es sur e

b. To prevent dam 43e c Fhe M 3,I') + =sts

c. IC prdVent E57Ai iC*.JZti;h ,in bijn st91 .linf fl3w '

391

~~

d.

0 p. , :. g re t El~ ck e.s L ie n 'D

l. 0 - L

- 5 _M *2)Y

_ a

.4 e l . , _ s . . .L. . . .

4 " *. Q $

F '

1 4

7. FFOCEDURE3 - NOFMAL, ABNCRMAL. EMERGENC'f AND PAGE L3 RADIOLOGICAL CONTROL-GUESTION- ~.03 '1.00)

Which of the.fc11cwing statements describes the correct action to t a t.e if, on a' reactor startup, criticality is achieved ABOVE the zero power rod insertion limits but BELOW the */- 1000 pcm criticality band?

a. Insert rods to the zero power insertion 1imit-and recalculate the ECF.

b. Discentinue the itsrtup, calculste and then-conduct the necessary borstior. to ensure that e r i t i c a l i t .i is 3:hiesed w thin the 1000 scii asnd.

c. Ccntinue with the stsctos, log 3i ng the concitions it which criticality was sc'.ieved and netify the nuciost engineering cept.

d. . Insert O N L'l the control bank rods to the bottom of the core and recst:viste the t C~.

~

t

a. Insert ONLY the-:cntr , b i o s. s - t : the bottom of the core and r e c o mrnanc e tne s t a r t e ,: using a 1/n pict to approach criticslity.

de:

u , - - 2,_ ;,! s- 1 . u. s lh - :' i '- ! ! a u l n -3 i t ; t 2 ", r; t ; r c J 2 r 31.3 the T a v i t e d '3 t e 2 ci Gencrstar I s 012 t 10's C70!edure* E-1*

C.'*elt~

s, It the taulten 3 0 ?nnot be tcentifiec f r o r: Ocservsttan of l 'G pressure, then AL H I I'.' + i H5IV b?;3sses sre snut and AFW tc the i Gs is i cisted.

!. A I s o l l e', E ' ~- C3hn:t a .J s t.- O fit k. .~ 5 cold;wn.

I ;e G ea ; ir 4 d i f f e r e n ; -2 bGt.Jeen % ,4 OC3 . ti j (de ! suited'3:G E " 0 s. ' l ' hSt (,0060 10{~ ; I I *. .

- 1. Li jb E31st1~n leidls Cn eithe' t?- l- ! ~2 dcun 7cn1tcrt ;r tne 0 0 n d e ~ 3.: t G;:nsurt 3onitorF ~rA 3 ;t i ;L P r c y n p t o rr - thst -

f svit ac 'I e 15t:.

as: 4 :ArEGG6* -~

c r N TIrrj E t 'n ,- : ,u: rx : .

r

. 4

7. PROCEDUREE - N O R ti A L , AENORMAL- E riEF C E r3 C f AHL PAGE la

- --~~~---~~--~~-- -~~~~~~~

--- EE515E551cEL c5DiR5L GUESTION .05 ~ (1.00'

'J h i c h o f the fallowing would cause 6. h .- grestest b i c l c.31 c 21 a s .m a j a to a man?

a. 0.1 Rad of F* a s t Neutttn.

b. 10.Rao o r' Gamms.

c. 20 Rad of Bets.

d. 0.5 Rid cf Alphs.

OU biIOl4 .0c (1.00i

'Jhich of t'h e ~ f 4110 wing describes whst is aie a n t by 'clothin3 Dey p s*le' ss it i s utilized iwQ t e r m i ni n 3 the e: tstence of B e t e - G a r.ini p es5 t a m i n a t i o n o n skin or clothing surt m 2? -

x -

Less than . P,, . . N -

3.

t : P T. sco m bj$.gravnA r3 measured alth a pancske probe. _J }- q N. 0.

c. . tus taan .: , . c .u., acca e r: 5 3rcuni m m.n... u atta . n.sar.

N N.

C, e Le15 k1&E C I C h jI d 'k i O .3 r' k i Ei f..C 3 3 Q[ wI b 3 3 89 O 3 I kNar'..*

I .: C ..i n t 6 0 f *, .* CSf T. L 3 9 t e .

N N s 4 LG'1 '_ i ;

. r, : til ' - . 4 . :* if : ..s .;. i n t + a s c r y t j. o r, .,

6ht - i,.'+-

4

, e, Ji., f. ; a *

1 r' s.' t. e .

s

@g F 4 O_ W g _ _ ^W

m. h .[ P k'- h

U*LOf t0 i Pe5C.cT 5tirt 6 * .41 (O '

_ ~II 3r r,Crm31 C *. e r 3 *, t r. g -r@g3vrn in; s

' * - " I U * :-

trC i ;1. twin] ?CE l t. 2. 30s O iIt Tc' C3:n 1014 112 t O *. 2 0 l a .J .

,ts - '. Whether c .. . i4 .. E T A Tt T i.' F ,r .40013 ci.9 *

. renstn 3 Hij i[ O W tl .

~~ .2 ri i D 'j e p e r d e b 7 I i G 3 C t 19 F l

? 1 ~r ., ?5 :.5r!

> 22! (?23 -

r;' n e a r 34 C_ :f

' ~

I'

. s.0 CPH ' t a n. . : r. :1 21 e c - . _; .1 - c ,

F h I l

_! 0.1 CIN f r O G. 79 rG3C'M . - 5 1 .' N N C E ' .

[ rJ T [ rJ , ' E O O !) . i [ 'i -

- A3s ~ ', 7 [ [. i) O t' "t*C s333

17 . PROCEDURE 5 - NORM AL, AE:NORti AL . EMERGENCY AND 'FAGE 15

~~~~~3550i55553i.~50EiRUI~~~~~~~~"~~~~~~~~~~~~

R QUESTION 7.05 (1.00:

Fill in-the blanks in the fcilowin3 statements re3arding the monitorin3 of AFD and actions to be tanen if specifications are not met.

The AFD shall be considered outside of its limits when at least

_____ OPERAE:LE excore ::nannel(s) is< are indicatinq the AFD to be .

cutside its limit. When the indicated AFD is outside its sllowsble limit it ra u s - te r est m ed tc sp eification+ within _____ ' t t .m .: or Thermsl ':cuer m u s t e .- reduced to less than _____*; of Fsted Thermal power witnin (time .

QUE3 TION

~

.09 (1.00' r i i '. - i n the bisnks with the apprcpriste limits listed in the precaut. tons sa:tton of the GD~s:

of._____.

i) A *.ced :hange of -/- ______ .'iii or a step chan3e should not be sbCGed"*.,

o)- The i:cror, concentratien aifferince ast een the o r e a Ior 1::e r sM the P.1

'n U 5 t re 31 emcee 6 _____pp&,

cl Q2 ii r4103 t i m ti e ' I r_ U r 9 - s t. o o t n t for :-J N I T l ' .,

~r 2 0 F.V s i? . _ _ _ _ a e _l F.

yy y . 7 ,- = _ e 1. . . . . .

("b- . * *k

4 **

{ '.~ ., L *$ d $ "* ~" fc

~

.. n. (o ,$4e $ b n ' bI e ";' '"t Na e $ D [8 F.

)hr $D {= 0 I 0 ?k I in sonor re l s i t e. s t : 2 n ;

- tJ: . e n *Ms .FD '

3 . T, i : 7 " c t I ~ :, E L . t. - aFC .:. . . i t .e 1. . . j ezc e ser o c, ;;r 's-'. I .. n.. ,. .

s , ' j : . .. -*

s .

_____e,w.6.1 e : . t a.

4 .4 , off / 1; _ _ .. . :, t . ' t- . .- ,; , .] . Q(d t .- ^r a r, 6 .he

.- J 4 LL:. s . .. .,.~%

,'; .;, y.

6

,, , t1 ,

7, m.* C [* O. . 7

_ 7. P .4

. , , , , . f *, p . .

_s c6 ,,

,,.g

.. . 3.

.. , 4, r ,s, 4

1 6* g) - ga I g j ,' , 4,,"

g ,

"WW 4 *

.m g y g .

, a

, 8 48.. 6 a *' e1' Il* ! . Iw - 'i' &

"e 6 , k f. / [e F.

".b ~^ . * 'u

.. . .e 0.e t* $

. + -

easas A " ~ *, 0 7 Y .i,

,yt. , 7 t 'J E " q *j cjEXT FAG ~ = 53 s

~

FOCEDlJRE5 - NORhAL, ABNORhAL- EhERGENCt' AND PAGE le RADIOLOGICAL CONTROL QUESTION .11 ( .50)

In orser t: 'aypass a Foel Handling equipment i.terloCF., whose permission is required?

u t;, E : _. _ .. .r., .1;_ 1 . .,, .c 3 Fill in the bisnf.s belew to Ccmplet-: the s t = t e .m e n t rejardin3 solid water operstions:

Whenever the plant is >till:1n3 letdown f r o ra :: H R , the _____

controi velve s h o o l rf be used to nalntain pressorer while the

_____ control valve should Oe fol;. 3 pen. Fower to the _____.

the _____ and _____ shoula re i 33ed out tc minimize the possibility of overpreisv: i:ing ive tc an II signal. Whenever the reactor Coolant t e tt.p e s t u r e is abova _____ de3.F. it i e .a s t o. e FCF must be in o,m e r s t l a n .

) g.% es - , . O p.

4w1 (4

. A .ce

'i:t the required 3Ct1Cn3 3r irr AIW3 If t le tri; b r e i k.O r i C5n (J O T b ) cpened 31 .1.i t e u. in rUnCtt!.D r e s t C T E t ~.. r, .. 0 1 0 e A l n 9 tr

..A. Por EnV a c t 1 ; n' t.s.3 +.

Ti!qUtres 1CCsl 3perEtiCn O' -icei* inclVGe t .1 e ldC3tiCn f r C Ta salCn the dE*;CG niU 0 4 DG O p e r 3 t e rl .

'*c$i k- --.$# # .,'iT ..a s

" ~

' Nn 3 i tilion b13 C f C8>f * .d h h . -* ". i . e 5 .. O3 r ist 3re se{Uentis11.

l o s o Fi Futonstic31li ntC thJ Q1e .-l. t1.I!

o- T h.; r e it s prec20*.cn to t ,.e . ._ :: . ** :Ir ; w.r ; r o c :.a t r e

. AGI-3"i to enau; e t3st ihe r. u el; *

.csced t- .S. t '4 w i t h i ": 4 noors

- IUming *he '; 1 ? E e ! : it e re 4. ' red -' :

b

[ C ". 3 . s ,i S t LI t e ?Or? re 31 tnt = :r.- vott n? .i . : .

lUE3~ ION ~.15 _

~'

--[l30)

. tit the inmediste'sCtions : r. AOI ~- 'FrcL: le -- twm 71ced'. sion.ing the Plant h6s been DOtii100 r t r. E1 111on .i t W G t. i h ire ? Je&G n t thst f10C0 prCducing CGndit!Ons %3. *:( /elCc .

(***ts CATE 3Et O' ; JiliIrJ U E D . t *J :iE) i ;- 1. C E ****;

4

7. PROCEDURES - NORMAL, ABNORMAL. EMEPGENCY'AND PAGE 17

~

~~~~EED56LUU5U L U tlTRUU~~~~~~~~~~~~~~~~ ~~~~~~~

GUESTION 1.16 (1.25i As stated in the facility's ALARA projramr what are the FIVE MINIhuh requirements to be' included in pre-job ALARA pisoning ar d .whi::h should be included by the co3ntrant superviscr en the pre-job ALARA plannin3 report?

GifE5 TION 7.17 (I.50i s) List the two r a d i c 1 c 31 c s 11 *. crtented limits that, if ..:ceeded. .c,31 d prompt the Eite Emergency Director to mose the assembly point for p i s r. t personnel to the employee omrfin3 tot' '0.51 bi Where is the pr e f er r ed e.s:a stion site for on-site personnel if evacuatico tc sn off-site ic:stion is required? (0.5~

c) What emergency condit On- ;c. whst 1sssifi:stions) r equir e ac tis s t or,

f the Technt: a1 Iuscort enter" ", . 5 N ,4 E C .* U ;a # _ ...*

. c.

4 8 .i t 5' M .; I, I tJ n G 1 t i C r: It d : ' ur .e *

S ii % 5 ( .[ 3 3-1 : , ko J t; Oi ff~c

- ' ' I -- * -- * * ~

, t m e, 9(i 3,' + -- *;, - - 3 ; , ,, 3 , , , , _

; r.1 ;

' ~ -"

~ " , ra n t i L r, p e ri *

! ~^ ,

~

r a* ,,

W .: r. I re -- i * ;; .

.~ '* - .

t:-

+1; a

. - Jlred [,

. it . a" .

._' ' ~ . *

~

' ' -' 2 - - - ' -

_,. t, -.

- ; +- .

7 ,

,9 * *

'* - +.9 4 (

'. 8 4 , J ,

g 4 - . ,,, - .e - 6 it# , .

, . a.

s e o

, m e l. - . y .

, . - 4 . .

+ g t I

{ TT $ h D , a* tr k$ $f$

p

~. FROCECURE5 - NCRHAL, A E'N O R M AL , EMEPGENCY A rlC .: AGE 13 ee u4s 0 t u yu G % i. <a,L-C0riwROL i GUESTION - .10

' 1.00)

Whst are +.he three 33rsneters that sre mcnitored tc -:atermine RC3 cocidown In accoro.s nce with Ed-0.de , h, a t u r3 5- ..L i r : v ,i s ,. l o n uccicown..

GUE5 HON . .1 (1.00)

.*I[hI s ') ( C di b e ' 4 d 1 b N. b d bU$& 'a 1TN bw 1 G ra t, C C ,A *i c tJ n Ps e r *3-') 37 lt 13 TseCOE5ary t0 i ri O 7 e & 2 G thE RCE DOT 1: 30i" I d d i t i O rt by 17. . WhV 13 th1E F 9 P s i r *3 d ?

, - - , ., I ,a * .. a)..J I O ,J C. *' I 1 L [T o-00 $ CCnbfO[ ~CGT4 9/iTV3t1CO* A01-E7A 3.36 / E r I G t/ s C A*2 0kli s t s f.d S t .i U $ t 06 e

. O , n' Pleted in lcc st t ans t hr'ou 3nsut the p 15 ri t . The pr 3:odore i cjentifies the f O I. l C W iD *2' 9er50nnel 35 GV6il6'01e IQ the Ghlft enjineer tC 9erfOrm 3p2CifiC t35k2 in the plant 3251?t3nt Shift PG31 nest Eied 4 335ist30t Unit '

OptTit0?i. Where Ere t09 5 '.002'.10ns t3 401Ch tnG5e cer500nel 30 to C3Pr, 3 8.' t tr-1* ?EI13hrG d u t l i= B ~ (Onl. InclVO9 IGC3*.~009 ?FFliC3D'.e tC 3 5 ingle 'Jnit' m

e _W ~s-~; ~.t C iJ ~.*: .

. .* . ., :s

"* ! 1 . * . ._. . . * . r b ped ) *e4,,7*

'1 . ... . ,.

.b5 h a3 n J e .. N M . .%

P e e

O b d % d b d' e og

.. . 6 . * . . .

- E' ( 3

.$ .! *. . V E I - . L - .

** r.

b

/

I -

. *' s d . J.

8.4 i FS

% ' 9 m

. " . [ l A. .

. . & . k 2 '. G . ' fl

' '* i E 3 ' O 7 f t *f f b.

,,' * , " ,' 3 I J .* 3 r e +;* Q 4 [ *. ; ' FQ}'i15tLOj ,

.. ' ri n '. ' l **

AUIC,

_.c s+.*(,-

. s 4 . . .

,1 .J -

1 - 88 * ,

r '_ 1

, _ 9 s .

y

...,'5_*

"i s +

~

4 f $ 4, t 1 -] < j ] 57 ," g 7['(( $TL t t

-2.-

n. 0 H t. N i m i R n. .it

.n,t- e - O c _t 0 L. _. .., t : - e.

- :. 0 . D y _.10. tb > nN-u n a i n T Iu-r b. Pn,GE 1,.r-GUESTION G.01 -

(*.00)

Frier to unbclting the ras:tcr vessel hesc. the sinimum.Joron con-centration must meet unich of the following requirements?

a. 2000 pr.m OR enoujh to ensure Leff is less than 0.75 whicheser is LEEE.

.' v u

v. ,

.c -ett.

c. _

.c . n .i _i r e a. a r d

. Enauf to enxur e 1ef' is leis thsn ':.:" JITHOUT regard tc ccncentrstion.

_u00 p p ni On. t .. ensure k e r.t .. t: tes3 thsn v . v ,s i c.

uhichever is e F,.E e n- cnv 3.i n t.e .

t ., . v u i

.,u E : ,. I O N u a.y,.u tJhich af Qe cilwing itatements C a n c e r r i r. 3 ihutdown Marjtn iSDH) con 51dGTEti3nE i? CGrieOt~

3 Uith 7Isq *lCi3 t h i r- 290 d O *3 r c .s E

tne 3DH reJUirementi Sre in:~50!E' cec?t*se 0; tn: : 53it: 11t' of i Fcsitive MTC.

b. " h .: nort rc3 4. c i C 4ir : ; . - i . j ., n F 3r 3DM equir@QentE J; CUT : :

E3L- . ;

T1 ~ 2s 9 3. t n! 1 ", 3 *. tel-eiEtVTO* enc i3 3: - - '. I *. 2 C .u i t ** : - . -: '6 100 r< ; den *

f. , ;. r, s sr t r. ,s 6.ra

_ .; .~ .. ' ; .e 5 .: .t. ,Gezu5te ;. D r. .i 15 4 . v s . .Or.[c ; aj '*e 3 Ocicted crit 1:11 r34 r. 0 5 i t 1 C n s

3 4

s I, D v e so? *.

>. li,5 f1100 i i nh l . 3 .

,C 4 at .ne "C0 17 -nCWr - ,0 e pirL15tly i n 3 e r ,. e d End Untrip-

" 3D1e* IT. inC"e&se. 311 s w E D C e- f0* t 'i - rr-tire ?nd WOTth shs11 'Or ra f d 6 to r E. A 3DM ~eqv1reFi e*5 .

Dl!EIIICI' E.0' l.C7 Win i l e 1. 's h Cr 1 2 ~~" 9 3 E u r L ; e r C0de 2 3 et9 ' .' 3 1 . .E " e t e r m i n e-j t0 de IN0fERibLE, h0W lOng dO V00 /*?Ve tC re5 tore th9 I O .J & E r, f e t N tO OPG' 5 01 '. ; t s Sef0T9 Tech 3peC5 "?quiPG 00 6. 0 i n i t 1 : I. : E .W t d O W n to Hot 5 t a rd :

1 .

. YCU FUIt 2 Rime Gi; t el y 5t3rt .* Der 3 b u t i 3.J r ;;eG if

( _ .

g

.O. LQ (k L ~su ,e 5 Ce 3{ QiGUteE G. hCnT

. q . _ . g r. j . . .m .

3 IIII% ' ** i. .C ; 8. , f-

V i.3 k.,, 6.J N.

4 i. . d. utu

_r u d. dt:... , , ts t aaea s

<e

I J.

4 S. ADMINISTRATIVE _ PROCEDURES. CONDITIONS, AND LIhTTATI0t$ PAGE ~0 3

GUE5 TION 8.04 , (1.00)

Technical 3pecificati'ans require two RHR l o c rs t to be OPERABLE durtn3 cold-shutdown. Certain equipment may be substituted for one of the RHP loops.

4 hich condition below will satisfy this substitution requirement 5

3. Four filled RC5 loops with two 5/Gs 107 leveliWidei

b. Four filled RC3 loops with one SI comp 3 r.d Rugi 5 0 *. level i :. Four filled RCE loops with tuc OPERABLE RCF s and one OPEFt,BLE AFW F ores wi th CST levet _ v !.

d. Four fillerj RC5 loops with one OPERABLE RCF ano one SI pump ,

GUE5 TION G .0i :1.50)

Indicate whe t.h e r slarms :. n the vertic31 boards litted below ire t-he responsibility :. f the Unit i Ealance : f r i s r,t 06F) operator, Unit : BGP cr'S3th GOPs.

r d *N* b bR

, o C s : n -] _1-: w e r - :in G L O D ,, T Q ,i 3 ..

, 0' './ - f' N o r*

{-d-25 (*1et037 - 12 310 I I 'EnVIi 7n G 13niLOrin3

i!E ] 'IC tJ 3.** , {.'1

. ., . - 'PcE :r i t. t- f .1 ; , 2 , : .

! : ~3

- : _ w w r, . + ,- e- by Ta: ni 3- ::ec: 1 . , - .: DiOF ~C M t.E 3 * ., IE1. 1- the *Ic 4

+hii *+7 L F.,0 ? 3 e n : .a?' I 'i 7 7 , s - .bOF~E6BLE.

t /t d r :orNeillsnce e *iLrement3 ' 71 "32f

, 11 ' .E' *

i i. I li s e -? .

i s t ' 'if

C l C T 2 1V C O n p l e t e '. W i t h 3. - th? PF0F_' i . .i . ITEDd<

m e g a s. e e4 e pI-. + M * .- ~ Gn177 E.-e tcr ~ip c * ' 7 ' 3' .. 2't73? I t '. t_ O 1

I ' 2 I T, i ~

-f'iC+ $sF .CJ, 3

}

% .' 4 %1 fe Yfb r ' * , f5 h h I kl 'I t

h] T%%%%

i J

i i

i

, .-.,m, - - - -

~

3. ADMINI3TRATIVE PROCEDURE 3 2 0rJDITI0rls . AND LIM ~TATIONS PAGE 1

. QUESTION S.07 - (2.00)

Indicate WHETHER cr !!0T the fc11 cuing conditiar.s ;EGUIFE ths+, the plant be in Hot 5t ar.dbv within orie noor.

a.. In Mode 1 with ene' cold l e.3 _in j ec t ion valve failed in tha closed, position.

b. In Mcde I with UHI 3.: c u m v 1 3 +. r st 13 ) gm 'a c r e r,

c. 9 1r-g e x c ae coc.

An Mode

c. 1 witu E, t d pr e s s ur e

< - psig.

d. In ricde i sithcot 3rLacrv ; 4 n t .; i n m e n t, into3ri t .

t.4 . s,.,s.-.

-GUE,. Ori :. 9 :.

natch the f o l10 win 3 c e s c t c. -

trtw- 2ttF the car.dttien esch is designeo 4 -

r. o prctect s .: s i ri s '. .

FEACTOR ~RIF ACCIDENT-rewar sa:ursions o,uring

a. werpewer te:+t - i.

1.; u sewer operation u, -

,ni .37-tha.,; D;,e n I r,31E 4

b. l 3.- -lir ., L o ri s . O ; rOQ drop

~

1 I ,1 t.- 1 61 = b. ef9 )4 h e 'I'h

I ') Yh4 . 'h bhUbib}

v?q

, u .- - ;* _ : ;;+ -

i

.. I c e ll .

p ; t i re.:

J $ h

~

F, fGu?r P 57 3e IO;i t i' s i

fi l"C.lles tGG "lUtti'

-- 3, J l 41 t s*, C r a i 41 ~~ r n *.

ar _'.!ICIi C .- *. d 1 t l o r. ?,

E. -'

f1k/ *

r (S;:

r. *

I i;2 OVE E *IOi< E . I '. ~l

~ ' ' + ' '

'5 6

-n 'he '

4;.'3 ,- : '

,~..- '. ;, e, A * -

L t 10 T. I.11i' I ~. " 1 J i,t r E #1 N; I 3.5

. n , ,,... j .

, .j 8 lr *9 _

s. ~P cu3n c:t I' C F ' ' t- r~~ ~

S. F cm RCG in*: ta 4 y- + '

- 4 -

[. #

I C ris I,I II P, It $ we Ie 1'~5 l , 9

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4 e bO FR w -.

.1.~

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, '. * ? * ' . ,,

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g- *k ,9 i, ; " l* . - y-

, r-e i e**rr C l * ~ ~, 7 ; ^ *^ fl ~ ! r.' U [ O 9 fi rJ[ ' ? ? * ~, E s t et

O .

b I

l

3. ADMINISTR ATI'!E PROCEDURES . C0r20ITION S . AND LIMITATION 3 PAGE 2-

a--------------

QUESTION 3.10 . (1.00)

Complete the following statements concerning refueling operations by filling in_the c o r t; e c t number.

