Text

Requalification Exam Rept 50-250/OL-86-02 on 860428-30.Exam Results:Six Reactor Operators & Four Senior Reactor Operators Passed Exams.Further Util Effort Required to Achieve Acceptable Stds
	ML20210U206
Person / Time
Site:	Turkey Point
Issue date:	05/16/1986
From:	Bill Dean, Munro J; NRC
To:	;
Shared Package
ML20210U203	List: ML20210U199; ML20210U206;
References
	50-250-OL-86-02, 50-250-OL-86-2, NUDOCS 8606020241
	Download: ML20210U206 (136)
	v • d • e

.. . _ _ _ _ _ .

ENCLOSURE 1 REQUALIFICATION EXAMINATION REPORT 250/0L-86-02 Facility Licensee: Florida Power and Light Company P. O. Box 14000 Juno Beach, FL 33408 Facility Name: Turkey Point Units 3 and 4 Facility Docket Nos.: 50-250 and 50-251

.I Written and oral requalification examinations were administered at Turkey Point Nuclear Plant near Florida City, Florida.

Chief Examiner:

William M. Dean

/k- Mr. [dMde-v

/N Date Signed Approved by: m John F. Munro, Acting Section Chief

[A!/E j' Date Signed Summary:

l Requalification Examinations on April 28-30, 1986 Written requalification examinations were administered to 8 R0s and 9 SR0s. Oral requalification examinations were administered to 5 R0s and 7 SR0s. Six (6) of the R0s and four (4) of the SR0s passed these examinations. (Note: Waivers of the oral examination were granted to 3 R0s and 2 SR0s who passed this portion of the requalification examination in February). :

The performance during this portion of the requalification examinations is an !

improvement, and though not above the NRC's minimum pass rate for a satisfactory i evaluation (80%), it is indicative that corrective actions applied to the Turkey ,

Point requalification training program are correcting past deficiencies. l

However, further effort is required to achieve acceptable standards, with ;

particular attention to familiarity with procedural related topics.

i 8606020241 ' 860516 DR ADOCK 05000250 l PDR j

REPORT DETAILS

1. Facility Employ.es Contacted:

C. Wethy, Vice President, Turkey Point

T. Finn, Assistant Operations Superintendent

W. Miller, Training Supervisor (Nuclear)

P. Baum, Operations Training Supervisor

V. Kaminskas, Reactor Engineer

G. Hollinger, Training Staff i

Attended E/it Meeting

2. Examiners:

William M. Dean Thomas Rogers William G. Douglas

Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided your training staff with a copy of the written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 4 to this report and the NRC Resolutions to these comments are

listed below,

a. R0 Exam (applicable SR0 exam question in parenthesis)

I (1) Question 1.09 (5.12)

NRC Resolution: Equivalent answer. No change to answer key required. ,

(2) Question 1.10 NRC Resolution: Based on requal training material on current core cycle, identification of the most significant effects on the Doppler defect will be required for full credit. No change to answer key.

(3) Question 1.12 NRC Resolution: Due to the possibility of interpreting the question differently than what was intended, will accept

" diminishing build-in of fission product poisons" as an alternate answer.

i Enclosure 1 2 May 16, 1986 (4) Question 2.02(e)

NRC Resolution: Existing system description erroneously lists an off position for the makeup mode selector switch. Verified by current system drawings and actual plant components. Question will be deleted.

(5) Question 2.03(6.06)

NRC Resolution: Agree with facility comment. Based on new revision to current system descriptions, answer key will be expanded to include all choices as correct.

(6) Question 2.05 NRC Resolution: Additional answer provided by facility will be accepted. Note, answer key addressed potential for additional reasonable answers.

(7) Question 2.08(b)(6.09(b))

NRC Resolution: System description lists valves as opening on an "S" signal, but valves are normally open. Per CCW system drawing

and in-plant verification, will accept recommended answer.

(8) Question 2.11(6.15)

NRC Resolution: Recommended answer is equivalent to existing answer key. No change required.

(9) Question 2.12 NRC Resolution: Correct identification of MCC and DC BUS will be required for full credit. Power source knowledge is significant for vital 120V instrument buses.

l (10) Question 2.14 NRC Resolution: Both references support existing answer key. No changes to answer key will be made.

(11) Question 3.10(a)(d)(e)

NRC Resolution: (a) System description does not agree with j logic diagram. Will accept "S" or "T".

(b) Answer key is in error. Correct answer is "T".

Enclosure 1 3 May 16, 1986 (c) Review of logic prints indicates all three answers are correct. This is not reflected in the system descriptions.

Question deleted.

(12) Question 3.14 NRC Resolution: Based on recent system changes listed in revised operations procedure but not reflected in material provided the NRC, will modify answer key as recomended.

(13) Question 3.17(6.14)

NRC Resolution: Answer key is in error for the situation provided. It will be modified to reflect the correct response.

One candidate was identified by the examiners as being told that the question asked for the " controlling" pressure transmitter and his exam will be graded commensurately. Other examinees will have credit taken off if they assume the transmitter is the controlling channel input and then will be graded according to this assump-tion.

(14) Question 4.01 NRC Resolution: Agree with comment. Answers (a) or (b) will be accepted.

(15) Question 4.06(a)

NRC Resolution: Due to recent procedural change not reflected in NRC-held material, question will be deleted as no correct answer exists.

(16) Question 4.08(b)

NRC Resolution: Based on additional material provided the NRC, recommended answer will be accepted.

(17) Question 4.09 NRC Resolution: Based on lack of requisite fire fighting training for licensed operators, will accept additional reasonable answers based on scenario provided in exam.

(18) Question 4.10(7.07)(a)

NRC Resolution: Will accept reasonable answers reflecting valid valve position indication contained within provided facility instructions and procedures.

J Enclosure 1 4 May 16, 1986 (19) Question 4.15 NRC Resolution: Since the PS-N authorizes normal startups and once boration is effected, a normal startup would be instituted.

No change to the answer key will be made.

(20) Question 5.11 NRC Resolution: Agree that it may be possible to interpret the question such that the desired answer may be precluded. Will accept additional answers that pertain to improved flux distri-bution characteristics.

(21) Question 6.07 NRC Resolution: Generic Westinghouse nomenclature identified by the facility as not applicable will not be required. The additional recommended answer already exists in the answer key.

(22) Question 6.12 NRC Resolution: Recommended answers are equivalent to existing answer key. No changes required.

(23) Question 7.04 NRC Resolution: Question's intent was to elicit responses that indicated a knowledge of what could be observed in the SFP transfer canal area that should be reported. Recommended answers provided by facility are reasonable substitutions for those in the answer key.

(24) Question 7.11 NRC Resolution: Agree with facility comment. Modification to answer key to delete SPING will be made. No penalty will be imposed on an incorrect fifth answer supplied by the candidate.

(25) Question 7.13 NRC Resolution: ONOP 33.1 lists as immediate act90n that certain valves be shut to isolate in-leakage. These valves will be required for full credit.

(26) Question 8.06(b)

NRC Resolution: Based on facility Health Physics Manual, no change to answer key will be made.

Enclosure.1 5 May 16, 1986 (27) Question 8.07(a)

NRC Resolution: The recommended answer, based on a recent administrative procedure change, will be accepted as equivalent to existing answer key.

(28) Question 8.08(b)

NRC Resolution: Recommended additional answer is already accounted for in existing answer key.

(29) Question 8.10 NRC Resolution: Agree with facility comments. Portinn of answer key in question will be an optional response.

(30) Question 8.12(b)

NRC Resolution: Sufficient flexibility exists in current answer ;

key to cover potential conditions requiring logging in Part II of the E00S book. No change to answer key made.

4 Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the oral examination were identified.

There were no generic weaknesses noted during the oral examination.

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

L ENCLOSURE 3 t&

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c'3 pie gou r ' o- : v. .? t on + :- a*' t! e n zi ar sheets. Points <ar 2;ch go+1t_cn r i n - ? e -: in ar= +5cses after the question. The oa- .ng p ;de revit es et 3 : -a t ' 0 *. In each estagor and 3 # inst grsce if at icist A O *. . I :mtnation ee," w:11 be picked op w (M hov"- >fter

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.A- ' O ~ A t. 'X O P E '.' A ' U E CATEGORY

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- " _ _ _ _ _ _. ' -_ .- .". _' n n _ _ _ _ . . _ ______

1. cRINCI: .::S O F NUC'_ EAR Fo.uEC

-! i$ 2 T 7; -29FER MiD FLUID C'.0W q[ -

m on

2. P'_ A N T DESIGN INCLUDING CAFC_TY a AND t.MERGEMCY SYSTEMS Q. 8 , < -

_ _~ _' n_' _~ INSTRUMENT 5 ANO CONTPOLS

~

2.

W n 2 .On

__'___' PROCEDUPES - NORMALt A8NORMALr

~~

_ _ _ _ _ . ____ ____ ________ 4.

EMERGENCf AND RADIOLOGICAL CONTFOL

.12-rt?- 100.00 TOTALS FINAL GRADE ________ ________%

All w o r ', done on this e'< a m i n a t i o n is my own. I have neither given not received aid.

