Text

Exam Rept 50-289/87-03OL on 870302-06.Exam Results:Three Candidates Passed All Portions of Exam.One Candidate Failed Simulator Portion of Exam
	ML20209J209
Person / Time
Site:	Crane
Issue date:	04/19/1987
From:	Coe D, Collins S, Keller R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20209J099	List: IR 05000289/1987003; ML20209J096;
References
	50-289-87-03OL, 50-289-87-3OL, NUDOCS 8705040238
	Download: ML20209J209 (70)
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i U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT l

EXAMINATION REPORT NO. 87-03(0L)

FACILITY DOCKET NO. 50-289 FACILITY LICENSE NO. DRP-50 LICENSEE: GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057 FACILITY: Three Mile Island Nuclear Station Unit 1 EXAMINATION DATES: March 2-6, 1987 CHIEF EXAMINER:

0 -

/

OI D. Coe, Reactor Eng neer (Lead Examiner)

Date REVIEWED BY:

)

YMMU R. Keller, Chief, P~roject Section 1C Date APPROVED BY:

b li b [l////Yki Nlkt/

S(muel J. Col' lins, ~ 0e'puty Director, DRP Date SUMMARY:

Examinations were administered to four Senior Reactor Operator (SRO)

candidates.

Three candidates passed all portions of the examination and were issued licenses. One candidate failed the simulator portion of the examination and was not issued a license.

8705040238 870420 PDR ADOCM 03000289 V

PDR

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>

REPORT DETAILS TYPE OF EXAMS:

Replacement EXAM RESULTS:

l SR0 l

l Pass / Fail l

I I

I l Written Exam l 4/0 l

l l

l Oral l

4/0 l

l l

l Simulator Examl 3/1 l

l l

l0verall l

3/1 l

l l

l 1.

CHIEF EXAMINER AT SITE:

D. H. Coe 2.

OTHER EXAMINERS:

B. Norris N. Dudley R. Keller 3.

Summary of generic deficiencies noted on oral exams:

This information is being provided to document areas of minor weakness in the licensee's training program which should aid the licensee in upgrading license and requalification training programs.

All candidates were unable to correctly interpret the wind direction recorder or the meaning of " southerly, westerly, etc." winds in that they stated direction given was where the wind was blowing towards, instead of from.

4.

Summary of generic deficiencies noted from grading of written exams:

This information is being provided to document areas of minor weakness in the licensee's training program to aid the licensee in upgrading license and requalification training programs.

Knowledge of the three functions of the EFW cavitating venturis.

The basis for each reactor trip.

Automatic actions associated with decreasing instrument air pressure.

I The effect of a loss of Train A power to HSPS.

The three approval routes for TCN's.

The three conditions which require Reactor Building integrity.

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5.

Personnel Present at Exit Interview:

.

NRC Personnel D. Coe, Chief Examiner

,

B. N rris, Examiner N. Dudley, Lead Examiner R. Conte, Senior Resident Inspector Facility Personnel M. Ross, Plant Operations Director 0. Shalikashvili, Manager Plant Training, TMI W. Thompson, Operator Training Manager, TMI R. Maag, Supervisor Licensed Operator Training 6.

Summary of NRC Comments made at exit interview:

No preliminary examination results were given. At the previous request of the TMI-1 Senior Resident Inspector (SRI), the Chief Examiner had reviewed the licensee's implementation of 6200-ADM-2682.10 " Trainee Evaluation -

Once-Back-On-The-Job" and reported those findings at this exit interview.

These findings were submitted to the SRI for inclusion in the next monthly inspection report.

Attachments:

1.

Writter Examination and Answer Key (SRO)

2.

Facility Comments on Written Examinations made after Exam Review 3.

NRC Response to Facility Comments

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NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_,T [l I - 1 _ _ _ _ _ _ _ _ _,. _ _ _ _ _, _ _,

REWiTOR 1VPE:

, P W R _- E g t J_1 7 7_,_, _ _,,,,_ _,

DA1E ADMINISTERED: _87/93/95________________

EXAMINER:

_NORRI@2_B,.,9. _________

MASTER

. _

CANDICATE:

I l.lS T R UC _T I D_I JS..?. L_ C A..' _U I.Ds_1 E :.

_--__ --

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- - -

lise seoarats p a c t? r 4 or the answers.

Write answers on one side cn]v.

Staple question sheet on top of thP answer Sheets.

Points for pat l.

quest 1on et r e ind)ratPt I r.

par eut 'ieses ai t er the cuestion.

lhe pessino orade r ecui t FS at lHhot 7~'

I fi ehCh CateCo"\\

and a i l fid !

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.ATEGORY

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I DA i t S Js:..aLLr

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V_ A L_ U_ E...T O I s_4

_. SCURE W,L ! r

. C A l E (3D R v

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25799__ _E9:90

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b.

THEORY OF IJUCLE AR H li> R F! A'J f OPERATION, FLUIDS. AND THERMODYNAMICS

_25199-_

25 99

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_ _ _ _ _ _ _ _ _

6.

PLANT SYSTEMS DESIC,N. ColJT Rrst,

AND INSTRUMENTATION

_25199__

25-90

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________ 7 PROCEDURES - NORM A;, ABNORMAL.

EMERGENCY AND RADIOLOGICAL CONTROL

.29199__ _29199

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________ 8.

ADMINISTRATIVE PROCEDURFS.

CONDITIONS, AND LIMITATIONS 199199__

________/.

Totals

___________

Final Grade All work done on this examination is my own.

I have neither given nor received aid.

_----_---

Candidate's Signature

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s N'. C CL E n A N.S St!IDE lNE S FOR LICE!$L E x AM] NM IOfc

.

.,

uring the adminastration of this ex ami nat i on the followine rules acol s:

Cheatino on t hs-eynm)natiun means air automatic denia] of v ra. e cu,r ) i r a t t t.n

.

and could

- -oi*

1a car e s: 5 v e r e pet.al t a en.

/.

Rest r oon trips are to be 12 m) t ed and only one candidate at a time may leave.

You must avo2d all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheat i ng, a

Use black ink o,

dark pencil gnly to facilitate legible reproductsons.

..

a Print your name in th9 blank Dr ovi ded on the cover sheet of the

..

examination.

Fill in the dat e on the cnver sheet of the ex ami nat i on tif necessary).

.

J 5.

Use only the paper provided for answers.

Print vcur n a n.E in t '. e-u:nw r r t oht -hand corner of the f I r ?.t cace of cw ct;

.

section rC the answc-w"eut.

Consecut : vel s n u nt r r eac h answer sheet, wrate "End of Categers

_" as

.

2.

appropr : att, start es-h cateoor. on a ney page. write gniv og nng _sice of the paper, anc write "Last Page" on the last answer sheet.

i 9.

Number each answer as to category a r. d number, for example, 1.4 6.3.

10. Skip at least three 12nes between each answer.

11. Separate answer sheet s from pad and place finished answer sheetr. face down on your desk or table.

.

12. Use abbreviations only if they are commonly used i n facility l i,t er_ a t u r e.

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.

I

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.

j 16. If parts of the examination are not clear as to intent, ask questions of the examiner only, 17. You must sign the statement on the cover sheet that indicates that the i

work is your own and you have not received or been given assistance in.

completing the examination.

This must be done after the examination has been completed.

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' f3. When you compi et e voor ex am a r.,st i on. you shal1:

a.

4ssemble voor ex ami nat i on as follows:

'li Emam atir e t i ons on t or,.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer.

b.

Turn in your copy of the exan.ination and all pages used to answer the ex ami nat i on questions.

c.

Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d.

Leave the examination area. as defined by the ex ami ner.

]f after leaving. vou are found in this area while the ex ami na t i on is still 2n p r c;c r ea r-5. v oiir ] i c e r.t. P M A '. bF Cien i ed or " e v o k e t;.

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5 E_lui982.9E_NUC6E65_E9WES_EL@91_gEEBOTigNz_E6UJpS _999 FACs

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QUE ST I O!J 5.t t

75-Which one of the f ol l owi ng tona)tions would result in the smallFst subcool i ng margin?

Assume RE pressure is the same for all cases.

Justify.

a.

Controlled natural c i r cul at i on c ool down i mmedi at el y f ol l owi nn a reactor trip from loss of flow.

b.

Cont i nus-d operatinr. at 5<.

power.

c.

All PCPs are operatirg at r.or ma l no-load temcerature after an extended shutdown.

QUE5110N L.0, 1.1 -

Dur 1 r.g ocwer oce at:on at ~ b5 v.1 t t tnrse Heat t nr Cno! ant Pumns tMP, in oper at i on, the f Ci.* t t ; h i.' E 1000 A is startec.

Assume ]CS is 3n Ge:t oma t 1 C.

Di scuss hot; t rie b e l r.- rat ameters will t!>ange d u r i r.g t t i s-transient:

a.

Feed f1ou (earh 015G)

(O.BO)

b.

OTSG level teach OYEG)

(0.80)

c.

RCS delta Tc (0.50)

OUESTION 5.03 (2.OOi List the FOUR factors that affect the heat transfer rate in a heat exchanger and discuss how a DECREASE in each factor affects the heat transfer rate.

Assume the other factors are constant.

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CATEGORV 05 CONTINUED ON NEXT PAGE *****)

5. _. * T_ H_ E_ O_ R_ Y _ O_ F_ _ N_ U_ C L_ E_ A_ N_ _P_ OWE. 9---P L A. ljT

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FLUIDS

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HOW and WHv would the actual cr 2 t I tal rod posi t i on varv 4 rom the estimated critical rad position (ECF) for each of the following si t uat i ons,

the reactor had operat ed at 100 */. for three months.