3) At least ______

feet of water shall be msintained over the top of irradiated fuel assemblies seated in the storage racks.

b) Prict to movement of tersdiated fuel in the reactor pressure vessel the reactor shall have been s ub e r i t i c'a l for at lesst _ _ _ _ _ _

hours.

GUE3 TION 8.11 41.00:

Fill in the bisnks to compl+te the fcilewing statement regarding temporarv siterations:

The Shift Engineer reviews requests to perr?rs. temporary siterations for completeness a rid :a* e:tness. verifles it has been reviewed by

_____ 3 r. d 3 p p r o v e ri .

_ _ _ . , _ snd that 5 ./ a n _____ is attached as r equir ed. H r. als: c e r f a e n.s _____

or e m e.r g e n c y conditions requialns temcorvr. siteratton1 QUESTION 5.1" t1.00 If a tellou Ccotrolled Ccry' :f an instracticn .s NOT svsilable ka a e r f o r t.

3 task ano the n?intcntncc- scneauling ofiira ti "DT.3 tiffed. what must ce done.ior 4 . o r L .a r *: act . .

s * : c n t.c c 1 1 e d : c :: . '

OUE57 ION B.13 ..5 Accorcing to IGNF AI-I. anst thr.;e perscnnel ibw. *1*.-le'

3n relt <- De i i '. H I I '~

"hi't Engineer :f 11: 1 1 C e n 10 '. fOnct10nia : J t i r4 3 Ih't +3v0 I 11cer s e I

(,#,J, L- *. ... .J UI D. A 7 3 . ~J

0 k 1s t O 4 O C t I i t2 L * *Or 1 8

[n} I?'2*7f..- "

3 t ', (8f F 1 /P U 1 i f;'

,' tn{

inP W3h his r e p t e E G r; t ; t i v e s . a1;t t9 Evt:S*.;; ; * ., 'O J re l l t .

IE anc s. a j issee c l e s t a i n; ; .

ntsaz ^ ?, ~ E j ' ** '( j [ ' v J T [ 9 ' ~ .'". N *!"'

# ', ais;

5. ADMINISTRATIVE PROCEDURE 5, CONDITION 5 ANE-LIMITATION 5' FAGE 23 GUESTION 5.15 (1.00)

Fill in-the' blanks in the following statement regaroing cles~rances:

When tagging a brester open that gives.an slarm. if it is to ce open for grester than _____. the electric 13ns shall lift the wires'to the annunciator-snd initial tne clestance s'eet. n The A5E will _____ the

_____ with a _____. When the cle=rance is eleaseo the electricians will connect the annuric i z t cr wro3 e n ri _____

tt on the return tc normsl iacticn ;f the :learsoce theet.

GUEETION 5.16 '1.00>

2 '+ ~4herei' rom whom c:n ' o .- s ter c e n t 2 i n m e r. t =ccess be :btained? *:0.75) b) c ri r to entry intc the-Icuer c on t a i na,e r t , on what :omponent must the 3E initists s :'o l t o r d e r clasesnec7 (0.25)

Oa.. t., - . , . u h, * ,.-.

t 1 . O V ,.

IJCini:Il Specif :stion 3/4.2,5- ONE F s r s ra e t e r = , gives limita'for t .- c. . D N E, t e l s t a r_ F Ir acete : Nt if the;e two par 2 meters?

. T*f.,

~ . c.c L

e; ort /; ,- -+

C ): - .e* 'y i o c '. t a m ; g. , [ , .3 ; . e, t ', , - . q S e i r i n -) rJU t Ln.

'G?Iing O i ;3r-;

,ti hE_ ?c :.ir t d r O .: e r t 1 s :( 5e? f: ,i, *. V C 1 e -S i PQ e* P12nt.

~hoo34 the c]* :Ivie :( 'o!_ 9 t- c b l e a t :s e' nae + vr ninad r anat are .1 e-potential Oroblemi 4= tori: ted uit: - t: 31nt .. .-* '

. l .i r e 7 O U E 3 7.~.I rl 6.I9 '! 1 Wh5' 3r e 6he t ! .' 2 r 3 r ; e q .. ; t : > . i J L;c ti)q f31i;ginj ccqtrol

. 3 , i t e rh 3 Ci.49t l de m '; ; n ' I i n , - #1, .

. . E n' - i . 't.;'

i 1 r. ' '

. :- : C r. 'l l t i n n i' 1; Ar4530 i ;. 9 c ,s

-- ,e E r e ' i '_ ' . 9' 1r ;}

- s13 l' ' S t e 3 Ni C o rs e ? S t o r 10 ~.> e 1 s 1.* t : [A*ECQC f' ~. 1 [ONTINOED "1

: * " f_ 4GE *as*

l L . .

l I

i-l 5. ADMINISTRATIVE PROCEDURE 5, CONDITIONS. At4D LInITATIONS~ PAGE 24 I

I

QUESTION B.20 . (1.50) i I List the FIVE bases for the tiinimum temperature for. criticality

!' limit of- the Techreical Specifications.

t I

l GUE3 TION G.21 (i.00) l he

- n s systemr subsystem.

r :- i n , cca.?onent ar device is de t e r ra i n e d to be

! INOFERAE.LE SOLELY becsuse i t. s emer3cncy power source is INOPERABLE, OR t 3OLELY because i ts n o r rr. .s l p o w e r source is INOFERAELE, il 9sy be considered OPERABLE _for the purpose of s a t i s f y in;3 the requirements of its applicable limi tin:3 c ondi t icn for : P e r a r. t c h e ;s r o v i de d twc :onditiens sre met. ist thess TWG ccnditions.

GUE 3 TI0 rl 3.2 '( . S i l'. i l e in Mode 2 .;nder 9 HAT C3NDITIONS

. T. 4 y that Unit's Assistant Shift Engineer (A5E' lene the contrul raam FOR WHAT REA50N51 GUE37 ION 3.23 '

1.00 4 hat 1, the facte ui:' Nrction cf snc what . +a it acccont fer as it I?F iles tb t he hast flus nat :hannel fa;+:. r ., s determinettoni c lE 3 [IOf! !.14 l 7

l '4 h a t 51 9 r'.e bssor - *

,- .;>, t; acon u r s g .. c st:.aje ilmtts-l N

u f *"

C.7- *. * -.s.. J 9T te' e n . ...a il ist t l' *: 3 ' 33 w i'. t s * :Pe ~^quiPed by I 4 c .- 4 *- t; h3sq c p e r t h l .3

. 6<. *I

,V, ' ' , . iyAni. 6 .

! N- : I. 9 . ' t .' " 3 3 " .!

4 it 8 i*9Q 4i f. d I A [ * " ej i *[ C r, a QY ' 4 -- 3 j j ( .3,?, 3 ,,g e r n 4 .

uw . 'i (* . 7.s

.- x . . - ,t : : y, es. . :- * ,e .. i i

i 1

(8$$$1 [ A I E ', i[i % 'f ') .3 I, C fj Y ! rilj [O (*j i'l (J 3 'Y I C .', e*j E 6 TAB *i

r, -

S. ADMINISTRATIVE PROCEDURE 5 CONDITION 5, AND LIh!TATI0ii5 PAGE 25 QUESTIOtJ 8.26 , ( .50$

uhy must a nitrogen blsnket be provided in the pressuricer and reactor vessel head during the earlv stages of a reactor coolant drain-operation?

GUESTION S.27 (1.00)

What'are the bases for the.fclicwing precautions associated with the UHI.

System:

s) Do not allow the Nitro 3en pressure to increase abo,e the hi3h alsrm setpoint.

b) When testing the hydraulic isoistian /31,e3 in the AUTO mode. ci sce' a wood block'under the hvdrault acevcoletor.

t <esa I st .r G Ic r, - i. i

(+ t s:e r e s *

s e E P C. OF E ant 94i~ stettes**etests)

r

?

[ .,

I l

i l -3. THEORY OF.HUCLEAR POWER PLANT GPERATION, FLUICS, AND PAGE 26

! THERMODYNAMICS ANSWERS -- SEQUOYAH 1&2 -35/11/12-0EAN, WH ANSWER 5.01 (1.00) d REFERENCE Westin3h ouse Resctor Physics, Section I-5, MTC snd Power Defect DPC, Fundamentals of Nuclear Paa: tor Engineering 039/000; A2.05(3.3/3.6) t ANSWEP 5.02 (1.50) s) Deeresse (+.5 ess b) Decrease I

l c) Increase I REFERENCE Muclear Fower Plsnt Operster Trng Fegrm. HTFF snd T h e r ni o . Sect ZZ App A* Fumps/ Centrifugal. P u n. p cPtracter tatic relationships (2.o/2.i) i

! Ad5WER 5.03 ' : . 0 -) -

.' .ity-

1) Hiqner .

T w .: iner xw:

-Oc- +c. *: e r+3ct l

l 's lower ' . > - :ic ' e w s *. e e t

=adt.teni

. T s v 3 r2 = : r .i i s e -

! 3 M :' ef'?!t Ji 41gner (Xenca .: c n c e n . c s t t c c tor. esses sdding negatt.e res:tivttv)

PUEEEUCE

t,' 1 ij o ; }. ,j n i 6 [{

u,. .g0..

, . 01 p. s

,. e . ' ..' s, . _ . .-.. 8 t ._ - ..

. a -+ . 1 I '

4 3 c ,5 b c) De:resse '..~ t.- :

b- Ir c r e .; ; e i :) 1r;ct'.?3s&

di Inc'asse

/

{

l t

r 1 .

I t

i

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE ;7 THERMODYNAMICS ANSWERS -- SEGUOYAH 1&Z -G5/11/12-DEAN, W n REFERENCE SON /WBN License Recual Training, ' Core Poisons' 001/000 K5.09 (3.5/3.7) ! K5.02 ( 2. i '3. 0 ) & K5.10 (3.9/4.li ANSWER 5.05 (1.00)

Heat source- downstream (+.5 es)

Hest sink- upstream REFEFENCE Nuclear Power Plant Operster Trsining Program, iTFF snc Thermoi lect E App A: . pumps /centrifu3al, NP5H (3.4.-I.33 ANSWER 5.06 2.00)

1) CentroL recs within

cr 13 s t e r- 5 of 3ravp cemand position .+.5 esi 2)~ Proper sequencing ano over1.3p of rao gr cup 3

3) Contral rod i n s e r *, t : n limits ire n. s t n t. a i n e d

4) AFD is osintsined within l i ci s t :

FEFERENCE 5d 75 E 3 '4 ~.-

1 , n, ,, n s n. , ;-.se . e ; a . ,:. ,f n . 2 .;.. r . - . r ..:

/iN E W E F ~ 5.07 ( .50' Optimtm po;nt wculd in o . , 3cwn snd to

ie left ~ * .

,5:

REFE;ENCE 5an/uEN License Cert T r rc3 , "Rescttvi?. Caefftcient

004.'000; i:5.15 (L.: .5>

1.0 .

1 I

_ 4 F

.s -

P -

uI ova 1

l .

guf

. B .- l .. N l .x un0Et OMA \

l N%N Pxf I

I I

1 4 - f (w;A boren)

J

. c __

i i t ' ' '

V(m) 3, w. ,.. .. g i ... . g 1 3 % 5 V ( ri

5. THEORY OF NUCLEAR POWER PLANT OPERATIOil, FLUIDS, AND PAGE 23 THERMODYNAMICS Ar4SWERS -- SEGUDYAH'1&2 -85/11/12-DEAN, W n ANSWER 5.08 (1.50)

1) At EOL/ Low temp, Pu-240 buildup snd increases the number of resonance peaks (+.50)

2) At EOL/High temp, the Pu-240 buildup is cconterscted 6 ,- the effects or clad creep and pellet e:pansion incre2-ing tha thermal conductivity cf scross the fuel rod gap hence the v uel is at s l o w.7 r temperature far a given RCE semperatore. i+1.0i REFERENCE IGN,'9BN License Cert Trng, 'Rescttvity Coefficients'. pp '/S 001 000; K5.4B (3.3/3.5)

ANSWER 5.07 (1.50)

Nomins1 tensile stress (+.5' Tenperstore below RTndt t+.5)

Sufficient sized surface cefert .5' REFERENCE 50:4 T5 B 3/4.4.

0 -) 2 00 k ! . f ri .J.; 3,:

Alf 59Er e 3 .1 'l 1.50 j]- 51 %,

d-I35 Ar. pro. M *.25 tcr t a c t c re e . c. ~ for antt. tti n te power -

l '.

~

I U -* 2 'I '

M -. %-4/g.%

v._. -.-

RE ?REtJCE 3 G .o -EN Lics,- le:

Trng. 'c osctcr inet;c:'. n-

., ' k/ ' ..g Y 4 h' s N

3. THEORY.0F NUCLEAR POWER FLANT GPERATION. FLUIDS, AND FAGE ;;

ANSWERS -- SEGUOYAH 1&2 -G5/11/12-0EAN.-W i AN5WER 5.11 (1.00)

~The xenon dip would be Isr 3ei :+.5)~snc cccur later :+.5' REFERENCE

'5GN/WBN Inst. Guice ' Review of Care Poisons'- p 5/5 Westinghouse Nuclest Trsining Operattons- pp I-5.'s 001/000; K5.33 (3.5/J.1)

. ~.

r,. H.:, ,A t F e..-

a a '..uu?

re;nove boric scia 'hst is srectpitsted an .spper : ore surfsces (*.5) terminate any bsilir,9 or s t e s n. 'ormation in upper nead region ~+.5)

EF E.;; EN C E Westinghouse Puf ~ . = t e.m s n sr vai r :p 4.Z-:7 EFE-Oll: EE3.1? i 3.3'4.

A H 3'J ER 5.13 .!.C. '

A l l r, s far r i s.e + c x : e n t . r' , - -. d c:r-- - s droppe; c. T. t s s l i :3ned rod $1.3) 7 7 7. 7.;. . -l' t. r E M -M e . n aJ . -. ..~

p t_ p. . ., T >*

L b" . f-w i. .* . - i, . . : '

A .N E ' i t. :' : [4 / l . 3 0 l'

.5c-Ec 5:v7 ce .5 When 32-123 is 2:tt.itec bv e teutron t' 9taa.:ss 4 J+mos .251 'cet unt&T3Cti .J i t .' Er 7 t +.25) that p r OduC . : Ee-L Ir sn3tha- f.e u t r e r.

15 PEFERENCE 3GNfuDN L i c e n s e i: .c r t t f i c 2 t t : c - c e t c. i n j . ' r ' .p i t r c n E a.i r c ; , 2nd Suc<crt ri u 1 & '

wv.e.pe

,t /. a r .

L', s,-

. pJ J r v .s - - ..--.:a.8

~-

5. THEORY OF NUCLEAR POWEP PLAr1T OPERATION, FLUIDS. A r!D PAGE 30 THERMODYNAMIC 3 ANSWERS -- 3EQUOYAH 1&2 -85/11/12-DEAN, W n e

ANSWER 5.15 11.50) <

1) Delayed neutrons born at lower _nerjiese so less likely to leat out providing a positive effec + . '" 5 )

Ei Delayei neutrons are b . st an svers3e' energy too low to cause fast fission which prov i es a negative effect (+.~5)

REFERENCE SON / WB r1 Li se Cert Teng. ' Neutron V inetics' 001,~:v; K5.47 (2.9/2.4i ANSWER 5.16 11.Z5)

1) As the fuel ourns out. less coron is required, which increases the ooron worth (v.5) Tios n h m>Ro b t

h**& (+-M )

) Pission prcoucts build up. accressin3 the acron worth (~.5)4P. 1: t-h-- 1 12.7 j t'* f-fv0 tv- -H . 2 5 7 REFERENCE 3 G r1/ 'J E; N License Cert Trnj. *:cre 'aisons'. oc 4

' C 4 M 0 0 : K5.06 ~3.~~3.37 A rL3 W E.: 5 . 1. 1.Cs Cue 'o

. the jrest+r a e c t e 5 5.s in tae t e w p s r. o - :i F'. _:;ts..t .:tting *ae .

OOr. Tel5t1Ye t" l6e Ci d r .s s 3 e Of tr e 1 r.1 '~ l . . * +.5- t'. G r i positive

" esc'.il f) 's i l l _ided >p.~ J' 9' 'tInj :a G T -

4 h t ; i *- ' ~f t?' ,

.- e-

[- o 3 1 6s.. ' 9 #- iA L' ) s *i } [ 5 1* *s 1 r L'

~7~~lENCE 6: _ j . . o i. e . .. . T r 31: r jG; .s r t :n , - .

.. .' I . . , ,y s ,,.-- .

) .

5. THEORY OF. NUCLEAR-POWER PLANT GPERATION, FLUIDS. AND PAGE 31-THERMODYNAMICS ANSWERS ---SEGUOYAH.112 -85.'11/12-DEAN, W ri ANSWER 5.18 -( 1. 0 0 )

a) _ Ratio of Critical Heat Flux ta Loesl H e a t F l u:.. (+.5 ea) b) BTU /lbm-des Ftor Rt REFERENCE Nuclest Power Plant Omerstor Trsintag Frogram. 'HTFF snd Thermo' 001/000; K5.45 (2.4/2.oi 6 ES.46 : 3,3.si ANSWER 5.17 (1.50) ,

-see attached curve 1/ First devistion is tc sccount for the fact taat the'opper core region is uncovered first and refillea last an a LOCA. (+.5)

) the second desistian is due to the resistsnce encountered in refilling the cor e follauing a s6s11 d e c- a i L3CA. . 5:

REFE ENCE 3GN IS 3 / J . .~ . T. E d 3GN CIAC Ch 15

.n r ,,.e.~.

n1 .- .. . ._ _ . ,>.

A33 HEE 5.20 1,'"

5ea stts:hed : u r .- e RE.EFENCE duc.esr t auer Plant G r- e r T n 3 c 'r j n . HirF :. ~ ~ c r .w e . r igore 13 pp 2R 002/000; F5.:1 5.1 ,.;

1 With the' first " tweak" of the heat cr. trol knob, the partial vapor blanket spreads ever the entire pen surface. We then find a thin layer of steam every- ,

where on the paa surface. As shown in a previous table of the==al cond tetivi-ties, steam is an excellent INSI::.ATOR; hence, the paa surface now presents an estremely large resistance to heat transfer. Assuming again that the electric heater can BAINTAIN the desired heat fluz, we know from the equation; .

~

k/A =

U(Tsurf ' TMg}

is constant ,

that if 6/A is then T, mustheld constant increase andsubstantiany rather U decreases (ondrasticany the order and of-* T,,N00*T). ,

If the paa surface had been a fuel rod in the reactor core and we anowed fun film boiling to take place, the metal of the fuel rod mish have melted er been seriously deformed or cracked. Radioactivity would then leak from the damaged

. rod into the coolant with severe ramifications. DNB, transition boillag, and full film boiling are EETER permitted in an operating reactor ander ordinary conditions. ,

Now, we should make a plot of the results of our simple expe_-$ ment. If the heat fluz is plotted against the temperature difference between the paa sur-face and liquid temperature, a figure'similar to the one below is obtained. .

10 '

C -

s D

5 G

\*F 10 i ,

a

.3 w .

3

.I I

$ 10 4

.o ,

8 A-B N ATUR AL CONVICTICN 8 -C, Nu LEATI s e c.ms F D E rit u notLtu s I

C-F RAxsm0N sci!.mg l

A G= DNS l 3 i 10 l # 3

. 10 IC 10 10 '

aT (Tsw.e. .Tset )

F

. . TIC":RI 18 30 C G WA*T2 N . ,

4 102

5. THEORf 0F NUCLEAR F0HER PLANT OPER ATIJN. FLUID 3r A '! D PAGE 3 T HERn0 DYN AriICS ANSWERS -- SEQUDYAH 112 -55/11/12-DEAN. W H ANSWER 5.21 : 1.50~-

for 0 ,s sssem, lies, 1 c. .rt= . 3 , 1

( + . - ,a .

1o r . v - 1 v. assemolies, 1/n=.*44 e

..se for-0-15 sssemblies. 1/M=.34G: ' + , 2 5 :> far 10 -15 sisemblies, l'h=. 17.

aee s t t a : n.ed gr yh tcr curv+s

. - ,s ;

FEFERENCE rJ ls,, r ,,c 1 a. Units . . - ..

. .a 5GN/9EN License Cer*,1ficstion 7 to3r

%utron i.:urcs: snd Svoerittcal nia l t '

n(, is- (3 n

,A V >' e- .-

v' de 1 w; - .7- : Oe e-w*

, ** *a -

MaQ*

- g e T D g ra *. C f'. w a w . . e . ) ')

fOT 2250 &CiE* C- S i t i, m ? ': $$2 '* .5*

~

W1th 7 3 'i g = 5~5

^

Th = *-

T - ];,3 + /- [ -]~ces in act.ermining Th

- . . h. 8u-a *..~f s hb 5 a s .

' ~ ~

Q Q ~. Q Cr (

l _ 1.

. * . . _ _ ~ . . ,

A *:^ s ... l L ri s r g i r, t3 7i ^ tc9I1 f. . - r r.z.s+- b- Z, [ r+1,O

#*^C'.~-

7 1

O , '- 'P fJ l l ,. . hf b

"+ $ l4 l t [ 9 fi gl s* .

,.- g.

v ,,;,.

1

. ~ ,,

- - - -4 + s ,

s

2. PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUhENTATION . PAGE 33 Ard5WER S -- SEQUDYAH 1&2 -35.'11'iz-DEp . u n ANSWER 6.01 (1.00:'

C REFERENCE

J A NCRODF 33.1 'CC5-F:n and cress Rclief' 50NF TE E? 4 4-:

)t0 c'0: C W ': - T ( : , - ~2 . 1 1 usurp 6,0- (1.00, b or L R EF E RE rJ C E

' G r4 F 3 -> s t e ra Oescrit. ' Electrics 1 D i s t. - i b v ?, i o n " -p L3 ':0 664000* l'4.1C # I4.11 t, 3 . 3 e a,O+

t l . o, u. r

,4 6. , . ._ _:3 :.u; E

p -- . , .

C ' b U I. *** * . L. p 3 l *1 F , - r. :. - : c t-

- 8 5- 8 ,

't

-i r e , 3 r. --

--i - [' - w t , , 3 4 ^

"., jr .'. *,

I .*

w A .";

.& . + w je , p s ~: - .

[ ?*1 I ~ - '." - * ,

i *, &

I

-+v?' .

s c e - . .i.. e

"~.'*:.~~".

. P. t E i .~ e ' i: *

3E9i'e ~ U Gi p 3 / i t, 91 ' * ? ,'. : I' .' 3 3 ~ ~ ' i ' + rt. - ' s c r i ,0 '

itean f' u m : 1 3stn'- ;; : - .

j ,k ' , _... +

t

-t ,.g.

g

,,,p C .)6 6

, * , , " , . ._

r -

'*A a ~!

b' t

T 5 e

> e ? -I

e 1

6. PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE 34 ANSWERS -- SEGUOfAH id2 -05/11/12-DEAN, W h ANSWER 6.05 (1.50) a) Open (+.5 ea) b) Open c) Closed FEFERENCE NA NCRODP 88.3 'CVCS' 50NP AOI-10A, pp 3-5 078/000; K3.02(3.4/3.6)

ANSWER 6.06 1. TJ b -

l Low Lube Oil Pressure (+.:5 es)

) Hi.jh C r an' : s se Pr es sur e

3) Phase E: a l ; n c e Relay 4Y Feverse Power Relay

5) Loss of Field Felav

_ p 3ger , - - 1

') Hijb Jaclet Mster Temper stur e SEFEFENCE r; A dCPODF E0.4 'EDG' 3DNP Stasel Generitcr H i n c.: .

sp :

t.. .

J o n, .- v .w ,. . . . .t....a.,. -

4. .

ANSUER i.07 I1.50>

s 1 : ". - p t : rs s r >

colant i+.:5 .r a r e s;ar e os E 1.m d o w r. 1 i n .i f r e ni .coling t.:ue r s : 1 t r' r u s e r none : t f t' u s e r ptpes.

r1.er '+ _5 si

EFEFENCE 3GdF ,3 De+t t.: .:, ' iv t t e , % , t g r. sro. G rw , 4' o'Ltau c u : t t. .. i np 4.!:

0:.i. 090; PWC -- ~

. 1. I, l . ! f 4. il a 2.4 1.1

6. PL ANT SYSTEri5 DESIGN, CONTROL. AND INSTRUMErJTATIOil PAGE 25 AM5WERS -- SEGUOYAH 1a2 -35/11/1 -OEAN, Wd ANSWER 6.08 (1.25)

SLc a) & de3 F (+.25) e r >*ml"W b) Inhibit H2 leaka3eVwhich may aire 3o ia the esive seat ' + . 5 '-

c) Delts P between the RCP dischar3e and the PIE - +.55 REFERENCE 30NP PLS pp J:; 3GNP Lesscn F 1 :, n '

5':I'. cp :~ 3 L.L . L' ~ '.: ..