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

kPPL5CkhiI5~55GUkTURE

1. PRIr4CIPLES OF NUCLEAG 90 W Ec: P '_ A N r OPEPATION. Pact

~~~~I555:5669555 C5 " 55dT~ EA55E55~AUD T ~iEUEU~EEUU GUESTION 1.01 ~1.00*

Which of the following descr bes the changes to 'he s t e :! m th-' oc or between the inlet and outi e' of a reel Inct id9el) turbine'

e. Enthalpy DECOEASES, Entropv DECPEASES. Oue ' t e ; OECREASES -

b. Enthalpv INCPEASE3- En'r.9v LNCREASES. 00sli t, INCREASES

c. E n t h s '. p , CONSTAtiT. 9-trany OECREASESv Guality DECREASES

d. Enttalpv DEC R' A .c 2 - '

o m. INCPEASES. Gus11tv DECREASES

e. E , . t h a l p ,.- I N C P E J. : E ': - E ri r c o m, IrJCRE ASES , Ovalltv INCPEASES

n. wo c e. T ". .' N.

. n. .'. ..n..'.'

~

?.* ' m : h e d ' t 3 sir e 4120 s',0ws ; c uar history and four possible samarium t r a c e .5 'r?Ic+1vit- vs t i *i - ' Cetget (3 3, c. or d .' the correct curve

cr disp' >tng the e ' p e ; '. e d Ismirium transient for the given power hister .

71 ' '_- ". T T_ n. b> 1_ . 0, 3 '. . n. o. i Attached C i '3 0 " e %!!' 2hou 2 Feuer history and avr possible enon tr;cs: 'resett- t v: t : x .- 0 lect 2- be c. - da the correct curve

313 p l O v t re 3 tte * ' 9 c t a i

. 9 q ~t " 3 re s t ? n t f o

. **ie J'.V9n power history.

(***** CATECC0Y 01 CONTINUED ON NEvr e :,g g ,,wss)

l. c c I 9 C I c '_ I ~. 22 4UC'_IAc 204Ec c' AN T OPERATION.

pacq -;

"HTc40 DYNAMICS. HEAT TRANSFER AND FLUID FLOW 9UESTION '. 04 (1.00' The roIctor .; critic 31 2 t.- 10 000 cps when s S c G F O R') #a:17 o p e r.

Assuming BOL cond;*. cns. no rcd motione and no ' e nctc r torp, chocre the ans-er below that best describes the values of T7vg and nuclege power for the resi;1 ting nrw steadv 7 tate. (POAH = coint of 2detng he:t).

. Final r y y .3 g e z !. e .- than intt;e1 Tavg. Fina' eower above

0AH.

b. Final T?vj gre:ter +han initial Tevg. Final power at PGAP.

2 C 1931 Tavj les: thsn initial T3vg. Final power at POAH.

d. Fin 21 Tav3 less than initial Tavg, Final power above PGAH.

QUESTION 1.05 ( 1. 0 0 :'

'Jith ,he reactor initially It s keff of 0.09. 3 certain reactivity change c2use the count rate tc d20ble. If this s!me amount of reactivity is Jainyector?

sdded to the r o v t or . which of the followir.3 will be the status of

2. 39DCritic31

. CritlCII

. SUp90Criti:21

d. Prompt Criticel QUE5 TION :.06 ( i.504 Ind ::.t- whether the follcwing Will INCREASE, DECPEASE. or PEMAIN THE SAME.

e. A"2:lable FCP NOSH ss volumetric flow rate increases. (0.5)

b. 9:ntmum required RCP NFSH ss volumetric f '. o w rate increeces. (0.5)

c. Ave:lsble NPSH to con 'ent a te (hotwell) pumps as condenser subcooling increases. (0.5)

(***** C A T E :.0 : f 01 CONTINUED ON NEXT OAGE *****)

1. PcINCl*LES 03 N ' ' C '_ E A I- '0WI; ': L A N T 00ERATI0tl. PAcg a T H E P.- 0 D Y N A M I C S , HEAT T' ANSCER AND C LUID FL0u O.H.ec.,TtnN. '

6.7 i'.50)

Indicate whether t7e f 3110w ing c h 3': :e 5 civie the different'al baron worth to become MORE NEG ATI')E. LESS N E G A T I'.' E . or RCMAIN THE SANE.

Co:stder each separ stelv.

2. E:o r o n concentration incre?ces ' O.5'

b. Moderstor temperature increa:as t0.5i

c. Core age incre :ce s +st ; c o n s t. r n t boron concentration) (0.Ti QUESTION 1.09 (1.00)

Arringe the following boiling o:,ises a 3:ece;3ted with ns'Oleste boiling snd departure from nucleate bolitng t. the order in which thev .icult occur in s channel with ornal floa and hi3h ' est f l er" .

1) Transition ?c:ltog

) o. l y c c : 1 : n.3

'i Cilm

., Ballin',

. . b - ;- o . ., . , 3 .: r,t :

.0. ; r, . i

?Un-tran . /. : : ..

,. ec e ;r g *. T g.ir e - ;-: ; -.: 5 -r? , : r. 3 a .g r t f c.11o w i n 3 've-tions ca ce r.mg : 1>st of :ne D:

r :m s t ar t frc.m 2 2 *. oue* uithout a reactor

r;:

, ' ' r, oces 1000 - : r ~s

-. < 1. > u inc'ea; at ,> tnt 3' (0.5) i uh, dce !c o i ?C5 ' low 2 ner e. 3 2

.etot 27 .

(0.5)

c. Wh f 1 :' e: s loop 2 S. 0 le,el decret3a

s h r ; n k. ) st point 4? (0.5)

d. . -i o 9 c ?vct::neer.?d h;gh Tavg (opertt:n3 'copi increase at

,- .nt ?' (0.5)

(***** CATEGORY 01 CONTINUE 0 ON NEXT PAGE *****)

1 l

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inCresZe. why does t '7 0 tOd 4 ..

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a i r t 'l r e gi g t . , ? 3ent;2.l' 3

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O I.' E 3 T E 7 M i.'2 ' '

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r ! t ; 3 r, z e i .. t , rt initial s h a r ". decre85e?

r.s

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- q ;, r h - tv. p r ; .Y c t i r r. 3r" tu- r o *t o '/ 31 mech 3ni ms.

12* ' e .n o s t '2'.gni f ic?nt STOCVetion mechar :m. .n.5

.: :t most I:gnif.::st - e :n e v t mechanist du l e it low (less ,

n:r

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caer i e , 3 '. (0,5) a , :s .-. r

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. 1 , . e., r \ ,

o ': : ;w and wh/ '. h e following will re rond to : loss of natural c t r ;u l _ + 0- 'lcw fcilowing I reactor trip from 100% equilibrium con-

a. t > . . i., .

. 4C5 wid: ty- temperat,vre difference (Delta T) (1.0)

'c . Oe*.?tto : i? 'ctween : fecid wide rsn3e and S/G presture (1.0)

(***** CATEG00f 01 CONTINUED ON NEXT PAGE *****)

i. .

c. p. I N r. I c L c.5 0 F 1 U r c A c. c o w c. o.

. - . ci.. A N T.

. O.PrPt.TT.n_N. c. g g - 3 THER.0 9 DYNAMICS, H E A T " A rJ S F E F A r' 0 FLUIS c '. 0 '4 k

.. . 3s s .t . Lea s s e o 1 W ith the r e s c *. o r operating at 10 0 ,c o u e r with Tavg = Tref :nd TCi ressure norm '.. w h ', :? the v.ib c o o l i n 3 c ' the CC57 e**** END OF CATEGOOY O' A* ***

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3. u;7 . '. ; a .gn gg _. : r. ,.c;.,idual thermsl b?rrier return

.o*ca -

the combined return lire

1. . . c, -

i 2 ., ,. p ., 3n . a -

we c ,md t .e d thera.il 5arrter return 6

. m .3 . ; 1 '. automst crt , : ' se all three individuel return

' t ir : ~) 1 2 +. t e r '. ' c o : .

d, u t g .- r t . ,w . . n e .1 .,, a= .ombined thermal barrier r e +. u r n its '. : l '. a v

m * . c 311- close the combtned return Itne

: o '. > t t ., n vylve.

OUE27T09 2.02 # I,2M l tefc cing to ,noctded F iq' c e .10 ') . incicate whether the followinq valves - . ,i rece:ve in GoEN. m0DUL4rt9, er CLOSCO :13nal fc- the given makeup mode

2 e '. e : t o r switch pe:t* or. vmo it7rt : Ljnel present.

114A [Il $ I. [ 0 I t4 i*i e ' 'T' _$

" .1

1. *s) O L II n T 1.

- .\ l.?* *' T.

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,e 1

i. d .e ,,9 .. .-..a -

d. 114"- .n -:0 cart W* L J .79 [J 'E

- - W(.c,

(***** CATEG00f 02 CONTINUED ON NEXT PAGE ******

PLANT D E S I';H IACLUDING SAFETY AND EMEPC.ENCY SYSTEMS c ,:, g g g 2.

-i (j 3 -

GUESTION 2 03 W Match the AFW T & T valve overspeed in C o l o .1, n A to the reset 13 cation er condition in Columr. ?. More than one answer may be correct for +ach.

ALL correct a n s 'd e r s are e g .it r e d *r # ell credit.

COLUMN A C O L U ** N S

1. Electrtes; a. ?sset # rom Control Roon,

b. Auto rnet on bus strippin3

2. rae c h a n :. c a l c Auto reset on auto 4 F 's itset

d. AUtC reset 4 hen EP99d decres?e3 9 E *? 5 e t 10 0 3 l l'/

GUESTION 2.04 (1.50$

M3tch the source in Column A tc the l o c : t . a r. It t: norm'lly collec s:

in Cel.in n . .

COLUMN A COLU.*N 9 7

1. PCo 43 Ses1 Le sk of f 2 Ces+e -%ldup ent

1. ' estocL:er R e l i e *' T .a n k

.: , 3 <-'--i T nk

2. CCW ?"r 3e r nk Vent oi-

d. Reset.- Coolant 0-_- T .nk

', 2 ri & 3e mp I '. e t $ ; U r, '~' F 1 . e f 'l- 3 " a

n . . - + +tn is .,c, .

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ce .de- ' - ' t 73 C '. 'J: . ' i m p e. - what v:lves sociated with the CCW o- >,-

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2tgnel? ( e. .5) n o. r.. .- . v n. N

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l - l '. a w i n g :.e-+-,

'< 2 '. uith *he I r, t a k e Coolin., u nter System (ICWS).

us * :: e rho Tacyr - .: ;- 3v;,-lied by *he TCUS? Do NOT in:1ude r ' d i n d a r. r '_+im (0.,5) 5 U ;- _ :n +he " r . <:. s ctrectiv 2ffe ted by a safetv

-- atjn11' ' . - . * .;- in yo..r - is:ser . Sow and why 1 +.

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-d, ,g t,lon t 1,iq; 7+;e.g 7.,,5ggng g ny g 3 ; g c g 11.j

r,' p ; c r i b g .c y 3 c l- gener teg 9 rod r,c;,ggon g;.gn31, n.. . '. c. " * '. n. o)

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q. u. ue e_ lv T n s. e

~ . 1 s '. (1.en; J-Descr.be *.e :r.rce 2nd *lowpath cf power from t h e 'i . +. a . ~CC *c 200~

' '> t t .r l 120 V In s t r ' nent e t : c- E* u s A> for the tol owin3 ccadition-cre"te,e bus es eC major componorta (transformers. switches. etc .

in voi r d e : c - i ,: *. l o n . It t2 .u' necesssrv to i n c 1 ' .' e b r e e b c- r :

3. Nort :1 At over O rs e r t an 0.'-

b. c.:t altarnste for lo:: o* inve"ter 3A t 0 . !

Ir er ter 3A he: been out cf tarvice for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months '0.5%

v t i n. y n., i_t e_ c_it. -

6 -

t' .. . n. r )

Desc :.be t ne O'io #1cupsth . '.i" r i n ,3 n o r m a l shutcown coolin3 oper;tions.

In c l :.i j e iccc ruction snd returns Inc cli msjor componants. Unive r.smes a" numbe-: 3re co' nece?c ar . -

OUEeTION 1.t2 < 1 . " ^-

'tst

. 'le 'k?EE u n c *. t a : of the 'lo r r m a l Containment Vent:lation Svstem.-

'***** END OF CATEGORY 0; *****)

~

3. ins';*_'ncNTS AtJO CON';': 5 oAGE ' :.

'i'.F S T I O N 3.01 (1.001 uht:5 of the 0llow tr 3 #

.- Corr?C' C o h C U " n ' cr3 the 50vece r- ? n g m: : S 3 n e, e '

hi3h voltage t' o t o f ' '

3 S u r : r. 3 e re2ctor - *- ' '; : et+her !* pinnel increa: _

3 t e _, c - 3 a ll t..r,

. J' the 5 : 3., 20'+ ge.

b. If one 14 channvi ' 13 leu ubtle at :over, t h .; Source Fsnge : gh en ' t 3- e: l '. be re-orrgiri

c. wo out ' four I' c : - rels above 10% cover will turn o t' 3 righ acl+: ,.

d. C .:r t r 3 s re2 ..:- nv+jown etthe- IP channel decreasing bel. u :-s will t u r e- r the hi3h voltage.

OUC5 TION 2E (1.00)

'5e :nput to the rod incertion limit calculstor usad as a direct indica-tion of reactor power it:

4 li%pul3e *re13009

b. a t.> c t : c n 3 e r e d High T3

c. Totil Steam Flow A t i r,

a n n .a r e d w:g- Pn1 g r t

Q t .I C. C *

F rJ

. S..S.3 ( ..

n- i Of the # 3'.lowin3 s:.gn213 that de-er ergi: e the d:emel ' C: e -3 d y To Start' l i g :- t , wh::h :. t alco inter 13cked to prever' *ie diesel from ittrtin'g?

c. Low Starting Air ~ e e : v r s?

spas-

b. Fev Switch in

. im I' i d T:nk ' evel

d. Lew tr3100e 0:1 Pressure

e. 'ow Prelvbe Oil T e at.c e r i t u r e rereee c A'r i; r 33 CONTINUED'ON HEXT o t.G E <<***>

.; q . ,: o. r .e :.

, e. , c c n. i .: c A r, 'r_ ...

'm E S T 12 9 3.04 (l.00i which ot +'+ fciloutng m:1+er,ction wovid ::vsa 3 pre?:' : " l a s e '.

Od:C3* Cr ?* O '. '

c. do :311 d im ,r -gm rupture 2 wefe e :e 193 rvs r ure

.: 'mpol-e i t r. e roptore

d. E3v=: : i n _a /sive l a s k s i. e

n. i .t e c. T I .,9

o. . , . e. . +. . a n. i.

,. th the re:ctor at 100 and tha -*c'm dump contrcl 'Ivstem in *e ' vg

e. ode- e 10 '. -tep lo s :# 9d occurs. -

As=vm:n3 no reactor rurt.

le Condenter 3 S 'J 1 : 12hle. and the .eactor oporstor m 2 *> .i a l l , QPgcATgg

', e

. c r. t r o l -:d:- w h - ' tha f oll aw :.ng woic id , cur if B a r.k i -2527

-e' C '/ ~_ G 2 9 ) ;t.- ; .s n .- -t .e. 5- t' *o cpen?

c : -a - , o _. m : ,,7 g,n> way;q open,

. A t r r; ,- ec. i'i~. .- i ' -j - _ r. .

.' a i - . ,

u; 3' .

-* .-, ',g.'- eld : s e r. .

, , ,,..,,,.3,

'h- 'o l ' : w . .g

, d : + : o r. - a 11 ver'.ilt :- - r .s a c t o -- .r:'.

= '_ w flow on 2/3 d e *. e c t o r s in l'3 locpt when C-7 rnd :-9 i,y

. riow c r. 2,' ] c e + e c t o r ,; in 1? l o o rs 1 when -9

- .aw '!cw or 1/2 de* acto *3 in 2/3 !aop- h e r. P-7 snd P-9 3 '_ o .i ' : v ;n 1,' 3 detector; in 2/3 loops when P-8

(***** C A T E C ' ' 03 C0t'TINUED ON r4EYT PAGE *****)

1

_. ..y e. - , i., .,. _ . ; + . -

s, n +in.,,,.-

_ _ . e A r_. _ '.,

QUESTION 3.07 (1.50i Answer ' RUE or CALSE to t5e f:11owin3

a. u t '. h no r o c m : ' ' o r. :o or,3re ; and *he rod: :n. .

. -1 tb. r..,-

, .,c,.... ..s. m o. +. s ,-

r. +.. ,=. . , . , +. n. .i . ::or r e . e . e. , + a. . -> =.' ,n_._'

n. < e,- -m.

. .,.e_

'. The bank o t e:

s p .i n t t w'.' ' '

cant : t e r. ! ;' the rod co-+- '

d2ne =.. ' a c t o r tw:+.. , -

U'-' o- N " U ; '_ . . g,

c. 0-1; one :f tFe t: 'oa ' ~. c . his- ;+:':3n?rv. or 1.+' : o :.1 :. c-

4. - . .

r,.p,n. u .. .. c , y . _-.._n. - .. -

,+

r . r. , 2 t , g, . .

,,,.c.

n.rqT .. c_ n , , .m n ,

_4i . e. r Ind; ?*? w h e * '- - *5e 'c' . : -*:'enant: c o r.c e r n i n 3 .s :=tance

+. n. m , c. t . *. . r a. . .=

n . ' . . r . (~"..

- .:- * : U C_ o- - C A L':.5_ .

. 1. . . ::T O ;e : a n n e c '. 3 ' cc ;a '. e 3 of a bridJe .: revit. J. :

+:mpe"5,vre 6 t 11 : ? :1 ? crg ; h 3 -. 3 9 i = 3 prOpor+; ohs 1

-- . r . . g ,

12 q.i t.u,,e . '- 1. - :iir r en t 4 q :- 3 the ha i d.2 9 .

. " E- (0.")

e, ,Sc r _ ,, 2 c. c :'. w :. '. r . d ; . :. + e 3 dow ac:le <10w)

. . - :. - .,. ,>= . s, i r. e,.

F g e, QTF . .

.., 1. n. * .

.- ;e c . *+-... .. S <

t. c 2 r e. t.i p 3 +. c. *. ,

y- s.

i-,,, .$,.7 : ..

.....s .

.,. <,.y

. , - .g, , n. . ea 3 m

<, t g r cs + *.p., g

,7 .

'o*he- the 0 c- c ower 0+1': 'enper2+or:- trip setpoint w :.11 r-dc:te -

y c e e,,e .

. n e r c.c..,c e , .- re e. n ' s r u e.

g ;., e. ' c. .

h a. " o '. .' '. w . n.,'

e = *. ' m a. t a. r

<1 r 3 e Ccr, ide- each separstel .

.. * , _ - a. s. .- ,. r. -

_ , 7=.- te.e) .

b. r g.3 ;g;; , ,+ , y, ated ,-cuer T 3 c3 ( 0 . 5

1. : r e_ e_ r i r ., _- 2_ . . c r a_ _ e_.i.ir a. .'.'..c_.

. _ _- . n. , ( c.a . " )

( v '< * *

CATE00'" " ' n_ d T.r_ n. u e_ n_ .. _ n. o. a. c_ .<. T. o .4 c r_ ressa, m______ ____________.._______J

T r

g :. . . - c. . * - ,<, .. e. n ,i t e c. _ _ c mm' r '- '2 QUE5' ION 3.10 M.> l

Indicate whethe" t' 2 #cliaw;r3 v 1.2 ' components recetve :

s ere-Injection;- '?' 2:e A Ire'.Ittonf. or 'P' ( c :' e s e E: Italc+1e- 2 1.g r, : 1 G r.1. ;ne : r. s w e r : : c r 3 c +. *' o r each val.e/componen+.

2 Con *ci.mant Sump P'im - .

'2 _etdown Line I';olat:cn ' a l 'e (5'l-204) e c r e s -: v r : : :. " %2ter: - 3 : '. v p Grcup A

d. CCF c. e a l S e t .'a n I:ol3+.:n '121 v e ' '10 - 191 )

e. C e t . '_ t : - s r t t ' e n + . '. : t i a n I:o'rtion -

.m e.

v r. r , -

- 3. 4. -. ,,. . .>-n. 3 e s' :n 6 h .e frllowin3 res- :- condittens in Column A with the rod :ceed Column C.

" C '_ ;' F ' A COLUMN B

.. witwar,u: 3 shut 0 un ' " c' in Shutdcan 1. O c ., m ovJ - cosition 2. 16 spm

3. 24 opm

b. 'J : ' c r e w : n 3 C o n t r o l Bank B in Centr:1 4. 4 >3 spm 5 :. r. 4 ? position \

5. 64 spm

6. 72 spm

. . tot tt: tr.:er tior. wit- tsv3 Tref bv

-'e3rees

.. A't:matic .ns er tion a :. t h Tavs Tref by

!.T decrees - .

, . <4,e a n.J -c c t r. na >

s . : . n. na 3

'. t * .Y . L of the 3 g ul; that will cause Main Steam 'ine Isolation.

. _ Set-

,c o : r . s*

r. o t re:v red.

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

T

c

7. , v. a. j c_ y c t_r.a. c_ e.1 T C., / r F.. ' 9 .'J T n. '. <.

- C. A G '.- ..'

O' JEST 10N 3.13 ( 1. 0 0 '-

t he f o11out i 3 quest ienc concern PRMS Ch,nnel P-10 ( 5.' G 91;ae , L: quid Act:vit. : : tori

s. whtt t/pe o *' d e t a c '. o r :: used) .9 .:

5. Whrt THREE contro' *

n:tions re carf r7ed bv thl chann?!? NOTE:

Redundant "o c ' : c n : count -

2'e. t.e.. clo in 3 MOV ~50 2nd ~51 wovid c .e t as coe. < o . .g. >

QUESTION ?.11 1. 0

' :s t ALL 'he interlock: *'tt mus' be :m t before the ;' H R s u c t :. o n . clatten velves (m00 '50 2. '51 -. se nc>enad.

OU STION :.tc i %-

Assoit w the cr.s r a " o. v m p t are running, what s13nal will o n t s : - ', e

vtom t:.:cil, i n : t : s t .e :u g e r.c v ccntain,ent filter deusing?

1. . 'a T. *L p p

. '.' . 1 4 e ( s. n. o.

'1h

. - & f -; t e; 3 . c O t .s .--

3 ' 'i g ? g .- [ -l e r.p t S t Q p *' r g i OygtlQ3d if 'Ng diggel

.- 3snchr r.,;#t *, .I & .s 3nd : n .: i n J a n e. r ar trip cc:v 1.

nie7? ON 3.i' u: &h ,* .c eac+3- (* -' 5 7. c. ra e r 2nd - '. Pr.tsrv ccctrol: in a u t o m 3 +. i c t c i 2 5 3 ',' r '. , 2 9 f GJv51ure t r : .tri; e . g r or_a2$ 5 g y *. 2 hl h. A 5 9 011, 3 B C

,e.et: c ,' 'en2 occur + cribe tha re son:o of the pressu 12er -

prollera c

21 - J t e'ri: , C e n t i r,u ? de 5ct [ tlon ur t: 1 ' : sup12er

,- . suc 2 : :

'21-0 or a enc'e- trip orcur:. Include all a p e- 1 :. c ? b l e etc.:nt1

( m r. THn OF CATEGOPY 03 aves.)

l 4

3

%, O' G; O C 7_ ^ * .* ~ ~

l O O r* R. L . .O SIC OMAL- E a' E C' G E N C Y ANO . ace .

--- i35?5E5GicIt 55sTE0E-~~~~~-- ---------------

O.l.iE.s c 'i ". ". 4.01 ' 1. . n o, i Which of +5= 'ollowing statements describes the correct usage af the Cr t::c'. Safet. run:tior; (CET) Status Treet while performing .r.y-E 9

'% 3ct:r T 1,: er 33fet, In;2ction

s. %e C3F Status reaes :e NOT mor: tored until E 0 c - E - .- 3 e z : + ..c

.,. c,werenes: c' G ed Pat? Cr;teria : reoutred :* 211 :mes. but +ha

37 St:+v 't aer tr e monttored or1 fte* it is d e t e r m i r. e d that

?I :n 'O' b -2 t er m:n : t ec

c. ":. ' o r :. ,3 c +' th+ "cr Status Trees commences as s c. c r. s the

. .n n e d i a t e :' ion : t e,, : sre completed,

f. CS Strtus Trees 2. e required to be monitored s oon er the pr:: +dur7 erterad and a valid SI 13 determined .c have o c .. * ' E.d .

epJ :.. se r. +

. .ce

. - 4. v.-_ ..33 hic'. -

w fellowing 'tztement: correctl/ describes the ma;or difference regar di g 5' + w m: net or. 2 9 *. .- e e n E0o-E-3 "S'G Tube Rupture

and ECA-3.1 5 ': -v :. e :upture w :. + :, :-= of Reactor Coolant--Subcooled Recoverf*')

Totn cre:edurec i t:11:e the same SI t : n tnation criteria and the

m- 3rmtr.2 tic, method .

b E-7 .11 NOT s '_ ' c a T' _ termination if a void entsts in the upper he-d ;f the . ' . shile ECA-3.1 will 2llow SI t e r :t i n a t i o n in

+, , . +.

+ .- . . ,

c. E -- ? term:iltes both '_WSI and H95I pumps simult:neously whil'e ECA-2.1 termir.:*+r the LHSI pumes when diF#erent eriteria from

'hr+ r quired to trip the HHSI pumps e"12t.

. E-3 oi; n z t e s bot? FSI pump s simuitsneousiv. while ECA-3.1

.cm. :t-; the ups! pimps one at a time, ereer, .ftre cy c .: CON'INUED CN NEXT PAGE *****)

.} , O - 6 e. ". r. .

S ?. ? -

ti'l.' n *,' * ' l '. : ,4. ',1, , { ~ * ", O

. $ E ' II' Y * , (19 p g,,

p> T ,~

e

~ '~~~~~~~~~~~~~~~~~~~~~~~~

Lb5IlA ld EUL

~

q ? .t i.* o '" .* f.i kj d,.'". (1..A.- <

'J I 's 1 C '1

hQ O 1 I, .2 *.I . r } I * ; I -? 'fl 9 3*: t $ reg 3I I ', " -} P[3Ft C[@3r?*qgg t 1- q g p p ,a .; g 7 7 When 9'9Cyting Il ;*3nce Ord4"* 9C' 0 " O P R t 10 ri mi-' ,, c.

- r. a. n c e.i r. +. _s ."a L l'i th9 Or IOP ;D 4 h l t. $ 1 1' d .- ;, ? ..

- + t e a. . _- or- s. the .iectr 00 1 s w i t e r r. g i;

t. '4 h e " r s t i. r 1 i j .

dOre f'r'*.

d'it6 t ?'s y ? P 'h 1 ': . O r.

"- *: '. 1 C '. 9 i r ". f a L . f21 d Q r S UiJ1t t i2 $,4 Q lfi + 3 *, n e d De# 0 ed .< 0 0 # q r F.1 n ' t e th "' O r 3 ! '/ ' ' *' t t' d r

.?3b .'Or"OE9: ..

. If ? rt -j u c t l i n g . . i '3 " : n C *? In ' T 'i f 34 in?ted -3 r e 3 ' th9 or131n31

-) > v ..# t F. a '. - .ti- 3 . :. e # 3 :t ' h r. 2 n t r 3 r.c e tO thp 2re? , r i r" .:

. sittilei i , s ,. ' r. : S a[ l on.:tcc Op0n hi3 O' i t

" If '-* ] P C t ' 2 , ?. J . i

-" : r;.. ' ' . TCc +c:p ce tter:3 following an SI

.' t.S the *' '.1 : w i r$ - .

w;+- 3rni c o r I ' t n a. . - .

I* * ,4 i'm -.,,3 *

9. *. I"-

1 osso 1--

. -

p ,;s . c.

, 2 .. .

. 31

. r. . .

_- } l' } .) ~ )( } ' ", h * *J D

.3r- .

ii ' ' "'- :I 59' r i.' n n i ra.

e*

5O-- , .r ss

; ; c'

~ . ,, , . , , .

I % I . g 9

. . k [ '_

";*'A WW ** V- 9

-f.P P g g pg 333,

'I .

t' L '

2 *o o r: 9 e m e: r g e n c - - 7

, dur9 .* O an ther. 2ny L.t c .' r - - -

t. h e +1%9 3f the trir. t+t en :

y e' p ' "i ' be Ora; 1 ra t e d ,

a..g .

8

.- .- i .. . c .O .. d. .

g

a, c c n. r. . :. : '- _ _

. . r , ._ . .t,: ,,_, c_ w e_ e r, n_ r. y 2.in c. A c _.., _

,OIP_9CICAL CONTPCL i v, )

01.'ESTION 2. 06 e

-_ndic:te . :.e+"-

ie # ' '. : w i n ; p r e c : v t l e r. : regardtn3 uni- : t :- + mr_. ,e i t o .

r o -. s.. .

_.- ._.. . , ri :.. ..-, .

..___._2 ,

tn m _. . .urr 4 or o n_ r u.. - l i n .r r e. -

--d'N

-e 3 LII O O , . .a.

~^

MTl 7_ +4 h h $ Ob- b '* * .I . .g llp$ C(

C"C7 5hc: 'd r: J' e ee; .e*' .i sye.e J - h i . cc. tic ' ', :h_11 co + ba . n t e ad 91.m "72

. degre.ss c

=vr9- -* p r ta 5:ioi': d ;t :- -ead o f' d29 ee: F J 'a r

.iie

. .. ._n.N 4.n_ -

.,.e..

'_ i s + all 'he ,i:. . + e c. car' t r- e c in C O C' - E 'oeactor f*

is or 5afe' q' f c.9 d W 3 t 9 F ;iclsticn. C

. n . 9: '. ; g r .

f 3: .. e r # : r, n ,- . c r - +' ; c g

e i, C.

/ec . f i c n i :n: : .d :ne :c 1 . ;- re i;1 red t' o r full cred1+.

. . u .,c . ,

u; r ep.. '

'artn -3, pipo r u p '. o r e ' . what 4 .tems of

': ra=- -- =n;2: : -

a: :- 20102 to be givan to the PS-N

_ ,, <g.- -

t i. n. ,

contact the DS-N?

. ; : :, y - _-.: . , . f .3 . . .1; ..3 .isec

. .0 'O.5*

n r-- re : .) c u .- ,: .e- : - to .:e w-ter to :cmbat 2 fire in the vicinity of energ;:sd. h i g r. -v o l t a g e electriell eo,vipment, what 2 o,recauticns must be ridhe r ec to while .i r i c : the w-ter 'cse=? .

n..;_;;.:.

_ _r %_ q , ,4 e/ < 4 > _; .

3. while cc- ' :c t in 3 an Independent V e r l +' 1 c a t i o n per A0n 0103.4 w"2t tre THoEc ie'.=.d5 bv wh ch valve posit:.cn can be verifict) ( 0 . -' 5 )

b. What .a r e your 2:tions if you find 3 valve out of position? (0.5)

(*x**a CATE".r y 04 CONTINUED ON NEXT DAGE *****)

4. Fc ore 9 Jc Ec - NOPMAL. ' M O R M .i t . E.MERGENCY AND

. c.g g g .o

" ' " ' ' " ' ' ' " " " " " ~ ~

"'75650EUU5C5L C 6UTEUL OUISTION 4.11 (1.00i

'J h s t are the shutoff head pressores listei in EOP-C-0 #ct oath t .o HHSI .d ' H5I ovmps below wh ic , SI flow needs to be verified $

GUE3 TION 4,12 <1.0^-

cunctienal oestoration Fracedure CF-5.1- 'c esponse to Nuclear Power Generrtion/ATus' her the ccer: tor trip the turbine es o r. e af te immediate act.ons, Howe"er ar e of the major concerns in the A T'J S t r : n e e r. t response eusiv:t;on; 1- the e n c e s: e l v e RCS pressore developed r;o e t- 5.3nificsnt he t'.? cf the primse/ coolInt, Since keepin3 the turbine on the line would n.it1=3 ate thl temperater? rice. w% is the t'.cbine tripped anyws,?

OUESTIO" 3.12 (1

uhj t 'hcro 2 p r e c 3 e t t : :. r ' m:te in E0P-ECA-0.0- " Loss of All A/C Power'.

.- mor tt-- ., csr e t .- i . ; 5es fer inform:tton oniv. but net for purposes of Lc ;' e ne, t :t icn?

~ c rns ,c , t e (,,<e, T r. Cr.* 007.~. 'Los cf 12 0 '.' U t t a l Instronent ' el 3P07*, whv. is there s ,

~

c :- c _ u t : : r. tc avoid redor n o e d # 1.3 w tc less han steam flow, assuminq a i

.:*:r trip hs not oc:"'r d'

n. l-lc : ' T. q u.

-. . a.1. ,*'..e,.'>3 03- t'.. 6% e q u t r .c d :per?tcr act :ns acc:rdin3 to OP 0202.2 if th4

", 'l.mn; ::toation- er:+e efter t% 3rd doub11n3 durin3 e 1/ rl epproach

'> t' .c 2 i t t. rnelnde 2n/ authorinetions requ' red +o continue startup

. pro'31 ems 2re d;s: ..erad.

?. Pr >jer' > ';tical cod position is below the insertion limit. (0.6) 3 ~ 'o, ted criticel red position deviztet frcm the ECC cod position

. 510 pcm. (0.o)

Jirvrus c A T- r cm V 04 CONTINUED ON NEXT DAGE *****)

2, : q n pp - - in 4 v, . ,7 e ? a A t, , '.-Tr.CErJCy A rJ D cagg y, CONTFOL e A M '___0

_--- GICAL w . . ,. ~*--

, 4 * .

' e . *l . 54 ! . - % 3* W 3+ 2re ALL

T es 111ed:ste Dr.e s*.c" Act.n- 'ar a rh e l f ' ' n c ' l e n cf 907" Soi.rce a nn :e

, h In n 913 T'

[

I 1 6 _ . 6 , ,

If*IA 'I e i t $ s E tJ C O F E'I f,'* I t:A T I C *' ***************'i

l

.a

b i 3

, , , t : ! 6 .

t.1 - i. - i

. i ;

hq[;r: j ...

. . .1: .. . . .l

. . .; j.

....;c... ,- . 't: i. f. . { ll!! !it'; pi y;clp, '. .'

. .: ..l . .

- i h-W .

iir j;'.jihi ..

i .; ;;

. ' .,e.d. .:if:.i liil

.i. ...

..i

i. : ." i . - .! . I I. , . i . m .

]

r : :. :I i. n; I .i. i . i.:

....-[... :::

.. . i: .

I- .

n ..n i.. r, l i

..a. .6.. .. ., .I .

I i..,

8; ii.

.I

~- .

,I c, :;,i ..i .i

.; !. h

. l .,

.;p i"ql .r:, p ....

.: !!D la l

t j. 'l '

i j.g

.l'g'i

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, , mg se V,t + 1/2 at 2 g = me-(E = 1/2 mv a=(Vf - 13 )/t A = A *4 A = A 3 e*

PE = mgn y =V + at * = e/t 1 =

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SUR = 26.06/T ,

SCR = 5/(1 - K,ff)

CR, = 5/(1 - Keffx)

SUR = 2So/t= + (s - o)T s CR j (1 - K,ff)) = CR 2 II ~ "eff2)

T = ( t*/s ) + ((s - o V Io ] -

M = 1/(1 - K,ff) = CR j/CR, T = 1/(o - s) M = (1 - X,ff,)/(1 - K,ff))

T = (s - o)/(Io) SDM = ( - K,ff)/K,ff a = (X,ff-1)/K,ff = AKeff/K,ff t= = 10 seconos I = 0.1 seconds'I o = ((t*/(T K,ff)] + [a,ff /(1 + IT)]

Id j j =Id P = (reV)/(3 x 1010) I jd) 2 ,2gd 2 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 10m. I curie = 3.7 x 1010 aps 1 gal. = 3.78 liters 1 kg = 2.21 lem 1 ff = 7.48 gal. I hp = 2.54 x 103 Btu /nr Density = 62.4 Itg/ft3 1 mw = 3.41 x 100 5tu/hr Density = 1 gm/cW lin = 2.54 cm Heat of vaporization = 970 Btu /lom 'F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm .

'C = 5/9 (*F-32) l 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/in. -

e = 2.718 1 - -

