IR 05000244/1988002

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Exam Rept 50-244/88-02OL on 880212.Exam Results:Reactor Operator Candidate Passed Section 3 of Written Exam.Waiver of Sections 1,2 & 4 Granted
ML17251B027
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/25/1988
From: Eselgroth P, David Silk
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17251B025 List:
References
50-244-88-02OL, 50-244-88-2OL, NUDOCS 8804050358
Download: ML17251B027 (21)


Text

U.S.

NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.

50-244/88-02 (OL)

FACILITY DOCKET NO.

50-244 FACILITY LICENSE NO.

OPR-18 LICENSEE:

Rochester Gas

& Electric Co.

FACILITY:

R.

E. Ginna EXAMINATION DATE:

February 12, 1988 CHIEF EXAMINER:

David Silk, Operations Engineer Date APPROVED BY:

Peter Esel th, Chief, PWR Section DRS Date SUMMARY:

Section 3 of the Reactor Operator written examination was administered to one candidate who requested, and was granted, a waiver of sections 1,

2 and 4 of the written examination and the operating examination.

The candidate passed section 3.

The examination review was held immediately following the examination.

No exit meeting was conducted for this trip.

8804050358 S80328 PDR ADOCK 05000244 V

DCD

DETAILS TYPE OF EXAMINATION:

Replacement EXAMINATION RESULTS:

RO Pass/Fai l Written 1/0 Operating Waived Overall 1 / 0 1.

CHIEF EXAMINER AT SITE:

D. Silk 2.

The facility examination review comments are on Attachment 2.

NRC resolutions to facility comments are on Attachment 3.

Attachments:

1.

Written Examination and Answer Key (RO)

2.

Facility Comments on Written Examination 3.

NRC Response to Facility Comments

ATTACHMENT 2 Ro Ee GZNNA COMMENTS ON NRC EXAM ADMINISTERED 2/12/88

F 01 b.

Recommendation:

Modify answer as follows:

A dropped rod will cause RCS temperature to decrease (0.5).

A dropped rod runback will occur causing average dT to decrease which will cause a lower RIL setpoint to be calculated.

Basis!

The Tavg portion of the RIL setpoint calculation. has a

constant which is set. to zero.

Therefore, the Tavg decrease does not affect the RIL setpoint.

I Reference:

RGE-29, Page

When the rod is dropped, a dropped rod signal will generate a

204 runback.

This is what'auses average dT to decrease.

Reference:

RGE-35, Page

3.02 3o Recommendation:

Change OTdT answer to "Increases" Basis:

When the turbine tripsg Tref goes to 547 F and turbine impulse pressure goes to zero.

Rod control sees Tavg greater than Tref and Rx power greater than turbine power and drives rods in.

This causes Tavg to go to 547 F which also closes steam dump.

Zn the calculation of the OTdT setpoint, if Tavg decreases below Tl, (573.5 F), then the setpoint increases.

Reference:

Tech Specs, Page 2.3-2 3.02 4o Recommendation:

Change the answer to "OPdT setpoint decreases" and delete the OTdT portion of this question.

Basis:

Assuming an upper detector fails high (candidate was told to assume it is a detector failure), the f(~Z) circuit in both OPdT and OTdT would decrease the setpoint.

At the same time the increase in PR indication would cause the rods to drive in reducing Tavg causing the OTdT setpoint to increase.

For the OTdT setpoint, it is unclear whether the decrease caused by the f(~I) or the increase caused by Tavg will be domi'nant.

The OPdT setpoint is* not affected by the Tavg decrease, therefore, the only affect is the.f(QI) effect.

Reference:

Tech Specs, Page 2.3-2 and 2.3<<3

Recommendation:

Delte this question Basis:

This topic is discussed in Lesson Plan R6701C, Page" 18.. It is under the heading

"Potential Inaccurate Readings".

The intent of this section of the LP is to alert the operator to situations where RVLIS is known to be inaccurate so they will know not to trust it during this portion of the transient.

There is no obgective or KA to know what happens to indicated level when the accumulators dump. It is more important to know it is unreliable in this situation.

F 04 Recommendation:

Change answer from "Reactor trips on low PZR pressure...." to <<Reactor trips due to low PZR pressure related trip (ex. low PZR press, OT~Tq low S/G press SI)..."

Basis:

It is unclear which condition will cause the reactor trip.

3.05 a.

Recommendation:

Add 2. to the answer.

Basis:

R-10A is indicative of a leak from the RCS. It monitors CNMT iodine which would be released through an RCS leak.

3o05 do Recommendation'.

Add 3. to the answer.

Basis:

When R-15 reaches its setpoint, an alarm is sounded.