01 U, r, VJQ. k b . 'J .:. (

t .r . . .2 0 .' C. ...: . .~r

A rJ 5 W E:. 6.0- i.1.25-s- ci a n i p o ; a t o r crane; i. : r'.:tiater crsn- 3rtpcer *itc.

"ully retractea; O 'a e r in5 :Cre *

~* . 5 ei i b) cath 3rtp er tube :- 2 siticn suttches .Z

.EFERENCE

.0, ' W ,1 ' ' ~

IGNP Svs Descrtp. " nc!:n3 i sto1 Q 3 4 , S ~e O ; 6 I [' ' [ . 5 ' ! . 3 '.

2.d3WE; 6.t .

; n > ; ; - , ,1 2 n

u: .-

a: ' i 0 I , i .' - 1 '

.nT' '

"I.

% C ** ~ C' h ,' F S e m . me S S ' s 4

.'*.* r '; '. .

_I l

m e ..

4

+ e ,

,. .d f 'g I & .-

_as r - 1-

- - - ' C ?, { , [ "

& f ~$ '

k I

I I

l l

l

5-. PlailT 3YSTEM3 OESIGN, CONTFOLr AND INSTRUnEr1 TAT G4 FAGE 23 ANSWERS -- 3E000YAH 1&2 -35./11'il-OEAN. W h 012/000; K4.06 ( 3 . ,2 / 3 . 5 )

AN3WER 5.12 (1.00' E m e r g e n c y _ w m p': " Containment 3p r :, J mip s : >Contsinrcont Sprs/ Ht E,;ch3rs, Containment spr n rJ o t:l e s : >U?r:- Cantsinment C : m ;: v t m e n t :. :Z Drains in the Emergency 3. m p *: + .15 eri bottom of the Cefuelin3 itr;l '. w e r ' omp ar toent' .

n., r e pmenet

- u rt F .: -t vescrtp,

-1 .1_

sont 2 pts. ^.s,

_: ;- ,1

, 3

.- _.-. ., 1

_: ..se, l ..,. v- .i ',. . . . .2 4 ANSWEF 6.12 (1.50' g,3 pr m)

Ch33e A C c n t a i r. m e n t Iac13' :n signal v rcr ei th 3r Unit L' 5 =i

-High Rse;;ation sijnsi f r a a, feel m ar 211 rig bi rig ar ea tsd monitors A. : Eld 2 ~

t h .= ..i t t .ent rad monitor:

- Mk Teme in av,qu3 sopn3 Fc (s . tr e -

R EF Ec: ENC E 30Nr T.s Cescr. A,1. ;.t Air ?;rt- :nd Cleanup I'e s ' mp 15 E:E-Osc: PWG-ic :.; ' , ,

an5u?~ >. = ' ~~ -'l so

e. H. .i - H. !

.. . . in so, . . _

IT - t an 2 * .

5eGCtbr trip 4L t: 1: T ' U -] '5 5 A . -t j i

b- E.oth riF r ti i: i+.Z5 es

,F4?V :nd 7; / p s s w s = ho r

+. . - . , .

- 7 .-

Fi:ed atar 1.! c l 3 t i o n er clore g,. h- '.O. V.

- _c. j le 3 0 /JI LCs10n II-i ' tT o r. .: e r. i: : *. e and F i a d u s '. e * .;. .'. .o 10 255'000; t: 4 . t i :.2 li

6. PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION FAGE 27 ANSWERS -- SEQUDYAH 1&2 -85/11/12-DEAN, W ct ANSWER 6.15 (A.25)

-Return lines from RHR loop (3I lines) (+.25 es)

-PZR surge liner both ends

-PZR sprav into PZR

-Ch3 line connection

-Ava chs line connection REFERENCE 5GrtP Lesson F1sn 'RC5'r op 34/35 002/000: V1.06 (3.7'4.01 & K1.02 (4.5'4.6) f F 1. 0 ~' e 4.1.J4.1) -

ANSWER 4.'a. (1.00)

RW5' Lo L Wel ('C%' and Con *,ainment Sump i. 3 v e l 1 ' *. s + .5)

C o ri t a i n m e n t Gump ') l v .e s (FC'!-s3 ~2 i-73) and FWST to RHF s u c t i on ( FC'/-7 4 - 3 2

-21. >+0.5)

REFEF EtJC E E O r!F 15 1.2, pp 3

.i , . i . c,, ; 6;.n- w (.. . .- ..-

t y e

-1 1*.! ,tt day:c+t ha.t f . . a o r- r -

nor r. 31 sol (2ge i+. ? 22 6

- ti d n

t r fwt.Ch IIA t ri 4 i) T C us. r

+I iO M5I # d I.' 6

, *C

, . e I [ f.I r r e ri k

- ~r 1 t- w. ~~~.~"6. " b C" 3 Il fl f' '$d/[4Q

f 316[*r[;I[ ) 13 ( I i j Q f 1 C(, ' .[ ]

f 6

w e' .h

, o-

6. PLANT SYSTEMS DESIGN. CONTROL', AND INSTRUMENTATION FAGE 3G AtlSWERS -- SEQUOYAH 112 -G5/11/12-DEAN, 4 rt M45WER 6.18 (2.00)

1) To upper hesd plenum i :. 3 holes tn :cre barrel f 1 : n.3 e (.5 es)

2) Between hot l e '3 discharge nor:les and upper care t,arrel outlets

3) Between baffle pistes ind ccre barrel

4) Around inserts in guide taimble tobes in the fvel assemb1:es REFES,ENCE MA NCRODP 39.1, 'FC3-Reacter ?cssel/ Core Ccrstr.ctien'

'J e s t i n g ho u s e PWF Systems t1 a n u s ; 'FCE*- 7- 7 :.1-3:

002/000; K6.L3(2.2': 3)

ANSWER s .1 :- a' 1.0'>

"So air cylinder sctusting - - ir t /s 3 .1 s r ' 1 ; t c h i n'3 '

injer- :re spring losded (+.5) : Un : n 3 them to lo:6 r trt c. e < t i s t c c. osition ' + .5' c.e-u r E n c_ ,r_-

.lne IGMF FHI-10 77 :

034,,a.; V: ^: :.1 :

. . :o turuEF ,

-,;;;g r ' ' - * *

?: 1" _ a ,' i

~

I ' O . ri _ .- #. .2 .. 4 aL-~'*

.J:nk I4 E . . . ._ : .

T w: :+:2t . . 'r -

.. . '. m . r. x ar it

,. ( I [ 5 ( * ','

- -4 . . - -

. s.

- e w g*

+ =

- ,=

. . L n, ti T a ( e2 . g n .: u: :i. . ,. G . f r ...

. a . ri s, o ri ,.e eriaTt.,upnc.Nins

,.r.;

.or ..o.

-s c --

s ______________________________ ______ ___ _______ ___

A N 3 '.J E E 3 - SEQUOYAH 112 -53/11<12-CE.W. 'J i n t,. . . i-7_ .;r. 3. 1 .._,e, The .11ghest reading upper,ic-or detectcr ir :o.T.psroo to the aversje cf the

. upper /lcwer detector si * !) ind gener ate 1 an alsrm at i.C: i n : r e a s l o g t' + . .' 5 : .

The cir.vi't +uto defests-below 50'. 3ower en ALL chanricts I..5)

REFERENCE 5.IN o Cystao C'escrip. ' E.: c - e JI?', N. t~

m. ,. , ..C,C,e.

.- ~. k. o . u. 2

..u.......: ., ,

I,. ... .. . +

A N 5 4 E ~: c.: (1.00~

.e>

, e .- i. .#

t. A ,,

m h e r r c, ,. 4 s tsi,ea t high ' + . ; .+

FEFE ENCi

't+ a *. t r.3he u s e 'J F ' v s t e n. 3 1 ' P r i ni s r .- httam Control'. r. p !;-14

~isc.

L ;s . e. ., 3 . ,* ..?._ + ;.

...s,..-.,t,,. 3 . -._4

~~a REFERENCE GGNc GGI-2 pp t!~~

~~001 10: A ; . T' ; , :. .- ;.:~~

~~1 ;,N su gF , 0 .: '~~

F

~~!. E3NT E-:~~

~~C- , , a~~
~~. t ,?s 9 ; a~~
e
- - . . 4. ,. .; & - .
4 A
. PROCEDURES . NORMAL, AENORMAL, EMERGENC) AND FAGE 41

~~~~~~~---~~~-----~~