Wehame, ft'/lb EMhelpy,9ts/lb EMfepy. Shs/lb a F Temp press. wge, Evap $ team C;tet Evep hem Ulmer Ever Steem r .a A A % s, s, y, vg og b ss s e 3305 3305 -0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 at 0.08859 8L01602 0.01402 2948 2948 3.00 1073.8 10762 0.0061 2.1706 2.1767 35 35 0.09991 1079 0 0.0162 2.1432 2.1594 40 0 01602 2446 2446 8 03 1071.0 40 0.12163 1068.1 1081.2 0 0262 2.1164 2.1426 45

0.01602 2037.7 2037.8 13.04 45 0.14744 1065.3 1083.4 0.0361 2.0901 2.1262 50 0.01602 1704.8 17048 18.05 60 0.17796 1059.7 1067.7 0.0535 2.0391 2.0946 60 0.01603 1207.6 1207.6 28.06 GO 0.2561 868 4 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 70 0.3629 0.01605 868.3 633 3 48.04 1048.4 1096 4 0.0932 1.9426 2.0359 80 80 0.5068 0.01607 633.3 468.1 58 02 1042.7 1100A 0 1115 13970 2.0086 90 80 0.6981 0.01610 468.1 350.4 68.00 1037.1 1105.1 0.1295 12530 1.9825 300 100 0.9492 0.01613 350.4 265.4 77.98 1031.4 1109.3 0.1472 1A105 1.9577 110 110 1.2750 0.01617 265.4 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 130 1A927 0.01620 203.25 130 157.33 97.96 1019A 1117A 0.1817 1.7295 1.9112 130 2.2230 0.01625 157.32 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 140 140 2.8892 0.01629 122.98 97.07 117.95 1008.2 1126.1 0.2150 1.4536 1.8686 150 150 3.718 0.01634 97.05 77.27 77.29 127.96 1002.2 1130.2 0.2313 1.6174 13487 160 160 4.741 0.01640 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1A295 170 170 5.993 0.01645 1.5480 12111 180 50.21 50.22 148.00 990.2 1138.2 0.2631 180 7.511 0.01651 1.7934 190 40.94 40.96 158.04 984.1 1142.1 0.2787 1.514S 190 9.340 0.01657 1.7764 300 33.62 33.64 168.09 977.9 1146.0 0.2940 1.4824 300 11.526 0.01664 1.7600 210 27.80 27.82 178.15 971.6 1149.7 0.3091 1.4509 210 14.123 0.01671 26.80 180.17 970.3 1150.5 0.3121 1A447 1.7968 212 ,

212 14.696 0.01672 26.78 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 220 17.186 0.01678 23.13 19.364 19.381 19833 958.7 1157.1 0.3388 1.3902 1.7290 230 I 230 20.779 0.01685 0.01693 16.304 16.321 ,

20845 952.1 1160.6 0.3533 1.3609 1.7142 240l 240 24.968 1.7000 250 29.825 0.01701 13.802 13.819 218.59 945.4 1164.0 0.3677 1.3323 250j 11.762 228.76 938.6 1167.4 0.3819 1.3043 1.6862 360 250 35.427 0.01709 11.745 10.060 438.95 931.7 1170.6 0.3960 1.2769 1.6729 270 270 41.856 0.01718 10.042 8.644 249.17 924.6 1173A 0.4098 1.2501 1.6599 280 1 280 49.200 0.01726 8 627 7.460 259.4 917.4 1175.8 0.4236 1.2238 1.6473 250 1 250 57.550 0.01736 7.443 300 67.005 0.01745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300l 5.626 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 310 77.67 0.01755 5.609 4.914 290.4 894.8 1185.2 0.4640 1.1477 1.6116 320 320 89.64 0.01766 4.896 3.788 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 840 117.99 0.01787 3.770 0.01811 2.939 2.957 332.3 862.1 1194.4 0.5161 1.0517 . 1.5678 360 360 153.01 0.5416 1.0057' 1.5473 380 0.01836 2.317 2.335 353.6 844.5 1198.0 l

380 195.73 5

l 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 400 247.26 0.01864 1.8444 1.8630 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 420 305.78 0.01894 1.4808 440

[

1.1976 1.2169 419.0 785.4 1204.4 0.6161 0A729 1.4890 440 381.54 0.01926 460 l

0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 466.9 0.0196 0.9746 480 02172 464.5 739.6 1204.1 0.6648 0.7871 1.4516

! 480 566.2 0.0200 0.7972 487.9 714.3 1202.2 0.8890 0.7443 1.4333 See 500 680.9 0.0204 0.6545 0.6749 l 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520

523 812.5 0.0209 0.5386 0.5596 536.8 657.5 1194.3 0.7378 0.6677 1.3954 540 l

540 962.8 0.0215 0.4437 0 4651 562.4 625.3 !!87.7 0.7625 0.6132 1.3757 540 SEO 1133.4 0.0221 0.3651 0.3871 589.1 589.9 1179.0 0.7876 0.5673 1.3550 580 540 1326.2 0.0228 0.2994 0.3222 550.6 1167.7 0A134 0.5196 1.3330 900 600 1543.2 0.0236 0.2438 0.2675 617.1 506.3 1153.2 0A403 0.4689 1.3092 820 620 1786.9 0.0247 0.1962 0.2208 646.9 454.6 1133.7 OA666 0.4134 1.2821 See 640 2059 9 0.0260 0.1543 0.1802 679.1 392.1 1107.0 0A995 0.3502 1.2458 560 640 2365.7 0 0277 0.1166 0.1443 714.9 0.0808 0.1112 758.5 310.1 1066.5 0.9365 0.2720 1.2086 480 640 2708.6 0.0304 0.0386 0.0752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 700 3094.3 0.0366 0 1.0612 705 0 0.0508 906.0 0 906.0 1.0612 705.5 3208.2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)

A.3 i

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0.01602 3302.4 3302 4 0 00 1075.5 1075.5 0 2.1872 2.1872 e 1021.3 e.8886 acee6 32.018 0.10 35.023 OA1602 2945.5 2945.5 3 03 10738 10768 0 0061 2.1705 2.1766 833 1022.3 e.10 i 0 01602 2004.7 2004 7 13.50 1067.9 1081 4 0 0271 2.1140 2 1411 13AD 1025.7 RIS 0.15 45.453 0 0422 '2 07?S 2.1160 gae 53.160 0 01603 1526.3 1526 3 21.22 1063 5 1084 7 21.22 10283 0.20 0.0641 2 016S 2.0809 32.54 1032 0 0.30 64 484 0 01604 3039 7 1039.7 32.54 1057.1 1089 7 0.30 0.01606 792.0 792.1 40.92 1052.4 1093.3 0.0799 1.9762 2.0M2 40.92 1034.7 0.40 0.40 72.869 0 01607 641.5 641.5 47.62 1048 6 1096 3 0 0925 1.9446 2.0370 4742 1036.9 e.5 0.5 79.586 0.1028 1.9186 2.0215 53.24 1038 7 0.6 85.718 0 01609 540 0 540.1 53 25 1045 5 1093 7 0.6 '

.466 94 5830 3042 7. 34003i 03 .. 3.8966 2.0083 . 58,10,.10sa3 42'

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9.7 ~ 90 09m (L01610 - 466 93 0.1117 1A775 1.9970 6239 1041.7 62.39 1040 3 1102.6 0.8 02 94.38 0.01611 411.67 411.69 0.01612 368 41 368.43 66 24 1038.1 1104 3 0.1264 13606 1.9870 66.24 1042.9 0.9 O.9 98.24 0.01614 333.59 313.60 69.73 1036.1 11058 0.1326 13455 1.9781 69.73 1044.1 1.0 1.0 101.74 0.1750 1.7450 1.9200 94A3 10512 RA 2.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116.2 0 01630 118 71 118 72 109.42 1013.2 1122 6 0.2009 1.6854 1.8864 109.41 1056.7 S.0 3.0 14147 0.2199 1.6428 1A626 120.90 1060.2 4.0 4.0 152.96 0.01636 90 63 90 64 120.92 1006 4 1127.3 162 24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 13443 130.18 1063.1 S.0 5.0 61.967 61.98 138 03 996.2 1134.2 0 2474 1.5820 1A294 138A1 1065A 6.0 6.0 170.05 0 01645 14421 1067.4 7A 7A I76 84 0.01649 53 634 53.65 144 83 992.1 1136 9 0.2581 1.5587 13168 S.0 182 86 0.01653 47.328 47.35 150 87 988.5 1139.3 02676 1.5384 12060 15024 1069.2 S.0 ISP27 0 01656 42.385 42 40 156.30 985.1 1141.4 0.2760 1.5204 1.7964 15628 10708 9.c 9.0 0 2836 1.5043 1.7879 161.23 1072J 30 10 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 26 80 ISO 17 970.3 1150.5 0.3121 1.4447 1.7568 180.12 1077.6 14.896 14.696 212.00 0.01672 26.782 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 . 1.7552 181.16 1077.9 15 15 213 03 20 227.96 0.01683 20 070 20.087 196 27 960.1 1156.3 0.3358 1.3962 1.7320 196 21 1082A 30 30 250.34 0.01701 13.7266 13 744 21S.9 945.2 1164.1 0 3652 1.3313 1.9995 2182 1 3 7.9 30 40 267.25 0 01715 10 4794 10 497 236.1 . 933.6 1169 3 03921 1.2844 1.6765 2360 1092.1 40 84967 8 514 250.2

923.9 1174.1 0.4112 1.2474 J.6586 250.1 1095.3 50 50 281.02 0.01727 60 292.71 0.01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1A440 262A 1098.0 SD 70 0.01748 6 1875 6 205 272.7 907A 1180 6 0 4411 1.1905 1A316 272.5 1100.2 M 302.93 281.9 1102.1 80 80 312 04 0.01757 5 4536 5 471 232.1

900.9 1183 1 0.4534 1.1675 13.208 90 320.28 0 01766 4.8777 4.895 290 7 894.6 1185.3 0 4643 1.1470 1.6113 290.4 1103.7 90 100 327A2 0 01774 4.4133 4.431 298.5 888.6 1187.2 0.4743 1.1284 1.6027 298.2 1105.2 ISO 120 341.27 0 01789 3 7097 3.728 312 6 877A 11904 0 4919 1.0960 1.5879 312.2 1107.5 120 140 353 04 0 01803 3 2010 3 219 325 0 868.0 1193 0 0.5071 1.0681 1.5752 324 5 1109.6 140 160 363 55 0 0;815 2.8155 2.834 336.1 859.0 1195.1 0.5206 1.0435 1.5641 335.5 1111.2 160 ISO 373 08 0 01827 2.5129 2.531 346.2 850 7 1196.9 0.5328 1.0215 1.5543 345.6 1112.5 180 2.2689 2.287 355.5 842.8 1198.3 0.5438 1 0016 1.5454 3542 ,2113.7 380 200 35180 0 01839 250 40097 0 01865 1.8245 1.8432 376.1 825 0 1201.1 0.5679 0 9585 1.5264 375A 1115.8 250 300 417 35 0 01859 1.523B 1.5427 394 0 806.9 1202.9 0.5882 0.9223 1.5105 392.9 1117.2 300 1.3255 409.8 794 2 1204 0 0 6015 0 8909 1.4968 408 6 II18 ! 350 350 til 73 001915 1.3064 780 4 1204 6 0 6217 0 8630 1.4847 422.7 111E 7 400 400 444 60 00193 1.14162 1.1610 424.2 450 4R28 0 0195 1.01224 1.0318 437.3 767.5 1204.8 0 6360 03378 1.4738 435.7 1118.9 480 0 0199 0 90787 0 9276 449.5 755.1 1204.7 0.6490 0 8148 1.4639 447.7 tilSA 900 500 467 01 S50 476 94 00199 0 82183 0 8418 460.9 743.3 12043 0 6611 0.7936 1.4547 458.9 11186 550 600 48520 0 0201 0.74962 0.7698 471.7 732.0 1203 7 0.6723 07738 1.4461 469.5 1116.2 000 700 .503 08 0.0205 0.63505 0 6556 491.6 710.2 1201.8 0.6928 0 7377 1.4304 488.9 1116.9 MD 800 51421 0 0209 0.54809 0.5690 509.8 689 6 11994 0 7111 0.7051 1.4163 506.7 1115.2 800 900 Ei! 95 00212 0 47 % S 05009 526 7 669 7 1196 4 0 7279 0.6753 1.4032 523 2 1113.0 900 0 4460 542.6 650 4 1192.9 0.7434 0 6476 1.M10 53',6 1110.4 1000 1 2000 544.59 0.0216 0 42435 037E3 0 4006 557.5 631.5 1189.1 0 7573 0.6216 1.3794 553.1 1107.5 1800 1100 SEE 2d 0.0220 3200 67.19 0 0223 0 34013 0.3625 571.9 613.0 1184 8 0.7714 0.5969 1.3683 5S69 1104.3 1200 '

594.6 1180 2 0.7843 0.5733 1.3577 500.1 1100 9 1300 1300 l:L77.42 e 0 0227 0 30722 0.321r9 585.6 i

1400 557 07 0 0231 0 27811 03018 598 8 5765 1175 3 0.7966 05507 1.3474 592.9 1097.1 1400 1500 5 % 20 0 0235 02h372 0.2712 611.7 550 4 1170.1 0.8055 0f283 1.3373 6052 1093.1 1500 2000 635 80 0.02",7 016760 0.1883 672.1 466.2 1138.3 0SC5 0 4256 1.7881 662 6 10G86 2000 2500 65d il 0 02c,f 0 10209 0 1307 731.7 361.6 1093.3 0 9139 0 3206 1.2345 718.5 1032.9 2500 3000 0 050/3 0.0850 301 8 218.4 1070 3 0 9728 0.1891 1.1619 7823 973.1 3000 655 33 0 0343 3298 2 70147 00508 0 0050d 906 0 0 9060 1.0612 0 1.0612 875.9 875.9 32002 '

~ -

TABLE A 3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE) f

' A.4 l---__-.-----

Tempmotwo. F m pse 300 400 900 000 700 000 900 1000 1100 3200 1300 1400 3500 to ) 100 200 392 5 45E3 511.9 571.5 631.1 H07 v 00161 3 A es 00 1160 2 11957 1241.8 1288 6 13361 1984 5 (101.74) s 0.1295 2.0t09 2.1152 2 1722 2.2237 2.270s 2J144 e 0.0161 78 I4 to 74 102 74 114.21 126 15 138 08 150 01 161 94 173 86 105 78 197.70 209 62 221.53 233 og 6 48 01 1145 6 1l44 8 1241.3 1288 2 1335 9 1354 3 1433 6 1483 7 1534.7 1586 7 1639 6 1603 3 174a0 1g03 g 6

(167 24) s 0.1795 1A716 1.9369 1.9943 2.0460 2 0932 213G7 2 1776 2 2159 2 2521 2.20M 2J194 23509 2.381 e 00161 3884 44 93 51 03 57.04 63 03 69 00 74 98 80 94 46 91 92 87 98 sa 104 80 110 76 116 72 30 A G8 02 1146 6 11937 1740 6 12 0.8 1335 5 1384 0 1433 4 1483 5 1534 6 1546 6 16395 1693.3 174 (19..21) s 01295 1.7926 1.8593 1.9173 1.9692 2 0166 2.0603 2.1011 2 1394 2 1757 2.2101 2 2430 2.274 e 00161 0 0166 29 893 33 963 37.985 Al ts6 45 978 49 964 53 946 57.926 61 905 65882 69358 73 833 15 6 68 04 16809 1192 5 1239 9 1287.3 1335 2 1383.8 1433 2 1443 4 1534 5 15465 1639 4 1603 2 1747 (213.03) e 01295 0.2940 1.8134 1.3720 1.9242 1.9717 2.0155 2.0563 2A946 2.1309 2.1653 2.1982 22297 2.259 e 0 0161 0 0166 22356 25 428 28 457 31 466 34 465 37.458 40 447 43 435 46 420 49 405 52J08 55J7 30 6 68 05 168 11 1191 4 1239.2 1286 9 1334.9 1383 5 1432 9 1443.2 1534.3 1586 3 1639.3 1803.1 174 (227.96) s 0.1295 0.2940 1.7805 1A397 18921 1.9397 1.9836 2 0244 2.0628 2.0991 2.13M 2.1665 2.1979 2.228 e 0 0161 0 0166 11 035 12 624 14.165 15685 17.195 18 699 20 199 21697 23 194 24689 26.143 27.67 40 e 68 10 168 15 1186 6 1236.4 1285.0 1333 6 1382.5 14321 1442.5 1533.7 15858 16388 1992 7 1747.5 (267.25) s 0.1295 0 2940 1.6992 1.M08 1A143 1A624 1.9065 1.9476 1.9560 2.0224 2.0569 2.0899 2.1224 2.15 e 0.0161 0.0156 7.257 8354 9 400 10 425 11 43S 12 444 13A50 14 452 15.452 16.450 17A44 14.445 19 40 4 68 15 16520 1181 6 1233.5 1283 2 1332 3 1381.5 1431.3 14413 1533 2 1585J 1638 4 1692 4 1747.

(292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1A168 1A612 1.9024 1.9410 1.9774 2.0120 2.0450 2.0765 2.1088 e 0.01'61 0 0166 0 0175 6.218 7.018 7.794 S.560 9.319 10 075 10 829 11 581 12J31 1321 13A29 14.571 30 6 68 21 16824 269 74 1233.5 1281 3 1330.9 1380.5 1430.5 1481.1 1532.6 1984.9 1638.0 1402A 1746A 180 (312.04) s 0.1295 0 2939 0 4371 1.6790 1.7349 1.7842 13289 1 8702 1.90B9 1.9454 1.9000 2.0131 20846 2A750 21041 e 4 935 5 588 6.216 6.833 0 0161 0.0166 0 0175 1227.4 7.443 8050 8655 9.258 9AGO 10Ato 11A00 11.65r 68 26 168 29 269 77 1279.3 1329 6 41379.5 1429 7 1480 4 1532.0 15844 1637A 1891A 1746.5 1802; too >

(327.82) s 0.1295 0.2939 04371 1.6516 1.7083 1.7586 13036 13451 1A839 1.9205 1.9552 1.9003 23899 2.0002 2.079=

, 00161 0 01 % 0 0175 4 0786 4.6341 5.1637 5.6831 6 1929 6 7006 7.2060 7.7006 S.2119 S.7130 9.2134 9.7131 120 h 6831 168 33 26981 1224.1 1277 4 13281 1378 4 1428 8 1479 8 1531.4 1583.9 1637.1 151J 1746.2 1802J 0.1295 0 2939 0 4371 1.6286 1.6872 1.7376 1.7829 1 3246 1A635 1.9001 13349 1.9600 1.9996 2.0300 2.068; (341.27) s e 0 0161 0 0166 0 0175 3 4651 3 9526 4 4119 4 4545 5 2995 5 7364 4.1709 6.4036 7A349 7A652 7A945 SJ23:-

140 4 6837 168 38 265 85 1220 8 1275 3 13268 1377 4 1478 0 1479 1 15308 1983 4 1436.7 1880.9 1745.9 1801/

(353 04) s 01295 02939 0 4370 1.6085 1.6686 1.71 % 1.7652 1.8071 1A461 13828 1.9176 1.9508 1.9825 2.0129 2.042 e 0.0161 0 0166 0 0175 3 0060 3 4413 3 8480 4.2420 4 6295 5.0132 5.3945 5.7741 6.1522 6.5293 '6.9055 728 100 6 64 42 168 42 269 89 1217.4 1273 3 1325 4 1376 4 1427.2 1478 4 1530.3 1982.9 1636.3 1 8 03 1745.4 1801:

(363 55) s 0.1294 C.2938 0 4370 1.5906 1.6522 1.7039 1.7499 1.7919 1A310 13678 1.9027 1.9359 1ABF6' 1.9980 2.02 e 0 0161 0 0166 0 0174 2 6474 3 0433 3.4093 3.7621 4.1054 4.4505 4.7907 5.1299 5.4657 53014 6.1363 6.47 180 4 68 47 16547 269 9/ 1213 8 1271.2 1324.0 1375 3 1426 3 1477.7 1529 7 1582.4 1435.9 1890.2 1745J 1801 (373.C3) s C.1294 0.2538 0 4370 1 5743 1.6376 1.6900 1 7362 1.7784 12176 1 8345 1AB94 13227 1.9545 1.9849 2.01

, 0 0161 0 0166 0 0174 2 3598 2.7247 3.0583 3.3783 3 M15 4 0000 4.3077 44128 4.9165 52391 S.5209 5 2215 200 a 68 52 168 51 269 94 12101 1269.0 1322E 1374.3 1425.5 1477.0 15291 1581.9 1635.4 1998 1745.0 1800.1 (351.80) s 01294 0293S 04359 1.5593 1.6242 1.6776 1.7239 1.7663 13057 1.8426 12776 1.9109 1.9427 13732 2Ast' e 0 0161 0 0165 0 0174 0 0186 2.150: 2.4662 2 6872 2.9410 3.1909 3.4382 36837 3.9278 4.1709 4.4131 4.464 250 > 68.56 166 63 270 05 3/5 10 1263 5 1319 0 1371.6 I423 4 1475 3 1527.6 1580 6 1634.4 158.9 17442 1800.

(400 97) s 01294 0.2937 0 4366 0 5667 1.5951 1.6502 1.6976 1.7405 1.7801 1.8173 1A524 13458 1.9177 1.9482 1.97 e 0 0161 0 0165 0 0174 0 0186 1.7665 2.0044 2.2263 2.4407 2 6509 2 8585 3 0643 3.2688 3.4721 3.6746 3A7 300 n! 64 79 1 % 74 27u 14 375.15 1257.7 1315 2 1368 9 1421.3 1473 6 15262 1579.4 1631.3 leBO 1743 4 1790 (417.35) : 0.1294 02937 0 4337 C5%5 1.5703 1.6274 1.6754 1.7192 1.7591 1.7964 13317 1A652 13072 1.9278 13 e 0 0161 0 0105 0 0174 0 018G 1.4913 1.7028 1A973 2.0332 2.2652 2 4445 2Atl9 2.7900 23730 3.1471 3JEC She a C8 92 IES 85 270 2". 375 21 1251.5 1311.4 1366 2 1419 2 14718 1524 7 1578.2 16323 197.1 1742.6 17W (431.73; . 0 1293 0 29M 0 43G7 0.5664 1.5403 1.6077 1.6571 1.7009 1.7411 1.7787 13141 1A477 13798 1.9105 1.94C e 0 0161 0 01E6 0 0174 0 0162 1 2841 1.4763 1.6499 1.8151 1.9759 2.1339 2.2901 2.4450 2 3807 2.7515 2.9 405 a 69 05 168 97 270 33 375 27 12451 1307.4 IM34 1417.0 14701 1523 3 1576.9 1631.2 1886 2 1741.9 1798 (444.60) s 01293 02935 0 4365 0 56G3 1.5282 1.5901, 1.6406 1.6850 1.7255 1.7632 1.7908 13325 13647 1A955 1.9 21 e 0 0161 0 0106 0 0174 0 0186 0 9919 1.1584 1 3037 1.4397 1.5708 1 6992 1A256 13507 2A746 2.1977 2.3 500 h 69 32 1E919 27051 375 38 1231.2 1299.1 1357.7 1412 7 1466 6 Ib20 3 1574 4 1629.1 3684 4 1740 3 (457.01) s 01297 02934 04354 05t60 14971 I5595 1.6123 165/8 16990 1.7371 1.7730 1A069 13393 14702 1AM TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)

A.5

~

gp Tempetelser, F Che ia. 700 000 (est.tsemp) 100 200 300 400 M0 400 000 1000 1100 1800 1300 1400 llet e 00161 0 01 % 0 0174 0 0186 0 7944 0 94 % 10726 1.1892 13000 14093 1 5160 16211 1.72$2 1 8284 1.tx '

380 e 69 54 169 42 270 70 37b e9 1215 9 1290 3 13bl 8 14083 1463 0 1517 4 15739 1627.0 1682 6 17348 1795 M8620) s 0.1292 0.2933 0 4M2 O Mb7 14b90 3.5329 15844 163bt 16769 1.7165 1.7517 3.7859 13384 1A4,4 Igyg e 00161 0 0lu 0 0174 0 0186 0 0704 0 7928 0 9072 1.0102 1.1078 12023 12948 138b8 1.4757 1.ud7 1 65!

700 6 69 84 169 6b 270 89 375 61 487 93 1281 0 1345 6 1403.7 14b9 4 1514 4 1%94 16248 luo7 17372 1794 15090 1. % 73 16154 14b80 36970 17335 17679 1 80 % 18318 1 861 :

003 C8) s 01291 0.2932 0 4MO O%% 06889 e 0 0161 0 01 % 0 0174 0 0186 0 0704 0 6774 0 7825 0 8759 0 9631 1 0470 1 1289 1.2093 1.2825 13609 1.444 800 a 10.11 169 88 271 07 375 73 487Ad 1773 1 1339 2 13991 14b5 R 1511 4 1%69 1622 7 167E9 1733 0 1792 018.2.) = 0.1290 0 2930 0 43t8 0 %S2 0 6885 14869 I 5484 1.5580 14413 16807 1.?!?5 17522 1.7851 18164 3.844 :

e 0 0161 0.0106 00174 0 0186 0 0204 05869 06858 07783 0 8504 0 9262 09998 107M 11430 1 2131 1.281 900 6 70 37 170 10 271.2G 375 84 487.83 1260 6 1332 7 1394 4 1452 2 15C4 5 1%44 1620 6 16771 17341 1791 (531.95) s 0 1290 0.2929 0 4357 0.% 49 0.6881 1.46b9 1.5331 1.5422 16263 1.E62 1.7033 1.7382 1.7713 1 6028 1 83;

! e 0.0161 0 0166 0.0174 0 0186 0 0204 05137 06080 0 6875 0.7603 0 8295 089% 0M22 1.02M 1.0901 1.1 53 1880 6 70 63 17033 271.44 375.96 487 79 1249.3 1325.9 1389.6 1448.5 1504 4 1541.9 1618 4 1675.3 1732.5 1790' (544.58) s 0.1269 0.2928 0 4355 0.5647 0 6476 1.4457 1.5149 1.5677 1.4126 16530 1.6905 1.72 % 1.7549 1.7905 1.82(

e 00161 001% 00174 0 0185 0.0203 04531 0 5440 0 6188 0 6865 0 7505 0 8121 0 8723 0 9313 0 9894 1.04(

1100 6 70 90 170.% 271 43 376 08 487.75 1237 3 1318 8 1384 7 1844 7 1502 4 15594 1616 3 1673.5 17310 1789 (5b628) s 0.1269 0.2927 0 4353 0.5644 0.6872 1.4259 1.4996 1.h42 1 6000 1.6410 1.6787 1.7141 1.7475 1.7793 1 Aos, e 0 0161 0 0166 0.0174 0 0185 0 0203 0 4016 0 4905 0 5615 0 6250 0 6845 0 7418 C.7974 0 8519 0.9055 0.95! .

1200 4 71.16 170.7A 271.82 376.20 487.72 1224.2 1311.5 1379.7 1440 9 1449 4 1556 9 1614.2 1671 6 1729 4 1787 '

(567.19) s 0.1288 0.2926 0.4351 0.5642 0.6868 1.4061 1.4851 1.5415 1.5883 1.6298 1 M79 1.7035 1.7371 1.7691 1.79s ,

e 0 01Cl 00166 00174 00185 0 0203 0.3176 0 4059 0 4712 0 $282 0 5409 0 6311 0 6794 0 7272 0.7737 0 811 '

1400 4 71.68 171 24 272 19 376 44 487 65 1194.1 12961 1369 J 1433 2 1493 2 1551 8 16099 1644 0 1726 3 1785 (587.07) s 0.1287 0.2923 0 4348 0.5636 0 6859 IJ652 1.4575 1.5182 1.5670 1.6096 3.6444 1.8845 1.7185 1.7508 1.781 ;

e 0.0161 0 0166 0.0173 0 0185 0 0202 0 0236 0.3415 0.4032 04555 0.5031 0 5482 0 5915 0 8336 0.6748 0.711 1600 6 72.21 171 69 272.57 376 69 487.60 616 77 J 279.4 1358 5 1425.2 1486 9 1546 6 1605 6 1664 3 1723.2 1782 (6C4 87) s 0 1286 0 2921 0 4344 0.% 31 0.68bl 0.8129 1.4312 1 4963 1.5478 1.5916 1 6312 1.H78 1.7022 1.7344 1.761 e 0 0160 0.0165 0 0173 0.0185 0 0202 0.0235 0 2906 0.3500 0.3988 0 4426 0 4836 0.5229 0 5409 0.5980 0 674 1800 a 72.73 172.15 272.95 376 93 487.56 615.58 3261.1 1347.2 1417.1 1480 6 1541.1 1601.2 I M O.7 1720.1 1779 (621/12) s 0.1264 0.2918 0.4341 05626 0.68'3 0.8109 1.4054 1.4748 1.5302 1.5753 16154 1.M28 16876 1.7204 1.751 i

e 0 0160 0.0165 0.0173 0.0184 0 0201 0.0233 0.2488 0.3072 0 3534 0 3942 0 4320 0 4680 0.5027 0.5M5 0 549 '

2000 6 73 26 172 60 273.32 377.19 487 53 614 48 1240.9 1353 4 1408 7 1447.1 1536 2 1596.9 1657.0 1717.0 1777.'

(635 80) s 0.1263 0.2916 0 4337 05621 06834 0.8091 1.3794 1.4578 1.5138 1.56C3 1.6014 1.6391 1.6747 1.7075 1.738 e 0.0150 0.0165 0.0173 0.0184 0.0200 0.0230 0 1681 0.2293 0.2712 0.3068 0.3390 0 M92 0.3980 0.4259 0.452 2500 4 74 57 173 74 274 27 377 82 487.50 612.08 1176.7 1303 4 1386.7 1457.5 1522.9 1585.9 1647A.17092 1770 (668.11) s 0.1280 0.2910 0 4329 0.5609 04815 0 4048 1.3076 1.4129 1.4766 1.5269 1.5703 1A084 1A4M 14796 1.713 e 0 0160 0 0165 0.0172 0 0183 0.0200 0.0228 0 0982 0 1759 0.2161 0.2484 0.2770 0.3033 0.3282 0.3522 0.375S 3000 A 75 83 17tS8 275.22 378 47 487.52 610 08 1060 5 1267.0 13632 1440.2 15014 1574.8 luS5 1701.4 17(ID (695.33) s 0.1277 0.29.4 0.4320 0.5597 0.6796 08009 1.1966 1.3692 1.4429 1.4975 1.5434 1.5641 1A21/ 1.C:61 1.648E e 0.0160 0 0165 0.0172 0.0183 0.0199 0.0227 0.0335 0.1588 01987 0.2301 0.2576 0.2827 OJ08% 0.3291 0.3513 3200 4 76 4 175.3 275 6 3787 487.5 609 4 800.8 1250 9 1353 4 1433.1 1503.8 1570.3 16343 1698.3 17618 f.705.08) s 01276 0 2902 0.4317 0.5592 0.6768 0.7994 0.9708 IJ515 1.4300 1.48 % 1.5335 1.5749 1A126 14477 1A80f e 0 0160 0.0164 0.0172 0 01E3 0 0199 0.0225 0.0307 0.1364 0 1764 0.2066 0 2326 0.2563 0.2784 0.2995 0.319 3500 a 77.2 176.0 276.2 3791 487.6 608 4 779 4 1224 6 13382 1422 2 14955 IM3.3 1629.2 1693 6 1757; a 0.1274 0.2899 0 4312 0 5585 0.6777 0.7973 0 9508 1.3242 1.4112 1.4709 1.5194 1.M18 1.8002 14358 1.669 I e 0 0159 0.0164 0.0172 0.0182 0.0198 0 0223 0.0287 0.1052 0.1463 0.1712 0.1994 02210 0.2411 0.2601 0.278' 4000 6 78.5 177.2 277.1 379.8 487.7 606.5 763.0 1174.3 1311.6 3403C 1481.3 1552.2 16192 1885.7 I?50.e t s 01271 0.2e93 0.4304 0.5573 0 6760 0 7940 0.9343 '1.2?S4 1J807 1.4461 1.4976 1.5437 1.9812 1.6177 1.651s

e 0 0159 0.0164 0 0171 0 0181 0.0196 0 0219 0.0268 0.0591 0.1038 0.1312 0 1529 0.1718 0.1990 0.2060 0.228 5000 a 81.1 179 5 2791 381.2 488.1 804 6 746.0 1042 9 1252.9 13(4 6 1452.1 1529.1 16039 1670.0 1737s a 0.1265 0.2861 0 4287 0.5550 0 6726 0.7880 0.9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.5481 1.5463 la214 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 0.181

4000 & 83.7 181.7 281.0 342 7 488 6 602 9 7363 9451 1188.8 1323 6 1422.3 1505 9 15820 1654.2 17243 s 0 1258 0.2670 0 4271 0 5528 O H93 0 7826 , 0.9026 1.0176 1.2615 IJ5N 1.4229 1.4743 1.5194 1.H93 1586; e 0.0158 0.0163 0 0170 0.0180 0 0193 0.0?!3 0.0248 0.0334 0 0573 0 031 A 0.1004 0.1160 0.1298 0.1424 0.1541 7000 4 86.2 184 4 283 0 384.2 489 3 401.7 729 3 901.8 1124.9 1281 7 1392 2 1482.6 1963 1 16386 1711.

I e 01252 0 2859 0 4256 O S07 0 6G63 0 7/77 0 8926 1.0350 12055 1.31}l 1.3904 1.44u6 1.4938 1.53'5 1.573!

TABLE A.4 PROPERTIES'OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED) l A.6 j l

e l 12 1A BA 3 33 la 30 3.3 g, ,3 s 3.3 8.3 gj' A / Ml A/ 1%

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l FIGURE A.5 MOLLIER ENTHALPY-ENTROPY DIAGRAM A.7 1

I I

1 s

l PROPEMTIES OF WATER 1 Density e (Ibsfit8)

PSIA Temp Saturated 2300 2400 2500 3000 1000 2000 2100 2200

(*F) Liquid 62.888 62.909 6233 62.951 63.056 62.414 62.837 62.846 62.867 32 62.822 62446 62.87 62.99 62.55 62.75 62.774 62.798 50 62.38 62.446 62.465 62.559 62.185 62.371 62.390 62.409 62.427 100 61.989 60.587 60.606 60.702 80.314 60.511 60.53 60.549 60.568 200 60.118 57.859 57.882 57.998 57.537 57.767 57.79 67.813 57.836 sco 57.310 54.342 54.373 54.529 54.218 54.249 54.28 54.311 400 53.651 53.903 54.11 53.86 53.89 53.925 53.95 53.825 410 53.248 53.475 53.79 63.425 53.46 53.50 53.53 53A9 52.798 53.025 53.36 53.40 420 53.065 53.09 53.265 52.575 52.925 52.95 52.99 53.02 430 52.356 52.54 52.56 52.275 52.125 52.42 52.45 52.475 52.51 440 51.921 52.21 52.41 52.065 52.10 52.14 52.175 450 51.546 51.66 52.025 61.64 51.68 51.725 51.76 51.96 460 51.020 51.175 51.56 51.61 51.175 51.22 51.25 51.30 51.50 470 50.535 50.70 51.1 5f.14 50.7 80.74 50.78 50.825 51A35 480 50.00 50.20 50.62 50.66 50.22 50.265 50.31 50.35 5C575 dic 49. 2 49.685 50.13 50.175 49.714 49.762 49.81 49.858 50.098 500 48.943 49.097 49.618 49.666 49.152 49.203 49.254 49.305 49.56 ;

48.31 48.51 49.05 49.101 510 48.68 48.735 49A1 47.91 48.46 48.515 48.57 48.625 520 47.85 48.155 48.45 47.86 47.919 47.978 48 037 48.096 530 47.17 47.29 47A9 47.296 47.362 47.428 47.494 47.56 540 46.51 47.23 46.726 46.794 46 862 48.93 47.27 550 45.87 46.59 46.658 45.92 45.994 46.068 46.142 46.216 46.29 ,. 46.66 560 45.25 45.62- 46.02 45.30 45.38 45.46 45.54 570 44.64 45.22 44.672 44.758 44.844 44.93 45.36 520 43.86 44.50 44.586 43.92 M.015 44.11 44.205 44.68 550 43.10 43.73 43.825 43.122 43.226 43.33 43.434 43.956 600 42.321 42.913 43.017 42.196 42.314 42.432 42.55 43.14 610 41.49 41.96 42.08 41.35 41.483 41A16 42.283 40.552 40.950 41.083 41.217 620 41.44 630 39.53 40.388 640 38.491 39.26 650 37.31 38.006 660 36.01 36.52 670 34.48 34A98 683 32.744 32.144 690 30.516 l

TABLE A.6 PROPERTIES OF WATER, DENSITY ,

A.8 _

l I

t

1 cc s' ]

1 1

1. C'cINCICLES Or "' t C L Ei o t' O '- E R c L a H T OPEPATION. PAGE 21 l

1

'HE -

H0----------------------

DYNAMICS, HEAT T'i ANSFEP----- AND FLUID FLOW ANS'JERS -- TURKEY POINT 3R4 -86/04/23-JERRY D O U G '_ A ':

ANSWEP 1.01 (1.00) d CEFEREMCE General Physics, Heat Tran fer Thermodynamic:, and Fluid i~ low- pp. 145 - 140 Turkey ocint. Therm:1-Hydr,v11e :'rinciples and Applic:t tons, op, ~ 45 --- 5 2 AN5 2 'ER 1.02 (1.00) d RECERENCE E!H* .-RQ-606, pp 4 5: Fig. J BSEP: 02-2/3-A. pp 177 - 1F0; 02-0G-A, op 60 - 61 9FNP: Xenco anc Samar '.- LP- pp 3, 6: RG 84/03/05

'o Westinghouse Nuclear Treining Operations, pp. I-5.77 -

rud e , coint. Pesctor Ecre Ccntrol- pp. 4 34 0 01 'C o n -MS .13 (3.7/4,0?

fins 9EF 1.03 (1.901 OEFEPE4CE EIH: C:'NT Vol ')II , CP:n+ar 10.1-83-86 SEE:: L/o 02-2/3-A. pp l'2 - 176; 02-0G-A, pp 57 - 60 u c. +, . nghouse Nuc le a r Reactor Theory, pp. I-5.77 - 70 Tur k ov Point, Reactor Core Control, pp. 4 28 001/000M5.13 (3. .0)

ANSWER 1.04 ( 1. ')0 )

d RECEPENCE 4estinghouse Reactor Physics, Section I-5, tiTC and Power Defect DPC. ' undamentals of Nuclear Reactor Engineering Turkey Point, Thermal-Hydrsulic Principles and Applications, Chapter 10 I

i 1

l

1. PRINCIPLES OF NUCLEAP PCWEP PLANT OPERATION, PAGE 22

~