Consider each case separ at el y :

a.

100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months is used in the ECP Instead of t h r-actual 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

b.

The actual bcro1 concentration tu 100 ppm lower than that used for the ECP.

c.

20 EFPD is used in the ECP instead of the actual 200 EFPD.

OtJE ST 1 O!!

5.id

.:.Oc)

Ind:cate at which t i n.c

r.

r nr P 1 1 e t-LFif or Flf e the f ol limi no ac r i ausit s are mor e sever o Lt.e.

rpca.?s ai-

& i onger L i nie spent at a hicher eowert.

Assume nr. cperator ac t i or, and that a]] syst ems operate prnper].

Ccnsider each cast seca? atel>.

Just1fy you-answer,

a.

Rod wi thdeawal ac t i t!E nt f r o ~. ]ow in the Source Rance or i nr t t, arn si gni f i c ant reactor toolant temperatur e increase.

b.

The fourth RCP is st ar t ed at 50 %.

Assume the st ar t ing i nt er l t:c k is not functional.

c.

Loss of all A/C paws: at 2005..

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CATEGORY 05 CONTINUED ON NEXT PAGE

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51._IUggBy_gf_ hug 6[@S_Pgy[5_SL991_g@gS@11gy _[Lpig@3_@yp F AM.

_1 H_ E R_ MDD v. N. a. M ; E_ S.

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"..c t2.4-Refer to Figure 5.J.

Two Nuclear Servace River Water centrifugal pumps are in parallel taking a suction on the river and discharging to a common header which supplies a heat exchanger.

Each pump has a di scharge chec k valve and its or essur e anc flow are measured between the pump and the chnEk valve.

For each si t uat i nr. bel ow, enmplete the table pr ovi ded on F l our s ".1

.

to indicate the e >: p e r_ t e d c h a r. g e in the Flow Rate. Di schar ge Pr essur e, a r. e Pumo Current.

Use ar r nwr in 1rdicate how the parameters should c h a r.c e :

a.

Pumos A L 8 ar e runn ng, Fump A shaft binds and RPM decreases by 50..

b.

Pump A is running. Pumo H is started.

c.

Pumps A L P ar e runni-L um: A shaft shears at the c c.u r,1 2 r ic batwee"

.

the p u i.: anr t'e 9.. O d.

Pump A r unt.: nc. ; o r-r1 t o r s-c ri.r s as shewn on F2uure S.!.

s e.

Pumos A L h r um. -. f u.m:.

E che L coise dish become= loose an:' c r e si t e s si gn11 i ca:it blc iac.e +: t the r 1.oc L valve.

DUESTION 5.07 ( 2. 0 0.*

A reactor at EDC is c r i t.1 c a l at lOEt-9) amps and rods ar e wi t hdrawn at 30 inches per minute f or 5 seconds.

Assume a Start up Rate is calculated immediately AFTER rod mot i on stops:

a.

HOW and WHi would the Suit change if the initial conditions were at EOC'

No cal cul at i ons are necessney.

(1.00)

b.

HOW and WHY would the SUR change if it were calculated just BEFORE rod rod stopped?

No c al cul at i ons ar e necessar y.

(1.00)

OUESTION 5.08 (1.75)

a.

What is the subcooling margin (i n degrees F) of the plant if the f ollowing conditions exist:

(1.00)

Thot 591 F Tavg = 579 F Tcold

=

567 F

=

Ppzr 2155 psig Psg

=

910 psig

=

b.

If power is raised from 50% to 100%, how will the subcooling margin change ( i nc r ease, decrease, or remain the same)?

Justify.

(0.75)

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DUF E l l OL.

5. c G f 1. ' m If reactor power is 3 r.c r e a s e d fenm 50*/. t c 100%, how will DIF F E RE N1 ) At rod worth change (i ncr ease, decrease, or remain the same) +or the f oll owi ng conditions?

Consider each case separ at el y.

,

a.

Rod position and baron concentr ati on are held constant, temper at ur e ic allowed to decrease.

b.

Borori is held const ant, rcde are withdrawn from 80*/. to maintain temperature constant.

c.

Rod position is constant, boren concentration is diluted to mai nt a2 n temperature constant.

i QUESTION 5.1O t3.00)

The plant h a c, been noeretIno e'

I t rO*.

power tor the Iast ten days when i t trips.

For thr* below times, state HUW and WHY Xenon will effect tne Shutdown Mar gi n (increase, decrease, or no effect).

Consider each case

separatelv ant' assume all other factors are constant.

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a.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the trip b.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the trio c.

100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months after the trip

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OUESTION 5.11 (1.50)

State TWO reasons that Emergency Feedwater can have a pr opor t i on at el y larger cooling effect on the RCS than Main Feedwater, assuming the same flow rate.

Assume RCPs are running QUESTION 5.12 (2.00)

List the FOUR primary parameters that affect DNB and can be controlled

by the Reactor Operator; and, assuming four-pump operation, briefly explain HOW and WHY an increase in each of the parameters affects the proximity to the minimum DNBR if the other three parameters are held constant.

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d DUESTION 6.01 (2.~5s

.

What are t h e..~1 H H E E f unc t 1 ons of thc cavi t at 2 nc vent ur1 s i r.ht a l 1 en or'. t * &

emergency feedwater line to each of the OTSGs?

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OUESTION 6.02 f3.00)

]

d Ref er to Figurer. 6.1 -

t2. 3.

The reactor is at 100% power with'all ICS stations ~in automat;c with ths excention.of Loop A Feodwater Eemand.

Assuming no operat or att2on, how will the below subsyst ems respond toa reactor trio and what will be the final value of the' indicated par amet or-

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Subsystem Parameter

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a.

Int egr aten Mast er t ie a de r pr ewar e l

j b.

Loon A F eudwat er I emnn - 4 UTSG 1ovel

4 c.

Lcop b Feedwat er Demona - H OTb6 l evel QUESTION 6.03 (1.50)

a.

Why does the reattor trip on a total loss of ICS/NNI HAND power when the plant is at 100% power?

(0.75)

'

b.

Why does the reactor trip on a total loss of ICS/NNI HAND power when the plant is at 5% power?

(0.75)

OUESTION 6.04 (3.20)

During operation at 100% power, the Letdown Line I sol at i on valve (MU-V3)

fails closed; subsequently, the Seal Return Isolation Valve (MU-V-26) fails

closed causing the reli ef valve to the RCDT to open.

Describe the resultant plant transient to the point of ES actuation.

Assume no operator action.

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

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-DUESTION e.05 (2.50)

l, s.

St at e the basis 4c-each of the b e-1 ow 1 i t.t e d Reac t or 1 r'J p ~;

t i. P t.

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1.

Nuclear power basec.on pupp mnnitors i

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2.

High Reactor Contant System prensure 3.

High Reactor Eiui l d2 nq pressure i

b.

Explain under what c ondi t i onn the CHANNEL bypast f eat ur e n+

the Rr5 would be used.

Desc r i b e '. t h e Icgic, changes that occur and the RF5 trips that are bypassed a n d /or i nsert ed.

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DUIS1IGN 6.Oc (;.7L2

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Refer to Floure 6. 1.

1hr c r-a - t e r is at 1005 power With a!! 3 CE s.t at i cos

,

in au t ort.at i c. Gr cup c erd r c'.; r ods art 70'. w i t h d r a y.'1'.

and N1-5 is selected fer ICS inout.

Asnum:iiq r. n o n c-a t e r actsori, what will be the efieet on thc j

ICS and the plant if N!-S ia:Is Jba

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QUESTION 6.07 (3.UO)

i j

Refer to Figure 6.4 to answer the f ol 1 owiYg nuest i ons, rons2 der each case

separately:

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a.

How will the system l i n eogd 'ch an g e i f' t,h e sec ond Letdown conl er is t o be placed in service 7

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(0.80)

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b.

Assume a spuricus 30 nsi n,Rhac t or Bui) olng ESAS si anal i 5.

received.

What automatic actions wi l / occur i n' tde ICCW system 7 ( 0. 80 ) \\.

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c.

As.sume the 30 psig Reac t or 'Bui I d a,nq ESAS s[3gnal is concurrent with an

undervoltage on the ID 4160 vol t lbus. ' What automatic' actions will occur in the ICCW system?

j (O.60)

s.

d.

What TWO automatic actions would happen directly as a result of-ICCW

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j flow decreasing to 500 gpm

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running Makeup pump?

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

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PAGE

6

DUESTION c.OE (2.00)

Instrument Air pressure 2s rior mal I v 200 psig.

L 2 st. IN ORDi-R. thc S1k automatic actions that will occur to try to maintain that pressurt.

Assume

~

each action is unsuccess'ful and that all systems are al i gned nor mal l y.

'Setpoints are not required.

\\

.q,0UESTION 6.' O9 (3.00)

Answer the follow questions about the Heat Si nk Protect 2on System (H5FS):

a.

List the FOUR condi ti ons that will cause EFW initiation. include setpoints where appr opr i at r.

(1.00)

L.

Lisi ths I@ condit:ons that w1.I cause MFW i sol at 1 on.

intlude (

set p a s r.'t s ' kiler t appr u:7r i at t.

( 0. 5n fi

c.

WHEN cne WHi is Tvar 1I comnens.ation used'

(O.75)

f d.

What woul d be the e f i et t on r omnonent s and -i tedi c at i ons on a loss of power to Ira: n 4 o-the H E P E ~-

(0.75)

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QUESTION 6.10 (2.80)

Fol l owi ng a design basi s LOCA. the Engineered Safeguards Features (ESF)

equipment prov2 des for the removal of reactor decay heat thermal energy from the cc e.