~~~~5d616L351CIE 55TiiE5L Ar45WERS -- S E Q U O Y M.I 112 -85/11/12-DEAN, W d ANSWER 7.05 (1.004 c
REFERENCE 10CFR20.5 FWG-15: 10 CFR~0 Knowled3e ( 3 . 4.' 3 . 0 )
AQSWER 7.06 (1.00) s d e - . m REFERENCE
[ pp tE NU.k 50NP RCL .
p Knowledo3e af fsc1i. 5.: c n 3.4'3.7i n N d W r_. _n
.v- '
. .vu s) Ihutcown ' + 5 ent .
b '- E t a t +. o i n o r. d o w n
~~i ) 5 h u t d o w r, "EFEFEtKE L 0 rd i s I . 4 . c, . :~~
... . .f , ., ,.' : r g r> . 3 .
s .e. j . *. -
Nfj-.j*r . .-
. . . J: A.J'
[* ' '[
, rt, i n e,i * . : ~ '
~~) e, ; m . , * ,, + . [ ~s :.~~
' EIEE EriCE
. m .& h b U 1 I) '020p ENC I (
) . 'J . 4e37
~~7. FROCEDURES - NORMAL, ADNORtiAL, ENERGEriCf AND FAGE 4 .~.~~
RADIOLOGICAL CONTROL ANSWERS -- SEGUOYAtj 1!: -:3 5 ' 11,12 -D E A N . W n AM5HER 7.09 ti.00) 31 5; 10 *: +.25 es respcosei b) 50 c & ^%O F: E r_ E n_ t h. .t., t 30N G0I-3E s n a G O C ':
F4G-7: Limit and e attiani (*,.5'4.0)
ANswEP .!O < .00) a> e.ery Nour '+.5 ea) b turbine clade r e s o n.i n c e s @ tch ccvid ,2, e r ' r e te f a t i j i> e cracking
-) e v e r ;. 12 .our; d) 63 3ouernct v?!/4 /ibretten R EF E F:E N C E
~~(, rl u2-;n,~~
>p
/; .,.. ; a te. --.
.4.1 4. .1.1 ut ,.._. ., .v, ~ ~.
...., .. . . :, < a . c . , .:- a
.. , .s,.
se, F,.-
4 u.
A g g g . .*. . ~.s t
~~s s r" .' + A M ~i ' , ,1 i n g [F 0 FEF'ifENCE Liijit i .- I ~. "' . p ;, ~~~
~
}!* s0L ?WG-3 .' ,2i H i s ;. d *.,_,_t.
. ...c...
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~~.; l , : i'~~
k
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h. * ~ 4 I I'*1 . I u *
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\
I l
l-
. PROCEDURES - NORr1AL. ABNORMAL. EriEF 7E 401 A r1C FAGE 41 i ~~~~EiDiOL551E3t EST4TRBT---~~- -~~~~~~~~~~------
AricWrrs -- SE000YAF.4 11; -55/11 ' t :-DE Arl, W ri 1
l i
~~i. .. . ,-~~
., v )
ANaW.E t .i-s
~~1) Decrease turbine load C+.25 ei e : p e n s e :.~~
l l
Zi '.% r i t y auto rod i n t e r t i a r. O f -
! 3/ ri r o u s i l / inser* rcds to rea i r.
~~5 : n 7:sj at Tref l 4) Oper, r' tr ip or-4er+ r.1 hC -~~
' P::m Av: Elig ~59 I 5' Open Dr.+342r; +e c.antrol ro . *G *: 5t 4 90 sin i t Boards A and B s) Notify Inst t :, close F-4 c a r. t a : t FEFE:ENCE 50 ri; FF-S.I. pp :
E F I - O '": ; FWG-L1 '4.5/4.7)
AN ?.WE F ~.14 (2.00' ai 1) C e n t r i 'mp 1 C h a r 3 t r; j F e ars ' . . ' AHU 3 ERCW Fump 4; : C "3 a n d' E.c a s t e r Fump -
s i
Spve Component Omalin3 E umt 1 AFu rump 4 f essur1:or Hemtet1 31 Fire pump ,+.15 93) bi To clest the diesel 9.:h ; i e t s sod ;eca: :in r :. - 3- a c :: o mu i s t e :
' O n b u 9 t i D i *. a +.I' FEFE ErCC
,Unp -* .U. -a- ,s ,.s * * ' ' s *
)
, i $ $ c Q i! O ; ~'d
> , 1 ) , * .' ~ U,
~~V,,.......~~
t UJJe vs . .Jc .s e .
Se fi'~~ U [ 9 ~,[$ % b
.ou s v r. .
. - . . r. v .
s - <- . ., av, .
.:- n 3 t' ,,r * ; 'P' . ,,'2.,,. ,', s E F- far i lD 4-.5 ,( , ti ' a ; r. ?.r .
'*-.t 1 - :dv :I .. .
- to De i v 2. 6 r 3
-"5i. r . i t ,. ;3s* .t* w,*h ~~ ir 6 in! D 1 i's * . gr3 i 7 . -1 in'#IG~ 4 , , - ,
13J
~ *
- P s f/l S r :b I-I-21S J r~ 10 7 0 E r 1 . " * +. 1 F i $ l 10.~ - '
l -Lit.:*.. SI-:'; ,r; . ,3 e , 3. - : ;,
7,, ,, n .; , . . r/
E r_l' E P f fl ((
21, tf F A t] I -+ ' . ~. t pt.u. . . .- - . . . . , , . , ._
'r ,, 4 ..4 I
r 7 FROCEDURES - NORMAL. AENORMAL, EMERGENCY AND PAGE 44
~~~~dddE6EddfCdE~CdtEREE~~~~~"~~~~~~~~~"~~~
ANSWERS -- SE000YAH 1&2 -9 5 / t 1.' t :-D E AN , un AN3WER 7.16 (1.25)
~~1) Description of job involvin3 si3nificant rsdistion.etc >+.25 ca)~~
~~2) Anticipated 3 of personnel to do job l~~
~~3) Anticipated 8 of msn-ncurs to de joa~~
~~4) Estir:ated tsdistion exposure in h e n - f: e 1~~
~~5) Wsys considered t. o reduce eaposure anc c:nt %1nstian spreac REFERENCE 10NP RCI-10 p ,c !~~
PNG-16: ^:n c w l e o 3.: of fscility ALARA -r a 3r n i3.4 3.')
\,+s e-.
ri e ny L *1 A I . 4 JVI
$l 1 ' i. 4E 9nt 's 5b s 3 3 d C6 h '[ II9s *** 23.
MFC air cci ne ' ' '
OI 8E'.4tt30.00g3 I<CUCr 3r.e,iceg i; 0 n t. 3 r . +,~i c* Aler t . 51+- e 03 t m e r g e n c ,- ot ,e n.2 r 11 E n. o r p r, c . 4 .!i AEFEFEEE 19NF I? - . ;s ;; ', ! IF-G, ,- 5 IU$*'". ',;t,fL . f. f 01}I*- #*i I i; r+ [ ^ .
m O...,-_. .a .. .
"Y . e S (I *i obtS [l Ua b I k s Ie# [
~~1. 4 e s . , .~~
, ; ,-- y o g i n .; ~H: ,; i.. .c p 4 r, q ~ .4 717 1 .e .7, - +[, t i E f ? f I A t:E
= c. , . :..e
, +
6 g ( O E g
i t__.
r I
i l- , .
l
~~7. PROCEDURES - NORNAL, A B t40 R N AL , EHERGENCf AME PAGE 45~~
~~~~i<h656L65153E~C6I4IRUE~~~~~ ~ ~~~~~" ~~~~~~~~~
l MISL4ERS -- SEQUOYMI 1&2 -9 5/11.'! -DE ArJ r W ri ANSWER 7.le (2.50) si'-CHG, SI ?. AHR pumps runnir.3 >+.25 es respcnze)
-Flow thrcush the B!T
-If RC3 press i 1500 pst3 .erifv 3I pump v.ca
-If RCE press ISO F HF p >; p, F flow bi '/ e c i f f Fanels iE 3 FiF 513 li ' .j c.
t 5
.a "r : e- p '. in : .4 6. l i n e d 2ress
-Verify Panels 6C. 60 and J . 9 r f. ? c, G dstk e:: c e p t Outlined areat
.i '!e r i f . AF4. pumps onninj
-AF7 1evel :ential valco: Ir, AU~O
-I r S / ., level 3 3 *l, , ,ertf- AFW ' 11: w
-S/C Blauriwn oisee cicse:
T,EFERENCE E .; - 3 r - ~ '
. c.>.
.t .
. . q =*
n<eJ* /.- p a, - , se* *s . _
l , 6 l . .*. .
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ETEREHCE e e* C. J - ',s e .)? ,'t ,% .
II[ i~l I, E ,' *,, *!
. *s.y. 4.,
l l
l l
l l
1 I
i
'. F90CEDURE3 - NORMAL, ABNORMAL, EMERGENC( AND PAGE 45
~~~~5dEEEEEEEE5E"_EEEEREE~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS --
3EQUDYAH 1&2 -G 5 /11,' 12 - D E A N , W d ANSWER 7.22 (1.25)
ASE-430v & 6.?kv Shutdown Board Foom (+.25 ea)
AUOs-HOV and Vent Board Room
-Diesel Generster Bldg
-o.?kv Unit G oa r ri s it. Turb B i rj.3
-Blending srss REFERENCE
'39NP AOI-:'A. ; r s t : a r. s i ] , '; 7.J i
8. ADMINISTRATIVE PROCEDURE 5, CONDITIONS, AND LIMITATIONS PAGE 47 ANSWERS -- SEQUOYAH 1&2 -85/11/12-DEAN. W M ANSWER G.01 (1.00) 4 REFERENCE ricG/ C AT/ FNP/ S ONP , TS, P. 3/4 9-1 004/0208 PWG-8 (3.6/4.4)
ANSWER 8.02 (1.00)
C REFERENCE NcG/ CAT /FNP/SONP. TS, pp. 3/4 1-1 and B 3/4 1-L 004/020i PWG-5 (2.0/4 1) A pug-S (3.6/4.4)
ANSWER G.03 '1,00,
+b F EFE R E rJ C E FNP/SONP Ti 5.4.3 010.'900: P u r. - 5 .:.:'J.t, A rs ?. u t r. 0.0a ( 1. ,, ;
3 R F F E F EllC E iJNP !3 3 J.: ...
c.o r , ,0 0 ; PLC r , 4.;<
i l
I l
l c
l S. ADMINISTRATIVE FROCEDURES, CONDITIONSr Atl0 L!d!T ATION 3 PAGE 4:3 ANSWERS -- SEQUOYAH 112 -f3 5 /11/12 -D E Arl , W H 1'
i AtJSWER 8.05 (1.50) a) Unit 2 b) Unit 2 c) Unit 1 REFERENCE 30NF AI-2 pp L0
4G ~3

3tation Directives rnlatec to :tatring'ictivities (~.3,'3.54 ANSWER 5.06 (1.00'
~~a. TF.UE .~~
~~0.51~~
~~b. FALSE 40.5)~~
REFERENCE r* .: G . T '3 , pp. 3'4 C : and r3 I n t er p r o t a t i o n 3.).]
Fr!F T3 ~.0.3 ; 3 0.4 30NF T3 3 03 3.;4 Fur,-5; TI knowleop .~.: 'I.'
AN34EF :,.-
~ y
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. '10 5
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~EL'EREHCE
~~,. T ! MNP T '3 -. .-t, 3 .: -;. 5 -3 - ;~~
P U .~. r : F e r. c y n : t i : - + i, o r, t t - l e v e '. .; t : ~ '.-
i I
i f
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~~3. ADMINI3TRATI/E FF0CEDURE3 C0rJ0!TICd3 Air: t nr;a;7093 pact 2:~~
~~ANSWEFS -- 3EGU0fAH 112 5/1LJ12-0EAN, W n ANSWEE 9.05 (1.50~~
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i 3. 'ADMIHISTRATIVE PROCEDURE 3. CONDITI0r13, AND LIMITATIGHS PAGE 50 ANSWERS -- SEGUOYAH id2 -05/11/12-DEAN, W N l PWG-23: Use of procedures /sta* ion directives ( 2. 8,' 3. 5 )
AHGNER 3 12 (1.00)
[
l
-Use the SE Office copy to make reprodvetion i+.25)
-5RO reviews ALL pages and stamps ' Controlled Copy' on each page (+.5)
-SRO signs and dates the Front F age (+.25) i REF EF EtJC E
[ 50FP AI-4, pp to-l l FWC 1: Obtain/Verifv controlled 9rocodore copy (3.5/4.')
! ANSWEF B.13 ( .75)
~~1) Another 3E i+.25 ea)~~
~~2) Asst Osorations Se: tion 5pvst~~
-3 ) Ops Section Spvsr l REFERENCE l ;1NF AI-2, pp 1 l
l FuG 3! Frcceoores/ Directives for Flint 3t af fin 3 setivities (2.G/3.5)
. ANSWER 5.14 i . ?. i
-A3Es +.25 ear
- On t a p Coordinety
-Anv JE ansi 3ned to at: 5,i t ( t REFEFENCE Iq rJP AI-3, pp 1
!- F4G-14 C le a r a ne c/T a 3 3 t n.3 r
~~u nd o r e s 3, t / l .0 l ANSWER S.15 s1.0C one 1 i1 cur satt*- tzj to stic:mracted Lordi. *4 -~~
~~:'.b l o <etr< '+..Na.~~
I I
REFERENCE 30NP AI-3, pp l
FWG-11: Tit 3tnp Clearance , 91, r + 4 2.: '4 :
i
8. ADtilNISTR ATIVE PROCEDURE S . C O N DI TI0tJ 5 Ar1D lit 1IT ATIGH 5 PAGE 51 AtJ5WERS -- SEGUOYAH 1a2 - 9 5.' 11/12 - D E A tJ . W M ANSWER 8.td (1.00) si SE on duty (+.25 ea)
Public Safety Special locked jlass enclosure in 3E office b )- Incore flux drive motor control power REFERENCE
$0tlP AI-8, pP 1':
103/000; A2.02 '::.2/3.2) 1 A2.05 (2.7.'3.1)
AH5WEF G.17 (1.00)
RCS Tav.3 3 P R Press i+.5 +;'
REFERENCE 3 0 rd P T1 3/4 2.5 PWC-3: Entrv l o .' e l concitions for
~~3.5'J.5' AHEWEE 3.15 t .??'~~
- r e s u l t. in an :pon circuit 2. - t .m 3 aqo t sm mt or ti mle, w h i c. +, w ja unw tec t ed. .3: f oter t t . .,r1.n ,0; . "t' '. . :* 2n o p e r. :tr;utt
~~t. 5.r, e i r., p .M 2n a :or r ent e r i r' *.~~
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. .. a i F., . ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 52 l
ANSWER 5 -- SEGUOYAH 1&2 -E5/11/12-DEAN, W h ANSWER 3.20 (1.50)
1. HTC within analyzed range (0.3)
2. Trip instrumentation within oper atin3 r ar.3o (0.3)
3. Above P-12 setpoint (0.3)
4. P:t capable of bein3 opersble (0.15) with a steam bubblo (0.15) (0.3i
5. Ra vessel above its RT (Nor) (0.3) l f
I REFEEENCE Cat.. Tie p. 3/4 1 - 1.~
FNP/SONF T E E:3 ' 4.1.1. 4 00t/050; FWG-5 (2.0/J.3)
ANSWER B.21 '1 001
~~1. Its .:arrespond:nj normal or e m e r -3.i n .: j tource is opersele. and~~
~~2. All its redinjsnt : o rn : o r. e n t i tro :serec'l+~~
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~~5. AD.4INISTRATIVE PROCEDURES,'CONDI'!OH5 AND LIMITATIGN5 PAGE 53~~
, ANSWERS -- SEGUOYAH 1&2 -85/11/12-DEAti..W n ANSWER 3.23 '1.00)
It is a cycle dependent function (+.25) that accounts for power distribution transients encountered during normal operations (4 .75)
REFERENCE SONP TE 3/4.Z.I 001/000; K5.46 (2.3/3.6)
ANSWER 3.24 (1.503
~~1) I gpm ensures dosage contribution will be small fraction of Fsrt 100 limits (+.5) in event of s tube rupture or steam line breat (+.25~~
~~2) 500 jpd ensures 3/G tube integrtts is maintstned (+.5) in the event of~~
~~a matn steam line ruptura or under LOCA conditions ( + . 2 5 '.~~
EEFERENCE 50NF T3 B3/4 a.a EFE-^3't P4G-5'(3.1/4.0,
! ANguER 8.2? (2.00) 1 ti C:m. uter Room; Au, Ins +.rument 9acm EDG Rooms: ruel Oil Fump Poon
~~.25 63i c) Est>citsh 6 continuous fire ostch '*. 5: with b a c i. u p fire suppression~~
(+.~5 for those aress in watch r edund arit systems,:omponents could be dswajed (+.25)
Estsblisa houriv fire waten 3:trcl for a+Mr areas :*.25i REFERENCE A=f7,,I l 3 J. .,a, a
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~~8. ADhItiISTRATIVE PROCEDURES, CONDITIOr5 AND LIh1TATIONS FAGE i; At!SWERS -- SEQUOY AH 1&2 -E5/11/12-DEAN, W h ANSWER 8.26 ( .50)~~
To prevent a potentially hazardous situation involving H2 (+.25) when air is initially admitted to the primary via the vents. (+.25
REFERENCE SONF PLS, pp 40 004/020; K5.16 (2.7/3.3)
ANSWEF S.27 (1.00) a) To avoid inadvertant initiation cf flow from the svstem during inadvertant RCS depressuri:ation transients. (+.5 ea) b) To protect the load cell from possicle damage.
REFERENCE SONF FLS, pp 84 006/050; PWG-7 (3.8/4.2)
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k ENCLOSURE 3 U. 3. NUCLEAR REGULATORY COMMISSION REACTOR OPER ATOR LICENSE EX ArtIN ATION
. FACILITY: SEGUGfAH 112 REACTOR TYFE: FWR-WEC4 DATE ADnINISTERED: G5/11/L EXAMINER: G E A rl , W ri AFCLI. ANT: ______ __________ ____
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question.sre indicsted in osrentheses after tne question. ine asssing grace reavires at lesst 2 *. i t. +s:n :?teJor y ano a final 3 race of st lesst 307.. E.: s m i n s t i c n :ceri .. :.1 1 be - icked 95 5t s
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f 1 PRINCIPLE 3 0F NUCLEAR F04ER PLANT OPE;ATIONr PAGE :
THERn0 DYNAMICS, HEAT TRANSFER AND FLUID FLOW GUESTION 1.01 ( 1. 00 :a The reactor is critics 1 st 1G.000_ cps when a 3 / G F O R') failm r- e n .
Assuming BOL conditions, no rod motion, and no r eactor tr . .
~~hoose the answer below that best describes the values of=Tsv3 snd nuclest power for the resulting new steady state. (POAH point of adding hest).~~
~~a. Fins 1 Tsvg jrester than initial Tsvg. Final power above POAH.~~
~~b. Finst Tsv3 3 rester than initisi Tsvgr Final power at PGAH.~~
~~c. Fins 1 Tavg less tnin initisl T s v -3 , Finsi pcwer at PGAH.~~
~~d. Finsi Tav3 less thsn initial Tsv3, Finsi power above POAH.~~
~~GUE3 TION 1.02 it.00i Which Cf the IOllCwing C3nCitiCns 40UlO Csuse s ! f fi curve to Oredict criticslit earlier than it will s:tus11. occuri~~
~~s. 3corce located too mesr cetector,~~
~~b. Fuel 2?semblies loroe i 1 3 :. far s nt -i e t e c t o r .~~
. H!ghs5t 4 0 r *. h *O. .
25 sand 1;9E i;-GeO f ' i t. .
~~d. C O r. t i O I T 3 -j latit ". D e t W E 9 r. # iel :35emr.;e3 13sceo s r: 0 Qete: TOT S U E I ~ I O rJ l ~I~~
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~~is :per; ting st ; iow tlow conciticn.~~
~~Ct t re e r. E t it t : L 9 F. i n 3 i ' .PC- in!Ottis .31Ve ~r. ' Fi e r 13 0 r. B T 96 5103. How~~
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1 PRINCIPLE 5 0F NUCLEAR POWER PLANT-OPERATION. PAGE 3 THERh0 DYNAMICS, HEAT TRANSFER AND FLUID FLOW GUE57I0t1 1.04 (1.50)
Incicste whether the following concitions will csuse the Fuel Tempersture Coefficient (pcm/deg F) to oecome HORE or LESS negative or ha.e NO EFFECT.
(assume all other parameters are constant)
1) The relative rstic of Pu-I40 to U-235 inc r ea ses Z) doderstar temperature decreases ifvel t e n.p e r a t u r e remains onstant)
~~2) Fuel t emp e-itur e incteases~~
_,.i 1. i s, u l E c.- ilm i. ,. , v i The p l .s n t is 3,c e r s t i n g ,s t 3 M. power. turoine in AUTO (IMP IN), when 1 c c r-Il reactsr coolsnt pump trips. Assumin3 a resctor trip does not e: cur.
there is no operster sctico snc r:c :cntrol is in MANUAL, indicate whe t.,e r the f ollowirig p ar sme.t er 5 will ce HIGHEP. LOWER ct 'ne SAME Et the end si the tr ansient compsrec to
heir t r i t, i a l islues, li 12 5.'; s t e s n. . p r e s s o r + >G.5
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~~1. PRINCIPLE 5 0F HUCLEAR POWER PLANT OPERATION. PAGE 5~~

~~,-------------------------FLOW THERHODYNAMICS HEAT TRAN5FER AND FLUID QUEETION 1.10 (1.00)~~

-In order to-schieve_the highest NPSH st the suction ci s pumpr indicate where the neost advantageous location of tne hest s o -J r C e and the hest sink would be' relative to the pump. (i.e. upstresm or cownstream)
GUE5 TION 1.11 ( .50?
The stmospheric F0FV fcr 'E' 3/G :ssrtistly opens to a throttling position during operstions.st 851 p o s er . DeE: ribe tne quality of tne stesm o ri .ne ocunstreem side of the F O R ') .
t.J U-: t 310!J a...-
i,t.c .su' List the 3 00nditioni neceEE5r. 'Or Crittle frictvre to OCCUR in metal.
luc:i.pp 1 s T_ . . *. :. . . . q ( ',
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~~a .~~
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the S2gnitude snQ tiis 3f cur! G re C G Of the ' ne L i. C O n O & n t T s t 10 0: Cl?
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u.z. 3r, c, e - #3; :- ::it/tte.3 t:n 3~ 2, w ' r :i .:!; log recircui '. ten
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i
1. FRIi4CIPLES OF t4UCLEAR POWER F L A t.' T OPERATION- FACE 6 THEF riO D Y N attic ---,-----------------------------AND 5 HEAT TRAt45FER FLUID FLOu QUE 5TIO ri 1.1- (1 0:'i Identify the nuclides compcsin3 the secondarv source utilized in your r eactor and describe how this source is 're3enerated'.
( 1 . .,. a u t, t- - - , .ri.., r1 1.10 Over :cre life there are 'wo effects that cause differentisl boron worth to chsn3e. List these two effects- taci* relative im.act on differentisi boron sorth snd in iic s t e ahich effe:' e r toe-o.erridin3 (sctor, GUE E TIOil 1.1: /'.00)
Pro :ae the definitiens "or the fallcwing t'e r m s :
s: D N E:F.
bi 3pec;fic Entrce.
G U t :. > t# 1;IO 1,~i'
~~2. ' e t c h the " e a c t o r ' .; c . : s r. t : n a r.n e l Ect11na Wster :or<e- indicatino the (cur~~
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~~f i r. s :. r e s s u r l : e r 11 a - ie3rees r-1 .' .is.g c.. p. p. .: nr . , s , --~~
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i
2. PLANT DESIGr4 INCLUDING BAFETY AND EnERGENCY SY5TEMS- PAGE QUE5 TION 2.01 -(1.00)
Which of the folloding components served by the Ccmponent Cooling uater System (CCW) could NOT cause an ine.rease in both CCW surge tant level and-CCW rsdiation monitor incication if 3 failure .:f the componerit being eccled occurred?
~~s. RCP bearin3 coolers~~
~~.b. EHR pump seal cooler~~
~~c. Spent Fuel :it Hest E:: changer~~
~~6. Ses! Water Hest Encnsnger GUE37I0rl 2.02 '1.00)~~
5. H R i r. l e t isolation valves 4-1 snd ~4-2 esch have an independent EC3 pressure transmitter associated w i t ,k them. Which of the following statements describing the effects of the transmitter associated-with ~4-1 failing high is correct-
~~a. If both ~4-t snd ~4- sre cpen- thev will shut.~~
~~c. If cpen, :-1 will shut s r. : l' flosece ~4-: will not De sbie to be cpened.~~
~~. If both 4-1 snc 4-: sre : hut- neither :.ne will be able to ce openea.~~
G. !! sen* "J '
all. - ni: t a - -
~4-1 73n C 3031t10neG is Gesired.
9 ~0-1 !?n 'E "
_v I l l *. o n s rl . I t ac:: t?; 3 3 tn* Oper ator , but 74-2 il'. :O" fe : ale '0
, Je diened 1i 1 *. is EhUt.
.:.s s r t
~~CATEGCf' 3[ [ Oil'I:JUE[ O rd fl E ) ~ P"GE *s***i W "' -- -------------z_-- - - - - - - - - _ _ _ , _ _ _ _ _ _ _ __~~
m
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t G E r.i t. t u..fn- sit n. .a Pn,bE a
GUESTION 'Z.03 - (1.00)
Which of'the foliotin3 is the preferred aroer of sal.e operation far inittstion of-Emetsency .,.cration as stated in n.e; ;.4-
~~3. 62-1~,5 !. 136(RWST Svetion '>sives), EiIT . In j e c t i o n 'I s 19 e s .~~
~~HCV-62-92?(Emergency E.o r s t e Handal Valve). F C t'- s '- 1 3 ( E etie r s e n c y E:o r s t e riOV i~~
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~~2. PLANT DE5IGN INCLUDING 5ACETi ArJD EnERGENCY SYSTEn5 PAGE .i~~
-GUE5 TION !.06 ,
( 1. 0 0
What are the FC5 piping penettsticns asde BELOW the horizontal c e n t e r-l i ne of tne piping- *:p ene tt st ion s with a -similst purpose are to be trested as one group)
GUE5 TION 2 07 (1.50?
Fill in the blanks in the s.atements belcw ccncerning the Emergencv Cas Treatment System
~~a. The a nnul u s 'J acuum Contrel 30cs stem is useo to establish sno Leep s~~
_____ eressure withir. to- _____. In enerienciest in which c c r: t s i n m e n t isoisti:n is requireo- this sucsjstam is _____ snd _____. 't.0i b) The Air :Isanup System p er f ct .: two functicos nering s LOCA. One is to maintain _____
n- + . - s cond f u n c *. ; c n
.. s :: _____ from str drawn from the innolus.' (0.5) r-
~~m. Jt .: r . n ;.j _ . c) m. . . = . ,.~~
Ir. :ic s t + whe r e the fclicwing CCS :enettsticos ~ occur by loop -segment.
(eg. Loop I intermedists leg nots tnan onc loc s e 3 merit may be requzred.
s: Ncenal Let w n
~~, i ::t :vt je :r:~~
~~i P;: 5prry ' L i r. e di RHE Inlet e' E~ cess Letocun Hest E.,c h a nge r Ic;et Lv .rr- :. . s O h .' . 6. :. $..-"..~~
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. FLANT DESIGN INCLUDING 1AFETi AND 'EMERGErJC f 3r: ten 3 FACE 10 OUE3 TION Z '. ) - (1.00)
Fill in the 21 nks in the statement below re3srding the Concensste Storage T a ril. :
The CST minimum water volume of _____ 3allons is sufficient to maintsin tne pisnt in hot standby for _____ hours, GiJE s ~i 1' 0r .. 1 1 4
~ .~ . v' u' ',
List the four AUTlnATIC trips of the AFW Terr. Turbine trip snc throttle v31.e and whether the trip has to be r e s a t ri ANttALL1 or NOT.
QUESTION : 12 '1.00)
Fill in the blarAs celow to c c m p l e r. e the statemer6 :ancerning Ao.:ili;r s Contral Air
~~The Centsinment Evilding ts suppitec a t +. h edonoant hesoers, each -'~~
E U.P L 1 , i n 3~ 2nd '31'-eI+ Ihese he3ders sfB is313teG on
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~~. PLANT DESIGN It4CLUDING 3AFETi AND E -i E F G E riC i S Y ET Eti E PAGE li GUESTION 2.16 (2.00'-~~
~~List the eight E3F'relsteo losos supplied by the ERCW Svstem.- (Trest~~
~~ommon or redundant :cmponents es :ne load-eg:several like heat exchsngers)~~
GUESTION 2.1< (1.25i Where are therm *. sleeves associstec with RCS penetrations located?
GUEETION 2.18 ( 1. 5 0 :'
~~ist the THREE C3 lest.sge vi c n t t c .- i n g systems thst must be GPERAPLE wnen the plant is opersting et 100*. power.~~
GUESTION Z.1? ;1.001 What ECC5 relatec co.Tgenents sre ta3 gem cut at .cw pressures to nelp prevent inadvertant over pressurl:stian at low temperatures?
OUE3 TION 2.23 i1.00; What- is the purpcse cf the interlock thst prsients the 'etdcwn isolstion salves fram openir.9 cr s,..'tting > r:l e i s sll tnree orifice isolation vslses are shut-hdE 5IIO3I 2+21 '.'2.Db si ' ;escribe the vnbacv arccess that cccer; alth the nsin furoine when fne OI Delts I setpCint is 9 ;: e e ~J A C " 'l.)'
di '.st 'he twc fccccits "inds' _: ses sac tne ticcess 3 ', Anica *i eir T unDeCI. 300U7s t1.0/
~
a' a i s s ATE]?TY 0; CGrlT c._E[ Zi* AGE t s:i)
Z. PLANT DESIGN INCLUDING 5AFETY AND'EMEF5ENCN 5YSTEME FAGE 1-
~00ESTION 2.22 - (1.25' Place the fcllowing svents tast occur in the diesel start sequence in.tne proper sequentisi order, ai Engine evnning slarm b) ERCW to Ht-Exchgr 1 opens cr Field Flash d:s Diesel nuffler room E: haust Fsn stsrts-e) Luce 011 pumps start to turr.
~~END OF CATEGORY 0; s**aa~~
3. INSTRUriENTS AND CONTROL 5 PAGE 13 GUE5 TION 3.01 . (1.00)
Which of the following would be the INITIAL respcnse of the feedwater flow due to the response of tne 5/G Water Level Control System if the steam-pressure transmitter ccntrollin3 tne SGWLC3 isiled HIGH st 50'; power?
~~a. Feed flow'would !NCREASE due'to the m e ': i n. u m steam pressure input~~
~~.tc the steam flcw si3nsl.~~
b. Feed flaw would ENCECASE que to the 1.ssel <ti l s ne s t c h e r r o r cetween actual and progtsamed level caused ov tne pr e s sur e instrument fallure.
c. Feeo flew would DECEEASE ave to the mismstco between steam and feeo flow sigt. sis cresed t. tne pressure in s t r omer.t fellore.
~~d. Feea flow woula recatn TM 3A,E cue tc the cominance or tne level~~
~
error.stgnal o er the f1:a error 313nal.
+. Feed ficw wavic -essin.RE EAnE ss i t .: s m tresser+ . 11 not sffect tne s t e s n- fIou s i j r. 31 U L, ._6aJ.
c '. , c fl
.).',- . . ',8 A.
U h l .: 3 st3tement De10w : j ' ,' , ' " 3 -'4EI! ' .27T ;** - rC ~~~'r!! 15 Carie!t"
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~~2. INSTRUNENT5 AND CONTROL 5 FAGE 14 GUESTION 3.03 -~~
(1.00)
Which staten.ent below.regaroing Diesel Generator loso. sequencing is correct if z LOCA occurs AFTEF s LOS5 OF POWER?
~~s. Loads alreadv sequentially connected will remain connected.~~
~~-b. Loads swsiting sequential loading thst are recuired-for an sccident will have their sequentist timers' reset to time zero.~~
~~c. The non-sccident le a rj z not yet connected uill be sequenced on cnce all sccident related loads sre connected.~~
~~d. ALL loadz will be stripped. then ONLY the accident related loadi will be sequential 1/ c o r.n e c t e d .~~
3UESTION 3.04 1.00)
'Jhich statement below regardin-g Steam Dump control is correct;
~~s. The FIRET 2 canta to mcdulate open are the LA57 2 banks to moculate open on s reacter trip,~~
~~d. The.FIFET steam dumt omnt modulates open fron, O to 407. riemand ind the remsining : esri 3 Tic d u l a t e to f ily open in subsequent LM. demand i n c r e n, e n t s .~~
c. ~s* 15 s 3 *, u ;-;;. ., the n , G e l i e, t. S 39JOenCe Of ZuCCeEilVe bine : th5t 2t' 0 ; '> " i n 3 ,
~,
~~iha 1si' b 5 n k-~~
~~is c -i v [ 3 t s. open 15 *ae i tr;t b i n Il to GeGdstiste shut, r**es C A T E ~, O r ' ~~ C O i.' T !;J d E O O ti rJ E ; ~ ? ACE **t*s~~
1
3. -INITRUMENTS AND CONTROL.i PAGE 15 QUESTION 3.05 (1.00)
~~Which of the following ststements concernin.3 the operation of the Reactor Trip creakers and Reactor Trip Eypass bresi.ers is correct?~~
~~a. Trippin3 is accomplisheo by an undervoir.a3e relay, normally held closed by 15 VDC power from the 1c31c cabinet,~~
~~c. A Train B trip si3nal will trip both RT bresk.er B a r.d Bvpass~~
~~r. e si.e r 5~~
~~c. The sisrm 'EYA (or EYER in G.ECATE' indicates the Eypass brester i s racked to the ' T s. s t ' posi+1on out is NOT closed.~~
o. Contrcl Power for the Reactor Trip 'resi.ers a ccmes from 120 VAC c 'n s r.n e l s I snd III for U rJIT 2's RTA and RTE respectively, r.e u e i T x_ r.s -
~~. . t. ;~~
. v

., ,
Indieste whether Ce following a t t u a t i c r. s will ARn OriLY , ARn AND ACTUATE or HAVE NO EFFECT on tne s t e s n. wmp systes.
5 0 ', : 4 e r . i i *. step icac increase. T s s 3 t T r e r' b, 5 ri e 3 r e e s F steam du.p p 3 i r, T s './ 3' n. c u e 3 7_9 r ; i 13 r
~~. 1*. pnue . ,!'. m:, s ;;, ;; :ac esse in ..~~
a i n .: *. cad f3r 3 iri n u t e s -
I;s3:Iref D, ' degrOes I* 10&sm dOMC3 in IE.3 no.ie C 4 Operst1Gr.
W6 ZerO O cwer. T-,g fl! } . ) .I 7. *
~~; 3. 14 _i in :7n FREI 3 Teo d e~~
-1t- '. { 5 TI: 3 I2t 1 itc tier -'Gim L'2:IV's I O T t f G l.l O f i? ~' ' c- t r . e , "* ..
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. .~4 3sG .G*er C C h'. L-34 s s. sa CATEGjf( Q3 CONTINUED GT4 rJ E ,t T FAGE
~~4 2 7 s 's~~
'3. INSTRUnENTS AND CONTROL 5 PAGE 16 GUESTION 3.08 - (2.50)
Match the following reactor prctection and control si3nsis in Column A to their associated logic coincidence in Column 5.
COLUMN A COLUMN B
~~a. 2 loop loss of flow trip ': p e r loop) 1 1. 2 9 */9~~
~~u. w&~~
~~b. P-6 (SRn turn-on on power ce:resse- 3. 1/3 4 2/3~~
~~c. P-12 (Lo-La Tav3 or, temperature decrease) 5. 1/4~~
~~6. 2/4~~
~~6. F:r high pressure trip '; p r e s s u r e increase) 7. 3/4~~
~~e. PRM high scwer rod stop (power increase)~~
QUESTION 3.0? ~ 5"- c / s o)
List the'\ Diesel engine snutdown trcubles which are bypassed wnen there hss oeen eri emergence start.
GUE3 TION ?.1C .i,50i
.ist the 6 cperstin3 criteria
.ast -:i s e t be satisfied to seccessfv11v stsr t s Reacto- Coolant FvmF.
QUI 5 TIGrJ ' 3.!1 1. t . '
s) 'J h s t is/sre the i n p u t ': s i to the UNIT 2 ri s i n Feedwster Evpsss Valve
~~entrcliersi : + . 5 :-~~
b) To ?.l s c e 'he ~~ sin Eeedwster 6VFss
, '! s l e i in A' T0n ATIC contr ol While a d low O Ou9r ? 'Jh st : O ra t t O l l e *
~~r i l s t e ') 03rdit3Ons EUs* De f'tidli3heG" *.E'~~
~~(***f* C A T E G ") F i ~~~
~~I; [ONTIt2VED ON r4 EXT FACE *****)~~
It,lSTRUMENTS AND CONTROLS. PAGE 17 3.
QUESTION i.12 - (1 00)
What automatic control sction occurs when a high rsdistion ccndition is detected by the following radiation monitors?
a) Fuel Pool. radiation monitors iG-RE-90-10; 2. -103) b) 5/G Blowdown monitors (1/2-PE CO-120 2. -121)
GUESTION 3.13 (1.50)
When nuclear power has oeen increaseo above the setpoint for per-missive F-10, the operator can manually block three protective festures. '
_ iit'these THREE festures that csn be biccked.
GUEETION 3.14 ( 1. 2 5 :-
What are the resctor trips which sre enabled / block.ed by the reactor trip system interlock F-7
t tJ L A i si.l (*
. $ . s, s
.L
.e, uJ J W h ii '- 31 -] n >31 5 Wi11 5LtoA3 tic 311y LD1hiEte tOA c?A~itiOn of the A U;; i 1 i a r ',
Datilding 09: IrEstnant 3ystem7
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s -.O , -
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~~3. INSTRUhENTS AND CONTROLE PAGE 1-6 QUESTION 3.19 . ( 1. 2 5 :'~~
The Detector Current Comparator receives input from all 4 upper and lower power range detectors. How are these inputt campsred, whst is tne alarn.
setpoint and when.is this circuitrv in operstion?
GUE5 TION 3.20 (1.00) 4tta the pressoricer level :cntr:t telector switch in mositten I/II, a failure causes the fsil:wir.g plan: 3 c e r. : s . (Assume no operator 3cticos tsken.-
~~1. C h a r it3 n 3 ficw e dis c e d to ninimum~~
~~2. P r e s s o r i:-s r level decreases~~
~~3. Letdown secured 2nd hesters aff~~
~~4. Level incresses until h13n level trip Which instrument failsd 'I or IIi snd in what direction did it fail?~~
GUE5 TION 3.21 (1.'5-uhi. sre t. - n41n Steam !so12 tion 31 -3 n s i s :nd waat are their setpcints?
GUESTION 3.2 ( 1. 5 ':
H.e t c h the rcc speed rstcyr=n a i n d i : s t i r. 3 rcc >a ed .ersus error si3nsl.
s
~~2 .t t~~
ENO ili CATECOIi 3 *****
~~4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15~~
~~~~R IEE6[UGECAE~C5sTE5E----~~-----~~~--------~~
GUESTION 4.01 (1.00)
On s unit startup, when reactor power resches 10%. ;ever31 indics-tions must be verified. Without any operator Ection, which of the fo11cwi~n3 is NOT o' o served st 10 *. .
~~a. 'F-7 Lo Fwt E; Tr ip Elo: Led' light off~~
~~b. I/R Trsin A Trip Elacksd* 113ht illuminsted~~
~~c. 'F-10 rluclear At Fower' permissive light i l l u n, i n s t e d~~
~~d. ' F -l 3 Tur'o ine He t At paver' cermiss:ve li3h +. off (1.v.0 OIJ___._iu tt 4.u. '~~
WhiCh Of th. fC11CWin3 iE NJ U ~ m Criti.:s1 ~;3fet I'>n c t L Qn~
5 C 3r e CD3.'n1
'O . Hest Sini -9
~~. Evber _;cality~~
~~o. C- . - ir e no t e inventors~~
,i_.f +g ) f 9.g. e s J .e .,,
Whi!h Cf t ,'. : #
C l l O b i r. ) W3010 _ ' .s i r - E ' E r 3 _1 E;*;*1-n ~
3 E C 2 ' 3 1 ~ +. 2 O n t r e,1 ; 4 6 * , * '.5: s i. i '_ * * '- : war
~~b. I.ar:TCTt"Ille; !*-t_' .~i s i ' .~~
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__- L ., .. ,. : -c to 1+r. : t i o r. w h i l :- ce-'orm;oj : o- "
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4. PPOCEDURE3 - NORnAL, ABNORMAL, EMERGENCY AtlD PACE 20 RADIOLOGICAL CONTROL GUE2TICN 4.04 (1.00)
-lhich of the folicwin3 statements describes the correct action to tske ife on a reactor startup, criticality is achievec ABOVE the :ero power t o r) insertion limitr but BELOW the +/- 1000 pca. criticslity band?
~~a. Insert rods to the :erc power Inserti n. limit.and recalculate the ECP.~~
~~b. .Ciscontinue the startup. c31co; ate a r.G then conduct the necessar>~~
boration to ens >re thst cr it c slity .
s achieved wi thir, the 1000 r.cm cand.
~~c. Continue with the startup. Ic33tn3 tqe :enditions st which critirslity wss a c h i e v e -j 3 n ei n o t ; f ,- tae nu;1 ear engineering dept.~~
~~d.- I c.19 .' t Qi!. ( , .w ::n,r;! bsnk red- tc the bottom of the ccre a r.o~~
~~eOBl;91slG tne E2 <~~
?. Ir. 4 n t ONLY the : ente 01 bsn.-: ;a the bot *,cm of-the core and f *; C a t.4 h 0 3 ; C- I Ei2*1Up Ufaf*3 ; 1 'h PlCt t3 1pprO3Ch Crit 1:311t).
f l, _ .3 . t u r
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r, nvN0 m .n- ,. E ri-trut . - th ..i n. r.JD PALE
.1