~~~~TUEEUUUEUd5EC5I'55dT TR U5FER~5UU~ FLU 56~FL5U ANSWERS -- TURKEY POINT 3&4 -86/04/28-JEPRY DOUGLAS 002/000-K5.02 (3.3/3.6)

ANSWER 1.05 (1.00)

C PEFERENCE HBR. Reactor Theory. Session 42, pp. 3 & 4 DPC, Fundamentsls of Huclest Reactor Engineering Turkey Pointr Fundamentals of Nuclear Reactor Physics, pp. 5-21 & 8-39 004/000-K5.08 (2.6/3.2)

ANSWER 1.06 (1.50)

a. Decreases (0,5)

5. Increases ( 0. 5 )

c. Increases (0.5)

REFEPENCE Turkey Point, Thermal-Hydraulic Principles and Applications, pp. 10 61 ANSWER 1.07 (1.50) as Less negative (0.5)

'o . Less negative (0.S)

c. Less negative (0.5)

REFERENCE Turkey Point, Reactor Core Control, Chapter 5, Fig. SNP-RF-9 ANSWER 1.08 (1.00) 4, 2, le 3 t0.33 pts for each switch necessary to get in correct order) (1.0)

REFERENCE NUS. Vol 4, pp 3.3-2 Turkey Pointe Thermal-Hydraulic Principles and Applications, pp. 13 20

. P R IN C I': L T.5 7F NUCLEAR PCWEP PLANT OPERATION, PAGE ~3

~ ~

~~~~YU5E56bEU555C5I~UEST~iE555 FEE ~dbD ELU50 EL6U ANSWEc5 -- TURKEY POINT 334 -96/04/28-JERRY 00iJ G L AS ANSWER 1.09 (2.00) 2 Establishment of reverse flow (0.5)

b. Less pressure drop across core (due to less total core flow) <0.5)

c. No longer transferrin 3 heat into 3/G causing cooldown/ contraction of water / steam in S/G r0.5)

d. Increased delta T in operating loop (with a pp r o::im a t e ly constant >

Tcold) (0.5)

P REFERENCE Turkey Point. Thermal-Hydraulic Principles and Applications, pp. 12 18 003/000-M5.02 (2.8/3.2)

-MS.03 (3.1/3.5)

-{5.04 ( 3 . 2 / 3 . S '-

000/015-EF1.02 (3.7/c.11 ANSWER 1,10 (1.50)

! 9uildup of ou (0.3), m,re ne3ative (0.3), overriding effect (0.3)

2. Clad c reep (0.3), less neqative (Q.3) p lef{ f O w M 5 & ckantgd fe.a 4 W a go have c =}=?S eforf T..er k e y Point, Requal Lesson P13n, Core Life Chan.ges, p. 16 ANS rec. 1.11 (1.00) ,

Because rod worth is proportional to the ratio of the flux at the ti'p of the rod to the average flu:- (0.7). A change in power does not significanti- change this ratio (0.3). (1.0)

REFERENCE Turkey ooint, Reactor Core Control, Chapter 6 ANSWER 1 12 ( .50)

Depletion of burnablepoisons((gq[ reg, (0.5)

%"' % *f W PO PM"1 raum shee drop Jack sf.y ek

% % S%*

i

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

1. ooINCIFLES OF NUCLEAR POWER PLANT OPERATION. PAGE 24

~~~~TAER566YU555C5I'555T~TE5U5EEP"5h6" FLU 56"EL60 ANSWERS -- TURKEY POINT 3&a -86/0ay 8-JERRY 00VGLAS REFERENCE Turkey Point, Peactor Core Control. P. 2-12 ANSWER 1.13 (1 00)

3. Oecay of Iodine (Tellurtum) (0.5)

b. Decav of X e ., o n 'O.56 REFERENCE Westinghouse Nuclear Training Operations, pp. I-5.64 & 65 Turkey Point. Reactor Core Control. pp. 4 12 001/000-K5.33 (3.2/3.5)

ANSWEF 1.14 (2.00) 3 Delts T increases (0.7) 2s That increases (as boiling oc:vrs in core) and Trold remains reletively constant (0.3) (1.0)

b. Tc_.1d will not follow P s t e a.n (0.7). Piteam will decrease (as bello"' occurs in S .' G ) while Teo]d rem = ins reletively constant

7: (1.0)

REcERENCE Genocal Physic 3, HT&FF. pp. 356 & 357 ANSUEP 1.15 (1.00)

T h e t. = 374.2 + .5 (56) = 602 (*/- 1) (0,5)

T7:+ G 2:35 sig = 653 (+/- 1) (CA r) " ! ^ 15 ' fp Subcooling = 51 (+/- 2) 'O 2"'

N $kaeke s %

g

'- r

- e e :. c y~c e de[trm < 2 e 4cody Turfey Point- RCS SD, p. 64 and Steam Tables fy 9,g

a

2. PLANT DESIGN INCLUSI'JG SAFETY AND EMEPGENCY SYSTEMS PAGE ;5 ANSWERS -- TURKEY POINT 3&4 -86/04/29-JERRY DOUGLAS ANSWER 2.01 (1.00) d REFERENCE Vurkey Po:.nt. Requ 1 Lesson Plan, RCP, F13 16 g /LU ANSWER 2.02 ( _.

(0.3 pts each)

a. MODULATED

b. CLOSED

c. OPEN

d. CLOSED a ::

REFSRENCE Surry, Chemical and Volume Control System, p. 52 Turkey Point, CVCS SD. F i .3 17 ANSWER 2.03 (:( ..~-

b g

1. a. c. e ,b,d W

2. e (0.25)

REFERENCE Turkey Point, Pequal Lesson Plan, AFW7 pp. 17 8. 18 ANSWER 2.04 (1.50)

1. e (0.5)

2. e (0.5)

3. b (0.5)

REFERENCE Turkey Point, RCP SD. p. 15 and CCW SD, p. 11 and CVCS SD, Fig. 1

s 4A-

"A

2. PLANT DESIGN INCLUDING SAFCTY AND EMERGENCY SYSTEMS PbGE 26 ANSWERS -- TURKEY POINT 3 !. 4 -86/04/29-JERRY DOUGLAS ANSWER 2.05 (1.50)

ANY SIX AT 0.25 POINTS EACH: '

1. PCP Seal Leak-off Low Flow (0.7 gpm)

2. F.CP Seal Leak-off H .sh Flow (5 g p 'ti )

3. RCP Sha#t No. 1 Seal Leck-off High Temp ( 2 :.5 .;M a r s es )

4. RCP Seal Water Bypass Low Flow (0.5 gpm)

5. RCP Labyrinth Seal Low GP '1?') ,

EVALUATE OTHERS ON 6, RCP No. 1 Seal Low dP (200 psid) th CASE-BY-CASE BAS h 7 RCP Standpipe Low Level (-l'?

8. RCP Standpipe High Level (+1')

9 P C C' Thermal Barrier Coolinq Water Hiah Temp (110 degrees)

(J (lLO Quk? <X M>k>r 6. awn k + Th Q REFEFENCE -

Turkey Point. Requal les=on Plan, PCP. p. 35 ANSWEP 2.06 (1.50) _

ANY FIVE AT 0.3 POINTS EACH: '

i. Group Step Counters _

2. Internal memory snd alarms

3. tc A convertars J. Eank Overlap Counter

5. Sisve C y e '. e r

6. Master Cycler PEFEC.ENCE TurFey Pnint, Pequal Lesson Plan. PPI, p. 21 ANSuEp 2,07 (1,50,

3. Trein 1 - pumps A and C (0.5)

Trsin 2 - pump B (0.5) 40TE: Train must be completely correct to get any credit

b. 9 (0.25) and C (0.25) S/Gs (0.5)

REFERENCE Turk.ev Point, Requal Lesson Plan, AFW, p. 9 and Plant Drawing 5610-T-E-4061

2. PLANT DESIGN INC'_UD ENO S AFETY AND EMERGENCY SYSTEMS PAGE 27 ANSWERS -- TURKEY POINT 3 e. 4 -86/04/28-JERRY DOUGLAS ANSWER 2.08 M b' a) SI pumps and the Poric Acid Eveporators (+.25 ea) ,35) b) The Emergency Containment Cooler i .et. outlet am ....-4 valves '

)

REFERENCE y TP' SD40, pp 8. M EPE-026:EK3.02(3.6/3.9) and 008/000:K1.02(3.3/3.4)

ANSWER 2.0c 1.50)

a. 1. CCW HEXs (31 (0.2)

'O 2)

2. TPCW HEys (2)

3. Lube Water System (0.1)

b. 1. C V- 2 201 (TPCW hex outlet Temp Control Valve) (0.4)

2. Closes (O'.3)

3. Allow Ell ICW to be directed to CCW WEXs (for cooling of vttal safeguard emaipment) (0.3)

REFERENCE Turbof Point. Fequal Lev on Plan, ICuS. pp. 4 3 10 AN32E0 2.10 (1,0C) 1 o mt Oemano Position (Step Counters) (0.2) - counts pulses from the rod control system logic cabinet (0.34 (0.5)

2. Individual Position (0.2) - rod position detector (LVDT) on CRDM rod travel housing transmits signal to oosition channel (0.3) (0.5)

RErERENCE T u r !< e v Point. Requ21 Lesson Plan, MPI, p. 7 ANSWEF 2.11 (1.00)

1. M?intain hot standby for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months and cooldown to 350 degrees. (0.5)

2. Msintain hot standby #ct 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months . (0.5)

2. PLANT DE5!GN INCLUOING 3ARETr AND EMERGENCY SYSTEMS PAGE :q ANSWEc? -- TURKEY POINT 314 -86/04/28-JEPRY 00UCLAS REFERENCE Turkey Point. Requal Lesson Plan, AFW, p. 7 ANSWER 2.12 (1.50)

3. MCC 3C (0.125), Eattery Char 3er (0.125). DC Bus 3A (0.125), Inverter 3A (0.125), 3P07 (0.5)

b. MCC 3C (0.125), CVT 3Y01A (0 125). Alternate Source Transfer Switch (0.125). Static Transfer Switch (0.1251- 3P07 (0.5)

c. MCC 3C (0.125), Battery Charger /0.125), DC Sus 3A (0.125), Inverter AS (0.125), 3P07 (0.5)

REFERENCE Turkey Point, Requal Lesson Plan 20-OL, 120 V Vital AC Inverters, pp. 8 & 9 ANSuRR 2 (1.00)

JahupQ v 64W2 .13 A, B, g' A Loop A Hot Leg (0.25), RHR pump (0.25), PHR HEX (0.25), Loops

& C Cold Lest (0.25)

REFERENCE Turkey Foint, ECCS SD, F;gure 9 ANSWER 2.14 (1.50)

1. Maintatn containment temperature below 120 degrees (0.5) 2 Provide suitable atmosphere for personnel access tfter SD (0.5)

3. orovide cooltnj to the CRDMs ,

(0.5)

RE;ERENCE T u r !< e y Foint. Containment Ventilation SD, p. 5 i

e f

i

3. INSTRUMENTE 'ANO CONTRO'_S PAGE 20 ANSWERS -- TURKEY POINT 3&4 -86/04/28-JERRY DOUGLAS ANSWER 3.01 (1.00)

I C

REFERENCE FNP, Excore Nuclear Instrumentation System WBN, LP - Excore Instrumentation, pp. 10, 13, & 14 Turkey Point, Excore NI SD, p. 76 and Fig. 17 ANSWER 3.02 (1.00) d 9EFERENCE TNP. Tavg. Delta T, and Pimp. pp. 23-25 VEGP, Training Text, Volume 6, p. 68-27 Turkey Point. RPI SD, p. 15 ANSWER 3.03 (1.00)

REFERENCE T u r k t+ y Point, Drzwin3 5610-T-L1, Sheets 9A and CR ANSWER 3.04 (1.00)

REFERENCE WBN, LP - Pressurizer Level Control System, p. 5 -

Nuclear Fewer Reactor Instrumentation Systems Handbook, Vol II, Ch. 15 Turkey Point, Requ31 Lesson Plan 62-OL, LERs and FOPS 000/028-K2.02 (2.6/2.7) 000/020-A2.01 (3.4/3.6)

ANSWER 3.05 (1.00) d

3. INSTRUMENTS AND CONTROLS PAGE 30 ANSWERS -- TURKEY POINT 3d4 -86/04/2S-JERRY DOUGLAS REFERENCE Turkey Point, SDCS SD, pp. 2&9 ANSWER 3.06 (1.00) b PEFEPENCE Turkey Point. RPS SD, p. 23 ANSWER 2.07 (1.501 s

a. FALSE (0.5)

b. TRUE (0.5)

c. FALSE (0.5)

REFERENCE Turkey Pointr Rod Control SO, pp. 16 & 39 ANSWER 3.09 (1.50)

a. TRUE

b. FALSE

c. FALSE REFERENCE Neelear Power Resator Ins *rumentation Systems Handbook, 'J o l . 1, Ch. 4 Components: Sensors / Detectors - Temperature Theor/ (2.5/2 4)

Failures (2.0/3.1) ,

003/000-M5,03 (3.1/3.5)

3. INSTRUMENTS ANO :0N"00LS PAGE '31 ANSWERS -- TURKEY POINT 3#4 -86/04/28-JERRY DOUGLAS ANSWER 3.00 (1.501

a. DECPEASE 'O.56

b. PEMAIN THE SAME d 0 '5 i

c. REMAIN THE SAME (0.5)

REFERENCE FNPr Tavgr Delta T, and Pimp. pp. 16 8 17 Sorry. Instrumentation henval. Sect. 9 p. IV .5.5 W E' N . LP - Seactor-Coolant T e m p e r a t .ir e Instrumentation. p. 8 CAT, OP-CN-SPS-IC-IPE. p. 23 VCS, Reactor,Protectton anc Logic

. Turk ey Doint. PoS SD, p. 2T 012/000 '<s.11 (2.CC ?:

ANSWER 3 10 ... . (h

a. Sod (0.2)

b. T (0.2)

c. 5 (0.2)

d. #T / '.0.2)

e. 2 os c ... . _-

REFERENCE Turkey Point, RPS 50, rr., 52 d 57 ANSWER 3.11 (1.00'

3. 6 ' (0.25)

b. 6 (0.25)

c. 1 (0.25)

d. 6 (0.25)

REFERENCE WBN. LP - Rod Control System, pp. 5 & C CAT, PSM-IRE Turkey Point, Rod Control 50 001/000-K4.02 (3.8/3.8)

3. INSTR *MENTS AMD CONTROLS PAGE 32 ANSWCRS -- TURKEY POINT 3&4 -86/04/28-JERRY DOUGLAS ANSWER 3.12 (1.00)

-t

1. Manual (0,24

2. Hi-Hi Containment Pressure (*P') 'O,2)

3. Hi Steam Flow coincident (0.2) with Low S/G pressure (0.2) or Low Tavs (0.2) (0.6)

REFERENCE Turkey Point, RPS SD, p. 30 ANSWER 3.13 (1.00)

a. Scintillation (0.4)

b. 1. Closes S/G liquid sample isolation valves (2800, 2801, 2002) (0.2)

2. Closes S/G blowdown FCVs (6278A, B, C) (0.2)

3. Closes blowdown dump valve to dischstge canal (6265) (0.2)

REFEREtJCE Turkey Point. Radiation Monitoring 50, pp. 32 & 35 ANSWER 3.14 ('

(t$.00AO,W I /

1. PCS pressure _ ' _ - psig (0.3)

2. RH9 sucticn from RWST (MOV-862A/0) (0.3) and RHR He:' outlet to

?WST or alternste low head SI valve 'MOV-863A/B) (0.3) are closed (0.1) (0.7)

SECERENCE T'; r : ay P-'o i n t . ECCS SDr p. 18 .

ANSWEP 3.15 ( .503 Loss of air flow through filter (low flow) (0.5)

REFERENCE Turkey Point, CS SD, p. 9 and Fig. 4

3. INST UMENTS ANO C 0 0 T R O '_5 ' AGE 33 ANSWERS -- TURKEY POINT 384 -86/04/29-JERRY DOUGLAS ANSWEP 3.16 (1.00)

A m-sin generator lockout ( 0 , -~ ) with the bus strippin3 .elav de-ener-Stred ( 0 . 3 '. will trip the OG output brecker. (1,0 REFE9EMCE Turkey Point, Requ:1 L e-i s o n Plan. E n.e r 3ency Load Sequence / Bus Stripping.

p. 12 a r. d Orawing 5610-T-L1 Sheet CC ANSWEP S.1< '1.00)

' C 'J - cPe 2 0.2), ' - ~ '

"-!~- - ' 2 ?? 00 f. bM A

C ') 45 e' om2t'c c se 3t '00e ps g (0 m)o r e '5 3 '_p' d e c[- ]g e s/--

a: 2: ,

p una oil cy acon x ps - r-:7 _phf-vrs e ur . 0)

REFERENCE Turke/ c'aint- C' Z R SD, 'ig. 25 I

\ - (c)-) fer ibeh y 4 PT~ 'N f c~s +Q con 4rallah chwe( .

if 1s As coatnauous cawatL _

y 4 correcH y T b fo_ Au con 4r> thy pcv -qst e o pee (+.lb ea) PCV-YSh C OPEA3 (f- 2 eri secms oper Presure acreau Pcemre actrewa , haulers eMrpt .

pcv-ussc Stud at L@psy Pcv -uss c etoys a,e zwps4 2% TLP cA (f'i3 psq pre,$ Surg cycles w y ,

~ w-mc mcu _p e #- r y v--- -

y --

v -----*r - -----w-w $ w - ---w ----T -'w-w -y--- ----+W--4 -+--m -*

4. :c0CEDURES - NO^MA_. A? NORMAL 7 EMERGENCY AND PAGE 34

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

~~~~Ed656[6dfE5E~U6NTR6L ANSWERS -- TURKEY POINT 344 -96/04/28-JERRY 000GLAS ANSWER 4.01 (1.00) ,

b orLL PEFERENCE E0P-E-0 PWG-11: Performing Immediste Actions (4.7/4.4)

ANSWER 4.02 (1.00) ,

d REFERENCE Westinghouse Background Info for ECA-3.ir pp 32 E?E-038; EM3.06(4.2/4.5)

ANSWEP 4.03 (1.00)

REFEPENCE TPT ADM 0103.4, pp 13-15 PWG-14: Tagging / Clearances (3.6/4.0)

ANSWER 4.02 (1.00)

C REFERENCE TPT E0P-E-0 Foldout Page EPE 074; PWG-11(4.5/4.6)

4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 35

'~~~~~~~~~~~~~~~~~~~~~~~

~~~~REU56[UU5 CAL'UUUTRUL ANSWERS -- TURKEY POINT 384 -56/04/25-JEPRY DOUGLAS ANSWEk 4.05 1( .50)

FALSE (0.5)

REFERENCE Turkey Point, Requal Lesson Plan. User's Guide for E0P, p. 5 I0)

ANSWER 4.06 (M

=. ...IT

/000WtbR T'

b. UNIT 4 (0 3)

c. BOTH UNITS (0.5)

REFERENCE TPT OP 0202.1, pp 2 & OP 0202.2 pp 5 PWG-7* Limitations and Precautions (3.5/4.0)

ANSWER 4.07 (1.50)

- F 'J Control Valves checked closed (0.3)

-FW Bypass Valves checked closed (0.3)

-5/G Blowdown Valves checked closed (0.3)

-5/G Sample Isol Valve checked closed (0.3)

-CLOSE F4 Isolation Valves (0.3)

REFERENCE '

tot E0P-E-0, pp 5 EPE 007; PWG-11(4.4/4.5)

d

)

i b 4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL ANSWERS -- TURKEY POINT 3d4 -86/04/28-JERRY 00VGLAS ANSWER 4.08 (1.50)

]. a) type of. emergency (+.25) location injury to personnel ,

j e:: tent of damage ,,,,

b) 300 or 301 ofJ49 [L#fI REFERENCE YPT EP 20102 pp 3

{

PWG-25: Verbal Reports (3.3/3.7)

ANSuER 4.09 (1.00)

-ose fos pattern only (+.5 es)

- ust be 10 feet or more from any energized electrical equipment

^~"^'

] t' readea64F dauswert/\

R ENCE TPT EP 20107, pp 2 PWG-19: Fire protection rqmnts(3.4/4.2) 1

! A r1SWER 4.10 (1.25)

.3 , Stem position Position indicator (O MM & "' 4888P (0.25)

(0.25)

~

! Flow indication , (0.25)

b. Do NOT change the valve position (0.25) and notify.your

supervisor (0.25) (0.5)

REFERENCE TPT ADM 0103.4, pp 2/3 1 oWG-13: Valve Lineups / Verifications (3.7/4.0) .

l 1

I I

h

? !

i I :

l [

1 l

4 1

! i l- -

l !

i 1

_ . . . . _ . .......,.~,...-_.._,._,___,_,_,-._,..,..-_,-....___..._......,__,......,,m. . - , . _ . , . _ , , , . . , _ _ _ , . . , _ .

4 PROCEDURES - NORM A' . A? NORMAL. EMEPGENCY AND P4gg

~~~~E5UIUEUGEU E~UUUTR6[~~~~~~~~~~~~~~~~~~~~~~~~

ANSWE59 -- TURKEY POINT ?da -8 6/O d.' 23 -JCPR f 0 0 !J O *. A 5 ANSWER 4._1 '1.00)

M.

4HSI - 1590 prig (1500 - 1600) (0.5)

LHSI - 225 prig ( 150 - 250) (0.5)

REFERENCE TFT E0P-E-0 ?? 6 006/000; MT.06(3.5/3.o)

ANSWER 4.12 (1.00)

Turbine is tripped so that the heat sink will be maintained as long as possible (6,5) on a total lots of feedwater ATWS (+.5)

REFERENCE Westinghouse B act:.gr ound Info on FR-S.1, pp 7, 76/77 EPE 020: EK3.12(4.4/4.7)

ANSWER 3.13 (1.00)

CRCs are written on the premise that at least ce A/C Emergency Bus is energized.

REFERENCE Westinghouse Esckground Info for ECA-0.0 EPE-055; EK3.02(4.3/4.6)

ANSWER 4.14 (1.00)

A reactor trip may result (+.7) as a 15% le /e1 s v3n a l has been introduced irto the trip logic ( + . 3 ;+

REFERENCE TPT ONOP 003.7. pp 5 062/0007 PWG-7(3.2/3.7)

4. PCCCE00RES - rJ O R M A L - ABNORMAL, EMEPCENCY AND PAgg 3g

'~~~~~~~~~ ~~~~ ~~~~~~

~~~~5dD5bLUEECAL'U65TRUL ANSWEPS -- TURKEY POINT 3&4 -86/04/28-JERRY 00UCLAS ANSWER 4.15 (1.50)

3. Reinsert the control banks (0.2) and borate as needed (0.2),

PS-N author.res startup (0.2) (0 6:.

b. Reinsert the control banks (0.2), e /aluate the ECC (0.2), need OPS SUP (0.2) and (0.1) RX SUPVR (0.2) permission to startup. (0.o)

REFEPENCE TPT OP 0202.2 pp 3 001/010; A2.07(3.6/4.2)

ANSWEP 4.16 ( 1. ?. S )

1. Establish (or meintain) cold shutdown baron concentration (0.3)

2. Trip (0,2i and rack out '0,2) reactor trip breakers, verify 3tl *ods on bottom (0.2) (0.6) 3 Check makeup controls to verify dilution not possible (0.2)

3. CCV-114A CLOSED (0.05)

b. FCV-1229 CLOSED to.05) c U-353 LOCMEO c'0 SED (0.05)

. (0.35)

PEFERENCE Ter9ey Point. ONOP *2100 p. 3

1-i '

r iA8v i1 ENCLOSURE 3 4

j. J. S. NUCLEAR REGULATOPY C0tTISSTON SENIOo ::E AC TOR OPERATOR LICENSE EXAMINATION CACTLITY: TUPKEY POINT 234 ,

, REACTOR T(PE: PWR-WEC3 OATE ADMINISTERED: 86/04/28 l YAMINER: DEAN, uM APCLICANT: ____ -___________________

INSTRUCTIONS TO APoLICANT:

! Use separ:te paper for the answers. Write answers on one side only.

Staple qu?: tion sheet on top cf the answer sheets. Points for each

questico see tndicated in parentheses after the question. The passing

grada requires at least 70% in each category and a final grade of at i least S0*, E: : e e. i n a t i o n papers will be picked up w (M hours after j the exam.,: tion : tarts. fav V i

j

. OF

' CATEGORY

. OF *P@LICANT'8

, CATEGOPY 4

VALUE 'O~AL SCOPE VALUE CATEGORY

-g _ -----_--- -------_ ----_---------------------_--------

2

'o'00

-- - M

~'. 5. THEORY OF NUCLEAR POWER PLANT j OPERATION, eLUIOS. AND .

1, . L -2 T'-!ER *.0 DY N A MIC S 1

TN T' 1- -~~~~~ %-'9

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

)

l'.17 T 142 e, p

___ --_li ---________ ________ 7. oROCEDURES - NORMAL, ABNORMAL,

. EMERGENCY AND 4ADIOLOGICAL j

y3,{

.e m, g <f. {

CONTROL

!' _ _ i ; ; _ _ _ _C '_ l _" ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS +

] 72.00 100.00 TOTALS i

i j

FINAL GRADE ---_--_-_--______% ,.

e j All work done en this enamination is Tiy own. I have neither given not received aid. i h

dPPL5C5UYI5~55GU TUR5~~~~~~~~~~~~~~ :

4 s

h I

5. THEORf 0F NUCLEAR POWER -_ ANT '3 r.E R A T I O N . 'tgIgg. AND PAGE 2 THERM 00*NAMICS QUESTION 5.01 ( 1 . 0 )

'4 h i c h o f the f,'lowin3 per* ctdent contsinment hydrogen contrtbutors is dependent n the " 4 d : :-

'- f i eld intensi+, ;ns ide con t a irm an t for the amount o r Sydrogen >' - V ;-

2 Zr

2 '-i 0' Ir0 - N m

5

b. 2Al + 3H 0--1 A1 0 - ?u u

c. Zr - CH 0-" 1, . r.v ;

y e.- . d q, u g -_ _ v + e OUESTION C . r'- 1.0".

r.g +-gge stor 7

emperrtv-n Ocef'icient (MTC) var 2s with certain plant cond:tisn . Concern:r.g - :- ertations. which one of the fol10 win 3 is

. rrect?

3. The MTC b e c c n.e- more negat've as baron concentr; tion is

nceersed.

b. "he CC causes m: 21 +' '. v distribution to be tilted t o w a r d s' the * .? u# +be core vt BOL.

. The MTC :r:es s ': *emperature changes because of the non-linesr d e r.s ; t y changes of water =2 temperature

n.nge5.

d. The :1 T C is not permitted by Technical Specifications to be positive in so, p1rnt opereting modes.

QUESTION 5.03 (1.00 Attsched Ci3vra i 220 thcws 2 power history and four possible samarium traces (reactivity vt time). Select (s. b. c, or d) the curve that correctly displays the e.mected samarium transient for the given power hictory.

(***** CATEGORY 05 C0tJTINUED Ott NEXT PAGE ***s*)

4 800- -

E.- . .... . . . . ..........

se at 3e 90 40 60 16 g . . . . . . . . . . . . . .

9 a a.

. g V . . I 5 .

Ie 80 30 9e 80 6# 18 b, i, . . . . . . . . . _ . _ _

L i

e'O is is de e'0 [0 ip l .

c. $

18 as 30 90 50 6p 7e d.

, E o

Q.

io ao no 5. s0 se se I

l TIME (,ORYS) l i

FIGURE #220 i

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

5. THEOPY OF NUCLEAR POWER oLANT OPERATION. FLUIDS. AND PAGE 3 OUESTION 5.04 (1.00)

Attached Figure t 219 shows 2 power history snd four possibl? :enon traces (reactivity vs t ime ' . Sel?ct (2 b. c. or d) the curv? thst correctly displays th? e"pected 'enon t'3nsient for the given power history.