For each raf the f oll owi ng c ases, identify the paths which this THERMAL ENERGY is intended to follow.

Start with the coolant leav2ng the break and continue to the point where the energy either c ol l ec ts or dissipates to the environment.

Be sure to list each system or heat transfer component used to transfer this heat.

Consider each case separately.

,

a.

During injection phase with the Reactor Bui l di.7g spray actuated.

b.

During recirculation phase with Reactor Building spray secured and normal Reactor Building pressure.

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(***** END OF CATEGORY 06

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i etdd fDN 7.01 i '.7L, I

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i TRUE or FALSE

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If actordance with 9100-IMP-42OO.03 " Rad Con /,'.hs/m i s t r y.

.

Acti ons Requi r ed y

on U.Yhe RMS Monitor

'l:

.when RMS Malfunctions":

If the vacuum pump

,

(exampIe: Fuel BuiId2nh monitor. RM-A4) b'ecomes inoperable, the iodine,

.

'

gas. and par ticul ate channels shall al so be considered inoperable;

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OUESTION 7.O2 (3.00)

}

c

+

s

,

.

In ac c or d a nc.tr with EP-1202-27 Cool down + rom Outside the Contrel Room."

"

g where.would you go to t r ans f er control of the below componynts to the IMERGD O

,

-

me:' c cs ope r a t a nr.

Match t h r>

1 et t er,s t a "t he numoer s:

.

a.

Communicat2cn System 1.

RST sP ti

]

b.

D2esel Gen er a t or IF

'

~'

RETCP-H

.

c.

EF-F-2B (Emergenty Feedi~a t er Pumo)

i d.

MS-V-4A (OT EG Atmnpnner i r, Domi Va ve)

,

3.

RS TEr.c

' '; g

.

Control Room

,

e.

MU-F-1B (Makeup Mn' ') '

j

,/

g g 5.

Locally at the

-

f.

MU-V-3 (Letdown Li ne' I sol at i on valve)

f Br eaker Patiel

,.

g.

NR-P-IC (Nuclear Ser vice R2ver Water Pumps

'

U.

None of the

h.

Pr essuri 2 er Heaters Grcup 9 ebnve

,

.,

.

i.

RC-V-2 (PORV B1oc IValve)

'![ '

'

(RB Emerge,k

]:

j.

RR-V-1B r

ncy Coo' ti tio Ri ver Wat er Pump I.').seiarpe Valve)

r s'

, 4

.

f

\\

t g

,b

~

GUESTION 7.03 ( 2.' 2 5 )

In accordance with thh-TMI I Technical L F U-i fi cations:

"

it

'

-( A ;

<.

a.

What i s the Mi ni mum Iemperature for Critigality?

.(0.75)

.

b.

What action must be taken dur2'ng power operations if the actual temdrature is less than the Minimyn:-Temperature for Criticality?(1.50)

'

,

.'

.

M '

,

.

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sy (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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It[_P69[EygSEg_ ;_ ggBb8L _99995$9L, EUEBggNO2,@gg

FAGE

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.

__

._

.

!

OUESTION 7.04 12.

Answer the f ol l owi ng i n' acc oroance wi t h 1203-16 " Reactor c o n j arit Pump.and Motor Malfunction":

,_

s

.

What are the TWO i ndi cat i ons of a failure of Number 1 s eal ?

(1.00)

a.

b.

-What'are the TWO indications cf a f ai l ur e of Number 7, seal'

(1.00)

i

,

c.

If Number

.1 seal has f a s 'l ed. what Immediate action must be taken

.

within 5 mi nutes?

( 0. 50 :-

OtlESTION 7.e5 C.O,

.

The plant wac at i 0 0'/.

o u e r.

e a result of a smalI break LDCA. the r eact or tr1ppen nr. i u.,

r r % v ir s2 Gube col i r.g mar gi r-3s n o ri 20r.

In a r: c ce d a n t: e wii t.

AIP 1:'l 0- 1

"fma:. t n- / l ur tr i ne Trip' what FOUR ac t f rt.6 cir r

'

' 'g' r e cui r ed'

!

I e.

?,

OUESTION 7.06 (2.50'

{

In accordance wi th 9100-ADM-4110.06 "Contr el of Locked Hinh Radiation Areas":

g needs to be a.

What determines if an ar ea a Locked High Radiation Area?

(0.50)

'

b.

Who has custody of the keys to a Locked HIgh Radiation Area?

(0.50)

c.

What actions should be taken if a key is found in the lock to a Locked High Radiation Area and the Rad Con Tech is not is the area?

Assume

,

I you eventually have to enter the area.

(1.50)

,

l QUESTION 7.07 (4.00)

In accordance with 1210-10 " Abnormal Transients Rules, Guides & Graphs":

a.

What TWO criteria REQUIRE that HPI be throttled?

(1.00)

b.

What TWO criteria ALLOW HPI to be throttled?

'(1.00)

it.

What FOUR criteria verify natural circulation?

(2.00)

i (***** CATEGORY 07 CONTINUED ON NEXT PAGE

- - - - )

. k Q

,

t.,

.

,-,

.x,

,

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-

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PROCEDORES'- NORMAL. ABNORMAL. EMERGENCY AND Pi.GF

.R.A_ D_I. O_ O..G.l C A. L_.C _O_N_ _T R. O...

_..

..

,

^

Ot!E5110N 7. %

i 2. 5( *

. Answer the below ouest2onn in accordance with 1507-3 " Main Fuel Handl2nc j

Bridge Operating I nst ruc t i ons ":

,

a.

What-i s the reason for the admi ni strat i ve prec aut i on "The bri dges shall i

not be de-energized when the fuel and control. rod masts are centered over the t r ansf er tube aves."

.(1.001

'b.

Why must you cush thF Dutton on the end of the bridge c on t r o l. ' h a n d ! 'e prior t o movi ng t he br 2 di;F>

(0.56)

'

c.

The bridge coerator 2s removing an Axial Power.5haping Rod (APSR) 'trom the core. but he has not placert the Function Sel ect or - t o t he Control Rod oosation.

What'is the consequence of this.actioni (1.00)

DUESTIGN 7.o9 t..ou)

Answer the f ollowi ng i r. accordance with had Con Procedure J eG ! "Releasino Rad 2coctive L2 quid Waste' refar t o F 2 qur es 7.1 -7. 5:

a.

Why ar e reci r cul at 2 on and i sol at ) on r equi r ed p er Bl oc k 30 (1.00)

b.

What does the Shift Supervisor's signature in Block 30 si gni f y?

-(1.00)

i

!

'

!

QUESTION 7.10 (7.50)

Answer the f oll owi ng in ac cor danc e wi t h OP-1104-4 "Decav Heat Removal System" refer to Figure 7.6:

a.

Identify curves 1.

3.

and 6.

(1.50)

b.

Curves 4A and 4B are both maximum RC. pressure for operation of the Decay Heat Removal syst em when runni ng react or coolant pumps;

,

Curve 4A i s for RCP C or D, Curve 4B i s for,RCP A or B.

WHV are the curves different?

,

'

(1.00)

e

!

J i

(***** END OF CATEGORY 07

- - - - )

!

i

...

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.

, -... ~.

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

..... - _ _ _ _ _.

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

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@:._9Q JNigTS@I1y{_f50pEQURE,@. CONIji'j _I ONF;1,f4NQ _ L;[Mll@T.I ONF P AE4

!T QUESTION E. :- )

i2.00)

TRUE /F ALEE and JLI5 i li i :

In accordance with AF-1029 " Conduct of Operations" the Shift Super vi sor or the Shift Foreman should be in charge of the Fire Brigade if radi oact a ve mat er i al is i nvol ved and the plant is in a Hot Sh u t d owr, condition.

DUESTION 8.02 (3.00)

In accordance with AP 1001A "Pr ocedur e Rev2ew anc Approval *:

a.

Use of a T errecr ar e Lhanar Nat2ce fTCN) 2s 12 mi teo to what lHREE Cases ~

( ! - "' V

-

b.

Descr 2 be TWO o+

the tio op t voec-of approval r ou t ec, for l i~ N s.

Incluns in your de5rr3pt;n'

1.

When each e t.p r t. v s : r o it r-r..a y / mu s t b r-L. E E :!.

?.

Who must a u r r a v r-

ne TCN bwf or e it may op imalempntk.

t !. %'- )

CUESTION B.03 ti.So)

Match the lechn2 cal Speci+statiori term (l et t er ) wi t h its appronr i at e definition (number ) :

a.

Channel Cal i br at i on 1.

The i nj ec t i on of a si mul at ed signal into thF-channel to Verify proper response, b.

Channel Check 2.

Ver i f i c at i on of acceptable channel performance by observation.

c.

Channel Test 3.

The adjustment of a channel such that it responds accurately to known values.

(*****

CATEGORY 08 CONTINUED ON NEXT PAGE

- - - - )

_

.

. _.. -.. _

..

.

. ~ B.

ADMINISTRA11VE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 13-

QUESTION 8.04 ( 1. 50) '

Answer the f ol l owi np i r. a c c or d a r.c F with TN1-1 Technical E p ec i f i c a t ) on c..

Assume the plant is in a Hot Standbv Condition:

a.

What actions are requi r ed if operating with minimum crew composition and one of the ROs becomes incapacitated?

(0.761 b.

Is the f ol l owi ng action proper by the Shift Supervi sor ?

Justify.(0.75)

,

15 minut es before scheduled ar ri val o4 the on-coming shift. an onr onyt ny RO call s in si c k.

The on-shift SS decides, due to his shi f t 's'

pr eser.t

.

'

overtime si t uat i on. to call in a replacement.