~~=----------------------------- ---~~

~~rad 10L0uAccm LONiFOL G,,J E d I Off 4.vo (1.v...v .i Which of the f c 110 w i n 3 w o .il d cause the 3reatest biolo 3ic al damage to s .wan3~~
~~s. 3.1 R3d of Fatt Neetran.~~
~~b. 10 Rae of Osama,~~
~~c. 2C F s c. of E.ets.~~
~~. nlpha.~~
~~c. v . ,.Kso - . ct GU i IOrJ 4.07 (i.00i s~~
Whici,Nof-the.followin3 describes shat i s .T. e s n t & r!otaing Det ec t ble ' 3:
it 1: utilidsi in determinir.3 tne :i s t anc e - Beta-Gamnia contsminstion n ik.in or c1cthin3 it.g r a c e s -.
's
i. [GI! Ihan '00 . - E U c ie .< 3 r G 8'no si ase !'5 U r 9 G With 3 "' U n C 3 k. O .
Probe. !
/ 7 }
's
. t. e u mn toe - ,, s bc. e v :, ; ,nc s2 m r,r ea u tn s iresr.
C. v e ,3 t . i : r,r.,[ t i m e 5 C 9 :i .a t O u r.0 ; 3Unti _.
tit e I i U r t.< C w i t .~ i. 3%O3r 3s
~~Q *Jfde d '!r Cne 'i 1~~
~~6.* t'.~~
~.' . ypf.. . . '-.- t 4 . p .: 1 ?.. .
.1 i _
~~_- +i ; ., +s .i f. - .:. T 1 n ..~~
~~c .~ _ ,~~
wi
~~te. m-~~
.c e .. ....
e .:
. ...a - ., iq . 3 2
. i
.a
+ .. . . .s &, u ,
j - .
.l... . . . . .,_Li
-. . s : _ _. *.*
I P 100 * .
r e g c 6,, r 3 * .; - ( t, p . ., ; _ h' th4 FC~ g* ; - ,, i l