QUISTION 5.05 (1.00)

Which of the curves en ' 'i e attached p2ge correctly shows the behavior of th9 Doppler Oniv c ower Caefficient vs. Power Level for both BOL and EOL conditicos?

nUESTION 5.06 (1.005 Cor esch of the " c l i c w i r. g . select from the choices in the parentheses, the most restrict .? conditicn For Shutdown M1srgin Muirements, assuming Mcde

or 2 canditions e"ist e) Time in core it #e (90L. MOL or EOL) b) Accident (Rod E;ection, Steamline ?reak or: nadvertant Dilution)

DUESTION 5.07 (2.00) ,

An ECP :s calen12ted for a startup 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a shutdown from 100%

steady state power. Indicate whether the actusi critical position will be GPEATER THAN, i_ESS THAN or the SAME 3: the ECP for the following conditions. @ce*# STM lum StePG UStb

1) 'he steam dump pressure setpoint is increased by 35 psi 3 ya c, woc. 7px

2) All steam generator levels are increased by 5% one minute be# ore the calculated ECP is to be reached

3) Condenser vacuum is reduced 3 '

Hg due to a small air leak

4) Reactor startup is delaved for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

(***** CATEGOPr 05 CONTINUED ON NEXT PAGE *****)

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5. TPEORf 0F NUCLEAR POWEP DLANT OPERATION. FLUIDS, AND PAGE a

'HE:MODYNAMICS QUESTION 5.08 (1.50i A motor d r :. v e r. centrifu3:1 mump .2 openating at rated flow. You then Itsr' closing down on the d:: charge valve. How (INCREASE. D E C R E A f a-: ,

ur REMAIN THE SAME) will each :t the following be affected?

a. Clo.

b. D i sc'ist ge Cressure

c. Motor Amps OUESTION 5.09 'i.50)

Indicate whether the following will INCREASE, DECREASE, or *EMAIN THE SAME.

s. Availabl2 PCP NPEH =. elometric flow rate increases. (0.5)

b. M i r :, m u m required RCD >!P S H as volumetric flow rate increases. 'O.5)

c. Available NPSH to cc7densate (hetwelli pump as condenser subcooling :n:re=ses- (0.5)

OUES "I" E.20 I.l.50

'ndi 3te whether the follow:,ng changes cause the differential boron a c t t .' to become MORE NEGATIVE. LESS NEGATIVE, or REMAIN THE SAME. -

Ocn 1 der each i,e p a r s t e l y .

Ecccr concentraticr. :ncreases (0.5)

b. Moderator temperature :. n c r e a s e s (0.5)

c. Core ?ge irereases (at a constant boron concentestion) (0.5)

QUEE" ION 5.11 ( .50) olacing fuel with relatively low assembly power on the periphery of the core produces a Low L e a k.a g e Loading Pattern. Aside from reduced neutron leakage, what ts the other main advantage gained in using this loading

' scheme?

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

5. THEORY OF NUCLE AR POWES: ot ANT OPEE:ATION, FLUIDS' A40 PAGE 5 T

QUESTION 5.12 (2.00)

Referring to ~igures S-27A and S-279, answer the following q u e s '. :. o n s concerning a Ic 33 of one GCo +ransient f r o ::. 22% ocwar withov+ a

. esctor trip.

a. why does loop : RCS ficw ineresse at point 3? ( 0. 5 )

b. Why does loop 1 RCS #10w increase at point 2? (0.5)

c. Why does laop 2 9/G 1evel decrease (Shrink) at point 4? (0.5)

d. why doei sectioneerad h:gh Tavg (oper a ting loop) increase vt point 3? (0.5) m., J :- _: r n_ e4 e.4.3 v t. 4. . .m. n -

I# resctor power increases from 50% to 100%, the aversge flu in +he nesctor doubles, with this 2"erage f iv> incr?- e, why dce; the rod worth remain eccentially constant.

QUEETION 5.14 (2.00i Indicate how the parameter 3 aelcw respond and the reason why + hey react ,

thrt wav. on a loss c' r. 3 t u r a l circulaticn following a trip 'om 100%

equilibrivo conditions *

a) FC3 wide range Delta T b) 01fference betweer, T/ cold) and P(steam)

( * *~* *

ENC OF CATEGORY 05 *****)

6-27A 0683 saast -o- aoos sitesi eewcLaan powsa m IIC pupr Loop eg (g) maassumiram panssues cesse:

4 I

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a 1

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%s L%/ (g[

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g, e 3E39 s** ' 33* * * *0

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w I i 1

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ese 630 430 e toe 0 130 sse sts l

+2 RCP TRIP - 22% POWER S-27 i l

8-270 0683 l 8 et P STEAM P90g c t sie 6sysk fu n.c. et u m gg

, es w 44e /mia a 3e 3 4 1 1

t 1 s

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2 RCP TRIP - 22% POWER '

S-27

-,---e- . - - - - . . . . . . + - <-+ --

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 5 nUESTION 6.01 (1.90)

The input to the rod irmertien limit calculator used as a direct indica-tion of reactor pouct -:

3. [Ypolse Pretsur9

5. Auct.cneered High Tave

c. '"otal Steam Flow

d. Atctieneered High Delta T OUE3 TION 6.02 1.00)

Of the following signal. that de-energize the diesel 'Readv To Start' light, wh:ch is also interlocked to prevent the diesel from s t a r t. i ng ?

3. ' ow 3 tar *ing Air Pressure

b. P+v %ltch i r. E: v r .= 9 ;

c. cw ?> id 7 ar: meve'

d. '. 3 W Crw10de Ci1 0' . . ' .I r e

.. .ow o reivi- "' ; l 'etiperature QUESTION 6.O? /1.00)

At

^

c- poue . u;th 'he stesa, dui.P control system in the Tavg mode,'a 10%

stwp i t s -; cf l' . a d cecurs. Assuming no reactor trip occurs, the condenser

. r. . i n l e . rnd the -9:ctor operator manually operates the control re. which of the following would occur if E'ank 1 (CV-2827 and CV-2828)

Itsam dump -! es failed to open?

a. c a r.i 2 ( C '.'- 2 8 2 3 6 CV-2830) wou'd open. _

b. Atmospheric dumps uould open.

c. S/G safeties would open.

1. No other steam '. 1 ees would open.

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

-_ ___ _-. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . -_-- __ _-_________ _ _ _ _ _ _ - - - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ -_ J

~

6. c ' AN T SYS TEF'S DESIGN r CONT 90L7 AND IrJ S T R U t4 E N T A '10 4 PAGE

?UE3' ION a.0a (1.00%

Which cf the following statements concerning the automatic isolation of component cooling water RCP thermal barrter #10w is correct?

a. High flow sensed in a r. individual thermal barrier return line will eutoma t ic ally close its individual retu r. line tsolaticn valve,

b. wigh f '. o w -s e n s e d in an ind;vidual thermal barrier return liv will automatically close the ecmbined return line 13cistion /31.e.

c. 'J igh " low sensed in the conbined thermal barrier r e t .i r n line will eutomat cr'Iv close all three individual eturn l i r. e - solation -21 es. ,

d. '2 i j h " low s e. ==_ .be combined +berma1 barrier return 1[* .4 a: ' . ' o '. e t ' + C 3 $ 1 *f close the COmDinEi r9 turn 1ine 5

t : :. , 21 q . p e T ,. .,; v.e;

. 4 . n n. 3, 1;':.. .e " 21 1 o w i n .3 eactor ccnd: $ 1ons in Colum- A with the rod speed Co.D..

. E' COLUMN A COLUMN ?

3, v i L : . d r ~. i, : n 3 i,hutdown 3=nk 9 in Shutdowr. 1 8 spm E: r '< 3 position 2. 16 spm

'3 . 24 spm

b. u:thdrswi.g Bank B in Control Senk E' 4. 48 spm position 5. 64 cpm

6. 72 inm

c. .4utomatic insertion with T?vs ~ Tref bv 2 degrees

d. Automatic insertion w1*,h Tavg Tre e by 5.5 degrees

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

1

GT o

6. PLANT SYSTEMS OESIGM- CONTROL. MD INST 90 MENTATION 00ESTION 6.06 u. . . i. I [#*1 Match the AcW T 8 "cl ce . easpeec tn Cel.in A to the reset '. o c a t t e n c-condit:cn ;r Column 8. ce- t' or one 3 newer m?. e carrect fcr each.

All co-cect ?nwe - tre r e e '. e - *:r #11 credit.

C O'.U n N A COLUMN 9

.. Electrt: . ' . a. Rese+ #ron Centrol Room

b. Auto reset on bus stripping

2. Mechanical . Auto reset en auto AFW start

d. Auto reset when speed decresses

e. Peset locally 90ESTION 6.09 (2.00; With the exception of .-ditatione list 211 8 o# the pa3tective, control and permissive cirev.ts which receive ?n irg + from DT-446 and PT-447

' turbine "irst I+?ge p"=-: ei. Identify circut's by nomenclature where E p p l i c t'.' l e . f

?g P - A '-

CNESTION 6.08 . ~))

u # c '. ' w : n g questionc :e -! wl-P 'he Intake Cooling Water Sv: tem (ICWS).

2 What =re the THPEE 103c3 supplied by the ICUS? Do NOT n:19de '

redundant loads. (0.5)

b. Wh2t valve in the ICV? 13 directly effe:ted by a safet,y injection sigr.31? Includ' in your answer, how and why it is affected. (1.0) s QUESTION 6.00 M. .e . 73

3) At ahat two points can UNIT 3 and UNIT 4 CCW ssstems be tied to3 ether?

b) Besides starting 2 CCJ : e n:: s , what valves essociated with the CCW system reposition un 2n 'S' signal?

OUESTION 6.10 ( .i Assuming the containment s ,: r a / pumps are runningr what signal will automaticilly initiate emercency containment filter dovcing?

(***** C A T EG0c:Y 06 CONTINUED ON NEXT PAGE *****)

i 4 1

PLANT SYSTEMS DESIGN, CONTPC'.. AND INS T RUfa EN T A T ION : AGE o 6.

(

5 nUESTION 6.11 (1.505

__st CIVE signals / components that ar e reset when the Rod Control Startup Pushbotton is depressed. ' .

QUEST!ON 6.12 (2.00)

List all the automatic actions.(3 of them e-ist) performed by the 90s Stripping releys.

! OUISTION 6.13 (1.50) i With the resctor at 50*. Power. S/G'A's steam pressure input .o the Steam Generator Water Level Control _Svstem f=.ils hiyh. Enpinn how this will affact the Lavel Controt System #ct 3/G A, and why this action OC2Or%. 4 I

O t F S 'I'J N 6 . *. 4 'i.:0)

With 'Te os. tor s' 757. power s r.d all primary cantrols in automatic, p r a z o. r i z e r :'-asure transmitter PT-445 fail high. Assumin3 no

) ;_ - r 2 t o ction oc:ur, describe the. response o' the pressorizer pressure co,. 91 syst?m. Continue descript:an until prersvrinea ereituru (4 s' -i b l -) or 6 a O a .; t 0 r trip GCCurs. (Include '6', paints a,ve . a. *la'.- ,

~'tTCTION 6.*5 '1.00)

.1 ALL '% d n;3n bases of the minimum level requirements of the co densate cr ge tank.

r.< * *

END OF CATEGORY 06 *****)

n i

l

7 PPCCEDUoES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 10

~~~~kbO5ULUG555E~5U5iiU[~~~~~~~~~~~~~~~~~~~~~~~~

GUESTION 7.01 (1.00)

Which of the following statements describes the correct usage of the Critical Scret. Curction (CSC$ Ststus Trees while e,erforming EOP-E-0

' Reactor Trip c3 Safety I n ; +; t i o n ' ')

3. The CSF Status Tr=s: tre NOT monitored in E0P-E-0.

b. Awareneis of ?ed 5 th Criteria is required at all times, but the CSF Status Tr ea1 e monitored only a#t ar it is deter mined that SI can 10T be t e r I t r. a t r . .

c. Mc itoring

w C 'i c Status Trees commences as soon as the imned ate acttan :' ms are completed.

d. CEr ets i v: r~ -

requir+d to be monitored as soon as the pro y. sr.. e n '. e r e d. ar d 3 alid SI is determined to have

ctor 2d.

m y TS ?IO *' '.00 t.;.0c' Which of e following i t 7tements correctly describes the major difference escrdin3 ST termination between E0P-E-3, ' '3 / G Tube Rupture' and ECA-3.1,

'S/C t ube Rupi. ora .s t t h Lns o# Ceretor Coolan+-Subcooled Recovery)

2. EctF recedures ot:11:e the same SI teamination criteria a rid the s a m ._ .erminatien methods,

b. C -- 3 u t i l N0' ' lou SI terminstio. if s void exists in the upper hssd o' 'Se vescel, while ECA-3.1 o'11 sllow SI termination in this r:

o : t :. o n .

c. E-3 tarr.ma' c bo'h LPSI and 451 pumps simultaneously while ECA-3.1 teriinatec the LHSI pumps when different eriteria from that required to 6. t i p 'Se HHSI pumps exist.

d. E-3 terminates c e t :- 4'-S! pump s simultaneously. while ECA-3.1 terminates the '8'2SI pum?s one at a time.

twvn* CATFOORY O' CONTINUED ON NEXT PAGE *****)

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

~

m m:.tJc:ES - Na cM L , *@ 00 MAL, EMERCCNCY A fJ D oACC 11 O ADIO'_9CIC r_ : 0 aJ 7 r,0 L n'J E I T IO N ?.03 (1.00'

'Jh:ch of the follcuing statements regarding plan + clearances :a cortect?

a. When e"ecuting a clearsnce o-der, each oper2 tion mett be conducted in the order in wh ich :t was given.

b. 'J h e n returning iv ' -

"t ; to service- the electriccl cwitching is done first, Wri+ ten perm

o ., c rom all clearance holders MUST be obtained c.

Mf oi v pv form:ng - tenporary lift for te=t purposes.

. !f c on 'uc + : ng a :lesrance in a contaminated area, the ORIGINAL copy of t~e n cleerence is left at the entrance to the area and is

nitialed appropr.ately by the operator upon his e"it.

90ES'!Or 04 '2 .OnT un, ,., .<:p t ig d a u n he Sco transfer canal, a peruan is stationed in the I-as of the SCC to men;tcr the 3FP and the tran #er canal. What are the 1 c o id i t : a n :- when he should alert the operator at the SFP uest E" changer Rcom (parsmeter values are not required) per OP 16125.4 'SFP Transfer C3na'. C 111ing or O.onping i Water to the SFP'?

QUESTICN 7.05 (1.50)

Indicate whether the following conditions will place you in a CSF RED PATH or NOT:

a) Containment pressure of 37 psis.

b) All 3 S/Gs at 25% level and AFW Flow of 300 spm.

c) PCS Subcooling is 10 degrees and PZR level is 12%.

OUESTION 7.06 (1.00)

Why is there a precautionary note in E0P-ECA-0.0, ' Loss of All A/C Power',

to monitor the CSF Stater Trees for information only, but not for Purpo;es of implementation?

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

7. oROCEDURES - NORMAL. ASNOPMAL, 5"E*GTNCY AND PAGE 12

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

~~~~55656LUGIEIC 55NTE5t OUESTION 7.07 (1.25)

3) While conducting an Independent Veatftcation, wh3t are 3 methods by which valve position ca, ;i e verified per AP 0103.4. 'Ir *1 ant Equip-ment Clearance Orders' (.75) b) What are .our actions 1 # vou find s valve out of position?

(0.5)

QUESTION 7.0S (1.50)

List all the substeps contained in E0P-E-0 'Peactor Trip or Safety Injection' for performing varifiestion of faedwater isoletion. (4 veri-

'1 cations and 1 action required for full credit)

OUESTION 00 II.00T cunctionni 9estoration Stocedure CP C.1, ' Response te Nuclear Power Generstion/ATW9', har +ha 3rerstor trip the tur:::ne as one of the immedtste acttons. However, one cf the m3jor c icerns in the ATWS t r atisier t re:ponse ev:1ur+:o-: 's t5e exces=1ve CS pre =sure developed due to zignificant hestup o r t; e pr; mary coolcr.'. Since keeping the turbine :n the line would mitigate tht: t9mperature rise. uny is the tur? no '.c1pped 3 r.y w s y '

00E9 TION -10 II.1n)

Whti- :cnductirg refucling operations, with a fuel assembly being removed rt om ths ccre md 1stched on the m e r. i p u l = t o r cr ne. sump levels in the c o n + a i r. m e n t in:resse 2nd c:distion levels Itsrt to rise indicating a r eilure o r 'ho ref*>eling cavity seal. uh s t irmediate actions are required o' the Oefueltog Oper2 tors in 3ccordance with ONOP 33.2 ' Refueling Cavity Sesl r ailure

QUECTION 7.11 - 1 . 2 " " /. 0 Lirt the 5 UNIT 3 Area R a d i s t i e r- Monitcrs critical to refueling that, if INOF EP AE:LE . -ould helt rat iel ing oper s:t ion s .

tx**** CATEGCPY 07 CONTINUED ON NEXT PAGE *****)

~. PROCEDUPES - NORMAL, ASNORMAL. EMERGENCY AND 7, G r. '?

- - - - c. a n. r 0 , c. es-r r ----_.------------------------------

2

,'i ._' C n_ 4 R. . . O '-

OUESTION 7.12 (1.50' W ith rod contr:1 in automatic u " '. l e at S n '. power, whst 3re e'l the immediate oper tor actione : # ;n3 1e rod droer i , s s o ni e no - *

,10 as atated i r. nNOP 1608.1 *rell .an3th c:C C Pa1f.+nct:en

GUESTION ' . *. 3 (1.06:

'he SRENT r i,. E L PIT HICH - CC' 'larm actuates. fi siin' n 3 a /31 d S;3h 1040' condi+ ce e ;t:- what cr tho immediate operator actions as ' ' -

s -:

n CNCR 33 1- TR C aol . v3 S -+.em Malfuncation'?

' .;1 qu?STr0s <1.rn-

'

1, 3) are The C1 2n m- e. .- r i t - F ?r the E- eries rocedures (E-0 idei+1c;; : r o '- t .n E '3 'GToi- u h i *- ret. ire: that sufficient AFW flow

g -

- ; ;; 'g. _c. a ,:- 2 . _, . e d ' What 3 the ba is for a l l o w i n.3 *his

,c..,-- .:

---ny , ..., . 4 Jhi'e _

e - P' r m i n 3 OF-TI-'.:- 'N 2tur21 Circulation Cooldcun'. sfter t h e C: u c.

. y 2 ? = 1. .- Plered in =crt:.r. to continue cooldcar +c Cold S h u :. d o w n , you n=

r e :ii t r ed to cool the 5'GT by d i..i n p ; n 3 st.u.

'th-t is the basi 3 b e h i rtd this

-teo and e'r. u .: n ' i t ', e cut - n'em rrovide s u f *' r i e n t coolin3'

'snt e END OF CATEG00Y 07 ***r*i e-- - .

c.% . -

2

3 ASMINISTRATIJE PROCEDUoES. r04DITIONS. AND LInITATIONS PAGE 14 Ol E S T U)N 9.01 '1.00)

If a safety limit is exceeded, the Nuclear Regulatory Commiston Operations Center shall be notified _____.

3. Within 1 hour.

b. Within 4 hourt.

c. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

d. Within 72 houri.

OUESTION 8.02 (1.00)

Ef control power is lost to a Unit 4 pressuricer power opersted relief velve while in mode 1 which stot: nent below is correct?

3. Toch spec, require no -rtion provided another POR') is operable and 311 pressur;:er co de sefetv valves rre operable.

b. Tech srecs r e qu i r 'e 'he power supply to be removed from the

?,sociated bl ac' - -l>e efter .er:fvi 3 .t to be opens if t h e P O R ')

.: not operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and cent nuous operation is desired.

.. 'ec'. scoe: requ;re the .ssoci2tud bloce velve to be shut and its power rem]ved '# t h e P O R') 14 not mada mperable within one hour and cont no ws ope e t : Or,

_ s desirabla.

. 'ech specs equire actLon to ha _nitiated within one hour to place t'se plant tii :t 'ctst hot s t aiidh within the following hour ~if the 0209 .: not a.a d e operable.

O'E?r~0N c.03 /1,00)

Answe TRU~ or C A'.3 E 'o the following

-: ) It a component's emergency power suppl,. s INOPERABLE but all other inpporting equipment f or that component is OPERABLE, than surveillance requirements on that component must still be performed within the proper time frame.

b) If it is required by In LCO Action Statement to be in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and then HOT S '-lU T D O W N in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , it is permissable to be in MOT STANOBY :n 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months then use the next 9 to be in HOT SHUTDOWN.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

9. A O MIM !S T C:ATIVE PROCEDUFES. CONDITIONS. AND LIMITATIONS PAGE 15 M'E 3 TTO 1 3.04 (1.00i

'n e n it 13 nece s :ry to use we'er to combat a fire in the vic:nity of e n e r ,: i r e d - high , ltage electrical equipment, what 2 precautions must be 2 chared *c nila vaing the wster hoses as stated in EP 2010~- *cire/

Espi12 on Eve gencie="?

OtJESTION 3.^5 (1.00; c 11 in 'he 51 : rM e in the statement below regarding Tech Spec requirements fo~ the CCw end ICW c y c.t e m = :

'he mo 'or 3 hall no+ be made critical unless _____ CCW pumps

. .? _____ CCu Heet Enchengers are operable. Additionally,

_____:u , ,, m p s and _____ICW headers are also required to be op e. :e rpj e ? * ' n a 3.n; < 1. 5,0 -

_ 'J : , o - ;,ermi::ien is 'equired to et ceed the ;ocally imposed whole body e .oe t o : e 'imit of 300 mren/wk. assuming a quarterly dose of 800 mrem 2 11 40' be e'ceeded' I" 3- individual hn s complated N :C Form-4 on filer what quarterly eaposure cr* 5e be Illowed to rece:ve without approval from the Plant danager sod without notifying Corporate Health Physics? ,

ci What on?titutes an sirborne radioactivity ares?

QUE3'ICN 3.07 (1.50) 34 !* pro:edural intent is not changed, whose approval is required for an On the Spot Change (OTSC)?

b) In the situation given abover what is done with the 3 copies of the OTSC generated by the originator? (ie. what is the routing or use of the 3 copies)

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

l 1

l T l 1

8. ADhINISTRATIVE PROCEDUPES, CONDITIONS, AND LIMITATIONS PACE 16 QUESTION 8.08 (1.00)

3) When notifying the NRC of a significant event via the Emergency Notification Svstem (ENS), with what segment of the NRC are vou communicating?

b) Aside from notifying the NRC after it is determined a significant event has occurred, what other two individuals (use titles) is it the direct responsibility of the PS-N to cont:ct?

OUESTION 8.00 (1.50)

'A' EOC has just been declared INOPERABLE with both units at power. What a*e the 3 requirements thct must be met to continue power operation?

QUESTION 8.10 - . . . _r_ /. '0 h Prior to a .tenber of the plant management staff arriving on site, what is ths order of succession to perform the dutie; _ the Emergency Coordinator 1* the P S ^1 becomes incapacitated' QUEC' ION S.11 (1.00)

If -n UNU90AL EVENT is declared, what 4 communications devices can be ut ilized to r.otify the State Warning Point within the required 15 minutes?

QUESTION 3.1C (1.50) 31 Jho :s -esponsible for logging common plant equipment in the Equipment Out of Service (E00S) book? (0.5) b) List a conditions that would require that an annunciator be recorded in Part II of the E005. (1.0)

OUESTIC'3 8.13 (1.00)

What is meant by the atstement in Technical Specifications that says "The provisions of Specif2 cation 3.0.4 are not applicable'?

(**~*** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8. ADMINISTR ATI'JE PROCEDl!*ES . CONry171gsg. AND LIMITATIONS : , r. 7 ; --

OUESTION E.14 (1.50)

A rece-t ( M a r : 1986) c' o w e r olant Engineering Safaty Evaluatic> was peaformed or D C '. o a d i r. g cIpsbilities. ren.ilting in modifications to

'~ m e r g e n - Operatin3 Proc di'ces and adjus*3ents to v31ve settings in both the ICW and CCW Iystem.. Wh-' .; ihe postulated scenario for which the e modt # i c 3 +. ; o r.1 wm- equirad? fInclude the status of both Units) 90ES TION' 9.1" (1.00's Wh/ Jre the ac': ]n statementi for r/S 3.1.4(Reactor Coolant Activity) more re,tr -* - u h e c. RCS *,m..er;+ ora ts g r a a t .: r than 500 degrees C7 s ***** END OF CATECORY 08 ***** )

(***********r* '~HD CF EXAMINATION ****** *********)

e I g ,L ,IINf' *1e (

L' ,

. f a ca . ,, . Cycle efficiency o (Nettork out)/(Energy in)

' 2

, o mg s e V,t = 1/2 at E = me- -

(E = 1/2 mv a = (Vf - 13 )/t A = AN A=Ae'* 3 PE = mgn vf = V, + at * = e/t x = zn2/t1/2 = 0.693/t1/2 t

UU 2 .s 1/2'If

E I *1 ')I *))

A=

[(t1/2)

Itd ))

,'E ' 9 3 I **

m=V avAo -

I=Ieo

-Ex Q = ph Q = mCpat h = UAa T I = I,e~"

Pwr = Wfah I'= I, 10'*/ M TVL = 1.3/u P = P 10 sur(t) HVL = -0.693/u P = P,e* ,

SUR = 26.06/T SCR = 5/(1 - K,ff)

CR, = 5/(1 - K,ff,)

SUR = 26s/t* + (s - o)T s CR;(1 - K,ffj) = CR2 II ~ "eff2)

T = ( t*/s ) + [(8 - o V I8 3

M " 1/(1 - Keff) = CR /CR j ,

. , gj(, , g) M = (1 - K,ff,)/(1 - K,ffj)

T = (s - o)/(Io) SDM = (1 - K,ff)/Keff a = (K,ff-1)/K,ff = AK,ff/K eff t= = 10 seconc .

A = 0.1 seconds a = ((t*/(T K,ff)] + [s,ff /(1 + IT)]

=Id I jd) 2 ,2 gd 2

P = (rev)/(3 x 1010) Idjj 22 2

I = eN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2.gf,,g) .

Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 x 1010 dps 1 gal . = 3.78 liters 1 kg = 2.21 lbm 1 ft< = 7.48 gal. 1 r.p = 2.54 x 10 Stu/hr .