The SS also decides that since the repl acement should arrive short l y af t er shift change (about 30 minutes)..to send h19 peccle home and let the'next shift start one person shcrt o'

mi ni mum.

J

DUESTION E.OS ( 2. 0 C'

It is di scover ed today. 5 harch da.

sh:ft (0/00 - 1500), that a monthlv surveillance on t h t-Re a c t o-Protectic, System due last Sunday. 22 February i

mid shift (2300 - 0700), was not per f or med.

This surveillance has been performed on time f or the past six months, i

is the system considered op er abl e?

Explain your answer.

QUESTION 8.06 (2.50)

Answer the following quest i ons in accordance with AP-1002 " Rules for the

,

Protection of Employees Working on Electrical and Mechanical Apparatus":

a.

When is doubl e val ve i sol ati on desired when working on mechanical systems?

(0.60)

i b.

When working on electrical circuits,.at what potential voltage-is a

'

grounding device required?

(0.30)

i -

c.

You are the Shift Foreman r evi ewi ng an Application for Apparatus to be Taken Out of Service for work on the 2A Emergency Feedwater pump.

Numerous Red and Blue tags are to be used.

The form has already been approved by the cognizant Department Foreman.

List FOUR of the responsi bili ti es associ at ed with YOUR approval of the form.

(1.60)

l

,

(*****

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

<

l

_ -

. _ _,, _ _, _

_ -~._._ _,

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-

.

~8.* ADMINISTRATIVE PROCEDURES.' CONDITIONS. AND LIMllA11DNH PA6F

~

~

.

QUESTION E.07 (1.50)

In accer car.te wi t -. 6 410- 1 MP-- 13u0. 02

"E mer cenc y Di r et t i on' : ont e the Emer gent y Support Di rec t or (ESD) arrives at the EOF. the responsib111 Lien of the Emergency Di r ec t or (ED) ar e split _between the ED and the ESD.

What are the TWO cases when the ESD can overrule-the ED?

i OUESTION B.08 (3.00)

'

6 Wo ~tmf t)<m. 0/

Using the Emergency Pl an Cl assi f i c ati on procedure provider. classify each

of the f oll owi ng sequence of events.

Consider each-sequence.separatelv.

Include in your JUSTIFICATION the specific par agr aph ~ ci ted.

/m b5l $rer $ /tNJ ~ ay // /d es.cJr Joya spect a/ e.venN:

The plant is at 755..

EOC.

The bt1ow equi o n.t

.t is unt - of - ser

-

fm each of tr.e events:

n ce

!

2A Emer gent v ieedwatei numn IC RE Emergency Cool i nn Unit IB Nuclear Se vi chIIate-oump IB Makeup E Purittratton pur.p a.

Hot leg leet of /u gnm - 2dentitled anc confirmed Loss of Bus ID - cannot tw r eener gi z ed Update on Hot leg breal - NOW 2SO gpm Loss of of f si te A/C - React or tr2o on power t o f l ow. FS Act uat i on on Law RCS pressure 1B DHR$ I[p wi11 not start b.

NI-7 (PR) fuses blow - replacement fuses also blow Rapid load decrease t o 50% order ed L compl et ed due t o pr obl ems on grid B OTSG Mai n FW valve fails closed - Reactor trips on high pressure Report of ex p l osi ons in the area of the Emergency Feetlwa t er pumps c.

I A Nucl ear Ser vi ce Water pump trips RM-A-d#keading2E5 cpm RM-L-[" beading IE4 cpm Makeup Tank level decreasing after a second Makeup Pump started

'

Steam line rupture outside RB - ES actuation on low RCS pressure, automatic Reactor Trip does not occur but manual works One control rod does not insert on the trip Main Steam Isolation Valve MS-VIA does not close fully i

QUESTION 8.09 (2.80)

In accordance with TMI-1 Technical Specifications, Reactor Building integrity must be in effect whenever any ONE of three sets of conditions

exists.

What are those THREE sets of condi t i ons?

a

l i

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

-.

.-

-, _

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. -,

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-.

.. -

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.

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-

D QUESTION 8.10 (2.00r The plant is in Het Ei andt.y wh e r e the on! y liFat serisor in t h e. I s ' f.) e c.r !

Generator ~room is found hanging ~by its wires.

In accordance with the TMI-1 Technical Speci f i c ati ons, what actions.-if any, should be taken by g

the Shi f t. Supervi sor?

'

OUESTION 8.11 81.20)

.

!

In accordance wi t h TM1-1 Technical Specification Bases.. Post - Atoi dent

]

RE emergency coolinc msv be accomplished by what THREE combinations of

. emergency cooling units and. spr ay - syst ems?

DUESTION C.12 sd.ou)

I The plant i e.

nper at i no at 1 0. >'e.

oner. al l-c ont r r*]

byst ems ar e in automat i c.

,

except as st at ed b r i nv. all wo.n mm.= n t is operable.

Usinn Section.3.0 of the Technical Sper)tiratioon providen, inr rat h si t ua t i on b e l o 6.. st at e If an

LCO Action Statement has been entered.

Justify your answer bv reference to the page number and car agraph h u mb et - ot the Technical Specification.

Consider each case separatelv.

[ Sections-3.0-3.1.2, 3.1.4-3.5. L 3. 7)

e

.-

_

. 3.. g,-.,4

> _.. -

_

__

a.

The Day Tank for Emer oency Di esel Generator 1A is having new pioina

installed.

b.

Makeup & Purification pump IC motor is being replaced, c.

Emergency Feedwater pump 28 failed its last-surveillance.

d.

Decay Heat Ri ver Water pump 1A breaker is racked out for replacement.

e.

Assume that all four of the above situations occur within one hour of-each other.

.

f I

(*****

END OF CATEGORY 08

- - - - )

(************* END OF EXAMINATION ***************)-

,

i-

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5*_ IUE9Ey_gE_Ug((E9B_000[S_S(901_OEES911001_ELUIDSt_90D FAFE

-

IBE?"bgt,tjejlpf ANSWERS -- TMI-1

- fi7 / 03 / 05-NORH I S.

E.

5.

ANSWER 5.01 i

75-Q,. - Natural Circulat)on Looldown (O..e5's Core delta-T during N

cooldown will approach full load delta-t (0.501 REFERENCE TM1-1 OPM Uc) 7 Chp? N 2.

Dos 72 -

9.

.---.---.---..--------------.

KtA ifs:

4.2/3.7 OO1000kS56 OO2OOGE509

...(KA'S)

ANSWER 5.O?

t:..

a.

"A" 01EC fecc 4)rw vi11 2orec-a w tO.40)

"E" DTSG 4eed i!nx will dsciease (0.40)

b.

"A'

07EG 1evel w21] 1 ric r ease (O.40)

"E'

O T Ei-level will decrease (0.40)

c.

RCS del t a Tc will r et ur n t o z ero (0.50)

REFERENCE TMI-1 SRO Exam 12/16/85. #b.04 TMI-1 OPM Vol 3.

Chpt F-3.

pgs 162-164

.--------------_------

KLA ifs:

4.2 OO2OOOk511

...(kA'H)

ANSWER 5.03 (2.00)

YO T

_ /$ 0n h7 1.

Delta T geg44 7-(0.25 each part)

heat transfer rate decreases 2.

Surface area Q Q /Q,e, %

heat transfer rate decreases

.

3.

Thickness

heat transfer rate increases g A f M y h M h,j

Thermal conductivity Cp heat transfer rate

- -' "-

g REFERENCE

TMI-1 Exam bank. SRO-1, Cues M 5.6 TMI-1 OPM Vol 7,

Chpt N-2.

pgs 168-171

.

-.

-

.

- -.

.

5s* THEORY OF N' !CL E AR POWER PLANT OPF. RATION _FLpipS _9fp PAi5F

.

,

j

1 mr!gOhNpp g.

ANSWERS -- TMI-l-87/03/OS-NORRIS.

P.

5.

k&A ifs:

3.6 OO 2020Gi.' i

... (L*,'r.)

ANSWER 5.04 (3.00)

a.

Actual critical rod position (ACP) Will be higher-(0.50)

due to Xenen and Samarium buildup ( 0. 5 3 )

b.

ACP will be l ower (0.50)

'

to compensate for the decreased reactivity of the boron (0.50)

r c.

ACP will be higher ( O. ht> >

due to fuel burr.uo (0.50)

REFERENCE TMI-l Exam bant. EPli (nct n u m b F " P d.'. OUPS M S.'

TM1-1 OPM Vol 6.

Ctir:t N-ace 52 38. L 79-99

.

TMl-1 OP 1103-15E. pas 11.i

- Je.O

_ _ _ _ _ _ - -. _ _ _ _ _ _ _. _ _ _.. _ _. _ _ - - - _ _ _ _ _ _ _ _ _ _. _ _ _ _ _

KLA ifs:

4.2 OO1010A207

...(AA*E)

)

ANSWER 5.05 (3.00>

i a.

fee-Sc6 (O.2O)

'

DOPC is lest neg,. r i ve (f uel temperature increase)

(O.80)

b.

EOC

,

(0.20)

MTC is.more negative (cold water)

(0.80)

1

c.

BOC

(0.20)

MTC is less negative (RCS heatup)

(0.80)

i REFERENCE

.

TMI-1 OPM Vol 8,

Chpt N-7, pg 68 TMI-1 FSAR Vol 9,

pgs 14.1-2, 14.1-9, 14.1-19, & Figs 14.1-6, 14.1-16

-

P""

TC.L.

T

'

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____

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...(KA'S)

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5.'

THEORY OF NUCIFAR POWER PLANT OPERATIONt J_L U I IjS,_ _ Atj D

. P ar4 lb

T_ H. F iiMO_ D v H. iaM. I J f.