erEtini 3r9E30r9 500
~~.e.t . + + - .~~
t - **, u n g: P ~. ' ; g z i . .: .- - e ,:+ ,
, F- ;:n 1:-ki *;2tOO .elcu.
5; "fmlin 3H'JtDOWN,
. ~ . ~ . . . t. l e t' : '04 : ;H~ i :. r '~ - 'LI 12.
..:O.r 'r .-..1 i .t
~~_sv 2m.6 . 1.:..l. .~~
s- .: : : ., . 4 -; - . . 6 s
.:, , r.
t.. ~. .- . . r
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. . . i p. : - a! , ;G .r; yl3-
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. ,-r . . . ., . , , . . .
.dI w .? h . .) -.f .$ b , 4J 'J b'. \ }
~~F1, iJ (. 88 I~~
~~4. PROCEDURE 5 --NORMAL: ABHORMAL, Eh ER GErJ C Y AND PAGE 22~~
~
~~~~53656L555C3L CENTR 5L'~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.07 (1.00)
Fill in the blanks in the following statements regarding the monitoring of AFD and actions to be taken if specifications are not met.
The AFD shall be considered outside of its limits when at least
_____ OPERABLE excore channel (s' is/ are indicating the AFD to be outside its limit. When the indicated AFD is outside its allowsble limit it must be restored to specif ic s tioris within _____
(times or Thermal Power must be reduced to less than _____.. of Rateo Thermal power within _____ (time:.
GUESTION J.10 i .5Ci If sn individual had alresov receiveo a whole codv dose of 1000 mrem this gu s r t e.r - the mstimum adcitional e ',: P o s u r e to the skin that he could receive this q u a r ". e r without exceeding 10CFF20 limits is _____ mrem.
GUESTION 4.11 (1.00-Fill in the ' c lank s with the sppro rlste 'inits . sted in the precsutions se:tien of the GCIs:
s. A 10sd ChsnJe Cf e *
,,___ . 78 :, , ,
' :i 4 & At isnje cf _ _ _ _ _ ' . Ja0uld not te e.;ceeded.
cf The *0rGn conc en ti s tic r.
> ;1f!ereDCe O e ', a e e (. ti.e Gr+3suricer s riQ t r. e CC2 post GOi A: COet _____FOm.
'i '~ ' P C: Iba sr%irg te90er ture j?tooint ict , ; ~ Tr ' ' R '! - ts , _ _ _ -; s j ugt.;;. : . a . . _- 3. . _- - .
EUt *2 f c 1 1 : .: ; . : ;4 : . t . tl fi s 5: ;: } C . 5 ", .? d W1(d
_e ;
' :- +
IF2T Car * :1 - ad C'itC T. C 3+t l. ;OI 9C' OrdMT !
'.'s 71 : s /- tha #. ?lo El '.1 . I the av , :.1 i .s r i '~O ') A.: E . r. 1 -,er +
rG i r ; ,' e -s
.:' ta,v:t j e . c. r s '. a r :l*.g+
J' :1:r+ 'he m c *. : r :ircrit 'a r e s E = .
- I I C c; the 3tfes' E t C T C: * : _- 1 t Li O 3I 2 7
' *7*a1 iATECCE }l [Or. INUED Gr1 r:E': T ? 4GE ****
~~4. PROCEDURE 5 - rJ06nAL, ABNORMAL- EMERGENCY ARID PAGE I3 FADI0 LOGICAL CONTROL~~
'0UEETIOti 4.13 ~ ( .50)
.Fcilowing's reactor' trip, how msny gallons of BOPON must be added for esch control rod that'is not fully inserted?
.00E3 TION 4.14 (1.50)
Ftll in the bisnks below to complete the statement regardin3 sclid sater operations:
-Whenever the plant is utilizing letdown from FHF -the _____
control valve should be used to maintsin presture. while ths
_____ control ssive sh:vid be fully cpen. Fcwer to the _ _ _ _ , , -
the -_---
and ----_
incold be t i _l _s e d out to n.10 i m i z e tne possibility of overpressurizing Sue tc sn II 3:gnal. 'J h e ne v e r the reactor cool' ant temper-tur+ ? :t aboye _____ deg F. .st least ona ECF must be in oparaLicr..
GUEITION a.15 (1.00-3- '+ut'is the srtmar, s.s.:vst: : c, s.eiter for c e n t s c. t n s t e d merecnnel ti s 7
lQtsi pl?nt Ev sC8 6 s t ~ ". -- 7 G 9 91 f A C b3 'EhGrd , s D el e 5 9 s e <Ti d ' :s 'C f-^ ?? f: ".Os
~~3 ri ca C l a ir a 3 1 *. *?~~
t.9 9 " C_ 6 n C *-
N[ 'O j 'g 8
'O'.s I)l C O, s'.I t .$. !
~~'hf "edtsired ,~~
-- - ~s 3 ,f "nE .
' F ; *. - ' + : . .: " 3
~~jn 49' . .3 C .~ ~. G ;~~
~~~+ .r $ +10e11 nt I. ' ' - ! 1 I C: in. 30t1on that 9: lilted i n I '.'" C~~
~~i 7 "- ~ Pitir~~
~4 Oir: 4 locsl : .0 9 e t t ; .
~9 2 .;-E- !. n ._ '* - t^- ' ' c ' t f .: n i P c te 4, ;-, ' *e m 1; , m .; s t :, e o p. e e+-
.; f 0. . - - - . , , :
e . > , 9 .
g g i 4 ,
~~g , , shf .~~
.Q f $ m' E T. S i t "i t f. Lp I'1' Pr'iE*.
EDS73 I ri ' " ~ ' ~^ TtIINUEO CT
> i s. 4 0 tyaaa 4
f
~~4. _ PROCEDURE 5 - NORhAL, A E:N G R h AL , EnEPGENCY AND PAGE 24~~
~~~~53556L55553L 55DT55L GUESTION 4.18 ,0.001 s) On a station blackcutt whst sre the 'I ' cad; tast re seaventially loaded automaticall,, anto tne diesels. ti.21 b; There is a precaution in the Less of Offsite Power procedure (AOI-35) to ensure t h s '. the diesels are losoec to 1600 MW within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months isssuming the diesels sre reautred thst 1:n 3 ) . _ What is the purpose :
this precaution 7 :0.E' QUE3 TION 4.1? (1.50) s) Wnat sre oper stin.3 per sonnel supposed +; do opon hearing 'Resctor Trip, -
abandoning control room' cve' the pu:lic sddress s y s t e n. ? (0. ?
b) Certain controlled instructions /plsnt referenced material is kept in the eunilisrt : onti n1 r o o n. te essist the operstor in safely s h u ', t i n 3 ' c c o l , o j dcwn t'w ;; ant List 3 af t ;w i e 10 i t, e n. s . (0 G)
GUE5TTOU 0.20 (1.-~i
J h a - sr> the /, o t a w a t i ;. A .: ' . : n e s ic:isted with . les- cf 125 VOC 'li t a l EsttS?i Eo3rc ! On Unit l '~ E ri!U r a ~O0 1 n 010 'i 0 *~E *sV0e of SnV FrCtettiJE s*ti:ns thst Cc7hr.
O!jEI~ ION 4411 1, 5 0
2 i Tist c o n d i t i c n s 48 0 3 ' a :- met tor tne I C C '3 suction to be shifted O i. t a .Ti s t i r. 51 1 '; LC t ~i s 2 i r' t
~~1 n iL *s ri l :- e i m p I 0110 41 n 3 2 n [I i r,3 t l a t i on ? i O . 5 '.~~
~~D) If 5 -2 0 n t a i n ri e n ' G U tt ,. rst,a ( F C '.' - a 3 7 Or -73) sn NOT be full / opened When In ! U t :<E I t i : 5-spoVe" 1: I3~~
~~C t. '~~
~~Lh2* *??*it!r sCt13n3 3re~~
.: quired' .Q'r c,e*** 2 4 TE :,GF - n; ~NWED ON NE/T :ASE *****!
4. PROCEDURES - NORMAL, AEHORhAL, EMERGENCY AND FAGE 5 RADIOLOGICAL CONTROL GUE3 TION 4.22 (2.50)
List ALL the immediate sction sue-steps from E-0, ' Reactor Trip or'Ssfety Injection' that allow you to accomplish the following immediate actions:
a) Verifv ECC3 status (1.0) b) Verify Containment Isolstien ar.d ECCS Alignment <0.5) c; Verifv AFW ststus (1.0)
GUESTION 4.23 .1.00)
What sr+ the three parsmeters that are monitored to determine RCS cocidown in ac:crosnee with EE-0.5 'Naturs1 Circulattor, Cooldown';
Q U E S TIGil 4.24 ~1.001 F* tor to c o o cie n c i n g a dstvrst C ir cul s tion Cooldown per ES-0.3, it :s nec e s s sr v to in:rease tne RC5 bar:c acid addition by 15%. Why is tnis cequirea?
3llEETI3b 4.!! l1.001 Flsca the eteps. listed 001:w, w e. i c h are per(crmeo during s pisnt startup, in tne propor se ventiai :rser.
Ir- Trsnsfe- 4 . ? F. / vntt' board 1A from 3tsrt E; o s !A to unit ststion tranaformet 1A.
~~' ' 'ini'er iC feedwater rejulating ,si /e c:ntr;i to A ij T C .~~
I' ~ : s r.s f er s ' c- 3 5 dumps to Tavg mode.
l' T,bre-fer ':j Gn'JOI to AUTO.
/***2* E N E- OF C ATEGOF Y :J ree**
.nsaseensstan. ENO C ,: E(A.,INATION s .a s s t a s s a a m a s .e s i
. foca v o s/t cycle efficiency o (Net work out)/(Energy in)
' 2 o o cg s o V,t + 1/2 at
[ = mC" .
I KE = 1/2 mv a = (Vf - 13 )/t A = AN A = A,e PE = agn Vf = V, + a t * = e/t x = an2/t1/2 = 0.693/t1/2 w , .p .-
A= n0 2 t
1/2'" " Ut ' M d 1 4
[(t1/2)
~~IID I) eE = 931 am -~~
. m = V,yAo -T.x Q.= m,oh I = I,e Q = mCpat Q = UA A T I = I e~"*
Pwr = Wfah I = I, 10~^/ M TVL = 1.3/u P = P,10 sur(t) HVL = -0.693/v P = Po e*/
SUR = 26.06/T SCR = S/(1 - K,ff)
CR, = S/(1 - K,ffx)
SUR = 26s/t* + (8 - o)T : CR j (1 - K,ffj) = CR 2 II ~ "eff2)
T = (1*/s) + [(8 - 8Y Iol
~~M " IIII - Keff) = CR /CR j ,~~
T = s/(p - s)
M " (I - Xeffo)/II - Xeff1)
T = (8 - o)/(Io) SOM = ( - K,ff)/K,ff
, = (K ,ff-1)/K ,ff = aK,ff/K,ff t* = 10 secona a = 0.1 seconds o = [(t*/(T K,ff)] + [i,ff (1 / + IT)]
j =Id I d) 2 ,2 gd 2 P = (teV)/(3 x 1010) I jd) 22 I = eN R/hr = (0.5 CE)/d2 (,,g,73)
R/hr = 6 CE/d2 (f,,g) _
Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 x 1010 dos l
i ga; . = 3.78 liters 1 kg = 2.21 lbm 1 ft+ = 7.48 gal. I hp = 2.54 x 10 Stu/hr .
Density = 62.4 lbg/ft3 1 m = 3.41 x 10 5tu/hr Density = 1 gm/cm3 lin = 2.54 cm Heat of vaporization = 970 Btu /lom *F = 9/5'C + 32
, Heat of fusion = 144 Stu/lbm ,
'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-1bf
( 1 ft. H 2
= 0.4335 lbf/in.
e = 2.718
,.y. - _ . _ , , _ , , . . . .,_...ms - _ , - . _ _ . _ . ._, _,._...._.-..m., _ _ _ . ,
Enthalpy. St$Ab Entropy. 313/10 m I Volume. ft'/tb T p Water Evep Steam Water Evep Steam W ater Evap Steam 8[ hg
~~g bl h eg 39 S ig *g~~
'I %g
-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 32 0.08859 0.01602 3305 3305 3 00 1073.8 1076.8 0 0061 2.1706 2.1767 35 85 0.09991 0.01602 2948 2948 8 03 1071.0 1079 0 0.0162 2.1432 2 1594 40 40 0.12163 0 01602 2446 2446 13.04 1068.1 1081 2 0 026? 2.1164 2.1426 45 45 0.14744 0 01602 2037.7 2037.8 18.05 1065.3 1083 4 0 0361 2.0901 2.1262 50 50 0.17795 0.01602 1704.8 1704.8 28.06 1059.7 1087.7 0.0 M 5 2.0391 2.0946 60 60 0.2561 0.01603 1207.6 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 70 0.3629 0.01605 868 3 868 4 633 3 48.04 1048 4 1096 4 0.0932 1.9426 2.0359 80 80 0.5068 0.01607 633.3 2.0086 60 468.1 58.02 1042.7 1100.8 0 1115 1.8970 SC 0.6981 0.01610 468.1 100 350.4 68 00 1031.1 1105.1 0.1295 1.8530 1.9825 100 0.9492 0.01613 350.4 77.98 1031.4 1109.3 0.1472 1.8105 1.9577 110 110 1.2750 0.01617 265.4 265.4 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 120 1.6927 0.01620 203.25 203.26 97.96 1019.8 1117.8 0.1817 1.7295 1.9112 130 130 2.2230 0.01625 157.32 157.33 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 140 140 2.8892 0.01629 122.98 150 97.07 117.95 1008.2 1126.1 0.2150 1.6536 1.8686 150 3.718 0.01634 97.05 160 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 4.741 0.01640 77.27 62.06 137.97 996.2 1134.2 0.2473 1.5822 1.8295 170 170 5.993 0.01645 62.04 180 50.22 148.00 990.2 1138.2 0.2631 1.54S0 1.8111 180 7.511 0.01651 50.21 100 40.96 158.04 984.1 1142.1 0.2787 1.5143 1.7934 190 9.340 0.01657 40.94 200 33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200 11.526 0.01664 33.62 210 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 14.123 0.01671 27.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01672 26.78 26.80 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 220 17.186 0.01678 23.13 230 19.381 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 20.779 0.01685 19.364 240 e 16.321 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 24.963 0.01693 16.304 250 '
13.819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 29.825 0.01701 13.802 228.76 938 6 1167.4 0.3819 1.3043 1.6862 260 260 35.427 0.01709 11.745 11.762
.238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 270 41.856 0 01718 10.042 10.060 249.17 924.6 1173.8 0.4098 1.2501 1.6599 280 280 49.200 0.01726 8.627 8.644 259.4 917.4 1176.8 0.4236 1.2238 1.6473 290 290 57.550 0.01736 7.443 7.460 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 300 67.005 0.01745 6.448 6.466 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 310 77.67 0.01755 5.609 5.626 290.4 894.8 1185.2 0.4640 1.1477 1.6116 320 320 89.64 0.01766 4.896 4.914 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 340 117.99 0.01787 3.770 3.788 360 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 153.01 0.01811 2.939 2.957 380 353.6 844.5 1198.0 0.5416 1.0057 1.5473 340 195.73 0.01836 2.317 2.335 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 400 247.26 0.01864 1.8444 1.8630 420 30S.78 0.01894 1.4808 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 440 t l
419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 381.54 0.01926 1.1976 1.2169 460 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 466.9 0.0196 0.9746 0.9942 464.5 739.6 1204.1 06648 0.7871 1.4516 41>0 450 5662 0.0200 0.7972 0.8172 487.9 714.3 1202.2 0.6890 0.7443 1 4333 500 500 680 9 0.0204 0.6545 0.6749 520 512.0 687.0 1199 0 0.7133 0.7013 1.4146 520 812.5 0.0209 0.5386 05596 540 536 8 657.5 1194.3 0.7378 0.6577 1.3954 540 962.8 0.0215 04437 0 4651 560 0.3871 562.4 625.3 1187.7 0.7625 0.6132 1.3757 5E0 1133.4 0.0221 0.3651 1.3550 580 0.3222 589.1 589.9 1179.0 0.7876 0.5673 580 1326.2 0.0228 0.2994 550.6 1167.7 0.8134 0.5196 1.3330 GOO 0.0236 0.2438 0.2675 617.1 600 1543.2 506.3 1153.2 0.8403 0.46S9 1.3092 620 0.0247 0.1962 0.2208 646.9
$20 1786.9 454.6 1133.7 0.8656 0.4134 1.2821 640 0.0260 0.1543 0.1802 679.1 640 2059 9 1107.0 0.8995 0.3502 1.2458 660 0 0277 0.1166 0.1443 714.9 392.1 660 2365.7 1068.5 0.9365 0.2720 1.2086 680 l 0.0304 0.0808 01112 758 5 310.1 640 2708.6 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 700 3094.3 0 0366 0.0386 0 0752 705.5 906.0 0 9060 1.0612 0 1.0612 705.5 32032 0.0508 0 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
Volume ft'pt> Lithelpy. Stu/lb Extripy. Stu/h a F Energy. Stu/lb Press lemP Evap Steam Waler Evap Steam Water Evep Steam Water Steam P "
Water pe4a pale F hy hg h, s, sq s, og e,
't 'M 's 0.0ss6 32.018 0.01602 3302.4 3302 4 0 00 1075.5 1075 5 0 2 1872 2.1872 0 1021.3 0.0886 0,10 35.023 0.01602 2945.5 29455 3 03 10738 10768 0 0061 2.1705 2.1766 3A3 1022.3 0.10 0.1b 4E453 0 01602 2004 7 2004 7 13 50 1067.9 10814 0 0271 2 1140 2 1411 13.50 1025 7 0.15 0.20 53.160 0 01603 1526.3 1526 3 21.22 1063 5 1084 7 0 0422 2.0728 2.1160 21.22 10283 0.20 <
0.30 (4 484 0 01604 1039 7 1039.7 32.54 1057.1 1089 7 0 0641 2 016S 2.0809 32.54 1032 0 0.30 0.40 72 869 0 01606 792.0 792.1 40 92 1052.4 1093.3 0.0799 1.9762 2.0562 40.9t 1034.7 0.40 0.5 79.5S6 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 8521E 0 01609 5400 5401 53 25 1045 5 1093 7 01028 1.9186 2.0215 53 24 1038 7 0.6 0.7 90 09 0 01610 465 93 466 94 5B 10 1042 7 1100 8 0.3 1 8966 2.0093 58.10 1040.3 0.7 0.8 94.38 0.01611 411.67 411.69 62.39 1040 3 1102.6 01117 1.8775 1.9970 62.39 1041.7 0.8 '
O.9 98.24 0.01612 368 41 368 43 66 24 1038.1 1104.3 01264 1.8606 1.9870 66.24 1042.9 0.9 1.0 101.74 0.01614 333.59 333 60 69.73 1036.1 1105 8 0.1326 13455 1.9781 69.73 1044.1 1.0 2.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116 2 0.1750 1.7450 1.9200 94A3 1051A 2.0 3f 14147 0.01630 118 71 118 73 109.42 1013 2 1122 6 0.2009 1.E854 1.8864 109.41 1056.7 8.0 4.0 152.96 0.01636 90 63 90 64 120.92 1006 4 1127.3 0.2199 1.6428 1.8626 120.93 1060.2 4.0 5.0 162 24 0.01641 73.515 73.53 130 20 1000 9 1131.1 0.2349 1.6094 13443 130.18 1063.1 5.0 6.0 170.05 0.01645 61.967 61.98 138 03 996.2 1134.2 0 2474 15820 1A294 138.01 1065 4' 6.0 7.0 176 84 0.01649 53 634 53 65 144 83 992.1 1136 9 02581 1.5587 1.8168 144.81 1067.4 7.0 80 182 86 001653 47.328 47.35 150 87 988.5 1139 3 02676 1.5384 1A060 15034 1069.2 8.0 9.0 1Sa 27 0 01656 42.385 42 40 156.30 965.1 1141.4 02760 1.5204 1.7964 156.28 1070 8 94 10 193.21 0.01659 38 404 38 42 161.26 982.1 1143.3 0 2836 1.5043 1.7879 161.23 1072.3 10 14.696 212.00 0 01672 26.782 26 83 183 17 970.3 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 20 087 196 27 960 1 1156.3 0.3358 1.3962 1.7320 19621 1082.0 to 30 250 34 0 01701 13 7266 13 744 218 9 945.2 1164.1 0 36S2 1.3313 1.6995 2185 1087.9 30 40 26725 0 01715 10 4794 10 497 236.1 , 933 6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 50 261 02 0.01727 8 4967 8 514 253.2 923 9 1174.1 0 4112 1.2474 1.6585 250.1 1095.3 S0 60 292 71 0.01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1.6440 262.0 1098 0 60 70 302.93 0.01748 6.1875 6 205 272.7 907.8 1180 6 04411 1.1905 1.6316 272.5 11032 70 80 312 04 0.01757 5 4536 5 471 232.1 ^ 900.9 11831 0 4534 1.1675 1.6208 281.9 1102.1 to 90 320 28 001766 4.8777 4 895 293 7 894 6 1185.3 04643 1.1470 1.6113 293.4 1103.7 90 100 327.82 0 01774 4.4133 4.431 298.5 888.6 1187.2 0.4743 1.1284 16027 298 2 1105.2 100 120 3C 27 0 01789 3 7397 3 728 312 6 877.8 11934 0 4919 1.0960 1.5679 312.2 1107 6 120 140 353 04 0 01833 32310 3 219 325 0 858 0 1193 0 0 5071 1 0681 15752 324 5 1109.6 140 160 363 55 0 0;815 2 6155 2 834 3361 859 0 11951 05205 1.0435 1.5641 335.5 1111.2 360 180 373 08 0 01827 2.5129 2.531 346 2 850 7 1196.9 0 5328 10215 1.5543 345.6 1112.5 180 200 35180 0 01839 2.2639 2 287 355.5 842.8 1198.3 0 5438 10016 1.5454 3542 1113.7 200 250 40097 0 01E65 1.8245 1.8432 3761 825 0 1201.1 0.5679 0 9585 1.5264 375.3 1115.6 250 300 417 35 0 01859 1.523B 1.5427 394 0 808 9 1202.9 0SSB2 09223 1.5105 392.9 1117.2 300 350 C- 1.73 001913 1.3064 1.3255 4098 794 2 1204 0 0 60M 08939 1.4968 409 6 11IB ! 350 400 444 60 0.0193 1.14162 1.1610 424 2 760 4 1204 6 0 6217 0 8630 1.4647 422.7 111E7 400 450 456 28 0 0195 1.01224 1.0318 437.3 767.5 1204.8 06360 0 8378 1.4738 4351 1118.9 450 500 46701 0 0193 0 90787 09276 449 5 7551 1204 7 06493 0 814S 1.4639 447.7 1118 8 500 553 47{.94 0 0199 0 82183 0 8412 460 9 743 3 1204 3 06611 07936 1.4547 456.9 1118 6 550 E00 48520 0 0201 074962 07693 471.7 732.0 12037 06723 07738 1.4461 469 5 1116 2 600 703 .502 08 ! 00205 063505 0 6556 491.6 710 7 1M18 0692R 07377 1.4304 ASS 9 1116 9 700 833 518 21 0 0239 054809 05690 509 8 V> 1169 4 0 7111 07051 1.4163 506 7 1115.2 800 900 DI 93 0 0212 0 4796S 05009 526 7 G; c. ~ 119o 4 0 7279 06753 1.4032 5232 1113 0 900 l 2000 544.5B 0 0216 0 42435 0 4460 50 f Mt' . 1192.9 0 7434 06476 1.3910 5306 1110 4 1000 1100 555 2e 0.0220 0 378f 3 0 4006 5. f. S 3. a 1189 1 0 7573 0 6216 1.3794 5531 1107.5 1100 3200 ,7.19 0 0223 0 34013 0.3625 57. s t, s . a 1184 8 0.7714 0 5969 1.36S3 5569 1104 3 1200 1300 l:577.42 0 0227 030722 0.3299 585 6 594 6 1180 2 0.7843 05733 1.3577 580 1 1100 9 1300 1400 537 07 0 0231 0 27871 0 3018 59B 8 576L I175 3 0 7966 0 5507 1.3474 592.9 1037.1 1400 1500 59620 00235 02b372 0.2772 611.7 558 4 I1701 0.8035 0 5253 1.3373 605 7 10931 1500 2000 635 80 0 02',7 0 167 % 01883 6721 4652 1133 3 08 m 04256 1.7b81 662 6 1003 6 2000 2500 66$11 0 02c,f 010209 01307 731 7 3616 1093 3 0 9139 03206 1,2345 718 5 1032.9 2500 3000 695 33 0 0343 0 050/3 0 0850 831 8 218.4 1070 3 0 9723 01891 1.1619 7823 973.1 3000 3298.2 701 47 0 0503 0 0 050d 906 0 0 906 0 1 0612 0 1 0612 875 9 875 9 370s.2 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE)
A.4
Empectm, F Abs press.
lbM la. 300 400 900 000 700 000 900 1000 1100 1200 1300 1400 1500 (sat. temp) 100 200 e 0 0161 392 5 452.3 611.9 571.5 631.1 490 7 3 A G8 00 11502 lith 7 1241.8 1288 6 13361 13845 (101.74) s 0.1295 2.0b09 2.1152 2.1722 2.2237 2.2708 2J144
, 0 0161 78 14 90 24 102 24 114.21 126 15 138 08 150 01 ~ 16194 173 86 185 78 197.70 200 62 221.53 6 h 68 01 1143 6 1144 8 1241.3 !?88 2 1335 9 1384 3 1433 6 14&3 7 1534 7 1586 7 1639 6 1693 3 1748 0.1795 1.8716 ,1.9369 1.9943 2.0460 2 0932 2 1369 21776 2 2159 2 2521 2.28 % 2.3194 23509 2.3811 2.4101 (162.24) s
, 00161 38 F4 44 93 51 03 57.04 63 03 60 00 74 98 30 94 86 91 92 87 98 84 104 80 110 76 116 72 30 6 68 02 1846 6 1193 7 12406 1210.8 1335 5 13840 1433 4 14B3 5 1534 6 1586 6 16395 1693.3 1747.
(192.21) s 01295 13926 1.8593 1.9173 1.9592 2 0166 2.0t03 2.1011 2 1394 2 1757 2 2101 2 2430 2.2744 2.3 e 00161 0 0166 29 899 33 963 37.995 41966 45.978 49 % 4 53 946 57.926 61 905 65 882 69458 73 833 7 35 4 68 04 168 09 11925 1239 9 1287.3 13352 1383 8 1433 2 1483 4 1534 5 1586 5 1639 4 16932 1747.8 1 (213.03) s 0 1295 0.2940 1 8134 1.8720 1.9242 1.9717 2.0155 2.0563 2.0946 2 1309 2.1653 2.1982 2.2297 2.2599 2 e 0 0161 0 0166 22356 25428 28 457 31 466 34 465 37.458 40 447 43 435 46 420 49 405 52 388 55.370 20 4 68 05 168 11 1191.4 1239.2 1286.9 1334.9 1383 5 1432 9 1483 2 1534 3 1586 3 1639 3 1693.1 1747 (227.96) s 0 1295 0.2940 1.7805 1A397 1.8921 1.9397 1.9836 2.0244 2 0628 2.0991 2.1336 2.1665 2.1979 2.22
, 00161 0 0166 II 035 12 624 14.165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26183 27.6 40 4 68 10 168 15 1186 6 1236.4 1285 0 1333 6 1382.5 1432.1 1482.5 1533.7 1585 8 16368 1992 7 1747 (267.25) s 0.1295 02940 1.6992 1.7608 1.8143 1.8624 1.9065 1.9476 1.9860 2.0224 2.0569 2.0899 2.1224 2.1 e 0.0161 0 0156 7.257 8 354 9 400 10 425 11435 12 446 13 450 14 452 15 452 16.450 17.448 18.445 1 60 & 68 15 16S 20 1161 6 1233 5 1283 2 1332 3 1381.5 1431.3 1481 8 1533 2 1555 3 1638 4 1692 4 1747 (29231) s 0.1295 0.2939 1.6492 1.7134 1.7681 1.8168 13612 1.9024 1.9410 1.9774 2.0120 2.0450 2.0765 2.106 8560 9.319 10 075 10 829 11 581 12.331 13.081 13.829 14.577
, 0 01'61 0 0166 0.0175 6 218 7.018 7.794 40 & 68 21 168 24 269 74 1230 5 1281 3 13309 1380 5 1430 5 1481.1 1532 6 1584 9 1638 0 1692.0 1746 8 180 (312.04) e 0.1295 0 2939 0 4371 1.6790 1.7349 1.7842 1.8289 1 8702 1.9089 1.9454 1.9800 2.0131 2.0446 2.0750 2.1 7.443 8050 8 655 9.258 9 860 10 460 11.060 11.659 e 0 0161 0.0166 0 0175 4 935 5 585 6 216 6.833 100 h 68 26 168 29 269 77 1727.4 1279 3 1329 6 41379 5 1429 7 1480 4 1532.0 15844 1637.6 1691.6 1746.5 (327.82) s 0.1295 0 2939 04371 1.6516 1.7083 1.7586 1.8036 1 3451 1.8339 1.9205 1.9552 1 9883 2)D199 2.0502 2
, 0 0161 0 0166 0 0175 4 0786 4.6341 5 1637 56831 6 1929 6 7006 7.2060 7J096 82119 83130 9.2134 9.713 120 A 68 31 168 33 269 81 1224.1 12774 13281 13784 1428 8 1479 8 1531.4 1583 9 1637.1 1691J 17462 1 (341.27) s 0.1295 0 2939 0 437!
1.6286 1.6872 1.7376 11829 1A246 13635 1 9001 1.9349 1.9680 1.9996 2.0300 2 v 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 7.8946 140 6 68 3' 168 38 26585 1220 8 1275 3 1326 8 1377.4 1428 0 1479 1 15308 1583 4 1636 7 1690 9 1745 9 (353 04) s 0 1295 0 2939 0 4370 1 6025 1 6686 1.7196 1.7652 1 8071 1A461 1 8828 1.9176 1.9503 1.9825 2.0129
, 00161 0 0166 0 0175 3 0060 3 4413 3 8480 4 2420 46295 5 0132 5 3945 5 7741 61522 6 5293 '6 9055 360 6 68 42 168 42 269 89 1217 4 1273 3 1325 4 1376 4 1427.2 1478 4 1530 3 1582.9 1636.3 1690.5 1745 6 (363 55) s 0.1294 0 2936 0 4370 1.5936 1.6522 1.7039 1.7499 1.7919 1 8310 13678 1.9027 1.9359 1.9676 1.998
, 0 0161 0 0166 0 0174 2 6474 3 0433 3 4093 3.7621 4.1064 4 4505 4.7907 5.1289 5 4657 5 3014 6.I36 i
180 h 68 47 165 47 2609/ 1213 8 12712 13?4 0 1375 3 1426 3 1477.7 1529 7 1582 4 1635 9 1640 2 17 53 (373.05) : C l294 0.2938 04370 1 5743 1.6376 1.6900 1 7362 13784 1.8176 1 8345 1.8894 1.9227 1 9545 1.96 l
, 0OlEl 00166 0 0174 23598 2.7247 3.0583 3 3783 3 6915 4 0008 4 3077 4.6128 4.9165 52191 5.52 200 e 68 52 168 51 269 94 12101 12690 1322f 1374 3 1425 5 1477.0 15291 1581.9 1635 4 1689 8 1745 0 (35i 60) : 01294 0 293S 04359 1.5593 1.6242 1.6776 1.7239 1.7663 18057 18426 1.8776 1.9109 1.9427 1.97
, C(161 0 0166 0 0174 00166 7150' 2 4667 2 6872 2.9410 3 1909 3 4382 3 6837 3 9278 4 1709 - 4 4131 4 250 e 68 65 166 63 270 05 3/510 1263 5 1319 0 1371 6 1423 4 1475 3 15216 1580 6 16344 16889 17442 18 0 1294 02937 0 4355 0 5567 1.5951 1 6502 1.6976 13405 1 7601 1 8173 1 8524 1.8d58 1.9177 1.9482 1
(400 97) s f
e 0 0161 00165 00174 0 0186 1.7665 2 0044 2 2263 2A407 2.6509 2 6555 3 0643 3 2688 3 4721 3 6746 300 A 66 79 155 74 27014 375.15 1237 7 13152 1368 9 I421.3 1473 6 1526 2 1579 4 1633 3 1688 0 1743 4 1 (417.35) : 0.1294 0 2937 0 4337 0 5665 1.5703 1.6274 1.6758 1J192 13591 1.7964 1A317 1.8652 13972 1.9278 1 e 0 0161 0 0166 0 0174 0 0186 1 4913 1 7028 1 897') 2 0332 2 2652 24445 2.6219 2.7980 2.9730 3.1471 350 a 68 92 163 85 270 7? 37521 1251 5 1311 4 1366 2 1419 2 1871 8 1524 7 1578 2 1632.3 1667.1 1742 (431 73; 01293 0 29 % 04357 0 568,4 1.5483 1.6077 1.6571 13009 1.7411 13787 1 8141 1A477 1279S 1.9:05 1 r 0 0161 0 0166 0 0174 0 0162 1 2841 1.4763 16493 1.8151 1 9759 21339 2 2901 2.4450 2.5987 2351 400 m 69 05 16847 270 33 375 27 1245 1 1307.4 1363 4 1417.0 14701 1523 3 1576 9 1631 2 1636 2 17419 (444 60) s 31293 02935 0 4365 0 56G3 1.5282 1.5901 1 6406 1.6850 1 7255 17632 13988 1.8325 12647 1.8955 e 0 0161 0 0166 0 0174 0 0186 0 9919 1.1584 13037 1.4397 1.5708 1 6992 1.8756 1.9507 2.0746 2.1977 500 h 69 32 169 14 270 51 3?5 3B 12311 12991 13573 tel? 7 1466 6 1520 3 1574 4 16291 1684 4 1740 3 1 (457.01) s 0 1292 02934 04364 0 5t60 1 4971 15595 1 6123 1 65/8 1 6090 17371 13730 1.8069 18393 1 8702 1 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)
- - _ _ _ . _ . . _ _ _ . _ _ _ ___a.3
m p,,n, Emperaler; F C/Mim (ul. lemp) 100 200 300 400 600 600 700 800 900 1000 1100 I200 1300 1400 1500 v 00161 0 0166 0 0174 0 0186 0 7944 094% 10726 31892 1.3008 14093 1 5160 16713 1.7252 1 8284 1.9309 600 4 69.58 169 42 270 70 37b49 (48620) s 0.1292 0.2933 0 4362 0 %57 1215 9 1290 ? 1351 8 I408 3 3463 0 1517 4 1571 9 1627.0 16826 1738 8 1795 6 14590 1.5325 1.5444 1.6351 16769 1 72n 17517 1 3s59 13184 14494 lay 9; e 0 0161 0 0166 0 0174 0 0185 0 0702 0 7928 0 9072 1.0102 1.1078 1 2023 1 2948 1.3858 14757 15647 16530 700 6 69 04 169 65 270 89 375 61 487 93 1281 0 1345 6 1403 7 14b9 4 1514 4 1%94 1624 8 1660 7 1737 2 1794 3 (503 Cs) s 0 1291 0.2932 04360 0 % 55 06809 1.5090 3.% 73 1 6154 1.6580 16970 17335 17676 1 Sch I8318 I8617 e 0 0161 0 01b& 0 0174 0 0186 0 0704 0 6774 0 7823 0 8759 0 9633 1 N70 1 1789 12093 128?5 13669 1.4446 300 h 70 11 169 88 271.07 375 73 487.88 1771 1 13392 13991 1455 8 15114 1566 9 16227 167E 9 17h 0 1792 9 (5182.)
~~0.1290 02930 0 4358 05652 0 6885 14669 I5484 1.59S0 16413 16807 13375 17522 17653 IB164 1 8464~~
, 0 0161 0.0166 0 0174 0 0186 0C234 0 5869 0 6858 0 7783 0 8504 0 9262 0 9998 1 0720 1 1430 1 2131 1.2825 900 6 70 37 170 10 271.26 375.84 487.83 1260 6 1332 7 1394 4 1452 2 15C8 5 1564 4 1620 6 16771 17341 1791 6 (531.95) s 0 1290 0.2929 0 4357 0.5649 06881 1.4659 1.5311 1.5822 16263 16662 1.7033 1.7382 3.7713 16028 13329 e 0 0161 0 0166 0.0174 0 0186 0 0204 0 5137 06080 0 6875 07603 08295 0 8966 0 % 22 1.0266 1.0901 1.1529 1000 6 70.63 170 33 271.44 375.96 487.79 1249 3 1325 9 1389.6 1448 5 1504 4 1561.9 1618 4 1675 3 1732.5 1790 3
($44.58) s 0.1269 0.2928 04355 0.5647 0.6876 1.4457 1.5149 1.5677 1.6126 16530 1.6905 1 7256 3 7589 1.7905 1.8207 e 00161 0 0166 0 0174 0.0185 0 0203 04531 0 5440 0 6188 06865 0 7505 0 8121 0 8723 0 9313 0 9894 1.0468 1100 4 70 90 170 % 271 63 376 08 48735 1237 3 13188 1384 7 14443 1502 4 1559 4 1616 3 1673 5 1731 0 1769.0 (55628) s 0.1269 0.2927 0.4353 0.5644 0.6872 1.4259 1.4996 1.5542 16000 1.6410 1.6787 1.7141 13475 1.7793 1.8097 e 0 0161 0 0166 0.0174 0 0185 0 0203 0 4016 0 4905 0.5615 0 6250 0 6815 0 7418 07974 08519 0.9055 0 9554 1200 4 71.16 170.78 271.82 376 20 487.72 1224 2 1311.5 13793 1440 9 14494 1556 9 1614 2 16716 1729 4 1787.6 (5e7.19) s 0.1288 02926 0 4351 0.5642 0.6668 1.4061 1.4851 1.5415 1.5883 16298 16679 13035 1.7371 1.7691 1.7996 e 00161 0 0166 0 0174 0 0185 0 0203 0.3176 0 4059 0 4712 05282 0 5809 0 6311 0 6798 0 7272 03737 0 8195 1400 4 71.68 171 24 272 19 376 44 487.65 1194 1 12961 1369 3 1433 2 1493 2 1551 8 1609 9 1668 0 1726 3 17850 (587.07) s 0.1287 0.2923 0.4348 0.5636 0 6859 1.3652 1.4575 1.5182 1.5670 16C96 1.6434 16845 1.7185 1.7508 1.7815