Density = 62.4 Itg/ft3 1 rav = 3.41 x 10 5tu/hr Density = 1 gm/cW lin = 2.54 cm Heat of vaporization = 970 Btu /lem *F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm . 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/in.

e = 2.718 me a h g ess me

.M" '

5 '- _ _ _ _

_ _ g

1 Enthalpy. Stw/lb Entropy. Ste/le a F Volume. ft'/lb '

Steam Water Steam

E p ss. Evep Steam Water Evep Ever y Water v he A,g 4, sa sq s, vf vg s

-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 0.06859 0.01602 3305 3305 82 3 00 1073.8 1076.8 0.006) 2.1706 2.1767 35 35 0.09991 0.01602 2948 2948 40 8 03 1071.0 1079 0 0.0162 2.1432 2.1594 40 0.12163 0 01602 2446 2446 45 l 13.04 1068.1 1081.2 0 0262 2.1164 2.1426 ,

45 0.14744 0.01602 2037.7 2037.8 50 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 '

50 0.17795 0.01602 1704.8 1704.8 60 28 06 1059.7 1087.7 0.0 M 5 2.0391 2.0946 60 0.2561 0.01603 1207.6 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 0.3629 - 0.01605 868.3 ' 868 4 70

'O.Orsor -* -633'.3- 433 3-

, 48.04 -10484 .- 1026 4i:. 0.0432: 1,94a6% .2.0359 .40 <

'80 ^ 0 5068 "

468.1 58.02 1042.7 1100.8 0 1115 1.8970 2.0086 90

$0 0.6981 0.01610 468.1 0.1295 1.8530 1.9825 300 350.4 68.00 1037.1 1105.1 100 0.9492 0.01613 350.4 0.1472 1A105 1.9577 110 265.4 77.98 1031.4 1109.3 <

110 1J750 0.01617 265.4 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 1.6927 0.01620 203.25 203.26 130 120 97.96 1019.8 1117A 0.1817 1.7295 1.9112 2.2230 0.01625 157.32 157.33 140 130 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 122.98 123.00 140 2 8892 0.01629 97.05 97.07 117.95 2008.2 1126.1 0.2150 1.6536 1.8686 150 l 150 3.716 0.01634 0.2313 1.6174 1.8487 160 l 77.27 77.29 127.96 1002.2 1130.2 160 4.741 0.01640 996.2 1134.2 0.2473 1.5822 1.8295 170 0.01645 62.04 62.06 137.97 170 5.993 990.2 1138.2 0.2631 1.5480 1.8111 180 0.01651 50.21 50.22 148.00 '

180 7.511 1142.1 0.2787 1.514S 1.7934 190 40.94 40.96 158.04 984.1 190 9340 0.01e57 977.9 1146.0 0.2940 1.4824 1.7764 200 11.526 0.01664 33.62 33.64 168.09 200 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 210 14.123 0.01671 27.80 27.82 180.17 9703 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01672 26.78 26.80 188.23 965.2 1153.4 0 3241 1.4201 1.7442 220 220 17.186 0.01678 23.13 23.15 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 230 20.779 0.01685 19364 19.381 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 240 24.968 0.01693 16.304 16.321 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29.825 0.01701 13.802 13.819 938.6 1167.4 0.3819 1.3043 1.6862 260 260 35.427 0.01709 11.745 11.762 228.76 238.95 931.7 1170.6 03960 1.27M 1.6729 270 l 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 5.609 5.626 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 l 310 77.67 0.01755 1.6116 320 4.896 4.914 290.4 894.8 1185.2 0.4640 1.1477 820 89.64 0.01766 1.0990 1.5892 340.

3.770 3.788 3113 878.8 1190.1 0.4902 340 117.99 0.01787 360 2.939 2.957 332.3 862.1 1194.4 0.5161 1.0517 . 1.5678 360 153.01 0.01811 1.0057 1.5473 380 2.317 2335 353.6 844.5 1198.0 0.5416 ;

380 195.73 0.01836 825.9 1201.0 0.5667 0.3607 1.5274 400 400 247.26 0.01864 1.8444 1A630 375.1 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 420 305.78 0.01694 1.4808 1.4997 440 419.0 785.4 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 0.6648 0.7871 1.4516 490 450 566.2 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 0.5596 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520 812.5 0.0209 0.5386 13954 540 04651 536.8 657.5 1194.3 0.7378 0.6577 540 962.8 0.0215 0.4437 1.3757 560 0.3871 562.4 6253 1187.7 0.7625 0.6132 SEO 1133.4 0.0221 03651 1.3550 580 0.3222 589.1 589.9 1179.0 0.7876 0.5673 l 580 1326.2 0.0228 0.2994 550.6 1167.7 0A134 0.5196 1.3330 dice ;

600 1543.2 0.0236 0.2438 0.2675 617.1 02403 0.4699 1.3092 620 l 0.1962 0.2208 646.9 5063 1153.2 620 1786.9 C.0247 679.1 454.6 1133.7 0.8666 0.4134 1.2821 640 !

640 2059 9 0.0260 0.1543 0.1802 0.1443 714.9 392.1 1107.0 03995 0.3502 1.2498 460 j 660 2365.7 0 0277 0.1166 1.2086 600 0.1112 758 5 310.1 1068.5 0.9365 0.2720 660 2708.6 0.0304 0.0808 0.0752 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 700 3094.3 0.0366 0.0386 0.0508 906.0 0 906.0 1.0612 0' ~~ 1.0612 705.!

. 705.5 3208 2 0.0508 0 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)

A.3

9 yeaume,itW Enthalpy. Str/ID Etteory. Stubb a F tmery. Sty /it Temp Water Evep 8:eem Treter Evep Steam Water Steam N S-Press. Weter Evap Steam pela F 9ene er sq vg hy hg h, sq s o s, er ar, 3302.4 0.00 107b.5 1075.5 0 2.1872 2.1872 8 1021.3 s.esas 0.0s86 32.018 0.01602 3302.4 {

4.10 35.023 0.01602 2945.5 2945.5 3 03 10738 10768 0 0061 2.1705 2.1766 3A3 1022.3 e.10 1 45.453 0.01602 2004.7 2004 7 13.50 1067.9 1081 4 0 0271 2 1140 2 1411 13.50 1025.7 0.15 0.15 0 0422 2 07?8 2.1160 0.20 53.160 0 01603 1526.3 1526 3 21.22 1063 5 1084 7 21.22 1028 3 0.20 64.484 0 01604 1039.7 1039.7 32.54 10b7.1 1089 7 0.0641 2.016S 2.0809 32.54 1032 0 0.30 0.30 0.40 72.869 0.01606 792.0 792.1 40.92 1052.4 1093.3 0.0799 1.9762 2.0562 40.92 1034.7 0.40 79.586 0 01607 641.5 641.5 47.62 1048 6 1096 3 0 0925 1.9446 2.0370 47.62 1036 9 0.5 0.5 0.6 85.71S O01609 540 0 540.1 53 25 1045 5 1093 7 0.1028 1.9185 2.0215 5324 1C38.7 0.6 0.01610 466.93 466 94 58 10 1042 7 1100 8 0.3 1 8966 2.0083 58.10 1040 3 0.7 0.7 90 09 0.8 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 01117 1.8775 1.9970 6239 1041.7 0.8 8.9 98.24 0.01612 368 41 368 43 66.24 1038.1 1104.3 0.1264 1A606 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 1.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116 2 0.1750 1.7450 1.9200 94A3 10512 2A 2.0 10941 1056.7 3.0 141.47 0.01630 118 71 118 73 109 42 1013.2 1122 6 0.2009 1.6854 1A864 3.0 90 63 90.64 120.92 1006.4 1127.3 0.2199 1.6428 1.8626 120.93 1060.2 4.0 4.0 152.96 0 01636 8.0 162 24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 13443 130.18 1063.1 8.0 8.0 170 05 0 01645 61.967 61.98 138 03 996.2 1134.2 0 2474 1.5820 13294 138.01 1065.4' S.0 7A 176 84 0.01649 53 634 53.65 144 83 992.1 1136 9 02581 1.5587 1A168 144.81 1067.4 7.0 8.0 182.86 0.01653 47.328 47.35 150.87 988.5 1139.3 02676 1.5384 12060 15034 1069.2 8.0 9.0 ISP 27 0 01656 42.385 42 40 156.30 985.1 1141.4 0.2760 1.5204 1.7964 15628 10708 9.0 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 26.80 1J0.17 970.3 1150.5 0.3121 1.4447 1.7568 180.12 1077.5 14.896 15 213.03 0.01673 26.274 26.29 181.21 969.7 1150.9 03137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20.070 20 067 196 27 9601 1156.3 0.3358 1.3902 1.7320 196.21 1082.0 to 30 250.34 0.01701 13.7266 13.744 218.9 945.2 1164.1 0 3652 1.3313 1.6995 218 4 1087.9 30 40 267.25 0 01715 10 4794 10 497 236.1 . 933.6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 0.01727 84967 8 514 250.2

923.9 1174.1 0 4112 1.2474 J.6586 254.1 1095.3 50 50 261.02 60 292.71 0.01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1.6440 242.0 1098.0 80 70 302.93 0.01748 6.1875 6 205 272.7 907A 1180 6 04411 1.1905 1.6316 272.5 1100.2 70 80 312.04 0.01757 5 4536 5 471 232.1

900.9 1183.i 0.4534 1.1675 1.6208 281.9 1102.1 80 90 320.28 0 01766 4.8777 4.895 290.7 894.6 1185.3 0.4643 1.1470 1.6113 290.4 1103.7 90 100 327.82 0 01774 4.4133 4.431 258.5 888.6 1187.2 0.4743 1.1284 1.6027 298.2 1105.2 100 120 341.27 0 01789 3 7097 3 728 312.6 8772 1190 4 0 4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 001803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 324.5 1109.6 140 160 363 55 0.01815 22155 2.834 336.1 859.0 1195.1 0.5206 1.0435 1.5641 335.5 1111.2 160 ,

180 373 08 0 01827 2.5129 2.531 346.2 850 7 1196.9 0.5328 1.0215 1.5543 345.6 1112.5 ISO '

200 351.80 0 01839 2.2689 2.287 355.5 842.8 1198.3 0.5438 1.0016 1.5454 3544 '1113.7 300 250 400 97 0 01865 1.8245 1.8432 376.1 825 0 1201.1 0.5679 0 9585 1.5264 375.3 1115.8 250 300 417 3b O01859 1.5239 1.5427 394 0 8089 1202.9 0.5882 0.9223 1.5105 392.9 1117.2 300 '

350 4 1.73 001913 1.3064 1.3255 409.8 794 2 1204 0 0 6015 08909 1.4968 408 6 1118 1 350 1 l

403 44460 0 0193 1.14162 1.1610 424.2 780 4 1204 6 0 6217 0 8630 1.4847 422.7 111E 7 400 450 45628 0 0195 1.01224 1.0318 437.3 767.5 1204.8 0.6360 02378 1.4738 43b.7 1118.9 480 f 500 467 01 0 0199 0 90787 0 9276 449.5 755.1 1204.7 0.6490 0.8145 1.4639 447.7 1118A 900 )

553 476 94 00199 0 82183 0.8418 460.9 743.3 1204 3 0.6611 0.7936 1.4547 458.9 1118 6 550 400 48520 0 0201 0.74 % 2 0.7698 471.7 732.0 1203 7 0.6723 0 7738 1.4461 469.5 1116.2 800 700 .503 08 0.0205 0.63505 0.6556 491.6 710.2 1201.8 0.6928 0.7377 1.4304 488.9 1116.9 700 !

833 51821 0 0209 0.54809 0.5690 509.8 689 6 1199 4 0.7111 0.7051 1.4163 506.7 1115.2 800 l 900 5 d.95 0 02i2 0 4796S 05009 526 7 669 7 1196 4 07279 0.6753 1.4032 523 2 1113.0 900 1000 5 ~4.53 0.0216 0 42435 04460 542.6 650 4 1192.9 0.7434 06476 1.3910 5306 1110.4 1000 1100 555 2d 0.0220 0 37863 0.4006 557.5 631 5 1189.1 07578 0.6216 1.3794 553 1 1107.5 1100 1230 ! 667.19 0 0223 0 34013 0.3625 571.9 613.0 1184 8 0.7714 0.5969 1.3653 566 9 1104.3 1200 1500 ' 577.42 0 0227 0 30722 0.3299 585.6 594.6 1880 2 0.7843 05733 1.3577 580.1 1500 9 1300 1400 .m 07 0 0231 0 27871 0 3018 598 8 576 5 1175 3 0.7966 05507 1.3474 592.9 1037.1 1400 1500 5 % 20 0 0235 02b372 0.2772 611.7 550 4 11701 0A055 05283 1.3373 605 2 1093.1 1500 2000 635 80 0.02",7 01626f., 0.1883 672.1 466.2 1136.3 0 8625 0 1256 1.7881 662 6 10GS 6 2000 2500. 65d11 0 0266 0 10209 01307 731.7 361 6 1093 3 09139 0 3206 1.2345 718.5 1032.9 2500 3000 69533 0 0343 0 050/3 0.0850 801 8 218.4 1070 3 0 9728 0.1891 1.1619 7824 973.1 3000 3298.2 701 47 0 0508 0 0 050d 905 0 0 906 0 10612 0 1.0612 875.9 875.9 32082 TABLE A 3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE)

A.4

.I ToisV s'atwo. F Abe prose.

lb/ sea. 300 400 500 400 7W) 800 900 1000 1100 1200 1300 1400 3500 hetleenp) 100 200

)

611.9 571.5 631.1 690 7 e 00161 392 5 452.3 l 3 4 et 00 1150 2 1195.7 1241.8 1788 6 ISM 1 1984 5 I (101.74) s 0.1295 2.0509 2.1152 2.1722 2.2237 22708 2J144 '

e 0 0161 78 14 90 24 10224 114 71 126 15 138 08 150 01 161 94 17386 185 78 197.70 top 62 221.53 233 45 5 6 68 01 1146 6 11#4 8 1241.3 1288 2 13359 1384 3 1433 6 1483 7 1534 7 1586 7 1639 6 1693 3 17440 1801 5 (167 24) s 0 1795 13716 1.9369 1.9943 2.0460 20932 2 1369 2 1776 2 2159 2 2521 2.28 % 23194 2J509 2.3811 2A101 e 0 016i 38 84 44 93 51 03 57.04 63 03 69 00 74 98 40 94 86 91 92 87 98 Os los 80 110 76 116 72 10 4 68 C2 1146 6 11937 1240 6 1287.8 1335 5 1384 0 1433 4 1483 5 1534 6 15466 1639 5 1693.3 1747.9 1803 4 (192.21) s 01295 1.7928 1.8593 1.9173 1.9692 2.0166 2.0603 2.1011 2.1394 2 1757 2.2101 2 2430 22744 2.3046 2.333 e 0 0161 0 0166 29 893 33 963 37.985 41 966 45 978 49 964 53 946 57.926 61905 65 882 69458 73 833 77 807 16 6 68 04 168 09 !!92 5 1239 9 1287.3 3335 2 13835 1433 2 1483 4 15345 1586 5 1639 4 1993.2 1747A 18034 (213.03) s 0 1295 0.2940 1.8134 1 8720 1.9242 1.9717 2.0155 2.0 % 3 2.0946 2.1309 2.1653 2.1982l e 0 0161 0 0166 22356 25 428 28 457 314H 34 465 37.458 40 447 43 435 46 420 49 405 52.388 55.370 58.352 30 e 68.05 168 11 1191.4 1239.2 1286 9 1334 9 1383 5 1432 9 1483 2 15M.3 1586.3 1639.3 1993.1 17472 1803.

(227.96) s 01295 0.2940 1.7805 12397 1.8921 1.9397 1.9836 2.0244 2.0628 2.0991 2.1336 2.1M5 2.1979 2.2282 2.257 e 0 0161 0 0166 !! O35 12.624 14.165 15 685 17.195 18 699 20 199 21.697 23 194 24 689 26.183 27476 29.16 40 6 68 10 168 15 11P6 6 1236 4 1285 0 1333 6 1382.5 1432.1 1482.5 1533.7 15858 1638 8 1992 7 1747.5 1(s03 0 (267.25) s 0.1295 0 2940 1.6992 1.7608 18143 1.8624 1.9065 1.9476 1.9460 2.0224 2.0569 2.0899 2 1224 2.1516 2.1807

.e 0.0161 0 0156 7.257 3 354 9 400 10 425 11 435 12 446 13.450 14 452 15.452 16.450 17A48 18 445 19.441 60 6 6815 165 20 1181 6 1234 5 1283.2 1332.3 1381.5 1431.3 14818 1533 2 1585.3 1638 4 16924 1747.1 1802A (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1A168 1A612 1.9024 1.9410 1.9774 2.0120 2.0450 2A765 2.1068 2.1359 e 0.01'61 0 0166 0.0175 6.218 7.018 7.794 8.560 9.319 10.075 10 829 11 581 12331 13ARI 13A29 14.577 to & 68 21 168 24 269 74 1230.5 1281 3 13305 1380 5 1430.5 1481.1 1532 6 1584.9 1638.0 1692.0 1746A 1802.5 (312.04) s 0.1295 0 2939 0.4371 1 6790 1.7349 1.7842 12289 1 8702 1.9089 1.9454 1.9800 2.0131 2.0446 2.0750 2.1041 e 0 0161 0.0166 0 0173 4 935 5.588 6.216 6.833 7.443 8 050 8655 9.258 9360 10.460 11A50 11.659 100 h 68 26 168 29 269 77 1227.4 1279.3 1329 6 41379 5 1429 7 1480 4 1532.0 1584 4 1637.6 1891.6 1746.5 1802.2 (327.82) s 0.1295 0.2939 0 4371 1.6516 1.7083 1.7586 1.8036 1A451 1.8839 1.9205 1.9552 1.9883 2A199 2.0502 2.0794 e 0 0161 0 01 % 0 0175 4 0786 4.6341 5 1637 5 6831 6 1925 6 7006 7.2060 7.7096 8.2119 8.7130 9.2134 9.7130 320 h 68 31 168 33 269 81 1224.1 1277.4 13281 1378 4 1428 8 14798 1531.4 1543.9 1637.1 18913 17442 1802A (341.27) s 0.1295 0 2939 0 4371 1.6286 1.6872 1.7376 1.7829 13246 1A635 1.9001 1.9349 1.9600 1A996 2.0300 2.0592 1

e 0 0161 0 0166 0 0175 3 4651 3 9526 4 4119 4.8585 5.2995 5.7364 61709 66036 7A349 7AES2 7A946 8.3233 140 4 68 35 168 33 269 85 1220 8 1275 3 13268 1377.4 1428 0 1479.1 1530 8 1543 4 1636 7 1890.9 1745.9 1801.7 (353 04) s 0 1295 0 29J9 0 4370 1.6085 1.6686 1.71 % 1.7652 1.8071 1A461 1A828 1.9176 1.9508 1.9825 2.0129 2.0421 e 0.0161 0 0166 0 0175 3 0060 3 4413 3 8480 4.2420 4 6295 5.0132 5.3945 5.7741 61522 6.5293 '6.9055 72411' ISO 4 48 42 168 42 269 89 1217.4 1273 3 1325 4 1376 4 1427.2 14784 1530.3 1542.9 1636.3 1830.5. 1745.6 1801.4 )

1.5906 1.6522 1.7039 1.7499 1.7919 1A310 1A678 1.9027 1.9359 13676 1.9980 2.0273 j (363 55) s 0.1204 0 2938 0 4370 e 0 0161 0 0166 0 0174 2 6474 3 0433 34093 3.7621 4.1064 4.4505 4.7907 5.1289 5 4457 5A014 6.1163 6.4704:

ISO 4 68 47 16847 260 91 1213 8 1271.2 1324.0 1375 3 1426 3 1477.7 1529 7 1582.4 1635.9 18eo.2 17453 1801.2 i (373.C4) s C.1294 0.2538 04370 1 5743 1.6376 1.6900 1 7362 1.7764 1A176 1.8345 12894 1.9227 1.9545 1.9449 2.0142 ;

e 00161 0 0166 0 0174 2 3598 2.7247 3.0583 3.3783 3 6515 4.0008 4.3077 4.6128 4.9165 52191 5.5208 52219 200 a 68.52 168 51 269 9s 12101 1269.0 13224 1374.3 1425.5 1477.0 15291 1541.9 1635 4 1689A 1745.0 1800.9' (351.80) s 01294 0 2935 04359 1.5593 1.6242 1.6776 1.7239 1.7663 1A057 1A426 1A776 1.9109 13427 1.9732 2A025, e 0 0161 0 0165 0 0174 0 0166 2.1504 24662 2.6872 2.9410 3 1909 3.4382 3G437 3 9278 4.1709 4.4131 4.6546 250 3 68 66 168 63 270 05 3/5.10 1263 5 1319 0 1371.6 1423 4 1475 3 1527.6 1540 6 1634.4 1688.9 1744 2 1800.2 !

(400 97) s C 1294 0.2937 0 4365 0.M57 1.5951 1.6502 1.6976 1.7405 1.7601 1.8173 12524 1A458 1.9177 1.9482 1.9776 e 0 0161 0 0165 0 0174 0 0186 1.7655 2.0044 2.2263 2.4407 2.6509 2 6585 3 0643 3.2648 3.4721 3.6746 3A764 300 4 64 79 IM 74 27u14 375.15 1257.7 1315 2 1368 9 14213 1473 E 1526.2 1579.4 1633.3 160',1 0 1743 4 1799.6 (417.35) s 0.1294 0.2937 0 4337 05%5 1.5703 1.6274 1.6758 1.7192 1.7591 1.7964 13317 1Jt652 1A972 1.9274 1A572 e 20161 0 0165 0 0374 0 018C 1.4913 1.7028 1.8970 2 0332 2.2652 2.4445 2A219 2.7980 2.9730 3.1471 3.3205 350 4 68 92 1ES 85 27024 375 21 1251 5 1311.4 13M 2 14192 14718 1524 7 1578.2 1632.3 1687.1 1742.6 1798.9 (431.73; e 0 1293 02935 0 43G7 0.56',4 1.5483 1.6077 1.6571 1.7009 1.7411 1.7787 12141 1A477 13798 1.9105 1.9400 e 0 01F.1 0 0106 0 0174 0 0162 12841 1.4763 1.6490 l.8151 1.9759 21339 2.2901 2.4450 2.5887 2.7515 2.9037 400 a 69 05 16797 270 33 375 27 12451 1307.4 1363 4 1417.0 1470 1 1573 3 1576.9 1631.2 1686 2 1741.9 1798.2 (444.60) s $1293 02935 0 4365 0 56G3 1.5282 1.5901 1.6406 1.6850 1.7255 1.7632 1.7988 12325 1A647 1.8955 1.925C e 0 0161 0 0106 C G174 0 0186 0 9919 1.1584 1 3037 1.4397 1.5708 1 6992 1A256 1.9507 2A746 2.1977 2.320C 500 4 09 32 359 19 270 M 375 28 1231.2 1299.1 1357.7 1412 7 14M 6 1520 3 1574 4 16291 8484 4 1740 3 1796.9 (457.01) s 01292 0 2934 04334 0 5t60 14971 1 55 % 1.6123 165/8 1.6990 1.7371 1.7730 1A069 1A393 14702 1A990 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)

A.5

I Se psess. - - eI

. gese. 300 300 800 400 000 400 700 000 000 8000 1100 3300 tage gago gget e OAISI 00144 0.0174 0 0le6 07944 GHW 197M l.1992 1.3008 14093 1.5100 1 A713 1.7252 gates 33gg age 4 es.58 389 42 270.70 3M 49 1215 9 12903 33512 3408.3 1463 0 1517.4 1571.9 INF.0 3324 3738A Syggs geg6JEl o 0.1292 02983 04362 S M 57 14590 3.5829 1.5844 143bt 14769 1.7355 1.7517 1.7e59 lanes 13494 gaygg e 0.0161 Dales 0.0174 0 0186 O M 04 0.7928 0 9072 3Altt 1.1078 12023 12948 1M58 1A757 3.5647 34530 7e0 6 4024 140.65 270 99 3M 61 487.93 IMID IM56 14031 lebt e 1514 4 IM94 1474.8 1ea0 7 17372 17ss.3 l 6 03.08) s 0.1291 0.2932 0 4MO 0 5055 06889 33090 IM73 161M !.6540 11970 1 7335 17679 I SO% 18318 I M17 e 0.0161 0 0166 0 0174 0 0106 0.11704 0.6M4 0 7823 OAM9 0 9633 1 0470 1.1209 12093 IJEDS 3.3669 IA446 338 6 70.11 36938 271.07 3M 73 487A8 1273.1 1339 2 1399.1 14M.a 15114 15H 9 16221 IMS9 1735 0 1792.9 0182.) = 0.1290 OJ93C 0.4358 O M 52 0. east IA069 13484 1.5900 1A413 1.6807 1.71M 11522 3.7851 1 8164 13464 l e 0.0161 CA166 00174 0 0186 0 0234 0 5869 0 4858 01713 0 3504 0.9262 0 9998 1 0720 1.1430 1.2131 IJS25 900 4 70.37 170.10 271.26 3MA4 48733 1M06 13321 1994.4 1452.2 35M 5 IM44 1620 6 16H.1 17M.I 17914 93135)s 0.1290 0.2929 0.4357 OM49 OGast 1A659 1A311 1.5822 142H 1.6 h 2 1.7033 IJ382 13713 13028 13329 e 0A141 00166 OA174 0 0186 0 0204 0 5137 0 6000 0 3SM EM03 08295 03966 09622 1.0966 3.0901 1.1529 agge 6 70A3 370.33 271A4 375M 487.79 1249.3 3325.9 13894 1448.5 1504.4 1561.9 lett 4 1675.3 17323 1790J i p44.38) s 0.1380 0.2928 0.4355 E5647 OA876 IA457 1.5149 IM77 IAIM I.6630 1.0005 1.7256 1.7589 1.7905 12207 e 0.0161 E0166 00174 OAISS oaf 03 0 4531 05440 0.6188 04865 01505 03121 08723 OASI3 09094 1A4eg 1880 4 70.90 17036 271A3 376.08 487.M 1237.3 ISISA 13847 1444J 1502 4 IM9.4 1616.3 1673.5 1733 A 1789.0 95625) e 0.1359 OJ927 OA353 0.5644 0A872 IA259 1A996 IAM2 3.6000 1A410 3.6787 IJ141 IJ475 1.7793 12007 e 0 0161 00165 0A174 0.0185 0.0f03 0 4016 0 4905 OMIS OU50 04845 0 7418 0.7974 0 8519 0.9065 0.05S4 1300 t 71.16 170.78 271A2 376.20 487J2 1224 2 1313.5 1879.7 3440.9 1449 4 1556 9 1634.2 1671A 1729.4 1787 4 367.19)s 0.1208 R29M OA351 0.5642 0A MS 1A061 1ASSI I.5415 33883 1.U98 1.6679 1.7035 IJ371 1.7601 3J936 e 0 0181 0.0166 0 0174 0.0185 0 0203 0.3176 0 4059 0.4712 0.5282 0.5009 0 6311 06798 0.7272 0.7737 0A195 1400 4 73.48 171.24 272.19 3M 44 48745 11M.1 1296.1 1369J 1433 2 1493.2 1551A 140D.9 1888.0 37MA 17864 t

SS7A7) e 0.1287 02923 0.4348 03636 0.M59 IJ652 1A575 1.5182 1.5570 1.6096 14484 1.8845 IJ185 1.7508 1.215 e 0.0161 0.0166 0.0173 00185 0.0f02 0.0236 0.341E CA032 E4555 0.5031 0.5482 0.5015 ES336 04748 0.7153 1800 6 72.21 171.69 272.57 376 69 487A0 616.77 $279.4 13545 14252 1486.9 1546.5 1605 6 1864J 17232 1782J WOLS7) s 0.1206 OJ921 0.4344 0.5631 SAS$1 03129 1.4312 1A968 1.5478 13916 14312 1.8478 1.732 1.7344 1.M67 e 0.0160 0 4165 0 0173 OA185 0.0202 0.0235 0.2906 0J500 0.3908 04426 04836 0.5229 0.5009 J3930 RGM3 1800 a 72J3 172.15 272.95 376.93 487.56 415.58 1861.1 13472 1417.1 14A0.6 1541.1 3401.2 1960.7 1720u1 3779.7 921.*ar) s 0.1384 OJ918 0.4341 0.5626 0.or3 OA109 1A054 1A7ES 1.5302 1.5753 1.4156 3.4628 1.0876 IJ204 IJ514 e 0OMO OA165 OA173 0.0184 oaf 01 0.0233 0.2488 0J072 0.3534 0J942 0.4320 0.4800 0.5 5 7 0.5365 0.5856 3000 6 73.26 172.60 273.32 3U.19 407.53 614.48 1240.9 1353.4 1408 1 1447.1 1536.2 1596.9 1657A 1717.0 157.1 53530)s 0.1283 0.2916 0 4337 0.5621 0.6834 OA091 1.3794 3.4578 1.5138 1.56C3 1.6014 14391 14743 IJ0M IJmt e 0.0160 0.0165 0.0173 0 0184 0.0200 0.0230 0.1681 0.2293 0 2712 0.3068 03390 0.3692 OJO90 0.4259 OA529-3500 6 7457 173 74 274.27 377A2 487.50 612.08 11M.7 1303.4 33063 1457.5 1522.9 1585.9 14471 17092 1770A MSS.11)s 0.1200 0.2910 0.4329 0.5609 EEB15 OA048 1.3076 1A129 1AM6 1.5269 1.5723 1A004 1A456 14796 1.7136 e 0 0160 0.0165 0.0172 0 0183 0.0200 0.0228 0.0082 0.1759 02161 0.2484 0.2770 03033 0.332 OJ522 OJ753 3000 A 75A3 17t. SS 2M.22 37847 487.52 610.08 1060.5 1267.0 1363.2 1440.2 1503A 1574A 36385 1701.4 3M1A L

95.33)s 0.1277 0.29w4 OA320 0.5597 04796 OA009 1.1966 3.3692 1A429 1.49M 1.5434 1.5841 14214 IAS41 1.4f98 l

e 0.0100 0.0165 0.0172 CA183 OA199 OA227 OA335 0.3838 0.1987 R2301 OJ5M OJB27 0A855 E3291 R3510 3200 4 M.4 175.3 246 3781 487.5 000 4 8002 3250.9 3353.4 1453.1 1503A 1570J 14343 1808.3 IM12 (705.08) s 0.12M 0.2902 0.4317 0.5592 0A708 01994 0.9708 3.3515 1A300 1A066 3.5335 3.5749 1 AIM 1A4n I m 06 e 0 0100 0.0164 0.0172 0.0183 0 0199 0.0225 0.0307 0.1364 0.1764 0.2066 0.23M 02563 0.2704 OJ995 03191t 3500 6 U.2 1M.0 276.2 3791 487.6 008.4 779.4 1224 6 1338.2 1422.2 1495.5 1563J 1829.2 1893 4 17b7.2 s 0.1274 0.2899 0 4312 0 5585 0 6777 03973 0.9508 IJ242 1A112 1.4709 1.5194 1.5618 1.EdElf 3A358 1AG91 e 0 0159 0.0164 0.0172 0.0182 04198 0 0223 0.0237 0.1052 0.1463 0.1752 0.1994 02210 OJ411 0.2601 4000 a 78.5 1U.2 277.1 379.8 487.7 606 5 M 3.0 1174.3 3311.6 3403 G 1481J 1552.2 1619A 14851 1750A 02783 e 3.1271 0.2a93 0.4304 0.5573 04760 0 7940 0.9343 12?54 IJ007 3.4461 1.4976 1.5417 1.5812 1A177 1A516 e 0 0159 0.0164 0.0171 0 0181 0.0196 0 0219 0.ONS 0.0591 0.1038 0.1312 0.1529 0.1718 R1890 0.2000 0220B 5000 a 31.1 179 5 279.1 381.2 488.1 804.6 746.0 1042.9 1252.9 1364 6 1452.1 1529.1 16039 1670.0 1737.4 s 0.1M5 0.2861 0 4287 0.5550 0 6726 0J800 0.9153 3.1593 1.3207 3A001 1 ASS 2 1.9061 13481 1.5863 14214 00159 0A163 OftO 0.0160 0A195 0.0216 0.0256 OIO397 0.0757 0.1020 0.1221 0.1391 0.1544 0.1884 8L181 4000 & 83.7 1813 281.0 342 7 488 6 602.9 736 1 945.3 1188 3 1323 6 1422.3 1505.9 1562 0 1654.2 1724.2 s 0.1258 0.2670 0.4271 0.5528 0 6693 038M ,0.9026 1A176 1.2615 1.3574 1A229 1A748 1.5194 1.5593 19862 e

0.0158 0.0163 0 0170 0.0100 0.0193 0.0713 0.0248 0.0334 00573 0 031 A 0.1004 0.1160 0.12 5 0.1424 &l542 7000 & 86.2 184 4 283 0 384.2 489.3 6011 729.3 901A 1124.9 1281 7 1392.2 1482.6 1963.1 163R.6 3711.1 s 0.1252 0.2859 OA256 0 5507 06G63 03/77 0 89M 1.0350 1.2055 IJDI 1 3904 1A4u6 IA9M 1.5395 1.5735 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED)

A.6

l l

a = = r.s w .., !