-

ANSWERE -- TM1-1-87/03/05-NORRIC, B.

5.

ANSWER 5.06 s 2.~ 4 0 )

(0.10 each)

Pump A

: Pump B Si tuati on : : Flow : Pr essur e : Current : : Flow : Pressure : Current

__________;;______:__________;-________;;______:-_________;________

A

:

V

:

'

V

^

__________;;_..____ _._

____

___.. ___;;__-___;- ___

_-_;_.--- _..

B

:

V

:XXXXXA: XXXXXXXXXX:XX)XXXXX

^

-_-_______: : _ _. _ _ _ _ ; _ _ _ _ _ _ _ _ _ _ ; _ _ _ _ _ _ _ _. : :______;__________ ________

.C

:

V

:

^

V

__________;;______;___-______;______..__;;_____-:-_________:________

D

:

-'

V

:XXXXXX:XX))XXX)XX:X7XXXXAx

___.____.... :...._';--_.-. _._;_..-- -.

"

,

.---..__:

_- ----

_. - _ -.. _ _..

E

V

:

V

.

.-.__-

.______._ _-.....--

.. ---_- __- -.._ _____ _- __...___.. _..---_-

Decrease V =

Increasr

'e

= No f.hange

=

REFERENCC TMI-1 OPM Vol 7 Chpt N-3, pgs 94-95,97-101, L 123-127

--___--___-_______-________--__________________

KLA Appendix A-Components:

Pumps #7/1F 2.8 ANSWER 5.07 (2.00)

a.

At EOC. beta effective is less (0.50)

which gives a higher SUR (0.50)

b.

Due to the rho dat factor (0.50)

the EUR would be higher (0.50)

REFERENCE TMI-1 OPM Vol 8,

Chpt N-7, pgs 7-14

_______________________________________________

KLA ifs:

3.1/3.4/3.6 OO1000K530 OO1000K547 015000A102

...(KA'S)

@ 2_]ME9El_OE_UgCLE A5_Egy[E_E6991_ GEES 9119N,_E69]p52_ AND

~

PAGE

7 H E fi h..C.T. v N i d.1t. E

..

.

ANSWERS -- 1M1-1-87/03/05-NORH1S.

b.

5.

ANSWER 5.08

,1.75)

a.

Tsat for 2170 psia (2155 psig)

(0.20)

= 647.44 F (0.40s SCM Tsat - That = e47.44 - 591 = 56.44 F ( 6. 4( )

=

6.

SCM will decrease (0.25>

Thot wi11 increase as power 2ncreases (O.St-)

REFERENCE TMI-1 OPM Vol 7 Chpt N-2.

pgs 73 - 97 Steam Tables

- ------------ --.--..--.--

.-----.

... --..-

KLA ifs:

4.2/3.7 OO1000t556 o u ? v uid rios

...iAA S.'

ANSWER 5.09 (1.50)

a.

Der.rease (0. 50 ear ti)

b.

Decrease c.

Increase REFERENCE TMI-1 OPM Vol 8,

Chpt N-7, p g c. 37-38

-----._---_-_ ___

KLA ifs:

2.9/2.2 OO1000K502 OO1010K504

...(KA's)

-

- -

-

- - -

-

- - -

.

-

.

-

- - - - - -

- -

-

h __ISE051_0E_UUCM.eb_EggR Et,.@y LQPEB@]1g h,E(Q[QL _@y0 PEE

T H E.:9 N OD..Y.f.J.F_... : J. F

--

ANSWERS --- TMJ-1-6 7 / 03 / uS -NDf<R 15.

h.

5.

ANSWER 5.1O (3.u0)

a.

Increases the SDM (0.50 for di r et t i on.

Xenon peaks about B hours after a trip O.50 for reasons b.

No effect on the EDM Xenon reactivit.

ic aper ox 2 mat el y EOual tO the ValUE i mmetii at el y after the trip t.

Detreases ihe RDM Xenon is v i r t u es ] 1 y cone REFERENCE TMI 1 F r c t e d u r r-1.

110:. Si. Do 15.'>

_.. _.._

-_.-_..--.-..-..--..'...._..---_. -- --_.

KLA ifs:

3.5.

4.1.

L ~. '/

OO 101 ohs 2t Ooloom 570 Ov 100Cd.533

...(hA'E2 ANSWER 5.11 (1.Mu, 1.

EFW is not p r eh e a t e ri (0.75 each)

2.

EFW is injected into the steam space ' d u r : ; r e r - ' '- ' t '_- +~ '

_

REFERENCE TM1-1 OPM Vol 1,

Chot B-4 pq 7 TMI-1 OPM Vol 7 Chat N-2.

pas 16E-171

_____

________ ______._ ________

_________. ___

KbA ifs: 3.2/4.1/3.9 059000K105 061000k104 061000K501

...(KA'5)

- - -

-

- -

.

-

5,_JHEOR v..pE NYCL epa. POWER _ PL ANJ OPERAT I Orj, _ F LUI DS., AND PeGE il

.TriEPMpDyt@'!C';,

_

d

,

ANSWERS -- TMI-1-87/03/05-NORR15, E.

5.

ANSWEH 5.12 s?.00)

1.

Reactor thermal power (0.?O)

Increased heat flux (0.15)

Closer t o mi ni mum DNBri (O. I b 7.

Reactor onwer imbalance (Uccer - 1 ower )

( 0. 20.'

Power peaki ng (0.15)

Clc er to minimum DNER (0.15)

3.

RCS Pressure (0.20)

Increase in subcooling (0.15)

Farther away from mi ni mum DNEb (0.15)

l

RCS lemperature (O.dQ>

Decreased subt col i rig

'0.15)

Closer to minimum DNER

,

(0.15)

REFERENCL TM1-1 1S, pgs 2-1 to T-3

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _., _ _ _.. _

KLA ifs:

3.8/4.0/3.7 OO2OOOA101 OO2OOOA109 007+>O04106

...(kA's)

l

4

!

-

- - -

- - - - -

--

._

-

=

_

. -.

. ~.

9.*_PL@gl_@y@lEUs_DEglyh,COBISQL,_@UQ_19@lBgDEyl@l199

PAGE

ANSWFHS -- TMi,

-87/03/US NORRIS.

b.

5.

4NSWER o.vl t i. 2 S.-

i i

1.

Limit EFW to a ruotured OTSG (0.75 each!

(to ensure sufficient feedwater to the intact OTSG).

'

2.

Li mi t mass and energv release i nt o the RB f or overpressure orat et t i on.

1 2.

Limit the flow to the OTSG to reduce excessive RCS overeccling, j

REFERENCE TMI-1 SRO Exam 12/ l ed ES. ** 6.uE TMI-1 OPM. Ucl 4,

Chpt I-1.

EFW, pgs 4b5

.-----...-------- -----------

KLA ifs:

3.4 Oo1000F40c

... ( I. A ' f' '

i i

.

i ANSWER o.62 ( 3. O* > >

a.

On the reactor t rif.,

i t.e set ani nt en i I shtit to the 1& r,cig hia'tO.30)

Atmospher1c dump v a i v e c, wi11 r el t eve i nitial pressor e surge (O.30)

,

?

Final pressure - 1010 pstg (O.40)

Y~ t Y2t d :t i on-(0.30)

b.

r

'

1_

i _.

3. _. -

_i.

,,

, e r g_.

.m

.. _ _.

(9,393 Avw /ever /im i ~, t/ ea,, W J4a-P&p A lv r

]

A OTSG 1evel - 30" on Start-Up range (O.40)

i c.

Low Ievel 1 i mi t wilI contr al Start-Up FW valve (0.50)

B OTSG level - 30" an Sta'-t-Up range (0.50)

REFERENCE TMI-1 OPM Vol 3,

Chpt F-3, pgs 150-153, 208-209 TMI-1 OPM Vol 3,

Chpt F-10, pgs 3

KLA ifs:

3.6/4.2/3.5

,

l 059000K107 061000A101 061000A307

...(KA*S)

i i

,

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

~,----w

-

,

y

- - - -..

,.,, _ _.. - _

%

- _ _ _ -

,_,_-.,..__y--

,,.

-,-

1-

- - - - -

hl_PL992._Eyi M M _DEEjDN. 10NIR L _@Np_][4SISUM NI91}nN

%

'?

c.usw:. s s -- w:,

-R / / 03 / 05-NOriFi l c.

h.

E

.

i-NEkFR t.u i t. S t.

'

th % Ru^2'c'-=+A<' nuce+< E '"

5c+"

+-'- - '

"' r ' '

a.

p pt ( b. 6 )

b.

RCS low pressur e tric on ever cooling ' E " ' n ;: :

st-'

(O.751 REFERENCE TMI-I OPM Vol 3.

Chet F-Z.

pt 1!

101 - 102, f fic TM1-1 OPM Vol 3,

Cnnt F-3.

pon TMI-1 1202-41. ogc 1-2 TMI-l Training Handcut 3210-86-0164 dated April 10.

1986

- - -.. - - - - - - - - - - - - - -.. - - - - - -.. - - - - - - - - - - - - - - - -

KLA ifs:

3. e>

016000h'C;

...ti,A'E>

ANSWE 6.04 t ?. ;'i -

Pr es.sur 2 7 er 1 evc i 6.. 'i i n c e e a e.e tnoe to M/i.O t e. M ear h 's MU-Vl? throttles closed tdue to i ncr easi ng F level)

P:r 1evel wi11 cant 2nue t c. 1ncrease idue to seal in3ection)

Seal inj wt11 stan v. hen makeuo tank coet emnty Pzr level will decrease (due to leakage past thermal bar r i er HK)

Pzr heaters will secur e at !.o w - L.o u level in p;r Reactor trip on low pressure HPI on low pressure REFERENCE TMI-l OFM Vol I.