No automatic valve/damper realignment occurs.

Reference:

RGE-39, Page

3o06 ce Recommendation:

Delete this question.

Basis:

The

"B" Diesel Generator does not have an Emergency position.

Reierence:

RGE-S, Page

A11ACilMfN1

NRC RESPONSE TO FACILITY COMMENTS guestion No.

3.01b Because lavg does not effect t.he RIL setpoint, the candidate will not be required to evplajn that a dropped rod causes Tavg

>cf j Q -(

.

1~<<! ".>~

', yo'ns iver r."y w(11 be:

A dropped run back will occur [0.3] causing average delta-T to decrease

[0.3] which will cause a

lower RIL setpoint to be calculated 3 02i!3 Comment accepted.

The answer key will be changed so that the OTDT setpoint will increase.

3.02+4 Comment accepted.

The answer key will be changed so that the OPDT setpoint will decrease.

The OTDT portion of the question will be DELETED and points will be redistributed so that each quf'stiotj

~.0" pil'i b-.;;,rt," C.4 points each.

3.03b Disagree with recommendation.

Since this question tests for an iroo".ant knowledge, the question will not be deleted.

3.04 Comment accepted.

Any low pressure related trip will be an acceptable answer.

3.05a Comment accepted.

Response 2 will be required for full credit.

3.05d 3.06c Comment accepted.

Response 3 will be required for full credit.

Due to the two additional required responses, each response to question 3.05 will be worth 0.27 points each.

Comment accept.

Part c will be DELETED and 0.2, 0.6 and 0.2 points will be redistributed to parts a, b, and d respectivel U.

S.

NUCLEAR REGULATORY COMM I SS ION'EACTOR OPERATOR LICENSE EXAMINATION FAC ILI TY:

G INNA REACTOR TYPE:

PWR-WEC2 DATE ADMINISTERED: 88/82/12 EXAMINER:

CANDIDATE:

D.

S ILK INSTRUCT IONS TO CANDI DATE:

Use separate paper for the answers.

Wri te answers on one side only.

Staple quest ion sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question.

The passing grade requires at least 78% in each category and a final grade of at least 88%.

Examination papers will be picked up six (6)

hours after the examination starts.

CATEGORY VALUE OF TOTAL CANDIDATE'

SCORE OF CATEGORY VALUE CATEGORY

%6~8-188. 88

-~<. F'c.8-Final Grade 3.

INSTRUMENTS AND CONTROLS Total s All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature

NRC RULES A

GUIDELINES FOR LICENSE E

INATIONS Dar ing. the admini stratinn of thi s'xamination the fol lowing rul es apply)

1.

Cheat ing on the ex ami nat i on. means-an automat i c deni al of your app 1 icat i on and could resul t in more severe penalties.

2 ~

Restroom trips are to be 1 imited and only one candidate at a time may 1 eave.

You must avoid al 1 contacts wi th anyone outsi de the examination room to avoid even the appearance or possibility of cheating.

Use black ink or dark pencil only to facilitate legible reproductions.

4.

Pr int your name in the blank provi'ded on the cover sheet of the examination.

5.

Fill in the date on the cover sheet of the examination (if necessary).

6.

Use only the paper provided for answers.

7.

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category

" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9.

Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer, sheets from pad and place finished answer sheets face down on your desk or table.

12.

Use abbreviations only if they are commonly used in facil'ity literature.

13.

The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14.

Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

r'6.

If parts of the examination are not clear as to intent, ask questions of the ex aminer onl y.

17.

You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assi stance in completing the examination.

This must be done after the examination has been complete Wh(~n you compl ate your examination, you shal 1 i C

a.

Assemble your examination as fol lows!

(1)

Exam questions on top.

(2)

Exam aids figures, tables, etc.

(3)

Answe'r pages inc'luding fi gures which are par t of the answer.

b.

Turn in your copy of the examination and al 1 pages used to answer the examinati on questions.

c.'urn in al 1 'scrap paper and the balance of the paper that you did not use for answering the questions.

d.

Leave the examination ar ea, as def ined by the examiner.

If af ter leaving, you are found in this area while the examination is stil 1 in progress, your license may be denied or revoke.

INSTRUMENTS-AND CONTROLS O'J! ST ION

"'. 8!

(2. 28)

}3e i des Rod Sequen e or Rod Devi at'.i on a!. ar ms or Group S

indi cat i one, NHAT

! HREE indi cat 1 ons can the oper" at or use

.e e::':

c

~ce of'

mi sal I gne rod'7 Lep Counter t.o ver 1 fy aJ:

.h

~'.!"e.'oc

.'")Lro.'v'.tern: n manu",.