0.0161 0 0166 0 0173 0 0185 0 0202 0.0236 0.3415 0 4032 0 4555 0.5031 0 5482 0 5915 0 6336 0 6748 0.7153 1600 4 72 21 171 69 272.57 376 69 487.60 61E77 12794 1358 5 1425 2 14EC 9 1546 6 1605 6 1664 3 17232 1722 3 (6C4 87) s 01266 0 2921 0 4344 0 5631 0.6851 0 8129 14312 1 4963 1.5478 1.5916 1 6312 1 6678 13072 1.7344 1.7657 e 0 0160 0 0165 0 0173 05185 0 0202 0 0235 0 2906 0 3500 0 3988 0 4426 0 4836 0 5229 0 5609 0 5980 0 6?43 1800 a 7233 172.15 272.95 376 93 487.56 615 58 1261.1 1347.2 1417.1 1480 6 1541.1 1601.2 16607 1720.1 1779 7 (621/12) s 0.1284 0.2918 0 4341 0 5626 0.68*3 0 8109 1.4054 1.4768 1.5302 1.5753 1 6156 1.6528 1 6876 1.7204 1.7516 e 0 0160 0.0165 0.0173 0 0184 0 0201 0 0233 02488 0 3072 0 3534 0.3942 0 4320 0 4680 0.5027 0 53f 5 0 5695 2000 6 73 26 172 60 273 32 377.19 487 53 6144E 1240 9 13534 1408 7 14471 1536 2 1596 9 1657.0 1717 0 1777.1 (635 BD) : 01263 0 2916 0 4337 05621 0 6834 06091 1.3794 14578 1.5138 1.5653 1.6014 1.6391 1.6743 1.7075 1.7359 e 0 0160 0.0165 0.0173 0 0184 0.0200 0 0230 01681 0 2293 0?712 0.30f 8 0 3390 0 3692 0.3930 0 4259 0 4529 2500 6 74 57 173 74 274.27 377.82 487.50 612.08 1176 7 1303 4 1386 7 14575 1522.9 1585 9 1647.8 1709 2 1770 4 (668.11) s 0.1280 0.2910 0 4329 0.5609 0.6815 0 8048 1.3076 1.4129 1.4766 1.5269 1.5703 1.6094 1.6456 1 6796 1.7116 e 0 0160 0.0165 0 0172 0 0183 0 0200 0.0228 0 0982 0 1755 0.2161 02484 0.2770 0 3033 0 3282 0 3522 0.3753 3000 h 75E3 17t88 27522 378 47 487.52 610 06 10$0 5 1267 0 1363.2 1440 2 15014 1574.8 1635 5 17014 17(1.8 (E95.33) : 0.1277 0 29J 0 4320 0.5597 0 6796 0 8009 1.1966 1.3692 1.4429 1.4975 1.5434 1.5641 1.62P I.6561 1.6688 e 0 0160 0 0165 0.0172 0.0183 0 0199 0 0227 0.0335 0 1588 0 1987 0.2301 0 2576 0 2827 0.306% 03291 0.3510 3200 A 76 4 175 3 275 6 378 7 487.5 609 4 800 8 12509 1353 4 1433.1 1503 8 1570 3 16343 1698 3 1761.2 OO5 CE s C1276 0 2902 0 4317 0.5592 0 6768 0 7994 0 9708 1.3515 1.4300 1.48 % 1.5335 1.5/49 IJ6126 1.6477 1.6806 e 0 0160 0 0154 0 0172 0 01E3 0 0199 0 0225 0 0307 0 1364 01764 0 20E6 02326 0 2563 0 2784 0 2995 0.319' 3500 6 77.2 176 0 276.2 3791 487.6 606 4 779 4 1224 6 1338 2 1422 2 1495 5 1563 3 16292 1693 6 17b7.2 s 0.1278 02899 0 4312 0 5585 0 6777 03973 0 9508 1.3242 1.4112 1 4709 1.5194 1.5618 1.6002 11353 1.6691 e 0 0159 0 0164 0 0172 0.0182 0 0198 0 0223 00287 0.1052 0 1463 01712 0 1994 0 22to 0 2411 0.2601 0 2783 4000 h 76.5 177 2 277.1 379.8 487.7 606 5 7630 1174.3 1311.6 1403 6 1481.3 1552.2 1619 8 16653 1750 6 s 01271 0.2893 0.4304 0.5573 0 6760 0 7940 0 9343 12754 1.3807 3.4461 1.497G 1.5417 1.5812 3.6177 1.6516 e 0 0159 0 0164 0 0171 0 0181 0.01 % 0 0219 0 0268 0.0591 0 1038 0.1312 0 1529 0 1718 OlS*0 0 2050 07203 5000 4 81 1 179 5 2791 381.2 488.1 604 6 746 0 1042 9 1252.9 13(a 6 1452 1 15291 1600 9 1670 0 1737.4 s 0.1265 0.2E61 0 4267 0.5550 0 6726 01880 0 9153 1.1593 1.3207 I.4001 1.4582 1.5061 1.'A81 1.5663 1.6216 e 0 0159 0.0163 0 0170 0 0160 0 0195 0 0216 0 0256 0 0397 0 0757 0.1020 0 1221 0.1391 0.1544 0 1684 0 1817 60C0 4 63.7 1813 281.0 3b2 7 APS 6 602 9 7363 9451 1168 8 1323 6 1422 3 1505 9 1562 0 1654 2 1724?
e 01258 0.2670 0 4271 05528 06693 07826 0 9026 1.0176 1.2615 1.35.N 1.4229 1.4743 1.5194 1.5593 1590.2 e 0.0158 0.0163 00170 0 0180 0 0193 00?!3 0 0248 0 0334 0 0573 0 031 A 01004 0 1160 0129E O1424 0.1542 7000 & 862 184 4 283 0 384 2 489 3 601 7 729 3 901.8 1124 9 1281 7 13922 1482.6 15631 1639 6 1711 1 s 01752 0 2859 04256 05507 06563 0 7/77 0 8926 10350 12055 131)I 11904 144v6 14938 1.53-5 1.5735 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED)
A.6
,,; . ,, , , , , , . , , ?m' , ,
3,,,
,- - r i h,,,, / , M,ml /, ,,,. , N, -
y, s
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,,,, A /M,TA / M // N 7x ! / hl/ i o'*
aid 5S( /K i N//I%
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FIGURE A.5 MOLLIER ENTHALPY-ENTROPY DIAGRAM A.7
_ _ __ _ .____ _ _ ____ _._ .-- .__.. -_ _ .__ _..._ _ __-._____=__- _ _ -.- - - _. -
PROPEL 4 TIES OF WATER r
Density c (Ibslil')
PSIA Temp Saturated 2400 2500 3000 2000 2100 2200 2300
(*F) Liquid 1000 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 50 62.38 62.55 62.465 62.559 62.390 62.409 62.427 62.446 100 61.939 62.185 62.371 60.568 60.587 60.606 60.702 60.314 60.511 60.53 60 549 200 60.118 57.859 57.882 57.998 57.537 57.767 57.79 57.813 57.836 300 57.310 54.373 54.529 54.249 54.28 54.311 54.342 400 53.651 53.903 54.218 53.89 53.925 53.95 64.11 53.475 53.79 53.825 53.86 410 53.248 53.50 53.53 53.69 53.025 53.35 53.40 53.425 53.46 420 52.798 53.09 53.265 52.95 52.99 53.02 53.065 430 52.356 52.575 52.925 52.51 52.54 52.56 52.275 51.921 52.125 52.42 52.45 52.475' 440 52.175 52.21 52.41 51.66 52.025 52.065 52.10 52.14 450 51.546 51.725 51.76 51.96 51.56 51.61 51.64 51.68 450 51.020 51.175 51.50 51.175 51.22 51.25 51.30 470 50.505 50.70 51.1 51.14 50.74 50.78 50.825 51.035 50.20 50.62 50.66 50.7 480 50.00 50.31 50.35 50 575 1
49.685 50.13 50.175 50.22 50.265 4DG 49.505 49.658 50.098 49.618 49.666 49.714 49.762 49.81 500 48.943 49.097 49.305 49.56 49.101 49.152 49.203 49.254 510 48.31 48.51 49.05 49.01 48.57 48,625 48.68 48.735 47.85 47.91 48.46 48.515 520 48 037 48.096 48.155 48.45 47.29 47.86 47.919 47.978 530 47.17 47.494 47.56 4729 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 4356 44.11 44.205 44.68 43.73 43 825 43.92 44.015 i 533 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 42.314 610 41.49 41.483 41.616 42283 40.950 41.083 41.217 41.35 620 40.552 41 44 530 39.53 40.388 640 38491 39.26 650 37.31 38.000 660 36.01 36.52 670 34.48 34 030 t
683 32.744 32.144 690 30.516 f
TABLE A.6 PROPERTIES OF WATER, DENSITY i
i
- A.8
1. PRIllCIPLE5 0F NUCLEAR POWER PL ANT OPERATION, PAGE 26 THERMODYNAnICG, HEAT TRANSFER AND FLUID FLOW ANSWERS -- SEGUOYAH 1&2 -55/11/12-DEAN, WH ANSWER 1.01 (1.00) d REFERENCE westinghouse Reactor Physicsr Section I-5r _H T C and Power Defect DPC, Fundsmentsis of Nuclest Resctor Engineering 039/000; A2/05(3.3/3.6)
AN5 WEE 1.0; (1.00)
.c EEFERENCE Westinghouse Nuclear Trainin3 Operstions, pp. I-4.19 - ~1 001/010; 1:5.16 ( 2 . 9. ' 3 . 5 :n ANSWER ~ L.03 :1.50) s' Oec ease '+.5
. es) 3' O.e c t .: .s s e 1, . : : sesa
~~r e _ p. .r. y c. .e_~~
.t. .
+>clesr Pcwer Fisnt C?ars cr Trr3 P r 3 r :a r HTFF snc hermor Sect ZE App f. F umps / Centr tivpl . Ponp :nstacteristic r el st t on shi; s t1.6s2.s>
c , e, un Na .n.
, c r. .
t .., L >U-
~~1. n, c r e ncgsti.c~~
~. \ seis :n .j + T u e Ii ~. e 2 5 negst;ve F.E F E 'i E 9 C E rJ U S - Val 3 unit .1 2aN/ WEN' License Cert trng- 'Resc. tit: ::efr:ctents' 001<000: P:5.4~ : 3.4/3.-)
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1. PRINCIPLES 0F NUCLEAR POWER PLANT OPERATION. PAGE 27 THERMODYNAMICS, HEAT TFANSFER AND FLUID FLG4 ANSWERS -- SEQUOYAH 1&2 -G 5 /11.' 12 -D E A N , 4M ANSWER 1.05 (2.50)
~~1) Lower (Higher Sta Flow P stm aecresses)~~
~~2) Higher (Less resistance tc flow Other RCPs speed up)~~
~~3) Lower :Less total ficw scross core delts T incresses, Tc 3ces down with rods in manus 1t 43 Higher 'ss aboser delts T incresses. Th increases)~~
~~5) Esme (Primary power = secondsty load)~~
~~CEFERENCE NUS, Vol 4r Units 1.3, 3.2 ANSWER 1.06 (Z.00)~~
~~1) Higner (Tavs increases sdos r e3stive res:tisit;)~~
~~2) Lower (Tav3 decresses cue tc :cla feeowater :adition)~~
~~3) No effect~~
~~1) Higher '(enen concen- stion incrssacs addin 3 ne 3stive reactivitv)~~
R EF E:: ENC E
'4 U 3 'J C l le U r. i t I1
, . , , . . a. , - . I ,.s.--
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. .es. .,
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A f 8 5 U E I !.0~ (I 50}
~~s. 5:3:*erse 4.5 es.~~
~~Oi I. acre 5se~~
~~) Se'! ?Ee N>ciesr Fower ^'snt Trn3 Fr 3rc.. d T F .C a r.d T . e r .a a . .ec t :~~~
Ap? A' WGr b ing I T3F-' ties of d
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't. PRINCIPLE 3 0F-NUCLEAR POWER FLANT OPERATION, PAQE 25 THERMODYNAMIC 3, . HEAT TRANSCER AND FLUID FLOW ANSWERS -- SEGUOYAH 1&C -35/11/12-DEAN, Wn ANSWER- 1.08 (2.00 a) Decrease (*.5 es) b) Increase c) Incresse d) Incresse REFERENCE SON /WBN License Requal irsining, ' Core Poisons' 001/000; K5.09 (3.5/3.7) & K5.02 (2.9/3.4) & K5.10 (3.9/4.1)
ANSWER 1.09 (1.50) s) Convection (+.5 ea) c') Radiation oc (o w ecklm c .i Conduction REFERENCE Nuclear Power Flsnt Orser Trng Frjm, HTFF & Thermo, pp 193-206 002/000; V.5.01 (3.1'3.4 ANSWER 1.10~ : 1. C :
He=t source- d o w ri s t r e s n, (+.5 es Heat sink- upstresm PEFERENCE ovulcar Fower ;lant Operstcr Traintnj Prc3rsa. HTFr and Thermo; Iect ZC App A: pumps centiifu3al. N P 3;i(3.4/3.
ANSWER 1,il >
.50)
Euper nested Stesa ' +.5)
R EF F.R E r4 C E 3 *, e s o isole s, ma'11er Disgr sm O*.0J'0IO J U 5 . i) 2 iE.o/3.0'
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~~1. FRINCIPLES OF NUCLEAR POWER PLANT OPERATION, FAGE )~~
THERMODYNAMICS, __--___---_-___-_---_____
HEAT TRANSFER AND FLUI D FLOW ANSWERS -- SEQUOYAH 1&2 -85/11/10-DEAN. 4 ri ANSWER 1.12 (1.50)
Nominal tensile stress (+.5)
Temperature below RTndt (+.5)
Sufficient sized surface d e f e c t -( + . 5 )
REFERENCE 30N TSr E 3/4.4.7 002/000; K5.18 (3.3/3.6i ANSWER 1 13 (1.5Gi
' M (+.25 for isctcpe. .25 for contribution to cower '- ": ' Pu-229 ' .AJh n - w, w U_- a oe . REFERENCE 3GrO WEN L i c ;-n t e Cart Trn3- ' es: tar .inett:3'- pp $ 001/0001 F5.47 ( 2. i . 'I . 4 A r! 9 '- E F !1 1 Tc- 1 r. c i r:1 p wovic ce 1 ? r y- - 1 r. a - rur 1 :- + . 5 .i
C. r~ r. ; '.'. n.j

.- ; c' 4 r - b s;h b e 'JI/ be e '- 6 og 'I, CI9 d1Edni * [*> [/ e WGEtin3h0V'2G duClO3r T T T i n ; ;+ ; , ."s p e sti;n:- pp I-5.~o .. .. y " , , ' ' I I) . . <) I ,, b,. 's e ..*,d- . j . V .' **p t'1 N b d E " 1+'$ . .. - riscc; "' t.. s t :t.d :. ,na- - +- - Jic.e act ' . - ..a .? prectst ~ ' t n *- F. . . . B t e E:Ti y DC i1Iri3 T I t 9 3 lh i*,iL:t1Dn . i'i- ' E ' ". r 9 31 J I-S FF E F El;C E Ne3D'AjhQUse E' U E 3.st6%5 6[- *p . +2-2~ t."7~ ) 1.. 4 . t. h. i+ ..,,; .. ';.b -t . m_.._________ ~

1. PRINCIPLES OF NUCLEAR F0uER P L 4r4 T JPERAT!Gil. FACE 30 THERn0DYNAnICS, HEAT TRANSFER AND FLUID FLOW AN5uERS -- SEQUDYAH 122 -G5 / t i.' t :-DE AN , Wn AN5WER 1.le fl.0!

Bets effective decresses i+.25) que te Fu-239 producia3 more of the core'1 power (+.25) and having a smsller E.ets fraction of approx. .00 0 i. + . 5 ' REFERENCE 30N/uBN Instr. Guider ' H e u t r c c. .- 1, c t i .: s ' - 99 s s01/0c... v, b. ,s.4, f..... - 2 . -. ANSWER 1 . '. T (t.00) > o t.e acorce + . . , ..i a h e r, 3b-123 is e c t 1 . s t.3 d by 3 neotren it produces a 3amas ~+.;5) that irteracts with E.e-9 (+.25) thst procuces Ee-I and another neutron (+.25) REFERENCE 3GN/uBN License Centtficstion Trsinin3, 'Neutton 3curces and 3ubcrt nult' 004/000; K5.0! : :.I/2,E: Ar459EF !.1~ .1.25)

~~At the f u .:.1 Purns c r. t . ' = .cr .: n t; rav.trec. w n : c c. incresses the c.o r o n wcf to - .5 - t M k ti M OWrrdf a%~~
~~be'i f b t b)~~

Zi rissicn procucts but'c u.. cecressin3 he ocrcn w3rth (+.5) *h._ t- +M ,,.u, 'EFERENCE 30fi MEri Li.enis L' e r C IFA3 'CCre EGischi*- . l. 4 ., n. 4 ? , r,u ? . }'c.r2 a : a 4 -ce i. .? . S. .,

~~r. , ,. , ..~~

. .rd. ':. l ic m . r- 2 .A? .i ;V! s> Fatia of Critical Heat Flu: to Local Hett Flu *+.5 es) o S TU/ l bm -c e.3 F(or R) REFEPENCE riuc ie s t Power P i s r. t G;mrstar Trsinin3 Program, 'HTFF end T h e r si o '

~~1. FRINCIPLEE OF NUCLEAR POWER PLANT OPERATION, PAGE 31~~

~ ~ ~~~~iEEEE665EEE1C5~~55IT i53U5F55~5E6~iLE16~EL60 ANSWERS - SEGUOYAH 1&2 -05/11/12-DEAN, Wn 001/000: K5.45 (2.4/2.?) & K5.46 (2.3/3.6) ANSWER 1.20 (1.75) See attached curve REFERENCE Nuclear Power Plant Oper Trng Prgm, HTFF and Thermo, Figure 13, pp 202 002/000; k5.01 (3.1/3.4) . ANSWER 1.21 (1.00) for 2250 psis, sat temp = 652 (+.5) with Tavg = 575, Th = 607 (+.5) 31ve +/- 2 degrees in determintng Th 45 degrees F REFERENCE Steam Tsoles snd 50tl PL3 002/000; A1.04 (3.?/4.1) ~ A rJS W ER 1. :1,00) 1 10000 pen.1: Delta e 2 62-l1 i.16.2 REFERENCE _: G rl REN License Certification Trn3 ' Reactor rtinetics'. op 3 001./000; A1.Os ':4.1/4.4) Arl$WER 1,23 '1.00) nstgin to crititslits decreases by 2. 3 +1.0 9EFERENCE 30N/WGN License Certifi:stian Trng. 'heotrcn sources :no 3vocrttic31 doit' 001,'> 00; H5.19 (4.2/4.3i With the' first " tweak" of the heat control kneb, the partial vapor blankas spreads.ever the entire paa surface. We them find a this layer of steam every-

where es the paa surface. As shawa is a previous table of thessal conductivia ties, steam is an escenest INgu!ATOR; hence, the paa surface new presents an entremely large resistance to heat transfer. Assuming again that the electric heater can llAINIAIN the desired heat flua, we know from the equaties; -

6/A a U(T,,,g - Tg) g that if 6/A is held sonstaat and U decreases drasticany and T is constaat, then 7, g mast increase rather substantia uy (en the order e M 00*T). , If the paa surface had been a inia 1 red in the. reacter core and we nueved fun film boiling to take place, the metal of the faal red might have asised er been - seriously defessed er cracked. Radioactivity would than leak from the damaged . red inta the coelaat with severe ramifications. DirB, transition boiling, and full film boiling are EEVER permitted la an operating reacter mader ordinary , conditions. , Now, we should make a plot of the results of our staple experiment. If the heat fluz is pletted against the temperature difference between the paa sur- , , face and liquid temperature, a figure'similar to the ese below is obtained. , 10' [ ~ C . s 's D 8 %. F

~~5 10 .~~

, ? e , y a , I . .a 4 4 .o 80 , 3 A*3 NATURAL CCNVECTION 3-C NuCLgATE son.mo FCE' ritu non. ins C-F TRANsmeN 90!Lmt A 4e DN3 3 ! ... gg

3

~~- 10 lC lC l0~~

~~AT(Ts.v .Tse:)~~
~~F t~~

~~.. TICURE 18 BOI:.DfG UAT 11 C*:RVE , 202 I~~

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEns FAGE 32 ANSWERS -- SEQUOYAH 1&2 -G5/11/12-DEAN. W H ANSWER 2.01 (1.00) a REFERENCE' GQNP 3ystem Descrip. 'CCW5', pp 7.1-4 009/0001 K1.04 (3.3/3.3)

ANSWER 2.02 (1.00) d REFERENCE FNP, RHR Lesson Flan, pp. 8 &9 NA NCRODP 85.2, 'RHR Eystem' 50NF tesson plan 'RHR 3vstem' pp 5 005/000-M4.07 (3. /3.5) AN3WER 2.03 1.00) -+- b FEFERENCE 5 0 e ;- Lesscn Plan 'CVC3' pp 14 ! A0I-24A ErE-024: PWG-11(J 0'4.0) 8 EAZ.?: i2. :.3, AN3WER 2.04 <!."Oi a> Open .5 .: 2 3 0 ;^ e n

~~) C1csed REF.IRENCE t2 ,:. _;ccr sg.I, 'CvCI=~~

~~50HF AGT-10A. pn 3-5 0~E 000; V 1. 7. : ' : .a/5.e l~~

~~2. PLANT DESIGN INCLUDING-SAFETY AND EMERGENCY 5'fSTEMS PAGE 33~~

~~. ANSWERS -- 3EGUOYAH 1&2 -85/11/12-DEAN, Wh ANSWER 2.05 (1.50)~~

~~a. FALSE 70.5)~~
~~b. FALSE (0.5)~~
~~c. TRUE (0,5)~~

REFERENCE FNP. Hsin Turbine and Aux'liirios- AP. 23 - 3~ . Westinghouse PuF: S y s t e ri s nsneal. 'Tuttine EHC E, stem' pp 3-6 045/000; A3.05 .2.6/2.?> ANSWEP 2.06 (1.00: -RHR Svstem Inlet f+.25 es) -Leop Drsin Lines -Differential Pressors taps far FC3 flow indicati n -Tygon hose.connectier.; REFERENCE r4 NCR00F 3.3.1 ' R C 3 -F i :: : n .] anc I r. ; - ..i r e n t a t t : n ' 50NP L+sson Plan 'RCE'- c: : ~ ~~ 4.p, : ; e- ; .,,,s,0 1.- s . / .r., .. _ . .,a 5 .. . 7_ . ,. ; .- + mt1:urg.. - _~.n*a .a vr l' rc3stive; Ennnigr s :: 59 3-. cen

~~h .s~~

~~, * ; .- 7 c 3.; . : r . ; r, t a i n th e r t s ; 3 : a l y '. e d ;~~

~~nutdown i + . 2 5 T 5.~~

bi d ec.:na a r y c c n ' s t n !,- 't ,rrios ..- < m l c. e b c71 % : t:n c s p h e r i : crs=soro; emove tirasrnn 1;r- . .; n i r. . .m p s ; . . ;. 5 >

~~EFERENCE ~'~~

~~3 ~. 'i *-' 3/3 ds:, T i , 1,I. **-** . , -t A;- Ii a r * . *,3 ,30- -3y4t.sm' pp }-$ a f ;, ufp. l. ,. . . _ .. , .~~

2. PLMF DESIGN INCLUDING 3AFETY AND Er1ERGENC Y . 5 YSTEr15 FAGE 34 ANSWERS -- SEGUOYAH 1&2 -65/11/12-DEAN, W M ANSWER 2.08 (2.50) a) Loop 3 Ir.termedia te (+.5 es) b) Loop 2 Hot c) Loops 1 & 2 Cold d '.' Loop 4 Hot e) Loop 3 Cold F;E rt r t rh.E 30NP t.esson Flan 'RC3*. pp 6/~

002/000: K 1. 0 6 ( 3. 7 '4. 0 ' 3 1:1.0S( 4.5, 4.d' f M1.0?.4.1/4.1) ANSWER - .'; . 9 (1.25i 7o & a Mde3 F ': + . 2 5 ' gm unrNe' IndiDit H2 10 3 k 3 '3 9 6 Wi .1 : h .Ti d ; .* 1

~~3 30iC0 ths ,-1i3 593L f ' 51 D '1 C) Delt3 E 0 9 t W 9 0 Ti th6 PIC d13CO3?)& E n ',~~
~~10 E2P . *.5' c c- F :_ .; .7 ..s r.. ;.~~

~~I i) N. E [ ' ~. C g~~

~~. 4~;. .'ONP~~

.. =. .n 1 : r. ' ; c. s: ' . c., r. -. . ' . . ' i. ~.. ; (,1 .- . ,. [ J . (, m . -?.... . } . >.,- ,u.i<.= AEIIIe[~ ~. . ' i -;Lc. ,: ,e c. ; - ' ~~ 1 * * -

.

p c ;, Ces,- 15. 'ArJ' cp .1 ,
~~- ~ '- :~~

~~.s ,,.* Y y .-.'u..-a ,- *a e ,r -. f j : e y r ." ,... t . - N ',. ! n E I. 1 1 3 1 .') s~~

~~2 ! *.c -~~

$

~~E ~i '.~~

~~- 2 ; r' ' ,* - F. [ a .:~~

~~r i r. 31 .] c 2 - - - -~~

~~. f' . - 7 ' i c i r,, I 1 [. . . . . .: , - at ;1 r : : i 1 - 2~~

a ? Gr ~ ept * .; *

,

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~~p.-.~~

2. PLANT DE51GN INCLUDING SAFETY AND EM ER GE tJ ~ ~; BYETEM5 PAGE 35 Ar45WERS -- SEGUOYAH 1a: -85 /11/12-DE Ara , un PEFERENCE .

30NP System Gescrip. 'AF4'. pp 6 061/000; K4.0~ (3.1/3.3i . AN"WER 2.*2 (1.00i rgers e) ma MG) PR sprsy; 'ORV; Hi-Hi contsinment pr,ssurc; ERCW (*.25 e-* FEFERENCE ~ 4estinghcuse fur i '. s t a n. s Manual ' Air 3vstems'. :p t - ,3 v , 8 ,.,t3.. v v .. - I.,.1. 3t 4 sm,.ecc. . .- - r. s. 11.v. .: t, .a, .c.l.. e. cu u *,- _

~~t. o> . 4 , a . . -'~~

ANSWER .L3 i t . :' A ' En.e r genc y sump : Cantainment 2pr:, P o m ,c s ' Cc.tsinment 3pr sy Ht E=:c h jr s: Containment Spray Nc:-let' U; par Cant?inment Compartment : Drains in tne bottom of the 5efuelinj : snsi '._ c +: r ; c a r. 3 r t m e n t . . Emer3ency 3 ump (+.15 es) 2.E F E P E H C E 3aur mes e sc- c. .i. cot 5pr. 5.:' ;q. ' ' 15 .,.3,.. . - s.. - .. g., .... 4 .1 . .t ;.- . . . .,.,t; ' - ~ ~ ~ ' Lc.s1 f-.7 E C T: - ' - '>r,*r ; .. .- er .** :.- [ .1 r . T' L * - - .F t. ' 4 . F..- -- y- .:... . . . -fi. e c e -- - -e ,s p 2.-- 1 e,,y .. .. , .- 3 o . t . . . , ,e e, ,a - ...

~~. PL Ar4T DE3IGil INCLIJOI?1G 3AFETY AND Er1ERGErlCY 3 (3 TEris FAGE -fo ANSWEFS --~~

S E 0tJOY A H IC -35/11/12-DEAN. W ri ^ AH: WER. ..15 .. . . . - (1. W) al H i - H. .1 level in any . .: < b. ', ,- ' ,.; . . ) , 6 . u ,s . eas SI signs 1 Resctor trip with la Tsvg * ~. 5 " A Gej ri b) Both MFF te ip , * . 2 5 e 2 MFuPV sno 0,pssses shot _c:-r: + _ - '

~~-8 -- - - im - t o c or.d wr Fe e du.s t e r t s o l s t i c r. <=1 e- close REFERENCE 30NP Le= san Flan ' Condensate and Feedaster Review'. pp 10 C e, -,~~

us, L. ,- +1-. . , . . . , .u . 4 ., AMiuE 2.14 (2.00i CCW Heal .- h g r : : Centainmc.nt iprsy Heit Y : n r.j r s ; EDGs: AF4 Backup; Cu En.er, MsLeop- Control E103 A C E .< t t e m : Aut 01d3 Ventilation Coolers: Av: Control Air Coipresscr= *.25 as REFE:ENCE 4estingho'.ise c u ,0 3,stom .1 s r e s s i . ' E F ' J ' e -? I . C T '. g ~V~ [~ ' , f ' ~, : . ane n- - rl c , , ,- t 5 . .- r - P 9 7 *I! rr 1 ; r:0i f i 9 'is FHi } ii .,7 t 5. ! } I r. s 3 e +. ~, 5 F. 3 -E [5 3i

~~J ! '4 t r:83~~
~~n*i3 e? -~~

~~s - i I r". -p w } r: t 3 T/ '. e -] .1. D e J i s "; e .~~

~~6. ; ; a~~

- 'te , ,? 1- ;r2-( + s r F F c 3 E H C '* ~ ~~HF .25 > *,r ? . R i, * ~ ~ * * ~> ~ . , T' ..~. . . . , -. . c .. ') 'J V . I1.Vt . , . -.. t , . ' . - , . _ ! .t -4 .a4 -+.. .:. PLANT DESIGN INCLUDING 3AFETY AND EMERGENCY SYSTEMS PAGE 37 ANSWERS -- SEQUOYAH 1&2 -85/11/12-DEAN. W d ANSWER 2.13 (1.50) -Lower containment staosphere particulate En3 {+.5 es) -Containment pocket sue,p level Monitoring system -Lewer containment atmosphere gaseous RMS REFERENCE 3GN TS 3/4.4.4 07;/0003 PWG-3 ;3.2/4.0 ANSWER 2.19 ( 1.00i -5I Pumps (+.25 es) -ONE Centrifugal Chsr3ing Pum:, -UHI Gags -Cold leg Accumulator I s o '$ a t i o n si.es , FEFERENCE iGNF 3ystem Gescrip. '5Ci'. pp i 010e:>O0 K1.0: (~.7 4 17 1.rl I N E F :.;0 i1.:0; tro,ent u s t e ,- f r. a ' l a r a t.,3 :n the s .~.e l l side ;r the regenerativo Ht E.:c n 3r

~~ia. . maintain PC5 tr.sssure in th+ H+ E , r r. y wit 0 tne high '.emp wateri AEFERENCE 30HE 1 / stem Descrlp. ' C '/ C 3 ' . pp 4~~
~~.0 ; 1:;.c3 i; ,i's,a-t 1~~

~~b _ _ _ _ _ _ _ _ ____.m_ _ _ _ _ _ _ _ _ _ _ _ _ _~~

2. PLAtlT DESIGN INCLUDING 3 AFETY At40 EMERGEriCY 3Y5TEhG PAGE 33 ANSWERS -- SEQUOYAH 1&2 -G 5 /11/12 -D E A r4 Hn AMSWER 2.21 (2.00) a) Turbine is runback for 1.5 seconds (+.25) st 200*. Per minute i+.25) waits 28.5 seconds i+.25) and repeats :.:le if setpoint not clest(*.25i b) -One of two MFPs trip 3,*. pcwer ( + . 2 5 .'

-83 Hester Drain t snk bypas- to condenser vsive leaves its seit C S *. losa ( .25i uro:ne :. 2 runback usird ths 31ve cosition limiter (+.25i tc ~ 5 *. cr 807.' respecttvely i .25) REFERENCE 3GNP System Gescrip. ' Turbine Centrol'- rs p 15 045/000; K4.12 i3.3/3.66 ArisWER 2.22 :.25~ -' pircci e-c-c-c-3 (+.25 for os:n in ccrr CEFE:ENCE - 3Gr!F Ot.siel ienerator u rnc: r. m 064,000; A 2. 0 . v2.7' M r

~~3. INSTRUMENTS AND CONTROL 5 PAGE 39 ANSWERS -- SEQUOYAH 1&2 -85/11/12-DEAN. Wd~~

~ ANSWER 3.01 (1.00) i REFERENCE Westin3h ouse PWR Systems Manual, '5GLC3' pp 1.-5 035/010; A2.03 (3.4/3.6) ANSWER 3 02 '1.00) C REFERENCE Westin3 house pup Systems hanval. Sect 4.2 'PIR Pressure'Contarol' 010.'0003 K4.03 (3.8/4.1) d F6 01 i 2. 7 ' 3.1 ) ! pug-4 ;3.o/3 7) .:.NSWEP 3.03 (1.00'- t o r et REFEFENCE iOOP system Deserip.

~~E l e c ', r i c 21 Oistributicn' -- 17.'20 064.'000: M4.10 f. V4.11 i. 3 . 5 3.0 l~~

~~Af3WER 3.OJ I. . ) ) i d kFFEFEiTE EGil : 'LE pp 22-24 O J '. :20: PWG - .3.i.'3.4i~~

~~3. INSTRUMENTS AND CONTROL 5 PAGE 40 ANSWERS -- 3EQUOYAH 1&2 -85/11/L2-DEAN, 4M ANSWER 3.05 .(1.00)~~

~~C REFERENCE SONP System Descrip. 'RPS*. pp 6 012/000; K2.01 (3.3/3.7) E K6.04 (3.3/3.6) & A4.06 (4.3/4.3) Ar45WER 3.06 (2.00) a) No effect b) Arm and actuate~~

). Arm and actuats d) Arm only REFEPENCE Farley SDr ' Steam Cump System". pp 3-:3 SONP System Descrio. ' Steam Dump System *. pp 6-8 041/0 O; K4.11 (2.3/3.ti a V4.14 i 5/2.3) ! KJ.17 r3 7/3.-)]

~~AN5WEP 3.O' 1. 5 0 .t si E' a t h '.5 es ai Esth~~

~~' A u *, c F EIE R E fJ '.E 3:iNP s y :i t e m Dascrip. 'Fod Costro! 5/ stem *. pp 1 001,'000; F O . Je ~ i1.3,3i 1~~

~~f.- r~~

3. INSTRUMENTS AND CONTROLS FAGE 41 ANSWERS -- SEQUOYAH 112 -85/11/12-0EAN, W ri ANSWER 3.08 (2 50)
~~a. 4 (0.5)~~
~~b. 2 (0.5'~~

~~> u . g= = s '~~

~~c. o~~
d. 6 (0 54 e . o.. .c.ai
~~e. a REFERENCE CAT, P5H, C N-IC -IP E , pp. :, :. 1- (Ans-4 2, 6, s. 5)~~

FNP, SD, ' Reactor Protection Systen'. tsbles 1 5 6 (Ans-4 2, 4, 4, 5) SONP System Descrip. 'RP5'. PP ?-12 :Ans-!,Z.6,6,5) 012.'000-K6.03 (2.1/2.5? O l 2 / C 0 0 -K 5 .1 -) i3.2/3.Si A tJ 5 W E F 0.09 M [/ 5 )

~~1) Low i.u c e 311 Pressore ':+.25 es)~~
~~) Hi c Crankesse Pressure~~
~~3) Phsse Estance Felsv~~
~~4) Rever sc. Power Reisy~~
~~5) Loss of Field Selsy i bi3a Jschet Jster ~e n. : e r a t : e REFEFENCE NA rJ C R C D P :0.4 'EDG' 3GNF Diesel Gener at or Hsndout pc E~~

.17,4: .. a f, , . 5 1 ., - ,: , 4 'u .,,_' A tli. U E F :.10 1.50i t- pat 3 in nc 0:~ +5 2s ~^ -Bear ng laft 1.u m p r unreing wi t h -- ; r i3-3-*j. - E' uc b ' l e in the cr a s sor 1:er . t.OW -. J.. sE*, .L 9 F .T - b *.: = . .-) & L f. 5 - & n ..'i .i .a '~ .3sLC -r O r ' t 3T IOwer ~ V ,. g c. c up h- c. r ,; 6 . t. ik A fl ? D U *~ ? 1* *VC~~bTI.** 3GNF 2 , t t .m : scrta. '?C2'. 2p L 5 IONF EGI -23. , .p ~-J

~~3. INSTRUMENTS AND CONTROLS PAGE 42 ANSWERS -- SEQUOYAH 1&2 -05/11/1;-DEAN, WH 003/000; K6.14(2.6/2.9)~~

ANSWER 3.11 (1.00.* a) _ Inputs are the S/G 1evel instruments (+.5) b)~ The output and' demand signals must oo a p p r o::ima t e l y 0 (+.5) REFERENCE SGNP GOI-Z pp 13 05?/000; A4.0G-(3.0/2.9) ANSWER 3.1; (1.001

3) Isolates the iv.<il i a r y building ventilation (+.5 es) b) Closes the discharge valve to the coolin3 tower . blowdown REFERENCE 30NP Requal Traintng Lesson Plan, Week 3 .i J. Osv . pp 47-51 072/00C; FZ.C3 I3.c/3. . ! 07L OOO; K4.01 i4.0 4 3i ANSWEP- 3.13 1.50-
~~1. - IFH iitjh F19" Peactcr Trip t0.Si~~
. IEF Hign Flu God 5tre 0.5 3, TRH Hi,jn Flu R e s.: t c r Trip - Law 5et:cint ).5i FEFEPENCE C a t. . 30-IFE. 9 '?

~~E d flP fLE FP 5 01L '00i A4.03 ~ 3 . 3.' : . ; i~~

3. INSTRUMENTS AND CONTROLS FAGE S3 ANSWERS -- 3EGUOYAH 1a2 -65/11,1:-CEAN, W d ANSWER 3.14 (1.25)

-PZR high water level i+.25 esi -P:R lo pressure -Lc primary coolant flaw -RCP bus unoervoltage or underfrequency -Lc24 of (Ica in st lesst two locas REFERENCE J 3 G tJ P P L:5

PP 012/000 K4.06 (3.2/3.Si ANSWEP 3.L5 <1.50' hsse A Containment Isolatian atJnsi from either Unit (*.5 ea)

~~-Hign Radiation signal from fuel n anol ir.g clo g stes rad monito s A + .. , Eicg _ hicst sent rso sionitera RE.;ERErJCE 3GNF , e, Cascr. J.4r ' C .: n~~

~~Ai, ;or.- and Clasnup ?.d' p;a l '!~~

~~EPE-0:C; FWG-1C (4 1 4.4~~

~~o;ugs ;,1; I,-~~

~~3: : c - r,~~

~~I- '3 ; o _. - alt- - :- - t ._ , p3wer; 7 a .. 3 it 7 ;t ai:~~
~~. L ; - .~ -~~
~~b FErERENCE 1: ro?1 *C **. ts * - '~~

~~'J .: '. i n. ,g. h. .,0 0 -: _ :UF ~~~

~~% . m. O t.~~

~~s ?6 6 . .F~~

~~dp Lf '~~

~~.9 e~~

3. INETRUMENTS AND CONTROLC PACE 44 ANSWERS -- SEGUOYAH 12.2 - 85/11'12-DEArt. Wn AN9'JER 3 17 (1.00)

RWST Le Level (-4297.) and Containment Sume Level 10% (+.5> Containment Sump Valves i. FC'l-4 3 2 1 7 3 ) and RWST to PHP auction (FCV-74-3 i -21) (+0.Si REFEREN:E SONF E3 1.C. pp 3 O v. o.v.vu k. ,-o . v : .: ...a.s! A rJG W ER 3.11 (1.50i - N c r t. s l : 490 VAC Ultal '. +.! es- -itandoy: 125 VOC Battery -nsintenance: 120 VAC ~.EFERENCE 3ONP 'Re/iew of Elec tr ic al tetrtbetice' :s Oc:/0004 K4.0: ;.4/2.? . rl _as. E r. 3 , ., . - 4 ....2-T . -; .; i .s h. t t r e a c t n a. ,: w - '1: c .c t : : * .: r i: .. sc- .reo t .: the svor23e cf the 4:er, lower deto: tat s- sn; 3 e r. e s t . - s r. I t :< r :t at 1,v; incroatinji+.25,. The circuit avtc isfesti Jelow 30'. towe- an ALL : Tannair (+.!i REFERENCE '0NP 3sttem Decer19 ' E .-: c c : e dI?'. : ,1 , t~ L. . r~ . s, . * . ') 1_L : iCL* h. .* . U ,* 4.s .s e . 2. . :. i i AiTj W (i . j . 2 f, ! . 0 :~ t t. c s o l ~ Chirine1 , T

~~tiled n l .v. -~~

T , t - , . . c. ft rasc W O E ',15 j h 0115 0 F tJ P ~ pit 4%f ~*TT.. ' i . ~ . 'i t . i .*'*}'* *p '[-{4 i e * .= . I ee m y e e . e Y e 'V e .. d* . OeU1 r 4 I 9 J . a. 2, E8 'k . I .<*t' u i i I l-4 i l I t l i I 4 n

~~3. INSTRUMENT 3 AND CONTROLS PAGE 45~~

-AN54ERS -- SEQUOYAH 112. -85/11/12-0EAN. 4 H ANSWER 3.21 t' 1. 7 5 :' Hi-Hi containneent pressur e > Z.G1 p313 (+.51 Hi3h steam Line-Flow Coincident with Low Steam Line Pressure (600 ps13 or Lc-l.o Tavg :540 des F. (6.75) High Steam Flow setpoint is st 4 0 *. flow from 0-20?. load (+.~5) tnen linearl / frcm 40-110*. flow f. ca ;0-100% load (+.25) REFERENCE 3GNP PLS pp 9-11 013/0005 K4.03 (3.?/4 ?,) ANGWER 3.~2 i1.50s See attsched sketch REFERENCE SON ~ FL3 pp 2 OCl>CGCI k4,&3 ,5 3.3~ i l 4 I. I t-t i i l l I I i i l . .i o 22- ~ A 000 SPEED FRO?ORfl0!:AL ::AND (5TEPS/l !!i) fl TMir.ur4 :, TEED = 72 Stept ' ... 2*F /g 4. i r. - \ DIAD T!.;0 - - . N 1.5'T j; i \, j i SPECD (J.!!! = 32 steps /nis. Y, h > l ' ! IMNi!i:U;t O! EED = S stenst'" , I 1ner .I o 3fo -1.b .1.0 ++ I i ++ 0 1.01.5 3.0 5.0 10.0 , fi ' i i ! 'F. l 4 IPi t I ROD SPif.D rn07.t:AF, il ! i / ,l I / \ / LOCI:UP !!)THDV.EAL +0.5 'f n P .i .~ s SNP REV 12 MAY 271982 4 PROCEDilRES - r10 R H A L . AE fl0RM AL r EnERGEriCY AriC ~ PAGE 46 RADIOLOGICAL C0t4 TROL AilSWERS -- SEGUOYAH 1&2 -35/L1/12-DEArte W ri AMSWER 4.01 (1.00) b REFEREtiCE Catr GP/1/A/6100/01, p. i .~. 50flP GOI-Z. pp 20 015/000; K4.07 (3.7/3.3) AtlSWER 4.02 (1.00) - a _C' REFEREtJCE F9c G r E P : ,5000,.^'. Status Tree 5 S G ti FP s, Status i t a.. s, %. f ' ' e - 10 ' Reccjnic:n3 E0P Entrv-level conditions ( 4 .1,' 4 . 5 ) kN;UEF 4.0: s . 0 0 's REFE;F.9CE i G r. AGE-24A. sp t 004/0:0; FWG-10 (~ Sca.5, ArJGWEi- 4.04 t , :> 0 Lar!F GOI-7 : :-

~~s - ,4 .. -- .~~

e '.'e, e / 8 P 4 4. / ,e $ ' 3, . 4 PROCEDURE 3 - NORMAL, AENORMAL, ENEFGENCY AND FAGE 47 ~ - - - ~ ~ - - - - - ~ ~ ~ ~ - ~ ~ ~~~~E 5[5[55555L C5tiH5L AN5WERS -- SEQUOYAH 11~ -85/11/12-DEAN, W r1 ANSWER 4.05 (1.005 s REFERENCE SONP E-2 035/010; A2.01 (4.5/4.s) 1 PWG-10 (4.1/4.5) ANSWER 4.06 (1.00) C REFERENCE 10CFR20.5 PWC-15: 10 CFR 0 knowled3e 3.' 2.:i . 5WEF 4.0- ;1.00 d R _r. -- . n : -.., _r_ r - / * . ~, ,f,. UC-(I jtg.-6.g p p., p ;ct_ t r 37

~~-1, :2-:n :2 - '~~

~~v / .116-li: Fric u l e.s c 3 e 3: A N b N b.h. E h [' .' 2 I) h I~~

~~, inot,doan *,5 e:~~

~~a' 5 t a r tisp~~

~~:autocan d: E w + d o u r.~~

~~FEFE;ENCE 509 TI 3.4...: 00- :20. ;sc- :.5/ .4~~

~~4. PROCEDURE 5 - NORMAL, ABNORMAL, E M E F G E N C 't AND FAGE 40~~

~ ~~ ~ ~ Edb[UL55EE L ddUTEUL'" ~~ ~ ~~~ ~ ~ ANSWERS -- SEGUOYAH 1&2 -95/11/12-DEAN, W M AN5uER 4.09 (1.00) 2; 15 minutes; 50; 30 minert e- i '+ . 25 eri REFERENCE

~~Q n, -: a. ,..u..~~

Ol s, ,0_v . r, u_ G0 ,.. s3 y, .-.a3 AN5WER 4,10 .50) 6500 oren. REFERENCE 10CFP ':.101 AN5u[E 2.'I . 1.3~ r' o 1: ,25 e2 r e s : r: e sy lw =, 4 c h Mo CEFE'ElCE 509 07 - ::E n; :a s t. G - .it5 g r.1 f r + : 5, r r c- ',' .

~~31 M a * ! ** L I. *. a 3-aw 1 a~~
~~1. i. '. 5 Z - [ r, 1. 5 - P : u t f; - r. . ) ,ir 3 : , * ; r, ccrrect ;rdsry E' E T E F E !J C E~~
ce

c in:-ge A. . r,

~~.a 4 1~~

p.

~~og g .. j op ,I 4~~

~~4. PROCEDURE 3 - NORMAL, AENORMAL, EHERGENCY AND PAGE 49~~