Chpi B-5.

pas e -- H.

12. L 49

--

.

...-- ---- ---.._..--..

- -- --_

KLA ifs:

3.7, 3.6 4.1.

L 3.8 OO4000A207 OO4020t302 OO4020K303 OO4020K3Ol

...tKA*S)

.

-

.

_,.. __.-_

_ > _ _..

. _

_

.

_.

.__

__

,

..

t -

'

6_.. PL A_ NT. S_.Y. S.T E M. 5.. D. E. S _I G_ N_.. C. ON T R. Ot

' AN

.-..

-

-- __

_

-

.

-

- _.D.l N..S.T.Ri lME. N.. _T _A_T _I.ON PAGE

.

ANSWERE -- TM!-I-37/03rOS-NCAR13. E '. :..

f.

k ANSWER e.05 c c. ht-)

i i

1-a.

1.

Prevent the minimum DNHR f rom decreasing below 1.30

- ( 0. 50 )

1

2.

Pretettion from a Startup accident from 1ow power Ak+.

( O. 2 5.$

l Pratection + rom.a slow rod wi t hdr awal from high power (O.?$-

i 3.

Steam 1ine break inside the Reattor Bu i I d i ng -AWG-.

(O. 7M LOCA.without.+ Lcw RCE pressur e tr i p 4 0. '. 5 '

.

?

)

b.

. CHANNEL Bypass

'

When testing RPS. on1v one channel at a time f gy.y gM

-.

Bvoassed - all A!JTriMA T I C tr i p. on that channel

.N'

,

j Inser i ed - r ior. r?

.7 j

Lontc 2<!

Ap

%,g g

'

&WY Sl$ 0

"I

\\

RFFEHFNCL e

TM1-1 OPM vnl ~.

I' h H I.. se t-1 4.. ?.i. L a1

)

.

_ _ _ _ _.. _ _ _.

_.. _....

.. ___..._________

hbA ifs:

4.,5 / 1. e, 012OOOh604 01200ur40.'

... (NW E i

J j

ANSWER 6.06 (l.75)

,

j 1.

Rods will withdraw at 30'/ min (0.25 each)

j 2.

Unit will go into track (neutron cross limits)

3.

Feedwater fIow wi)I decrease (due to neutron cross 1 i mi t 5)

,

4.

Megawatts will decrease (due to turbine header pressure decreasing)

5.

Tavg wi11 i ncr east-rapidlv (due to MW decreasing whi1e rods are moving out)

6.

Pressurizer level will increase (due to Tavg i ncr easi ng )

7.

Reactor trip on high pressure REFERENCE

.,

TM1-1 OPM Vol 3,

Chpt F-3.

pgs 173-175

.--------------_--

i KLA ifs:

4.0 015000K304

...(KA*S)

i

,

d i

I i

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

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6t- % 931 5Y@ led 5_DEgl@yt,COyl@ Opt _@UQ_lN51Byb[y191[OU PAGE 7 *>

<

ANSWERE IN)- 1-87.03/05-NDRRIS.

E.

[..

l

ANSWF F; 6.07_

t 3. fr,.; ;

a.

Start the second ICCW pump (0.40 each)

i and put the second ICCW cool er-into service.

./S~

b.

IC-V2/3/4/6 shut (u.ac ear h )

IC-V74 opens ( U. Pr

..r a

c.

Pump 1 A wi 11 trip and be locked out iO.00 ratti-Pump 1B will start d.

1.

Standby cump wi11 auto start-(< 550 gpm 1CCW.f 1 owi-( 0. 4 0 er t I.,

'

2.

RCPs will auto trip is550 opm-ICCW flow AND <22 onm wal inim tion)

,

i REFERiW E

,

j-TMI-l OPM Uc)

F.

Chpi E - l +. >. r u t-4-6 F.

,

l TM1-1 OPM Vol 1.

Chrit b.e. o,f.n

- - -.. _ _ _ _ _. - - - - _.......

.

-.. _ _

. _ - - _.....

i KLA ifs:

3.7/3.9/3.4

OO9000h102 000u?M 302 OOvo 1 S A;' 10

... O A 5)

.

4).

I j

ANSWER 6.08 (2.00)

!

j (85 psig) Standby I A corror essor s t eer t s-( O. 2 5. e a c h,: 0.50

(80 psig) Service Air X-connect opens (IA-VI)-

correct order)

(70 psig) D1ock v a l ve =- open to admit Back Up IA

(60 psig) Non-essential loads isolated (IA-V26)

>

these three j

(60 psig) Er - 1 r

^;-

'

r----'

-7-(SA-VS)

>

any

-

'

(60 psig)

-Hour Air switching valves modulate open >

ce d er-

REFERENCE

$*/'WC C kt!' Y* f **90 N bert f f*JJ WN * k E offf TMI-l OPM Vol 6,

Chpt M-2, p g t, 4-S

,

------------- -----------------

$

KLA ifs 3.5 f

078000K402

...(KA'5)

i f

I i

,

I i

i

a k

i i

t

.

!

11 l

k

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- - -

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

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.-.

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.- -

-

6 _,PL @N1_SyST, EMS,,DFSIRN.,, CON TRtu., AN!)_ I N51hgMENig} 10y FWI

> A

'

ANSWERS -- IMI-l-9 / e 4 / OS -N:N.15.

h.

5.

'!

'

ANSWER 6.e4 (3. oui i

a.

Low OTSG 1evel ( 0.15 )

1 0 ' / < ! S,

(o.nf e d ) :C.

<

!

Loss of al) RCPs (0.25)

I Loss of both MFW pumps (0.?5; I

High RB pres (0.15)

i

>4 psig (O.10)

i

!

b.

High OTSG level (0.15)

> 94*/.

(0.161

!

Low OTSG pressure (O.151

< 600 psig (O.10)

$/cl e a /w o)<t

/rej fpet* E

.

(c. att s")

m

^

c.

knen E. v: has been i s n 4 s s s eg op p,py e me. 34,f/, & *fy" jz-tu.:b!

)

More attur ate, i ric:, at i rm of 1.) i sr, l e v e l so. X oo r-

'

d.

One =, r d o4 EFW valvre n e'

0156 2 r.cp ( E F - V-2Oi,/ C s (t#. lb each)

Aut o star t of F F -P-2e, jwapefu M4

,,, vptr. IM j

Aut c, i sol at i on of one sei t MrW va l ver, per OT SG,( F W-V-5sWi; A /16b /17F >

Lost of half of H506 Cont of Room instrumentation Lose, of ICS input tn Hi gh 6e Low 1evel 1 i m) t s

!

REFERENCE I

TM1-1 OPM Vol 3.

Chpt F 10 por 2-3, 5.

9, L 11

,

_______._.___._ ______.____. __ ______.____ __ ____

)

KLA ifs:

3.6/3.4/3.4/4.6

'

059000A201 059000k419 061000A205 061000K402

...tkA'S!

l

!

)~

ANSWER 6.10 (2.80>

a.

Vapor to RB atmosphere - > RB emergency cool i ng -> Mechani cal : Dr af t Cooling Tower (MDCT) -> River / atmosphere (0.20 each)

,

i i

Vapor to RB atmosphere -> RB spray - > RB sump (O.20 each)

b.

Fluid to RB sump -> DHR (LPI) pumps -> DHR coolers -> DHCCW ->

DHRWS -> MDC1 -> Rivkr/ atmosphere y

(0.20 each)

l REFERENCE TMI OPM Vol 1,

Chpts B-6.

B-7, B-9 j

Vol 2,

Chpts D-1, D-4, D-5

_______________________________________________

K8 A ifs 3.9/3.6/3.9/4.3/3.8/4.2

,

OOOO26K302 OO603ON403 OO6030k601 OO6050SGO4 022OOOSGO4

"

j O26020SGO4

...(KA'S)

>

.

. - - - -

-

.

2r._*_PRQGEDURE5_,_fjgStjAL t,@EfjgRt1Ak EMERGEUGY_ AND

PAGE

690URDG1 gel _@9IR0ic ANSWERS -- TMI-2-87/03/05-NORRIS, B.

S.

ANSWER 7.v1 (

75)

TRUE (0.75)

RFFERENCE TM1-1 9100- 1 MP-4 209. O'. rg I'

-... _-- _.-

.......- --.--- -.

- - - - -.. -.. - _ - - - - _ - -

KLA ifs:

4.0 072OOO5GOG

...(kA'5)

ANSWER 7.Q?

t'.'>

% t,2,4 S fe :

t'.'. 3 0 each)

a.

b.

g.

K 1, J, 3 o{

ford er 3 ws'/l c.

n.

b Q my csess wv d.

% ),5 1.