.2 .3 14 gg g, , , , .. , ,

led

' t . " ...ff.

'~ d%/ huJj%'~ ~

'" Ab<Nll' /'/q' ~/JN -

~ dh7L4A / N//,r'y2-

/j YLX/Ae A /~ N ea%,j //r ~

~ lbNN / A/ /)*,yJ ~

~ MMDB yjMjy'y<- -l

~ /4&2W y/ . ;

%- N /2- ;

. . ~ .

///

- ' ~

ii-

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hf %, .;. 9;~

l

- ra MNn7)g

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w 7

&' w 5L/ /'<'

MMNMpy; // -

FMXW/M/?<'/ .

- MXMM/75/ .

%% wn/ -

.JNM Y/>5/ - - .. ..

FIGURE A.5 MOLLIER ENTHALPY-ENTROPY DIAGRAM A.7

PROPFHTIES OF WATER Donelly e (Ibstit')

PSIA Temp saturated 2300 2400 2500 8000 2000 2100 2200 Liquid 1000

(* F) _

62.909 62.93 62.951 63.056 62.846 62.867 62.888 32 62.414 62.637 62.846 62.87 62.99 62.774 62.798 62.822 50 62.38 62.55 62.75 62.465 62.559 62.409 62.427 62.446 62.185 62.371 62.390 60.702 100 61.989 60.568 60.587 60.606 60.511 60.53 60.549 200 60.118 60.314 57.859 57.882 57.996 57.767 57.79 57.813 57.836 300 57.310 57.537 54.342 54.373 54.529 54.249 54.28 54.311 400 53.651 63.903 54.218 63.95 54.11 53.86 53.89 53.925 53.475 53.79 53.825 53A9 410 53.248 53.46 53.50 53.53 53.025 53.36 53.40 53.425 '

420 52.798 53.02 53.065 53.09 53.265 52.575 52.925 52.95 52.99 430 52.356 52.51 52.54 52.56 52.275 52.125 52.42 52.45 52.475 440 51.921 52.14 52.175 52.21 52.41 51.66 52.025 52.065 62.10 450 51.546 51.68 51.725 51.76 51.96 51.175 51.56 51.61 $1.64 450 51.020 51.22 51.25 51.30 51.50 50.70 51.1 Sf.14 51.175 470 50.505 60.74 50.78 50.825 51.035 50.20 50.62 50.66 50.7 480 50.00 80.265 80.31 50.35 50 575 49.685 50.13 50.175 50.22 400 49.505 49.81 49.858 50.098 49.618 49.666 49.714 49.762 500 48.943 49.097 49.254 49.305 49.56 49.05 49.101 49.152 49.203 510 48.31 48.51 48.735 49.01 48.57 48.625 48.68 47.85 47.91 48.46 48.515 48.45 520 48.037 48.096 48.155 47.29 47.86 47.919 47.978 530 47.17 47.494 47.56 47.89 47.23 47.296 47.362 47.428 540 46.51 46 862 46.93 47.27 46.59 46.658 46.725 46.794 550 45.87 46.068 46.142 46.216 46.29 - 46.86 45.25 45.92 45.994 46.02 560 45.46 45.54 45.62 45.22 45.30 45.38 570 44.64 44344 44.93 45.36 44.50 44.586 44.672 44.758 530 4366 44.015 44.11 44.205 44.68 43.73 43.825 43.92 590 43.10 43.226 43.33 43.434 43256 42.913 43.017 43.122 600 42.321 42.432 42.55 43.14 41.96 42.08 42.196 42.314 610 41.49 41.35 41.483 41A16 42.283 40.950 41.083 41.217 620 40.552 41.44 630 39.53 40.388 640 38.491 39.26 650 37.31 38.006 660 36.01 36.52 670 34.48 34A98 680 32.744 32.144 690 30.516 I TABLE A.6 PROPERTIES OF WATER, DENSITY

.g

A.8 \

n

5. THE3P-' 0F NUCLEAR POWE? SLANT OPERATION. FLUIDS, AND PAGE 19

'4EoM0'; .4*ICS ANSWEPS -- TUPKE( POINT 38a -86/04/28-DEAN, W M AP9WER 5,01 (1.00) d REFERENCE' FNP FSAR CH 15 Westinghouse Accident and Transient Analysis, pp 4.21 EPE-009; EK3.11(4.4/4.5)

ANSWER 5.02 (1.00)

C REFERENCE Westinghouse Peactor Physics, pp. I-5.2 - *5 .

Westinghcuse CNTO 'Reacter Co c Control' pp 1-1"'2?

001/000 V5.26(3.3/3.5)

ANSWER 9.03 (1.00i i

REFERENCE .

EIH' L-PG-606, pp 4 Si T:9 4 BSEP: 02-2/3-A, pp 177 - 180; O2-0G-A, pp 60 - 61 0FNP Xenon and Samarium LP, pp 5, 6; RO 84/03/05 Westinghcute Nuclear Training Operations, pp. I-5.77 - 'o T u - '<. e y ooir t- Reactor Core Ccntrol, pp. 4 34 001/000-K5.13 (3.7/4.0)

ANSWEP 5.04 (1.00)

C REFERENCE IIH: CPNT,Vol ')II , Chapter 1^.1-83-86 BSEP: L/P O2-2/3-A. pp 172 - 176; 02-0G-A, pp 57 - 60 Westinghouse Nuclear Reactor Theory, pp. I-5.77 - 79 Turkey Point, Reactor Core Control, pp. 4 28

5. THEORY OF NUCLEAR POWER *LANT OPERATION. FLUIOS, AND PAGE 19 ANSWERS -- TURKEY POINT 3&4 -86/04/28-DEAN. W M 001/000-K5.13 (3.7/4.0)

ANSWER 5.05 (1.00) e REFERENCE TPT 1985 Requal Cycle I Lescon Plan, " Core Life Changes' 001/000; K5.ao(3.4/3.7)

ANSWER 5.06 (1.00' c) EOL (+.5 es)

'3 ) Stesmline 9reak REFERENCE TRT TS S3.2-1 001/050; pug-5(2.9/4.31 ANSWEP 5.0/ 12.00)

1) Higher (Tavg increases edds negative reactivitv)

2) Lower (Tavs decreases due to cold feedwater addition) -

3) iJ o effect

2) Higher (Xenon concentration increasec adding negative reactivity)

REFERENCE NUS. 'J o l 3, Unit 11 Westinghouse CNTO 001/000 M5.29 (3.7/3.9) a K5.38 (3.5/4.1)

ANSWER 5.08 (1.5^$

a. , DECREASE (+0.5 es)

5. INCREASE e, DECPEASE L

~

5. 'HEORY OF NUCLEAR POWER o' ANT OPERATION, FLUIOS. ANC : AGE O

--- i iE R 6 5 s s iC i------------------- - ~ ~ --- ~ ~ ~ ----- - ~ ~ ~

A f4 5'-ER S -- TURKEY POINT 384 -86 '0 U 20 -0E AN , W n REFE ENCE Gever31 ohysics, HT ' FF' PP. 319 - ?34 App A: Centr. Pump il h a r a c es. Ficw (2.6/2.6)

ANSWER 5.0c 't.504

2. Decreases (0,5)

b. Incretter (0.ii

c. Increaaes (0.5)

REFERENCE

'urkey Point. Thermal-Hydraulic Principles and Applications, pp. 10 61 App. A: NOSH ( 3. U3. 6 )

ANSWER 5.10 ('.50)

a. _n2 egative (0.5)

. - . Lies negStive (0.5)

. _ess negati,e (0.5)

REF,ERENCE

'or t ey oo :. n t . Reactor Core Control, Chapter 5 F13 SNP-RF-9 ,

004enec: t(5.06.3.0/3.3)

A N G 'E R 5.11 ( .50)

It reducec vec=a' f'"once (+.5) &nq4- ebrt axw.M f aua;3tus , c'9, M3 b' M ,

REFEPENCE M W So.d G.Op'h ' Of E#"" g

'07 Requ21 Cycle I 1985 lesson plan ' Core Life Chan.3es' ge oM)

5. THEORY OF NUCLEAR o0WER P!_ A N T OPERATION, F UIDS. AND PAGE 21 ANSWERS -- TURMEY POINT 3i4 -86/04/28-5EAN. W M ANSWER 5.12 (2.00)

a. Establishment of reverse flow (0.5)

b. Less pressure drop across core (due to less total core #10w) (0.5)

c. No longer transfercing heat into S/G causing ecoldown/ contraction of water /stean. in S/G (0,5)

d. Increased delta T in apariting loop (with approximately constant Teold) (0.5)

REFERENCE Turkey Point, Thermal uydraulic Principles and Applications, pp. 12 18 003/000-K5.02 (2.8/3.2)

-MS.03 ~3.1/3.5)

-K5.04 (3.2/3.5) 000/015-04.1.02 3.d 1 -

ANSWEF 5.12 (1.00)

Because rod worth is prcportional to the ratio o* +he fluy at the tip .

of the rad to the average l o v 'O.7). A change in power do?s not significantly ch:nge thic ratio (0.3). (1.0)

REFEFEUCE Turkoy o: int. Resctor Core Control, Chsster 6 001/000; RS.02(2.o/3.4)

ANSJER !.14 (2.00) a) Delta T will increase (+.7) as Thot goes up due to boiling in the core and Teold remains fairly constant (+.3) b) Teold will not follow Psta. (+.7) as Pstm decreases due to boiling off in the S/G and Te ren.ains fairly constant (+.3)

REFERENCE 5 Westinghouse Mitigating Core Damage, pp 1.15/16 EPE-017; EK1.01(0.4/4.6)

4. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 22 A N 5!4 E P S -- T U R E Y POINT 3&4 -86/04/20-DEANr W M ANSWER 6.01 '.1.00) d REFEFENCE FNP, Tav3, Delta T, and Pimp, pp. 23-25 VEGP. Training T e:: t , Volume 6, p. 63-27 Turkey Point, ,PI SDr '

p. 15 001/000; l' 5 . 0 4 ( '4 . ? / 4 . 7 )

A N S'4 E P 6.02 (1.00)

=

REFERENCE

'orkey Point, O r a v i n g 5 610 - T '_1 Sheets OA and 98 064/000: F 4 O '5 f 2 . 9 / 3 . 2 i A N 5 'J E 0 L , ') '3 ('_ M '

d 9ETEPENCE Turvev Point. SDC3 SD, pp. 2a9 041/020t M4.14'.2.5/2.8)

A N S 'J E P o,04 (1.00) d 9EFERENCE i Turkey Point, Requal Lesson Plan, RCP, Fi3 16 003/000; K1.12(3.0/3.3) o

6. oLANT SYSTEMS DESIGN. CONTROL, AND INSTPUMENTATION oAGE 23 ANSWERS -- TURMEY 001NT 314 -84/04/28-DEAN, W n ANSWER 6.05 (1.00)

a. 6 (0.25)

b. 6 (0.;Ss

c. 1 (0,25)

d. 6 (0.25)

REFERENCE WSN. LP - Rod Control S */ s t e m . pp. 5 & 9 CAT. PSM-IRE Turk e / Point. Rod Control SD 001/A00-V4.^2 (3.8/3.8) t.S ANSWER 6.0e ->

i )

1. I. c. e , 8;d. (M( -tr)

2. ? 'O.25)

PEFERENCE Turkey oo i n *, 7 Pequal Lec1on c'12n. AFW. p. 1.- d 18 0e1/000; 04.06(4.0/4.2)

ANSWEP 6,07 (2.00)

1) Oeference St3nal #or comparison with 2ctual ste2m #10w (+.25 ee) 2? *-13 (input to P-7)

3) C~ Icte rm c ;mp load rejection c o r: t r e l l e r )

41 S/G 1evel orogrsmme-

5) C-5 IsteIm dump r a te module)

6) Rod C o.n t r o l

< ~) o-2 -

15% rod stop)

9) N r 'c i. n e Load Limit O u r *- = O.

" C.r E ;:E 'IC E NCRODP 30.1, ' Main Steam 1vstem' TP7 SD127, fig 7 045/000; M4.10 '2.4/z.' ' vc 12(3.3/3.6) 041/020; e4 11(2.8/3.1) *

>i2'000; K1.06(3.1/3.1) l l

$. otANT S(grEMS OE5Ir,N. coniggt. Ang IngrpUt1ENTATION :. . c q

. ;i ANSWEPS -- T'iP':EY DOINT 3 !. a -96/Od/28-0E:N. W M ANSWEC' 6 . ') 8 (1.50) 3 i. CCW uEts (3) ...:

. +i c r_ u H. r. v. . _- (7)

m. e. '..

3. Lube u ster System ( 0 . '. i

~

b. 1. C 9 - 2 ~' 0 '. (TPCW HEX Ot. 'et t emp Control " alvei '0.ar

2. Clcanc ( 0 7)

3. L11cs Ill ICW to -

directsd tc CCW WIYs (for cooll13 of vitsi safegestd egotpunt' 3) r c_ r r o r y r e_.

= -

'.ic!e, D o t r, ' , 0-qual ' . e : -' n ~13n. ICWS. pp. 4 2 10

, _ , . ,,, , =_ c c_, -. r_. . ._r,

cmys m

c. o w e,. n, :

x v8 . n, n. <. q_ . a m.., _' s . r., t. ,s . va /m,.s . 9 )

c ;!3 .: c u 5.0o # (*

ei SI ovmps ; ,d the Ecric Acid Evrearetors

' (* 25 esi p15 5 ~l, Emergenes contain nr ' ' -ler p avt'at r_ ,

valves ..

aqr < _ '> c q -g,

-T sea 0 pp 3. g EOE-C~.6:EM3.02(3.6'3.CT .s n d 008/000*Kl.02(3.3/3.4) -

ANSWEC 6-10 ( .50) l Les, o# 2r #10w +a r o '_i g h f ilter (low flow) (0.5)

REFEOEFCE Turkey Point, CS SD, P. ? 2nd Fig. 4 0 2' 'OC O : A2.01(3.0/3.3)

I

{

i l

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6. S'_. AN T SYSTEMS OESIGN , CONTROL. AND Dis rPU~ENT ATION P A r, E 25 ANSWERS -- TUPKEr POINT 314 -26104' 8-0EAN. W h ANSWER 6.11 (1.50)

ANY CIVE AT O.3 DOINTS EACH:

1. Group Step Counters

2. Internal temory and alarnis

3. P to A convrrtert

4. ::ank Over'cp Counter 5 Slave Cyclar

. Mu ster Cveler REFERENCE

'orkey Point, Requal Lesson olin, RPI. p. 21 001/010: K6.0e(3.6/3.7)

ANSWER 6.12 (2.00)

1) Openz 311 breckers feeding e qi.i i p va n t from tF bus '+.25 e=>

2) Ooens all dMV feeder oraeers

2) Ohsens valves to EDG cr2-3ing air motors [d M S Q Q y,<;7pg7 g yS N

4) BlockI n o . - s a f a '. y loads from being sequenced S) ? loc! 2 aute-start f Tur'o ine Gener ator A u '- 01.o nP .Y.. eh 2. W[,Lg a. g g g 6 ) . P l o c 'r : auto-statt of C' u pumps on low heeder pressur_( ta^

g }- M, 7i Opens steam supply valves to AFW pu m p s (4MGA/ pours) .

9i " rips EDC generetor breder (if diesel it supplying the 4KU bus)

?ECEOENCE

- c. - a...

en 7n.. , . ,,, .,.4.,

06 0'000; R4.'.0/3.5/4.0)

ANS4ER 6.13 (1.50)

-S/C Oress used for density compensation of ; team flow, so i f precsvre fails high, steem flow input to the SCWLCS will increase (+1.0)

-W3'Wf will cause FWRV to open, level will increase untti level error counteracts th? steam flow / feed flow mismatch (+.5)

REFERENCE NA NCRODP C3.12 'SGWLC and Protection

TPT SD11, pp 25 Fig 1?

035/010: A2.03(3.4/3 6)

s. :t 4a? 9 ' c T c

3 O E S I G '1. CONTROL, A r20 INSTRUMENTATION : AGE ff ANSWERS -- TOP'Er C G IrJ T 214 -86/04/28-0EAN. W M ANSWER 6,14 <1.00)

~

5 , op'n: (0.2). ^- ~-

- ';- 'A

~i pres gre d rep; ( . M c t0 Yd C rI;t n t gel ly c1 7ses 2]&at2000f'p513 (0 2)r ;' 0 =-

C'J Preft4 w 30 -

gg a,a r ' feg/ - '_ nkg '~

/M)

REFEREM: I T u r '< r/ ocint. PZo c3 F:.g. 25 010/000; K 3 A ' ' 3 8. ' 3. 9 )

/

ANsuER 5- < .00,

i e s .nt .n h: t s t a r.d h t/ +' o - 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months and cooldown to 350 de,rees. ~

(0.5)

! ,at s+rnebv e 2 m2:nt r r 23 hoizr s . (0.5)

n. c wqnc.

T .r u- P a i ra - ?< qual L e-I s o n P'sn. Acu. p.

~

02 ,, : cuc. reg,3e4,1s

'g.O . f,f(Al* W icoaoou w"* (.:,rrte.f a3Sen/ %

t(q ( a w n. w AyutL full V 4 fie p @rZ&& l

~

pmW 4 I pe,gv qSrc op. &dG & .

W cnAA cusW % e y umvom Mot & h40 S M c d L M f.sti p4444aa 4 -

a inoa p q $6tra & etow> PA'w on1% aM wt afis gx grup.s ,

M'Y I

l._.____.-__.__.._ . . _ . . . _ _

. . . .. ,,..__,m. , , , . . . _ _ _ . _ ,_ , _ . .

7

-' CCEDUPES - NOPM AL . A 8 t> 0 P M A L . EMERGENCY AND c , r. 27 R A D IO'_0 0 !C 3 '- " '3 " T R O '_

AN5WERS -- TURME( POINT 2 ?. 4 -3e/03/2G-DEAN. W M ANSWER ~.01 ( 1 . 0 0

_m REFERENCE EOP-E-0 P'!G - 11 ; t erforming I:u e d i a t e Actions (4.3/4.4)

ANEWER 7.02 (1.00) d RECEPENCE Westtoghouse 5:s:Pground Info t' o r ECA-3.1, pp 32 E :' E -- 0 3 9 : :K ? . 06 ( 4. 2/ 4. 5

~

ANSWER C' 3 '1 00) a REFERENCI TPT A0r 0103.4 Pp 13-15

c. u g _. . : : Tagging /O'e2 .ances(3.6./4.0)

A *J 5 V E : '.04 '. 1 . 0 0 )

-SCP canel 2!out to empty (+.25 ea)

-SFP approaches high level M f d6

-SFP Wi 3h ' ems M)

-SCP level decreases while the canal level is changing REFERENCE TPT GP 16125.4, pp 2 034/000; P!4 G-3 ( 2. 3 / 3. 2 T l

7 re0CEDURES - NORMAL, ABNORMAL- EMERGENCY A rid CAGE 29

~

~~~~65D50LUUEC5L~CUUUUL ANSWERS -- TURKEY P O I tJ T 3a4 -86/04/28-DEAN, W M ANSWER 7.05 11.50) a) NO (+.5 ea) b) YE5 c) NO REFERENCE TPT E0P-F-0 CSF Status Trees PNG-10: EOR Entry Level Condi+1ons (4.1/4.5)

ANSWER 7.06 i1.00i FRGs are uritten on the premise that 3+ least ene A/C Emer3ency 90s is ener3 i red.

REFERENCE Westin3h ouse Back3round Info for ECA-0.0 E:'E-035: E 3 . 0 2 ( 4 . 3 / 4 . 6 )

AHSUER ~.07 .1.25) a :' ? tem oosttien (&.25 er

cosition indicator low indiration 7 %A gg wpQ b) 00 not che rr 3e the valve position (+.25) and notify your supervisor (+ 25)

REFEFENCE TPr ADM 0103.4, pp 2/3 oWG-13: Valve Lineups /Verificctions (3.7/4.0)

7 PPOCEDUPES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 29

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

R DIEL55iCit-C5sTR5t ANSWEPS -- TUFMEY POINT 3&4 -86/04/28-DEAN. W M ANGWER 7.0E (1.50

-FW Control Valves checked closed (+.3 ea) cw Bypsse yglves .

-S/G Slowdown Valves * *

-S/C Sample Iici Vlv '

-CLOSE FW Isolation Valves REFERENCE TPT E0P-E-Or pp 5 EPE 007; P 'J G - l l ( 4 . 4 / 4 . 5 )

A tJ S W E R 7,09 (1.00)

Turbine tu tripped se that the heat sink will be "saintained 33 long as possible (+.5) on a tots 1 loss of feedwater AT ~ (+.5)

RE3ERENCE Westinghouse B ackground I r. f o or FP-S.i. pp 7 ~s/77 EPE 020; EM3.12(4.4/4.7)

ANSWER 7.10 (1.20) .

-Return assembly to core end leave it latched (+.3 e?)

-Move ' vel "fer car to the SFP

-Close the f v -e l "fer canal gate velve

-exit containment REFERENCE TPT OtanF 33 27 pp 5 EFI 026; PWG-ll(4.1/4.3) l l

1

7 OROCEDURES - NORMAL. ABNORMALr EMERGENCY A N FAGE 30

~~~~Ed656[UU55d[~CUUTEU[~~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- T U G: KEY POINT 32.4 -86/04/28-DEAN, W M l *d ANSWER 7.11 -

R-2 (Containment Operating Floor- 58' level) (+.25 ea)

R-7 (SF Bids Xfer Canal Aree- 58' level)

--19(5F Bldg Exhaust Duct)

R-21(SF Eld : North Well)

- - ~ ^ P:5 '

.f-, -r~

g *4 hk M MM S# 7/

REFERENCE gbel N Mf k N

TPT OP 16002.3 pp 8/9 M %#^' -forW c* A erron#"3 fifA1-072/000; PWG-7(2.9/3.2) N ANSWE7 7.12 (1.50) if runba-ce has not o c c u r r e .-; . tun turbine becL +

.- 707 (*.6) put rod control in manual 6 * . 3' centrol Tavs and Tr e# r'ig toron (+.6)

REFERENCE ror gNoo 1608.1 pp o/10 EoE 003; OWC-11(4.2/4.4)

ANSUER 7.12 (1.00T top ?iy SFO Fump in service ( + . 2 5 4-r.J Isolate ir leakage sources by shutting DI water makeup valve (3-821)

SFP Heat Exchanger Outlet (3-820)

SFP rilter Common Outleb (3-7988)

(~ +*l f [cr U S ,+ N O la f~I500 A ^

REFERENCE Muhad TPT ONOP 033.1, pp 5 034/000: PWG-11(2.0/4.1)