~~~~E did[EdfddE~CdilTREE~~~~~~~~~~~~~~~~~~~~~~~~ ANSWERS -- SEQUOYAH 1&2 -65/11/12-DEAN, 4h ANSWER 4.13 ( .50) 350 3allons REFERENCE ~GN E5-0.1, pp 1 EPE-005; EK3.06 (3.7/4.2) ANSWER 4.L4 (1.50) low pressure letdown; RHR letdown; SI Accumvister Isolation Valves; II pumps; one of two centrifugal char 3in3 pumpst 160; ( .25 ea) REFERENCE SONF GOI-1 pp I/4 004/000; L:6,02 3.G/1,1) 1 006/00C; A1.Ct (3,1/3,4) ANSWER. 4.15 t' t . 0 0 's s) 4stts 33r ilu c l e s t ;-isnt ~ ( *.5 es) b~ '.ontrcl Evilding t.un:n Poem (Elevstion ~32 REFEFEMCE

~~GNF IF ~. pp L ! IP~i, op 5 PUG-3s' Actions i r. Facility E-Plan (Z.?f4.7' A rli W E R 4.': '1.50) li De:reese tur b ii.e load (+.25 es response-~~
*!arifv =jte rca insertion OR.

3< Manus 11. Insert rods to maintain Tsv9 =+ 'tef Ji Or.en r' t*iv'c:eskers at MG 3et Poem A' 31:3 ~57 Ti O p e r. b e c- s i e r s to control rod nG sets at a 3 - :' S Unit Boards A ano B di ni c t :. f / I.es t to c10se P-4 contsct REFEC.ENCE 304? FR-3.1, c p' 2 %*em h . . . ,$&,'* ,, T ,. , &s ,~@. -. l I

4. PROCEDURES - NORMALr A B r4 0 R ri A L , EMERGENCY AND PAGE 50 RADIOLOGICAL CONTROL ANSWERS -- 3EQUOYAH 112 -35/11/12-DEAN, y ri ANSWER 4 .1, t 1.00>
~~1) Phase B Isolation (+.25)~~

) At least 1 of the 4 CCP '5I P u ni g s Ronntn3 i+.25) A RID RC5 Pressure decressing uncontrolleo t +.:Ei to 1:50 Psig i + . 2 5 .i REFERENCE SONF C o l ej o u t Ps3+ 003/000; PWG-10 ': 4 .1,' 4 . 2 ) Ar4 S W ER 4.la i2.00 s) 1) Centrifu331 Char 3 i n 3 Pomp z' AHU 3> ERCu - .; rn p 4) CC5 and Booster Pumrs

~~5) 5 pare Compcnert Co a l ii. 3 F u ni p si AFU Pump 's Pressurl et Hesters 3} Fire pump **.15 es)~~

D) IO Cl33r 'he iteE01 / hEl*;i : E n ri EUterc,6fJerE Of iCCumul3ted C olTab v ; t i'O l O 3 4.I FEFEPENCE EONF AGI op ; - n_4,Oo.: 1.1 : .! a. ^

~~.) !61 O(, *[.~~

, c _.! 3, r8 5 w E F . t '; ,E 3 c c . :. e 3 v., > h .- _ . , - ,2; r, : n '. : 21 :cm Soc c2c; ,c taeir respectt/e C n G C P.1 1 I t E - 3: t0 thi S t i r O P T 12. t e LOC 3llOn sn- trin5fer COntr013. **.~' J' I ACI-23 ::: :r [i f t t*e P:Wera ~ AO[ ~~' in+r01 7 0 G r,i in3 Cree 530 lei . - n a r i <. ,, . tor. -I ' E 0 r O n -- D 1 1 ' t 10 r. Isoi- t'2-4' ' ' ' Curv+ E cov II-Zi [ n i r. r V C t 1 0 0 iII-22) ~ 3I-l!" H ,. i t- T rid Ce ut j0 tJ I". 3 D ri 4 * ,'

~~3) LNr- r : : 3 0 I - :. . : ( C : r, s F e e ' 10+ i L: - . C '.' C E ) (+0.1 es to mi.~~

af 0.3) PE~EECNCE 3Ofi P A0$~[IA? ?" d 3 I --- - .. ng,- , , . ++.e-i ttt-VO1* t a. ~. -.. - i

4. PROCEDURES - N O R ri A L , A E: N O R ri A L , EnERGENCY AND PAGE 51 RADIOLOGICAL CONTROL ANSWERS -- SEGUOYAH 1&2 -8 5 /11,12 -D E A ri . W r1 ANSWER 4.20 (1.50)
1) Resctor Trip-Turbine Trip d i.i e to s11 ri F W R V , Re.gulatory E:v p a s s and r13IV s going shut csusing a loss of feedwater-!. lo EG level coinciaent with Stm/ Feed Fica mismatch and/cr lo-lo 5/G 1evel ~+.5)

~~Zi riDAFW S ump 1 P - Ei s n ri TDAFW PumF start on lo-ic 5'G level i .25 ee below'~~

~~3) itean dump snd 5/G blowdcwn . s 1 '. e s f a t '. clase~~
~~4) Normsl LTDN and orifice isolstion valves fail close~~
~~5) All 4 EDGs start- but do not tie onto shutdown ocards REFEPENCE SGH- 40I-21.1, ;s p t/2 E p r _.a_~~

_ ,v p i. r., m.. , . n , ...- a.1 EN$NbR A 2I l' 1.5 si RUET level I ? ". s r. d E D n * ; ; n m e r. t ~. U r:, 7 . - r- 1 10 '. +. Oi itop the r - - , :.3 .Oee,ic , ; H I, i ' gi j ; rs d ' ~ d T r, -r ~ ' j n, ; *1,* REFEE T** ' E !, .j ~ ~ . . * , -_ - r, ,* -- - , - , - _ ~,_e.. . s - t . s ~ hE5N5

1-

~- ~ }[ ~ f4' -. , r, ' n 3 ,~5 - -- .. - , 7 {}- - ~ -] - - - { ~ ,' ---- .pi- ~, , .e - :, - ~ C ;=_ ,Q 1* 0 bif f .t C ". 4iD c - . , . .. :E :F lijo- : c e r-

~~tn - t r. e c - ien:~~

~~- 9T4 - ~_~ ~- D ~ re - .-*d G37* ! ~' d;rF ~ '^: s ;tllnAJ ITe2~~

~~-'-i. .e:'-~~

~~, e '. ' sy n~~

~~I n -]~~

te . '.c 9 5 . . 'r*7:, ,' 3 ,1 'i e -. 1n r19 .iL - l. ' .: Q . ,. , s? L .c.N Mr *. <e*LT'? ' L:6 .* D1J6 -=. .a. .Ie ...c.'_ . i .-

~~5. J'~~

$ .t C ,"s C C.' --j g* . r* C . . ..C..- g . *

~~g 4 m 2 - y 1 m b = # t I g' g .-~ .a.y e~~

~~3 4~~

~~4. PROCEDURES - r10 R M A L . ABr40RMAL. EMERGENCv .'. N E FAGE !!~~

PADI0 LOGICAL CONTROL At15WERS -- SE0001Ai4 112 , -9 5.' 1 ' ' I : -D E Art - -. r re i! . .,W _ .t r. ,._ . 1 . v.v. , Core E >: i t T/C i+.33 es/ T-Hot

~~n. s., : a vaccc11n3 RE EREr4CE~~

~~-nN c 'a -Q.Jr ?? :~~

~~a.-_~~

.rt-O_4 . tna.u. . -.- ~Ar43WER J.;4 (1.~ e This i s to :cmper.sa*e - cr ':.. r e i l : t ,- c, ae . :. s s u r i : e r n --b rp -Wr. Ob a w 30rl E3-0.3 9p 3 _..*rt*c_,,s -- _f., t .. w 1 4 . .4 A ll'3 tJ E E ' d.$ '[ -, **_-e.,- : t is . .- ._, . -....,c 0 0 *s 2. ~ l AEFEFENCE

~~(#,i-~~
~~c art : r n. s r .. 'f .~~

-

ML20151Y475

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REFERENCE:

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