5 t,2,5 j

,g(g f, g

g g, y,

k l,'t 3.
J.
K I,2 f f O.
f all ec Rf 71P')
as REFERENCE TM1-1 1202-37, pgs 3-4 TMI-1 OPM Vol 2,
Chot F-9.
on 13 TMI-1 Lesson Plan 11.2.01.262 Remote S/D Panel, L earni ng Objectives OL P
_- -___. ______-________. --- -
__.._________
KLA ifs:
4.1/4.O OOOO68A121 OOOO68K201
...(NA'5)
ANSWER 7.03 (2.25)
(w) e a.
525 F (NO t ol er ance al 1 owed)
. 0. L t/g, b.
The reactor shalI be
-?:-
t
'
'
'

&,
_-
=:-t eq::?
t=
c-

t :- t :- t": ::?ru!ct=c
t-
.t-
!^rr-tir~ due te der er' ri t!c.
.751
_
2^
REFERENCE TMI-1 TS pg 3-6
____ ________ _______.. ____________ ________
KLA ifs:
4.4 OO2020SGOO
...(KA'S)
.
l
.
-
- - -
- - - - - - - - - - - - -
_
? _*_E8 0EE998ES. _NgSyg( g_ 9@ggSUg( t_{U[Sg [ggy _Afgp PAGE
0

80UOWE:W _L0tHSDt ANSWERS -- TM1-2-87/03/05-NORR15, 6.
f,.
ANSWER 7.04 (2.50:
a.
1.
High No.
I seal leakoff flow (> 5 gpm)
(0.50 each)
2.
High No.
I seal outlet temperature (>.2OOF)
b.
1.
Hi gh standpipe l o.P )
('
60">
.
2.
High vibration () 0.002
')
t.
Close the No.
I seal leakoff valve REFERENCE TM1-1 12 C 3 - l o.
005
..s I.*
_ _...... _.
._......
..
....--
-. - _ _. - -
KLA ifs:
3.2/~.6 003000A201 00 '00 n 1O'
( F A ' r, i
...
ANSWER 7.05 t'.uo)
1.
Trip al1 RCW so.75 each)
2.
Initiate HPI 3.
Initiate EFW
Raise OTSG level te 90-951.
REFERENCE TM1-1 ATP 1210-1. pg 4.0
________________-______________._______________
KLA ifs:
4.8 OOOOO9A201
...(KA'5)
. -
- -
-
- - - -
-
- -
-
- -
Zt * E80CEQUEES_ _NOEU@(t_@BNDEU@Lt_EUL90[ ngl _99D
!M6 TC

_
Sf410LDO M L 5ty.31 era
-
ANSWERS -- TM1-1-87/03/05-NORRIS, F.
5.
ANSWER 7.Oc t;.50)
a.
> 1000 mrem in one hour at one f oot (0.50)
b.
Group Rad Con Supervisor ( 0. :5s Control Room ( 0. 5 )
.
c.
1.
Order every one out of the a ea.
(0.50 eact.
2.
Fefore enterino the area. call for assistance.
3.
After the ar ea is cleared. lock the area and notafy Rad Lon.
REFERENCE TMI 1 9100-AUN-uIlv.Dc. roc e-
,
.
_ _... _ _ _ _ _... _ _. _ _. _.. - - _.... _ _.... _. -... _ -,.. _ _
KLn IFu:
3.4 19400lb10'
...tFA'Ei ANSWER 7.07 (4,00; a.
1.
550 gom/ pump (to p r e v e r. t pump runout)
to.50 each)
2.
To prevent violation of Bri t t l e Frac tur e/ Thermal Shoci cur ve limits b.
1.
If LPI > 1000 gpm per loop AND st abl e for 20 minutes 2.
If Subcooling Margin ser = 25 F
-'T "- : --' --.- -
'
c.
1.
RCS delta T Incr easen to 30F to SOF and stabl e ano Th < 600F 2.
Incore thermocouple temperatures stabilize and tract-Th 3.
Tc temperatures approach saturation for OTSG pressure 4.
Verify heat removal from OTSGs by steam flow and feed flow REFERENCE TMI-1 ATP-1210-10, pgs 3.0, 4.0, 10.0-11.0
_______________________________._______________
KLA ifs 4.2/4.3/4.3 OOOOO9A234 OO2OOOA201 OO6050K402
...(KA'S)
.
F 2 z * PBQCEQ'iBEg_;_NpS$96, _ @SNpSM962.,EMEBgENCy_9Np F atW
-
_
Sekl 069.G.'ieb. 9997 56.-

ANSWERS -- TM1-1-87/03/05-NORRIE.
B.
F,.
ANSWER 7.08 12.5v>
a.
Damage may occur due to movement of the bridge (the system i nt er l oc k r.
are not operative when the bridge is deenergized)
(1.00)
l b.
Al er t personnel that the bridge is movi ng ' t war ni ng bel l )
(0.50s c.
It i s possible to move the bridge with the APSR not fully withdrawr, into the mast.
(1. O
,
l REFERENCE TMI-1 1507-3. nos 6.0 11.6 L 75.0

- - - - - -. - - - - - - -...

- - - - - - - - -. - - - - - - - -
KLA IF s:
3.4/3.0 034000h601 034005-40i
...tVW9i ANSWER 7.09 t?.Oe)
a.
1.
Retirc - to ent. ore prope-mtyton such that a repr es4nt at i ve f. ample can be dr awn (ar t or to release)
(0.50)
!
2.
Isolate - t o ensur e no addi t ) ona l 11ould is added to the tank (be+ ore the r el ease is complete)
(0.50)
I b.
Ensure that the proietted dos &. when added to t ot al inteorated do%e to date, wil not exceed total 15 allowable dose.
(1.00)
!
REFERENCE TM1-1 1104-29. pg E3-1 TMI-1 1621, pgs 4-5, L9

i KLA ifs:
2.8/4.1/3.9 068000A202 068000K401 0680005G05
...(KA'S)
,
1
l
-
7. _* PSgCEDUPEE_ _ UDSU% 9B' QSM% _EMESGENCy_9ND PAGF 3)

j
,RA'g!rjLorr!;At _ { D'g i sy(_
j ANSWERS -- TMI-1-87/03/OS-NORRJb, b.
S.
i
,
!
itNSWER 7.1O t2.501 a.
Curve 1 - NDT curve (0.50 eac t i)
3-Minimum RCS or essure and temperature to maintain fuel clad romrrest. ion wi t h no RCPs runnino c.,
- Mi n i m.im RCP NPEH b.
Cur ve 4B 1s 1ower due ta the 5,uc t i on for DHR being off Icon B.
t ). +. n REFERENCE TMI-1 OP-1104-4 pas FS-1 L Ee-:
c--
_.. u
. - -.....
...... -
..
.... -.
-.... -.... -.
KLA ifs:
3.6 1.9 OO500uk402 O u b Out * > ;
...s&A'r.)
9: _*_@pMJ N]S]R9T)$'E_ PRO;EpilRES _ CpNp]Tj gNS _ AND, LJt11] ATJ pNS P AG F:
IN

2 4NSWERE -- TMj-1
- 87 / 03 / OF --NOR R I S.
b.
6.
ANSWEh E.ui (i.ve False (0.50)
Procedure specifically prohibits the minimum shift crew from participating 2n the fire brigade (0.701 REFERENCE TMI-1 AP-1029, pg= 11.0-12.0
_ _ _ _. - _ _ _ _ _ _ _ _ _ _. _ _ _.. _ _ - - _ _. - - - - - - - - - _ _..... - - _
KLA ifs:
4.2 194001K116
...(K4'S)
ANSWER O.0;
'.L0
'
a.
1.
lo ent.ure orderl> operatJons + or short ner 1 ods, when existing procedures do
'.'t apalv.
no.50$
O.
Wh e s. the tiianoc 1s of a t empe,r ar y nat ur r and shoold nct r et ul t i ri a permanent changr.
10.50)
3.
When t i n.e or conditions, ric or-t permit the u%e of a PCR.
tO.SU)
.
b.
(any TWO required. at 0.75 each)
1.
Normal Anproval Route
- MUST be user? If the intent i s t o be changed (0.45)
- approvalm are tho same as for a PCR (taw Table Two)
(0.30)
2.
Two Memher s of GPLJN Management Sta++ Approval Route
- used if - needed immediatelv (0.15)
- intent not altereo (0.]L)
- procedure to classified as "Important to Safety" or " Environmental Impact Rel ated" (0.15)
- appr oved by two Responsible Technical Reviewers (0.15)
one of which holds and SRO license on TMI-!
(0.15)
3.
Shift Supervisor Approval Route
- used if - needed i mmedi at el y (0.15)
intent not altered (0.15)
-
- procedure cl assi f i ed as "Not 1mportant t o Saf ety" i
or "Non-Environmental Impact Related" (0.15)
- normal approvals are not available (0.15)
- approval by Shift Super vi sor only (0.15)
REFERENCE AP IOO1A, pgs 14-16
_______________________________________________
KLA 1Fst 3.9 194001A102
...(KA'S)
i
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et_._egMINIS18911MG E60CEQg8ESt_CgyO111gyS _@gD_ LIM _11011095 PG+
3-
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.
ANSWERS -- Thl-1-87/03/05-NORR15.
b.
.
ANSWER R.0; t1.50)
a.
(0.50 each.'
b.
c.
REFERENCE TMI-1 TS, pgs 1-3 L 1-4
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ _ _.. - - _ _ _ _ - _ _ _ _ _ - - - _ _ - - - - _ -
ALA ifs:
4.1 012OOOSG01 (> A 5)
...
ANSWEP H.ria 4 1. *.o
,
a.
Octaro a reliri to.40)
within two hourc (0.35s b.
No 10.25)
may not intontionally leavo e position vacant (u.50)
REFERENCE TM1-1 TS, pg 6-2
____________________________-__.________..______
KLA ifs 3.4 194001A103
...tNA'S)
ANSWER 8.05 (2.00)
The item i s NOT operable.
(1.00)
Surveillance intervals for a monthly are not to exceed 7.75 days (1.00)
( 25*/. of 31 days)
REFERENCE TM1-1 TS pg 1-8
_______________________________________________
KLA ifs 4.3 012OOOSGOB
...(KA*S)
,
8_ _. _* A_ D_ M, _I N.. _I F_ T_ R_ A_ T_ _I V_ E_ _ P_ R.. O C_ E_ I_. U_ R_ F S_
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ANSWER 8.et
<2.50, s.
> 200 F (0.30 eachi
> 200 psig b.
>or=
600 vol ts ( 0. 3t -
c.
1.
Ensure the fcm is complete and correct (0.40 earn; 2.
Ensur e the maintenante Individual is cualificd 3,
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Verify that TE are not viclated W that redundant testing g
reauireme'itc are v s-r 2 f 2 e d REFERENEF TMl-1 p oceuur e A '.. ' t.r.
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Event classificction to.7S pach)
Site evacuation REFERENCE TMI-1 procedure 6410-IMP-13OO.07, pg 3
___________ ________ __ __.______.._______ _____
KLA ifs:
4.4 194001All6
...(VA'S)
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a.
Site Area Emergency (0.50 for Action Level,0.50 for Just i f i cat i on)-
RCS leakage greater than makeup capacity - only IC MU pump kvailable