~. PROCEDURES - NORMALr A8 NORMAL, EMERGENCY AND PAGE 31

"~~~~~~~~~~~~~~~~~~~~~~~

~~~'kI656[6G565(~C0556L ANEWERS -- TUPUEY POINT M4 -96/04/29-DEAN. W M ANSWEP 7.14 (1.50;-

Thi: is becauce you could be in E-3 without an intact S/G (+.5) such that feed flow me/ be throttled aelcw the minimum (+.5) to prevent either S/G overfill or ors overcooling '&.5) .

REFERENCE

'4e s t i ngho u s e ?ackground In#o on SI Termination /Reinitiation. pp 5 EPE 00C; EA2.34(3.i'4.2>

AN3LCP 7.15 (1.30)

? asis: reduces the potential for steam bubble formation in the top of the U-tube- ( + . 7 '+ when tne FCS is ti e p r e s s i r i ~ o rd (+.3)

'he PPR ayatem trjec' ion .S 1 to the cold lags id return is from the hot leg: IF.3: 'RWP will not f'% through the S/Gs' WFERFMCE

^:' i' E0P-ES-C.2 pp 9; W5m'inghom_e E' a c k g r o u n d I- #o for EG-0.2r pp 54 EcE-c'a: E r 3 .11 e. : n'2 o,

l l

8. ADMICS'R ATI'.'E PROCEDUPE'i . CONDITIONS. ANO '_InIT A TIONS PAGE 32 l A.'4SWEFS -- TUFFEf 0 0 I'J T 214 -96/04/28-0EAN. u e l ANSWEP 3.01 ( 1. n 0

3 REFERENCE McG. Station Directive 3.1?- p. t and 10CFR50.72(b)

Cat. Station Directive 2.8.1 p. 6 of enel (2) and 10CFR50.72(b)

CNP-0-EIP-26.0- pp 8 T:T Ao 0103.'2* 10CFR50.72(b:

WG-2: Noti foing off plant personnel (2.8/3.8) {

-1.i ? U E R 3.02 1.00)

DEcG r.EE NA .t2 vs 2.4.4 Toi TS 3.1-12 010/000: A2.03 ( 4 . 1 / 4 . 2

ANSWEP e.03 (1,06-

-) TRUE (+.5 ea)

I c) TRUE -

REFERENCE tot T9 93.0.1, E3.0.5 PWG-5: TS Mnew19dge(2.9/3.9)

ANS9ER 8.04 (1.00)

-use fSg pattern only ('.5 ea)

-must be 10 feet er more from any energi:ed electrical equipment

- d.ur:

REFERh'+NCE- ofx terawaOG oxMm TPT EP 20107. pp 2 P!J G-17 : Cite protection rqmnts(3.4/4.2)

I

_ _ _ _ADMINIS

?.

_ _ _ _ _ _:_'ATIVE ;_ _ _ _ _ _________________

CONDITIONS- AND LIMITATIONS

_ _'R O C E D________

U R E _______

S.

oAGE 33 A tJ S N E R S -- T'JOFEY POINT 3d4 -86/04/29-DEAN, W M ANSWEP 8.05 t 1.00 3: 3: 3: : (+.25 ee)

EEFTRENCE TPT TS 3.4.4/3.4.5 008/0301 PWG-5(2.9/2.')

ANSWER 8 06 (1.50) r/ WP D e p .r r +, m e n t Supervisor (+,5 ea) b- 2750 arem c) Airborne concentr.?t en: e".ceed 25". of MPC for anv isotope

c. e c e p e u1>L e_

._.m, .

'c" H e' sanosir p r- 22- 32-h cus-15: Facility R Wcan?.3/2.C') .

~

(.g 6 \ (.kW8 ANSWR 3.07 (i.50) a) : ammbers #

or r4L.3 75C /LAcrt6 Off

< Ph-(+.5) one of wham-is 590 licensed

(+ 25) b C75C Log (+.25 ea) -

wor k i:.3 : a p :-

'ocedures group (fcr transmittal tc the PNSC)

R.e e e_ r.s e r. kc e_

TFT :: 010o.3 pp 6 e PWG-21: Controlled c rocedures(3.8/4.1)

ANSWER 8.08 (1.00) e NPC Operations Center in Bethesda, MD (e.5) b) Outy Call Supervisor (+.25 ea)

Vice Pres: dent of 90 clear Ops (or his alternate)

REFERENCE h TPT AP 0103.12, pp 2 s

8. ADMINISTR ATI')E PROCEDURES , CONDITIONS, AND LIMITATIONS PAGE 34 ANSWERS -- TURKEY POINT 77.4 -96/04/28-DEAN, W n PWG-36: E-Plan (2.9/4.7)

ANSWER 8.09 (1.50)

1) B EDG is tested (dallvi (+.5 es.)

2) B EDGs associated ESF 2re OPERABLE on both units

3) Either S/U XFRMR is OPERABLE REFEPENCE TPT TS 3.7.2(b) 064/050: PWG-5(3.1/4.1)

(1 *)

ANSWEP 9.10 W NWE (*.3 for individual. +.2 for order)

E U ..- :c. r'-+ :' . [w; 2 o 1 RCO on shift REFERENCE TPT EP 20101, pp 3 PWG-36: E-PLAN (2.9/4.7)

ANSWER 9.11 (1.00)

1) Hot Ring Down Telephone (+.25 eai

2) JAWAS

3) Commerciel Telephone

4) Local Government Radio PEFEPENCE TPT EP 20101, pp 31 PWC-36: E-PLAN (2.9/4.7)

8. ADnINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONG PAGE 35 ANSWERS -- TURNEY COINT 3d4 -86/04/28-DEAN, W M ANSWER 8.12 (1.50) an Unit 3 PCO (+.5) b) Not resulting from plant testing (+.25 ea for any d)

Not under investigation Not correctable Requires e PWO to correct Pu.m31ns in effect for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months REFEPE4CE TPT ;? 0'03,2 pp 20 FWG-23: Etsff Activities (2.2/3.5)

A N S W E .C. 8.13 (1.00)

Entry lato an Operationsi Mode may be made '+.54 even if the conditions for en LCO are not met (+.5)

OECERENCE ror T9 3.0.4 PWC-5: -S Mnewledge(2.0'3.9)

ANSWER 8 14 (1.50) -

-one unit at cold shutdown (+.3 ea)

-one unit at power

-LOCA on the operating unit

-Loss of off-s te power

-one EDG catl to load REFERENCE TPT J5E-L-86-59 EPE-056; EK3.02(4.4/4.7)

S. ADMINIS TP A TI'!E o 0C EOU; E2 CONDITIONSr AND LIMITATIONS PAGE '36 ANSWERS -- TURREf POINT 334 -86/04/28-DEAN, W M ANSWER 8.15 (1.00)

With T e m p e r a +,v r e ".~ 0 0 de3rees. the release of activity to the environment due to I SCTR in precluded * .7 ) since Psst is SG PORV lift setpoint(+.9)

REFERENCE T :* r TE B3.1-6 00^/020: P W G '5 ( 2 9.' C .1 )

I

ACCELERATED REQUAL I NRC TEST RESPONSES SECTION 1 NM4 RO QUESTION 1.09 SRO QUESTION 5.12 Referring to Figures S-27A and S-27B, answer the following questions concerning a loss of one RCP transient from 22% power without a reactor trip.

a. Why does loop 2 RCS flow increase at point 3?

b. Why does loop 1 RCS flow increase at point 2?

c. Why does loop 2 S/G level decrease (shrink) at point 4?

d. Why does auctioneered high Tavg (operating loop) increase at point 8?

RESPONSE

b. Please accept as a response to part (b.) a typical pump curve for parallel centrifugal pumps with an explanation of how the system resistance curve shifts upon loss of one pump.

REFERENCE:

CNTO The:7no Book II Page 10.46 total page explanation with graphic examples.

1

0L2-3:dsp:04/30/86 Page1

f.CCELERATED REQU AL I NRC TEST RESPONSES SECTION 1 RO QUESTION 1.10 Over core life there are TWO major changes that affect the doppler defect. List these TWO effects, indicate how each affects the doppler defect, and indicate which is the overriding effect. Assume present core cycle.

RESPONSE

During recent training of operators by Westinghouse, instructors gave 4 factors affecting Doppler Only Power Defect over Core life

1. Burnup (of U238) and Conversion (Pu210)

2. FuelPellet Densification

3. Change in Helium Gap Thermal Conductivity f 4. Clad Creep Item 1-3 were considered to make Doppler Only Power Defect more negative over core life.

Item 4 will make Doppler Only Power Defect Less Negative.

After initial core load Items 1-3 will be overriding factors. We request your answer key be changed to accept this response as another acceptable answer.

REFERENCE:

CNTO Reactor Core Control for PWR's Page 2 2-48. (This reference is for initial core load only)

0L2-3.dsp:04/30/86 l' age 3

ACCELET a ; > .)11EQUALI NRC TEST liESPONSES SECTION 1 RO QUESTION 1.12 Referring to Figure 115, what causes the leveling off of the critical boron concentration efter the initial sharp decrease?

RESPONSE

There seems to be perceived ambiguities on this question. Two trains of thought were exhibited during the exam. Depending on the students point of reference (see drawing) their answers were different.

Point 1 - One group assumed the question wanted to know why the sharp drop stopped and began to level off. The correct answer for this assumption would be, "the result of the build-in of Fission Product Poisons".

Point 2 - This answer reflects the intent of the question.

We request that both answers be considered acceptable for the answer key.

i

REFERENCE:

)

Marked up copy ofNRC Figure 115.

l I

I l

l l

ftOL2-3:dsp:04/30/86 Page 2 4

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i 0 s i s o e m is SURNUP (SWD/MTU)

FIGURE SNP-RF-14: CRITICAL BORON CONCENTRATION CURVE (REV 2)

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

ACCELERATED REQUAL I NRC TEST RESPONSES SECTION 2 RO QUESTION 2.02 Referring to provided Figure 200, indicate whether the following valves receive an OPEN, MODULATED, or CLOSED signal for the given makeup mode selector switch position. 6 Assume start signalis present.

c. 114Ain AUTO (when making up) -

b. 113B in DILUTE i

c. 114B in ALT DILUTE

d. 114B in BORATE ,

c. 113Ain OFF

RESPONSE

1 Valve position of 113A is to be closed when the Reactor Control Makeup Selector, as opposed to Mode Selector Switch, is in the off position. Question references Makeup Mode Seleckr switch which has no off position. All operators assumed the switch referenced was the Reactor Makeup Control Switch

REFERENCE:

5610-T-D-19

OI,2-3:dsp 04/30/86 l'a ge t

ACCELERATED REQUAL I NRC TEST RESPONSES SECTION 2 RO QUESTION 2.03 SRO QUESTION 6.06 Match the AFW T & T valve overspeed in Column A to the reset location or condition in Column B. More than one answer may be correct for each. ALL correct answers are required for full credit. ,

Column A Column B

1. Electrical a. Reset from Control Room j

2. Mechanical b. Auto reset on bus stripping

c. Auto reset on auto AFW start

d. Auto reset when speed decreases

e. Resetlocally ,

RESPONSE

1. Electrical The initial assumed condition for the start signal was an auto start present. In this condition all choices would be correct with the possibility oflocal reset if the remote ;

local key switch was put in the local position.

REFERENCE:

SD #117

a. page 15

b. Page 17 and Figure 7

c. Figure 7

d. Page 16 and Lesson 73, Page 5

e. Page 15 .

0L2-3:dsp.04 /30/86 Page 2

/. to .iCRATED REQUAL I NRL TEST RESPONSES SECTION 2 RO QUESTION 2.05 Excluding vibration alarms, list SIX Control Room alarms that would be DIRECTLY indicative of abnormal operation of the RCP seal assembly.

3

RESPONSE

Please accept as an additional answer RCP Pump or Motor High Temperature (H 9/6) for indication of seal package trouble. Low seal leak-off flows could cause high pump bearing temperatures which could be indicative ofimminent seal package trouble.

REFERENCE:

ONOP 0208.10, Page 10 i

l l

I l

l

0L2-3:dsp:04/30/8(i Page.1

~

ACCELERA iu .EQUALI NRC TEST ret ,PONSES SECTION 2 RO QUESTION 2.08 SRO QUESTION 6.09

a. At what two points can UNIT 3 and UNIT 4 CCW systems be tied together?

b. Besides starting 2 CCW pumps, what valves associated with the CCW system ,

reposition on an "S" signal?

RESPONSE

Accept for part B as an answer "open outlet valve" only. During normal operation -

alignment of the ECC/CCW systems for modes 1 & 2, inlets and bypasses are maintained open.

REFERENCE:

5610-T-E-4512, Sheet 2 SD-040, Figure 3

0 L2-3:dsp-04/30/86 inage4

ALCELERATEDIW(w, NRC TEST RESPONSEt'.

SECTION 2 RO QUESTION 2.11 SRO QUESTION 6.15 What are ALL the design bases of the minimum level requirements of the condensate storage tank?

7

RESPONSE

Accept as an additional answer to Part 1, " Maintain Hot Standby for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months and cooldown and go on RHR". Normal terminology of operations personnel equates 350*F and going on RHR as being synonymous..

SOURCE:

T.S. Bases 3.8 k

i l

l i

i

01,2-3 d-p 04/30/86 P.u:e 5 i

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

~

ACCELlm .1 ED REQUAL i NRC TEST RESPONSES SECTION 2 RO QUESTION 2.12 Describe the source and flowpath of power forom the vital MCC to 3P07 (Vital 120 V Instrumentation Bus A) for the following conditions. Provide buses and major components (transformers, switches, etc.) in your description. It is not necessary to include breakers.

a. Normal AtPower Operation

b. First alternate for loss ofinverter 3A

c. Inverter 3A has been out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

RESPONSE

Accept answer of major components and voltages for flow path to vital AC panels. Normal and off-normal operations of vital AC equipment and alignment are executed with procedural guidance in hand with no memory extracted line up.

i

0L2 3:dsp 04/30/86 15 ci c l

~ '

ACCELERATED REQUAL 1 NRC TEST RESPONSES SECTION 2

~

RO QUESTION 2.14 i

List the THREE functions of the Normal Containment Ventilation System.

RESPONSE: ,

Accept answers according to System Description #29 and FSAR Volume 3 Section 9.10 due to multiple sources ofinformation available for this question.

REFERENCE:

FSAR 9.10-1 l

01.2-3 dsp.04/30/86 l'. ige 7

~

ACCELERATED REQUAL I NRC TEST RESPONSES SECTION 3 RO QUESTION 3.10 Indicate whether the following valves / components receive a "S" (Safety Injection), "T" (Phase A Isolation), or "P"(Phase B Isolation) signal. Only one answer is correct for each valve / component.

a. Containment Sump Pump

b. Letdown Line Isolation Valve (SV-204) -

c. Pressurizer Heaters, Backup Group A

d. RCP Seal Return Isolation Valve (MOV-381)

e. Containment Ventilation Isolation

RESPONSE

Your question stated "Only one answer is terrect for each valve / component" which is not entirely correct.

I We re. quest you amend your answer key to accept the following answers .

a. We request that you accept answers "S" or "T". The "S" and "T" signals will prevent the pumps from starting and will stop the pumps if they are running.

d. Any Automatic SI signal ("S") will generate a Phase A ("T") containment isolation signal. Based on this information, MOV-381 will close if either an "S" or a "T" signal is generated. It is the "T" signal that actually causes the valve to close. For this reason, we request that you accept "S" or "T" as correct answers or change the answer to"T".

e. We request that you accept answers "S" or "T". Any SI signal ("S") as well as a manual Phase A ("T") containment isolation signal will give you containment '

ventilation isolation. ,

i REFERENCE.

a. 5610-T-L1, Sheet 24 A 5610-T-L1, Sheet 11 l 5610-T-E-4518 Sheet 2

d. 5610-T-L1, Sheet 11 i l

5610-T-E-4505, Sheet l p

e. 5610-T-L1, Sheet 11 l

l

0 L2-3:d sp-04/30/86 l'.c 1 !

~ '

m 'LER ATED REQUAL 1 NRC TEST RESPONSES

, SECTION 3 RO QUESTION 3.14 List ALL the interlocks that must be met before the RHR suction isolation valves (MOV-750 & 751) can be opened.

. RESPONSE:

The setpoint for the high pressure closure has recently been changed to 525 i 10 psig.

Please amend your answer key to reflect this change.

REFERENCE:

I OP 0202.1 Page 2 ' Note' following Step 4.3.2 l

1 i

0L2 3.dsp.04/30/86 P. ige 2 '

ACCELERATiaL ..juALI NRC TEST RESPONSES SECTION 3 RO QUESTION 3.17 SRO QUESTION 6.14 With the reactor at 75% power and all primary controls in automatic, pressurizer pressure transmitter PT-445 fails high. Assuming no operator actions occur, describe the response of the pressurizer pressure control system. Continue description until pressurizer pressure ,

, is stable or a reactor trip occurs. Include all applicable setpoints.

RESPONSE

The question asked for response to high failure of PT-445. Many students gave the same answer the answer key did. However, other students gave the correct response reflected in Pressurizer and Relief System S.D. 9 Figure 25,instead of the response for a high failure of PT-444. We requestyou amend your answer key to accept either answer as correct.

Our basis for asking for either answer is that during the exam several questions were asked in reference to this question. Their questions were answered by the examiner based on your answer key,

REFERENCE:

SD 9, Figure 25 J

COI.2-3 dsp 04/30/mi l'a ge. 3

ACCELEIL'. LED R hyUAL I l NRC TEST RESPONSES SECTION 4 i i

RO QUESTION 4.01 Which of the following statements describes the correct usage of the Critical Safety !

Function (CSF) Status Trees while performing FOP-E-O " Reactor Trip or Safety Injection'?

I

a. The CSF Status Trees are NOT monitored until EOP-E-O is exited. ,

b. Awareness of Red Path criteria is required at all times, but the CSF Status Trees are monitored only after it is determined that SI can NOT be terminated.

c. Monitoring of the CSF Status Trees commences as soon as the immediate action steps are completed.

d. CSF Status Trees are required to be monitored as soon as the procedure is entered and a valid SI is determined to have occurred.

RESPONSE

We request that you accept answer A or B.

Answer A is true if there has been a simple Reactor Trip. In E-0 Reactor Trip or Safety Injection Step 4 when SIis verified NOT to exist the procedure is left and a transition to ES-0.1 Reactor Trip response is performed. At this point CFS's will be monitored.

Answer B is referring to Step 28 in E-0 where CSF monitoring will begin after verifying that SI flow should not be terminated. The Westinghouse Owners Group EOP-E-0 states that Critical Safety function Status Trees will be monitored whenever 1.) Directed to by E-0 or 2.) Whenever a transition from E-0 is performed.

By this definition neither answer is totally correct and depending on the students assumptions either answer A or B is correct. Please amend your answer key to accept either A or B as a correct answer.

REFERENCE:

3-EOP-F-0, Page 2 COL 2-3:dsp:04/30/86 l'.me 1

ACCELERATED REQUAL 1 NRC TEST RESPONSES SECTION 4 RO QUESTION 4 06 Indicate whether the following precautions regarding unit startup/heatup operations are applicable to UNIT 3, UNIT 4 or BOTH UNITS:

a. The temperature differential between the prese izer liquid and the RCS should ,

not exceed 190 degrees F.

b. Criticality shall not be achieved below 522 degrees F.

c. Pressurizer heatup rate should not exceed 90 degrees F/hr.

RESPONSE

Due to a recent procedure change your answer to part (a) is incorrect. However, some students answered the question knowing that the information that you were utilizing to write the exam did not reflect this recent change. For this reaso_n.we ask that the following answers be accepted.

Unit 4 (with an explanation),or Both Units 3 and 4 REFERENCE 3-OP-041.2 and 4-OP-041.2 l

l I

1 l

l l

OL2-3:dsp 04/30/86 Pace 2 l

ACCELERATED REQUAL 1 1 NRC TEST RESPONSES SECTION 4 RO QUESTION 4.08 i

a. When reporting an emergency (eg, pipe rupture), what 4 iten.s ofinformation are required per EP 20102, to be given to the PS-N over the phone?

i

b. What 2 PAX extension numbers should be used to contact the PS-N? ,

9

RESPONSE

Fires, explosions, injuries and other emergencies are reported to the PS-N by using the Emergency / Fire Phene PAX extension 260. This information is taught in GET to all new employees and posted throughout the plant en PAX phones.. The operators also have to test operability of this phone daily. For this reason, we request you expand your answer key to accept any two of the following extensions; 260,300 and 301.

e 9

i l

~.

. mm-se , . -

l

_ CCELERATED REQUAL 1 NRC TEST RESPONSES SECTION 4 RO QUESTION 4.09 When it is necessary to use water to combat a fire in the vicinity of energized, high-voltage electrical equipment, what 2 precautions must be adhered to while using the water hoses?

I

RESPONSE

EP 20107 is the primary guidance document for the establishment, make-up and essignations of the Fire Brigade. At Turkey Point RCO's are not members of the fire brigade and are not trained in specific fire fighting procedures and for this reason we request you accept a wider variation of possible common sense answers from the RCO's.

l C

~,

0L2 3 dsp 04/30/86 ,, ,4

~

1:LERATED RLQU AL 1 NRC TEST RESPONSES SECTION 4 i

RO QUESTION 4.10 SRO QUESTION 7.07 Q. While conducting an Independent Verification per ADM 0103.4, what are THREE methods by which valve position can be verified?

b. What are your actions if you fini. a valve out of position? !

RESPONSE

We ask you to amend your answer key to reflect wider variation of possible answers. For instance, ADM 031 gives a means of verification by position indicators. A wide variety of position indicators exist (eg, local light indication, remote light indication, stem mounted position indicators). AP-0103.19 utilizes Control Room light indications due to ALARA and contamination considerations.

This list of methods is not the definitive list but is open for interpretation depending on valve location and valve construction.

REFERENCE:

l ADM-031, Page 8 AP-0103.4, Page 3 AP-0103.19, Pages 23 and 27 l

OI.2-3 d-p 04/30/86 Page5

ACCELERATEI) REQUAL 1 NRC TEST RESPONSES SECTION 4 RO QUESTION 4.15 Describe the required operator actions according to OP 0202.2 if the following situations crise after the 3rd doubling during a 1/M approach to criticality. Include any cuthorizations required to continue startup if no problems are discovered.

c. Projected critical rod position is below the insertion limit.

b. Projected critical rod position deviates from the ECC rod position by 560 pcm.

RESPONSE: -

Answer A. Answer key has PS-N authorizing start-up for this scenario, however, OP 0202.2 page 5 step 4.11.1 does not substantiate this answer. 'We ask you to amend your answer key to accept a wider variation of answers since no specific mention of who must

(- give authorization to restartis in the procedure.

REFERENCES:

a. OP-0202.2, Page 2, Step 4.3.3 OP-0202.2, Page 5, Step 4.11.1

0L2-3:dsp:04/30/86 Page 6

ACCELER ATED REQUAL I NRC TEST RESPONSES SECTION 5 i

SRO QUESTION 5.11 l

l Placing fuel with relatively low assembly power on the periphery of the core produces a l Low Leakage Loading Pattern. Aside from reduced neutron leakage, what is the other !

1 main advantage gained in using this loading scheme? i 1

i l

RESPONSE: .

l The question stated "Aside from reduced neutron leakage..." Some candidates assumed this precluded neutron economy and vessel fluence concerns. We ask that you take this into consideration when grading this question. !

l l

l

{

0L2 3 dsp 04/30/86 Pa<ae I

ACCELERATED MLQUAL I NRC TEST RESPONSES

. SECTION 6 SRO QUESTION 6.07 With the exception ofindication, list all 8 of the protective, control and permissive circuits which receive an input from PT-446 and PT-447 (turbine first stage pressure). Identify circuits by nomenclature where applicable. (eg P-6) t RESPONSE: 7 i

The Answer Key references such nomenclatures as P-13, C-7 and C-5 which are not used at Turkey Point. This should be taken into consideration during the grading process.

Another 1st stage pressure originated signal is TREF.

SOURCE:

Logic Drawing 5610-T-D-18A sheet 1

0L2-3:dsp 04/30/86 Page1

. . . u . . - . - . -

~

AUUELERATED REQUAL I NRC TEST RESPONSES SECTION 6 j l

SRO QUESTION 6.12 ;

List all the automatic actions (8 of them exist) performed by the Bus Stripping relays.

RESPONSE: .

?

l Note that the answers in the answer key correspond to the following: ,

1&2 = Bus Stripping 3 = Diesel Start 4 = X-2 Relays Energized 7 = Starts Auxiliary Feed Pumps Because answers 1 and 2 together make up our bus stripping action, we request that you accept a total of(7) answers instead of the (8) requested.

O01.2-3 d>p:04/30/BG Page 2

ACC ui ATED REQUAL 1 NRC TEST RESPONSES SECTION 7 SRO QUESTION 7.04 When pumping down the SFP transfer canal, a person is stationed in the area of the SFP end the transfer canal. What are the 4 conditions when he should alert the operator at the SFP Heat Exchanger Room (parameter values are not required) per OP 16125.4, "SFP Transfer Canal-Filling or Pumping Water to the SFP"? :

RESPONSE: '

Because this procedure is normally performed by non-licensed operators, specific requirements are not committed to memory by the licensed operators. Therefore, other logical problems should also be considered as correct.

Other problems which might be encountered during pump down could be:

Spent FuelPit Low Level Vortering High Radiation Leaks through Keyway Gate Gasket to Canal l

l COL 2-3:dsp:04/30/86 l' age 1

1 ACCELERATED REQUAL I NRC TEST RESPONSES SECTION 7 SRO QUESTION 7.11 List the 5 UNIT 3 Area Radiation Monitors critical to refueling that, if INOPERABLE, would haltrefuelingoperations.

1 1

RESPONSE

Sping is not an area monitor. Therefore, we request that it be deleted from the Answer Key and the question should be modified to reflect (4) Area Radiation Monitors instead of(5).

l .

E.

(

01.2-3 dsp.04/30/86 l' age 2

A UCELERATED REQE AL 1 NRC TEST RESPONSES SECTION 7 SRO QUESTION 7.13 The SPENT FUEL PIT HIGH LEVEL alarm actuates. Assuming a valid high level condition exists, what are all the immediate operator actions as stated in ONOP 33.1,"SFP Cooling System Malfunction"?

t

. (.

RESPONSE

Statement to the elTect that isolation of all sources ofin-leakage should be sufficient.

~

01.2-3 dsp 04/30'86 I) age 3

ACCELERATED REQUAL I

~

NRC TEST RESPONSES

. . SECTION 8 SRO QUESTION 8.06 a) Whose permission is required to exceed the locally imposed whole body exposure limit of 300 mrem /wk, assuming a quarterly dose of 800 mrem will NOT be exceeded?

b) If an individual has a completed NRC Form-4 on file, what quarterly exposure can he be allowed to receive without approval from the Plant Manager and without notifying Corporate Health Physics?

c) What constitutes an airborne radioactivity area?

RESPONSE

b) Correct answer should be 2150 mR.

SOURCE:

0-ADM-600 pg. 32 Sect.5.18.1.C.1.a & b l

l

OI.2 3:dsp 04!30 M g,,, ;

i,CCELERATED REQUAL I NRC TEST RESPONSES SECTION 8 SRO QUESTION 8.07 e) If procedural intent is not changed, whose approval is required for an On the Spot Change (OTSC)?

b) In the situation given above, what is done with the 3 copies of the OTSC ,

generated by the originator? (ie. what is the routing or use of the 3 copies)

RESPONSE: -

The answer to part (a) should be modified as follows to accurately reflect procedural guidance:

1) Both individuals approving the OTSC package shall be on the OTSC Authorization List.

2) The final OTSC package approval signature shall be the current PS-N or SRO designee.

SOURCE:

AP 109.3 pg. 8 & 9 Step 8.2.1.1 & 8.2.1.2 1

f )l,2-3 cisp 04/30/86 l' age 2

ACCELE n; .D REQUALI

~

NRC TEST liESPONSES SECTION 8 SRO QUESTION 8.08 e) When notifying the NRC of a significant event via the Emergency Notification System (ENS), with what segment of the NRC are you communicating?

b) Aside from notifying the NRC after it is determined a significant event has occurred, what other two individuals (use titles) is it the direct responsibility of I the PS-N to contact? .,

RESPONSE

We request that the answer to part (b) be modified as follows:

Alternately the N.E.D.O. (Nuclear Energy Duty Officer) should be another acceptable answer in addition to of the Vice President of Nuclear Operations when it is off hours.

1 SOURCE:

AP 103.12 pg.18, Steps 3 and 6 i

OI.2-3:dsp 04/30/86 l' age 3

ACLLoERATED REQU/. > i NRC TEST RESPONSES SECTION 8 SRO QUESTION 8.10 Prior to a member of the plant management staff arriving on site, what is the ordgr of succession to perform the duties of the Emergency Coordinator if the PS-N becomes incapacitated?

i

/

RESPONSE: $ .;

The way the question was worded, " Prior to a member of the plant management staff crriving on site.....," allows for the assumption that there are no SRO licensed plant staff individuals on site. For this reason, we request that the "SRO Licensed Plant Staff" portion l

be considered optional or deleted.

~.

k.

i COI.2 3.dsp:04/3016 Page 4

ACCELERATED REyi AL1 NRC TEST RESPONSES

., SECTION 8 SRO QUESTION 8.12 l

a) Who is responsible for logging common plant equipment in the Equipment Out of Service (EOOS) book?

b) List 4 conditions that would require that an annunciator be recorded in PartII of .

1 the EOOS.

RESPONSE

The referenced procedure has at least (7) conditions instead o,f the (5) listed in the Answer Key. They are not flagged individually and for this reason, we request that you review the Answer Key and the referenced procedure page and take this information into consideration during the grading process.

REFERENCE:

AP-0103.2, Page 21

0113 d p 04'30/86 l' age 5

.-_ _. .

ML20210U206

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