Eg>~LATN HrJ>>Aa dro ped

~ od (a ssume no r facto,

'.I i p)

wi I!

a ffe:.".t

>he Rod

!nseyt i on L imi L

{RI. )

e'o.'".

I-c! udge:

parameter chanr es whi ch af fect

! he R:L sotpoir i.

Q) )

QU[ Q~~

~lyl (2. i"'P.)

For each c

Overpower 1 er. per a.z.ur 0'.>'/

p ower each cor'u 1 automaL'L c c ld'

1 on be'w BTA.

"

HOM ( INCBEAS'

D CREAS

.

NC CHANGC) the Dif ferenti al: emper ature AND the Over temperatur-c Di Eferenti a!.

e trip setpo>nts wi'.! change.

Assume t he plant has been at.

for two wee! s and that no r eactor trip occurs as a result of tiun.

Cons.: drr eac,i separately.

Assume a! I control..> are in F'ressur i=er sprav va! ves inadvertantl y ac tua-e Steam Generator AR'V, PCV-3411, fails OPEN A tu. b~ne

'I i p QccuI

.-~&Me.. c'.tat'-><Ma~~. I-'M~<:l~aH ~..',

. 5l't

>I gg g~ y nag iw W I wi In rp+ns Ansv;er the fol!owing ruesti ons TRJE or FALSE regarding t.he Reactor Vesse!

eve nd lcat] on System (PVLIS ).

a.

Dur vol inc na'ural circulation conditions RVLIS provides indica" ion of RCS d content b. Accumulator injection into a voided downcomer region wi1 1 cause indicated level to momentarily decrease.

c.

A di sconnected~jCET wi 11 read 547 F

(No load Tavg).

5e l

d.

Vessel level is:, below the top 'of the core when CET temperatures are greater than Tsat.

e.

RVLIS provides a direct subcooling margin readout.

(<4484 CATEGORY 83 CONTINLIED ON NEXT PAGE 444>f<$ )

).

INSTRUMENTS AND CONTROL PAGE

.

gE=T}QNI

. Sr, (2. 5$ )

~A~) ttl ti)e p 1 ant a t 7D/ power',

BO POTH "Cr

! evel tr ansmi ttrrs (I T" 1}

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a

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<<ind LT-1 CS t <<'.->>!r'Ipor a f>>rs wh'h e tl"f>> e" p l r'eac tf)r tr cause CF ntrol systf ms

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HL'IM a) It tl.el

&<<

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. ol lowing

'. is" of process rad1ati on muni tars at the ~}arAI poi nt.

LHOOSE thl:- appr o>>ri ate respol;se fr om be} ow.

c. a>>

<<

<< ~

A<<n automatic va ve/d Thr>>

<<sl or III i s indi cat QVL Y al) al arm aCtuat amper realignment occur-

'. ve of a.'al'. frum th

-

PCS es I<<<<r>>TC'o. e

. lan ol)I=

I eispof)se may be requi.red.

a b.

R-c.

R-d.

R-R-

} Df! 1 n e I'lo I 1 t ol Par tiru.l ate Monitor i cul ate Monitor team E>;haust Moni tor I loll 1 <<.r)l SA Cof)ta '

<<men t At moispher i c Containment Atmo.,pheric 1:3 Au>ci } i ary Building Part

Air E'c tor and Gland S

i7 Component Cooling Aate'

r)LIEST I QN 3. Sb a.

Qn a loss o4 oF fsi te power, WHICH OIME diesel generator tri.p would not be I i kel y to occur.

Assume SI si gnal i s not present and no spur i ous die el generator trip actuations occur.

b.

On a, bl ackout si,gnal with no SI si gnal, (I!HAT 1 oads, if any, ar e re-energized af terr~the diesel generators start and come up to rated speed and vol tage'?

HB-.~; i )-l d.

NHAT af fect, i f any, wi1 1 the loss of the '8'attery have on the

'8'iesel Generator I

44~ (2 b';.

()II)!I)IIIII)I: CATEGORY S~~

CONTINUED ON NEXT PAGE l))')I')II)II)

INSTRUJ".ENTS AND CONTROL

'"'UEST.-'UN

. 87 (3. 88)

J>:i th t.') B dl'.

< I O'A'D

~

's>u I>

~

~ L the; ) !ant

~ I

'>L

~ s

~

1 Cl Qf t:'>B p L

I t 1g at 188% pod(>r, a

1 eak deve! Ops in l he RCS J liat i - be. I r d

"h

> chargirg

"y tBIII.

AssuIII ng

~,o Q

"I'aw '.I a( '1on-I".!.

a'."