,
(para 3.5.1.A)
OR Failure of any ECCS to start and run - Bus ID was deener gi r ed and Ir DHR p u rr p would not start (para 3.7.2)
b.
General Emergency Loss of phys 2ca] securitv control of the vital ar ea - exolosiens i ri og the area of the EFW pumps (para 3.3.1)
M c.
General Eme cent v Poterit 2 a 2 4or e r ! e a s t-o+
1aros amour.t of r adi nat t 2 <3 i s I c.s e of al]
three bee 2 et r ( p a r,. c.4.ie REFERE NCF 1M1-1 or ocedur e em i t i - I MP-W O.1.
E or 1 tesur e 2
_ - - - _ _ - - - - _ _ _. - - _.. -... - - - _ - - -. - - - - - - _ _ - - - -. _ _ - - -
KLA ifs:
4.4 194001A116
...(kA'5s ANSWER 8.09 (2.80)
1.
RCS pressure
>cr= 300 psig, and (0.40)
RCS temperature > o r r-200 F.
and
!
Nuclear fuel is 2n the ccre.
(0.40)
(O.40)
2.
RCS is open to the atmosphere, and (0.40)
,
SDM is less than that required for a refueling shutdown.
(0.40)
3.
Prior to positive reactivity insertions (boron or rods)
(0.40)
which would result in SDM less than 1*/. delta K/K.
(0.40)
REFERENCE TM1-1 TS, pg 3-41
________ ____ _____.__________________________
KLA ifs 4.3 OOOO69A201
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REFERFNCE TM1-1 15. ogs 3-06 b,- 8 7 LER 86-012-0.' d a t 91 f1c t obor e2 1986
---.---------.-------- --....---------
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KLA ifs:
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ANSWER 8.I1 ( 1. 2c e Three emer genc v c r.c 1 : n g un: t,
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Two spray systems One spra, system and orie emer gent e c ool i ru: unit REFERENCE TMI-1 TS, pg 3-2'

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Releasing Radioactive Liquid Waste
Form 16112 RADIOLOGICAL CONTROLS INPUT TO UQUID RELEASE PERMIT RCP 1621
@) Release Number
@ Time For Release Minimum Estimated h Lost Actual
-
I Refeose Permit *
[
M.nutes
@ Release Recommended By Release information Completed By Rod. Controls Tech. A (Sign)
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h Release Doto:.
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FR-84 Alorm Setpoint of I I gpm initials FR-84 (Hi Uq. Release Flow) Test Sot.
initials RM-L6 Operable per SP 1301-1 (Check Source)
initials h
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Revision 36 Form 16211 OPERATIONS IfJPUT TO UQUlO REIASE FHMff RCP 1621 i
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(Shift sucervisoO
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Soeccioper.v.C M N h For Urwi.4 Changes in the MDCT Row or Actual Reloose Rote the Follo
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1621 Revision 37 Form 14214
@ Nuir,uW Rolocas y
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Date Time (Attach a copy of oil
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CHEMISTRY PARAMETERS I
-
Analyses Performed By-
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(Chemistry Tecn.)
DATE/ TIME of Anc.Ysis-RESULT
__
UMIT

i pH 4.5 - 9.5 (1) !
Conductmty
<10 umho (2) !
Boron PPM (3) !
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l Record result in step @.
0.7 PPM NOTE-1. Umit at tank to erste not exceeding limit of 6 - 9 pH ct plant I
dischorge.
2. Must be < 10 umno to consider water with a pH less then 6 or greater than 9. If conductMty is >10 umno and pH is less than 6.0 or greater than 9.0; release must be opproved by Chemistry Supervisor or his designee with a wntten evoluotion ottoched to release form
@ RM-L6 Setpoints
.
'
A Background Umitations hote:
Monitor Response is from@
1. If orther the RM-L6 monitor resporue or background < 3600 com. go to h 2. If RM-L6 monitor to se > 3600 com. ond bockground is > 3600 but < 27.000.
calculate "e"in
A4.
3. If Bockground > 27.000 com decontaminate the RM-L6 liner and return to @
A-1.
4. e = 3 X ] (Monitor %wde
)+
[2 X(Bkg
=l l
(Monitor Response
)
Note:
Ife> 0.2gshand/ordeconRM-L6linerandreturnto h.If e < 0.2.

.
v B.
High Alarm Setpoint 2x [(MorwtorResponse
) + (Bkg
]=l
)
l C.
Alert Setpoint 1.5X [(MonitorResponse
.
) + (Bkg
}=l l
h and h v61ues on Form 1621-2.
Record e mewacto,-on RM.m D.F. = (RM-L6 High Alorm
)= l l Record the result in step h 31.8 E2-4 w
w...

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Nuclear THI-i Radiological Controls Procedure 1621 Tltie Revision No.
Releasing Radioactive Licuid Waste
Form 1621-5 h CONTACT CONTROL ROOM OPERATOR FOR FOLLOWING DATA NAME OF CR0 CONTACTED a.
PF.ESENT MDCT FLOW gpm.
b.
MAX MDCT FLOW WHICH CAN BE MADE AVAILABLE gpm c.
TIME AVAILABLE FOR RELEASE min. (200 to 1200 min)
d.
Usable MDCT FLOW gpm (must be > 5000 but < 38000)
h MINIMUM M CT FLOW (0.9 x usable MDCT Flow from h d)
Record
.
.
on Step 21 on Form 1621-2, (must be > 5000 GPM).
h 107.
D.F.Fromh MPC D.F.Fromh Boron MAXIMUM
.l l
0.F.Fromh
'
RM-L6
g RR max. MIN MDCT FROM O21
=l l R.R MAX (5.55 to 30 gpm)
REQUIRED 0.F.FROMh h FR-84 ALARM SETPOINT = RR max Record this value athon Fo h RR Actual - (0.9 x RR max
)-l lgpm cord this value at 25 on Form 1621-2.
h Estimated time of release - Est. Vol. to be released gal =
MIN RR Actual (from 25)
gpm RecordthisvalueathonForm1621-2.
h Estimated Reading of RM-L6:
,
cpm (Fromh)
+
cpm (RM-L6 Background)
cpm
=
RecordthisvalueonStephonForm1621-2.
h Estimated Reading of RM-L7:.
cpm (Fromh)
-
cpm (RM-L7 Background) =
CP*
DilutionFactor(Fromh)
RecordthisvalueonStephonForm1621-2.
E2-5 0963c prkeg
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ATTACHMENT 3 NRC RESOLUTION TO FACILITY COMMENTS ON THE WRITTEN EXAMINATION Question Resolution 5.02 Candidate assumptions are normally considered during grading.
5.03 Comment accepted based on given reference.
(Original answer came directly from TMI-1 examination bank).
5.05a Comment accepted based on reference to actual TMI-I Doppler co-efficient change which differs from the NRC generic reference.
5.11 Delete the words " reducing pressure (thus temp)" from answer since this was not specifically asked for in the question.
6.02a MS-V3's are controlled by the bias setpoint.
Significant point is the shift in bias.
Comment not accepted.
6.02b Accepted based on given reference.
6.03 Accepted based on given reference.
NRC answer was a best guess
'
as to which trip would occur first.
6.05a Answer key clarified by removing the word "AND".
6.05b Additional correct answer added based on given reference.
6.07 Incorrect point distribution corrected.
6.08 Valve name changed to reflect facility terminology based on given reference.
<
,
,
6.09a Both setpoints will be required for full credit.
6.09c Additional answer required for full credit based on given reference.
6.09d Answer key clarified to denote inoperable components. Will not accept licensee proposed answer fcr full credit. Question elicits a more detailed response.
'
_
o
---
-
m -
... *
Question Resolution 7.02 Answer modified to allow credit for a response which indicates the candidate knows which components are transferred at one of the RSTSP's and which are transferred locally.
Based on EP-1202-37.
7.03 Delete the portion of the answer which specifies the required minimum shutdown margin and substitute "The reactor shall be shutdown" which is defined as having a shutdown margin greater than the above minimum.
7.07-Accepted based on given reference.
Referenced procedure changed prior to examination.
8.06c Accepted based on given reference.
Original NRC answer assumed Foreman responsibilities included CR0 job functions.
4.08b Accepted based on given reference.
s.SSc Not accepted.
Emergency Plan gives a sufficient basis for the stated conditions-to be classified as a General Emergency.
8.10 Delete the words " declare the fire system inoperable" since taking action to establish a fire watch presumes the local fire system is inoperable.

J

v t e Inspection Report - Crane - 1987003
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1987 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 20(0) 21(0) 22(0) 24(0) 25(0) 26(0) 99(0) 7(0) 8(0) 9(0) 10(0) 12(0) 14(0) Security Operator Exams Emergency Planning Other

IR 05000289/1987003

Text

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