B I I ~ au ( oIIIa J. 1 c

~

IAHAT cl'lang Bs ocl ut 1 I'>

LJ.'B ma! n I'l'!J! >'<<

=.'t =-'r I y

~ BP

'Ad Bl'

stems and J'JHE>

J do (,J P5B '"I <<,",gL.'a o cul as

1ar.'o;;I.'i ti'!)n.

Include compof!Bfits wl)'J1 al B a

~

. Voted a

I

'c;1d 1 t I ons or signal s.

(~<<9'<<

."le steam dump 5ys em 1. 5 al ITIed (>JHIQ I TAO permi 55 1 ve ='u'

n o d,.r for hl; >>al ves to actuate?

be met:.

(8. 8)

b.

After'

he plant has stabl i "ed from a

'5% load reject po~.,el-(JHATI a f rp,ct I<<i! 1 a

ol d leg RTD fai I!ng dul<<"

Sv5 t('m '

o From

'$8%

J>a v"B on tJ'1B steam (8. ))

c'.

EXP'AIN J!OIA and J'JHY RCS heat removal

~i I

be accompl i shed i f DC po~l~I to Lhe condense."

=team dumps occurs conc r ren'- y wi t tr i o fr om 188% power As>sume r o operator ac t,I rJn i s

. a J;Bl~.

a loss

~

Jl aoldn

~

( 'L. 6)

DUESTIQN 3.89 (2. '~8)

tl"O. >,1!1

'Al th I

6,"

po~<er

.

Idl<<T 1 5 the DIFFERENCE o --e= suri" B." pressure channel spec t to the fol ': ming i tems?

in the p'an respons-to a con-fa.!. i no LOhl ver sus

"'."i!:ng HIGH

.-r Bssu. i "er Jleaters i~rBssur i "er spray val ves RCS pressur e Over tempel ature Dif<erent ial Temperature runback ( 8 4

>1.'Ill$'ATEGORY 83 CONT INUED ON NEXT PAGE

>J'

IJI 4 4 )

'Lg 3.

INSTRUMENTS AND CONTROLS BLUEST ION

...

3 9

.(2. 15)

For EAC! I of the following two cases, STATE YES or NO as to whether t;he rear tor wi I '. tr i p in respon~ e to a simul taneous fai 1ur e LOW of BOTH Intermedi a'

Range channels.

JUSTIFY each answer r by inc).uding the

<<'3(

3 e'cted

.ivstem (s)

and perm's5. Ve (s)

I) Reactor star tup in progress and at 5% power

.)

The reactor is at =8/ steadv state power (8. 05)

(8. 85)

b.

Assume ihe r eac tor i s at 188/

power when one inter medi at>:-: Range

"hanne

fal '.'IG)I, fo lowed immediately by a reactor trip (from ot(ier cau es).

NHAT action, if any, wi11 have to be taken dur ing emer gen y pr ocedur es tn ensure proper operati on of the Nucl ear Instrumentat i on Systems (8. 05)

(88>kt>k END OF CATEGORY 83 88444)

( 4 4 + f8 4 8 8 8 4 8 8 >k END OF E XAMI NATION

$ 4 4 >h 4 $ 4

>I< 4 8 4 '4 4 4 8 )

INSTRu~ENTS AND CONTROLS PAGE ANSWERS -- GINNA-88/$ 2/12-D.

-SIL.K WER (2...8)

P(:";ter flat"age i~lIS c ~ f ' '~'ttc~D

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pp I.

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P RAP'C EO 3. 8/3. 3 wjP 1 8&f7).; 8 4 8! 0888K 182

.. (KA'S)

Ql P l~ IE P (2. 68)

QPd'ochanqe Decreases

'~ ~c ch a'1c)c REFERENCE

'

R -581C E(3 3.

OidT Decreases De" r eases

<<6 t

".q 0 ">>

~

e~Q 1

~~. 9/4. 3 3. /3. 8 3. 1/3. 3

$ 12$ 88K582 8128$ 8K482 812888K581

.

~. (KA')

'S INSTRUMENTS AND CONTROLS PAGE

i-"!NSMERS --

G INNA-88/82/12-0.

SILK ANSWER 3.83 (2. 8$ )

FALSE h.

TR~'E FAi SE d.

IRU,,

e.

FAI SE REFER'LANCE LP R678 1,C

'

R678".C 8$3874A116

."8.4 pts each3 pp 4 I'F12~ ib) 18 i

I

~ wt)4

~ 11

~ a)ale 4. 4/4. 6 8888!74A1 12 8888?4A 181

...(KA'S)

ANSjAER:. 84

'2. 58)

REFERENCE CVCS RGE-16 p

LP R1681C EQ LI'3$81 C EQ LP R35$ 1C LO LP R49$ 1 C EO

~j.

)

3. 4.

t'.l.a 4.5. f VCT Qut:let Val ve (LCV-112C) closes

".$.43 RiAST Mal(eup Va I ve ('V-112B) opens C8. 43 Control rods w" ihdr'aw to:j!aint:ain Tavg to counter the boro!i add" t:i cn {8. 63 Tavg decreases when cont, cl rods ar e jul l y wi thdrawn C8. 5'3 Reac tor t. i ps an low PZR pr essur e f rom RCS shr ini:age C8. 63 r:!.~> ~-;

~ j 3.6/3.7 3.5/3.8 3,9/3.9 3.4/3.6 2.2/2.2 3.4/3.6

$ 16$ 88K381 881$ 88K4$5 881888K4$ 3 816$ 88K312 8818$ 8K186

... (KA'S)

816$ 88K31

INSTRUMENTS AND CONTROLS PAGE

- 8 ANSMERS -- GONNA-88/$2/12-D.

S1LK

)(">>JJ!'

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a I

e

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8/4'73888K4!81

... (t A')

ANSNER 3. 86

[~68.)

a.

Refer se pc~er ~r3.

C~> -":

J

~

b.

The (sel ected)

ser vi ce ~ate.

pumps 5~.

>0 and the (running)

9~>Ql MIT>.

CCN pumps a J L~.e g d..".'one ('he G wi:1 be aol e to star'" )

REFERENCE DG RGE-8 pp 5) 11, '2

'.9 LP R888l.C FQ 1. =. e, 2. 2, 2.3,7.2,7.5 3. 6/3. 9 3. 2/3. 6 3. 9/4. 2 3. 5/4. 8

$6488$ K41$

864888K482

$64$ 88K283 864$ 88K1$2

...(KA')

.3~

INSYRUNENTS AND CONTROLS ANSWERS -- 6 I MN!A C-88/82/12-D.

SIL PAGE

- 9 ANS<AER

(3. $8)

<Fk pump';i tl i p C$,

Y<<w<

>

~ f

. ow ~ontl ol v

,',"'FM,.ump..-; '

<OVs r. I o

on S.

al ves<

se CB. 25 S o'

758 p ",i g i n the RCS C8.'".53 ose C$ 253 ur. SI8 C8. 253 3 when NFN pump br eal:ers open

~ 33 AFI,<!:

."IDAF TDAF pu. ips stal L! pu<wp st a:"t s C

the;eac tor tr i pumps d) schal" g 8. 253 on 8. 253 on C8

)51 valves S'S C8. 253 Lo Lo SG 1 evel when levy'I shl 1 flks f 'Qm open CS.

when pumps start

<"8..53

!~EFERENCE UFSAR I.ig.

A~4! system LP R42$ 1C LP R4381C

<'

RGE-42 po 2, S EO 4.5, "8 EO 2.6,2. 7 I Z w~ ~

< I 3 Bc'.8$ 8K4$2 3. '/3. 4 4. 5/4.

E>

85988BK419 859$ $8K416

...(KA'S)

ANSWER 3.88 (2. 98)

Condenser ava i 1 ab 1 e Ci rcul at ing i<<at er Running C8.4 pts each3 Steam dumps wi'

actu-te (or unless P-4 was reset after the plant stabi lized af ter the 'ad r ej ection the dumps would not actuate)

C8.53 The condens-r ARVs and SG sa

$5 Tavg decrea ARVs wil'ain s'arn dump valves wi l l. not open fety valves open to provide a heat sin<~

ses the safety val ves wl 1 1 close tain SG pressure at 1858 psig (Tavg S52 F)r8. 4 pts each

REFERENCE Steam Dump LP R IC81C LP R45$ 1C 2 ~ 8/2. 9 841828K418 System RGE-45 pp 3, 4, 6 EO 1. 3 ~.-

EO 2 1'j"2'~ 2

3. 2/3. 3 2.S/2. 8 3. 4/3. 6 841828K414 84182$ K3$ 1 84 1 828K2$ 1

...(KA')

<< I INSTRUNENTS AND CONTROLS ANSWERS -- 6 INNA-88/82/12-D.

SILK PAGE

< <<4< ~D '<t)ER

(2. AS)

I=ai 1.'ng Lo! <

I=a'.'nc.

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Sp<r

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Pr o'ski; e Q'"<<1 mut<aC

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GN Rer:.di r c I o=ed In!:r eae<" s to PORV -"etpoi nt Occur a L meed] a tel y P

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